ML16049A032

Initial Exam 2015-302 Draft Administrative Documents

ML16049A032
Person / Time
Site:	Browns Ferry
Issue date:	02/18/2016
From:	Division of Reactor Safety II
To:	Tennessee Valley Authority
References
Download: ML16049A032 (32)

Text

ES-401, Rev. 9 BWR Examination Outline Form ES-401-1 Facility: Browns Ferry Date of Exam: December 2015 Tier Group RO K/A Category Points SRO-Only Points K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

Total A2 G*

Total

1.

Emergency &

Abnormal Plant Evolutions 1

N/A N/A 18 6

2 9

4 Tier Totals 27 10

2.

Plant Systems 1

28 5

2 10 3

Tier Totals 38 8

3. Generic Knowledge and Abilities Categories 1

2 3

4 10 1

2 3

4 7

1.

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., except for one category in Tier 3 of the SRO-only outline, the ATier 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 and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate K/A 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 (IR) 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 1 and 2 from the shaded systems and K/A categories.

7.

• The generic (G) K/As in Tiers 1 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.

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; if fuel 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

1. 1 does not apply). Use duplicate pages for RO and SRO-only exams.

9.

For Tier 3, select topics from Section 2 of the K/A 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.

3 3

4 4

3 3

1 2

1 1

1 1

4 5

5 5

4 4

2 2

3 2

3 3

2 3

2 2

2 1

1 1

1 1

1 1

1 2

1 1

3 3

4 3

4 4

3 4

4 3

3 3

3 2

2 2

2 1

2 4

3 7

2 1

6 4

10 3

2 2

1 5

3 20 27 38 7

26 12 3

3 5

8 0

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 9 T1G1 BWR EXAMINATION OUTLINE FORM ES-401-1 Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 Ability to perform specific system and integrated plant procedures during all modes of plant operation.

295001G2.1.23 4.3 4.4 Partial or Complete Loss of AC / 6 Station blackout: Plant-Specific.....................

295003AK1.06 3.8 4.0 Partial or Total Loss of DC Pwr / 6 Battery charger.......................................

295004AK2.01 3.1 3.1 Main Turbine Generator Trip / 3 Reactor SCRAM........................................

295005AK3.01 3.8 3.8 SCRAM / 1 RPS...................................................

295006AA1.01 4.2 4.2 Control Room Abandonment / 7 Reactor SCRAM.........................................

295016AK3.01 4.1 4.2 Partial or Total Loss of CCW / 8 System loads..........................................

295018AK2.01 3.3 3.4 Partial or Total Loss of Inst. Air / 8 Status of safety-related instrument air system loads (see AK2.1 - AK2.19)..................................

295019AA2.02 3.6 3.7 Loss of Shutdown Cooling / 4 Reactor recirculation.................................

295021AK2.07 3.1 3.2 295023AA1.04 Refueling Accidents / 8 Radiation Monitoring Equipment 3.4 3.7 High Drywell Pressure / 5 Standby gas treatment/FRVS: Plant-Specific...........

295024EA1.20 3.5 3.6 Page 1 of 2 1:34 PM 03/03/2015

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 9 T1G1 BWR EXAMINATION OUTLINE FORM ES-401-1 High Reactor Pressure / 3 Alternate rod insertion: Plant-Specific..............

295025EK3.06 4.2 4.4 Suppression Pool High Water Temp. /

5 Knowledge of the purpose and function of major system components and controls.

295026G2.1.28 4.1 4.1 295028EA2.03 High Drywell Temperature / 5 Reactor water level 3.7 3.9 Low Suppression Pool Wtr Lvl / 5 Ability to verify that the alarms are consistent with the plant conditions.

295030G2.4.46 4.2 4.2 Reactor Low Water Level / 2 Natural circulation: Plant-Specific..................

295031EK1.02 3.8 4.1 SCRAM Condition Present and Power Above APRM Downscale or Unknown

/ 1 Shutdown margin.......................................

295037EK1.07 3.4 3.8 High Off-site Release Rate / 9 Stack-gas monitoring system: Plant-Specific..........

295038EA1.01 3.9 4.2 Plant Fire On Site / 8 Actions contained in the abnormal procedure for plant fire on site 600000AK3.04 2.8 3.4 Generator Voltage and Electric Grid Distrurbancecs Operational status of offsite circuit 700000AA2.05 3.2 3.8 Page 2 of 2 1:34 PM 03/03/2015

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 9 T1G2 BWR EXAMINATION OUTLINE FORM ES-401-1 Low Reactor Water Level / 2 Ability to prioritize and interpret the significance of each annunciator or alarm.

295009G2.4.45 4.1 4.3 High Off-site Release Rate / 9 Condenser air removal system: Plant-Specific.........

295017AA1.06 3.2 3.2 Inadvertent Cont. Isolation / 5 & 7 Standby gas treatment system/FRVS: Plant-Specific....

295020AK2.11 3.2 3.4 295029EK2.02 High Suppression Pool Wtr Lvl / 5 HPCI: Plant specific..................................

3.4 3.6 High Secondary Containment Area Temperature / 5 Area temperature......................................

295032EA2.01 3.8 3.8 Secondary Containment Ventilation High Radiation / 9 Personnel protection..................................

295034EK1.01 3.8 4.1 Secondary Containment High Sump/Area Water Level / 5 Isolating affected systems............................

295036EK3.03 3.5 3.6 Page 1 of 1 1:34 PM 03/03/2015

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 9 T2G1 BWR EXAMINATION OUTLINE FORM ES-401-1 RHR/LPCI: Injection Mode Inadequate room cooling 203000A2.08 2.9 3.0 Shutdown Cooling Motor operated valves 205000K2.02 2.5 2.7 HPCI Reactor pressure control: BWR-2,3,4 206000K3.02 3.8 3.8 LPCS Ability to execute procedure steps.

209001G2.1.20 4.6 4.6 SLC Ability to shutdown the reactor in certain conditions 211000K3.01 4.3 4.4 RPS Perform individual control rod SCRAM testing 212000A4.13 3.4 3.6 IRM Changing detector position 215003K5.03 3.0 3.1 Source Range Monitor SRM channels/detectors 215004K2.01 2.6 2.8 APRM / LPRM IRM/APRM recorder 215005A4.01 3.2 3.1 APRM / LPRM Assignment of LPRM's to specific APRM channels 215005K5.06 2.5 2.6 RCIC Prevent water hammer: Plant-Specific 217000K4.01 2.8 2.8 Page 1 of 3 1:34 PM 03/03/2015

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 9 T2G1 BWR EXAMINATION OUTLINE FORM ES-401-1 ADS Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.

218000G2.4.30 2.7 4.1 ADS Nuclear boiler instrument system 218000K1.03 3.7 3.8 PCIS/Nuclear Steam Supply Shutoff Testability 223002K4.02 2.7 2.9 SRVs Air (Nitrogen) supply: Plant-Specific 239002K6.02 3.4 3.5 Reactor Water Level Control TDRFP speed: TDRFP 259002A1.07 2.6 2.6 SGTS Suppression pool 261000K1.03 2.9 3.1 AC Electrical Distribution Breaker tripping 262001A3.01 3.1 3.2 UPS (AC/DC)

Motor generator outputs 262002A1.02 2.5 2.9 UPS (AC/DC)

Static inverter 262002K6.03 2.7 2.9 DC Electrical Distribution Meters, dials, recorders, alarms and indicating lights 263000A3.01 3.2 3.3 EDGs Opening normal and/or alternate power to emergency bus 264000A2.06 3.4 3.4 Page 2 of 3 1:34 PM 03/03/2015

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 9 T2G1 BWR EXAMINATION OUTLINE FORM ES-401-1 Instrument Air Containment air system 300000K3.01 2.7 2.9 Instrument Air Filters 300000K5.13 2.9 2.9 Component Cooling Water Loss of CCW pump 400000A2.01 3.3 3.4 Component Cooling Water Valves 400000K6.01 2.7 2.8 Page 3 of 3 1:34 PM 03/03/2015

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 9 T2G2 BWR EXAMINATION OUTLINE FORM ES-401-1 CRD Hydraulic Reactor power 201001A3.06 2.8 2.8 Control Rod and Drive Mechanism CRD drive pressure 201003A1.02 2.8 2.8 Recirculation Flow Control Scoop tube operation: BWR-2,3,4 VFD's 202002A3.03 3.1 3.0 RBM Initiation point (30%): BWR-3,4,5 215002K4.03 2.9 3.0 Primary CTMT and Aux.

Ability to prioritize and interpret the significance of each annunciator or alarm.

223001G2.4.45 4.1 4.3 Fuel Handling Equipment Interlock failure 234000A2.01 3.3 3.7 Reactor/Turbine Pressure Regulator Turbine inlet pressure vs. turbine load 241000K5.05 2.8 2.9 Main Turbine Gen. / Aux.

Generator controls 245000A4.02 3.1 2.9 Reactor Feedwater RFP turbine seal system: TDRFP's-Only 259001K6.10 2.5 2.5 Radwaste Reactor building equipment drains: Plant-Specific 268000K1.03 2.6 2.9 Radiation Monitoring Stack gas radiation monitoring system 272000K2.03 2.5 2.8 Page 1 of 2 1:34 PM 03/03/2015

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 9 T2G2 BWR EXAMINATION OUTLINE FORM ES-401-1 Fire Protection Personnel protection 286000K3.02 3.2 3.4 Page 2 of 2 1:34 PM 03/03/2015

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 9 T3 BWR EXAMINATION OUTLINE FORM ES-401-1 Conduct of operations Knowledge of conduct of operations requirements.

G2.1.1 3.8 4.2 Conduct of operations Ability to execute procedure steps.

G2.1.20 4.6 4.6 Conduct of operations Knowledge of how to conduct system lineups, such as valves, breakers, switches, etc.

G2.1.29 4.1 4.0 Equipment Control Ability to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity.

G2.2.1 4.5 4.4 Equipment Control Knowledge of the process for controlling equipment configuration or status G2.2.14 3.9 4.3 Equipment Control Knowledge of the process for conducting special or infrequent tests G2.2.7 2.9 3.6 Radiation Control Knowledge of radiation monitoring systems G2.3.15 2.9 3.1 Radiation Control Ability to comply with radiation work permit requirements during normal or abnormal conditions G2.3.7 3.5 3.6 Emergency Procedures/Plans Knowledge of EOP entry conditions and immediate action steps.

G2.4.1 4.6 4.8 Emergency Procedures/Plans Knowledge of the parameters and logic used to assess the status of safety functions G2.4.21 4.0 4.6 Page 1 of 1 1:34 PM 03/03/2015

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 9 SRO T1G1 BWR EXAMINATION OUTLINE FORM ES-401-1 Partial or Complete Loss of AC / 6 Knowledge of the purpose and function of major system components and controls.

295003G2.1.28 4.1 4.1 Main Turbine Generator Trip / 3 Electrical distribution status........................

295005AA2.08 3.2 3.3 Control Room Abandonment / 7 Drywell pressure......................................

295016AA2.05 3.8 3.9 Partial or Total Loss of CCW / 8 System pressure.......................................

295018AA2.05 2.9 2.9 Partial or Total Loss of Inst. Air / 8 Instrument air system pressure........................

295019AA2.01 3.5 3.6 High Reactor Pressure / 3 Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.

295025G2.4.30 2.7 4.1 295031G2.1.25 Reactor Low Water Level / 2 Ability to interpret reference materials, such as graphs, curves, tables, etc.

3.9 4.2 Page 1 of 1 1:34 PM 03/03/2015

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 9 SRO T1G2 BWR EXAMINATION OUTLINE FORM ES-401-1 Loss of Main Condenser Vac / 3 Condenser vacuum/absolute pressure....................

295002AA2.01 2.9 3.1 295010AA2.06 High Drywell Pressure / 5 Drywell temperature 3.6 3.6 High Secondary Containment Area Radiation Levels / 9 Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

295033G2.4.47 4.2 4.2 Page 1 of 1 1:34 PM 03/03/2015

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 9 SRO T2G1 BWR EXAMINATION OUTLINE FORM ES-401-1 SLC Ability to use plant computer to evaluate system or component status.

211000G2.1.19 3.9 3.8 IRM Knowledge of limiting conditions for operations and safety limits.

215003G2.2.22 4.0 4.7 SGTS Low system flow 261000A2.01 2.9 3.1 EDGs Loss of off-site power during full-load testing 264000A2.07 3.5 3.7 Component Cooling Water High/low surge tank level 400000A2.02 2.8 3.0 Page 1 of 1 1:34 PM 03/03/2015

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 9 SRO T2G2 BWR EXAMINATION OUTLINE FORM ES-401-1 CRD Hydraulic Valve openings 201001A2.11 2.6 2.7 Control Rod and Drive Mechanism Reactor Scram 201003A2.05 4.1 4.1 Traversing In-core Probe 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 215001G2.2.44 4.2 4.4 Page 1 of 1 1:34 PM 03/03/2015

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 9 SRO T3 BWR EXAMINATION OUTLINE FORM ES-401-1 Conduct of operations Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, no-solo operation, maintenance of active license status, 10CFR55, etc..

G2.1.4 3.3 3.8 Conduct of operations Knowledge of primary and secondary chemistry limits G2.1.34 2.7 3.5 Equipment Control Knowledge of the process for controlling equipment configuration or status G2.2.14 3.9 4.3 Equipment Control Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.

G2.2.25 3.2 4.2 Radiation Control Knowledge of radiation monitoring systems G2.3.15 2.9 3.1 Emergency Procedures/Plans Knowledge of fire protection procedures.

G2.4.25 3.3 3.7 Emergency Procedures/Plans Knowledge of the emergency plan.

G2.4.29 3.1 4.4 Page 1 of 1 1:35 PM 03/03/2015

ILT 1510 Administrative Topics Outline Form ES-301-1 Facility:

Browns Ferry NPP Date of Examination:

11/16/2015 Examination Level: RO Operating Test Number:

15-10 Administrative Topic (see Note)

Type Code*

Describe activity to be performed Conduct of Operations - 1 D,R JPM - 557 Placing an RPS Channel in Trip Conduct of Operations - 2 N,R JPM - 675 Determine The Required Action For Control Rod Withdrawal (Calculate Period)

Equipment Control D,R JPM - 680 Perform Jet Pump Mismatch And Operability Radiation Control P,R JPM - 544 Review a Radiological Survey Map 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, Class(R)oom (D)irect from bank (< 3 for ROs; < 4 for SROs and RO retakes)

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

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

(S)imulator

ILT 1510 Administrative Topics Outline Form ES-301-1 Reactor Operator Conduct of Operation

1. JPM - 557

Title:

Placing an RPS Channel in Trip

==

Description:==

Given Turbine Stop Valve #3 limit switches failed the surveillance 3-SR-3.3.1.1.14(8I) Turbine Stop Valve Closure - RPS Trip (Channel A1/A2) and RPT Trip (System A & B) Logic System Functional Test.

The RO is going to determine the correct number and location of the RPS Fuses to remove to place the channel in the tripped condition.

The task is completed when both fuses are identified in to 3-OI-99 Reactor Protection System. A hard copy of 3-OI-99 will be provided.

K/A: 2.1.25; Ability to interpret reference materials, such as graphs, curves, tables, etc.

2. JPM - 675

Title:

Determine the required action for rod pull (calculate period)

==

Description:==

Provided initial IRM reading and a Doubling Time with a second set of IRM readings, the RO will calculate the current period and determine that it is faster than procedurally allowed and he will indicate that the rod should be reinserted.

K/A: 2.1.37; Knowledge of procedures, guidelines, or limitations associated with reactivity management.

Equipment Control

1. JPM - 680

Title:

Perform Jet Pump Mismatch and Operability SR (Alternate Path)

Description:

Provided with Jet Pump Instrument reading and a copy of the surveillance, the RO is going to determine 2-SR-3.4.2.1, Jet Pump Mismatch and Operability is not met for Jet Pump 15.

K/A: 2.2.12; Knowledge of surveillance procedures.

Radiation Control

1. JPM - 544

Title:

Review a Radiological Survey Map

==

Description:==

Provided an RWP and a Survey Map without equipment being identified, determine if the work in the area can be completed without exceeding exposure limits. The Candidate has to know equipment locations to correctly answer the questions in the JPM.

K/A: 2.3.7; Ability to comply with radiation work permit requirements during normal or abnormal conditions.

ILT 1501 Administrative Topics Outline Form ES-301-1 Facility:

Browns Ferry NPP Date of Examination:

11/16/2015 Examination Level: SRO Operating Test Number:

15-10 Administrative Topic (see Note)

Type Code Describe activity to be performed Conduct of Operations M,R JPM - 678 Shift Staffing - SRO Conduct of Operations N,R JPM - 677 Fuel Handling / fuel storage, determine compliance with guidelines.

Equipment Control M,R JPM - 676 Review Completed SR (SRO)

Radiation Control P,R JPM - 544 Review a Radiological Survey Map Emergency Plan M,R JPM - 679 Upgrade PAR on wind shift.

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, Class(R)oom (D)irect from bank (< 3 for ROs; < 4 for SROs and RO retakes)

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

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

(S)imulator

ILT 1501 Administrative Topics Outline Form ES-301-1 Senior Reactor Operator Conduct of Operation

1. JPM - 678

Title:

Shift Staffing - SRO

==

Description:==

Provided with a crew complement, the SRO determines if his staff meets the minimum shift requirements. The list of people appears to be below the minimum; however an SRO can be moved down to an RO position to fill the Crew Complement. The Emergency Responder position is also down one, so a callout is required.

K/A: 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.

2. JPM - 677

Title:

Fuel Handling fuel storage, determines compliance with guidelines.

==

Description:==

Provided with Nuclear Fuel Storage physical locations and configurations, the SRO must determine if the fuel is being stored within the guidance of the procedure. In this case there are new fuel bundles stored in locations that are not allowed.

K/A: 2.1.35 Knowledge of the fuel-handling responsibilities of SROs.

Equipment Control

1. JPM - 676

Title:

Review Completed SR (SRO)

==

Description:==

Provided a completed SR-3.4.2.1 that the Unit Operator completed on his shift, the SRO is to review the SR for completeness and accuracy. The SR is filled out incorrectly and identified as meeting the surveillance requirements, however the surveillance requirements are not met and the SRO must identify that and determine the correct LCO.

K/A: 2.2.22; Knowledge of limiting conditions for operations and safety limits Radiation Control

1. JPM - 544

Title:

Review a Radiological Survey Map

==

Description:==

Provided an RWP and a Survey Map without equipment being identified, determine if the work in the area can be completed without exceeding exposure limits. The Candidate has to know equipment locations to correctly answer the questions in the JPM.

K/A: 2.3.7; Ability to comply with radiation work permit requirements during normal or abnormal conditions.

Emergency Plan

1. JPM - 679

Title:

Upgrade PAR on wind shift

==

Description:==

Provided an EPIP-5 General Emergency declaration form and new information about meteorological conditions determine that the PAR needs to be adjusted to include a new sector for sheltering. That will require the SRO to fill out another form with the new information.

K/A: 2.4.44; Knowledge of emergency plan protective action recommendations

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:

Browns Ferry NPP Date of Examination: 11/16/2015 Exam Level: RO SRO-I SRO-U Operating Test No.: 15-10 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code*

Safety Function

a.

JPM 80A Respond to a Control Rod Drift In. IAW AOI-85-5 A,D,S 1

b.

JPM 276 EHC Auto Cooldown D,L,S 4

c.

JPM 672A Loss Of Reference APRM To Rod Block Monitor (RBM)

A,N,S 7

d.

JPM 257A EOI Appendix-6E Injection Subsystem Lineup CS System II A,D,EN,L,S 2

e.

JPM 670A EOI Appendix-11F Alternate RPV Pressure Control Systems: RFPT On Minimum Flow A,M S 3

f.

JPM 669 EOI-Appendix-14A N2 Makeup To Primary Containment N,S 5

g.

JPM 631 Restore Offsite Power to 4KV shutdown board at PNL 9-23 D,P,S 6

h.

JPM 190 Respond to Off-Gas Post-Treatment Radiation HI-HI-HI (RO Only)

A,M,P,S 9

In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i.

JPM 673 Automatic Start Failure of A & C Fire Pumps E,N 8

j.

JPM 674 Aligning Emergency EECW Makeup To Spent Fuel Pool E,N,R 9

k.

JPM 307 Start up and synchronize Unit 3 Preferred MMG Set D

6 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 (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams (R)CA (S)imulator 4-6/4-6/2-3

< 9/< 8/<4

> 1/> 1/>1

>1/>1/>1 (control room system)

>1/>1/>1

> 2/> 2/>1

< 3/< 3/< 2 (randomly selected)

>1/>1/>1

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

a. JPM 80A

Title:

Respond to a Control Rod Drift In. IAW AOI-85-5

==

Description:==

While performing Surveillance 3.1.3.3, Control Rod Exercise Test for partially withdrawn control rods the ATC Operator will respond to a single control rod drift per AOI-85-5, Rod Drift In. as he continues with the surveillance multiple control rods will begin to drift in and the ATC Operator will respond by inserting a manual scram per AOI 5, Rod Drift In. Once scram report is given the JPM will end.

K/A: 201002 Reactor Manual Control System A2.02; Ability to (a) predict the impacts of the following on the REACTOR MANUAL CONTROL SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Rod Drift Alarm

b. JPM 276

Title:

EHC Auto Cooldown

==

Description:==

The BOP Operator will commence a cooldown of the reactor plant to 20 psig utilizing Main Turbine Bypass Valves with EHC Auto Cooldown function per OI-47, Turbine-Generator System. Once the initial cooldown has commenced the US will direct the BOP Operator to adjust the setpoint to 100 psig. After setpoint has been changed the JPM will end.

K/A: 239001Main and Reheat Steam System: A4.09 Ability to manually operate and/or monitor in the control room: Reactor pressure

c. JPM 672A

Title:

Loss Of Reference APRM To Rod Block Monitor (RBM)

==

Description:==

The ATC Operator will begin raising reactor power to achieve 40%

per Control Rod Movement Data Sheet for placing Feedwater Heaters and Moisture Separator Drain System in service. As reactor power is raised, APRM Ch 2 will fail downscale and impose a Control Rod Withdrawal Block which requires the APRM to be bypassed, to allow control rod movement. Once the Control Rod Withdrawal Block is cleared, and rod movement has continued, the JPM will end.

K/A: 215002 Rod Block Monitor System A2.03; Ability to (a) predict the impacts of the following on the ROD BLOCK MONITOR SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of associated reference APRM channel: BWR-3,4,5

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

d. JPM 257A

Title:

EOI Appendix-6E Injection Subsystem Lineup CS System II

==

Description:==

The ATC Operator has been directed to inject water into the RPV and restore water level using Core Spray System II per EOI-Appendix-6E, Injection Subsystems Lineup Core Spray System II. The operator will determine that FCV-75-51, CORE SPRAY SYS II OUTBD INJECT VALVE and FCV-75-53, CORE SPRAY SYS II INBD INJECT VALVE are not in proper alignment. Once the alignment is corrected, injection flow to RPV is established and reactor water level is > TAF

(-162 in) the JPM will end.

K/A: 209001 Low Pressure Core Spray System A4.08 Ability to manually operate and/or monitor in the control room: Reactor water level

e. JPM 670A

Title:

EOI Appendix-11F Alternate RPV Pressure Control Systems: RFPT On Minimum Flow

==

Description:==

The BOP Operator has been directed to lower reactor pressure to 800 - 1000 psig by placing A RFPT in Alternate Pressure Control per EOI-Appendix-11F. As speed reaches 350 RPM the A RFPT will trip and require the operator to start B RFPT for pressure control. Once 2B RFPT is in service and reactor pressure is lowering the JPM will end.

K/A: 239001 Main and Reheat Steam System A1.01 Ability to predict and/or monitor changes in parameters associated with operating the MAIN AND REHEAT STEAM SYSTEM controls including: Main steam pressure

f. JPM 669

Title:

EOI-Appendix-14A N2 Makeup To Primary Containment

==

Description:==

The BOP Operator has been directed to lower Drywell Hydrogen Concentration per EOI-Appendix-14A. The operator will need to determine that Drywell Hydrogen Concentration is greater than Suppression Chamber Hydrogen Concentration and begin purging the Drywell. Once Drywell Hydrogen Concentration begins to lower the JPM will end.

K/A: 223001 Primary Containment System and Auxiliaries A2.04; Ability to (a) predict the impacts of the following on the PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: High containment/drywell hydrogen concentration

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

g. JPM 631

Title:

Restore Offsite Power to 4KV shutdown board at PNL 9-23

==

Description:==

The BOP Operator has been directed to restore offsite power to 4KV Shutdown Board IAW 0-OI-82. The operator will parallel offsite to the running Diesel Generator, Once the Diesel Generator is separated from the grid the JPM will end.

K/A: 262001 A.C. Electrical Distribution; A4.02 Ability to manually operate and/or monitor in the control room: Synchroscope, including understanding of running and incoming voltages

h. JPM 190

Title:

Respond to Off-Gas Post-Treatment Radiation HI-HI-HI(RO Only)

==

Description:==

The BOP Operator will respond to OFF-GAS POST TREATMENT RADIATION HI-HI-HI annunciator. The operator will close FCV 28, OFF-GAS SYSTEM ISOLATION VALVE and then perform immediate actions of AOI-66-2, Off-gas Post-treatment Radiation Hi-Hi-Hi. The operator will reduce core flow to 50-60% and then insert a manual reactor scram. The operator will continue with subsequent actions. Once the standby Stack Dilution fan is started the JPM will end.

K/A: 271000 Offgas System: A2.16; Ability to (a) predict the impacts of the following on the OFFGAS SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of offgas system loop seals (2.9/3.2)

i. JPM 673A

Title:

Automatic Start Failure of A & C Fire Pumps

==

Description:==

The Operator has been directed to start A and C Electric Fire Pumps per 0-OI-26, High Pressure Fire Protection System from the 4KV Shutdown Boards. The operator will start A and C Fire Pumps from their local breaker cubicles. Once both fire pumps have been started the JPM will end.

K/A: 286000 Fire Protection System A2.08; Ability to (a) predict the impacts of the following on the FIRE PROTECTION SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Failure to actuate when required

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

j. JPM 674

Title:

Aligning Emergency EECW Makeup To Spent Fuel Pool

==

Description:==

The Operator has been directed to align EECW Makeup to Unit 2 Spent Fuel Pool per 2-AOI-78-1 Attachment 2. The operator will locate and align EECW to Spent Fuel Pool by utilizing fire hoses and isolation valves. Once the lineup is made and water is flowing into the Spent Fuel Pool the JPM will end.

K/A: 233000 Fuel Pool Cooling and Clean-up; A2.02; Ability to (a) predict the impacts of the following on the FUEL POOL COOLING AND CLEAN-UP; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Low pool level

k. JPM 307

Title:

Start up and synchronize Unit 3 Preferred MMG Set

==

Description:==

The Operator has been directed to synchronize the Unit 3 Unit Preferred MMG Set per 0-OI-57C. The operator will perform local operations to synchronize U3 MMG set to the Battery Board. Once Unit 3 MMG Set has been transferred per 0-OI-57C the JPM will end.

K/A: 262002 Uninterruptable Power Supply (A.C./D.C.) A1.02; Ability to predict and/or monitor changes in parameters associated with operating the UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.)

controls including: Motor generator outputs

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:

Browns Ferry NPP Date of Examination: 11/16/2015 Exam Level: RO SRO-I SRO-U Operating Test No.: 15-10 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code*

Safety Function

a.

JPM 80A Respond to a Control Rod Drift In. IAW AOI-85-5 A,D,S 1

b.

JPM 276 EHC Auto Cooldown D,L,S 4

c.

JPM 672A Loss Of Reference APRM To Rod Block Monitor (RBM)

A,N,S 7

d.

JPM 257A EOI Appendix-6E Injection Subsystem Lineup CS System II A,D,EN,L,S 2

e.

JPM 670A EOI Appendix-11F Alternate RPV Pressure Control Systems: RFPT On Minimum Flow A,M S 3

f.

JPM 669 EOI-Appendix-14A N2 Makeup To Primary Containment N,S 5

g.

JPM 631 Restore Offsite Power to 4KV shutdown board at PNL 9-23 D,P,S 6

In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i.

JPM 673 Automatic Start Failure of A & C Fire Pumps E,N 8

j.

JPM 674 Aligning Emergency EECW Makeup To Spent Fuel Pool E,N,R 9

k.

JPM 307 Start up and synchronize Unit 3 Preferred MMG Set D

6 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 (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams (R)CA (S)imulator 4-6/4-6/2-3

< 9/< 8/<4

> 1/> 1/>1

>1/>1/>1 (control room system)

>1/>1/>1

> 2/> 2/>1

< 3/< 3/< 2 (randomly selected)

>1/>1/>1

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

a. JPM 80A

Title:

Respond to a Control Rod Drift In. IAW AOI-85-5

==

Description:==

While performing Surveillance 3.1.3.3, Control Rod Exercise Test for partially withdrawn control rods, the ATC Operator will respond to a single control rod drift per AOI-85-5, Rod Drift In. As he continues with the surveillance, multiple control rods will begin to drift in and the ATC Operator will respond by inserting a manual scram per AOI 5, Rod Drift In. Once scram report is given the JPM will end.

K/A: 201002 Reactor Manual Control System A2.02; Ability to (a) predict the impacts of the following on the REACTOR MANUAL CONTROL SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Rod Drift Alarm

b. JPM 276

Title:

EHC Auto Cooldown

==

Description:==

The BOP Operator will commence a cooldown of the reactor plant to 20 psig utilizing Main Turbine Bypass Valves with EHC Auto Cooldown function per OI-47, Turbine-Generator System. Once the initial cooldown has commenced the US will direct the BOP Operator to adjust the setpoint to 100 psig. After setpoint has been changed the JPM will end.

K/A: 239001Main and Reheat Steam System: A4.09 Ability to manually operate and/or monitor in the control room: Reactor pressure

c. JPM 672

Title:

Loss Of Reference APRM To Rod Block Monitor (RBM)

==

Description:==

The ATC Operator will begin raising reactor power to achieve 40%

per Control Rod Movement Data Sheet for placing Feedwater Heaters and Moisture Separator Drain System in service. As reactor power is raised, APRM Ch 2 will fail downscale and impose a Control Rod Withdrawal Block which requires the APRM to be bypassed to allow control rod movement. Once the Control Rod Withdrawal Block is cleared, and rod movement has continued, the JPM will end.

K/A: 215002 Rod Block Monitor System A2.03; Ability to (a) predict the impacts of the following on the ROD BLOCK MONITOR SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of associated reference APRM channel: BWR-3,4,5

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

d. JPM 257A

Title:

EOI Appendix-6E Injection Subsystem Lineup CS System II

==

Description:==

The ATC Operator has been directed to in water into the RPV and restore water level using Core Spray System II per EOI-Appendix-6E, Injection Subsystems Lineup Core Spray System II. The operator will determine that FCV-75-51, CORE SPRAY SYS II OUTBD INJECT VALVE and FCV-75-53, CORE SPRAY SYS II INBD INJECT VALVE are not in proper alignment. Once the alignment is corrected, injection flow to RPV is established and reactor water level is > TAF

(-162 in) the JPM will end.

K/A: 209001 Low Pressure Core Spray System A4.08 Ability to manually operate and/or monitor in the control room: Reactor water level

e. JPM 670A

Title:

EOI Appendix-11F Alternate RPV Pressure Control Systems: RFPT On Minimum Flow

==

Description:==

The BOP Operator has been directed to lower reactor pressure to 800 - 1000 psig by placing A RFPT in Alternate Pressure Control per EOI-Appendix-11F. As speed reaches 350 RPM the A RFPT will trip and require the operator to start B RFPT for pressure control. Once 2B RFPT is in service and reactor pressure is lowering the JPM will end.

K/A: 239001 Main and Reheat Steam System A1.01 Ability to predict and/or monitor changes in parameters associated with operating the MAIN AND REHEAT STEAM SYSTEM controls including: Main steam pressure

f. JPM 669

Title:

EOI-Appendix-14A N2 Makeup To Primary Containment With

==

Description:==

The BOP Operator has been directed to lower Drywell Hydrogen Concentration per EOI-Appendix-14A. The operator will need to determine that Drywell Hydrogen Concentration is greater than Suppression Chamber Hydrogen Concentration and begin purging the Drywell. Once Drywell Hydrogen Concentration begins to lower the JPM will end.

K/A: 223001 Primary Containment System and Auxiliaries A2.04; Ability to (a) predict the impacts of the following on the PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: High containment/drywell hydrogen concentration

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

g. JPM 631

Title:

Restore Offsite Power to 4KV shutdown board at PNL 9-23

==

Description:==

The BOP Operator has been directed to restore offsite power to 4KV Shutdown Board IAW 0-OI-82. The operator will parallel offsite to the running Diesel Generator, Once the Diesel Generator is separated from the grid the JPM will end.

K/A: 262001 A.C. Electrical Distribution A4.02 Ability to manually operate and/or monitor in the control room: Synchroscope, including understanding of running and incoming voltages

i. JPM 673A

Title:

Automatic Start Failure of A & C Fire Pumps

==

Description:==

The Operator has been directed to start A and C Electric Fire Pumps per 0-OI-26, High Pressure Fire Protection System from the 4KV Shutdown Boards. The operator will start A and C Fire Pumps from their local breaker cubicles. Once both fire pumps have been started the JPM will end.

K/A: 286000 Fire Protection System A2.08; Ability to (a) predict the impacts of the following on the FIRE PROTECTION SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Failure to actuate when required

j. JPM 674

Title:

Aligning Emergency EECW Makeup To Spent Fuel Pool

==

Description:==

The Operator has been directed to align EECW Makeup to Unit 2 Spent Fuel Pool per 2-AOI-78-1 Attachment 2. The operator will locate and align EECW to Spent Fuel Pool by utilizing fire hoses and isolation valves. Once the lineup is made and water is flowing into the Spent Fuel Pool the JPM will end.

K/A: 233000 Fuel Pool Cooling and Clean-up; A2.02; Ability to (a) predict the impacts of the following on the FUEL POOL COOLING AND CLEAN-UP; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Low pool level

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

k. JPM 307

Title:

Start up and synchronize Unit 3 Preferred MMG Set

==

Description:==

The Operator has been directed to synchronize the Unit 3 Unit Preferred MMG Set per 0-OI-57C. The operator will perform local operations to synchronize U3 MMG set to the Battery Board. Once Unit 3 MMG Set has been transferred per 0-OI-57C the JPM will end.

K/A: 262002 Uninterruptable Power Supply (A.C./D.C.) A1.02; Ability to predict and/or monitor changes in parameters associated with operating the UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.)

controls including: Motor generator outputs

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:

Browns Ferry NPP Date of Examination:

11/16/2015 Exam Level: RO SRO-I SRO-U Operating Test No.:

15-10 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code*

Safety Function

b.

JPM 276 EHC Auto Cooldown D,L,S 4

c.

JPM 672A Loss Of Reference APRM To Rod Block Monitor (RBM)

A,N,S 7

d.

JPM 257A EOI Appendix-6E Injection Subsystem Lineup CS System II A,D,EN,L,S 2

In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i.

JPM 673 Automatic Start Failure of A & C Fire Pumps E,N 8

j.

JPM 674 Aligning Emergency EECW Makeup To Spent Fuel Pool E,N,R 9

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 (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams (R)CA (S)imulator 4-6/4-6/2-3

< 9/< 8/<4

> 1/> 1/>1

>1/>1/>1 (control room system)

>1/>1/>1

> 2/> 2/>1

< 3/< 3/< 2 (randomly selected)

>1/>1/>1

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

b. JPM 276

Title:

EHC Auto Cooldown

==

Description:==

The BOP Operator will begin commence a cooldown of the reactor plant to 20psig utilizing Main Turbine Bypass Valves with EHC Auto Cooldown function per OI-47, Turbine-Generator System. Once the initial cooldown has commenced the US will direct the BOP Operator to adjust the setpoint to 100 psig. After setpoint has been changed the JPM will end.

K/A: 239001Main and Reheat Steam System: A4.09 Ability to manually operate and/or monitor in the control room: Reactor pressure

c. JPM 672A

Title:

Loss Of Reference APRM To Rod Block Monitor (RBM)

==

Description:==

The ATC Operator will begin raising reactor power to achieve 40%

per Control Rod Movement Data Sheet for placing Feedwater Heaters and Moisture Separator Drain System in service. As reactor power is raised, APRM Ch 2 will fail downscale and impose a Control Rod Withdrawal Block which requires the APRM to be bypassed to allow control rod movement. Once the Control Rod Withdrawal Block is cleared and rod movement has continued the JPM will end.

K/A: 215002 Rod Block Monitor System A2.03; Ability to (a) predict the impacts of the following on the ROD BLOCK MONITOR SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of associated reference APRM channel: BWR-3,4,5

d. JPM 257A

Title:

EOI Appendix-6E Injection Subsystem Lineup CS System II

==

Description:==

The ATC Operator has been directed to inject water into the RPV and restore water level using Core Spray System II per EOI-Appendix-6E, Injection Subsystems Lineup Core Spray System II. The operator will determine that FCV-75-51, CORE SPRAY SYS II OUTBD INJECT VALVE and FCV-75-53, CORE SPRAY SYS II INBD INJECT VALVE are not in proper alignment. Once the alignment is corrected, injection flow to RPV is established and reactor water level is > TAF

(-162 in) the JPM will end.

K/A: 209001 Low Pressure Core Spray System A4.08 Ability to manually operate and/or monitor in the control room: Reactor water level

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

i. JPM 673A

Title:

Automatic Start Failure of A & C Fire Pumps

==

Description:==

The Operator has been directed to start A and C Electric Fire Pumps per 0-OI-26, High Pressure Fire Protection System from the 4KV Shutdown Boards. The operator will start A and C Fire Pumps from their local breaker cubicles. Once both fire pumps have been started the JPM will end.

K/A: 286000 Fire Protection System A2.08; Ability to (a) predict the impacts of the following on the FIRE PROTECTION SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Failure to actuate when required

j. JPM 674

Title:

Aligning Emergency EECW Makeup To Spent Fuel Pool

==

Description:==

The Operator has been directed to align EECW Makeup to Unit 2 Spent Fuel Pool per 2-AOI-78-1 Attachment 2. The operator will locate and align EECW to Spent Fuel Pool by utilizing fire hoses and isolation valves. Once the lineup is made and water is flowing into the Spent Fuel Pool the JPM will end.

K/A: 233000 Fuel Pool Cooling and Clean-up; A2.02; Ability to (a) predict the impacts of the following on the FUEL POOL COOLING AND CLEAN-UP; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Low pool level

ES-401, Rev. 9 BWR Examination Outline Form ES-401-1 Facility: Browns Ferry Date of Exam: December 2015 Tier Group RO K/A Category Points SRO-Only Points K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

Total A2 G*

Total

1.

Emergency &

Abnormal Plant Evolutions 1

N/A N/A 18 6

2 9

4 Tier Totals 27 10

2.

Plant Systems 1

28 5

2 10 3

Tier Totals 38 8

3. Generic Knowledge and Abilities Categories 1

2 3

4 10 1

2 3

4 7

1.

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., except for one category in Tier 3 of the SRO-only outline, the ATier 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 and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate K/A 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 (IR) 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 1 and 2 from the shaded systems and K/A categories.

7.

• The generic (G) K/As in Tiers 1 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.

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; if fuel 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

1. 1 does not apply). Use duplicate pages for RO and SRO-only exams.

9.

For Tier 3, select topics from Section 2 of the K/A 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.

3 3

4 4

3 3

1 2

1 1

1 1

4 5

5 5

4 4

2 2

3 2

3 3

2 3

2 2

2 1

1 1

1 1

1 1

1 2

1 1

3 3

4 3

4 4

3 4

4 3

3 3

3 2

2 2

2 1

2 4

3 7

2 1

6 4

10 3

2 2

1 5

3 20 27 38 7

26 12 3

3 5

8 0

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 9 T1G1 BWR EXAMINATION OUTLINE FORM ES-401-1 Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 Ability to perform specific system and integrated plant procedures during all modes of plant operation.

295001G2.1.23 4.3 4.4 Partial or Complete Loss of AC / 6 Station blackout: Plant-Specific.....................

295003AK1.06 3.8 4.0 Partial or Total Loss of DC Pwr / 6 Battery charger.......................................

295004AK2.01 3.1 3.1 Main Turbine Generator Trip / 3 Reactor SCRAM........................................

295005AK3.01 3.8 3.8 SCRAM / 1 RPS...................................................

295006AA1.01 4.2 4.2 Control Room Abandonment / 7 Reactor SCRAM.........................................

295016AK3.01 4.1 4.2 Partial or Total Loss of CCW / 8 System loads..........................................

295018AK2.01 3.3 3.4 Partial or Total Loss of Inst. Air / 8 Status of safety-related instrument air system loads (see AK2.1 - AK2.19)..................................

295019AA2.02 3.6 3.7 Loss of Shutdown Cooling / 4 Reactor recirculation.................................

295021AK2.07 3.1 3.2 295023AA1.04 Refueling Accidents / 8 Radiation Monitoring Equipment 3.4 3.7 High Drywell Pressure / 5 Standby gas treatment/FRVS: Plant-Specific...........

295024EA1.20 3.5 3.6 Page 1 of 2 1:34 PM 03/03/2015

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 9 T1G1 BWR EXAMINATION OUTLINE FORM ES-401-1 High Reactor Pressure / 3 Alternate rod insertion: Plant-Specific..............

295025EK3.06 4.2 4.4 Suppression Pool High Water Temp. /

5 Knowledge of the purpose and function of major system components and controls.

295026G2.1.28 4.1 4.1 295028EA2.03 High Drywell Temperature / 5 Reactor water level 3.7 3.9 Low Suppression Pool Wtr Lvl / 5 Ability to verify that the alarms are consistent with the plant conditions.

295030G2.4.46 4.2 4.2 Reactor Low Water Level / 2 Natural circulation: Plant-Specific..................

295031EK1.02 3.8 4.1 SCRAM Condition Present and Power Above APRM Downscale or Unknown

/ 1 Shutdown margin.......................................

295037EK1.07 3.4 3.8 High Off-site Release Rate / 9 Stack-gas monitoring system: Plant-Specific..........

295038EA1.01 3.9 4.2 Plant Fire On Site / 8 Actions contained in the abnormal procedure for plant fire on site 600000AK3.04 2.8 3.4 Generator Voltage and Electric Grid Distrurbancecs Operational status of offsite circuit 700000AA2.05 3.2 3.8 Page 2 of 2 1:34 PM 03/03/2015

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 9 T1G2 BWR EXAMINATION OUTLINE FORM ES-401-1 Low Reactor Water Level / 2 Ability to prioritize and interpret the significance of each annunciator or alarm.

295009G2.4.45 4.1 4.3 High Off-site Release Rate / 9 Condenser air removal system: Plant-Specific.........

295017AA1.06 3.2 3.2 Inadvertent Cont. Isolation / 5 & 7 Standby gas treatment system/FRVS: Plant-Specific....

295020AK2.11 3.2 3.4 295029EK2.02 High Suppression Pool Wtr Lvl / 5 HPCI: Plant specific..................................

3.4 3.6 High Secondary Containment Area Temperature / 5 Area temperature......................................

295032EA2.01 3.8 3.8 Secondary Containment Ventilation High Radiation / 9 Personnel protection..................................

295034EK1.01 3.8 4.1 Secondary Containment High Sump/Area Water Level / 5 Isolating affected systems............................

295036EK3.03 3.5 3.6 Page 1 of 1 1:34 PM 03/03/2015

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 9 T2G1 BWR EXAMINATION OUTLINE FORM ES-401-1 RHR/LPCI: Injection Mode Inadequate room cooling 203000A2.08 2.9 3.0 Shutdown Cooling Motor operated valves 205000K2.02 2.5 2.7 HPCI Reactor pressure control: BWR-2,3,4 206000K3.02 3.8 3.8 LPCS Ability to execute procedure steps.

209001G2.1.20 4.6 4.6 SLC Ability to shutdown the reactor in certain conditions 211000K3.01 4.3 4.4 RPS Perform individual control rod SCRAM testing 212000A4.13 3.4 3.6 IRM Changing detector position 215003K5.03 3.0 3.1 Source Range Monitor SRM channels/detectors 215004K2.01 2.6 2.8 APRM / LPRM IRM/APRM recorder 215005A4.01 3.2 3.1 APRM / LPRM Assignment of LPRM's to specific APRM channels 215005K5.06 2.5 2.6 RCIC Prevent water hammer: Plant-Specific 217000K4.01 2.8 2.8 Page 1 of 3 1:34 PM 03/03/2015

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 9 T2G1 BWR EXAMINATION OUTLINE FORM ES-401-1 ADS Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.

218000G2.4.30 2.7 4.1 ADS Nuclear boiler instrument system 218000K1.03 3.7 3.8 PCIS/Nuclear Steam Supply Shutoff Testability 223002K4.02 2.7 2.9 SRVs Air (Nitrogen) supply: Plant-Specific 239002K6.02 3.4 3.5 Reactor Water Level Control TDRFP speed: TDRFP 259002A1.07 2.6 2.6 SGTS Suppression pool 261000K1.03 2.9 3.1 AC Electrical Distribution Breaker tripping 262001A3.01 3.1 3.2 UPS (AC/DC)

Motor generator outputs 262002A1.02 2.5 2.9 UPS (AC/DC)

Static inverter 262002K6.03 2.7 2.9 DC Electrical Distribution Meters, dials, recorders, alarms and indicating lights 263000A3.01 3.2 3.3 EDGs Opening normal and/or alternate power to emergency bus 264000A2.06 3.4 3.4 Page 2 of 3 1:34 PM 03/03/2015

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 9 T2G1 BWR EXAMINATION OUTLINE FORM ES-401-1 Instrument Air Containment air system 300000K3.01 2.7 2.9 Instrument Air Filters 300000K5.13 2.9 2.9 Component Cooling Water Loss of CCW pump 400000A2.01 3.3 3.4 Component Cooling Water Valves 400000K6.01 2.7 2.8 Page 3 of 3 1:34 PM 03/03/2015

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 9 T2G2 BWR EXAMINATION OUTLINE FORM ES-401-1 CRD Hydraulic Reactor power 201001A3.06 2.8 2.8 Control Rod and Drive Mechanism CRD drive pressure 201003A1.02 2.8 2.8 Recirculation Flow Control Scoop tube operation: BWR-2,3,4 VFD's 202002A3.03 3.1 3.0 RBM Initiation point (30%): BWR-3,4,5 215002K4.03 2.9 3.0 Primary CTMT and Aux.

Ability to prioritize and interpret the significance of each annunciator or alarm.

223001G2.4.45 4.1 4.3 Fuel Handling Equipment Interlock failure 234000A2.01 3.3 3.7 Reactor/Turbine Pressure Regulator Turbine inlet pressure vs. turbine load 241000K5.05 2.8 2.9 Main Turbine Gen. / Aux.

Generator controls 245000A4.02 3.1 2.9 Reactor Feedwater RFP turbine seal system: TDRFP's-Only 259001K6.10 2.5 2.5 Radwaste Reactor building equipment drains: Plant-Specific 268000K1.03 2.6 2.9 Radiation Monitoring Stack gas radiation monitoring system 272000K2.03 2.5 2.8 Page 1 of 2 1:34 PM 03/03/2015

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 9 T2G2 BWR EXAMINATION OUTLINE FORM ES-401-1 Fire Protection Personnel protection 286000K3.02 3.2 3.4 Page 2 of 2 1:34 PM 03/03/2015

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 9 T3 BWR EXAMINATION OUTLINE FORM ES-401-1 Conduct of operations Knowledge of conduct of operations requirements.

G2.1.1 3.8 4.2 Conduct of operations Ability to execute procedure steps.

G2.1.20 4.6 4.6 Conduct of operations Knowledge of how to conduct system lineups, such as valves, breakers, switches, etc.

G2.1.29 4.1 4.0 Equipment Control Ability to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity.

G2.2.1 4.5 4.4 Equipment Control Knowledge of the process for controlling equipment configuration or status G2.2.14 3.9 4.3 Equipment Control Knowledge of the process for conducting special or infrequent tests G2.2.7 2.9 3.6 Radiation Control Knowledge of radiation monitoring systems G2.3.15 2.9 3.1 Radiation Control Ability to comply with radiation work permit requirements during normal or abnormal conditions G2.3.7 3.5 3.6 Emergency Procedures/Plans Knowledge of EOP entry conditions and immediate action steps.

G2.4.1 4.6 4.8 Emergency Procedures/Plans Knowledge of the parameters and logic used to assess the status of safety functions G2.4.21 4.0 4.6 Page 1 of 1 1:34 PM 03/03/2015

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 9 SRO T1G1 BWR EXAMINATION OUTLINE FORM ES-401-1 Partial or Complete Loss of AC / 6 Knowledge of the purpose and function of major system components and controls.

295003G2.1.28 4.1 4.1 Main Turbine Generator Trip / 3 Electrical distribution status........................

295005AA2.08 3.2 3.3 Control Room Abandonment / 7 Drywell pressure......................................

295016AA2.05 3.8 3.9 Partial or Total Loss of CCW / 8 System pressure.......................................

295018AA2.05 2.9 2.9 Partial or Total Loss of Inst. Air / 8 Instrument air system pressure........................

295019AA2.01 3.5 3.6 High Reactor Pressure / 3 Knowledge of events related to system operations/status that must be reported to internal orginizations or outside agencies.

295025G2.4.30 2.7 4.1 295031G2.1.25 Reactor Low Water Level / 2 Ability to interpret reference materials, such as graphs, curves, tables, etc.

3.9 4.2 Page 1 of 1 1:34 PM 03/03/2015

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 9 SRO T1G2 BWR EXAMINATION OUTLINE FORM ES-401-1 Loss of Main Condenser Vac / 3 Condenser vacuum/absolute pressure....................

295002AA2.01 2.9 3.1 295010AA2.06 High Drywell Pressure / 5 Drywell temperature 3.6 3.6 High Secondary Containment Area Radiation Levels / 9 Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

295033G2.4.47 4.2 4.2 Page 1 of 1 1:34 PM 03/03/2015

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 9 SRO T2G1 BWR EXAMINATION OUTLINE FORM ES-401-1 SLC Ability to use plant computer to evaluate system or component status.

211000G2.1.19 3.9 3.8 IRM Knowledge of limiting conditions for operations and safety limits.

215003G2.2.22 4.0 4.7 SGTS Low system flow 261000A2.01 2.9 3.1 EDGs Loss of off-site power during full-load testing 264000A2.07 3.5 3.7 Component Cooling Water High/low surge tank level 400000A2.02 2.8 3.0 Page 1 of 1 1:34 PM 03/03/2015

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 9 SRO T2G2 BWR EXAMINATION OUTLINE FORM ES-401-1 CRD Hydraulic Valve openings 201001A2.11 2.6 2.7 Control Rod and Drive Mechanism Reactor Scram 201003A2.05 4.1 4.1 Traversing In-core Probe 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 215001G2.2.44 4.2 4.4 Page 1 of 1 1:34 PM 03/03/2015

NAME / SAFETY FUNCTION:

K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC:

KA RO SRO IR ES-401, REV 9 SRO T3 BWR EXAMINATION OUTLINE FORM ES-401-1 Conduct of operations Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, no-solo operation, maintenance of active license status, 10CFR55, etc..

G2.1.4 3.3 3.8 Conduct of operations Knowledge of primary and secondary chemistry limits G2.1.34 2.7 3.5 Equipment Control Knowledge of the process for controlling equipment configuration or status G2.2.14 3.9 4.3 Equipment Control Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.

G2.2.25 3.2 4.2 Radiation Control Knowledge of radiation monitoring systems G2.3.15 2.9 3.1 Emergency Procedures/Plans Knowledge of fire protection procedures.

G2.4.25 3.3 3.7 Emergency Procedures/Plans Knowledge of the emergency plan.

G2.4.29 3.1 4.4 Page 1 of 1 1:35 PM 03/03/2015

ILT 1510 Administrative Topics Outline Form ES-301-1 Facility:

Browns Ferry NPP Date of Examination:

11/16/2015 Examination Level: RO Operating Test Number:

15-10 Administrative Topic (see Note)

Type Code*

Describe activity to be performed Conduct of Operations - 1 D,R JPM - 557 Placing an RPS Channel in Trip Conduct of Operations - 2 N,R JPM - 675 Determine The Required Action For Control Rod Withdrawal (Calculate Period)

Equipment Control D,R JPM - 680 Perform Jet Pump Mismatch And Operability Radiation Control P,R JPM - 544 Review a Radiological Survey Map 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, Class(R)oom (D)irect from bank (< 3 for ROs; < 4 for SROs and RO retakes)

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

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

(S)imulator

ILT 1510 Administrative Topics Outline Form ES-301-1 Reactor Operator Conduct of Operation

1. JPM - 557

Title:

Placing an RPS Channel in Trip

==

Description:==

Given Turbine Stop Valve #3 limit switches failed the surveillance 3-SR-3.3.1.1.14(8I) Turbine Stop Valve Closure - RPS Trip (Channel A1/A2) and RPT Trip (System A & B) Logic System Functional Test.

The RO is going to determine the correct number and location of the RPS Fuses to remove to place the channel in the tripped condition.

The task is completed when both fuses are identified in to 3-OI-99 Reactor Protection System. A hard copy of 3-OI-99 will be provided.

K/A: 2.1.25; Ability to interpret reference materials, such as graphs, curves, tables, etc.

2. JPM - 675

Title:

Determine the required action for rod pull (calculate period)

==

Description:==

Provided initial IRM reading and a Doubling Time with a second set of IRM readings, the RO will calculate the current period and determine that it is faster than procedurally allowed and he will indicate that the rod should be reinserted.

K/A: 2.1.37; Knowledge of procedures, guidelines, or limitations associated with reactivity management.

Equipment Control

1. JPM - 680

Title:

Perform Jet Pump Mismatch and Operability SR (Alternate Path)

Description:

Provided with Jet Pump Instrument reading and a copy of the surveillance, the RO is going to determine 2-SR-3.4.2.1, Jet Pump Mismatch and Operability is not met for Jet Pump 15.

K/A: 2.2.12; Knowledge of surveillance procedures.

Radiation Control

1. JPM - 544

Title:

Review a Radiological Survey Map

==

Description:==

Provided an RWP and a Survey Map without equipment being identified, determine if the work in the area can be completed without exceeding exposure limits. The Candidate has to know equipment locations to correctly answer the questions in the JPM.

K/A: 2.3.7; Ability to comply with radiation work permit requirements during normal or abnormal conditions.

ILT 1501 Administrative Topics Outline Form ES-301-1 Facility:

Browns Ferry NPP Date of Examination:

11/16/2015 Examination Level: SRO Operating Test Number:

15-10 Administrative Topic (see Note)

Type Code Describe activity to be performed Conduct of Operations M,R JPM - 678 Shift Staffing - SRO Conduct of Operations N,R JPM - 677 Fuel Handling / fuel storage, determine compliance with guidelines.

Equipment Control M,R JPM - 676 Review Completed SR (SRO)

Radiation Control P,R JPM - 544 Review a Radiological Survey Map Emergency Plan M,R JPM - 679 Upgrade PAR on wind shift.

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, Class(R)oom (D)irect from bank (< 3 for ROs; < 4 for SROs and RO retakes)

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

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

(S)imulator

ILT 1501 Administrative Topics Outline Form ES-301-1 Senior Reactor Operator Conduct of Operation

1. JPM - 678

Title:

Shift Staffing - SRO

==

Description:==

Provided with a crew complement, the SRO determines if his staff meets the minimum shift requirements. The list of people appears to be below the minimum; however an SRO can be moved down to an RO position to fill the Crew Complement. The Emergency Responder position is also down one, so a callout is required.

K/A: 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.

2. JPM - 677

Title:

Fuel Handling fuel storage, determines compliance with guidelines.

==

Description:==

Provided with Nuclear Fuel Storage physical locations and configurations, the SRO must determine if the fuel is being stored within the guidance of the procedure. In this case there are new fuel bundles stored in locations that are not allowed.

K/A: 2.1.35 Knowledge of the fuel-handling responsibilities of SROs.

Equipment Control

1. JPM - 676

Title:

Review Completed SR (SRO)

==

Description:==

Provided a completed SR-3.4.2.1 that the Unit Operator completed on his shift, the SRO is to review the SR for completeness and accuracy. The SR is filled out incorrectly and identified as meeting the surveillance requirements, however the surveillance requirements are not met and the SRO must identify that and determine the correct LCO.

K/A: 2.2.22; Knowledge of limiting conditions for operations and safety limits Radiation Control

1. JPM - 544

Title:

Review a Radiological Survey Map

==

Description:==

Provided an RWP and a Survey Map without equipment being identified, determine if the work in the area can be completed without exceeding exposure limits. The Candidate has to know equipment locations to correctly answer the questions in the JPM.

K/A: 2.3.7; Ability to comply with radiation work permit requirements during normal or abnormal conditions.

Emergency Plan

1. JPM - 679

Title:

Upgrade PAR on wind shift

==

Description:==

Provided an EPIP-5 General Emergency declaration form and new information about meteorological conditions determine that the PAR needs to be adjusted to include a new sector for sheltering. That will require the SRO to fill out another form with the new information.

K/A: 2.4.44; Knowledge of emergency plan protective action recommendations

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:

Browns Ferry NPP Date of Examination: 11/16/2015 Exam Level: RO SRO-I SRO-U Operating Test No.: 15-10 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code*

Safety Function

a.

JPM 80A Respond to a Control Rod Drift In. IAW AOI-85-5 A,D,S 1

b.

JPM 276 EHC Auto Cooldown D,L,S 4

c.

JPM 672A Loss Of Reference APRM To Rod Block Monitor (RBM)

A,N,S 7

d.

JPM 257A EOI Appendix-6E Injection Subsystem Lineup CS System II A,D,EN,L,S 2

e.

JPM 670A EOI Appendix-11F Alternate RPV Pressure Control Systems: RFPT On Minimum Flow A,M S 3

f.

JPM 669 EOI-Appendix-14A N2 Makeup To Primary Containment N,S 5

g.

JPM 631 Restore Offsite Power to 4KV shutdown board at PNL 9-23 D,P,S 6

h.

JPM 190 Respond to Off-Gas Post-Treatment Radiation HI-HI-HI (RO Only)

A,M,P,S 9

In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i.

JPM 673 Automatic Start Failure of A & C Fire Pumps E,N 8

j.

JPM 674 Aligning Emergency EECW Makeup To Spent Fuel Pool E,N,R 9

k.

JPM 307 Start up and synchronize Unit 3 Preferred MMG Set D

6 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 (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams (R)CA (S)imulator 4-6/4-6/2-3

< 9/< 8/<4

> 1/> 1/>1

>1/>1/>1 (control room system)

>1/>1/>1

> 2/> 2/>1

< 3/< 3/< 2 (randomly selected)

>1/>1/>1

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

a. JPM 80A

Title:

Respond to a Control Rod Drift In. IAW AOI-85-5

==

Description:==

While performing Surveillance 3.1.3.3, Control Rod Exercise Test for partially withdrawn control rods the ATC Operator will respond to a single control rod drift per AOI-85-5, Rod Drift In. as he continues with the surveillance multiple control rods will begin to drift in and the ATC Operator will respond by inserting a manual scram per AOI 5, Rod Drift In. Once scram report is given the JPM will end.

K/A: 201002 Reactor Manual Control System A2.02; Ability to (a) predict the impacts of the following on the REACTOR MANUAL CONTROL SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Rod Drift Alarm

b. JPM 276

Title:

EHC Auto Cooldown

==

Description:==

The BOP Operator will commence a cooldown of the reactor plant to 20 psig utilizing Main Turbine Bypass Valves with EHC Auto Cooldown function per OI-47, Turbine-Generator System. Once the initial cooldown has commenced the US will direct the BOP Operator to adjust the setpoint to 100 psig. After setpoint has been changed the JPM will end.

K/A: 239001Main and Reheat Steam System: A4.09 Ability to manually operate and/or monitor in the control room: Reactor pressure

c. JPM 672A

Title:

Loss Of Reference APRM To Rod Block Monitor (RBM)

==

Description:==

The ATC Operator will begin raising reactor power to achieve 40%

per Control Rod Movement Data Sheet for placing Feedwater Heaters and Moisture Separator Drain System in service. As reactor power is raised, APRM Ch 2 will fail downscale and impose a Control Rod Withdrawal Block which requires the APRM to be bypassed, to allow control rod movement. Once the Control Rod Withdrawal Block is cleared, and rod movement has continued, the JPM will end.

K/A: 215002 Rod Block Monitor System A2.03; Ability to (a) predict the impacts of the following on the ROD BLOCK MONITOR SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of associated reference APRM channel: BWR-3,4,5

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

d. JPM 257A

Title:

EOI Appendix-6E Injection Subsystem Lineup CS System II

==

Description:==

The ATC Operator has been directed to inject water into the RPV and restore water level using Core Spray System II per EOI-Appendix-6E, Injection Subsystems Lineup Core Spray System II. The operator will determine that FCV-75-51, CORE SPRAY SYS II OUTBD INJECT VALVE and FCV-75-53, CORE SPRAY SYS II INBD INJECT VALVE are not in proper alignment. Once the alignment is corrected, injection flow to RPV is established and reactor water level is > TAF

(-162 in) the JPM will end.

K/A: 209001 Low Pressure Core Spray System A4.08 Ability to manually operate and/or monitor in the control room: Reactor water level

e. JPM 670A

Title:

EOI Appendix-11F Alternate RPV Pressure Control Systems: RFPT On Minimum Flow

==

Description:==

The BOP Operator has been directed to lower reactor pressure to 800 - 1000 psig by placing A RFPT in Alternate Pressure Control per EOI-Appendix-11F. As speed reaches 350 RPM the A RFPT will trip and require the operator to start B RFPT for pressure control. Once 2B RFPT is in service and reactor pressure is lowering the JPM will end.

K/A: 239001 Main and Reheat Steam System A1.01 Ability to predict and/or monitor changes in parameters associated with operating the MAIN AND REHEAT STEAM SYSTEM controls including: Main steam pressure

f. JPM 669

Title:

EOI-Appendix-14A N2 Makeup To Primary Containment

==

Description:==

The BOP Operator has been directed to lower Drywell Hydrogen Concentration per EOI-Appendix-14A. The operator will need to determine that Drywell Hydrogen Concentration is greater than Suppression Chamber Hydrogen Concentration and begin purging the Drywell. Once Drywell Hydrogen Concentration begins to lower the JPM will end.

K/A: 223001 Primary Containment System and Auxiliaries A2.04; Ability to (a) predict the impacts of the following on the PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: High containment/drywell hydrogen concentration

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

g. JPM 631

Title:

Restore Offsite Power to 4KV shutdown board at PNL 9-23

==

Description:==

The BOP Operator has been directed to restore offsite power to 4KV Shutdown Board IAW 0-OI-82. The operator will parallel offsite to the running Diesel Generator, Once the Diesel Generator is separated from the grid the JPM will end.

K/A: 262001 A.C. Electrical Distribution; A4.02 Ability to manually operate and/or monitor in the control room: Synchroscope, including understanding of running and incoming voltages

h. JPM 190

Title:

Respond to Off-Gas Post-Treatment Radiation HI-HI-HI(RO Only)

==

Description:==

The BOP Operator will respond to OFF-GAS POST TREATMENT RADIATION HI-HI-HI annunciator. The operator will close FCV 28, OFF-GAS SYSTEM ISOLATION VALVE and then perform immediate actions of AOI-66-2, Off-gas Post-treatment Radiation Hi-Hi-Hi. The operator will reduce core flow to 50-60% and then insert a manual reactor scram. The operator will continue with subsequent actions. Once the standby Stack Dilution fan is started the JPM will end.

K/A: 271000 Offgas System: A2.16; Ability to (a) predict the impacts of the following on the OFFGAS SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of offgas system loop seals (2.9/3.2)

i. JPM 673A

Title:

Automatic Start Failure of A & C Fire Pumps

==

Description:==

The Operator has been directed to start A and C Electric Fire Pumps per 0-OI-26, High Pressure Fire Protection System from the 4KV Shutdown Boards. The operator will start A and C Fire Pumps from their local breaker cubicles. Once both fire pumps have been started the JPM will end.

K/A: 286000 Fire Protection System A2.08; Ability to (a) predict the impacts of the following on the FIRE PROTECTION SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Failure to actuate when required

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

j. JPM 674

Title:

Aligning Emergency EECW Makeup To Spent Fuel Pool

==

Description:==

The Operator has been directed to align EECW Makeup to Unit 2 Spent Fuel Pool per 2-AOI-78-1 Attachment 2. The operator will locate and align EECW to Spent Fuel Pool by utilizing fire hoses and isolation valves. Once the lineup is made and water is flowing into the Spent Fuel Pool the JPM will end.

K/A: 233000 Fuel Pool Cooling and Clean-up; A2.02; Ability to (a) predict the impacts of the following on the FUEL POOL COOLING AND CLEAN-UP; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Low pool level

k. JPM 307

Title:

Start up and synchronize Unit 3 Preferred MMG Set

==

Description:==

The Operator has been directed to synchronize the Unit 3 Unit Preferred MMG Set per 0-OI-57C. The operator will perform local operations to synchronize U3 MMG set to the Battery Board. Once Unit 3 MMG Set has been transferred per 0-OI-57C the JPM will end.

K/A: 262002 Uninterruptable Power Supply (A.C./D.C.) A1.02; Ability to predict and/or monitor changes in parameters associated with operating the UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.)

controls including: Motor generator outputs

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:

Browns Ferry NPP Date of Examination: 11/16/2015 Exam Level: RO SRO-I SRO-U Operating Test No.: 15-10 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code*

Safety Function

a.

JPM 80A Respond to a Control Rod Drift In. IAW AOI-85-5 A,D,S 1

b.

JPM 276 EHC Auto Cooldown D,L,S 4

c.

JPM 672A Loss Of Reference APRM To Rod Block Monitor (RBM)

A,N,S 7

d.

JPM 257A EOI Appendix-6E Injection Subsystem Lineup CS System II A,D,EN,L,S 2

e.

JPM 670A EOI Appendix-11F Alternate RPV Pressure Control Systems: RFPT On Minimum Flow A,M S 3

f.

JPM 669 EOI-Appendix-14A N2 Makeup To Primary Containment N,S 5

g.

JPM 631 Restore Offsite Power to 4KV shutdown board at PNL 9-23 D,P,S 6

In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i.

JPM 673 Automatic Start Failure of A & C Fire Pumps E,N 8

j.

JPM 674 Aligning Emergency EECW Makeup To Spent Fuel Pool E,N,R 9

k.

JPM 307 Start up and synchronize Unit 3 Preferred MMG Set D

6 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 (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams (R)CA (S)imulator 4-6/4-6/2-3

< 9/< 8/<4

> 1/> 1/>1

>1/>1/>1 (control room system)

>1/>1/>1

> 2/> 2/>1

< 3/< 3/< 2 (randomly selected)

>1/>1/>1

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

a. JPM 80A

Title:

Respond to a Control Rod Drift In. IAW AOI-85-5

==

Description:==

While performing Surveillance 3.1.3.3, Control Rod Exercise Test for partially withdrawn control rods, the ATC Operator will respond to a single control rod drift per AOI-85-5, Rod Drift In. As he continues with the surveillance, multiple control rods will begin to drift in and the ATC Operator will respond by inserting a manual scram per AOI 5, Rod Drift In. Once scram report is given the JPM will end.

K/A: 201002 Reactor Manual Control System A2.02; Ability to (a) predict the impacts of the following on the REACTOR MANUAL CONTROL SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Rod Drift Alarm

b. JPM 276

Title:

EHC Auto Cooldown

==

Description:==

The BOP Operator will commence a cooldown of the reactor plant to 20 psig utilizing Main Turbine Bypass Valves with EHC Auto Cooldown function per OI-47, Turbine-Generator System. Once the initial cooldown has commenced the US will direct the BOP Operator to adjust the setpoint to 100 psig. After setpoint has been changed the JPM will end.

K/A: 239001Main and Reheat Steam System: A4.09 Ability to manually operate and/or monitor in the control room: Reactor pressure

c. JPM 672

Title:

Loss Of Reference APRM To Rod Block Monitor (RBM)

==

Description:==

The ATC Operator will begin raising reactor power to achieve 40%

per Control Rod Movement Data Sheet for placing Feedwater Heaters and Moisture Separator Drain System in service. As reactor power is raised, APRM Ch 2 will fail downscale and impose a Control Rod Withdrawal Block which requires the APRM to be bypassed to allow control rod movement. Once the Control Rod Withdrawal Block is cleared, and rod movement has continued, the JPM will end.

K/A: 215002 Rod Block Monitor System A2.03; Ability to (a) predict the impacts of the following on the ROD BLOCK MONITOR SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of associated reference APRM channel: BWR-3,4,5

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

d. JPM 257A

Title:

EOI Appendix-6E Injection Subsystem Lineup CS System II

==

Description:==

The ATC Operator has been directed to in water into the RPV and restore water level using Core Spray System II per EOI-Appendix-6E, Injection Subsystems Lineup Core Spray System II. The operator will determine that FCV-75-51, CORE SPRAY SYS II OUTBD INJECT VALVE and FCV-75-53, CORE SPRAY SYS II INBD INJECT VALVE are not in proper alignment. Once the alignment is corrected, injection flow to RPV is established and reactor water level is > TAF

(-162 in) the JPM will end.

K/A: 209001 Low Pressure Core Spray System A4.08 Ability to manually operate and/or monitor in the control room: Reactor water level

e. JPM 670A

Title:

EOI Appendix-11F Alternate RPV Pressure Control Systems: RFPT On Minimum Flow

==

Description:==

The BOP Operator has been directed to lower reactor pressure to 800 - 1000 psig by placing A RFPT in Alternate Pressure Control per EOI-Appendix-11F. As speed reaches 350 RPM the A RFPT will trip and require the operator to start B RFPT for pressure control. Once 2B RFPT is in service and reactor pressure is lowering the JPM will end.

K/A: 239001 Main and Reheat Steam System A1.01 Ability to predict and/or monitor changes in parameters associated with operating the MAIN AND REHEAT STEAM SYSTEM controls including: Main steam pressure

f. JPM 669

Title:

EOI-Appendix-14A N2 Makeup To Primary Containment With

==

Description:==

The BOP Operator has been directed to lower Drywell Hydrogen Concentration per EOI-Appendix-14A. The operator will need to determine that Drywell Hydrogen Concentration is greater than Suppression Chamber Hydrogen Concentration and begin purging the Drywell. Once Drywell Hydrogen Concentration begins to lower the JPM will end.

K/A: 223001 Primary Containment System and Auxiliaries A2.04; Ability to (a) predict the impacts of the following on the PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: High containment/drywell hydrogen concentration

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

g. JPM 631

Title:

Restore Offsite Power to 4KV shutdown board at PNL 9-23

==

Description:==

The BOP Operator has been directed to restore offsite power to 4KV Shutdown Board IAW 0-OI-82. The operator will parallel offsite to the running Diesel Generator, Once the Diesel Generator is separated from the grid the JPM will end.

K/A: 262001 A.C. Electrical Distribution A4.02 Ability to manually operate and/or monitor in the control room: Synchroscope, including understanding of running and incoming voltages

i. JPM 673A

Title:

Automatic Start Failure of A & C Fire Pumps

==

Description:==

The Operator has been directed to start A and C Electric Fire Pumps per 0-OI-26, High Pressure Fire Protection System from the 4KV Shutdown Boards. The operator will start A and C Fire Pumps from their local breaker cubicles. Once both fire pumps have been started the JPM will end.

K/A: 286000 Fire Protection System A2.08; Ability to (a) predict the impacts of the following on the FIRE PROTECTION SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Failure to actuate when required

j. JPM 674

Title:

Aligning Emergency EECW Makeup To Spent Fuel Pool

==

Description:==

The Operator has been directed to align EECW Makeup to Unit 2 Spent Fuel Pool per 2-AOI-78-1 Attachment 2. The operator will locate and align EECW to Spent Fuel Pool by utilizing fire hoses and isolation valves. Once the lineup is made and water is flowing into the Spent Fuel Pool the JPM will end.

K/A: 233000 Fuel Pool Cooling and Clean-up; A2.02; Ability to (a) predict the impacts of the following on the FUEL POOL COOLING AND CLEAN-UP; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Low pool level

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

k. JPM 307

Title:

Start up and synchronize Unit 3 Preferred MMG Set

==

Description:==

The Operator has been directed to synchronize the Unit 3 Unit Preferred MMG Set per 0-OI-57C. The operator will perform local operations to synchronize U3 MMG set to the Battery Board. Once Unit 3 MMG Set has been transferred per 0-OI-57C the JPM will end.

K/A: 262002 Uninterruptable Power Supply (A.C./D.C.) A1.02; Ability to predict and/or monitor changes in parameters associated with operating the UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.)

controls including: Motor generator outputs

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:

Browns Ferry NPP Date of Examination:

11/16/2015 Exam Level: RO SRO-I SRO-U Operating Test No.:

15-10 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code*

Safety Function

b.

JPM 276 EHC Auto Cooldown D,L,S 4

c.

JPM 672A Loss Of Reference APRM To Rod Block Monitor (RBM)

A,N,S 7

d.

JPM 257A EOI Appendix-6E Injection Subsystem Lineup CS System II A,D,EN,L,S 2

In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i.

JPM 673 Automatic Start Failure of A & C Fire Pumps E,N 8

j.

JPM 674 Aligning Emergency EECW Makeup To Spent Fuel Pool E,N,R 9

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 (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams (R)CA (S)imulator 4-6/4-6/2-3

< 9/< 8/<4

> 1/> 1/>1

>1/>1/>1 (control room system)

>1/>1/>1

> 2/> 2/>1

< 3/< 3/< 2 (randomly selected)

>1/>1/>1

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

b. JPM 276

Title:

EHC Auto Cooldown

==

Description:==

The BOP Operator will begin commence a cooldown of the reactor plant to 20psig utilizing Main Turbine Bypass Valves with EHC Auto Cooldown function per OI-47, Turbine-Generator System. Once the initial cooldown has commenced the US will direct the BOP Operator to adjust the setpoint to 100 psig. After setpoint has been changed the JPM will end.

K/A: 239001Main and Reheat Steam System: A4.09 Ability to manually operate and/or monitor in the control room: Reactor pressure

c. JPM 672A

Title:

Loss Of Reference APRM To Rod Block Monitor (RBM)

==

Description:==

The ATC Operator will begin raising reactor power to achieve 40%

per Control Rod Movement Data Sheet for placing Feedwater Heaters and Moisture Separator Drain System in service. As reactor power is raised, APRM Ch 2 will fail downscale and impose a Control Rod Withdrawal Block which requires the APRM to be bypassed to allow control rod movement. Once the Control Rod Withdrawal Block is cleared and rod movement has continued the JPM will end.

K/A: 215002 Rod Block Monitor System A2.03; Ability to (a) predict the impacts of the following on the ROD BLOCK MONITOR SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of associated reference APRM channel: BWR-3,4,5

d. JPM 257A

Title:

EOI Appendix-6E Injection Subsystem Lineup CS System II

==

Description:==

The ATC Operator has been directed to inject water into the RPV and restore water level using Core Spray System II per EOI-Appendix-6E, Injection Subsystems Lineup Core Spray System II. The operator will determine that FCV-75-51, CORE SPRAY SYS II OUTBD INJECT VALVE and FCV-75-53, CORE SPRAY SYS II INBD INJECT VALVE are not in proper alignment. Once the alignment is corrected, injection flow to RPV is established and reactor water level is > TAF

(-162 in) the JPM will end.

K/A: 209001 Low Pressure Core Spray System A4.08 Ability to manually operate and/or monitor in the control room: Reactor water level

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

i. JPM 673A

Title:

Automatic Start Failure of A & C Fire Pumps

==

Description:==

The Operator has been directed to start A and C Electric Fire Pumps per 0-OI-26, High Pressure Fire Protection System from the 4KV Shutdown Boards. The operator will start A and C Fire Pumps from their local breaker cubicles. Once both fire pumps have been started the JPM will end.

K/A: 286000 Fire Protection System A2.08; Ability to (a) predict the impacts of the following on the FIRE PROTECTION SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Failure to actuate when required

j. JPM 674

Title:

Aligning Emergency EECW Makeup To Spent Fuel Pool

==

Description:==

The Operator has been directed to align EECW Makeup to Unit 2 Spent Fuel Pool per 2-AOI-78-1 Attachment 2. The operator will locate and align EECW to Spent Fuel Pool by utilizing fire hoses and isolation valves. Once the lineup is made and water is flowing into the Spent Fuel Pool the JPM will end.

K/A: 233000 Fuel Pool Cooling and Clean-up; A2.02; Ability to (a) predict the impacts of the following on the FUEL POOL COOLING AND CLEAN-UP; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Low pool level