ML033100055

Final Section C Operating

ML033100055
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	10/03/2003
From:	Gosekamp M Entergy Nuclear Vermont Yankee
To:	Conte R NRC/RGN-I/DRS/OSB
Conte R
References
50-271/03-301
Download: ML033100055 (59)

Text

Appendix D Scenario Outline Form ES-D-1 Vermont Yankee Facility :

(1 999 NRC)Modified Scenario No.:

1 Op-Test No.:

Examiners:

Operators:

ACRO CRO CRS Objectives: Evaluate the crews ability to operate plant equipment to support a normal power ascension, respond to and evaluate (Technical Specification) a level instrument failure and the resultant reactivity addition transient. Recognize and take action for a Recirc Pump failure, recognize and limit the positive reactivity from a Recirc Pump speed transient. Determine the affect of a loss of a 480 VAC ECCS bus on plant operation, and to implement the EOPs to monitor and control plant parameters for a major primary containment steam leak resulting in emergency depressurization as well as recognizing the inability to spray the drywell Initial Conditions: lC-G7(Snapshot) 30% power, approaching conditions for second Feedwater Pump Start Turnover: See Attached Shift Turnover Sheet Malf.

No.

Key 1 RC04 Key 2 RR07B RR08B Key 3 RRIO 3600 sec 100% @

Key 4 ED05C Key 5 300 sec MS06 Key 6 1000 sec

.4% @

10% @

RH03A RFHP05 Event Type*

CRO CRS CRO CRS ACRO I

CRO CRS CRO CRS CRO I

CRS ACRO c

CRO CRS ACRO M

CRO CRS c

ACRO N/A (N)ormal, (R)eactivity Event Description Continue power ascension IAW OP 0105 Start the second Feedwater Pump Inadvertent RClC initiation (TS) 5 minutes after RFP start B Recirc Pump lower and upper seal failure A Recirc Pump speed controller failure, pump speed increasing 480 VAC ECCS Bus 8 fails Steam line leak in the drywell - emergency depressurization Drywell Spray Valve does not open (B valves have no power)

HPCl aux oil pump ACB open - out of service for governor oil leak repair (I)nstrument, (C)omponent, (M)ajor P

SIMULATOR OPERATOR INSTRUCTIONS FOR SCENARIO (#I)

GENERAL REQUIREMENTS 9

9 9

9 9

9 All chart recorders will be rolled forward, timed and dated.

Paper from selected chart recorders will be saved for the examination team as requested.

All procedures, flow charts, curves, graphs, etc., will be returned to their normal storage place and closed.

All markable procedures, boards, etc., will be erased.

All paper used by the previous crew will be removed and kept for the examination team as requested.

The simulator operator, or designated person, will keep a rough log of all communications into and out of the control room during the scenario as requested by the examination team.

INITIAL SETUP 9 IC-67. setup for -30% power getting ready to start the C Feedwater Pump P Ensure the A Feedwater Pump is running with C in Standby P Place HPCl out of service (Preinsert RFHPO5, Aux oil pump ACB open) PTL aux oil pump switch 9 Preinsert RH03A (RHR A Cont Spray 26A fails to open) 9 Mark con-demin status board NBIC in service DURING THE SCENARIO The examination team will determine when each event is to be inserted and when to freeze and will inform the simulator operator.

> EVENT I Provide copy of VYOPF 2404.02 for rod withdraw sequence.

Support crew as Reactor Engineer as requested.

9 EVENT 2 If crew continues to raise power direct them to start the second feedpump at 40% power. When directed as A 0 to perform prestart checks for Feedpump start inform Control Room checks are completed. Seal water temperatures are normal after the feedwater pump start 9 EVENT 3 After conditions stable for 5 minutes insert RClC start.

Acknowledge request as I&C. They know of no reason why RClC started. Report that RClC initiation relays K-1 and K-2 are energized, and the investigation continues.

9 EVENT 4 Insert seal leak rate low and ramp up after recognized by crew.

Use RDRI2 to secure seal purge. Recirc cooling is SWR 58

9 EVENT 5 Insert malfunction after the A pump is on master control.

Attempt to provide a slow speed increase to allow operators to recognize it and take actions. Master Controller fails. If they place A in Manual pump speed control will work.

Acknowledge request as I&C to respond to CR to investigate Recirc Flow Control trouble.

P EVENT 6 Insert malfunction as soon as plant stable following Event 5.

Allow crew time to discuss plant status, plans for continued operation/shutdown. Support crew as requested on bus failure.

It will not be available anytime soon.

P EVENT 7 Insert leak at the lower severity. After the scram insert the leak at the higher severity 9 EVENT 8 Acknowledge request to attempt manual opening of Outbd Drywell Spray Valve (RHR-26A). At Exam Team direction after ED is performed, remotely open requested valve to allow sprays.

Rf RH 46 (RHR26A)

After vessel depressurization and RHR 26A opened via local TERMINATION manual operation or as Exam Team directs.

Event No.

1 2

3 4

5 6

7 8

c SIMULATOR OPERATOR INSTRUCTIONS FOR SCENARIO (#I)

(con?)

Malf. No.

Verify RWM latched to GRP 64 RFHP05 Preinsert RH03A Preinsert RC04 Key1 RR07B Key2 RR08B Key2 RR10 Key3 100% @ 3600 sec ED05C Key4 MS06 Key5

.4% @ 300 sec MS06 Key6 10% @ 1000 sec RH03A Preinsert EventType* I Event Description I RHR CONT SPR VLV (26A) FAIL TO OPEN CRo 1 Continue power ascension IAW OP 0105 CRS N

CRO Start the second Feedwater Pump CRS ACRO I

CRO Inadvertent RClC initiation (TS)

CRS CRo 1 B Recirc Pump lower and upper seal failure CRS After A pump is on the master controller A Recirc Pump speed I

CRo CRS I controller failure, pump speed increasing ACRO C

CRO 480 VAC ECCS Bus 8 fails CRS Steam line leak in the drywell - emergency depressurization After drywell RRUs started post loss of Bus 8 M

CRO CRS Steam leak will cause drywell temperature to exceed 280 degrees and require RPV-ED. After manual or auto scram on high drywell pressure

SHIFT TURNOVER (#I 1

PLANT CON DlTlON S:

Approximately 30% power Sequence A2 Group 64, Control rod 10-27 No rapid shutdown sequence is available INOPERABLE EQUIPMENTILCOS:

HPCl is out of service for repair of a governor oil leak SCHEDULED EVOLUTIONS:

0 OP 0105 Phase 4 step 24 page 82 0

Raise power to 40% CTP at 1 %/ I min Start C RFP at 40% power for PMT of seal replacement. Place A RFP in STBY At 45% speed transfer Recic pump speed control to master manual control SURVEILLANCES DUE THIS SHIFT:

None ACTIVE CLEARANCES:

0 N/A GENERAL INFORMATION:

CONTROL ROOM SHIFT TURNOVER CHECKLIST &mrb 1 Parameted Allowable Checks Component Condnimit 06 I 18 cs Am sys No Alarms/Opr

1. I CS-7 A/B cs PP Am AUTOIO r Closed RHR Sys RHR PP AmIcID RHR FI 139A/B G O O gpm No A l d O p r AUTO/Opr Open Open Open Open Closed A500 gpm 250 - <87.3"F N o A l d O p r In AUTO ON Open IHPCI-14.25.19.

I 21,57,58 I Closed HPCI Flow I

b v

NOTE 1 : STA walkthrough to include status check of the Control Room Pyrotronics Panel.

NOTE 2: In the event minimum shift staffing levels cannot be met, actions to be initiated are specified in AP 0894.

NOTE 3: Control Room staff shall contact VELCO whenever abnormal yard conditions exist. (CAR910370Pl)

VYAPF 0152.01 AP 0152 Rev. 22 Page 1 of 1 LPC #5

TECH. SPEC./TEC"ICAL REQUIREMENTS MANUAL, SYSTEMSKOMP0"TS INOPERABLE SY STEWCOMPONENT TECH.

D ATE/TIME SPEC./TRM DECLARED UNPLANNED PARAGRAPH INOPERABLE LCO 3*SE, 2 OPERATIONS REQUIRED SWCRS LOGGING, TESTING OR ALLOWABLE DATE/TIME, INITIALS (ER970390-03)

INOPERATIVE OPERABLE mop OF OTHER ACTION TIME DECLARED u c a &v'fioQ-FS

/Yd+/5 VYAPF 0152.02 AP 0152 Rev. 22 Page 1 of 1

ov ov ov oa3v oa3v VLS 0x3 sa3 xo H S WYS a=ds

CONTROL ROOM TURNOVER SHEET Date:

%dCy Shift: @ Nights

~-

munciators (Existing, New, Nuisance,

Disabled, Restored)

M d u e

&+et&

Afe4.d VYAPF 0152.04 AP 0152 Rev. 22 Page 1 of 1

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

1 Scenario No.:

1 Event No.:

I Page -I-of 10 Event

Description:

Increasing reactor power from 30% CTP to 40% with flow IAW OP 0105 P

Time Position CRS CRS CRO ACRO

~

CRO CRS CRO Applicants Actions or Behavior Perform crew brief for the Dower increase Direct continued Dower ascension IAW OP 0105 Phase 4 step 24 Request a peer check for the reactivity increase if one is not assigned Raise reactor power with flow 1 % CTP/I Min, For each flow increase:

Turns controller 2-1 84-16-1N1 B manual knob in the clockwise direction Monitors recirc pumps for expected speed increase Directs RBAO to monitor MG lube oil temperatures Maintains pump speeds within 5% of each other Monitors nuclear instrumentation for proper response Monitors feedwater level control system response to the power increase 0

0 0

Monitor plant parameters/assist as necessary Make preparations for second Feedwater Pump start Report recirc speeds at 45% as indicated on controller 2-1 84-1 6-1 Nl B Direct recirc flow control transferred to master manual control Transfer recirc flow control to master manual control as flows 0

0 0

Verify N B speed > or equal to 45% on 2-184-16-1N!B Ensure feedwater low flow interlock is clear (Alarms 9-4-B-6/F-6 Use D (Display) button on controllers 2-184-16-1NB to observe P and S values Adjust master controller SC-2-184-14 to match the speed on the I nd ivid ual controllers If necessary adjust the Bias on the second controller to be shifted to match its speed to the master controllers speed When speed signals are matched transfer to the master Controller by depressing the auto/manual push button on the Individual controllers A(B).

Appendix D Required Operator Actions Form ES-D-2 Event

Description:

Start second Feedwater pump prior to 40% CTP Position CRS ACRO CRO CRO ACRO Applicants Actions or Behavior Direct startup of C Feedwater Pump per Phase 4 section B of OP 0105 Start the second feedwater pump per OP 0105 Phase 4.B 0

Review Phase 2 & 4 Precautions and Administrative Limits 0

Verify both heater strings are in service 0

Verify Standby Lube Oil pimp in service Close feed pump discharge valve (FDW-4C) 0 Position C pump control switch to Start 0

Verify pump breaker closes, discharge valve opens and auxiliary lube oil pump stops 0

Check seal water temp 0

Monitor lube oil and bearing temps until stabilized 0

Monitor running current (max. 666 amps) 0 Check Bus 3 / 4 undervoltage relay targets Request a peer checker if one is not assigned Observe system flow and reactor level stabilizes Report C Feedwater Pump placed in service Place A Feedwater Pump in Standby 0

0 Control switch placed in Auto Open Feedwater Pump Discharge Valve (FDW-4A)

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

1 Scenario No.:

1 Event No.:

3 Page 3 of I O Event

Description:

Inadvertent RClC start. Electrical short in low level sensing circuit (KI & K2 energize)

Initial Automatic Actions: RClC initiation and injection, No alarms, except for alarm typer Effects (General Sequence): Power and level increase. Very minor (positive reactivity addition)

CRS Enteddirect actions IAW OT 31 I O, Positive Reactivity Insertion.

May refer to OT 31 14, Reactor High Level ACRO CRO CRS Verifies by two or more independent indications that RClC initiation is spurious, informs CRS.

Secure RClC 0

Press RClC Turbine Trip pushbutton 0

Verify turbine trips and RPM decreasing 0

Report minimum flow valve open I Verify reactor power and level return to normal.

HPCl is Inoperable. Declare RClC hoperable IAW 3.5.E.3 commence a shutdown to 4 5 0 PSlG within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. May call 3.5.G.3 Same actions Direct I&C investigate cause of failure.

CRS I Informs Operations Management of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> shutdown LCO

Appendix D Required Operator Actions Form ES-D-2

~ Op-Test No.:

1 Scenario No.:

1 Event No.:

4 Page 4 of 10 Event

Description:

B Recirc Pump lower and upper seal failure Cause: Worn seals Initial Automatic Actions: Initially receive alarms 9-4 G-I & G-2 Effects (General Sequence): Both seals on the B Recirc pump fail requiring pump removal and isolation, increasing drywell temperature/pressure until isolated Posit ion CRO / ACRO CRS CRO CRO Applicants Actions or Behavior Recognizehake action IAW 9-4 G-2 & G-I, inform CRS

_Ip -

0 0

0 Monitor B Recirc Pump parameters Determine failure of both pump seals, inform CRS Monitor Drywell equipment drain sump, temperature and drywell pressure Enteddirect actions IAW ON 3142, Recirc Pump Seal Failure Enteddirect actions IAW OT 31 17, Rector Instability, and OT 31 18, Recirc Pump Trip Refer to Tech Spec 3.6.G and direct actions for single loop operation, inform RE 0

Direct B Recirc Pump shutdown and isolation 0

May direct monitoring for reactor instabilities Secure and isolate the B recirc pump IAW ON 3142 0

Open B Recirc Pump MG Set Drive Motor Breaker 0

Close suction valve RV-43B 0

When suction indicates closed, close discharge bypass valve RV-54B and discharge valve RV-53B 0

Direct Aux Operator to secure seal purge IAW OP 21 11 Determine operating point on COLR Figure 2.4-1 Monitor LPRM readings by selecting STBLTY on ERFIS 0

May initiate stability monitoring

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

1 Scenario No.:

1 Event No.:

5 Page of 10 Event

Description:

A Recirc Pump speed controller failure, pump speed increasing Cause: Master Controller output failure high Initial Automatic Actions: Reactor power rise, alarms 9-5 D-2 81 0-3 Effects (General Sequence): Pump speed increasing, power rise CRO CRO 1

ACRO

-+---- I Applicants Actions or Behavior Recognize/report rising reactor power, inform CRS Recognizelreport A Recirc Pump speed rising, inform CRS Recognizehake actions IAW 9-5 Monitor flow and power to confirm control rod blocks Enteddirect actions IAW OT 31 IO, Positive Reactivity Insertion Direct the manual control of A Pump controller When directed adjust speed of A Recirc Pump to 50-70%

Place pump controller in I Manual by depressing the auto/manual controller push button on controller 2-1 84-1 6-1A adjust pump speed by turning the manual knob on 2-184-16-1A to adjust pump speed to 50-70% speed Do not exceed 1% CTP/min power change 0

0 0

0 Contact I&C and inform them of the recirc flow controller failure Monitor RPV level pressure and power for return to normal Assist as necessary

Form ES-D-2 Appendix D Required Operator Actions 3p-Test No.:

1 Scenario No.:

1 Event No.:

6 P a g e L o f 10

vent

Description:

Loss of 480 VAC Bus 8 2ause: Bus fault due to ground on 8 nitial Automatic Actions: Half scram, PClS Group 3 isolation, multiple alarms Time Position CRO / ACRO CRS CRO / ACRO CRO ACRO Amlicant's Actions or Behavior RecognizeAake actions IAW 9-5 K-I, inform CRS 0

0 Recognize half scram and PClS GP 3 isolation Recoanize loss of 480 VAC Bus 8 Take actions for loss of Bus 8 0

0 Direct identification of lost loads Direct backup of PClS GP 3 Determine 7 day LCO required. B EDG INOP IAW OP 2143 Precaution g Refer to Tech Spec 3.5.B Tech Spec 3.10.A.4. Buses 3,4, 8, 9, energized and operable 0

No action statement 0

Recommend a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> cold shutdown IAW AP 0151 page 5 responsibility 23. As Time permits or by follow-up questions Direct trou bleshooting/repair Determine the following loads lost on Bus 8, inform CRS 0

DrywellRRUs 0

A RPS half scram 0

PClS GP 3 isolation 0

B CRD pump loss 0

BRBCCWpump 0

ATBCCWpump BRHR 0

BCS 0

BSBGT Stack Flow Indicator FT-108-22 ODCM Table 3.1.2 B SBLC pump Stack Gas I, II indication loss Loss of RWCU (CU-15 loss of power)

Vital MG Set swap to DC drive Loss of RClC (RCIC-15 loss of Dower)

Amendix D Reauired ODerator Actions Form ES-D-2 1.:

1 ACRO CRS ACRO Scenario No.:

1 Event No.:

6 (contd)

Page 7 of 10 Backup Group 3 isolation IAW posted Operator Aid CRP 9-3 AC-8, DRYWELL PURGE AC-7A, DRYWELL VENT AC-6A, DRYWELL 3 VENT AC-20, Nz MAKE-UP AC-10, TORUS PURGE AC-7B, TORUS VENT AC-GB, TORUS 3 VENT AC-9, AIR PURGE SUPPLY AC-22B, DRYWELL MAKE-UP SGT-6, VENT TO SBGT AC-23, N2 PURGE SUPPLY AC-7, VENT TO RTF-5 AC-22A, TORUS MAKE-UP CA-38A, CTMT COMPR SUCT CA-38B, CTMT COMPR SUCT CRP 9-26 HVAC-9, RB VENT SUPPLY HVAC-10, RB VENT SUPPLY HVAC-12, RB VENT EXHAUST HVAC-I 1, RB VENT EXHAUST RB supply/exhaust fans off RSF-1A off REF-1A off RSF-1 B off REF-1 B off CRP 9-25 SBGT REF-2A on REF-2B on CRP 9-47 VG-26, CAM SUPPLY INBD VG-76A, CAM RETURN INBD VG-23, CAM SUPPLY OUTBD VG-76B, CAM RETURN OUTBD CAD Panel A NG I I A, 12A, 13A VG 22A, 9A Direct drywell RRUs restarted Restart drywell RRUs CRP 9-25 RRU 3NB control switch to A&B run CRP 9-25 RRU 4NB control switch to A&B run

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

1 Scenario No.:

1 Event No.:

7 P a g e L o f 10 Event

Description:

Steam leak in drywell - emergency depressurization Cause: A MSL 18 inch pipe rupture between reactor vessel and flow restrictor Initial Automatic Actions: High drywell pressure scram Effects (General Sequence): Slowly rising drywell pressure to scram setpoint then rapid increase Time Position CRO / ACRO CRS CRO ACRO CRO Applicants Actions or Behavior Recognizing rising drywell pressure, inform CRS 0

Check backpanel indications Recognize/take actions IAW 9-5 G-I & F-I 0

Check for leaks Maximize drywell cooling MCA keylock to bypass on CRP 9-25 0

CRP 9-25 RRU 3NB control switch to A&B run. (already done)

CRP 9-25 RRU 4NB control switch to A&B run. (already done)

Enteddirect actions IAW OT 31 1 I, High Drywell Pressure Direct manual scram per OT 3100 and enterldirect actions IAW EOP-I and 3.

Direct power reductiodtransfer house loads/manual scram Insert manual scram when directed/recognize automatic scram on high drywell pressure, inform CRS.

0 Press manual scram pushbuttons 0

Depress PB 1 on feedwater master controller CRP 9-5 0

Reactor mode switch to shutdown CRP 9-5 0

Insert IRMs/SRMs on CRP 9-5 0

Select IRM recorders on CRP 9-5 Report reactor power ~ 2 %

Report all control rods inserted 0

After verifying the RPV is recovering leave one RFP running, and place one in standby, and one in pull to lock CRP 9-6 0

Verify closed scram discharge vent and drain valves (6) on CRP 9-5 Recognize/report EOP-1 and 3 entries on high drywell pressure.

Monitor and report RHR, CS, EDG and SBGT initiations and PClS GROUP 2, 3, noting failures from previous power failure.

0 0

Group II valve switches to the closed position LRW 82/83/94/95 on CRP 9-4 Maintain level in 127-1 77 using preferred system (Feedwater and RCIC)

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 1 Scenario No.: 1 Event No.:

7 (contd)

Page 9 of 10 Time Position ACRO CRS ACRO CRS Applicants Actions or Behavior Close MSlVs to control cooldown rate if necessary due to steam flow from auxiliaries.

Attempt reactor pressure control below 1055 psig, report pressure lowering with MSIVs closed.

Report drywell/torus pressure trending up to 10 psig.

Direct Torus Sprays on A RHR loop before torus pressure reaches 10 psig.

Spray the torus as directed 0

Place A and D RHR pumps in PULL TO LOCK.

B and C RHR pumps in PULL TO LOCK.

Close/verify closed HX BYPASS RHR-65A Verify adequate SW pumps are operating to handle RHRSW pump demand.

Verify no more than one SW pump is in standby mode.

OR 0

0 0

IF a LPCl initiation signal is present, THEN place RHRSW PP A&C LPCl AUTOSTOP OVERRIDE SWITCH keylock switch to MANUAL OVERRD (3-M-2 will annunciate).

0 Start RHRSW pump A or C When conditions permit, verify RHRSW pump cooling water flow is 3 - 6 gpm.

If necessary, adjust RHRSW DISCHARGE, RHR-89A as follows:

0 Maintain RHRSW heat exchanger flow 2950 to 3140 gpm.

Maintain RHRSW pressure greater than 20 psid above RHR pressure.

IF reactor water level is greater than TAF, THEN 0

0 Open TORUS SPRAYKLG RHR-39A 0

Open TORUS SPRAY RHR-38A turn the RHR A/C LOGIC CTMT SPRAY VLV LPCl SIG BYPASS to MAN.

Direct drywell sprays with A RHR loop before reaching Unsafe region of DWSIL graph 0

0 Verify safe on DSlC 0

Verify torus level c 22.8 ft and in Safe Verify RRUs tripped or order shutdown

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

1 Scenario No.:

1 Event No.:

8 Page I O of 10 Event

Description:

Drywell spray valve does not open Cause: Containment spray valve mechanically binds in the closed position Initial Automatic Actions: N/A Effects (General Sequence): Valve will not open from Control Room Time CT

~

Position ACRO CRS ACRO ACRO CRS Applicant's Actions or Behavior Place " A RHR loop in Drywell spray per OP 2124, Appendix C 0

Open RHR-31A 0

Open RHR-26A 0

Recognize loss of valve position indication when drywell spray valve opened 0

Report inability to open RHR-26A Direct ACRO to coordinate with Aux Operator to locally open RHR-26A loop spray valve Recognize torus IeveVpressure cannot be maintained in the "safe" region of PSP graph or drywell temperature cannot be maintained below 280°F, Exits EOP-1, RPV pressure leg, enteddirect actions IAW EOP-5 0

Recognize RHR-26B not available due to bus loss 0

Direct rapid depressurization with bypass valves. May go direct to Emergency Depressurization 0

Open bypass valves by going to raise on the bypass opening jack on CRP 9-7 Do not exceed 40% steam flow as indicated on CRP 9-5 steam flow indicators Perform an Emergency Depressurization when directed Prevent injection from CS and RHR Pumps:

0 0

0 RV-71A switch to open 0

RV-71C switch to open 0

RV-71 B switch to open 0

RV-71D switch to open Report Aux Operator is able to manually open " A RHR Drywell Spray valve Recognize/report lowering drywell pressure once valve is open if RHR A loop pumps are running at that time.

Core spray AIB pump control switches pull to lock RHR A/B/C/D pump control switches pull to lock Open all SRVs on CRP 9-3 Classify event IAW A 0 3125 Alert per A-3-b/A-3-a

Appendix D Scenario Outline Form ES-D-1 acility:

Vermont Yankee (new)

Scenario No.:

2 Op-Test No.:

ixaminers:

Operators:

ACRO CRO CRS Dbjectives: Evaluate the crews ability to operate plant equipment in response to a loss of the startup transformers during closed cycle operation. Evaluate the Technical Specification for a loss of one off-site power source, and commence a plant shutdown to ensure NPDES compliance.

Recognize a stuck FWRV and take actions to avert a high reactor water level scram. Recognize and respond to an LPRM upscale failure. Recognize and respond to a loss of main condenser vacuum, ATWS, and SLC system failures.

nitial Conditions: IC-9, 100% power, preparing to chlorinate the Circ Water System rurnover: See Attached Shift Turnover Sheet Event No.

Event Type*

Event Description Malf. No.

ACRO CRS Place CW in Closed Cycle for chlorination 1

ACRO C

CRO CRS Key 1 ED-02A Preinsert ANN Failure FW-O9A 9-5-E-2 Key 2 NM2-24-41 B NM5D 97%

2 Loss of Startup Transformers R

CRO C

CRS Power Reduction with stuck Feedwater regulating valve Soft panel FRV A lockup red light out 3

LPRM upscale failure, APRM D upscale APRM D failure is Automatically deleted when LPRM 24-41 B is bypassed ACRO I

CRO CRS 4

ACRO c

CRO CRS Key 3 MC-8 7%

Key 3 modify MC-8 50%

120 See Main Condenser air inleakage (minor) 5 After control rod insertion for event 5 has started.

ACRO M

CRO CRS Main Condenser large air Leak Loss of Vacuum Turbine Trip / LNP ACRO M

CRO CRS Preinsert RD 12A 69%

RD 12B 74%

Preinsert SLOl A SL02 B Hydraulic ATWS / Level Power Control I

CRO CRS SLC A Pump Failure / B Squib Failure Bypass APRM A Preinsert NM-O6A APRM A INOP, Bypass APRM A prior to insertion (I)nstrument, (C)omponent, (M)ajor (N)ormal, (R)eactivity

SIMULATOR OPERATOR INSTRUCTIONS FOR SCENARIO (#2)

GENERAL REQUIREMENTS All chart recorders will be rolled forward, timed and dated.

Paper from selected chart recorders will be saved for the examination team as requested.

All procedures, flow charts, curves, graphs, etc., will be returned to their normal storage place and closed.

All markable procedures, boards, etc., will be erased.

All paper used by the previous crew will be removed and kept for the examination team as requested.

The simulator operator, or designated person, will keep a rough log of all communications into and out of the control room I during the scenario as requested by the examination team.

INITIAL SETUP

> IC-9 Summer Time IC-Hybrid Cycle P APRM A INOP and bypassed DURING THE SCENARIO The examination team will determine when each event is to be inserted and when to freeze and will inform the simulator operator.

> EVENT1 P EVENT2

> EVENT3 If asked, chemistry is chlorinating service water. When asked if weir is overflowing:

if level is > 225 ft, yes

. if level is 225 ft, no

. When directed report traveling screens in off and service water strainer breakers open OSAO when asked - report MOD T-3 open on all 3 phases, and visible damage to the startup transformers. If chemistry is asked, no chlorine has yet been added to the circ water system If TBAO is sent to the A FWRV report no obvious damage is visible. If the crew recommends locking up the A FWRV direct them as Operations Management to transfer control to local manual and lock up the valve.

> EVENT 4 If reactor engineer is asked about bypassing LPRM 24-41 B, inform them that as long as Technical Specifications are satisfied it can be bypassed. When LPRM 24-41 B is bypassed verify that APRM D failure (NM05D) automatically deletes itself. If not delete it manually.

> EVENT 5 No cause for the main condenser air leak will be found

> EVENTS 7 & 8 There appears to be nothing wrong with SLC pump A or Squib valve B (this infers an SLC switch failure)

TERMINATION P SLC injecting 9 RPV level controlled > -19

> Control rod insertion in progress

> Containment parameters under control

> Exam Team directs

SIMULATOR OPERATOR INSTRUCTIONS FOR SCENARIO (#2)

(con 't)

Malf. No.

Key 1 ED-02 Preinsert ANN Failure FW-O9A 9-5-E-2 Key 2 NM6D N M2 24-41 B Key 3 MC-8 7%

Key 4 50% 120 sec MC-8 Preinsert RD 12A 69%

RD12B 74%

Preinsert SLOl A SL02 B Event Type*

ACRO CRS ACRO C

CRO CRS R c CRO CRS ACRO I

CRO CRS ACRO C

CRO CRS

~

ACRO M

CRO CRS ACRO M

CRO CRS CRO CRS Event Description Place CW in Closed Cycle for chlorination Loss of Startup Transformers Power Reduction with stuck Feedwater regulating valve Soft panel A FRV lockup light out LPRM upscale failure, APRM upscale failure Main Condenser air inleakage (minor)

Main Condenser large air Leak Loss of Vacuum Turbine Trip / LNP Hydraulic ATWS / Level Power Control SLC A Pump Failure / B Squib Failure

SHIFT TURNOVER (#2)

PLANT CONDITIONS:

0 Approximately 100% power 0

Rapid shutdown sequence is latched INOPERABLE EQUIPMENTILCOS:

0 APRM A is INOP and bypassed SCHEDULED EVOLUTIONS:

0 Place Circ Water in closed cycle for chlorination after relieving the watch 0

Service water is to be chlorinated also SURVEILLANCES DUE THIS SHIFT:

0 None ACTIVE CLEARANCES:

0 NIA GENERAL INFORMATION:

3900-4500 v DG A/B BKR CONT SELECT Switches Bus 819 Bus 314 Other 4KV ACB's SAJ Transformer Aux Transformer Cond Backpress SW PPs A/B/CID Cond Sys Feed Sys CST Level (ER20001509-06)

Inst. Air Press Rx Water Level Rx Press Rx Power SLC sys SLC Tk Level ConriTapelFlow I NORWAlt F'wr NOTE 1: STA walkthrough to include status check of the Control Room Pyrotronics Panel.

NOTE 2: In the event minimum shift staffing levels cannot be met, actions to be initiated are specified in AP 0894.

NOTE 3: Control Room staff shall contact VELCO whenever abnormal yard conditions exist. (CAR910370Pl)

VYAPF 0152.01 AP 0152 Rev. 22 Page 1 of 1 LPC #5

TECH. SPEC./TEC"ICAL REQUIREMENTS M A N AL SYSTEMSKOMPONENTS INOPERABLE 2 a' VYAPF 0152.02 AP 0152 Rev. 22 Page 1 of 1

SHIFT BRIEFING CHECKLIST Mode Switch Position: L Shift:

8Af Night Day Date: %%!!

Plant Status: Rx Power 106 %

Rx Water Level: 166 I' Rx Pressure: h d r HP Clock (Note 3) /D Significant Equipment Out of Service (No e 1)-

APhWl A -2mPc?J q f N J e d Special Instructions or Considerations (Pertinent Night Orders, Unusual Conditions) (MOOID93010P2)

Briefing Conducted By:

Control Room Supervisor Previous twelve hour full power average during steady state operation >1592 MWt?

Yes 0 No NIA If no and unplanned, notify the Supervisor, Operations Support.

Attendees:

Spare Shift SM OR CRS CRO STA ACRO ACRO Shift Chem Tech.

Rad. Prot. Tech.

Sec. Shift Supv.

A 0 A 0 A 0 Approved by:

Duty Shift Manager Note 1: Include Tech. Spec. Systems/Components entered on VYAPF 0152.02 for which active measures by Operations must be taken and list those actions. (ER970390-01 & -02)

Note 2: Ensure evolutions that may affect radiological conditions such as HPCI, RCIC, Core Spray and RHR operations are brought to the attention of the Radiation Protection Technician.

Note 3: State I-P clock number. IF clock has been reset, discuss the event that resulted in the reset.

VYAPF 0152.03 AP 0152 Rev. 22 Page 1 of 1 LPC #2

CONTROL ROOM TURNOVER SHEET Date: irL;$aj\\L_

Shift: @ Nights Annunciators (Existing, New, Nuisance,

Disabled, Restored)

1. O MCJ

/qnt/*UNCl'&ddrs Surveillances DoneDue

/VONe/

volutions/Transients,

p/a& c u '19 =

eel uipment Out ofmeturned to Service Other VYAPF 0152.04 AP 0152 Rev. 22 Page 1 of 1

Appendix D Reauired ODerator Actions Form ES-D-2 Op-Test No.:

I Scenario No.:

2 Event No.:

1 Page 2 of 12 Event

Description:

Place CW in closed cycle for chlorination Time Position CRS CRO CRO CRO CRO CRO CRO CRO CRO ACRO / CRO Applicants Actions or Behavior Direct traveling screens to off, service water strainer breakers opened and circ water placed in closed cycle for chlorination Review prerequisites and admin limits to ensure they are satisfied Verify all CW and CWB pumps running Verify sufficient fans o to maintain condenser vacuum 1.O to 5.0 inches Call Chemistry to determine if service water will also be chlorinated Request a peer check Open recirc gate to > 70%

0 0

0 Recirc gate switch released Recirc gate switch on CRP 9-6 positioned to open and held (Throttle)

Position verified >70% on CRP 9-6 PI-104-3 Verify wier level c 225 ft (LI-104-10-1) on CRP 9-7 Direct an A 0 to check CW-7 open sufficiently to ensure no flow over of weir Close/check closed all intake gates 0

A intake gate control switch positioned to closed on CRP 9-6 0

B intake gate control switch positioned to closed on CRP 9-6 0

C intake gate control switch positioned to closed on CRP 9-6 Intake gates verified closed on CRP 9-6 POI-104-1A POI-104-1B POI-104-IC Verify backpressure < 5.0 (monitor backpressure)

Appendix D Required Operator Actions Form ES-D Op-Test No.:

1 Scenario No.:

2 Event No.:

2 Page 2 of 2 Event

Description:

Loss of Startup Transformers Time

~

Position

~

ACRO CRS CRS CRS CRS ACRO SE CRS ACRO CRS Applicant's Actions or Behavior

~

Diagnose and report loss of startup transformers Enter ON 31 50, Loss of Startup Transformers Send an operator to the relay house to complete VYOPF 2141.01/02.

Verify MOD T-3 open.

Visually inspect startup transformers.

Consult Technical Specifications 3.1 O.A.4, 3.1 O.B.3, 3.5.D.C Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> verify Main Transformer backfeed is available -

observation of plant status Enter 7 day LCO IAW 3.10.B.C Direct voltages checked on Bus 3, 4, 8, 9, on panel meters and ERFIS Check voltages on Bus 3, 4, 8, 9 as directed BUS 8 El-9-8-27 BUS 9 El-9-8-28 Bus3 Bus4 Check voltages on Bus 3,4, 8, 9, on ERFIS (ECCS status screen)

Direct EDG availability checked Check CRP 9-8 for normal standby conditions (no EDG alarm)

Direct Circ Water shifted to open cycle

Appendix D Required Operator Actions Form ES-D-2 1

ACRO CRS CRS CREW ACROKRO CRS CRS CREW CREW CRS CRO ACRO Scenario No.:

2 Event No.:

2 (cont'd)

Page 3 of 12 Shift Circ water to open cycle Open intake gates to 100%

0 Inform Chemistry proceeding to open cycle A intake gate control switch positioned to open on CRP 9-6 B intake gate control switch positioned to open on CRP 9-6 C intake gate control switch positioned to open on CRP 9-6 0

0 Intake gates verified open on CRP 9-6 POI-104-1A POI-104-1B POI-104-IC Fully close the recirc gate 0

0 Recirc gate switch on CRP 9-6 positioned to closed and held (Throttle)

Position verified 0% on CRP 9-6 PI-104-3 Recirc gate switch released Fully lower bypass gates (A & B) 0 0

0 0

0 Bypass gate A control switch to open on CRP 9-6 Bypass gate B control switch to open on CRP 9-6 Monitor fore-bay level on LI-104-2A on CRP 9-6 Monitor fore-bay level on Ll-I 04-2B on CRP 9-6 Monitor ERFIS and report NPDES status Notify DCO and Operations Manager Direct power reduction to 25 CTP at I 1 O%/minute to 27.0 to 27.5 mlbm/hr Monitor river temperature points M036/M037 Notify IS0 New England of power reduction Brief crew on plant status 0

0 0

Startup Transformer status 25% CTP as soon as possible Hot shutdown in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Unusual Event on Loss of Startup Transformers Potential LNP on a reactor scram Request maintenance point of contract assigned Direct Chemistry technician notify stake holders of unplanned power reduction Contact ISONELCO, inform them of power reduction Direct stability monitor verified operable Reduce recirc pump speed to a core flow of 27.0 to 27.5 mlbms/hr at the rate directed by the CRS 0

Turns controller 2-1 84-16-IN1 B manual knob in the counterclockwise direction on CRP 9-5 Adjust speed load changer per Figure 2 of OP 0105

Amendix D Reauired ODerator Actions Form ES-D Op-Test No.:

1 Scenario No.:

2 Event No.:

3 Page 4 of 12 Event

Description:

Power reduction with a stuck feedwater regulating valve P

Time Position CRO CRS CREW CRS CRS CRS CRO Applicants Actions or Behavior Report increasing reactor level Direct power reduction stopped until reactor level can be stabilized Check actual FRV positions on ERFIS.

Determine A FRV is not responding.

Contact Operations Management and recommend actions to deal with the stuck FWRV Brief crew on plans to deal with stuck feedwater regulating valve Direct the A FWRV transferred to individual manual and then to local manual Control and locked up Transfer the A FWRV to individual manual control as follows:

Press the display push button on FDW 12A individual controller Compare the S and V signals Verify the 3 and V signals are matched Depress the AIM push button on the FDW 12A controller Verify the green auto Led goes out on the FDW 12A controller Verify the red manual Led comes illuminates on the FDW 12A controller Then direct an A 0 to establish communications with the control room and take local manual control of the A FWRV in accordance with OP 2172

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

1 Scenario No.:

2 Event No.:

4 Page 5 of 12 Event

Description:

LPRM Upscale Failure, W scram RPS Time Position CRO CRS CRS ACRO CRS ACRO/CRO CRS CRS Applicants Actions or Behavior

_a P

Report LPRM 24-41 B upscale failure, APRM D hi hi, % scram Direct ACRO check LPRM 24-41 B on back panel May direct APRM D bypassed at this time and the W scram reset, if not it will be done in the subsequent steps Check and report LPRM 24-41 B failed upscale and APRM D reading 120%

Direct LPRM 24-41 B bypassed in accordance with ARS-9-5-M-I/M-3/N-7 OP 2456 Obtains OP 2456 0

0 Record time of bypass 0

0 0

Return APRM D to service 0

Notifies Shift Manager of APRM Rod block specification in TRM Table 3.2.5 not satisfied with APRMs A & D bypassed Bypass LPRM 24-41 B and verify bypass light on Reports APRM D returned to normal Determine APRM GAFs are/are not required Record time APRM D returned to service Enters control rod block LCO of TRM 3.2.5 Directs 1/2 scram reset if not already done

~

Appendix D Required Operator Actions Form ES-D-2 Position CREW CRS ACRO ACRO ACRO CRS CRO CRO Crew CRS ACRO CRS CRO CRS Applicants Actions or Behavior P

Report increased AOG flow/lowering condenser vacuum Enter ON 31 20, High Condenser Backpressure, and direct actions Verify all circ water and circ water booster pumps running on CRP 9-6 0

Circ water pump A red light on Circ water pump B red light on 0

Circ water pump C red light on Circ water Booster pump A red light on Circ water Booster pump B red light on Circ water Booster pump C red light on Verify 51 6 A open/throttled Verify steam seal pressure > 1 psig on PI-101-7 on CRP 9-7 Event

Description:

Minor Condenser Air lnleakage Direct core flow reduced t 29.5 to 29 mlbm @ less than or equal to 10%

CTP/Min Reduce core flow to 27.5 to 29.0 mlbm as directed 0

Master flow controller on CRP 9-5 rotated counter clockwise Report increasing RPV level Diagnose/recalI the A FRV as stuck using ERFIS, hold power reduction until RPV level is controlled Direct ACRO to monitor reactor level due to stuck FRV Monitor and control RPV level as directed Direct control rods inserted to maintain backpressure < 5 Insert control rods as directed (Rapid S/D seq)

Turn on select power 0

0 0

Depresses select button for control rod Drives control rod in with continuous insert to to insert limit of the rapid shutdown sequence Selects next rod in sequence and repeats step Brief crew that if a scram is necessary and LNP will occur causing a Loss of Feedwater/Condensate/MSIVs

Amendix D Reauired OPerator Actions Form ES-D-2 Op-Test No.:

1 Scenario No.:

2 Event No.:

6 Page 7 of 12 Event

Description:

Main Condenser large air inleakage, Loss of Vacuum, Turbine Trip, Loss of Normal Power Time I

Position 1

Applicants Actions or Behavior 1

CRS I Direct manual scram prior to 6.5 vacuum I

CRO I Scram the reactor as directed CRO 1 Attempt manual scram, report partial rod motion, reactor power ~ 2 %

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

1 Scenario No.:

2 Event No.:

7 Page 8 of 12 Event

Description:

Hydraulic ATWS / Level power control Time CT CT CT Position CRO CRO CRS CRS ACRO STA CRS Applicant's Actions or Behavior Initiate ARVRPT Trip recirc pump drive motor breakers Scram response Depress PB I on feedwater master controller CRP 9-5 Reactor mode switch to shutdown CRP 9-5 when steam flow <40%

Insert IRMs/SRMs on CRP 9-5 Select IRM recorders on CRP 9-5 Report reactor power when RPV level reaches 9 0 Report when reactor power is <2%

After verifying the RPV is recovering leave one RFP running, and place one in standby, and one in pull to lock CRP 9-6 when reactor power/steam flow allows Verify closed scram discharge vent and drain valves (6) on CRP 9-5 Enter EOP-1 0

Direct Table A automatic action confirmed Enter EOP-2 and direct:

0 ADS inhibited 0

0 Confirm ARVRPT Reactor mode switch to shutdown when steam,flow is <.5 mlbm/hr Inhibit ADS 0

0 Logic A inhibit collar depressed and rolled clockwise on CRP9-3 Logic B inhibit collar depressed and rolled clockwise on CRP9-3 Confirm Table A when directed Direct injection into the RPV terminated IAW OE 31 07 Appendix GG

Appendix D Required Operator Actions Form ES-D-2 3.:

1 ACRO CRS CRS Scenario No.:

2 Event No.:

7 (cont'd)

Page 9 of 12 Inhibit HPCl by depressing and rotating the inhibit collar on CRP 9-3 clockwise Terminate injection IAW OE 31 07 Appendix GG 0

Inhibit RHWCS by placing control switches on CRP 9-3 in pull to lock 0

RHRA 0

RHRC 0

RHRB 0

RHRD 0

CSA 0

CSB Inhibit feedwater and condensate by placing 0

0 RFP NBIC on CRP 9-6 pull to lock FWRV A/B shut using feedwater master controller Continue to lower RPV level until reactor power is 2%

Direct boron injection before torus temperature is > 1 10°F

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

1 Scenario No.:

2 Event No.:

8 Page 10 of 12 Event

Description:

SLC A Pump failure, B Squib failure, (ATWS Continuing)

Time CT CT CT Position CRO CRO CRS CRO CRS Applicants Actions or Behavior Inject boron 0

SLC control switch on CRP 9-5 to SYSl or SYS 2 Confirm pump start by red light for pump on CRP 9-5 CU 15 shut by green light only on CRP 9-4 CU 18 shut by green light only on CRP 9-4 CU 68 shut by green light only on CRP 9-4 0

Amber light out of CRP 9-5 0

ANN 9-5-A-1 squib continuity loss 0

Discharge pressure on CRP 9-5 PI-I 1-65 do not indicate the pump deadheaded 0

Red flow light on on CRP 9-5 indicating flow >30 GPM 0

SLC tank level lowering as indicated on CRP 9-5 LI-I 1-66 0

If system fails start other system Inject SLC with the B pump Report to the CRS the SLC system failures of A SLC pump, B Squib Verify RWCU isolates on CRP 9-4 0

0 0

Verify squib valve fires by Diagnose the A SLC pump failed to start and the B squib valve failed to fire 0

0 report SLC is injecting When reactor power is level > 1 9 and the level at which power went below 2% using H PCI/RCIC/CRD 2%, direct injection reestablished to maintain RPV Reestablish RPV injection to maintain RPV level in the ordered band Direct control rods inserted IAW Appendix BB/G

Appendix D Required Operator Actions Form ES-D-2 Op-Test I CT I.:

1 Scen:

CRO CRO I No.:

2 Event No.:

8 (contd)

Page 11 of 12 Insert control rods as directed Start all available CRD pumps.

Position the RWM keylock bypass switch to BYPASS concurrently If necessary, perform the following to open the CRD flow control valve.

Place FIC 3-301 CRD Flow Control in manual.

Adjust. FIC 3-301 CRD Flow Control to restore drive water pressure.

Close CRD-56 CRD Charging Water Header Supply Adjust CRD-PCV-20 DRIVE WTR PRESS CONTROL VALVE to achieve drive water differential pressure to between 300 and 500 psid.

The appropriate rod select template (MI) may be used as an aid, if desired.

The operator may initial, checkoff, or comment in the space provided after each control rod as appropriate.

Continuously insert control rods, using the ROD MOVEMENT CONTROL switch, to position 00 as follows:

Insert control rods using the sequence given on Figure I.

IF the sequence of Figure II is inadvertently started, THEN notify the CRS, insert all possible control rods in that sequence and proceed to the sequence given on Figure I.

IF, while inserting control rods, a control rod is mispositioned, THEN notify the CRS, insert that control rod to 00 and continue in the sequence.

IF, while inserting control rods, a control rod in the sequence is partially inserted, THEN insert that control rod to 00 and continue in the sequence.

IF, while inserting control rods, a control rod in the sequence cannot be moved or is at 00, THEN skip that control rod and continue in the sequence.

WHEN all possible control rods have been inserted per Figure 1(11),

THEN continue to insert control rods per Figure ll(1).

WHEN all control rods that can be inserted have been inserted, THEN inform the CRS.

APP BB Start all available CRD pumps.

Close CRD-56 CRD Charging Water Header Supply.

Fully OPEN CRD-PCV-20 DRIVE WTR PRESS from CRP 9-5.

Adjust CRD-PCV-22 CLG WTR PRESS to achieve drive water differential pressure between 300 and 500 psid.

When all control rods that can be inserted have been inserted, Then inform the CRS

Appendix D Required Operator Actions Form ES-D-2 OD-Test No.:

1 Scenario No.:

2 Event No.:

8 (cont'd)

Page 12 of 12 CRS ACRO ACRO ACRO Enter and direct actions in EOP-3 0

Restart Drywell RRUs 0

Initiate torus cooling 0

Before torus pressure reaches 10 psig, spray the torus Restart all drywell RRUs when directed.

0 0

0 0

0 0

MCA keylock to bypass on CRP 9-25 CRP 9-25 Blocking relay reset push button depressed CRP 9-25 RRU I N B control switch to A&B run CRP 9-25 RRU 2NB control switch to A&B run CRP 9-25 RRU 3NB control switch to A&B run CRP 9-25 RRU 4NB control switch to A&B run Initiate torus cooling when directed Place 0

0 0

0 0

A and D RHR pumps in PULL TO LOCK.

B and C RHR pumps in PULL TO LOCK.

Close/verify closed HX BYPASS RHR-65NB Verify adequate SW pumps are operating to handle RHRSW pump demand.

Verify no more than one SW pump is in standby mode.

OR IF a LPCl initiation signal is present, THEN place RHRSW PP A&C LPCl AUTOSTOP OVERRIDE SWITCH keylock switch to MANUAL OVERRD (3-M-2 will annunciate).

Start RHRSW pump A or C /B or D When conditions permit, verify RHRSW pump cooling water flow is 3 - 6 gpm.

If necessary, adjust RHRSW DISCHARGE, RHR-89NB as follows:

0 0

Maintain RHRSW heat exchanger flow 2950 to 3140 gpm.

Maintain RHRSW pressure greater than 20 psid above RHR pressure.

IF reactor water level is greater than TAF, THEN 0

turn the RHR A/C or B/D LOGIC CTMT SPRAY VLV LPCl SIG BYPASS to MAN.

0 Open TORUS SPRAYELG RHR-39N39B Open TORUS COOLING RHR-34N34B Spray the torus when directed.

0 Open RHR 39NB After Freeze, determine EAL in accordance with AP 31 25 as S-7-c.

Amendix D Scenario Outline Form ES-D-1 Op-Test Facility:

Vermont Yankee New Scenario No.:

3R No.:

Examiners:

Operators:

Objectives: Evaluate the crews response to a fault on 480 volt Bus 898 and to take the required Technical Specification actions for the bus loss. Recognize and take action for a trip of the running TBCCW pump with a failure of the automatic and manual start of the standby RBCCW pump. The complete loss of TBCCW will cause condensate and feedwater pump bearing temperatures to rise to the alarm set points. They will attempt to transfer house loads to the startup transformers but the breakers will not close. They will scram the reactor due to degrading conditions in the feed and condensate pump bearings. The fast and residual bus transfer to the startup transformers will fail when the turbine trips after the scram causing an LNP. The crew will enter OT 31 00 / EOP 1 (scram) and OT 3122 (LNP).

After the plant is stabilized a steam leak will occur in the drywell compounded by a loss of high pressure feed. EOP 3 will be entered to control primary containment parameters. After drywell sprays are initiated HPCl will trip. RPV level will lower due to the loss of high pressure feed sources and an RPV-ED will be preformed to allow low pressure injection sources to restore RPV level above TAF.

Multiple injection valve auto open failures will occur requiring operator actions to restore RPV level above TAF IC-9 100% power. RClC is out of service Initial Conditions:

See Attached Shift Turnover Sheet Turnover:

Event No. I Malf. No.

Event Description RF RCR05 N/A RClC 15 ACB opened after RClC 15 is closed (RCIC 00s)

CS03A p rei nsert Core Spray A injection valve auto open failure CS03B preinsert I

Core Spray B injection valve auto open failure I

RH07A Preinsert 1

I 1 RHR A injection valve auto open failure 1

C 1 Failure of breaker 23 to close manually

Amendix D Scenario Outline Form ES-D-1 ED12A ED12B Preinsert 1

1 1 ED19B SW 14A 2

SWdiOGswl2b I

3 I N/A RROIA 5% @ 800 sec ramp See above preinserts C

I C

C N

M C

(N)ormal, (R)eactivity Failure of breaker 13 to close manually (Switch I/O) No malfunction for this side is available Failure of Bus 1 and 2 to auto transfer to the startup transformers Loss of Bus 898 Trip of A TBCCW pump and failure of auto and manual starts of the B TBCCW pump Power reduction due to increasing component temperatures Recirc loop rupture HPCl turbine trip, loss of all high pressure feed Failure of injection valves to auto open Q_

(I)nstrument, (C)omponent, (M)ajor

SIMULATOR OPERATOR INSTRUCTIONS FOR SCENARIO (#3R)

GENERAL REQUIREMENTS 9

9 9

9 9

All chart recorders will be rolled forward, timed and dated.

Paper from selected chart recorders will be saved for the examination team as requested.

All procedures, flow charts, curves, graphs, etc., will be returned to their normal storage place and closed.

All markable procedures, boards, etc., will be erased.

All paper used by the previous crew will be removed and kept for the examination team as requested.

The simulator operator, or designated person, will keep a rough log of all communications into and out of the "control room ' I during the scenario as requested by the examination team.

INITIAL SETUP 9 IC-9,100% CTP, RClC 00s DURING THE SCENARIO The examination team will determine when each event is to be inserted and when to "freeze" and will inform the simulator operator.

P EVENT 1 If the Control Room sends maintenance or an A 0 to investigate the loss of RUPS "B"/Bus 89B, inform the crew that:

0 at RUPS 1 B - the Gen overhnder voltage lite is on and BKR "CB" is open (AC output BKR).

at MCC 89B - breaker "feed from UPS I B" is open. If the crew attempts to close the maintenance tie, it will trip.

0 if requested maintenance should inform the crew that there appears to be a fault on MCC89B and a work order is being initiated.

9 EVENT 2 If sent to investigate the loss of TBCCW report the A TBCCW pump breaker tripped and no reason for the start failure of the B TBCCW pump.

> EVENT 3 When directed to control recirc lube oil temperatures insert SWR

58.

After the manual scram and LNP if VELCO/AO/Maintenance are asked to report a cause for the LNP no cause will be found.

> EVENT 5 When sent to investigate the cause for the HPCl trip report a large oil leak has caused a loss of hydraulic and bearing oil.

> EVENT 6 If sent to manually open RHR 27B it will not open.

TERMINATION:

Reactor water level restored to above TAF and controlled with low pressure ECCS pumps. Exam Team directs.

SIMULATOR OPERATOR INSTRUCTIONS FOR SCENARIO (#3R)

Event Type

• Event Description Event No.

Malf. No.

RC05 Preinsert NIA RCIC isolation (RCIC 00s)

RF RCRO5 NIA RCIC 15 ACB opened after RCIC 15 is closed (RCIC 00s)

CS03A preinsert I

Core Spray A injection valve auto open failure CS03B preinsert I

Core Spray B injection valve auto open failure RH07A I

RHR A injection valve auto open failure Preinsert ED2 1 Preinsert EDdi08swz Preinsert ED12A Failure of breaker 23 to close manually Failure of breaker 13 to close manually (Switch VO) No malfunction for this side is available C

C ED 12B Preinsert I

Failure of Bus 1 and 2 to auto transfer to the startup transformers ED 19B C

Loss of Bus 89B SW14A SWdiO6swl2b Trip of A TBCCW pump and failure of auto and manual starts of the B TBCCW pump 2

C N

NIA RROlA

.5% @ 800 sec ramp H P O 1 See above preinserts Power reduction due to increasing component temperatures 5

Recirc loop rupture 4

M C

~

HPCI turbine trip, loss of all high pressure feed 5

6 Failure of injection valves to auto open (N)ormal, (R)eactivity (I)nstrument, (C)omponent, (M)ajor

SHIFT TURNOVER (#3R)

PLANT CONDITIONS:

0 Approximately 100% power.

Rapid shutdown sequence is latched RClC is 00s due to a failed steam flow D/P cell causing a rrious i latio INOPERABLE EQUIPMENT/LCOS:

RClC 14 days Technical Specifications 3.5.G.2. Entered 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> ago SCHEDULED EVOLUTIONS:

I/C is working on the failed RCIC steam flow D/P cell SURVEILLANCES DUE THIS SHIFT:

0 None ACTIVE CLEARANCES:

0 N/A I

GENERAL INFORMATION:

CONTROL ROOM SHlFT TURNOVER CHECKLIST Parameter/

Allowable Checks Component Cond/Limit 06, I 18 CS A/B Sys No A l d O p r J, I cs-7 A/B I Open 1

1 1

cs PP An3 I AUTO/Opr I /.I CS-5 A/B, 11 A/B Open J

CS-26 A/B, 12 A/B Closed CS FI-14-5OAlB 600 gpm

4.

RHR Sys I No AlarmdOpr I J-I RHR PP A/B/CID I AUTO/Opr 21,57,58 I Closed HPCI Flow I

I

/I

~~

ConVTapdFIow 1AUT0/4250/<100 I I

I NORWAlt Pwr I

I RPS MG A/B Power Avail.

Off-Gas Act Norm Trend Stack Gas Act Norm Trend Ref-2 A/B SBGT 9KW Hbs EUH-2&4 SGT-2N3A SGT-lA/B, 2B, 3B, 4A/B, 5 I Closed 1-0.25 to -2.0 inches I

./I v

Rx Bldg D P H20 DrywelUTorus DIP 21.8 psid TONS Water Level TVS-86 Closed

/.

t/

OP 21 15, Rg 1 I

I I

I I

I TIME 00%

NOTE 1: STA walkthrough to include status check of the Control Room Pyrotronics Panel.

NOTE 2: In the event minimum shift staffing levels cannot be met, actions to be initiated are specified in AP 0894.

NOTE 3: Control Room staff shall contact VELCO whenever abnormal yard conditions exist. (CAR910370Pl)

REMARKS:

m m

VYAPF 0152.01 AP 0152 Rev. 22 Page 1 of 1 LPC #5

TECH. SPEC./TECHNICAL REQUIREMENTS MANUAL SYSTEMSKOMPONENTS INOPERABLE OPERATIONS REQUIRED TECH.

D ATE/TIME LOGGING, TESTING OR ALIBwABLE DATE/T1ME SPEC.iTRh4 DECLARED UNPLANNED OTHER ACTION TIME DECLARED SYSTEWCOMPONENT PARAGRAPH INOPERABLE LCO (ER970390-03)

INOPERATIVE OPERABLE R c S C 3S*G. 2 fjrpa: h&

'pp 8 l o p.--

ff&

SWCRS x VYAPF 0152.02 AP 0152 Rev. 22 Page 1 of 1

SHIFT BRIEFING CHECKLIST Mode Switch Position:

&d Night Shift:

O M Day Date: %day Special Instructions or Considerations (Pertinent Night Orders, Unusual Conditions) (MOOID930 1 OP2)

N O Briefing Conducted By:

Control Room Supervisor Previous twelve hour full power average during steady state operation >1592 MWt?

d y e s 0 No 0 N/A If no and unplanned, notify the Supervisor, Operations Support.

Attendees:

Spare Shift SM OR CRS CRO STA ACRO ACRO A 0 A 0 A 0 Shift Chem Tech.

Rad. Prot. Tech.

Sec. Shift Supv.

Approved by:

Duty Shift Manager Note 1: Include Tech. Spec. Systems/Components entered on VYAPF 0152.02 for which active measures by Operations must be taken and Iist those actions. (ER970390-01 & -02)

Note 2: Ensure evolutions that may affect radiological conditions such as HPCI, RCIC, Core Spray and RHR operations are brought to the attention of the Radiation Protection Technician.

Note 3: State HP clock number. IF clock has been reset, discuss the event that resulted in the reset.

VYAPF 0152.03 AP 0152 Rev. 22 Page 1 of 1 LPC #2

CONTROL ROOM TURNOVER SHEET Equipment Out ofmeturned to Service RGK-Other Date: +

Shift:

Days Nights 0

VYAPF 0152.04 AP 0152 Rev. 22 Page 1 of 1

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

Scenario No.: 3R Event No.: 1 CRS Direct maintenance to investigate the loss of MCC 89B.

I CRS I

Review Tech Specs and determine per 3.10.B.4 and 3.5.A.4.b enter a 7-day LCO for "E" LPCI.

1 ACRO Direct A 0 to document indicating lights at RUPS 1 B and MCC 89B per OP 2143.

I CRS I Brief the Crew on the 7 day LCO, and the A LPCl loop will not inject if needed. I

Appendix D Required Operator Actions Form ES-D-2 Position

~

CRO CRO CRS CRS CRO CRS STA CRS ACRO CRS Applicant's Actions or Behavior Recognize a loss of running TBCCW pump Attempt to start the standby TBCCW pump, recognize both TBCCW pumps have tripped.

Direct maintenance and an A 0 to attempt to reset the breaker to restart a TBCCW pump Direct the CRO to begin lowering recirc speed to 27.5-29 mlb/hr at a rate not to exceed 10% RTPlmin Begin lowering Recirc speed using the master controller at a rate directed by the CRS 0

Adjusts master controller SC-2-184-14 in the counter clockwise direction scription:

Respond to a IOSS Of TBCCW Direct the crew to monitor the Condensate and Feed pump bearing temperatures Report when ERFIS alarms for Feed and Condensate pump temperatures High Direct the ACRO to transfer House Loads to the Startup Transformers treakgrs wih not close ttem t to # ansfer house loads to the startup transformers and report that the Turn on sync scope 0

Turn on sync scope 0

0 Insert sync key in 13 bkr Place 13 bkr control switch to close Report 13 bkr close failure Insert sync key in 23 bkr Place 23 bkr control switch to close Report 23 bkr close failure Direct a reactor scram and carry out actions in OT3100, and possible LNP.

Appendix D Required Operator Actions Form ES-D-2

~

Position CRO ACRO Event

Description:

Respond to a Reactor Scram with a loss of Off Site Power.

(I CRS ACRO ACRO CRS CRS CRO Applicant's Actions or Behavior Report reactor scram. Take scram actions 0

Press manual scram pushbuttons 0

0 0

Insert IRMs/SRMs on CRP 9-5 0

0 Report reactor power <2%

0 0

Depress PB 1 on feedwater master controller CRP 9-5 Reactor mode switch to shutdown CRP 9-5 when steam flow <40%

Select IRM recorders on CRP 9-5 Report all control rods inserted After verifying the RPV is recovering leave one RFP running, and place one in standby, and one in pull to lock CRP 9-6 0

Verify closed scram discharge vent and drain valves (6) on CRP 9-5 Recognize/report EOP-1 and 3 entries on high drywell pressure.

Recognize and inform CRS of Turbine Trip with Loss of Off Site Power Report power on buses 3,4,8,9 from the Diesels Enter and direct actions IAW OT 3122 LNP Respond to LNP IAW 3122.

0 Verify DG start SW pumps start 0

Station AC start 0

0 Restart drywell RRUs Depress blocking relay reset on CRP 9-25 Inform CRS that Buses 1 and 2 failed to transfer and the 13 and 23 breakers will not close.

Enter and direct crew actions IAW OT 3100, Rx Scram and EOP-1, RPV Control Direct reactor water level maintained 127" - 177" per EOP-1 with HPCI.

Report feed and condensate is unavailable.

Amendix D Reauired ODerator Actions Form ES-D-2 Op-Test 1.:

CRO/ACRO ACRO CRS Scenario No.:

3R Event No.:

3 (cont'd)

Page 4 of 9 Maintain reactor water level as directed with HPCI.

e e

e e

e e

e e

e e

e Open TEST RETURN HPCI-24.

Close/check closed PUMP DISCHARGE HPCI-19.

Throttle open FULL FLOW TEST HPCl21 8-10 seconds.

Start HPCl GL SL VAC FN-2-IA.

Verify both trains of SBGT start. (As time permits)

Open MINIMUM FLOW HPCI-25.

Open STEAM SUPPLY HPClI4.

As time permits, verify that STM LINE DRAIN HPCI-42 and HPCI-43 close.

Start AUX OIL PUMP P-85-1A and monitor SI 23-2 TURBINE SPEED.

As flow increases above 800 gpm, verify that MINIMUM FLOW HPCI-25 closes.

Control recirc flow rate to the CST and turbine speed by:

(BMO-200-7R-01)

a.

b.

C.

Adjusting HPCl FLOW CONTROLLER FIC 23-1 08, or Throttling FULL FLOW TEST HPCI-21 as necessary.

If HPCl FLOW CONTROLLER FIC 23-1 08 automatic feature fails:

1)

2)

Place HPCl PUMP FLOW CONTROLLER FIC 23-108 in MANUAL.

Control flow using the MANUAL knob.

Monitor the following HPCl parameters:

Parameters Normal Ranse Trip Point Exhaust Pressure 0-50 psig 130 psig Suction Pressure 6-30 psig 15 in. Hg Vac.

Stm Supply Pressure 150-1 120 psig 270 psig Turbine Speed

>2200-4000 rpm 5000 rpm Discharge Pressure

30 GPM SLC tank level lowering as indicated on CRP 9-5 LI-I 1-66 0

0 0

Verify squib valve fires by 0

0 0

0 Direct injection subsystems CS "A", CS "Bo and RHR "A" lined up for injection.

Lineup injection subsystems, as directed.

ShutRHR34A Shut RHR39A 0

ShutRHR38A Direct ADS inhibited.

Inhibit ADS 0

0 Logic A inhibit collar depressed and rolled clockwise on CRP9-3 Logic B inhibit collar depressed and rolled clockwise on CRP9-3

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

CT CRS I CRS ACRO/CRO CRS AC RO/CRO CRS CRS Scenario No.:

3R Event No.: 5 (contd)

Page 9 of 9 With the reactor shutdown and reactor pressure greater than the shutoff head of the low pressure systems, initiate RPV-ED BEFORE RPV level reaches -19 inches Standard:

Initiate RPV-ED (begin opening valves) BEFORE RPV level reaches -48 inches Direct all SRVs opened.

Open all SRVs on CRP 9-3 0

RV-71A switch to open 0

RV-71C switch to open 0

RV-71B switch to open 0

RV-71D switch to open Action is taken to restore RPV water level above -1 9 inches by operating available low pressure ECCS system(@ when RPV pressure decreases below the shutoff head of the low pressure systems Standard:

0 All available ECCS pumps are lined up for injection and running prior to RPV pressure reaching the injection valve open permissive pressure.

No pumps are secured until adequate core cooling is assured.

Initiate manual opening of injection valves within 1 minute of reaching valve open permissive pressure 0

0 Report failure of RHR-27A, CS-12A and CS-I26 to AUTO open and start to open them.

Direct RHR and CS injection valves opened.

~~~

Manually open RHR 27A and CS 12A and 128 injection valves as directed.

Direct reactor level restored to > TAF and then > 127 using RHWCS.

Consult AP 3125 and determine an Alert EAL has been reached IAW AP 31 25, A-3-a and/or A-3-b.

May be performed after the freeze