ML051880415

Initial Submittal of the Scenarios for the Monticello Initial Examination - May 2005

ML051880415
Person / Time
Site:	Monticello
Issue date:	05/02/2005
From:	Mcneil D NRC/RGN-III/DRS/OLB
To:
References
50-263/05-301, ES-D-1 50-263/05-301
Download: ML051880415 (59)

Text

Append ix D , Re v. 9 Scenario Outline Form ES -D-1 Facility: MNGP Scenario No .: 1 Op -Test N o.: W 90115 Examiners: Operators:

Initial Conditions: Approx imately 90% reac tor po wer, read y to com plete T urbine-G ene rator test 104 0-01 qua rterly requ irem ents and return to full pow er after turb ine tes ting. Norm al electrical lineup.

RCIC is inoperable due to planned maintenance on the turbine stop valve and is scheduled to be return ed to service tom orrow.

Tu rnov er: Com plete Test 1040-01 and raise reactor power to 100%. Load Dispatcher requests a rate of 5 - 7 M W e / m inute.

Event M alf. Event Event No. No. Type* Description Com plete steps 23-25 of test 1040 -01. (Turbine Bypass Valve 1 N/A N (BOP) Exercise and Speed Load Changer Exercise portions of Tu rbine-Gene rator testing ).

R (RO) Raise power with recirc pumps.

N/A I (RO) APRM #4 Fails Inop 2 NI14D C (RO) Single Control Rod S cram due to failed RPS fus e and reco very CH05 (SRO) T.S. LCO review for APRM I (BOP) HPCI inadvertent initiation 3 HP01 (SRO) T.S. LCO entry, shutdown requirement with RCIC inop HPC I steam line break (ram p)

HP07 Failure of group 4 isolation (HPCI Isolation Valves fail to close 4 M (ALL)

HP08 on PCIS automatic action)

Unable to manually isolate HPCI EO P 1300 entry (Secondary Contain m ent Control)

EOP 1100 entry (RPV Control) Scram 5 CH22A M (ALL)

SDV failure to close (RPV - Secondary containment leak) scram will not reset (cannot isolate SDV)

EOP 2002 entry (Emergency RPV Depressurization) 6 S054-01 C (BO P) 1 ADS SRV fails to manually open (opens 1 non-ADS SRV)

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Append ix D , Re v. 9 Required Operator Actions Form ES -D-2 Op -Test N o.: W 90115 Sce nario No.: 01 Event No.: 01 Page 2 of 13 Eve nt Desc ription: Com plete steps 23-25 of T urbine - Ge nerator test 1040-01. T his is the portion of the test that is required to be performed quarterly and requires reactor power to be <90%. All required steps (1-22) h ave bee n already com pleted .

T ime Position Applicants Actions or Behavior SRO Directs the completion of the test steps 23 and 24.

BOP Reviews test steps BOP Verifies reactor power is <90%

Verifies Main Condenser vacuum is 24.5 or greater and the Circ Water BOP system is in the n orm al lineup .

Performs step 23 Records generator gross load Selects respective valve with BYPASS VALVE TEST pushbutton Time valve opening:

Press BYPASS VALVE TEST pushbutton Time the bypass valve travel to the OPEN position by the chan ge in p osition indication lights BOP Record time to OPEN Record generator gross load Timing valve closing:

Release the BYPASS VALVE TE ST pushbutton Time the bypass valve travel to the CLOSE position by the change in position indication light Record time to CLOSE Return the BYPASS VALVE TE ST SW ITCH to the OFF position Respond to annunciator 5-B-32 (MAIN STEAM LINE LEAKAGE)

This alarm is expected when performing this test and the ARP RO m ay not b e referred to.

The ARP NOTE states that the alarm may initiate due to TBPV opening Performs step 24 Slo wly operates the SP EE D LO AD CH AN GER control switc h in BOP LO W ER dire ctio n until a slight decrease in generator load is noted Observes control valve and bypass valve position

Append ix D , Re v. 9 Required Operator Actions Form ES -D-2 Op -Test N o.: W 90115 Sce nario No.: 01 Event No.: 01 Page 3 of 13 Eve nt Desc ription: Com plete steps 23-25 of T urbine - Ge nerator test 1040-01. T his is the portion of the test that is required to be performed quarterly and requires reactor power to be <90%. All required steps (1-22) h ave bee n already com pleted .

Verifies the bypass valve OPENS slightly as the control valves CLOSE to reduce load After operating on the speed governor control for a few minutes, restore turbine control to the pressure regulator by operating the SPEED LO AD CH ANGE R in the RAISE direction W HEN the pressure regulator takes control, THEN raise the SPEED LO AD CH ANGE R to its high speed stop.

RO Respond to annunciator 5-B-32 (MAIN STEAM LINE LEAKAGE)

Th is alarm is exp ecte d wh en p erform ing this test The ARP NOTE states that the alarm may initiate due to TBPV opening BOP Notifies SRO that test steps 23 and 24 are completed.

Append ix D , Re v. 9 Required Operator Actions Form ES -D-2 Op -Test N o.: W 90115 Sce nario No.: 01 Event No.: 02 Page 4 of 13 Eve nt Desc ription: Raise reactor power with recirculation pumps from ~90% in order to achieve 100%

power. At approximately 93.5% power annunciators will be received and a half scram will initiate due to #4 APRM failing INOP . Con trol Ro d 10 -43 w ill fully insert due to a failed fus e on the A scram bus .

Th e cre w sh ould stop raising pow er, diag nos e the failure, b ypass the APRM and rese t the ha lf scra m .

The Nuclear Engineer will be consulted for guidance for the control rod and will be told to withdraw the control rod using continuous withdraw to return it to position 48. The SRO should also refer to Te chn ical Sp ecifica tions for the APRM and determ ine tha t no LCO con dition is re quired.

T im e Position Applicants Actions or Behavior SRO Directs reactor power be raised to 100%

Refers to C.2 POW ER OPERATIONS:

Verifies no changes were made to the rod pattern (Nuclear Engineer states no changes)

Dem ands and Reviews 3D Monicore Periodic Log (Nuclear Engineer states all conditions are satisfied to raise reactor p ow er to 98% )

SRO Ve rifies H ydrogen W ate r Chem istry is in servic e (Inform ed that it is)

Verifies APRM readings against the NSSS Heat Balance at each of the following intervals:

Every 10% power Every 15 minutes Raises reactor power with recirc pumps by raising speed on both pumps RO and monitoring reactor power response BOP Provides peer check Acknowledge and report annunciators 5-A-3 (ROD W ITHDRAW BLO CK), 5-A-30 (APR M H I HI INOP CH ANN EL 4,5,6), 5-B-3 RO (REACTOR NEUTRON SCRAM TRIP), 5-B-5 (REACTOR AUTO SCR AM CH ANN EL B) & 5-A-27 (RO D D RIFT ).

RO Repo rt Rx powe r, level, pressure Informs SRO that APRM #4 Hi Hi or INOP light is lit and the APRM RO indicates the same power as the other APRMs Inform s S RO that co ntrol ro d 10-43 has fully inserted (m ay initially RO diagnose that the blue scram light is lit and that the rod scram m ed).

Goes to back panel and observes on APR M #4 that the INOP light is lit BOP and reports this to the SRO SRO Directs #4 APRM bypassed when diagnosis is complete per 5-A-30 SRO Directs half scram be reset after APR M is bypasse d per 5-B-5

Append ix D , Re v. 9 Required Operator Actions Form ES -D-2 Op -Test N o.: W 90115 Sce nario No.: 01 Event No.: 02 Page 5 of 13 Eve nt Desc ription: Raise reactor power with recirculation pumps from ~90% in order to achieve 100%

power. At approximately 93.5% power annunciators will be received and a half scram will initiate due to #4 APRM failing INOP . Con trol Ro d 10 -43 w ill fully insert due to a failed fus e on the A scram bus .

Th e cre w sh ould stop raising pow er, diag nos e the failure, b ypass the APRM and rese t the ha lf scra m .

The Nuclear Engineer will be consulted for guidance for the control rod and will be told to withdraw the control rod using continuous withdraw to return it to position 48. The SRO should also refer to Te chn ical Sp ecifica tions for the APRM and determ ine tha t no LCO con dition is re quired.

RO Bypasses #4 APRM RO Resets half scram Dete rm ines T .S. applicability 3.1 .A a nd verifies requirem ents o f table SRO 3.1.1 are met Reviews ARP for rod drift and is sent to C.4-B.01.03.C (Control Rod Drifting):

Verifies proper CR D system operating param eters RO Refers to B.01.03-05.H (CRD H ydraulic System - System Ope ration) (W hich directs actions for B.05.05-05.G Reco very from an Inadvertent Control Rod Insertion)

Verifies core therm al power and m argins to therm al lim its have not been exceeded Refers to B.05.05-05.G.1 (RECOVERY FROM AN INADVERTENT CONTROL ROD INSERTION:

Determ ines that only one con trol rod inadvertently inserted m ore RO than three notches into the core and proceeds to step 6.

Determines that with reactor power >50%, the Nuclear Engineer must be notified for guidance.

SRO Notifies Ops m anager, Engineering and W ork Control W hen notified that the fuse was replaced for control rod 10-43 and when SRO provided recovery guidance from the Nuclear Engineer, directs control rod 10-43 be returned to positio n 48 by contin uous notch with draw al.

W ithdraws the control rod to position 48 using continuous notch RO with draw al.

Append ix D , Re v. 9 Required Operator Actions Form ES -D-2 Op -Test N o.: W 90115 Sce nario No.: 01 Event No.: 03 Page 6 of 13 Eve nt Desc ription: After crew brie f or when dire cte d by the lead evaluator, HPC I will inadvertently initiate. Th e cre w is expe cted to note a chan ge in M W e ou tput and/o r HP CI alignm ent fo r injection.

Actions to respond to the abnormal event are expected per C.4-G (INADVERTENT ECCS INIT IAT ION ). The SR O w ill determ ine tha t a 24 hou r LC O is requ ired.

T ime Position Applicants Actions or Behavior RO/BOP May report MW e lowering Reports annunciator 5-B-24 (REACTOR WATER LEVEL HI/LO)

Refer to C.4-B.5.07.A (LOSS OF REACTOR W ATER LEVEL RO CON TRO L)

Notify Shift Supervision RO Reports RPV water level is rising BOP Reports HPCI initiation BOP Notes D/W pressure <2 psig and RPV water level is >-48inches SRO Directs HPCI shutdown Performs Actions to secure HPCI per C.4-G (INADVERTANT ECCS INITIAT ION):

Depress and hold HPCI remote turbine trip PB BOP Verify HPCI turbine stopped (observe zero speed)

Place HPCI Aux Oil Pump in PTL After ~5 seconds, release HPCI remote turbine trip PB BOP Report HPCI shutdown Performs subsequent Operator Actions of C.4-G:

Investigate the cause of the initiation and correct BOP W HE N the ca use of initiation h as b een determ ined, AN D the condition is corrected, AND the system reset, THEN return the affected systems to the desired lineup, as required by the current plant conditions.

RO Repo rt Rx powe r, level, pressure De term ines T.S . applicability (3.5.A.)

Exce pt as specified in section 3.5.A.3, the High Pressure Coolant Injection (HPC I) Syste m and the Auto m atic Depressurization System (ADS) shall be operable whenever the SRO reactor pre ssure is gre ate r than 150 psig and irradiate d fu el is in the reactor vessel except during reactor vessel hydrostatic tests.

If the requirements or conditions of 3.5.A.1, 2 or 3 cannot be met, an orderly shutdown of the reactor shall be initiated and the reactor shall be placed in a condition which the affected

Append ix D , Re v. 9 Required Operator Actions Form ES -D-2 Op -Test N o.: W 90115 Sce nario No.: 01 Event No.: 03 Page 7 of 13 Eve nt Desc ription: After crew brie f or when dire cte d by the lead evaluator, HPC I will inadvertently initiate. Th e cre w is expe cted to note a chan ge in M W e ou tput and/o r HP CI alignm ent fo r injection.

Actions to respond to the abnormal event are expected per C.4-G (INADVERTENT ECCS INIT IAT ION ). The SR O w ill determ ine tha t a 24 hou r LC O is requ ired.

equipment is not required to be operable within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SRO Determines shutdown required by T.S.

SRO Notifies Ops m anager, Engineering and W ork Control SRO Directs crew brie f (P ast, Present, P lan, Po ll)

Append ix D , Re v. 9 Required Operator Actions Form ES -D-2 Op -Test N o.: W 90115 Sce nario No.: 01 Event No.: 04 Page 8 of 13 Event

Description:

After the HPCI initiation event, a steam leak in the HPCI system becom es evident when annunciator 3-B-56 (HIGH ARE A TEM P STEAM LEAK) alarms. HPCI area temperatures and radiation leve ls ann unc iator 4-A-11 REACT OR BU ILDING HIG H R AD IAT ION ) will be ob served to rise.

EO P-1300 Secon dary Containm ent Control, will be entered. Th e autom atic group 4 prima ry con tainm ent iso lation will not func tion an d HPC I cannot be m anu ally isolated.

T ime Position Applicants Actions or Behavior Repo rts annunciator 3-B-56 (H IGH A REA TEM P ST EAM LEAK ):

Monitor area temperatures as indicated by TR-4926 on C-21 and determ ine affected area(s).

Refer to the following procedures:

C.4-B.2.4.A (STEAM LEAKS OUTSIDE PRIMARY BOP CONTAINMENT)

C.5.1-1300 (SECONDARY CONTAINMENT CON TRO L)

A.2-101 (CLASSIFICATION OF EM ERGENCIES)

C.4-B.8.7.A (VENTILATION SYSTEM FAILURE)

Reports annunciator 20-A-32 (HPCI ROOM V-AC-8B TROUBLE)

BOP Recognize both HPCI room fans are running BOP Reports EOP entry condition Enters C.4-B.02.04.A, Steam Leaks Outside Primary Containment Evacuate personnel from area BOP Isolate leak Monitor indications Scram SRO Directs check of secondary containment temperatures Repo rts HPC I area tem perature is above (or app roaching) m ax safe from TR-4626 (A REA TEM PE RAT URE M ONITOR) on C-20 and (if BOP checked), HPCI radiation levels are rising from SPD S screen 110 or HP CI room AR M o n Pa nel C -20.

Repo rts annunciator 4-A-11 (R EAC TO R BU ILDING HI RAD IATIO N):

Check ARM Indicator and Trip Units AND determine affected areas and radiation levels.

Evacuate personnel from affected areas BOP Notify Radiation Protection to survey area Consider initiating the EF T Hig h R adiation M ode if there is detection of radiation outside or within the MCR.

Re fer to C .5 (EM ER GE NC Y O PERA TIN G P RO CE DU RE S), A.2 (EMERGENCY PRO CEDURES) and B.05.02 (AREA

Append ix D , Re v. 9 Required Operator Actions Form ES -D-2 Op -Test N o.: W 90115 Sce nario No.: 01 Event No.: 04 Page 9 of 13 Event

Description:

After the HPCI initiation event, a steam leak in the HPCI system becom es evident when annunciator 3-B-56 (HIGH ARE A TEM P STEAM LEAK) alarms. HPCI area temperatures and radiation leve ls ann unc iator 4-A-11 REACT OR BU ILDING HIG H R AD IAT ION ) will be ob served to rise.

EO P-1300 Secon dary Containm ent Control, will be entered. Th e autom atic group 4 prima ry con tainm ent iso lation will not func tion an d HPC I cannot be m anu ally isolated.

RADIATION MONITORING SYSTEM)

Enters EOP-1300 (Secondary Containment Control) and directs:

SRO Isolate leak Ope rate area coolers Attempts to isolate HPCI Steam Isolation Valves:

Takes the control switch for MO-2034 and MO-2035 to close (HPCI STEAM LINE ISOLATION VALVES)

BOP Reports MO-2034 will NOT close Reports MO-2035 cycles closed and back open (may diagnose this is due to th e initiatio n signal)

Append ix D , Re v. 9 Required Operator Actions Form ES -D-2 Op -Test N o.: W 90115 Sce nario No.: 01 Event No.: 05 Page 10 of 13 Eve nt Desc ription: Pe rform s a Re actor Sc ram per C.4-A (Reacto r Scram ). T he SD V vent valves will fail to close upon the scram, which provides an additional primary to secondary un-isolable leak. The attem pt to isolate the leak by resetting the sc ram will not be suc ces sful.

T ime Position Applicants Actions or Behavior Enters EOP-1100 (RPV Control) and Directs Reactor Scram Determines un-isolable primary leak into the reactor building SRO Directs scram before temperature, radiation level, or water levels exceed max safe pararmeter Perfo rms imm ediate scram action s of C .4-A (RE ACT OR SCRAM ):

Pushes manual scram PBs RO Places reactor mode switch in shutdown Reports reactor scram, mode switch in shutdown, all rods inserted Perform s subs equent sc ram actions C.4-A (R EAC TO R SC RAM ):

Control RPV water level Place low power feed controller in auto and set for ~15 inches RO Close both FRVs Close both FW block valves Insert IRMs and SRMs Select IRM s to recorders Verify SDV vent and dra in valves isolate Perform s subs equent sc ram actions C.4-A (R EAC TO R SC RAM ):

Announce reactor scram BOP Verify electric plant line-up At 0 MW E, open 8N4 and 8N5 (disconnects)

Trip main turbine RO Reports SDV vent valves open SRO Directs SDV vent valve isolation by re-setting scram Attempts to re-set scram:

Place DISCH VOL ISOL TEST switch to ISO RO Verify reactor mode switch in shutdown Place DISCH V OL H IGH W TR B YP switch in BYP Reset scram

Append ix D , Re v. 9 Required Operator Actions Form ES -D-2 Op -Test N o.: W 90115 Sce nario No.: 01 Event No.: 05 Page 11 of 13 Eve nt Desc ription: Pe rform s a Re actor Sc ram per C.4-A (Reacto r Scram ). T he SD V vent valves will fail to close upon the scram, which provides an additional primary to secondary un-isolable leak. The attem pt to isolate the leak by resetting the sc ram will not be suc ces sful.

RO Reports scram will not reset (reset switch is overridden)

SRO Directs RPV cooldown not to exceed 97/F/hr BOP Initiates RPV cooldown SRO As 2 area radiation levels are approaching max safe conditions, may direct Anticipate Emergency Depressurization per EOP 1100 over-ride BOP If directed to anticipate emergency depressurization, coordinate with the RO and open turbine bypass valves to initiate a re actor cooldow n in excess of 97/F/hr

Append ix D , Re v. 9 Required Operator Actions Form ES -D-2 Op -Test N o.: W 90115 Sce nario No.: 01 Event No.: 06 Page 12 of 13 Eve nt Desc ription: W hile continuing to monitor secondary containment temperature and radiation levels, when 1 area is above max safe and another is approaching max safe, the SRO m ay direct the anticipation of emergency RPV depressurization and direct a cooldown exceed 97°F/hr. W hen 2 or more areas are above max safe, an emergency RPV depressurization will be performed. One of the 3 ADS SRVs will not open and an addition non-ADS SRV will be opened for a total of 3 SRVs. W hen the R PV is dep ressurized an d RPV wate r level is stable, the sc ena rio is co m plete.

T ime Position Applicants Actions or Behavior As 2 area radiation levels are approaching max safe conditions, may SRO direct Anticipate Emergency Depressurization per EOP 1100 override.

If directed to anticipate emergency depressurization, coordinate with the BOP RO and open turbine bypass valves to initiate a re actor cooldow n in excess of 97/F/hr BOP Reports 2 area radiation levels are above max safe conditions Enters EOP 2002, Emergency RPV Depressurization:

Verifies all rods inserted Ve rifies D /W pre ssure <2 psig SRO Directs prevention of Core Spray and LPCI Verifies torus level > -5.9 ft Directs opening of 3 ADS SRVs En ters E OP 1200, P rim ary Co nta inm ent Control:

SRO Directs Torus Cooling Initiates Torus Cooling:

Verifies Tours suction valve open Starts RHRSW pump(s) and adjusts flows Open Torus Cooling INBD injection valve 8 seconds Starts RHR pum p(s)

BOP Open RHR Discharge to Torus Open Torus Cooling INBD injection valve to adjust flow (4000gpm for 1 pump / 8000gpm for 2 pumps)

Verify minimum flow valve closed Ve rify H eat Ex changer dP is at least 2 0 psid BOP Opens 3 ADS SRVs BOP Reports 1 ADS SRV will not open

Append ix D , Re v. 9 Required Operator Actions Form ES -D-2 Op -Test N o.: W 90115 Sce nario No.: 01 Event No.: 06 Page 13 of 13 Eve nt Desc ription: W hile continuing to monitor secondary containment temperature and radiation levels, when 1 area is above max safe and another is approaching max safe, the SRO m ay direct the anticipation of emergency RPV depressurization and direct a cooldown exceed 97°F/hr. W hen 2 or more areas are above max safe, an emergency RPV depressurization will be performed. One of the 3 ADS SRVs will not open and an addition non-ADS SRV will be opened for a total of 3 SRVs. W hen the R PV is dep ressurized an d RPV wate r level is stable, the sc ena rio is co m plete.

SRO Directs opening of 1 non-ADS SRV BOP Opens 1 non-ADS SRV RO Maintains RPV water level

Append ix D , Re v. 9 Scenario Outline Form ES -D-1 Facility: MNGP Sce nario No.: 2 Op -Test N o.: W 90115 Exam iners: Operators:

Initial Conditions: Approximately 100% reactor power. Normal electrical lineup. HPCI is inoperable due to planned maintenance on the auxiliary oil pump and is scheduled to be returned to service tomorrow. Surveillance test 0143, Drywell - Torus Monthly Vacuum Breaker Check is to be perform ed.

Tu rnover: Perform surveillance test 0143.

Event M alf. Event Event No. No. Type* Description N (BOP) Perform test 0143, Drywell - Torus Vacuum Bk r Check N/A 1 C (BOP) B drywell - torus vacuum bkr fails to fully close PC07A (SRO) T.S . LCO e ntry for P CIS 2 RR13A I (RO) Recirc Scoop Tube Lockout and Subsequent Reset C (BOP) 4160V AC Essential Bus #15 Lockout 3 ED05E C (RO) Loss of and start #12 CRD pum p due to the bus lockout (SRO) T.S. LCO entries due to loss of power C (BOP) A SRV fails open and is closed by pulling fuses 4 AP01A R (RO) Rapid Power Reduction due to open SRV 5 RR1B M (ALL) Leak inside Primary Containment / scram (ATW S)

EOP 1200 (Primary containment Control) and EOP 2007 PP04 6 I (RO) (Failure to Scram ) entry PP06 Rods insert when ATW S (ARI) initiation, exit EOP 2007

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Append ix D , Re v. 9 Required Operator Actions Form ES -D-2 Op -Test N o.: W 90115 Sce nario No.: 02 Event No.: 01 Page 2 of 16 Eve nt Desc ription: Perform ance of S urveillance test 014 3, Torus-D rywell Mon thly Vacuu m Break er Check is to be executed. A marked up copy of the test to provide Shift Manager approval to comm ence, reason for performance and prerequisites will be provided. During the performance of the tes t for the second vacuum bre ak er, it will be fo und to stic k in the partially open condition, wh ich will resu lt in the term ination of the test and a T.S . LCO e ntry.

T im e Position Applicants Actions or Behavior BOP Reviews tes ting requiremen ts and steps to perform Conducts or insures a pre-job brief per OW I01.09 is performed:

SRO Obtains an existing pre-job brief from the data base OR Uses the OPERATIONS PRE-JOB BRIEFING GUIDE Perform s Ste p 1 of test:

BOP Directs out plant operator to open air isolation valve AI-215 Opens CV-7956 on panel C06 Perform s Ste p 2 of test:

BOP Selects AO-2382A, Torus-DW Vac Breaker, on valve select sw itch 16A-S6 0, S uppression C ham ber to Drywe ll Vac B kr Vlv Sel Sw (Pan el C-04)

Perform s Ste p 3 of test:

BOP Opens AO-2382A by placing valve operation switch 16A-S61, Suppression Chamber to Drywell Vac Bkr Vlv Op Sw, (Panel C-

04) to TEST Perform s Ste p 4 of test:

Verify AO-2382A OPEN ED by observing the following:

The green indicating light is OFF and the red indicating BOP light is ON above the valve select switch, 16A-S60 The green indicating light is OFF and the red indicating light is ON on the wall mounted cabinet in the northeast corner of the Re actor Building at elevation 935.

Perform s Ste p 5 of test:

Verify the following annunciators are in ALARM:

BOP 5-A-41 (CR VAC BKR DW /TORUS) 5-A-42 (LOCAL VAC BKR DW /TORUS)

Reports Annunciator 5-A-41 (CR VAC BKR DW /TORU S) and 5-A-42 OATC/BOP (LOCAL VAC BKR DW /TORUS)

Reviews Annunciator Response and determines that the alarm was due OATC/BOP to the surveillance test BOP Perform s Ste p 6 of test:

Append ix D , Re v. 9 Required Operator Actions Form ES -D-2 Op -Test N o.: W 90115 Sce nario No.: 02 Event No.: 01 Page 3 of 16 Eve nt Desc ription: Perform ance of S urveillance test 014 3, Torus-D rywell Mon thly Vacuu m Break er Check is to be executed. A marked up copy of the test to provide Shift Manager approval to comm ence, reason for performance and prerequisites will be provided. During the performance of the tes t for the second vacuum bre ak er, it will be fo und to stic k in the partially open condition, wh ich will resu lt in the term ination of the test and a T.S . LCO e ntry.

Place valve operation switch 16A-S61 to OFF Perform s Ste p 7 of test:

Verify AO-2382A CLOSE D by observing the following:

The green indicating light is ON and the red indicating BOP light is OFF above the valve select switch, 16A-S60 The green indicating light is ON and the red indicating light is OFF on the wall mounted cabinet in the northeast corner of the Reactor Building at elevation 935.

Perform s Ste p 8 of test:

Verify the following annunciators are RESET:

BOP 5-A-41 (CR VAC BKR DW /TORUS) 5-A-42 (LOCAL VAC BKR DW /TORUS)

Re ports the following ann unc iators rese t:

OATC 5-A-41 (CR VAC BKR DW /TORUS) 5-A-42 (LOCAL VAC BKR DW /TORUS)

Perform s Ste p 9 of test:

BOP Select AO-2382B, Torus-DW Vac Breaker, on valve select switch 16A-S60 (Panel C-04)

Perform s Ste p 10 of tes t:

BOP OPEN AO-2382 by placing valve operation switch 16A-61 (Panel C-04) to TEST.

Perform s Ste p 11 of tes t:

Verify AO-2382B OPEN ED by observing the following:

The green indicating light is OFF and the red indicating BOP light is ON above the valve select switch, 16A-S60 The green indicating light is OFF and the red indicating light is ON on the wall mounted cabinet in the northeast corner of the Re actor Building at elevation 935.

BOP Re ports that BOT H the red and gree n indicating lights are lit.

Reports Annunciator 5-A-41 (CR VAC BKR DW /TORU S) and 5-A-42 OATC/BOP (LOCAL VAC BKR DW /TORUS)

Append ix D , Re v. 9 Required Operator Actions Form ES -D-2 Op -Test N o.: W 90115 Sce nario No.: 02 Event No.: 01 Page 4 of 16 Eve nt Desc ription: Perform ance of S urveillance test 014 3, Torus-D rywell Mon thly Vacuu m Break er Check is to be executed. A marked up copy of the test to provide Shift Manager approval to comm ence, reason for performance and prerequisites will be provided. During the performance of the tes t for the second vacuum bre ak er, it will be fo und to stic k in the partially open condition, wh ich will resu lt in the term ination of the test and a T.S . LCO e ntry.

Reports that the ARP references Tech Specs 3.7.A.4 and requires OATC/BOP notification of the system engineer Requests the valve position from the Out Plant Operator and reports that BOP BO TH indicating lights are lit.

Perform s Ste p 13 of tes t:

BOP Place valve operation switch 16A-S61 (Panel C-04) to OFF BOP Reports th at B OTH indicating lights rem ain lit SRO Directs termination of test SRO Notifies Ops Mgr, Engineering, and Work Control Enters T.S. LCO 3.7.A.4.and recognizes 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> LCO condition based on:

W hen primary containment integrity is required, all eight drywell-suppression chamber vacuum breakers shall be operable and positioned in the closed position as indicated by the position indication system, except during testing and except as specified in 3.7.A.4.b through 3.7.A.4.d below.

Any drywell-suppression chamber vacuum breaker may be nonfully closed as indicated by the position indication and alarm system provided that drywell to suppression chamber differential SRO pres sure de cay does not exce ed that shown on figure 3 .7.1 Up to two drywell-suppression chamber vacuum breakers may be inoperable provided that:(1) the vacuum breake rs are determ ined to be fully closed and a t least one position alarm circuit is operable or (2) the vacuum breaker is secured in the closed position or replaced by a blank flange.

Dryw ell-sup pres sion cha m ber vacu um brea kers m ay be c ycled, one a t a tim e, during conta inm ent inerting and deinerting operation s to assist in purging air or nitrogen from the suppres sion cham ber vent heade r If requirements of 3.7.A.4 cannot be met, the reactor shall be placed in a Cold Shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Directs initiation of test 0213 as directed to be performed upon failure of SRO test 0143

Append ix D , Re v. 9 Required Operator Actions Form ES -D-2 Op -Test N o.: W 90115 Sce nario No.: 02 Event No.: 02 Page 5 of 16 Eve nt Desc ription: After the crew has exited the Surveillance procedure, Annunciator 4-C-5 (FLUID DR IVE A S COOP T UBE LO CK) will alarm . The #11 R ecirc Pum p scoop tube will be locke d. S hortly after the annunciator alarms, a report from the plant will indicate that the out plant operator bumped against the Recirc MG lube oil pressure switch which caused the lockout condition. The crew is exp ecte d to reset the sc oop tube bas ed o n this inform ation.

T ime Position Applicants Actions or Behavior Responds to annunciators 4-C-5 / 4-C-10 (FLUID DRIVE A/B SCOOP TU BE LO CK):

Reports alarm to SRO OATC Verifies automatic actions If scoop tube lock is to be reset, refer to Ops Manual Section B.01.04-05.H.2.

SRO Acknowledge s an nun ciator repo rts SRO After report of cause for the lock by RP tech, Directs scoop tube be reset Performs O ps Manual Section B.01.04-05.H.2. Actions:

Coordinates with the Reactor Building Operator to verify that the OATC Adjustable Speed Drive (ASD) indication displays a steady state value of 0000 an d that the ASD RU N pus hbutton light is ON (green).

Resets the Scoop Tube by depressing P/B 2A S2A OATC Resets Annunciator and reports #11 Recirc Scoop Tube is Reset SRO Acknowledge s rep ort SRO May perform crew brie f (P ast, Present, P lan, Po ll)

Append ix D , Re v. 9 Required Operator Actions Form ES -D-2 Op -Test N o.: W 90115 Sce nario No.: 02 Event No.: 03 Page 6 of 16 Eve nt Desc ription: Es sentia l Bus 15 lock out oc curs as dire cte d by the Lead Ex am iner. T he BO P w ill resp ond to the e lectric p lant alarm s, observes 15 bus 0 voltage an d lock out alarm and repo rt to SR O.

The RO will re spond to the loss of the #11 CR D pum p and sta rt the #12 CR D pum p. T he SR O will enter a T .S. LC O reco gnize the requirem ent fo r a no rm al reactor s hutd own .

T ime Position Applicants Actions or Behavior BOP Responds to numerous annunciators on panel C08:

Reports annunciator 8-B-18 (BUS 15 LOCKOUT)

Verify Automatic Actions:

4160V Breakers associated with sources or brea kers tha t could bac kfe ed B us 1 5 T RIP .

(152-501, 152-502, 152-511, 152-308, 152-509)

Enter C.4-B.9.6.C (LOSS OF BUS 15)

BOP Performs Subsequent Operator Action of C.4-B.09.06.C:

Determ ine if Bus 15 is being powered by 1AR or its respective EDG Shutdow n ED Gs n ot required to supply their respective bus IF po wer was lost to B us 1 5, THE N exec ute C .4-B.09.07.C (ABNOR MAL PRO CEDU RES - LOSS OF PO W ER TO LC-103 OR ITS M CCS) concurrently.

IF Bus 15 is de-energized, THEN perform the following:

Place the following control switches in PULL-TO-LOCK:

152-511/CS, 1AR TRANS TO 15 BUS 152-502/CS, 11 STBY DIESEL GEN T O 15 BUS IF an extended loss of Bus 15 is anticipated, THEN consider feeding LC-103 from LC -104 per E.4-07 (RESTO RE LC-103 FRO M LC-104)

BOP Rem ote Shutdown of Diesel from C-08 with Emergency Start signal Present (Ops Man B0.9.08-05)

In the back of Panel C-08, jumper terminals 5 and 6 on the Fast Start relay (95-7 for 11 EDG and/or 95-8 for 12 EDG) of the diesel(s) to be shutdown Place the control switch of the emergency diesel(s) to be shutdown in the PULL-TO-LO CK position.

Rem ove the jum per from terminals 5 and 6 on the Fas t Start relay 95-7 for 11 EDG and/or 95-8 for 12 EDG RO Reports annunciator 5-B-17 (CHARGING W ATER LO PRESS)

Append ix D , Re v. 9 Required Operator Actions Form ES -D-2 Op -Test N o.: W 90115 Sce nario No.: 02 Event No.: 03 Page 7 of 16 Eve nt Desc ription: Es sentia l Bus 15 lock out oc curs as dire cte d by the Lead Ex am iner. T he BO P w ill resp ond to the e lectric p lant alarm s, observes 15 bus 0 voltage an d lock out alarm and repo rt to SR O.

The RO will re spond to the loss of the #11 CR D pum p and sta rt the #12 CR D pum p. T he SR O will enter a T .S. LC O reco gnize the requirem ent fo r a no rm al reactor s hutd own .

RO Performs Imm ediate Operator Actions of C.4-B.01.03.A (LOSS OF CRD PUMP FLOW )

Verify a CRD pum p is running (starts #12 CRD pump)

RO Reports reacto r po we r, pressure and level.

BOP Perform s Su bse que nt O pera tor Ac tions o f C.4 -B.09.07 .C Monitor system operation and take appropriate actions for the following systems:

RBCCW Stator Cooling Drywell Ventilation Service W ater Hydrogen Seal O il IF power to MCC -131 is lost, THEN refer to B.09.02-05.H.3, Less than Full Cooling for Generator Transformer, for permissible transformer loading IF annunciator 8-B-1 (NO. 2R XFMR TROUBLE0 is in ALARM, THEN verify B2145, 2R AUXILIARY XFMR COOLING AUTO TR AN SF OR ME R S W ITC H, has tra nsferred to the alterna te source (MCC-121)

Verify or establish Primary Containment integrity, using the attached tables Verify or establish Secondary Containment integrity, using the attached tables IF po wer is lost to LC-1 03, T HE N re fer to th e attache d tables to determine items of concern:

MCC -131 MCC -132 MCC -133A MCC -134 BOP Performs B.09.02-05.H.3:

IF there is less than full cooling available for the generator transformer, THEN find the permissible load for any combination of pumps and fans out of service by the following method:

Count the total number of fans which are out of service

Append ix D , Re v. 9 Required Operator Actions Form ES -D-2 Op -Test N o.: W 90115 Sce nario No.: 02 Event No.: 03 Page 8 of 16 Eve nt Desc ription: Es sentia l Bus 15 lock out oc curs as dire cte d by the Lead Ex am iner. T he BO P w ill resp ond to the e lectric p lant alarm s, observes 15 bus 0 voltage an d lock out alarm and repo rt to SR O.

The RO will re spond to the loss of the #11 CR D pum p and sta rt the #12 CR D pum p. T he SR O will enter a T .S. LC O reco gnize the requirem ent fo r a no rm al reactor s hutd own .

on the co olers which are still in opera tion (tho se w ith pumps running)

Multiply the tota l num ber of pum ps out of servic e by 3 Add a. and b. (above) to obtain equivalent fans out of service Refer to the following table to obtain permissible load.

NOT E: Loss of MCC -131 results in loss of 7 pumps and 21 fans Permissible load is determined to be 482 MVA / Equivalent Low Side Current KILOAM PS is 12.66 Inform s SR O o f limits SRO Directs lowering of reacto r po we r to achieve <482 MVA or 1 2.6 6 Kilo Am ps SRO Enters T.S. to determine applicable LCOs:

3.7.D.1 Primary Containment Isolation Valves (PCIVs)

During reactor pow er operating conditions, all Prima ry Containm ent autom atic isolation valves and all prim ary system instrument line flow check valves shall be ope rable as s pec ified in 3.7 .C.2 In the event one or more penetration flow paths with two PCIVs inoperable, reactor operation in the run mode m ay continue prov ided that within the s ubs equ ent 1 hou r restore the valves to operable status, or at least one valve in each line having inoperable valves is deactivated in the isolated condition 3.5.A.1 ECCS Systems Except as specified in section 3.5.A.3, both Core Spray subsystems and the Low Pressure Coolant Injections (LPC I) Subsystem (LP CI Mode of RHR Sys tem ) shall be operable whenever irradiated fuel is in the reactor vessel and the reactor water temperature is greater than 212°F If the requiremen ts or conditions of 3.5.A.1, 2, or 3 cannot be m et, a n orderly shutd ow n of the re actor shall be initiated and the reactor shall be placed in a condition in which the affected equipment is not required to be operable within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 3.7.B.1 Standby Gas Treatment System

Append ix D , Re v. 9 Required Operator Actions Form ES -D-2 Op -Test N o.: W 90115 Sce nario No.: 02 Event No.: 03 Page 9 of 16 Eve nt Desc ription: Es sentia l Bus 15 lock out oc curs as dire cte d by the Lead Ex am iner. T he BO P w ill resp ond to the e lectric p lant alarm s, observes 15 bus 0 voltage an d lock out alarm and repo rt to SR O.

The RO will re spond to the loss of the #11 CR D pum p and sta rt the #12 CR D pum p. T he SR O will enter a T .S. LC O reco gnize the requirem ent fo r a no rm al reactor s hutd own .

Two separate and independent standby gas treatment system circuits shall be operable at all times when secondary containment integrity is required, except as spe cified in sec tions 3 .7.B.1 After one of the stan dby gas treatm ent sys tem circ uits is made or found to be inoperable for any reason, reactor operation and fuel handling is permissible only during the succeeding seven days 3.4.A.1 Standby Liquid Control System The standby liquid control system shall be operable at all tim es when fue l is in the rea cto r an d the re actor is not shut dow n by control ro ds, ex cept as specified in 3.4.A .2 From and after the date that a redundant component is made or found to be inoperable, reactor operatio n is perm issible only during the following 7 days provided that the redundant component is operable.

3.9.A.1 Auxiliary Electrical Systems The reactor shall not be made critical unless all the following requirements are satisfied:

At least two (2) NSP transmission lines, ass ociated switchgea r, and at leas t two offsite power sources are fully operational and energized to carry power to the plant 4160V AC buses as follows:

2R and 1R transformers, or 1R and 1AR transformers, or 2R and 1AR transformers (source from 10 transform er)

Bo th diesel generato rs are operable and capable of feeding their designated 4160 volt buses 4160V Buses #15 and #16 are energized 480V L oad C enters #103 and #104 are energized W hen the mode switch is in Run, the availability of electric power shall be as specified in 3.9.A, except as

Append ix D , Re v. 9 Required Operator Actions Form ES -D-2 Op -Test N o.: W 90115 Sce nario No.: 02 Event No.: 03 Page 10 of 16 Eve nt Desc ription: Es sentia l Bus 15 lock out oc curs as dire cte d by the Lead Ex am iner. T he BO P w ill resp ond to the e lectric p lant alarm s, observes 15 bus 0 voltage an d lock out alarm and repo rt to SR O.

The RO will re spond to the loss of the #11 CR D pum p and sta rt the #12 CR D pum p. T he SR O will enter a T .S. LC O reco gnize the requirem ent fo r a no rm al reactor s hutd own .

specified in 3.9.B or the reactor shall be placed in the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SRO Notifies Ops Mgr, Engineering, and Work Control SRO May perform crew brie f (P ast, Present, P lan, Po ll)

Append ix D , Re v. 9 Required Operator Actions Form ES -D-2 Op -Test N o.: W 90115 Sce nario No.: 02 Event No.: 04 Page 11 of 16 Eve nt Desc ription: After the c rew has stabilized con ditions from 15 B us loc kout, the A SRV will open.

The imm ediate actions to close the SRV will be unsuccessful, but when RPV power is lowered and fuses are removed per C.4-B.03.03.A (STUCK OPEN RELIEF VALVE) the SRV will close. The crew m an e lect to initiate a m anu al scram as a con servative a ction.

T im e Position Applicants Actions or Behavior Responds to annunciator 3-A-9 (AUTO BLOW DOW N RELIEF VLV LEAK ING):

BOP Reports alarm to SRO Refers to C.4-B.03.03.B (RELIEF VALVE LEAKING)

Resp onds to ann unciator 5-A-46 (SR V O PEN ):

Reports alarm to SRO Check am ber indicating light on Panel C03 to determine which valve is open.

OATC Refer to C .4 (ABNO RM AL PR OC EDU RES )

Verify proper instrumentation response as required by Technical specification Table 4.14.1, Note 4, per Procedure 0408a (SRV PO SITIO N IND ICAT ION R ESP ON SE C HEC K).

SRO Acknowledge s an nun ciator repo rts Performs Im mediate Operator Actions of C.4.B.03.03:

Place the handswitch for the affected SRV to the OPEN position and then return it to the normal position (Operator cycles A SRV control switch)

IF SRV D, G, or H open, THEN perform the following:

BOP Place their respective switches (2E-S4E, 2E-S4G, 2E-S4H on C-03) in CLOSE.

Place DIV II Lo-Lo SET LOGIC switch (HS-S3B) on Control Room Panel C-253D in BYPASS. (not required for A SRV)

Notify Shift Supervision SRO Acknowledge s an nun ciator repo rts Performs Subsequent Operator Actions:

Mon itor and control Reactor press ure RO If SRV remains open, THEN execute C-4-F (RAPID POW ER RED UC TIO N) conc urrently to reduce R eactor pow er.

SRO Directs lowering of reactor powe r per C.4-F Performs Imm ediate Operator Actions of C.4-F:

RO Redu ce recirculation flow as necess ary

Append ix D , Re v. 9 Required Operator Actions Form ES -D-2 Op -Test N o.: W 90115 Sce nario No.: 02 Event No.: 04 Page 12 of 16 Eve nt Desc ription: After the c rew has stabilized con ditions from 15 B us loc kout, the A SRV will open.

The imm ediate actions to close the SRV will be unsuccessful, but when RPV power is lowered and fuses are removed per C.4-B.03.03.A (STUCK OPEN RELIEF VALVE) the SRV will close. The crew m an e lect to initiate a m anu al scram as a con servative a ction.

IF co re flow is <32 Mlbm /hr, THE N exec ute C .4-B.05.01.02 .A (CONTRO L OF NEUTRO N FLUX OSCILLATIONS) concurrently IF co ndition requ ire initiation of a m anu al scram , TH EN exe cute C.4-K (IMMEDIATE REACTOR SHUTDOW N)

Notify Shift Supervision Performs Subsequent Operator Actions of C.4-F:

Determine if the reactor is operating in the allowed region of the power flow map:

IF an unanalyzed or unallowed region of the power-flow map is entered, THEN imm ediately exit by inserting control rods or changing recirculation flow.

RO If time allow s an d co nditions ha ve stabilized fo r at leas t 5 minutes, demand an Official 3D-Monicore calculation and check therm al lim its. If thermal limit Action Limits are reached, perform the appropriate actio ns per O PS Manual C.2-05.B.1. (this canno t be dem anded from the simu lator)

IF po wer m ust be red uce d further, T HE N ins ert co ntrol rods to position 04 or deeper using RW M Rapid Power Reduction Menu Performs Subsequent Operator Actions of C.4-B.03.03.A:

IF SRVs A, B, C or D are open by an electrical signal RED LIGHT O N), THEN, remove the respective four (4) fuses listed BOP below for the affected SR V(s):

Directs the Reactor Building Operator to remove the following fuses located in the Cable Spreading Room Panel C-32:

2E-F3A, 2E-F4A, 2EF7A, 2EF8A Tw o m inutes after th e direction, the Reac tor Bu ilding O pera tor rep orts BOP that the fuses are pulled and the BOP observes that the A SRV indicates closed.

SRO Acknowledges report and directs reactor power reduction to be stopped.

Reviews T.S. and determines 1 ADS valve inoperable and enter s a 14 SRO day LCO per 3.5.A.3.h.

SRO Notifies Ops Mgr, Engineering, and Work Control SRO May perform crew brie f (P ast, Present, P lan, Po ll)

Append ix D , Re v. 9 Required Operator Actions Form ES -D-2 Op -Test N o.: W 90115 Sce nario No.: 02 Event No.: 05 Page 13 of 16 Eve nt Desc ription: A leak develops in the D rywell. Th e BO P will observ e an d rep ort Drywell leak age ,

tem pera ture, and p ressure rising . SRO d irects reac tor sc ram .

T ime Position Applicants Actions or Behavior Reports annunciator 4-B-35 (DRYWELL - TOR US HI PRESS)

Check Drywell and Torus pressure indicated by PR-2994 on C04 Check the following indications to determine if a primary system leak in the Drywell exists:

Drywell Particulate level indicated by RR-7993 on C02 Drywell Equipm ent and F loor Drain Sum p levels indicated by LR-7409 on C04 BOP Drywell Equipment and Floor drain Sump Pump flows indicated by FR-2544 on C04 Drywell and Torus air temperature (TR 23-15 on C21)

Drywell radiation level indicated by RI-7860A on C257 and RI-7860B on C258 IF primary syste m leak age is indica ted, T HE N re fer to C .4 (AB NO RM AL OP ER AT ING PR OC ED UR ES) AN D A .2 (EMERGENCY PRO CEDURES)

Performs Subsequent Operator Actions of C.4-B.04.04.F:

Mon itor Drywell pressure a nd tem perature IF Drywell pressure or temperature is rising, THEN determine status of operating Drywell coolers, AND place the standby Drywell cooler in service IF the UNIDENTIFIED LEAK RATE has increased, THEN perform the following:

BOP Monitor RBCC W surge Tank level and discharge pressure Mon itor Recirc Pum p Seal pressu re If the change in unidentified leak rate has increased by more than 0.5 gpm within any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period, THEN notify the Operations Manager, AND Manager System Engineering Re fer to T ech Spe c 3.6.D Repo rts Drywell tem perature and p ressure ap proaching E OP entry BOP conditions SRO Directs reactor scram per C.4-K

Append ix D , Re v. 9 Required Operator Actions Form ES -D-2 Op -Test N o.: W 90115 Sce nario No.: 02 Event No.: 06 Page 14 of 16 Eve nt Desc ription: W hen the SRO dire cts a re actor scram , the RO will insert a m anual rea cto r scram ,

and observe and report all rods NOT fully inserted and reactor power >3%. EOPs 1100 (RPV CON TRO L), 1200 (PRIMARY CON TAINMEN T CO NTR OL) AND 2007 (FAILURE TO SCRAM ) are entered due to drywell conditions and failure to scram. The initiation of the ATW S (ARI) system will be suc ces sful and a ll control rods will insert. EOP 2007 will be e xited a nd E OP 110 0 will be re -ente red.

Drywell cooling, Torus spray and Drywell sprays will be initiated. W hen plant conditions are stable with D rywell Sp rays secu red, the sc ena rio is co m plete.

T im e Position Applicants Actions or Behavior Performs Immediate Operator Actions of C.4-K (IMMEDIATE REACTOR SHUDOW N)

RO Initiate a MANUAL REAC TOR SCRAM by depressing REACTO R SCRAM A and B pushbuttons (5A-S3A AND 5A-S3B), then enter C.4-A (REACTOR SCRAM)

Performs Imm ediate Operator Actions of C.4-A:

Places reactor mode switch in shutdown RO Determine if all control rods are inserted to or beyond position 04 Reports reactor scram, mode switch in shutdown, all rods NOT inserted, reactor powe r is > 3% (or m ay provide indicate d pow er level)

Reports EOP entry conditions based upon drywell pressure and/or BOP tem perature SRO Enters EOPs 1100, 1200, 2007 Directs:

ADS inhibited SRO MSIV low low water level isolation bypassed Prevention of Core Spray Reac tivity control per hard card Performs actions:

Inhibits ADS by placing both ADS inhibit switches in bypass Bypasses MSIV isolation by placing all 4 key lock switches on back panel to bypass BOP Prevents injec tion from Co re Spray:

Place CS INJECTION BYPASS switch to BYPASS Close CS INJECTION O UTBO ARD valves Close CS INJECTION INBOA RD valves

Append ix D , Re v. 9 Required Operator Actions Form ES -D-2 Op -Test N o.: W 90115 Sce nario No.: 02 Event No.: 06 Page 15 of 16 Eve nt Desc ription: W hen the SRO dire cts a re actor scram , the RO will insert a m anual rea cto r scram ,

and observe and report all rods NOT fully inserted and reactor power >3%. EOPs 1100 (RPV CON TRO L), 1200 (PRIMARY CON TAINMEN T CO NTR OL) AND 2007 (FAILURE TO SCRAM ) are entered due to drywell conditions and failure to scram. The initiation of the ATW S (ARI) system will be suc ces sful and a ll control rods will insert. EOP 2007 will be e xited a nd E OP 110 0 will be re -ente red.

Drywell cooling, Torus spray and Drywell sprays will be initiated. W hen plant conditions are stable with D rywell Sp rays secu red, the sc ena rio is co m plete.

Performs Reactivity Hard Card actions:

Verifies mode switch in shutdown Runs recirc pum ps back to minimum speed RO Trips both recirc pumps Activates ATWS Inserts control rods per C.5-3101 RO Reports all control rods fully inserted SRO Exits EOP 2007 and re-enters EOP 1100 SRO Directs drywell cooling initiated per C.5-3503 Initiates drywell cooling:

Place fan sw itches in off BOP Byp ass E CCS fan trip Starts fans (only 2 & 4 are available)

Report drywell cooling in service SRO Directs Torus Spray initiation per C.5-3502 Initiates torus sprays:

Place CNTMN T 2/3 height C/S to bypass Place CNTMN T Spray/Cooling LPCI initiation C/S to bypass Open MO -2006 BOP Open MO -2010 Throttle open MO-2008 Line up RHRSW Report torus spray in service Observes drywell temperature and pressure continuing to rise and SRO directs drywell sprays per C.5-3502 Initiates drywell sprays:

BOP Place CNTM NT 2/3 height C/S to bypass

Append ix D , Re v. 9 Required Operator Actions Form ES -D-2 Op -Test N o.: W 90115 Sce nario No.: 02 Event No.: 06 Page 16 of 16 Eve nt Desc ription: W hen the SRO dire cts a re actor scram , the RO will insert a m anual rea cto r scram ,

and observe and report all rods NOT fully inserted and reactor power >3%. EOPs 1100 (RPV CON TRO L), 1200 (PRIMARY CON TAINMEN T CO NTR OL) AND 2007 (FAILURE TO SCRAM ) are entered due to drywell conditions and failure to scram. The initiation of the ATW S (ARI) system will be suc ces sful and a ll control rods will insert. EOP 2007 will be e xited a nd E OP 110 0 will be re -ente red.

Drywell cooling, Torus spray and Drywell sprays will be initiated. W hen plant conditions are stable with D rywell Sp rays secu red, the sc ena rio is co m plete.

Place CNTM NT Spray/Cooling LPCI initiation C/S to bypass Open M O-2021 Open M O-2023 Verify closed MO-2009 Verify closed MO -2012 & MO-2013 Directs securing torus and/or drywell sprays when containment SRO pressu re low ers to 2 ps ig Continues to monitor drywell temperature and pressure and BOP controls sprays as directed and manually secures Drywell Spray before Drywell pressure goes below 0 psig.

SRO May perform crew brie f (P ast, Present, P lan, Po ll)

Append ix D , Re v. 9 Scenario Outline Form ES -D-1 Facility: MNGP Sce nario No.: 3 Op -Test N o.: W 90115 Exam iners: Operators:

Initial Conditions: Approximately 100% reactor power. Normal electrical lineup. HPCI is inoperable due to planned m ainten anc e on the aux o il pum p an d is sc hed uled to be return ed to service tom orrow.

Surveillance test 0225-14-IA-1, Reactor Water Cleanup Valve Operability and Position Indication Te sts is to be perform ed.

Tu rnover: Perform surveillance test 0225 IA-1.

Event M alf. Event Event No. No. Type* Description 1 CH07B C (RO) CRD F CV fails closed N/A N (BOP) Perform test 0225-14-IA-1 (shuts down RWCU) 2 DS165- C (BOP) MO -2398 closure outside required range 02 (SRO) T.S. LC O en try due to test failure 3 FW 20A C (RO) A FW REG valve lock up and subsequent reset 4 B54 (SRO) Loss of power to Alternate S/D panel, T.S. LCO C (BOP) RFP bearing high temp / vibration FW 15A 5 RFP Rem ove from service FW 16A R (RO) Rapid Power Reduction to 50%

TU03D C (BOP) Main turbine vibrations with failure to auto trip TU03E 6 Turbine Bypass Valves Failure to Open TC07B M (ALL) Scram due to turbine vibrations(ATW S)

TC07D PP04 ATW S, EO P 1100 , 1200, & 2007 e ntry 7

PP06 Level Power control and SBLC injection required

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Append ix D , Re v. 9 Required Operator Actions Form ES -D-2 Op -Test N o.: W 90115 Sce nario No.: 03 Event No.: 01 Page 2 of 12 Eve nt Desc ription: The RO may recognize CRD flow indications lowering or after about 2 minutes respond to annunciator 5-B-41 (CRD H I TEMPERA TUR E) and diagnose a failure of the in service CR D F CV . Action s to swap the in service CRD FC V will be initiated pe r B.01 .03.

T ime Position Applicants Actions or Behavior RO Resp onds to ann unciator 5-B-41 (C RD HI TE MP ERA TU RE):

Directs the Reactor Building Operator to determine the high temperature CRD by monitoring TR-3-244 at Panel C-59 Refers to B.01.03 (CRD HYDRAULIC SYSTEM SYSTEM OPERATION)

Notify Shift Supervision and System Engineer SRO Acknowledges report, direct swap to the B FCV RO Performs actions to swap FCV per B.01.03:

If, CRD Flow Control Valve B, CV-3-19B, is in standby, and CR D Flow C ontrol Valve, CV-3-19A, is in service, Then pe rform the following:

Open valve CRD-18-2, Flow Control Valve CV-3-19B Outlet Isolation. (Out Plant Action)

Open valve CRD-16-2, Flow Control Valve CV-3-19B Inlet Isolation. (Out Plant Action)

Place CRD Flow Controller, FC-3-301, to manual Close CV-3-19A with CRD Flow Controller At Panel C-05 , place the CRD Flow Con trol Valve Selector Switch to the B flow control valve position Slowly open CV-3-19B while monitoring system pressures with CRD flow controller to obtain desired flow. If recirc pump seal injection is in service, desired flow is 54 to 56 gpm minus 0.4 gpm for each isolated HCU.

Plac e CRD Flow Control in auto Close valve CRD-18-1, Flow Control Valve CV-3-19A Outlet Isolation. (Out Plant Action)

Close valve CRD-16-1, Flow Control Valve CV-3-19A Inlet Isolation. (Out Plant Action)

RO Reports CRD FCV B in service SRO Ack nowledges Repo rt SRO Notifies Ops Mgr, Engineering, and Work Control

Append ix D , Re v. 9 Required Operator Actions Form ES -D-2 Op -Test N o.: W 90115 Sce nario No.: 03 Event No.: 02 Page 3 of 12 Eve nt Desc ription: Performance of Surveillance test 0255-14-IA-1, Reactor Water Cleanup Valve Operability and Position Indication Tests is to be executed. A marked up copy of the test to provide Shift Manager approval to comm ence, reason for performance and prerequisites will be provided. The test requires the RW CU system be removed from service via normal procedure B.02.02-05. During the performance of the test MO-2398 stroke time will exceed the allowed time, which will result in the term ination of the test and a T.S . LCO e ntry.

T ime Position Applicants Actions or Behavior BOP Reviews tes ting requiremen ts and steps to perform SRO Conducts or insures a pre-job brief per OW I-01.09 is performed:

Obtains an existing pre-job brief from the data base OR Uses the OPERATIONS PRE-JOB BRIEFING GUIDE BOP Performs Step 1 of test 0225-14-IA-1:

IF the Reactor W ater Cleanup system is in operation, THEN place bo th filter-de m ineralizer units in H OL D, A ND ST OP both cleanup recirculation pumps using Ops Man B.02.02-05 (REACTOR W ATER CLEANUP - SYSTEM OPERATION)

Direct Reactor Building Operator to remove RW CU Filter/Dem ineralizers A and B and place in HOLD Stops #11 and #12 RW CU pum ps BOP Responds to annunciator 4-B-21 (CLEAN UP FILTER DEMIN FAILURE)

Check RW CU Filter Demin Panel C-82 to determine alarm received Alarm received due to testing event, expected BOP Perform s Ste p 3 of test:

CLO SE valve M O-23 97, RW CU Inlet Inboard Isol, and record closing time.

OPEN Valve MO-2397 and record opening time.

BOP Perform s Ste p 5 of test:

CLO SE valve M O-23 98, RW CU Inlet Outboard Isol, and record closing tim e Observes and reports to SRO that closing time was >22 seconds and exceeded LST tim e SRO Acknowledges report, directs test to be stopped and declares MO-2398 inoperab le and review T.S . 3.7.D .1 During reactor pow er operating conditions, all Prima ry Containment automatic isolation valves and all primary system instrument line flow check valves shall be operable except as spe cified in 3.7.D .2 3.7.D .2.a: In the event one o r m ore p ene tration flow paths with one PCIV inoperable, reactor operation in the run mode m ay continue provided that within the subseque nt 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> (8 hou rs for M SIVs an d 72 hou rs for EF CV s) restore the va lve to operable status, or at least one valve in each line having an inoperable valve is deactivated in the isolated condition SRO Notifies Ops Mgr, Engineering, and Work Control

Append ix D , Re v. 9 Required Operator Actions Form ES -D-2 Op -Test N o.: W 90115 Sce nario No.: 03 Event No.: 03 Page 4 of 12 Eve nt Desc ription: The A Feed Regulating Valve will lock up. Annunciator 5-B-40 (FW CON TRO L VALVE LOC KED) will alarm. W ith the plant at steady state conditions, RPV water level will not be impacted and the B RFV will maintain RPV water level stable. The RO should enter and use procedure C.4-B.05.07.A to reset the lock out condition and then return the FW REG valve to autom atic co ntrol.

T ime Position Applicants Actions or Behavior RO Resp onds to ann unciator 5-B-40 (FW CO NT RO L VAL VE LO CKE D):

Reports alarm to SRO Monitor Reactor water level IF Reactor water level is NOT being maintained by the Reactor W ater L evel Con trol Syste m , TH EN refer to C.4-B.05.07.A (ABNORMAL PRO CEDURE - LOSS OF REACTOR W ATER LEVEL CO NTR OL)

IF Reactor water level is being controlled manually, THEN one Operator shall be assigned to monitor and control Reactor water level.

IF amber RESET lights for CV-6-12A (6A-S3A) and CV-6-12B (6A-S3B) are no t illuminated , AN D A nnu nciator B-5-32 (MAIN STEAM LEAKAGE) is also in ALARM, TH EN refer to C.4-B09.13.E (ABNOR MAL PRO CEDU RE - LOSS O F Y-30)

RO Performs Imm ediate Operator Actions of C.4-B.05.07.A:

Control Reactor level in MANUAL using any unlocked FW REG valve M/A station.

Notifies SRO RO Performs Subsequent Operator Actions of C.4-B.05.07.A:

IF both FW REG valves are locked up, THEN reset one valve as follows: (only one FW REG valve is locked)

IF level control cannot be restored from the Control room, THEN dispatch an operator to take local manual control of the locked FW REG valve IF additional actions are required to control Reactor level, THEN use any or all of the following:

FW LOW flow valve RW CU reject Recirc pump speed adjustment Throttling of FW Block valves MO-1133 and MO-1134 IF one of the FW REG valves is locked up, AND an attempt has NOT been made to reset the lockup, THEN perform the following to re set it:

Verify M/A station in MANUAL Verify M/A station output meter is at the black m em ory pointer Verify no major air leakage at the valve Depress the reset pushbutton for the affected FW REG valve IF a FW REG valve is still locked up, THEN take local manual control per B.05.07-05 (REACTOR LEVEL CON TRO L -

SYSTEM OPERATION)

Append ix D , Re v. 9 Required Operator Actions Form ES -D-2 Op -Test N o.: W 90115 Sce nario No.: 03 Event No.: 03 Page 5 of 12 Eve nt Desc ription: The A Feed Regulating Valve will lock up. Annunciator 5-B-40 (FW CON TRO L VALVE LOC KED) will alarm. W ith the plant at steady state conditions, RPV water level will not be impacted and the B RFV will maintain RPV water level stable. The RO should enter and use procedure C.4-B.05.07.A to reset the lock out condition and then return the FW REG valve to autom atic co ntrol.

Control Reactor level between 30 and 40 inches Notify the System Engineer to investigate the cause and correct if po ssible W HEN the cause has been corrected, THEN restore Reactor Level Control to automatic per B.05.07-05 RO Reports alarm 5-B-40 reset RO Reports FW REG valve lock up reset SRO Directs FW RE G valve be returned to autom atic RO Performs action of B.05.07.A to return the FW REG valve to automatic:

IF one Feedwater Control MAN/AUTO Station is in MANUAL and the other is in AU TO and autom atic co ntrol of both Feedwater Regulating valves is possible and desired, THEN perform the following:

Maintain Reactor Water Level between +30 and +40 inches If the Vessel Level Master Co ntroller, 6-83, is in MANU AL, place it in AUTO by performing the following:

Adjust setpoint dial on Vessel Level Master station, 6-83, to place the deviation meter needle in the green band, THEN place the Vessel Level Master station, 6-83, in AUTO Slowly adjust the Feedwater Control MAN/AUT O station that is in MANU AL until the stations output on the horizontal scale approximately matches the demand signal on the sta tion s vertica l scale Pla ce the Fe edwa ter Co ntrol M AN /AU TO Sta tion in AUTO Verify automatic control properly maintains desired level RO Reports that the A FW REG valve is in automatic control SRO Notifies Ops Mgr, Engineering, and Work Control SRO May conduct c rew brief (P ast, Present, P lan, Po ll)

Append ix D , Re v. 9 Required Operator Actions Form ES -D-2 Op -Test N o.: W 90115 Sce nario No.: 03 Event No.: 04 Page 6 of 12 Eve nt Desc ription: Annunciator 5-B-54, ASDS TRAN SFER SW ACTVD OR PW R FAIL alarms due to a trip of supply breaker Circuit 14 on Y-80. The RO will send the outplant operator to investigate and the S RO will enter T ech nical Specifications to determ ine the LCO.

T ime Position Applicants Actions or Behavior RO Responds to annunciator 5-B-54 (ASDS TRANSFER SW ACTVD OR PW R FA IL):

Reports alarm to SRO Determ ines cause of alarm If power failure is cause, then dispatch operator to the EFT building, and direct operator to verify the following power supplies are available:

Y-80 Circit 14 D-100 Circuit 14 C-292 fuses SRO Notifies the following per the ARP:

Shift Supervision System Engineer Plant Electrician SRO Refers to Technical Specifications 3.13.A:

3.1 3.A .1: T he system controls on the AS DS panel shall be operable whenever that system/component is required to be operable 3.13.A.2: If system controls required to be operable by Specification 3.13.A.1 are made or found to be inoperable, restore operability within 7 days, or perform one of the following; Provide equivalent s hutdo wn capability and with in 60 days restore the inoperable system controls to operable; or Establish a continuous fire watch in the cable spreading room and the back-panel are a of the control roo m and within 60 days restore the inoperable system controls to operable; or Verify the operability of the fire detectors in the cable spreading room and the back panel area of the control room and establish a hourly fire watch patrol and within 60 days restore the inoperable system controls to operable; or Place the reactor in a condition where the systems for which the system con trols at the ASD S are inop erab le are not required to be operable within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SRO May conduct c rew brief (P ast, Present, P lan, Po ll)

Append ix D , Re v. 9 Required Operator Actions Form ES -D-2 Op -Test N o.: W 90115 Sce nario No.: 03 Event No.: 05 Page 7 of 12 Eve nt Desc ription: The #11 Reactor Feed Pump (RFP) will degrade. Alarms 6-A-26 (RFP BEARING HIGH TEMP) and 6-A-1 (RFP HIGH VIBRATION) will provide warning to the crew. The initial RFP vibration report will be 4.8 mils, which requires power reduction and RFP trip. Reactor power will be lowered rapidly to <50% , the RFP w ill be tripped. C.4-F (R APID P OW ER R EDU CT ION) an d C.4-B.05 .01.02.A (N EU TR ON FLU X O SC ILLA TIO NS ) will be en tered .

T ime Position Applicants Actions or Behavior BOP Resp onds to ann unciator 6-A-26 (R FP B EAR ING H IGH T EM P):

Reports alarm to SRO Monitors TR-1712 (Panel C-20) and determine affected bearing(s)

Dispatch T.B. operator to the Turbine Building Monitor affected Reactor Feed Pump vibration (Panels C-297A and C-297B)

Ve rify adequate Re actor Fe ed Pum p lube oil flo w and lube oil cooling. Refer to B.6.5-05 (CONDENSATE AND REACTOR FEE DW ATE R - SY TEM OP ERA TIO N) and p erform concu rrently with this proced ure Notify System Engineer BOP Responds to annunciator 6-A-1 (RCT FEED PUMP P-2A HIGH VIBRA TIO N):

Reports alarm to SRO Dispatc h an Op erato r to investigate IF the Operator reports that the vibration level is in the ALERT range (2.5 to 4.5 Mils), THEN notify the Shift Supervision and System Engineer IF the Operator reports that the vibration level is in the DANGER range (>4.5 Mils), THEN perform the following:

Reduce Rx power per C.4-F (RAPID POW ER REDUCTION W HEN R x Power is < 50%, THEN TRIP 11 RFP Notify System Engineer SRO Directs Rapid Power Reduction per C.4-F to 50%, then trip #11 RFP RO Performs Imm ediate Operator Actions of C.4-F:

Redu ce recirculation flow as necess ary IF co re flow is <32 Mlbm /hr, THE N exec ute C .4-B.05.01.02 .A (CONTRO L OF NEUTRO N FLUX OSCILLATIONS) concurrently IF co ndition requ ire initiation of a m anu al scram , TH EN exe cute C.4-K (IMMEDIATE REACTOR SHUTDOW N)

Notify Shift Supervision RO Performs Subsequent Operator Actions of C.4-F:

Determine if the reactor is operating in the allowed region of the power flow map:

IF an unanalyze d or un allowe d re gion of the pow er-flow m ap is entered, THEN imm ediately exit by inserting control rods or changing recirculation flow.

If time allow s an d co nditions ha ve stabilized fo r at leas t 5

Append ix D , Re v. 9 Required Operator Actions Form ES -D-2 Op -Test N o.: W 90115 Sce nario No.: 03 Event No.: 05 Page 8 of 12 Eve nt Desc ription: The #11 Reactor Feed Pump (RFP) will degrade. Alarms 6-A-26 (RFP BEARING HIGH TEMP) and 6-A-1 (RFP HIGH VIBRATION) will provide warning to the crew. The initial RFP vibration report will be 4.8 mils, which requires power reduction and RFP trip. Reactor power will be lowered rapidly to <50% , the RFP w ill be tripped. C.4-F (R APID P OW ER R EDU CT ION) an d C.4-B.05 .01.02.A (N EU TR ON FLU X O SC ILLA TIO NS ) will be en tered .

minutes, demand an Official 3D-Monicore calculation and check therm al lim its. If thermal limit Action Limits are reached, perform the appropriate actio ns per O PS Manual C.2-05.B.1. (this canno t be dem anded from the simu lator)

IF power must be reduced further, THEN insert control rods to position 04 or deeper using RW M Rapid Power Reduction Menu BOP At #50% power, trips #11 RFP RO Performs Imm ediate Operator Actions of C.4-B05.01.02.A:

IF core flow is #32 M lbm /hr, THE N determ ine if the stability BUFFER or EXCLUSION regions have been entered IF neutron flux oscillation s are observe d fo r an y rea son while operating in the stability BUFFER or EXCLUS ION regions, THEN initiate a MANUAL REACTO R SCRAM Notify Shift Supervision RO Performs Subsequent Operator Actions of C.4-B.01.02.A:

IF the stability EX CL US ION region is en tered , OR the stability BUFFER region has been entered in an uncontrolled fashion, THEN imm ediately perform either of the following until the Reactor is operating outside of the stability BUFFER region:

Incre ase Recircu lation flow , OR Insert control rods using C.4-F (RAPID POW ER REDUCTION)

IF Reactor power is oscillating in response to pressure control perturbations, THEN refer to B.05.09-05 (MAIN STEAM PRESSURE CONTROL - SYSTEM OPERATION)

IF an unanalyze d or un allowe d re gion on the Pow er-Flow m ap is entered that is not part of the stability EXCLUSION or BUFFER regions, THEN imm ediately exit by inserting control rods or changing recirculation flow SRO Notifies Ops Mgr, Engineering, and Work Control SRO May conduct c rew brief (P ast, Present, P lan, Po ll)

Append ix D , Re v. 9 Required Operator Actions Form ES -D-2 Op -Test N o.: W 90115 Sce nario No.: 03 Event No.: 06 Page 9 of 12 Eve nt Desc ription: The rap id power chan ge results in ma in turbine bearing vibrations. Annunciator 7-B-33 (TUR B VIBRATION H IGH) will alarm. Vibrations will continue to rise requiring the crew to scram and initiate a turb ine trip.

T ime Position Applicants Actions or Behavior BOP Resp onds to ann unciator 7-B-33 (T UR B VIBR ATIO N H IGH):

Reports alarm to SRO Monitors Turbine vibration as indicated on VR-1716 (Panel C-07)

IF T urbine vibra tion rem ains at 10 Mils, T HE N re fer to C .3 (SHUTD OW N PRO CEDU RES), AND remove the Turbine-Generator from service IF T urbine vibra tion is rising, THE N re fer to C .4-F (RA PID POW ER RED UCT ION), AND remove the Turbine-Generator from service, W HEN reactor power has been reduced to 15%

power IF Turbine vibration approaches 15 Mils, THEN perform the following:

Reduce recirculation flow to minimum Initiate a manual Reactor scram Manually trip the Turbine-Generator Notify Shift supervision and System Engineer BOP Reports tu rbine vibration s rising on 3 bearings and approaching 15 Mils SRO Direct R eacto r Scram per C.4-K and Turbine-Generato r trip

Append ix D , Re v. 9 Required Operator Actions Form ES -D-2 Op -Test N o.: W 90115 Sce nario No.: 03 Event No.: 07 Page 10 of 12 Eve nt Desc ription: An ATW S condition will exist when a reactor scram is initiated. The main turbine will autom atically trip (if not m anu ally tripped) on h igh vibrations . The turb ine bypass valves will fail to open resulting in significant energy addition to the torus and reactor power / level swings. EOPs 1100 (RPV CONTROL), 1200 (PRIMARY CONTAINMENT CONTROL) and 2007( FAILURE TO SCRAM) will be entered. Alternate control rod insertion actions will allow individual rods to be inserted and level/p ow er control will be utilize d to control re actor powe r. T he autom atic RC IC flow controller fails downscale requiring manual operation to raise RPV water level after SBLC has been initiated and hot shutd ow n boron weight has been achieved. The scenario is term inated when RP V w ate r level is returned to +9 - +48 inches.

T ime Position Applicants Actions or Behavior RO Performs Immediate Operator Actions of C.4-K (IMMEDIATE REACTOR SHUDOW N)

Initiate a MANUAL REAC TOR SCRAM by depressing REACTO R SCRAM A and B pushbuttons (5A-S3A AND 5A-S3B), then enter C.4-A (REACTOR SCRAM)

RO Performs Imm ediate Operator Actions of C.4-A:

Places reactor mode switch in shutdown Determine if all control rods are inserted to or beyond position 04 Reports reactor scram, mode switch in shutdown, all rods NOT inserted, reactor power is >3% (or may provide indicated power level)

BOP Reports turbine trip, failure of TBPVs to open BOP Repo rts EOP entry conditions bas ed upon torus tem perature SRO Enters EOPs 1100 (RPV CONTROL), 1200 (PRIMARY CONTAINMENT CONTROL) and , 2007 (FAILURE TO SCRAM)

SRO Directs:

ADS inhibited MSIV low low water level isolation bypassed Prevention of Core Spray Rea ctivity co ntrol per ha rd card BOP Performs actions:

Inhibits ADS by placing both ADS inhibit switches in bypass Bypasses MSIV isolation by placing all 4 key lock switches on back panel to bypass Prevents injec tion from Co re Spray:

Place CS INJECTION BYPASS switch to BYPASS Close CS INJECTION O UTBO ARD valves Close CS INJECTION INBOA RD valves RO Performs R eactivity Hard Card actions:

Verifies mode switch in shutdown Runs recirc pumps back to minimum speed Trips both recirc pumps Activates ATWS Takes actions per C.5-3101 De-energize scram logic by taking RPS system

Append ix D , Re v. 9 Required Operator Actions Form ES -D-2 Op -Test N o.: W 90115 Sce nario No.: 03 Event No.: 07 Page 11 of 12 Eve nt Desc ription: An ATW S condition will exist when a reactor scram is initiated. The main turbine will autom atically trip (if not m anu ally tripped) on h igh vibrations . The turb ine bypass valves will fail to open resulting in significant energy addition to the torus and reactor power / level swings. EOPs 1100 (RPV CONTROL), 1200 (PRIMARY CONTAINMENT CONTROL) and 2007( FAILURE TO SCRAM) will be entered. Alternate control rod insertion actions will allow individual rods to be inserted and level/p ow er control will be utilize d to control re actor powe r. T he autom atic RC IC flow controller fails downscale requiring manual operation to raise RPV water level after SBLC has been initiated and hot shutd ow n boron weight has been achieved. The scenario is term inated when RP V w ate r level is returned to +9 - +48 inches.

subchannel test switches to TEST Increase cooling water differential pressure and use RMCS to insert control rods SRO Directs SBLC injection RO Initiates SBLC:

Turns C /S to either system 1 or system 2 Verifies RWCU trips and the following valves closed MO -2397 MO -2398 MO -2399 Selected pump running light on Disc harg e pressu re sligh tly high er than reactor p ressu re SBLC tank level lowering SRO Observes the following:

RPV water level above -126 inches SRVs open Torus tem perature abo ve 110 °F SRO D ire cts prevent R PV injection from :

Condensate & Feedw ater HPCI LPCI BOP Prevents RPV injection:

Condensate & Feedw ater Verify closed A main feed reg valve Verify closed B main feed reg valve Verify closed low flow feed reg valve HPCI If not running, place aux oil pump in PTL If running:

Trip and hold P/B Verify stopped Place aux oil pump in PTL W ait 5 seco nd s, release P/B Verify HO-7 remains closed LPCI Op en knife sw itches to byp ass LPCI 5 min se al in Close LPCI INJ OTBD valves Reports systems are prevented to SRO SRO Directs the following parameters monitored and reported:

Append ix D , Re v. 9 Required Operator Actions Form ES -D-2 Op -Test N o.: W 90115 Sce nario No.: 03 Event No.: 07 Page 12 of 12 Eve nt Desc ription: An ATW S condition will exist when a reactor scram is initiated. The main turbine will autom atically trip (if not m anu ally tripped) on h igh vibrations . The turb ine bypass valves will fail to open resulting in significant energy addition to the torus and reactor power / level swings. EOPs 1100 (RPV CONTROL), 1200 (PRIMARY CONTAINMENT CONTROL) and 2007( FAILURE TO SCRAM) will be entered. Alternate control rod insertion actions will allow individual rods to be inserted and level/p ow er control will be utilize d to control re actor powe r. T he autom atic RC IC flow controller fails downscale requiring manual operation to raise RPV water level after SBLC has been initiated and hot shutd ow n boron weight has been achieved. The scenario is term inated when RP V w ate r level is returned to +9 - +48 inches.

RPV water level reaches -126 inches Reactor power <3%

SRVs rem ain closed RO Reports reactor power (or RPV water level) is <3%, continues control rod insertion SRO Directs RPV water level be maintained between the current level and

-149 inches BOP Recognizes RCIC running at minimum speed, reports to SRO, takes manual control SRO Directs torus cooling BOP Initiates torus cooling:

Verifies RHR pum ps running Opens MO -2007, MO-2009, Close MO-2003 Opens MO -2006, MO-2008, Close MO-2002 RO Reports S BL C tank le vel is at hot sh utd own boron weight (1040 gal)

SRO Directs RPV water level be restored and maintained to +9 - +48 inches BOP Slo wly injec ts to RP V by:

Raising RCIC flow rate and/or Injec ting from feed and con den sate

Append ix D , Re v. 9 Scenario Outline Form ES -D-1 Facility: MNGP Sce nario No.: 4 Op -Test N o.: W 90115 Examiners: Operators:

Initial Conditions: Approximately 20% reactor power with a startup in progress. Current step in procedure C.1 is VIII.A.3. The initial next task to support the startup is to transfer control to the A main FW REG valve from the Low flow FW REG valve. Normal electrical lineup. HPCI is inoperable due to m ainten anc e on the aux o il pum p an d is sc hed uled to be return ed to service tom orrow.

Tu rnov er: Co ntinue reac tor startup.

Even M alf. Event Event t

No. Type* Description No.

1 N/A N (RO) Trans fer to A FW REG valve from L ow Flow V alve R (RO) Continue power rise with control rods 2 CH02 C (RO) W ithdrawal of CRD with High Drive Pressure I (RO) RPS EPA b kr failure 3 PP01A Xfer RPS to A lt powe r supply (SRO) T.S. LC O for EP A bkr failure 4 SW 01A C (BOP) Respond to R BC CW pum p trip C (BOP) High F.W . conductivity, scram, start RCIC, shutdown MC 01A /B Cond ensate & F eedwa ter, close MSIVs, and shutdown Circ 5 water MC 02A /B SRO T.S . LCO d ue to RP V co ndu ctivity EO P 1100 , 1200 entry Feed water block valve fail to open 6 RR01B M(ALL) Low flow FRV fail closed Break on recirc line (ramp). Drywell temperature / pressure rise, Place torus and drywell sprays in service RCIC flow controller failure in auto , tak e m anual control, subsequent R CIC trip 7 RC03 C (BOP)

Initiate 2 CRD pump and SBLC injection Em ergency RPV Depressurization due to low RPV water level

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op -Test N o.: W 90115 Sce nario No.: 04 Event No.: 01 Page 2 of 18 Eve nt Desc ription: A reacto r startu p is in progre ss w ith initial cond itions being ~20% pow er. Current step of C.1 (STARTUP) is VIII.A.3. The initial task will be to transfer control to the A main FW Reg valve from the Low F low FW Re g valve and contin ue to raise re actor powe r by w ithd rawing control rods .

T ime Position Applicants Actions or Behavior SRO Conducts shift brief SRO Directs o ne F W RE G valve be plac e in se rvice.

BEFORE feed flow exceeds the capacity of CV-6-13, Low Flow FW Reg valve (about 20%), THEN transfer control to one of the Main FW RO Reg valves per B.05.07-05 (REACTOR LEVEL CON TROL - SYSTEM OPERATION)

Refers to B.05.07-05 (Transfer of Level Control From FW LOW FLOW REG C V-6-13, to A MAIN FW REG VA LVE CV-6-12A, and verifies prerequisite conditions:

RO CV-6-13 Manual Loading Station Low Flow Valve (6-85) controlling level in AUTO A M ain FW Reg Vlv, C V-6-12A is not LOC KED (C V-6-12A /B Lock Reset PB 6A-S3A (Panel C-05) is OFF Continues with Operator Actions of procedure B.05.07-05:

Verify the following initial conditions:

MO-1133, Hp Fw Line A Block Valve is CLOSED CV-12A F eedw ate r Control M/A S tatio n (6 -84A ) is in MANUAL CV-6-12A controller (6-84A) output reading ZERO (horizontal scale)

CV-6-12A controller (6-84A) bias control reading ZER O, O R slightly negative RO CV-6-12B controller (6-84B) is in MANUAL CV-6-12B controller (6-84B) output reading ZERO (horizontal scale)

CV-6-12B controller (6-84B) bias control reading ZER O, O R slightly negative Ve ssel Level (F eedw ate r) M aster Co ntrol (6 -83) is in MANUAL Master Control (6.83) output reading is ZERO (horizontal scale)

OPEN MO-1133

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op -Test N o.: W 90115 Sce nario No.: 04 Event No.: 01 Page 3 of 18 Eve nt Desc ription: A reacto r startu p is in progre ss w ith initial cond itions being ~20% pow er. Current step of C.1 (STARTUP) is VIII.A.3. The initial task will be to transfer control to the A main FW Reg valve from the Low F low FW Re g valve and contin ue to raise re actor powe r by w ithd rawing control rods .

Place CV-6-12A controller (6-84A) in AUTO Slowly OPEN CV-6-12A from Master Control (6-83)

Mo nitor R eac tor Le vel as flow is tra nsferred from CV 13 to CV-6-12A Continue to OPEN CV-6-12A until Low Flow Valve controller (6-85) indicates CV-6-13 is approximately 5% open Transfer feedwater control to automatic by performing the following:

Ve rify 1/3 E lem ent Control PB (6A -S2) is on Single Element control Verify vessel level is between +30 and +40 inches Adjust the se tpoint of the M aste r Co ntrol (6-83) to ZERO the deviation meter (in green band), THEN switch the Master Control (6-83) to AUTO Trans fer Low F low V alve c ontro ller (6-85) to MANU AL, THEN, slowly CLOSE CV-6-13 IF level was not at the desired level at the time of transfer, THEN gradually adjust setpoint of the Master Control (C-83) as desired between +30 and +40 inches Verify autom atic leve l control is fun ctioning pro perly to maintain desired level Adjust the setpoint of Low Flow Valve controller (6-85) 4 to 5 inches below the Master Level Control Setpoint RO Reports that the A FW REG valve is in service.

SRO Ack nowledges report SRO Directs reactor power be raised with control rods RO Continues power increase by withdrawing control rods to ~30%

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op -Test N o.: W 90115 Sce nario No.: 04 Event No.: 02 Page 4 of 18 Eve nt Desc ription: After the FRV has bee n placed in service, the crew will continue to raise reactor power by withdrawing control rods. The second control rod will not be able to be withdrawn with normal drive pressure and Operations Procedure B.01.03-05.H.4 (WITHDRAWAL OF A CRD UNDER HIG H D RIV E PRE SSUR E) w ill be use d to withdraw the con trol rod.

T ime Position Applicants Actions or Behavior SRO Directs reactor power be raised with control rods OATC Continues power increase by withdrawing control rods to ~30%

Reports that the selected control rod will not withdraw under normal OATC drive pressure and enters B.01.03-05.H.4 (WITHDRAWAL OF A CRD UNDER HIGH DR IVE PRESSURE)

SRO Ack nowledges report Performs the actions from B.01.03-05.H.4:

Raises drive water pressure to approximately 30 psid higher than initial value by throttling closed on MO 3-20, Drive Pressure to CRD and observing psid indication on DPI 3-303, OATC Drive W ater DIFF Press.

Attempts to withdraw the control rod Reports that the control rod successfully withdraws Returns d rive water psid to the previous pressure SRO Acknowledge s rep ort.

OATC Continues power increase by withdrawing control rods to ~30%

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op -Test N o.: W 90115 Sce nario No.: 04 Event No.: 03 Page 5 of 18 Eve nt Desc ription: After the control rod has been repositioned, the A RPS bus will be lost resulting in a half scram. Investigation will reveal a faulty EPA breaker downstream of the A RPS MG set. The SRO will review T.S. 3.1.C and then direct RPS bus A be powered from the alternate supply. The RO will reset the ha lf scra m .

T ime Position Applicants Actions or Behavior RO Responds / reports numerous annunciators on panel C05 BOP Responds / reports numerous annunciators on panel C05 ALL Determines a loss of A RPS bus power Directs R eac tor Bu ilding O pera tor to investiga te Receives report that and EPA breaker indicates tripped and has BOP an acrid sm ell Relays report to SRO Co nsu lts T.S . 3.1.C Except as specified below, both channels of the power monitoring system for the MG set or alternate source supplying each reactor protection system bus shall be operable with the following se tpoints :

SRO W ith one RPS electric power monitoring channels for the MG set or alternate source supplying each reactor protection system bus inoperable, restore the inoperable channel to Operable status within 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or remove the associated RPS MG set or alternate power supply from sevice.

SRO Directs RP S bus A be pow ered from alternate powe r supply Coordinates with Reactor Building Operator to power RPS bus B from BOP alternate supply per B.09.12 SRO Directs RPS half scram be reset Resets half scram Turns Scram Logic Reset Switch on Panel C05:

RO To the Grp 1 & 4 position AND To the Grp 2 & 3 position Rese ts annunc iators Directs Secondary Containment Isolation be reset and SBGT be SRO returned to STBY condition.

SRO May perform crew brie f (P ast, Present P lan, Po ll)

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op -Test N o.: W 90115 Sce nario No.: 04 Event No.: 04 Page 6 of 18 Eve nt Desc ription: Th is eve nt begins with a trip of the runn ing R BC CW pum p with a sub seq uen t failure of the standby pump to start on low pressure. The BOP operator should manually start the standby pump, observe system pressure restored, and report status to the SRO. RW CU will trip on high tem pera ture a nd w ill be resta rted.

T ime Position Applicants Actions or Behavior Resp onds to ann unciator 6-B-32 (R BCC W LOW DISC H PR ESS ):

Reports alarm to SRO Repo rts failure of standby pum p to start BOP Chec k system pressure If system pressure is less than 30 psig, Then refer to C.4-B.02.05.A (LOSS OF RBCCW FLOW)

Perform s actions of C.4-B.02 .05.A (LOS S O F RB CC W FLO W ):

Verify a RBCCW pump is running BOP Notify SRO that standby pump was started and is running and system pressure is returned to normal May dispatch operator to check status of RBCC W pumps Responds to RW CU pum p trip on high tem p due to R BC CW event (this BOP is dependent upon the RBCCW flow/pressure and operator response time for restarting a pump), by reporting RW CU pum p trip.

SRO Direct restoration of RWCU Restore RW CU per B.02.02-05:

Verifies MO-2399, 2404 and 2405 closed Ve rifies F /D are pre coate d and in hold Verifies RW CU pum ps not running Places switch 12A-S7 on Panel C-04 in Bypass Opens MO -2400 RW CU F/D bypass BOP Throttles open MO-2399 Throttles open MO-3501 Starts RW CU pum p Directs F/D placed in service Close MO-2400 Fully open MO -2399 Acknowledges report and notifies Operations Manager, System SRO Engineering

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op -Test N o.: W 90115 Sce nario No.: 04 Event No.: 04 Page 7 of 18 Eve nt Desc ription: Th is eve nt begins with a trip of the runn ing R BC CW pum p with a sub seq uen t failure of the standby pump to start on low pressure. The BOP operator should manually start the standby pump, observe system pressure restored, and report status to the SRO. RW CU will trip on high tem pera ture a nd w ill be resta rted.

SRO May conduct c rew brief (P ast, Present, P lan, Po ll)

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op -Test N o.: W 90115 Sce nario No.: 04 Event No.: 05 Page 8 of 18 Eve nt Desc ription: This event begins with indications of high conductivity in the condensate and feedwater system that escalates to the extent that the crew will take actions per C.4-06.03.B and initiate a reactor scram and isolate the reactor from the problem by starting RCIC for level control and then sec uring con den sate , feed wate r, circ w ater a nd c losing the M SIVs.

T ime Position Applicants Actions or Behavior Resp onds to ann unciator 6-A-35 (C ON D D EM IN SYST EM TR OU BLE):

Reports alarm to SRO BOP Dispatc h T urbine Bu ilding O pera tor to C -80 p ane l to inves tigate alarm Relays Turbine Building Operator report to SRO Responds to annunciator 4-B-1 (CLEAN U P HI CO NDU CTIVITY)

Reports alarm to SRO No tify the Shift Che m ist to investigate high c ond uctivity condition IF HW C has tripped and is determined to be the cause of the high conductivity condition, no further actions are required IF high conductivity condition is due to reactor shutdown, THEN no further actions are required Check Reactor W ater conductivity recorded at CR-12-144 on C-04 Check condensate demin and feedwater conductivities on process computer BOP IF the source of high conductivity is the Reactor W ater Cleanup F/D effluent, THEN , imm ediately remove the RW CU system from service in accordance with Ops Man Section B.02.02-05.F, Shutdown Procedures Ba ck wa sh and precoat R W CU filter/dem ins if ne cessary in accordance with B.02.02-05 (REACTOR W ATER CLEANUP -

SYSTEM OPERATION)

IF a main condenser tube leak is indicated, THEN refer to C.4-B.06.03.B (ABNORM AL PROCEDUR ES - CONDENSER TUBE LEAKAGE)

Consider raising RW CU filter/demin flow to a maximum flow of 85 gpm each Notify Shift Supervision and System Engineer SRO Directs entry to C.4-B.06.03.B (COND ENSER TUBE LEAKAGE)

BOP Performs Subsequent Operator Actions of C.4-B.06.03.B:

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op -Test N o.: W 90115 Sce nario No.: 04 Event No.: 05 Page 9 of 18 Eve nt Desc ription: This event begins with indications of high conductivity in the condensate and feedwater system that escalates to the extent that the crew will take actions per C.4-06.03.B and initiate a reactor scram and isolate the reactor from the problem by starting RCIC for level control and then sec uring con den sate , feed wate r, circ w ater a nd c losing the M SIVs.

Monitor condensate demineralizer conductivities Notify chemistry to initiate Reactor water sampling or monitor in-line instruments to determine ongoing conductivity and chloride changes Operate RW CU at maximum filter flow Directs Re actor Building O perator to raise R W CU filter/dem in flows to 85 gpm on each filter/dem in Monitor the following to determine the severity of the tube leakage:

Condensate demineralizer inlet conductivity (SPDS FOR MAT 603)

Condensate demineralizer effluent conductivity (SPDS FOR MAT 603)

Hotwell level (including reject valve operation) (SPDS FOR MAT 601)

Reactor water conductivity on CR-12-144, Panel C-04 IF tube leakage is such that Reactor water chemistry Tech Spec limits will eventually be reached, THEN enter C.3 (SHUTDOW N)

Re fers to Tech Spe cs 3 .6.C.3 Except as specified in 3.6.C.2.b above, the reactor coolant water shall not exceed the following limits with steaming rates greater than or equal to 100,000 lbs. per hour Conductivity 5umho/cm ,

SRO Chloride ion 0.5 ppm If Specification s 3.6.C .1 th rough 3.6.C .3 are not m et, a n orderly shutd ow n shall be initiated and the re actor shall be in the cold shutdow n condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Performs Subsequent Operator Actions of C.4-B.06.03.B:

IF a valid Cond ens ate D em ineralizer Influent Cond uctivity reading of greater than or equal to (>) 1.0 umho/cm is received, AND C ondensate Demineralizer Conductivity shows and BOP increasing trend, THEN perform the following:

Reduce recirculation flow to a minimum Man ually scram the Reac tor and exec ute C.4-A (REA CT OR SCR AM ) concurren tly with this proced ure

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op -Test N o.: W 90115 Sce nario No.: 04 Event No.: 05 Page 10 of 18 Eve nt Desc ription: This event begins with indications of high conductivity in the condensate and feedwater system that escalates to the extent that the crew will take actions per C.4-06.03.B and initiate a reactor scram and isolate the reactor from the problem by starting RCIC for level control and then sec uring con den sate , feed wate r, circ w ater a nd c losing the M SIVs.

SRO Directs re acto r shu tdow n pe r C.4-B.06.03 .B Shuts down the reactor by performing the following:

RO Reduce recirculation speed at minimum Insert a manual scram Performs Imm ediate Operator Actions of C.4-A:

Places reactor mode switch in shutdown RO Determine if all control rods are inserted to or beyond position 04 Reports reactor scram, mode switch in shutdown, all rods inserted Performs Subsequent Operator Actions of C.4-A PART A:

Ve rify C .4-A P AR T B is perform ed concurrently Control Reactor water level between +9 and +48 by performing the following:

W HEN Reactor water level starts to increase, THEN perform the following as required:

Place CV-6-13, Manual Loading Station Low Flow Valve in Auto with a level controller setpoint of 15 to 20 CLO SE both M ain FW Re g Valves via their respective Feedwater Control M/A Station RO CLOSE MO-1133, HP FW Line A Block Valve, and M O-11 34 HP FW Line B Block V alve W HEN Reactor water level reaches +15 to 20, THEN verify CV-6-13, Manual Loading Station Low Flow Valve, is CLOSED Monitor Reactor power Insert SRM and IRM detectors Switch recorders to IRM and continue to monitor power by ranging down the IRMs to maintain indication on scale Verify the Scram D ischarge Volume vent and drain valves close

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op -Test N o.: W 90115 Sce nario No.: 04 Event No.: 05 Page 11 of 18 Eve nt Desc ription: This event begins with indications of high conductivity in the condensate and feedwater system that escalates to the extent that the crew will take actions per C.4-06.03.B and initiate a reactor scram and isolate the reactor from the problem by starting RCIC for level control and then sec uring con den sate , feed wate r, circ w ater a nd c losing the M SIVs.

Verify that the Recirc pumps have runback to minimum speed or have tripped by performing the following:

IF the Recirc scoop tube is locked, THEN reset the scoop tube lock to allow the runback IF the Recirc pum p sp eed can not be red uce d to minimum speed, THEN trip the pump IF any Recirc pumps have tripped, THEN perform the following:

CLOSE discharge valve for the tripped pump, AND after 5 minutes, give the discharge valve a 3 second OPEN signal.

Refer to B.01.04-05 (REACTOR RECIRCULATION SYSTEM - SYSTEM O PERAT ION) for methods of controlling temperature stratification IF plant fed from 1R, THEN verify 115KV Voltage >

116.0KV (SUB101)

Restart the tripped recirc pumps IF the Reactor scram can be RESET , THEN perform the following:

Place the DISCH VOL ISOL T EST switch (Panel C-05) in ISOL Verify the REACTOR MOD E switch in SHUT DOW N or REFUEL Pla ce the DISC H VO L H IGH W TR BYP s witc h in BYPASS RESET the scram using the SCRAM RESE T switch Evacuate personnel from the Reactor Building 896 Floor and Equipment Drain Tank Room W HE N all scram valves are C LO SED (b lue sc ram lights OFF), THEN place the DISCH VOL ISOL TEST switch in NORM Verify the SDV vent and drain valves OPEN Verify the CRD scram accum ulators recharge W HEN Annunciator 5-B-30 (DISCH VOLUME TANK NOT DRAINED) is RESET, THEN, verify the DISCH

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op -Test N o.: W 90115 Sce nario No.: 04 Event No.: 05 Page 12 of 18 Eve nt Desc ription: This event begins with indications of high conductivity in the condensate and feedwater system that escalates to the extent that the crew will take actions per C.4-06.03.B and initiate a reactor scram and isolate the reactor from the problem by starting RCIC for level control and then sec uring con den sate , feed wate r, circ w ater a nd c losing the M SIVs.

VOL HIGH W TR BYP switch in NORM Performs Subsequent Operator Actions of C.4-A PART B:

Ve rify C .4-A P AR T A is perform ed concurrently Announce over the plant paging system that a Reactor scram has occurred IF opening 8N4 will result in a loss of power to 2R, based on know n pre-scram 345KV ring bus status, TH EN p erform a closed bus transfer from 2R to 1R as follows:

Place 152-302/CS 1R RES XRMR SEC TO 13 BUS ACB 152-302 to CLOSE (Panel C-08 Place 152-301/CS 2R XFMR SEC TO 13 BUS ACB 152-301 to TRIP (Panel C-08)

Place 152-402/CS 1R RES XFMR SEC TO 14 BUS ACB 152-402 to CLOSE (Panel C-08)

Place 152-401/CS 2R XFMR SEC TO 14 BUS ACB 152-401 to TRIP (P anel C-08).

Place 152-102/CS 1R RES XFMR SEC TO 11 BUS BOP ACB 152-102 to C LOS E (Pane l C-08).

Place 152-101/CS 2R XFMR SEC TO 11 BUS ACB 152-101 to TRIP (P anel C-08).

Place 152-202/CS 1R RES XFMR SEC TO 12 BUS ACB 152-202 to C LOS E (Pane l C-08).

Place 152-201/CS 2R XFMR SEC TO 12 BUS ACB 152-201 to TRIP (P anel C-08).

OP EN k nife switch 16/C31 (Pa nel C-31).

W HEN Generator power is approximately 0 MW e, THEN OPEN 8N 4 and 8N5.

TRIP the Turbine using TURB INE EMERG ENCY TR IP switch on C-07.

IF the Turbine has tripped auto m atic ally or by o perator action in the above step, THEN perform the following:

Verify that the Turbine-Generator field breaker is OPEN via light indication at C-08 or mechanical flag indication on the field breaker

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op -Test N o.: W 90115 Sce nario No.: 04 Event No.: 05 Page 13 of 18 Eve nt Desc ription: This event begins with indications of high conductivity in the condensate and feedwater system that escalates to the extent that the crew will take actions per C.4-06.03.B and initiate a reactor scram and isolate the reactor from the problem by starting RCIC for level control and then sec uring con den sate , feed wate r, circ w ater a nd c losing the M SIVs.

STOP the amplidyne by placing the REGULATOR TRAN SFER switch to the OFF position START the Turbine auxiliary oil pump Verify Turbine exhaust hood sprays are in service IF Gland Seal steam is not available, THEN OP EN the Main C ondens er vacuum breake rs Verify the Main Steam pressure control system or LOW -LOW Set is controlling Re actor pressu re Pla ce the PO ST SC RAM switch on C-25 to O N, AN D verify all available Drywe ll Re circulation F ans are operatin g in accordance with Ops Manual B.05.16-01 (DRYW ELL ATMO SPHERE COO LING - FUNCTION AND GEN ERAL DESCR IPTION OF SYST EM) Table 1.

Performs Subsequent Operator Actions of C.4-B.06.03.B:

IF a valid Cond ens ate D em ineralizer Influent Cond uctivity reading of greater than or equal to (>) 5.0 umho/cm is received, BOP AND C ondensate Demineralizer Effluent Conductivity shows an increasing trend, THEN perform the following:

Manually initiate RCIC to maintain RPV water level Initiates RCIC per B.02.03-05 or may use Hard Card:

At any time while performing this procedure, IF conditions permit, THEN place RHR in Torus Cooling for cooling/mixing the Torus water, per Ops Man Section B.03.04-05 Verifies flow controller in AUTO and set to 80%

OP EN M O-20 96, RC IC Coo ling W ater Supply valve Place P-211 (RCIC Barometric Condenser Vacuum Pum p)

BOP Handswitch, 13A-S15, in the START position OP EN C V-2104 , RCIC P um p Minim um Flow Valve OPEN the following:

MO -2107, RC IC Pum p Disch Inbd va lve MO -2106, RC IC Pum p Disch O tbd valve OP EN M O-20 78, RC IC Turb ine Steam Supply valve Verify the following valves are closed:

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op -Test N o.: W 90115 Sce nario No.: 04 Event No.: 05 Page 14 of 18 Eve nt Desc ription: This event begins with indications of high conductivity in the condensate and feedwater system that escalates to the extent that the crew will take actions per C.4-06.03.B and initiate a reactor scram and isolate the reactor from the problem by starting RCIC for level control and then sec uring con den sate , feed wate r, circ w ater a nd c losing the M SIVs.

CV -284 8 an d CV-2849 , RC IC C ond Pum p Discharge to CRW CV -208 2A and CV -208 2B, RC IC S team Line D rain to Main Condenser Verify SI-7321, RCIC Turbine Speed Indicator is increasing, indicating that unit is rolling Verify AO-13-22, RCIC Injection Testable Ckv, is open Verify RCIC pum p flow is maintained at desired level BOP Performs Subsequent Operator Actions of C.4-B.06.03.B:

Secures Condensate and Feedwater by performing the following:

Close FRVs Stop both FW pumps Stop Recombiner condensate pumps Stop Condensate pumps Secures Steam to the condenser by performing the following:

Close MSIVs Verify MSL D rain valves, MO-23 73 and M O-23 74 are closed Isolate the circulating water flow to the condenser by performing the following:

Stop the circulating water pumps Verify the condenser outlet valves close Close the condenser inlet valves, MO-1156 and MO-1157, using the local control switches SRO May conduct c rew brief (P ast, Present, P lan, Po ll)

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op -Test N o.: W 90115 Sce nario No.: 04 Event No.: 06 Page 15 of 18 Eve nt Desc ription: After the reactor has been isolated, a small primary system leak will develop in the drywe ll. W hen directed to re-estab lish conde nsa te and fee dwa ter, the feed wate r block va lves w ill not open from the control room and the low flow feed reg valve will not function. SBLC injection and a sec ond CR D pum p will be s tarted to injec t water into the RP V.

T ime Position Applicants Actions or Behavior BOP Reports RPV water level below +9 inches Enters EOP 1100 Directs RPV injections with Condensate and FW SRO Directs RPV injection with SBLC Directs RPV injection with 2 CRD pumps Directs ADS inhibited Repo rts Drywell tem perature and p ressure rising / EOP 1200 entry BOP condition Starts Condensate and Feed water pumps and attempts to open FW RO block valves. Reports failure of block valves to open.

En ters E OP 1200 (P rim ary Co nta inm ent Control)

SRO Directs Drywell cooling initiated Directs Torus Sprays initiated Places 2nd CRD pum p in service:

Starts 2 nd pum p Directs Reactor Building Operator to perform the following:

RO Verify close MO -168 Ope n CR D-30 an d CR D-8 Close C RD 7-1 and C RD 7-2 Initia tes SB LC for RP V level control:

RO Starts 1 SBLC pum p Verifies injection Initiates drywell cooling:

Place fan sw itches in off BOP Byp ass E CCS fan trip Starts fans (only 2 & 4 are available)

Report drywell cooling in service BOP Initiates torus sprays:

Place CNTMN T 2/3 height C/S to bypass

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op -Test N o.: W 90115 Sce nario No.: 04 Event No.: 06 Page 16 of 18 Eve nt Desc ription: After the reactor has been isolated, a small primary system leak will develop in the drywe ll. W hen directed to re-estab lish conde nsa te and fee dwa ter, the feed wate r block va lves w ill not open from the control room and the low flow feed reg valve will not function. SBLC injection and a sec ond CR D pum p will be s tarted to injec t water into the RP V.

Place CNTMN T Spray/Cooling LPCI initiation C/S to bypass Open MO -2006 Open MO -2010 Throttle open MO-2008 Line up RHRSW Report torus spray in service BOP Inhibits ADS by placing both ADS inhibit switches in bypass SRO May conduct c rew brief (P ast, Present, P lan, Po ll)

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op -Test N o.: W 90115 Sce nario No.: 03 Event No.: 07 Page 17 of 18 Eve nt Desc ription: The RCIC flow controller will fail in automatic. If the RCIC controller is taken to m anu al, for injection. D rywell tem pera tures and pres sure will rise re quiring drywe ll spray initiation.

The leak rate will surpass the ability of mak e up systems requiring an Emergency Depressurization after RPV water level reaches -126 inches and before RPV water level reaches -149 inches. Three ADS SRVs will be opened and ECCS pumps will inject to restore RPV water level above TAF. ECCS will be se cured a s ne ces sary to resto re an d m aintain RP V water lev el betw een +9 - +48 inc hes .

T im e Position Applicants Actions or Behavior Reports the RCIC turbine injection is 0 and may diagnose the flow BOP con troller is failed in auto. If taken to m anu al, the inje ction rate w ill rise.

(RC IC will subseq uently after drywell sprays are initiated).

Resp onds to ann unciator 4-A-9 (RC IC TU RBIN E TR IPPED ):

Reports alarm to SRO BOP Verify Rx water level is being maintained by FW and /or ECCS system s as nec essary Determ ine cause of R CIC turbine trip, correct as necess ary Observes drywell temperature and pressure continuing to rise and SRO directs drywell sprays per C.5-3502 Initiates drywell sprays:

Place CNTM NT 2/3 height C/S to bypass Place CNTM NT Spray/Cooling LPCI initiation C/S to bypass BOP Open M O-2021 Open M O-2023 Verify closed MO-2009 Verify closed MO-2012 & M O-2013 W hen RPV water level is below -126 inches and before RPV water level SRO reaches -149 inches, enters EOP 2002 (EMERGENCY DEPRESSURIAZATION)

Enters EOP 2002, Emergency RPV Depressurization:

Verifies all rods inserted Verifies D /W pressu re <2 psig SRO Directs prevention of Core Spray and LPCI Verifies torus leve l > -5.9 ft Directs opening of 3 ADS SRVs BOP Opens 3 ADS SRVs BOP/RO Reports RPV water level above -126 inches (TAF)

Appendix D, Rev. 9 Required Operator Actions Form ES-D-2 Op -Test N o.: W 90115 Sce nario No.: 03 Event No.: 07 Page 18 of 18 Eve nt Desc ription: The RCIC flow controller will fail in automatic. If the RCIC controller is taken to m anu al, for injection. D rywell tem pera tures and pres sure will rise re quiring drywe ll spray initiation.

The leak rate will surpass the ability of mak e up systems requiring an Emergency Depressurization after RPV water level reaches -126 inches and before RPV water level reaches -149 inches. Three ADS SRVs will be opened and ECCS pumps will inject to restore RPV water level above TAF. ECCS will be se cured a s ne ces sary to resto re an d m aintain RP V water lev el betw een +9 - +48 inc hes .

Coord inates with BOP o perator to m onitor RPV w ater level and secure RO ECCS injection as necessary to end up with 1 Core Spray system maintaining level between +9 - +48