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| number = ML101610660
| number = ML101610660
| issue date = 03/28/2010
| issue date = 03/28/2010
| title = Summer 2005-301 Final Simulator Scenarios (Section 10)
| title = 301 Final Simulator Scenarios (Section 10)
| author name =  
| author name =  
| author affiliation = NRC/RGN-II
| author affiliation = NRC/RGN-II
Line 16: Line 16:


=Text=
=Text=
{{#Wiki_filter:Appendix 0 Facility:
{{#Wiki_filter:Appendix 0D Appendix                                                    Scenario Outline Scenario        Outline                                            Form Form ES-O-1 ES-D-1 Final Final Facility:
V. C. Summer Examiners:
Facility:    V. C.
Initial Conditions:
V. C. Summer Summer                               Scenario No.:
100% IC, AT MOL. Scenario Outline Final Scenario No.: 1 Operators:
Scenario     No.:             11            Op-Test No.:
Op-Test No.: Form ES-O-1 2005-301 CRS RO PO Turnover:
Op-Test     No.:   2005-301 2005-301 Examiners:
Thunder storms in the area, severe weather check list being implemented. "A 1" train maintenance week. S/G A Small tube leak, approx. 8 gpd; MAL-RCS002A.
Examiners:                                                                Operators:
Motor Driven EFW Pump 'A' Impeller replacement in progress with 48 hours to complete, have done 12 hours so far. B S/G rad monitor (RMG-19B) is OOS. Event Event Type*
Operators:                                                        CRS CRS RO RD PO PD Initial Conditions:
Event Description No. 1 RO (I) Turbine Impulse Pressure Transmitter PT-446 Fails Low. 2 BOP (I) Steam Generator Steam Flow Transmitter Failure, 474 fails LOW. RO (C) VCT suction valve 115C fails closed (hot short at motor). This will cause the 3 SRO (TS) running Charging pump to cavitate and fail requiring entry into AOP-1 02.2 BOP(N) and TS evaluation of loss of one CCP. 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. RO (R) Reduce power to take the unit off line. In accordance with GOP-4B Power 5 BOP (N) Operation Mode 1 (Descending Power). MDS calls and requests that due to approaching severe thunderstorm he would like to increase the power descension rate to 1 %/min. BOP (C) During the Down power, the 0 FRV fails as is, this will cause the operator to 6 have to place the 0 FRV in manual and control the A SG in manual during the Shut Down. (AOP-21 0.1). 7 RO(C) SG Tube Leak on the "c" SG, ramping to approximately the output of the SRO(TS) existing charging pump(s). Ramp up over a 5 minute period. (AOP-112.2).
Initial  Conditions:    100% IC, 100%    IC, AT AT MOL.
M (All) S/G tube rupture on the C SG to full flow of a tube (600 gpm ramped in over 3 8 min), requires reactor trip. The Reactor will not trip (ATWS) (EOP-13.0, Entry, Response to Abnormal Nuclear Power Generation).
MDL.
BOP (C) When the reactor trips there is a Loss of power on the lOB emergency bus 9 due to the thunderstorm.
Turnover:
The Emergency Diesel generator does not start automatically.  
Turnover:        Thunder storms storms inin the  area, severe the area, severe weather weather check check listlist being being implemented.
.. (N)ormal, (R)eactlvlty, (I)nstrument, (C)omponent, (M)aJor Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 1 Page --L of 2Q.. Event
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 hours to complete, have done 12 hours 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)
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:==
== 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 hours, 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


Turbine Impulse Pressure Transmitter PT-446 Fails Low. Time Position Applicant's Actions or Behavior AOP-401.7 RO Operator acknowledges annunciator 6152-5 (RCS TAVG-TREF DEV HI/LO), recognizes IPT0446 failure, and responds lAW AOP-401.7 RO Place ROD CNTRL BANK SEL Switch in MAN. RO Ensure TREF 1 ST STG PRESS Switch is positioned to the operable channellPT0447, CH IV). RO Adjust Control Rods until Tavg is within I.O°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 status light dim). RO c. Verify Tavg is within I.O°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).
Appendix D Appendix  D                                Required Operator Required   Operator Actions Actions                                  Form Form ES-D-2 ES-D-2 Op Test Op      No.:
BOP Place STM DUMP MODE SELECT in STM PRESS. BOP Notify I&C to place AMSAC in BYPASS Within 6 hours, place the failed channel bistables in a tripped condition.
Test No.:   11    Scenario No.:
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 Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 2 Page 3 of ..1.2.--Event
Scenario   No.: 11  Event No.:
Event No.:   22                                      Page Page
                                                                                                        - 33    of of ..1.2.-
20 Event


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


Steam Generator Steam Flow Transmitter Failure, 474 fails LOW. Time Position Applicant's Actions or Behavior AOP-401.3 BOP The BOP operator acknowledges annunciator 624 4-4 in alarm, recognizes the failure of IFT0474 and responds lAW AOP-401.3 BOP Depending on response time, annunciator 6241-5 (SG A LVL DEV) may also alarm. BOP Verify the failed channel is the controlling channel. Select the operable flow channel: BOP Place FW CONTROL CHANNEL SEL Switch to the operable channel. Place STEAM CONTROL CHANNEL SEL Switch to the operable channel. Verify Turbine Load is LESS THAN 950 MWe. Preferred is % turn on limiter. Using any method available, reduce Turbine Load by 40 MWe to 50 BOP MWe. (The preferred method is Yz turn on the load limiter) (The crew 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).
Event
Expected plant response = rods step in and Group 1 steam dumps open. BOP Verify only one SG is AFFECTED.
BOP Adjust the Feedwater Flow Control Valve as necessary to restore 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 SGs is normal. Restore the AFFECTED SG control systems to normal: BOP Place the Feedwater Flow Control Valve in AUTO. Place the Feedwater Pump Speed Control System in AUTO. REFER TO SOP-210, FEEDWATER SYSTEM. SRO Within six hours, place the failed channel protection bistables in a tripped condition:
SRO evaluates Tech Spec Table 3.3-3 Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 3 Page of .2Q.. Event


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


VCT suction valve 115C fails closed (hot short at motor). This will cause the running Charging pump to cavitate and fail requiring entry into AOP-102.2 and TS evaluation of loss of one CCP. Time Position Applicant's Actions or Behavior AOP*102.2 Operator acknowledges that annunciators 614 4-2 (CHG PP B/C TRIP), RO 6145-1 (CHG LINE FLO HI/LO), 6172-2,6182-2, & 619 2-2 (RCP A, B, C #1 SEAL INJ FLO LO) are all in alarm, recognizes the "B" Charging Pump has tripped, and responds lAW AOP-102.2 Check if Charging Pump flow is normal: IF Charging Pump has tripped or flow is abnormal, THEN perform the following:
Steam Generator Steam            Steam Flow Generator Steam      Transmitter Failure, Flow Transmitter Failure, 474 474 fails fails LOW.
o Ensure the Charging Pump is secured. o Close all Letdown Isolation Valves: PVT-8149A(B)(C), LTDN ORIFICE A(B)(C) ISOL. PVT-8152, LTDN LINE ISOL. RO LCV-459, L TDN LINE ISOL. LCV-460, L TDN LINE ISOL. (Expected plant response = RML*1 alarm on Letdown Isolation.)
LOW.
o Close FCV-122, CHG FLOW. o Verify CCW flow to the RCP Thermal Barriers is GREATER THAN 90 gpm on FI-7273A(B), THERM BARR FLOW GPM. n Display Dedicated Display ZZRCPBRG on the IPCS to monitor RCP temperatures. (RML-1 expected alarm -letdown isolation.)
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.
CRS/SE o Contact Electrical and Mechanical Maintenance to investigate.
BOP        Verify the failed channel is the controlling channel.
Verify Charging System valve lineup: RO o IF Charging Pump suction is aligned to the VCT, THEN ensure both LCV-115C(E), VCT OUTLET ISOL, are open. CRS/SE Send someone to locally open the breaker for valve 115C and then to manually open the valve. SRO SRO evaluates Tech Spec 3.5.2 and determines 72 hr. action statement.
Select the operable flow channel:
o Ensure the following valves are open: MVG-81 06, CHG PP. MVT-8109A(B)(C), CHG PP A(B)(C). RO MVG-8130A(B), LP A SUCT TO CHG PP c. MVG-8131A(B), LP B SUCT TO CHG PP c. MVG-8132A(B), CHG PP C TO LP A DISCH. MVG-8133A(B), CHG PP C TO LP B DISCH o Check the Charging header valve lineup as follows: RO Ensure MVG-81 07, CHG LINE ISOL, is open. Ensure MVG-8108, CHG LINE ISOL, is open. Ensure FCV-122, CHG FLOW, is in MAN and CLOSE. RO Ensure the following valve is open:
Place FW CONTROL CHANNEL SEL Switch to the operable channel.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 3 Page 5 of .22-Event
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:==
== Description:==


VCT suction valve 115C fails closed (hot short at motor). This will cause the running Charging pump to cavitate and fail requiring entry into AOP-102.2 and TS evaluation of loss of one CCP. Time Position Applicant's Actions or Behavior PVT-8147, ALT CHG TO RCS LP A. D Locally verify Charging Pump suction pressure is between 50 psig BOP and 100 psig as indicated on the following (building operator to report 52 psig): PI-151A, SUCTION PRESS, for Charging Pump A. With Shift Supervisor's permission, start a Charging Pump, while RO monitoring RCP temperatures.
Event
REFER TO SOP-102, CHEMICAL AND VOLUME CONTROL SYSTEM. (SEE SOP 102 section III.B below) WHEN a Charging Pump is operating, THEN place Charging and RO Normal Letdown in service .. REFER SOP-102, CHEMICAL AND VOLUME CONTROL SYSTEM. (SEE SOP-102 Section IV.M below) SOP-102 Section III.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" charging pump to "B" Train. (If SRO the crew chooses, they might start "A" CCW pump and "A" charging pump to get a charging pump back while they are waiting to get "C" charging pump racked up on "B" Train. If so the steps below are nearly identically except for "A" Train component numbers) RO To start XPP-0043C, PUMP C, on miniflow, complete Attachment VB if 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:
Building 1) L9004A, CHILLED WATER EXPANSION TNK A LV, or ILl09004-VU, CHILL WATER EXP TK A LEVEL IND (IB-412).
: 2) L9006A, CHILLED WATER EXPANSION TNK B LV, or ILl09006-VU, CHILL WATER TK B LEVEL IND (IB-412).
Verify PI-121, CHG PRESS PSIG, is between 2650 psig and 2850 psig. Monitor the following for proper pump operation:
RO a. LR-459, PZR % LEVEL & LEVEL SP. b. FI-130A, RCP A INJ FLO GPM. c. FI-127A, RCP B INJ FLO GPM. d. FI-124A, RCP C INJ FLO GPM. RO Ensure the B train of Component Cooling is operating per SOP-118. RO Ensure the B train of Chill Water is operating per SOP-501. RO Ensure XPP-43C-PP1, CHG PP C AUX OIL PP, is running. Building Verify IP100153A, CHG PUMP C SUCT HDR PRESS IND, indicates Appendix 0 Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 3 Page 6 of 2Q.. Event


== Description:==
== 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:


VCT suction valve 115C fails closed (hot short at motor). This will cause the running Charging pump to cavitate and fail requiring entry into AOP-102.2 and TS evaluation of loss of one CCP. Time Position Applicant's Actions or Behavior pump suction pressure is greater than 15 psig (AB-388).
Appendix DD Appendix                                          Required Operator Required      Operator Actions Actions                                         Form Form ES-D-2 ES-D-2 Op Test Op  Test No.:
RO Start XPP-0043C, PUMP C. (PEER D) RO Verify XPP-43C-PP1, CHG PP C AUX OIL PP, stops automatically when the Charging Pump comes up to full speed. Building Verify IP100153A, CHG PUMP C SUCT HDR PRESS IND, indicates pump suction pressure is greater than 15 psig (AB-388).
No.:   11      Scenario No.:
Monitor the following to verify proper pump operation:
Scenario    No.:   11    Event No.:
: 1) Charging Pump C running current is between 30 amps and RO 50 amps. 2) PI-121, CHG PRESS PSIG, is between 2650 psig and 2850 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. RO Place PCV-145, LO PRESS LTDN, in MAN and open to 70%. (PEER D) RO Place TCV-144, CC TO L 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:
Event     No.:   33                                            Page Page       55    of of .22-20 Event
RO a. LCV-459, L TDN LINE ISOL. b. LCV-460, L TDN LINE ISOL. Ensure the following Charging Line Isolation Valves are open: RO a. MVG-8107, CHG LINE ISOL. b. MVG-8108, CHG LINE ISOL. RO Slowly open FCV-122, CHG FLOW, to establish 60 gpm flow as indicated on FI-122A, CHG FLOW GPM. Open Orifice Isolation Valves to obtain the desired Letdown flow rate (60 gpm to 120 gpm): RO 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). Adjust FCV-122, CHG FLOW, as required to maintain TI-140, REGEN RO HX OUT TEMP of, between 250°F and 350°F while maintaining Pressurizer level. RO Adjust PCV-145, LO PRESS LTDN, to maintain PI-145, LO PRESS L TDN PRESS PSIG, between 300 psig and 400 psig.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 3 Page --1-of .22..-----Event


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


VCT suction valve 115C fails closed (hot short at motor). This will cause the running Charging pump to cavitate and fail requiring entry into AOP-102.2 and TS evaluation of loss of one CCP. Time Position Applicant's Actions or Behavior RO Place PCV-145, LO PRESS LTON, in AUTO. Adjust TCV-144, CC TO LTON HX, potentiometer as necessary to RO maintain the desired VCT temperature and place in AUTO. Refer to VCS Curve Book, Figure V11.15. RO When Pressurizer level matches reference level, place FCV-122, CHG FLOW, in AUTO per Section IV. RO After the Letdown temperatures have stabilized, place TCV-143, L TON TO VCT OR OEMIN, in OEMIN/AUTO.
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).
Can move on to next event when chg and letdown restored (no need to wait until level deviation cleared).
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 4 Page --L of 2Q.. ---Event
 
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 hours)
 
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:==
== Description:==


The building operator calis the control room and reports that, while on his rounds, he discovered a significant amount of oil on the floor in the TDEFP room and it appears that the governor may have leaked ali its oil onto the floor. Time Position Applicant's Actions or Behavior Building Building operator reports oil leak on TDEFP governor (FCV now). Crew determines TDEFP is inoperable and decides to remove it from service by taking both 2030 valve switches to the closed position.
Event
Both SRO/BOP annunciators 623 2-3 and 622 2-3 (TD EFP AUTOSTART DEFEATED) alarm as the 2030 valves close. (May also choose to disable the TDEFP by tripping the Trip & Throttle valve or by closing and removing power from 2802A & 2802 B). SRO SRO evaluates Tech Spec 3.7.1.2 and determines that a plant shutdown is necessary (Hot Standby within 6 hours)
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 5 Page 9 of 2Q.. ------Event


== Description:==
== 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.


Reduce power to take the unit off line. In accordance with GOP-4B Power Operation Mode 1 (Descending Power). MDS calls and requests that due to approaching severe thunderstorm he would like to increase the power descension rate to 1 %/min. Time Position Applicant's Actions or Behavior GOP-4B Reduce load by one of the following methods: BOP 1) By use of the DEC LOAD RATE circuit 2) By use of the load limiter SRO MDS calls and requests that the load decrease be raised to 1 %/min because of approaching severe thunderstorm.
Appendix DD Appendix                                      Required Operator Required     Operator Actions Actions                                          Form Form ES-D-2 ES-D-2 Op Test Test No.:
As load decreases, adjust Megavars using GEN FIELD VOL T ADJ as BOP requested by the Load Dispatcher and within the Estimated Generator Capability Curve (Enclosure A). RO Maintain Tavg within the control band by Control Rod motion or boron concentration changes. Borate per SOP-106, 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)
No.:  11    Scenario No.:
: 1) within limits. 2) Control Rods above the Rod Insertion Limit.
No.:  11    Event No.:
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 6 Page...:!.Q...
No.:                                                                        ..lQ..
of ..lQ.. -Event
Op                  Scenario                  Event
                                                            - 66                                              Page    10 of Page...:!.Q... of     20 Event


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


During the Down power, the 0 FRV fails as is, this will cause the operator to have to place the 0 FRV in manual and control the A SG in manual during the Shut Down. (AOP-21 0.1). Time Position Applicant's Actions or Behavior AOP-210.1 As load decreases, BOP operator notices that FCV-0478 is failed as is and takes manual control of the valve lAW AOP-21 0.1. (Could possibly BOP receive annunciator 624 1-5 SG A L VL DEV.) Crew may also decide to conservatively stop the load reduction 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.
Event
Manually adjust the AFFECTED Feedwater Flow Control Valve as necessary to maintain Narrow Range SG level between 60% and 65%: BOP o PVT-478, SG A FWF. o PVT-488, SG B FWF. o PVT-498, SG C FWF. SRO Dispatch I&C to determine cause of auto control failure.
Appendix 0 Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 7 Page 11 of 20 -Event


== Description:==
== 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.


SG Tube Leak on the "e" SG, ramping to approximately the output of the existing charging pump(s). Ramp up over a 5 minute period. (AOP-112.2).
Appendix 0D Appendix                                        Required Operator Required      OperatorActions Actions                                     Form Form ES-D-2 ES-D-2 Op Test Op  Test No.:
Time Position Applicant's Actions or Behavior RO RO acknowledges that annunciator 6462-1 (MN STM LINE RMG-19 HI RAD) is in alarm and pulls the ARP. RO Verify the alarm is valid and identify the Main Steam line affected by observing RM-G19A, B, and C and RlR-8. SRO Request Health Physics perform radiological surveys around the Main Steam lines. SRO Direct Chemistry to sample all Steam Generators for activity.
No.:  11    Scenario No.:
Align the condenser exhaust to the Auxiliary Building Charcoal Exhaust as follows: Building a. Open XVB0011O-AR, MN&AUX COND VAC PP CHAR EXH DISCH VALVE (TB-436).
Scenario  No.:    11      Event No.:
: b. Close XVB00109-AR, MN&AUX COND VAC PUMP ATMOS DISCH VALVE (TB-436).
Event    No.:    77                                          Page Page
BOP Reduce all Steam Generator blowdown flows to minimum. SRO If the alarm is valid, refer to AOP-112.2.
                                                                                                                    - 1111 of of
AOP-112.2 (approx 90% power) 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:
20 20 Event
: a. Open FCV-122, CHG FLOW, as necessary to maintain PZR level 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. BOP The tube leak may eventually cause annunciator 624 3-5 (SG C LVL DEV) to alarm (expected alarm). Reduce Letdown to one 45 gpm orifice. a) Set PCV-145, LO PRESS LTDN, to 70%. b) Ensure PVT-8149A, LTDN ORIFICE A ISOL, is RO c) Close both PVT-8149B(C), LTDN ORIFICE B(C) ISOL. d) Adjust PCV-145, LO PRESS LTDN, to maintain PI-145, LO PRESS L TDN PRESS PSIG, between 300 psig and 400 psig. e) Place PCV-145, LO PRESS LTDN, in AUTO. IF PZR level continues to decrease, THEN perform the following RO Close PVT-8149A, LTDN ORIFICE A ISOL. RML-1 should alarm due to letdown isolation (expected alarm) SRO Check if 51 is required At some point near this step Pressurizer Pressure will drop below the Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 7 Pag e...1L of .22.. --Event


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


SG Tube Leak on the "C" SG, ramping to approximately the output of the existing charging pump(s). Ramp up over a 5 minute period. (AOP-112.2).
Event
Time Position Applicant's Actions or Behavior Tech Spec 3.2.5 DNB value of 2206#. The SRO should evaluate and verbalize the 2 hr. LCO RO Verify VCT level is being maintained between 20% and 40%. Estimate the RCS leak rate using IPCS CHGNET. Calculate the RCS leak rate. lAW STP-114.002, OPERATIONAL LEAK SRO/SE TEST. Comply with Tech Spec 3.4.6.2 action statement.
Determines that shutdown to mode 3 within 6 hours is required Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 8 Page.....:!1...
of 2Q.. Event


== Description:==
== 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


S/G tube rupture on the C SG to full flow of a tube (600 gpm ramped in over 3 min), requires reactor trip. The Reactor will not trip (ATWS) (EOP -13.0, Entry, Response to Abnormal Nuclear Power Generation).
Appendix DD Appendix                                      Required Operator Required      Operator Actions Actions                                    Form Form ES-D-2 ES-D-2 Op  Test No.:
Time Position Applicant's Actions or Behavior Tube rupture 600 gpm ramp over 3 min after Tech Spec eval. Acknowledges annunciator 616 1-5 (PZR LCS DEV HIILO and responds lAW direction of CRS or if time allows lAW ARP. SRO CRS directs the RO to insert a manual reactor trip and that they will actuate SI when directed by EOP-1.0 EOP-13.0 RO Verify Reactor Trip: Trip the Reactor using both Reactor Trip Switches.
Op Test  No.:   11    Scenario No.:
RO IF the Reactor will NOT trip OR is NOT subcritical, THEN insert Control Rods at the fastest control rod insertion rate CRITICAL SRO Direction given to trip the reactor locally using Attachment 1 Follow-up question -may ask SRO to classify this emergency event (Site Area Emergency)
Scenario  No.:
Verify Turbine/Generator Trip: BOP Verify all Turbine STM STOP VLVs are closed. Depress Emerg Trip Sys TRIP. Ensure Generator Trip I (after 30 second delay) BOP 1) Ensure the GEN BKR is open. 2) Ensure the GEN FIELD BKR is open. 3) Ensure the EXC FIELD CNTRL is tripped. Ensure EFW Pumps are running: BOP starts "B" EFW Pump (It has BOP not auto started because SG level is not yet below 35% and SI has probably not yet actuated.)
                                    -- 11      Event No.:
Initiate emergency boration of the RCS: Ensure at least one Charging Pump is running. Verify PZR pressure is LESS THAN 2335 psig. RO Verify SI ACT status light is NOT lit. Verify SI flow on FI-943, CHG LOOP B CLD/HOT LG FLOW GPM. GO TO Step 5. Observe the CAUTION prior to Step 5. (Emergency boration is not required if SI has actuated by this point and SI flow is verified)
Event   No.:   77                                          Page Pag  e ...1L 12  of of .22..
Building Operator locally trips the RTBs at this point. Building Verify all Reactor Trip and 'Bypass Breakers are open. Verify all Rod Bottom Lights are lit. Verify Reactor Power level is decreasing.
20 Event
5 Verify Containment Ventilation Isolation Valves closed by RO verifying the Safety INJECTION monitor lights are dim, (Time permitting, perform EOP-1.0 steps 1 -8 in conjunction with this Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 8 Page --2i. of 22.. ----Event


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


S/G tube rupture on the C SG to full flow of a tube (600 gpm ramped in over 3 min), requires reactor trip. The Reactor will not trip (ATWS) (EOP -13.0, Entry, Response to Abnormal Nuclear Power Generation).
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.
Time Position Applicant's Actions or Behavior procedure)
period. (AOP-112.2).
Appendix 0 Required Operator Actions Form ES-O-2 Op Test No.: --L Scenario No.: 1 Event No.: 9 Page ....:!.?.
(AOP-1 12.2).
of 2Q.. Event
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 hours 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:==
== Description:==


When the reactor trips there is a Loss of power on the lOB emergency bus due to the thunderstorm.
Event
The Emergency Diesel generator does not start automatically.
Time Position Applicant's Actions or Behavior BOP operator notes that there is no power on IDB and that the diesel did BOP not start. He notes that there is a lockout on XFMR-XTF31 (by recognizing annunciator 639 4-2 in alarm). BOP operator also notes that annunciator 6376-1 (DG B ENG START FAIL) is in alarm BOP operator depresses the "B" DG Emergency Start Pushbutton and BOP notes that the diesel does start and the DG breaker does close to energize 1 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 Verify Reactor Trip: Trip the Reactor using either Reactor Trip Switch. RO Verify all Reactor Trip 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. BOP Ensure Generator Trip (after 30 second delay): Ensure the GEN BKR is open. Ensure the GEN FIELD BKR is open. 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 CNDSR EXH RM-A9 HI RAD should come in and is an expected alarm with a tube rupture. Check if 51 is actuated:
RO Check if either SI ACT status light is bright on XCP-6107 1-1 or Any red first-out SI annunciator is lit on XCP-626 top row. Actuate SI using either SI ACTUATION Switch. Complete ATTACHMENT 3,51 EQUIPMENT VERIFICATION. (If not BOP already done, the BOP operator should be throttling EFW flow to zero to the "C" SG because it has been identified as the ruptured SG).OAP-103.4 SRO Announce plant conditions over the page system. RO Verify RB pressure has remained LESS THAN 12 psig on PR-951, '
Appendix 0 Required Operator Actions Form ES-D-2 Op Test No.: --L Scenario No.: 1 Event No.: 9 Page of 2Q... Event


== Description:==
== 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


When the reactor trips there is a Loss of power on the lOB emergency bus due to the thunderstorm.
Appendix DD Appendix                                        Required Operator Required      OperatorActions Actions                                      Form Form ES-D-2 ES-D-2 Op Test  No.:
The Emergency Diesel generator does not start automatically.
Test No.:          Scenario No.:                                                                                    --2i.        22..
Time Position Applicant's Actions or Behavior RB PSIG (P-951), red pen. Check RCS temperature:
Op
With any RCP running, RCS Tavg is stable at OR trending to 55rF. BOP 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 55rF. Check PZR PORVs and Spray Valves: PZR PORVs are closed. PZR Spray Valves are closed. RO 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. 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 LG FLOW GPM. Note: RCS pressure should be about 1800 psig so no RCP trip should be required.
              - 11    Scenario    No.:
Verify no SG is FAULTED: BOP No SG pressure is decreasing in an uncontrolled manner. No SG is completely depressurized.
                                        - 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:
Verify Secondary radiation levels indicate SG tubes are NOT RUPTURED:
RO RM-G19A(B)(C), STMLN HI RNG GAMMA. RM-A9, CNDSR EXHAUST GAS ATMOS MONITOR. RM-L3, STEAM GENERATOR BLOWDOWN LIQUID MONITOR. RM-L 10, SG BLOWDOWN CW DISCHARGE LIQUID MONITOR. CRITICAL SRO GO TO EOP-4.0, STEAM GENERATOR TUBE RUPTURE, Step 1. Check if RCPs should be stopped: Check if either of the following criteria is met: Annunciator XCP-612 4-2 is lit (PHASE B ISOL). RO OR RCS pressure is LESS THAN 1400 psig AND SI flow is indicated on FI-943, CHG LOOP B CLD/HOT LG FLOW GPM. Note: RCS pressure should be about 1800 psig so it should not be necessary to secure any RCPs SRO Identify the RUPTURED SG(s):
RM-G19A(B)(C), STMLN HI RNG GAMMA.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: ......L. Scenario No.: _1_ Event No.: ..L Page ..JL of .2Q.. Event
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:==
== Description:==


When the reactor trips there is a Loss of power on the lOB emergency bus due to the thunderstorm.
Event
The Emergency Diesel generator does not start automatically.
Time Position Applicant's Actions or Behavior Narrow Range level in any SG increasing in an uncontrolled manner, OR High Radiation on any of RM-G19A(B)(C), STMLN HI RNG GAMMA, OR Local hand held radiation monitor readings taken by Health Physics on the blowdown lines at following penetrations:
XRP0326, SG A Blowdown Line (AB-412 West Pen). XRP0224, SG B Blowdown Line (IB-412 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 line PWR RELIEF A(B)(C) SETPT Controller(s) in MAN and closed. BOP Adjust the PWR RELIEF A(B)(C) SETPT Controller(s) to 8.85 (1150 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. BOP WHEN RCS Tavg is LESS THAN P-12 (552°F), THEN place both STM DUMP INTERLOCK Switches to BYP INTLK. BOP Verify the Steamline PORV closed. BOP IF at least one MD EFW Pump is running, THEN isolate the TD EFW Pump by placing PVG-2030, STM SPL Y TO TD EFP to CLOSE. Open XMC1DB2Y 05EH, EMERG FEEDWATER PUMP MAIN STEAM BOP/Bldg BLOCK XVG2802B-MS (AB-463).
Close XVG02802B-MS, MS HEADER C EF PUMP TURBINE SUPPL Y VLV Close the following for each RUPTURED SG: BOP SG Blowdown, PVG-503A(B)(C).
MS Drain Isolation, PVT-2843A(B)(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).
Verify Narrow Range level in each RUPTURED SG is GREATER THAN 30% [50%]. BOP a. Stop EFW flow to each RUPTURED SG: 1) Close FCV-3551, MD EFP TO SG C. 2) Close FCV-3556, TD EFP TO SG C. 3) Maintain Narrow Range level in C SG GREATER THAN 40% [50%]. BOP/SRO Verify each RUPTURED SG pressure is GREATER THAN 350 psig. SRO Determine the required core exit TC temperature for RCS cooldown.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 9 Page ---2!L of 22-Event


== Description:==
== 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.


When the reactor trips there is a Loss of power on the lOB emergency bus due to the thunderstorm.
Appendix DD Appendix                                          Required Operator Required        Operator Actions Actions                                          Form Form ES-D-2 ES-D-2 Op  Test No.:
The Emergency Diesel generator does not start automatically.
Op Test  No.:  11    Scenario No.:
Time Position Applicant's Actions or Behavior SRO/RO Check if any RCP is running (all running).
Scenario  No.:    11      Event No.:
Dump steam from each INTACT SG: WHEN RCS Tavg is LESS THAN P-12 (552"F), THEN: Place both STM DUMP INTERLOCK Switches to BYP INTLK. Place both STMLN SI TRAIN A(B) Switches to BLOCK. BOP Verify PERMISV C-9 status light is bright on XCP-6114 1-3. Verify the MS Isolation to open.Valves, PVM-2801A & B are open Place the STM DUMP CNTRL Controller in MAN Place the STM DUMP MODE SELECT Switch in STM PRESS. Adjust the STM DUMP CNTRL Controller to fully open the Bank 1 Steam Dump Valves. RO While cooling down, a high vibration on "C" RCP may occur. If so, secure RCP "C" a required by SOP*101 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) Switches.
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:
Reset Containment Isolation:
RO RESET PHASE A -TRAIN A(B) CNTMT ISOL. RESET PHASE B -TRAIN A(B) CNTMT ISOL. Place both ESF LOADING SEQ A{B) RESETS to: BOP a. NON-ESF LCKOUTS. b. AUTO-START BLOCKS. Establish Instrument Air to the RB: RO a. Start one Instrument Air Compressor and place the other in Standby. b. Open PVA-2659, INST AIR TO RB AIR SERVo C. Open PVT-2660, AIR SPLY TO RB. RO Stop both RHR pumps SRO Verify core exit TC temperature is LESS THAN the value determined in Steps 8 through 10 Stop the RCS cooldown:
RO         RESET PHASE A - TRAIN A(B) CNTMT ISOL.
BOP a. Ensure Step 10 is completed.  
                                                              -                                ISOL.
: b. Adjust steam dump setpoints as necessary to maintain desired core exit TC temperature.
RESET PHASE BB - TRAIN A(B) CNTMT ISOL.
BOP Verify each RUPTURED SG pressure is stable OR increasing.
Place both ESF LOADING SEQ A(B)                      A{B) RESETS to:
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 9 Page ...:!2.. of 2Q.. Event
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:==
== Description:==
When the reactor trips there is a Loss of power on the lOB emergency bus due to the thunderstorm.
 
The Emergency Diesel generator does not start automatically.
Event
Time Position Applicant's Actions or Behavior RO/SRO Verify RCS subcooling on TI-499A(B), A(B) TEMP is GREATER THAN 50°F. Depressurize the RCS using Normal PZR Spray at the maximum rate: (PCV-444C should not be opened if "c" RCP has been secured in a previous step) CRITICAL Using RCP A: 1) Open PCV-444D, PZR SPRAY. RO 2) Close PCV-444C, PZR SPRAY, if RCP C is NOT running Using RCPs BAND C: 1) Open PCV-444C, PZR SPRAY. 2) Close PCV-444D, PZR SPRAY, if RCP A is NOT running. Use maximum available spray until anyone of the following criteria is met: PZR level is GREATER THAN 68% [54%]. OR RCS subcooling on TI-499A(B), A(B) TEMP "F, is LESS THAN 30"F. 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:
 
RO 1) Close both PCV-444C(D), PZR SPRAY. 2) Close PVT-8145, PZR SPRAY FR CVCS. Check if SI flow should be terminated:  
== Description:==
: a. RCS subcooling on TI-499A(B), is GREATER 30"F b. Secondary Heat Sink is adequate:
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.
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.  
automatically.
: d. PZR level is GREATER THAN 18% [38%]. RO Stop all but one Charging Pump and place in Standby. Establish Normal Charging:  
Time Time         Position Position                                           Applicants Actions Applicant's     Actions or or Behavior Behavior Verify RCS Verify    RCS subcooling subcooling on        on TI-499A(B),
: a. Close FCV-122, CHG FLOW. RO b. Open both MVG-8107 and MVG-81 08, CHG LINE ISOL. c. Adjust FCV-122, CHG FLOW, to obtain 60 gpm Charging flow. d. Close both MVG-8801A(B), HI HEAD TO COLD LEG INJ. RO Control FCV-122, CHG FLOW, to maintain PZR level. Verify SI flow is NOT required:
Tl-499A(B), A(B) A(B) TEMPTEMP is  is GREATER GREATER ROISRO RO/SRO          THAN 50°F.
RO a. RCS subcooling on TI-499A(B), is GREATER THAN '30"F. b. PZR level is GREATER THAN 18% [38%]. This is the endpoint of this JPM or as directed by the NRC.
THAN       50°F.
Appendix D Required Operator Actions Form ES*D*2 Op Test No.: 1 Scenario No.: 1 Event No.: 9 Page -2.£.. of 22------Event
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:==
== Description:==
When the reactor trips there is a Loss of power on the lOB emergency bus due to the thunderstorm.
The Emergency Diesel generator does not start automatically.
Time Position Applicant's Actions or Behavior 


Appendix D Facility:
Event
V. C. Summer Examiners:
 
Scenario Outline Final Scenario No.: 2 Operators:
== Description:==
Form ES-D-1 Op-Test No.: 2005-301 CRS RO PO Initial Conditions:
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.
At approximately 39% power and increasing.
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 in the area, severe weather check list being implemented. "A 1" train maintenance week. S/G A Small tube leak, approx. 8 gpd; MAL-RCS002A.
Turnover:          Thunder storms Thunder  storms in in thethe area, area, severe severe weather weather check check listlist being being implemented.
Motor Driven EFW Pump 'A' Impeller replacement in progress with 48 hours to complete, have done 12 hours so far. B S/G rad monitor (RMG-19B) is OOS. At the point of the GOP-4 Step 3.11.J when the second feed water pump is going to be placed in service. The crew is to place the B Main Feed Water Pump in service lAW SOP-210, Section III. Step 2.7.k Event Event Type*
implemented.
Event Description No. 1 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 SRO (TS) approximately 3 minutes from current position.
Al "A       train maintenance 1" train maintenance week.
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. 5 RO (I,R) Power Range Channel N44 failure high with the failure of the rods to move. SRO (TS) The rods will not move in any direction in Manual or Automatic.
week.
RO (R) Small steam leak occurs allowing determination of a required reactor shut 6 BOP (N) down. The crew may initiate a Rx Trip since Rods already will not move. SRO (N) When a trip Signal is inserted, the reactor will not trip. Large Steam Line Break occurs on the C Steam Generator upstream of the 7 All (M) MSIVs. "C" MSIV fails to shut automatically.
S/G AA Small S/G          Small tube tube leak, leak, approx.
The "c" feed water isolation valve does riot isolate automatically.
approx. 88 gpd;      MAL-RCSOO2A.
8 BOP (C) A Reactor Building Cooling Unit fails to start automatically.
gpd; MAL-RCS002A.
9 RO (C) 'B' Train Containment Spray pump fails to start automatically.
Motor       Driven EFW Motor Driven        EFW Pump Pump 'A'A Impeller Impeller replacement replacement in  in progress progress with with 4848 hours hours to to complete, complete, have have done done 12  12 hours hours so so far.
10 RO (I) Flow meter (FI-7368) for A Train of Containment Spray fails low. Actual spray is occurring.  
far.
.. (N)ormal, (R)eactlvlty, (I)nstrument, (C)omponent, (M)aJor Appendix 0 Required Operator Actions Form ES-D-2 Op Test No.: _1_ Scenario No.: 1 Event No.: 1 Page 2 of L Event
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:==


== Description:==
== 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.


The BOP will place the second feed water pump in service lAW SOP-210. Time Position Applicant's Actions or Behavior SOP-210 Place B FPT SPEED CONTROL in Cascade Mode as follows: 1) Increase the MASTER SPEED CNTRL (MCB mla station) in MAN until the Feed Pump speed demand, as indicated on SCY-509C, is between 4100 rpm and 5000 rpm (indicated on GRAPHIC 310 BOP screen only). (PEER D) 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. BOP Stop TPP22B-PP2, AUX OIL PP, and return the switch to AUTO. (PEER D) BOP Stop Feedwater Pump B TURN GEAR and return switch to AUTO. (PEER D) 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 SPEED BOP CNTRL (MCB MIA 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)
Appendix DD Appendix                                        Required Operator Required      Operator Actions Actions                                 Form Form ES-D-2 ES-D-2 Op Test Op  Test No.:
TURB DRN VLV (MCB). End of placing 2 nd FWP in service event.
No.:
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 2 Page _3_ of 2.L Event
                - 11    Scenario No.:
Scenario   No.:
                                      - 11    Event No.:
Event   No.:
                                                              - 22                                          Page Page --L 4      of of .1.1....
21 Event


== Description:==
== 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


Feedwater Flow transmitter (477) Failure, fails HIGH, with a slow ramp at approximately 3 minutes from current position.
== Description:==
Time Position Applicant's Actions or Behavior AOP 401.3 FT-477 STEAM FLOW FAILURE. Enter AOP-401.3.
 
First 7 steps are Immediate Operator Actions. FCV-478 will travel closed. Alarm XCP-624, 4-4 SG A FWF>STF MISMA TCH BOP 1 Verify the failed channel is the controlling channel. 2 Select the operable flow channel: BOP
minutes from minutes   from current current position.
* Place FW CONTROL CHANNEL SEL Switch to the operable channel.
position.
* Place STEAM CONTROL CHANNEL SEL Switch to the operable channel CRS/BOP 3 Verify Turbine Load is LESS THAN 950 MWe. CRS/BOP 4 Verify only one SG is AFFECTED.
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.
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 to between 60% and 65%. 7 Check if Feedwater Pump speed control is operating properly:
failure.
* Feedwater Header pressure is GREATER THAN Main Steam CRS/BOP Header pressure
CRS/SE CRS/SE          No  repair will No repair    will occur occur for     this event.
* Feed flow is normal for steam and flow and power level
for this  event.
* All operating Feedwater Pump speeds and flows are balanced CRS/BOP 8 Verify Narrow Range level in all SGs is normal. 9 Restore the AFFECTED SG control systems to normal: CRS/BOP
End of FT-477 failure failure event.
* Place the Feedwater Flow Control Valve in AUTO
 
* Place the Feedwater Pump Speed Control System in AUTO. REFER' TO SOP-210, FEEDWATER SYSTEM 10 Within six hours, place the failed' channel protection bistables in a ' tripped condition:
Appendix D Appendix  D                                  Required Operator Required     Operator Actions Actions                            Form Form ES-D-2 ES-D-2 Op Test No.:
: a. Identify the associated bistables for the failed channel. REFER TO ' Attachment
Op Test  No.: --L1    Scenario No.:
: 1. b. Record the following for each associated bistable on SOP-401, REACTOR PROTECTION AND CONTROL SYSTEM, CRS Attachment I:
Scenario No.:   11      Event No.:
* Instrument.
Event   No.:     33                                  Page Page   55  of of .1.:!....
* Associated Bistable.
21 Event
* Bistable Location.
* STPs. c. Notify the I&C Department to ' place the identified bistables in trip.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 2 Page --L of .1.1.... ---Event


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


Feedwater Flow transmitter (477) Failure, fails HIGH, with a slow ramp at approximately 3 minutes from current position.
Time Position Applicant's Actions or Behavior TS 3.3.1, Table 3.3-1, item 14 11 Determine and correct the cause of the channel failure. CRS/SE No repair will occur for this event. End of FT-477 failure event.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: --L Scenario No.: 1 Event No.: 3 Page 5 of .1.:!....
Event
Event


== Description:==
== 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.


Running EH pump trips. (Must manually start other pump) Time Position Applicant's Actions or Behavior ARP 6311-2 Running EHC pump trips event BOP A EHC Pump trips, Receives alarm XCP 631,1-2, EHC FLUID PRESS LO, BOP reviews ARP and hands to CRS. Crew mayor may not reference SOP-222 SWITCHOVER OF THE EHC PUMPS for starting the idle EHC pump. BOP/CRS Start the idle EHC pump. Verify the following:
Appendix D0 Appendix                                          Required Operator Required   Operator Actions Actions                                      Form Form ES-D-2 ES-D-2 Op  Test No.:
* Starting amps decay off within 30 seconds.
Op Test No.: _1_1    Scenario No.:
* The started pump discharge pressure is greater than 1550 psig BOP/CRS as indicated at the EHC unit by HFPM-A OUTPUT PRESSURE or HFPM-B OUTPUT PRESSURE.
Scenario No.:       11    Event No.:
* EHC header pressure is greater than 1550 psig as indicated by PI-5676, EHC FLUID PRESS PSIG. Place the previously running EHC pump switch in After-Stop.
Event  No.:    44                                          Page Page  --L 6    of of 2L21 Event
BOP/CRS CRS may direct placing pump in PTL due to apparent motor failure. End of running EHC pump trips event.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: _1_ Scenario No.: 1 Event No.: 4 Page --L of 2L Event


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


Pressurizer pressure channel 444 gradual failure high. Control severity to prevent a trip. I Time Position Applicant's Actions or Behavior AOP-401.5 Receives annunciators XCP 616 2-3 PZR PRESS HI/LO, 6162-5 PZR RO CNTRL PRESS HI, 6164-4 PRT LVL LOI TEMP/PRESS/LVLlHI Verifies PT-444 is failing high CRS Enters AOP-401.5, Pressurizer Pressure Control Channel Failure. Verifies first 3 steps are completed which are immediate actions. 1. Verify the PZR PORVs are closed:
Event
* 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. PRESS PSIG
* PI-456. PRESS PSIG
* PI-457. PRESS PSIG RO 3. Check if PI-444. CNTRL CHAN PRESS PSIG is NORMAL 3. IF PT-444 failed, then perform the following:
CRS/RO a) Ensure the PZR Spray Valves are closed:
* PCV-444C.
PZR SPRAY
* PCV-4440, PZR SPRAY b) Control PZR PRESS MASTER CONTROL in MAN. RO c) Operate the PZR Heaters and Spray Valves in manual to control RCS pressure between 2220 psig and 2250 psig. CRS Will probably reach the 2206 psig ONB Tech Spec 3.2.5 at which point the CRS should verbalize the 2 hr LCO requirement.
d) Within one hour; close MVG-8000B.
RELIEF 444 B ISOL. CRS Per TS 3.4.4.b, must also remove power from block valve, XVG-8000B because it would not. CRS/RO 4. Check If PI-445. CNTRL CHAN PRESS PSIG, indication is NORMAL CRS/RO 5. Ensure ROD CNTRL BANK SEL Switch is In AUTO. CRS/RO 6. Maintain RCS pressure between 2220 pslg and 2250 psig. CRS/SE 7. Determine and correct the cause of the channel failure. CRS Reference TS 3.4.4.b. for PORV failure. Must remove power from block valve in this case.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 5 Page 7 of 21 --Event


== Description:==
== 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.


Power Range Channel N44 failure high with the failure of the rods to move. The rods will not move in any direction in Manual or Automatic.
Appendix DD Appendix                                            Required Operator Required    OperatorActions Actions                                            Form Form ES-D-2 ES-D-2 Op Test  No.:
Time Position Applicant's Actions or Behavior AOP-401.10 Start of N-44 Failure and Rods Fail To Move event. Crew should enter:
Test No.:    11    Scenario No.:
* AOP-401.10 for N-44 Failure (steps 1&2 are immediate actions) .
No.:    11    Event No.:
* AOP-403.4 for Stuck Control Rods (steps 1&2 are immediate actions).
No.:    55 Op                    Scenario                    Event                                                            Page Page
RO should notice rods did not move when N-44 failed. N-44 starts failing hi, the following alarms are received:
                                                                                                                            - 77      of of
XCP 620 1-1 PR HI SETPT FLUX HI XCP 620 1-4 PR CHAN DEV RO XCP 6201-5 PR UP DET FLUX HI DEV AUTO DEFEAT XCP 620 5-1 ROD CNTRL SYS FAIL URGENT XCP 6201-6 PR LO DET FLUX HI DEV AUTO DEFEAT 1. Verify normal indication on Power Range Channel N-44. ROfCRS IF Power Range Channel N-44 has failed, THEN place the ROD CNTRL BANK SEL Switch in MAN. (Should be a discussion of GOP Appendix A requirement to have rods in AUTO if any PZR PORV is isolated.)
                                                                                                                                          -2121 Event
RO 2. Stabilize any plant transients in progress.
 
CRSfRO 3. Maintain stable plant conditions CRS/RO 4. Verify no testing .is in progress on the operable Power Range channels.
== Description:==
CRSfRO 5. Place ROD STOP BYPASS Switch for the failed Power Range channel in BYPASS. CRS/RO 6. Verify the appropriate Rod Stop Bypass status light is lit:
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.
* For N-44, B2 OP ROD STOP BYP (XCP-6111 4-4). CRS/RO 7. Adjust Control Rods to maintain Tavg within I.O°F of Tref. The empty fuse holders should NOT be reinstalled as this will allow a small amount of current flow through the blown fuse indicator
move. TheThe rods rods will will not not Event Descri P tiow move inin any move       any direction direction inin Manual Manual oror Automatic.
: 8. Deenergize the failed Power Range channel:
Automatic.
* Remove the CONTROL POWER fuses from the POWER CRS/RO RANGE A drawer of N-44.
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:
* Remove the INSTR POWER fuses from the POWER RANGE B drawer of N-44. 9. Align the Power Range channel comparator circuits:
enter:
: a. Place the following switches to the failed Power Range channel (N-44) position:
                                        *.      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
CRS/RO
* COMPARATOR CHANNEL DEFEAT Switch (on the COMPARATOR AND RATE drawer)
* For N-44,,_B2_OP_RO
* UPPER SECTION Switch (on the DETECTOR CURRENT COMPARATOR drawer)
                                      .__For_N-44          B2 OP ROD          STOP BYP D_STOP_BY                (XCP-6111 P_(XCP-61            4-4).
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 5 Page --L of 21 -Event
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 hours.}    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:==


Power Range Channel N44 failure high with the failure of the rods to move. The rods will not move in any direction in Manual or Automatic.
Description,    PowerRange Power   Range Channel Channel N44      failure high N44 failure   high with with the the failure failure of ofthe  rodstoto move.
Time Position Applicant's Actions or Behavior
the rods       move. The The rods rodswill will not not Event                  move inin any   direction inin Manual any direction      Manual or orAutomatic.
* LOWER SECTION Switch (on the DETECTOR CURRENT COMPARATOR drawer). CRS/RO 10. Ensure NR-45 is selected to the appropriate operable channels.
Automatic.
: 11. Within six hours, place the failed channel protection bistables in a tripped condition:
move Time Time          Position Position                                            Applicants Actions Applicant's     Actions or orBehavior Behavior shutdown, then shutdown,          then performs performs the  the following:
: a. Identify the associated bistables for the failed channel (N-44). REFER to Attachment
following:
: 1. b. Record the following for each associated bistable on SOP-401. CRS/SE REACTOR PROTECTION AND CONTROL SYSTEM, Attachment I:
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
* Instrument
: a. Notify
* Associated Bistable
: a. Notify thethe following following plantplant personnel:
* Bistable Location.
personnel:
* STPs. c. Notify the I&C Department to place the identified bistables in trip. CRS/RO 12. Verify Reactor Power is LESS THAN 75%. CRS 13. Refer to Tech Spec 3.3.1. {Trip bistables within 6 hours.} CRS/SE 14. Determine and correct the cause of the Power Range channel failure. Cause of failure will not be determined for this event. AOP-403.4 Following are the actions for Failure of Control Rods to Move. Steps 1& CRS 2 are immediate actions. This event will be occurring simultaneously with the N44 failure so the crew will be forced to prioritize between the two AOPs. RO 1. The ROD CNTRL BANK SEL Switch is already in MAN RO 2. Main Turbine load is already stabilized CRS/RO 3. Stop any boration or dilution in progress 1. Adjust Control Rods to maintain Tavg within 1.0 degrees of Tref. NOTE -Step 4: If Tavg has remained within 1.5°F of Tref , Control Rods should be moved one or two steps in or out to verify proper operation.
SE SE                      **      Management Management            Duty Duty    Supervisor Supervisor
CRS/RO Since Control Rods will NOT move, THEN perform the following:
                                            ** Reactor Reactor Engineering Engineering
* Adjust Main Turbine load until Tavg is within 5°F of Tref
: b. Decrease
* Initiate GTP-702, Attachment IV.A. INOPERABLE CONTROL ROD CRS CRS evaluates Tech Specs 3.1.3.1.C which will require a plant Appendix 0 Required Operator Actions Form ES-O-2 Op Test No.: 1 --Scenario No.: 1 Event No.: 5 Page 9 of 21 -Event
: 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:==
== Description:==


Power Range Channel N44 failure high with the failure of the rods to move. The rods will not move in any direction in Manual or Automatic.
Event
Time Position Applicant's Actions or Behavior shutdown, then performs the following:
Building operator (if dispatched) reports that the urgent failure is from power cabinet 2BD a. Notify the following plant personnel:
SE
* Management Duty Supervisor
* Reactor Engineering
: b. Decrease Main Turbine Load to 50 MW at a rate determined by BOP the Shift Supervisor. (Refer to GOP-4B, POWER OPERATION, MODE 1 -DESCENDING, starting with Step 3.3) c. Maintain Tavg within 5 degrees of Tref using the following:
BOP/RO
* Main Turbine Load adjustment
* RCS Boration.
Refer to SOP-1 06, REACTOR MAKEUP WATER SYSTEM Appendix D Required Operator Actions Form ES-D-2 Op Test No.: --L Scenario No.: --L Event No.: -L Page...1.2..
of 21.. Small steam leak occurs allowing determination of a required reactor shut down. The crew may Event


== Description:==
== 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


initiate a Rx Trip since Rods already will not move. When a trip signal is inserted, the reactor will not trip. Time 1 Position 1 Applicant's Actions or Behavior NOTE While attempting to lower load, the SMALL STEAM LEAK will initiate.
Appendix0D Appendix                                                  RequiredOperator Required      OperatorActions Actions                                         Form FormES-D-2 ES-D-2 OpTest Op       No.:
NOTE to over 1 min IE 5 instantaneous
TestNo.:  ---                   1     ScenarioNo.:
-then increase as necessary until decision is made to Booth trip Rx and SI Operator Increase break to IE7 on Rx trip. Operator will respond to below annunciators by pulling ARPs and RO following CRS directions:
Scenario       No.:       11      EventNo.:
XCP 6062-2 RBCU 1A12A DRN FLO HI XCP 607 2-2 RBCU 1 BI2B DRN FLO HI CRS SRO will evaluate Tech Spec for DNB TS 3.2.5 for low PZR Pressure when it occurs. (2206 psig) CRS/RO As the leak escalates and conditions deteriorate, the crew is expected to trip the reactor prior to automatic actuation.
Event     No.:     77                                              Page Page
CRITICAL Directs the RO to trip the reactor. CRS/RO RO manually trips the reactor.
                                                                                                                                  - 1111  of of
Appendix 0 Required Operator Actions Form ES-D-2 Op Test No.: ----1-Scenario No.: 1 Event No.: 7 Page 11 of 21 --Event
                                                                                                                                                -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:==
== Description:==


Large Steam Line Break occurs on the C Steam Generator upstream of the MSIVs. "C n MS IV fails to shut automatically.
fails    shutautomatically.
The "C n feed water isolation valve does not isolate automatically.
fails totoshut    automatically. The      The "C n Cfeed feedwater waterisolation isolation valve valvedoesdoesnot notisolate isolateautomatically.
Time Position Applicant's Actions or Behavior EOP-1.0 NOTE Large Steam Break should occur at this time. An AUTO SI may occur prior to MANUAL actuation due to size of steam break. 1. Verify Reactor Trip: (Reactor did not trip automatically.
automatically.
Isolate EFW flow to "C" S/G)
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.
* Trip the Reactor using either Reactor Trip Switch RO
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.
* Verify all Reactor Trip and Bypass Breakers are open.
steam     break.
* Verify all Rod Bottom Lights are lit.
1.1. Verify Verify Reactor Reactor Trip:  Trip: (Reactor (Reactor did  did not not trip trip automatically.
* Verify Reactor Power level is decreasinQ.  
automatically. Isolate Isolate EFW        flow EFW flow to "C" S/G) to  C    S/G)
: 2. Verify Turbine/Generator Trip: (Secure RCPs Hi 3) a. Verify all Turbine STM STOP VLVs are closed. BOP 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. BOP 3. Verify both ESF buses are energized.  
                                        ** Trip  Trip the the Reactor Reactor usingusing either either Reactor Reactor Trip  Trip Switch Switch RO RO
: 4. Check if SI is actuated:  
                                        * .      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:
: a. Check if either:
* SI ACT status light is bright on XCP-61 07 1-1. OR ALL
                                              ** SI ACT status light is bright on XCP-61           XCP-6107      07 1-1.
* Any red first-out SI annunciator is lit on XCP-626 top row. b. Actuate SI using either SI ACTUATION Switch. GO TO Step 6. 5. Check if SI is required:  
OR ALL                     ** Any red first-out SI annunciator is lit on XCP-626 top row.
: a. Check if any of the following conditions exist:
: b. Actuate SI using either SI ACTUATIO            ACTUATION         N Switch.
* PZR pressure LESS THAN 1850 psig. OR
GO GO TO Step      Step 6.
* RB pressure GREATER THAN 3.6 psig. ALL OR
5.
* Steamline pressure LESS THAN 675 psig. OR
: 5. Check Check if        if SI SI isis required:
* Steamline differential pressure GREATER THAN 97 psid. b. Actuate SI using either SI ACTUATION Switch. RO At some point after the Rx Trip, a High-3 should have occurred and the RO will secure all RCPs CRS/BOP 6. Complete ATTACHMENT 3, SI EQUIPMENT VERIFICATION.
required:
BOP operator manually closes "C" MSIV and "C" FWIV.
: a.      Check
Appendix 0 Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 8 Page 12 of 21 -Event
: 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:==
== Description:==


A Reactor Building Cooling Unit fails to start automatically.
Event  
Time Position Applicant's Actions or Behavior RO Notes that RBCU XFN-0064B did not auto start in SS on the SI and manually starts XFN-0064B CRS/SE 7. Announce plant conditions over the page system. CRS/RO 8. Verify RB pressure has remained LESS THAN 12 psig on PR-951, RB PSIG (P-951), red 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). RO IF either annunciator is NOT lit, THEN actuate RB Spray by placing the following switches to ACTUATE: Both CS-SGA 1 and CS-SGA2. OR Both CS-SGB1 and CS-SGB2. MVG-3003A(B}, SPRAY HDR ISOL LOOP A(B). RO b) Verify Phase B Isolation by ensuring RB PRA Y/PHASE B ISOL monitor lights are bright on XCP-61 05. c) Ensure the following are open: RO MVG-3001A(B), RWST TO SPRAY PUMP A(B) SUCT. MVG-3002A(B), NAOH TO SPRAY PUMP A(B) SUCT.
Appendix 0 Required Operator Actions Form ES-O-2 Op Test No.: 1 Scenario No.: 1 Event No.: 9 Page ---1l. of ..1.:!...
---Event


== Description:==
== 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


'8' Train Containment Spray pump fails to start automatically.
Appendix DD Appendix                                            Required Operator Required      OperatorActions Actions                                           Form Form ES-D-2 ES-D-2 Op Test Op  Test No.:
Time Position Applicant's Actions or Behavior d) Ensure both RB Spray Pumps are running Of the RO has not RO alread'l.
No.: --L1 Event
done SOl at this l2.oint the RO manuall'l.
starts the "B" RB Sl2.ra'l.l2.uml2.
that did not auto start on the Phase B isolation signal.l Appendix D Required Operator Actions Form ES-D-2 Op Test No.: --L Scenario No.: 1 Event No.: 10 Page 14 of 21 ----Event


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


Flow meter (FI-7368) for A Train of Containment Spray fails low. Actual spray is occurring.
Event
Time Position Applicant's Actions or Behavior e) Verify RB Spray flow is GREATER THAN 2500 gpm for each operating train on FI-7368, SPR PP A DISCH FLOW GPM. RO FI-7378, SPR PP B DISCH FLOW GPM. (At this point the RO notes that there is no flow indicated on FI-7368 but that all other indications are normal and diagnoses it as a failed indicator. ) RO f) Stop all RCPs (if not already stopped on Phase B). CRS/RO BOP CRS/RO CRS/RO 9. Check RCS temperature:
 
* With no RCP running, RCS Tcold is stable at OR trending to 557"F. IF RCS temperature is LESS THAN 557"F 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 closed. d) IF RCS cooldown continues, THEN: (Could get red path on EOP-15.0 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 flow as necessary to stabilize RCS temperature at 557"F. (3) IF RCS cooldown continues, THEN close:
== Description:==
* MS Isolation Valves, PVM-2801A(B)(C).
 
* MS Isolation Bypass Valves, PVM-2869A(B)(C).
Scenario No.:
By step 9 in EOP-1.0 the faulted SG should have been diagnosed as "C" and EFW to "C" SG should be secured (FCV closed) (OAP-103.4)  
Scenario Flow meter Flow No.:
: 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:
meter (FI-7368) 1I (FI-7368) for Event No.:
* MVG-8000A, RELIEF 445 A ISOL.
Event  No.:
* MVG-8000B, RELIEF 444 B ISOL.
forAATrain Train of 10 10 of Containment Containment SpraySpray fails fails low.
* MVG-8000C, RELIEF 445 B ISOL. d. Verify at least one PZR PORV Block Valve is open. OPEN one Block Valve unless it was closed to isolate an open PZR PORV. 11. a. Check if RCPs should be stopped: Check if either of the following criteria is met:
low. Actual Page Actual spray Page      14
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 10 Page 15 of 2.1 -------Event
                                                                                                                                - 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:==
== Description:==


Flow meter (FI-7368) for A Train of Containment Spray fails low. Actual spray is occurring.
Event
Time Position Applicant's Actions or Behavior
 
* Annunciator XCP-612 4-2 is lit (PHASE B ISOL) . OR
== Description:==
* RCS pressure is LESS THAN 1400 psig AND SI flow is indicated on FI-943, CHG LOOP B CLD/HOT LG FLOW GPM. b. Stop all RCPs (already stopped).  
Flow meter Flow meter (FI-7368)
: 12. Verify no SG is FAUL TED:
(Fl-7368) for   for AATrain Train ofofContainment Containment Spray Spray fails fails low.
* No SG pressure is decreasing in an uncontrolled manner .
low. Actual Actual spray spray isis occurring.
* No SG is completely depressurized . CRS/BOP GO TO EOP-3.0, FAULTED STEAM GENERATOR ISOLATION, Step 1. Crew will leave this procedure and transition to EOP-3.0, step 1. EOP-3.0 1. Ensure all the following are closed: CRS/BOP
occurring.
* MS Isolation Valves, PVM-2801A(B)(G).
Time Time      (  Position Position                                             Applicants Actions Applicant's   Actions or   or Behavior Behavior
* MS Isolation Bypass Valves, PW-2869AIB)(Cl-
                                              *. Annunciator XCP-612 Annunciator         XCP-612 4-2   4-2 isis litlit (PHASE (PHASE BB ISOL)ISOL)..
: 2. Check if any SG is NON-FAULTED:
OROR
ALL
                                              *. 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.
* Pressure in any SG is stable or increasing.
GPM.
* Any SG is not completely depressurized  
b.b.             Stop all Stop     all RCPs RCPs (already (already stopped).
: 3. Identify any FAULTED SG(s): ALL
stopped).
* Any SG pressure decreasing in an uncontrolled manner. OR
: 12. Verify
* Any SG is NOT completely depressurized
: 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:
: 4. Close the following valves for each FAULTED SG:
* FW Flow Control FCV-498 CRS/BOP
                                    ** FW     FW Flow Flow Control Control FCV-498 FCV-498 CRS/BOP CRS/BOP              **       FW FW Isolation, Isolation, PVG-1611C PVG-1611 C
* FW Isolation, PVG-1611 C
                                    ** SG    SG Blowdown.
* SG Blowdown.
Blowdown. PVG-503CPVG-503C
PVG-503C
                                    *___FW_Flo
* FW Flow Control Bypass FCV-3341 5. Complete the isolation of each FAULTED SG: a. Close SG Chemical Feed Isolation, MVK-1633C  
* FW Floww_Control_B  Control Bypassypass_FCV-FCV-3341 3341 5.
: b. Close MS Drain Isolation PVT -2843C c. Close MS Drain Isolation, PVT-2877B for SG C. d. Place the Steam line PWR RELIEF C SETPT Controller in MAN and closed. ALL e. Place the Steamline Power Relief C Mode Switch in PWR RLF f. Close FCV-3551 MD EFP TO SG C g. Close FCV-3556 TD EFP TO SG C h. Locally unlock and close XVG01 017C-EF SG C MTR DR EF PUMP SUPPLY HEADER VALVE (IB-423).  
: 5. Complete Complete the      the isolation isolation ofof each each FAULTED FAULTED SG:        SG:
: i. Locally unlock and close XVK01 019C-EF SG C MTR DR EF PUMP SUPPL Y STOP CHK VLV (IB-423).
a.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 10 Page of .1.:!... Event
: 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:==
== Description:==


Flow meter (FI-7368) for A Train of Containment Spray fails low. Actual spray is occurring.
Event
Time Position CRITICAL BOP j. k. I.
* 1 ) 2) Applicant's Actions or Behavior Locally unlock and close XVG01 018C-EF SG C TURB DR EF PUMP SUPPLY HDR VALVE (IB-423).
Locally unlock and close XVK01020C-EF SG C TURB DR EF PUMP SUP STOP CHK VALVE (IB-423) Close and locally deenergize the appropriate valve for SG C FAULTED: For SG C: Open XMCIDB2Y 05EH. EMERG FEEDWATER PUMP MAIN STEAM BLOCK XVG2802B-MS (AB-463).
Close MVG-2802B MS LOOP C TO TD EFP Faulted SG is Isolated 6. Check if Secondary radiation levels are normal: a. Check radiation levels normal on all un isolated radiation monitors:
* RM-G19C STMLN HI RNG GAMMA.
* RM-L3, STEAM GENERATOR ALL BLOWDOWN LIQUID MONITOR.
* RM-LiO. SG BLOWDOWN CW DISCHARGE LIQUID MONITOR.
* RM-A9, CNDSR EXHAUST GAS ATMOS MONITOR. b. Notify Chemistry to sample all SG secondary sides and screen samples for abnormal activity using a frisker. 7. Check if SI flow should be reduced: a. RCS subcooling on TI-499A(B), A(B) TEMP OF is GREATER THAN 30"F. b. Secondary Heat Sink is adequate:
* Total EFW flow to INTACT SGs is GREATER THAN 450 gpm. ALL OR CRS/RO CRS/RO CRS/BOP
* Narrow Range level is GREATER THAN 30% [50%] in at least one INTACT SG. c. RCS pressure is stable OR increasing.
: d. PZR level is GREATER THAN 18% [38%] (IF PZR LEVEL
< 18%[38%], THEN transition to EOP-2.0, see attachment of EOP-2.0 steps) 8. Reset both SI RESET TRAIN A(B) Switches.
: 9. Reset Containment Isolation:
* RESET PHASE A TRAIN A(B) CNTMT ISOL.
* RESET PHASE B TRAIN A(B) CNTMT ISOL. 10. Place both ESF LOADING SEQ A(B) RESETS to: a. NON-ESF LCKOIJTS.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: --L Scenario No.: 1 Event No.: 10 Page 17 of 21 --Event


== Description:==
== 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&deg;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.


Flow meter (FI-7368) for A Train of Containment Spray fails low. Actual spray is occurring.
Appendix DD Appendix                                        Required Operator Required      OperatorActions Actions                                           Form Form ES-D-2 ES-D-2 Op  Test No.:
Time Position Applicant's Actions or Behavior b. AUTO-START BLOCKS. 11. Establish Instrument Air to the RB: a. Start one Instrument Air Compressor and place the other in CRS/RO Standby. b. Open PVA-2659, INST AIR TO RB AIR SERVo c. Open PVT-2660.
Op Test  No.: --L1    Scenario No.:
AIR SPLY TO RB CRS 12. GO TO EOP-1.2, SAFETY INJECTION TERMINATION, Step 1. If previously entered EOP-2.0, EOP-2.0 will transition back to EOP-1.2. EOP-1.2 CRS/RO Stop all but one Charging Pump and place in Standby. (Stop A Chg Pump) CRS/RO Verify RCS pressure is stable OR increasing.
Scenario  No.:     11    Event No.:
Establish Normal Charging:  
Event   No.:     10 10                                            Page Page
: 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 MVG-8801A(B), HI HEAD TO COLD LEG INJ CRS/RO Control FCV-122, CHG FLOW, to maintain PZR level. Note SI terminated and normal charging restored.
                                                                                                                        - 1818  of of   21 21 Event
CRS/RO Stops both RHR pumps 6. Verify SI flow is NOT required:
CRS/RO a. RCS subcooling on TI-499A(B), is GREATER THAN 30&deg;F c. PZR level is GREATER THAN 18% r38%]. 7. Check if RB Spray should be stopped: a. Check if any RB Spray Pumps are running. b. Verify RB pressure is LESS THAN pressure is LESS THAN 11 psig. CRS/RO c. Depress both RESET TRAIN A(B) RB SPRAY. d. Verify EOP-14.0, RESPONSE TO INADEQUATE CORE COOLING, has NOT been implemented.
: e. Stop both RB Spray Pumps and place in Standby. f. Close MVG-3003A(B), SPRAY HDR ISOL LOOP A(B). 9. Check if Letdown can be established:  
: a. Verify PZR level is GREATER THAN 30% [50%] b. Establish Normal Letdown: CRS/RO 1) Adjust FCV-122, CHG FLOW, to obtain 60 gpm Charging flow. 2) Set PCV-145, LO PRESS LTDN, to 70%. 3) Open TCV-144, CC TO LTDN HX. 4) Open PVT-8152, LTDN LINE ISOL.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: --L Scenario No.: 1 Event No.: 10 Page 18 of 21 ---...;.. Event


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


Flow meter (FI-7368) for A Train of Containment Spray fails low. Actual spray is occurring.
Event
Time Position Applicant's Actions or Behavior 5) Open both LCV-459 and LCV-460, L TDN LINE ISOL. 6) Open desired Orifice Isolation Valve(s) to obtain 60 gpm to 120 gpm:
* PVT-8149A, L TDN ORIFICE A ISOL (45 gpm).
* PVT-8149B, LTDN ORIFICE B ISOL (60 gpm).
* PVT-8149C, LTDN ORIFICE C ISOL (60 gpm). 7) Adjust FCV-122, CHG FLOW, to maintain TI-140, REGEN HX OUT TEMP "F, between 250"F and 350"F while maintaining PZR level. 8) Adjust PCV-145, LO PRESS LTDN, to maintain PI-145, LO PRESS LTDN PRESS 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 a. Set FCV-113 A&B, BA FLOW, Controller to 8.6. j. Ensure the Reactor Makeup System is in AUTO. 10. Transfer Charging Pump suction to the VCT: CRS/RO a. Open both LCV-115C(E), VCT OUTLET ISOL. k. Close both LCV-115B(D), RWST TO CHG PP SUCT. Examiners should end scenario at this point as SI is now secured and charging and letdown are restored.
EOP-2.0 {if 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-1.2 transition.
: 1. Check if RCPs should be stopped: a. Check if either of the following criteria is met:
* Annunciator XCP-612 4-2 is lit (PHASE B ISOL). OR ALL
* RCS pressure is LESS THAN 1400 psig AND SI flow is indicated on FI-943, CHG LOOP B CLD/HOT LG FLOW GPM. b. Stop all RCPs. 2. Verify no SG is FAUL TED: CRS/BOP No SG pressure is decreasing in an uncontrolled manner. *
* No SG is completely depressurized.
: 3. Check INTACT SG levels: CRS/BOP a. Verify Narrow Range level in INTACT SGs is GREATER THAN 30% [50%].
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: ----L-Scenario No.: 1 Event No.: 10 Page 19 of 21 --Event


== Description:==
== 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%].
[50%].


Flow meter (FI-7368) for A Train of Containment Spray fails low. Actual spray is occurring.
AppendixDD Appendix                                            RequiredOperator Required      OperatorActions Actions                                        Form FormES-D-2 ES-D-2 TestNo.:
Time Position CRS/RO CRS/RO ALL Applicant's Actions or Behavior e. Control EFW flow to maintain Narrow Range level in each INTACT SG between 40% [50%] and 60%. 4. Reset both SI RESET TRAIN A(B) Switches.
OpTest  No.: ----L-1    Scenario No.:
: 5. Reset Containment Isolation:
No.:     11    EventNo.:
* RESET PHASE A -TRAIN A(B) CNTMT ISOL.
No.:     10 Op                    Scenario                   Event           10                                           Page Page
* RESET PHASE B -TRAIN AJB) CNTMT ISOL. 6. Check if Secondary radiation levels are normal: a. Check radiation levels normal on:
                                                                                                                        - 1919  of of
* RM-G19A(B)(C), STMLN HI RNG GAMMA.
                                                                                                                                      -2121 Event
* RM-A9, CNDSR EXHAUST GAS ATMOS MONITOR.
* RM-L3, STEAM GENERATOR BLOWDOWN LIQUID MONITOR.
* RM-L 10, SG BLOWDOWN CW DISCHARGE LIQUID MONITOR. b. Place SVX-9398A(B)(C), SG A(B)(C) SMPL ISOL, in AUTO. m. Notify Chemistry to sample all ' SG secondary sides and 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, RELIEF 445 A ISOL. 2) MVG-8000B RELIEF 444 B ISOL. 3) MVG-8000C, RELIEF 445 B ISOL. CRS/RO If any PZR PORV opens because of high PZR pressure, Step 7.b should be repeated after pressure decreases to LESS THAN 2300 psig, to ensure the PORV recloses.
: b. Verify all PZR PORVs are closed. c. Verify at least one PZR PORV Block Valve is open. 8. Place both ESF LOADING SEQ A(B) RESETS to: CRS/BOP a. NON-ESF LCKOUTS. CRS/RO b. AUTO-START BLOCKS. 9. Establish Instrument Air to the RB: a. Start one Instrument Air Compressor and place the other in Standby.
Appendix D Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 10 Page 20 of 21 --Event


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


Flow meter (FI-7368) for A Train of Containment Spray fails low. Actual spray is occurring.
Event  
Time Position ALL ALL CRS/RO Applicant's Actions or Behavior b. Open PVA-2659, INST AIR TO RB AIR SERVo C. Open PVT-2660, AIR SPLY TO RB. 10. Check if SI flow should be reduced: a. RCS subcooling on TI-499A(B), A(B) TEMP "F, is GREATER THAN 30"F. b. Secondary Heat Sink is adequate:
* Total EFW flow to INTACT SGs is GREATER THAN 450 gpm. OR
* Narrow Range level is GREATER THAN 30% [50%] in at least one INTACT SG. C. RCS pressure is stable increasing.
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), if not then continue)
GO TO Step 11. o. GO TO EOP-1.2, SAFETY INJECTION TERMINATION, Step 1. 11. Check if RB Spray should be stopped: a. Check if any RB Spray Pumps are running b. Verify RB pressure is LESS THAN 11 psig c. Depress both RESET TRAIN A(B) , RB SPRAY. NOTE -Step 11.d
* RB Spray must run for a minimum of two hours.
* Anytime RB Spray Pumps are stopped, MVG-3003A(B), SPRAY HOR ISOL LOOP (B), should be closed for containment isolation.
: d. Consult with TSC personnel concerning RB Spray System operation.
: 12. Check if RHR Pumps should be stopped: a. Check RCS pressure:
: 1) RCS pressure is GREATER THAN 250 psig 2) RCS pressure is stable OR increasing.
: b. Check if any RHR Pump is running with suction aligned to the Appendix 0 Required Operator Actions Form ES-D-2 Op Test No.: 1 Scenario No.: 1 Event No.: 10 Page 21 of 21 -----Event


== Description:==
== 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.


Flow meter (FI-7368) for A Train of Containment Spray fails low. Actual spray is occurring.
Appendix DD Appendix                                        Required Operator Required      OperatorActions Actions                                        Form Form ES-D-2 ES-D-2 Op Test  No.:
Time Position Applicant's Actions or Behavior RWST c. Stop any RHR Pump which is running with suction aligned to the RWST and place in Standby. 13. Check if RCS pressure is stable OR decreasing.
Test No.:  11    Scenario No.:
This would be a "do loop" back to step1 until PZR Level was greater CRS/RO than 18% [38%] RETURN TO Step 1. This is end of EOP-2.0 for this scenario. 
No.:      11    Event No.:
No.:    10 Op                  Scenario                  Event            10                                            Page Page
                                                                                                                        - 2020  of of
                                                                                                                                      - 2121 Event


Appendix D Scenario Outline Form ES-D-1 Facility:
== Description:==
I vc Summer I Scenario No.: 3 (SPARE) Op-Test No.: 2005-301 Examiners:
 
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:
Operators:
Initial Conditions:
initial Conditions:
The Unit is in Mode 2 with a MOL reactor startup in progress.
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 has initiated the reactor startup per GOP-3. Source range counts are stable and Control bank '0' is presently at 100 steps. 11M data now projects criticality at 116 steps on Control bank '0'. Continue with the reactor startup beginning with step 3.11.q of GOP-3, and stabilize reactor power between 1-3%. "A 1" maintenance week S/G "A," Small tube leak, approx. 8 gpd. Event Malf. No. I Event Event Description No. Position Type* 1 RO R Pull control rods to establish critical reactor. BOP C Train 'A' Service Water Pump A trips and spare "c" pump needs to be aligned and 2 SRO (TS) started. RO I Controlling channel Pressurizer Level Transmitter (IL T-459) fails low and LID 3 isolates.
Turnover:        The  previous crew The previous     crew has has initiated initiated the     reactor startup the reactor    startup per  per GOP-3.
AOP-401.6 BOP N Re-establish letdown. 4 (SOP-102)
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.
BOP I Steam Generator B PORV Pressure Transmitter (IPT-2010) fails high. BOP 5 operator takes manual control and closes PCV-201 O. BOP/RO C Letdown line break inside Containment.
steps. 11M 1IM data data now now projects projects criticality criticality at at 116 116 steps steps on  on Control Control bankbank D. Continue
AOP isolates letdown which terminates the 6 SRO (TS) leak. Crew places excess letdown in service. AOP-101.1  
                '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%.
& SOP-102 RO C RCP "A" High Vibration (discussion about PZR spray) and seal failure when 7 secured. (AOP-101.2) (SOP-101)
between   1-3%.
ALL M Small break LOCA (approx 400 gpm). Ramp leak in over a 5 minute period to allow 8 entry into AOP-1 01.1 again. (vary ramp rate as necessary to give operators time to make "manual" reactor trip decision in AOP-101.1 prior to getting auto trip and time to manual SI in EOP-1.0 prior to auto SI). BOP or C Safety injection Train 'A' fails to automatically or manually actuate (troubleshooting 9 RO this event for the rest of the scenario).
Al "A     maintenance week 1" maintenance SIG "A,"
and 'B' Charging pump fails to automatically start when safety injection is initiated but will manual start. The reactor fails to automatically trip & fails to trip from RO*side MCB switch but will trip from BOP side .. * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D, Page 39 of 39 Scenario Event Description VC Summer-2005-301 Op-Test No.: Scenario No.: Event No.: Page __ of __ Event
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:==
== Description:==


Time Position Applicants Actions or Behavior I I I GOP-3.0 I q. Within 15 minutes before achieving criticality, verify Tavg greater than or equal to 551&deg;F. r. Announce criticality over the page system. s. Verify critical rod position is above the Rod Insertion Limit per Tech Spec 3.1.3.6. t. At the AUDIO COUNT RATE CHANNEL drawer, place the following switches in OFF: 1) AUDIO MULTIPLIER.  
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&deg;F.
551 &deg;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.
: 2) CHANNEL SELECTOR.
3.11 Increase Reactor Power to 10-3% as follows: / a. Establish a stable Startup Rate of less than one decade per minute. b. At 7.5x1 0-6%, perform the following:  
SELECTOR.
: 1) Verify P6 Permissive energizes to bright. 2) Verify a minimum of one decade overlap between Source Range Channels and Intermediate Range Channels.  
3.11 Increase Reactor Power to 10-3% as follows:                 /I
: c. Prior to 10 0 CPS, perform the following:  
: a. Establish a stable Startup Rate of less than one               decade per minute.
: 1) Momentarily place SR TRAIN A Switch in BLOCK. 2) Verify SR A TRIP BLCK Permissive energizes to bright. 3) Momentarily place SR TRAIN B Switch in BLOCK. 4) Verify SR B TRIP BLCK Permissive energizes to bright. d. Select one Intermediate Range Channel and one Power Range Channel on NR-45, NIS RECORDER.  
: b. At 7.5x1 0-6%, perform the following:
: e. Stabilize Reactor Power at 10-;)%. This ends the pull to criticality event. RO A SWP trips. RO responds to various alarms and references the ARP: XCP-604 1-2: SWP A/C TRIP Appendix D, Page 39 of 39 Scenario Event Description VC Summer-2005-301 Op-Test No.: Scenario No.: Event No.: Page __ of __ Event
: 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:==
== Description:==


Time Position Applicants Actions or Behavior XCP-604 3-3: SW CCW HX A FLO LOITEMP HI XCP-604 3-4: DG A CLR SW FLO LO TEMP HI CRS/RO ARP is handed to CRS, the IB operator is dispatched to SW PP house to investigate.
Time Time        Position Position                            Applicants Actions Applicants  Actions oror Behavior Behavior XCP-604 3-3:
Electricians may also be notified.
XCP-604          3-3: SW Sw CCW CCW HX HX AA FLOFLO LOITEMP LO/TEMP HI    HI XCP-604 3-4:
CRS Decision should be made to place C SWP on A Train CORRECTIVE ACTIONS: I. Place the spare Service Water Pump in service per SOP-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 EA 04, SERVICE WATER PUMP XPP0039A-SW, complete Attachment V. ALL b. Start XPP-0039C, PUMP C TRAIN A. (PEER D) RO c. Verify MVB-3116C, SWP C DISCH, automatically opens. ALL/Building  
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.
: d. Ensure sufficient Service Water Pump C cooling water flow, by throttling the following (SW-436):  
to investigate. Electricians Electricians may may also also be  notified.
: 1) XVT03157C-SW, sw PP C MTR UPPER BRG CLG WTR SUP VALVE, to obtain upper bearing flow between 10 gpm and 12 gpm. 2) XVT03158C-SW, sw PP C MTR LOWER BRG CLG WTR SUP VALVE, to obtain lower bearing flow between 3 gpm and 4 gpm. ALL/Building  
be notified.
: e. At XPN-13, C SERVICE WATER SCREEN Control Panel (SW-436), verify proper traveling screen operation, as follows: 1) Place the Screen Selector Switch, in HAND. 2) Verify proper screen operation and screen wash flow. 3) Place the Screen Selector Switch, in AUTO. RO f. Stop XPP-0039A, PUMP A, and place the control switch, in PULL TO LK NON-A. RO g. Verify MVB-3116A, SWP A DISCH, automatically closes. Appendix D, Page 39 of 39 Scenario Event Description VC Summer-2005-301 Op-Test No.: Scenario No.: Event No.: Page __ of __ Event
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:==
== Description:==
Time Position Applicants Actions or Behavior ALL/Building
 
: h. Re-verify Service Water Pump C cooling water flow and adjust as necessary, by throttling the following (SW-436):
Event
: 1) XVT03157C-SW, SW PP C MTR UPPER BRG CLG WTR SUP VALVE, to obtain upper bearing flow between 10 gpm and 12 gpm. 2) XVT03158C-SW, SW PP C MTR LOWER BRG CLG WTR SUP VALVE, to obtain lower bearing flow between 3 gpm and 4 gpm. ALL/Building I. Rack down XSW1EA 04, SERVICE WATER PUMP XPP0039A-SW (SW-425).
ALL/Building
: j. At XPN-11, A SERVICE WATER SCREEN, Control Panel (SW-436), place the Screen Selector Switch, in OFF. 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 is the L T-459 Failure, PZR Level Controlling channel. L T-459 Fails low and Letdown isolates.
The following alarms are received:
XCP-614 5-1: CHG LINE FLO HIILO XCP-616 1-3: BLCK HTRS ISOL LTDN PZR LCS LO XCP-616 1-5: PZR LCS DEV HIILO XCP-616 3-1: PZR HTR CNTRL OR BU GRP 1/2 TRIP XCP-616 4-6: SCR OUTPT LOSS Appendix D, Page 39 of 39 Scenario Event Description VC Summer-2005-301 Op-Test No.: Scenario No.: Event No.: Page __ of __ Event


== Description:==
== Description:==
Time Position Applicants Actions or Behavior I Crew enters AOP-401.06 PZR Level Control and Protection Channel Failure. Step 1 is an immediate action. AOP-401.6 RO 1 Place PZR LEVEL CNTRL Switch to the position with two operable channels.
 
RO 2 Select an operable channel on PZR LEVEL RCDR. RO 3 Control the PZR Heaters as necessary to maintain PZR pressure:
Time Time        Position Position                          Applicants Actions Applicants   Actions oror Behavior Behavior ALL/Building h.
CNTRL GRP Heaters. BU GRP 1 Heaters. BU GRP 2 Heaters. RO 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-102.1, LOSS OF LETDOWN, while continuing with this procedure.
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):
RO 2.1 Place FCV-122, CHG FLOW, in MAN and close. RO 2.2 Place PCV-145, LO PRESS LTDN, in MAN and open to 70%. (PEER D) RO 2.3 Place TCV-144, CC TO LTDN HX, in MAN and open to 100%. RO 2.4 Place TCV-143, LTDN TO VCT OR DEMIN, in VCT. RO 2.5 Open PVT-8152, LTDN LINE ISOL. RO 2.6 Open the following:
the following  (SW-436):
: a. LCV-459, L TON LINE ISOL. b. LCV-460, L TON LINE ISOL. Appendix 0, Page 39 of 39 Scenario Event Description VC Summer-2005-301 Op-Test No.: Scenario No.: Event No.: Page __ of __ Event
: 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:==
== Description:==
Time Position Applicants Actions or Behavior RO 2.7 Ensure the following Charging Line Isolation Valves are open: a. MVG-81 07, CHG LINE ISOL. b. MVG-81 08, CHG Llt:-JE ISOL. RO 2.8 Slowly open FCV-122, CHG FLOW, to establish 60 gpm flow as indicated on FI-122A, CHG FLOW GPM. RO 2.9 Open Orifice Isolation Valves to obtain the desired Letdown flow rate (60 gpm to 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-140, REGEN HX OUT TEMP of, between 250&deg;F and 350&deg;F while maintaining Pressurizer level. RO 2.11 Adjust PCV-145, LO PRESS LTDN, to maintain PI-145, LO PRESS L 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 TDN HX, potentiometer as necessary to maintain the desired VCT temperature and place in AUTO. Refer to VCS Curve Book, Figure 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-143, LTDN TO VCT OR DEMIN, in DEMIN/AUTO.
 
RO 5 Check if PZR LVL MASTER CONTROLLER is responding appropriately:
Event
* Verify Charging flow is normal and responding to PZR level error.
* Verify PZR level is stable at OR trending to program level. Appendix D, Page 39 of 39 Scenario Event Description VC Summer-2005-301 Op-Test No.: Scenario No.: Event No.: Page __ of __ Event


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


Time Position Applicants Actions or Behavior CRS/SE 6 Within six hours, place the failed channel protection bistables in a tripped condition:  
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.
: a. Identify the associated bistables for the failed channel REFER TO Attachment 1 . b. Record the following for each associated bistable on SOP-401, REACTOR PROTECTION AND CONTROL SYSTEM, Attachment I:
Channel    Failure. Step Step 1I is is an an immediate immediate action.
* Instrument.
action.
* Associated Bistable.
AOP-401.6 AOP-401.6 RO RD                Place PZR LEVEL CNTRL Switch to the position with two 11 Place operable channels.
* Bistable Location.
RO RD            2 Select an operable channel on PZR LEVEL RCDR.
* 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. The next event is IPT-2010 slowly failing high which results in SG PORV IPV-2010 (8 Loop) slowly going full open. Valve controller can be taken to Manual and closed. No alarms are associated with this event. ALL Crew should notice some excess RCS cooling, increased steam flow and finally notice IPV-201 0 is going open. CRS/BOP CRS and/or BOP should recommend placing 2010 controller in Manual and attempting to close. BOP IPV-2010 placed in Manual and closed. CRS/SE MWR should be written and work order generated to repair transmitter.
RO RD            3 Control the PZR Heaters as necessary to maintain PZR pressure:
This concludes the 2010 failing open event. Appendix D, Page 39 of 39 Scenario Event Description VC Summer-2005-301 Op-Test No.: Scenario No.: Event No.: Page __ of __ Event
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,            &deg;F, between 250&deg;F and 350&deg;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:==
== Description:==


Time Position Applicants Actions or Behavior The Letdown leak inside containment is the next event. The following alarms are received as leak progresses:
Event
XCP-642 3-3: RB ACC AREA RM-G5 HI RAD XCP-642 3-4: RB ACC AREA RM-G5 TRBL XCP-642 3-5: INCOR INSTR AREA RM-G14 HI RAD XCP-642 3-6: INCOR INSTR AREA RM-G14 TRBL AOP-101.1 RO 1 Verify PZR level is at or trending to program level. 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 PCV-145, LO PRESS LTDN. To 70% 2) Ensure PVT-8149A.
LTDN ORIFICE A ISOL. is open. 3) Close both PVT-8149B(C).
LTDN ORIFICE B(C) Appendix D, Page 39 of 39 Scenario Event Description VC Summer-2005-301 Op-Test No.: Scenario No.: Event No.: Page __ of __ Event


== Description:==
== Description:==
Time Position Applicants Actions or Behavior ISOL. 4) Adjust PCV-145. LO PRESS LTDN. to maintain PI-145. LO PRESS LTDN PRESS PSIG. between 300 psig and400 psig. 5) Place PCV-145, LO PRESS LTDN. in AUTO. CRS/RO 2 Check if 51 is required:
 
: a. Check if any of the following criteria are met:
Time Time        Position Position                         Applicants Actions Applicants   Actions or or Behavior Behavior The Letdown leak inside containment is the next event.
* PZR level is decreasing with Charging maximized and Letdown minimized.
The following alarms are received as leak progresses:
* PZR level is approaching 12%.
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.
* PZR pressure is approaching 1870 psig.
level.
* VCT level is approaching 5%. SI should NOT be required, crew should follow AL TERNA TlVE ACTION of step 2 which is to GO TO STEP 3 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-114.002.
IF PZR IF        level is PZR level   is decreasing.
OPERATIONAL LEAK TEST. 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.
decreasing. THENTHEN perform perform the the following:
RO 4 Verify RCS pressure is GREATER THAN 2210 psig. a) Ensure all PZR Heaters are on. b) the PZR Spray Valves are closed c) Ensure the PZR PORVs are closed. IF any PORV fails to close, THEN close its Siock Valve. BOP/CRS 5 Verify no SG tubes are leaking: a. Narrow Range level in no SG is increasing with feed flow LESS THAN steam flow. b. Radiation levels on all of the following are normal:
following:
* RM-G19A(S)(C).
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:
STMLN HI RNG GAMMA.
45 gpm    orifice:
* RM-A9. CNDSR EXHAUST GAS ATMOS MONITOR.
1)Set PCV-145, 1)Set  PCV-145, LO  LO PRESS PRESS LTDN.       To 70%
* RM-L3. STEAM GENERA TOR SLOWDOWN Appendix 0, Page 39 of 39 Scenario Event Description VC Summer-2005-301 Op-Test No.: Scenario No.: Event No.: -----------Page __ of __ Event
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:==
== Description:==


________________________
Event
_ Time Position RO RO RO Applicants Actions or Behavior LIQUID MONITOR.
* RM-LiO. SG BLOWDOWN CW DISCHARGE LIQUID MONITOR. c. No steam flowlfeed flow mismatch (feed flow low). d. As determined by Chemistry sample analysis of ALL SG secondary sides for activity.
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 PRT LVL LO ITEMP/LVLlPRESS HI (XCP-616 4-4). is not lit. d. Verify at least one PZR PORV Block Valve is open. 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 PARTICULATE(IODINE)(GAS)
ATMOS MONITOR. b. RB Sump levels are normal c. RB pressure is LESS THAN 1.5 psig d. The following annunciators are NOT lit:
* RBCU IAl2A DRN FLO HI (XCP-606 2-2).
* RBCU IB/2B DRN FLO HI (XCP-607 2-2). Conditions are not normal, so the alternative action of isolating letdown will be performed.
7 Attempt to isolate leakage as follows: a) Close all Letdown Isolation Valves: 1) PVT-8149A(B)(G)
L TDN ORIFICE A(B)(C) ISOL. 2) LCV-459. L TDN LINE ISOL 3) LCV-460, L TDN LINE ISOL b) Check RCS parameters for indications of leakage. Leakage should be isolated by the above actions. Crew should wait and verify no further leakage occurs. Since Normal Letdown will remain isolated, crew should place EXCESS LETDOWN in service. REFER TO SOP-102. CHEMICAL AND VOLUME CONTROL SYSTEM Appendix D, Page 39 of 39 Scenario Event Description VC Summer-2005-301 Op-Test No.: Scenario No.: Event No.: Page __ of __ Event


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


Time Position Applicants Actions or Behavior I The following is from SOP-102: RO 2.1 Ensure HCV-137, XS LTDN HX, is closed. RO 2.2 Place PVM-8143, XS LTDN TO VCT(PEER D) RO 2.3 If required, reset Phase A Isolation by depressing the following:  
Time Time        Position Position                              Applicants Actions Applicants       Actions oror Behavior Behavior ISOL.
: a. RESET PHASE A -TRAIN A CNTMT ISOL. b. RESET PHASE A -TRAIN B CNTMT ISOL. RO Open the following:  
ISOL.
: a. MVT-81 00, SEAL WTR RTN ISOL. b. MVT-8112, SEAL WTR RTN ISOL. RO 2.5 Ensure MVG-9583, FROM XS L TDN HX, is open. RO 2.6 Open PVT-8153, XS LTDN ISOL. RO 2.7 Open PVT -8154, XS L TDN ISOL. RO 2.8 Establish Excess Letdown flow as follows: a. Slowly throttle open HCV-137, XS LTDN HX. b. Monitor TI-139, XS LETDOWN HX OUT TEMP of, to maintain less than 165&deg;F. c. Monitor the following to ensure flow between 0.2 gpm and 5.0 gpm: 1) FR-154A, RCP SL LKOFF HI RANGE. 2) FR-154B, RCP SL LKOFF LO RANGE. This concludes establishing Excess Letdown. More steps do remain from AOP-101.1 for determining if leakage is isolated, but can commence the A Rep high vibration event at this time. Appendix D, Page 39 of 39 Scenario Event Description VC Summer-2005-301 Op-Test No.: Scenario No.: Event No.: Page __ of __ Event
: 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:==
== Description:==


Time Position Applicants Actions or Behavior Crew receives annunciator XCP-617 1-3: RCPA VIBR HI RO should notice frame and shaft vibration levels are escalating.
== Description:==
A RCP should be secured based on increasing levels. The following steps would apply from SOP-101 for securing the RCP. 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. RO 2.2 If the Reactor Coolant System is solid, place PCV-145, LO PRESS L TDN, in MAN. RO 2.3 Secure one of the following Reactor Coolant Pumps as required:  
Time Time       Position Position                            Applicants Actions Applicants  Actions or or Behavior Behavior MONITOR.
: a. XPP-0030A, PUMP A. RO 2.4 If the Reactor Coolant System is solid, return PCV-145, LO PRESS L TDN, to AUTO, if desired. RO 2.5 Verify Seal Injection to the secured Reactor Coolant Pump using the applicable following indicator:  
LIQUID MONITOR.
: a. FI-130A, RCP A INJ FLO GPM. RO 2.6 Maintain Component Cooling Water to the secured Reactor Coolant Pump thermal barrier until RCS temperature is less than 150&deg;F. BOP 2.7 Place the following controllers in MAN, as required for the affected RCS loop and maintain Narrow Range Steam Generator level between 60% and 65%: Appendix D, Page 39 of 39 Scenario Event Description VC Summer-2005-301 Op-Test No.: Scenario No.: Event No.: Page __ of __ Event
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:==
== Description:==


Time Position Applicants Actions or Behavior a. PVT-478, SG A FWF. b. FCV-3321, LOOP A MAIN FW BYP. CRS 2.8 If not already in Hot Standby, proceed to Hot Standby lAW GOP-5, Reactor Shutdown From Startup To Hot Standby (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. 5x1 0-5% power. Prior to commencing shutdown, should go ahead and begin Small Break LOCA Event. CRS/SE 3.1 Complete GTP-702 Attachment II.K, Operational Mode Change Plant Shutdown -Entering Mode 3 Or Plant Trip To Mode 3 From Modes 1 Or 2. RO 3.2 Select both Intermediate Range Channels on NR-45, NIS RECORDER.
Event


===3.3 Insert===
== Description:==
Control Rods with a manual Reactor trip as follows: CRS a. Perform a Pre-job brief per OAP-100.3, Human Performance Tools. RO b. Select one Intermediate Range and one Source Range Channel on NR-45, NIS RECORDER BOP c. Ensure both Motor Driven Emergency Feedwater Pumps are running. RO d. (Optional)
 
If desired, commence RCS boration prior to performing a manual Reactor trip: 1) Open MVT-81 04, EMERG BORATE. 2) Ensure XPP-13A(B), BA XFER PP A(B), is running. 3) Verify greater than 30 gpm flow on FI-11 0, EMERG BORATE FLOW GPM. 4) Refer to STP-134.001, Shutdown Margin Verification, to determine the required boron concentration needed for the anticipated Plant Mode and temperature:
Time Time  [    Position Position The following The Applicants Applicants Actions following is from from SOP-102:
Anticipated Mode: Anticipated RCS temperature:
SOP-102:
OF Required Boron: ppm 5) When boration is no longer desired, perform the following:
Actions or or Behavior Behavior                I RO                  Ensure HCV-137, 2.1 Ensure      HCV-137, XSXS LTDN HX, is closed.
a) Close MVT-81 04, EMERG BORATE. b) Verify no flow on FI-110, EMERG BORATE Appendix D, Page 39 of 39 Scenario Event Description VC Summer-2005-301 Op-Test No.: __ _ Scenario No.: ____ Event No.: __ _ Page __ of __ Event
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,                                   &deg;F, to maintain less than 165&deg;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:==
== Description:==
.
 
_________________________
Event
_ Time Position RO Applicants Actions or Behavior FLOW GPM. e. Place RX TRIP Switch CS-CR01 in TRIP. f. Verify all Reactor Trip and Bypass Breakers are open. g. Verify all Rod Bottom lights are lit. h. If two or more Control Rods are not fully inserted, then emergency borate as follows: 1) Open MVT-8104, EMERG BORATE. 2) Verify greater than 30 gpm flow on FI-110, EMERG BORATE FLOW GPM. 3) If required, refer to AOP-1 06.1, Emergency 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.  
== Description:==
: i. Verify Reactor Power level is decreasing.  
 
: j. Ensure RCS temperature is being maintained between 555&deg;F and 559&deg;F using the Steam Dump System or Steam line PORVs. k. Place both SOURCE RANGE HIGH FLUX AT SHUTDOWN Switches in BLOCK. I. When Reactor Power decreases below 7.5 x 10-6%, complete the following:
Time Time        Position Position                                  Actions or Applicants Actions Applicants            or Behavior Behavior Crew receives annunciator XCP-617 XCP-61 7 1-3:
: 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.
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.
This concludes the high vibration on A RCP event. The Small Break LOCA event can now commence if not already performed earlier. The following steps would again be the repeat of AOP-101.1 until the size of the leak would require EOP-1.0 entry for TRIP and SI. Appendix D, Page 39 of 39 Scenario Event Oescription VC Summer-2005-301 Op-Test No.: Scenario No.: Event No.: Page __ of __ Event
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&deg;F.
150&deg;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:==
== Description:==


Time Position Applicants Actions or Behavior The following annunciators should come into alarm: XCP 606 2-2: RBCU 1A12A DRN FLO HI XCP 607 2-2: RBCU 1 B/2B DRN FLO HI XCP 616 3-6:PZR PCS LO BU HTRS ON AOP-101.1 1 Verify PZR level is at or trending to program level. 1 IF PZR level is decreasing.
Event
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. To 70% 2) Ensure PVT-8149A.
LTON ORIFICE A ISOL. is open. 3) Close both PVT-8149B(C).
LTON ORIFICE B(C) ISOL. 4) Adjust PCV-145. LO PRESS LTON. to maintain PI-145. LO PRESS LTON PRESS PSIG. Between 300 psig and 400 psig. 5) Place PCV-145, LO PRESS LTON. in AUTO. 2 Check if 51 is required:
: a. Check if any of the following criteria are met:
* PZR level is decreasing with Charging maximized and Letdown minimized.
* PZR level is approaching 12%.
* PZR pressure is approaching 1870 psig.
* VCT level is approaching 5% b. Perform the following:
: 1) Trip the Reactor.
: 2) GO TO EOP-1.0. REACTOR TRIP/SAFETY INJECTION ACTUATION.
WHEN EOP-1.0 Immediate Actions are complete, THEN actuate SI. Appendix 0, Page 39 of 39 Scenario Event Description VC Summer-2005-301 Op-Test No.: Scenario No.: Event No.: Page __ of __ Event


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


Time Position Applicants Actions or Behavior Crew should transition to EOP-1. O. The first 5 steps are immediate operator actions. A Train of SI will fail to actuate in BOTH Manual and Automatic.
Time Time        Position Position                        Applicants Actions Applicants    Actions oror Behavior Behavior
Individual components can be manually started. Reactor will NOT trip in Automatic.
: a. PVT-478,
Reactor can be tripped manually from the BOP side MCB Switch. 1 Verify Reactor Trip:
: a. PVT-478, SG          EWE.
* Trip the Reactor using either Reactor Trip
SG A FWF.
* Verify all Reactor Trip and Bypass Breakers are open.
FCV-3321, LOOP A MAIN FW BYP.
* Verify all Rod Bottom Lights are lit.
: 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).
* Verify Reactor Power level is decreasing.
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%
2 Verify Turbine/Generator Trip: a. Verify all Turbine STM STOP VL 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.
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: &deg;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&deg;F and 559&deg;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:
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 may have actuated by this time. Step 5 is the final immediate action.
* SI ACT status light is bright on XCP-61 07 1-1 . OR
: a. Check if either:
* 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 ACTUATION Switch. c. GO TO Step 6. 6 Initiate ATTACHMENT 3, SI EQUIPMENT VERIFICATION.
                                  *. SI ACT status light is bright on XCP-6107 XCP-61 07 1-1 1-1..
The "B" Charging pump fails to automatically start on S/. The operator is expected to attempt to manually start "B" Charging pump and it will start. Appendix D, Page 39 of 39 Scenario Event Description VC Summer-2005-301 Op-Test No.: ---Scenario No.: Event No.: -------Page __ of __ Event
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:==
== Description:==


________________________
== Description:==
_ Time Position Applicants Actions or Behavior 7 Announce plant conditions over the page system. 8 Verify RB pressure has remained LESS THAN 12 psig on PR-951, RB PSIG (P-951), red pen. 8 Perform the following:
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:
a) Verify both the following annunciators are lit:
* XCP-612 3-2 (RB SPR ACT).
* 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:
* XCP-612 4-2 (PHASE B ISOL).
* Both CS-SGA 1 and CS-SGA2. OR
IF either annunciator is NOT lit, THEN actuate RB Spray by placing the following switches to ACTUATE:
* Both CS-SGB1 and CS-SGB2. b) Verify Phase B Isolation by ensuring RB SPRAY/PHASE B ISOL monitor lights are bright on XCP-61 05. c) Ensure the following are open:
* 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-3001A(B), RWST TO SPRAY PUMP A(B) SUCT.
* MVG-3002A(B), NAOH 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 flow is GREATER THAN 2500 gpm for each operating train on:
* MVG-3003A(B), SPRAY HDR ISOL LOOP A(B).
* FI-7368, SPR PP A DISCH FLOW GPM.
d) Ensure both RB Spray Pumps are running.
* FI-7378, SPR PP B DISCH FLOW GPM. f) Stop all RCPs. 9 Check RCS temperature:
e) Verify RB Spray Spray flow is GREATER THAN 2500 gpm for each operating train on:
* With any Rep running, RCS Tavg is stable at OR trending to 557:F. Appendix D, Page 39 of 39 I Scenario Event Description VC Summer-2005-301 Op-Test No.: Scenario No.: Event No.: -----------Page __ of __ Event
* 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:==
== Description:==


________________________
== Description:==
_ Time Position Applicants Actions or Behavior OR
Time Time        Position Position                           Applicants Actions Applicants  Actions oror Behavior Behavior OR OR
* With no RCP running, RCS Tcold is stable at OR trending to 557"Fc) 9 IF RCS temperature is LESS THAN 557"F AND decreasing, THEN: a) Place the STM DUMP CNTRLControlier 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 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 557"F. e) IF RCS cooldown continues, THEN close:
* 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 Valves, PVM-2801A(B)(C).
* MS Isolation Bypass Valves, PVM-2869A(B)(C).
* MS Isolation Bypass Valves, PVM-2869A(B)(C).
* IF RCS temperature is GREATER THAN 557"F AND increasing, THEN: a) Verify PERMISV C-9 status light is bright on XCP-6114 1-3. b) IF the Condenser is available, THEN ensure Condenser Steam Dump Valves are open. c) IF the Condenser is NOT available, THEN open the Steam line PORVs, PCV-2000(2010)(2020):  
IF RCS temperature is GREATER THAN 557F            557"F AND increasing, THEN:
: 1) Place the PWR RELIEF A(B)(C) SETPT Controllers in MAN and closed. Appendix D, Page 39 of 39 Scenario Event Description VC Summer-2005-301 Op-Test No.: Scenario No.: Event No.: Page __ of __ Event
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:==
== Description:==


Time Position Applicants Actions or Behavior 2) Place the Steamline Power Relief A(B)(C) Mode Switches in PWR RLF. 3) Adjust the PWR RELIEF A(B)(C) SETPT Controllers as necessary to reduce RCS temperature.
Time Time        Position Position                          Applicants Actions Applicants   Actions or or Behavior Behavior
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:
: 2) Place the Steamline Power Relief A(B)(C) Mode Switches in PWR RLF.
* MVG-8000A, RELIEF 445 A ISOL.
: 3) Adjust the PWR   PWR RELIEF RELIEF A(B)(C) SETPT Controllers as necessary to reduce RCS temperature.
* MVG-8000B, RELIEF 444 B ISOL.
10 Check PZR PORVs and Spray Valves:
* MVG-8000C, RELIEF 445 B ISOL. d. Verify at least one PZR PORV Block Valve is open .. 11 Check if RCPs should be stopped: a. Check if either of the following criteria is met:
: a. PZR PORVs are closed.
* Annunciator XCP-612 4-2 is lit (PHASE B ISOL) . OR
: b. PZR Spray Valves are closed.
* RCS pressure is LESS THAN 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, Page 39 of 39}}
: 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}}

Latest revision as of 23:18, 11 March 2020

301 Final Simulator Scenarios (Section 10)
ML101610660
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 03/28/2010
From:
NRC/RGN-II
To:
References
2005-301, 50-395/05-301
Download: ML101610660 (62)
v • d • e


Text

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 <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> to complete, have done 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 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)

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 <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, 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 <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />)

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 <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 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 <br />1.347 hours <br />0.00802 weeks <br />0.00184 months <br /> hours to to complete, complete, have have done done 12 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 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:

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:

    • 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.

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-401.10 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.

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 <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.} 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

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

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%].

[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.
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:

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:

  • . 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:

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:

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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