Latest revision as of 23:18, 11 March 2020

Text

301 Final Simulator Scenarios (Section 10)
	ML101610660
Person / Time
Site:	Summer
Issue date:	03/28/2010
From:	; NRC/RGN-II
To:	;
References
	2005-301, 50-395/05-301
	Download: ML101610660 (62)
	v • d • e

Appendix 0D Appendix Scenario Outline Scenario Outline Form Form ES-O-1 ES-D-1 Final Final Facility:

Facility: V. C.

V. C. Summer Summer Scenario No.:

Scenario No.: 11 Op-Test No.:

Op-Test No.: 2005-301 2005-301 Examiners:

Examiners: Operators:

Operators: CRS CRS RO RD PO PD Initial Conditions:

Initial Conditions: 100% IC, 100% IC, AT AT MOL.

MDL.

Turnover:

Turnover: Thunder storms storms inin the area, severe the area, severe weather weather check check listlist being being implemented.

implemented.

Al "A maintenance week.

1" train maintenance SIG A Small tube leak, approx. 8 gpd; MAL-RCS002A.

S/G MAL-RCSOO2A.

Motor Driven EFW Pump 'A' A Impeller replacement in progress with 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months to complete, have done 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months so far.

B S/G rad monitor (RMG-19B) is OOS. DOS.

Event Type*

Event Type* Event Description No.

11 RD (I)

RO Turbine Impulse Pressure Transmitter PT-446 Fails Low.

2 BOP (I) Steam Generator Steam Flow Transmitter Failure, 474 fails LOW.

RD (C)

RO VCT suction valve 115C ll5C fails closed (hot short at motor). This will cause the 3 SRD (TS)

SRO running Charging pump to cavitate and fail requiring entry into AOP-1 ADP-1 02.2 BDP(N)

BOP(N) and TS evaluation of loss of one CCP.

SRD(TS)

SRO(TS) The building operator calls the control room and reports that, while on his 4 rounds, he discovered a significant amount of oil on the floor in the TDEFP room and it appears that the governor may have leaked all its oil onto the floor.

RD RO (R) Reduce power to take the unit off line. In accordance with GDP-4B GOP-4B Power BDP BOP (N) Operation Mode 11 (Descending Power). MDS MDS calls and requests that due to 5

approaching severe thunderstorm he he would like to increase the power descension rate to 11%/min.

BOP (C) During During the Down power, the 00 FRV fails as as is, is, this will cause cause the operator to 66 have have to place thethe 00 FRV in in manual manual and and control the A SG SG in in manual manual during during the the Shut Shut Down.

Down. (AOP-210.l).

(AOP-21 0.1).

RD RO(C)(C) SG Tube Leak on on the C"c" SG, ramping to approximately the output of of the 7 existing existing charging charging pump(s).

pump(s). Ramp up up over aa 55 minute minute period.

period. (AOP-112.2),

(AOP-112.2).

SRO(TS)

M M (All)

(All) S/G S/G tube tube rupture on on the the CC SG to full SG to full flow flow of of aa tube tube (600 (600 gpm gpm ramped ramped inin over over 33 88 mm), requires reactor min), requires reactor trip. The Reactor trip. The Reactor will not trip will not trip (ATWS)

(ATWS) (EOP-l (EOP-13.0, 3.0, Entry, Entry, Response Response to to Abnormal Abnormal Nuclear Nuclear PowerPower Generation).

Generation).

BOP BOP (C)(C) When When thethe reactor reactor trips trips there there isis aa Loss Loss of of power power on on the the 1DB lOB emergency emergency busbus 99 due due to to the the thunderstorm.

thunderstorm. The The Emergency Emergency Diesel Diesel generator generator does does not not start start automatically.

automatically.

(N)ormal, .. (I)nstrument, (C)omponent, (R)eactlvlty, (l)nstrument, (N)ormal, (R)eactivity, (C)omponent, (M)ajor(M)aJor

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

Op Test No.: 11 Scenario No.:

Scenario No.: 11 Event No.:

Event No.: 11 Page Page --L2 of of 2Q..

20 Event

Description:

Event

Description:

Turbine Impulse Turbine Impulse Pressure Pressure Transmitter Transmitter PT-446 PT-446 Fails Fails Low.

Low.

Time Time Position Position Applicants Actions Applicant's Actions or or Behavior Behavior AOP-401 .7 AOP-401.7 Operator acknowledges Operator acknowledges annunciator annunciator 6152-5 615 2-5 (RCS (RCS TAVG-TREF TAVG-TREF DEVDEV RO RO HI/LO), recognizes IPT0446 HI/LO), recognizes 1PT0446 failure, failure, and and responds responds lAWlAW AOP-401.7 AOP-401 .7 RO ROD CNTRL BANK SEL Switch in MAN.

Place ROD MAN.

Ensure TREF 11 ST ST STG PRESS Switch is positioned to the operable RO channel 1PT0447, CH channellPT0447, OH IV).

IV).

RO Adjust Control Rods until Tavg is is within I.O°F 1.0° F of Tref.

RO Check if Main Turbine load Is GREATER THAN 10%.

Within one hour, verify the following permissives are dim:

RO P13. 1ST STG PRESS.

P7. REACTOR TRIP BLOCKED.

Restore automatic rod control:

a. Check if automatic rod control is desired.

b. Verify reactor power is GREATER THAN 15% (C-5 (0-5 status light dim).

RO c. Verify Tavg is within I.O°F 1.0° F of Tref.

d. Place ROD CNTRL BANK SEL Switch in AUTO (Crew may choose to return the rods to 230 steps prior to returning rods to auto but this is considered a good practice, not a requirement).

BOP Place STM DUMP MODE SELECT in STM PRESS.

BOP Notify I&C to place AMSAC in BYPASS Within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , place the failed channel bistables in a tripped condition.

SRO SRO evaluation of Tech Spec Table 3.3.3 (allow crew to fill out bistable trip sheet before moving on to next event

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

Test No.: 11 Scenario No.:

Scenario No.: 11 Event No.:

Event No.: 22 Page Page

- 33 of of ..1.2.-

20 Event

Description:

Event

Description:

Steam Generator Steam Steam Flow Generator Steam Transmitter Failure, Flow Transmitter Failure, 474 474 fails fails LOW.

LOW.

Time Time Position Position J Applicants Actions Applicant's Actions or or Behavior Behavior AOP-401.3 The BOP The BOP operator operator acknowledges acknowledges annunciator annunciator 624 624 4-4 4-4 in in alarm, alarm, BOP BOP 1FT0474 and responds lAW AOP-401.3 recognizes the failure of IFT0474 Depending on response time, annunciator 6241-5 624 1-5 (SG A LVL DEV) may BOP also alarm.

BOP Verify the failed channel is the controlling channel.

Select the operable flow channel:

Place FW CONTROL CHANNEL SEL Switch to the operable channel.

BOP Place STEAM CONTROL CHANNEL SEL Switch to the operable channel.

Verify Turbine Load is LESS THAN 950 MWe. Preferred is % 1/2 turn on limiter.

Using any method available, reduce Turbine Load by 40 MWe to 50 MWe. (The preferred method is Yz 1/2 turn on the load limiter) (The crew BOP may decide to borate to avoid RAOC concerns and, if so, would likely turn on BU heaters for improved mixing. This would not be required for such a small load decrease but would be a good practice). Expected plant response = = rods step in and Group 1 I steam dumps open.

BOP Verify only one SG is AFFECTED.

Adjust the Feedwater Flow Control Valve as necessary to restore BOP feed flow to the AFFECTED SG.

BOP Restore Narrow Range level in all SGs to between 60% and 65%.

Check if Feedwater Pump speed control is operating properly:

a. Feedwater Header pressure is GREATER THAN Main Steam BOP pressure.

b. Feed flow is normal for flow and power level.

c. All operating Feedwater Pump speeds and flows are balanced BOP Verify Narrow Range level in all SOs SGs is normal.

Restore the AFFECTED SG control systems to normal:

Place the Feedwater Feedwater Flow Flow Control Valve in AUTO. Place the Feedwater BOP Pump Speed Control System in in AUTO. REFER TO SOP-210, SOP-210, FEEDWATER SYSTEM.SYSTEM.

Within six Within hours, place six hours, place the failed channel protection bistables in in aa R

SRO tripped condition:

tripped SRO evaluates condition: SRO evaluates TechTech Spec Spec Table Table 3.3-3 3.3-3

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

Test No.: 11 Scenario No.:

Scenario No.: 11 Event No.:

Event No.: 33 Page ~

Page 4 of of .2Q..

20 Event

Description:

Event

Description:

VCT suction VCT suction valve 115C fails valve 115C fails closed closed (hot (hot short short at at motor).

motor). This This will will cause cause the the running running Charging Charging pump to pump to cavitate and fail cavitate and fail requiring requiring entry entry into into AOP-102.2 AOP-1 02.2 andand TSTS evaluation evaluation ofof loss loss of of one one CCP.

CCP.

Time Time ( Position Position Applicants Actions Applicant's Actions oror Behavior Behavior AOP-1 02.2 AOP*102.2 Operator acknowledges Operator acknowledges that that annunciators annunciators 614 4-2 (CHG 614 4-2 (CHG PP PP B/C TRIP),

TRIP),

614 5-1 (CHG 6145-1 (CHG LINE LINE FLO FLO HI/LO),

HI/LO), 6172-2,6182-2, 617 2-2, 618 2-2, && 619 619 2-22-2 (RCP (RCP A, A, B, B,

RO RO SEAL INJ C #1 SEAL INJ FLO FLO LO)LO) are all all in in alarm, alarm, recognizes recognizes the "B" B Charging Charging Pump has Pump has tripped, tripped, and and responds responds lAW lAW AOP-102.2 AOP-1 02.2 Check ifif Charging Check Charging Pump Pump flow flow is is normal:

normal:

IFIF Charging Pump has tripped or flow is abnormal, THEN perform the following:

oEl Ensure the Charging Pump is secured.

oEl Close all Letdown Isolation Valves:

PVT-8149A(B)(C), LTDN ORIFICE A(B)(C) ISOL.

PVT-8152, LTDN LINE ISOL.

LCV-459, L LTDN TDN LINE ISOL.

RO LCV-460, L LTDN TDN LINE ISOL.

(Expected plant response = RML*1 = RML-1 alarm on Letdown Isolation.)

oEl Close FCV-122, CHG FLOW.

oEl Verify CCW COW flow to the RCP Thermal Barriers is GREATER THAN 90 Fl-7273A(B), THERM BARR FLOW GPM.

gpm on FI-7273A(B),

Lin Display Dedicated Display ZZRCPBRG on the IPCS to monitor RCP temperatures.

(RML-1 expected alarm -letdown letdown isolation.)

CRS/SE Elo Contact Electrical and Mechanical Maintenance to investigate.

Verify Charging System valve lineup:

RO Elo IF Charging Pump suction is aligned to the VCT, THEN ensure both LCV-1 150(E), VCT OUTLET ISOL, LCV-115C(E), ISOL, are open.

Send someone to locally open the breaker for valve 1115C Send 150 and then to ORS/SE CRS/SE manually open the valve. valve.

SRO evaluates SRO evaluates Tech Spec Spec 3.5.2 3.5.2 andand determines 72 72 hr.

hr. action SRO SRO statement.

statement.

Elo Ensure Ensure thethe following following valves valves are are open:

open:

MVG-8106, MVG-81 06, CHG CHG PP. PP.

MVT-8109A(B)(C),

MVT-8109A(B)(C), CHG CHG PP PP A(B)(C).

RO RO MVG-8130A(B),

MVG-8130A(B), LP LP A A SUCT SUCT TO TO CHG CHG PP PP C.c.

MVG-8131A(B),

MVG-8131A(B), LP BB SUCT TO LP SUCT CHG PP TO CHG PP C.c.

MVG-81 MVG-8132A(B), 32A(B), CHG CHG PP PP C TO LP C TO LP A A DISCH.

DISCH.

MVG-8133A(B),_CHG_PP_C MVG-8133A(B), CHG PP C TO_LP_B_DISCH TO LP B DISCH Elo Check Check thethe Charging Charging header header valvevalve lineup lineup as as follows:

follows:

Ensure Ensure MVG-8107, MVG-81 07, CHG CHG LINELINE ISOL, ISOL, isis open.

open.

RO RO Ensure Ensure MVG-8108, MVG-8108, CHG CHG LINELINE ISOL, ISOL, isis open.

open.

Ensure_FCV-122,_CHG_FLOW,_is_in_MAN_and_CLOSE.

Ensure FCV-122, CHG FLOW, is in MAN and CLOSE.

RO RO Ensure the Ensure the following following valve valve isis open:

open:

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

No.: 11 Scenario No.:

Scenario No.: 11 Event No.:

Event No.: 33 Page Page 55 of of .22-20 Event

Description:

Event

Description:

VCT suction VCT valve 115C suction valve 1150 fails fails closed closed (hot (hot short short at motor). This at motor). will cause This will cause the the running running Charging Charging pump to pump to cavitate cavitate and and fail fail requiring requiring entry entry into into AOP-102.2 AOP-1 02.2 and and TSTS evaluation evaluation ofof loss loss of of one one CCP.

CCP.

Time Time Position Position Applicants Actions Applicant's Actions oror Behavior Behavior PVT-8147, ALT PVT-8147, ALT CHG CHG TO TO RCSRCS LP LP A.A.

D Locally verify LI Locally verify Charging Charging Pump Pump suction suction pressure pressure is is between between 50 50 psig psig and 100 and 100 psig indicated on the following (building psig as indicated (building operator operator report to report 52 52 BOP psig):

P1-i 51A, SUCTION PRESS, for Charging Pump A.

PI-151A, Shift Supervisor's With Shift Supervisors permission, permission, start aa Charging Charging Pump, Pump, while monitoring RCP temperatures. temperatures. REFER TO SOP-102, SOP-I 02, CHEMICAL RD RO AND VOLUME CONTROL SYSTEM. (SEE SOP 102 section III.B 111.8 below)

WHEN a Charging Pump is operating, THEN place Charging and RD RO Normal Letdown in service service.... REFER SOP-102, SOP-I 02, CHEMICAL AND VOLUME CONTROL SYSTEM. (SEE SOP-102 SOP-I 02 Section IV.M below)

SOP-102 Section III.B lIl.B Crew instructs the building operator to perform Attachment VB (Floor instructor to provide copy of Attachment VB if requested by crew) to mechanically and electrically align "C" C charging pump to "B" B Train. (If SRO the crew chooses, they might start "A" A CCW COW pump and "A" A charging pump to get a charging pump back while they are waiting to get "C" 0 charging pump racked up on "B" B Train. If so the steps below are nearly identically except for "A" A Train component numbers)

XPP-00430, PUMP C, on miniflow, complete Attachment VB if To start XPP-0043C, RD RO Charging Pump C is to be aligned to Train B.

Following the completion of Attachment VA(B), Chilled Water Expansion Tank levels should be monitored for indications of equalization:

. . 1) L9004A, CHILLED WATER EXPANSION TNK A LV, or Building 1L109004-VU, CHILL WATER EXP TK A LEVEL IND (IB-412).

ILl09004-VU,

2) L9006A, CHILLED WATER EXPANSION TNK BB LV, or ILl09006-VU ILl09006-VU,,_CHILL CHILL WATER TK_B_LEVEL_IND_(16-412).

TK B LEVEL IND (IB-412).

Verify P1-121, PI-121, CHG PRESS PSIG, is between 2650 psig psig and 2850 psig.

Monitor the following for proper pump operation:

a. LR-459, PZR % % LEVEL & LEVEL SP.

RO

b. FI-130A, ROP

b. RCP A INJ INJ FLO FLO GPM.

GPM.

c. FI-127A, RCP BB INJ FLO GPM. GPM.

d._FI-124A,_

d. FI-124A,RCP_C_INJRCP C INJ_FLO_GPM FLO GPM..

RD RO Ensure Ensure the BB train of of Component Cooling Cooling is is operating operating per SOP-118.

SOP-118.

RD RO Ensure Ensure the B B train of of Chill Water Water is is operating operating per per SOP-501.

SOP-501.

RD RO Ensure Ensure XPP-43C-PP XPP-43C-PP1, 1, CHG CHG PP PP C C AUX AUX OILOIL PP, PP, isis running.

Building Building Verify Verify 1P100153A, IP100153A, CHG CHG PUMPPUMP C SUCT HDR C SUCT HDR PRESS PRESS IND, IND, indicates indicates

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

No.: 11 Scenario No.:

Scenario No.: 11 Event No.:

Event No.: 33 Page Page 66 of of 2Q..

20 Event

Description:

Event

Description:

VCT suction VCT suction valve valve 115C 1150 fails fails closed closed (hot (hot short short at motor). This at motor). This will will cause cause the the running running Charging Charging pump to pump to cavitate cavitate and and fail fail requiring requiring entry entry into into AOP-102.2 AOP-1 02.2 and and TS TS evaluation evaluation of of loss loss of of one one CCP.

COP.

Time Time Position Position Applicants Actions Applicant's Actions or Behavior or Behavior pump suction pump suction pressure pressure is greater greater than 15 15 psig (AB-388).

(AB-388).

RO RO Start XPP-0043C, PUMP Start XPP-0043C, PUMP C. (PEER D)

C. (PEER Li)

RO Verify XPP-43C-PP1, CHG CHG PP C AUX OIL PP, stops automatically when the Charging Pump comes comes up to full speed.

IP100153A, CHG PUMP Verify IP100153A, PUMP C SUCT HDR HDR PRESS PRESS IND, IND, indicates Buildin g Building pump suction pressure is greater than 15 psig (AB-388).

Monitor the following to verify proper pump operation:

1) Charging Pump C running current is between 30 amps and 50 amps.

RO P1-121, CHG PRESS PSIG, is between 2650 psig and 2850

2) PI-121, psig.

3) XVG-9684C-CC, CCW TO CHG PP C, is open.

SOP-102 Section IV.M RO Place FCV-122, CHG FLOW, in MAN and close.

Place PCV-145, LO PRESS LTDN, in MAN and open to 70%. (PEER RO D)

El)

RO Place TCV-144, CC TO L LTDN TDN HX, in MAN and open to 100%.

RO Place TCV-143, LTDN TO VCT OR DEMIN, in VCT.

RO Open PVT-8152, LTDN LINE ISOL.

Open the following:

RO a. LCV-459, LTDN LTDN LINE ISOL.

b. LCV-460, LTDN LTDN LINE ISOL.

Ensure the following Charging Line Isolation Valves are open:

RO a. MVG-8107, CHG LINE ISOL.

b. MVG-8108, CHG LINE ISOL.

Slowly open FCV-122, CHG FLOW, to establish 60 gpm flow as RO indicated on Fl-i 22A, CHG FLOW GPM.

FI-122A, GPM.

Open Orifice Isolation Valves to obtain the desired Letdown flow rate (60 gpm to 120 120 gpm):

RO RO a.

a. PVT-8149A, LTDN ORIFICE PVT-8149A, ORIFICE A A ISOL ISOL (45(45 gpm).

gpm).

b. PVT-8149B,

b. PVT-8149B, LTDN LTDN ORIFICE BB ISOL ISOL (60(60 gpm).

gpm).

C. PVT-8149C, LTDN

c. LTDN ORIFICE ORIFICE C C ISOL ISOL (60(60 gpm).

gpm).

Adjust FCV-122, CHG CHG FLOW, as as required to to maintain maintain Tl-140, TI-140, REGENREGEN RO RO HX OUT HX OUT TEMP °F, of, between 250°F 250°F and 350°F while maintaining and 350°F maintaining Pressurizer Pressurizer level.level.

Adjust PCV-145, Adjust PCV-145, LO LO PRESS PRESS LTDN, LTDN, toto maintain maintain P1-i 45, LO PI-145, LO PRESS PRESS RO RO LTDN PRESS LTDN PRESS PSIG, PSIG, between between 300 300 psig psig and and 400 400 psig.

psig.

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

Test No.:

1 Scenario No.:

Scenario No.:

- 11 Event No.:

Event No.:

- 33 Page Page --1-7 of of .22..-

20 Event

Description:

Event

Description:

VCT suction VCT suction valve valve 115C 115C fails fails closed closed (hot (hot short short at at motor).

motor). This This will will cause cause the the running running Charging Charging pump to pump to cavitate cavitate and and fail fail requiring requiring entry entry into into AOP-102.2 AOP-1 02.2 andand TSTS evaluation evaluation ofof loss loss of of one one CCP.

CCP.

Time Time Position Position Applicants Actions Applicant's Actions or Behavior or Behavior RD RO Place PCV-145, Place PCV-145, LO PRESS LTON, LO PRESS LTDN, in in AUTO.

AUTO.

Adjust TCV-1 44, CC Adjust TCV-144, CC TOTO LTON LTDN HX, HX, potentiometer potentiometer as as necessary necessary to to RD RO maintain the maintain the desired desired VCT VCT temperature temperature and and place place in in AUTO.

AUTO. Refer Refer to to Curve Book, VCS Curve Book, Figure Figure V11.15.

VII.15.

When Pressurizer When Pressurizer level level matches matches reference reference level,level, place place FCV-122, FCV-122, CHG CHG RD RO FLOW, in FLOW, in AUTO AUTO per per Section Section IV. IV.

RD After the Letdown temperatures have stabilized, place TCV-143, LLTDN TON RO TO VCT OR OEMIN, DEMIN, in OEMIN/AUTO.

DEMIN/AUTO.

Can move on to next event when chg and letdown restored (no need to wait until level deviation cleared).

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

No.:

- 11 Scenario No.:

Scenario No.:

- 11 Event No.:

Event No.:

- 44 Page Page --L 8 of of 2Q..

20 Event

Description:

Event Descnption:

The building The building operator operator caliscalls the the control control room room and reports that, and reports that, while while on on his rounds, he his rounds, he discovered discovered aa significant amount significant amount of of oil oil on on the floor inin the the floor the TDEFP TDEFP roomroom and and itit appears appears that that the the governor governor may may have leaked have leaked ali all its oil onto its oil onto the the floor.

floor.

Time Time Position Position Applicants Actions Applicant's Actions oror Behavior Behavior Building Building Building operator Building operator reports reports oil oil leak leak onon TDEFP TDEFP governorgovernor (FCV(FCV now).

now).

Crew determines Crew determines TDEFP TDEFP isis inoperable inoperable and and decides decides to to remove remove itit from from service by by taking both both 2030 valve switches switches to the closed closed position.

position. Both Both annunciators 623 annunciators 623 2-3 2-3 and and 622 622 2-32-3 (TD (TD EFPEFP AUTOSTART AUTOSTART DEFEATED)DEFEATED)

SROIBOP SRO/BOP alarm as alarm as the the 2030 2030 valves valves close.close. (May (May also also choose choose to to disable disable the the TDEFP by tripping the Trip & Throttle valve or by by closing and removing powerfrom power from 2802A2802A&2802 & 2802 B).

SRO evaluates Tech Spec 3.7.1.2 and determines that a plant shutdown SRO is necessary (Hot Standby within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months )

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

Test No.: 11 Scenario No.: 11 Op

-- Scenario No.:

-- Event No.:

Event No.:

- 55 Page Page

- 99 of of 2Q..

20 Event

Description:

Event

Description:

Reduce power Reduce power to take the to take the unit unit off line. In off line. In accordance accordance withwith GOP-4B GOP-4B Power Power Operation Operation Mode Mode 11 (Descending Power).

(Descending Power). MDSMDS calls calls and and requests requests that that due due to to approaching approaching severe severe thunderstorm thunderstorm hehe would like would like to to increase increase the the power power descension descension raterate to to 11 %/min.

%/min.

Time Time Position Position Applicants Actions Applicant's Actions or or Behavior Behavior GOP-4B GOP-4B Reduce load by one of of the following methods:

BOP 1) By By use use of the DEC LOAD RATE circuit

2) By use use of the load limiter limiter MDS calls and requests that the load MDS load decrease be raised raised to 11%/mm

%/min SRO because of approaching severe thunderstorm.

As load decreases, adjust Megavars using GEN FIELD VOL VOLT T ADJ as BOP requested by the Load Dispatcher and within the Estimated Generator Capability Curve (Enclosure A).

Maintain Tavg within the control band by Control Rod motion or boron RO concentration changes.

Borate per SOP-106, SOP-i 06, Reactor Makeup Water System, to maintain the following parameters: (Good practice to turn on Backup heaters during RO boration to improve mixing but not procedurally required)

1) ~I1I within limits.

2) Control Rods above the Rod Insertion Limit.

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

No.: 11 Scenario No.:

No.: 11 Event No.:

No.: ..lQ..

Op Scenario Event

- 66 Page 10 of Page...:!.Q... of 20 Event

Description:

Event

Description:

During the During the Down Down power, power, the the 0El FRV FRV fails fails as as is, is, this this will will cause cause the the operator operator to have to to have to place the 0U place the FRV in FRV in manual manual and and control control the SG in the AA SG in manual manual during during the the Shut Shut Down.

Down. (AOP-21 0.1).

(AOP-210.1).

Time Time H Position Position Applicants Actions Applicant's Actions or or Behavior Behavior AOP-210.1 As load decreases, BOP operator notices that FCV-0478 FCV-0478 is failed as is and takes manual control of the valve lAW AOP-21 AQP-210.1.0.1. (Could possibly BOP receive annunciator 624 1-5 SG SG A LLVL DEV.) Crew VL DEV.) Crew may may also decide to BOP conservatively stop the load reduction reduction until until they can determine that they have manual control of the valve but this would not be required because it is not in the procedure.

Manually adjust the AFFECTED Feedwater Flow Control Valve as necessary to maintain Narrow Range SG level between 60% and 65%:

BOP oLI PVT-478, SG SC A FWF.

oLi PVT-488, SG B FWF. EWE.

oLI PVT-498, SG C FWF. FWE.

SRO Dispatch I&C l&C to determine cause of auto control failure.

Appendix 0D Appendix Required Operator Required OperatorActions Actions Form Form ES-D-2 ES-D-2 Op Test Op Test No.:

No.: 11 Scenario No.:

Scenario No.: 11 Event No.:

Event No.: 77 Page Page

- 1111 of of

~

20 20 Event

Description:

Event

Description:

SG Tube SG Tube Leak Leak on the "e" on the SO, ramping C SG, ramping to to approximately approximately the the output output of of the the existing existing charging charging pump(s). Ramp pump(s). Ramp upup over over aa 55 minute minute period.

period. (AOP-112.2).

(AOP-1 12.2).

Time Time Position Position Applicants Actions Applicant's Actions or or Behavior Behavior RD acknowledges RO acknowledges that that annunciator annunciator 6462-1 646 2-1 (MN(MN STMSTM LINELINE RMG-19 RMG-19 HI HI RD RO RAD) is in alarm RAD) is in alarm and and pulls pulls the the ARP.

ARP.

Verify the Verify the alarm alarm isis valid valid and and identify identify the the Main Main Steam Steam lineline affected affected byby RD RO observing RM-G19A, observing RM-G19A, B, B, and and C C and and RlR-8.

RIR-8.

Request Health Request Health Physics Physics perform perform radiological radiological surveys surveys around around thethe Main Main SRO SRO Steam lines.

Steam lines.

SRO Direct Chemistry to sample all Steam Generators for activity.

Direct Align the condenser exhaust to the Auxiliary Building Charcoal Charcoal Exhaust as follows:

XVB001 10-AR, MN&AUX COND VAC PP CHAR EXH DISCH

a. Open XVB0011O-AR, B ui ding Building VALVE (TB-436).

XVBOO1 09-AR, MN&AUX COND VAC PUMP ATMOS DISCH

b. Close XVB00109-AR, VALVE (TB-436).

BOP Reduce all Steam Generator blowdown flows to minimum.

SRO If the alarm is valid, refer to AOP-112.2.AOP-1 12.2.

AOP-1 12.2 (approx 90% power)

AOP-112.2 If they have not already done so in previous event, the crew may elect to Note stop the load reduction and stabilize power at this point (but not required by procedure).

Check if PZR level can be maintained:

a. Open FCV-122, CHG FLOW, as necessary to maintain PZR level RD RO this will cause annunciator 614 5-1 (CHG LINE FLO HI/LO) to alarm

- expected alarm).

b. Verify PZR level is at or trending to program level.

The The tube leak leak may eventually cause annunciator 624 624 3-5 (SG C C LVL BOP DEV) to alarm (expected alarm). alarm).

Reduce Letdown to one 45 45 gpm gpm orifice.

orifice.

a) Set a) Set PCV-145, PCV-145, LO LO PRESS LTDN, LTDN, to to 70%.

70%.

b) Ensure b) Ensure PVT-8149A, PVT-8149A, LTDN LTDN ORIFICE ORIFICE A ISOL, ISOL, is open~

is open RO RO c) Close c) Close bothboth PVT-8149B(

PVT-8149B(C), C), LTDN LTDN ORIFICE ORIFICE B(C) B(C) ISOL.

ISOL.

d) Adjust PCV-145, LO PRESS d) Adjust PCV-145, LO PRESS LTDN, to maintain LTDN, to maintain P1-i 45, LO PI-145, LO PRESS PRESS LTDN PRESS PSIG, LTDN PRESS PSIG, between between 300 300 psig and 400 psig and 400 psig.

psig.

e) e) Place Place PCV-145, PCV-145, LO LO PRESS PRESS LTDN, LTDN, in in AUTO.

AUTO.

IF PZR level continues to IF PZR level continues to decrease, THEN decrease, THEN perform perform the the following following RD RO Close Close PVT-8149A, PVT-8149A, LTDN LTDN ORIFICE ORIFICE A A ISOL.

ISOL.

RML-1 should alarm RML-1 should alarm duedue to to letdown letdown isolation isolation (expected (expected alarm) alarm)

SRO SRO Check Check ifif SI 51 isis required required At some At some pointpoint near near this this step step Pressurizer Pressurizer Pressure Pressure willwill drop drop below below the the

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

Op Test No.: 11 Scenario No.:

Scenario No.:

-- 11 Event No.:

Event No.: 77 Page Pag e ...1L 12 of of .22..

20 Event

Description:

Event Descnption: SG Tube SG Tube Leak Leak on on the the "C" SG, ramping C SG, ramping toto approximately approximately the the output output of of the the existing existing charging charging pump(s). Ramp pump(s). Ramp upup over over aa 55 minute minute period.

period. (AOP-112.2).

(AOP-1 12.2).

Time Time Position Position Applicants Actions Applicant's Actions oror Behavior Behavior Tech Spec Tech Spec 3.2.53.2.5 DNBDNB value value of of 2206#.

2206#. The The SRO SRO should should evaluate evaluate and and verbalize the verbalize the 22 hr.

hr. LCO LCO RO RO Verify VCT level is is being maintained between 20% and 40%.

Estimate the RCS leak rate using using IPCS CHGNET.

Calculate the RCS RCS leakleak rate.

rate. lAW lAW STP-114.002, STP-1 14.002, OPERATIONAL OPERATIONAL LEAK LEAK SRO/SE TEST.

Comply with Tech Spec 3.4.6.2 action statement. Determines that shutdown to mode 3 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months is required

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

Op Test No.: 11 Scenario No.:

Scenario No.: 11 Event No.:

Event No.: 88 Page 13 of Page.....:!1... of 2Q..

20 Event

Description:

Event

Description:

S/G tube S/G tube rupture rupture on on the the C C SG SG toto full full flow flow of of aa tube tube (600 (600 gpm gpm ramped ramped inin over over 33 min),

mm), requires requires reactor trip.

reactor trip. The The Reactor Reactor will will not not trip trip (ATWS)

(ATWS) (EOP (EOP -13.0,

-13.0, Entry, Entry, Response Response to to Abnormal Abnormal Nuclear Nuclear Power Generation).

Power Generation).

Time Time Position Position Applicants Actions Applicant's Actions or or Behavior Behavior Tube rupture Tube rupture 600 600 gpm gpm ramp ramp over over 33 min mm after after Tech Tech Spec Spec eval.

eval.

Acknowledges annunciator 616 1-5 1-5 (PZR LCS LOS DEV HIILO Hl/LO and responds lAW direction of CRS lAW ORS or if time allows lAW ARP.

ORS directs CRS directs the RO RD to insert a manual manual reactor reactor trip andand that they will SRO SRO actuate SI when directed by by EOP-1.0 EOP-1 .0 EOP-1 3.0 EOP-13.0 Verify Reactor Trip:

RD RO Trip the Reactor using both Reactor Trip Switches.

IF the Reactor will NOT trip OR is NOT subcritical, THEN insert Control RD RO Rods at the fastest control rod insertion rate CRITICAL Direction given to trip the reactor locally using Attachment 1I SRO Follow-up question - may ask SRO to classify this emergency event (Site Area Emergency)

Verify Turbine/Generator Trip:

BOP Verify all Turbine STM STOP VLVs are closed.

Depress Emerg Trip Sys TRIP.

Ensure Generator Trip Trip (after 30 second delay)

I

1) Ensure the GEN BKR is open.

BOP

2) Ensure the GEN FIELD BKR is open.

3) Ensure the EXC FIELD CNTRL is tripped.

Ensure EFW Pumps are running: BOP starts B "B" EFW Pump (It has BOP not auto started because SG level is not yet below 35% and SI has probably not yet actuated.)

Initiate emergency boration of the RCS:

Ensure at least one Charging Pump is running.

Verify PZR pressure is LESS THAN 2335 psig.

Verify SI ACT status light is NOT lit.

RD RO Verify SI flow on FI-943, CHG LOOP BB OLD/HOT CLD/HOT LG FLOW GPM.

GO TO Step 5. Observe the CAUTION prior to Step 5.

(Emergency boration is not required ifif SI has (Emergency has actuated by by this point and SI flow is verified)

Building Operator locally trips the RTBs at this point.

Building

. Verify all all Reactor Trip and 'Bypass Breakers are and Bypass are open.

open.

Building Building Verify all Rod Bottom Lights Lights are lit. lit.

Verify Verify Reactor Reactor Power Power level level isis decreasing.

decreasing.

Verify Containment 55 Verify Containment Ventilation Ventilation IsolationIsolation Valves Valves closed closed by by RD RO verifying verifying the the Safety INJECTION Safety INJECTION monitor monitor lights lights are are dim, dim, (Time (Time permitting, permitting, perform perform EOP-1EOP-1.0 .0 steps steps 11 - 88 in in conjunction with with this

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

Test No.: Scenario No.: --2i. 22..

Op

- 11 Scenario No.:

- 11 Event No.:

Event No.:

8 Page Page 14 of of 20 Event

Description:

Event

Description:

S/G tube rupture S/G tube rupture on on the the CC SG SG toto full flow of full flow of aa tube tube (600 (600 gpm gpm ramped ramped inin over over 33 min),

mm), requires requires reactor trip.

reactor The Reactor trip. The will not Reactor will not trip trip (ATWS)

(ATWS) (EOP -13.0, Entry, (EOP -13.0, Entry, Response Response to to Abnormal Abnormal Nuclear Nuclear Power Generation).

Power Generation).

Time Time Position Position j Applicants Actions Applicant's Actions or or Behavior Behavior procedure) procedure)

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

No.: --L1 Scenario No.:

Scenario No.: 11 Event No.:

Event No.: 99 Page Page ....:!.?.

15 of of 2Q..

20 Event

Description:

Event

Description:

When the When the reactor reactor trips trips there Loss of there isis aa Loss of power power on on the the lOB 1DB emergency emergency busbus due due to to the the thunderstorm. The thunderstorm. The Emergency Emergency Diesel Diesel generator generator does does not not start start automatically.

automatically.

Time Time Position Position Applicants Actions Applicant's Actions oror Behavior Behavior BOP operator notes BOP notes that there is no no power power on IDB 1DB and that that the diesel did not not start. He notes He notes that that there there isis aa lockout lockout onon XFMR-XTF31 (by (by BOP BOP recognizing annunciator 639 4-2 in alarm). BOP operator also notes that annunciator 6376-1 637 6-1 (DG B ENG START FAIL) is in alarm BOP operator depresses the "B" B DG DG Emergency Start Start Pushbutton and BOP BOP notes that the diesel does start and the DG notes DG breaker breaker does close to energize 11DB. DB.

Verify the Reactor is subcritical: Power Range channels indicate RO LESS THAN 5%.

Intermediate Range channels indicate a negative startup rate SRO GO TO Step 15. Observe the CAUTION prior to Step 15.

SRO RETURN TO the Procedure and Step in effect (EOP-1.0).

EOP-1 0 EOP-1.0 Verify Reactor Trip:

Trip the Reactor using either Reactor Trip Switch.

RO Verify all Reactor Trip and' and Bypass Breakers are open.

Verify all Rod Bottom Lights are lit.

Verify Reactor Power level is decreasing.

Verify Turbine/Generator Trip:

Verify all Turbine STM STOP VLVs are closed.

Ensure Generator Trip (after 30 second delay):

BOP Ensure the GEN BKR is open.

Ensure the GEN FIELD BKR is open.

Ensure_the_EXC_FIELD_CNTRL_is_tripped.

Ensure the EXC FIELD CNTRL is tripped.

BOP Verifies Power on both ESF busses

. At some point after the reactor trip Hi Rad on RMA-09. 645 1-3 1-3 CNDSR EXH RM-A9 HI RAD should come in and is an expected alarm with aa tube rupture.

Check if if SI 51 is actuated:

Check ifif either SI ACT status light is bright on XCP-6107 1-1 Check 1-1 or Any red RO first-out SI SI annunciator annunciator is is lit on XCP-626 lit on XCP-626 top row.

Actuate Actuate SI SI using using either either SI SI ACTUATION Switch. Switch.

Complete Complete ATTACHMENT ATTACHMENT 3, SI EQUIPMENT VERIFICATION.

3,51 VERIFICATION. (If (If not not already already done,done, the the BOP BOP operator operator should should be be throttling throttling EFW EFW flow flow to to BOP BOP zero to the C "C" SG because itit has SG because has been been identified identified as as the the ruptured SG). OAP-1 03.4 SG).OAP-103.4 SRO SRO Announce Announce plant plant conditions conditions over over the the page page system.

system.

RO RO Verify Verify RBRB pressure pressure has has remained LESS LESS THANTHAN 12 12 psig psig on on PR-951, PR-951, '

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

No.: --L1 Scenario No.:

Scenario No.: 11 Event No.:

Event No.: 99 Page ~

Page 16 of of 2Q...

20 Event

Description:

Event

Description:

When the When the reactor reactor trips trips there there isis aa Loss Loss of of power on the power on the lOB 1DB emergency emergency bus bus due due toto the the thunderstorm. The thunderstorm. The Emergency Emergency Diesel Diesel generator generator does does not not start start automatically.

automatically.

Time Time Position Position Applicants Actions Applicant's Actions or or Behavior Behavior RB PSIG RB PSIG (P-951),

(P-951), red red pen.

pen.

Check RCS Check RCS temperature:

temperature:

With any RCP With any ROP running, running, RCS RCS Tavg Tavg isis stable stable at at OR OR trending trending to to 55rF.

557° F.

BOP BOP WHEN Narrow WHEN Narrow RangeRange SG level isis GREATER SG level GREATER THAN THAN 30%30% [50%][50%] in in atat least one least one SG, THEN control SG, THEN control EFW EFW flow as as necessary necessary to stabilize stabilize RCSRCS temperature at temperature at 55rF.

557°F.

Check PZR Check PZR PORVsPORVs and and Spray Spray Valves:

Valves:

PZR PORVs PZR PORVs are are closed.

PZR Spray Valves are closed.

Verify power is available to at least one PZR PZR PORVPORV Block Valve.

RO MVG-8000A, RELIEF 445 A ISOL.

MVG-8000B, RELIEF 444 B ISOL.

MVG-8000C, RELIEF 445 B ISOL.

Verify at least one PZR PORV Block Valve is open Check if RCPs should be stopped:

RCS pressure is LESS THAN 1400 psig AND SI flow is indicated on RO FI-943, CHG LOOP B CLD/HOT OLD/HOT LG FLOW GPM.

Note: RCS pressure should be about 1800 psig so no RCP ROP trip should be required.

Verify no SG is FAULTED:

BOP No SG pressure is decreasing in an uncontrolled manner.

No SG is completely depressurized.

Verify Secondary radiation levels indicate SG tubes are NOT RUPTURED:

RM-G19A(B)(C), STMLN HI RNG GAMMA.

RO RM-A9, ONDSR CNDSR EXHAUST GAS ATMOS MONITOR.

RM-L3, STEAM GENERATOR BLOWDOWN LIQUID MONITOR. MONITOR.

RM-L10, RM-L 10, SG BLOWDOWN OW CW DISOHARGE DISCHARGE LIQUID MONITOR.

CRITICAL GO TO EOP-4.O, EOP-4.0, STEAM GENERATOR TUBE RUPTURE, Step Step 1. 1.

SRO SRO Check Check ifif RCPs RCPs shouldshould be be stopped:

stopped:

Oheck Check ifif either either ofof the the following following criteria criteria isis met:

met:

Annunciator Annunciator XOP-612 XCP-612 4-2 4-2 is is lit (PHASE BB ISOL).

lit (PHASE ISOL).

RO RO OR OR ROS RCS pressure pressure isis LESS LESS THAN THAN 1400 1400 psigpsig AND AND SI SI flow flow isis indicated indicated on on FI-943, FI-943, OHGCHG LOOP LOOP BB OLD/HOTCLD/HOT LG LG FLOWFLOW GPM. GPM.

Note:

Note: ROS RCS pressure pressure shouldshould be be about about 18001800 psig psig so so itit should should not not be be necessary to secure necessary to secure any RCPs any ROPs SRO SRO Identify Identify the the RUPTURED RUPTURED SG(s): SG(s):

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

Op Test No.: ......L.

1 Scenario No.:

Scenario No.: _1_ 1 Event No.:

Event No.: ..L9 Page Page ..JL 17 of of .2Q..

20 Event

Description:

Event

Description:

When the When the reactor reactor trips trips there there is is aa Loss Loss of of power power on on the the lOB 1DB emergency emergency bus bus due due to to the the thunderstorm. The thunderstorm. The Emergency Emergency DieselDiesel generator generator does does notnot start start automatically.

automatically.

Time Time I Position Position Applicants Actions Applicant's Actions or or Behavior Behavior Narrow Range Narrow Range level level in in any any SG SG increasing increasing in in an an uncontrolled uncontrolled manner, manner, OR OR High Radiation High Radiation on on any any of of RM-G19A(B)(C), STMLN HI RNG GAMMA, OR RM-G19A(B)(C),

Local hand held radiation monitor readings taken by Health Physics on blowdown lines at the blowdown at following penetrations:

penetrations:

XRP0326, SG A Blowdown Blowdown Line Line (AB-412 (AB-412 West Pen). Pen).

XRP0224, SG B B Blowdown Blowdown Line Line (IB-412 East East Pen XRP0219, SG C Blowdown Line (IB-412 East Pen),

OR As determined by Chemistry ample analysis for abnormal activity using a frisker.

Isolate flow from each RUPTURED SG: Place the Steam Steamlineline PWR RELIEF A(B)(C) SETPT Controller(s) in MAN and closed.

Adjust the PWR RELIEF A(B)(C) SETPT Controller(s) to 8.85 (1150 BOP psig).

Place the Steamline Power Relief A(B)(C) Mode Switch(s) in PWR RLF.

Place the PWR RELIEF A(B)(C) SETPT Controller(s) in AUTO.

WHEN RCS Tavg is LESS THAN P-12 (552°F), THEN place both STM BOP DUMP INTERLOCK Switches to BYP INTLK.

BOP Verify the Steamline PORV closed.

IF at least one MD EFW Pump is running, THEN isolate the TD EFW BOP Pump by placing PVG-2030, STM SPL SPLY Y TO TD EFP to CLOSE.

Open XMC1DB2Y XMC1 DB2Y 05EH, O5EH, EMERG FEEDWATER PUMP MAIN STEAM BLOCK XVG28O2B-MS XVG2802B-MS (AB-463).

BOP/Bldg Close XVGO28O2B-MS, XVG02802B-MS, MS HEADER C EF PUMP TURBINE SUPPLY SUPPLY VLV Close the following for each RUPTURED SG:

SG Blowdown, PVG-503A(B)(C).

BOP MS Drain Isolation, PVT-2843A(B)(C).

MS_Drain_Isolation,_PVT-2877B_for_SG_C.

MS Drain Isolation, PVT-2877B for SG C.

Close the following for each RUPTURED SG:

BOP MS Isolation Valve, PVM-2801A(B)(C AND_MS_Isolation_Bypass_PVM-2869A(B)(C).

AND MS Isolation Bypass PVM-2869A(B)(C).

Verify Narrow Narrow Range Range levellevel inin each each RUPTURED SG SG isis GREATER GREATER THAN 30% [50%].

a. Stop EFW EFW flow to each RUPTURED RUPTURED SG: SG:

BOP 1)

1) Close FCV-3551, MD MD EFPEFP TO SG SG C.

2) Close FCV-3556, TD EFP TO SG SG C.

3)

3) Maintain_Narrow_Range_level_in_C_SG_GREATER_THAN_40%_[50%].

Maintain Narrow Range level in C SG GREATER THAN 40% [50%].

BOP/SRO BOP/SRO Verify each RUPTURED Verify each RUPTURED SG SG pressure pressure is is GREATER GREATER THAN THAN 350 350 psig.

psig.

Determine Determine the the required required core core exit exit TCTC temperature temperature for for RCS RCS SRO SRO cooldown.

cooldown.

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

Op Test No.: 11 Scenario No.:

Scenario No.: 11 Event No.:

Event No.: 99 Page Page ---2!L 18 of of 22-20 Event

Description:

Event

Description:

When the When the reactor reactor trips trips there there isis aa Loss Loss ofof power power onon the 1DB emergency the lOB emergency bus bus due due to to the the thunderstorm. The thunderstorm. The Emergency Emergency Diesel Diesel generator generator does not start does not start automatically.

automatically.

Time Time Position Position ) Applicants Actions Applicant's Actions or or Behavior Behavior SRO/RO SRO/RO Check ifif any Check any RCP RCP isis running running (all running).

(all running).

Dump steam Dump steam from from each each INTACT INTACT SG: SG:

WHEN RCS WHEN RCS Tavg Tavg isis LESS LESS THANTHAN P-12 P-12 (552"F),

(552F), THEN:

THEN: Place Place both both STM DUMP INTERLOCK STM DUMP INTERLOCK Switches Switches to BYP INTLK.

to BYP INTLK. Place Place both both STMLN STMLN SI TRAIN SI TRAIN A(B) A(B) Switches Switches to BLOCK.

to BLOCK.

Verify PERMISV Verify PERMISV C-9 C-9 status status light light is is bright bright on XCP-61 14 1-3.

on XCP-6114 1-3.

BOP BOP Verify the MS MS Isolation to open.Valves, PVM-2801APVM-2801A & B are open Place the STM STM DUMP CNTRL Controller in MAN Place the STM Place STM DUMP DUMP MODE MODE SELECTSELECT Switch Switch in in STM PRESS.

PRESS.

Adjust the STM DUMP CNTRL Controller to fully open the Bank 11 Steam Dump Valves.

RO While cooling down, a high vibration on "C" C RCP may occur. If so, secure RCP "C" C a required by SOP*101 SOP-I 01 BOP Verify Narrow Range level in SGs A & B 30% [50%].

BOP Control EFW flow to maintain in SGs between 40% [50%] and 60%.

RO Verify power is available to the PZR PORV Block Valves:

RO Verify all PZR PORVs are closed.

RO Verify at least one PZR PORV Block Valve is open.

RO Reset both SI RESET TRAIN A(B) A{B) Switches.

Reset Containment Isolation:

RO RESET PHASE A - TRAIN A(B) CNTMT ISOL.

- ISOL.

RESET PHASE BB - TRAIN A(B) CNTMT ISOL.

Place both ESF LOADING SEQ A(B) A{B) RESETS to:

BOP a. NON-ESF

a. NON-ESF LCKOUTS.

b. AUTO-STAR AUTO-START T BLOCKS.

BLOCKS.

Establish Establish Instrument Instrument Air to the RB:

a. Start one

a. one Instrument Instrument Air Compressor Compressor and place place the the other other in in Standby.

Standby.

RO RO

b. Open PVA-2659,

b. Open PVA-2659, INST INST AIR AIR TOTO RB RB AIRAIR SERV.

SERVo

c. Open PVT-2660, C. Open PVT-2660, AIR SPLY SPLY TO TO RB. RB.

RO RO Stop both Stop both RHR RHR pumps pumps Verify Verify core core exit exit TC TC temperature temperature is is LESS LESS THANTHAN the the value value SRO SRO determined in Steps determined in Steps 88 through through 10 10 Stop the RCS Stop the RCS cooldown: cooldown:

a.

a. Ensure Ensure StepStep 10 10 is is completed.

completed.

BOP BOP

b. Adjust

b. Adjust steam steam dump dump setpoints setpoints as as necessary necessary to to maintain maintain desired desired core core exit TC temperature.

exit TC temperature.

BOP BOP Verify each RUPTURED Verify each RUPTURED SO SG pressure pressure is is stable stable OR OR increasing.

increasing.

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

Test No.: 11 Scenario No.:

Scenario No.: 11 Event No.:

Event No.: 99 Page Page ...:!2..

19 of of 2Q..

20 Event

Description:

Event

Description:

When the the reactor reactor trips trips there there isis aa Loss Loss ofof power power on the lOB on the 1DB emergency emergency bus When bus due due to to the the thunderstorm. The thunderstorm. The Emergency Emergency Diesel Diesel generator generator does does not not start start automatically.

automatically.

Time Time Position Position Applicants Actions Applicant's Actions or or Behavior Behavior Verify RCS Verify RCS subcooling subcooling on on TI-499A(B),

Tl-499A(B), A(B) A(B) TEMPTEMP is is GREATER GREATER ROISRO RO/SRO THAN 50°F.

THAN 50°F.

Depressurize the Depressurize the RCS RCS using using Normal Normal PZR PZR SpraySpray at at the the maximum maximum rate: (PCV-444C rate: (PCV-444C should should not not be opened ifif "c" be opened C RCP RCP has has been secured been secured inin a previous a previous step) step)

CRITICAL Using RCP Using RCP A: A:

CRITICAL

1) Open

1) Open PCV-444D, PCV-444D, PZR PZR SPRAY.

SPRAY.

RO RO 2) Close

2) Close PCV-444C, PCV-444C, PZR PZR SPRAY, ifif RCP RCP C C isis NOT NOT running running Using RCPs BAND Using RCPs B AND C:

1) Open PCV-444C, PZR SPRAY.

1) SPRAY.

Close PCV-444D,

2) Close PCV-444D, PZR SPRAY, ifif RCP A is is NOT running.

Use maximum available spray until anyone any one of the following criteria is met:

PZR level is GREATER THAN 68% [54%].

OR RCS subcooling on TI-499A(B), Tl-499A(B), A(B) TEMP "F, F, is LESS THAN 30"F. 30F.

OR RCS pressure is LESS THAN RUPTURED SG(s) pressure AND PZR level is GREATER THAN 18% [38%].

Upon meeting one of the above criteria, Stop RCS depressurization: depressurization:

RO PCV-444C(D), PZR SPRAY.

1) Close both PCV-444C(D),

2) Close PVT-8145, PZR SPRAY FR CVCS.

Check if SI flow should be terminated:

a. RCS subcooling on Tl-499A(B), TI-499A(B), is GREATER 30F 30"F

b. Secondary Heat Sink is adequate:

RO/BOP (Total EFW flow available to INTACT SGs is GREATER THAN 450 gpm.

OR Narrow Range SG level is GREATER THAN 30% [50%] in at least one INTACT SG.)

c. RCS pressure is stable OR increasing.

d.

d. PZR level is is GREATER THAN 18% 18% [38%].

RO Stop all but one Charging Pump Stop Pump and place in in Standby.

Establish Normal Normal Charging:

Charging:

a. Close

a. Close FCV-122, CHG CHG FLOW.

FLOW.

RO RO b.

b. Open Open bothboth MVG-8107 MVG-8107 and and MVG-8108, MVG-81 08, CHG CHG LINE LINE ISOL.

ISOL.

c.

c. Adjust FCV-122, FCV-122, CHG CHG FLOW,FLOW, to to obtain obtain 60 60 gpm gpm Charging Charging flow.

d. Close both MVG-8801A

d. Close both MVG-8801A(B), HI HEAD TO (B), HI HEAD TO COLD COLD LEG LEG INJ.INJ.

RO RO Control Control FCV-122, FCV-122, CHG CHG FLOW,FLOW, to to maintain maintain PZR PZR level.

level.

Verify Verify SISI flow flow is is NOT NOT required:

required:

a. RCS subcooling on TI.-499A(B)

a. RCS subcooling on TI-499A(B),, isis GREATER GREATER THAN THAN '30"F.

30F.

RO RO

b. PZR

b. PZR level level isis GREATER GREATER THAN THAN 18% 18% [38%].

[38%].

This the endpoint This isis the endpoint of of this this JPM JPM oror asas directed directed by by the the NRC.

NRC.

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

No.: 1 Scenario No.:

No.: 1 Event No.:

No.: -2.£..

Op Scenario Event

- 99 Page Page 20 of of 22-20 Event

Description:

Event

Description:

When the the reactor reactor trips trips there there isis aa Loss Loss of of power power on on the the lOB 1DB emergency emergency bus When bus due due to to the the thunderstorm. The thunderstorm. The Emergency Emergency Diesel Diesel generator generator does does not start automatically.

not start automatically.

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

7 Appendix DD Appendix Scenario Outline Scenario Outline Form Form ES-D-1 ES-D-1 Final Final Facility:

Facility: V. C.

V. Summer C. Summer Scenario No.:

Scenario No.: 22 Op-Test Op-Test No.:

No.: 2005-301 2005-301 Examiners:

Examiners: Operators:

Operators: CRS CRS RO RO PO P0 Initial Conditions:

Initial Conditions: At approximately At approximately 39% 39% power power and and increasing.

increasing.

Turnover:

Turnover: Thunder storms Thunder storms in in thethe area, area, severe severe weather weather check check listlist being being implemented.

implemented.

Al "A train maintenance 1" train maintenance week.

week.

S/G AA Small S/G Small tube tube leak, leak, approx.

approx. 88 gpd; MAL-RCSOO2A.

gpd; MAL-RCS002A.

Motor Driven EFW Motor Driven EFW Pump Pump 'A'A Impeller Impeller replacement replacement in in progress progress with with 4848 hours0.0561 days 1.347 hours 0.00802 weeks 0.00184 months hours to to complete, complete, have have done done 12 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months hours so so far.

far.

BB S/G rad rad monitor monitor (RMG-19B)

(RMG-19B) is is OOS.

OOS.

At the pointpoint of the GOP-4 StepStep 3.11.J 3.11 .J when when the second feed water pump is going to be placed placed inin service. The crew is to place is place the B Main Feed Feed Water Pump Pump in service lAW SOP-210,Section III. III. Step 2.7.k Event Event Type*

Event Type* Event Description No.

11 BOP (N) The BOP will place the second feed water pump in service lAW SOP-210.

2 BOP (I) Feedwater Flow transmitter (477) Failure, fails HIGH, with a slow ramp at 2 SRO (TS) approximately 3 minutes from current position.

3 3 BOP (C) Running EH pump trips. (Must manually start other pump) 4 RO (I) Pressurizer pressure channel 444 gradual failure high. Control severity to SRO (TS) prevent a trip.

55 RO (l,R)

(I,R) Power Range Channel N44 N44 failure high with the failure of the rods to move. move.

SRO (TS) The rods will not not move in any direction in Manual or Automatic.

RO (R) (R) Small steam steam leak leak occurs allowing allowing determination of of aa required reactor shutshut 66 BOP BOP (N) (N) down.

down. The crew crew may may initiate initiate aa Rx Rx Trip since since Rods Rods already already will not not move.

move.

SRO SRO (N) (N) When aa trip signal Signal is is inserted, inserted, thethe reactor willwill not not trip.

Large Steam Line Large Steam Line Break occurs on Break occurs on the the CC Steam Steam Generator Generator upstream upstream of of the the 77 All All (M)

(M) MSIVs.

MSIVs. "C" C MSIV MSIV fails fails to to shut shut automatically.

automatically. The "c" feed water The C water isolation isolation valve valve does does notriot isolate isolate automatically.

88 BOP BOP (C) (C) AA Reactor Reactor Building Building Cooling Cooling UnitUnit fails fails to start automatically.

to start automatically.

99 RO RO (C)(C) B

'B' Train Train Containment Containment Spray Spray pump pump fails fails to start automatically.

to start automatically.

Flow Flow meter meter (Fl-7368)

(FI-7368) for for AA Train Train of of Containment Containment SpraySpray fails fails low.

low. Actual Actual 10 10 RO RO (I) I spray spray isis occurring.

occurring.

(N)ormal, .. (I)nstrument, (C)omponent, (N)ormal, (R)eactivity, (R)eactlvlty, (l)nstwment, (C)omponent, (M)ajor (M)aJor 1

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

No.: _1_1 Scenario No.:

Scenario No.: 11 Event No.:

Event No.: 11 Page Page 22 of of L 21 Event

Description:

Event

Description:

The BOP The BOP will will place place the the second second feed feed water water pump pump in in service service lAW lAW SOP-210.

SOP-210.

Time Time Position Position Applicants Actions Applicant's Actions or or Behavior Behavior SOP-210 SOP-210 Place B Place B FPTFPT SPEED CONTROL in in Cascade Mode Mode as follows:

1) Increase

1) Increase the MASTER MASTER SPEED SPEED CNTRL (MCB mla rn/a station) in in MAN Feed Pump until the Feed Pump speed demand, as indicated indicated on SCY-509C, is between 4100 rpm and 5000 rpm (indicated on GRAPHIC 310 screen only). (PEER D) LI)

BOP

2) Adjust the SP value (up and down arrows) on B FPT SPEED CONTROL until turbine RPM is within 25 rpm of SCY-509C rpm (indicated on GRAPHIC 310 screen only).

3) Click on the C icon on the B FPT SPEED CONTROL (S icon) face plate.

Stop TPP22B-PP2, AUX OIL PP, and return the switch to AUTO.

BOP (PEER D) LI)

Stop Feedwater Pump B TURN GEAR and return switch to AUTO.

BOP (PEER D) LI)

If more than one Main Feedwater Pump is operating, perform the following for the pump being placed in service:

a. Adjust the setpoint potentiometer dials on PUMP B B SPEED BOP CNTRL (MCB MIA M/A station) as necessary to maintain all operating Feedwater Pumps within 120 RPM of each other.

b. When plant load is greater than 15%, close MOV-1-5(B) TURB DRN VLV (MCB).

nd End of placing 2 2 FWP in service event.

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

Op Test No.: 11 Scenario No.:

Scenario No.: 11 Event No.:

Event No.: 22 Page _3_

Page 3 of of 2.L 21 Event

Description:

Feedwater Flow Feedwater Flow transmitter transmitter (477)

(477) Failure, Failure, fails fails HIGH, HIGH, with with aa slow slow ramp ramp at at approximately approximately 33 Event from current minutes from current position.

position.

minutes Time Time Position Position Applicants Actions Applicant's Actions or or Behavior Behavior AOP 401.3 AOP 401.3 FT-477 STEAM FT-477 STEAM FLOW FLOW FAILURE.

FAILURE. Enter Enter AOP-401.3.

AOP-401.3. First First 77 steps steps are are Immediate Operator Actions.

Immediate Operator Actions. FCV-478 will FCV-478 will travel travel closed.

closed.

XCP-624, 4-4 Alarm XCP-624, 4-4 SG SG A A FWF>STF FWF>STF MISMA MISMATCH TCH BOP BOP 11 Verify the Verify the failed failed channel channel is is the the controlling controlling channel.

channel.

2 Select the operable flow channel:

- Place FW Place FW CONTROL CONTROL CHANNEL CHANNEL SEL Switch to the operable BOP BOP channel.

. Place STEAM CONTROL CHANNEL SEL Switch to the operable channel CRS/BOP 3 Verify Turbine Load is LESS THAN 950 MWe.

CRS!BOP CRS/BOP 4 Verify only one SG is AFFECTED. AFFECTED.

CRS/BOP 5 Adjust the Feedwater Flow Control Valve as necessary to restore feed flow to the AFFECTED SG.

CRS/BOP 6 Restore Narrow Range level in all SGs SOs to between 60% and 65%.

7 Check if Feedwater Pump speed control is operating properly:

- Feedwater Header pressure is GREATER THAN Main Steam CRS/BOP Header pressure

- Feed flow is normal for steam and flow and power level

.* All operating Feedwater Pump speeds and flows are balanced CRS/BOP 8 Verify Narrow Narrow Range level in all SOs SGs is is normal.

9 Restore the AFFECTED SG control systems to normal:

- Place the Feedwater Flow Control Valve in AUTO CRS/BOP

- PlacePlace thethe Feedwater Feedwater Pump Pump SpeedSpeed Control System in AUTO.

REFER_TO REFER' TO_SOP-210,_F SOP-210, FEEDWATER EEDWATER_SYSTEM SYSTEM 10 10 Within six hours, hours, place the failed failed' channel protection protection bistables in in aa ' tripped tripped condition:

condition:

a.a. Identify Identify thethe associated bistables bistables for for the the failed channel. REFER TO ' Attachment TO Attachment 1. 1.

b. b. Record Record the the following following for for each each associated associated bistable bistable onon SOP-401, SOP-401, REACTOR REACTOR PROTECTIO PROTECTION N AND AND CONTROL CONTROL SYSTEM, SYSTEM, CR5 CRS Attachment Attachment I:I:

- Instrument.

Instrument.

- Associated Associated Bistable.

Bistable.

- Bistable Location.

Bistable Location.

- STPs. STPs.

c.c. Notify Notify the I&C Department the I&C Department to place the to ' place the identified identified bistables bistables inin trip.

trip.

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

No.:

- 11 Scenario No.:

Scenario No.:

- 11 Event No.:

Event No.:

- 22 Page Page --L 4 of of .1.1....

21 Event

Description:

Feedwater Flow Feedwater Flow transmitter transmitter (477)

(477) Failure, Failure, fails fails HIGH, HIGH, with with aa slow slow ramp ramp at at approximately approximately 33 Event

Description:

minutes from minutes from current current position.

position.

Time Time Position Position Applicants Actions Applicant's Actions oror Behavior Behavior TS 3.3.1, TS 3.3.1, Table Table 3.3-1, 3.3-1, item item 14 14 11 Determine 11 Determine and and correct correct the the cause cause of of the the channel channel failure.

failure.

CRS/SE CRS/SE No repair will No repair will occur occur for this event.

for this event.

End of FT-477 failure failure event.

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

Op Test No.: --L1 Scenario No.:

Scenario No.: 11 Event No.:

Event No.: 33 Page Page 55 of of .1.:!....

21 Event

Description:

Event

Description:

Running EH Running EH pump pump trips.

trips. (Must (Must manually manually start start other other pump) pump)

Time Time I Position Position Applicants Actions Applicant's Actions or or Behavior Behavior ARP 6311-2 ARP 631 1-2 Running EHC Running EHC pump pump trips trips event event A EHC Pump trips, Receives Receives alarm XCP 631,1-2, 631, 1-2, EHC FLUID PRESS BOP LO, BOP reviews ARP and hands to CRS.

LO, Crew mayor Crew may or may not reference SOP-222 SOP-222 SWITCHOVER SWITCHOVER OF OF THE THE EHC EHC PUMPS for for starting starting the the idle idle EHC EHC pump.

BOPICRS BOP/CRS Start the idle EHC pump.

Verify the following:

. Starting amps decay off within 30 seconds.

. The started pump discharge pressure is greater than 1550 1550 psig BOPICRS BOP/CRS as indicated at the EHC unit by HFPM-A OUTPUT PRESSURE or HFPM-B OUTPUT PRESSURE.

. EHC header pressure is greater than 1550 psig as indicated by P1-5676,_EHC_FLUID_PRESS_PSIG.

PI-5676, EHC FLUID PRESS PSIG.

Place the previously running EHC pump switch in After-Stop.

BOP/ORS BOP/CRS CRS may direct placing pump in PTL due to apparent motor failure.

End of running EHC pump trips event.

Appendix D0 Appendix Required Operator Required Operator Actions Actions Form Form ES-D-2 ES-D-2 Op Test No.:

Op Test No.: _1_1 Scenario No.:

Scenario No.: 11 Event No.:

Event No.: 44 Page Page --L 6 of of 2L21 Event

Description:

Event

Description:

Pressurizer pressure Pressurizer pressure channel channel 444 444 gradual gradual failure failure high.

high. Control Control severity severity to to prevent prevent aa trip.

trip.

I Time Time Position Position Applicants Actions Applicant's Actions or or Behavior Behavior AOP-401 .5 AOP-401.5 Receives annunciators Receives annunciators XCP XCP 616 2-3 PZR 616 2-3 PZR PRESS PRESS HI/LO,HI/LO, 6162-5 616 2-5 PZR PZR RO RO CNTRL PRESS CNTRL PRESS HI, HI, 6164-4 616 4-4 PRTPRT LVL LVL LOI LOI TEMP/PRESS/LVLlHI TEMP/PRESS/LVL/Hl Verifies PT-444 is failing high AOP-401 .5, Pressurizer Pressure Control Channel Enters AOP-401.5, Channel Failure.

CRS CRS Verifies first 3 steps steps are completed which are immediate immediate actions.

1. Verify the PZR

1. PZR PORVs PORVs are closed:

. PCV-445A. PWR RELIEF RO ** PCV-445B. PWR RELIEF (did not close; requires closing block valve)

- PCV-444B. PWR RELIEF

2. Compare the PZR control channel indication to the protection channel indications:

RO ** PI-455.P1-455. PRESS PSIG

- PI-456.

P1-456. PRESS PSIG

- PI-457.P1-457. PRESS PSIG RD RO 3. P1-444. CNTRL CHAN PRESS PSIG is NORMAL Check if PI-444.

3. IF PT-444 failed, then perform the following:

a) Ensure the PZR Spray Valves are closed:

CRS/RO

. PCV-444C. PZR SPRAY

.__PCV-444D,_PZR_SPRAY PCV-4440, PZR SPRAY b) Control PZR PRESS MASTER CONTROL in MAN.

RD RO c) Operate the PZR Heaters and Spray Valves in manual to control RCS_pressure_between_2220_psig_and_2250_psig.

RCS pressure between 2220 psig and 2250 psig.

Will probably reach the 2206 psig ONB DNB Tech Spec 3.2.5 at which point CRS the CRS should verbalize the 22 hr LCD LCO requirement.

d) Within one hour; close MVG-8000B. RELIEF 444 BB ISOL.

CRS Per TS 3.4.4.b, must also remove power from block valve, XVG-8000B because it would not.

4. Check If P1-445. PI-445. CNTRL CHAN PRESS PSIG, indication indication is CRS/RD CRS/RO NORMAL CRS/RO 5. Ensure ROD CNTRL BANK SEL Switch is In In AUTO.

CRS/RO CRS/RO 6. Maintain RCS pressure between

6. Maintain between 2220 2220 pslg pslg and and 2250 2250 psig.

psig.

CRS/SE 7. Determine and correct the cause of the channel failure.

Reference TS 3.4.4.b. for PORV failure. Must Must remove power power from block block CRS valve in in this case.

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

Test No.: 11 Scenario No.:

No.: 11 Event No.:

No.: 55 Op Scenario Event Page Page

- 77 of of

-2121 Event

Description:

Power Range Power Range Channel Channel N44N44 failure failure high with the high with the failure failure of of the the rods rods to to move.

move. TheThe rods rods will will not not Event Descri P tiow move inin any move any direction direction inin Manual Manual oror Automatic.

Automatic.

Time Time Position Position ( Applicants Actions Applicant's Actions or or Behavior Behavior AOP-401.1O AOP-401.10 Start of Start of N-44 N-44 Failure Failure and and RodsRods Fail Fall To To Move Move event.event. Crew Crew should should enter:

enter:

. AOP-401.

AOP-401.10 10 for for N-44 N-44 Failure Failure (steps (steps 1&2 1&2 are are immediate immediate actions) actions). .

. AOP-403.4 AOP-403.4 for for Stuck Stuck Control Control Rods Rods (steps (steps 1&2 1&2 are are immediate immediate actions).

actions).

RO should RO should notice notice rods rods diddid not not move move when when N-44 N-44 failed.

failed.

N-44 starts N-44 starts failing failing hi, hi, the following alarms the following alarms are received:

are received:

XCP 620 1-1 1-1 PR PR HIHI SETPT FLUX FLUX HI HI XCP 620 620 1-41-4 PR PR CHAN DEV DEV RO 620 1-5 PR XCP 6201-5 PR UPUP DETDET FLUXFLUX HI DEV AUTO DEFEAT HI DEV DEFEAT XCP 620 5-1 ROD CNTRL SYS FAIL URGENT 620 1-6 PR LO DET FLUX HI DEV AUTO DEFEAT XCP 6201-6

1. Verify normal indication on Power Range Channel N-44.

IF Power Range Channel N-44 has failed, THEN place the ROD RO/CRS ROfCRS CNTRL BANK SEL Switch in MAN.

(Should be a discussion of GOP Appendix A requirement to have rods in AUTO ifify any PZR PORV is isolated.)

RO 2. Stabilize any plant transients in progress.

CRS/RO CRSfRO 3. Maintain stable plant conditions

4. Verify no testing .is in progress on the operable Power Range CRS/RO channels.

5. Place ROD STOP BYPASS Switch for the failed Power Range CRS/RO CRSfRO channel in BYPASS.

6. Verify the appropriate Rod Stop Bypass status light is lit:

CRS/RO

For N-44,,_B2_OP_RO

.__For_N-44 B2 OP ROD STOP BYP D_STOP_BY (XCP-6111 P_(XCP-61 4-4).

11_4-4).

CRS/RO 7. Adjust ControlControl Rods to maintain Tavg within 1.0°F I.O°F of Tref.

The empty empty fuse holders should NOT be reinstalled as this will allow allow a small amount of of current flow through the blown blown fuse indicator

8. Deenergize the

8. the failed PowerPower Range Range channel:

channel:

.* Remove Remove the the CONTROL CONTROL POWER POWER fuses fuses from the the POWER POWER CRS/RO CRS/RO RANGE A drawer RANGE A drawer of of N-44.

N-44.

.* Remove Remove the the INSTR INSTR POWERPOWER fuses fuses from from the the POWER POWER RANGE RANGE BB drawer_of_N drawer of N-44. -44.

9. Align

9. Align the the Power Power RangeRange channel channel comparator comparator circuits: circuits:

a.

a. Place Place the the following following switches switches to to the the failed failed Power Power Range Range channel channel (N-44) position:

(N-44) position:

CRS/RO CRS/RO ** COMPARAT COMPARATOR OR CHANNEL CHANNEL DEFEAT DEFEAT Switch Switch (on(on the the COMPARAT COMPARATOR OR ANDAND RATE RATE drawer)drawer)

- UPPER UPPER SECTION SECTION Switch Switch (on (on thethe DETECTOR DETECTOR CURRENT CURRENT COMPARAT COMPARATOR OR drawer) drawer)

AppendixDD Appendix RequiredOperator Required OperatorActions Actions Form FormES-D-2 ES-D-2 OpTest Op TestNo.:

No.: 11 Scenario No.:

Scenario No.: 11 EventNo.:

Event No.: 55 Page Page --L8 of of

-2121 EventDescription:

Descri P tion PowerRange Power Range Channel Channel N44 N44 failure failure high high with with the failure of the failure ofthe the rods rodstoto move.

move. The The rods rodswill will not not Event move ininany any direction direction inin Manual Manual or orAutomatic.

move Automatic.

Time Time Position Position Applicants Actions Applicant's Actions or orBehavior Behavior

. LOWER SECTION LOWER SECTION Switch Switch (on (on the the DETECTOR DETECTOR CURRENT CURRENT COMPARATOR drawer).

COMPARATOR drawer).

CRS/RO CRS/RO 10. Ensure

10. Ensure NR-45 NR-45 is is selected selected to to the the appropriate appropriate operable operable channels.

channels.

11. Within six

11. Within six hours, hours, place place the the failed failed channel channel protection protection bistables bistables in in aa tripped tripped condition:

condition:

a. Identify

a. Identify the the associated associated bistables bistables for for the the failed tailed channel channel (N-44).

(N-44).

REFER to Attachment REFER to Attachment 1. 1.

b. Record

b. Record the the following following for for each each associated associated bistablebistable onon SOP-401.

SOP-401, REACTOR PROTECTION REACTOR PROTECTION AND AND CONTROL CONTROL SYSTEM, SYSTEM, CRS/SE CRS/SE Attachment I:I:

Attachment

- Instrument Instrument Associated Bistable

. Associated

Bistable Location.

. Bistable Location.

- STPs.

c. Notify the I&C l&C Department to place the identified bistables in trip.

CRS/RO CRS/RO 12. Verify Reactor Power is LESS THAN 75%.

CRS 13. Refer to Tech Spec 3.3.1. {Trip (Trip bistables within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .} hours.)

CRS!SE 14. Determine and correct the cause of the Power Range channel CRS/SE failure.

Cause of failure will not be determined for this event.

AOP-403.4 Following are the actions actions for Failure of of Control Rods to Move. Steps 1& 1&

2 are immediate actions. This event will be occurring simultaneous simultaneously ly CRS with the N44 failure so so the crew will be be forced to to prioritize prioritize between between the the two AOPs.

AOPs.

RD RO 1. The

1. The ROD ROD CNTRL CNTRL BANK BANK SEL SEL Switch Switch is is already already in in MAN MAN RO RO 2.

2. Main Main Turbine Turbine load load isis already already stabilized stabilized CRS/RO CRS/RO 3.

3. Stop Stop any any boration boration or or dilution dilution in in progress progress 1.

1. Adjust Adjust Control Control Rods Rods to to maintain maintain Tavg Tavg within within 1.01.0 degrees degrees of of Tref.

Tref.

NOTE NOTE - Step Step 4: 4: IfIf Tavg Tavg hashas remained remained within within 1.5°F 1.5°F ofof Tref, Tref , Control Control Rods Rods should should be be moved moved one one or or two two steps steps in in or or out out to to verify verify proper proper operation.

operation.

CRS/RO CRS/RO Since Since Control Control Rods Rods will will NOT NOT move, move, THEN THEN perform perform the the following:

following:

Adjust Adjust MainMain Turbine Turbine loadload until until Tavg Tavg isis within 5°F of within 5°F ofTref Tref

.* Initiate GTP-702, Attachment Initiate GTP-702, Attachment lV.A, IV.A. INOPERABL INOPERABLE CONTROL E CONTROL ROD ROD CRS CRS CRS CRS evaluates evaluates Tech Tech Specs Specs 3.1.3.1.C 3.1.3.1.C which which willwill require require aa plant plant

Appendix0D Appendix RequiredOperator Required OperatorActions Actions Form FormES-O-2ES-D-2 TestNo.:

OpTest No.: 11 ScenarioNo.:

No.: 11 EventNo.:

No.: 55 Op

-- Scenario Event Page Page 99 of of

-2121 Event

Description:

Description, PowerRange Power Range Channel Channel N44 failure high N44 failure high with with the the failure failure of ofthe rodstoto move.

the rods move. The The rods rodswill will not not Event move inin any direction inin Manual any direction Manual or orAutomatic.

Automatic.

move Time Time Position Position Applicants Actions Applicant's Actions or orBehavior Behavior shutdown, then shutdown, then performs performs the the following:

following:

Building operator Building operator (if (if dispatched) dispatched) reportsreports thatthat the the urgent urgent failure failure isis from from power cabinet power cabinet 2BD 2BD

a. Notify

a. Notify thethe following following plantplant personnel:

personnel:

SE SE ** Management Management Duty Duty Supervisor Supervisor

- Reactor Reactor Engineering Engineering

b. Decrease

b. Decrease Main Main Turbine Turbine LoadLoad to to 5050 MWMW at at aa rate rate determined determined by by BOP BOP the Shift the Shift Supervisor.

Supervisor. (Refer (Refer to to GOP-4B, GOP-4B, POWER POWER OPERATION, OPERATION, MODE_I_

MODE _DESCENDING,_startin 1 - DESCENDING, startingg_with_Step with Step _3.3)3.3)

c. Maintain

c. Maintain Tavg Tavg within within 55 degrees degrees of of Tref using the following:

Tref using the following:

BOP/RO ** Main Turbine Load Load adjustment BOP/RO

- RCS Boration. Refer to to SOP-1 SOP-i 06, 06, REACTOR MAKEUP MAKEUP WATER SYSTEM

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

Op Test No.: --L1 Scenario No.:

Scenario No.: --L 1 Event No.:

Event No.: -L 6 Page Page...1.2..

10 of of 21..

21 Small steam Small steam leak leak occurs occurs allowing allowing determination determination of of aa required required reactor reactor shut shut down.

down. The The crew crew may may Event

Description:

Event

Description:

initiate aa Rx initiate Rx Trip Trip since since Rods Rods already already will will not move. When not move. When aa trip trip signal signal isis inserted, inserted, the the reactor reactorwill will not trip.

not trip.

Time Time 1 Position Position 1I Applicants Actions Applicant's Actions or or Behavior Behavior NOTE NOTE While attempting While attempting to to lower lower load, load, the the SMALL SMALL STEAM STEAM LEAK LEAK will will initiate.

initiate.

I~

lE over over 1I minmm NOTE to NOTE to 55 instantaneous lE IE instantaneous - then then increase increase as as necessary necessary until until decision decision is is made made to to Booth Booth trip Rx trip Rx and and SISI Operator Operator Increase break Increase break to to IE7 T on IE on RxRx trip.

trip.

Operator will Operator will respond respond to to below below annunciators annunciators by by pulling ARPs and and following CRS directions:

following CRS directions:

RD RO XCP 6062-2 XCP 606 2-2 RBCURBCU 1A12A IA/2A DRN DRN FLO FLO HI HI XCP 607 2-2 RBCU 1IB/2B BI2B DRN FLO HI HI SRO will evaluate Tech Spec for DNB TS 3.2.5 for low PZR Pressure CRS when it occurs. (2206 psig)

As the leak escalates and conditions deteriorate, the crew is expected to to CRS/RO trip the reactor prior to automatic actuation.

CRITICAL Directs the RO RD to trip the reactor.

CRS/RO RD manually trips the reactor.

RO

Appendix0D Appendix RequiredOperator Required OperatorActions Actions Form FormES-D-2 ES-D-2 OpTest Op No.:

TestNo.: --- 1 ScenarioNo.:

Scenario No.: 11 EventNo.:

Event No.: 77 Page Page

- 1111 of of

-2121 EventDescription: LargeSteam Large Steam Line Line Break Breakoccurs occurson on the the CC Steam Steam Generator Generatorupstream upstreamof ofthe the MSIVs.

n MSIVs. "CC MS IV MSIV Event

Description:

fails shutautomatically.

fails totoshut automatically. The The "C n Cfeed feedwater waterisolation isolation valve valvedoesdoesnot notisolate isolateautomatically.

automatically.

Time Time Position Position ApplicantsActions Applicant's Actions or orBehavior Behavior EOP-1 .0 EOP-1.0 Large Steam Large Steam Break Break should should occur occur at at this this time.

time. An An AUTO AUTO SI Si may may occur occur NOTE NOTE prior to prior to MANUAL MANUAL actuationactuation due due to to size size ofof steam break.

steam break.

1.1. Verify Verify Reactor Reactor Trip: Trip: (Reactor (Reactor did did not not trip trip automatically.

automatically. Isolate Isolate EFW flow EFW flow to "C" S/G) to C S/G)

- Trip Trip the the Reactor Reactor usingusing either either Reactor Reactor Trip Trip Switch Switch RO RO

. Verify Verify all all Reactor Reactor Trip Trip and and Bypass Bypass Breakers Breakers are are open.

open.

- VerifyVerify all all Rod Rod Bottom Bottom Lights Lights are lit.

are lit.

. Verify Verify Reactor Reactor Power Power level level is is decreasinQ.

decreasing.

2. Verify

2. Verify Turbine/Generator TurbinelGenerator Trip: Trip: (Secure (Secure RCPs RCPs Hi Hi 3) 3)

a. Verify all

a. all Turbine STM STM STOPSTOP VLVs VLVs are are closed.

closed.

BOP BOP b. Ensure

b. Ensure Generator Trip (after 30 second second delay):

1) Ensure the GEN BKR is open.

1)

2) Ensure the GEN FIELD BKR is open.

3) Ensure the EXC FIELD CNTRL is tripped.

BOP BOP 3. Verify both ESF buses are energized.

4. Check if SI is actuated:

a. Check if either:

- SI ACT status light is bright on XCP-61 XCP-6107 07 1-1.

OR ALL ** Any red first-out SI annunciator is lit on XCP-626 top row.

b. Actuate SI using either SI ACTUATIO ACTUATION N Switch.

GO GO TO Step Step 6.

5.

5. Check Check if if SI SI isis required:

required:

a. Check

a. Check if any of if any of the the following conditions conditions exist: exist:

.* PZR PZR pressure pressure LESS LESS THANTHAN 1850 1850 psig.

psig.

OR OR

- RB RB pressure pressure GREATERGREATER THAN THAN 3.6 3.6 psig.

psig.

ALL ALL OR OR

- Steamline Steamline pressure pressure LESS LESS THAN THAN 675 675 psig.

psig.

OR OR

- Steamline Steamline differential differential pressure pressure GREATER GREATER THAN THAN 97 97 psid.

psid.

b._Actuate_S I_using_eith

b. Actuate SI using either er_SI_ACTU SI ACTUATION ATION_Swi Switch.

tch.

At some point At some point after the after Rx the Rx Trip, Trip, aa High-3 High-3 shouldshould havehave occurred occurred and and RO RO the the RO RO will will secure secure all all RCPs RCPs CRS/BOP CRS/BOP 6.6. Complete Complete ATTACHME ATTACHMENT NT 3,3, SI SI EQUIPMEN EQUIPMENT T VERIFICAT VERIFICATION. ION. BOP BOP operator manually operator manually closes closes C "C" MSIV MSIV and and C"C" FWIV.

FWIV.

Appendix0D Appendix RequiredOperator Required OperatorActions Actions Form FormES-D-2 ES-D-2 OpTest TestNo.:

No.:

Op 11 ScenarioNo.:

Scenario No.: 11 EventNo.:

Event No.: 88 Page Page

- 1212 of of ~

21 21 EventDescription:

Event

Description:

ReactorBuilding AA Reactor Building Cooling Cooling Unit Unitfails failstotostart startautomatically.

automatically.

Time Time Position Position I Applicants Actions Applicant's Actions or orBehavior Behavior Notes that Notes that RBCU RBCU XFN-0064B XFN-0064B did did not not auto auto start start in in SS SS on on the the SISI and and RO RO manually starts manually starts XFN-0064B XFN-0064B CRS/SE CRS/SE 7. Announce

7. Announce plant plant conditions conditions over over the the page page system.

system.

8. Verify

8. Verify RB RB pressure pressure has has remained remained LESS LESS THANTHAN 12 12 psig psig on on PR-951, PR-951, CRS/RO CRS/RO RB PSIG (P-951), red RB PSIG (P-951), red pen.

pen.

88 Perform Perform the the following:

following:

a) Verify a) Verify both both the the following following annunciators annunciators are are lit:

lit:

XCP-612 3-2 XCP-612 3-2 (RB(RB SPRSPR ACT).ACT).

XCP-612 4-2 XCP-612 4-2 (PHASE (PHASE BB ISOL). ISOL).

IF either annunciator is IF either annunciator is NOT lit, NOT lit, THEN THEN actuate actuate RB RB Spray Spray by by placing placing the the RO RO following switches following switches to to ACTUATE:

ACTUATE:

Both CS-SGA Both CS-SGA11 and and CS-SGA2.

CS-SGA2.

OR OR Both CS-SGB1 Both CS-SGB1 and and CS-SGB2.

CS-SGB2.

MVG-3003A(B), SPRAY HDR MVG-3003A(B}, HDR ISOL LOOP A(B).

b) Verify Phase B Isolation by ensuring RB PRA Y/PHASE PRAY/PHAS E B ISOL RO RO monitor lights are bright on XCP-61 XCP-6105. 05.

c) Ensure the following are open:

RO RO MVG-3001A(B), RWST TO SPRAY PUMP A(B) SUCT.

MVG-3001A(B),

MVG-3002A(B),_NAOH_

MVG-3002A(B), NAOH TO TO_SPRAY SPRAY _PUMP PUMP A(B) SUCT..

A(B)_SUCT

Appendix0D Appendix RequiredOperator Required OperatorActions Actions Form FormES-O-2 ES-D-2 OpTest TestNo.:

No.:

Op

- 11 Scenario No.:

Scenario No.:

- 11 EventNo.:

Event No.:

- 99 Page Page ---1l.

13 of of ..1.:!...

21 Event

Description:

Event

Description:

B Train

'8' Train Containment ContainmentSpray Spray pump pumpfails failstoto start startautomatically.

automatically.

Time Time Position Position Applicants Actions Applicant's Actions or or Behavior Behavior d) Ensure both d) Ensure both RBRB Spray Spray PumpsPumps are running Of are running (Ifthe the RO RO has has not not already done alread'l. done SOl so, at this l2.oint at this point the the RO RO manuall'l.

manually starts starts the the "B" B RB RB RO RO Spray pump that Sl2.ra'l.l2.uml2. that did did not not auto start on auto start on the the Phase Phase BB isolation isolation signaL) signal.l

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

No.: --L1 Event

Description:

Event

Description:

Scenario No.:

Scenario Flow meter Flow No.:

meter (FI-7368) 1I (FI-7368) for Event No.:

Event No.:

forAATrain Train of 10 10 of Containment Containment SpraySpray fails fails low.

low. Actual Page Actual spray Page 14

- 14 of spray isis occurring.

occurring.

of 21 21 Time Time Position Position Applicants Actions Applicant's Actions or or Behavior Behavior e) Verify e) Verify RB RB Spray Spray flowflow isis GREATER GREATER THAN THAN 2500 2500 gpm gpm forfor each each operating train operating train onon FI-7368, SPR FI-7368, SPR PP PP AA DISCH DISCH FLOW FLOW GPM. GPM.

RO RD FI-7378, SPR FI-7378, SPR PP BB DISCH PP DISCH FLOW FLOW GPM. GPM.

(At this (At this point point the the RORD notesnotes that there isis no that there no flow flow indicated indicated on on FI-7368 Fl-7368 butbut that all other indications that all other indications are are normal normal and and diagnoses diagnoses itit as as aa failed failed indicator.))

indicator.

RD RO f) Stop Stop all all RCPs RCPs (if not already (if not already stopped stopped on on Phase Phase B).

B).

9.

9. Check RCS Check RCS temperature:

temperature:

. With no RCP RCP running, running, RCS RCS Tcold is stable at OR trending to 557F.

557"F.

IF RCS temperature is LESS THAN 557"F 557F AND decreasing, THEN:

a) Place the STM DUMP CNTRL Controller in MAN and closed.

b) Place the STM DUMP MODE SELECT Switch in STM PRESS.

c) Ensure all Steamline PORVs and Condenser Steam Dumps are CRS/RD CRS/RO closed.

d) IF RCS cooldown continues, THEN:

(Could get red path on EOP-15.0 EOP-1 5.0 if throttle too much)

(1) IF Narrow Range SG level is LESS THAN 30% [50%] in all SGs, THEN reduce EFW flow as necessary to stop the cooldown, while maintaining total EFW flow GREATER THAN 450 gpm.

(2) WHEN Narrow Range SG level is GREATER THAN 30% [50%]

in at least one SG, THEN control EFW EFW flow as necessary to stabilize RCS temperature at 557F. 557"F.

(3)

(3) IF IF RCS cooldown continues, THEN close: close:

.* MS MS Isolation Valves, PVM-2801A PVM-2801A(B)(C). (B)(C).

.__MS_Isola

MS Isolation tion_Bypass_

Bypass Valves,_PVM Valves, PVM-2869A(B)(C).

-2869A(B)(C).

By By step step 99 in in EOP-1 EOP-1.0 .0 the the faulted SG SG should should have have been been diagnosed diagnosed as as C "C"

BOP BOP and and EFW EFW to to C SG should "C" SG should be be secured secured (FCV (FCV closed) closed) (OAP-1 (OAP-103.4) 03.4) 10.

10. Check Check PZR PZR PORVs PORVs and and Spray Spray Valves:

Valves:

a.

a. PZR PZR PDRVs PORVs are are closed.

closed.

b.

b. PZR PZR Spray Spray Valves Valves are are closed.

closed.

c.c. Verify Verify power power is is available available to to at at least least oneone PZR PZR PORV PORV Block Block Valve:

Valve:

.* MVG-8000A ,

MVG-8000A, RELIEF 445 RELIEF 445 AA ISOL.

ISOL.

CRS/RO CRS/RO ** MVG-8000B MVG-8000B,, RELIEF RELIEF 444 444 BB ISOL.

ISOL.

- MVG-8000C MVG-8000C, , RELIEF RELIEF 445 445 BB ISOL.

ISOL.

d.

d. Verify Verify at at least least one one PZRPZR PORV PORV Block Block Valve Valve isis open.

open.

OPEN OPEN one one Block Block Valve Valve unlessunless itit was was closed closed to to isolate isolate anan open open PZRPZR PORV.

PORV.

111.

1. Check Check ifif RCPsRCPs should should be be stopped:

stopped:

CRS/RO CRS/RO a.a. Check Check ifif either either of of the the following following criteria criteria isis met:

met:

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

No.: 11 Op Scenario No.:

Scenario No.: 11 Event No.:

Event No.:

-1010 Page Page

- 1515 of of 2.1 21 Event

Description:

Event

Description:

Flow meter Flow meter (FI-7368)

(Fl-7368) for for AATrain Train ofofContainment Containment Spray Spray fails fails low.

low. Actual Actual spray spray isis occurring.

occurring.

Time Time ( Position Position Applicants Actions Applicant's Actions or or Behavior Behavior

. Annunciator XCP-612 Annunciator XCP-612 4-2 4-2 isis litlit (PHASE (PHASE BB ISOL)ISOL)..

OROR

. RCS pressure RCS pressure isis LESS LESS THAN THAN 1400 1400 psig psig AND AND SI SI flow flow isis indicated indicated on FI-943, on FI-943, CHG CHG LOOPLOOP BB CLD/HOT CLD/HOT LG LG FLOW FLOW GPM.

GPM.

b.b. Stop all Stop all RCPs RCPs (already (already stopped).

stopped).

12. Verify

12. Verify no no SGSG isis FAUL FAULTED:

TED:

. No SG No SG pressure pressure is is decreasing decreasing in in an an uncontrolled uncontrolled manner manner..

. No SG is No SG is completely completely depressurized depressurized.

CRS/BOP CRS/BOP GOGO TO EOP-3.0, FAULTED TO EOP-3.0, FAULTED STEAM STEAM GENERATOR GENERATOR ISOLATION, ISOLATION, Step Step 1. 1.

Crew will leave this procedure and transition to EOP-3.0, step 1. 1.

EOP-3.O EOP-3.0

1. Ensure all the following are closed:

CRS/BOP ** MS Isolation Valves, PVM-2801A(B)(G). PVM-2801A(B)(G).

- MS Isolation Bypass Valves, PW-2869AIB)(Cl- PW-2869A(B)(C).

2. Check if any SG is NON-FAULTED: NON-FAULTED:

ALL ** Pressure in any SG is stable or increasing.

- __Any_SG_

Any SG is is_not_comp not completelyletely_depres depressurized surized

3. Identify any FAULTED SG(s):

- Any SG pressure decreasing in an uncontrolled manner.

ALL OR -

__Any_SG_

Any SG is_NOT_com is NOT pletely_depre completely depressurizedssurized 4.

4. Close the following valves for each FAULTED SG:

- FW FW Flow Flow Control Control FCV-498 FCV-498 CRS/BOP CRS/BOP ** FW FW Isolation, Isolation, PVG-1611C PVG-1611 C

- SG SG Blowdown.

Blowdown. PVG-503CPVG-503C

___FW_Flo

FW Floww_Control_B Control Bypassypass_FCV-FCV-3341 3341 5.

5. Complete Complete the the isolation isolation ofof each each FAULTED FAULTED SG: SG:

a.

a. Close Close SG SG Chemical Chemical Feed Feed Isolation, Isolation, MVK-1633C MVK-1633C b.

b. Close Close MS MS Drain Drain Isolation Isolation PVT-2843C PVT-2843C c.c. Close Close MS MS Drain Drain Isolation, Isolation, PVT-2877B PVT-2877B for for SG SG C. C.

d.

d. Place the Steam Place the Steamline PWR line PWR RELIEF RELIEF C C SETPT SETPT Controller Controller in in MAN MAN and closed.

and closed.

ALL ALL e.

e. Place Place the the Steamline Steamline PowerPower Relief Relief CC Mode Mode Switch Switch in in PWR PWR RLF RLF f.f. Close Close FCV-3551 FCV-3551 MD MD EFP EFP TOTO SGSG CC g.g. Close Close FCV-3556 FCV-3556 TD TD EFPEFP TOTO SG SG CC h.h. Locally Locally unlock unlock and and close close XVGO1O17 XVG01 017C-EF C-EF SG SG CC MTR MTR DR DR EF EF PUMP PUMP SUPPLYSUPPLY HEADER HEADER VALVE VALVE (IB-423). (IB-423).

I.i. Locally Locally unlock unlock and and close close XVKO1O19 XVK01 019C-EF C-EF SG SG CC MTR MTR DR DR EF EF PUMP_SUP PUMP SUPPL PLYY STOP_CHK STOP CHK VLV VLV (IB-423).

(IB-423).

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

Op Test No.: 11 Scenario No.:

Scenario No.: 11 Event No.:

Event No.: 10 10 Page ~

Page 16 of of .1.:!...

21 Event

Description:

Event

Description:

Flow meter Flow meter (FI-7368)

(Fl-7368) forfor AA Train Train of of Containment Containment Spray fails low.

Spray fails ow. Actual Actual spray spray isis occurring.

occurring.

Time Time Position Position Appilcants Actions Applicant's Actions oror Behavior Behavior j.j. Locally unlock Locally unlock andand close close XVG01 XVG01O18C018C-EF -EF SG SG CC TURB TURB DR DR EF EF PUMP SUPPLY PUMP SUPPLY HDR VALVE (IB-423).

HDR VALVE (18-423).

k.k. Locally unlock Locally unlock and and close close XVK01020C-EF XVK01020C-EF SG SG C C TURB TURB DR DR EFEF PUMP SUP PUMP SUP STOP CHK STOP CHK VALVE VALVE (IB-423)

(IB-423)

I.I. Close and Close and locally locally deenergize deenergize the the appropriate appropriate valvevalve forfor SG SG C C FAULTED:

FAULTED:

. For ForSGC:

SG C:

11)) Open XMCIDB2Y Open XMCIDB2Y 05EH. 05EH.

EMERG FEEDWATER FEEDWATER PUMP PUMP MAIN STEAM BLOCK BLOCK XVG28O2B-MS (AB-463).

XVG2802B-MS (AB-463).

2) Close MVG-2802B MS MS LOOP LOOP C TO TD EFP EFP CRITICAL Faulted SG is Isolated BOP

6. Check if Secondary radiation levels are normal:

a. Check radiation levels normal on all un unisolated isolated radiation monitors:

. RM-G19C STMLN HI RNG GAMMA.

RM-L3, STEAM GENERATOR

. RM-L3, GENERATOR ALL ALL BLOWDOWN LIQUID MONITOR.

BLOWDOWN RM-LIO. SG BLOWDOWN

. RM-LiO. BLOWDOWN CW DISCHARG DISCHARGE E LIQUID MONITOR.

. RM-A9, CNDSR EXHAUST GAS ATMOS MONITOR.

b. Notify Chemistry to sample all SG secondary sides and screen samples_for_

samples for abnormal_ac tivity_using_

abnormal activity using a_frisker.

a frisker.

7. Check if SI flow should be reduced:

a. RCS subcooling on TI-499A(B), A(B) TEMP OF is GREATER THAN 30F. 30"F.

b.

b. Secondary Heat Sink is is adequate:

.* Total EFW EFW flow to INTACT SGs is GREATER THAN 450 gpm. gpm.

ALL OR OR

.* Narrow Narrow Range level is is GREATER THAN 30% 30% [50%]

[50%] in in at at least least one INTACT one INTACT SG. SG.

c.

c. RCS pressure RCS pressure is is stable OR increasing.

stable OR increasing.

d.

d. PZR PZR level level isis GREATER GREATER THAN THAN 18% 18% [38%]

[38%] (IF(IF PZR PZR LEVELLEVEL <<

18%[38%],

18%[38%], THEN THEN transition transition toto EOP-2.0, EOP-2.0, see see attachment attachment of of EOP EOP-2.0 2.0 steps) steps)

CRS/RO CRS/RO 8. Reset

8. Reset both both SISI RESET RESET TRAIN TRAIN A(B)

A(B) Switches.

Switches.

9. Reset

9. Reset Containment Containment Isolation:

Isolation:

CRS/RO CRS/RO ** RESET PHASE RESET PHASE A A TRAIN A(B) CNTMT TRAIN A(B) CNTMT ISOL. ISOL.

__RESET_P

RESET PHASE HASE_BB TRAIN_A(B TRAIN A(B))_CNTMT_I CNTMT ISOL. SOL.

10. Place

10. Place both both ESFESF LOADING LOADING SEQ SEQ A(B)

A(B) RESETS RESETS to: to:

CRS/BOP a.

a. NON-ESF NON-ESF LCKOIJTS.

LCKOIJTS.

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

No.: --L1 Scenario No.:

No.: 11 Event No.:

No.: 10 Op Scenario Event 10 Page Page

- 1717 of of

- 2121 Event

Description:

Event

Description:

Flow meter Flow meter (FI-7368)

(Fl-7368) for Train of for AA Train Containment Spray of Containment Spray fails fails low.

low. Actual Actual spray spray isis occurring.

occurring.

Time Time ) Position Position

b. AUTO-START BLOCKS.

Applicants Actions Applicant's Actions oror Behavior Behavior

b. AUTO-START BLOCKS.

11. Establish Instrument 1 1. Establish Instrument Air Air to to the RB:

the RB:

a.

a. Start one Instrument Start one Instrument Air Air Compressor Compressor and and place place the the other other in in CRS/RO CRS/RO Standby.

Standby.

b.

b. Open PVA-2659, Open PVA-2659, INST INST AIR TO RB AIR TO RB AIRAIR SERVo SERV.

c.

c. Open PVT-2660.

Open PVT-2660. AIR SPLY SPLY TO TO RB RB CRS CRS 12. GO

12. GO TOTO EOP-1.2, EOP-1.2, SAFETYSAFETY INJECTION INJECTION TERMINATION, TERMINATION, Step Step 1.

1.

previously entered EOP-2.0, IfIf previously EOP-2.0, EOP-2.0 EOP-2.0 will transition back back to EOP-1.2.

EOP-1 .2.

EOP-1.2 EOP-1 .2 Stop all but one Charging Pump and place in Standby. (Stop A Chg CRS/RO Pump)

CRS/RO Verify RCS pressure is stable OR increasing.

Establish Normal Charging:

a. Close FCV-122, CHG FLOW.

CRS/RO b. Open both MVG-8107 and MVG-8108, CHG LINE ISOL.

c. Adjust FCV-122, CHG FLOW, to obtain 60 gpm Charging flow.

d. Close_both_

Close both MVG-8801A MVG-8801A(B), HI HEAD (B),_HI_HEA TO COLD D_TO_COL LEG INJ D_LEG_INJ CRS/RO Control FCV-122, CHG FLOW, to maintain PZR level.

Note SI terminated and normal charging restored.

CRS/RO Stops both RHR pumps

6. Verify SI flow is NOT required:

CRS/RO a. RCS subcooling on Tl-499A(B), TI-499A(B), is GREATER THAN 30°F c.__PZR_lev

c. PZR level el_is_GREA is GREATER TER THAN_18%

THAN 18%_[38%]. r38%].

7. Check if RB Spray should be stopped:

a. Check Check if any RB Spray Pumps are running.

b. Verify RB pressure is

b. is LESS THAN pressure is is LESS LESS THAN 1111 psig.

CRS/RO c. Depress

c. Depress both both RESET RESET TRAINTRAIN A(B) RB SPRAY. SPRAY.

d.

d. Verify EOP-14.0, EOP-14.0, RESPONSE TO TO INADEQUA INADEQUATE TE CORE CORE COOLING, has NOT been COOLING, has NOT been implemented.. implemented

e. Stop

e. both RB Stop both RB Spray Spray Pumps Pumps andand place place in in Standby.

Standby.

f.f. Close_MVG -3003A(B),_SPRAY_HD Close MVG-3003A(B), SPRAY HDR ISOL LOOP R_ISOL_LO A(B).

OP A(B).

Check ifif Letdown

9. Check

9. Letdown can can be be established:

established:

a. Verify

a. Verify PZR level is PZR level is GREATER GREATER THAN THAN 30% 30% [50%]

[50%]

b.

b. Establish Establish Normal Normal Letdown:

Letdown:

1) Adjust

1) Adjust FCV-122, FCV-122, CHG CHG FLOW, FLOW, to to obtain obtain 6060 gpm gpm Charging Charging CRS/RO

..dIJI flow.

flow.

2) Set

2) Set PCV-145, PCV-145, LO LO PRESS PRESS LTDN,LTDN, to to 70%.

70%.

3) Open TCV-144,

3) Open TCV-144, CC CC TOTO LTDN LTDN HX. HX.

4) Open_PVT-8

4) Open PVT-8152, 152,_LTDN_

LTDN LINE_ISOL.

LINE ISOL.

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

Op Test No.: --L1 Scenario No.:

Scenario No.: 11 Event No.:

Event No.: 10 10 Page Page

- 1818 of of 21 21 Event

Description:

Event

Description:

Flow meter Flow meter (FI-7368)

(Fl-7368) for for AA Train Train of of Containment Containment Spray Spray fails fails low.

sow. Actual Actual spray spray isis occurring.

occurring.

Time Time Position Position Applicants Actions Applicant's Actions or or Behavior Behavior 5)

5) Open both Open both LCV-459 LCV-459 and and LCV-460, LCV-460, LLTDN TDN LINELINE ISOL.

ISOL.

6)

6) Open desired Open desired Orifice Orifice Isolation Isolation Valve(s)

Valve(s) to to obtain obtain 60 60 gpm gpm toto 120 gpm:

120 gpm:

PVT-8149A, LLTDN

. PVT-8149A, ORIFICE AA ISOL TDN ORIFICE ISOL (45(45 gpm).

gpm).

. PVT-8149B, PVT-8149B, LTDN LTDN ORIFICE ORIFICE BB ISOL ISOL (60 (60 gpm).

gpm).

. PVT-8149C, PVT-8149C, LTDN LTDN ORIFICE ORIFICE C C ISOL ISOL (60(60 gpm).

gpm).

7) Adjust

7) Adjust FCV-122,FCV-122, CHG CHG FLOW,FLOW, to maintain TI-140, to maintain TI-i 40, REGEN REGEN HX OUT HX OUT TEMPTEMP "F, F, between between 250"F 250F and 350"F 350F while maintaining PZR level.

8) Adjust PCV-145,PCV-145, LO LO PRESS PRESS LTDN, LTDN, to maintain maintain PI-145, P1-i 45, LOLO PRESS LTDN PRESS LTDN PRESS PRESS PSIG, PSIG, between 300 psig and 400 psig.

9) Place PCV-145, LO PRESS LTDN, in AUTO.

10) Place TCV-144, CC TO LTDN HX, in AUTO.

9. Check the Reactor Makeup System:

CRS/RO FCV-1 13 A&B, BA FLOW, Controller to 8.6.

a. Set FCV-113 j.j. Ensure the Reactor Makeup System is in AUTO.

10. Transfer Charging Pump suction to the VCT:

CRS/RO LCV-li5C(E), VCT OUTLET ISOL.

a. Open both LCV-115C(E),

LCV-1 1 5B(D), RWST TO CHG PP SUCT.

k. Close both LCV-115B(D),

Examiners should end scenario at this point as SI is now secured and charging and letdown are restored.

EOP-2.O EOP-2.0 {if necessa~l (if necessary)

The following are applicable steps of EOP-2.0, Loss of Reactor or Secondary Coolant. This would be entered if PZR Level was too low for EOP-1 EOP-1.2 .2 transition.

1. Check if RCPs should be stopped:

1.

a. Check ifif either

a. either of the following criteria is of the is met:

.* Annunciator XCP-612 4-2 is is lit (PHASE B B ISOL).

ISOL).

OR ALL RCS pressure

- RCS pressure is is LESS LESS THAN THAN 1400 1400 psig psig AND AND SI SI flow flow is is indicated indicated on FI-943, on FI-943, CHG CHG LOOP LOOP BB CLD/HOT CLD/HOT LG LG FLOW FLOW GPM. GPM.

b. Stop all

b. Stop all RCP5.

RCPs.

2.

2. Verify Verify no no SGSG isis FAULTED:

FAULTED:

CRS/BOP CRS/BOP ** NoNo SGSG pressure pressure isis decreasing decreasing in in an an uncontrolled uncontrolled manner.

manner.

- NoNo SGSG isis completely completely depressurized depressurized..

3. Check

3. Check INTACT INTACT SG SG levels:

levels:

CRS/BOP CRS/BOP a. Verify Narrow

a. Verify Narrow Range Range level level in in INTACT INTACT SGs SGs isis GREATER GREATER THAN THAN 30% 30%

[50%].

AppendixDD Appendix RequiredOperator Required OperatorActions Actions Form FormES-D-2 ES-D-2 TestNo.:

OpTest No.: ----L-1 Scenario No.:

No.: 11 EventNo.:

No.: 10 Op Scenario Event 10 Page Page

- 1919 of of

-2121 Event

Description:

Event

Description:

Flowmeter Flow meter(FI-7368)

(Fl-7368)for forAATrain Train of ContainmentSpray ofContainment Sprayfails fails low.

low. Actual Actual spray sprayisis occurring.

occurring.

Time Time Position Position Applicants Actions Applicant's Actions or orBehavior Behavior

e. Control EFW

e. Control EFW flowflow to to maintain maintain Narrow Narrow RangeRange level level inin each each INTACT SG INTACT SG between between 40% 40% [50%]

[50%] and and 60%.

60%.

CRS/RO CRS/RO 4. Reset

4. Reset both both SI SI RESET RESET TRAINTRAIN A(B) A(B) Switches.

Switches.

5.5. Reset Reset Containment Containment Isolation:

Isolation:

CRS/RO CRS/RO RESET

RESET PHASE A

PHASE A -TRAIN

-TRAIN A(B) A(B) CNTMT CNTMT ISOL. ISOL.

- __RESET_P RESET PHASE HASE_B_-T RAIN_A(B)_

B -TRAIN CNTMT_ISO AJB) CNTMT ISOL.L.

6. Check ifif Secondary

6. Check Secondary radiation radiation levels levels are are normal:

normal:

a. Check

a. Check radiation radiation levels levels normal normal on: on:

RM-G19A(B)(C), STMLN

. RM-G19A(B)(C), STMLN HI HI RNG RNG GAMMA.GAMMA.

RM-A9, CNDSR

. RM-A9, CNDSR EXHAUST EXHAUST GAS ATMOS MONITOR. MONITOR.

RM-L3, STEAM

. RM-L3, STEAM GENERATOR GENERATOR BLOWDOWN BLOWDOWN LIQUID LIQUID MONITOR.

ALL ALL RM-L10,

- RM-L BLOWDOWN CW DISCHARGE 10, SG BLOWDOWN DISCHARGE LIQUID MONITOR.

b. Place SVX-9398A(B)(C),

SVX-9398A(B)(C), SG A(B)(C) SMPL ISOL, in AUTO.

m. Notify Chemistry to sample all all' SG secondary sides and screen' screen samples for abnormal activity using a frisker.

7. Check PZR PORVs and Block Valves:

a. Verify power is available to the PZR PORV Block Valves:

1) MVG-8000A

1) MVG-8000A,, RELIEF 445 445 A ISOL.

2) MVG-8000B MVG-8000B RELIEF 444 BB ISOL. ISOL.

3) MVG-8000C

3) MVG-8000C,, RELIEF RELIEF 445 445 BB ISOL.

ISOL.

CRS/RO CRS/RO IfIf any any PZR PZR PORV PORV opensopens because because of of high high PZRPZR pressure, pressure, Step Step 7.b7.b should should be be repeated repeated afterafter pressure pressure decreases decreases to to LESS LESS THAN THAN 2300 2300 psig, psig, to ensure the PORV to ensure the PORV recloses. recloses.

b. Verify

b. all PZR Verify all PZR PORVs PORVs are are closed.

closed.

c.c. Verify at least Verify at least one one PZRPZR PORV PORV BlockBlock Valve Valve isis open.

open.

8.8. Place Place both both ESF ESF LOADING LOADING SEQ SEQ A(B)A(B) RESETS RESETS to: to:

CRS/BOP CRS!BOP a.a. NON-ESF NON-ESF LCKOUTS.

LCKOUTS.

b.b. AUTO-STAR AUTO-START T BLOCKS.

BLOCKS.

9.9. Establish Establish Instrument InstrumentAir Airto the RB:

to the RB:

CRS/RO CRS/RO a.a. Start Startoneone Instrument InstrumentAir AirCompressor Compressorand and place place thethe other otherinin Standby.

Standby.

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

Test No.: 11 Scenario No.:

No.: 11 Event No.:

No.: 10 Op Scenario Event 10 Page Page

- 2020 of of

- 2121 Event

Description:

Event

Description:

Flow meter Flow (Fl-7368) for meter (FI-7368) for AA Train Train of of Containment Containment SpraySpray fails fails low.

low. Actual Actual spray spray isis occurring.

occurring.

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

b. Open

b. PVA-2659, INST Open PVA-2659, INST AIRAIR TOTO RBRB AIRAIR SERVo SERV.

c. Open C. Open PVT-2660, PVT-2660, AIR AIR SPLYSPLY TO TO RB.RB.

10. Check

10. Check ifif SISI flow flow should should be be reduced:

reduced:

a. RCS

a. RCS subcooling subcooling on TI-499A(B), A(B) on TI-499A(B), A(B) TEMPTEMP "F, F, is is GREATER GREATER THAN 30"F.

THAN 30F.

b. Secondary

b. Secondary Heat Heat Sink Sink is is adequate:

adequate:

. TotalTotal EFW EFW flowflow to to INTACT INTACT SGs SGs is is GREATER GREATER THAN THAN 450 450 gpm.

OR Narrow Range

. Narrow Range level is GREATER THAN 30% 30% [50%] in at least one INTACT one INTACT SG. SG.

c. RCS pressure is stable increasing.

C.

ALL NOTE - Step 10.d If PZR level is LESS THAN 18% [38%], the PZR should refill from SI flow after pressure is stabilized.

n. PZR level is GREATER THAN 18% [38%]

(IF PZR still less than 18%[38%], then go to Step 11), 1 1), if not then continue) GO TO Step 11. 1 1.

o. GO TO EOP-1.2, SAFETY INJECTION TERMINATION, TERMINATION, Step 1.

1 1. Check if RB Spray should be stopped:

11.

a. Check if any RB Spray Pumps are running

b. Verify RB pressure is LESS THAN 1111 psig

c. Depress both RESET TRAIN A(B) A(B) , RB SPRAY.SPRAY.

ALL NOTE-Step NOTE - Step 11.d 11.d

.* RB Spray must must run for aa minimum minimum of of two hours.

.* Anytime RB Spray Pumps Pumps are are stopped, stopped, MVG-3003A MVG-3003A(B), (B), SPRAY SPRAY HDR HOR ISOL ISOL LOOPLOOP (B), (B), should should be be closed closed for containment containment isolation.

isolation.

d.

d. Consult Consult with TSC personnel with TSC personnel concerning concerning RB RB Spray Spray System System operation.

operation.

12.

12. Check Check ifif RHR RHR PumpsPumps shouldshould be be stopped:

stopped:

a. Check RCS

a. Check RCS pressure:

pressure:

CRS/RO CRS/RO 1)

1) RCS RCS pressure pressure is is GREATER GREATER THAN THAN 250 250 psig psig 2)

2) RCS RCS pressure pressure isis stable stable OR OR increasing.

increasing.

b.__Check_i

b. Check iff_any_RHR_

any RHR Pump is running Pump_is_run with suction ning_with_su aligned_to_the ction_aligned to the

Appendix0D Appendix RequiredOperator Required OperatorActions Actions Form FormES-D-2 ES-D-2 TestNo.:

OpTest No.:

Op

- 11 Scenario No.:

Scenario No.:

- 11 EventNo.:

Event No.:

-1010 Page Page

- 2121 ofof

-2121 EventDescription:

Event

Description:

Flowmeter Flow meter(FI-7368)

(Fl-7368) for forAATrain Train of ContainmentSpray ofContainment Sprayfails failslow.

low. Actual Actual spray spray isis occurring.

occurring.

Time Time Position Position ( RWST Applicants Actions Applicant's Actions or or Behavior Behavior RWST c.c. Stop Stop any any RHR RHR PumpPump which which isis running running with with suction suction aligned aligned to to the the RWST and RWST and place place inin Standby.

Standby.

13. Check

13. Check ifif RCS RCS pressure pressure isis stable stable OR OR decreasing.

decreasing.

This would be a do loop This would be a "do loop" back back toto step1 stepi until until PZR PZR Level Level was was greater greater CRS/RO CRS/RO than 18%

than 18% [38%]

[38%]

RETURN TO RETURN TO Step Step 1.1.

This isis end This end of of EOP-2.0 EOP-2.O for for this this scenario.

scenario.

Appendix D0 Appendix Scenario Outline Scenario Outline Form Form ES-D-1 ES-D-1 Facility:

Facility: Ivc VC Summer Summer I Scenario No.:

Scenario No.: 33 (SPARE)

(SPARE) Op-Test No.:

Op-Test No.: 2005-301 2005-301 Examiners:

Examiners: Operators:

Operators:

initial Conditions:

Initial Conditions: The Unit The Unit isis in in Mode Mode 22 with MOL reactor with aa MOL reactor startup startup in in progress.

progress.

Turnover:

Turnover: The previous crew The previous crew has has initiated initiated the reactor startup the reactor startup per per GOP-3.

GOP-3. Source Source range range counts counts are are stable stable and and Control bank Control bank '0' D is is presently presently at at 100 100 steps.

steps. 11M 1IM data data now now projects projects criticality criticality at at 116 116 steps steps on on Control Control bankbank D. Continue

'0'. Continue with with the the reactor reactor startup beginning with startup beginning with step step 3.11.q 3.11 .q of GOP-3, and of GOP-3, and stabilize stabilize reactor reactor power power between 1-3%.

between 1-3%.

Al "A maintenance week 1" maintenance SIG "A,"

S/G A, Small tube leak, approx. 8 gpd.

Event Event MaIf. No. I/

Malf. Event Event Description No. Position Type*

Type*

RO R Pull control rods to establish critical reactor.

11 BOP C Train 'A' A Service Water Pump A trips and spare "c" C pump needs to be aligned and 2 SRO (TS) started.

RO II Controlling channel Pressurizer Level Transmitter (IL T-459) fails low and LID (ILT-459) 3 isolates.

AOP-401 AOP-401.6 .6 BOP N N Re-establish letdown.

4 (SOP-i (SOP-102) 02)

BOP II Steam Generator Generator B B PORV Pressure Transmitter (IPT-2010) fails high. BOP BOP 55 operator takes manual control and closes PCV-2010. PCV-201 O.

BOP BOP/ROI RO CC Letdown line line break break inside inside Containment.

Containment. AOP isolates isolates letdown letdown which which terminates the the 66 SRO SRO (TS) leak.

leak. Crew places excess Crew places excess letdown letdown in in service.

AOP-l0l.l AOP-101.1 & & SOP-102 SOP-102 RO RO CC RCP RCP A"A" High High Vibration Vibration (discussion (discussion about PZR spray) about PZR spray) andand seal seal failure failure when when 77 secured.

secured. (AOP-101.2)

(AOP-101.2)

(SOP-lOl)

(SOP-101)

ALL ALL MM Small Small break break LOCA LOCA (approx (approx 400 400 gpm).

gpm). Ramp Ramp leak leak inin over over aa 55 minute minute period period to to allow allow entry entry into into AOP-l0l.l AOP-1 01.1 again.again. (vary(vary ramp ramp rate rate asas necessary necessary to to give give operators operators time time to to 88 make make manual "manual" reactor reactor trip trip decision decision in in AOP-1 AOP-101.1 01.1 prior prior to to getting getting auto auto trip trip and and time time to to manual manual Si SI in in EOP-1.0 EOP-1.0 prior prior toto auto auto Si).

SI).

BOP BOP or or CC Safety injection Train Safety injection Train 'A' A fails to automatically fails to automatically or or manually manually actuate actuate (troubleshooting (troubleshooting RO RO this this event event for the rest for the rest of of the the scenario),

scenario). and and B'B' Charging Charging pumppump fails fails to to automatically automatically 9 start start when safety injection when safety injection isis initiated initiated but but will will manual manual start.

start. The The reactor reactor failsfails to to automatically automatically trip trip && fails fails toto trip trip from from ROside RO*side MCB MCB switch switch but but will will trip trip from from BOPBOP side..

side ..

(N)ormal, (N)ormal, (R)eactivity, (R)eactivity, (l)nstrument, (I)nstrument, (C)omponent, (C)omponent, (M)ajor (M)ajor Appendix Appendix D, D, Page Page 39 39 of of 39 39

Scenario Event Scenario Event Description Description VC VC Summer-2005-301 Summer-2005-301 Op-Test No.:

Op-Test No.: Scenario No.:

Scenario No.: Event No.:

Event No.: Page Page _ _ of of _ _

Event

Description:

Event

Description:

Time Time Position Position Applicants Actions Applicants Actions or or Behavior Behavior I I I Within 15

q. Within

q. 15 minutes minutes before GOP-3.O GOP-3.0 before achieving achieving criticality, criticality, verify Tavg Tavg I

greater than or greater or equal equal to 551°F.

551 °F.

r.r. Announce criticality criticality over over the the page system.

s. Verify critical rod position is above the Rod Rod Insertion Insertion Limit per per Tech Spec 3.1.3.6.

t. At the AUDIO COUNT RATE CHANNEL drawer, place the following switches in OFF:

MULTIPLIER.

1) AUDIO MULTIPLIER.

2) CHANNEL SELECTOR.

SELECTOR.

3.11 Increase Reactor Power to 10-3% as follows: /I

a. Establish a stable Startup Rate of less than one decade per minute.

b. At 7.5x1 0-6%, perform the following:

1) Verify P6 Permissive energizes to bright.

2) Verify a minimum of one decade overlap between Source Range Channels and Intermediate Intermediate Range Channels.

c. Prior to 10 100 CPS, perform perform the following:

1)

1) Momentarily place SR TRAIN TRAIN A Switch in BLOCK.

2) Verify SR A TRIP BLCK Permissive energizes to bright.

3) Momentarily Momentarily place SR TRAIN B B Switch in BLOCK.

BLOCK.

4)

4) Verify SR SR B B TRIP BLCK BLCK Permissive energizes energizes to bright.

bright.

d. Select

d. Select one one Intermediate Intermediate Range Range Channel Channel and and one one Power Power Range Range Channel Channel on on NR-45, NR-45, NISNIS RECORDER RECORDER..

Q3%*

e. Stabilize

e. Stabilize Reactor Reactor Power Power at at 110-;)%.

This ends the This ends the pull pull to to criticality criticality event.

event.

RO RO AA SWPSWP trips. RO responds trips. RO responds to to various various alarms alarms and and references references the the ARP:

ARP:

XCP-604 XCP-604 1-2: 1-2: SWP SWP A/C A/C TRIP TRIP Appendix Appendix D, D, Page Page 39 39 of of 39 39

Scenario Event Scenario Event Description Description VC VC Summer-2005-301 Summer-2005-301 Op-Test No.:

Op-Test No.: Scenario No.:

Scenario No.: Event No.:

Event No.: Page _ _ of Page of _ _

Event

Description:

Event

Description:

Time Time Position Position Applicants Actions Applicants Actions oror Behavior Behavior XCP-604 3-3:

XCP-604 3-3: SW Sw CCW CCW HX HX AA FLOFLO LOITEMP LO/TEMP HI HI XCP-604 3-4:

XCP-604 3-4: DG DG AA CLR CLR SWSW FLO FLO LO TEMP HI LO TEMP HI CRS/RO CRS/RO ARP isis handed handed to CRS,CRS, the the IB lB operator operator isis dispatched dispatched to to SW SW PPPP house house to investigate.

to investigate. Electricians Electricians may may also also be notified.

be notified.

CRS CRS Decision should Decision should be be made made to to place place C C SWP SWP on on AA Train Train CORRECTIVE ACTIONS:

CORRECTIVE Place the spare I. Place spare Service Service Water Pump in service per SOP- SOP-117.

117.

ALL 2.1 Shift from Service Water Pump A to Service Water Pump C in service, as follows:

a. With the exception of racking down XSW1 XSW1EA EA 04, SERVICE WATER PUMP XPP0039A-SW,XPPOO39A-SW, complete Attachment V.

ALL b. Start XPP-0039C, PUMP C TRAIN A. (PEER D) LI)

RO c. Verify MVB-3116C, MVB-31 160, SWP C DISCH, automatically opens.

ALL/Buildin ALL/Building g d. Ensure sufficient Service Water Pump C cooling water flow, by throttling the following (SW-436):

1) XVTO31 57C-SW, sw XVT03157C-SW, SW PP C MTR UPPER BRG CLG WTR SUP VALVE, to obtain upper bearing flow between 10 gpm and 12 12 gpm.

2) XVTO3158C XVT03158C-SW, -SW, SWsw PP C MTR LOWER BRG CLG WTR SUP VALVE, to obtain lower bearing flow between 33 gpm and 44 gpm.

ALL/Buildin ALL/Building g e.e. At XPN-1 XPN-13, C SERVICE 3, C SERVICE WATER SCREEN SCREEN Control Control Panel Panel (SW-436), verify proper proper traveling screen screen operation, as as follows:

1)

1) Place Place the the Screen Screen Selector Selector Switch, in HAND.

Switch, in HAND.

2) Verify proper screen operation

2) Verify proper screen operation and and screen screen wash wash flow.

3) Place

3) Place the the Screen Screen Selector Selector Switch, Switch, in in AUTO.

AUTO.

RD RO f.f. Stop Stop XPP-0039A, XPP-0039A, PUMP PUMP A,A, and and place place the the control control switch, switch, in in PULL PULL TO TO LK LK NON-A.

NON-A.

RD RO g. Verify

g. Verify MVB-31 MVB-3116A,16A, SWP SWP A A DISCH, DISCH, automatically automatically closes.

closes.

Appendix Appendix D, D, Page Page 39 39 of of 39 39

Scenario Event Scenario Event Description Description VCVO Summer-2005-301 Summer-2005-301 Op-Test No.:

Op-Test No.: Scenario No.:

Scenario No.: Event No.:

Event No.: Page _ _ of Page of _ _

Event

Description:

Event

Description:

Time Time Position Position Applicants Actions Applicants Actions oror Behavior Behavior ALL/Building h.

ALL/Building h. Re-verify Re-verify Service Service Water Water Pump Pump C C cooling cooling water water flow flow and and adjust adjust as necessary, by throttling as necessary, by throttling the following (SW-436):

the following (SW-436):

1) 1) XVT03157C-SW, XVTO31 570-SW, SW SW PP PP C MTR UPPER C MTR UPPER BRGBRG CLGCLG WTR WTR SUPSUP VALVE, to to obtain obtain upper upper bearing bearing flow flow between between 10 10 gpm gpm and and 12 12 gpm.

gpm.

XVTO3158C-SW, SW PP

2) XVT03158C-SW, PP C MTR LOWERLOWER BRG BRG CLG WTR SUP VALVE, to obtain lower lower bearing flow between 3 gpm and 4 gpm.

ALL/Building ALL/Building I. XSW1 EA 04, SERVICE WATER PUMP Rack down XSW1EA XPP0O39A-SW (SW-425).

XPP0039A-SW ALL/Building ALL/Building XPN-1 1, A SERVICE WATER SCREEN, Control Panel j.j. At XPN-11, (SW-436),

place the Screen Selector Switch, in OFF.

ALL/Building ALL/Building k. Complete Attachment V.

ALL I. Ensure proper Service Water flow through the operable Train A Chiller per SOP-501.

This ends the A SWP trip event.

The following event event is the LT-459 L T-459 Failure, PZR Level Controlling Controlling channel.

channel.

LT-459 LT-459 Fails low and Fails low Letdown isolates.

and Letdown isolates. The The following following alarms alarms are are received:

received:

XCP-614 XCP-614 5-1: 5-1: CHG CHG LINE FLO HI/LO LINE FLO HIILO XCP-616 XCP-616 1-3: 1-3: BLCK BLCK HTRS HTRS ISOL ISOL LTDN LTDN PZR PZR LOS LCS LO LO XCP-616 1-5: PZR LOS XCP-616 1-5: PZR LCS DEV HIILO DEV HI/LO XCP-616 XCP-616 3-1: 3-1: PZR PZR HTR HTR CNTRL CNTRL OR OR BUBU GRP 1/2 TRIP GRP 1/2 TRIP XCP-616 XCP-616 4-6: 4-6: SCR SCR OUTPT OUTPT LOSS LOSS Appendix Appendix D,D, Page Page 39 39 of of 39 39

Scenario Event Scenario Event Description Description VC VC Summer-2005-301 Summer-2005-301 Op-Test No.:

Op-Test No.: Scenario No.:

Scenario No.: Event No.:

Event No.: Page Page _ _ of of _ _

Event

Description:

Event

Description:

Time Time Position Position Applicants Actions Applicants Actions oror Behavior Behavior I Crew enters Crew enters AOP-401.06 AOP-401.06 PZR PZR Level Level Control Control and and Protection Protection Channel Failure.

Channel Failure. Step Step 1I is is an an immediate immediate action.

action.

AOP-401.6 AOP-401.6 RO RD Place PZR LEVEL CNTRL Switch to the position with two 11 Place operable channels.

RO RD 2 Select an operable channel on PZR LEVEL RCDR.

RO RD 3 Control the PZR Heaters as necessary to maintain PZR pressure:

CNTRL GRP Heaters.

BU GRP 1I Heaters.

BU GRP 2 Heaters.

RO RD 4 Verify Letdown is in service. 4 Re-establish Letdown.

REFER TO SOP-102, CHEMICAL AND VOLUME CONTROL SYSTEM.

IF Letdown can NOT be established, THEN REFER TO AOP AOP-102.1, 102.1, LOSS OF LETDOWN, while continuing with this procedure.

RO RD 2.1 Place FCV-122, CHG FLOW, in MAN and close.

RO RD 2.2 Place PCV-145, 2.2 PCV-145, LO PRESSPRESS LTDN, in in MAN MAN and open to 70%. (PEER Li) 70%. D)

RO RD 2.3 2.3 Place Place TCV-144, TCV-144, CC CC TOTO LTDN LTDN HX, in MAN HX, in MAN andand open to 100%.

100%.

RO RD 2.4 Place TCV-143, 2.4 Place TCV-143, LTDN LTDN TO TO VCT VCT OROR DEMIN, DEMIN, inin VCT.

VCT.

RO RD 2.5 Open PVT-8152, 2.5 Open PVT-8152, LTDN LTDN LINELINE ISOL.

ISOL.

RO RD 2.6 2.6 Open the following:

Open the following:

a. LCV-459, LTDN

a. LCV-459, LTON LINE LINE ISOL.

ISOL.

b. LCV-460,

b. LCV-460, LTDN LTON LINE LINE ISOL.

ISOL.

Appendix Appendix D,0, Page Page 39 39 of of 39 39

Scenario Event Description Scenario Event Description VC VC Summer-2005-301 Summer-2005-301 Op-Test No.:

Op-Test No.: Scenario No.:

Scenario No.: Event No.:

Event No.: Page Page _ _ of of _ _

Event

Description:

Event

Description:

Time Time Position Position Applicants Actions Applicants Actions or or Behavior Behavior RO 2.7 Ensure 2.7 Ensure thethe following Charging Charging LineLine Isolation Isolation Valves are open:

MVG-.8107,

a. MVG-81 07, CHG LINE ISOL.

MVG-8108,

b. MVG-81 CHG Llt:-JE 08, CHG ISOL.

LINE ISOL.

RO 2.8 Slowly open FCV-122, CHG FLOW, to establish 60 gpm flow as indicated on FI-122A, Fl-122A, CHG FLOW GPM.

RO 2.9 Open Orifice Isolation Valves to obtain the desired Letdown flow rate (60 gpm to 120 120 gpm):

a. PVT-8149A, LTDN ORIFICE A ISOL (45 gpm).

b. PVT-8149B, LTDN ORIFICE B ISOL (60 gpm).

c. PVT-8149C, LTDN ORIFICE C ISOL (60 gpm).

RO 2.10 Adjust FCV-122, CHG FLOW, as required to maintain TI- TI 140, REGEN HX OUT TEMP of, °F, between 250°F and 350°F while maintaining Pressurizer level.

RO 2.11 Adjust PCV-145, LO PRESS LTDN, to maintain PI-145, P1-145, LO PRESS L LTDN TDN PRESS PSIG, between 300 psig and 400 psig.

RO 2.12 Place PCV-145, LO PRESS LTDN, in AUTO.

RO 2.13 Adjust TCV-144, CC TO L LTDN TDN HX, potentiometer as necessary to maintain the desired VCT temperature and place in AUTO. Refer to VCS Curve Book, Figure VII.15. V11.15.

RO 2.14 When Pressurizer level matches reference level, place FCV-122, CHG FLOW, in AUTO per Section IV.

RO 2.15 After the Letdown temperatures have stabilized, place TCV TCV-143, 143, LTDN TO VCT OR DEMIN, in DEMIN/AUTO.

RO 5 Check if PZR LVL MASTER MASTER CONTROLLER is is responding appropriately:

appropriately:

.* Verify Charging flow is normal and responding to to PZR level error.

.* Verify PZR level is stable at OR level is OR trending to program program level.

level.

Appendix Appendix D, D, Page Page 3939 ofof 39 39

Scenario Event Scenario Event Description Description VC VC Summer-2005-301 Summer-2005-301 Op-Test No.:

Op-Test No.: Scenario No.:

Scenario No.: Event No.:

Event No.: Page _ _ of Page of _ _

Event

Description:

Event

Description:

Time Time Position Position Applicants Applicants Actions Actions oror Behavior Behavior CRSISE CRS/SE Within six 66 Within six hours, hours, place place the the failed failed channel channel protection protection bistables in bistables in a tripped condition:

Identify the associated bistables for the failed channel

a. Identify REFER TO Attachment 11..

b. Record the following for each associated bistable on SOP-401, REACTOR PROTECTION AND CONTROL SYSTEM, Attachment I:

- Instrument.

. Associated Bistable.

. Bistable Location.

. STPs.

c. Notify the I&C Department to place the identified bistables in trip.

7 Determine and correct the cause of the channel failure This concludes the L T-459 failure event.

LT-459 The next event is IPT-2010 slowly failing high which results in SG PORV IPV-2010 (B (8 Loop) slowly going full open.

Valve controller can be taken to Manual and closed. No alarms are are associated with this event. event.

ALL Crew Crew should should notice notice some some excess RCS cooling, increasedincreased steam flow and and finally notice notice IPV-2010 IPV-201 0 isis going going open.

open.

CRS/BOP CRS CRS and/or and/or BOP BOP should should recommend placing placing 2010 2010 controller controller in in Manual Manual andand attempting attempting toto close.

BOP BOP IPV-2010 IPV-2010 placed placed in in Manual Manual and and closed.

closed.

CRS/SE CRS/SE MWR should MWR should bebe written written and and work work order order generated generated to to repair repair transmitter.

transmitter.

This concludes concludes thethe 2010 2010 failing open open event.

event.

Appendix Appendix D, D, Page Page 39 39 of of 39 39

Scenario Event Scenario Event Description Description VCVC Summer-2005-301 Summer-2005-301 Op-Test No.:

Op-Test No.: Scenario No.:

Scenario No.: Event No.:

Event No.: Page Page _ _ of of _ _

Event

Description:

Event

Description:

Time Time Position Position Applicants Actions Applicants Actions or or Behavior Behavior The Letdown leak inside containment is the next event.

The following alarms are received as leak progresses:

XCP-642 3-3: 3-3: RB ACC AREA RM-G5 HI HI RAD XCP-642 XCP-642 3-4: 3-4: RB RB ACC ACC AREA RM-G5 TRBL TRBL XCP-642 3-5: 3-5: INCOR INCOR INSTR INSTR AREA RM-G14 HI HI RAD RAD XCP-642 XCP-642 3-6: 3-6: INCOR INCOR INSTR INSTR AREA RM-G14 TRBL TRBL AOP-1O1.1 AOP-101.1 RO RO I1 Verify PZR level Verify PZR level is is at or trending at or trending toto program program level.

level.

IF PZR IF level is PZR level is decreasing.

decreasing. THENTHEN perform perform the the following:

following:

a) a) Open Open FCV-1 FCV-122.22. CHG CHG FLOW FLOW as as necessary necessary to to maintain maintain PZR PZR level level b) IF b) IF PZR level continues PZR level continues toto decrease, decrease, THEN THEN reduce reduce Letdown Letdown to to one one 45 gpm orifice:

45 gpm orifice:

1)Set PCV-145, 1)Set PCV-145, LO LO PRESS PRESS LTDN. To 70%

LTDN. To 70%

2)

2) Ensure Ensure PVT-8149A.

PVT-8149A. LTDN LTDN ORIFICE ORIFICE A A ISOL.

ISOL. isis open.

open.

3)

3) Close_both_PVT-8149B(C)._LTDN_ORIFICE_B(C)

Close both PVT-8149B(C). LTDN ORIFICE B(C)

Appendix Appendix D, D, Page Page 3939 of of 39 39

Scenario Event Scenario Event Description Description VC VC Summer-2005-301 Summer-2005-301 Op-Test No.:

Op-Test No.: Scenario No.:

Scenario No.: Event No.:

Event No.: Page _ _ of Page of _ _

Event

Description:

Event

Description:

Time Time Position Position Applicants Actions Applicants Actions oror Behavior Behavior ISOL.

ISOL.

4) Adjust

4) PCV-145. LO Adjust PCV-145. LO PRESS PRESS LTDN.LTDN. to to maintain maintain P1-145. LO PI-145. PRESS LTDN LO PRESS LTDN PRESS PSIG. between PRESS PSIG. between 300 300 psig and400 psig and400 psig. psig.

5) Place PCV-145,

5) Place PCV-145, LO LO PRESS PRESS LTDN.LTDN. in in AUTO.

AUTO.

CRS/RO 2 Check if 51 SI is required:

a.

a. Check ifif any jjy of the following criteria are met: met:

. PZR PZR level is is decreasing with Charging maximized and Letdown minimized.

. PZR level is approaching 12%.

. PZR pressure is approaching 1870 psig.

. VCT level is approaching 5%.

SI should NOT be required, crew should follow AL TERNA TlVE ALTERNAT IVE ACTION of step 2 which is to GO TO STEP 3 CRSISE CRS/SE 3 Determine RCS leak rate:

a. Estimate the RCS leak rate. REFER TO IPCS CHGNET.

b. Calculate the RCS leak rate. REFER TO STP-1 STP-114.002.

14.002.

OPERATIONAL LEAK TEST.

OPERATIONAL

c. Check if the RCS leak rate is GREATER THAN Tech Spec 3.4.6.2

d. Comply with the applicable Tech Spec 3.4.6.2 action statement.

RO 4 Verify RCS pressure is GREATER THAN 2210 psig.

a) Ensure all PZR PZR Heaters Heaters are are on.

b) the PZR Spray Spray Valves are are closed c) Ensure Ensure the PZR PZR PORVs PORVs are are closed. IF IF any any PORV fails to close, THEN close, THEN close its Block close its Siock Valve.

Valve.

BOP/CRS BOP/CRS 55 Verify Verify nono SG SG tubes tubes are are leaking:

leaking:

a. Narrow

a. Narrow Range Range level level inin no SG is no SG is increasing increasing with with feed feed flow flow LESS LESS THANTHAN steam steam flow.

flow.

b. Radiation

b. Radiation levels levels onon all all of the following of the following are are normal:

normal:

.* RM-G19A(B RM-G19A(S)(C). )(C). STMLN STMLN HI RNG GAMMA.

HI RNG GAMMA.

.* RM-A9.

RM-A9. CNDSR CNDSR EXHAUST EXHAUST GAS GAS ATMOS ATMOS MONITOR.

MONITOR.

.__RM-L3._S

RM-L3. STEAM TEAM_GEN GENERA TOR SLOWDOWN ERATOR_B LOWDOWN Appendix Appendix D, Page 39 0, Page 39 ofof 39 39

Scenario Event Scenario Event Description Description VCVC Summer-2005-301 Summer-2005-301 Op-Test No.:

Op-Test No.: Scenario No.:

Scenario No.: No.:

Event No.: Page Page _ _ ofof _ _

Event -----

Event Event

Description:

Time Time Position Position Applicants Actions Applicants Actions or or Behavior Behavior MONITOR.

LIQUID MONITOR.

LIQUID

. RM-LIO.

RM-LiO. SG BLOWDOWN CW DISCHARGE LIQUID MONITOR.

No steam flowlfeed

c. No flow/feed flow mismatch mismatch (feed (feed flow low).

low).

d. As determined by Chemistry sample analysis of ALL SG secondary sides for activity.

RO 6 Check the PZR PORVs:

a. Check if RCS pressure is LESS THAN 2335 psig.

b. Verify all PZR PORVs are closed.

c. Check if PRT conditions are normal by verifying

/TEMP/LVL/PRESS HI (XCP-616 4-4). is not lit.

PRT LVL LO ITEMP/LVLlPRESS

d. Verify at least one PZR PORV Block Valve is open.

RO 7 Check If Reactor Building conditions are normal:

a. RB radiation levels are normal on the following:

. RM-GS. RB PERSONNEL ACCESS AREA GAMMA.

. RM-G6. 17 RB REFUEL BRIDGE AREA GAMMA.

RM.-A2. RB SAMPLE LINE

. RM-A2.

PARTICULATE(IODINE)(GAS) ATMOS MONITOR.

b. RB Sump levels are normal

c. RB pressure is LESS THAN 1.5 1.5 psig

d. The following annunciators are NOT lit:

. RBCU IAl2A IAI2A DRN FLO HI (XCP-606 2-2).

.* RBCU IB/2B IB/2B DRN FLO HI (XCP-607 2-2).

Conditions are not normaI normal, so the alternative action of isolating letdown will be performed.

RD RO 77 Attempt to isolate leakage as follows:

a) Close all Letdown Isolation Isolation Valves:

1) PVT-8149A(B)(G) LTDN

1) LTDN ORIFICE A(B)(C) ISOL. ISOL.

2) LCV-459.

2) LCV-459. LTDN LINE ISOL LTDN LINE ISOL 3)

3) LCV-460, LTDN LTDN LINE ISOLISOL b) Check RCS parameters for indications of of leakage.

leakage.

Leakage Leakage should be be isolated by above actions.

by the above actions. Crew Crew should wait and and verify nono further leakage occurs. Since Since Normal Letdown will remain isolated, crew should place EXCESS LETDOWN should place LETDOWN in service.

service.

REFER REFER TO TO SOP-i SOP-102.02. CHEMICAL CHEMICAL AND AND VOLUME VOLUME CONTROL CONTROL SYSTEM SYSTEM Appendix D, Appendix D, Page Page 3939 of of 39 39

Scenario Event Description Scenario Event Description VCVC Summer-2005-301 Summer-2005-301 Op-Test No.:

Op-Test No.: Scenario No.:

Scenario No.: Event No.:

Event No.: Page Page _ _ of of _ _

Event

Description:

Event

Description:

Time Time [ Position Position The following The Applicants Applicants Actions following is from from SOP-102:

SOP-102:

Actions or or Behavior Behavior I RO Ensure HCV-137, 2.1 Ensure HCV-137, XSXS LTDN HX, is closed.

RO 2.2 Place PVM-8143, XS LTDN Place PVM-8143, LTDN TOTO VCT(PEER D) LI)

RO 2.3 If required, reset Phase A Isolation by depressing the following:

a. RESET PHASE A - TRAIN A CNTMT ISOL.

b. RESET PHASE A - TRAIN B CNTMT ISOL.

RO Open the following:

MVT-8100,

a. MVT-81 00, SEAL WTR RTN ISOL.

b. MVT-8112, SEAL WTR WTRRTN RTN ISOL.

RO 2.5 Ensure MVG-9583, FROM XS LLTDN TDN HX, is open.

RO 2.6 Open PVT-8153, XS LTDN ISOL.

RO 2.7 Open PVTPVT-8154,

-8154, XS L LTDN TDN ISOL.

RO 2.8 Establish Excess Letdown flow as follows:

a. Slowly throttle open HCV-137, XS LTDN HX.

b. Monitor TI-i 39, XS LETDOWN HX OUT TEMP of, TI-139, °F, to maintain less than 165°F.

c. Monitor the following to ensure flow between 0.2 gpm and 5.0 gpm:

1) FR-i

1) 54A, RCP SL LKOFF HI RANGE.

FR-154A,

2) FR-154B, RCP SL LKOFF LO RANGE.

This concludes establishing Excess Letdown. More steps do remain from A OP- 101.1 for determining if leakage is AOP-101.1 isolated, but can commence the A RCP Rep high vibration event at this time.

Appendix Appendix D,D, Page Page 3939 of of 39 39

Scenario Event Description Scenario Event Description VC VC Summer-2005-301 Summer-2005-301 Op-Test No.:

Op-Test No.: Scenario No.:

Scenario No.: Event No.:

Event No.: Page Page _ _ of of _ _

Event

Description:

Event

Description:

Time Time Position Position Actions or Applicants Actions Applicants or Behavior Behavior Crew receives annunciator XCP-617 XCP-61 7 1-3:

RCPAVIBRHI RCPA VIBR HI RO should notice frame and shaft vibration levels are escalating. A RCP should be secured based on increasing levels. The following steps would apply from SOP-101 SOP-1O1 for securing the RCP.

RD RO 2.1 Place the Pressurizer Spray Valve for the affected Reactor Coolant Pump in MAN and close:

a. PCV 444D, PZR SPRAY, for Reactor Coolant Pump A.

RD RO PCV-1 45, LO 2.2 If the Reactor Coolant System is solid, place PCV-145, PRESS L LTDN, TDN, in MAN.

RO 2.3 Secure one of the following Reactor Coolant Pumps as required:

a. XPP-0030A, PUMP A.

RD RO 2.4 If the Reactor Coolant System is solid, return PCV-145, LO PRESS LTDN, LTDN, to AUTO, if desired.

RD RO 2.5 Verify Seal Injection to the secured Reactor Coolant Pump using the applicable following indicator:

a. Fl-i

a. 30A, RCP A INJ FI-130A, INJ FLO GPM.

GPM.

RO 2.6 2.6 Maintain Component Component Cooling Water to the secured Reactor Coolant Pump thermal barrier until until RCS temperature is less than is less 150°F.

150°F.

BDP BOP 2.7 2.7 Place the following controllers Place the controllers in in MAN, as required MAN, as required for for the the affected RCS affected RCS loop loop and and maintain Narrow Range maintain Narrow Range Steam Steam Generator Generator level level between between 60% and 65%:

60% and 65%:

Appendix Appendix D, D, Page Page 39 39 of of 39 39

Scenario Event Scenario Event Description Description VCVC Summer-2005-301 Summer-2005-301 Op-Test No.:

Op-Test No.: Scenario No.:

Scenario No.: Event No.:

Event No.: Page Page _ _ of of _ _

Event

Description:

Event

Description:

Time Time Position Position Applicants Actions Applicants Actions oror Behavior Behavior

a. PVT-478,

a. PVT-478, SG EWE.

SG A FWF.

FCV-3321, LOOP A MAIN FW BYP.

b. FCV-3321, CRS 2.8 If not already in Hot Standby, proceed to Hot Standby lAW Reactor Shutdown GOP-5, Reactor Shutdown FromFrom Startup To Hot Hot Standby (Mode (Mode 2 To Mode 3).

The following steps are from GOP-5, Reactor Shutdown from Mode 2 to Mode 3. These steps will place the Reactor below 7. 7.5x10-5%

5x1 0-5% power. Prior to commencing shutdown, should go ahead and begin Small Break LOCA Event.

CRSISE CRS/SE 3.1 Complete GTP-702 Attachment II.K, lI.K, Operational Mode Change Plant Shutdown - Entering Mode 3 Or Plant Trip To Mode 3 From Modes 1I Or 2.

RO 3.2 Select both Intermediate Range Channels on NR-45, NIS RECORDER.

3.3 Insert Control Rods with a manual Reactor trip as follows:

CRS a. Perform a Pre-job brief per OAP-100.3, CAP-i 00.3, Human Performance_Tools.

Performance Tools.

RO b. Select one Intermediate Range and one Source Range Channel_on_NR-45,_NIS_RECORDER Channel on NR-45, NIS RECORDER BOP c. Ensure both Motor Driven Emergency Feedwater Pumps are_running.

are running.

RO d. (Optional) If desired, commence RCS boration prior to performing aa manual Reactor trip:

1)

1) Open MVT-8i04, MVT-81 04, EMERG BORATE.

2) Ensure XPP-i3A(B),

XPP-13A(B), BA XFER PP A(B), is running.

3) Verify greater than 30 gpm flow on Fl-il FI-11 0, EMERG BORATE FLOW GPM. GPM.

4) Refer to STP-134.OOi, STP-134.001, Shutdown Shutdown Margin Verification, to determine the required boron concentration needed for the anticipated Plant Mode and temperature:

Anticipated Mode:

Mode:

Anticipated RCS RCS temperature:

temperature: °F OF Required Required Boron:

Boron: ppm ppm

5) When boration

5) boration is no longer is no longer desired, desired, perform perform the the following:

a) Close MVT-8i04, a) Close MVT-81 04, EMERG EMERG BORATE.

BORATE.

b)_Verify_no_flow_on_Fl-i b) Verify no flow on FI-110, 10,_EMERG_BORATE EMERG BORATE Appendix Appendix D, D, Page Page 3939 of of 39 39

Scenario Event Scenario Description VC Event Description VC Summer-2005-301 Summer-2005-301 Op-Test No.:

Op-Test No.: _ __ Scenario No.:

Scenario No.: _ _ _ _ Event Event No.:

No.: _ __ Page _ _ of Page of _ _

Description:

Event

Description:

Event Time Time Position Position Applicants Actions Applicants Actions or or Behavior Behavior FLOW GPM.

FLOW GPM.

RO RO e. Place

e. Place RX RX TRIP Switch CS-CR01 TRIP Switch CS-CRO1 in in TRIP.

TRIP.

f.f. Verify Verify allall Reactor Reactor Trip Trip and Bypass Breakers and Bypass Breakers are are open.

open.

g. Verify all

g. Verify all Rod Rod Bottom Bottom lights lights are are lit.

lit.

h. IfIf two or more

h. Control Rods more Control Rods are are not not fully inserted, inserted, then emergency borate as follows:

1) Open

1) Open MVT-8104, MVT-8104, EMERGEMERG BORATE.

BORATE.

2) Verify greater than

2) than 30 30 gpm flow on FI-110, Fl-i 10, EMERG EMERG BORATE FLOW GPM.

AOP-i 06.1, Emergency

3) If required, refer to AOP-1 Boration, to establish greater than 30 gpm flow.

4) Borate 2500 gallons if two Control Rods are not fully inserted.

5) Borate 5800 gallons if greater than two Control Rods are not fully inserted.

i. Verify Reactor Power level is decreasing.

j. Ensure RCS temperature is being maintained between 555°F and 559°F using the Steam Dump System or Steamline Steam line PORVs.

k. Place both SOURCE RANGE HIGH FLUX AT SHUTDOWN Switches in BLOCK.

I. When Reactor Power decreases below 7.5 xx 10-6%, 10-6%,

complete the following:

1) Verify P6 Permissive de-energizes to dim.

2) When on scale indication is observed, select both Source Range Channels on NR-45, NIS RECORDER RECORDER..

This concludes the high vibration on A A RCP event. The Small Break Break LOCA event event can now now commence if not already performed performed earlier. earlier. The following stepssteps would again be be the repeat of ofAOP-1O1.

AOP-101.1I until the size of of the leak would require EOP-I.O EOP-1.0 entry entry for TRIP andand SI.

SI.

Appendix Appendix D, D, Page Page 39 of 39 39 of 39

Scenario Event Scenario Event Oescription Description VC VC Summer-2005-301 Summer-2005-301 Op-Test No.:

Op-Test No.: Scenario No.:

Scenario No.: Event No.:

Event No.: Page Page _ _ of of _ _

Event

Description:

Event

Description:

Time Time Position Position Applicants Applicants Actions Actions or or Behavior Behavior The following The following annunciators annunciators shouldshould come come into into alarm:

alarm:

XCP 606 2-2: RBCU 1A12A IA/2A DRN FLO HI XCP 607 2-2: RBCU 1IBI2B B/2B DRN FLO HI XCP 616 3-6:PZR PCS PCS LO BU BU HTRS ON AOP-101.1 AOP-1O1.1 1I Verify PZR level is at or trending to program level.

1I IF PZR level is decreasing. THEN perform the following:

a) Open FCV-122. CHG FLOW. as necessary to maintain PZR level b) IF PZR level continues to decrease, THEN reduce Letdown to one 45 gpm orifice:

1) Set PVT-145, LO PRESS LTON. LTDN. To 70%

2) Ensure PVT-8149A. LTON LTDN ORIFICE A ISOL. is open.

3) Close both PVT-8149B(

PVT-8149B(C). C). LTDN LTON ORIFICE B(C)

ISOL.

4) Adjust PCV-145. LO PRESS LTDN. LTON. to maintain P1-145.

PI-145. LO PRESS LTDN LTON PRESS PSIG. Between Between 300 psig and 400 psig.

5) Place PCV-145, LO PRESS LTDN. LTON. in AUTO.

22 Check ifif SI 51 is required:

a. Check Check ifif any any ofof the following criteria are are met:

met:

.* PZR PZR level is decreasing level is decreasing with with Charging Charging maximized maximized and and Letdown Letdown minimized.

minimized.

.* PZR level is PZR level is approaching 12%. 12%.

.* PZR pressure PZR pressure is is approaching approaching 1870 1870 psig.

psig.

.* VCT VCT level is approaching level is approaching 5% 5%

b.b. Perform Perform the the following:

following:

1)

1) Trip the Reactor.

Trip the Reactor.

2)2) GO GO TO TO EOP-1 EOP-1.0. .0. REACTOR REACTOR TRIP/SAFET TRIP/SAFETY Y INJECTION INJECTION ACTUATIO ACTUATION. N. WHEN WHEN EOP-1.O EOP-1.0 Immediate Immediate Actions Actions are are complete, THEN actuate complete, THEN actuate SI. SI.

Appendix Appendix D, 0, Page Page 3939 ofof 39 39

Scenario Event Scenario Event Description Description VC VC Summer-2005-301 Summer-2005-301 Op-Test No.:

Op-Test No.: Scenario No.:

Scenario No.: Event No.:

Event No.: Page Page _ _ of of _ _

Description:

Event

Description:

Event Time Time Position Position Applicants Applicants Actions or or Behavior Behavior Crew should transition to EOP-1.

Crew EOP-1.O.O. The first 5 steps are The first immediate operator actions.

immediate A Train of SI SI will fail fail to actuate in in BOTH BOTH ManualManual and and Individual components can be manually started.

Automatic. Individual Reactor will NOT trip in Automatic. Reactor can be tripped manually from the BOP side MCB Switch.

1I Verify Reactor Trip:

. Trip the Reactor using either Reactor Trip

. Verify all Reactor Trip and Bypass Breakers are open.

. Verify all Rod Bottom Lights are lit.

. Verify Reactor Power level is decreasing.

TurbinelGenerator Trip:

2 Verify Turbine/Generator

a. Verify all Turbine STM STOP VL VLVs Vs are closed.

b. Ensure Generator Trip (after 30 second delay):

1) Ensure the GEN BKR is open.

2) Ensure the GEN FIELD BKR is open.

3) Ensure the EXC FIELD CNTRL is tripped.

3 Verify both ESF buses are energized.

4 Check if SI is actuated:

SI may have actuated by this time. Step 5 is the final immediate action.

a. Check if either:

. SI ACT status light is bright on XCP-6107 XCP-61 07 1-1 1-1..

OR

.* Any red first-out SI annunciator is lit on XCP-626 top row.

(If no SI then: GO TO Step 5.)

b. Actuate SI using either SI ACTUATIOACTUATION N Switch.

c.

c. GO GO TOTO Step Step 6.6.

66 Initiate Initiate ATTACHME ATTACHMENT 3, SI NT 3, SI EQUIPMEN EQUIPMENT T VERIFICAT VERIFICATION.

ION.

The B "B" Charging Charging pump fails to automatically start start on on SI.

S/.

The operator operator is expected to attempt attempt to to manually manually start B "B" Charging Charging pump pump andand it will start.

start.

Appendix Appendix D, D, Page Page 39 of 39 39 of 39

Scenario Event Scenario Event Description Description VC VC Summer-2005-301 Summer-2005-301 Op-Test No.:

Op-Test No.: Scenario No.:

No.: - - - - EventEvent No.:

No.: Page Page _ _ of of _ _

- - - Scenario ---

Event Event

Description:

Time Time Position Position Applicants Actions Applicants Actions or or Behavior Behavior I 77 Announce plant conditions conditions over over the page system.

8 Verify RB pressure has remained LESS THAN 12 psig on PR-951, RB PR-951, RB PSIG PSIG (P-951), red red pen.

pen.

8 Perform the following:

a) Verify both the following annunciators are lit:

XCP-612 3-2 (RB SPR ACT).

XCP-612 4-2 (PHASE B ISOL).

IF either annunciator is NOT lit, THEN actuate RB Spray by placing the following switches to ACTUATE:

CS-SGA11 and CS-SGA2.

Both CS-SGA OR

Both CS-SGB1 and CS-SGB2.

b) Verify Phase BB Isolation by ensuring RB SPRAY/PHASE B ISOL monitor lights are bright on XCP-61 XCP-6105.

05.

c) Ensure the following are open:

MVG-3001A(B), RWST TO SPRAY PUMP A(B) SUCT.

MVG-3002A(B), NAOH TO SPRAY PUMP A(B) SUCT.

MVG-3003A(B), SPRAY HDR ISOL LOOP A(B).

d) Ensure both RB Spray Pumps are running.

e) Verify RB Spray Spray flow is GREATER THAN 2500 gpm for each operating train on:

Fl-7368, FI-7368, SPR PP A DISCH FLOW GPM.

FI-7378, FI-7378, SPR SPR PPPP BB DISCH DISCH FLOW FLOW GPM.

GPM.

f) Stop all RCPs.

Stop all RCPs.

99 Check RCS temperature:

Check RCS temperature:

With any RCP With any running, RCS Rep running, RCS Tavg Tavg is is stable at OR stable at OR trending to 557:F.

trending to 557:F.

Appendix Appendix D,D, Page Page 3939 of of 39 39

Scenario Event Scenario Event Description Description VC Summer-2005-301 VC Summer-2005-301 Op-Test No.:

Op-Test No.: Scenario No.:

Scenario No.: No.: - - - - - Page Event No.: Page _ _ of of _ _

Event Event Event

Description:

Time Time Position Position Applicants Actions Applicants Actions oror Behavior Behavior OR OR

With no RCP running, RCS Tcold is stable at OR 557Fc) trending to 557"Fc) 9 IFIF RCS RCS temperature is LESS THAN 557"F 557F AND decreasing, THEN:

CNTRLController in MAN and a) Place the STM DUMP CNTRLControlier Closed b) Place the STM DUMP MODE SELECT Switch in STM PRESS.

c) Ensure all Steamline PORVs and Condenser Steam Dumps are closed.

d) IF RCS cooldown continues, THEN:

1) IF Narrow Range SG level is LESS THAN 30%

[50%] in all SGs, THEN reduce EFW flow as necessary to stop the cooldown, while maintaining total EFW flow GREATER THAN 450 gpm.

2) WHEN Narrow Range SG level is GREATER THAN 30% [50%] in at least one SG, THEN control EFW flow as necessary to stabilize RCS temperature at 557F.

557"F.

e) IF RCS cooldown continues, THEN close:

MS Isolation Valves, PVM-2801A(B)(C).

MS Isolation Bypass Valves, PVM-2869A(B)(C).

IF RCS temperature is GREATER THAN 557F 557"F AND increasing, THEN:

a) Verify PERMISV C-9 status light is bright on XCP-61 light is XCP-611414 1-3.

1-3.

b) IF b) IF the Condenser is is available, available, THEN THEN ensure ensure Condenser Condenser Steam Steam Dump Dump Valves Valves are are open.

open.

c) IF c) the Condenser IF the Condenser is NOT available, is NOT available, THEN THEN open open the the Steamline Steam line PORVs, PCV-2000(201 0)(2020):

PCV-2000(2010)(2020):

1)

1) Place the PWR Place the PWR RELIEF RELIEF A(B)(C)

A(B)(C) SETPT SETPT Controllers Controllers in in MAN MAN and closed.

and closed.

Appendix Appendix D, D, Page Page 3939 of of 39 39

Scenario Event Scenario Event Description Description VCVC Summer-2005-301 Summer-2005-301 Op-Test No.:

Op-Test No.: Scenario No.:

Scenario No.: Event No.:

Event No.: Page _ _ of Page of _ _

Event

Description:

Event

Description:

Time Time Position Position Applicants Actions Applicants Actions or or Behavior Behavior

2) Place the Steamline Power Relief A(B)(C) Mode Switches in PWR RLF.

3) Adjust the PWR PWR RELIEF RELIEF A(B)(C) SETPT Controllers as necessary to reduce RCS temperature.

10 Check PZR PORVs and Spray Valves:

a. PZR PORVs are closed.

b. PZR Spray Valves are closed.

c. Verify power is available to at least one PZR PORV Block Valve:

. MVG-8000A, RELIEF 445 A ISOL.

. MVG-8000B, RELIEF 444 B ISOL.

. MVG-8000C, RELIEF 445 B ISOL.

d. Verify at least one PZR PORV Block Valve is open ..

open..

11 Check if RCPs RCP5 should be stopped:

a. Check if either of the following criteria is met:

.* Annunciator XCP-612 4-2 is lit (PHASE B ISOL) ISOL)..

OR

.* RCS pressure is LESS THAN 1400 1400 psig AND SI flow is indicated on FI-943, CHG LOOP B CLD/HOT LG FLOW GPM.

b. Stop all RCPs.

Conditions are probably not met for securing any RCPs.

GO TO Step 12.

Examiners may end exam at this point.

Appendix D, Appendix D, Page Page 39 39 of of 39 39

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