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2013 Clinton Power Station Initial License Examination As-Administered SRO Written Examination
	ML13276A135
Person / Time
Site:	Clinton
Issue date:	08/27/2013
From:	David Reeser; Operations Branch III
To:	Jennings T; Exelon Generation Co
	David Reeser
Shared Package
ML11354A434	List: ML13276A133; ML13276A135; ML13291A027; ML13291A029; ML13291A031; ML13291A033;
References
	Download: ML13276A135 (118)
	v • d • e

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version 1 ID: 896367 Points: 1.00 The unit was operating in Mode 2 with NO LCOs in effect when multiple annunciators were received on 1H13-P877-5060. 1H13-P877 indications are as follows:

The following is an excerpt from ITS 3.8.4 DC Sources - Operating:

3.8.4 DC Sources - Operating LCO 3.8.4 The Division 1, Division 2, Division 3, and Division 4 DC electrical power subsystems shall be OPERABLE.

Applicability: Modes 1, 2, and 3.

Actions Condition Required Action Completion Time A. One battery charger on A.1 Restore battery terminal 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Division 1 or 2 inoperable. voltage to greater than or equal to the minimum established float voltage.

AND A.2 Verify battery float current 2 Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months amps.

AND A.3 Restore battery charger to 7 days OPERABLE status B. One battery on Division 1 or 2 B.1 Restore battery to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months CPS OPS ILT EXAM Page: 1 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version inoperable. OPERABLE status.

For the conditions provided in the stem:

ITS LCO Actions(s) associated with Condition(s) _____(1)_____ must be entered.

Entry into Mode 1 _____(2)_____ permitted by Technical Specifications.

A. (1) A ONLY (2) is B. (1) A AND B (2) is C. (1) A ONLY (2) is NOT D. (1) A AND B (2) is NOT Answer: D Answer Explanation D is correct - The meter indications (DC amps and volts) provided in the stem indicate that DC MCC 1A is deenergized (Battery Charger and Battery outputs are deenergized). If either source was energized (battery or battery charger), the DC voltage and amperage meters would be indicating values > 0.

With DC MCC 1A deenergized, required actions are to declare Division 1 DC electrical power subsystem inoperable per ITS 3.8.4 and enter Required Actions A (A.1, A.2, and A.3) and B.1, with actions to be completed within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . The definition of 125VDC electrical power system is that it consists of 4 independent subsystems, each containing a battery, associated battery charger, and all associated control equipment and interconnecting cabling. This information is described in ITS B3.8.4.

Per ITS 3.0.4, when an LCO is not met, entry into a MODE or other specified condition in the Applicability shall only be made:

When the associated ACTIONS to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time;

After performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability of entering the MODE or other specified condition in the Applicability, and establishment of risk management actions, if appropriate; exceptions to this Specification are stated in the individual Specifications, or

When an allowance is stated in the individual value, parameter, or other Specification.

This specification shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.

Since Conditions A and B both have 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months completion time limits and the LCO does not specify that 3.0.4 does NOT apply, then entering Mode 1 is NOT permitted by Technical Specifications.

CPS OPS ILT EXAM Page: 2 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version A is incorrect but plausible if the examinee incorrectly diagnoses the indications in the stem as a trip of the Division 1 Battery Charger only and then determines that ONLY ITS 3.8.4 Condition A must be entered based on that diagnoses. Part B of the answer is also incorrect but plausible if the examinee incorrectly recalls the requirements specified in ITS 3.0.4 for changing Modes with an LCO NOT met.

B is incorrect but plausible if the examinee incorrectly recalls the requirements specified in ITS 3.0.4 for changing Modes with an LCO NOT met.

C is incorrect but plausible if the examinee incorrectly diagnoses the indications in the stem as a trip of the Division 1 Battery Charger only and then determines that ONLY ITS 3.8.4 Condition A must be entered based on that diagnoses.

KA Justification: This question meets the KA because the examinee must be able to determine the extent of the loss of DC using the indications provided in the stem.

SRO Justification - linked to SRO only Task 140109.23 (Apply the administrative requirements for execution of Technical Specifications and Off-Site Dose Calculation Manual Requirements). Also linked to 10CFR55.43(b)(2), Facility operating limitations in the Technical Specifications and their bases.

CPS OPS ILT EXAM Page: 3 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Question 1 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 1 Difficulty: 0.00 System ID: 896367 User-Defined ID: CL-ILT-812650 Cross Reference Number:

The unit was operating in Mode 2 with NO LCOs in effect when Topic:

multiple annunciators were received o Num Field 1:

Num Field 2:

Text Field:

CPS OPS ILT EXAM Page: 4 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Comments: General Data Technical Reference with

ITS 3.8.4 Revision Number:

ITS 3.0.6

5060.01 (1E) Rev. 27a

5060.02 (2E) Rev. 26

OP-CL-108-104-1001 Rev. 7 Justification for Non SRO CFR NA Link:

Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, New Bank, Modified)

Low KA Justification (if NA required):

Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)

ILT Supplied Ref (If appropriate): None (i.e. ABN-##)

Excluded

Reference:

(i.e. None Ensure ON-## not provided)

LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)

General Information Question Level (RO/SRO) SRO Station Clinton Cognitive Level Higher (3SPR)

KA Data KA Number / System Name: 295004 Partial or Complete Loss of D.C. Power Category / KA Statement: AA2. Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER : AA2.02 Extent of partial or complete loss of D.C. power (CFR: 41.10 / 43.5 /

45.13)

RO Value: 3.5 SRO Value: 3.9 Tier: 1 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.10 10CFR55-43 (SRO) Data: 43.5 CPS OPS ILT EXAM Page: 5 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Question 1 Table-Item Links

General Question Data - Site Ownership Clinton Associated objective(s):

Question 1 / 76 263000.12 Given BATTERY & DC DISTRIBUTION System operability status OR key parameter indications, plant conditions, and a copy of Tech Specs, DETERMINE if Tech Spec Limiting Condition for Operations have been met, and required actions if any.

.1 AC Electrical Distribution

.2 Switch Gear Heat Removal CPS OPS ILT EXAM Page: 6 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version 2 ID: 896368 Points: 1.00 The reactor was at rated power when an event occurred.

Current plant conditions are as follows:

Parameter Value Trend Reactor Power 4% Cycling Suppression Pool Temperature 139°F Rising RPV Pressure 930 psig Cycling on SRVs Suppression Pool Level 16'5" Lowering Containment Temperature 125°F Rising Containment Pressure 1.1 psig Rising RPV Level Unknown NA All appropriate EOPs have been entered for the current conditions.

CPS OPS ILT EXAM Page: 7 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Given these conditions, which of the following actions is required?

A. Perform blowdown ONLY.

B. Initiate containment spray AND lower RPV pressure.

C. Initiate containment spray AND perform a blowdown.

D. Lower and maintain Reactor Pressure at 600 - 800 psig.

Answer: A Answer Explanation A is correct - per EOP-6 Primary Containment Control, if pool temperature and RPV pressure cannot be held below Fig P, Heat Capacity Limit, a blowdown must be performed per EOP-3 Emergency RPV Depressurization.

B & C are incorrect but plausible if the examinee misreads Figure O Containment Spray Initiation Limit graph.

D is incorrect but plausible - the Pool Temperature leg of EOP-6 directs lowering RPV pressure to stay below the HCTL unless RPV Flooding has been entered.

KA Justification: This question meets the KA because the examinee must be able to interpret the conditions listed in the stem and then determine required actions.

SRO Justification: - The question is SRO ONLY level because the evaluation of plant parameters (pool level and temperature) require the use of details on EOP-6. The interpretation of the data and applying it to the limits of these details is an SRO only function at Clinton Power Station. Also linked to SRO only task 440201.12 (Respond to a low Suppression Pool level per EOP_6). Also related to 10CFR55.43(b)(5) for assessment of facility conditions.

CPS OPS ILT EXAM Page: 8 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Question 2 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 2 Difficulty: 0.00 System ID: 896368 User-Defined ID: CL-ILT-812651A Cross Reference Number:

The reactor was at rated power when an event occurred.

Topic:

Current plant conditions are as follows:

Num Field 1:

Num Field 2:

Text Field:

CPS OPS ILT EXAM Page: 9 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Comments: General Data Technical Reference with 4402.01 Rev. 29 Revision Number:

Justification for Non SRO CFR NA Link:

Question History: (i.e. LGS OC 2011 NRC EXAM NRC-05, OYS CERT-04)

Question Source: (i.e. New, Modified Bank, Modified)

Low KA Justification (if NA required):

Revision History: Revision Converted OC 2011 NRC History: (i.e. Modified EXAM Q82 for application distractor b to make at CPS.

plausible based on OTPS review)

ILT Supplied Ref (If appropriate): None (i.e. ABN-##)

Excluded

Reference:

(i.e. 4402.01 (EOP-6) - Pool Ensure ON-## not provided) Temperature and Drywell/Containment Pressure Legs LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)

General Information Question Level (RO/SRO) SRO Station Clinton Cognitive Level Higher (3SPR)

KA Data KA Number / System Name: 295030 Low Suppression Pool Water Level Category / KA Statement: EA2. Ability to determine and/or interpret the following as they apply to LOW SUPPRESSION POOL WATER LEVEL :

EA2.02 Suppression pool temperature (CFR: 41.10 / 43.5 / 45.13)

RO Value: 3.9 SRO Value: 3.9 Tier: 1 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.10 10CFR55-43 (SRO) Data: 43.5 CPS OPS ILT EXAM Page: 10 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Question 2 Table-Item Links NRC EXAM - NUREG 1021 Question Cognitive Level Comprehension or Analysis - (H)igher Cognitive Level

General Question Data - Site Ownership Clinton

General Question Data - Ops Program Senior Reactor Operator

General Question Data - Initial/Continuing Initial Training Associated objective(s):

Question 2 / 77 LP87558.01.17 Given a condition resulting in approaching the Heat Capacity Limit, Fig. P, and a diagram of EOP-6, determine when it would be appropriate to Blowdown.

CPS OPS ILT EXAM Page: 11 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version 3 ID: 896369 Points: 1.00 The plant is in Mode 5 with core alterations in progress. Spent fuel is being temporarily stored in the upper containment pool racks.

At 0100, the following annunciators were received:

5067-3L Hi-Hi Level Drywell Sump Equip/Flr Drn

5067-4L High Flow Drywell Equip Drn

5068-7A Refuel Bellows Leakage The Refueling SRO reports that Polar Crane AND Refueling Bridge Area Radiation Monitors (ARMs) are in HIGH Alarm.

Which listed action is required to be performed?

A. Establish secondary containment.

B. Secure the operating Shutdown Cooling loop.

C. Enter and execute CPS 4001.02 Automatic Isolation.

D. Initiate makeup to FC system by opening 1SX016A/B, SX Emergency Makeup To Spent Fuel Pool Valves.

Answer: A Answer Explanation A is correct:

Failure of the refueling bellows will result in draining the upper containment pools to the Drywell Equipment Drain system and reducing the level of water/shielding above the fuel stored in the upper containment pool racks and the RPV.

Receipt of annunciator 5068-7A is a symptom of reactor cavity leakage during refueling requiring entry into CPS 4011.01 Reactor Cavity Leakage During Refueling.

If level approaches the top of any irradiated fuel, level cannot be restored, or high radiation levels exist, CPS 4011.01 Reactor Cavity Leakage During Refueling, subsequent action step 4.4 directs the following actions:

Enter EOP-1 RPV Control (use ECCS to restore level above the fuel)

Prohibit access to Cnmt Refueling Floor

Establish Secondary CNMT integrity CPS 4011.01 also directs refilling the reactor cavity to the normal refueling level using the following systems:

Preferred systems for level restoration should be those systems which inject from clean water sources. These include:

Condensate/Feedwater

CRD

Fuel Pool Cooling CPS OPS ILT EXAM Page: 12 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version

Cycled Condensate

Makeup Condensate

Secondary systems for level restoration include:

RHR through Shutdown Cooling

HPCS

LPCS

LPCI

ECCS Water Leg Pumps

SLC Test Tank B is incorrect but plausible - 4011.01 step 4.2 directs securing the operating shutdown cooling RHR pump(s) if the leakage source has not been identified. The annunciators provided in the stem identify the leakage source making this step NA.

C is incorrect but plausible - the examinee may select this choice if they incorrectly believe that the conditions in the stem are symptoms of an auto isolation condition (high rad or lowering pool level).

D is incorrect but plausible - performing emergency makeup to the spent fuel pool is directed by CPS 4011.02 Spent Fuel Pool Abnormal Water Level Decrease to restore water level in the spent fuel pool.

Leakage from the refueling bellows will not affect spent fuel pool water level and makeup methods to the upper containment pools are prescribed in CPS 4011.01.

KA Justification: This question meets the KA because the examinee must be able to interpret the conditions listed in the stem, determine that a fuel handling accident has occurred based on the High Rad alarms, and then determine required actions.

SRO Justification - linked to 10CFR55.43(b)(5) Assessment of facility conditions and selection of appropriate procedures during emergency situations and 10CFR55.43(b)(7) for SRO Fuel handling facilities and procedures. Also linked to SRO only task 999999.12 Direct refueling activities as refueling supervisor.

CPS OPS ILT EXAM Page: 13 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Question 3 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 2 Difficulty: 0.00 System ID: 896369 User-Defined ID: CL-ILT-812652A Cross Reference Number:

The plant is in Mode 5 with core alterations in progress. Spent Topic:

fuel is being temporarily stored Num Field 1:

Num Field 2:

Text Field:

CPS OPS ILT EXAM Page: 14 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Comments: General Data Technical Reference with

CPS 5067.03 (3L) Rev.

Revision Number: 32b

CPS 5067.04 (4L) Rev.

31

CPS 5068.07 (7A) Rev.

24

CPS 4011.01 Rev. 4f

CPS 4011.02 Rev. 6b Justification for Non SRO CFR NA Link:

Question History: (i.e. LGS River Bend 2010 NRC NRC-05, OYS CERT-04) Exam (Question 79)

Question Source: (i.e. New, Bank Bank, Modified)

Low KA Justification (if NA required):

Revision History: Revision Converted River Bend 2010 History: (i.e. Modified NRC EXAM Q79 for distractor b to make application at CPS.

plausible based on OTPS review)

ILT Supplied Ref (If appropriate): None (i.e. ABN-##)

Excluded

Reference:

(i.e. None Ensure ON-## not provided)

LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)

General Information Question Level (RO/SRO) SRO Station Clinton Cognitive Level Higher (3SPK)

KA Data KA Number / System Name: 295023 Refueling Accidents Category / KA Statement: AA2. Ability to determine and/or interpret the following as they apply to REFUELING ACCIDENTS: AA2.04 Occurrence of fuel handling accident (CFR: 41.10 / 43.5 / 45.13)

RO Value: 3.4 SRO Value: 4.1 Tier: 1 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.10 10CFR55-43 (SRO) Data: 43.5 CPS OPS ILT EXAM Page: 15 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Question 3 Table-Item Links NRC EXAM - NUREG 1021 Question Cognitive Level Comprehension or Analysis - (H)igher Cognitive Level

General Question Data - Site Ownership Clinton

General Question Data - Ops Program Senior Reactor Operator

General Question Data - Initial/Continuing Initial Training Associated objective(s):

Question 3 / 78 PB401101.01.05 Describe the required actions if the source of leakage cannot be quickly identified during a reactor cavity leak CPS OPS ILT EXAM Page: 16 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version 4 ID: 896370 Points: 1.00 The plant has been operating at rated conditions for several months.

On March 10th at 0000 it was discovered that the 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months channel check of the Reactor Vessel Water Level instruments required by ORM 2.2.12 Feedwater System / Main Turbine Trip Testing Requirement 4.2.12.1 had NOT been performed since March 9th at 0800.

A risk assessment has NOT been performed.

Given these conditions, when is the LATEST the surveillance can be completed and remain in compliance with the Operational Requirements Manual?

A. Perform the surveillance prior to March 10th at 0800.

B. Perform the surveillance prior to March 10th at 1200.

C. Perform the surveillance prior to March 11th at 0000.

D. Currently NOT in compliance. Enter the ACTIONS of ORM 2.2.12 immediately.

Answer: C Answer Explanation C is correct: ORM TR 4.2.12.1 has a frequency of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . With the 1.25 times grace period permitted by ORM 1.3.2, the surveillance was required to be performed by 2300 on March 9th (March 9th 0800 + 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months + 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months = March 9th at 2300 hours0.0266 days 0.639 hours 0.0038 weeks 8.7515e-4 months ).

ORM 1.3.3 states that if it is discovered that a Testing Requirement was not performed within its specified Frequency, then compliance with the requirement to declare the Operational Requirement not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit of the specified Frequency, whichever is greater. This delay period is permitted to allow performance of the Testing Requirement. A risk evaluation shall be performed for any Testing Requirement delayed greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and the risk impact shall be managed.

A is incorrect but plausible if the examinee applies the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months extension from the last time the surveillance was performed.

B is incorrect but plausible if the examinee applies the 12 surveillance frequency to the time of discovery or thinking the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months allowance can't be used without a risk assessment.

D is incorrect but plausible if the examinee fails to recognize that ORM 1.3.3. allows a delay of entering actions.

KA Justification: This question meets the KA because the examinee must be able to apply ORM 1.3.3 to the conditions listed in the stem, and based on that analysis, determine required ORM actions. Also received approval from the NRC CE to use this question as a Tier 1 question.

SRO Justification - CPS SRO (only) Task 140109.23: Apply the administrative requirements for execution of Technical Specifications and Off-Site Dose Calculation Manual Requirements. Also related to 10CFR55.43(b)(2) Facility operating limitations in the technical specifications.

CPS OPS ILT EXAM Page: 17 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Question 4 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 2 Difficulty: 0.00 System ID: 896370 User-Defined ID: CL-ILT-812653 Cross Reference Number:

The plant has been operating at rated conditions for several Topic:

months. On March 10th at 0000 it was Num Field 1:

Num Field 2:

Text Field:

CPS OPS ILT EXAM Page: 18 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Comments: General Data Technical Reference with ORM 1.3.3 Rev. 67 Revision Number:

Justification for Non SRO CFR NA Link:

Question History: (i.e. LGS MNGP 2009 ILT NRC NRC-05, OYS CERT-04) Exam Question Source: (i.e. New, Bank Bank, Modified)

Low KA Justification (if NA required):

Revision History: Revision Converted MNGP 2009 History: (i.e. Modified NRC EXAM Q78 for distractor b to make application at CPS.

plausible based on OTPS review)

ILT Supplied Ref (If appropriate): ORM section 1.0 - 1.3 (i.e. ABN-##)

Excluded

Reference:

(i.e. None Ensure ON-## not provided)

LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)

General Information Question Level (RO/SRO) SRO Station Clinton Cognitive Level Higher (3SPR)

KA Data KA Number / System Name: 295005 Main Turbine Trip Category / KA Statement: 2.2.22 Knowledge of limiting conditions for operations and safety limits. (CFR: 41.5 / 43.2

/ 45.2)

RO Value: 4.0 SRO Value: 4.7 Tier: 1 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.5 10CFR55-43 (SRO) Data: 43.2 CPS OPS ILT EXAM Page: 19 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Associated objective(s):

Question 4 / 79 245000.12 Given MAIN TURBINE (TG) System operability status OR key parameter indications, plant conditions, and a copy of Tech Specs, DETERMINE if Tech Spec Limiting Condition for Operations have been met, and required actions if any.

CPS OPS ILT EXAM Page: 20 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version 5 ID: 896371 Points: 1.00 A feedwater transient has occurred resulting in a reactor scram.

All systems functioned as designed.

EOP-1 RPV Control was entered.

Which of the following 4 (four) annunciators, if received simultaneously, would be prioritized the highest?

A. 5003-5M CNMT/DW IA Isol Vlv Closed B. 5041-4C Low Press Control Bldg IA Ring Hdr C. 5041-5E Low Press Turbine Bldg Serv Air Hdr D. 5041-4B Low Press Radwaste Bldg IA Ring Hdr Answer: A Answer Explanation A is correct:

A loss of air to the containment/drywell will result in the closure of the inboard Main Steam Isolation Valves. This will eliminate use of the main turbine bypass valves for pressure control and will require shifting pressure control to the alternate pressure control methods listed in EOP-1 (SRVs, RCIC, MSL Drains, RWCU recirc or reject modes).

B is incorrect but plausible - a loss of control building instrument air will result in a loss of plant ventilation systems and plant chillers, but will have no effect on pressure / level control strategies in EOP-1.

C is incorrect but plausible - the examinee may select this choice if they incorrectly determine that air to the containment is supplied from TB SA. Containment instrument air is supplied from Turbine Building Instrument Air header, not service air.

D is incorrect but plausible - the examinee may select this choice due to the loss of air to 1N66-F060 OG System Discharge Isolation Valve resulting in a loss of condenser vacuum - however this valve fails as-is on a loss of air - vacuum would not be affected.

KA Justification: This question meets the KA because the examinee must be able to interpret the conditions listed in the stem, and determine how the conditions listed in the stem affect pressure and /or level control strategies in EOP-1, and then prioritize the alarms based on that analysis.

SRO Justification - linked to SRO (only) Task 440101.01: Respond to a Reactor Pressure Vessel control emergency per EOP-1. Also related to 10CFR55.43(b)(5) for assessment of facility conditions, i.e. which mitigation strategies remain available, and selection of appropriate procedures.

CPS OPS ILT EXAM Page: 21 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Question 5 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 1 Difficulty: 0.00 System ID: 896371 User-Defined ID: CL-ILT-812654A Cross Reference Number:

A feedwater transient has occurred resulting in a reactor scram.

Topic:

All systems functioned as desi Num Field 1:

Num Field 2:

Text Field:

CPS OPS ILT EXAM Page: 22 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Comments: General Data Technical Reference with CPS 4004.01 Instrument Revision Number: Air Loss Rev. 9e CPS 5003.05 (5M) Rev.

30c CPS 5041.04 (4B & 4C)

Rev. 27 CPS 5041.05 (5E) Rev. 29a Justification for Non SRO CFR NA Link:

Question History: (i.e. LGS No Previous NRC Exam NRC-05, OYS CERT-04) Usage Question Source: (i.e. New, New Bank, Modified)

Low KA Justification (if NA required):

Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)

ILT Supplied Ref (If appropriate): None (i.e. ABN-##)

Excluded

Reference:

(i.e.

CPS 5003.05 (5M)

Ensure ON-## not provided)

CPS 5041.04 (4B & 4C)

CPS 5041.05 (5E)

LORT PRA: (i.e. Yes or No or #) Yes LORT Question Section: (i.e, NA A-Systems or B-Procedures)

General Information Question Level (RO/SRO) SRO Station Clinton Cognitive Level Higher (3SPK)

KA Data KA Number / System Name: 295019 Partial or Complete Loss of Instrument Air Category / KA Statement: 2.4.45 Ability to prioritize and interpret the significance of each annunciator or alarm. (CFR:

41.10 / 43.5 / 45.3 / 45.12)

RO Value: 4.1 SRO Value: 4.3 Tier: 1 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.10 10CFR55-43 (SRO) Data: 43.5 CPS OPS ILT EXAM Page: 23 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Question 5 Table-Item Links NRC EXAM - NUREG 1021 Question Cognitive Level Comprehension or Analysis - (H)igher Cognitive Level

General Question Data - Site Ownership Clinton

General Question Data - Ops Program Senior Reactor Operator

General Question Data - Initial/Continuing Initial Training Associated objective(s):

Question 5 / 80 PB400401.01.04 Describe the effect a loss of Instrument Air has on the following:

.1 Reactor Protection System (RPS)

.2 Main Steam Isolation Valves

.3 Automatic Depressurization System (ADS)

.4 Condenser Vacuum System (CA)

.5 Feedwater System (FW)

.6 Condensate/Condensate Booster System (CD/CB)

.7 Reactor Water Cleanup System (RT)

.8 Off-Gas System (OG)

.9 Drywell Purge System (VQ)

.10 CNMT, Fuel, Auxiliary, Turbine and Radwaste Building HVAC systems (VR, VF, VA, VT, VW)

.11 Plant Chillers (WO)

.12 Drywell and CNMT Equipment/Floor Drain System (RE/RF)

CPS OPS ILT EXAM Page: 24 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version 6 ID: 896372 Points: 1.00 The unit was operating at full power when severe weather caused a loss of power to the 345KV Switchyard North AND South busses and a Main Generator trip.

All appropriate immediate operator actions were taken.

Current plant conditions are as follows:

SRV 1B21-F051D is full open.

SRV 1B21-F051C is cycling open and closed.

The 'A' RO reports Reactor Power is fluctuating between 7% and 10%.

Reactor water level is cycling between minus 30" and plus 10.

Suppression pool level is 19' 3" and slowly rising.

Suppression pool temperature is 108°F and slowly rising.

Which ONE of the following actions is directed by the CRS?

A. Insert control rods using CPS 4100.01 Reactor Scram.

B. Stabilize RPV pressure below 1065 psig using Turbine Bypass Valves.

C. Restore and maintain reactor water level between RPV Level 3 and 8.

D. Stabilize RPV pressure below 1065 psig using the SRVs.

Answer: D Answer Explanation D is correct:

A loss of the 345KV Switchyard North and South Busses will result in a loss of the RAT Transformers A, B, and C and a generator trip. This will result in a loss of BOP power in the plant, removing the Main Condenser as a heat sink.

The current conditions provided in the stem indicate that an ATWS has occurred. Each SRV can pass approximately 6% reactor power, so with one SRV full open and the second cycling open and closed, reactor power is between 6 and 12%. Per the pressure leg of CPS 4404.01 ATWS RPV Control, stabilize RPV pressure below 1065 psig using main turbine bypass valves. Use other methods below if needed.

Since the Main Condenser is not available due to the loss of BOP power, SRVs are required to be used to control reactor pressure.

A is incorrect but plausible - with reactor power above 5%, the power leg of EOP-1A directs inserting control rods per CPS 4411.08, not CPS 4100.01.

B is incorrect but plausible - EOP-1A directs stabilizing pressure below 1065 psig using turbine bypass valves, however, with a loss of BOP power the bypass valves are not available and other pressure control methods will have to be employed.

C is incorrect but plausible if the examinee incorrectly diagnoses the conditions in the stem and determines that RPV level should be maintained L3 to L8 per EOP-1 RPV Control or per Level Band A of EOP-1A ATWS RPV Control.

CPS OPS ILT EXAM Page: 25 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version KA Justification: This question meets the KA because the examinee must be able to evaluate and interpret the plant conditions provided in the stem and determine required actions based on the evaluation.

SRO Justification - linked to SRO only task 440401.02 (Enter and Execute EOP-1A when required) and 10CFR55.43(b)(5) Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations.

CPS OPS ILT EXAM Page: 26 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Question 6 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 2 Difficulty: 0.00 System ID: 896372 User-Defined ID: CL-ILT-887214A Cross Reference Number:

The unit was operating at full power when severe weather Topic:

caused a loss of power to the 345KV Switc Num Field 1:

Num Field 2:

Text Field:

CPS OPS ILT EXAM Page: 27 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Comments: General Data Technical Reference with CPS 4404.01 ATWS RPV Revision Number: Control Rev. 29 Justification for Non SRO CFR NA Link:

Question History: (i.e. LGS 2005 Monticello NRC Exam NRC-05, OYS CERT-04)

Question Source: (i.e. New, Bank Bank, Modified)

Low KA Justification (if NA required):

Revision History: Revision Converted MNGP 2005 History: (i.e. Modified NRC EXAM Q88 for distractor b to make application at CPS.

plausible based on OTPS review)

ILT Supplied Ref (If appropriate): None (i.e. ABN-##)

Excluded

Reference:

(i.e. EOP-1A Ensure ON-## not provided)

LORT PRA: (i.e. Yes or No or #) Yes LORT Question Section: (i.e, NA A-Systems or B-Procedures)

General Information Question Level (RO/SRO) SRO Station Clinton Cognitive Level Higher (3SPR)

KA Data KA Number / System Name: 295025 High Reactor Pressure Category / KA Statement: 2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation. (CFR: 41.5 / 43.5 / 45.12 / 45.13)

RO Value: 4.4 SRO Value: 4.7 Tier: 1 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.5 10CFR55-43 (SRO) Data: 43.5 CPS OPS ILT EXAM Page: 28 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Associated objective(s):

Question 6 / 81 LP87553.01.12 Given a diagram of EOP-1A, appropriate EOP-support procedures, and simulated plant conditions determine which course of action should take priority over others:

.01 Establishing RPV water level in accordance with the Level Bands provided in the Level Path.

.02 Preventing LPCS/LPCI injection not needed for core cooling if drywell pressure is above 1.68 psig

.03 Defeating interlocks for inserting control rods using CPS No. 4411.08, ALTERNATE CONTROL ROD INSERTION

.04 Use of CPS No. 4100.01, REACTOR SCRAM vs. CPS No. 4411.08, ALTERNATE CONTROL ROD INSERTION, to insert control rods CPS OPS ILT EXAM Page: 29 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version 7 ID: 896373 Points: 1.00 A transient has occurred resulting in a loss of coolant accident requiring a blowdown per EOP-3 Emergency RPV Depressurization, which is complete.

Plant conditions have stabilized.

Given the detail below:

If both Fuel Zone instruments were inoperable, which, if any, of the following scenarios will require entry into EOP-2 RPV Flooding? (Assume the instruments are NOT indicating erratically.)

RPV Level RPV Pressure DW Temp Cnmt Temp Scenario 1 -147" 55 psig 325°F 140°F Scenario 2 -139" 114 psig 275°F 205°F Scenario 3 -147" 45 psig 305°F 209°F A. Scenario 1 ONLY B. Scenario 3 ONLY CPS OPS ILT EXAM Page: 30 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version C. Scenarios 2 & 3 ONLY D. None of the scenarios Answer: C Answer Explanation C is correct:

Per the level leg overrides in EOP-1 and 1A, RPV Flooding is required if RPV water level is unknown.

Per the instructions in Detail A (not provided in the stem) and CPS 4411.07 RPV Level Instrumentation:

RPV water level instruments may be unreliable due to boiling in the instrument legs if drywell or containment temperature is above Fig. B, RPV Saturation Temperature.

Do not use an RPV water level instrument if level is at or below Fig. C, Minimum Usable Levels.

> Fig. B? < Min Usable Level? Flooding Required?

Scenario 1 Yes No No Scenario 2 No Yes Yes Scenario 3 Yes Yes Yes Therefore, RPV Flooding is required for scenarios 2 and 3.

A is incorrect but plausible if the examinee incorrectly determines that RPV flooding is only required when operating above the saturation curve of Fig. B.

B is incorrect but plausible if the examinee incorrectly determines that RPV flooding is only required when operating below the minimum usable level value and above Fig. B.

D is incorrect but plausible if the examinee incorrectly determines that RPV flooding is not required based on the conditions provided in the stem.

KA Justification: This question meets the KA because the examinee must be able to interpret the affect of high DW temperature conditions on reactor water level indications.

SRO Justification - linked to SRO only task 440301.02 (Enter and Execute EOP-2 Flooding during NON-ATWS conditions) and 10CFR55.43(b)(5) Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations. The question is also SRO ONLY level because the evaluation of plant parameters requires knowledge of the usage instructions of details on EOP-1. The interpretation of the data in the table and determining level is unknown to determine an entry condition into EOP-2 is the SRO's job at Clinton. Knowledge of EOP-2 RPV Flooding direct entry conditions is NOT RO level knowledge per the SRO Only clarification guidance.

CPS OPS ILT EXAM Page: 31 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Question 7 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 2 Difficulty: 0.00 System ID: 896373 User-Defined ID: CL-ILT-887232 Cross Reference Number:

aA transient has occurred resulting in a loss of coolant accident Topic:

requiring a blowdown per EOP-3 Em Num Field 1:

Num Field 2:

Text Field:

CPS OPS ILT EXAM Page: 32 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Comments: General Data Technical Reference with

CPS 4411.07 Rev. 6 Revision Number:

4401.01 RPV Control Detail A RPV Water Level Instruments Rev.

29 Justification for Non SRO CFR NA Link:

Question History: (i.e. LGS No NRC Exam usage NRC-05, OYS CERT-04)

Question Source: (i.e. New, New Bank, Modified)

Low KA Justification (if NA required):

Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)

ILT Supplied Ref (If appropriate): None (i.e. ABN-##)

Excluded

Reference:

(i.e. Detail A in EOP-1, 1A, 3, 6 Ensure ON-## not provided) and SAG-1 LORT PRA: (i.e. Yes or No or #) Yes LORT Question Section: (i.e, NA A-Systems or B-Procedures)

General Information Question Level (RO/SRO) SRO Station Clinton Cognitive Level Higher (3SPR)

KA Data KA Number / System Name: 295028 High Drywell Temperature Category / KA Statement: EA2. Ability to determine and/or interpret the following as they apply to HIGH DRYWELL TEMPERATURE : EA2.03 Reactor water level (CFR: 41.10 / 43.5 / 45.13)

RO Value: 3.7 SRO Value: 3.9 Tier: 1 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.10 10CFR55-43 (SRO) Data: 43.5 CPS OPS ILT EXAM Page: 33 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Associated objective(s):

Question 7 / 82 LP87554.01.01 Given plant conditions, determine if entry/re-entry to EOP-2, RPV Flooding is required.

CPS OPS ILT EXAM Page: 34 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version 8 ID: 896374 Points: 1.00 The plant is in Mode 1. The B Reactor Operator is performing CPS 9000.01D001 CONTROL ROOM SURVEILLANCE LOG - MODE 1, 2, 3 DATA SHEET.

The B Reactor Operator informs the CRS that Drywell Average Air Temperature is 155°F.

This _____(1)_____ exceed the Technical Specification Limit, which is based on NOT exceeding

_____(2)_____ during a DBA LOCA.

A. (1) DOES (2) 330°F in the drywell B. (1) DOES NOT (2) 330°F in the drywell C. (1) DOES (2) 185°F in the containment D. (1) DOES NOT (2) 185°F in the containment Answer: A Answer Explanation A is correct - per TS 3.6.5.5, DW average air temperature shall be less than or equal to 146.53°F.

Per TS B3.6.5.5, the limitation on drywell average air temperature ensures that the peak drywell temperature during a design basis loss of coolant accident (LOCA) does not exceed the design temperature of 330°F.

B is incorrect but plausible if the examinee incorrectly recalls the TS LCO value for DW average temperature.

C is incorrect but plausible - during a DBA LOCA, heat is transferred from the Drywell to the Containment.

185°F is the Containment design temperature. The examinee may select this response of he/she incorrectly recalls the bases for the LCO.

D is incorrect but plausible - during a DBA LOCA, heat is transferred from the Drywell to the Containment.

185°F is the Containment design temperature. The examinee may select this response of he/she incorrectly recalls the bases for the LCO.

KA justification - this question meets the KA because the examinee must be able to compare the value for DW average air temperature in the stem and recall if it exceeds an LCO limit, and an assumption in the TS bases.

SRO Only justification - Part 2 of the question requires knowledge of TS Bases for DW average air temperature which is SRO only knowledge, and is linked to 10CFR55.43(b)(2) facility operating limitations in the technical specifications and their bases.

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EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Question 8 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 1 Difficulty: 3.00 System ID: 896374 User-Defined ID: CL-ILT-887273 Cross Reference Number:

The plant is in Mode 1. The B Reactor Operator is performing Topic:

CPS 9000.01D001 CONTROL ROOM SURVEIL Num Field 1:

Num Field 2:

Text Field:

CPS OPS ILT EXAM Page: 36 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Comments: General Data Technical Reference with Technical Specification Revision Number: LCO 3.6.5.5 and B3.6.5.5 Justification for Non SRO CFR NA Link:

Question History: (i.e. LGS No NRC Exam usage NRC-05, OYS CERT-04)

Question Source: (i.e. New, Bank: Duplicate of CL-ILT-Bank, Modified) 6893 Low KA Justification (if NA required):

Revision History: Revision Added answer plausibility, History: (i.e. Modified KA justification, and SRO distractor b to make only justification plausible based on OTPS statements.

review)

ILT Supplied Ref (If appropriate): None (i.e. ABN-##)

Excluded

Reference:

(i.e. None Ensure ON-## not provided)

LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)

General Information Question Level (RO/SRO) SRO Station Clinton Cognitive Level Memory (1F)

KA Data KA Number / System Name: 295012 High Drywell Temperature Category / KA Statement: AA2. Ability to determine and/or interpret the following as they apply to HIGH DRYWELL TEMPERATURE : AA2.01 Drywell temperature (CFR: 41.10 / 43.5 / 45.13)

RO Value: 3.8 SRO Value: 3.9 Tier: 1 RO Group: 2 SRO Group: 2 10CFR55-41 (RO) Data: 41.10 10CFR55-43 (SRO) Data: 43.5 CPS OPS ILT EXAM Page: 37 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Associated objective(s):

Question 8 / 83 223001.14 Given PRIMARY CONTAINMENT System operability status and a copy of Tech Specs, DISCUSS the bases for the PRIMARY CONTAINMENT System Tech Spec LCO, related safety limits and Limiting Safety System Settings.

CPS OPS ILT EXAM Page: 38 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version 9 ID: 896508 Points: 1.00 The plant is operating at rated power when a partial loss of Drywell Cooling (VP) occurs, resulting in the following conditions:

Drywell Average Air Temperature rises and stabilizes at 145.6°F

Drywell-to-Primary Containment d/p rises and stabilizes at +1.1 psid Which ONE of the following describes:

(1) the required action, AND (2) the bases for performing that action?

A. (1) Restore the Drywell-to-Primary Containment d/p to within its Tech Spec limits.

(2) Prevent Weir wall overflow, should an inadvertent upper pool dump occur.

B. (1) Restore Drywell-to-Primary Containment d/p to within its Tech Spec limits.

(2) Prevent direct communication of the blowdown energy contained in the drywell airspace, to the suppression pool inventory, should a LOCA occur.

C. (1) Restore the Drywell Average Air Temperature to within its Tech Spec limits.

(2) Prevent Drywell temperatures from exceeding the drywell structural design temperature, should a LOCA occur.

D. (1) Restore the Drywell Average Air Temperature to within its Tech Spec limits.

(2) Prevent Drywell temperatures from exceeding the drywell EQUIPMENT QUALIFICATION temperatures, should a complete loss of VP occur.

Answer: B Answer Explanation B is correct:

Per Tech Spec 3.6.5.4, Drywell-to-containment differential pressure shall be -0.2 psid and 1.0 psid.

Per Tech Spec 3.6.5.5 Drywell average air temperature shall be 146.53°F.

With the conditions provided in the stem, the ITS 3.6.5.4 limit has been exceeded and required action A.1 must be performed within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Per ITS B3.6.5.4, Drywell-to-primary containment differential pressure is an assumed initial condition in the analyses that determine the primary containment thermal hydraulic and dynamic loads during a postulated loss of coolant accident (LOCA).

If drywell pressure is less than the primary containment airspace pressure, the water level in the weir annulus will increase and, consequently, the liquid inertia above the top vent will increase. This will cause top vent clearing during a postulated LOCA to be delayed, and that would increase the peak drywell pressure. In addition, an inadvertent upper pool dump occurring with a negative drywell-to-primary containment differential pressure could result in overflow over the weir wall.

CPS OPS ILT EXAM Page: 39 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version The limitation on negative drywell-to-primary containment differential pressure ensures that changes in calculated peak LOCA drywell pressures due to differences in water level of the suppression pool and the drywell weir annulus are negligible. It also ensures that the possibility of weir wall overflow after an inadvertent upper pool dump is minimized. The limitation on positive drywell-to-primary containment differential pressure helps ensure that the horizontal vents are not cleared with normal weir annulus water level and limits drywell pressure during an accident to less than the drywell design pressure.

A is incorrect but plausible if the examinee incorrectly believes that containment pressure is higher than drywell pressure and that the concern is overflow of the weir wall into the drywell should an inadvertent upper pool dump occur.

C & D are incorrect but plausible if the examinee incorrectly determines that DW average temperature has exceeded the limit and the bases for ITS 3.6.5.5.

KA justification - this question meets the KA because the examinee must be able to determine that drywell pressure has exceeded the technical specification limit based on the conditions provided in the stem.

SRO Only justification - although the first part of the question can be answered using RO knowledge of LCO limits (above the double line), the second part requires knowledge of the tech spec bases for the specifications, which is SRO only knowledge. Linked to 10CFR55.43(b)(2) Facility operating limitations in the technical specifications and their bases.

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EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Question 9 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 2 Difficulty: 0.00 System ID: 896508 User-Defined ID: CL-ILT-896508 Cross Reference Number:

The plant is operating at rated power when a partial loss of Topic:

Drywell Cooling (VP) occurs, resultin Num Field 1:

Num Field 2:

Text Field:

CPS OPS ILT EXAM Page: 41 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Comments: General Data Technical Reference with

ITS 3.6.5.4 and Revision Number: B3.6.5.4

ITS 3.6.5.5 and B3.6.5.5 Justification for Non SRO CFR NA Link:

Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) history Question Source: (i.e. New, Bank Bank, Modified)

Low KA Justification (if NA required):

Revision History: Revision Revised CL-ILT-6053 for History: (i.e. Modified use in the ILT 12-1 NRC distractor b to make Exam plausible based on OTPS review)

ILT Supplied Ref (If appropriate): None (i.e. ABN-##)

Excluded

Reference:

(i.e. None Ensure ON-## not provided)

LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)

General Information Question Level (RO/SRO) SRO Station Clinton Cognitive Level Higher (3-SPK/R)

KA Data KA Number / System Name: 295010 High Drywell Pressure Category / KA Statement: AA2. Ability to determine and/or interpret the following as they apply to HIGH DRYWELL PRESSURE: AA2.02 Drywell pressure (CFR: 41.10 / 43.5 / 45.13)

RO Value: 3.8 SRO Value: 3.9 Tier: 1 RO Group: 2 SRO Group: 2 10CFR55-41 (RO) Data: 41.10 10CFR55-43 (SRO) Data: 43.5 CPS OPS ILT EXAM Page: 42 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Associated objective(s):

Question 9 / 84 223001.14 Given PRIMARY CONTAINMENT System operability status and a copy of Tech Specs, DISCUSS the bases for the PRIMARY CONTAINMENT System Tech Spec LCO, related safety limits and Limiting Safety System Settings.

CPS OPS ILT EXAM Page: 43 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version 10 ID: 896376 Points: 1.00 The plant was operating at rated thermal power.

The 'B' RO reports that Auxiliary Building Steam Tunnel temperature indicates 165°F.

Rad levels in the plant are normal.

T Area Temperature Limits (°F)

Rec Area Alarm Max Normal Max Safe Pt 1 HPCS Pump Room 104 130 140 2 Aux Bldg Aisl El 707' 6" (West) 104 130 140 3 RHR Pump Room A 104 130 140 4 RHR Heat Exch Room A 104 130 140 5 RHR Pump Room B 104 130 140 6 RHR Heat Exch Room B 104 130 140 7 RHR Pump Room C 104 130 140 8 Aux Bldg RCIC Pump Room 104 130 200 9 Aux Bldg RCIC Instr Pnl Rm 104 130 200 10 LPCS Pump Room 104 130 140 11 Aux Bldg Access Aisle EL 737' (West) 104 130 140 12 Aux Bldg Access Aisle EL 737' (East) 122 130 140 13 Aux Bldg RW Pipe Tunnel 122 130 200 14 Aux Bldg Below MS Tunnel 150 156 200 15 RWCU Pump Room A 104 130 200 16 RWCU Pump Room B 104 130 200 17 RWCU Pump Room C 104 130 200 18 Aux Bldg Steam Tunnel 148 163 200 19,20 Fuel Pool Clg Heat Exch Rm 122 122 135 Which of the following actions, if any, are required?

A. Verify Fuel Building Ventilation System (VF) is running, and if NOT, restart VF.

B. Verify Turbine Building Ventilation System (VT) is operating, and if NOT, restart VT.

C. Secure the Fuel Building Ventilation System (VF) and start the Standby Gas Treatment System (VG).

D. No actions are required until Auxiliary Building Steam Tunnel temperature has exceeded max safe temperature.

Answer: A Answer Explanation A is correct - per CPS 4406.01 Secondary Containment Control, Auxiliary Building Steam Tunnel Temperature above 148°F requires entry into EOP-8. Per the directions in EOP-8, if VF isolates and VF Exhaust radiation is below 10 mr/hr, VF is restarted in an attempt to lower secondary containment temperatures.

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EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version B is incorrect but plausible if the examinee determines that operation of the VT system will lower ABST temperature. The examinee may select this response based on EOP-9 Radioactivity Release Control direction to restart VT if VT is shutdown.

C is incorrect but plausible if the examinee incorrectly determines that VG should be started to mitigate the conditions in the stem. VG provides no cooling to the secondary containment and violates the directions provided in EOP-8.

D is incorrect but plausible if the examinee fails to recognize that EOP-8 entry conditions are exceeded with any area temperature above max normal values (regardless of rad levels in the plant)..

KA justification - this question meets the KA because the examinee must be able to intepret the indications provided in the stem and determine which actions are required to mitigate the high ABST temperature condition.

SRO Only justification - the direction to restart VF is contained in an EOP-8 override which is an SRO only function at CPS and is supported by an SRO only task 100509.06 (Execute EOP Overrides).

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EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Question 10 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 2 Difficulty: 0.00 System ID: 896376 User-Defined ID: CL-ILT-812659A Cross Reference Number:

The plant was operating at rated thermal power. The 'B' RO Topic:

reports that Auxiliary Building Steam Num Field 1:

Num Field 2:

Text Field:

CPS OPS ILT EXAM Page: 46 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Comments: General Data Technical Reference with CPS 4406.01 Rev. 29 Revision Number:

Justification for Non SRO CFR NA Link:

Question History: (i.e. LGS No previous NRC Exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, New Bank, Modified)

Low KA Justification (if NA required):

Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)

ILT Supplied Ref (If appropriate): None (i.e. ABN-##)

Excluded

Reference:

(i.e. 4406.01 (If included as a Ensure ON-## not provided) reference in the remainder of the exam, the VF override information must be removed.

LORT PRA: (i.e. Yes or No or #) Yes LORT Question Section: (i.e, NA A-Systems or B-Procedures)

General Information Question Level (RO/SRO) SRO Station Clinton Cognitive Level Higher (3-SPK/R)

KA Data KA Number / System Name: 295032 High Secondary Containment Area Temperature Category / KA Statement: 2.2.44 Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and l directives affect plant and system conditions. (CFR: 41.5 /

43.5 / 45.12)

RO Value: 4.2 SRO Value: 4.4 Tier: 1 RO Group: 2 SRO Group: 2 10CFR55-41 (RO) Data: 41.5 10CFR55-43 (SRO) Data: 43.5 CPS OPS ILT EXAM Page: 47 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Associated objective(s):

Question 10 / 85 LP85802.2.2.44 Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions. (Moved from 2.4.48)

CPS OPS ILT EXAM Page: 48 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version 11 ID: 896377 Points: 1.00 The plant is in Mode 2 at approximately 1% RTP. It is anticipated that Mode 1 will be entered within the next hour.

While performing a channel check on the "A" channel of the Containment Building Exhaust Radiation monitoring system, the channel fails downscale and is declared inoperable.

What action is required in accordance with Technical Specifications?

A. Place the channel in trip within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

B. Place the channel in trip within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . Otherwise, isolate the penetration within the following 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

C. Place the channel in trip within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Otherwise, isolate the penetration flow paths within the following 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

D. Place the channel in trip within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Otherwise, restore secondary containment isolation capability within the following 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Answer: C Answer Explanation C is correct:

The Containment Building Exhaust Radiation Monitors are listed in ITS Table 3.3.6.1.1-1 Primary Containment and Drywell Isolation Function 2.h and Table 3.3.6.2-1 Secondary Containment Isolation Instrumentation Function 4.

Per ITS B 3.3.6.1 and B 3.3.6.2, the Exhaust Radiation - High signals are initiated from radiation detectors that are located on the ventilation exhaust piping coming from the drywell and containment.

The signal from each detector is input to an individual monitor whose trip outputs are assigned to an isolation channel. Four channels of Containment and Drywell Ventilation Exhaust-High Function are available and are required to be OPERABLE to ensure that no single instrument failure can preclude the isolation function.

Per ITS 3.3.6.1 action D.1 and ITS 3.3.6.2 action A.1 place channel in trip within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Isolation capability is maintained by the other 3 channels.

A is incorrect but plausible if the examinee incorrectly applies 3.3.6.1 A.1.

B is incorrect but plausible if the examinee incorrectly applies 3.3.6.1 B.1.

D is incorrect but plausible if the examinee incorrectly applies 3.3.6.2 B.1.

KA justification - this question meets the KA because the examinee must be able to determine the impact of a failed Containment Building Exhaust Radiation monitor on the Primary and Secondary Containment Isolation Instrumentation specifications, and determine what actions are required to mitigate the consequence of the failure.

SRO only justification - linked to SRO only task 140109.23 (Apply the administrative requirements for execution of Techinical Specifications and Off-Site Dose Calculation Manual Requirements) and 10CFR55.43(b)(2) Facility operating limitations in the technical specifications and their bases.

CPS OPS ILT EXAM Page: 49 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version CPS OPS ILT EXAM Page: 50 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Question 11 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 2 Difficulty: 0.00 System ID: 896377 User-Defined ID: CL-ILT-887274A Cross Reference Number:

The plant is in Mode 2 at approximately 1% RTP. It is Topic:

anticipated that Mode 1 will be entered wit Num Field 1:

Num Field 2:

Text Field:

CPS OPS ILT EXAM Page: 51 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Comments: General Data Technical Reference with

ITS 3.3.6.1 and 3.3.6.2 Revision Number:

CPS 3315.03 Appendix A Rev. 9

CPS 5140.61 Rev. 0b Justification for Non SRO CFR NA Link:

Question History: (i.e. LGS No previous NRC Exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, Bank - duplicate of CL-ILT-Bank, Modified) 0775 Low KA Justification (if NA required):

Revision History: Revision Added answer plausibility, History: (i.e. Modified KA justification, and SRO distractor b to make only justification plausible based on OTPS statements.

review)

ILT Supplied Ref (If appropriate): ITS 3.3.6.1 and 3.3.6.2 (i.e. ABN-##) (including Table 3.3.6.1-1 and Table 3.3.6.2-1)

Excluded

Reference:

(i.e. NA Ensure ON-## not provided)

LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)

General Information Question Level (RO/SRO) SRO Station Clinton Cognitive Level Higher (3-SPK/R)

KA Data KA Number / System Name: 223002 Primary Containment Isolation System/Nuclear Steam Supply Shut-Off Category / KA Statement: A2. Ability to (a) predict the impacts of the following on the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: A2.06 Containment instrumentation failures (CFR: 41.5 / 45.6)

RO Value: 3.0 SRO Value: 3.2 Tier: 2 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.5 10CFR55-43 (SRO) Data: NA CPS OPS ILT EXAM Page: 52 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Associated objective(s):

Question 11 / 86 272000.12 Given AR/PR System operability status OR key parameter indications, plant conditions, and a copy of Tech Specs, DETERMINE if Tech Spec Limiting Condition for Operations have been met, and required actions if any.

CPS OPS ILT EXAM Page: 53 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version 12 ID: 896378 Points: 1.00 A procedural deficiency during an Engineering Change resulted in the air sparging valve to the SLC Storage Tank being opened for 1 (one) month before it was discovered open and subsequently closed.

At the beginning of the month SLC Storage Tank parameters were as follows:

4000 gallons

13.4% Boron Concentration By Weight (1) How was SLC Tank Level affected during this period?

(2) After the air sparging valve has been closed, how is SLC operability verified?

A. (1) Higher due to moisture absorption from the air.

(2) Verify SLC Storage Tank Level is less than 4737 gallons ONLY.

B. (1) Higher due to moisture absorption from the air.

(2) Direct Chemistry to re-sample SLC Storage Tank concentration, then verify the concentration of boron in solution is within the limits of Figure 3.1.7-1.

C. (1) Lower due to increased evaporation rate.

CPS OPS ILT EXAM Page: 54 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version (2) Verify SLC Storage Tank Level is greater than 3574 gallons ONLY.

D. (1) Lower due to increased evaporation rate.

(2) Direct Chemistry to re-sample SLC Storage Tank concentration, then verify the concentration of boron in solution is within the limits of Figure 3.1.7-1.

Answer: D Answer Explanation D is correct:

This question is based on an actual event at CPS (LER 2004-02-001) where the air sparging valve to SLC was found open and caused SLC Tank Level to lower due to excessive evaporation.

Tank level changes will also affect SLC Tank boron concentration. With boron concentration unknown, SLC operability cannot be determined without performing a sample of the tank contents, which is performed by the Chemistry department.

ITS 3.1.7 requires SLC tank sampling monthly, if boron or water are added, or if tank temperature drops below 70 degrees, but not for this particular case. Per OP-AA-108-115-1002 Supplemental Consideration For On-Shift Immediate Operability Determinations, a senior licensed operator (SRO) on the operating shift crew is responsible for the determination of whether an SSC is operable. The senior licensed operator is assisted by others, as required. For this case, the on-shift SRO is responsible for getting an up to date sample of the SLC Tank to ensure boron concentration meets the requirements of TS Figure 3.1.7-1.

For the event detailed in LER 2004-02-001, SLC concentration was found at 14.1%, above the upper limit of 13.8% the day after the air sparger valve was closed.

A is incorrect but plausible - In AR 213560213560 the investigating operator reported moisture and condensation on top of the tank coming from the tank vent. The examinee may select this response based on the conclusion that moisture absorption would cause tank level to rise. Verifying SLC storage tank level below 4737 is plausible if the examinee follows Figure 3.1.7-1 to the right and uses 13.4% boron concentration.

B is incorrect but plausible - In AR 213560213560 the investigating operator reported moisture and condensation on top of the tank coming from the tank vent. The examinee may select this response based on the conclusion that moisture absorption would cause tank level to rise.

C is incorrect but plausible - Verifying SLC storage tank level above 3574 is plausible if the examinee follows Figure 3.1.7-1 to the left and uses 13.4% boron concentration.

KA justification - this question meets the KA because the examinee must be able to predict the impact of an open air sparger valve on the SLC system and the actions required to mitigate the consequences.

SRO justification - linked to SRO only tasks 101406.01 (Apply the administrative requirements of OPERABILITY DETERMINATION), and 999999.07 (Apply Technical Specification Requirements). Also related to 10CFR55.43(b)(2) Facility operating limitations in the technical specifications and their bases.

CPS OPS ILT EXAM Page: 55 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Question 12 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 2 Difficulty: 0.00 System ID: 896378 User-Defined ID: CL-ILT-812661A Cross Reference Number:

A procedural deficiency during an Engineering Change resulted Topic:

in the air sparging valve to the SLC Num Field 1:

Num Field 2:

Text Field:

CPS OPS ILT EXAM Page: 56 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Comments: General Data Technical Reference with

OP-AA-108-115-1002 Revision Number: Rev. 2

CPS 5066.06 Rev. 25d

ITS 3.1.7 Justification for Non SRO CFR NA Link:

Question History: (i.e. LGS No previous NRC Exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, New Bank, Modified)

Low KA Justification (if NA required):

Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)

ILT Supplied Ref (If appropriate): None (i.e. ABN-##)

Excluded

Reference:

(i.e. None Ensure ON-## not provided)

LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)

General Information Question Level (RO/SRO) SRO Station Clinton Cognitive Level Higher (3-SPK)

KA Data KA Number / System Name: 211000 Standby Liquid Control System Category / KA Statement: A2. Ability to (a) predict the impacts of the following on the STANDBY LIQUID CONTROL SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

A2.06 Valve openings (CFR: 41.5 / 45.6)

RO Value: 3.1 SRO Value: 3.3 Tier: 2 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.5 10CFR55-43 (SRO) Data: NA CPS OPS ILT EXAM Page: 57 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Associated objective(s):

Question 12 / 87 211000.12 Given STANDBY LIQUID CONTROL System operability status OR key parameter indications, plant conditions, and a copy of Tech Specs, DETERMINE if Tech Spec Limiting Condition for Operations have been met, and required actions if any.

CPS OPS ILT EXAM Page: 58 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version 13 ID: 896379 Points: 1.00 A transient has occurred requiring entry into EOP-2 RPV Flooding.

Shutdown criteria is met.

Which of the following scenarios represents a condition where injection flow can be slowed or stopped?

A. Inject with Reactor Core Isolation Cooling (RCIC) until RPV pressure starts to rise.

B. Inject with Condensate / Condensate Booster (CD/CB) Pumps until SRV tailpipe temperatures begin to rise.

C. Inject with High Pressure Core Spray (HPCS) until 1E22-F004 HPCS To CNMT Outbd Isln Valve closes at Level 8.

D. Defeat Motor Driven Reactor Feed Pump (MDRFP) Level 8 interlocks and inject with the MDRFP until SRV acoustic monitor alarms and Main Steam Line Flow indications are received.

Answer: D Answer Explanation D is correct:

Per the EOP Technical Bases, EOP-2, RPV flooding, is used to cool the core when RPV water level cannot be determined. The specified actions first depressurize the RPV, then control injection to establish and maintain one of the following conditions:

The RPV flooded to the elevation of the main steam lines. The core will then be cooled by full submergence. This condition may ultimately be achieved under either shutdown or failure-to-scram conditions.

RPV pressure above the Minimum Steam Cooling Pressure. The core will then be cooled by submergence or steam cooling. Since reactor power must be at least 6%-10% to generate the amount of steam required to sustain the Minimum Steam Cooling Pressure, this condition is applicable only under ATWS conditions.

Following the blowdown, the RPV is flooded to the main steam lines using the MDRFP (ok to defeat MRDFP interlocks per 4410.00C008), Condensate / Condensate Booster, CRD, HPCS, LPCS, LPCI, RHR through shutdown cooling, FP, SX through RHR B, FC, ECCS water leg pumps, SLC, CY, and Portable fire pump.

Steam-driven systems are not listed since, with SRVs open and the reactor shutdown, the RPV will depressurize to below the turbine stall pressures.

MDRFP and HPCS - The high RPV water level MDRFP and HPCS trips may be defeated to permit use of these pumps for flooding. If RPV water level is unknown, the inputs to the trip logic must be considered invalid.

CPS 1005.09M002 STA/IA Guide Sheet provides methodology for determining when level is at the Main Steam Lines and includes the following:

Assess using multiple and diverse items:

CPS OPS ILT EXAM Page: 59 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version

Acoustic Monitors (may clear when < MSL)

SRV/ADS Tail Pipe Temp (will lower when > MSL; will slowly raise up if < MSL)

RPV pressure - ~ 10 psig rise indicates at MSL's; sudden large increase indicates solid.

MSL - Flow / Hi Flow dP

SP Level increase after initial drop?

Drastic step changes on level?

Fill Rate vs. Leak/Usage Rate?

Not expected to reach MSL when > 7% RTP (SRV cap).

A is incorrect but plausible if the examinee fails to recall that RCIC will not be available for injection following the blowdown as described above.

B is incorrect but plausible if the examinee fails to recogize that rising SRV tailpipe temperatures is indicative that RPV level is below the MSLs.

C is incorrect but plausible if the examinee fails to recall that level must be raised to the Main Steam Lines and that the inputs to the HPCS level 8 trip logic must be considered invalid.

KA justification - This question meets the KA because the examinee must have knowledge of the mitigation strategies employed during EOP-2 RPV Flooding.

SRO only justification - linked to 10CFR55.43(b)(5) Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency conditions. Requires knowledge of specific procedure content to perform RPV Flooding. Also linked to SRO only task 100509.16d (Demonstrate knowledge of symptom based EOP mitigation strategies).

CPS OPS ILT EXAM Page: 60 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Question 13 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 2 Difficulty: 0.00 System ID: 896379 User-Defined ID: CL-ILT-812662A Cross Reference Number:

A transient has occurred requiring entry into EOP-2 RPV Topic:

Flooding. Shutdown criteria is met. Whic Num Field 1:

Num Field 2:

Text Field:

CPS OPS ILT EXAM Page: 61 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Comments: General Data Technical Reference with

CPS 1005.09M002 Revision Number: Rev. 7

CPS 4403.01 Rev. 29

EOP Tech Bases pg. 6-1 Rev. 6 Justification for Non SRO CFR NA Link:

Question History: (i.e. LGS No previous NRC Exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, New Bank, Modified)

Low KA Justification (if NA required):

Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)

ILT Supplied Ref (If appropriate): None (i.e. ABN-##)

Excluded

Reference:

(i.e. None Ensure ON-## not provided)

LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)

General Information Question Level (RO/SRO) SRO Station Clinton Cognitive Level Higher (3-SPK/R)

KA Data KA Number / System Name: 259002 Reactor Water Level Control System Category / KA Statement: 2.4.6 Knowledge of EOP mitigation strategies. (CFR: 41.10 / 43.5 / 45.13)

RO Value: 3.7 SRO Value: 4.7 Tier: 2 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.10 10CFR55-43 (SRO) Data: 43.5 CPS OPS ILT EXAM Page: 62 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Associated objective(s):

Question 13 / 88 LP87554.01.06 Given plant conditions after entry to EOP-2, RPV FLOODING, and a copy of EOPs, determine the appropriate actions for these conditions.

CPS OPS ILT EXAM Page: 63 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version 14 ID: 896380 Points: 1.00 Plant conditions are as follows:

Core alterations are in progress.

Division 2 NSPS Inverter has been shutdown to perform routine outage maintenance.

An irradiated fuel bundle is attached to the Refueling Bridge Mast which is nearing the upender in Containment.

Then, the following annunciators were received:

5002-4N NSPS INV SOURCE XFR ALT SOURCE

5002-5N NSPS INV TROUBLE The C Area Operator informs the MCR that the Division I NSPS Inverter has transferred to its alternate source.

Which of the following actions, if any, is required by CPS Technical Specifications?

A. NO further ITS actions are required.

B. Immediately suspend Core Alterations.

C. Restore the inverter to operable status in 7 days.

D. Immediately restore the Division 1 uninterruptible AC bus electrical power distribution subsystem to OPERABLE status.

Answer: B Answer Explanation B is correct - per ITS 3.8.8 Division 1 or 2 NSPS Inverter shall be operable. Per B3.8.8, OPERABLE NSPS Inverters required the associated bus to be powered from the inverter through inverted DC voltage from the required Class 1E DC bus, with the output within the design voltage and frequency tolerances.

Since the Div 1 NSPS inverter has transferred to its alternate AC source, the inverter is INOPERABLE.

With one or more required AC, DC, or uninterruptible AC bus electrical power distribution subsystems inoperable:

A.1 - Immediately declare affected required feature(s) inoperable, OR

A.2.1 - Immediately suspend CORE ALTERATIONS.

AND

A.2.2 - Immediately suspend handling of irradiated fuel assemblies in the primary and secondary containment.

AND

A.2.3 - Immediately initiate action to suspend operations with a potential for draining the reactor vessel.

AND CPS OPS ILT EXAM Page: 64 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version

A.2.4 - Immediately initiate action to restore required divisional inverters OPERABLE status.

A is incorrect but plausible - the Div 1 NSPS inverter is INOPERABLE when powered from its alternate AC source which is unlike the RPS inverters which are NOT rendered inoperable by a transfer to the alternate source.

C is incorrect but plausible - this is the required action for ITS 3.8.7 - Inverters Operating.

D is incorrect but plausible - this is the required action for an inoperable NSPS Distribution Subsystem (ITS 3.8.10). Per B3.8.10, operability of the distribution system is maintained by keeping the distribution system energized at proper voltages, therefore ITS 3.8.10 is met and this action is not required.

KA justification - this question meets the KA because the examinee is required to determine how a transfer of the Div 1 NSPS Inverter affects the ability to continue performing core alterations.

SRO only justification - although the required actions are < 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months actions, the determination of operability comes from the ITS Bases, and is therefore SRO only knowledge. Linked to 10CFR55.43(b)(2) Facility operating limitations in the technical specifications and their bases.

CPS OPS ILT EXAM Page: 65 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Question 14 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 1 Difficulty: 0.00 System ID: 896380 User-Defined ID: CL-ILT-887275 Cross Reference Number:

Plant conditions are as follows: Core alterations are in Topic:

progress. Division 2 NSPS Inverter has b Num Field 1:

Num Field 2:

Text Field:

CPS OPS ILT EXAM Page: 66 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Comments: General Data Technical Reference with

ITS 3.8.8 & B3.8.8 Revision Number: Inverters - Shutdown

CPS 5002.04 (4N) Rev.

33b

CPS 5002.05 (5N) Rev.

30d Justification for Non SRO CFR NA Link:

Question History: (i.e. LGS No previous NRC Exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, Bank - CL-ILT-0837 Bank, Modified)

Low KA Justification (if NA required):

Revision History: Revision Added answer plausibility, History: (i.e. Modified KA justification, and SRO distractor b to make only justification plausible based on OTPS statements. Revised the review) question stem and answers for plausibility.

ILT Supplied Ref (If appropriate): ITS 3.8.8 & 3.8.10 (i.e. ABN-##)

Excluded

Reference:

(i.e. ITS B3.8.8 & B3.8.10 Ensure ON-## not provided)

LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)

General Information Question Level (RO/SRO) SRO Station Clinton Cognitive Level Memory (1F)

KA Data KA Number / System Name: 262002 Uninterruptable Power Supply (A.C. /D.C.)

Category / KA Statement: 2.1.23 Ability to perform specific system and integrated plant procedures during all modes of plant operation. (CFR: 41.10 / 43.5 / 45.2 / 45.6)

RO Value: 4.3 SRO Value: 4.4 Tier: 2 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.10 10CFR55-43 (SRO) Data: 43.5 CPS OPS ILT EXAM Page: 67 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Associated objective(s):

Question 14 / 89 700004.12 Given NSPS System operability status OR key parameter indications, plant conditions, and a copy of Tech Specs, DETERMINE if Tech Spec Limiting Condition for Operations have been met, and required actions if any.

CPS OPS ILT EXAM Page: 68 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version 15 ID: 896381 Points: 1.00 The plant was operating at rated thermal power when a loss of DC MCC 1A occurred.

Which one of the following identifies the effect this will have on the RCIC system and what action is required to be taken per Tech Spec 3.5.3 RCIC System?

Under these conditions, the RCIC system is INOPERABLE _____(1)_____.

(2) In addition to restoring the RCIC System to OPERABLE status, what else does Technical Specifications REQUIRE?

A. (1) AND unavailable (2) perform CPS 9051.01 HPCS Pump & HPCS Water Leg Pump Operability B. (1) BUT available (2) perform CPS 9051.01 HPCS Pump & HPCS Water Leg Pump Operability C. (1) AND unavailable (2) perform an ESOMs log review for information concerning HPCS system operability.

D. (1) BUT available (2) perform an ESOMs log review for information concerning HPCS system operability.

Answer: C Answer Explanation C is correct:

Per WC-AA-101 On-Line Work Control Process and ER-AA-310 Implementation of the Maintenance Rule, the terms AVAILABLE and UNAVAILABLE are defined as follows:

Available - An SSC that is capable of performing its intended function(s). An SSC that can be restored to functional status within the timeframe associated with realistic conditions using proceduralized operator actions.

Unavailability - The condition where equipment is out-of-service (e.g. tagged out) for corrective or preventive maintenance, or can not perform its Maintenance Rule function.

A loss of DC MCC 1A renders the RCIC System unavailable because RCIC cannot perform its intended function within the timeframe associated with realistic conditions using proceduralized operator actions.

Per ITS B3.5.3, OPERABILITY of HPCS is therefore verified within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months when the RCIC System is inoperable. This may be performed as an administrative check, by examining logs or other information, to determine if the HPCS is out of service for maintenance or other reasons. Verification does not require performing the Surveillances needed to demonstrate the OPERABILITY of the HPCS System.

A is incorrect but plausible if the examinee determines that the HPCS system operability test is required to be performed to satisfy ITS 3.5.3 required action A.1.

B is incorrect but plausible if the examinee fails to recognize that RCIC is rendered unavailable by a loss of Div 1 DC power, and that the HPCS system operability test is required to be performed to satisfy ITS 3.5.3 required action A.1.

CPS OPS ILT EXAM Page: 69 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version D is incorrect but plausible if the examinee fails to recognize that RCIC is rendered unavailable by a loss of Div 1 DC power.

KA justification - this question meets the KA because the examinee is required to know the impact of a loss of DC power to the RCIC system in order to answer the question.

SRO only justification - the determination of SSC availability/unavailability is an SRO function at CPS and is supported by SRO only task 115112.01 Apply the administrative requirements of ON-LINE RISK ASSESSMENT. In addition the administrative actions required to verify HPCS system operability is contained in the Tech Spec Bases, which is SRO only knowledge. Linked to 10CFR55.43(b)(2) Facility operating limitations in the technical specifications and their bases.

CPS OPS ILT EXAM Page: 70 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Question 15 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 1 Difficulty: 0.00 System ID: 896381 User-Defined ID: CL-ILT-812664A Cross Reference Number:

The plant was operating at rated thermal power when a loss of Topic:

DC MCC 1A occurred. Which one of th Num Field 1:

Num Field 2:

Text Field:

CPS OPS ILT EXAM Page: 71 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Comments: General Data Technical Reference with

ITS 3.5.3 & B3.5.3 Revision Number:

CPS 4201.01C001 Rev. 1

WC-AA-101 Rev. 20 Justification for Non SRO CFR NA Link:

Question History: (i.e. LGS Modelled from Brunswick NRC-05, OYS CERT-04) 2008 NRC Exam (Q81)

Question Source: (i.e. New, Bank Bank, Modified)

Low KA Justification (if NA required):

Revision History: Revision Revised Brunswick 2008 History: (i.e. Modified NRC Exam Q81 for distractor b to make applicability to CPS.

plausible based on OTPS review)

ILT Supplied Ref (If appropriate): None (i.e. ABN-##)

Excluded

Reference:

(i.e. None Ensure ON-## not provided)

LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)

General Information Question Level (RO/SRO) SRO Station Clinton Cognitive Level Higher (2RI)

KA Data KA Number / System Name: 217000 Reactor Core Isolation Cooling System Category / KA Statement: A2. Ability to (a) predict the impacts of the following on the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: A2.05 D.C. power loss (CFR: 41.5 / 45.6)

RO Value: 3.3 SRO Value: 3.3 Tier: 2 RO Group: 1 SRO Group: 1 10CFR55-41 (RO) Data: 41.5 10CFR55-43 (SRO) Data: NA CPS OPS ILT EXAM Page: 72 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Associated objective(s):

Question 15 / 90 217000.14 Given REACTOR CORE ISOLATION COOLING (RI) System operability status and a copy of Tech Specs, DISCUSS the bases for the REACTOR CORE ISOLATION COOLING (RI) System Tech Spec LCO, related safety limits and Limiting Safety System Settings.

CPS OPS ILT EXAM Page: 73 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version 16 ID: 896382 Points: 1.00 The reactor was operating at 90% power with CPS 9031.10 RPS Main Steam Line Isolation Valve Channel Functional test in progress.

Testing was completed satisfactorily for 1B21-F022A, 22B, 22C, and 22D Main Steam Line A (B, C, D)

Inboard MSIVs.

Then, when the test pushbutton was depressed for 1B21-F028A Main Steam Line A Outboard MSIV, the following indications were observed:

'A' Main Steam Line Flow dropped from 3.00 mlbm/hr to 2.94 mllbm/hr.

Annunciator 5005-3C Div 1 or 4 MSIV CL Trip was received.

Computer Point B21NC047 Main Steam Line Isolation Valve Ch. A indicated tripped.

Red AND Green position indicating lights for 1B21-F028A were illuminated.

When the test pushbutton was released for 1B21-F028A Main Steam Line A Outboard MSIV, the following indications were observed:

'A' Main Steam Line Flow returned to 3.00 mlbm/hr.

Annunciator 5004-3C Div 1 or 4 MSIV CL Trip remained locked in.

Computer Point B21NC047 Main Steam Line Isolation Valve Ch. A indicates tripped.

Red position indicating lights for 1B21-F028A is illuminated.

Green position indicating lights for 1B21-F028A is extinguished.

Required notifications have been performed.

Given these conditions, which of the following actions is permitted / required?

(1) Complete testing of 1B21-F028B, 28C, and 28D by placing the Division 1 Sensor Bypass switch in BYPASS, performing the remainder of the test, and then returning the Division 1 Sensor Bypass switch to NORMAL.

(2) Declare 1B21-F028A INOPERABLE per ITS 3.6.1.3 Primary Containment Isolation Valves (PCIVS).

(3) Declare Post Accident Monitoring Instrumentation INOPERABLE for 1B21-F028A per ITS 3.3.3.1 PAM Instrumentation.

A. 1 ONLY B. 3 ONLY C. 1 AND 2 ONLY D. 2 AND 3 ONLY Answer: A Answer Explanation A is correct:

This question is based on CPS OPEX where the RPS trip annunciator and computer point failed to reset when the MSIV test pushbutton was released during performance of CPS 9031.10 RPS Main Steam Line Isolation Valve Channel Functional. Reference AR 1219006 and AR 814833814833

CPS OPS ILT EXAM Page: 74 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Limit switches mounted on each of the eight Main Steam Line Isolation Valves (MSIV) provide trip inputs to RPS. The switches on the inboard valves, 1B21-F022A(B/C/D), and the outboard valves, 1B21-F028A(B/C/D), are arranged so that closing of at least one valve in two or more lines will cause a scram.

During the test sequence described in the stem, the MSIV is partially stroked closed until the limit switches providing input to RPS are actuated.

Since the indications provided in the stem prove that 1), the MSIV actually stroked closed, 2) actuated the RPS logic, and 3) indicated properly, it can be concluded that the 28A is OPERABLE per ITS 3.3.1.1 RPS Instrumentation, 3.6.1.3 PCIVs, and 3.3.3.1 PAM Instrumentation. To complete surveillance 9031.10 however, the Div 1 Sensor Bypass Switch will have to be positioned to BYPASS as permitted by CPS 9031.10 step 5.5, to allow the surveillance to be completed without causing a scram when testing the remaining MSIVs.

B is incorrect but plausible - MSIV position indication is required to be operable per ITS 3.3.3.1 PAM Instrumentation. The examinee may select this response if he/she believes that failure of the RPS limit switch to reset constitutes inoperability of the PAM instrumentation for 28A.

C is incorrect but plausible - 1B21-F028A is a PCIV required to be operable per ITS 3.6.1.3. The examinee may select this response if he/she incorrectly believes that the indications provided in the stem require 1B21-F028A to be declared inoperable for containment isolation. Since 1B21-F028A did move when the valve was tested, nothing in the stem suggests that the valve cannot fulfill its containment isolation function.

D is incorrect but plausible if the examinee incorrectly believes that 1B21-F028A is inoperable for containment isolation and for PAM instrumentation functions.

KA justification - this question meets the KA because the examinee is required to predict the impact of MSIV closure on the Main Steam System and use the Main Steam procedure to mitigate the consequences.

SRO justification - linked to 10CFR55.43(b)(2) Facility operating limitations in the technical specifications and their bases and to SRO Only Task 140109.23 (Apply the administrative requirements for Execution of Technical Specifications or Off-Site Dose Calculation Manual Requirements).

CPS OPS ILT EXAM Page: 75 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Question 16 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 1 Difficulty: 0.00 System ID: 896382 User-Defined ID: CL-ILT-812665 Cross Reference Number:

The reactor was operating at 90% power with CPS 9031.10 Topic:

RPS Main Steam Line Isolation Valve Channe Num Field 1:

Num Field 2:

Text Field:

CPS OPS ILT EXAM Page: 76 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Comments: General Data Technical Reference with

ITS 3.3.1.1 Revision Number:

ITS 3.6.1.3

CPS 9031.10 Rev. 25c Justification for Non SRO CFR NA Link:

Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, New question Bank, Modified)

Low KA Justification (if NA required):

Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)

ILT Supplied Ref (If appropriate): None (i.e. ABN-##)

Excluded

Reference:

(i.e. None Ensure ON-## not provided)

LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)

General Information Question Level (RO/SRO) SRO Station Clinton Cognitive Level Higher (3SPK)

KA Data KA Number / System Name: 239001 Main and Reheat Steam System Category / KA Statement: A2. Ability to (a) predict the impacts of the following on the MAIN AND REHEAT STEAM SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: A2.03 MSIV closure (CFR: 41.5 / 45.6)

RO Value: 4.0 SRO Value: 4.2 Tier: 2 RO Group: 2 SRO Group: 2 10CFR55-41 (RO) Data: 41.5 10CFR55-43 (SRO) Data: NA CPS OPS ILT EXAM Page: 77 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Associated objective(s):

Question 16 / 91 239001.14 Given MAIN STEAM System operability status and a copy of Tech Specs, DISCUSS the bases for the MAIN STEAM System Tech Spec LCO, related safety limits and Limiting Safety System Settings.

CPS OPS ILT EXAM Page: 78 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version 17 ID: 896383 Points: 1.00 Plant conditions are as follows:

Operating at 80% RTP

Reactor vessel pressure is 1000 psig

Control rod scram time testing was in progress per CPS 9813.01 CONTROL ROD SCRAM TIME TESTING, and is now complete.

Test results were as follows:

Control Rod Time (sec) to Notch Position Control Rod Time (sec) to Notch Position 13 (from 48) 13 (from 48) 12-33 1.41 32-53 2.10 12-17 1.49 36-45 1.42 16-53 1.42 40-33 1.53 16-25 1.41 40-25 1.46 24-49 1.48 44-41 1.46 24-41 1.43 48-25 1.53 24-29 1.42 52-17 1.48 24-13 1.43 Assuming that there are NO control rods stuck in the withdrawn position, what actions are required per Technical Specifications?

A. Fully insert 32-53 in 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months and disarm in 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

B. Declare ONLY 32-53 "slow". NO further LCO actions are required.

C. Declare all tested control rods "slow". Be in Mode 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

D. Declare ONLY 12-17, 24-49, 32-53, 40-33, 48-25, and 52-17 "slow"; NO further LCO CPS OPS ILT EXAM Page: 79 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version actions are required.

Answer: D Answer Explanation D is correct - per ITS Table 3.1.4-1 note (c), with reactor steam dome pressure at 1000 psig, the scram time criteria to notch position 13 is interpolated at < 1.465 seconds (1.40 + 1.53) / 2.

Since 6 control rods exceed this value (12-17, 24-49, 32-53, 40-33, 48-25, and 52-17), per Note 1 these OPERABLE control rods are considered "slow". Per LCO 3.1.4 a. No more than 10 OPERABLE control rods shall be "slow", and no OPERABLE control rod that is "slow" shall occupy a location adjacent to another OPERABLE control rod that is "slow" or a withdrawn control rod that is stuck.

Since 6 control rods are "slow" and none are adjacent, no further LCO actions are required.

A is incorrect but plausible if the examinee incorrectly determines that rod 32-53 is inoperable and enters LCO 3.1.3 C.1 and C.2.

B is incorrect but plausible if the examinee fails to interpolate scram time critera per table 3.1.4-1 note C and determines the maximum scram time limit is 1.53 seconds.

C is incorrect but plausible if the examinee fails to interpolate scram time critera per table 3.1.4-1 note C and determines the maximum scram time limit is 1.40 seconds.

KA justification - this question meets the KA because the examinee must have knowledge of the scram time limits for the Control Rod Drive Hydraulic System in technical specifications to answer this question.

SRO only justification - linked to 10CFR55.43(b)(2) Facility operating limitations in the technical specifications and their bases.

CPS OPS ILT EXAM Page: 80 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Question 17 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 1 Difficulty: 0.00 System ID: 896383 User-Defined ID: CL-ILT-887276A Cross Reference Number:

Plant conditions are as follows: Operating at 80% RTP Reactor Topic:

vessel pressure is 1000 psig Contro Num Field 1:

Num Field 2:

Text Field:

CPS OPS ILT EXAM Page: 81 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Comments: General Data Technical Reference with ITS 3.1.4 and Table 3.1.4-1 Revision Number:

Justification for Non SRO CFR NA Link:

Question History: (i.e. LGS No previous NRC exam NRC-05, OYS CERT-04) usage Question Source: (i.e. New, Bank - modelled from CL-Bank, Modified) ILT-0315 Low KA Justification (if NA required):

Revision History: Revision Bank - added answer History: (i.e. Modified plausibility, KA justification, distractor b to make and SRO only justification plausible based on OTPS statements. Changed review) scram times for each control rod from CL-ILT-0315.

ILT Supplied Ref (If appropriate): ITS 3.1.3 & 3.1.4 (i.e. ABN-##)

Excluded

Reference:

(i.e. None Ensure ON-## not provided)

LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)

General Information Question Level (RO/SRO) SRO Station Clinton Cognitive Level Higher (3SPR)

KA Data KA Number / System Name: 201001 Control Rod Drive Hydraulic System Category / KA Statement: 2.2.38 Knowledge of conditions and limitations in the facility license. (CFR: 41.7 / 41.10 /

43.1 / 45.13)

RO Value: 3.6 SRO Value: 4.5 Tier: 2 RO Group: 2 SRO Group: 2 10CFR55-41 (RO) Data: 41.10 10CFR55-43 (SRO) Data: 43.1 CPS OPS ILT EXAM Page: 82 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Associated objective(s):

Question 17 / 92 201001.12 Given Control Rod Drive Hydraulic System operability status OR key parameter indications, plant conditions, and a copy of Tech Specs, DETERMINE if Tech Spec Limiting Condition for Operations have been met, and required actions if any.

CPS OPS ILT EXAM Page: 83 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version 18 ID: 896384 Points: 1.00 The plant is in Mode 5 performing core alterations.

Fuel bundle 22-49 is scheduled to be moved from the core to the spent fuel pool. The following sequence of events occurred:

Grapple was lowered over the bail handle for fuel bundle 22-49 and engaged.

Grapple Engaged light was verified to be LIT.

Mast could NOT be rotated.

Upon lifting fuel bundle 22-49, the SLACK CABLE light cleared, but the HOIST LOADED light remained out.

Under these conditions:

(1) Describe the effect, if any, on the refueling interlocks.

(2) Describe the actions the Refueling SRO must direct.

A. (1) Fuel bundle lifting is restricted by system interlocks.

(2) Place fuel bridge in Computer (PLC) Override mode.

B. (1) Fuel bundle lifting is restricted by system interlocks.

(2) Use Jog Up pushbutton until Grapple Normal Up light is lit.

C. (1) Further lifting of the fuel bundle is NOT restricted by system interlocks.

(2) Return fuel bundle 22-49 to full down.

D. (1) Further lifting of the fuel bundle is NOT restricted by system interlocks.

(2) Place fuel bundle 22-49 in the upper upender and initiate an Action Request (AR).

Answer: C Answer Explanation C is correct - Main Hoist loaded light provides input to Rod Block Interlock #1 and #2 circuitry, which prevents control rod withdrawal when the refueling bridge is over the core and loaded. The hoist loaded interlock does not prevent the mast from being raised or the bridge from being moved. The hoist loaded interlock is verified during performance of CPS 9090.01 Refueling Interlocks Operability Test /

One Rod Out Interlock Operability.

Per CPS 3703.01 Core Alterations limitation 6.26, upon loss of refuel bridge operability, place the load in a safe condition and discontinue use of the refuel bridge for handling of fuel bundles or control rods within the RPV.

Per CPS 3703.01 Core Alterations precaution 4.29, if normal refuel bridge (F15) operation is impaired due to equipment failure or plant conditions, then the Fuel Handling Supervisor - SRO shall: 1) Place the fuel in a safe condition, 2) Immediately inform the MCR of unexpected or unplanned fuel handling issues.

A is incorrect but plausible if the examinee fails to correctly recall the function of the Hoist Loaded interlock, and also incorrectly determines Computer (PLC) Override can be used when moving fuel. CPS 3703.01 limitation 6.25.2 expressly prohibits moving fuel with the F15 Bridge when in Computer Override.

B is incorrect but plausible if the examinee fails to correctly recall the function of the Hoist Loaded interlock, and also incorrectly determines that the jog button can be used in this condition. There are no provisions in CPS 3703.01 for performing this action.

CPS OPS ILT EXAM Page: 84 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version D is incorrect but plausible if the examinee fails to recognize the required actions if refuel bridge operability is lost.

KA justification - this question meets the KA because the loss of the hoist loaded interlock affects the function of the one-rod-out interlock which prevents rod withdrawal when the hoist is loaded. The examinee is required to predict the impact of a failure of the hoist loaded interlock, and based on that prediction determine required action to mitigate the failure.

SRO justification - linked to SRO only task 999999.12 (Direct Refueling Activities as the Refueling Supervisor) and 10CFR55.43(b)(7) Fuel handling facilities and procedures.

CPS OPS ILT EXAM Page: 85 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Question 18 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 2 Difficulty: 3.00 System ID: 896384 User-Defined ID: CL-ILT-887277 Cross Reference Number:

The plant is in Mode 5 performing core alterations. Fuel Topic:

bundle 22-49 is scheduled to be moved Num Field 1:

Num Field 2:

Text Field:

CPS OPS ILT EXAM Page: 86 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Comments: General Data Technical Reference with CPS 3703.01 Rev. 27 Revision Number:

Justification for Non SRO CFR NA Link:

Question History: (i.e. LGS Fitzpatrick 2008 NRC Exam NRC-05, OYS CERT-04)

Question Source: (i.e. New, Bank Bank, Modified)

Low KA Justification (if NA required):

Revision History: Revision Converted Fitzpatrick 2008 History: (i.e. Modified NRC EXAM Q93 for distractor b to make application at CPS.

plausible based on OTPS review)

ILT Supplied Ref (If appropriate): None (i.e. ABN-##)

Excluded

Reference:

(i.e. None Ensure ON-## not provided)

LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)

General Information Question Level (RO/SRO) SRO Station Clinton Cognitive Level Higher (3SPK)

KA Data KA Number / System Name: 234000 Fuel Handling Category / KA Statement: A2. Ability to (a) predict the impacts of the following on the FUEL HANDLING EQUIPMENT ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: A2.01 Interlock failure (CFR: 41.5 / 45.6)

RO Value: 3.3 SRO Value: 3.7 Tier: 2 RO Group: 2 SRO Group: 2 10CFR55-41 (RO) Data: 41.5 10CFR55-43 (SRO) Data: NA CPS OPS ILT EXAM Page: 87 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Associated objective(s):

Question 18 / 93 LP86614.01.08 Describe the operations, automatic functions and/or interlocks of the following:

.01 IFTS system

.02 IFTS winch

.03 IFTS upenders

.04 IFTS Flap Valve

.05 IFTS Bottom Valve

.06 IFTS Fill Valve

.07 IFTS Drain Valve

.08 Fuel Handling Platform (F11)

.09 Fuel Handling Platform (F11) Trolley

.10 Fuel Handling Platform (F11) Hoist

.11 Fuel Handling Platform (F11) Grapple

.12 Refuel Bridge (F15)

.13 Refuel Bridge (F15) Trolley

.14 Refuel Bridge (F15) Hoist

.15 Refuel Bridge (F15) Grapple

.16 IFTS Hydraulic Supplies

.17 Monorail Hoist

.18 Frame-mounted Hoist

.19 Underwater Television Camera System

.20 Refuel Mast Grapple Camera CPS OPS ILT EXAM Page: 88 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version 19 ID: 896385 Points: 1.00 Complete the following two statements regarding the interpretation and execution of the Emergency Operating Procedures (EOPs):

An ARROW pointing at a step in an EOP leg indicates that the crew _____(1)_____.

When executing a leg of the EOPs, all steps are _____(2)_____.

A. (1) has completed the referenced step (2) followed in order, even if an emergency depressurization parameter is exceeded further down the leg B. (1) has completed the referenced step (2) omitted up to the blowdown step if an emergency depressurization parameter is exceeded further down the leg C. (1) is maintaining or waiting for a specific plant condition (2) followed in order, even if an emergency depressurization parameter is exceeded further down the leg D. (1) is maintaining or waiting for a specific plant condition (2) omitted up to the blowdown step if an emergency depressurization parameter is exceeded further down the leg Answer: C Answer Explanation C is correct:

Per OP-CL-101-111-1001 Strategies For Successful Transient Mitigation:

Operators are expected to utilize the EOP marking standards IAW CPS 1005.09, Emergency Operating Procedure (EOP) And Severe Accident Guideline (SAG) Program.

When executing a leg of the EOPs, all steps should be followed in order to allow the use of all of the mitigating systems to be used and their effectiveness assessed, even if a blowdown parameter is exceeded further down in the leg.

Per 1005.09 Emergency Operating Procedure (EOP) and Severe Accident Guideline (SAG) Program step 8.13.4.5:

When actions have progressed to a point where the crew is maintaining or waiting for specific plant condition, an arrow should be used to mark their place.

A is incorrect but plausible because there is a marking standard to indicate a completed step (line through the step number).

B is incorrect but plausible because there is a marking standard to indicate a completed step (line through the step number) and if the examinee incorrectly recalls that EOP steps are required to be performed in order as described above.

D is incorrect if the examinee incorrectly recalls that EOP steps are required to be performed in order as described above.

CPS OPS ILT EXAM Page: 89 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version KA justification - this question meets the KA because it tests the interpretation and execution of EOP steps.

SRO only justification - linked to SRO only tasks 100509.06 (Execute EOP Overrides), 100509.07 (Execute EOP Decision Symbols), and 100509.08 (Execute and EOP Wait Symbol).

CPS OPS ILT EXAM Page: 90 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Question 19 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 1 Difficulty: 0.00 System ID: 896385 User-Defined ID: CL-ILT-812668 Cross Reference Number:

Complete the following two statements regarding the Topic:

interpretation and execution of the Emergency Num Field 1:

Num Field 2:

Text Field:

CPS OPS ILT EXAM Page: 91 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Comments: General Data Technical Reference with CPS 1005.09 Rev. 9a Revision Number: OP-CL-101-111-1001 Rev.

8 Justification for Non SRO CFR NA Link:

Question History: (i.e. LGS QC 2011 NRC Exam Q98 NRC-05, OYS CERT-04)

Question Source: (i.e. New, Bank Bank, Modified)

Low KA Justification (if NA required):

Revision History: Revision Converted QC 2011 NRC History: (i.e. Modified EXAM Q98 for application distractor b to make at CPS.

plausible based on OTPS review)

ILT Supplied Ref (If appropriate): None (i.e. ABN-##)

Excluded

Reference:

(i.e. None Ensure ON-## not provided)

LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)

General Information Question Level (RO/SRO) SRO Station Clinton Cognitive Level Memory (1F)

KA Data KA Number / System Name: NA Category / KA Statement: 2.1.20 Ability to interpret and execute procedure steps. (CFR: 41.10 / 43.5 / 45.12)

RO Value: 4.6 SRO Value: 4.6 Tier: 3 RO Group: NA SRO Group: NA 10CFR55-41 (RO) Data: 41.10 10CFR55-43 (SRO) Data: 43.5 CPS OPS ILT EXAM Page: 92 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Associated objective(s):

Question 19 / 94 LP87552.01.06 Given a set of EOP flowcharts, recall 4 of the rules for using the EOP flowcharts, in accordance with CPS No. 1005.09, EMERGENCY OPERATING PROCEDURE PROGRAM section 8.13 without error.

CPS OPS ILT EXAM Page: 93 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version 20 ID: 896386 Points: 1.00 The plant is operating at rated thermal power.

You are reviewing scheduled work for the following day. You notice a maintenance activity that requires removal of a system from service that will change on-line risk level to RED.

Under these conditions, which of the following is correct?

A. Removal of the system from service is NOT permitted.

B. The maintenance activity must be performed around the clock.

C. Protected equipment and pathways must be posted before maintenance may begin.

D. Maintenance may begin once all parts and materials are pre-staged at the work location.

Answer: A Answer Explanation A is correct - per WC-AA-101 On-Line Work Control Process Attachment 3 Configuration Risk Management Criteria, it is unacceptable to voluntarily enter red risk level.

B is incorrect but plausible - required if Yellow risk level is entered.

C & D are incorrect but plausible - required if Yellow or Orange risk levels are entered.

KA justification - this question meets the KA because the examinee must be knowledgeable of the process for managing maintenance activities to answer this question.

SRO only justification - supported by SRO only task 115112.01 (apply the administrative requirement of On-Line Risk Assessment) and 140109.10 (apply the administrative requirements of systems/equipment to be removed from service or found to be out of service).

CPS OPS ILT EXAM Page: 94 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Question 20 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 1 Difficulty: 0.00 System ID: 896386 User-Defined ID: CL-ILT-887432 Cross Reference Number:

The plant is operating at rated thermal power. You are Topic:

reviewing scheduled work for the followi Num Field 1:

Num Field 2:

Text Field:

CPS OPS ILT EXAM Page: 95 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Comments: General Data Technical Reference with

WC-AA-101 Rev. 20 Revision Number:

Justification for Non SRO CFR NA Link:

Question History: (i.e. LGS OC 2010 NRC Exam NRC-05, OYS CERT-04)

Question Source: (i.e. New, Bank Bank, Modified)

Low KA Justification (if NA required):

Revision History: Revision Converted OC 2010 NRC History: (i.e. Modified EXAM Q20 (SRO) for distractor b to make application at CPS.

plausible based on OTPS review)

ILT Supplied Ref (If appropriate): None (i.e. ABN-##)

Excluded

Reference:

(i.e. None Ensure ON-## not provided)

LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)

General Information Question Level (RO/SRO) SRO Station Clinton Cognitive Level Memory (1P)

KA Data KA Number / System Name: NA Category / KA Statement: 2.2.17 Knowledge of the process for managing maintenance activities during power operations, such as risk assessments, work prioritization, and coordination with the transmission system operator.

(CFR: 41.10 / 43.5 / 45.13)

RO Value: 2.6 SRO Value: 3.8 Tier: 3 RO Group: NA SRO Group: NA 10CFR55-41 (RO) Data: 41.10 10CFR55-43 (SRO) Data: 43.5 CPS OPS ILT EXAM Page: 96 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Associated objective(s):

Question 20 / 95 LP85802.2.2.17 Knowledge of the process for managing maintenance activities during power operations, such as risk assessments, work prioritization, and coordination with the transmission system operator.

CPS OPS ILT EXAM Page: 97 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version 21 ID: 896387 Points: 1.00 The plant was operating at rated thermal power when the following sequence of events occurred:

Date Time Event Actions Taken 1/1/2013 0800 VC 'A' was removed from service for Entered LCO 3.7.3 A.1 Restore Control maintenance. Room Ventilation subsystem to OPERABLE status within 7 days.

1/3/2013 0800 VC 'B' Supply Fan (0VC03CB) tripped. Entered LCO 3.7.3 F.1 Be in MODE 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

1/3/2013 1000 VC 'B' was restored to service. Div 2 VC was declared OPERABLE.

Given the current time is 1/3/2013 at 1000, the Main Control Room Ventilation System 'A' must be restored to OPERABLE status by...

A. 1/8/13 0800 B. 1/9/13 0800 C. 1/10/13 0800 D. 1/10/13 1000 Answer: A Answer Explanation A is correct:

Per ITS 1.3 Completion Times, once a condition has been entered, subsequent divisions, subsystems, components, or variables expressed in the Condition, discovered to be inoperable within limits, will not result in separate entry into the Condition unless specifically stated. The Required Actions of the Condition continue to apply to each additional failure, with Completion Times based on initial entry into the Condition.

For ITS 3.7.3 Control Room Ventilation System, separate condition entry is not specified. Condition A is entered at 1/1/13 at 0800 when VC Train A was removed from service and continued when VC 'B' Supply fan tripped. Therefore, VC 'A' must be restored to OPERABLE status on 1/8/13 0800 (7 days from the time Condition A was entered).

B is incorrect but plausible - the examinee may select this choice if he/she incorrectly applies the completion time extension of ITS 1.3. Since VC 'B' was restored to OPERABLE status before VC 'A', the completion time extension of ITS 1.3 is not allowed.

C is incorrect but plausible - the examinee may select this choice if he/she incorrectly believes the 7 day LCO for VC 'A' begins when VC 'B' was declared inoperable. 1/3/13 0800 + 7 days = 1/10/13 0800.

D is incorrect but plausible - the examinee may select this choice if he/she incorrectly believes the 7 day LCO for VC 'A' restarts when VC 'B' was declared operable. 1/3/13 1000 + 7 days = 1/10/13 1000.

KA justification - this question meets the KA because the examinee has to determine how to track the LCOs for a system with multiple divisional subsystems with concurrent inoperabilities.

CPS OPS ILT EXAM Page: 98 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version SRO justification - this question is SRO only because use and application of Technical Specifications is an SRO only function at CPS and is supported by SRO only task . It is also linked to 10CFR55.43(b)(2)

Facility operating limitations in the technical specifications and their bases.

CPS OPS ILT EXAM Page: 99 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Question 21 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 1 Difficulty: 0.00 System ID: 896387 User-Defined ID: CL-ILT-890544A Cross Reference Number:

The plant was operating at rated thermal power when the Topic:

following sequence of events occurred: Da Num Field 1:

Num Field 2:

Text Field:

CPS OPS ILT EXAM Page: 100 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Comments: General Data Technical Reference with

ITS 1.3 Revision Number:

Justification for Non SRO CFR NA Link:

Question History: (i.e. LGS No NRC Exam Usage NRC-05, OYS CERT-04)

Question Source: (i.e. New, New Bank, Modified)

Low KA Justification (if NA required):

Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)

ILT Supplied Ref (If appropriate): ITS 3.7.3 (i.e. ABN-##)

Excluded

Reference:

(i.e. ITS 1.3 Ensure ON-## not provided)

LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)

General Information Question Level (RO/SRO) SRO Station Clinton Cognitive Level Higher (3-SPR/K)

KA Data KA Number / System Name: NA Category / KA Statement: 2.2.23 Ability to track Technical Specification limiting conditions for operations. (CFR: 41.10 /

43.2 / 45.13)

RO Value: 3.1 SRO Value: 4.6 Tier: 3 RO Group: NA SRO Group: NA 10CFR55-41 (RO) Data: 41.10 10CFR55-43 (SRO) Data: 43.2 Associated objective(s):

Question 21 / 96 LP85802.2.2.23 Ability to track Technical Specification limiting conditions for operations.

CPS OPS ILT EXAM Page: 101 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version CPS OPS ILT EXAM Page: 102 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version 22 ID: 896388 Points: 1.00 Current plant conditions require venting the Primary Containment to stay below Figure D Primary Containment Pressure Limit (PCPL).

The Station Emergency Director (SED) has authorized exceeding release rate limits.

Given these conditions, 1) which containment venting path is preferred to be used, and 2) how low should containment pressure be lowered?

Vent the containment using the...

A. Hydrogen Purge Supply Path until containment pressure is restored to the normal range.

B. Hydrogen Purge Supply Path just long enough to maintain containment pressure below PCPL.

C. CCP Supply Path Modification until containment pressure is restored to the normal range.

D. CCP Supply Path Modification just long enough to maintain containment pressure below PCPL.

Answer: B Answer Explanation B is correct:

Per CPS 4411.06 Emergency Containment Venting, Purging, and Vacuum Relief discussion item 4.2:

"Once successfully venting, the amount vented should be minimized, if possible, to limit radioactivity releases and to prevent CNMT pressure from going negative due to temperature dropping or other reasons."

Per 4411.06 Table A Vent and Purge Paths, the "Vent Using CCP Supply Path Modification" is used only as a last resort because the release path is not monitored or filtered.

A is incorrect but plausible if the examinee incorrectly recalls the venting strategy listed above.

C and D are incorrect but plausible if the examinee incorrectly recalls the advantages and disadvantages of the two flowpaths listed from Table A of 4411.06.

KA justification - this question meets the KA because the examinee is required to recall containment venting strategies that are employed to control radiation releases.

SRO only justification - linked to SRO Only task 440201.15 (Determine when to exceed release limits when executing EOPs) and 10CFR55.43(b)(4) Radiation hazards that may arise during normal and abnormal situations, including maintenance activities and various contamination conditions.

CPS OPS ILT EXAM Page: 103 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Question 22 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 2 Difficulty: 0.00 System ID: 896388 User-Defined ID: CL-ILT-812671 Cross Reference Number:

Current plant conditions require venting the Primary Topic:

Containment to stay below Figure D Primary Co Num Field 1:

Num Field 2:

Text Field:

CPS OPS ILT EXAM Page: 104 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Comments: General Data Technical Reference with CPS 4411.06 Rev. 6 Revision Number:

Justification for Non SRO CFR NA Link:

Question History: (i.e. LGS 2011 QDC NRC Exam NRC-05, OYS CERT-04)

Question Source: (i.e. New, Bank Bank, Modified)

Low KA Justification (if NA required):

Revision History: Revision Converted QC 2011 NRC History: (i.e. Modified EXAM Q96 for application distractor b to make at CPS.

plausible based on OTPS review)

ILT Supplied Ref (If appropriate): None (i.e. ABN-##)

Excluded

Reference:

(i.e. None Ensure ON-## not provided)

LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)

General Information Question Level (RO/SRO) SRO Station Clinton Cognitive Level Memory (1F)

KA Data KA Number / System Name: NA Category / KA Statement: 2.3.11 Ability to control radiation releases. (CFR: 41.11 / 43.4 / 45.10)

RO Value: 3.8 SRO Value: 4.3 Tier: 3 RO Group: NA SRO Group: NA 10CFR55-41 (RO) Data: 41.11 10CFR55-43 (SRO) Data: 43.4 CPS OPS ILT EXAM Page: 105 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Associated objective(s):

Question 22 / 97 LP87558.01.08 Given a diagram of EOP-6, explain the use and/or function of the following inserts:

.01 Detail A, RPV Water Level Instruments

.02 Detail Z, NPSH/Vortex Limits

.03 Figure B, RPV Saturation Temperature

.04 Figure C, Minimum Usable Levels

.05 Figure D, Primary Containment Pressure Limit

.06 Figure N, Pressure Suppression Pressure

.07 Figure O, Containment Spray Initiation Limit

.08 Figure P, Heat Capacity Limit

.09 Figure Q, SRV Tail Pipe Limit CPS OPS ILT EXAM Page: 106 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version 23 ID: 896389 Points: 1.00 In order to maintain an ACTIVE status, a Senior Reactor Operator (NOT qualified as a Shift Manager) must actively stand watch as the _____(1)_____ for a MINIMUM of _____(2)_____ hours per calendar quarter.

A. (1) Control Room Supervisor (CRS) ONLY (2) 56 B. (1) Control Room Supervisor (CRS) ONLY (2) 40 C. (1) Control Room Supervisor (CRS) OR Work Execution Coordinator (WEC)

(2) 56 D. (1) Control Room Supervisor (CRS) OR Work Execution Coordinator (WEC)

(2) 40 Answer: A Answer Explanation A is correct - per OP-AA-105-102:

4.1.1. MAINTAIN an active license by actively performing the functions of RO, SRO, or SROL.

2. SRO licenses by performing the duties of Shift Manager or Unit Supervisor for a minimum of seven 8-hour or five 12-hour shifts per calendar quarter, including turnover to the next shift.

B is incorrect but plausible if the examinee fails to recall the minimum number of hours required to maintain active status. To reactivate an RO or SRO license to an "active status" 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months of shift functions in the presence and under the sore direct supervision of an active RO or SRO must be performed.

C is incorrect but plausible if the examinee fails to recall that WEC watches do not count for active license maintenance purposes.

D is incorrect but plausible if the examinee fails to recall that WEC watches do not count for active license maintenance purposes and the minimum number of hours required to maintain active status. To reactivate an RO or SRO license to an "active status" 40 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months of shift functions in the presence and under the sore direct supervision of an active RO or SRO must be performed.

KA justification - this question meets the KA because the examinee is required to be knowledgeable of the requirements for maintaining an active license in order to answer the question.

SRO only justification - knowledge of the requirements for maintaining an active SRO license is SRO only knowledge.

CPS OPS ILT EXAM Page: 107 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Question 23 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 1 Difficulty: 0.00 System ID: 896389 User-Defined ID: CL-ILT-887293 Cross Reference Number:

In order to maintain an ACTIVE status, a Senior Reactor Topic:

Operator (NOT qualified as a Shift Manager Num Field 1:

Num Field 2:

Text Field:

CPS OPS ILT EXAM Page: 108 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Comments: General Data Technical Reference with OP-AA-105-102 Rev. 9 Revision Number:

Justification for Non SRO CFR NA Link:

Question History: (i.e. LGS No NRC Exam usage NRC-05, OYS CERT-04)

Question Source: (i.e. New, Modified from CL-ILT-6131 Bank, Modified)

Low KA Justification (if NA required):

Revision History: Revision Modified from CL-ILT-6131 History: (i.e. Modified to convert question to an distractor b to make "SRO Only" question plausible based on OTPS review)

ILT Supplied Ref (If appropriate): None (i.e. ABN-##)

Excluded

Reference:

(i.e. None Ensure ON-## not provided)

LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)

General Information Question Level (RO/SRO) SRO Station Clinton Cognitive Level Memory (1F)

KA Data KA Number / System Name: NA Category / KA Statement: 2.1.4 Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, no-solo operation, maintenance of active license status, 10CFR55, etc. (CFR:

41.10 / 43.2)

RO Value: 3.3 SRO Value: 3.8 Tier: 3 RO Group: NA SRO Group: NA 10CFR55-41 (RO) Data: 41.10 10CFR55-43 (SRO) Data: 43.2 CPS OPS ILT EXAM Page: 109 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Associated objective(s):

Question 23 / 98 LP85801.2.1.4 Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, no solo operation, maintenance of active license status, 10CFR55, etc.

CPS OPS ILT EXAM Page: 110 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version 24 ID: 896390 Points: 1.00 A plant startup is in progress. Reactor power is at 16%.

GCB 4506 has just been closed and the Load Selector adjusted until Load Set indicated 500 MWe.

The 'A' RO reports #1 Turbine Bypass Valve at 50% open.

Given these conditions:

(1) Should annunciator 5006-5M Bypass Valve Open Check LPSP be alarming?

(2) Has the Rod Pattern Controller operability status changed?

A. (1) no (2) no B. (1) no (2) yes C. (1) yes (2) no D. (1) yes (2) yes Answer: C Answer Explanation C is correct:

Annunciator 5006.05 (5M) Bypass Valve Open Check LPSP alarms when any bypass valve is open >

1.0% with APRM power > 14%, therefore annunciator 5006-5M should be in alarm.

Per ITS Table 3.3.2.1-1, the Rod Pattern Controller is required to be operable with thermal power 16.7% RTP. With the Bypass Valve open, Turbine First Stage pressure will be lower which will cause the RPC to enforce pattern constraints longer than is required (conservative). Therefore, the RPC was operable before the event, and remains operable after the event.

A is incorrect but plausible if the examinee incorrectly recalls the setpoint for annunciator 5006-5M.

B is incorrect but plausible if the examinee incorrectly recalls the setpoint for annunciator 5006-5M and incorrectly recalls the impact of an open bypass valve on the operability of the RPC.

C is incorrect but plausible if the examinee incorrectly recalls the impact of an open bypass valve on the operability of the RPC.

KA justification - this question meets the KA because the examinee is required to determine that 5006-5M should be in alarm based on the conditions provided in the stem.

SRO only justification - part 1 of this question can be answered using RO level knowledge. Part 2 can only be answered by knowing the content of ITS Table 3.3.2.1-1 which is SRO only knowledge and is linked to 10CFR55.43(b)(2) Facility operating limitations in the technical specifications and their bases.

CPS OPS ILT EXAM Page: 111 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Question 24 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 2 Difficulty: 0.00 System ID: 896390 User-Defined ID: CL-ILT-887295A Cross Reference Number:

A plant startup is in progress. Reactor power is at 16%. GCB Topic:

4506 has just been closed and the L Num Field 1:

Num Field 2:

Text Field:

CPS OPS ILT EXAM Page: 112 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Comments: General Data Technical Reference with

CPS 5006.05 (5M) Rev.

Revision Number: 32d

ITS 3.3.2.1 Justification for Non SRO CFR NA Link:

Question History: (i.e. LGS No previous NRC Exam NRC-05, OYS CERT-04) usage.

Question Source: (i.e. New, New question Bank, Modified)

Low KA Justification (if NA required):

Revision History: Revision New question.

History: (i.e. Modified distractor b to make plausible based on OTPS review)

ILT Supplied Ref (If appropriate): None (i.e. ABN-##)

Excluded

Reference:

(i.e. 5006-5M Ensure ON-## not provided)

LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)

General Information Question Level (RO/SRO) SRO Station Clinton Cognitive Level Higher (3-SPK)

KA Data KA Number / System Name: NA Category / KA Statement: 2.4.46 Ability to verify that the alarms are consistent with the plant conditions. (CFR: 41.10 /

43.5 / 45.3 / 45.12)

RO Value: 4.2 SRO Value: 4.2 Tier: 3 RO Group: NA SRO Group: NA 10CFR55-41 (RO) Data: 41.10 10CFR55-43 (SRO) Data: 43.5 CPS OPS ILT EXAM Page: 113 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Associated objective(s):

Question 24 / 99 LP85804.2.4.46 Ability to verify that the alarms are consistent with the plant conditions.

CPS OPS ILT EXAM Page: 114 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version 25 ID: 896391 Points: 1.00 An ATWS has occurred. Current plant conditions are as follows:

EOP-1A ATWS RPV Control has been entered.

The plant is at 35% power

Multiple SRVs are open controlling pressure on Low-Low Set.

Reactor Water Level is cycling between -20 and +30 inches.

Suppression Pool Temperature is 111°F.

Under these conditions, the level control band is selected to _____(1)_____.

The bases for these actions is to _____(2)_____.

A. (1) reduce subcooling (2) reduce the potential for core instabilities B. (1) reduce subcooling (2) reduce the rate of heat addition to the suppression pool C. (1) reduce reactor power (2) reduce the potential for core instabilities D. (1) reduce reactor power (2) reduce the rate of heat addition to the suppression pool Answer: D Answer Explanation D is correct:

With the conditions provided in the stem, RPV water level should be lowered to reduce reactor power (Level Band C) of EOP-1A level leg. Per the EOP Tech Bases, lowering RPV water level minimizes reactor power and the rate of heat addition to the suppression pool, thereby prolonging the time to reach the Heat Capacity Limit.

A is incorrect but plausible if the examinee incorrectly determines the incorrect level control strategy.

B is incorrect but plausible if the examinee incorrectly determines the incorrect level control strategy and the bases.

C is incorrect but plausible if the examinee incorrectly recalls the bases for lowering level to reduce power.

KA justification - this question meets the KA because it requires knowledge of the level reduction strategies contained in the EOP bases to answer the question.

SRO only justification - linked to SRO only task 440401.05 (Determine when to lower RPV level when executing EOP-1A) and 10CFR55.43(b)(5) Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations.

CPS OPS ILT EXAM Page: 115 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Question 25 Info Question Type: Multiple Choice Status: Active Always select on test? No Authorized for practice? No Points: 1.00 Time to Complete: 1 Difficulty: 0.00 System ID: 896391 User-Defined ID: CL-ILT-887321A Cross Reference Number:

An ATWS has occurred. Current plant conditions are as Topic:

follows: EOP-1A ATWS RPV Control has been Num Field 1:

Num Field 2:

Text Field:

CPS OPS ILT EXAM Page: 116 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Comments: General Data Technical Reference with

CPS 4404.01 Rev. 29 Revision Number:

EOP Tech Bases (pg.

5-18) Rev. 6 Justification for Non SRO CFR NA Link:

Question History: (i.e. LGS No NRC Exam usage NRC-05, OYS CERT-04)

Question Source: (i.e. New, New Bank, Modified)

Low KA Justification (if NA required):

Revision History: Revision New question History: (i.e. Modified distractor b to make plausible based on OTPS review)

ILT Supplied Ref (If appropriate): None (i.e. ABN-##)

Excluded

Reference:

(i.e. EOP-1A Ensure ON-## not provided)

LORT PRA: (i.e. Yes or No or #) No LORT Question Section: (i.e, NA A-Systems or B-Procedures)

General Information Question Level (RO/SRO) SRO Station Clinton Cognitive Level Memory (1P)

KA Data KA Number / System Name: NA Category / KA Statement: 2.4.18 Knowledge of the specific bases for EOPs. (CFR: 41.10 / 43.1 / 45.13)

RO Value: 3.3 SRO Value: 4.0 Tier: 3 RO Group: NA SRO Group: NA 10CFR55-41 (RO) Data: 41.10 10CFR55-43 (SRO) Data: 43.1 CPS OPS ILT EXAM Page: 117 of 118 27 August 2013

EXAMINATION ANSWER KEY ILT 12-1 NRC SRO Written Exam - Final Version Associated objective(s):

Question 25 / 100 LP87553.01.12 Given a diagram of EOP-1A, appropriate EOP-support procedures, and simulated plant conditions determine which course of action should take priority over others:

.01 Establishing RPV water level in accordance with the Level Bands provided in the Level Path.

.02 Preventing LPCS/LPCI injection not needed for core cooling if drywell pressure is above 1.68 psig

.03 Defeating interlocks for inserting control rods using CPS No. 4411.08, ALTERNATE CONTROL ROD INSERTION

.04 Use of CPS No. 4100.01, REACTOR SCRAM vs. CPS No. 4411.08, ALTERNATE CONTROL ROD INSERTION, to insert control rods CPS OPS ILT EXAM Page: 118 of 118 27 August 2013

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