Text

301 Final SRO Exam (Part 2 of 2)
	ML091320204
Person / Time
Site:	Hatch
Issue date:	05/01/2009
From:	; NRC/RGN-II
To:	;
References
	Download: ML091320204 (62)
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58.

Unit 2 is operating at 100% power.

o 2T41-C007B, "Rx Bldg Vent Exhaust Fan," is tagged out o 2T41-C007A, "Rx Bldg Vent Exhaust Fan," Trips With no operator action, which ONE of the following predicts how the Rx. Bldg differential pressure (DP) and Rx. Bldg monitored radioactive release rate will be affected?

The Rx. Bldg negative pressure will be (1) before the fan tripped.

The Rx. Bldg stack release rate will be (2) before the fan tripped A. (1) the same as (2) higher than B. (1) the same as (2) lower than

c. (1) less than (2) higher than D. (1) less than (2) lower than Page: 58 of 100 4/28/2009

59.

Unit 1 was operating at 100% power when a reactor scram occurred.

IMMEDIATELY following the scram, the APRMs indicate reactor power is at 5%

o Standby Liquid Control (SBLC) has NOT been injected.

10 minutes LATER Rod Worth Minimizer (RWM) displays the following:

Based on these conditions, which ONE of the following completes both of these statements?

lAW 31EO-EOP-103-1, "Control Rod Insertion Methods," RWM (1) required to be bypassed to insert control rods.

With the current control rod configuration, the reactor (2) remain subcritical under ALL conditions, without boron injection.

A. (1) is (2) will B. (1) is (2) will NOT C. (1) is NOT (2) will D. (1) is NOT (2) will NOT Page: 59 of 100 4/28/2009

60.

Unit 1 is operating at 18% power.

The following alarms are received soon after a cold water injection into the reactor:

o MAIN STEAM LINE RADIATION HIGH (601-425) o MAIN STEAM LINE RADIATION HIGH-HIGHJINOP (603-125) o Main Steam Line radiation levels are 6,000 mRem/hr (increasing) o Main Steam Isolation Valves are OPEN o IB31-FOI9 and IB31-F020, "Reactor Recirculation Sample Valves" are CLOSED Which ONE of the following identifies whether all automatic actions have occurred and the required action(s) IAW 34AB-B21-001-1, "Main Steam Line High Radiation or Suspected Fuel Element Failure."

All automatic actions _ _ _ occurred and the operator is required to _ _ _ _ __

A. have; scram the reactor and then close the MSN s.

B. have; perform a fast reactor shutdown IAW 34GO-OPS-014, "Fast Reactor Shutdown," and then close the MSNs.

C. have NOT; scram the reactor and then close the MSN s.

D. have NOT; perform a fast reactor shutdown IAW 34GO-OPS-014, "Fast Reactor Shutdown,"

and then close the MSN s.

Page: 60 of 100 4128/2009

61.

Unit 2 is shutting down for a refueling outage.

o Instrument Air has been aligned to the DW.

o At 10:00 a pneumatics header line breaks inside the DW causing an air flow rate of 50 SCFM Which ONE of the following choices completes this statement?

Air being supplied to the DW pneumatics header isolation valves (1) automatically isolate (2)

A. (1) will (2) immediately B. (1) will (2) following a 10 minute delay C. (1) will NOT (2) because the Instrument Air flow is below the DW Pneumatics isolation setpoint D. (1) will NOT (2) because the flow rate sensing point is upstream of where the Instrument Air ties into the DW Pneumatics header Page: 61 of 100 4/28/2009

62.

Unit 1 was operating at 100% power when a total loss of Reactor Building Closed Cooling Water (RBCCW) occurred.

With NO operator action, which ONE of the following describes how the Reactor Water Cleanup System (RWCU) will be affected?

(1) will automatically close when the RWCU Non-Regenerative Heat Exchanger outlet temperature increases to AT LEAST (2) .

A. (1) ONLY IG31-POOl, "Rx Water Cleanup Vlv" (2) 1300 p B. (1) ONLY IG31-P004, "Rx Water Cleanup Vlv" (2) 1300 p

c. (1) ONLY IG31-POOl, "Rx Water Cleanup Vlv" (2) 1400 p D. (1) ONLY IG31-P004, "Rx Water Cleanup Vlv" (2) 1400 p Page: 62 of 100 4128/2009

63.

Unit 1 has experienced an accident that results in these Primary Containment parameters:

o Hydrogen concentration .... 8%

o Oxygen concentration ....... 7%

o Drywell (DW) pressure .... 14 psig and slowly increasing o Torus level ........................ 280 inches (steady)

Which ONE of the following identifies a required action IAW 31EO-PCG- 001-1, "Primary Containment Gas Control" chart, and the reason for this action?

Given these conditions, the operator is required to _ _ _ _ __

A. spray the DW to reduce the flammability AND scrub radionuclides B. spray the DW ONLY to reduce the flammability. Spray flow does NOT scrub radionuclides.

C. vent the Suppression Chamber to reduce the flammability AND scrub radionuclides D. vent the Suppression Chamber ONLY to reduce the flammability. Venting through the Torus does NOT scrub radionuclides.

Page: 63 of 100 4/28/2009

64.

A fire is reported on Unit 1, in the "IF" 4I60VAC bus.

The fIre suppression that is available in this room is _ __

A. automatically actuated Carbon Dioxide agent B. automatically actuated Halon agent C. manually actuated Carbon Dioxide agent D. manually actuated Halon agent Page: 64 of 100 4128/2009

65.

Which ONE of the following completes BOTH statements regarding degraded system voltage lAW 34AB-Sll-00I-0, "Operation With Degraded System Voltage"?

The normal minimum voltage at the 230KV bus with either Unit in Modes 1, 2, or 3 is _ _.

IF the 4160VAC bus voltages can NOT be restored and maintained above a minimum of , TIffiN within 30 minutes start the Emergency Diesel Generators.

A. 233KV; 3825 volts B. 233KV; 3255 volts C. 225KV; 3825 volts D. 225KV; 3255 volts Page: 65 of 100 4/28/2009

66.

Which ONE of the following defines the purpose of the Rod Worth Minimizer (RWM) lAW Technical Specifications.

A. Ensures that fuel enthalpy does not exceed 280 cal/gm during a control rod drop accident when power is 2:: 29%.

B. Ensures that fuel enthalpy does not exceed 280 cal/gm during a control rod drop accident when reactor power is < 10%.

C. Ensures that the Minimum Critical Power Ratio remains greater than 1.08, while withdrawing control rods, when power is 2:: 29%.

D. Ensures that the Minimum Critical Power Ratio remains greater than 1.08, while withdrawing control rods, when reactor power is < 10%.

Page: 66 of 100 4/28/2009

67.

Unit 2 RCIC has tripped with an Initiation Signal present. The trip condition has been corrected and RCIC is needed for injection.

Pf*LAMPIKEY PFUGHT ON SETPOIHT OFF flOW NOTE: The light next to the "M" on the above controller is ILLUMINATED.

Which ONE of the following completes the following statements lAW 34S0-E51-001-2, "Reactor Core Isolation Cooling (RCIC) System"?

The controller (1) setup correctly for a manual RCIC start with an initiation signal present.

This controller is located on panel (2)

A. (1) is (2) 2Hll-P601 B. (1) is NOT (2) 2Hll-P601 C. (1) is (2) 2HII-P602 D. (1) is NOT (2) 2HII-P602 Page: 67 of 100 4/28/2009

68.

Which ONE of the following choices completes this CAUTION in 34GO-OPS-OOl-I, "Plant Startup"?

Extended operation (1) is undesirable. The decision to continue operation in this condition will require the approval of the manager Operations. If the startup is to be suspended for an extended period of time, the control rods will normally be (2)

A. (1) just below or just above the point of criticality (2) inserted to an all rods in condition to ensure subcriticality B. (1) just below or just above the point of criticality (2) notched in and out to maintain power at the Point Of Adding Heat

c. (1) in the OPRM ARMED region ofthe Power to Flow map (2) withdrawn using the continuous withdraw method instead of raising Recirculation Flow to exit the region D. (1) in the OPRM ARMED region of the Power to Flow map (2) restricted to the single notch withdrawal method instead of raising Recirculation Flow to exit the region Page: 68 of 100 4128/2009

69.

The crew is implementing a tagout for the Unit 2 Core Spray system and the 2E21-FOI9A, "Torus Suction Valve" keylock control switch at panel P601 has been placed in the "CLOSED" position.

STRAINERS

I I

I I

I N.D.

---_If! I 1_ REF.19

~3-X2~ I I P601 SHT.2 I KEY LOCK AO I~r-O~

F019 A L-c=J~~C Which ONE of the following predicts how the valve and actuator will respond if the solenoid valve power is removed?

2E21-F019A will 0)

Air will be (2) the 2E21-F019A actuator.

A. (1) stroke open (2) vented off of B. (1) stroke open (2) supplied to

c. (1) remain closed (2) vented off of D. (1) remain closed (2) supplied to Page: 69 of 100 4/28/2009

70.

The MCPR fuel cladding integrity Safety Limit ensures that:

A. during normal operation and transients at least 99.9% due NOT experience Transition Boiling.

B. the peak cladding temperature during the design basis LOCA does not exceed the limits in 10CFR46.

C. the calculated total oxidation of the cladding shall no where exceed 0.17 times the total cladding thickness before oxidation.

D. fuel thermal-mechanical design limits are not exceeded any where in the core during normal operation.

Page: 70 of 100 4/28/2009

71.

Unit 1 is at 100% power, late in core life.

o The "lB" Control Rod Drive (CRD) pump is tagged out o All control rods are withdrawn The following sequence of events occur:

o 10:00 the "lA" CRD pump trips o 10:05 an operator attempts to restart the "IA" CRD pump and is NOT successful o 10: lOa System Operator reports several CRD scram accumulators are less than 940 psig IAW with Tech Specs 3.1.5, which ONE ofthe following is the LATEST time that the Reactor Mode Switch MUST be in the Shutdown position?

A. 10:00 B. 10:10 C. 10:30 D. 11:00 Page: 71 of 100 4/28/2009

72.

Unit 1 was at 35% power when the Hydrogen Injection System was placed in service in AUTOMATIC - EXTERNAL mode IAW 34S0-P73-00l-1, "Hydrogen and Oxygen injection and Control for HWC" section 7.1.2, "Placing IP73-R025, Hydrogen Controller, in EXTERNAL."

o Power is raised from 35% power to 100% power o At 100% power hydrogen flow rate indicates 40 SCFM Which ONE of the following answers both of these statements?

IAW 34S0-P73-001-1, "Hydrogen and Oxygen injection and Control for HWC", hydrogen injection flow rate is the normal 100% power flow rate.

Radiation levels in the Condenser Bay will stabilize ___ expected normal full power radiation levels.

A. above; at B. below; at C. below; below D. above; above Page: 72 of 100 4/28/2009

73.

Unit 1 is shutting down for a refueling outage.

o A nonnal "Initial" Drywell (DW) entry at power is required.

Which ONE of the following completes the following statement lAW 31 GO-OPS-005-0, "Primary Containment Entry."

Before a nonnal "Initial" DW entry is allowed, Oxygen (02) concentration must be at least

_ _ _ and reactor power must be less than or equal to _ __

A. 19.5%;

10%

B. 19.5%;

15%

C. 23.5%;

10%

D. 23.5%;

15%

Page: 73 of 100 4128/2009

74.

Unit 1 is operating at 70% power when a transient occurs.

Current plant conditions:

o Reactor water level ............ +5 inches (lowest level reached) o Reactor pressure................ 1080 psig (highest pressure reached) o Drywell pressure ................ 1.90 psig (highest pressure reached)

Which ONE of the following completes both of these statements?

Entry conditions have been met or exceeded _-->..;(1::....<.)_ _ Emergency Operating Procedure (EOP) flow chart(s).

lAW 34AB-C71-001-2, "Scram Procedure", performance ofthe RC-l, RC-2 and (2) placards are required IMMEDIATE actions.

A. (1) ONLY for the Reactor Controls (RC)

(2) TC-l B. (1) ONLY for the Primary Containment (PC)

(2) RC-3

c. (1) for BOTH the RC and PC (2) RC-3 D. (1) for BOTH the RC and PC (2) TC-l Page: 74 of 100 4128/2009

75.

Unit 2 is in Mode 3.

o Reactor pressure ................... 35 psig o Reactor Water Level ............ 40 inches (stable) o Main Condenser Vacuum .... "0" in. Hg. Vac o The "2B"Residual Heat Removal (RHR) pump is operating in Shutdown Cooling (SDC) o The "2A" loop of RHR is tagged out A Logic System Functional Test results in an inadvertent High Drywell pressure LOCA signal that can NOT be reset.

Which ONE of the following predicts BOTH the status of "2B" RHR pump and how reactor pressure will be controlled lAW 34S0-EII-01O-00l-2, "RHR System" and/or 34AB-EII-00l-2, "Loss of SDC"?

The "2B" RHR pump _->..(""'-0<---_ and reactor pressure will be controlled by _ _..>..:(2::..L)_ _

A. (1) remains running (2) raising RWL to the Main Steam Lines (MSL) and opening the MSL drain valves, defeating the low vacuum trips as necessary.

B. (1) remains running (2) opening the MSN s and using the Main Turbine Bypass Valves to send steam to the Main Condenser, defeating the low vacuum trips as necessary.

c. (1) trips (2) opening the MSN s and using the Main Turbine Bypass Valves to send steam to the Main Condenser, defeating the low vacuum trips as necessary.

D. (1) trips (2) raising RWL to the Main Steam Lines (MSL) and opening the MSL drain valves, defeating the low vacuum trips as necessary.

Page: 75 of 100 4/28/2009

76.

Unit 1 is in Mode 5 with all control rods fully inserted and Shutdown Cooling In Service. Both RPS MG Sets are in service following the completion of 57SV-C71-005-1, RPS Power Monitors Ff&c.

While reviewing the completed surveillance package, the SS notes the following "AS LEFT" trip setpoints for two Equipment Protection Circuit Breakers:

1C71-P003A 1C71-P003C Breaker 52-3A Breaker 52-3C Overvoltage 131.5 volts 131.4 volts Undervoltage 107.6 volts 108.1 volts Underfrequency 56.8 Hz 57.7 Hz Which ONE of the following identifies the status of the Equipment Protection Circuit Breakers and the required action, if any?

[Reference provided]

A. ONLY one breaker is INOPERABLE; no required Tech Spec actions at this time B. BOTH breakers are INOPERABLE; no required Tech Spec actions at this time C. ONLY one breaker is INOPERABLE; place the associated RPS Bus on the alternate power supply in 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months D. BOTH breakers are INOPERABLE; place the associated RPS Bus on the alternate power supply in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Page: 76 of 100 4/28/2009

77.

Unit 2 is in Mode 4 and the "B" loop of RHR is in Shutdown Cooling.

Which ONE of the following identifies the low suction pressure trip setpoint for the Fuel Pool Cooling Pump and the required action in accordance with 34AB-G41-001, "Loss of Fuel Pool Cooling," if the pump trips and is no longer available?

A. 8 psig; Place RHR in the Fuel Pool Cooling Assist Mode B. 8 psig; Install 2 digital temperature monitoring instruments in the fuel pool C. 3 psig; Place RHR in the Fuel Pool Cooling Assist Mode D. 3 psig; Install 2 digital temperature monitoring instruments in the fuel pool Page: 77 of 100 4128/2009

78.

Which ONE of the following identifies the minimum number of SRVs required for emergency depressurization in accordance with 3 1EO-EOP-O 15-2, "CP-l Flowchart," and the EOP bases for this minimum number of SRVs?

A. 4; This is the least number of SRVs that can evenly distribute the heat load in the Suppression PooL B. 5; This is the least number of SRV s that can evenly distribute the heat load in the Suppression PooL C. 4; This is the least number of SRVs that the ECCS makeup flow can accommodate given the amount of steam flow that occurs at the minimum alternate RPV Flooding pressure.

D. 5; This is the least number of SRVs that the ECCS makeup flow can accommodate given the amount of steam flow that occurs at the minimum alternate RPV Flooding pressure.

Page: 78 of 100 4/28/2009

79.

Given the following plant conditions:

o A steam line break inside the Drywell o All R WL instruments display erratic indication simultaneously The steps to perform Emergency Depressurization for these conditions are contained on EOP flowchart _ __

Assuming Drywell temperature is at 215°P, the Wide Range RWL Instruments

_ _ _ be used to determine RWL after the Minimum Core Flooding Interval has been completed.

A. CP-IONLY; can B. CP-2 ONLY; can C. CP-IONLY; canNOT D. CP-2 ONLY; canNOT Page: 79 of 100 4128/2009

80.

Unit 2 was operating at 100% power when a loss of 600VAC "2D" occurred.

Which ONE of the following choices completes both of these statements concerning the power supply for 2R25-S063, Vital AC Distribution Bus and Tech Specs applicable to 600 V AC "2D" and Essential Cabinet "2B"?

lMMEDlATELY following the loss of 600VAC "2D", 2R25-S063 will be powered from (1) ill accordance with Tech Specs, a Required Action Statement must be entered for (2)

A. (1) the Vital AC Batteries (2) 600VAC "2D" ONLY B. (1) 600 V AC "2C" (2) 600VAC "2D" ONLY C. (1) the Vital AC Batteries (2) 600VAC "2D" AND also for Essential Cabinet "2B" D. (1) 600 V AC "2C" (2) 600VAC "2D" AND also for Essential Cabinet "2B" Page: 80 of 100 4/28/2009

81.

Unit 1 is operating at 100% power and the following conditions currently exist:

o Primary containment venting is in progress IAW 34S0-T 48-002-1, Containment Atmospheric Control and Dilution Systems o Drywell pressure is 0.6 psig and steady o Drywell unidentified leakage has risen from the previous steady state value of 3 gpm to 55 gpm over the last 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Which ONE of the following completes the following statement?

In accordance with _ _ _ _ , the SOONEST required action is to _ _ __

A. 73-EP-EIP-00I-0, Emergency Classification & Initial Actions; declare an emergency within 15 minutes based on the RCS leak rate B. 73-EP-EIP-00I-0, Emergency Classification & Initial Actions; declare an emergency within 15 minutes based on drywell pressure C. 00AC-REG-00I-0, Reporting Requirements - Form REG 0024; make a 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months report to the NRC based on the initiation of any nuclear plant shutdown required by the plant's tech specs D. 00AC-REG-00I-0, Reporting Requirements - Form REG 0024; make an 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months report to the NRC based on the condition of the nuclear plant, including its principal safety barriers, being seriously degraded Page: 81 of 100 4/28/2009

82.

Unit 2 was operating at 100% power when an unisolable steam line break occurred in the Main Steam Line Tunnel area.

The following Reactor Building radiation conditions currently exist:

o 2D11-K609A,RBPOTCONTAMAREARADIATION ..................... 22mR1hr o 2D11-K609B,RBPOTCONTAMAREARADIATION ..................... 20mRIhr o 2Dll-K609C, RB POT CONTAM AREA RADIATION ..................... 20 mRlhr o 2Dll-K609D, RB POT CONTAM AREA RADIATION ..................... 19 mRlhr o 2D21-K601F, 130' ELEVATION AREA (NORTHWEST) Tip Area .... 1100 mRlhr o The next highest area radiation reading ................................................... 200 mRlhr Which ONE of the following choices completes the following statements?

The Unit 2 Standby Gas Treatment system (1) received an auto start signal.

IAW 31EO-EOP-014-2, "Secondary Containment Flowchart," the SS is required to enter (2)

A. (1) has (2) 34GO-OPS-13-2, "Plant Shutdown" B. (1) has (2) 31EO-EOP-OIO-2, "RC RPV Control" point A C. (1) has NOT (2) 34GO-OPS-13-2, "Plant Shutdown" D. (1) has NOT (2) 31EO-EOP-OIO-2, "RC RPV Control" point A Page: 82 of 100 4128/2009

83.

Unit 1 was operating at 50% power when a scram occurs due to a loss of feedwater.

45 seconds after the Scram the following conditions exist:

o Reactor Mode switch ........... SHUTDOWN o Reactor power .... ...... ........... 10%

o Reactor pressure .... ..... .... ..... 1000 psig, highest since scram and stable o Reactor water level ............... -40 inches, lowest since scram and slowly decreasing o )Hll-P603 RPS White scram lights ....... "A" Channel EXTINGUISHED

..1.- "B" Channel ILLUMINATED o Full Core Display blue scram lights ......... llluminated Which ONE of the following choices completes both of these statements?

The _ _~(1:o....1)'--_ _ depressurized the Scram air header.

The Shift Supervisor is required to enter _ _(>..:2:..L.)_ _ IAW 31EO-EOP-0l1-1, "RCA RPV Control ATWS."

A. (1) Alternate Rod Insertion (ARI) Valves (2) 31EO-EOP-103-1, "Control Rod Insertion Methods" B. (1) Alternate Rod Insertion (ARI) Valves (2) 34AB-C11-005-1, "Control Rod Insertion Methods"

c. (1) Backup Scram Valves (2) 31EO-EOP-103-1, "Control Rod Insertion Methods" D. (1) Backup Scram Valves (2) 34AB-C11-005-1, "Control Rod Insertion Methods" Page: 83 of 100 4128/2009

84.

A reactor scram has occurred on Unit 2 and the following conditions currently exist:

o Reactor Power .............................. 7%

o Reactor water level...................... -38 inches (stable) o Reactor pressure .......................... 350 psig (slowly decreasing) o DW pressure ................................ 1.7 psig (stable)

Which ONE of the following choices completes the following statement IAW 3IEO-EOP-1l7-2, "CP-3, ATWS Level Control"?

Reactor Water Level (1) required to be lowered and the SS is required to enter (2)

A. (1) is (2) 31EO-EOP-114-2, "Preventing mjection into the RPV" B. (1) is NOT (2) 31EO-EOP-114-2, "Preventing mjection into the RPV" C. (1) is (2) 31EO-EOP-113-2, "Terminating and Preventing mjection into the RPV" D. (1) is NOT (2) 31EO-EOP-llO-2, "Alternate RPV Water Level Control" Page: 84 of 100 4128/2009

85.

Today is December 13, 2009 and Unit 2 has just commenced a startup. As the reactor operator was completing the withdrawal of the 9th control rod, the following annunciator began alarming:

RMCSIRWM ROD BLOCK OR SYSTEM TROUBLE (603-239)

After further investigation, the SS declared the Rod Worth Minimizer (RWM) inoperable. The last startup was conducted on February 22,2009 and the RWM was also inoperable at that time, i.e., the last startup was conducted without RWM available.

Which ONE of the following identifies whether rod movement (withdrawal and insertion) can administratively continue and any required actions in accordance with Tech Spec 3.3.2.1, Control Rod Block mstrumentation?

A. Rod withdrawal and insertion can continue ONLY if a 2nd licensed operator verifies the pull sequence and the RWM is manually bypassed.

B. Rod withdrawal and insertion can continue without any restrictions if the RWM is manually bypassed.

C. Rod withdrawal is NOT allowed. Rod insertion is NOT allowed except by scram.

D. Rod withdrawal is NOT allowed. Rod insertion is allowed ONLY if a 2nd licensed operator verifies the insertion sequence and the RWM is manually bypassed.

Page: 85 of 100 4/28/2009

86.

Unit 1 was at 80% power when an unisolable Main Steam Line break occurred in the Turbine Building.

The following conditions currently exist:

o Prompt Offsite Dose results ... ..... ............... 1050 mRlhr peak TEDE o Reactor power ............................................. All Rods Full-In o Reactor pressure .......................................... 900 psig o Reactor Water Level............. ................ ...... 35 inches Which ONE of the following choices completes both of the following statements?

IAW with 31EO-EOP-014-1, "Radioactivity Release Control" EOP flowchart, the crew (1) required to emergency depressurize the reactor.

IAW 73EP-EIP-00l-0, "Emergency Classification and Initial Actions", the crew (2) required to declare a General Emergency.

A. (1) is (2) is B. (1) is (2) is NOT C. (1) is NOT (2) is D. (1) is NOT (2) is NOT Page: 86 of 100 4/28/2009

87.

Unit 1 is in Mode 3 and the following conditions exist:

o "IB" Residual Heat Removal (RHR) aligned for Shutdown Cooling (SDC) o "IB" RHR loop flow ...................... 7,700 gpm o Reactor Coolant temperature ......... 274°F o Reactor Pressure ......................... ... 30 psig o Reactor Water Level ...................... +37 inches o Both Reactor Recirculation Pumps are secured The "IB" RHR pump trips and neither RHR loop can be aligned for SDC.

Which ONE of the following answers both of these statements?

Reactor water level (1) adequate to ensure there is a flow path available for reactor coolant natural circulation.

The operator is required to increase monitoring of temperature and pressure IAW 34AB-EII-00I-I, "Loss of Shutdown Cooling," by using (2)

A. (1) is (2) 34GO-OPS-013-I, "Normal Plant Shutdown," Attachment 1, "Cooldownl Depressurization Check" B. (1) is NOT (2) 34GO-OPS-013-I, "Normal Plant Shutdown," Attachment 1, "Cooldownl Depressurization Check"

c. (1) is (2) 34GO-OPS-OI5-I, "Maintaining Cold Shutdown or Refuel Condition," Attachment 1, "Monitoring Cold Shutdown And Refuel Parameters" D. (1) is NOT (2) 34GO-OPS-OI5-I, "Maintaining Cold Shutdown or Refuel Condition," Attachment 1, "Monitoring Cold Shutdown And Refuel Parameters" Page: 87 of 100 4/28/2009

88.

Unit 2 is in Mode 5, with fuel movement in progress. The Refueling Bridge mast temporarily binds as an irradiated fuel bundle is being lowered toward the core. The bundle drops from the grapple and lands on the top of the core.

The following two annunciators alarm:

o REFUELING FLOOR VENT EXHAUST RADIATION HIGH (601-409-2) o REFUELING FLOOR VENT EXHAUST RADIATION HI-fi (601-403-2)

Which ONE of the following choices completes the following statements?

The annunciator setpoint is the maximum normal operating value, which requires entering SC-Secondary Containment Control Flowchart (31-EO-EOP-014).

IAW 31EO-EOP-014-2, "Secondary Containment Control" (SC chart), the operator is required to perform actions IAW _ _ _ __

A. REFUELING FLOOR VENT EXHAUST RADIATION HIGH; 34AB-T22-003-2, "Secondary Containment ControL" B. REFUELING FLOOR VENT EXHAUST RADIATION HI-HI; 34AB-T22-003-2, "Secondary Containment ControL" C. REFUELING FLOOR VENT EXHAUST RADIATION HIGH; 34S0-T41-006-2, "Refueling Floor Ventilation System."

D. REFUELING FLOOR VENT EXHAUST RADIATION HI-HI; 34S0-T41-006-2, "Refueling Floor Ventilation System."

Page: 88 of 100 4128/2009

89.

Unit 2 scrammed on low reactor water level due to a loss of the Condensate system.

Current plant conditions are:

Control rods ................................... Fully inserted

Reactor Water Level.................... -135 inches and stable

Reactor Pressure ........................... 900 psig, being controlled by LLS

Torus Level ................................... 180 inches and slowly increasing

Torus Temperature ........................ 192°F and slowly increasing Which ONE of the following choices answers both of these statements lAW 31EO-EOP-012-2, Primary Containment Control EOP Flowchart?

The plant is in the (1) region of the Heat Capacity Temperature Limit (HCTL).

If the plant enters the UNSAFE region, then the operator (2) allowed to reduce pressure and return to the SAFE region to avoid an unnecessary Emergency Depressurization.

Reference provided A. (1) Safe (2) is B. (1) Safe (2) is NOT C. (1) Unsafe (2) is D. (1) Unsafe (2) is NOT Page: 89 of 100 4/28/2009

90.

A small break Loss Of Coolant Accident (LOCA) has occurred on Unit 2.

The following conditions exist:

o Control Rods ...................................... All Rods ill o Reactor Water Level ..... ..................... 9 inches / stable o Torus Level ........................................ 150 inches / slowly increasing o Drywell pressure ............. ................... 4 psig / slowly increasing o Bulk Average Drywell temperature ... 2700 P / slowly increasing Based on these conditions, the operator is required to enter _~C1,-,-)__ and _ _.l.!(2:="L)_ _

Reference provided A. (1) 31EO-EOP-100-2, "Miscellaneous Emergency Overrides" (2) override the LOCA signal to the drywell cooling fans B. (1) 31EO-EOP-100-2, "Miscellaneous Emergency Overrides" (2) override the LOCA signal to the drywell chillers

c. (1) 34S0-EII-01O-2, "RHR System" (2) initiate RHR in the Drywell Spray mode D. (1) 34S0-EII-01O-2, "RHR System" (2) initiate RHR in the Torus Spray mode Page: 90 of 100 4/28/2009

91.

Unit 1 is in Mode 5.

o Boil Off time as calculated from Attachment 2, Vessel and Cavity Boil Off Time, of 34AB-EII-00l-1, "Loss of Shutdown Cooling" has been exceeded following a sustained loss of Shutdown Cooling o Secondary Containment is NOT intact and a radiation release is occurring that can NOT be terminated o A General Emergency has been declared 73EP-EIP-018-0, "Prompt Offsite Dose Assessment", results indicate the following dose values exist:

o 1 mile is 5 REM TEDE o 10 miles is 0.5 REM TEDE lAW NMP-EP-109, Protective Action Recommendations, the Emergency Director will issue _ _ _ __

Reference Provided A. PAR 1 B. PAR2 C. PAR3 D. PAR4 Page: 91 of 100 4128/2009

92.

Unit 1 is operating at 100% power when one Reactor Water Cleanup (RWCU) temperature switch (lG31-N062A - Hx Room) fails upscale.

Which ONE of the following identifies how this temperature switch failure will affect the RWCU system and the action required IAW Tech Specs?

References provided A. RWCU will auto isolate; Place the channel in the tripped condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

B. RWCU will NOT auto isolate; Isolate the affected penetration flowpath within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

C. RWCU will auto isolate; Tracking RAS only.

D. RWCU will NOT auto isolate; Place the channel in the tripped condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Page: 92 of 100 4128/2009

93.

Unit 1 is operating at 100% power with the "IB" Residual Heat Removal (RHR) Pump tagged out.

o A fuel oil fire ignites on the "IA" Emergency Diesel Generator (EDG) o The "IA" EDG room CO2 system did NOT automatically actuate o The red ready light in the hall next to "IA" EDG room door is EXTINGUISHED Which ONE of the following choices completes both of these statements?

IAW 34S0-X43-005-0, "Diesel Generator Building Carbon Dioxide System," the action(s) that must be taken INSIDE the EDG building to manually actuate the "IA" EDG CO2 system is to (1)

Four hours after the "IA" EDG is declared inoperable, the plant (2) required to enter Tech Spec LCO 3.0.3.

A. (1) depress and hold the "IA" EDG room CARDOX START pushbutton (2) is B. (1) depress and hold the "IA" EDG room CARDOX START pushbutton (2) is NOT C. (1) place the "IA" EDG room CARDOX Pilot Control Valve in the OPEN position.

(2) is D. (1) place the "IA" EDG room CARDOX Pilot Control Valve in the OPEN position.

(2) is NOT Page: 93 of 100 4128/2009

94.

Which ONE of the following choices answers both of these statements The procedure than contains the guidance for whose authority is required to reset lockout relays and relay targets is _ _ _ __

The MINIMUM authorization(s) required to reset the Unit 1 Recirculation Pump MG Set Lock-out Relays after the trip cause has been investigated and considered NOT to be detrimental to the equipment is/are _ _ __

A. 31-GO-OPS-021, "Manipulation of Controls and Equipment" the Shift Supervisor AND Shift Manager B. 31-GO-OPS-021, "Manipulation of Controls and Equipment" the Shift Supervisor C. 30AC-OPS-003, "Plant Operations" the Shift Manager AND Shift Supervisor D. 30AC-OPS-003, "Plant Operations" the Shift Supervisor Page: 94 of 100 4128/2009

95.

Which ONE of the following identifies an activity that requires a Temporary Modification (TM) tag and whether a Plant Review Board's (PRB) review is required to implement the TM lAW 40AC-ENG-018-0, "Temporary Modification Control"?

Note: Assume that neither activity is a tag hanging hazard.

A. Pulling the annunciator card for "CORE SPRAY SYSTEM II ACTUATED", (601-101) to disable a nuisance alarm; A PRB review is required.

B. Pulling the annunciator card for "CORE SPRAY SYSTEM II ACTUATED", (601-101) to disable a nuisance alarm; A PRB review is NOT required.

C. Changing the Unit 2 HPCI oil filter from a standard cartridge oil filter to a water scavenging oil filter for one week; A PRB review is required.

D. Changing the Unit 2 HPCI oil filter from a standard cartridge oil filter to a water scavenging oil filter for one week; A PRB review is NOT required.

Page: 95 of 100 4128/2009

96.

Which ONE of the following completes these two statements IAW NMP-AD-006, "Infrequently Performed Tests and Evolutions" (IPTE)?

The lowest level of authority that is allowed to perform the function of "Senior Line Manager" (SLM) is an off-duty (1)

The SLM conducting the brief (2)

_>=.L._ have a direct role in the performance of the test/evolution.

A. (1) Shift Supervisor (2) must B. (1) Shift Supervisor (2) can NOT C. (1) Shift Manager (2) must D. (1) Shift Manager (2) can NOT Page: 96 of 100 4/28/2009

97.

A major Loss of Coolant Accident (LOCA) has occurred on Unit 2.

The following conditions currently exist:

o Drywell Pressure ........................... 54 psig, slowly increasing o Torus Pressure .......... .... ... .............. 52 psig, slowly increasing o Drywell Radiation ......................... 2500 RIHr, slowly increasing o Reactor water level ........................ -165 inches, stable o Wide Range Torus Water Level..... > 300 inches Which ONE of the following identifies the required procedure to vent the Primary Containment and the release rate requirements during the venting process lAW 31EO-EOP-012-2, "Primary Containment Control"?

A. 34S0-T48-002-2, "Containment Atmospheric Control & Dilution Systems, Section 7.3.3, Fast Drywell Vent";

vent irrespective of offsite release rates.

B. 31EO-EOP-101-2, "Emergency Containment Venting";

vent irrespective of offsite release rates.

C. 34S0-T48-002-2, "Containment Atmospheric Control & Dilution Systems, Section 7.3.3, Fast Drywell Vent";

venting MUST be secured if approaching General Emergency Release Rate Limits.

D. 31EO-EOP-101-2, "Emergency Containment Venting";

venting MUST be secured if approaching General Emergency Release Rate Limits.

Page: 97 of 100 4128/2009

98.

Which ONE of the following choices answers both of these statements IAW with the requirements of 73EP-RAD-OOI-O, "Radiological Event"?

The (1) is the MINIMUM level of qualification necessary to declare a Radiological Event AND will make immediate decisions concerning Emergency Call List notifications.

When an Area Radiation Monitor (ARM) UNEXPECTEDLY alarms and radiation levels in the vicinity of the monitor have risen to AT LEAST greater than (2) times normal, then a Plant Page Announcement is required.

A. (1) Shift Manager (2) 2 B. (1) Control Room Shift Supervisor (2) 2 C. (1) Shift Manager (2) 10 D. (1) Control Room Shift Supervisor (2) 10 Page: 98 of 100 4/28/2009

99.

Unit 1 has an ATWS with the following conditions:

o Reactor power .... ............ 3%

o Reactor pressure ............. 960 psig and steady; MSN s open o Reactor water level ........ -70 inches and steady o HPCI and CRD Pumps.. Unavailable RCIC is being used in accordance with 3 lEO-EOP-109-1 , Alternate Boron Injection; however, RCIC has a stearn leak causing one Secondary Containment (SC) area temperature to exceed the Max Safe Value and another area is approaching the Max Safe Value.

Which ONE of the following is the EOP bases for allowing RCIC to continue to operate and the procedure that provides the steps for jumpering the high temperature isolation signal?

A. RCIC is being used to shutdown the reactor; 31EO-EOP-109-1, "Alternate Boron Injection" B. RCIC is being used to maintain inventory and adequate core cooling; 31EO-EOP-11O-1, "Alternate RPV Water Level Control" C. RCIC is being used to shutdown the reactor; 31EO-EOP-IOO-l, "Miscellaneous Emergency Overrides" D. RCIC is being used to maintain inventory and adequate core cooling; 31EO-EOP-IOO-l, "Miscellaneous Emergency Overrides" Page: 99 of 100 4/28/2009

100.

Unit 1 was operating at 100% power when the following events occurred.

o Time: 07:57 All Main Turbine Bypass Valves fail full open o Time: 08:00 Reactor power is 88% and the MSIVs remain open with RPV pressure at 700 psig o Time: 08:00 An operator closes the MSIV s and the reactor automatically scrams o Time: 08:04 Low Low Set automatically arms and actuates Which ONE of the following identifies the EARLIEST time that an NRC notification is required IAW with 00AC-REG-001-0, "Federal and State Reporting and Federal Document Posting Requirements," including the name of the required form that is required to be used for the NRC notification?

A. 09:00; Emergency Notification Network (ENN) form TRN-001, "Southern Nuclear Emergency Notification. "

B. 09:00; Emergency Notification System (ENS) form OPS-0065, "Checklist for Notification Of Significant Events Report."

C. 12:00; Emergency Notification Network (ENN) form TRN-001, "Southern Nuclear Emergency Notification. "

D. 12:00; Emergency Notification System (ENS) form OPS-0065, "Checklist for Notification Of Significant Events Report."

Page: 100 of 100 4/28/2009

HLT 4 NRC Written Exam SRO Index of References

1. 34AB-B21-002-2, "RPV Water Level Corrections" Page 7 of 12

2. Unit 2 EOP Graph 12A, RHR Pump NPSH Limit, (Suppression Pool Water Level Below 146")

Unit 2 EOP Graph 12B, RHR Pump NPSH Limit, (Suppression Pool Later Level At or Above 146")

3. Unit 1 Tech Spec Section 3.3.8.2, "RPS Electric Power Monitoring"

4. Unit 2 Heat Capacity Temperature Limit (HCTL) Curve (EOP Graph 2) 5 Unit 2 Drywell Spray mitiation Limit (DWSIL) Curve (EOP Graph 8)

6. NMP-EP-109, Attachment 1, page 3 of3 (PAGs are blanked out)

7. 0 TRM Table TlO.l-l "Master Equipment Cross Reference - Sorted By MPL,"

Sheet 15 of 22 o LFD-I-PCIS-29, "RWCU System Isolation Area Temperature - High" o LFD-I-PCIS-30 Sheet 1 of 2 "RWCU System Isolation Area Ventilation Diff.

Temperature - High" o LFD-I-PCIS-30 Sheet 2 of 2 "RWCU System Isolation Area Ventilation Diff.

Temperature - High" o TS 3.3.6.1, "Primary Containment Isolation mstrumentation" Pages 3.3-47, 3.3-48, 3.3-49, 3.3-50 and 3.3-54 ("Allowable Values" are blanked out.)

SNC PLANT E. I. HATCH I Pg 7 of 12 DOCUMENT TITLE:

RPV WATER LEVEL CORRECTIONS IDOCUMENT NUMBER:

34AB-B21-002-2 VERSION No:

6.11 ATTACHMENT _1 Att. Pg.

TITLE: DRYWELL RTD GROUPS AND CAUTION 1 AND 2 3 of 3 CAUTION 1 (CONTINUED)

2. FOR THE FOLLOWING TABLE, THE WATER LEVEL INSTRUMENT READS ABOVE MINIMUM INDICATED LEVEL FOR THE ASSOCIATED MAXIMUM RUN TEMPERATURE MEASURED BY THE HIGHEST TEMPERATURE IN THE ASSOCIATED RTD GROUP.

MINIMUM

a. NARROW RANGE INDICATED MAXIMUM RUN (0 TO +60 IN.)

LEVEL {IN .} TEMPERATURE {'F}

0 UPT0273 INSTRUMENT RTDGROUP 6 274 TO 350 2C32-R606A & C 1 9 351 TO 399 2C32-R606B 2 27 400 OR ABOVE MINIMUM

b. WIDE RANGE INDICATED MAXIMUM RUN

(-150 TO +60 IN)

LEVEL {IN.} TEMPERATURE {'F}

-150 UP TO 197 INSTRUMENT RTDGROUP

- 130 198 TO 350 2B21-R604A & R623A 1

- 122.5 351 TO 399 2B21-R604B & R623B 2

- 90 400 OR ABOVE MINIMUM

c. FLOODUP RANGE INDICATED MAXIMUM RUN LEVEL {IN.} TEMPERATURE {'F}

INSTRUMENT RTDGROUP 2B21-R605 0 UP TO 190 1

16 191 TO 250 (0 TO +400 IN.)

46 251 TO 350 2C32-R655 2 60 351 TO 399 (0 TO +200 IN.)

102 400 OR ABOVE

d. FUEL ZONE MINIMUM

(-317 TO -17 IN.)

INDICATED MAXIMUM RUN LEVEL {IN.} TEMPERATURE {'F}

INSTRUMENT RTDGROUP

- 317 UP TO 280 2B21-R623B 2

- 299 281 AND ABOVE 2B21-R623A 1 MGR-0009 Ver. 4

!GRAPH IiAJ U UNIT 2 RHR Pump NPSH Limit (Suppression Pool Water Level At or Above 146")

25 B e1ow 10 pSlg . *L.L..--/: ! , ; ,

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~------1-------+------+------+------+------t------1-------r------t------t-------r------1-------t-------~------1------- r------+------1-------r------1-------fC~~"£~A I t I I I ! I I I I t I I I I I I , I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 1 I I I I I I I I I I , I I I I I I I I I I I t I I I I I I I I I I I I I I I I I I I I I I I I I I J I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I J I I I I I 1 I I I I 16 I I J I I ~ ! ~ 1 I I I I I I I 1 I I I I o 2000 4000 6000 8000 10000 12000 FLOW (gpm)

NOTE: May use SPDS Emergency Displays in place of this Graph.

Suppression Chamber Pressure.

- Safe operating region is below the applicable pressure line.

IGRAPH 12BI UNIT 2 RHR Pump NPSH Limit (Suppression Pool Water Level Below 146")

25 23 Below 10 psig*

TORUS TEMP 21 (OF) 18 o 2000 4000 6000 8000 10000 12000 FLOW (gpm)

NOTE: May use SPDS Emergency Displays in place of this Graph.

Suppression Chamber Pressure.

- Safe operating region is below the applicable pressure line.

RPS Electric Power Monitoring 3.3.8.2 3.3 INSTRUMENTATION 3.3.8.2 Reactor Protection System (RPS) Electric Power Monitoring LCO 3.3.8.2 Two RPS electric power monitoring assemblies shall be OPERABLE for each inservice RPS motor generator set or alternate power supply.

APPLICABILITY: MODES 1, 2, and 3, MODES 4 and 5 with any control rod withdrawn from a core cell containing one or more fuel assemblies or with both residual heat removal (RHR) shutdown cooling (SDC) isolation valves open.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or both inservice A.1 Remove associated 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months power supplies with one inservice power electric power monitoring supply(s) from service.

assembly inoperable.

B. One or both inservice B.1 Remove associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months power supplies with both inservice power electric power monitoring supply(s) from service.

assemblies inoperable.

C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A or B AND not met in MODE 1, 2, or 3.

C.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (continued)

HATCH UNIT 1 3.3-67 Amendment No. 195

RPS Electric Power Monitoring 3.3.8.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Initiate action to fully Immediately associated Completion insert all insertable Time of Condition A or B control rods in core not met in MODE 4 or 5 cells containing one or with any control rod more fuel assemblies.

withdrawn from a core cell containing one or more fuel AND assemblies or with both RHR SDC isolation valves D.2.1 Initiate action to restore Immediately open. one electric power monitoring assembly to OPERABLE status for inservice power supply(s) supplying required instrumentation.

OR D.2.2 Initiate action to isolate Immediately the RHRSDC.

HATCH UNIT 1 3.3-68 Amendment No. 195

RPS Electric Power Monitoring 3.3.8.2 SURVEILLANCE REQUIREMENTS

N()TE------------------------------------------------------------

When an RPS electric power monitoring assembly is placed in an inoperable status solely for performance of required Surveillances, entry into the associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the other RPS electric power monitoring assembly for the associated power supply maintains trip capability.

SURVEILLANCE FREQUENCY SR 3.3.8.2.1 ------------------------------N()TE----------------------------

()nly required to be performed prior to entering M()OE 2 or 3 from M()OE 4, when in M()OE 4 for

~ 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Perform CHANNEL FUNCTI()NAL TEST. 184 days SR 3.3.8.2.2 Perform CHANNEL CALIBRATI()N. The 184 days Allowable Values shall be:

a. ()vervoltage s 132 V, with time delay set to s 4 seconds.

b. Undervoltage ~ 108 V, with time delay set to s 4 seconds.

c. Underfrequency ~ 57 Hz, with time delay set to s 4 seconds.

SR 3.3.8.2.3 Perform a system functional test. 184 days HATCH UNIT 1 3.3-69 Amendment No. 232

I GRAPH 2 I UNIT 2 HEAT CAPACITY TEMPERATURE LIMIT 260 1777777777777777777777777777777 0 77777777777777 7 777 777 777 7 7777 7 7 7 7 7 > 7 7 >7 > I I > > ;; 7 >; 7 > 7 > 7 > 2 ; 7, > "

220 ~~~~~~~~====~==~--~~~~~~~

TORUS Rx WATER PRESS TEMP 200 (psig) eF)

I ~

160 !;'Y;~~4~~~4~~~4 I*SAFE]

140 I>'$'$'$'$'$'$'$'$'$'$'$'$~ "" ~'$'$'$'$1 120 r ///U ,/, / U / / / 1 V / / / 'q 80 98 120 140 160 180 193 200 TORUS WATER LEVEL (in)

NOTE: May use SPDS Emergency Displays in place of this Graph.

Safe operating is below the applicable pressure line.

j*GRAPH8j UNIT 2 DRYWELL SPRAY INITIATION LIMIT 500 1'744' A44444~4444Y" 74'>1 1 ',(9CA444444' b444444£A49%44' 7444444%444444' 7444~44~44444LIA44444£A44"::1 DW400 I~J2?!2$'q1W ~ ~~~~~f~1 TEMP (OF) 300 li49S6£A4SSSSI5o' 7'

[SAFE ]

200 17<S£A,<S<S<S<S<S~ I 100 1'" / / / / / / 4 o 10 20 30 40 DRYWELL PRESSURE (psig)

NOTE: May use SPDS Emergency Displays in place of this Graph.

NMP-EP-109 souIHERNA Protective Action Recommendations Version 2.0 COMPANY

& ,.S.,wy.",W.,uo Page 11 of 19 Attachment 1 , Flowchart (Page 3 of 3)

PARt YES ~ SHELTER 0-2 mile radius And downwind to 5 miles NO Advise Remainder of EPZ to Monitor Local CONTINUE RadiofTV Stations/

ASSESSMENT TARs for Additional Return to START YES. Information Consider the use of KI PAR 2 in accordance with EVACUATE State plans and policy NO o- 2 mile radius Refer to site specific And downwind to 5 miles Table 1 or computer program for affected Advise Remainder of -YES zones EPZ to Monitor Local RadiofTV Stations/ CONTINUE TARs for Additional ASSESSMENT Information Return to START NO Consider the use of KI in accordance with State plans and policy PAR 3 EVACUATE Refer to site specific o- 5 mile radius NO- YES. And downwind to Table 1 or computer 10 miles program for affected zones Advise Remainder of EPZ to Monitor Local RadiofTV Stations/

TARs for Additional Information Consider the use of KI CONTINUE in accordance with ASSESSMENT .NO- State plans and policy Return to START Refer to site specific Table 1 or computer program for affected YES zones PAR 4 Evaluate the Need for PARs Beyond 10 Miles - Refer to Table 2 Printed: 4/22/2009

TABLE T10.1-1 (SHEET 15 OF 22)

MASTER EQUIPMENT CROSS REFERENCE - SORTED BY MPL LOSS OF FUNCTION MPL NUMBER,S} SPECIFICATION DIAGRAMS 1G11-R037 ODCM 2-1 (3.a.) N/A 1G11-R045 ODCM 2-1 (3.b.) N/A 1G11-R345 ODCM 2-1 (3.a.) N/A 1G11-R600 TS LCO 3.4.5.a N/A 1G31-N061A,D,E,H,J,M TS 3.3.6.1-1 (5.b.) LFD-1-PCIS-30 1G31-N062A,D,E,H,J,M TS 3.3.6.1-1 (5.a.) LFD-1-PCIS-29 1G31-N062A,D,E,H,J,M TS 3.3.6.1-1 (5.b.) LFD-1-PCIS-30 1G31-N661A,D,E,H,J,M TS 3.3.6.1-1 (5.b.) LFD-1-PCIS-30 1G31-N662A,D,E,H,J,M TS 3.3.6.1-1 (5.a.) LFD-1-PCIS-29 1G31-N662A,D,E,H,J,M TS 3.3.6.1-1 (5.b.) LFD-1-PCIS-30 1G31-N663A,D,E,H,J,M TS 3.3.6.1-1 (5.b.) LFD-1-PCIS-30 1H11-P603 TRM T3.3.3-1 (3.) N/A 1H21-P4103 TSR 3.3.10.4.a N/A 1H21-P4103 TSR 3.3.10.7.a N/A 1H21-P4104 TSR 3.3.10.4.b N/A 1H21-P4104 TSR 3.3.10.7.b N/A 1L51-NOO5 U2 TRM T3.3.6-1 (1.d.) N/A 1L51-NOO6 U2 TRM T3.3.6-1 (2.b.) N/A 1L51-N007 U2 TRM T3.3.6-1 (2.a.) N/A 1L51-N008 U2 TRM T3.3.6-1 (2.c.) N/A 1L51-N105 U2 TRM T3.3.6-1 (4.8.) N/A 1N11-N042A,B,C TRM TLCO 3.3.13 N/A 1N30-F005 TSR 3.3.10.2 8 N/A 1N30-F005 TSR 3.3.10.6 N/A 1N30-F006 TSR 3.3.1 0.2-8 N/A 1N30-F006 TSR 3.3.10.6 N/A 1N30-F007 TSR 3.3.10.2 8 N/A 1N30-F007 TSR 3.3.10.6 N/A 1N30-F008 TSR 3.3.10.2 8 N/A 1N30-F008 TSR 3.3.10.6 N/A 1N30-F009 TSR 3.3.10.3 N/A 1N30-F009 TSR 3.3.10.6 N/A HATCH UNIT 1 TRM Revision 52

Trip System "A" Trip System "B" r------------, r ....... - - - - - - - - - - - - ,

Channels Channels At A2 A3 B1 B2 B3 Pump Room Heat Exchg. Room CUPS Room Pump Room Heat Exchg. Room CUPS Room Trip Logic Trip Logic

,.----------1. IC71A-I -;- K36SA

1. IC71A-

-;- K36SD

..!.. IC71A*

I

..&.. IC7lA*

Contacts Open -:- K368A i K368D On HighAmb. ..!.. lC71A- ..J.. IC71A-

-r K371A -r K371D Temperature (Typical of 6)

Sl~ <> lA71B-K6S Actuatiqn Logic Actuatiqn Logic IA71B- lA71B- ..&..

1-----K2S---.-

Contacts Open

~

K6S -.- ,

To Cause :

Ac:mation I (Typical of2) :

I Closure of Inboard Group S PCIS Closure of Outboard Group S PCIS Valve IG31-FOOI Valve 1G31-FOO4 Minimum Cbagnel Requirements for System Isolation Capabjlity; In order to maintain the capability to isolate the RWCU system on high area temperature, channels in one of the following combinations must be either operable or maintained in the tripped condition.

AlorBl AND Elem.Ref. LFD-I-PCIS-29 A2orB2 H-1623 1

.AND TS 3.3.6.1-1, Item 5.a H-17817 H-17818 A3 orB3 ,.--_ _~-,--.....--...,.IRWCU System Isolation Temperature - High H-19811 H-19820 v.O 1/13/95

Trip System "Aft r--~~----~--~-~~----~

Channels Al A2 A3 Pump Room Heat Exchg. Room CUPS Room Trip 1:.

lC71A-Logic________ . _..

K366A --:-

I l~l~ ~ :

K369A ... Contacts Open 2C71A- ~ On High Di1l'.

L_~~ ___ ~

D72A lA71B-K28

> ~

Temperature (lYpicalof3)

____ ~ __ ~

Actuatiqn Logic IA7IB- --'=---.

1(28",

1C:0p001

,. - To Cause

Actuation Closure of Inboard Group 5 PCIS Valve 1G31*FOO 1 Minimum ChADnei RcqgimDCDts for System hoJatiQD CaJ)lbUitl';

See Sheet 2 of 2 for statement of minimum channel requirements.

Elem. Ref.

H-16231 H-17817 H-17818 H-19811 H-19820

Trip System "B" r-~~--------~----~-~~

Channels I Pum~loom Heat~h; Room c~~oom I Trip Logic IC7lA* ~ __________ ..

I066D -:-

IC7lA.

..L 1069D i contacts Open lC71A- ..L On HighDiff.

L ___ ~ ____

K372D lA71B- <>

...... Temperature (1Ypical of 3)

K65 _ _ _ _ _ _ _ _ _ _ _

ActuatiQn Logic IA71B- -+. __ .. ~C-on-tac-ts---Opcm--'

K6S i 1_. To Cause Actuation Closure of Outboard Group 5 PCIS Valve I G31-FOO4 Minimum Cblnod RcguircmcPts for System Isolatioo Cap.bUitY; In order to maintain Group 5 PCIS isolation capability on high ventilation differential temperature, channels in one of the following combinations must be either operable or maintained in the tripped condition.

Elem. Ref. AlorBl H-16231 AND H*17817 AlorB2 H-17818 AND H-19811 A3 orB3 H-19820

Primary Containment Isolation Instrumentation 3.3.6.1 3.3 INSTRUMENTATION 3.3.6.1 Primary Containment Isolation Instrumentation LCO 3.3.6.1 The primary containment isolation instrumentation for each Function in Table 3.3.6.1-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.6.1-1.

ACTIONS

N 0 TE-----------------------------------------------------------

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Place channel in trip. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for channels inoperable. Functions 2.a, 2.b, and 6.b AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for Functions other than Functions 2.a, 2.b, and 6.b B. ---------------N OTE------------- B.1 Restore isolation 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Not applicable for capability.

Function S.c.

One or more automatic Functions with isolation capability not maintained.

C. Required Action and C.1 Enter the Condition Immediately associated Completion referenced in Time of Condition A or B Table 3.3.6.1-1 for the not met. channel.

(continued)

HATCH UNIT 1 3.3-47 Amendment No. 195

Primary Containment Isolation Instrumentation 3.3.6.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. As required by Required 0.1 Isolate associated main 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action C.1 and referenced steam line (MSL).

in Table 3.3.6.1-1.

OR 0.2.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND 0.2.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months E. As required by Required E.1 Be in MODE 2. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action C.1 and referenced in Table 3.3.6.1-1.

F. As required by Required F.1 Isolate the affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Action C.1 and referenced penetration flow in Table 3.3.6.1-1. path(s).

G. As required by Required G.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action C.1 and referenced in Table 3.3.6.1-1. AND OR G.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Required Action and associated Completion Time of Condition F not met.

H. As required by Required H.1 Declare Standby Liquid 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Action C.1 and referenced Control (SLC) System in Table 3.3.6.1-1. inoperable.

OR H.2 Isolate the Reactor 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Water Cleanup (RWCU) System.

(contmued)

HATCH UNIT 1 3.3-48 Amendment No. 195

Primary Containment Isolation Instrumentation 3.3.6.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME I. As required by Required 1.1 Initiate action to restore Immediately Action C.1 and referenced channel to OPERABLE in Table 3.3.6.1-1. status.

1.2 Initiate action to isolate Immediately the Residual Heat Removal (RHR)

Shutdown Cooling System.

SURVEILLANCE REQUIREMENTS

NOTES-------------------------------------------------------

1. Refer to Table 3.3.6.1-1 to determine which SRs apply for each Primary Containment Isolation Function.

2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains isolation capability.

SURVEILLANCE FREQUENCY SR 3.3.6.1.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.6.1.2 Perform CHANNEL FUNCTIONAL TEST. 92 days on an ALTERNATE TEST BASIS SR 3.3.6.1.3 Perform CHANNEL CALIBRATION. 92 days on an ALTERNATE TEST BASIS (continued)

HATCH UNIT 1 3.3-49 Amendment No. 234

Primary Containment Isolation Instrumentation 3.3.6.1 SURVEILLANCE REQUIREMENTS _(continued)

SURVEILLANCE FREQUENCY SR 3.3.6.1.4 Perform CHANNEL CALIBRATION. 184 days SR 3.3.6.1.5 Perform CHANNEL CALIBRATION. 24 months SR 3.3.6.1.6 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months HATCH UNIT 1 3.3-50 Amendment No. 234

Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 4 of 4)

Primary Containment Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION C.1 REQUIREMENTS VALUE

4. RCIC System Isolation (continued)

g. RCIC Suppression Pool 1,2,3 F SR 3.3.6.1.1 Area Differential SR 3.3.6.1.2 Temperature - High SR 3.3.6.1.5 SR 3.3.6.1.6

h. Emergency Area Cooler 1,2,3 F SR 3.3.6.1.1 Temperature - High SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6

5. RWCU System Isolation

a. Area Temperature - High 1,2,3 1 per area F SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1 .6

b. Area Ventilation 1,2,3 1 per area F SR 3.3.6.1.1 Differential Temperature - SR 3.3.6.1.2 High SR 3.3.6.1.5 SR 3.3.6.1.6

c. SLC System Initiation 1,2 1(e) H SR 3.3.6.1.6

d. Reactor Vessel Water 1,2,3 2 F SR 3.3.6.1.1 Level - Low Low, Level 2 SR 3.3.6.1 .2 SR 3.3.6.1.5 SR 3.3.6.1.6

6. RHR Shutdown Cooling System Isolation

a. Reactor Steam Dome 1,2,3 F SR 3.3.6.1.1 Pressure - High SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6

b. Reactor Vessel Water 3,4,5 2 (d) SR 3.3.6.1.1 Level - Low, Level 3 SR 3.3.6.1 .2 SR 3.3.6.1.5 SR 3.3.6.1.6 (c) SLC System Initiation only inputs into one of the two trip systems.

(d) Only one trip system required in MODES 4 and 5 when RHR Shutdown Cooling System integrity maintained.

HATCH UNIT 1 3.3-54 Amendment No. 195

ML091320204

Text

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