ML12318A357

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Initial Exam 2012-301 Draft Administrative Documents
ML12318A357
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 11/13/2012
From:
NRC/RGN-II
To:
Tennessee Valley Authority
References
50-259/12-301, 50-260/12-301, 50-296/12-301, ES-301-1 50-259/12-301, 50-260/12-301, 50-296/12-301
Download: ML12318A357 (26)
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Text

ILT 1205 Administrative Topics Outline Form ES-301-1 Facility:

Browns Ferry NPP Date of Examination:

5/7/2012 Examination Level: RO/SRO Operating Test Number:

1205 Administrative Topic Type Describe activity to be performed (see Note)

Code Conduct of Operations D

2.1.3 1 Verification of Off Site PoweiAvailability to 4.16 kV SROIRO Ala Shutdown Boards

/

Conduct of Operations P

2.1.19 ICS Logs ROA1b 2.1.18 NRC event notification due to HPCI valve failure SROA1b N

Equipment Control N

2.2.12 Complete Primary Containment Nitrogen Leakage and RO A2 Consumption Surveillance and evaluate Acceptance Criteria 2.2:12 Complete Primary Containment Nitrogen Leakage and SRO A2 N

Consumption Surveillance, evaluate Acceptance Criteria, and determine Technical Specifications Radiation Control N

2.3.11 Calculate Airborne Effluent Release Rate iaw 0-SI-4.8.b.1.a.1 SRO/ROA3 Emergency Plan M

2.4.4 1 Classify an Event SROA4 NOTE: All items (5 tota1) 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 (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 1205 Administrative Topics Outline Form ES-301-1 Reactor Operator

1. Verification of Off Site Power Availability to 4.16 kV Shutdown Boards Direct 0-SR-3.8.1.A.1 Marks 500KV and 16 1KV Sources as Qualified. Completes Attachment 1 for Unit 3 accurately, records indicated voltages for step 7.2[5] and does not sign acceptance criteria, does not sign acceptance criteria for 7.4[1J, and marks acceptance criteria satisfied on Surveillance Task Sheet as NO.

2.1.31 Ability to locate control room switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup. Importance R04.6

2. ICS Logs Previous 2-SR-2 or 3-SR-2 Perform Operator logs using ICS screens in accordance with 2-SR-2 nstrumn1 Checks and Observations for log tables 1.1, 1.6 1.25, and 1.30. Verify acceptance criteria are satisfied in accordance with notes.

2.1.19 Ability to use plant computers to evaluate system or component status. RO 3.9

3. Complete Primary Containment Nitrogen Leakage and Consumption Surveillance and evaluate Acceptance Criteria

/

/

New 3-SI-4.7.A.2.A, Primary Containment Nitrogen Leakage and Consumption Completes Surveillance and determines that it des not meet acceptance criteria. Determines that an LCO must be entered and informs the Unft Supervisor.

2.2.12 Knowledge of surveillance procedures RO 3.7

4. Calculate Airborne Effluent Release Rate jaw 0-SI-4.8.b.1.a.1 New 0-SI-4.8.B. l.a. 1, 2-EOI Appendix-12 Calculate Stack Release Rate and Total Site Release Fraction determine it does not meet Acceptance Criteria, and determine that vent flowrate must be reduced in accordance with 2-EOI Appendix-12.

2.3.11 Ability to control radiation releases RO 3.8

ILT 1205 Administrative Topics Outline Form ES-301-1 Senior Reactor Operator

1. Verification of Off Site Power Availability to 4.16 kV Shutdown Boards Direct 0-SR-3.8.1.A.1 Marks 500KV and 161KV Sources as Qualified. Completes Attachment 1 for Unit 3 accurately, records indicated voltages for step 7.2[51 and does not sign acceptance criteria, does not sign acceptance criteria for 7.4[ 1j, and marks acceptance criteria satisfied on Surveillance Task Sheet as NO.

2.1.31 Ability to locate control room switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup. Importance SRO 4.3

2. NRC event notification due to HPCI Valve Failure New NPG-SPP-03.5, Regulatory Reporting Requirements Determine NRC event notification requirements, as the Shift Manager due to a failure of the FIPCI Pump Injection Valve. Determines Technical Specification actions required.

2.1.18 Ability to make accurate, clear, and concise logs, records, status boards, and reports.

Importance SRO 3.8

3. Complete Primary Containment Nitrogen Leakage and Consumption Surveillance, evaluate Acceptance Criteria, and determine Technical Specifications New 3-SI-4.7.A.2.A, Primary Containment Nitrogen Leakage and Consumption Completes Surveillance, recognizes that it does not meet acceptance criteria, and determines Technical Specification actions required.

2.2.12 Knowledge of surveillance procedures. SRO 4.1

4. Calculate Airborne Effluent Release Rate jaw 0-SI-4.8.b.1.a.1 New 0-SI-4.8.B.1.a.1, 2-EOI Appendix-12 Calculate Stack Release Rateand Total Site Release Fraction determine it does not meet Acceptance Criteria, and determine that vent flowrate must be reduced in accordance with 2-EOI Appendix-12.

/

2.3.11 Ability to control radiation releases SRO 4.3

ILT 1205 Administrative Topics Outline Form ES-301-1

5. Classify an Event Modified EPIP-1 and 3 Emergency Classification Procedure and Alert The event is classified as an Alert 1.1 -A2 and the Initial Notification appendix is completed with the correct information. Event is classified within 15 minutes and Initial Notification is completed within 15 minutes of classification.

2.4.4 1 Knowledge of emergency action level thresholds and classifications. Importance SRO 4.6

ES-201 Examination Outline Quality Checklist Form ES-201-2 Facihy Date of Examination: c Initials Item Task Description 1.

a.

Verify that the outline(s) fit(s) the appropriate model, in accordance with ES-401.

w

R

b. Assess whether the outline was systematically and randomly prepared in accordance with I

Section D.1 of ES-401 and whether all 1</A categories are appropriately sampled.

5

c.

Assess whether the outline over-emphasizes any systems, evolutions, or generic topics.

ç,

d. Assess whether the justifications for deselected or rejected K/A statements are appropriate.

!1

( j5 2.

a.

Using Form ES-301-5, verify that the proposed scenario sets cover the required number of normal evolutions, instrument and component failures, technical specifications, S

and major transients.

I)j Pr M

b. Assess whether there are enough scenario sets (and spares) to test the projected number u

and mix of applicants in accordance with the expected crew composition and rotation schedule without compromising exam integrity, and ensure that each applicant can be tested using A

at least one new or significantly modified scenario, that no scenarios are duplicated T

from the applicants audit test(s), and that scenarios will not be repeated on subsequent days.

0 c.

To the extent possible, assess whether the outline(s) conform(s) with the qualitative R

and quantitative criteria specified on Form ES-301-4 and described In Appendix D.

3.

a.

Verify that the systems walk-through outline meets the criteria specified on Form ES-301-2:

(1) the outline(s) contain(s) the required number of control room and in-plant tasks W

distributed among the safety functions as specified on the form I

(2) task repetition from the last two NRC examinations is within the limits specified on the form T

(3) no tasks are duplicated from the applicants audit test(s)

(4) the number of new or modified tasks meets or exceeds the minimums specified on the form (5) the number of alternate path, low-power, emergency, and RCA tasks meet the critena on the form.

b.

Verify that the administrative outline meets the criteria specified on Form ES-301-1:

(1) the tasks are distributed among the topics as specified on the form (2) at least one task is new or significantly modified (3) no more than one task is repeated from the last two NRC licensing examinations

c.

Determine if there are enough different outlines to test the projected number and mix of applicants and ensure that no items are duplicated on subsequent days.

4.

a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered intheappropriateexamsections.
b. Assess whether the 10 CFR 55.41/43 and 55.45 samphng is appropriate.

_ J4 N

c.

Ensure that 1</A importance ratings (except for plant-specific priorities) are at least 2.5.

R

d. Check for duplication and overlap among exam sections.

A e.

Check the entire exam for balance of coverage.

L f.

Assess whether the exam fits the appropnate job level (RO or SRO).

Printed Na e/S atur Date C: NRC Chief aminer (#

,4L.OaIiM

/3 gild V

d. NRC Supervisor fljj/

Note:

  1. Independent NRC reviewer Initial items in Column c; chief examiner concurrence required.

Not applicable for NRC-prepared examination outlInes ES-201, Page 26 of 28

R T ES-401, Rev. 9 BWR Examination Outline Form ES-401-1 (PRIVATE )Facility:

Browns Ferry Date of Exam:

RO KIA Category Points SRO-Only Points Tier Group K1KKKKATAG1 A2 G*

Total I

2(3 4

5 6

1 213 4

  • ITotal 1.

i 3

4 3

=

3 3

=

20 3

4 7

Emergency&

2 T T 1

1 1

7 1

2 3

Abnormal Plant

NIA NIA

V Evolutions Tier Totals 4

6 4

=

27 6

10 1

33223232222 26 2

3 5

2.

2 TTTTT 12 0

1 2

3 Plant

Systems Tier Totals

!8..

3 5

8

3. Generic Knowledge and Abilities 1

2 3

4 10 1

2 3

4 7

Categories 2

2 3

3 1

2 2

2 1.

Ensure that at least two topics from every applicable KIA category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 ofthe SRO-only outline, the Tier Totals in each KIA 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 +/- I 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.

Systemslevolutions 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 KIAs 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 I and 2 from the shaded systems and KIA categories.

7.

The generic (G) KIAs 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.

8.

On the following pages, enter the KIA 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 tue 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

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

9.

For Tier 3, select topics from Section 2 ofthe KIA catalog, and enter the KIA numbers, descriptions, IRs, and pointtotals (#) on Form ES-4014. Limit SRO selections to K!As that are linked to 10 CFR 55.43.

I

Ground isolation.

Redundant D.C. power supplies: PIant:ecc.

Knowledge of less than one hour technical specification action statements for systems.

Reactor water level A.C. electrical distribution Effects on componentlsystem operations Instrument air system valves: Plant-Specific Increasing drwell cooling Secondary containment ventilation RPS

?

ES-401, REV 9 TIGI BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME I SAFETY FUNCTION:

IR Kl K2 KS K4 K5 KB Al A2 A3 A4 G TOPIC:

RO SRO 3.3 3.3

[] [] fJ [] []

LI Actual core flow 295001AA2.03 Partial or Complete Loss of Forced LI LI LI Core Flow Circulation I 1 & 4 295003AK3.04 Partial or Complete Loss of AC /6 3.0 3.2 LI LI LI LI LI LI LI LI LI [1 295004AK1.02 Partial or Total Loss of DC Pwr /6 3.2 3.4 [ LI LI LI LI LI Li LI LI LI LI 295005G2.2.39 Main Turbine Generator Trip /3 3.9 4.5 LI LI LI LI LI LI LI LI LI LI 295006M2.03 SCRAM /

4.0 4.2 LI LI LI LI LI LI LI 1] LI LI LI 29501 6AA1.04 Control Room Abandonment / 7 3.1 3.2 LI LI LI LI LI LI 1 LI LI LI LI 29501 8AK1.01 Partial or Total Loss of CCW / 8 3.5 3.6 LI LI LI LI LI LI LI LI LI LI 295019AA1.02 Partial or Total Loss of Inst. AirI8 33 3.1 LI LI LI LI LI LI LI LI LI LI 295021AK3.03 LossofShutdoWnCooling/4 2.9 2.9 LI LI 1 LI LI LI LI LI LI LI LI 295023AK205 Refueling Acc Cooling Mode! 8 3.5 3.7 LI 1 LI LI LI LI LI LI LI LI LI 295024EK2.05 High Drywell Pressure 15 3.9 4.0 LILILILILILILILILILI Page 1 of 2 9/6/2011 2:58PM

5 700000AAI.05 Generator Voltage and Electric Grid Distrurbancecs ES-401, REV 9 TI GI BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME I SAFETY FUNCTION:

IR KI 1(2 K3 K4 KS KB Al A2 A3 A4 G TOPIC:

RO SRO 295025EK3.02 High Reactor Pressure 13 3.9 4.1

[]

D C] C] C] C] C] C]

Recirculation pump trip: Plant-Specific 295028EK1.02 Suppression Pool High WaterTemp.!

3.5 3.8 C] C] C] C] C] C] C] C] C] C]

Steam condensation 5

295028EK2.01 High Drywell Temperature /5 3.7 4.1 C]

C] C] C] C] LI C] C] C] C]

Drywell spray: Mark-l&ll 295030G2.2.22 Low Suppression Pool Wtr Lvi I 4.0 4.7 C] C] [] C]

C] ci C] C] C]

Knowledge of limiting conditions for operations and safety limits.

295031EK2.15 Reactor Low Water Level /2 3.2 3.2 C]

C] C] C] C] C] C] C] C] C]

AC. distribution: Plant-Specific 295037EA2.06 SCRAM Condition Present and Power 4.0 4.1 C] [] C] C] C] C] C]

C] [] C]

Reactor pressure Above APRM Downscale or Unknown

/1 295038G2.4.46 High Off-site Release Rate! 9 4.2 4.2 jj ci C]

r]C]L] C] C]

Ability to verify that the alarms are consistent with the plant conditions.

600000G2.2.40 Plant Fire On Site / 8 3.4 4.7 C] C] C] C] C] L]C] C] C] C]

Ability to apply technical specifications for a system.

1 3.9 4.0 C]C]C]C]LIC]LIC]

Engineered Safty Features Page 2 of 2 916/2011 2:58 PM

NAME! SAFETY FUNCTION:

High Reactor Pressure /3 High Reactor Water Level /2 Loss of CR0 Pumps/ I High Suppression Pool Wtr Lvi / 5 High Secondary Containment Area Radiation Levels / 9 Secondary Containment Ventilation High Radiation / 9 Secondary Containment High SumplArea Water Level /5 ES-401, REV 9 KA 295007AA1.05 295008AK2.1O 295022G2.4.1 295029EK2.09 295033EK3.O1 295034EK1.02 295036EA2.03 TIG2 BWR EXAMINATION OUTLINE FORM ES-401-1 IR K1 1<2 1(3 1(4 1(5 1(6 M A2 A3 A4 G TOPIC:

RO SRO 3.7 3.8 L] [1 E

[1 LI 1] LI E] U U]

Reactor/turbine pressure regulating system 2.7 2.8 U] [j] U] U] U] U] [] U] U] U] []

RHR (ability to drain): Plant-Specific 4.6 4.8 U] U] U] U] U] U] U] U] U] U] ]

Knowledge of EOP entry conditions and immediate action steps.

3.1 3.2 U]

U] U] U] U] U] U] U] U] U]

RCIC: Plant-Specific 3.3 3.5 U] U] ] U] U] U] U] U] U] U] U]

Emergency depressurization 4.1 4.4 J U] U] U] U] U] U] U] U] U] U]

Radiation releases 3.4 3.8 U] U] U] U] U] U] U] ]J U] U] U]

Cause of the high water level Page 1 of I 9/6/2011 2:58PM

ES-401, REV 9 T2GI BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME! SAFETY FUNCTION:

IR 1(1 1(2 K3 1(4 K5 1(6 Al A2 A3 A4 G TOPIC:

RO SRO 2030001<2.01 RHR!LPCI: Injection Mode 3.5 3.5

[] ] El El El

[] [] fl fl []

Pumps 203000K3.04 RI-IRILPCI: Injection Mode 4.6 4.6 El El

[] [] [] [] [] [] []

Adequate core cooling 205000A2.06 Shutdown Cooling 3.4 3.5 El fl El fl El []

SDCIRI-IR pump trips 206000A2.08 HPCI 3.9 4.2 El El El El El El LI El LI El tHigh suppression pool temperature: BWR-23,4 209001G2.4.48 LPCS 4.2 4.2 El LI El El El El El El El [1 Ability to verify that the alarms are consistent with the plant condittons.

2110001<2.01 SIC 2.9 3.1 El )

[]

[)

]

SBLC pumps 212000A1.O1 RPS 2.8 2.9 El El El El El El El [J RPS motor-generator output voltage 21500302.4.2 IRM 4.5 4.6 El El El El El El El El El El Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.

2150031<2.01 IRM 2.5 2.7 El I El El El El El El El El El IRM channels!detectors 215004A1.04 Source Range Monitor 3.5 3.5 El El El El El El ll El El El El Control rod block status 215005K4.01 APRM I LPRM 3.7 3.7 El El El lil El El El El El El El Rod withdrawal blocks Pagelof3 9/6/2011 2:58PM

ES4OI, REV 9 T2GI BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME I SAFETY FUNCTION:

IR Kl K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 217000K5.07 RCIC 3.1 3.1

[] [] Q

[] [] [J Q

Assist core cooling 218000A4.07 ADS 3.5 3.8 El

[] El [] El [] [] (] J ADS valve acoustical monitor noise: Plant-Specific 2230021<6.03 PClSINucIear Steam Supply Shutoff 2.9 3.1

[] [] [] []

EJ El [] []

Process radiation monitoring system 2390021<1.07 SRVs 3.6 3.8

[] [] fl [] [] {] [] [] Q []

Suppression pool 2390021(5.04 SRVs 3.3 El El El El El El El El El El Tail pipe temperature monitoring 259002A1.05 Reactor Water Level Control 2.9 2.9 El El El El El El FWRVfstartup level control position: Plant-Specific.

259002K4.02 Reactor Water Level Control 2.8 3.0 El El El El El El El El El El Bypassing of the RWM: Plant-Specific 2610001<1.03 SGTS 2.9 3.1 El El El El El El El El El El Suppression pool 262001A3.01 AC Electrical Distribution 3.1 3.2 El El El El El El El El ] El U Breaker tripping 2620021<3.17 UPS (ACIDC) 2.9 3.1 El ] J El El El El El El El El Process monitoring: Plant-Specific 2630001<1.03 DC Electrical Distribution 2.6 2.8 J El El El El El El El El El El Battery ventilation Page 2 of 3 91612011 2:58 PM

T2GI BWR EXAMINATION OUTLINE IR KI K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO D U fl [] [] {J

[] []

Load shedding and sequencing UUDElEL1L1ElU 2.6 2.7 EIUElULJLI 2.7 2.8 ES-401, REV 9 KA NAME I SAFETY FUNCTION:

284000A3.05 EDGe 264000K5.06 EDGe FORM ES-401-1 300000A4.Oi Instrument Air 400000K6.07 Component Cooling Water fl Load sequencing Ri El Pressure gauges Breakers, relays, and disconnects Page 3 of 3 9/612011 2:58 PM

ES4OI, REV 9 T2G2 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME I SAFETY FUNCTION:

IR 1(1 1(2 K3 1(4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 201 002G2.1.25 RMCS 3.9 4.2

[] [] U ]

LI LI LI LI Ability to interpret reference materials such as graphs, monographs and tables which contain performance data.

201006A3.01 RWM 3.2 3.1 LI LI LILILI LI LI LI LI LI System window and light indication: P-Spec(Not-BWR6).

214000A4.02 RPIS 3.8 3.8 LI LI LI LI LI LI LI LI LI LI Control rod position 219000K3.01 RHRILPCI: Torus/Pool Cooling Mode 3.9 4.1 LI LI [] LI LI LI LI LI LI LI LI Suppression pool temperature control 2300001(202 RHRILPCI: Torus/Pcol Spray Mode 2.8 2.9 LI II LI LI LI LI LI LI LI LI LI Pumps 2560001(1.18 Reactor Condensate 2.9 3.0 i1 LI LI LI LI LI LI LI LI LI LI Circulating water system 259001A2.07 Reactor Feedwater 3.7 3.8 LI LI LI LI LI LI LI ] LI LI LI Reactor water level control system malfunctions 271000A1.15 Oflas 2.7 2.8 LI LI LI LI LI LI tJ LI LI LI LI Steam supply pressures 2720001(6.02 Radiation Monitoring 2.5 2.7 LI LI LI LI LI LI LI LI LI LI D.C. power 2880001(4.03 Plant Ventilation 2.8 2.9 LI LI LI 11 LI LI LI LI LI LI LI Automatic starting and stopping of fans 290001 K5.O1 Secondary CTMT 3.3 3.4 LI LI LI LI LI LI LI LI LI LI Vacuum breaker operation: BWR4 Page 1 of2 9/6/201 1 2:58PM

ES-401, REV 9 T2G2 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME I SAFETY FUNCTION:

IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 290003K1.03 Control Room HVAC 2.8 2.9 Remote air intakes: Plant-Specific Page 2 of 2 9/612011 2:58 PM

ES-401, REV 9 T3 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME! SAFETY FUNCTION:

IR KI K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 2.7 3.4

G2.1.15 Conduct of operations

[] [] [] []

[] [] [] [] [j Knowledge of administrative requirements for temporary management directives such as standing orders, night orders, Operations memos, etc.

G2.1.38 Conduct of operations 3.7 3.8

[] []

[]

[]

Knowledge of the stations requirements for verbal communication when implamenting procedures G2.2.3 Equipment Control 3.8 3.9 El El El El El El El LJ (multi-unit license) Knowledge of the design, procedural and operational differences between units.

G2.2.6 Equipment Control 3.0 3.6 El Knowledge of the process for making changes to procedures G2.3.15 Radiation Control 2.9 3.1

[] []

E]

Knowledge of radiation monitoring systems G2.&4 Radiation Control 3.2 3.7 El El El El ci El El El El [1 J Knowledge of radiation exposure limits under normal and emergency conditions G2.3.5 Radiation Control 2.9 2.9 El El El El LI El [1 El LI El J Ability to use radiation monitoring systems G2.4.2 Emergency Procedures/Plans 4.5 4.6 Li El El El El El El LI El El {]

Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions.

El El El El El El Knowledge of the bases for prioritizing safety functions during abnormal/emergency operations.

G2.4.22 Emergency Procedures/Plans 3.6 4.4 El El El El G2.4.6 Emergency Procedures/Plans 3.7 4.7 El El El El El El El El El El Knowledge symptom based EOP mitigation strategies.

Page 1 of I 9/612011 2:58PM

SRO TIGI BWR EXAMINATION OUTLINE IR Kl 1<2 K3 K4 K5 K6 Al A2 A3 A4 G RO SRO 3.0 3.1 OflDEiflflOIUD 3.1 3.1 OUE1LIOflD 3.8 4.2 DDODDLIU1JUO 4.4 4.0 OODDE 3.2 42 3.7 4.1 FORM ES-401-1 TOPIC:

lndMdual jet pump flows: Not-BWR-1&2 Turbine valve position Knowledge of low power I shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation strategies.

Reactor vessel metal temperature Ability to locate and operate components, including local controls.

Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.

Knowledge of surveillance procedures.

ES-401, REV 9 KA NAME I SAFETY FUNCTION:

295001AA2.04 Partial or Complete Loss of Forced Core Flow Circulation /1 & 4 295005AA2.03 Main Turbine Generator Trip 13 2950 18G2.4.9 Partial or Total Loss of CCW /8 295021M2.05 Loss of Shutdown Cooling /4 295026G2.1.30 Suppression Pool High Water Temp. /5 295028G2.2.25 High Drwefl Temperature /5 295038G2.2.12 High Off-site Release Rate! 9 Page 1 of I 9/60l1 2:58PM

ES-401 REV 9 SRO TIG2 BWR EXAMINATION OUTLINE FORM ES4OI-1 KA NAME I SAFETY FUNCTION:

IR KI 1(2 K3 K4 1(5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 29500802.4.18 High Reactor Water Level /2 3.3 4.0

[] [] [] [] [] [J []

J Knowledge of the specific bases for EOPs.

295013M2.02 High Suppression Pool Temp. /5 3.2 3.5 J Localized heating/stratification 29502002.2.37 Inadvertent Cont. Isolation / 5 & 7 3.6 4.6

[1 D LI LI LI LI LI LI LI Ability to determine operability and/or availability of safety related equipment 1)1 Page 1 of 1 9/6/2011 2:58PM

ES-401, REV 9 SRO T2GI BWR EXAMINATION OUTLINE FORM ES.401-1 KA NAME I SAFETY FUNCTION:

IR KI K2 K3 K4 K5 KS Al A2 A3 A4 0 TOPIC:

RO SRO 206000A2.17 HPC 3.9 4.3

[] [] [] fl

[]

tHPCI inadvertent initiation: BWR-23,4 211000G2.2.38 SLC 3.6 4.5

[1

[]

[] [] fl j Knowledge of conditions and limitations in the facility license.

215003G2.1.27 IRM 3.9 4

[J []

[] [] []

[J [] []

Knowledge of system purpose and or function.

223002G2.4.20 PCISlNuclear Steam Supply Shutoff 3.8 4.3

[] []

[] []

[] []

Knowledge of operational implications of EOP warnings, cautions and notes.

239002A2.04 SRVs 4.1 4.2

[]

j [J ADS actuation Page 1 of 1 9/612011 2:58 PM

ES-401, REV 9 SRO T2G2 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME I SAFETY FUNCTION:

IR 1(1 1(2 1(3 1(4 1(5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 202002A2.03 Recirculation Flow Control 2.6 2.7 El H H H H El H l1 H H H Loss of D.C.

214000G2.2.42 RPIS 3.9 4.6 H H H H El H H H H H Ability to recognize system parameters that are entry-level conditions for Technical Specifications 233000G2.2.39 Fuel Pool CoolinglCleanup 3.9 4.5 H H H H H H H H H H 1 Knowledge of less than one hour technical specification action statements for systems.

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ES-401, REV 9 SRO T3 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME! SAFETY FUNCTION:

IR Ki K2 KS K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO G2.1.17 Conductof operations 3.9 4.0

[]

[J fl

[] [] []

Abilityto make accurate, clearand concise verbal reports.

G2.2.14 Equipment Control 39 4.3 L] LI LI LI LI ü LI Li LI [

Knowledge of the process for controlling equipment configuration or status G2.2.4 Equipment Control 3.6 3.6 LI ciri LI LI LI LI Li LI Li (multi-unit) Ability to explain the variations In control board layouts, systems, instrumentation and procedural actions between units at a facility.

G2.3.12 Radiation Control 3.2 3.7

[1 LI LI LI LI LI LI LI LI LI Knowledge of radiological safety principles pertaining to licensed operator duties G2.3.15 Radiation Control 2.9 3.1 LI LI LI LI LI LI LI LI LI LI Knowledge of radiation monitoring systems G2.4.31 Emergency Procedures/Plans 4.2 4.1 LI LI LI LI LI LI LI LI LI LI Knowledge of annunciators alarms, indications or response procedures G24.37 Emergency Procedures/Plans 3.0 4.1 LI LI LI LI LI LI LI LI El LI [I Knowledge of the lines of authority during implamentation of an emergency plan.

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ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility:

Browns Ferry NPP Date of Examination:

5/7/20 12 Exam Level: RO/SROI/SROU Operating Test No.:

1205 Control Room Systems@ (8 for RO); (7 for SRO-l); (2 or 3 for SRO-U, including I ESF)

System I JPM Title Type Code*

FIZ.n

a. Recirc Pump trip, power oscillations and loss of ability to A N S 1

insert rods require manual reactor scram

b. Remove RFPT A from service A, N, S 2
c. Rapid Depressurization with Turbine Bypass Valves EOI L N S 3

Appendix-11H

d. EHC Auto Cooldown L, N, 5 4
e. EOI Appendix-13 Emergency Venting Primary Containment A, EN, P, S 5
f. 01-82 Parallel D/G with Off-Site Power D, S 6
g. Off-Gas Post-Treatment Radiation HI-HI-HI A, D, L, S 9
h. Returning an IRM to service from Bypass D, L, S 7(R0 only)

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

i. Vent and Re-pressurize the Scram Pilot Air Header D, E, R 1
j. 3-AOI-100-2, Attachment 3, Part A-Start RCIC from outside D E R 7

the_Control_Room

k. O-SSI-2-1, Attachment 2 A, D, E 8

All RO and SRO-l 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 I SRO-I I SRO-U

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 (A)lternate path 4-6/2-3 (5)(5)(3)

(C)ontrol room (D)irect from bank

<91<81<4 (6)(5)(2)

(E)mergency or abnormal in-plant

? 1I? 1I1 (3)(3)(2)

(EN)gineered safety feature

-I-I1 (control room system) (1)(1)(1)

(L)ow-Powerl Shutdown 1I1I1 (4)(3)(1)

(N)ew or (M)odified from bank including 1(A) 2I 21?1 (4)(4)(2)

(P)revious 2 exams

<31< 31< 2 (randomly selected) (1)(1)(1)

(R)CA 1I1/1 (2)(2)(1)

(S)imulator (8)(7)(3)

ILT 1205 Control Room!ln-Plant Systems JPM Narrative Control Room Systems:

a.

Recirc Pump trip, power oscillations and loss of RPIS require manual reactor scram

  • Alternate PathlNew/Simulator
  • 2/3-AOI-68-1A, Recirc Pump Trip/Core Flow Decrease OPRMs Operable.
  • 295001 Partial or Complete Loss of Forced Core Flow Circulation, AA2.02 Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION : Neutron monitoring.

IMPORTANCE: RO 3.1 SRO 3.2

  • The operator will perform the actions of 2/3-AOI-68-lA, Recirc Pump Trip/Core Flow Decrease OPRMs Operable. This will direct the operator to insert control rods to less than 92.5% load line to suppress power oscillations. After the operator has inserted at least one control rod, a failure of Rod Control Power will occur. Power oscillations will ramp in and the following alarm will come in, OPRM Pre-Trip Condition, 2-9-5A window 18. With power oscillations present, the ARP will direct the operator to manually scram the reactor in these conditions.
b. Remove RFPT A from Service (Unit 2 or 3)
  • Alternate PathlNew/Simulator
  • 259001 Reactor Feedwater System A4.04 Ability to manually operate and/or monitor in the Control Room: System valves. IMPORTANCE: RO 3.1 SRO 2.9
  • Operator will be directed remove the 2A/3A RFPT from service in accordance with 2/3 3, Reactor Feedwater System. The operator will identify that the RFPT A discharge check valve fails to close and take actions in accordance with 2/3-01-3 c.

Rapid Depressurization with Turbine Bypass Valves, EOI Appendix-11H (Unit 2 or 3)

  • Low Power/New/Simulator
  • 241000 Reactor/Turbine Pressure Regulating System A4.06 Ability to manually operate and/or monitor in the control room: Bypass valves IMPORTANCE: RO 3.9 SRO 3.9
  • Operator is directed to perform operations necessary to establish the Main Condenser as an Alternate RPV pressure control system for Rapid Depressurization as directed by 2-EOI Appendix-i iH
d. EHC Auto Cooldown (Unit 2 or 3)
  • Low-Power/New/Simulator
  • 2/3-01-47, Turbine Generator System
  • 239001 Main and Reheat Steam System A4.09 Ability to manually operate and/or monitor in the control room: Reactor Pressure IMPORTANCE: RO 3.9 SRO 3.3

ILT 1205 Control Roomlln-Plant Systems JPM Narrative

  • Operator is directed to commence an Auto Cooldown with EHC in accordance with 2/3 47, Turbine Generator System. Operator must utilize the Human Machine Interface (HMI) of the EHC system to commence a cooldown as well as adjust final target pressure.

e.

EOI Appendix-13 Emergency Venting Primary Containment (Unit 2 or 3)

  • Alternate Path JENgineered Safety Feature /Previous /Simulator
  • 295024 High Drywell Pressure EA2.01 Ability to determine and/or interpret the following as they apply to HIGH DRYWELL PRESSURE: Drywell Pressure IMPORTANCE: RO 4.2 SRO 4.4
  • Operator is directed to emergency vent Primary Containment to restore and maintain Drywell Pressure below 55 psig as directed by 2/3-EOI Appendix-13, Emergency Venting Primary Containment. Emergency Venting of the Suppression Chamber through the Hardened Wetwell Vents will be unsuccessful and the operator will vent the Drywell to Secondary Containment via Primary Containment vent duct failure.

f.

01-82 Parallel DIG with Off-Site Power Source (Unit 2 or 3)

  • Direct from bank/Simulator
  • 0/3-01-82, Standby Diesel Generator System
  • 264000 Emergency Generators (Diesel/Jet) A4.04 Ability to manually operate and/or monitor in the control room: Manual start, loading, and stopping of emergency generator IMPORTANCE: RO 3.7 SRO 3.7
  • Operator will perform actions necessary to parallel the A/3A Diesel Generator (DG) with the Off-Site power source in accordance with 0/3-01-82, Standby Diesel Generator System.

g.

Off-Gas Post-Treatment Radiation HI-HI-HI (Unit 2 or 3)

  • Alternate PathlDirect from bank/Low power/Simulator
  • 2/3-ARP-9-4C, Window 35 and 2/3-AOI-66-2, Offgas Post-Treatment Radiation HI-HI-HI
  • 271000 Offgas System A2.04 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: Offgas system high radiation IMPORTANCE: RO 3.5 SRO 3.8
  • Operator is directed to respond to Offgas Post-Treatment Radiation HI-HI-HI alarm in accordance with 2/3-ARP-9-4C Window 35. Operator will determine that the Offgas Isolation valve 2/3-FCV-66-28 failed to close; operator will close the valve then refer to 2/3-AOI-66-2, Offgas Post-Treatment Radiation HI-HI-HI, and perform the actions of 2/3-AOI-66-2 insert a core flow runback and reactor scram. Operator will then shut the MSIVs.

ILT 1205 Control Roomlln-Plant Systems JPM Narrative

h. Returning an IRM to service from Bypass (Unit 2 or 3) (RO only)
  • Direct from bank/Low-Power/Simulator
  • 215003 Intermediate Range Monitor System A2.02 Ability to (a) predict the impacts of the following on the IRM System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

IRM mop condition IMPORTANCE: RO 3.5 SRO 3.7

  • Operator is directed to return a bypassed IRM to service in accordance with 2/3-OI-92A, Intermediate Range Monitors. Operator must fully insert the IRM and then range the IRM to the proper scale to prevent a half scram when un-bypassed.

In-Plant Systems:

i.

Vent and Re-pressurize the Scram Pilot Air Header

  • Direct from bank/Emergency or Abnormal In-Plant/RCA Entry
  • 1-EOI Appendix-1B, Venting and Re-pressurizing the Scram Pilot Air Header
  • 295015 Incomplete SCRAM AA1.01 Ability to operate and/or monitor the following as they apply to 1NCOMPLETE SCRAM: CRD hydraulics IMPORTANCE: RO 3.8 SRO 3.9
  • Operator will simulate the component manipulations required to vent and subsequently re-pressurize the Scram Pilot Air Header as directed by 1-EOI Appendix 1B, Venting and Re-pressurizing the Scram Pilot Air Header.

j.

3-AOI-100-2, Attachment 3, Part A-Start RCIC from outside the Control Room

  • Direct from bank/Emergency or Abnormal In-Plant/RCA Entry
  • 3-AOI-100-2, Control Room Abandonment, Attachment 3, Part A
  • 295016 Control Room Abandonment AA1.07 Ability to operate and/or monitor the following as they apply to CONTROL ROOM ABANDONMENT: Control room/local control transfer mechanisms IMPORTANCE: RO 4.2 SRO 4.3
  • Operator will simulate performing operations necessary to align RCIC from outside the Control Room as directed by 3-AOI-100-2, Control Room Abandonment.

k.

O-SSI-2-1, Attachment 2

  • Alternate Path/Direct from bank/Emergency or Abnormal In-Plant
  • 0-551-2-1, Unit 2 Reactor Building Fire EL 519 through 565 West of Column Line Ru
  • 600000 Plant Fire on Site AA2.16 Ability to determine and interpret the following as the apply to PLANT FIRE ON SITE: Vital equipment and control systems to be maintained and operated during a fire IMPORTANCE: RO 3.0 SRO 3.5

ILT 1205 Control Roomlln-Plant Systems JPM Narrative

  • Time Critical JPM for an operator to simulate performing designated steps of an SSI as directed by the Unit 2 Unit Supervisor and O-SSI-2-l. Operator will have to simulate starting the 2D RHR pump using the manual breaker close pushbutton after the breaker fails to close.
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