ML19032A147

Final SRO Written Exam 2019-301 - Delay Release Two Years

ML19032A147
Person / Time
Site:	Brunswick
Issue date:	01/22/2019
From:	NRC/RGN-II
To:
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Download: ML19032A147 (28)

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ES-401 Site-Specific SRO Written Examination Form ES-401-8 Cover Sheet U. S. Nuclear Regulatory Commission Site-Specific SRO Written Examination Applicant Information Name:

Date: 

Facility / Unit: Brunswick Unit 1/2 Region:

I II III IV Reactor Type: W CE BW GE Start Time:

Finish Time:

Instructions Use the answer sheets provided to document your answers. Staple this cover sheet on top of the answer sheets. To pass the examination you must achieve a final grade of at least 80 percent overall, with 70 percent or better on the SRO-only items if given in conjunction with the RO exam; SRO-only exams given alone require a final grade of 80 percent to pass. You have 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to complete the combined examination, and 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> if you are only taking the SRO portion.

Applicant Certification All work done on this examination is my own. I have neither given nor received aid.

Applicant's Signature Results RO/SRO-Only/Total Examination Values

______ / ______ / ______

Points Applicant's Score

______ / ______ / ______

Points Applicant's Grade

______ / ______ / ______

Percent

SRO Written Exam Reference Index

1.

0ASSD-02, Section A, Unit 2 CRS Actions, Figure 1

2.

0EOP-01-UG, Users Guide, Attachments:

5 (Drywell Spray Initiation Limit) 8 (Core Spray NPSH Limit) 13 (Core Spray Vortex Limit) 25 (Unit 1 RPV Level at LL4) 27 (Unit 1 RPV Level at LL5)

3.

0EOP-03-SCCP, Table SC-3, Area Radiation Limits

4.

0OI-01.07, Notifications, Attachment 1, Reportability Evaluation Checklist

5.

AD-EP-ALL-0109, Offsite Protective Action Recommendations,, BNP Offsite PAR Determination Worksheet

6.

Core Map

7.

0PEP-02.1, Brunswick Nuclear Plant Initial Emergency Actions, System Malfunctions, Hazards, and Fission Product Barriers sections.

8.

LL-30024 SH0006, 125/250 Volt DC System Control Building Distribution Panel 3A

9.

Technical Specifications, 3.1.3 Control Rod OPERABILITY

10. Technical Specifications, 3.1.4 Control Rod Scram Times

11. Technical Specifications, 3.3.1.1 Reactor Protection System (RPS)

Instrumentation

12. Technical Specifications, 3.3.6.1 Primary Containment Isolation Instrumentation

13. Technical Specifications, 3.3.8.2 Reactor Protection System (RPS)

Electric Power Monitoring

14. Technical Specifications, 3.5.1 ECCSOperating

15. Technical Specifications, 3.6.4.3 Standby Gas Treatment (SGT) System

16. Technical Specifications, 3.8.7 Distribution SystemsOperating

76. Unit One is performing a startup with the following conditions:

IRM C is Inoperable and bypassed All other IRMs are on range 1 Mode switch in Startup Subsequently, the high voltage power supply on IRM G fails low.

[Reference Provided]

Which one of the following completes both statements below?

The ability to manually withdraw control rods using the Rod Movement Control Switch is (1).

Tech Spec 3.3.1.1, Reactor Protection System (RPS) Instrumentation, requires placing IRM G in trip in (2).

(1) NOT affected (2) 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> (1) NOT affected (2) 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (1) prevented (2) 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> (1) prevented (2) 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> A.

B.

C.

D.

Page: 76 of 100 12/20/2018

77. Unit Two is at 100% power when the 2A Reactor Feed Pump trips and reactor water level lowers to 180 inches.

Which one of the following completes both statements below?

Reactor Recirc pumps will runback to Speed (1).

2AOP-04.0, Low Core Flow, (2) steps to reset the runback signal.

(1) Limiter 1 (2) includes (1) Limiter 1 (2) does NOT include (1) Limiter 2 (2) includes (1) Limiter 2 (2) does NOT include A.

B.

C.

D.

Page: 77 of 100 12/20/2018

78. A complete Loss of Offsite Power occurs.

DG2, DG3, and DG4 have failed.

NOTE: RHR Loop B Valve Nomenclature 2-E11-F015B, Inboard Injection Valve Which one of the following completes both statements below?

Given this condition, if a valid auto open signal demand to 2-E11-F015B subsequently occurs, the valve (1) auto open.

The CRS will direct 4160V Bus E4 to be energized IAW (2).

(1) will (2) EOP-01-SBO-06, 4160V E-BUS CROSSTIE (1) will (2) EOP-01-SBO-08, SUPPLEMENTAL DG ALIGNMENT (1) will NOT (2) EOP-01-SBO-06, 4160V E-BUS CROSSTIE (1) will NOT (2) EOP-01-SBO-08, SUPPLEMENTAL DG ALIGNMENT A.

B.

C.

D.

Page: 78 of 100 12/20/2018

79. Unit Two is in MODE 4 with SDC in service on RHR loop A when a Reactor Steam Dome Pressure High signal occurs due to I&C error.

A-03 2-1, Core Spray Or RHR Pumps Running, annunciator has cleared.

Reactor Steam Dome Pressure High signal has been restored to operable by I&C.

Which one of the following completes both statements below?

RHR Inboard Injection Isolation Valve, E11-F015A (1) auto close.

IF RHR piping cooldown or drain down is NOT a concern, THEN the procedural steps for restoring RHR Loop A are contained in (2).

(1) will (2) 0AOP-15.0, Loss of Shutdown Cooling (1) will (2) 2OP-17.0, Residual Heat Removal System Operating Procedure (1) will NOT (2) 0AOP-15.0, Loss of Shutdown Cooling (1) will NOT (2) 2OP-17.0, Residual Heat Removal System Operating Procedure A.

B.

C.

D.

Page: 79 of 100 12/20/2018

80. Unit Two is at 100% power. Unit One is a refueling outage with MCC 1CA under clearance.

The following events occur on Unit Two:

RPS EPA-3 tripped open due to a failure of its voltage sensing logic.

RPS EPA-4 remained closed.

RPS B was transferred to its alternate power supply IAW 2OP-03, Reactor Protection System Operating Procedure, Section 6.3.2, Transferring RPS Bus B from Normal to Alternate Power.

[Reference Provided]

IAW Tech Specs, which one of the following completes both statements below?

(1) RPS electric power monitoring assembly(ies) is(are) inoperable.

Unit Two operation (2) allowed to continue indefinitely.

(1) One (2) is (1) One (2) is NOT (1) Two (2) is (1) Two (2) is NOT A.

B.

C.

D.

Page: 80 of 100 12/20/2018

81. Unit One has entered the ATWS Procedure.

Current plant conditions:

APRMs 16% power Mode Switch Shutdown ARI Initiated Recirc Pumps Tripped RPV water level 150 inches Torus temperature 95°F Drywell pressure 2 psig MSIVs Open Which one of the following completes both statements below?

IAW ATWS Procedure RC/Q leg, the priority action is to (1).

IAW ATWS Procedure RC/L leg, the highest reactor water level that can be established by the CRS as the upper end of the level band is (2).

(1) initiate SLC (2) 90 inches (1) initiate SLC (2) 206 inches (1) terminate and prevent injection into the RPV (2) 90 inches (1) terminate and prevent injection into the RPV (2) 206 inches A.

B.

C.

D.

Page: 81 of 100 12/20/2018

82. Unit Two Reactor Water Level trip units B21-LTM-N024A-1-1 (Low Level 2) and B21-LTS-N024A-1-2 (Low Level 3) were both taken out of service on Monday at 3 AM to perform SR 3.3.6.1.2 and SR 3.3.6.1.3 IAW 0MST-PCIS21Q, PCIS Rx Water LL2 and LL3 Div I Trip Unit Chan Cal and Func Test.

[Reference Provided]

IAW LCO 3.3.6.1, PCIS Instrumentation, which one of the following completes the statement below?

IF the allowable time to perform the surveillance expires, and the instruments have not yet been returned to service, THEN the latest time these channels must be placed in the tripped condition is:

Monday at 3 PM Monday at 9 PM Tuesday at 3 AM Tuesday at 9 AM A.

B.

C.

D.

Page: 82 of 100 12/20/2018

83. Unit Two was operating at 50% power and an event occurred.

The following alarms and indications are noted:

A-02 (5-4) ECCS Div I RPT/ARI TR (red bar)

In alarm A-02 (5-8) ECCS Div II RPT/ARI TR (red bar)

In alarm A-05 (3-5) Reactor Vess Hi Press (yellow bar)

NOT in alarm A-03 (5-9) RHR Reactor Press Lo (red bar)

NOT in alarm A-05 (5-5) Pri Ctmt Hi/Lo Press (yellow bar)

In alarm A-03 (4-9) RHR High Drywell Press (red bar)

In alarm HPCI Equip Area High Temp 150°F RCIC Equip Area High Temp 180°F Subsequently, A-02 alarms 5-4 and 5-8 clear.

[Reference Provided]

Which one of the following completes both statements below?

(assume no circuit alterations have been performed)

Group (1) valves are closed.

IAW OI-01.07, Notifications, the reportability for these conditions is first required to be made to the NRC within (2).

(1) 5 ONLY (2) four hours (1) 5 ONLY (2) eight hours (1) 5 and 9 (2) four hours (1) 5 and 9 (2) eight hours A.

B.

C.

D.

Page: 83 of 100 12/20/2018

84. Unit Two is operating at 100% power when the turbine bypass valves open due to an EHC pressure regulator failure.

Assuming no operator action, which one of the following completes the statement below?

The first RPS scram signal that will be generated will be the (1) signal.

IAW the bases for Tech Spec 3.3.1.1, RPS Instrumentation, this RPS scram signal (2) assumed (credited) in the overpressurization protection analysis.

(1) MSIV closure (2) is also (1) MSIV closure (2) is NOT (1) Turbine Trip/Turbine Stop Valves closure (2) is also (1) Turbine Trip/Turbine Stop Valves closure (2) is NOT A.

B.

C.

D.

Page: 84 of 100 12/20/2018

85. Unit Two was manually scrammed.

The crew has entered RSP.

6 control rods are still at position 02.

Which one of the following completes both statements below?

The RSP (1) required to be exited.

The CRS will direct LEP-02, Alternate Control Rod Insertion, (2).

(1) is (2) Section 2.2, Control Rod Insertion Verification (1) is (2) Section 2.3, Reset RPS and Initiate a Manual Scram (1) is NOT (2) Section 2.2, Control Rod Insertion Verification (1) is NOT (2) Section 2.3, Reset RPS and Initiate a Manual Scram A.

B.

C.

D.

Page: 85 of 100 12/20/2018

86. Unit Two has evacuated the control room due to a fire and is performing 0ASSD-02, Control Building, Section A, Unit 2 CRS Actions.

Current conditions are as follows:

RPV level (B21-LI-5977) is 25 inches and stable Reactor pressure is 700 psig Drywell temperature (Point 1 on 2-CAC-TR-778) is 252°F RCIC is injecting at 500 gpm

[Reference Provided]

IAW 0ASSD-02, which one of the following completes both statements below?

(consider each statement separately)

RPV water level is currently (1) TAF.

Section A, Attachment 1, Unit 2 Reactor Vessel Rapid Depressurization, (2) required.

(1) above (2) is (1) above (2) is NOT (1) below (2) is (1) below (2) is NOT A.

B.

C.

D.

Page: 86 of 100 12/20/2018

87. A General Emergency has just been declared.

An unisolable HPCI line break has occurred.

Reactor Building negative pressure indicates 0 inches H2O.

Drywell radiation monitors indicate 2400 R/hr.

Dose assessments project that the on-going rad release will be 1100 mrem TEDE and 4511 mrem CDE thyroid at the site boundary in one hour.

There are no known offsite impediments to evacuation.

Weather conditions for today (January 22nd) are:

Temperature 62°F Upper wind speed 9.8 mph Lower wind speed 7.3 mph Upper wind direction 318.9° Lower wind direction 314.3°

[Reference Provided]

IAW AD-EP-ALL-0109, Offsite Protective Action Recommendations, which one of the following identifies the minimum required zones for evacuation?

12 and 13 11, 12, and 13 1, 2, 12, and 13 1, 2, 11, 12, and 13 A.

B.

C.

D.

Page: 87 of 100 12/20/2018

88. With Unit Two operating at 100% power, an inadvertent actuation of one Core Spray logic system occurs with the BOP operator observing the following:

SW-V103, RBCCW HXS SW INLET VLV closed SW-V106, RBCCW HXS SW INLET VLV open SW-V111, CONV SW TO VITAL HEADER VLV closed SW-V117, NUC SW TO VITAL HEADER VLV open 0AOP-16.0, RBCCW System Failure, is entered to supply reactor building closed cooling water from the conventional service water header.

Service water flow cannot be determined.

Which one of the following completes both statement below?

Core Spray Logic (1) inadvertently actuated.

IAW 0AOP-16.0, the conventional service water header (2) required to be declared INOPERABLE for Tech Spec 3.7.2, SW System and UHS.

(1) A (2) is (1) A (2) is NOT (1) B (2) is (1) B (2) is NOT A.

B.

C.

D.

Page: 88 of 100 12/20/2018

89. Unit Two is in MODE 4 with the following conditions:

SDC in service with ONLY the 2A RHR pump running RPV pressure is 0 psig RPV level is being maintained 200-220 inches Secondary Containment is considered functional per the requirements of 0AP-022, BNP Outage Risk Management.

Subsequently, the following timeline occurs:

Time 1100 A-03 (4-2) Reactor ADS Lo Water Level (red bar) is in alarm A-03 (2-1) Core Spray or RHR Pumps Running has cleared 1101 0AOP-15.0, Loss of Shutdown Cooling, was entered 1110 RPV pressure is 3 psig 1121 RVCP is entered 1130 A-02 (5-4) & (5-8) ECCS Div I(II) RPT/ARI Trip (red bar) are in alarm 1145 A-03 (6-9) Reactor Low Wtr Level Initiation (red bar) is in alarm A-03 (2-1) Core Spray or RHR Pumps Running is in alarm 1146 RPV water level has stabilized just below the A-03 (6-9) setpoint

[Reference Provided]

Which one of the following completes ERWh statementV below?

IAW 0AOP-15.0, at time 1101, the CRS will direct (1).

The highest EAL classification for this event is (2).

(1) the 2C RHR pump to be started (2) an Alert (1) the 2C RHR pump to be started (2) a Site Area Emergency (1) raising RPV water level to a band of 200 inches to 220 inches (2) an Alert (1) raising RPV water level to a band of 200 inches to 220 inches (2) a Site Area Emergency A.

B.

C.

D.

Page: 89 of 100 12/20/2018

90. Unit Two is operating at 100% power. CRD Pump B is under clearance.

The following control rods have been declared SLOW.

14-23 22-07 30-27 30-31 42-23 Subsequently CRD Pump A trips due to filter d/p.

A-05 (1-2), CRD Hyd Temp High, is received.

The AO reports that CRD 26-31 temperature is reading 350 F and slowly rising.

(This is the only CRD with a high temperature alarm) 0PT-14.2.1, Single Rod Scram Insertion Times Test, can NOT be performed.

[Reference Provided]

IAW A-05 (1-2) and Tech Specs, which one of the following completes both statements below?

Control Rod 26-31 must be declared (1).

Unit Two can remain at 100% power operation (2).

(1) INOP (2) for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (1) INOP (2) for 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> (1) SLOW (2) for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (1) SLOW (2) indefinitely A.

B.

C.

D.

Page: 90 of 100 12/20/2018

91.

Which one of the following completes both statements concerning a loss of level in the spent fuel pool?

Entry into SCCP is first required when spent fuel pool water level is below (1).

IAW 0PEP-02.2.1, Emergency Action Level Technical Bases, 26.67 feet (2) correlate to a water level 10 feet above the top of the fuel racks.

(1) Tech Spec 3.7.7, Spent Fuel Storage Pool Water level, LCO limit (2) does (1) Tech Spec 3.7.7, Spent Fuel Storage Pool Water level, LCO limit (2) does NOT (1) the A-04 (6-6), Fuel Pool Level Low, alarm setpoint (2) does (1) the A-04 (6-6), Fuel Pool Level Low, alarm setpoint (2) does NOT A.

B.

C.

D.

Page: 91 of 100 12/20/2018

92. The following timeline occurs on Unit Two:

Time 1000 Steam Cooling is entered with RPV pressure at 600 psig using SRVs 1005 Continuous pneumatic supply to the SRVs is lost 1007 The 2A RHR is running and lined up for injection IAW Steam Cooling, which one of the following completes both statements below?

The reactor pressure band is limited to no more than (1).

Time (2) is the earliest that RPV pressure control is required to transition to EDP.

(1) 800 psig (2) 1005 (1) 800 psig (2) 1007 (1) 1050 psig (2) 1005 (1) 1050 psig (2) 1007 A.

B.

C.

D.

Page: 92 of 100 12/20/2018

93. IAW 0PEP-02.2.1, Emergency Action Level Technical Basis, for SU6.1, Automatic or Manual Scram Fails to Shutdown the Reactor, which one of the following completes both statements below?

[Reference Provided]

An automatic initiation of ARI, that reduces reactor power to <2%, (1) considered a successful automatic scram.

A reactor shutdown achieved by the performance of 0EOP-01-LEP-02, Alternate Rod Insertions, actions (2) constitutes a successful manual scram.

(1) is (2) does (1) is (2) does NOT (1) is NOT (2) does (1) is NOT (2) does NOT A.

B.

C.

D.

Page: 93 of 100 12/20/2018

94. Which one of the following completes both statements below IAW AD-OP-ALL-0105, Operability Determinations and Functionality Assessments?

The lowest level of approval for a Prompt Determination of Operability is by the (1).

The use of a Compensatory Measure (2) be used to restore a Structure, System, or Component (SSC) to OPERABLE.

(1) Shift Manager (2) can (1) Shift Manager (2) can NOT (1) CRS (2) can (1) CRS (2) can NOT A.

B.

C.

D.

Page: 94 of 100 12/20/2018

95. Unit Two is operating at 100% power with an active LCO (3.5.1, ECCS - Operating, Condition A) for RHR Pump 2A being Inoperable. The RHR pump is scheduled to be out of service for 5 days.

[Reference Provided]

Which one of the following completes both statements below?

IAW AD-WC-ALL-0200, On-Line Work Management, the RHR Pump 2A (2) required to be worked 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s/day until equipment is returned to operability.

IF RHR Room Cooler 2B is declared INOPERABLE at the same time as RHR Pump 2A, THEN Tech Spec 3.5.1, Condition J (1) required to be entered.

(1) is NOT (2) is (1) is NOT (2) is NOT (1) is (2) is (1) is (2) is NOT A.

B.

C.

D.

Page: 95 of 100 12/20/2018

96. Unit Two is in MODE 1 with all equipment OPERABLE.

The supply breaker to Substation E8, AK7, Bus E4 to Sub E8, tripped open, which caused a loss of power to Standby Gas Treatment (SGT) Train 2B.

The supply breaker cannot be reclosed.

[Reference Provided]

Which one of the following completes both statements below IAW Tech Specs?

The crew (1) required to enter LCO 3.6.4.3, Standby Gas Treatment (SGT)

System, Condition A.

LCO (2) applies to this condition.

(1) is (2) 3.0.3 (1) is (2) 3.0.6 (1) is NOT (2) 3.0.3 (1) is NOT (2) 3.0.6 A.

B.

C.

D.

Page: 96 of 100 12/20/2018

97. IAW AD-EP-ALL-0204, Distribution of Potassium Iodide Tablets in the Event of a Radioiodine Release, which one of the following identifies who approves the administration of KI for onsite personnel?

EOF Director Radiation Protection Supv Emergency Coordinator EOF Radiological Assessment Manager A.

B.

C.

D.

Page: 97 of 100 12/20/2018

98. The BSEP Radioactive Liquid Release Permit is being approved with the following step filled out on the permit:

10. Confirm the following instrumentation is OPERABLE:

a. Liquid Radwaste Radioactivity Monitor, 2-D12-RM-K604 INOP

b. Liquid Radwaste Effluent Flow Measurement Device, 2-G16-FIT-N057 CRS IAW 0OP-06.4, Discharging Radioactive Liquid Effluents to the Discharge Canal, which one of the following completes both statements below?

The BSEP Radioactive Liquid Release Permit (1) include a Shift Manager approval signature.

This Radioactive Liquid Release (2) if 2-D12-RM-K604 is INOP.

(1) does (2) can still occur (1) does (2) is NOT allowed (1) does NOT (2) can still occur (1) does NOT (2) is NOT allowed A.

B.

C.

D.

Page: 98 of 100 12/20/2018

99. The STA is not in the control room.

An accident has occurred requiring entry into the EOPs.

The SM has just made an EAL declaration.

IAW AD-OP-ALL-1001, Conduct of Abnormal Operations which one of the following completes both statements below?

The STA is required to report to the affected Control Room no later than (1) after being notified of entry into the EOPs.

The (2) position is required to perform an independent assessment of the Emergency Plan classification.

(1) 10 minutes (2) STA (1) 10 minutes (2) CRS (1) 5 minutes (2) STA (1) 5 minutes (2) CRS A.

B.

C.

D.

Page: 99 of 100 12/20/2018

100. Unit Two is at 100% power when a LOOP occurs. Current plant conditions are below:

UA-12 (2-4) South RHR RM Flood Level Hi (blue bar)

In alarm UA-12 (2-3) South CS RM Flood Level Hi (blue bar)

In alarm A-05 (5-6) Pri Ctmt Press Hi Trip (red bar)

In alarm Reactor water level 150 inches IAW SCCP, which one of the following completes both statements below?

A primary system (1) discharging into the reactor building.

RB HVAC is required to be placed in service IAW (2).

(1) is (2) SEP-04, Reactor Building HVAC Restart Procedure (1) is (2) OP-37.1, Reactor Building Heating and Ventilation System Operating Procedure (1) is NOT (2) SEP-04, Reactor Building HVAC Restart Procedure (1) is NOT (2) OP-37.1, Reactor Building Heating and Ventilation System Operating Procedure A.

B.

C.

D.

Page: 100 of 100 12/20/2018