Text

05000250/2017301 and 05000251/2017301 Final SRO Written Exam - Delay Release 2 Yrs
	ML17349A188
Person / Time
Site:	Turkey Point
Issue date:	12/15/2017
From:	; NRC/RGN-II
To:	; Florida Power & Light Co
References
	Download: ML17349A188 (35)
	v • d • e

ES-401 Site-Specific SRO Written Examination Form ES-401-8

Cover Sheet

As-administered version of the

2017-301 Turkey Point SRO

Written Examination with

U.S. Nuclear Regulatory Commission changes incorporated:

Site-Specific SRO Written Examination

1) Question 89 - Answer Key

change

Applicant Information

Name: 2) Question 90 - Pen and Ink

change

Date: Facility/Unit

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 9 hours1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months to complete the combined examination and 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months if you are only taking

the SRO-only portion.

Applicant Certification

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

Applicants Signature

Results

RO/SRO-Only/Total Examination Values / / Points

Applicants Score / / Points

Applicants Grade / / Percent

ES-401, Page 50 of 52

NRC L-17 -1 EXAM SECURE INFORMATION

Question # 76

Given the following conditions:

Unit 3 is at 100% power.

Subsequently:

A pressurizer safety valve fails partially open.

3-EOP-E-1, Loss of Secondary or Reactor Coolant, is in progress.

RCS subcooling lowers to a MINIMUM of 22°F.

The PZR safety valve closes.

Current plant conditions are:

3B Charging Pump is running.

Pressurizer level is 100%.

PZR pressure 1750 psig and rising.

RCS subcooling is 65°F and rising.

All SG NR levels are 33% and stable

PRT pressure is 60 psig and stable.

Which one of the following completes the statements below?

RCPs (1) currently running.

The US (2) perform 3-EOP-ES-1.1, SI Termination.

A. (1) are

(2) will

B. (1) are

(2) will NOT

C. (1) are NOT

(2) will

D. (1) are NOT

(2) will NOT

NRC L-17 -1 EXAM SECURE INFORMATION

Question # 77

Given the following conditions:

Unit 3 is operating at 100% power.

Subsequently:

Unit 3 experiences a loss of all AC.

3-EOP-ECA-0.0, Loss of all AC Power, is entered with the following:

Total AFW flow to Unit 3 is 185 gpm.

ALL SG NR levels are off-scale low.

Pressurizer level is 3% and lowering.

Which one of the following completes the statements below?

The US will direct implementation of (1) .

The NEXT transition directed by the US will be to (2) .

A. (1) 3-EOP-FR-H.5, Response To Steam Generator Low Level

(2) 3-EOP-ECA-0.1, Loss of All Power Recovery Without SI Required

B. (1) 3-EOP-FR-H.5, Response To Steam Generator Low Level

(2) 3-EOP-ECA-0.2, Loss of All Power Recovery With SI Required

C. (1) 3-ONOP-075, Auxiliary Feedwater System Malfunction

(2) 3-EOP-ECA-0.1, Loss of All Power Recovery Without SI Required

D. (1) 3-ONOP-075, Auxiliary Feedwater System Malfunction

(2) 3-EOP-ECA-0.2, Loss of All Power Recovery With SI Required

NRC L-17 -1 EXAM SECURE INFORMATION

Question # 78

Given the following conditions:

Unit 3 experiences a loss of all AC power from 100% power.

3-EOP-ECA-0.0, Loss of All AC Power, is entered with the following:

Unit 4 EDGs are running loaded.

3B 4kV Bus is on fire.

3A EDG is locked out.

3A Condensate Pump, red light is ON.

3C RCP, red light is ON.

Which one of the following completes the statements below?

The US will prioritize to (1) .

After the action is completed with expected response, the US will NEXT direct

performance of (2) .

A. (1) realign 3D 4kV Bus

(2) Attachment 6, 3A 4KV Bus Restoration

B. (1) realign 3D 4kV Bus

(2) Attachment 1, 3A 4KV Bus Stripping

C. (1) reset 3A EDG lockout

(2) Attachment 6, 3A 4KV Bus Restoration

D. (1) reset 3A EDG lockout

(2) Attachment 1, 3A 4KV Bus Stripping

NRC L-17 -1 EXAM SECURE INFORMATION

Question # 79

Given the following conditions:

Both units are at 100% power.

4A EDG is OOS.

Subsequently:

Unit 4 experiences a LOOP coincident with the loss of 4D23 Vital DC bus.

4-EOP-E-0, Reactor Trip or Safety Injection, IOAs are in progress.

Which one of the following (1) identifies a train of Tech Spec Accident Monitoring

Instrumentation that is NOT available and (2) procedure implementation to

restore power to 4D23 DC bus?

A. (1) Reactor Vessel Level Monitoring

(2) 4-ONOP-003.5, Loss of DC Bus 4D23, will be performed

simultaneously with 4-EOP-E-0, Reactor Trip or Safety Injection

B. (1) Reactor Vessel Level Monitoring

(2) 4-ONOP-003.5, Loss of DC Bus 4D23, will be entered once the unit has

been stabilized IAW 4-EOP-ES-0.1, Reactor Trip Response

C. (1) Drain Down Level Indication

(2) 4-ONOP-003.5, Loss of DC Bus 4D23, will be performed

simultaneously with 4-EOP-E-0, Reactor Trip or Safety Injection

D. (1) Drain Down Level Indication

(2) 4-ONOP-003.5, Loss of DC Bus 4D23, will be entered once the unit has

been stabilized IAW 4-EOP-ES-0.1, Reactor Trip Response

NRC L-17 -1 EXAM SECURE INFORMATION

Question # 80

Given the following conditions:

Both Units are at 100% power.

Both Units MVAR load suddenly start fluctuating.

Subsequently:

Unit 3 Main Generator parameters are:

22 kV

860 MWe

350 MVAR in the LEAD

Hydrogen pressure is 65 psig

Which one of the following completes the statements below?

The US will direct maintaining Main Generator reactive load below a MAXIMUM

of (1) .

The US will direct steps from (2) to mitigate this event.

REFERENCE PROVIDED

A. (1) 200 MVAR in the LEAD

(2) 3-ONOP-090, Abnormal Generator MW/MVAR Oscillation

B. (1) 200 MVAR in the LEAD

(2) 0-ONOP-004.6, Degraded Switchyard Voltage

C. (1) 300 MVAR in the LEAD

(2) 3-ONOP-090, Abnormal Generator MW/MVAR Oscillation

D. (1) 300 MVAR in the LEAD

(2) 0-ONOP-004.6, Degraded Switchyard Voltage

NRC L-17 -1 EXAM SECURE INFORMATION

Question # 81

Given the following conditions:

Unit 3 tripped from 100% power.

While 3-EOP-ES-0.1, Reactor Trip Response, was in progress a transition

to 3-EOP-FR-H.1, Response to Loss of Secondary Heat Sink, was made.

RCS bleed and feed is established.

Subsequently:

The BOP establishes flow from the A Standby SG Feed Pump.

SG NR levels are off-scale low.

Which one of the following identifies the NEXT required action?

A. Remain in 3-EOP-FR-H.1, Response to Loss of Secondary Heat Sink, and

restore SG NR level.

B. Immediately terminate RCS bleed and feed and

transition to 3-EOP-ES-1.1, SI termination.

C. Transition to 3-EOP-ES-0.1, Reactor Trip Response and

verify natural circulation.

D. Transition to 3-EOP-E-1, Loss of Reactor or Secondary Coolant and

close any PORV that is open.

NRC L-17 -1 EXAM SECURE INFORMATION

Question # 82

Given the following conditions:

Core re-load is in progress on Unit 4.

Containment Purge is in progress.

Subsequently:

The Refueling SRO reports a dropped spent fuel assembly in the

containment.

R-4-11, Containment Air Particulate Process Monitor, and R-4-12,

Containment Air Gaseous Process Monitor, are rising.

Which one of the following the identifies (1) the NEXT procedure and (2) the

associated action directed by the US?

A. (1) 4-ONOP-033.3, Accidents Involving New or Spent Fuel

(2) stop Containment Purge

B. (1) 4-ONOP-033.3, Accidents Involving New or Spent Fuel

(2) close the Equipment Hatch Fast Closure Door

C. (1) 4-ONOP-067, Radioactive Effluent Release

(2) stop Containment Purge

D. (1) 4-ONOP-067, Radioactive Effluent Release

(2) close the Equipment Hatch Fast Closure Door

NRC L-17 -1 EXAM SECURE INFORMATION

Question # 83

Given the following conditions:

PRMS R-14, Plant Vent Gaseous Effluent Monitor, high alarm actuates.

RI-1418B, Aux Building E/W corridor ARM, high alarm actuates.

Field operator reports B GDT is at 87 psig and slowly lowering.

Which one of the following completes the statements below?

The US will direct re-alignment of the waste gas system IAW (1) .

The contents of B GDT (2) required to be transferred to another GDT.

A. (1) 0-ONOP-066, High Area Radiation Monitoring System Alarm

(2) are NOT

B. (1) 0-ONOP-066, High Area Radiation Monitoring System Alarm

(2) are

C. (1) 3-ONOP-067, Radioactive Release

(2) are NOT

D. (1) 3-ONOP-067, Radioactive Release

(2) are

NRC L-17 -1 EXAM SECURE INFORMATION

Question # 84

Given the following conditions:

Unit 3 is at 100% power.

3-OSP-038.4, Spent Fuel Pit Bridge Crane Operability Test, is in progress.

Fuel Transfer canal is empty.

It is 10:00 am

Keyway gate is accidentally hit and starts leaking.

SFP Level is 56 feet and lowering.

ANN X4/1, ARMS HI RADIATION, alarms.

RI-3-1421B, Unit 3 Spent Fuel Pit North Wall, reads 21 mR/hr and rising.

Which one of the following completes the statement below?

At 10:10 am the EC declares (1) .

The State and County are required to be notified by (2) .

REFERENCE PROVIDED

A. (1) an Alert

(2) 10:15 am

B. (1) an Alert

(2) 10:25 am

C. (1) an Unusual Event

(2) 10:15 am

D. (1) an Unusual Event

(2) 10:25 am

NRC L-17 -1 EXAM SECURE INFORMATION

Question # 85

Given the following conditions:

Unit 3 experiences a LOCA from 100% power.

Cold Leg Recirculation is being initially aligned.

The RO places 3A and 3B Containment Spray Pumps in PULL-TO-LOCK.

Subsequently:

DCS indicates an Orange path on Containment.

Which one of the following completes the statements below?

The US will .

NOTE:

3-EOP-ES-1.3, Transfer To Cold Leg Recirculation

3-EOP-FR-Z.1, Response to High Containment Pressure

A. immediately transition to 3-EOP-FR-Z.1

B. direct to re-start one Containment Spray Pump,

then transition 3-EOP-FR-Z.1

C. implement 3-EOP-ES-1.3 and 3-EOP-FR-Z.1 simultaneously

D. continue ONLY implementation of 3-EOP-ES-1.3

NRC L-17 -1 EXAM SECURE INFORMATION

Question # 86

Given the following conditions:

A LOCA occurred on Unit 3.

3B 4kV bus is locked out.

The BOP just completed Attachment 3 of 3-EOP-E-0, Reactor Trip or Safety

Injection.

Subsequently:

A field operator reports that smoke is coming from 3A SI pump bearing.

The following alarms are received sequentially:

ANN H4/1, SI PP 3A MOTOR OVERLOAD.

ANN H3/1, SI PP 3A TRIP.

Which one of the following completes the statements below?

The US supervisor will direct performance of (1) to correct the condition, if

the crew failed to carry these actions, CET temperatures (2) expected to

rise above 700°F.

A. (1) 3-EOP-FR-C.3, Response To Saturated Core Cooling

(2) are NOT

B. (1) 3-EOP-FR-C.3, Response To Saturated Core Cooling

(2) are

C. (1) 3-ARP-097.CR.H, Control Room Response - Panel H

(2) are NOT

D. (1) 3-ARP-097.CR.H, Control Room Response - Panel H

(2) are

NRC L-17 -1 EXAM SECURE INFORMATION

Question # 87

Given the following conditions:

Unit 3 is at 7% power.

Subsequently:

N-3-43, Power Range Nuclear Instrument, fails low.

Which one of the following completes the statements below?

IAW Tech Specs, N-3-43 (1) required to be placed in the tripped condition

within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

With N-3-43 OOS, power (2) required to be maintained below 10% power.

A. (1) is NOT

(2) is

B. (1) is NOT

(2) is NOT

C. (1) is

(2) is

D. (1) is

(2) is NOT

NRC L-17 -1 EXAM SECURE INFORMATION

Question # 88

Given the following conditions:

Unit 3 is at 100% power.

The Steam Jet Air Ejector Hogging Jet is in service.

3C SG experiences a SG tube leak.

Subsequently:

3-EOP-E-3, Steam Generator Tube Rupture, is in progress

3C SG NR level is rising rapidly.

3C SG pressure is 425 psig and lowering.

RWST level is 198,000 gallons and lowering.

Which one of the following completes the statements below?

SJAE SPING (1) OPERABLE.

The US will NEXT implement (2) .

A. (1) is

(2) 3-EOP-ECA-3.1, SGTR With Loss of Reactor Coolant-Subcooled

Recovery Desired.

B. (1) is

(2) 3-EOP-ECA-3.2, SGTR With Loss Of Reactor Coolant-Saturated

Recovery Desired

C. (1) is NOT

(2) 3-EOP-ECA-3.1, SGTR With Loss of Reactor Coolant-Subcooled

Recovery Desired.

D. (1) is NOT

(2) 3-EOP-ECA-3.2, SGTR With Loss Of Reactor Coolant-Saturated

Recovery Desired

NRC L-17 -1 EXAM SECURE INFORMATION

Question # 89

Given the following conditions:

Unit 4 is operating at 100% power.

Backwashing 4A ICW/CCW and 4B ICW/TPCW strainers, is in progress.

While restoring:

4-50-324, ICW/CCW Basket Strainer A Inlet Isol, experiences a sheared pin

(valve handwheel spins freely) and remains closed.

POV-4-4883, ICW to TPCW Heat Exchangers Isolation Valve, is failed closed

and will not re-open.

Which one of the following completes the statements below?

4-NOP-019, Intake Cooling Water System, limitations for strainer backwashing

(1) violated.

Unit 4 US (2) required to be in at least HOT SHUTDOWN within the

following 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months .

A. (1) are

(2) is

B. (1) are

(2) is NOT

C. (1) are NOT

(2) is

D. (1) are NOT

(2) is NOT

NRC L-17 -1 EXAM SECURE INFORMATION

Question # 90 Pen and Ink change

performed during

Given the following timeline: administration (Ref

Student Question

10:00 am Unit 3 experiences a LOCA from 100% power. Feedback Form #16)

10:10 am RCS pressure is 450 psig and lowering.

10:10 am CET subcooling is 17°F and lowering.

10:10 am Containment pressure is 27 psig and rising slowly.

10:10 am Both CHRRMS channels read 5 x 103 R/hr.

10:15 am There is a report of a loud noise in the Aux Building.

10:15 am Containment pressure is 21 psig and rapidly lowering.

10:16 am ANN X4/1, ARMS HI RADIATION, alarms.

Which one of the following completes the statements below?

During crew response to the conditions stated above, the mitigating actions of

0-ONOP-066, High Area Radiation Monitoring, that do NOT interfere with the

applicable EOP (1) allowed to be performed in parallel.

The highest classification for this event is (2) .

REFERENCE PROVIDED

A. (1) are

(2) General Emergency

B. (1) are

(2) Site Area Emergency

C. (1) are NOT

(2) General Emergency

D. (1) are NOT

(2) Site Area Emergency

NRC L-17 -1 EXAM SECURE INFORMATION

Question # 91

Given the following conditions:

Unit 3 is at 85% power.

Control Bank D Demand Counters are at 170 steps.

Control Bank D RPIs indicate 168 steps except control rod H-12 at 55 steps.

A Flux Map estimates H-12 position at 167 steps.

Which one of the following completes the statements below?

Flux maps will ensure (1) limits are NOT violated.

Upon failure of a second RPI on Control bank D the US (2) be required to

be in at least HOT STANDBY within the next 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months .

A. (1) shutdown margin

(2) will NOT

B. (1) shutdown margin

(2) will

C. (1) power distribution

(2) will NOT

D. (1) power distribution

(2) will

NRC L-17 -1 EXAM SECURE INFORMATION

Question # 92

Given the following conditions:

Unit 4 is in MODE 6.

The crew commenced rod unlatching.

Subsequently:

Annunciator I4/6, CNTMT SUMP HI LEVEL, alarms.

Reactor Cavity water level is 56 feet and lowering.

4-ONOP-041.3, Excessive Reactor Coolant System Leakage, is in progress.

Which ONE of the following completes the statement below?

Operator action to close the Containment Purge Isolation valves will be

performed following a required transition to (1) .

The US will direct to (2) .

A. (1) 4-ONOP-033.2, Refueling Cavity Seal Failure

(2) monitor containment for airborne contamination

B. (1) 4-ONOP-033.2, Refueling Cavity Seal Failure

(2) place PAHMS in service

C. (1) 4-ONOP-041.8, Shutdown LOCA [MODE 5 OR 6]

(2) monitor containment for airborne contamination

D. (1) 4-ONOP-041.8, Shutdown LOCA [MODE 5 OR 6]

(2) place PAHMS in service

NRC L-17 -1 EXAM SECURE INFORMATION

Question # 93

Given the following conditions:

Core off-load to the SFP is in progress on Unit 3.

3-12-031, Unit 3 Fuel Transfer Tube Gate Valve, is OPEN.

SFP is currently aligned for purification.

Subsequently:

ANN H1/2, SFP HI TEMP, alarms.

Field operator reports:

SFP temperature is 150°F and slowly rising.

SFP level is stable at 57 feet.

Which one of the following completes the statements below?

The US will direct implementation of (1) .

The SFP Purification loop (2) required to be shutdown.

A. (1) 3-ONOP-033.1, Spent Fuel Pit Cooling System Malfunction

(2) is NOT

B. (1) 3-ONOP-033.1, Spent Fuel Pit Cooling System Malfunction

(2) is

C. (1) 3-ONOP-030, Component Cooling Water Malfunction

(2) is NOT

D. (1) 3-ONOP-030, Component Cooling Water Malfunction

(2) is

NRC L-17 -1 EXAM SECURE INFORMATION

Question # 94

Given the following conditions:

Unit 3 is in MODE 5.

Unit 4 is in MODE 4.

Which one of the following identifies the responsibilities of the SRO assigned to

the STA position?

The SRO assigned to the STA (1) required to remain within 10 minutes of

the control room and (2) allowed to assume command and control

responsibilities.

A. (1) is NOT

(2) is

B. (1) is NOT

(2) is NOT

C. (1) is

(2) is

D. (1) is

(2) is NOT

NRC L-17 -1 EXAM SECURE INFORMATION

Question # 95

Given the following conditions:

At 0000 on 8/01/2017, a Unit 4 shutdown to MODE 3 is commenced.

At 0630 on 8/01/2017, Unit 4 enters MODE 3.

At 2200 on 8/02/2017, the first reactor vessel head stud is de-tensioned.

Which one of the following completes the statements below?

In accordance with Technical Specifications, the EARLIEST time that fuel

movement may commence is (1) .

The basis for this time requirement is to ensure that sufficient time has elapsed to

allow (2) .

A. (1) 0630 on 08/04/17

(2) the radioactive decay of short-lived fission products. This limits public

dose in case of a fuel handling accident.

B. (1) 0630 on 08/04/17

(2) the fuel assemblies to cool. This ensures that boiling will be prevented

in the Spent Fuel Pool in case of a loss of forced flow.

C. (1) 2200 on 08/05/17

(2) the radioactive decay of short-lived fission products. This limits public

dose in case of a fuel handling accident.

D. (1) 2200 on 08/05/17

(2) the fuel assemblies to cool. This ensures that boiling will be prevented

in the Spent Fuel Pool in case of a loss of forced flow.

NRC L-17 -1 EXAM SECURE INFORMATION

Question # 96

Given the following conditions:

Unit 3 is operating at 100% power.

It is discovered that 3A EDG monthly surveillance was LAST performed 33

days ago.

Which of the following completes the statements below?

3A EDG (1) OPERABLE.

The surveillance interval (2) allowed to be extended by 25% beyond the due

date.

A. (1) is NOT

(2) is

B. (1) is NOT

(2) is NOT

C. (1) is

(2) is

D. (1) is

(2) is NOT

NRC L-17 -1 EXAM SECURE INFORMATION

Question # 97

Given the following conditions:

Unit 3 is preparing for performance of 0-OSP-040.16, Initial Criticality After

Refueling and Nuclear Design Verification.

Which ONE of the following completes the statements below in accordance with

OP-AA-1000, Conduct of Infrequently Performed Tests or Evolutions (IPTE)?

The IPTE Manager (1) required to be an active licensed SRO.

Unit 3 - Unit Supervisor (2) to assume the role of the IPTE Manager.

A. (1) is

(2) is allowed

B. (1) is

(2) is NOT allowed

C. (1) is NOT

(2) is allowed

D. (1) is NOT

(2) is NOT allowed

NRC L-17 -1 EXAM SECURE INFORMATION

Question # 98

Given the following conditions:

Unit 3 is in MODE 3 during a plant heatup.

RI-3-6311A, Containment High Range Radiation Monitor, fails.

RI-3-6311B is declared inoperable after determining that there is an existing

common equipment problem.

Which one of the following completes the statements below?

Techs Specs (1) entry into MODE 2.

The Unit Supervisor will determine that the Containment High Radioactivity input

into the Control Room Ventilation Isolation (2) OPERABLE.

REFERENCE PROVIDED

A. (1) does NOT allow

(2) remains

B. (1) does NOT allow

(2) is NOT

C. (1) allows

(2) remains

D. (1) allows

(2) is NOT

NRC L-17 -1 EXAM SECURE INFORMATION

Question # 99

Given the following conditions:

Unit 3 and Unit 4 are in MODE 1.

Subsequently:

Fire alarms are received in Fire Zone 098, Units 3 and 4 Cable Spreading

Room.

Black smoke is entering the Control Room atmosphere.

Cable Spreading Room Halon FAILS to automatically discharge.

Which one of the following completes the statements below?

The Halon System will be manually actuated IAW (1) .

NRC notification is required within (2) .

REFERENCE PROVIDED

A. (1) 0-ONOP-16.8, Response to a Fire/Smoke Detection System Alarm

(2) 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

B. (1) 0-ONOP-16.8, Response to a Fire/Smoke Detection System Alarm

(2) 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months

C. (1) 0-ONOP-105, Control Room Evacuation

(2) 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

D. (1) 0-ONOP-105, Control Room Evacuation

(2) 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months

NRC L-17 -1 EXAM SECURE INFORMATION

Question # 100

Which one of the following completes the statements below regarding the

delegation of SM/Emergency Coordinator responsibilities?

The decision to notify federal, State and Local authorities (1) allowed to be

delegated.

The action to notify federal, State and Local authorities (2) allowed to be

delegated.

A. (1) is

(2) is

B. (1) is

(2) is NOT

C. (1) is NOT

(2) is

D. (1) is NOT

(2) is NOT

76 A

77 D

78 D

79 B

80 A

81 A

82 A

83 D

84 D

85 D

86 C

87 D

88 C

89 B - Question Answer Revised - Refer to Post-Exam Comment Item #2

Resolution in the Turkey Point 2017-301 Exam Report, Enclosure 2

90 B

91 D

92 A

93 B

94 D

95 A

96 C

97 D

98 C

99 A

100 C

L-17-1 NRC Written Exam References

L-17-1 NRC Written Exam References List

SRO Only References

PCB Section 4 figures

EAL Tables:

EPIP-20101, Duties of Emergency Coordinator, Attachment 1 - F668,

Hot Conditions Table, Rev 12

EPIP-20101, Duties of Emergency Coordinator, Attachment 2 - F669,

Cold Conditions Table, Rev 5

TS 3.3.3.3

LI-AA-102-1001, Regulatory Reporting, Attachment 1 (Pages 1

through 8), Rev 11

L-17-1 NRC Written Exam References

INSTRUMENTATION

ACCIDENT MONITORING INSTRUMENTATION

LIMITING CONDITION FOR OPERATION

3.3.3.3 The accident monitoring instrumentation channels shown in Table 3.3-5 shall be OPERABLE.

APPLICABILITY: As shown in Table 3.3-5.

ACTION:

a. As shown in Table 3.3-5.

b. The provisions of Specification 3.0.4 are not applicable to ACTIONS in Table 3.3-5 that require a

shutdown.

c. Separate Action entry is allowed for each Instrument.

SURVEILLANCE REQUIREMENTS 4.3.3.3 Each accident monitoring instrumentation channel shall be demonstrated OPERABLE by performance of

the CHANNEL CHECK and CHANNEL CALIBRATION at the frequencies shown in Table 4.3-4.

TURKEY POINT - UNITS 3 & 4 3/4 3-45 AMENDMENT NOS. 260 AND 255

L-17-1 NRC Written Exam References

Redacted text- blocked out

TABLE 3.3-5

TURKEY POINT - UNITS 3 & 4

ACCIDENT MONITORING INSTRUMENTATION

TOTAL MINIMUM APPLI-

NO. OF CHANNELS CABLE

INSTRUMENT CHANNELS OPERABLE MODES ACTIONS

1. Containment Pressure (Wide Range) 2 1 1, 2, 3 31, 32

2. Containment Pressure (Narrow Range) 2 1 1, 2, 3 36

3. Reactor Coolant Outlet Temperature THOT (Wide Range) 2-2 Detectors 1-2 Detectors 1, 2, 3 31, 32

per Channel per Channel

4. Reactor Coolant Inlet Temperature TCOLD (Wide Range) 2-2 Detectors 1-2 Detectors 1, 2, 3 31, 32

per Channel per Channel

5. Reactor Coolant Pressure - Wide Range 2 1 1, 2, 3 31, 32

3/4-3-46 6. Pressurizer Water Level 2 1 1, 2, 3 31, 32

7. Auxiliary Feedwater Flow Rate 2/steam 1/steam 1, 2, 3 31, 32

generator generator

8. Reactor Coolant System Subcooling Margin Monitor 2(2) 1(2) 1, 2, 3 31, 32

9. PORV Position Indicator (Primary Detector) 1/valve 1/valve 1, 2, 3 33

AMENDMENT NOS. 260 AND 255

10. PORV Block Valve Position Indicator 1/valve 1/valve 1, 2, 3 33

11. Safety Valve Position Indicator (Primary Detector) 1/valve 1/valve 1, 2, 3 32

12. Containment Water Level (Narrow Range) 2 1 1, 2, 3 36

13. Containment Water Level (Wide Range) 2 1 1, 2, 3 31, 32

L-17-1 NRC Written Exam References

Redacted text- blocked out

TURKEY POINT - UNITS 3 & 4

TABLE 3.3-5 (Continued)

ACCIDENT MONITORING INSTRUMENTATION

TOTAL MINIMUM APPLI-

NO. OF CHANNELS CABLE

INSTRUMENT CHANNELS OPERABLE MODES ACTIONS

14. In Core Thermocouples (Core Exit 4/core 2/core 1, 2, 3 31, 32

Thermocouples) quadrant quadrant

15. Containment High Range Area Radiation 2 1 1, 2, 3 34

16. Reactor Vessel Level Monitoring 2(1) 1(1) 1, 2, 3 37, 38

System

17. Neutron Flux, Backup NIS (Wide Range) 2 1 1, 2, 3 31, 32

18. DELETED

3/4 3-47

19. High Range-Noble Gas Effluent Monitors

a. Plant Vent Exhaust 1 1 ALL 34

b. Unit 3-Spent Fuel Pit Exhaust 1 1 ALL 34

c. Condenser Air Ejectors 1 1 1, 2, 3 34

AMENDMENT NOS. 260 AND 255

20. RWST Water Level 2 1 1, 2, 3 31, 32

21. Steam Generator Water Level (Narrow Range) 2/stm. Gen. 1/stm. Gen. 1, 2, 3 31, 32

22. Containment Isolation Valve Position Indication* 1/valve 1/valve 1, 2, 3 39

TABLE NOTATIONS

1. A channel is eight sensors in a probe. A channel is OPERABLE if a minimum of four sensors are OPERABLE.

2. Inputs to this instrument are from instrument items 3, 4, 5 and 14 of this Table.

Applicable for containment isolation valve position indication designated as post-accident monitoring instrumentation (containment

isolation valves which receive containment isolation Phase A, Phase B, or containment ventilation isolation signals).

L-17-1 NRC Written Exam References

TABLE 3.3-5 (Continued)

ACTION STATEMENTS

ACTION 31 With the number of OPERABLE accident monitoring instrumentation channel(s) less than the

Total Number of Channels either restore the inoperable channel(s) to OPERABLE status within

30 days, or submit a Special Report to the Commission pursuant to Specification 6.9.2 within the

next 14 days outlining the action taken, the cause of the inoperability, and the plans and schedule

for restoring the system to OPERABLE status.

ACTION 32 With the number of OPERABLE accident monitoring instrumentation channels less than the

Minimum Channels OPERABLE, either restore the inoperable channel(s) to OPERABLE status

within 7 days, or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT

SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 33 Close the associated block valve and open its circuit breaker.

ACTION 34 With the number of OPERABLE Channels less than required by the Minimum Channels

OPERABLE requirements, initiate the preplanned alternate method of monitoring the appropriate

parameter(s), within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , and:

1) Either restore the inoperable channel(s) to OPERABLE status within 7 days of the event,

or

2) Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2

within the next 14 days outlining the action taken, the cause of the inoperability, and the

plans and schedule for restoring the system to OPERABLE status.

ACTION 35 DELETED

ACTION 36 With the number of OPERABLE accident monitoring instrumentation channels less than the

Minimum Channel OPERABLE, either restore the inoperable channel to OPERABLE status within

30 days, or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT

SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 37 With the number of OPERABLE channels one less than the Total Number of Channels, restore

the system to OPERABLE status within 30 days. If repairs are not feasible without shutting down,

prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the

next 14 days outlining the action taken, the cause of the inoperability and the plans and schedule

for restoring the system to OPERABLE status.

TURKEY POINT - UNITS 3 & 4 3/4 3-48 AMENDMENT NOS. 260 AND 255

TABLE 3.3-5 (Continued)

ACTION STATEMENTS

ACTION 38 With the number of OPERABLE channels less than the Minimum Channels OPERABLE

requirements, restore the inoperable channel(s) to OPERABLE status within 7 days. If repairs

are not feasible without shutting down:

1. Initiate an alternate method of monitoring the reactor vessel inventory; and

2. Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2

within the next 14 days outlining the action taken, the cause of the inoperability and the

plans and schedule for restoring the system to OPERABLE status; and

3. Restore at least one channel to OPERABLE status at the next scheduled refueling.

ACTION 39 With the number of OPERABLE channels less than the Minimum Channels OPERABLE

requirement, verify position by an alternate means (e.g. administrative controls, ERDADS,

alternate position indication, or visual observation) within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , and restore the inoperable

channel(s) within 7 days, or comply with the provisions of Specification 3.6.4 for an inoperable

containment isolation valve.

TURKEY POINT - UNITS 3 & 4 3/4 3-49 AMENDMENT NOS. 260 AND 255

ML17349A188

Text

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