Text

Final SRO Written Exam
	ML13106A201
Person / Time
Site:	Watts Bar
Issue date:	04/15/2013
From:	; NRC/RGN-II
To:	; Tennessee Valley Authority
References
	Download: ML13106A201 (46)
	v • d • e

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:

04/03/13 Facility/Unit:

Watts Bar/ Unit 1 Region:

I Q II Ill IV fl Reactor Type: WE CE j BW D3E L 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 80.00 percent overall, with 70.00 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 80.00 percent to pass. You have 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-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 portion.

Applicant Certification All work done on this examination is my own.

I have neither given nor received aid.

Applicants Signature Results RO/SRO-OnIy/Total Examination Values

/

Points Applicants Scores

/

I Points Applicants Grade I

/

Percent ES-401, Page 31 of33

03-2013 WATTS BAR NRC SRO LICENSE EXAM 4/3/2013

76. Given the following:

Initial Conditions Unit 1 is at 50% RTP.

Reactor Trip breaker RTB is closed.

Bypass breaker BYA is racked in and closed.

Current Conditions An automatic Reactor trip signal is generated due to Low SIG level.

RTB and BYA UV trip coils are deenergized but fail to actuate.

- The remainder of the reactor protection circuitry (RPS) operates as designed.

Which ONE of the following completes the statements below?

In response to the reactor trip signal (1) will open.

The first notification to the NRC of the reactor trip breaker(s) opening is required within a maximum of (2) hours in accordance with NPG-SPP-03.5, Regulatory Reporting Requirements.

Li)

L)

A.

only RTB will open 4

B.

BYA and RTB will open 4

C.

only RTB will open 8

D. BYA and RTB will open 8

Page 76

03-2013 WATTS BAR NRC SRO LICENSE EXAM 4/3/2013

77. Given the following:

Unit 1 operating crew is currently performing 1-ECA-3.1, SGTR and LOCA

- Subcooled Recovery.

ECCS flow has been terminated and normal charging is in service.

Containment conditions are normal.

RVLIS indicates 94%.

Pressurizer level is 62% and rising.

RCS subcooling is 137°F.

RCPs were stopped in accordance with the EOP5 prior to 1-ECA-3.1 entry and the crew is attempting to establish RCP Emergency Restart Criteria.

Which ONE of the following completes the statements below?

In order to start a RCP, (1) is required to be raised.

If the crew is unable to start an RCP, the procedure directs (2) i)

A. pressurizer level the crew to continue in 1-ECA-3.1 B. pressurizer level a transition to 1-ECA-3.2, SGTR and LOCA Satu rated Recovery C. RCS subcooling the crew to continue in 1-ECA-3.1 D. RCS subcooling a transition to 1-ECA-3.2, SGTR and LOCA Saturated Recovery Page 77

03-2013 WATTS BAR NRC SRO LICENSE EXAM 4/312013

78. Given the following:

Unit 1 is operating at 43% power with a turbine load increase in progress.

A failure in the turbine control system resulted in an inadvertent ramp increase in reactor power to 49% in less than one minute before the operating crew stabilized the unit.

The Pressurizer pressure dropped below the minimum allowed by Tech Spec LCD 3.4.1, RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits before beginning to return to normal.

The SRO is evaluating Tech Spec LCD 3.4.1 and determines the conditions did not require an entry into a REQUIRED ACTIDN.

Which DNE of the following completes the statement below?

The pressurizer pressure was first below Tech Spec LCO 3.4.1 minimum when the pressurizer pressure dropped to less than (1) but the condition did not result in entry into the REQUIRED ACTIDN because the (2) w A. 2217 psig condition represents short term perturbations where actions to control pressure variations might be counterproductive B.

2214 psig conditions represent short term perturbations where actions to control pressure variations might be counterproductive C.

2217 psig current reduced power condition eliminates the potential for violation of the accident analysis bounds D.

2214 psig current reduced power condition eliminates the potential for violation of the accident analysis bounds Page 78

03-2013 WATTS BAR NRC SRO LICENSE EXAM 4/312013

79. Given the following:

Unit 1 is operating at 100% power when the following occurs:

1100

- The steam line leaving SG #3 breaks inside containment.

1101

- Safety injection occurs due to containment pressure.

1103

- Containment Phase B isolation occurs.

1104

- CR0 reports SG #3 pressure is 675 psig and dropping and the other 3 SG pressures are stable at 860 psig.

1105

- Operating Crew enters 1 -E-2, Faulted Steam Generator Isolation.

Which ONE of the following completes the statements below?

The 15 minute clock to make a required REP declaration is first initiated (1)

The correct classification is an (2)

L1)

A.

1101 NOUE B.

1101 ALERT C.

1104 NOUE D.

1104 ALERT Page 79

03-2013 WATTS BAR NRC SRO LICENSE EXAM 413/2013

80. Given the following:

Unit 1 is operating at 100% power when a loss of 1 20V AC Vital Instrument Power Boards 1-I occurs.

The OAC trips the reactor and the crew enters 1 -E-0, Reactor Trip or Safety Injection, in accordance with required IMMEDIATE ACTION of 1-AOI-25.01, Loss of 120V AC Vital Instrument Power Boards 1-I or 2-I.

A transition is made to ES-0.1, Reactor Trip Response.

Pressurizer level is uncontrolled due to a loss of air to containment.

Which ONE of the following completes the statements below?

Performance of 1-AOl-25.01 is to be continued (1)

Air to containment (2) be restored with steps in 1-AOI-25.01.

Li)

L)

A. only after ES-0.1 is complete will B. only after ES-0.1 is complete will NOT C.

concurrently with ES-0.1 will D.

concurrently with ES-0.1 will NOT Page 80

03-2013 WATTS BAR NRC SRO LICENSE EXAM 4/312013

81. Given the following:

Unit 1 is operating at 100% power.

1930 Annunciator 228-C, ERCW HDR 2B STRAINER AP HI alarms. The alarm clears following strainer backwash.

2100 Annunciator 224-C, ERCW HDR lB STRAINERz\\P HI alarms. The alarm clears following strainer backwash.

0030 Annunciator 223-C, ERCW HDR 1A STRAINER AP HI alarms. The alarm clears following strainer backwash.

0230 Annunciator 227-C, ERCW HDR 2A STRAINER AP HI alarms. The alarm clears following strainer backwash.

0330 Annunciator 228-C, ERCW HDR 2B STRAINER AP HI alarms again.

The following approximate values have remained constant on the ERCW system throughout the event:

0-PI-67-18A, A ERCW SUP HDR PRESS 95 psig 0-PI-67-17A, B ERCW SUP HDR PRESS 105 psig 1-PI-67-61, 1AERCWSUPHDRFLOW

- 2250gpm 1-PI-67-62, lB ERCW SUP HDR FLOW

- 1750 gpm 2-PI-67-61, 2A ERCW SUP HDR FLOW

- 8250 gpm 2-Fl-67-62, 2B ERCW SUP HDR FLOW

- 5000 gpm Which ONE of the following completes the statement below?

In addition to the procedure for backwashing the strainers, additional guidance for these conditions can be found in A. SOI-67.01, Essential Raw Cooling Water System, Section 8.8, Cross-Tie Header iBto 2A B. 0-PI-OPS-1-IBE, Preparations and Response Strategies for Intake Intrusion/Blockage Event C. S0I-67.01, Essential Raw Cooling Water System, Section 8.5, Cross-Tie B-Train ERCW Supply Headers D. AOI-13, Loss of Essential Raw Cooling Water, Section 3.4, Supply header Rupture in Yard Downstream of Strainer or Plugged Strainer Page 81

03-2013 WATTS BAR NRC SRO LICENSE EXAM 4/3/2013

82. Given the following:

An accidental radiological release from the Condensate Demin System occurred due to a system mis-alignment while configuring the plant for a planned release.

Which ONE of the following completes the statements below in accordance with EPIP-1, Emergency Plan Classification Logic?

An ALERT would be first required to be declared if the unplanned release sample results exceed (1) times the ODCM Limit.

The radiation monitor indication on (2) is the primary indication to be used to quantify the release.

w t)

A.

2 ICS B.

2 O-M-12 C.

200 ICS D.

200 0-M-12 Page 82

03-2013 WATTS BAR NRC SRO LICENSE EXAM 4/3/2013

83. Given the following:

Unit I is operating at 100% power.

A fire has been reported in the Auxiliary Building on Elevation 692.

AOI-30.1, Plant Fires, has been entered.

Which ONE of the following completes the statements below?

The Unit SRO/Shift Manager decision to declare an Appendix R fire must be based on the magnitude of the fire and its potential effect on the equipment/components necessary to (1)

If the fire is determined to have started in Unit 2 TD-AFWP room and spreads into the Corridor Area Al B, 1 -AOl-30.2 C.54 (2) required to be performed in addition to 1-AOI-30.2 C.60.

REFERENCE PROVIDED A.

(1) mitigate a design basis accident (2) is NOT B. (1) mitigate a design basis accident (2)is C. (I) achieve and maintain cold shutdown (2) is NOT D. (1) achieve and maintain cold shutdown (2)is Page 83

03-2013 WATTS BAR NRC SRO LICENSE EXAM 4/312013

84. Given the following:

While operating at 100% a small break LOCA occurred on Unit 1.

The operating crew has progressed through the emergency instructions and has placed RHR Train A in service in accordance with SOI-74.01, Residual Heat Removal System, during performance of ES-I.2, Post LOCA Cooldown and Depressurization.

The STA identifies a YELLOW path to FR-C.3, Saturated Core Cooling, and the SRO makes the transition.

Which ONE of the following completes the statements below?

The basis of FR-C.3 is to (1)

After entering FR-C.3, a transition to AOl-i 4, Loss of RHR Shutdown

Cooling, (2) be directed.

A.

establish RCS cooling via SGs will B.

establish RCS cooling via SGs will NOT C. restore subcooling using ECCS will D. restore subcooling using ECCS will NOT Page 84

03-2013 WATTS BAR NRC SRO LICENSE EXAM 41312013

85. Given the following:

Unit 1 was operating at 100% power when a LOCA occurs.

After the operating crew entered 1 -E-1, Loss of Reactor or Secondary Coolant, the OAC reported the following:

- Containment pressure 2.9 psig and rising.

- Containment Spray Pump lA-A started and tripped.

- Containment Spray Pump lB-B failed to start.

The SRO enters 1-FR-Z.1, High Containment Pressure.

During performance of 1-FR-Z.1, the OAC reports:

Containment pressure is 1.8 psig and dropping.

Containment Spray Pump I B-B has been started at the breaker and is deilvering flow.

Containment Sump level at 86%.

Assuming all Status trees except CONTAINMENT are GREEN, which ONE of the following identifies the correct procedure usage by the Unit Supervisor?

A. Remain in 1-FR-Z.1 until a transition is directed, then return to 1-E-1.

B.

Remain in 1-FR-Z.1 until a transition is directed, then implement FR-Z.2, Containment Flooding.

C. Immediately transition to FR-Z.2, Containment Flooding, and return to 1-FR-Z.1 when a transition is directed from FR-Z.2.

D. Immediately transition to FR-Z.2, Containment Flooding, and return to 1-E-1 when a transition is directed from FR-Z.2.

Page 85

03-2013 WATTS BAR NRC SRO LICENSE EXAM 4/3/2013

86. Given the following:

Unit 1 is operating at 100% power with RCS Operational Leakage values of:

0.03 gpm

- Identified 0.02 gpm

- Unidentified Annunciator 110-B, LO PRESS LTDN FLOW/PRESS HI, alarms.

1-Pl-62-81, LP LETDOWN PRESS, is oscillating between 310

- 360 psig.

1-Fl-62-82, LETDOWN FLOW, is oscillating between 70

- 75 gpm.

OAC places 1-HIC-62-81A, LETDOWN PRESS CONTROL, to MANUAL after determining the valve was oscillating and reduces the oscillation on 1-Pl-62-81 to between 310 to 330 psig.

After 1-HIC-62-81A was placed to MANUAL an AUO sent to investigate reports back: Pl-62-81C, LP LETDOWN PRESS, oscillating between 310 psig and 330 psig. PI-62-116, REACTOR COOLANT FILTER INLET PRESSURE oscillating between 190 psig and 200 psig.

Which ONE of the following completes the statement below?

As a result of the pressure changes above, the actual leakage from the RCS (1) change.

In order to mitigate the consequences, the SRO will direct the performance of SOI-62.01, CVCS-Charging and Letdown, (2)

A. (1) will (2) Section 8.18, Bypassing Reactor Coolant Filter.

B. (1) will (2) Section 8.15, Bypassing 1-PCV-62-81, CVCS LETDOWN HX PRESS CNTL, for Local Control.

C. (1) will NOT (2) Section 8.18, Bypassing Reactor Coolant Filter.

D. (1) will NOT (2) Section 8.15, Bypassing 1-PCV-62-81, CVCS LETDOWN HX PRESS CNTL, for Local Control.

Page 86

03-2013 WATTS BAR NRC SRO LICENSE EXAM 41312013

87. Given the following:

With Unit 1 operating at 100% power an inadvertent actuation of Train A Safety Injection during SSPS testing.

The operating crew has entered ES-i.1, SI Termination.

During performance of the step to RESET SI the crew determines Train A failed to reset.

An operator dispatched to the Aux Instrument Room with Appendix G, Reset of Train A Safety Injection Signal at R Panels, is unable to reset the SI at the SSPS cabinets.

Which ONE of the following completes the statements below?

While performing 1 -E-0, Reactor Trip or Safety Injection, actuation of both Trains of Safety Injection (1) required prior to the transition to ES-i.1.

To terminate the ECCS flow and restore normal charging in accordance with ES-i.i requires (2)

LIJ L?)

A.

was an operator to be dispatched with ES-1.1 Appendix E, Operation of MOVs at Train A Electrical Board B.

was Instrument Maintenance to block SI using lMI-99.040, Auto SI Block C.

was NOT an operator to be dispatched with ES-1.1 Appendix E, Operation of MOV5 at Train A Electrical Board D.

was NOT Instrument Maintenance to block SI using IMl-99.040, Auto SI Block Page 87

03-2013 WATTS BAR NRC SRO LICENSE EXAM 413/2013

88. Given the following:

Unit 1 is operating at 100% power.

Lower Compartment Coolers lB-B, iC-A and iD-B are in service.

CRDM Coolers lA-A and lB-B are in service.

A large ERCW leak occurs in the Auxiliary Building which is isolated by closing the following three valves:

1-ISV-67-523A, LOWER CNTM VENT CLR 1A & 1C ERCW SUP ISOL in the Auxiliary Building.

1-FCV-67-83, LOWER CNTM CLR HDR A ERCW SUP ISOL and i-FCV-67-91, LOWER CNTM CLR HDR C ERCW SUP ISOL in the Annulus.

Following the isolation of the ERCW, the lower containment average air temperature begins to slowly rise and the operating crew begins action to limit the temperature increase.

Which ONE of the following completes the statements below?

TR-3.6.3 Lower Compartment Cooling (LCC) System (1) entry into a Required Action.

Aligning CRDM Cooler (2) to lower containment in accordance with SOI-30.03, Containment HVAC and Pressure Control, will provide additional cooling in lower containment.

Li)

A.

requires iC-A B.

requires iD-B C. doesNOTrequire iC-A D. does NOT require 1 D-B Page 88

03-2013 WATTS BAR NRC SRO LICENSE EXAM 4/3/2013

89. Given the following:

Unit 1 is operating in Mode 2 being returned to service following a refueling outage.

MFPT IA is in service supplying water to the steam generators.

MFPT 1 B 250v trip bus is energized.

Which ONE of the following completes the statements below?

The bases for requiring the MFPT 250v DC trip busses to be energized is toprovidefor (1)

If power is removed from a MFPT 250v trip bus, the entry into the REQUIRED ACTION to restore power within 48 hrs may be delayed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months when (2)

Li)

A.

AFW pump auto start logic placing the 2nd MFPT in service B.

AFW pump auto start logic entering MODE I from MODE 2 C. auto MFW isolation capability placing the 2nd MFPT in service D. auto MFW isolation capability entering MODE 1 from MODE 2 Page 89

03-2013 WATTS BAR NRC SRO LICENSE EXAM 41312013

90. Assuming Unit 1 is operating at 100% power, which ONE of the following identifies how the projection of severe thunderstorms to occur within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months would affect the performance of the activities listed below, if scheduled, in accordance with Tech Spec 3.8.1, AC Sources Operating?

Consider each activity separately Activity 1 Sl-82-13, 24 Hour Load Run

- DG lA-A.

Activity 2

- Place clearance to tag DG 2A-A for a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months outage.

LCO 3.8.1 would prohibit the performance of A. Activity 1 çjy B. Activity 2 pjjy C. both Activities 1 and 2 D. neither Activity I nor 2 Page 90

03-2013 WATTS BAR NRC SRO LICENSE EXAM 4/3/2013

91. Given the following:

Unit 1 is operating at 100% power.

Annunciator 138-E, PANEL M-9 MOTOR TRIPOUT, alarms and it is determined the CRDM Cooler 1 D-B fan tripped.

Fire Safe Shutdown Equipment, OR-14.10.1, is entered.

Before the operating crew can place an additional CRDM fan in service, the elevated CRDM temperatures result in changes in the indicated rod positions on the CERPI monitors.

The unit remains stable at 100% power with no indication of actual rod movement.

Which ONE of the following completes the statements below?

Tech Spec 3.0.3 would be first required to be entered due to inoperable rod position indications (ARPI) when more than one ARPI in a single (1) indicated greater than the allowed deviation in accordance with Tech Spec LCO 3.1.8, Rod Position Indication.

For the Unit to remain in MODE 1 with CRDM Cooler 1 D-B INOPERABLE beyond the OR-I 4.10.1 allowance of 30 days (2) require the performance and documentation of an engineering evaluation.

A.

group does B.

group does NOT C.

bank does D.

bank does NOT Page 91

03-2013 WATTS BAR NRC SRO LICENSE EXAM 4/312013

92. Given the following:

Unit 1 is operating at 100% power.

1000

- Crew enters LCO 3.0.3 due to indications that both Reactor Trip Breakers are inoperable. SSPS has been determined to be operable.

1045

- A valid reactor trip signal is generated and neither of the Reactor Trip Breakers opened or could be opened by the OAC. The operating crew enters the EOP network.

1050

- AUO reports ALL Reactor Trip and Bypass Breakers open, CRDM MG Set 1 B output breaker open but CRDM MG Set 1A output breaker could not be opened.

1135

- The operating crew is ready to transition from ES-0.1, Reactor Trip Response, to the applicable GO procedure.

In accordance with Technical Specifications, which ONE of the following completes the statements below?

The BASES of LCO 3.0.3 allowing up to 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to initiate action to place the unit in MODE 3 is (1)

After the Unit enters Mode 3, the conditions (2)

REFERENCE PROVIDED A. (1) to prepare for an orderly shutdown before initiating a change in unit operation (2) allow the unit remain in Mode 3 indefinitely B. (1) to prepare for an orderly shutdown before initiating a change in unit operation (2) require the unit to proceed to Mode 4 C. (1) permit a limited time period to restore required conditions for safe operation (2) allow the unit remain in Mode 3 indefinitely D. (1) permit a limited time period to restore required conditions for safe operation (2) require the unit to proceed to Mode 4 Page 92

03-2013 WATTS BAR NRC SRO LICENSE EXAM 41312013

93. Given the following:

Unit 1 is operating at 100% power.

HPFP pump control switch alignment: HS-26-1A, IA-A HPFP PMP

- IN A AUTO (STANDBY) HS-26-4A, 1 B-B HPFP PMP

- PULL A-P AUTO HS-26-9A, 2A-A HPFP PMP

- PULL A-P AUTO HS-26-1 IA, 2B-B HPFP PMP

- IN A AUTO (STANDBY) and tagged HPFP pump 2B-B is tagged with a Hold Order.

Fire Ops reports that during performance of 0-FOR-26-7-A, 18 Month Test of High Pressure Fire Protection Pump lA-A, the pump failed acceptance criteria when it did not deliver the required head when the required flow was established.

Which ONE of the following completes the statements below?

The failure of HPFP pump lA-A results in an (1)

The HPFP system conditions (2) a change in the HPFP pump handswitch alignment in accordance with SOI-26.01, High Pressure Fire Protection System.

LIJ A.

entry into OR-14.2 required actions require B.

entry into OR-14.2 required actions do NOT require C.

OR-i 4.2 Tracking ONLY entry require D.

OR-I 4.2 Tracking ONLY entry do NOT require Page 93

03-2013 WATTS BAR NRC SRO LICENSE EXAM 4/312013

94. Given the following:

Unit 1 is operating at 100% power when conditions require a reactor trip and safety injection to be initiated.

The Shift Manager/SED declares a GENERAL EMERGENCY (GE) based on Fission Product Barrier Matrix EAL status.

Which ONE of the following completes the statements below in accordance with EPIP-5, General Emergency?

When making the notification of the GE to the State of Tennessee, the Shift Manager/S ED will identify (1)

If a manual call out of the individuals on the current Weekly Duty list is required due to failure of both the Preferred and Alternate methods of activating the ERO, the Fitness for Duty question (2) required to be verbally asked.

A.

aN EALs that are currently met is B. pjjy the EALs for which the declaration is being made is C.

aN EALs that are currently met is NOT D. 2 pjy the EALs for which the declaration is being made is NOT Page 94

03-2013 WATTS BAR NRC SRO LICENSE EXAM 4/312013

95. Given the following:

Unit 1 is cooling down for a refueling outage.

The Shift Manager has temporarily relieved the Unit Supervisor who has been called for a random drug screen.

The only individuals holding an active NRC license that are currently in the Main Control Room (MCR) are:

- the OAC (RO license),

- the CR0 (RO license), and

- the Shift Manager (SRO license).

Which ONE of the following completes the statements below?

Consider each of the conditions to occur separately.

If 1-E-O, Reactor Trip or Safety Injection, entry was required due to a Safety Injection occurring, the Shift Manager would (1) the procedure reader.

In accordance with NPG-SPP-1O.O, Plant Operations, the earliest the Shift Manager could be relieved of the MCR Command and Control function by one of the ROs is after the unit enters (2) ci A.

become MODE 4 B.

become MODE 5 C. assign one of the ROs to be MODE 4 D. assign one of the RO5 to be MODE 5 Page 95

03-2013 WATTS BAR NRC SRO LICENSE EXAM 4/3/2013

96. Given the following:

Unit 1 is operating at 100% power.

A system engineer and MIG technician have come to the control room with a work order to install a temporary alteration (TA) on the Loose Parts Monitoring System (LPMS).

The TA installs additional recorders and analyzers in order to collect data to troubleshoot recurring spurious LPMS alarms.

The additional equipment will be powered from available 120V AC wall receptacles.

LPMS will remain operable while the TA is installed.

The TA will remain installed, with the equipment continuously connected, for 120 days.

Which ONE of the following completes the statements below in accordance with NPG-SPP-09.5, Temporary Alterations?

A 50.59 screening review (1) required to be performed for the TA.

A Temporary Alteration Control Form (TACF)

(2) required to be implemented for the TA.

Li)

A.

is is B.

is is NOT C.

is NOT is NOT D.

is NOT is Page 96

03-2013 WATTS BAR NRC SRO LICENSE EXAM 413/2013

97. Which ONE of the following completes the statements below in accordance with Tech Specs?

The maximum extension time allowed for the completion of a Surveillance Requirement (SR) with a 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months FREQUENCY is (1)

If the 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR was later discovered to have NOT been completed within the maximum allowable extension time, the requirement for declaring the equipment inoperable can be delayed for a maximum of (2) hours.

Li)

A.

3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months 12 hours B.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 12 hours C.

3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months 24 hours D.

24hours 24hours Page 97

03-2013 WATTS BAR NRC SRO LICENSE EXAM 4/3/2013

98. Given the following:

Unit 1 is at 100% power.

The Monitor Tank is to be released.

Which ONE of the following identifies...

(1) how 0-RM-90-122, Liquid Radwaste Effluent Line, being inoperable would affect the planned release, and (2) the permit requirements to restart the release if it isolated due to low Cooling Tower Blowdown (CTBD) flow?

(1)

(2) 0-RM-90-122 inoperable Low CTBD flow A. 2 independent samples Release can not be restarted until a required prior to the release.

new release permit generated after it is isolated due to low CTBD flow.

B. 2 independent samples Release can be continued if required prior to the release.

restarted within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months with existing release permit.

C. Samples will be required at Release can not be restarted until a least every 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months during the new release permit generated after

release, it is isolated due to low CTBD flow.

D. Samples will be required at Release can be continued if least every 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months during the restarted within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months with release.

existing release permit.

Page 98

03-2013 WATTS BAR NRC SRO LICENSE EXAM 41312013

99. Given the following:

A fire is occurring at the Watts Bar Hydro Plant.

Fire Operations is currently staffed with 2 qualified fire brigade leaders and 6 fire brigade members on site.

The Shift Manager directs 1 of the fire brigade leaders and 2 fire brigade members to report to the Watts Bar Hydro Plant to provide assistance in extinguishing the fire.

Which ONE of the following completes the statement below in accordance with the Part II

- Fire Protection Plan?

The onsite Fire Brigade composition A.

is reduced but remains at or above the minimum required staffing B.

is unchanged due to the WB Hydro Station being on the Watts Bar site C.

is less than minimum and requires immediate action to restore the minimum staffing D. is less than minimum but no action is required unless neither of the fire brigade members return within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Page 99

03-2013 WATTS BAR NRC SRO LICENSE EXAM 41312013 100. Given the following:

A General Emergency has been declared on Unit 1.

All REP emergency centers are operational.

Which ONE of the following completes the statement below?

In accordance with the Radiological Emergency Plan, the Site Emergency Director can be relieved of the responsibility for (1) by the (2)

Li)

A. Protective Action Recommendations CECC Director B.

Emergency Dose Approvals RP Manager C.

Emergency Dose Approvals CECC Director D. Protective Action Recommendations RP Manager Page 100

03-2013 WATTS BAR NRC SRO LICENSE EXAM 4/3/2013 ID 1

007 EA2.06 176 A

2 009 EA2.38 177 A

3 027AA2.04278 B

4 040 AG2.4.41 179 C

5 057 AG2.4.11 80 C

6 062 AG2.4.45 181 B

7 059 AG2.4.21 82 C

8 067 AA2.04 83 D

9 W/E07 EG2.4.18 484 C

10 W/EI5EA2.285 B

11 004A2.23 186 C

12 006A2.13287 A

13 022A2.0488 D

14 059 G2.2.22 89 A

15 064 G2.2.25 290 A

16 001 A2.01 191 A

17 029 G2.2.40 292 A

18 086 A2.02 93 D

19 G2.1.17 194 D

20 G2.1.395 D

21 G2.2.11 196 A

22 G2.2.1297 C

23 G 2.3.6 198 B

24 G 2.4.26 99 A

25 G2440 100 A

Page 1

03-2013 WATTS BAR NRC SRO LJCENSE EXAM 4/312013 REFERENCE PACKAGE 1.

AOl-i 1, Loss of Condenser Vacuum, Revision 0029, Appendix A (1 page) 2.

i-AOl-30.2 APP B, Fire Safe Shutdown Elevation Diagrams (1 page) 3.

Tech Spec LCO 3.3.1, Reactor Trip System (RTS) Instrumentation System (16 pages)

WBN Loss of Condenser Vacuum AO[1 I Unft I Rev. 0029 0

0

-J 0

-J C-)

Ui Ui 0

C-)

=

Append[x A (Page 1 off)

Condenser Vacuum [CS Graph LU C

NOTE: This Appendix is an lOS ControHed Graph and should NOT be modified without Corporate Computer Engineering acknowledgement.

LU 0

=

c1 rq LC)

(H-L!) flSSdd NGNOD Page 9 of 9

WBN Fire Safe Shutdown Elevation 1-AOl-30.2 APP B Unit I Diagrams Rev. 0000 Page 10 of 16 692.0-All Chrging Pmp 10 1-AOI-30.2 0.58 692.0-A12 SIS Pmp lB-B l-A0l-30.2 0.58 692.0-Al3 SIS Pmp lA-A l-AOl-30.2 0.58 692.0-A14 CDCT Rm l-AOl-30.2 0.60 692.0-A27 Concentrate Filter l-AOl-30.2 C.60 692.0-A29 BA Evap Pkg Rm B l-AOl-30.2 0.60 692.0-A30 BA Evap Pkg Rm A l-AOl-30.2 0.60 692.0-A3l Hyperfiltration Eq Rm A 1-AOl-30.2 0.60 7.0 AB EL 692.0 ELEVATION DIAGRAM Auxiliary Building El 692.0 Diagram ROOM ROOM NAME PROCEDURE 692.0-Al A Corridor 1 -AOl-30.2 0.53 692.0-Al B Corridor 1 -AOl-30.2 0.54 692.0-A1C Corridor 1-AOl-30.2 0.55 692.0-A2 Valve Gallery l-AOI-30.2 0.60 692.0-A3 Gas Decay Tk Rm l-AOI-302 0.60 692.0-A4 Chemical DrTk Rm l-AOl-30.2 0.60 692.0-AS Gas Decay Tk Rm 1-AOl-30.2 0.60 692.0-A6 Aux FW Pmp lA-S l-AOl-30.2 0.60 692.0-A7 Pipe Gallery 1-AOl-30.2 0.56 692.0-A8 Pipe Gallery & Oh l-AOl-30.2 0.59 ROOM ROOM NAME PROCEDURE 692.0-AlS SRST Rm l-AOl-30.2 0.60 692.0-A16 Valve Gallery 1-AOI-30.2 0.60 692.0-Al7 RPV Stud Maintenance Rm 1-AOl-30.2 0.60 692.0-Al8 CRT Storage Rm 1-AOl-30.2 0.58 692.0-Al9 SIS Pmp 2A-A l-AOl-30.2 0.60 692.0-A20 SIS Pmp 2B-B l-AOl-30.2 0.60 692.0-A2l Chrging Pmp 20 l-AOl-30.2 0.60 692.0-A22 Chrging Pmp 2B-B l-AOl-30.2 0.60 692.0-A23 Chrging Pmp 2A-A l-AOl-30.2 0.60 692.0-A24 Pipe Gallery & Oh 1-AOl-30.2 0.60 692.0-A9 Chrging Pmp lA-A 692.0-AlO Chrging Pmp lB-B 1-AOl-30.2 0.60 l-AOl-30.2 0.57 692.0-A25 Pipe Gallery 692.0-A26 Aux FW Pmp 2A-S 1-AOl-30.2 0.60 l-AOl-30.2 0.60

RTS Instrumentation 3.3.1 3.3 INSTRUMENTATION 3.3.1 Reactor Trip System (RTS) Instrumentation LCO 3.3.1 The RTS instrumentation for each Function in Table 3.3.1-1 shall be OPERABLE.

APPLICABILITY:

According to Table 3.3.1-1.

ACTIONS NOTE-Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more Functions with A.1 Enter the Condition referenced Immediately one or more required channels in Table 3.3.1-1 for the inoperable, channel(s).

B.

One Manual Reactor Trip B.1 Restore channel to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months channel inoperable.

OPERABLE status.

OR B.2.1 Be in MODE 3.

54 hours6.25e-4 days 0.015 hours 8.928571e-5 weeks 2.0547e-5 months AND B.2.2Open reactor trip breakers 55 hours6.365741e-4 days 0.0153 hours 9.093915e-5 weeks 2.09275e-5 months (RTBs).

(continued)

Watts Bar-Unit 1 3.3-1

ACTIONS (continued)

RTS Instrumentation 3.3.1 (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C.

One channel or train C.1 Restore channel or train to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months inoperable.

OPERABLE status.

OR C.2 Open RTBs.

49 hours5.671296e-4 days 0.0136 hours 8.101852e-5 weeks 1.86445e-5 months D.

One Power Range Neutron NOTE

FluxHigh channel The inoperable channel may be inoperable, bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing and setpoint adjustment of other channels.

D.1.1 Place channel in trip.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months AND D.1.2 Reduce THERMAL POWER 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months to 75% RTP.

OR D.2.i Place channel in 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months trip.

AND NOTE Only required to be performed when the Power Range Neutron Flux input to QPTR is inoperable.

D.2.2 Perform SR 3.2.4.2.

Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OR D.3 Be in MODE 3.

78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months Watts Bar-Unit I 3.3-2 Amendment 68

ACTIONS (continued)

RTS Instrumentation 3.3:1 (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F.

One channel inoperable.

NOTE

The inoperable channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing of other channels.

E.1 Place channel in trip.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR E.2 Be in MODE 3.

78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months F.

THERMAL POWER> P-6 F.1 Reduce THERMAL POWER 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and < P-b, one Intermediate to < P-6.

Range Neutron Flux channel inoperable.

PR F.2 Increase THERMAL 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months POWER to> P-b.

G.

THERMAL POWER> P-6 and G.1 Suspend operations Immediately

< P-iC, two Intermediate involving positive reactivity Range Neutron Flux channels additions.

inoperable.

AND G.2 Reduce THERMAL POWER 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to < P-6.

H.

THERMAL POWER < P-6, Rb Restore channel(s) to Prior to increasing one or two Intermediate OPERABLE status.

THERMAL POWER Range Neutron Flux channels to > P-6 inoperable.

Watts Bar-Unit 1 3.3-3 Amendment 68

RTS Instrumentation 3.3 1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME One Source Range Neutron 1.1 Suspend operations involving Immediately Flux channel inoperable, positive reactivity additions.

J.

Two Source Range Neutron J.1 Open RTBs.

Immediately Flux channels inoperable.

K.

One Source Range Neutron K.1 Restore channel to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months Flux channel inoperable.

OPERABLE status.

OR K.2 Open RTB5.

49 hours5.671296e-4 days 0.0136 hours 8.101852e-5 weeks 1.86445e-5 months L.

Required Source Range L.1 Suspend operations involving Immediately Neutron Flux channel positive reactivity additions.

inoperable.

AND L.2 Close unborated water source 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months isolation valves.

AND L.3 Perform SR 3.1.1.1.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter (continued)

Watts BarUnit 1 3.3-4

ACTIONS (continued)

RTS Instrumentation 3.3.1 (continued)

CONDITION REQUIRED ACTION COMPLETION TIME M.

One channel NOTE inoperable.

The inoperable channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing of other channels.

M.1 Place channel in trip.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR M.2 Reduce THERMAL POWER to 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months

< P-7.

N.

One Reactor Coolant Flow--

NOTE Low channel inoperable.

One channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing.

N.1 Place channel in trip.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR N.2 Reduce THERMAL POWER to 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months

< P-7.

Watts Bar-Unit 1 3.3-5 Amendment 68

ACTIONS (continued)

RTS Instrumentation 3.3.1 (continued)

CONDITION REQUIRED ACTION COMPLETION TIME 0.

One Low Fluid Oil Pressure

NOTE Turbine Trip channel The inoperable channel may be inoperable, bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing of other channels.

0.1 Place channel in trip.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR 0.2 Reduce THERMAL POWER to 76 hours8.796296e-4 days 0.0211 hours 1.256614e-4 weeks 2.8918e-5 months

< P-9.

P.

One train inoperable.

NOTE--------

One train may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing provided the other train is OPERABLE.

P.1 Restore train to OPERABLE 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months status.

OR P.2 Be in MODE 3.

30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months Watts Bar-Unit 1 3.3-6 Amendment 68

ACTIONS (continued)

RTS Instrumentation 3.3.1 (continued)

CONDITION REQUIRED ACTION COMPLETION TIME Q.

One RTB train inoperable.

NOTE One train may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing, provided the other train is OPERABLE.

Q.1 Restore train to OPERABLE 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months status.

OR Q.2 Be in MODE 3.

30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months R.

One channel R.1 Verify interlock is 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable, in required state for existing unit conditions.

OR R.2 Be in MODE 3.

7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months S.

One channel S.1 Verify interlock is 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable, in required state for existing unit conditions.

OR S.2 Be in MODE 2.

7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months Watts Bar-Unit 1 3.3-7 Amendment 68

RTS Instrumentation 3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME T.

One trip mechanism T.1 Restore inoperable trip 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months inoperable for one mechanism to OPERABLE RTB.

status.

OR T.2.1 Be in MODE 3.

54 hours6.25e-4 days 0.015 hours 8.928571e-5 weeks 2.0547e-5 months AND T.2.2 Open RTB.

55 hours6.365741e-4 days 0.0153 hours 9.093915e-5 weeks 2.09275e-5 months U.

One Steam Generator Water

-NOTE Level Low-Low channel One channel may be bypassed inoperable, for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing.

U.1.1 Place channel in trip.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months AND U.1.2 For the affected protection set, 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months set the Trip Time Delay (T

5) to match the Trip Time Delay (T M).

OR U.2 Be in MODE 3.

78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months (continued)

Watts Bar-Unit 1 3.3-8 Amendment 68

ACTIONS (continued)

RTS Instrumentation 3.3.1 (continued)

CONDITION REQUIRED ACTION COMPLETION TIME V.

One Vessel AT channel

NOTE

inoperable.

One channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing.

V.1 Set the Trip Time Delay 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months threshold power level for (T 5) and (TM) to 0% power.

OR V.2 Be in MODE 3.

78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months W.

One channel NOTE inoperable.

One channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing.

W.1 Place channel in trip.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR W.2 Be in MODE 3.

78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months X.

One channel NOTE inoperable.

One channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing.

X.1 Place channel in trip.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OR X.2 Reduce THERMAL POWER to 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months

< P-7.

Watts Bar-Unit 1 3.3-9 Amendment 68

RTS Instrumentation ACTIONS (continued) 3.3.1 CONDITION REQUIRED ACTION COMPLETION TIME Y.

One, two or three Turbine Y.1 Place channel(s) in trip.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Stop Valve Closure channels inoperable.

OR Y.2 Reduce THERMAL POWER to 76 hours8.796296e-4 days 0.0211 hours 1.256614e-4 weeks 2.8918e-5 months

< P-9.

Z.

Two RTS Trains inoperable Z.1 Enter LCO 3.0.3.

Immediately Watts Bar-Unit 1 3.3-10 Amendment 68

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 1 of 9)

Reactor Trip System Instrumentation APPLICABLE MODES NOMINAL OR OTHER REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION SPECIFIED CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT CONDITIONS ManualReactor 1,2 2

B Trip 3

(a) 4 (a) 5(a) 2 C

2.

Power Range Neutron Flux a.

High 1,2 4

D b.

Low 1

(b) 2 4

E 3.

Power Range Neutron Flux Rate a.

High Positive 1

2 4

E Rate b.

High Negative Rate

- Deleted 4.

Intermediate Range 1

(b) 2 2

F, G Neutron Flux 2

2 H

(continued)

(a)

With Reactor Trip Breakers (RTB5) closed and Rod Control System capable of rod withdrawal.

(b)

Below the P-1O (Power Range Neutron Flux) interlocks.

(c)

Above the P-6 (Intermediate Range Neutron Flux) interlocks.

(d)

Below the P-6 (Intermediate Range Neutron Flux) interlocks.

Watts Bar-Unit 1 3.3-15 Amendment 18

RTS Instrumentation 3.3.1 Tabe 3.3.1-1 (page 2 of 9)

Reactor Trip System Instrumentation APPLICABLE MODES NOMINAL OR OTHER REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION SPECIFIED CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT CONDITIONS 5.

Source Range 2

(d) 2 I, J Neutron Flux 3(a) 4(a), 5(a) 2 J, K 3(e) 4 (e) 5(e) 1 L

6.

Overtemperature AT 1, 2 4

W 7.

Overpower AT 1

2 4

W 0U.

I0.UIItCr Pressure a.

Low 1

4 X

b.

High 1,2 4

W (continued)

(a)

With RTBs closed and Rod Control System capable of rod withdrawal.

(d)

Below the P-6 (Intermediate Range Neutron Flux) interlocks.

(e)

With the RTBs open.

In this condition, source range Function does not provide reactor trip but does provide indication.

(f)

Above the P-7 (Low Power Reactor Trips Block) interlock.

Watts Bar-Unit 1 3.3-16 Amendment No. 52

RTS instrumentation 3.3.1 Table 3.3.1-1 (page 3 of 9)

Reactor Trip System Instrumentation APPLICABLE MODES NOMINAL OR OTHER REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION SPECIFIED CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT CONDITIONS 9.

Pressurizer Water 1

3 X

Level-High 10 Reactor Coolant 3 per N

Flow-Low loop 11 Undervoltage l

1 per bus M

RCPs 12 Underfrequency 1 per bus M

RCPs (continued)

(f)

Above the P-7 (Low Power Reactor Trips Block) interlock.

Watts Bar-Unit 1 3.3-17 Amendment 47, 68

Table 3.3.1-1 (page 4 of 9)

Reactor Trip System Instrumentation RTS Instrumentation 33.1 APPLICABLE MODES NOMINAL OR OTHER REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION SPECIFIED CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT CONDITIONS 13.

SG Water Level 1, 2 3/SG U

Low-low Coincident with:

a)

VesseLT 1,2 3

V Equivalent to power 50% RTP With a time delay (Ts) if one steam generator is affected or A time delay (Tm) if two or more steam generators are affected OR b)

VesseLT 1,2 3

V Equivalent to power> 50%

RTP with no time delay (Ts and Tm =

0) 14.

Turbine Trip a.

Low Fluid il>

3 0

Oil pressure b.

Turbine Stop 4

Y Valve Closure (I)

Above the P-9 (Power Range Neutron Flux) interloCk.

(continued)

Watts Bar-Unit 1 3.3-18 Amendment 7

Table 3.3.1-1 (page 5 of 9)

Reactor Trip System Instrumentation RTS Instrumentation 3.3.1 APPLICABLE MODES NOMINAL OR OTHER REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION SPECIFIED CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT CONDITIONS 15.

Safety Injection (SI) 1, 2 2 trains P

SR 3.3.1.13 NA NA Input from Engineered Safety Feature Actuation System (ESFAS) i-,,

(d)

Below the P-6 (Intermediate Range Neutron Flux) interlocks.

(continued)

Watts Bar-Unit 1 3.3-19

Table 3.31-1 (page 6 of 9)

Reactor Trip System Instrumentation RTS Instrumentation 3.3.1 APPLICABLE MODES NOMINAL OR OTHER REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION SPECIFIED CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT CONDITIONS 17.

ReactorTip 1,2 2trains Q

Breakers (I) 3(a) 4 (a) 5(a) 2 trains C

18.

Reactor Trip 1, 2 1 each T

Breaker per RTB Undervoltage and Shunt Trip 3(a) 4 (a) 5 (a) 1 each C

Mechanisms per RTB 19.

Automatic Trip 1, 2 2 trains P

Logic 3(a) 4 (a) 5 (a) 2 trains C

(a)

With RTBs closed and Rod Control System capable of rod withdrawal.

(j)

Including any reactor trip bypass breakers that are racked in and closed for bypassing an RTB.

Watts Bar-Unit 1 3.3-20

ML13106A201

Text

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