ML17165A477

302 Draft Administrative Documents

ML17165A477
Person / Time
Site:	Watts Bar
Issue date:	06/14/2017
From:	Tennessee Valley Authority
To:	NRC/RGN-II
References
50-390/13-302, 50-391/13-302 50-390/OL-13, 50-391/OL-13
Download: ML17165A477 (59)

Text

ES-301 Administrative Topics Outline Form ES-301-1 Reactor Operator

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Watts Bar Date of Examination: October 2013 Examination Level: RO SRO Operating Test Number: 302 Administrative Topic Type Describe activity to be performed (See Note) Code*

1. Perform Hand Calculation Of Boric Acid And Primary Water Integrator Settings For Manual Makeup To VCT.

Conduct of Operations M,R 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc. (3.9/4.2) (CFR: 41.10 /

43.5 / 45.12) l

2. Determine AFW Pump Requirements Conduct of Operations N,R 2.1.32 Ability to explain and apply system limits and precautions. 3.8/4.0 (CFR: 41.10 / 43.2 / 45.12)

3. Review 1-SI-0-4, Monthly Surveillances.

Equipment Control M,R 2.2.12 Knowledge of surveillance procedures.3.7/4.1 (CFR 41.10 / 45.13)

4. Calculate Stay Time For Emergency Exposure M,R 2.3.4 Knowledge of radiation exposure limits under Radiation Control normal or emergency conditions.3.2/3.7 (CFR:

41.12/43.4/45.10)

Emergency Procedures /

N/A N/A Plan NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

• Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (< 3 for ROs; < 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (> 1)

(P)revious 2 exams (< 1; randomly selected)

ES 301, Page 22 of 27

ES-301 Administrative Topics Outline Form ES-301-1 RO Admin JPM Summary 1 Task/KA/Safety Function:

PERFORM SOI-62.02, BORON CONCENTRATION CONTROL, APPENDIX C, CALCULATION OF BORIC ACID AND PRIMARY WATER INTEGRATOR SETTING FOR MANUAL MAKEUP TO VCT (RCS). / 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc. (3.9/4.2) (CFR 41.10 / 43.5 / 45.12)/ 2.1 Conduct of Operations.

Task Standard:

The applicant performs SOI-62.02, Boron Concentration Control, Appendix C, CALCULATION OF BORIC ACID AND PRIMARY WATER INTEGRATOR SETTING FOR MANUAL MAKEUP TO VCT (RCS), and calculates:

1.) The total VCT addition to be 367 +/- 1 gallon.

2.) The BA flow rate to be 10.60 gpm. (10.729 gpm is acceptable, if applicant elects to perform conservative calculation.)

3.) The amount of BA to be entered into the BA integrator to be 48 gallons +/- 1 gallon.

4.) The amount of PW to be entered into the PW integrator to be 318 gallons +/- 1 gallon.

Critical Steps:

CALCULATE total VCT addition volume needed for desired level. (Rounded to the nearest whole number.)

CALCULATE 1-FC-62-139, BA TO BLENDER FCV-62-140 CONTROL, flow setpoint.

CALCULATE TOTAL flow rate.

CALCULATE [Y] BA Fraction.

CALCULATE 1-FQ-62-139, BA BATCH COUNTER Setting.

CALCULATE [Z] PW Fraction.

CALCULATE 1-FQ-62-142, PW BATCH COUNTER Setting.

The applicant will perform actions of the following procedures:

SOI-62.02, Boron Concentration Control.

TI-59, Boron Tables.

2 Task/KA/Safety Function:

DETERMINE AFW PUMP REQUIREMENTS / 2.1.32 Ability to explain and apply system limits and precautions (3.8/4.0) (CFR 41.10/43.2/45.12) / 2.1 Conduct of Operations.

Task Standard:

The applicant determines:

1.) No starting limitations have been violated.

2.) 1B-B AFW pump may be restarted immediately, or at any time after 2125. The 1A-A AFW pump cannot be restarted on October 15, 2013.

3.) Determines that Electrical Maintenance (EM) must be notified to perform 2500-volt megger, bridge, and dc high-potential tests after the 1B-B AFW pump tripped by instantaneous overcurrent relay operation.

Critical Steps:

Applicant determines:

No starting limitations have been violated based on GOI-7, Generic Equipment Operating Guidelines.

1B-B MD AFW Pump may be started immediately, or at any time after 2125. The 1A-A MD AFW pump cannot be restarted on October 15, 2013.

Electrical Maintenance (EM)must be notified to perform 2500-volt megger, bridge, and dc high-potential tests after a 6,900-volt motor has been tripped by relay operation The applicant will perform actions of the following procedures:

GOI-7, Generic Equipment Operating Guidelines.

3 Task/KA/Safety Function:

REVIEW 1-SI-0-4, MONTHLY SURVEILLANCES. / 2.2.12 Knowledge of surveillance procedures. (3.7/4.1) (CFR 41.10/45.13) / 2.2 Equipment Control.

Task Standard:

The applicant reviews a completed 0-SI-4, Monthly Surveillance, and determines that the following 5 ITEMS are exceeding MCD limits OR have exceeded specified values:

1. ITEM 4: 1-PI-1-1C, SG 1 Press, is exceeding its MCD value.

2. ITEM 7: 1-PI-68-336C PZR PRESS is exceeding its MCD value.

3. ITEM 13: 1-TI-68-43C LOOP 3 HL TEMP is exceeding its MCD value.

4. ITEM 25: 1-FI-68-93C CHARGING FLOW is within its MCD value, but exceeding the 20 gpm limit of NOTE (32).

5. ITEM 29: 1-PI-62-81C LP LETDOWN PRESS is exceeding its MCD value.

The applicant indicates that the following actions are required (in no particular order) for each of the 5 items identified:

1. SM/Unit SRO must be notified of each item that exceeds limits.

2. A Work Order (WO) or Service Request (SR) must be prepared for each item that exceeds limits.

3. ITEM 25 requires a calibration of 1-FI-68-93C CHARGING FLOW.

Critical Steps:

ITEM 4: 1-PI-1-1C, SG 1 Press, is exceeding its MCD value.

ITEM 7: 1-PI-68-336C PZR PRESS is exceeding its MCD value.

ITEM 13: 1-TI-68-43C LOOP 3 HL TEMP is exceeding its MCD value.

ITEM 25: 1-FI-68-93C CHARGING FLOW is within its MCD value, but exceeding the 20 gpm limit of NOTE (32). Also requires calibration of the flow instrumentation.

ITEM 29: 1-PI-62-81C LP LETDOWN PRESS is exceeding its MCD value.

The applicant will perform actions of the following procedures:

1-SI-0-4, Monthly Surveillances.

4 Task/KA/Safety Function:

CALCULATE STAY TIME FOR EMERGENCY EXPOSURE / 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions. (3.2/3.7) (CFR 41.12/43.4/45.10) /

2.3 Radiation Control.

Task Standard:

The applicant:

1. Calculates the total dose received performing the assigned tasks to be 19.8 Rem TEDE and 180 REM to the hands. (Acceptable Range 19.6 - 19.8 TEDE , Hands 180 REM).

2. Determines the restrictions contained in EPIP-15, Emergency Exposure Guidelines, Section 3.1.4, Post Exposure Evaluations, are to be applied to the AB AUO.:

Critical Steps:

Calculates the total dose received performing the assigned tasks to be 19.8 Rem TEDE and 180 REM to the hands. (Acceptable Range 19.6 - 19.8 TEDE , Hands 180 REM).

Determines that personnel receiving emergency or accident exposures should be restricted from further occupational exposure pending the outcome of exposure evaluations and, if necessary, medical surveillance The applicant will perform actions of the following procedures:

EPIP-15, Emergency Exposure Guidelines.

5 Not Applicable

ES-301 Administrative Topics Outline Form ES-301-1 Senior Reactor Operator

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Watts Bar Date of Examination: October 2013 Examination Level: RO SRO Operating Test Number: 302 Administrative Topic Type Describe activity to be performed (See Note) Code*

1. Perform Hand Calculation Of Boric Acid And Primary Water Integrator Settings For Manual Makeup To VCT.

Conduct of Operations M,R 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc. (3.9/4.2) (CFR:

41.10 / 43.5 / 45.12) l

2. Determine AFW Pump Requirements.

Conduct of Operations N,R 2.1.32 Ability to explain and apply system limits and precautions. 3.8/4.0 (CFR: 41.10 / 43.2 / 45.12)

3. Determine Risk Level using EOOS Software.

2.2.14 Knowledge of the process for controlling Equipment Control M,R equipment configuration or status. 3.9/4.3 (CFR 41.10 / 43.3 / 45.13)

4. Determine Requirements for Authorizing Emergency Exposure.

Radiation Control M,R 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.3.2/3.7 (CFR:

41.12/43.4/45.10)

5. Classify an Event.

Emergency Procedures / 2.4.41 Knowledge of the emergency action level M,R Plan thresholds and classifications. 2.9/4.6 (CFR:

41.10 / 43.5 / 45.11)

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

• Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (< 3 for ROs; < 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (> 1)

(P)revious 2 exams (< 1; randomly selected)

ES 301, Page 22 of 27

ES-301 Administrative Topics Outline Form ES-301-1 SRO Admin JPM Summary 1 Task/KA/Safety Function:

PERFORM SOI-62.02, BORON CONCENTRATION CONTROL, APPENDIX C, CALCULATION OF BORIC ACID AND PRIMARY WATER INTEGRATOR SETTING FOR MANUAL MAKEUP TO VCT (RCS). / 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc. (3.9/4.2) (CFR 41.10 / 43.5 / 45.12)/ 2.1 Conduct of Operations.

Task Standard:

The applicant performs SOI-62.02, Boron Concentration Control, Appendix C, CALCULATION OF BORIC ACID AND PRIMARY WATER INTEGRATOR SETTING FOR MANUAL MAKEUP TO VCT (RCS), and calculates:

1.) The total VCT addition to be 367 +/- 1 gallon.

2.) The BA flow rate to be 10.60 gpm. (10.729 gpm is acceptable, if applicant elects to perform conservative calculation.)

3.) The amount of BA to be entered into the BA integrator to be 48 gallons +/- 1 gallon.

4.) The amount of PW to be entered into the PW integrator to be 318 gallons +/- 1 gallon.

Critical Steps:

CALCULATE total VCT addition volume needed for desired level. (Rounded to the nearest whole number.)

CALCULATE 1-FC-62-139, BA TO BLENDER FCV-62-140 CONTROL, flow setpoint.

CALCULATE TOTAL flow rate.

CALCULATE [Y] BA Fraction.

CALCULATE 1-FQ-62-139, BA BATCH COUNTER Setting.

CALCULATE [Z] PW Fraction.

CALCULATE 1-FQ-62-142, PW BATCH COUNTER Setting.

The applicant will perform actions of the following procedures:

SOI-62.02, Boron Concentration Control.

TI-59, Boron Tables.

2 Task/KA/Safety Function:

DETERMINE AFW PUMP REQUIREMENTS / 2.1.32 Ability to explain and apply system limits and precautions (3.8/4.0) (CFR 41.10/43.2/45.12) / 2.1 Conduct of Operations.

Task Standard:

The applicant determines:

1. NO motor start limitations have been violated based on the history provided

2. 1B-B AFW pump can be started at 2125 on October 15, 2013. The 1A-A AFW pump cannot be restarted on October 15, 2013.

3. Electrical Maintenance (EM) must be notified to perform 2500-volt megger, bridge, and dc high-potential tests after the 1B-B AFW pump tripped by instantaneous overcurrent relay operation.

4. LCO 3.7.5, Auxiliary Feedwater (AFW) System, Action B is applicable, and the 1B-B AFW pump must be declared INOPERABLE, and restored to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

Critical Steps:

Applicant determines that the 1B-B MD AFW Pump may be started immediately, or at 2125.

Applicant determines the 1A-A MD AFW pump cannot be restarted on October 15, 2013.

Applicant determines that Electrical Maintenance (EM) must be notified to perform 2500-volt megger, bridge, and dc high-potential tests after a 6,900-volt motor has been tripped by relay operation.

Applicant refers to LCO 3.7.5, and determines that CONDITION B applies The applicant will perform actions of the following procedures:

GOI-7, Generic Equipment Operating Guidelines.

LCO 3.7.5, Auxiliary Feedwater (AFW) System.

3. Task/KA/Safety Function:

DETERMINE RISK LEVEL, CDF AND LERF MULTIPLIERS USING EOOS SOFTWARE/2.2.14 Knowledge of the process for controlling equipment configuration or status. (3.9/4.3) (41.10/43.3/45.13) /2.2 Equipment Control.

Task Standard:

The applicant determines:

1. Removing the 1A-A Diesel Generator from service in the WBN EOOS program results in a CDF of 4.36, a LERF of 4.57, and RISK remains GREEN for CDF and LERF.

2. Removing the 2B-B ERCW Strainer from service in addition to the 1A-A Diesel Generator in the WBN EOOS program results in a CDF of 25.9, Risk changes to ORANGE, and the LERF changes to 8.1, and Risk changes to YELLOW.

Critical Steps:

Calculate Core Damage Frequency (CDF) and Large Early Release Frequency (LERF)

Multiplier for the unit configuration using EOOS (Calculate Risk Measure(s) Button) for the 1A-A Diesel Generator out of service. Removing the 1A-A Diesel Generator from service in the WBN EOOS program results in a CDF of 4.36, a LERF of 4.57, and RISK remains GREEN for CDF and LERF.

Calculate Core Damage Frequency (CDF) and Large Early Release Frequency (LERF)

Multiplier for the unit configuration using EOOS (Calculate Risk Measure(s) Button) for the 1A-A Diesel Generator and 2B-B ERCW Strainer out of service. Removing the 2B-B ERCW Strainer from service in addition to the 1A-A Diesel Generator in the WBN EOOS program results in a CDF of 25.9, Risk changes to ORANGE, and the LERF changes to 8.1, and Risk changes to YELLOW The applicant will perform actions of the following procedures/equipment:

NPG-SPP-09.11.1, Equipment Out of Service (EOOS) Management.

WBN EOOS Computer Program

4 Task/KA/Safety Function:

CALCULATE STAY TIME FOR EMERGENCY EXPOSURE / 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions. (3.2/3.7) (CFR 41.12/43.4/45.10) /

2.3 Radiation Control.

Task Standard:

The applicant determines:

1. The exposure expected to be received by the AB AUO during the completion of Tasks 1 through 3 to be 19.8 REM TEDE and 180 REM Extremities.

2. The Shift Manager as the SED must authorize the exposure in writing using EPIP-15, Emergency Exposure Guidelines, Appendix B, Authorization to Exceed Occupational Dose Limits Form.

3. Determines the restrictions contained in EPIP-15, Emergency Exposure Guidelines, Section 3.1.4, Post Exposure Evaluations, are to be applied to the AB AUO.

Critical Steps:

The exposure expected to be received by the AB AUO during the completion of Tasks 1 through 3.

Determine that the SITE EMERGENCY DIRECTOR is the ONLY person that can authorize the Emergency Exposure.

Determine the restrictions, if any, that are imposed on the AB AUO after receipt of the emergency exposure.

The applicant will perform actions of the following procedures:

EPIP-15, Emergency Exposure Guidelines.

5. Task/KA/Safety Function:

CLASSIFY THE EVENT. / 2.4.40 Knowledge of SRO responsibilities in emergency plan implementation.(2.5/3.3) (CFR 41.10 / 43.5 / 45.11) / 2.4 Emergency Procedures / Plan.

Task Standard:

The applicant :

1.) Within 15 minutes, classifies the event as a GENERAL EMERGENCY per EALs 1.1.2 Loss, 1.2.2, Potential Loss and 1.3.2 Loss.

2.) INITIATES EPIP-5, GENERAL EMERGENCY Appendix A, General Emergency Initial Notification Form, and completes:

a. Item 3. - EAL Designators - 1.1.2 Loss, 1.2.2, Potential Loss and 1.3.2 Loss.

b. Item 4. - Brief Description of the Event - Fuel Clad barrier breach, with a concurrent loss of coolant greater than the capacity of the CCP and indications of a LOCA Outside Containment. (Applicant description will vary)

c. Item 5. - Radiological Conditions - EITHER Minor releases within federally approved limits OR Release Information not known checked or otherwise indicated on form.

d, Item 6. - Time that applicant declared the event and the date.

e. Item 7. - Meteorological Conditions. Wind Speed and direction correctly entered. (15 mph and 125 degrees).

f. Item 8. - Recommendation 2 selected, and the proper area to be evacuated indicated on the form (110-170 degrees indicated).

3.) INITIATES EPIP-5, GENERAL EMERGENCY Appendix H, Initial - Protective Action Recommendations, and determines that RECOMMENDATION 2 is applicable, Critical Steps:

Within 15 minutes, classifies the event as a GENERAL EMERGENCY per EALs 1.1.2 Loss, 1.2.2, Potential Loss and 1.3.2 Loss.

INITIATES EPIP-5, GENERAL EMERGENCY Appendix A, General Emergency Initial Notification Form, and completes:

Item 3. - EAL Designators - 1.1.2 Loss, 1.2.2, Potential Loss and 1.3.2 Loss.

Item 4. - Brief Description of the Event - Fuel Clad barrier breach, with a concurrent loss of coolant greater than the capacity of the CCP and indications of a LOCA Outside Containment.

(Applicant description will vary)

Item 5. - Radiological Conditions - EITHER Minor releases within federally approved limits OR Release Information not known checked or otherwise indicated on form.

Item 6. - Time that applicant declared the event and the date.

Item 7. - Meteorological Conditions. Wind Speed and direction correctly entered. (15 mph and 125 degrees).

Item 8. - Recommendation 2 selected, and the proper area to be evacuated indicated on the form (110-170 degrees indicated).

INITIATES EPIP-5, GENERAL EMERGENCY Appendix H, Initial - Protective Action Recommendations, and determines that RECOMMENDATION 2 is applicable, The applicant will perform actions of the following procedures:

EPIP-1 Emergency Plan Classification Flowpath.

EPIP-5 General Emergency.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Reactor Operator

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Watts Bar Date of Examination: October 2013 Exam Level: RO SRO-I SRO-U Operating Test Number:302 Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety System / JPM Title Type Code*

Function A. Aux Feedwater LCV to Bypass Reg Transfer During Plant Startup. A,L,N 4S 059 A4.08 3.0/2.9 CFR 41.7/45.5 to 45.8 B Perform ES-1.3, Transfer to Containment Sump. A, EN, M 3 EA1.11 4.2/4.2 CFR 41.7/45.5 / 45.6 C. Return N43 Power Range To Service. M 7 015 A4.02 3.9/3.9 CFR 41.7 / 45.5 to 45.8 D. Perform a Manual Makeup to the VCT. A, M 2 004 A4.12 3.8/3.3 CFR 41.7 / 45.5 to 45.8 E. Transfer 1A RCP Board from Alternate to Normal. D 6 062 A4.01 3.3/3.1 CFR 41.4/45.5 to 45.8 F. Align 1B-B CCS Pump to 1B Supply Header. M 8 008 A4.01 3.3/3.1 CFR: 41.7 / 45.5 G. Complete 1-SI-85-2, Reactivity Control Systems Movable Control Assemblies (Modes 1 and 2). A, M 1 001 A4.03 4.0/3.7 CFR 41.7/45.5 to 45.8 H. Respond to RHR Pump Trip Per AOI-14. D 4P 025 AA1.09 3.1/3.2 CFR: 41.7 / 45.5 / 45.6 In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

I. Bypassing 1-PCV-62-81, CVCS LETDOWN HX PRESS CNTL, For Local Control D,E,R 2 004 A1.11 3.0/ 3.0 CFR 41.5/45.5 J. Local Restart of C&SS Air Compressors. A,D,E 8 065 AK3.08 3.7/3.9 CFR 41.5,41.10 / 45.6 / 45.13 K. Transfer 250v DC TURB BLDG DIST BD #1 from Normal to Alternate. D 6 063 A4.02 2.8/2.9 CFR 41.7

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

• Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank <9 / <8 / <4 (E)mergency or abnormal in-plant >1 / >1 / >1 (EN)gineered safety feature - / - / >1 (L)ow-Power / Shutdown >1 / >1 / >1 (N)ew or (M)odified from bank including 1(A) >2 / >2 / >1 (P)revious 2 exams <3 < 3 / < 2 (randomly selected)

(R)CA >1 / >1 / >1 (S)imulator

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Summary A. Task/KA/Safety Function:

TRANSFER FROM AUX FEEDWATER LCV TO BYPASS REG VALVE DURING STARTUP /

059 A4.08 Ability to manually operate and/or monitor in the control room: Feed regulating valve controller (3.0/2.9) CFR: 41.7/45.5 to 45.8/ Safety Function 4S Task Standard:

The applicant:

1.) Performs the actions required to transfer feedwater supply from 1-1-LIC-3-156A, SG 2 SUPPLY FRM PMP A-A to 1-LIC-3-103A, SG 4 MFW BYPASS REG CONTROL.

2.) Diagnoses the failure of 1-LCV-3-156A, SG 2 SUPPLY FRM PMP A-A OPEN and places 1-HS-3-118AAFW PMP A-A in STOP, PULL-TO-LOCK to terminate the overfill of SG 2.

Critical Steps:

PLACE SG 2 Bypass Reg Valve in MANUAL AND SLOWLY OPEN valve ENSURE 1-LIC-3-156A, SG 2 SUPPLY FRM PMP A-A closes as required to maintain SG 2 level on program.

Applicant locates 1-HS-3-118A, A-A MD AFWP, and rotates the handswitch to the LEFT to the STOP position. Applicant may pull the handswitch out to the STOP, PULL-TO-LOCK position.

Alternate Path:

During transfer from Auxiliary Feedwater to Main Feedwater level control, 1-LCV-3-156, SG 2 SUPPLY FRM PMP A-A fails OPEN, requiring the 1A-A MD AFW Pump to be stopped from the MCR.

List of Steps that Constitute an Alternate Path Applicant locates 1-HS-3-118A, A-A MD AFWP, and rotates the handswitch to the LEFT to the STOP position. Applicant may pull the handswitch out to the STOP, PULL-TO-LOCK position.

If similar to an event in the Dynamic Scenario, then an explanation of how it is different. Not applicable The applicant will perform actions of the following procedures:

SOI-3.02, Auxiliary Feedwater System."

Documentation justifying classification of Engineered Safety Function, when applicable:

Not Applicable

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 B. Task/KA/Safety Function ALIGN ECCS PUMPS BY PERFORMING ES-1.3, TRANSFER TO CONTAINMENT SUMP. /

EA1.11 Ability to operate and monitor the following as they apply to a Large Break LOCA:

Long-term core cooling (4.2/4.2) CFR 41.7 / 45.5 / 45.6 / Safety Function 3.

Task Standard:

Applicant performs aligns the ECCS pumps for containment sump recirculation using ES-1.3, Transfer to Containment Sump.

List of Critical Steps ENSURE cntmt sump valves 1-FCV-63-72 and 1-FCV-63-73 OPEN. IF ONE cntmt sump valve can NOT be fully opened, THEN STOP and PULL TO LOCK RHR pump on the associated train.

ISOLATE SI pump miniflow.

ISOLATE RHR crossties.

ALIGN charging pump and SI pump supply from RHR.

ISOLATE charging pump suction from RWST.

ISOLATE SI pump suction from RWST.

CLOSE 1-FCV-63-1.

Alternate Path:

During performance of ES-1.3, Transfer to Containment Sump, the applicant will be unable to fully open 1-FCV-63-73, requiring the 1B-B RHR Pump to be placed in STOP, PULL-TO-LOCK.

List of Steps that Constitute an Alternate Path ENSURE cntmt sump valves 1-FCV-63-72 and 1-FCV-63-73 OPEN.

IF ONE cntmt sump valve can NOT be fully opened, THEN STOP and PULL TO LOCK RHR pump on the associated train.

If similar to an event in the Dynamic Scenario, then an explanation of how it is different.

Scenario contains a loss of recirculation sump due to the failure of both RHR pumps, and an immediate transition from ES-1.3, Transfer to Containment Sump, Step 1 RNO to 1-ECA-1.1, Loss of RHR Sump Recirculation.

Procedure Name/Number and Section pertaining to the task.

ES-1.3, Transfer to Containment Sump.

Documentation justifying classification of Engineered Safety Function, when applicable:

Task is associated with ECCS alignment to establish long term core cooling.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 C. Task/KA/Safety Function RETURN N43 POWER RANGE TO SERVICE / 015 A4.02 Ability to manually operate and/or monitor in the control room: NIS indicators (3.9/3.9) CFR 41.7 / 45.5 to 45.8/

Safety Function 7 Task Standard:

The applicant :

1.) Returns the following switches from the N43 position to the NORMAL.

a. DETECTOR CURRENT COMPARATOR switch for UPPER SECTION

b. DETECTOR CURRENT COMPARATOR switch for LOWER SECTION.

c. COMPARATOR CHANNEL DEFEAT 2.) Returns the following switches from the N43 position to the OPERATE position:

a. ROD STOP BYPASS,

b. POWER MISMATCH BYPASS.

3.) Performs actions of SOI-98.01, DISTRIBUTED CONTROL SYSTEM, to RESTORE 1LPY0920412R from BYPASS to NORMAL.

List of Critical Steps 1.) Returns the following switches from the N43 position to the NORMAL.

a. DETECTOR CURRENT COMPARATOR switch for UPPER SECTION

b. DETECTOR CURRENT COMPARATOR switch for LOWER SECTION.

c. COMPARATOR CHANNEL DEFEAT 2.) Returns the following switches from the N43 position to the OPERATE position:

a. ROD STOP BYPASS,

b. POWER MISMATCH BYPASS.

3.) Performs actions of SOI-98.01, DISTRIBUTED CONTROL SYSTEM, to RESTORE 1LPY0920412R from BYPASS to NORMAL.

List of Steps that Constitute an Alternate Path Not Applicable.

If similar to an event in the Dynamic Scenario, then an explanation of how it is different.

Scenario removes a different power range channel (N41) from service. And does not encompass performance of SOI-98.01, Distributed Control System.

Procedure Name/Number and Section pertaining to the task.

1-AOI-4, Nuclear Instrumentation Malfunctions.

SOI-98.01, Distributed Control System.

Documentation justifying classification of Engineered Safety Function, when applicable:

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Not applicable D. Task/KA/Safety Function ESTABLISH MANUAL MAKEUP TO THE VCT / 004 A4.12 Ability to manually operate and/or monitor in the control room: Boration/dilution batch control (3.8/3.3) CFR 41/7 / 45.5 to 45.8/

Safety Function 2.

Task Standard:

The applicant 1.) Aligns the makeup control system to perform a MANUAL makeup of 97 gallons, and raises VCT level from 35% to approximately 40%.

2.) After the controls fail, terminates the boration by placing 1-HS-62-230A BA PMP A and 1-HS-62-232A BA PMP B in the STOP position per AOI-3, Malfunction of Reactor Makeup Control.

List of Critical Steps TURN 1-HS-62-140A, VCT MAKEUP CONTROL, to START.

OPEN 1-FCV-62-128, MAKEUP TO VCT INLET, OR 1-FCV-62-144, MAKEUP TO VCT OUTLET.

STOP boric acid transfer pumps.

Alternate Path:

When manual makeup is begun, 1-FCV-62-140, BA TO BLENDER and 1-FCV-62-128, MAKEUP TO VCT INLET or 1-FCV-62-144, MAKEUP TO VCT OUTLET fail open and cannot be closed. 1-FC-62-139, BA TO BLENDER FCV-62-140 CONTROL fails, causing boric acid flow rate to go to maximum. Requires stopping of the boric acid transfer pumps to terminate the boration.

List of Steps that Constitute an Alternate Path STOP boric acid transfer pumps.

If similar to an event in the Dynamic Scenario, then an explanation of how it is different.

Not Applicable.

Procedure Name/Number and Section pertaining to the task.

SOI-62.02, Boron Concentration Control.

AOI-3, Malfunction of Reactor Makeup Control.

Documentation justifying classification of Engineered Safety Function, when applicable:

Not applicable

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 E. Task/KA/Safety Function:

TRANSFER 6.9 KV RCP BOARD 1A FROM ALTERNATE TO NORMAL / 062 A4.01 Ability to manually operate and/or monitor in the control room: All breakers (including available switchyard) (3.3/3.1) CFR 41.4/45.5 to 45.8 / Safety Function 6.

Task Standard:

The applicant performs actions in accordance with SOI-202.1 Section 8.1 to transfer 1A RCP Board from its ALTERNATE to NORMAL power supply and restore the RCP control switches to a normal alignment List of Critical Steps:

ENSURE 1-HS-68-8BA, RCP 1 ALTERNATE BKR & XFER SELECTOR [1-M-5], PUSHED IN to place ACB 2522 auto transfer in MANUAL.

PLACE AND HOLD 1-HS-68-8AA, RCP 1 NORMAL BKR & LIFT PMP, in START, AND PLACE 1-HS-68-8BA, RCP 1 ALTERNATE BKR & XFER SELECTOR, in STOP.

Alternate Path:

Not applicable List of Steps that Constitute an Alternate Path Not applicable If similar to an event in the Dynamic Scenario, then an explanation of how it is different:

Not Applicable Procedure Name/Number and Section pertaining to the task:

SOI-202.1, 6.9KV Reactor Coolant Pump Board 1A.

Documentation justifying classification of Engineered Safety Function, when applicable:

Not Applicable

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 F. Task/KA/Safety Function ALIGN 1B-B CCS PUMP TO 1B SUPPLY HEADER/008 A4.01 Ability to manually operate and/or monitor in the control room: CCW indications and controls (3.3/3.1)(CFR: 41.7 /

45.5)/Safety Function 8 Task Standard:

The applicant:

1.) Performs valve manipulations to align CCS Pump 1B-B to the 1B Supply header.

2.) Performs actions required to start CCS Pump 1B-B.

List of Critical Steps Applicant locates.1-HS-70-38A, CCS PMP 1B-B, and rotates the handswitch to the STOP position, then pulls the handswitch out to the PULL-TO-LOCK position.

Applicant contacts the Console Operator and directs the Console Operator (as an AUO) to place the listed breakers to ON.

The applicant locates 1-HS-70-34A, CCS PMPS 1A & 1B SUCT XTIE and rotates the handswitch to the LEFT to the CLOSE position.

Applicant locates 1-HS-70-34A, CCS PMPS 1A & 1B SUCT XTIE and rotates the handswitch to the LEFT to the CLOSE position.

Applicant locates 1-HS-70-26A, CCS PMP 1B TO C-S DISCH XTIE, and rotates the handswitch to the RIGHT to the OPEN position.

Applicant locates 1-HS-70-27A, CCS PMP 1B TO C-S DISCH XTIE, and rotates the handswitch to the RIGHT to the OPEN position.

Applicant locates 1-HS-70-64A, CCS PMP 1B TO C-S SUCT XTIE, and rotates the handswitch to the RIGHT to the OPEN position.

Applicant locates 1-HS-70-74A, CCS PMP 1B TO C-S SUCT XTIE, and rotates the handswitch to the RIGHT to the OPEN position Applicant contacts the Console Operator as an AUO and directs the Console Operator (as an AUO) to place the listed breakers to OFF.

Applicant locates 1-HS-70-38A, CCS PMP 1B-B, and rotates the handswitch to the START position.

List of Steps that Constitute an Alternate Path Not Applicable If similar to an event in the Dynamic Scenario, then an explanation of how it is different.

Similar to Scenario 4, Event 1, which alternates 1B-B and 1A-A CCS pumps but the pumps remain aligned to CCS Header A. This JPM requires operation of multiple valves to support alignment.

Procedure Name/Number and Section pertaining to the task.

SOI-70.01, Component Cooling Water (CCS) System, Section 8.1, Align Pump 1B-B to Supply Header 1B.

Documentation justifying classification of Engineered Safety Function, when applicable:

Not Applicable

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 G. Task/KA/Safety Function:

COMPLETE 1-SI-85-2, REACTIVITY CONTROL SYSTEMS MOVABLE CONTROL ASSEMBLIES (MODES 1 AND 2)/ 001 A4.03 Ability to manually operate and/or monitor in the control room: CRDS mode control (4.0 / 3.7) CFR 41.7/45.5 to 45.8 / Safety Function 1 Task Standard:

The applicant:

1. Selects the CBC position on 1-RBSS, ROD BANK SELECT.

2. Inserts, then withdraws Control Bank C rods 10 steps.

3. Selects the CBD position on 1-RBSS, ROD BANK SELECT.

4. Inserts, then withdraws Control Bank D rods 10 steps.

5. Diagnoses the continuous insertion of Control Bank D Group 2 rods.

6. Performs a reactor trip in response to the continuous insertion of the Group 2 rods.

List of Critical Steps:

PLACE 1-RBSS, ROD BANK SELECT, in CBC.

() MOVE Control Bank C at least ten Steps in any one direction, as indicated on the appropriate Step Counter, and VERIFY movement of the rods in the proper direction is indicated on the appropriate RPIs.

PLACE 1-RBSS, ROD BANK SELECT, in CBD.

() MOVE Control Bank D at least ten Steps in any one direction, as indicated on the appropriate Step Counter, and VERIFY movement of the rods in the proper direction is indicated on the appropriate RPIs.

After it has been determined that the rod insertion cannot be stopped, TRIP the reactor Alternate Path After Control bank D is inserted to 210 steps, when the applicant attempts to withdraw Control Bank D to its previous position Control Bank D Group 2 rods insert. Upon diagnosis of the continuous rod insertion, the applicant trips the reactor.

List of Steps that Constitute an Alternate Path 1-AOI-2, Malfunction of Reactor Control System, Section 3.2, Uncontrolled Rod Bank Movement, IMMEDIATE ACTION STEP, Step 1.

If similar to an event in the Dynamic Scenario, then an explanation of how it is different:

Not Applicable.

Procedure Name/Number and Section pertaining to the task:

1-SI-85-2,Reactivity Control Systems Movable Control Assemblies (Modes 1 and 2).

1-AOI-2, Malfunction of Reactor Control System, Section 3.2, Uncontrolled Rod Bank Movement.

Documentation justifying classification of Engineered Safety Function, when applicable:

Not Applicable

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 H. Task/KA/Safety Function RESPOND TO RHR PUMP TRIP PER AOI-14/ 025 AA1.09 Ability to operate and / or monitor the following as they apply to the Loss of Residual Heat Removal System: LPI pump switches, ammeter, discharge pressure gauge, flow meter, and indicators (3.2/3.1) CFR: 41.7 / 45.5 / 45.6 /Safety Function 4P Task Standard:

The applicant responds to the trip of 1A RHR pump in accordance with AOI-14, Loss of RHR Shutdown Cooling, Section 3.5, RHR Pump 1A-A Trip and places the 1B RHR pump in service.

List of Critical Steps CLOSE RHR Hx outlets and bypass.

ALIGN RHR pump 1B-B discharge.

START RHR pump 1B-B.

ADJUST 1-FCV-74-28 to establish RHR flow within the RHR Pump operating flow limits in SOI-74.01 Appendix A.

ALIGN RHR Hx bypass flow.

ALIGN RHR pump 1B-B to CVCS.

List of Steps that Constitute an Alternate Path Not Applicable If similar to an event in the Dynamic Scenario, then an explanation of how it is different.

Not applicable.

Procedure Name/Number and Section pertaining to the task.

SOI-74.01, Residual Heat Removal System.

AOI-14 Loss Of RHR Shutdown Cooling.

Documentation justifying classification of Engineered Safety Function, when applicable:

Not applicable.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 I. Task/KA/Safety Function BYPASSING 1-PCV-62-81, CVCS LETDOWN HX PRESS CNTL, FOR LOCAL CONTROL

/004 A1.11 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the cvcs controls including: Letdown and Charging Flows (3.0/ 3.0) CFR 41.5/45.5 /Safety Function 2 Task Standard:

Applicant performs SOI-62.01, CVCS - Charging and Letdown, Section 8.15, Bypass 1-PCV-62-81, CVCS LETDOWN HX PRESS CNTL, for Local Control, and stabilizes pressure.

List of Critical Steps THROTTLE CLOSED 1-ISV-62-673, CVCS LETDOWN HEADER ISOLATION [A5U/737] until pressure rise indicated in MCR or Aux Cntl Rm THROTTLE OPEN 1-BYV-62-672, CVCS LETDOWN PCV-62-81 BYPASS [A5U/737] while CLOSING 1-ISV-62-673, CVCS LETDOWN HEADER ISOLATION.

List of Steps that Constitute an Alternate Path Not applicable.

If similar to an event in the Dynamic Scenario, then an explanation of how it is different.

Not applicable Procedure Name/Number and Section pertaining to the task.

SOI-62.01, CVCS - Charging and Letdown.

Documentation justifying classification of Engineered Safety Function, when applicable:

Not applicable.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 J. Task/KA/Safety Function LOCAL RESTART OF C&SS AIR COMPRESSORS / 065 AK3.08 Actions contained in EOP for loss of instrument air (3.7/3.9) (CFR 41.5,41.10 / 45.6 / 45.13) / Safety Function 8 Task Standard:

The applicant has aligned and started A and B Air Compressors using AOI-10, Loss of Control Air, Attachment 1, Local Restart of C&SS Air Compressors.

Control Air (Non-Essential) pressure has been re-established.

List of Critical Steps RESET high oil temp switches at each air compressor (0-TS-32-40, -35, and -30).

RESET Common Alarm using 0-HS-32-25B, COMPRESSOR A, B, C RESET [0-L-240, yellow PB].

PLACE the following C&SS Compressors to HAND [0-L-240]:

START Compressor A by pushing 0-HS-32-25E.

IF Compressor A does NOT Auto load, THEN PLACE 0-HS-32-43A and -43B to ON (Local 0-JB-291-226).

IF Compressor A does NOT load from local panel, THEN:

a. CLOSE 0-ISV-32-578, STATION AIR COMPR A UNLOADING HDR ISOL.

b. VENT 0-TV-32-579, STATION AIR COMPR A UNLOADING HDR TEST START Compressor B by pushing, 0-HS-32-26B.

List of Steps that Constitute an Alternate Path IF Compressor A does NOT Auto load, THEN PLACE 0-HS-32-43A and -43B to ON (Local 0-JB-291-226).

IF Compressor A does NOT load from local panel, THEN:

a. CLOSE 0-ISV-32-578, STATION AIR COMPR A UNLOADING HDR ISOL.

b. VENT 0-TV-32-579, STATION AIR COMPR A UNLOADING HDR TEST If similar to an event in the Dynamic Scenario, then an explanation of how it is different.

Not applicable Procedure Name/Number and Section pertaining to the task.

1-AOI-10 Loss of Control Air.

Documentation justifying classification of Engineered Safety Function, when applicable:

Not applicable.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 K. Task/KA/Safety Function TRANSFER 250V DC TURB BLDG DIST BD #1 FROM NORMAL TO ALTERNATE/ 063 A4.02 Ability to manually operate and/or monitor in the control room: Major breakers and control power fuses (2.8 / 2.9) CFR 41.7/45.5 to 45.8/ Safety Function 6.

Task Standard:

The applicant transfers the 250V DC Turbine Building Distribution Board #1 from its Normal to Alternate supply per SOI-239.01, 250V Battery Board 1, Section 8.7.1, Transfer from Normal to Alternate.

List of Critical Steps PLACE AUTO/MANUAL SUPPLY XFER SWITCH CS-101, to the MAN position.

CLOSE and HOLD ALT SUPPLY FROM 250V BATTERY BD 2, control switch until transfer is complete.

PLACE NORM SUPPLY FROM 250V BATTERY BD 1, control switch in the TRIP position.

List of Steps that Constitute an Alternate Path Not Applicable If similar to an event in the Dynamic Scenario, then an explanation of how it is different.

Not applicable.

Procedure Name/Number and Section pertaining to the task.

SOI-239.01, 250V Battery Board 1.

Documentation justifying classification of Engineered Safety Function, when applicable:

Not applicable.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Instant Senior Reactor Operator

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Watts Bar Date of Examination: October 2013 Exam Level: RO SRO-I SRO-U Operating Test Number: 302 Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety System / JPM Title Type Code*

Function A. Aux Feedwater LCV to Bypass Reg Transfer During Plant Startup. A,L,N 4S 059 A4.08 3.0/2.9 CFR 41.7/45.5 to 45.8 B Perform ES-1.3, Transfer to Containment Sump. A, EN, M 3 EA1.11 4.2/4.2 CFR 41.7/45.5 / 45.6 C. Return N43 Power Range To Service. M 7 015 A4.02 3.9/3.9 CFR 41.7 / 45.5 to 45.8 D. Perform a Manual Makeup to the VCT. A, M 2 004 A4.12 3.8/3.3 CFR 41.7 / 45.5 to 45.8 E. Transfer 1A RCP Board from Alternate to Normal. D 6 062 A4.01 3.3/3.1 CFR 41.4/45.5 to 45.8 F. Align 1B-B CCS Pump to 1B Supply Header. M 8 008 A4.01 3.3/3.1 CFR: 41.7 / 45.5 G. Complete 1-SI-85-2, Reactivity Control Systems Movable Control Assemblies (Modes 1 and 2). A, M 1 001 A4.03 4.0/3.7 CFR 41.7/45.5 to 45.8 H. N/A In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

I. Bypassing 1-PCV-62-81, CVCS LETDOWN HX PRESS CNTL, For Local Control D,E,R 2 004 A1.11 3.0/ 3.0 CFR 41.5/45.5 J. Local Restart of C&SS Air Compressors. A,D,E 8 065 AK3.08 3.7/3.9 CFR 41.5,41.10 / 45.6 / 45.13 K. Transfer 250v DC TURB BLDG DIST BD #1 from Normal to Alternate. D 6 063 A4.02 2.8/2.9 CFR 41.7

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

• Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank <9 / <8 / <4 (E)mergency or abnormal in-plant >1 / >1 / >1 (EN)gineered safety feature - / - / >1 (L)ow-Power / Shutdown >1 / >1 / >1 (N)ew or (M)odified from bank including 1(A) >2 / >2 / >1 (P)revious 2 exams <3 < 3 / < 2 (randomly selected)

(R)CA >1 / >1 / >1 (S)imulator

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Summary A. Task/KA/Safety Function:

TRANSFER FROM AUX FEEDWATER LCV TO BYPASS REG VALVE DURING STARTUP /

059 A4.08 Ability to manually operate and/or monitor in the control room: Feed regulating valve controller (3.0/2.9) CFR: 41.7/45.5 to 45.8/ Safety Function 4S Task Standard:

The applicant:

1.) Performs the actions required to transfer feedwater supply from 1-1-LIC-3-156A, SG 2 SUPPLY FRM PMP A-A to 1-LIC-3-103A, SG 4 MFW BYPASS REG CONTROL.

2.) Diagnoses the failure of 1-LCV-3-156A, SG 2 SUPPLY FRM PMP A-A OPEN and places 1-HS-3-118AAFW PMP A-A in STOP, PULL-TO-LOCK to terminate the overfill of SG 2.

Critical Steps:

PLACE SG 2 Bypass Reg Valve in MANUAL AND SLOWLY OPEN valve ENSURE 1-LIC-3-156A, SG 2 SUPPLY FRM PMP A-A closes as required to maintain SG 2 level on program.

Applicant locates 1-HS-3-118A, A-A MD AFWP, and rotates the handswitch to the LEFT to the STOP position. Applicant may pull the handswitch out to the STOP, PULL-TO-LOCK position.

Alternate Path:

During transfer from Auxiliary Feedwater to Main Feedwater level control, 1-LCV-3-156, SG 2 SUPPLY FRM PMP A-A fails OPEN, requiring the 1A-A MD AFW Pump to be stopped from the MCR.

List of Steps that Constitute an Alternate Path Applicant locates 1-HS-3-118A, A-A MD AFWP, and rotates the handswitch to the LEFT to the STOP position. Applicant may pull the handswitch out to the STOP, PULL-TO-LOCK position.

If similar to an event in the Dynamic Scenario, then an explanation of how it is different. Not applicable The applicant will perform actions of the following procedures:

SOI-3.02, Auxiliary Feedwater System."

Documentation justifying classification of Engineered Safety Function, when applicable:

Not Applicable

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 B. Task/KA/Safety Function ALIGN ECCS PUMPS BY PERFORMING ES-1.3, TRANSFER TO CONTAINMENT SUMP. /

EA1.11 Ability to operate and monitor the following as they apply to a Large Break LOCA:

Long-term core cooling (4.2/4.2) CFR 41.7 / 45.5 / 45.6 / Safety Function 3.

Task Standard:

Applicant performs aligns the ECCS pumps for containment sump recirculation using ES-1.3, Transfer to Containment Sump.

List of Critical Steps ENSURE cntmt sump valves 1-FCV-63-72 and 1-FCV-63-73 OPEN.

IF ONE cntmt sump valve can NOT be fully opened, THEN STOP and PULL TO LOCK RHR pump on the associated train.

ISOLATE SI pump miniflow.

ISOLATE RHR crossties.

ALIGN charging pump and SI pump supply from RHR.

ISOLATE charging pump suction from RWST.

ISOLATE SI pump suction from RWST.

CLOSE 1-FCV-63-1.

Alternate Path:

During performance of ES-1.3, Transfer to Containment Sump, the applicant will be unable to fully open 1-FCV-63-73, requiring the 1B-B RHR Pump to be placed in STOP, PULL-TO-LOCK.

List of Steps that Constitute an Alternate Path ENSURE cntmt sump valves 1-FCV-63-72 and 1-FCV-63-73 OPEN.

IF ONE cntmt sump valve can NOT be fully opened, THEN STOP and PULL TO LOCK RHR pump on the associated train.

If similar to an event in the Dynamic Scenario, then an explanation of how it is different.

Scenario contains a loss of recirculation sump due to the failure of both RHR pumps, and an immediate transition from ES-1.3, Transfer to Containment Sump, Step 1 RNO to 1-ECA-1.1, Loss of RHR Sump Recirculation.

Procedure Name/Number and Section pertaining to the task.

ES-1.3, Transfer to Containment Sump.

Documentation justifying classification of Engineered Safety Function, when applicable:

Task is associated with ECCS alignment to establish long term core cooling.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 C. Task/KA/Safety Function RETURN N43 POWER RANGE TO SERVICE / 015 A4.02 Ability to manually operate and/or monitor in the control room: NIS indicators (3.9/3.9) CFR 41.7 / 45.5 to 45.8/

Safety Function 7 Task Standard:

The applicant :

1.) Returns the following switches from the N43 position to the NORMAL.

a. DETECTOR CURRENT COMPARATOR switch for UPPER SECTION

b. DETECTOR CURRENT COMPARATOR switch for LOWER SECTION.

c. COMPARATOR CHANNEL DEFEAT 2.) Returns the following switches from the N43 position to the OPERATE position:

a. ROD STOP BYPASS,

b. POWER MISMATCH BYPASS.

3.) Performs actions of SOI-98.01, DISTRIBUTED CONTROL SYSTEM, to RESTORE 1LPY0920412R from BYPASS to NORMAL.

List of Critical Steps 1.) Returns the following switches from the N43 position to the NORMAL.

a. DETECTOR CURRENT COMPARATOR switch for UPPER SECTION

b. DETECTOR CURRENT COMPARATOR switch for LOWER SECTION.

c. COMPARATOR CHANNEL DEFEAT 2.) Returns the following switches from the N43 position to the OPERATE position:

a. ROD STOP BYPASS,

b. POWER MISMATCH BYPASS.

3.) Performs actions of SOI-98.01, DISTRIBUTED CONTROL SYSTEM, to RESTORE 1LPY0920412R from BYPASS to NORMAL.

List of Steps that Constitute an Alternate Path Not Applicable.

If similar to an event in the Dynamic Scenario, then an explanation of how it is different.

Scenario removes a different power range channel (N41) from service. And does not encompass performance of SOI-98.01, Distributed Control System.

Procedure Name/Number and Section pertaining to the task.

1-AOI-4, Nuclear Instrumentation Malfunctions.

SOI-98.01, Distributed Control System.

Documentation justifying classification of Engineered Safety Function, when applicable:

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Not applicable D. Task/KA/Safety Function ESTABLISH MANUAL MAKEUP TO THE VCT / 004 A4.12 Ability to manually operate and/or monitor in the control room: Boration/dilution batch control (3.8/3.3) CFR 41/7 / 45.5 to 45.8/

Safety Function 2.

Task Standard:

The applicant 1.) Aligns the makeup control system to perform a MANUAL makeup of 97 gallons, and raises VCT level from 35% to approximately 40%.

2.) After the controls fail, terminates the boration by placing 1-HS-62-230A BA PMP A and 1-HS-62-232A BA PMP B in the STOP position per AOI-3, Malfunction of Reactor Makeup Control.

List of Critical Steps TURN 1-HS-62-140A, VCT MAKEUP CONTROL, to START.

OPEN 1-FCV-62-128, MAKEUP TO VCT INLET, OR 1-FCV-62-144, MAKEUP TO VCT OUTLET.

STOP boric acid transfer pumps.

Alternate Path:

When manual makeup is begun, 1-FCV-62-140, BA TO BLENDER and 1-FCV-62-128, MAKEUP TO VCT INLET or 1-FCV-62-144, MAKEUP TO VCT OUTLET fail open and cannot be closed. 1-FC-62-139, BA TO BLENDER FCV-62-140 CONTROL fails, causing boric acid flow rate to go to maximum. Requires stopping of the boric acid transfer pumps to terminate the boration.

List of Steps that Constitute an Alternate Path STOP boric acid transfer pumps.

If similar to an event in the Dynamic Scenario, then an explanation of how it is different.

Not Applicable.

Procedure Name/Number and Section pertaining to the task.

SOI-62.02, Boron Concentration Control.

AOI-3, Malfunction of Reactor Makeup Control.

Documentation justifying classification of Engineered Safety Function, when applicable:

Not applicable

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 E. Task/KA/Safety Function:

TRANSFER 6.9 KV RCP BOARD 1A FROM ALTERNATE TO NORMAL / 062 A4.01 Ability to manually operate and/or monitor in the control room: All breakers (including available switchyard) (3.3/3.1) CFR 41.4/45.5 to 45.8 / Safety Function 6.

Task Standard:

The applicant performs actions in accordance with SOI-202.1 Section 8.1 to transfer 1A RCP Board from its ALTERNATE to NORMAL power supply and restore the RCP control switches to a normal alignment List of Critical Steps:

ENSURE 1-HS-68-8BA, RCP 1 ALTERNATE BKR & XFER SELECTOR [1-M-5], PUSHED IN to place ACB 2522 auto transfer in MANUAL.

PLACE AND HOLD 1-HS-68-8AA, RCP 1 NORMAL BKR & LIFT PMP, in START, AND PLACE 1-HS-68-8BA, RCP 1 ALTERNATE BKR & XFER SELECTOR, in STOP.

Alternate Path:

Not applicable List of Steps that Constitute an Alternate Path Not applicable If similar to an event in the Dynamic Scenario, then an explanation of how it is different:

Not Applicable Procedure Name/Number and Section pertaining to the task:

SOI-202.1, 6.9KV Reactor Coolant Pump Board 1A.

Documentation justifying classification of Engineered Safety Function, when applicable:

Not Applicable

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 F. Task/KA/Safety Function ALIGN 1B-B CCS PUMP TO 1B SUPPLY HEADER/008 A4.01 Ability to manually operate and/or monitor in the control room: CCW indications and controls (3.3/3.1)(CFR: 41.7 /

45.5)/Safety Function 8 Task Standard:

The applicant:

1.) Performs valve manipulations to align CCS Pump 1B-B to the 1B Supply header.

2.) Performs actions required to start CCS Pump 1B-B.

List of Critical Steps Applicant locates.1-HS-70-38A, CCS PMP 1B-B, and rotates the handswitch to the STOP position, then pulls the handswitch out to the PULL-TO-LOCK position.

Applicant contacts the Console Operator and directs the Console Operator (as an AUO) to place the listed breakers to ON.

The applicant locates 1-HS-70-34A, CCS PMPS 1A & 1B SUCT XTIE and rotates the handswitch to the LEFT to the CLOSE position.

Applicant locates 1-HS-70-34A, CCS PMPS 1A & 1B SUCT XTIE and rotates the handswitch to the LEFT to the CLOSE position.

Applicant locates 1-HS-70-26A, CCS PMP 1B TO C-S DISCH XTIE, and rotates the handswitch to the RIGHT to the OPEN position.

Applicant locates 1-HS-70-27A, CCS PMP 1B TO C-S DISCH XTIE, and rotates the handswitch to the RIGHT to the OPEN position.

Applicant locates 1-HS-70-64A, CCS PMP 1B TO C-S SUCT XTIE, and rotates the handswitch to the RIGHT to the OPEN position.

Applicant locates 1-HS-70-74A, CCS PMP 1B TO C-S SUCT XTIE, and rotates the handswitch to the RIGHT to the OPEN position Applicant contacts the Console Operator as an AUO and directs the Console Operator (as an AUO) to place the listed breakers to OFF.

Applicant locates 1-HS-70-38A, CCS PMP 1B-B, and rotates the handswitch to the START position.

List of Steps that Constitute an Alternate Path Not Applicable If similar to an event in the Dynamic Scenario, then an explanation of how it is different.

Similar to Scenario 4, Event 1, which alternates 1B-B and 1A-A CCS pumps but the pumps remain aligned to CCS Header A. This JPM requires operation of multiple valves to support alignment.

Procedure Name/Number and Section pertaining to the task.

SOI-70.01, Component Cooling Water (CCS) System, Section 8.1, Align Pump 1B-B to Supply Header 1B.

Documentation justifying classification of Engineered Safety Function, when applicable:

Not Applicable

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 G. Task/KA/Safety Function:

COMPLETE 1-SI-85-2, REACTIVITY CONTROL SYSTEMS MOVABLE CONTROL ASSEMBLIES (MODES 1 AND 2)/ 001 A4.03 Ability to manually operate and/or monitor in the control room: CRDS mode control (4.0 / 3.7) CFR 41.7/45.5 to 45.8 / Safety Function 1 Task Standard:

The applicant:

1. Selects the CBC position on 1-RBSS, ROD BANK SELECT.

2. Inserts, then withdraws Control Bank C rods 10 steps.

3. Selects the CBD position on 1-RBSS, ROD BANK SELECT.

4. Inserts, then withdraws Control Bank D rods 10 steps.

5. Diagnoses the continuous insertion of Control Bank D Group 2 rods.

6. Performs a reactor trip in response to the continuous insertion of the Group 2 rods.

List of Critical Steps:

PLACE 1-RBSS, ROD BANK SELECT, in CBC.

() MOVE Control Bank C at least ten Steps in any one direction, as indicated on the appropriate Step Counter, and VERIFY movement of the rods in the proper direction is indicated on the appropriate RPIs.

PLACE 1-RBSS, ROD BANK SELECT, in CBD.

() MOVE Control Bank D at least ten Steps in any one direction, as indicated on the appropriate Step Counter, and VERIFY movement of the rods in the proper direction is indicated on the appropriate RPIs.

After it has been determined that the rod insertion cannot be stopped, TRIP the reactor Alternate Path After Control bank D is inserted to 210 steps, when the applicant attempts to withdraw Control Bank D to its previous position Control Bank D Group 2 rods insert. Upon diagnosis of the continuous rod insertion, the applicant trips the reactor.

List of Steps that Constitute an Alternate Path 1-AOI-2, Malfunction of Reactor Control System, Section 3.2, Uncontrolled Rod Bank Movement, IMMEDIATE ACTION STEP, Step 1.

If similar to an event in the Dynamic Scenario, then an explanation of how it is different:

Not Applicable.

Procedure Name/Number and Section pertaining to the task:

1-SI-85-2,Reactivity Control Systems Movable Control Assemblies (Modes 1 and 2).

1-AOI-2, Malfunction of Reactor Control System, Section 3.2, Uncontrolled Rod Bank Movement.

Documentation justifying classification of Engineered Safety Function, when applicable:

Not Applicable

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 H. Not applicable.

I. Task/KA/Safety Function BYPASSING 1-PCV-62-81, CVCS LETDOWN HX PRESS CNTL, FOR LOCAL CONTROL

/004 A1.11 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the cvcs controls including: Letdown and Charging Flows (3.0/ 3.0) CFR 41.5/45.5 /Safety Function 2 Task Standard:

Applicant performs SOI-62.01, CVCS - Charging and Letdown, Section 8.15, Bypass 1-PCV-62-81, CVCS LETDOWN HX PRESS CNTL, for Local Control, and stabilizes pressure.

List of Critical Steps THROTTLE CLOSED 1-ISV-62-673, CVCS LETDOWN HEADER ISOLATION [A5U/737] until pressure rise indicated in MCR or Aux Cntl Rm THROTTLE OPEN 1-BYV-62-672, CVCS LETDOWN PCV-62-81 BYPASS [A5U/737] while CLOSING 1-ISV-62-673, CVCS LETDOWN HEADER ISOLATION.

List of Steps that Constitute an Alternate Path Not applicable.

If similar to an event in the Dynamic Scenario, then an explanation of how it is different.

Not applicable Procedure Name/Number and Section pertaining to the task.

SOI-62.01, CVCS - Charging and Letdown.

Documentation justifying classification of Engineered Safety Function, when applicable:

Not applicable.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 J. Task/KA/Safety Function LOCAL RESTART OF C&SS AIR COMPRESSORS / 065 AK3.08 Actions contained in EOP for loss of instrument air (3.7/3.9) (CFR 41.5,41.10 / 45.6 / 45.13) / Safety Function 8 Task Standard:

The applicant has aligned and started A and B Air Compressors using AOI-10, Loss of Control Air, Attachment 1, Local Restart of C&SS Air Compressors. Control Air (Non-Essential) pressure has been re-established.

List of Critical Steps RESET high oil temp switches at each air compressor (0-TS-32-40, -35, and -30).

RESET Common Alarm using 0-HS-32-25B, COMPRESSOR A, B, C RESET [0-L-240, yellow PB].

PLACE the following C&SS Compressors to HAND [0-L-240]:

START Compressor A by pushing 0-HS-32-25E.

IF Compressor A does NOT Auto load, THEN PLACE 0-HS-32-43A and -43B to ON (Local 0-JB-291-226).

IF Compressor A does NOT load from local panel, THEN:

a. CLOSE 0-ISV-32-578, STATION AIR COMPR A UNLOADING HDR ISOL.

b. VENT 0-TV-32-579, STATION AIR COMPR A UNLOADING HDR TEST START Compressor B by pushing, 0-HS-32-26B.

List of Steps that Constitute an Alternate Path IF Compressor A does NOT Auto load, THEN PLACE 0-HS-32-43A and -43B to ON (Local 0-JB-291-226).

IF Compressor A does NOT load from local panel, THEN:

a. CLOSE 0-ISV-32-578, STATION AIR COMPR A UNLOADING HDR ISOL.

b. VENT 0-TV-32-579, STATION AIR COMPR A UNLOADING HDR TEST If similar to an event in the Dynamic Scenario, then an explanation of how it is different.

Not applicable Procedure Name/Number and Section pertaining to the task.

1-AOI-10 Loss of Control Air.

Documentation justifying classification of Engineered Safety Function, when applicable:

Not applicable.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 K. Task/KA/Safety Function TRANSFER 250V DC TURB BLDG DIST BD #1 FROM NORMAL TO ALTERNATE/ 063 A4.02 Ability to manually operate and/or monitor in the control room: Major breakers and control power fuses (2.8 / 2.9) CFR 41.7/45.5 to 45.8/ Safety Function 6.

Task Standard:

The applicant transfers the 250V DC Turbine Building Distribution Board #1 from its Normal to Alternate supply per SOI-239.01, 250V Battery Board 1, Section 8.7.1, Transfer from Normal to Alternate.

List of Critical Steps PLACE AUTO/MANUAL SUPPLY XFER SWITCH CS-101, to the MAN position.

CLOSE and HOLD ALT SUPPLY FROM 250V BATTERY BD 2, control switch until transfer is complete.

PLACE NORM SUPPLY FROM 250V BATTERY BD 1, control switch in the TRIP position.

List of Steps that Constitute an Alternate Path Not Applicable If similar to an event in the Dynamic Scenario, then an explanation of how it is different.

Not applicable.

Procedure Name/Number and Section pertaining to the task.

SOI-239.01, 250V Battery Board 1.

Documentation justifying classification of Engineered Safety Function, when applicable:

Not applicable.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Upgrade Senior Reactor Operator

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Watts Bar Date of Examination: October 2013 Exam Level: RO SRO-I SRO-U Operating Test Number: 302 Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety System / JPM Title Type Code*

Function A. Aux Feedwater LCV to Bypass Reg Transfer During Plant Startup. A,L,N 4S 059 A4.08 3.0/2.9 CFR 41.7/45.5 to 45.8 B Perform ES-1.3, Transfer to Containment Sump. A, EN, M 3 EA1.11 4.2/4.2 CFR 41.7/45.5 / 45.6 C. Not Applicable D. Not Applicable E. Not Applicable F. Not Applicable G. Not Applicable H. Not Applicable In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

I. Bypassing 1-PCV-62-81, CVCS LETDOWN HX PRESS CNTL, For Local Control D,E,R 2 004 A1.11 3.0/ 3.0 CFR 41.5/45.5 J. Local Restart of C&SS Air Compressors. A,D,E 8 065 AK3.08 3.7/3.9 CFR 41.5,41.10 / 45.6 / 45.13 K. Transfer 250v DC TURB BLDG DIST BD #1 from Normal to Alternate. D 6 063 A4.02 2.8/2.9 CFR 41.7

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

• Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank <9 / <8 / <4 (E)mergency or abnormal in-plant >1 / >1 / >1 (EN)gineered safety feature - / - / >1 (L)ow-Power / Shutdown >1 / >1 / >1 (N)ew or (M)odified from bank including 1(A) >2 / >2 / >1 (P)revious 2 exams <3 < 3 / < 2 (randomly selected)

(R)CA >1 / >1 / >1 (S)imulator

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Summary A. Task/KA/Safety Function:

TRANSFER FROM AUX FEEDWATER LCV TO BYPASS REG VALVE DURING STARTUP /

059 A4.08 Ability to manually operate and/or monitor in the control room: Feed regulating valve controller (3.0/2.9) CFR: 41.7/45.5 to 45.8/ Safety Function 4S Task Standard:

The applicant:

1.) Performs the actions required to transfer feedwater supply from 1-1-LIC-3-156A, SG 2 SUPPLY FRM PMP A-A to 1-LIC-3-103A, SG 4 MFW BYPASS REG CONTROL.

2.) Diagnoses the failure of 1-LCV-3-156A, SG 2 SUPPLY FRM PMP A-A OPEN and places 1-HS-3-118AAFW PMP A-A in STOP, PULL-TO-LOCK to terminate the overfill of SG 2.

Critical Steps:

PLACE SG 2 Bypass Reg Valve in MANUAL AND SLOWLY OPEN valve ENSURE 1-LIC-3-156A, SG 2 SUPPLY FRM PMP A-A closes as required to maintain SG 2 level on program.

Applicant locates 1-HS-3-118A, A-A MD AFWP, and rotates the handswitch to the LEFT to the STOP position. Applicant may pull the handswitch out to the STOP, PULL-TO-LOCK position.

Alternate Path:

During transfer from Auxiliary Feedwater to Main Feedwater level control, 1-LCV-3-156, SG 2 SUPPLY FRM PMP A-A fails OPEN, requiring the 1A-A MD AFW Pump to be stopped from the MCR.

List of Steps that Constitute an Alternate Path Applicant locates 1-HS-3-118A, A-A MD AFWP, and rotates the handswitch to the LEFT to the STOP position. Applicant may pull the handswitch out to the STOP, PULL-TO-LOCK position.

If similar to an event in the Dynamic Scenario, then an explanation of how it is different. Not applicable The applicant will perform actions of the following procedures:

SOI-3.02, Auxiliary Feedwater System.

Documentation justifying classification of Engineered Safety Function, when applicable:

Not Applicable

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 B. Task/KA/Safety Function ALIGN ECCS PUMPS BY PERFORMING ES-1.3, TRANSFER TO CONTAINMENT SUMP. /

EA1.11 Ability to operate and monitor the following as they apply to a Large Break LOCA:

Long-term core cooling (4.2/4.2) CFR 41.7 / 45.5 / 45.6 / Safety Function 3.

Task Standard:

Applicant performs aligns the ECCS pumps for containment sump recirculation using ES-1.3, Transfer to Containment Sump.

List of Critical Steps ENSURE cntmt sump valves 1-FCV-63-72 and 1-FCV-63-73 OPEN.

IF ONE cntmt sump valve can NOT be fully opened, THEN STOP and PULL TO LOCK RHR pump on the associated train.

ISOLATE SI pump miniflow.

ISOLATE RHR crossties.

ALIGN charging pump and SI pump supply from RHR.

ISOLATE charging pump suction from RWST.

ISOLATE SI pump suction from RWST.

CLOSE 1-FCV-63-1.

Alternate Path:

During performance of ES-1.3, Transfer to Containment Sump, the applicant will be unable to fully open 1-FCV-63-73, requiring the 1B-B RHR Pump to be placed in STOP, PULL-TO-LOCK.

List of Steps that Constitute an Alternate Path ENSURE cntmt sump valves 1-FCV-63-72 and 1-FCV-63-73 OPEN.

IF ONE cntmt sump valve can NOT be fully opened, THEN STOP and PULL TO LOCK RHR pump on the associated train.

If similar to an event in the Dynamic Scenario, then an explanation of how it is different.

Scenario contains a loss of recirculation sump due to the failure of both RHR pumps, and an immediate transition from ES-1.3, Transfer to Containment Sump, Step 1 RNO to 1-ECA-1.1, Loss of RHR Sump Recirculation.

Procedure Name/Number and Section pertaining to the task.

ES-1.3, Transfer to Containment Sump.

Documentation justifying classification of Engineered Safety Function, when applicable:

Task is associated with ECCS alignment to establish long term core cooling.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 C. Not Applicable D. Not Applicable E. Not Applicable F. Not Applicable G. Not Applicable H. Not Applicable I. Task/KA/Safety Function BYPASSING 1-PCV-62-81, CVCS LETDOWN HX PRESS CNTL, FOR LOCAL CONTROL

/004 A1.11 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the cvcs controls including: Letdown and Charging Flows (3.0/ 3.0) CFR 41.5/45.5 /Safety Function 2 Task Standard:

Applicant performs SOI-62.01, CVCS - Charging and Letdown, Section 8.15, Bypass 1-PCV-62-81, CVCS LETDOWN HX PRESS CNTL, for Local Control, and stabilizes pressure.

List of Critical Steps THROTTLE CLOSED 1-ISV-62-673, CVCS LETDOWN HEADER ISOLATION [A5U/737] until pressure rise indicated in MCR or Aux Cntl Rm THROTTLE OPEN 1-BYV-62-672, CVCS LETDOWN PCV-62-81 BYPASS [A5U/737] while CLOSING 1-ISV-62-673, CVCS LETDOWN HEADER ISOLATION.

List of Steps that Constitute an Alternate Path Not applicable.

If similar to an event in the Dynamic Scenario, then an explanation of how it is different.

Not applicable Procedure Name/Number and Section pertaining to the task.

SOI-62.01, CVCS - Charging and Letdown.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 J. Task/KA/Safety Function LOCAL RESTART OF C&SS AIR COMPRESSORS / 065 AK3.08 Actions contained in EOP for loss of instrument air (3.7/3.9) (CFR 41.5,41.10 / 45.6 / 45.13) / Safety Function 8 Task Standard:

The applicant has aligned and started A and B Air Compressors using AOI-10, Loss of Control Air, Attachment 1, Local Restart of C&SS Air Compressors. Control Air (Non-Essential) pressure has been re-established.

List of Critical Steps RESET high oil temp switches at each air compressor (0-TS-32-40, -35, and -30).

RESET Common Alarm using 0-HS-32-25B, COMPRESSOR A, B, C RESET [0-L-240, yellow PB].

PLACE the following C&SS Compressors to HAND [0-L-240]:

START Compressor A by pushing 0-HS-32-25E.

IF Compressor A does NOT Auto load, THEN PLACE 0-HS-32-43A and -43B to ON (Local 0-JB-291-226).

IF Compressor A does NOT load from local panel, THEN:

a. CLOSE 0-ISV-32-578, STATION AIR COMPR A UNLOADING HDR ISOL.

b. VENT 0-TV-32-579, STATION AIR COMPR A UNLOADING HDR TEST START Compressor B by pushing, 0-HS-32-26B.

List of Steps that Constitute an Alternate Path IF Compressor A does NOT Auto load, THEN PLACE 0-HS-32-43A and -43B to ON (Local 0-JB-291-226).

IF Compressor A does NOT load from local panel, THEN:

a. CLOSE 0-ISV-32-578, STATION AIR COMPR A UNLOADING HDR ISOL.

b. VENT 0-TV-32-579, STATION AIR COMPR A UNLOADING HDR TEST If similar to an event in the Dynamic Scenario, then an explanation of how it is different.

Not applicable Procedure Name/Number and Section pertaining to the task.

1-AOI-10 Loss of Control Air.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 K. Task/KA/Safety Function TRANSFER 250V DC TURB BLDG DIST BD #1 FROM NORMAL TO ALTERNATE/ 063 A4.02 Ability to manually operate and/or monitor in the control room: Major breakers and control power fuses (2.8 / 2.9) CFR 41.7/45.5 to 45.8/ Safety Function 6.

Task Standard:

The applicant transfers the 250V DC Turbine Building Distribution Board #1 from its Normal to Alternate supply per SOI-239.01, 250V Battery Board 1, Section 8.7.1, Transfer from Normal to Alternate.

List of Critical Steps PLACE AUTO/MANUAL SUPPLY XFER SWITCH CS-101, to the MAN position.

CLOSE and HOLD ALT SUPPLY FROM 250V BATTERY BD 2, control switch until transfer is complete.

PLACE NORM SUPPLY FROM 250V BATTERY BD 1, control switch in the TRIP position.

List of Steps that Constitute an Alternate Path Not Applicable If similar to an event in the Dynamic Scenario, then an explanation of how it is different.

Not applicable.

Procedure Name/Number and Section pertaining to the task.

SOI-239.01, 250V Battery Board 1.

Documentation justifying classification of Engineered Safety Function, when applicable:

Not applicable.

ES-401 , Rev. 9 PWR Examination Outline Form ES4OI-2 Facility: L4/9r 13 Date of Exam: OC7Z i3ER o/ 3 RO K/A Category Points SRO-Only Points Tier Group KKKKKKAAAAG A2 G* Total I 2 3 4 5 6 1 2 3 4 Total

1. 1 33 3 3 3 3 18 3 3 6 Emergency &

Abnormal Plant 2 7 N/A 2 2 N/A 9 2 2 4 Evolutions Tier Totals 4 4 5 5 5 4 27 5 5 10 I 3 2 3 3 2 2 3 22 3 3 28 3 2 5 2.

Plant 2 1 1 1 1 1 1 1 1 1 1 0 10 1 1 i 3 Systems TierTotals 4 3 4 4 3 3 4 3 3 4 3 38 *5 3 8

3. Generic Knowledge and Abilities Categories I 2 3 4 10 1 2 fI 3 4 7 3 2 2 3 1 2j2 2 I . Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (i.e., exceptforone category in Tier 3 ofthe SRO-only outline, the Tier Totals in each K/A category shall not be less than two).

2. The point total for each group and tier in the proposed outline must match that specified in the table.

The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions.

The final RO exam must total 75 points and the SRO-only exam must total 25 points.

3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted andjustified; operationally important, site-specific systems that are not included on the outiine should be added. Refer to section D.1 .b of ES-401 for guidance regarding the elimination of inappropriate KIA statements.

4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.

5. Absent a plant-specific priority, only those K/As having an importance rating (lR) of 2.5 or higher shall be selected.

Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

6. Select SRO topics for Tiers I and 2 from the shaded systems and K/A categories.

7. *The generic (G) K/As in Tiers I and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to section D.1 .b of ES-401 for the applicable KAs.

8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; iffuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note # I does not apply). Use duplicate pages for RO and SRO-only exams.

9. For Tier 3, select topics from Section 2 of the KIA catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43..

ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETYFUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO OO7EK1 02 -

Reactor Trip Stabilization - Recovery 3.4 3.8 Shutdown margin j j

/1 008AK2.O1 Pressurizer Vapor SpaceAccident/3 2.7 2.7 j j Valves OO9EK1 02 Small Break LOCA I 3 3.5 4.2 j j J j Use of steam tables 015AK2.08 RCP Malfunctions I 4 2.6 2.6 COWS 022AK1 .01 Loss of Rx Coolant Makeup I 2 2.8 3.2 j j j j Consequences of thermal shock to RCP seals 026AA2.03 Loss of Component Cooling Water I 8 2.6 2.9 j j J The valve lineups necessary to restart the COWS while bypassing the portion of the system causing the abnormal condition 029EK2.06 ATWS / 1 2.9 3.1 j j Breakers, relays, and disconnects.

O4OAA1.19 -

Steam Line Rupture Excessive Heat 3.83.9 Postaccident monitoring panel indicators j j j j Transfer / 4 054AK3.04 Loss of Main Feedwater /4 4.4 4.6 LI LI El LI LI El Actions contained in EOPs for loss of MEW 055EA2.03 Station ackout /6 3.9 4.7 Actions necessary to restore power 056AG2.l .7 Loss of Off-site Power /6 4.4 4.7 TJj Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.

Page 1 of 2 6/26/2012 4:30PM

ES-401, REV 9 T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 058AK3.01 Loss of DC Power /6 3.4 3.7 D El LI LI D LI D LI LI LI UseofdccontrolpowerbyD/Gs 062AA1 .01 Loss of Nucear Svc Water /4 3.1 3.1 Nuclear service water temperature indKDations 065AK3.03 Loss of Instrument Air /8 a93.4 Knowing effects on plant operation of isolating certain equipment from instrument air 077AG2.4.45 Generator Voltage and Electric Grid 4.1 4.3 j D [j Ability to prioritize and interpret the significance of each Disturbances / 6 annunciator or alarm.

WEO4EA1 .3 LOCA Outside Containment /3 3.8 4.0 J J Desired operating results during abnormal and emergency situations.

WEO5EA2.2 -

Inadequate Heat Transfer Loss of 3.7 4.3 Adherence to appropriate procedures and operation Secondary Heat Sink /4 within the limitations in the facilitys license and amendments.

wellEG2.1 .2 Loss of Emergency Coolant Recirc. / 4 3.9 4.2 Ability to interpret reference materials such as graphs, monographs and tables which contain performance data.

Page 2 of 2 6/26/2012 4:30PM

ES-401, REV 9 T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETY FUNCTION: IA K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 001 AG2.4.49 Continuous Rod Withdrawal / 1 4.6 4.4 El LI LI D LI D LI El LI LI Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.

036AA1 .04 Fuel Handling Accident / 8 3.1 3.7 El El D D El LI i El LI LI El Fuel handling equipment during an incident 037AKi05 Steam Generator Tube Leak /3 3.7 4 D LI LI LI El LI D D El D Actions contained in proceduresfor radiation monitoring, RCS water inventory balance, S/G tube failure and plant shutdown 051 AA2.02 Loss of Condenser Vacuum /4 3.9 4.1 LI LI LI D El El El El D LI Conditions requiring reactor and/or turbine ffip 068AA1 .12 Control Room Evac. / 8 4.4 El El El El El El El El El El Auxiliary shutdown panel controls and indicators 076AK3.06 High Reactor Coolant Activity / 9 3.2 3.8 j El El El El El El Actions contained in EQP for high reactor coolant activity WEO6EK2.2 Degraded Core Cooling /4 3.8 4.1 El El El El [] Facilitys heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems and relations between the proper operation of these systems to the operation of the facility.

WEO8EK1 .1 -

RCS Overcooling PTS /4 3.5 3.8 Components, capacity, and function of emergency El El El El El El El El El El systems.

WEO9EA2.2 Natural Circ. /4 3.4 3.8 El El El El El El El El El El Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments.

Page 1 of 1 6/26/2012 4:30PM

ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 003A4.07 Reactor Coolant Pump 2.6 2.6 j j j RCP seal bypass 003K5.04 Reactor Coolant Pump 323.5 j j j j j Effects of RCP shutdown on secondary parameters, such as steam pressure, steam flow and feed flow 004G2.l .23 Chemical and Volume Control 4.3 4.4 j j j j Ability to perform specific system and integrated plant procedures during all modes of plant operation.

005A1 .07 Residual Heat Removal 2.5 3.1 j j j j j Determination of test acceptability by comparison of recorded valve response times with Tech-Spec requirements 005K2.03 Residual Heat Removal 2.7 2.8 RCS pressure boundary motor-operated valves 006A3.03 Emergency Core Cooling 4.1 4.1 LI LI LI L] LI LI LI LI ESFAS-operated valves 007K4.0l Pressurizer Relief/Quench Tank 2.6 2.9 LI LI LI Quench tank cooling LI LI LI LI LI LI LI 008G2.4.1 1 Component Cooling Water 4.0 4.2 LI LI LI LI LI LI LI LI LI LI Knowledge of abnormal condition procedures.

010A3.O1 Pressurizer Pressure Control 3.0 3.2 LI LI LI LI LI LI LI LI PRT temperature and pressure during PQRV testing LI LI 012K5.01 Reactor Protection 3.3 3.8 LI LI LI LI ] LI LI LI LI LI LI DNB 013K6.01 Engineered Safety Features Actuation 2.7 3.1 LI LI LI LI LI ] LI LI LI LI LI Sensors and detectors Pagelof3 6/26/2012 4:30PM

ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME/SAFETYFUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 022A1 .02 Containment Cooling 3.6 3.8 j j Containment pressure J J J 025A1 .03 Ice Condenser 2.5 2.5 j Glycol flow to ice condenser air handling units j j J 025A4.O1 Ice Condenser 3.0 2.7 j j Ice condenser isolation valves 026A2.03 Containment Spray 4.1 4.4 j Failure of ESF j

039K3.05 Main and Reheat Steam 3.6 3.7 RCS LI 059K1 .04 Main Feedwater 3.4 3.4 S/GS water level control system 061 K4.04 Auxiliary/Emergency Feedwater 3.1 3.4 Prevention of AFW runout by miting AFW flow 061 K6.02 Auxiliary/Emergency Feedwater 2.6 2.7 Pumps LI LI LI LI LI [] LI LI LI LI LI 062K4.07 AC Electrical Distribution 2.7 3.1 One-line diagram of 4kV to 480V distribution, including LI LI LI LI LI LI LI LI LI LI sources of normal and alternative power 063K2.01 DC Electrical Distribution 2.9 3.1 Major DC loads LI LI LI LI LI LI LI LI LI LI 064A2.05 Emergency Diesel Generator 3.1 3.2 Loading the ED/G LI LI LI LI LI LI LI LI LI LI Page2of3 6/26/2012 4:30PM

ES-401, REV 9 T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IA Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 064K1 .02 Emergency Diesel Generator 3.1 3.6 DIG cooling water system 073K3.0l Process Radiation Monitoring 3.6 4.2 Radioactive effluent releases 076G2.1.28 Service Water 4.1 4.1 Knowledge of the purpose and function of major system components and controls.

078A4.01 Instrument Air 3.1 3.1 Pressure gauges 078K3.03 Instrument Air 3.0 3.4 Cross-tied units 103K1.08 Containment 3.6 3.8 SIS, including action of safety injection reset Page 3 of 3 612612012 4:30 PM

ES-401, REV 9 T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 002K1.17 ReactorCoolant 3.5 3.8 j j j MT/G 01 1 K2.02 Pressurizer Level Control 3.1 3.2 j j j J j PZR heaters 014K3.02 Rod Positionindication 2.5 2.8 Plant computer 01 7A3.01 In-core Temperature Monitor 3.6 3.8 LI LI El El El El lndicaUons of normal, natural and interrupted circulation of RCS 029K4.02 Containment Purge 2.9 3.1 Negative pressure in containment El 033A1.02 Spent Fuel Pool Cooling 2.8 3.3 j j Radiation monitoring systems 035K6.02 Steam Generator 3.1 3.5 El LI El El El Secondary PORV El El El El El 045K5.17 Main Turbine Generator 2.5 2.7 Relationslup between moderator temperature coefficient El El El El El El El El El El and boron concentration in RCS as T/G load increases 068A2.02 Liquid Radwaste 2.7 2.8 Lack of tank recirculation prior to release El El El El El El El [J El El El 079A4.0l Station Air 2.7 2.7 Cross-tie valves with AS El El El El El El El El El El Page 1 of 1 6/26/2012 4:30 PM

ES-401, REV 9 T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO G2.l .43 Conduct of operations 4.1 4.3 j J J j j j Ability to use procedures to determine the effects on reactivity of plant changes G2.1 45 Conduct of operations 4.34.3 j j j Ability to identify and interpret diverse indications to validate the response of another indication G2.l.8 Conduct of operations 3.4 4.1 j J j Ability to coordinate personnel activities outside the control room.

G2.2.1 Equipment Control 4.5 4.4 J J j j j j AbHity to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity.

G2.2.7 Equipment Control 2.9 3.6 j j j j Knowledge of the process for conducting special or infrequent tests G2.3.15 Radiation Control 2.9 3.1 j j Knowledge of radiation monitoring systems Ga3.4 Radiation Control 3.2 3.7 Knowledge of radiation exposure limits under normal and emergency conditions G2.4.20 Emergency Procedures/Plans 3.8 4.3 El El El El El El El El El El Knowledge of operational implications of EOP warnings, cautions and notes.

G2.4.28 Emergency Procedures/Plans 3.2 4.1 El El El El El El El El El El Knowledge of procedures relating to emergency response to sabotage.

G2.4.29 Emergency Procedures/Plans 3.1 4.4 El El El El El El El El El El Knowledge of the emergency plan.

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ES-401, REV 9 SRO T1G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 008AA2.02 Pressurizer Vapor Space Accident /3 3.9 4.1 PZR spray valve position indicators and acoustic monitors 054AA2.08 Loss of Main Feedwater /4 2.9 3.3 Steam flow-feed trend recorder 055EG2.2.36 Station Blackout / 6 3.1 4.2 j J [ Ability to analyzetheeffectofmaintenance activities, such as degraded power sources, on the status of limiting conditions of operations 058AA2.O1 Loss of DC Power / 6 3.7 4.1 j j j That a loss of dc power has occurred; verification that substitute power sources have come on line 077AG2.2.37 Generator Voltage and Electric Grid 3.6 4.6 Ability to determine operability and/or availability of safety Disturbances / 6 related equipment weO5EG2.l .2 -

Inadequate Heat Transfer Loss of 4.6 4.6 Ability to execute procedure steps.

Secondary Heat Sink /4 El El El El El El El El Page 1 of 1 6/26/2012 4:30PM

ES-401, REV 9 SRO T1G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 028AG2.4.21 Pressurizer Level Malfunction /2 4.0 4.6 j j Knowledge of the parameters and logic used to assess the status of safety functions 068AG2.l .7 Control Room Evac. /8 4.4 4.7 j J Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.

076AA2.06 High Reactor Coolant Activity / 9 2.2 2.5 Response of PZR LCS to changes in the letdown flow rate WE1 5EA2.2 Containment Flooding /5 2.9 3.3 Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments.

Page 1 of 1 6/26/2012 4:30 PM

ES-401, REV 9 SRO T2G1 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 004G2.2.12 Chemical and Volume Control 3.7 4.1 Knowledge of surveillance procedures.

013G2.2.40 Engineered Safety Features Actuation Ability to apply technical specifications for a system.

059A2.05 Main Feedwater 3.1 3.4 Rupture in MFW suction or discharge line 061A2.06 Auxiliary/Emergency Feedwater 2.7 3.0 Back leakage of MFW 064A2.09 Emergency Diesel Generator 3.1 3.3 Synchronization of the ED/G with other electric power supplies Page 1 of 1 6/26/2012 4:30 PM

ES-401, REV 9 SRO T2G2 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME / SAFETY FUNCTION: IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 001 G2.l .31 Control Rod Drive 4.6 4.3 El Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup.

015A2.04 Nuclear Instrumentation 3.3 3.8 El El El El El El El [] El El El Effects on axial flux density of control rod alignment and sequencing, xenon production and decay, and boron vs.

control rod reactivity changes 034A3.01 Fuel Handling Equipment 2.5 3.1 El El El El El El El El El El Travel limits Page 1 of 1 6/26/2012 4:30 PM

ES-401, REV 9 SRO T3 PWR EXAMINATION OUTLINE FORM ES-401-2 KA NAME I SAFETY FUNCTION: IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO G2.l .38 Conduct of operations 3.7 3.8 j Knowledge of the stations requirements for verbal com m unication when im plamenting procedures G2.21 Equipment Control 2.9 41 j j j j j j Knowledge of pre- and post-maintenance operability requirements.

G2.2.23 Equipment Control 3.1 4.6 EJ j Ability to track Technical Specification limiting condions for operations.

G2.3.14 Radiation Control 3.4 3.8 j j Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities G2.3.6 Radiation Control 2.0 3.8 j j Ability to aprove release permits G2A18 Emergency Procedures/Plans 3.3 4.0 El El El El El El El El El Knowledge of the specific bases for EOPs.

G2.4.43 Emergency Procedures/Plans 3.2 3.8 El El El El El El El El El El Knowledge of emergency communications systems and techniques.

Page 1 of 1 6/26/2012 4:30PM