ML041410415

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V. C. Summer April 2004 Exam 50-395/2004-301 Draft Scenarios
ML041410415
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Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 04/28/2004
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To:
Office of Nuclear Reactor Regulation
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Download: ML041410415 (13)
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Text

V. C. SUMMER EXAM 50-39512004-301 APRIL 19 23,2004 April 28, 2004 (written)

I

Appendix D ........................ . Scenario Oidline F'orm ES-D-1 Facility: V. C. Summer Scenario No.: 1 Op-Test No.: 1 Examiners: Operators:

Initial Conditions: IC-14 100% Power BQL. @% GPD Tube beak on the " A SIG. Erneraency Feed Water Pumo 'B' (XPP-21B) inonerable fur maintenance.

Turnover:

Event I Maif. I Event I Event 40 of 41 NUREG-1021. Draft Revision 9

41 of 41 NUREG-1021, Draft Revision 3 Appendix ......D

............................. Scenario

-................Outline

......................... Form ES-D-1 Facility: V. C. Summer Scenario No.: 2 Op-Test No.: 1 Examiners: Operators:

Initial Conditions: IC-XX 25% Pawer MOL. 25 GPD Tube Leak on the A SIG. Emeraencv Feed Water PumD B (XPP-22 B) inoperable for maintenance. Severe Thunderstorm watch in effect.

Turnover: Ram0 unit UD to 58% Dower Event Malf.

Ne. No.

la N/A Ib N/A 2 cvc-17 3 CND-1 4 MSS9 5 RCS3 PRS5 PRSB pace Break 50gpm to 6QQgpmramped in ever 7  ? Failure of Phase A containment isolation to occur.

I (N)orm vity, (I)nstrument, (C)omponent, (M)ajar 40of 41 NUREG-I 021, Draft Revision 9

Synopsis of Scenario.

Desire is to be at the point that a transfer is being made from bypass FRVs to FRVs. (Whatever power this begins at, and to continue to ramp unit towards 50%.

~

Event 1 Ramp up (Reactivity for RO, and Normal for BOP swapping to FRVs Event 2 Running charging pump has sheared shaft. RQ should start ccw, and another Charging pump and control charging flow.

Event 3 In service Vacuum pump trips, BOP should start standby vacuum pump and open associated valve.

Event 4 Selected steamline flow transmitter fails low, BOP should take manual control and control S/G level.

Event 5 RCP with spray valve trips (does not cause a reactor trip ~ 3 8 %power). 88 takes action to control RCS pressure due to loss of a spray valve.

Event 6 Failure of Pressurizer protection pressure transmitter(Beginning of steam space break).

When steam space break get large enough Crew should SI. Phase A will not actuate( can be performed manually).

Scenario to be terminated at the entry to post loca cooidown and depressurization or at the discretion of the bead Examiner.

41 of 41 NUREG-I 021, graft Revision 9

Appendix D Scenario Outline Form ES-B-1 Facility: V. C. Summer Scenario No.: 3 Op-TeSt NO.: I Examiners: Operators:

Initial Conditions: IC-XX 100% Power EOL. 25 GPP Tube Leak on the " A 36.Residual Heat Removal PumD 'B' (XPP-XXB) inoperable for maintenance. Severe Thunderstorm watch in effect.

Turnover: 100% aower. B RHR lnonerable for two hours RTS 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

-Malf. No.

PRS2 2 NIA 3

~

4 FWM2 EQSl1 FWM-14

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7 RCS5

- a RHRZA (N)orrnal, (R)eac /ity, (I)nstrument, (C)omponent, (M)ajor 400f 41 NUREG-1021, Draft Revision 9

Synopsis of Scenario #3 100% power EOL 'B' RHR pump T/O. LBLOCA with A RHR pump trip requires entry in to Loss of recirculation capability.

Event 1 PT-461 spikes low several times over a 3 minute time frame. Then fails low.(this should isolate letdown.

Event 2 80 Restores letdown.

Event 3 Feedwater heater event HD 02A this should cause a ss c 30 mw load. and lower DA vel.

unit may have to reduce power.

Event 4 Condensate pump trips requiring start of another condensate pump.

Event 5 Loss of 120V instrument bus.

Event 6 FW master controller fails low, this will have the BOP take manual control of FP speed.

Event 7 Large Break LOCA.

Event 8 ' A RHR Pump trips upon startup. Loss of Recirculation cspability.

Scenario to be terminated at the entry to post loca CQOldQWnand depressurization or at the discretion of the bead Examiner.

41 of 41 NUREG-1021, Draft Revision 9

Appendix D Scenario Outline Form ES-D-I Facility: V. C. Summer Scenario No.: 2 Op-Test No.: 1 Examiners: - Operators:

Initial Conditions:- Power MOL. 25 GPD Tube Leak on the "A" §/G. Emeraency Feed Water Pump 'B' (XPP-218) inoperable for maintenance. Severe Thunderstorm watch in effect.

Turnover: Rams unit up to 50% sower

~~

(Nlormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Synopsis of Scenario.

40of 41 NUREG-1021, DraR Revision 9

Desire is to be at the point that a transfer is being made from bypass FRVs to FRVs. (Whatever power this begins at, and to continue to ramp unit towards 50%.

Event 1 Ramp up (Reactivity for RO, and Normal for BOP swapping to FRVs.

Event 2 Running charging pump has sheared shaft. RO should start ccw, and another Charging pump and control charging flow.

Event 3 In service Vacuum pump trips, BOP should start standby vacuum pump and open associated valve.

Event 4 Selected steamline flow transmitter fails low, BOP should take manual control and control S/G level.

Event 5 RCP with spray valve trips (does not cause a reactor trip 4 8 % power). RQ takes action to control RCS pressure due to loss of a spray valve.

Event 6 Failure of Pressurizer protection pressure transmitter(Beginning of steam space break).

When steam space break gel performed manually). 8 rge enough Crew should SI. Phase A will not actuate( can be Scenario to be terminated at the entry to post loca cooldown and depressurization or at the

...~ discretion of the Lead Examiner.

41of 41 NUREG-1021, Draft Revision 9

Appendix D Scenario Outline Form E§-D-I I

Facility: V. C. Summer Scenario No.: 1 Op-Test No.: 1 Examiners: Operators:

I zr Initial Conditions: IC-14 100% Power BOL. @ %GPD Tube Leak on the A SW. Emeraenc)

I Event Description TDEFW over-speeds on start and will not reset.

PRE I TUR 1 (C) .Failure of Turbine to auto trip (operator can trip from MCB).

0ATWS Reactor fails to trip (C)BOP Running EH pump trips. (Must manually start other pump)

(I) BOP Selected P-imp fails low (C) RO Letdown Pressure Control Valve PCV-145 fails closed (N) RO Place excess letdown in service (I) RO PT-444 fails High fd 7iZ/dxc- # .2 (C)BOP FW pump trip (due to EH leak). ts~d.M- 1 2 B

M-All Total Loss of Main Feed.(EH leak gets larger) 0A MDEFW trip on overcurrent. (After first verification) 40of 41 NUREG-1021, Draft Revision 9

  • (Njormal, (Rjeactivity, (Ijnstrument, (C)omponent, (M)ajor Synopsis of Scenario.

are to set the simulator up for an total loss of feed ATWS.

Event..i-%elected P-imp fails low interaction from RO and BOP to take Rods to manual and select out failed channel. Could be diagnosed from either.

3 Event 2'-PCV-I45 fails Closed, this will cause a loss of letdown and the RO will have to deal with relief lifting, isolating letdown. May establish excess letdown.(Could be used as a normal).

Event 3il -PT-444 fails high, this will cause the spray valves to open, one PORV to open. The R 6 will need to close the sprays in manual and close the PORV prior to a trip parameter being met.

After the valves are closed, and parameters are stabilized. The next event can be initiated.

I 5

EventA An EH leak on one of the Main feed pumps causes a loss of the feed pump (only one) after actions are taken to stabilize the plant, the EH leak will get worse and the remaining feed pumps will trip.

wc7 Du- A L - 6 0 !cG%.-& (,*,h.i p z J . 4 s+j< ".,n.-y&. 3 Event 5 the reactor and turbine does not trip, the TDEFW pump trips on overspeed. After the A MDEFW pump is verified running in EOQ-13.0, it will trip on over current. This will put the plant in EOP-13.0 ( The reactor trip breakers will be opened locally when S/G levels are less than 45% wide range). This will cause the crew to go to boss of heat sink / feed and bleed.

Scenario to be terminated at the discretion of the Lead Examiner.

~.~

41of 41 NUREG-I021 Draft Revision 9

Appendix D Scenario Outline Form E§-D-I Facility: V. C. Summer Scenario No.: 3 Bg-Test No.: 1 Examiners: Operators:

~-

watch in effect.

Turnover: 100% Dower. B RHR Inoperable for two hours RTS 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

. And cause crew to

...... I (i<)orniti!,

.......L !..

(H)eactivity, (I)ristruinent, (C)cmponwt. (h4)aior Synopsis of Scenario #3 40of 41 NUREG-1024, Draft Revision 9

100% power EQL 'B' RHR pump T/O. LBLOCA with A RHR pump trip requires entry in to Loss of recirculation capability.

Event 1 PT-461 spikes low several times over a 3 minute time frame. Then fails low.(this should isolate letdown.

Event 2 RO Restores letdown.

Event 3 Feedwater heater event HDO3-028 this should cause a loss of 30 mw load, and lower DA level, unit may have to reduce power.

Event 4 Condensate pump trips requiring start of another condensate pump.

Event 5 Loss of 12OV instrument bus.

Event 6 FW master controller fails low, this will have the BOP take manual control of FP speed.

Event 7 Large Break LOCA.

Event 8 'A RHR Pump trips upon startup. Less of Recirculation capability.

Scenario to be terminated at the entry to post loca cooldewn and depressurization or at the discretion of the Lead Examiner.

410f 41 NUREG-1021, Draft Revision 9

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