ML101590071

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Initial Exam 2010-301 Draft Administrative Documents
ML101590071
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 05/03/2010
From:
NRC/RGN-II
To:
Progress Energy Carolinas
References
50-324/10-301, 50-325/10-301
Download: ML101590071 (20)
v • d • e


Text

ES..401, Rev. 9 BWR Examination Outline Form ES-401-1 Facility:

BRUNSWICK Date of Exam: APRIL 2010 RO K/A Category Points SROOnIy Points Tier Group KKKKKKAAAAG A2 G*

Total 1

2 3

4 5

6 1

2 3

4 Total

=

=

1.

1 4

3 20 3

4 7

Emergency &

2 T

2 1

7 1

2 3

Abnormal Plant

N/A N/A Evolutions TierTotals

6 27 6

10

= -

- = -= =

1 323 22333212 26 2

3 5

2.

2 1

1 1

11 1

21 1

1 1

12 0

1 2

3 Plant

Systems Tier Totals 3

3 4

5 4

3 2

3 38 3

5 8

=

=

=

3. Generic Knowledge and Abilities 1

2 3

4 10 1

2 3

4 7

Categories 3

3 2

2 2

2 1

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 of the SRO-only outline, the Tier Totals in each K/A category shall not be less than two).

2.

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

The final point total for each group and tier may deviate by 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.

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 I and 2 from the shaded systems and K/A categories.

7, The generic (G) K/As in Tiers I and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system.

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. I does not apply).

Use duplicate pages for RO and SRO-only exams.

9.

For TierS, select topics from Section 2 of the KIA catalog, and enter the K1A numbers, descriptions, IRs, and point totals (U) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.

E8-401 1 Rev. 9 BWR examination Outline Form ES-401-1 Facility:

BRUNSWICK Date of Exam: APRIL 2010 RO KIA Category Points SRO-Only Points Tier Group K

K K

K K

K A

A A

A G

A2 G*

Total 1

2 3

4 5

6 1

2 3

4 Total

1.

1 4

3 3

4 3

3 20 3

4 7

Emergency &

2 1

1 1

2 1

1 7

1 2

3 Abnormal Plant NIA NIA Evolutions Tier Totals 5

4 4

6 4

4 27 4

6 10 1

3 2

3 2

2 3

3 3

2 1

2 26 2

3 5

2.

1 1

1 1

1 1

2 1

1 1

1 12 0

1 2

3 Plant 2

Systems Tier Totals 4

3 4

3 3

4 5

4 3

2 3

38 3

5 8

3. Generic Knowledge and Abilities 1

2 3

4 10 1

2 3

4 7

Categories 3

3 2

2 2

2 1

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 +/- 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.

Systemslevolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justifiedj 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 KIA statements.

4.

Select topics from as many systems and evolutions as possiblej 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 1 and 2 from the shaded systems and KIA categories.

7.
  • The generic (G) KIAs in Tiers 1 and 2 shall be selected from Section 2 of the KIA 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 the group and tier totals for each category in the table abovej 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 KIA catalog, and enter the KIA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. limit SRO selections to KIAs that are linked to 10 CFR 55.43.

,.. _0._..

ES-401, REV 9 TIG1 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME ISAFETY FUNCTION:

IR 1(1 K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPIC:

RO SRO 295001AK1.03 Partial or Complete Loss of Forced 3.6 4.1 fl E E fl Thermal limits Core Flow Circulation / 1 & 4 295003AA2.05 Partial or Complete Loss of AC /6 3.9 4.2

[]

Whether a partial or complete loss of AC. power has occurred 295004AA102 Partial or Total Loss of DC Pwr / 6 3.8 4.1

[]

fl Systems necessary to assure safe plant shutdown 295005AA1.07 Main Turbine Generator Trip 13 3.3 3.3 D fl H H H Li A.C. electrical distribution 295006AK1.02 SCRAM / 1 3.4 3.7 U Li LI H LI Li H LI H fl Shutdown margin 295016G2.4.1 Control Room Abandonment 17 46 4.8 H

r Kno1edge of EOP entry conditions and immediate action steps.

295018AA1.02 Partial or Total Loss of CCW /8 3.3 3.4 fl System loads 295019G2.2.37 PartialorTotalLossoflnst.AirI8 3.6 4.6 H H H H Ability to determine operability and/or availability of safety related equipment 295021AA2.02 LossofShutdownCooling/4 3.4 H H H H H H H fl LI H RHRlshutdown cooling system flow 295023AK3.03 Refueling Acc Cooling Mode / 8 3.3 3.6 H H 1 H H H fl fl H H LI Ventilation isolation 295024G2.2.37 High Orywell Pressure / 5 3.6 4.6 H H H H H H H H H H Ability to determine operability and/or availability of safety related equipment Page 1 of 2 06/18/2009 8:52 AM ES-401, REV 9 KA NAME I SAFETY FUNCTION:

295001AK1.03 Partial or Complete Loss of Forced Core Flow Circulation I 1 & 4 295003AA2.05 Partial or Complete Loss of AC 16 295004AA1.02 Partial or Total Loss of DC Pwr 16 295005AA1.07 Main Turbine Generator Trip 13 295006AK1.02 SCRAM 11 295016G2.4.1 Control Room Abandonment 17 295018AA1.02 Partial or Total Loss of CCW 18 295019G2.2.37 Partial or Total Loss of Inst. Air I 8 295021AA2.02 Loss of Shutdown Cooling I 4 295023AK3.03 Refueling Ace Cooling Mode I 8 295024G2.2.37 High Orywell Pressure I 5 T1G1 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.6 4.1

~ 0 0 0 0 0 0000 3.9 4.2 0 0 0 0 0 0 0 ~ 0 0 0 3.8 4.1 0 DOC 0 0 ~ 0 0 0 0 3.3 3.3 0 0 0 0 0 0 ~ 0 0 0 0 3.4 3.7

~ 0 DOC COO 0 0 0 4.6 4.8 0 0 0 0 [] 0 COO 0 ~

3.3 3.4 0 0 0 0 0 [] ~ 0 0 0 0 3.6 4.6 0 0 0 0 0 0 0 0 0 0 ~

3.4 3.4 0 0 0 0 0 0 [] ~ 0 0 0 3.3 3.6 0 0 ~ 0 0 0 0 [] [] 0 0 3.6 4.6 0 0 0 0 0 0 0 ODD ~

Page 1 of2 FORM ES-401-1 TOPIC:

Thermal limits........................................

Whether a partial or complete loss of AC. power has occurred..............................................

Systems necessary to assure safe plant shutdown.......

AC. electrical distribution..........................

Shutdown margin.......................................

Knowledge of EOP entry conditions and immediate action steps.

System loads..........................................

Ability to determine operability andlor availability of safety related equipment RHRlshutdown cooling system flow Ventilation isolation.................................

Ability to determine operability andlor availability of safety related equipment 0611812009 8:52 AM

ES-401, REV 9 TIGI BWR EXAMINATION OUTLINE FORM ES-401-1 Generator Voltage and Electiic Grid 3.3 Distrurbancecs KA NAME I SAFETY FUNCTION:

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

TOPIC:

RO SRO 295025EA2.05 High Reactor Pressure I 3 3.4 3.6

[] fl Decay heat generation 295026EA1.01 Suppression Pool High Water Temp. /

4.1 4.1 fl Suppression pool cooling 5

295028EK3.05 High Drywell Temperature / 5 3.6 3.7 Reactor SCRAM 295030EK2.09 Low Suppression Pool Wtr Lvl /5 2.5 2.8 SPDSIERISICRIDS/GDS: Plant-Specific 295031 EK3.03 Reactor Low Water Level I 2 4.14.4

[]

D E fl El fl Spray cooling 295037EK1.03 SCRAM Condition Present and Power 4.2 4.4 Boron effects on reactor power (SBLC)

Above APRM Downscale or Unknown

/1 295038EK2.12 High Off-site Release Rate / 9 3.5 3.8 E fl flfl Feedwater leakage control: BWR-6 600000AK2.01 Plant Fire On Site I 8 2.6 2.7 Sensors / detectors and valves 700000AK1.02 3.4 Over-excitation Page 2 of 2 06/18/2009 8:52 AM ES-401, REV 9 T1G1 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME I SAFETY FUNCTION:

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

RO SRO 295025EA2.05 High Reactor Pressure 13 3.4 3.6 0 0 [] 0 0 0 0 ~ 0 0 0 Decay heat generation.................................

~~~~~~~~~~~~~~

---~~~~~=-=-~~~~~~-=~=-~~--~=-~=-~~~~----~------~-------

295026EA1.01 Suppression Pool High Water Temp. I 4.1 4.1 0 0 0 0 0 0

~ 0 [] 0 n Suppression pool cooling..............................

5 295028EK3.05 High Drywell Temperature 15 3.6 3.7 0 0 ~ 0 0 0 0 0 [] 0 []

Reactor SCRAM.........................................

295030EK2.09 Low Suppression Pool Wtr Lvl/S 2.S 2.8 0 ~ 0 0 0 [] 0 0 0 [] 0 SPDS/ERIS/CRIDS/GDS: Plant-Specific..................

295031EK3.03 Reactor Low Water Level/2 4.1 4.4 0 0 ~ 0 0 [] 0 0 [] 0 []

Spray cooling.........................................

295037EK1.03 SCRAM Condition Present and Power 4.2 4.4

~O[]OD[]OOOOO Boron effects on reactor power (SBLC).................

Above APRM Downscale or Unknown 11 295038EK2.12 High Off-site Release Rate 1 9 3.5 3.8

[]~OOOOOO[][]O Feedwater leakage control: BWR-6.....................

600000AK2.01 Plant Fire On Site I 8 2.6 2.7 O~[]DODDO[]DO Sensors I detectors and valves 700000AK 1.02 Generator Voltage and Electric Grid 3.3 Distrurbancecs 3.4

~OOOOOOOOOO Over -excitation Page 2 of2 06/18/2009 8:52 AM

NAME / SAFETY FUNCTION:

High Reactor Water Level 12 Inadvertent Reactivity Addition I I Incomplete SCRAM / I Inadvertent Cont. Isolation 15 & 7 High Secondary Containment Area Temperature! 5 High Secondary Containment Area Radiation Levels I 9 Secondary Containment High Differential Pressure / 5 T1G2 BWR EXAMINATION OUTLINE IR Ki k2 K3 K4 K5 K6 Al A2 A3 A4 G RO SRO 3.0 3.2 4.0 4.3 4.6 4.8 3.6 3.7 3.9 4.0 3.6

3.6 TOPIC

Moisture carryover Cause of reactivity addition Bypassing rod insertion blocks Knowledge of EOP entry conditions and immediate action steps.

Secondary containment ventilation Affected systems so as to isolate damaged portions....

Secondary containment ventilation system ES-401, REV9 KA 295008AK1.01 295014AA203 295015AK3.01 295020G24.1 295032EK2.02 295033EA1.05 295035EA1.01 FORM ES-401-1 Page 1 of 1 06/18/2009 8:52 AM ES-401, REV 9 KA NAME I SAFETY FUNCTION:

295008AK1.01 High Reactor Water Levell 2 295014AA2.03 Inadvertent Reactivity Addition /1 295015AK3.01 Incomplete SCRAM 11 295020G2.4.1 Inadvertent Cont. Isolation /5 & 7 295032EK2.02 High Secondary Containment Area Temperature 15 295033EA 1.05 High Secondary Containment Area Radiation Levels I 9 295035EA1.01 Secondary Containment High Differential Pressure I 5 T1G2 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.0 3.2

~ 0 0 0 0 0 0 0 0 0 0 4.0 4.3 0 COD 0 0 0 ~ 0 0 0 3.4 3.7 0 0 ~ 0 0 0 0 0 0 0 0 4.6 4.8 0 [] 0 0 0 0 0 0 0 0 ~

3.6 3.7 0 ~ 0 0 0 0 0 0 0 0 0 3.9 4.0 0 0 0 0 0 0 ~ 0 0 0 0 3.6 3.6 0 0 0 0 0 0 ~ 0 0 0 0 Page 1 of 1 FORM ES-401-1 TOPIC:

Moisture carryover....................................

Cause of reactivity addition..........................

Bypassing rod insertion blocks........................

Knowledge of EOP entry conditions and immediate action steps.

Secondary containment ventilation.....................

Affected systems so as to isolate damaged portions....

Secondary containment ventilation system..............

06/18/2009 8:52 AM

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

IR Ki K2 K3 K4 K5 1(6 Al A2 A3 A4 G TOPIC:

RO SRO 203000K1.01 RHRJLPCI: Injection Mode 2.8 2.8 El fl fl

[]

Condensate storage and transfer system: Plant-Specific 205000G2.4.21 Shutdown Cooling 4.0 4.6 Knowledge of the parameters ond logic used to assess the status of safety functions 206000K4.02 HPCI 3.9 4

fl System isolation: BWR-2,3,4 209001K3.O1 LPCS 3.8 3.9 H H H H El H H H H H Reactor water level 209001K3.03 LPCS 2.9 3.0 H H H H H H H H H H Emergency generators 211000K101 SLC 3.0 3.3 H H H H H El H H H H Corespraylinebreakdetection: Plant-Specift 211000K1.09 SLC 3.2 3.4l H H H H H H H H El H Core spray system: Plant-Specific 212000K2.O1 RPS 3.2 3.3 El H H H H H H E H H RPS motor-generator sets 215003A2.02 IRM 35 3.7 H

H H fl H H H H H IRM mop condition 2150041<5.03 Source Range Monitor 2.8 2.8 El El El H H H H H H H Changing detector position 215005A2.05 APRM / LPRM 3.5 3.6 H El El H H H H Loss of recirculation flow signal Page 1 of 3 06/18/2009 8:52 AM ES-401, REV 9 T2G1 BWR EXAMINATION OUTLINE KA NAME I SAFETY FUNCTION:

IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 203000K1.01 RHRlLPCI: Injection Mode 2.8 2.8

~ 0 0 0 0 0 0 0 0 0 0 205000G2.4.21 Shutdown Cooling 4.0 4.6 0 0 0 0 0 0 0 0 0 0 ~

206000K4.02 HPCI 3.9 4

DDD~ODDDDDD 209001K3.01 LPCS 3.8 3.9 DD~DD[JDDDDD 209001K3.03 LPCS 2.9 3.0 DD~DDODDDDD 211000K1.01 SLC 3.0 3.3

~DDDDDDDDDD 211000K1.09 SLC 3.2 3.4

~DDDDDDDDDD 212000K2.01 RPS 3.2 3.3 D~DDDDDDDDD 215003A2.02 IRM 3.5 3.7 DDDDDDD~DDD 215004K5.03 Source Range Monitor 2.8 2.8 n [J 0 0 ~ 0 0 0 0 0 0 215005A2.05 APRM I LPRM 3.5 3.6 0 0 0 0 0 0 0 ~ 0 0 Page 1 of 3 FORM ES-401-1 TOPIC:

Cendensate storage and transfer system: Plant-Specific Knowledge of the parameters and logic used to assess the status of safety functions System isolation: BWR-2.3,4 Reactor water level Emergency generators Cere spray line break detection: Plant-Specific Core spray system: Plant-Specific RPS motor-generator sets IRM inop condition Changing detector position Loss of recirculation flow signal 06/18/2009 8:52 AM

ES-401, REV 9 T2GI 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 215005A2.07 APRM I LPRM 3.2 3.4 El fl []

fl Recirculation flow channels flow mismatch 217000A1,01 RCIC 3.7 3.7 f

J LI LI LI [

RClCflow 217000A1.04 RCIC 3.6 3.6 LI LI Reactor pressure 218000K3,01 ADS 4.4 4.4 Restoration of reactor water level after a break that does not depressunze the reactor when required 223002A3.03 PCIS/Nuclear Steam Supply Shutoff 2.5 2.8 LI LI LI LI LI LI LI i LI LI SPDS/ERIS/CRIDS/GDS: Plant-Specific 239002A404 SRVs 4.3 4.3 LI LI LI LI LI LI LI LI LI LI Suppression pool temperature 2590021(6.04 Reactor Water Level Control 3.1 3.1 LI LI LI LI LI LI LI LI LI LI Reactor feedwater flow input 261000A3.01 SGTS 3.2 3.3 LI LI LI LI LI LI LI LI LI LI System flow 262001K6.01 AC Electrical Distribution 3.1 3.4 LI LI LI LI LI LI LI LI fl LI D.C. power 2620011(6.02 AC Electrical Distribution 3.6 3.9 fl fl LI LI LI LI LI LI LI LI Off-site power 262002G2.4.3 UPS (AC/DC) 3.7 39 LI LI LI LI LI LI LI LI LI LI Ability to identify post-accident instrumentation.

Page 2 of 3 06/18/2009 8:52 AM ES-401, REV 9 T2G1 BWR EXAMINATION OUTLINE FORM ES-401*1 KA NAME I SAFETY FUNCTION:

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

RO SRO 215005A2.07 APRM / LPRM 3.2 3.4 DOC 0 0 0 0 21 0 0 0 Recirculation flow channels flow mismatch 217000A1.01 RCIC 3.7 3.7 000000210000 RCICflow 217000A 1.04 RCIC 3.6 3.6 000000210000 Reactor pressure 218000K3.01 ADS 4.4 4.4 002100000000 Restoration of reactor water level after a break that does not depressurize the reactor when required 223002A3.03 PCIS/Nuclear Steam Supply Shutoff 2.5 2.8 000000002100 SPDS/ERIS/CRIDS/GDS: Plant-Specific 239002A4.04 SRVs 4.3 4.3 0 0 0 0 0 0 [] 0 0 21 0 Suppression pool temperature 259002K6.04 Reactor Water Level Control 3.1 3.1 0 0 0 0 0 21 0 0 0 0 0 Reactor feedwater flow input 261000A3.o1 SGTS 3.2 3.3 0 0 0 0 0 0 0 0 21 0 0 System flow 262001K6.01 AC Electrical Distribution 3.1 3.4 0 0 0 0 0 21 0 0 0 0 0 D.C. power 262001K6.02 AC Electrical Distribution 3.6 3.9 COD 0 0 21 0 0 DOC Off-site power 262002G2.4.3 UPS (AC/DC) 3.7 3.9 0 0 0 0 0 0 0 ODD 21 Ability to identify post-accident instrumentation.

Page 2 of3 06/18/2009 8:52 AM

ES-401, REV 9 T2G1 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 263000K2.01 DC Electrical Distribution 3.1 3.4

[]

Major D.C. loads 264000A1.01 EDGs 3.0 3.0 Lube oil temperature 300000K5.13 Instrument Air 2.9 2.9 D

Filters 400000K4.01 Component Cooling Water 3.4 3.9 E

Automatic start of standby pump Page 3 of 3 06/18/2009 8:52 AM ES-401, REV 9 T2G1 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME I SAFETY FUNCTION:

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

RO SRO 263000K2.01 DC Electrical Distribution 3.1 3.4 0 ~ 0 0 0 0 0 0 0 0 0 Major D.C. loads 264000A 1.01 EDGs 3.0 3.0 0 0 0 0 0 0 ~ 0 0 0 0 Lube oil temperature 3OOO00K5.13 Instrument Air 2.9 2.9 0 U 0 0 ~ 0 0 0 0 0 0 Filters 400000K4.01 Component Coolin9 Water 3.4 3.9 0 0 0 ~ 0 0 0 0 0 0 0 Automatic start of standby pump Page 3 of 3 06/18/2009 8:52 AM

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

IR Kl K2 K3 K4 KS K6 Al A2 A3 A4 G

TOPIC:

RO SRO 201001A1.03 CRD Hydraulic 2.9 2.8 CR0 system flow 201002K6.O1 RMCS 2.5 2.6 Select matrix power 201006K5.01 RWM 3.3 3.7 fl fl Minimize clad damage if a control rod drop accident (CRDA) occurs: P-Spec(Not-BWR6) 214000A3.04 RPIS 3.5 3.8 j D J RCIS: Plant-Specific 216000K2.O1 Nuclear Boiler Inst.

2.8 2.8 El Analog trip system: Plant-Specific 230000A1.06 RHRJLPCI: TonislPool Spray Mode 3.3 3.3 Suppression pool level 234000A4.02 Fuel Handling Equipment 14 3.7 E

Control rod drive system 259001A2.06 Reactor Feedwater 3.2 3.2 D [] E [3 [3 [3 [3 j fl [3 E Loss of AC. electrical power 272000K305 Radiation Monitoring 3.5 3.7

[3 [3

[3 [] [3 [3 [3 [3 [3 [3 Offgas system 2880001(1.04 Plant Ventilation 2.62.6

[3 [3 [3 [3 [3 [3 [3 [3 [3 [3 Applicable component cooling water system: Plant-Specific 290002G2.4.46 Reactor Vessel Internals 4.2 4.2 Ability to verify that the alarms are consistent with the plant conditions.

Page 1 of 2 06/18/2009 8:52 AM ES*401, REV 9 T2G2 BWR EXAMINATION OUTLINE FORM ES-401*1 KA NAME f SAFETY FUNCTION:

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

RO SRO 201001A1.03 CRD Hydraulic 2.9 2.8 DODDOO~OOOD CRD system flow 201002K6.01 RMCS 2.5 2.6 OODOO~DDDOO Select matrix power 201006K5.01 RWM 3.3 3.7 OOOO~OODODD Minimize clad damage if a control rod drop accident (CRDA) occurs: P-Spec(Not-BWR6) 214000A3.04 RPIS 3.5 3.8 DOOODDDD~OD RCIS: Plant-Specific 216000K2.01 Nuclear Boiler Inst.

2.8 2.8 O~DOOOOODDO Analog trip system: Plant-Specific 230000A 1.06 RHRlLPCI: ToruslPool Spray Mode 3.3 3.3 OOOOOO~DODD Suppression pool level 234000A4.02 Fuel Handling Equipment 3.4 3.7 OODODDOOO~O Control rod drive system 259001A2.06 Reactor Feedwater 3.2 3.2 o 0 0 0 0 0 0 ~ n 0 f~

Loss of AC. electrical power 272000K3.05 Radiation Monitoring 3.5 3.7 DC~DOOOODDD Offgas system 288000K1.04 Plant Ventilation 2.6 2.6

~OOCODOODOO Applicable component cooling water system: Plant-Specific 290002G2.4.46 Reactor Vessellntemals 4.2 4.2 ODOOOOOOOO~

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

Page 1 of 2 06/18/2009 8:52 AM

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

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

RO SRO 290003K401 Control Room HVAC 3.1 3.2 LI LI LI LI LI LI LI LI System initiations/reconfiguration: Plant-Specific Page 2 of 2 06/18/2009 8:52 AM ES-401, REV 9 T2G2 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME I SAFETY FUNCTION:

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

RO SRO 290003K4.01 Control Room HVAC 3.1 3.2 0 0 0 ~ 0 0 0 0 0 0 0 System initiations/reconfiguration: Plant-Specific Page 2 of 2 06/18/2009 8:52 AM

RO SRO 3.9 4

Knowledge of system purpose and or function.

4.6 4.3

, fl Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup.

3.6 4.3

[]

Knowledge of conservative decision making practices 3.9 E fl D []

Ability to determine the expected plant configuration using design and configuration control documentaion 3.2 4.2

[]

[] [

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

3.9 4.5 D

Knowledgeoflessthanonehourtechnicalspeciflcation action statements for systems.

3.4 3.8 El Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities 2.0 3.8

[] []

[]

[] [

Ability to aprove release permits

[1 El El Knowledge of EOP entry conditions and immediate action steps.

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

JR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G TOPJC:

G2.1.27 G2.1 31 G2.1.39 G2.2.1 5 G2.2.25 G2.2.39 G2.3.14 G2.3.6 Conduct of operations Conduct of operations Conduct of operations Equipment Control Equipment Control Equipment Control Radiation Control Radiation Control G2.4.1 Emergency Procedures/Plans 4.6 4.8 02.4.9 Emergency Procedures/Plans 3.8 4.2 El El El El El El El El El LI I strategies.

Knowledge of low power I shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation Page 1 of 1 06/1812009 8:52 AM ES-401, REV 9 KA NAME I SAFETY FUNCTION:

G2.1.27 Conduct of operations G2.1.31 Conduct of operations G2.1.39 Conduct of operations G2.2.15 Equipment Control G2.2.25 Equipment Control G2.2.39 Equipment Control G2.3.14 Radiation Control G2.3.6 Radiation Control G2.4.1 Emergency Procedures/Plans G2.4.9 Emergency Procedures/Plans T3 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.9 4

D D D D D DOD D D ~

4.6 4.3 D D D DOD 0 D D D ~

3.6 4.3 D DOD DOD 0 0 [] ~

3.9 4.3 0 0 0 0 ODD 0 D 0 ~

3.2 4.2 DOD 0 D D DOD D ~

3.9 4.5 0 0 ODD 0 0 0 0 0 ~

3.4 3.8 0 0 0 0 0 0 [] D 0 ~

2.0 3.8 ODD 0 D [] [] ODD ~

4.6 4.8 0 0 0 0 0 0 [] 0 [] 0 ~

3.8 4.2 0 0 0 ODD D [] u 0 ~

Page 1 of 1 FORM ES-401-1 TOPIC:

Knowledge of system purpose and or function.

Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup.

Knowledge of conservative decision making practices Ability to determine the expected plant configuration using design and configuration control documentaion Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.

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

Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities Ability to aprove release permits Knowledge of EOP entry conditions and immediate action steps.

Knowledge of low power / shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation strategies.

06/1812009 8:52 AM

ES-401, REV 9 KA 295006G2.2.22 295021AA2.03 295023G2.4.46 295026EA2.03 295028EA2.05 295038G2.2.42 6OtJ000G2.2.37 NAME I SAFETY FUNCTION:

SCRAM/i Loss of Shutdown Cooling /4 Refueling Acc Cooling Mode / 8 Suppression Pool High Water Temp. /

5 High Drywell Temperature / 5 High Off-site Release Rate! 9 Plant Fire On Site / 8 SRO TIGI BWR EXAMINATION OUTLINE IR Ki K2 K3 K4 K5 K6 Al A2 A3 A4 G

RO SRO 4.0 4.7 EEDDDDE1DE 3.5 3.5 4.2 4.2 3.9 4.0 3.6 3.8 3.9 4.6 3.6 4.6 FORM ES-401-1 TOPIC:

Knowledge of limiting conditions for operations and safety limits.

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

Reactor pressure Torus/suppression chamber pressure: Plant-Specific...

Ability to recognize system parameters that are entry-level conditions for Technical Specifications Ability to determine operability and/or availability of safety related equipment Page i of 1 06/i8!2009 8:52 AM ES-401, REV 9 SRO T1G1 BWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION:

IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 295006G2.2.22 SCRAM 1 1 4.0 4.7 0 0 0 0 0 0 0 0 0 0 ~

295021AA2.03 Loss of Shutdown Cooling /4 3.5 3.5 0 0 0 0 0 0 0 ~ [] 0 0 295023G2.4.46 Refueling Acc Cooling Mode 1 8 4.2 4.2 0 0 0 0 0 0 0 0 0 0 ~

295026EA2.03 Suppression Pool High Water Temp. 1 3.9 4.0 0 0 0 [J 0 0 0 21 0 0 0 5

295028EA2.05 High Orywell Temperature /5 3.6 3.8 0 0 [] 0 0 0 0 21 0 0 0 295038G2.2.42 High Off-site Release Rate 1 9 3.9 4.6 0 0 0 [] [] 0 0 0 0 0 ~

600000G2.2.37 Plant Fire On Site 1 8 3.6 4.6 0 0 0 0 0 0 0 0 0 0 ~

Page 1 of 1 FORM ES-401*1 TOPIC:

Knowledge of limiting conditions for operations and safety limits.

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

Reactor pressure......................................

Torus/suppression chamber pressure: Plant-Specific...

Ability to recognize system parameters that are entry-level conditions for Technical Specifications Ability to determine operability and/or availability of safety related equipment 06/1812009 8:52 AM

ES-401, REVS KA NAME! SAFETY FUNCTION:

295008AA2.05 High Reactor Water Level 1 2 295014G2.1.19 Inadvertent Reactivity Addition/i 295029G2.1.7 High Suppression Pool Wtr Lvi / 5 SRO TIG2 BWR EXAMINATION OUTLINE IR Ki K2 k3 k4 K5 K6 Al A2 A3 A4 G

RO SRO 2.9 3.1 3.9 3.8 4.4 4.7 FORM ES-401-1 TOPIC:

Swell Ability to use plant computer to evaluate system or component status.

Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instwment interpretation.

Page 1 of 06/18/2009 8:52 AM ES-401, REV 9 SRO T1G2 BWR EXAMINATION OUTLINE KA NAME I SAFETY FUNCTION:

IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G RO SRO 295008AA2.05 High Reactor Water Levell 2 2.9 3.1 0 0 0 0 0 0 0 ~ [] 0 0 295014G2.1.19 Inadvertent Reactivity Addition 11 3.9 3.8 0 0 0 0 0 0 0 CJ 0 [] ~

295029G2.1.7 High Suppression Pool Wtr LvllS 4.4 4.7 0 0 0 0 0 0 0 0 0 0 ~

Page 1 of 1 FORM ES-401-1 TOPIC:

Swell.................................................

Ability to use plant computer to evaluate system or component status.

Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation.

06118/2009 8:52 AM

ES.401, REV 9 SRO T2G1 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 212000A2.12 RPS 4.0 4.1 Main turbine stop control valve closure 217000G2.4.8 RCIC 3.8 4.5 Knowledge of how abnormal operating procedures are used in conjunction with EOPs.

2.39002G2.2.25 SRVs 3.2 4.2 fl fl Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.

262002G2.1.23 UPS (AC/DC) 4.3 4.4 Ability to perform specific system and integrated plant procedures during all modes of plant operation.

300000A2.OllnstrumentAir 2.9 2.8 Airdryerandfiltermalfunctions Page 1 of 1 06118/2009 8:52 AM ES-401, REV 9 KA NAME I SAFETY FUNCTION:

212000A2.12 RPS 217000G2.4.8 RCIC 239002G2.2.25 SRVs 262002G2.1.23 UPS (ACIDC) 300000A2.01 Instrument Air SRO T2G1 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 4.0 4.1 0 0 0 0 0 0 0 2J 0 0 0 3.8 4.5 0 0 0 0 0 0 0 0 0 0 ~

3.2 4.2 0 0 0 0 0 0 0 0 0 0 ~

4.3 4.4 0 0 0 0 0 0 0 0 0 0 ~

2.9 2.8 0 0 0 0 0 0 0 2J 0 0 0 Page 1 of 1 FORM ES-401-1 TOPIC:

Main turbine stop control valve closure Knowledge of how abnormal operating procedures are used in conjunction with EOPs.

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

Ability to perform specific system and integrated plant procedures during all modes of plant operation.

Air dryer and filter malfunctions 06118/2009 8:52 AM

ES-401, REV 9 SRO 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 204000G223 RWCU 3.8 3.9 LI LI LI LI LI (multi-unit license) Knowledge of the design, procedural and operational differences between units.

214000A2.03 RPIS 3.6 3.9 LI LI LI LI LI LI []

[lfljOvertravel/in-out 233000G2.4.34 Fuel Pool CoolinglCleanup 4.2 4.1 LI LI LI LI LI LI LI LI LI LI Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects Page 1 of 1 06/18/2009 8:52 AM ES-401, REV 9 SRO T2G2 BWR EXAMINATION OUTLINE KA NAME I SAFETY FUNCTION:

IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 204000G2.2.3 RWCU 3.8 3.9 0 0 0 0 0 0 0 0 0 0 ~

214000A2.03 RPIS 3.6 3.9 nOD 0 0 0 0 ~ 0 0 0 233000G2.4.34 Fuel Pool Cooling/Cleanup 4.2 4.1 0 0 0 0 0 0 0 0 0 0 ~

Page 1 of 1 FORM ES-401-1 TOPIC:

(multi-unit license) Knowledge of the design, procedural and operational differences between units.

Overtravellin-out Knowledge of RO tasks performed outside the main control room during an emergency and the resultant operational effects 06/1812009 8:52 AM

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

ER Ki K2 1<3 K4 1<5 K6 Al A2 A3 A4 G TOPIC:

RO SRO G2.1 42 Conduct of operations 2.5 3.4 fl El fl fl i

Knowledge of new and spent fuel movement procedures G2.1.5 Conduct of operations 2.9 3.9 Ability to locate and use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.

G2.2.15 EquipmentControl 3.9 4.3

[]

Abilitytodeterminetheexpectedplantconflguration using design and configuration control documentaion G2.222 Equipment Control 4.0 4.7 fl fl El, Knowledge of limiting conditions for operations and safety limits.

02.3.1 1 Radiation Control 3.8 4.3 E El El El El El El El El Ability to control radiation releases G2.4.17 Emergency Procedures/Plans 3.9 4.3

{]

Knowledge of EOP terms and definitions.

02.4.35 Emergency Procedures/Plans 3.8 4.0 El El El El El El El El El El Knowledge of local auxiliary operator tasks during emergency and the resultant operational effects Page 1 of 1 06/18/2009 8:52 AM ES-401. REV 9 KA NAME I SAFETY FUNCTION:

G2.1.42 Conduct of operations G2.1.5 Conduct of operations G2.2.15 Equipment Control G2.2.22 Equipment Control G2.3.11 Radiation Control G2.4.17 Emergency Procedures/Plans G2.4.35 Emergency Procedures/Plans SRO T3 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 2.5 3.4 0 0 0 0 0 0 0 0 0 0 ~

2.9 3.9 0 0 0 0 0 0 0 0 0 0 ~

3.9 4.3 DOD 0 0 0 0 0 0 0 ~

4.0 4.7 0 0 0 DOD 0 0 0 0 ~

3.8 4.3 0 0 0 0 0 0 0 0 0 0 ~

3.9 4.3 0 0 0 0 0 0 0 0 0 0 ~

3.8 4.0 0 0 0 0 0 0 0 0 0 0 ~

Page 1 of 1 FORM ES-401*1 TOPIC:

Knowledge of new and spent fuel movement procedures Ability to locate and use procedures related to shift staffing. such as minimum crew complement. overtime limitations. etc.

Ability to determine the expected plant configuration using design and configuration control documentaion Knowledge of limiting conditions for operations and safety limits.

Ability to control radiation releases Knowledge of EOP terms and definitions.

Knowledge of local auxiliary operator tasks during emergency and the resultant operational effects 06/18/2009 8:52 AM

DRAFT ES-301 Administrative Topics Outline Form ES-301-1 Facility:

Brunswick Date of Examination: April 2010 Examination Level:

RO SRO-i Operating Test Number:

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

Code*

R, M, D Core Performance Check

- APRM parameter check Conduct of Operations R, M, P Drywell Average Air Temperature Calculation Conduct of Operations R, P (SRO-l only) Refueling Technical Specifications R, D RCC Clearance Equipment Control R, M Calculation of Stay Times Radiation Control R, M (5R0-l only) Emergency Action Level Determinations Emergency Procedures/Plan NOTE:

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

  • Type Codes & Criteria:

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

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

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

\\k R FT ES-301 Administrative Topics Outline Form ES-301-1 Facility:

Brunswick Date of Examination: April 2010 Examination Level: RO

  • SRO-J
  • Operating Test Number: DRAFT Administrative Topic Type Describe activity to be performed (see Note)

Code*

R,M,D Core Performance Check - APRM parameter Conduct of Operations check R,M,P Drywell Average Air Temperature Calculation Conduct of Operations R,P (SRO-I only) Refueling Technical Specifications R,D RCC Clearance Equipment Control R,M Calculation of Stay Times Radiation Control R,M (SRO-I only) Emergency Action Level Emergency Procedures/Plan Determinations NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

  • Type Codes & Criteria:

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

(N)ew or (M)odified from bank (;:: 1)

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

Conduct of Operations Core Performance Check ROISROI R, M, D K/A 2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation This is a banked modified Administrative JPM that will require the examinee perform 1PT-O1.i1 recognizing APRM GAF adjustment required. Modified to allow performance in a classroom setting.

Conduct of Operations Drywell Average Air Temperature Calculation (RO Only)

R, M, P K/A 2.1.20 Ability to interpret and execute procedure steps This is a modified classroom Administrative JPM that will require the examinee perform OPT-i 6.2. Modified to allow performance in a classroom setting and values changed resulting in different answer. This JPM was used on one of the last two NRC exams (November 08) and was randomly selected for this exam.

Conduct of Operations Evaluate Refueling Technical Specifications (SRO-l Only)

R, P K/A 2.1.40 Knowledge of refueling administrative requirements This is a banked classroom Administrative JPM that requires the examinee to evaluate Technical Specifications to allow removal of Shutdown Cooling from operation during Refueling operations. This JPM was used on one of the last two NRC exams (April 08) and was randomly selected for this exam.

Equipment Control RCC Clearance R, D K/A 2.2.13 Knowledge of tagging and clearance procedures This is a banked classroom Administrative JPM that will require the examinee identify Clearance Boundaries for RBCCW Pump 2C by completing Attachment 4 of OPS-NGGC-i 301.

Radiation Control Calculation of Stay Times R, M K/A 2.3.7 Ability to comply with radiation work permit requirements during normal and abnormal conditions This is a modified banked classroom Administrative JPM that will require the examinee to determine the total dose accumulated for two workers and if any Brunswick administrative dose limitations will be exceeded. Modified the values and area resulting in a different answer.

Emergency ProcedureslPlan Emergency Action Level Determinations (SRO-l Only)

R, M K/A 2.4.29 Knowledge of the Emergency Plan This is a modified banked classroom Administrative JPM that will require the examinee to classify an emergency per PEP-02.1. Modified to incorporate NEI 99-0 1 EAL5.

Conduct of Operations Core Performance Check RO/SROI R, M, D KIA 2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation This is a banked modified Administrative JPM that will require the examinee perform 1 PT-01.11 recognizing APRM GAF adjustment required. Modified to allow performance in a classroom setting.

Conduct of Operations Drywell Average Air Temperature Calculation (RO Only)

R, M, P KIA 2.1.20 Ability to interpret and execute procedure steps This is a modified classroom Administrative JPM that will require the examinee perform OPT-16.2. Modified to allow performance in a classroom setting and values changed resulting in different answer. This JPM was used on one of the last two NRC exams (November 08) and was randomly selected for this exam.

Conduct of Operations Evaluate Refueling Technical Specifications (SRO-I Only) R, P KIA 2.1.40 Knowledge of refueling administrative requirements This is a banked classroom Administrative JPM that requires the examinee to evaluate Technical Specifications to allow removal of Shutdown Cooling from operation during Refueling operations. This JPM was used on one of the last two NRC exams (April 08) and was randomly selected for this exam.

Equipment Control RCC Clearance R, D KIA 2.2.13 Knowledge of tagging and clearance procedures This is a banked classroom Administrative JPM that will require the examinee identify Clearance Boundaries for RBCCW Pump 2C by completing Attachment 4 of OPS-NGGC-1301.

Radiation Control Calculation of Stay Times R, M KIA 2.3.7 Ability to comply with radiation work permit requirements during normal and abnormal conditions This is a modified banked classroom Administrative JPM that will require the examinee to determine the total dose accumulated for two workers and if any Brunswick administrative dose limitations will be exceeded. Modified the values and area resulting in a different answer.

Emergency Procedures/Plan Emergency Action Level Determinations (SRO-I Only)

R, M KIA 2.4.29 Knowledge of the Emergency Plan This is a modified banked classroom Administrative JPM that will require the examinee to classify an emergency per PEP-02.1. Modified to incorporate NEI 99-01 EALs.

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: Brunswick Date of Examination: April 2010 Exam Level: RO SRO-I Operating Test No.: DRAFT Control Room Systems@ (8 for RO); (7 for SRO-I)

System / JPM Title Type Code*

Safety Function

a. Bypass a LPRM 5, D 7
b. Restart RBHVAC with Failure to Isolate 5, A, D 9
c. Place B Loop RHR in SPC lAW hard card NSW header failure 5, A, P 5
d. Place HPCI in Pressure control 5, A, P 3
e. 230 kV Bus in Service 5, D 6
f. Secure Main Turbine with failure of PCB to open 5, A, N 4
g. SULCV in service after scram S, L, D 2
h. (RO only) Restart CRD S, D 1

In-Plant Systems@ (3 for RO/SRO-I)

i. LEP-Ol Alternate Coolant Injection, SLC w/ Fire Water R, M, E 2
j. Fire Pump power supply to alternate D

8 k.SAMADG R,P,M,E 6

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-l / SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank 9 I 8 I 4

(E)mergency or abnormal in-plant 1 I 1 I 1

(EN)gineered safety feature

- /

I 1 (control room system)

(L)ow-Power / Shutdown 1 /

1 I 1

(N)ew or (M)odified from bank including 1 (A) 2 /

2 I 1

(P)revious 2 exams 3 /

3 I 2 (randomly selected)

(R)CA (S)imulator ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Brunswick Date of Examination: April 2010 Exam Level: RO

  • SRO-I.

Operating Test No.: DRAFT Control Room Systems@ (8 for RO); (7 for SRO-I)

System I JPM Title Type Code*

Safety Function

a. Bypass a LPRM S, D 7
b. Restart RBHVAC with Failure to Isolate S,A, D 9
c. Place BLoop RHR in SPC lAW hard card - NSW header failure S,A, P 5
d. Place HPCI in Pressure control S,A, P 3
e. 230 kV Bus in Service S, D 6
f. Secure Main Turbine with failure of PCB to open S,A, N 4
g. SULCV in service after scram S, L, D 2
h. (RO only) Restart CRD S,D 1

In-Plant Systems@ (3 for RO/SRO-I)

i. LEP-01 Alternate Coolant Injection, SLC wI Fire Water R,M,E 2
j. Fire Pump power supply to alternate D

8

k. SAMA DG R,P,M, E 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 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank
59/:58/:54 (E)mergency or abnormal in-plant 2:1/2:1/2:1 (EN)gineered safety feature

- / - / 2:1 (control room system)

(L)ow-Power / Shutdown 2:1/2:1/2:1 (N)ew or (M)odified from bank including 1 (A) 2:2/2:2/2:1 (P)revious 2 exams

5 3 / :5 3 / :5 2 (randomly selected)

(R)CA 2:1/2:1/2:1 (S)imulator

a.

Bypass a LPRM 215005 A2.02 Ability to predict impacts on APRM and based on those predictions, use procedures to correct, control or mitigate consequences of those abnormal conditions.

This is a banked simulator JPM that will require the examinee to bypass an LPRM.

b.

Restart RBHVAC with Failure to Isolate 288000 A3.01 Ability to monitor Plant Ventilation System automatic isolation/initiation signals in the control room This is a modified banked simulator JPM that will require the exam inee to restart the RB Ventilation system. As an alternate path when the fans are started the high radiation condition alarm re-occur and the exam inee will have to isolate the system.

c.

Place B Loop RHR in SPC lAW hard card NSW header failure 219000 A4.12 Ability to manually operate and/or monitor in the control room:

suppression pool temperature.

This is a banked simulator JPM that will require the examinee to place the B loop of RHR into SPC. As an alternate path they will have to use the conventional service water header. This is an engineered safety feature JPM. This JPM was used on one of the last two NRC exams (Nov. 08) and was randomly selected for this exam.

d.

Place HPCI in Pressure Control 295025 EA1.04 Ability to operate and/or monitor the following as they apply to High Reactor Pressure: HPCI (plant specific)

This is a banked simulator JPM that will require the examinee to place HPCI into pressure control mode of operation. As an alternate path there is a exhaust diaphragm failure. This JPM was used on one of the last two NRC exams (Nov. 08) and was randomly selected for this exam.

e.

230 kV Bus in Service 262001 A4.01 Ability to manually operate and/or monitor in the control room: All breakers and disconnects (including available switchyard)

This is a banked simulator JPM that will require the examinee energize 230 kV Bus 2B.

a. Bypass a LPRM 215005 A2.02 Ability to predict impacts on APRM and based on those predictions, use procedures to correct, control or mitigate consequences of those abnormal conditions.

This is a banked simulator JPM that will require the examinee to bypass an LPRM.

b. Restart RBHVAC with Failure to Isolate 288000 A3.01 Ability to monitor Plant Ventilation System automatic isolation/initiation signals in the control room This is a modified banked simulator JPM that will require the examinee to restart the RB Ventilation system. As an alternate path when the fans are started the high radiation condition alarm re-occur and the examinee will have to isolate the system.
c. Place BLoop RHR in SPC lAW hard card - NSW header failure 219000 A4.12 Ability to manually operate and/or monitor in the control room:

suppression pool temperature.

This is a banked simulator JPM that will require the examinee to place the B loop of RHR into SPC. As an alternate path they will have to use the conventional service water header. This is an engineered safety feature JPM. This JPM was used on one of the last two NRC exams (Nov. 08) and was randomly selected for this exam.

d.

Place HPCI in Pressure Control 295025 EA 1.04 Ability to operate and/or monitor the following as they apply to High Reactor Pressure: HPCI (plant specific)

This is a banked simulator JPM that will require the examinee to place HPCI into pressure control mode of operation. As an alternate path there is a exhaust diaphragm failure. This JPM was used on one of the last two NRC exams (Nov. 08) and was randomly selected for this exam.

e. 230 kV Bus in Service 262001 A4.01 Ability to manually operate and/or monitor in the control room: All breakers and disconnects (including available switchyard)

This is a banked simulator JPM that will require the examinee energize 230 kV Bus 2B.

f.

Main Turbine Shutdown 245000 A2.01 Ability to predict impacts of a turbine trip on the Main Turbine Generator and Auxiliary Systems; and based on those predictions, use procedures to correct, control or mitigate consequences of those abnormal conditions.

This is a new simulator JPM that will require the examinee to shutdown the turbine. As an alternate path one of the PCBs will fail to auto open and the examinee will have to open the PCB manually.

g.

SULCV in service after scram 295001 A4.02 Ability to manually start/control a RFP in the control room.

This is a banked low power simulator JPM that will require the examinee to place the Startup Level Control Valve in service, restart a Reactor Feed Pump and restore RPV water level.

h.

(RO only) Restart CRD 201001 A2.01 Ability to predict the impact of a CRD pump trip on the CRD Hydraulic System and use procedures to correct, control or mitigate the consequences.

This is a banked simulator JPM that will require the examinee to restart the CRD system.

i.

LEP-Ol Alternate Coolant Injection, SLC wI Fire Water 295031 EA1.08 Ability To Operate/Monitor Alternate Coolant Injection Systems.

This is an in-plant JPM that will require the examinee to simulate aligning Fire Water to the SLC pumps for alternate coolant injection per LEP-Ol. This JPM is performed in the RCA. This JPM was modified due to a plant modification incorporating a new connector to the fire water hose.

j.

Fire Pump power supply to alternate 286000 Al.05 Ability to predict and/or monitor changes in parameters associated with operating the Fire Protection System controls including: System lineups.

This is a banked in-plant JPM that will require the examinee to simulate the transfer of the Electric Fire Pump to its alternate power supply and start the Electric Fire Pump locally.

k.

SAMA DG 295003 AAI.02 Ability to Operate and/or Monitor Emergency Generators as it applies to a Station Blackout This is a banked in-plant JPM that will require the examinee to simulate aligning the SAMA Diesel to a battery charger. This JPM is performed in the RCA. This JPM was modified due to a plant modification to the equipment. This JPM contains actions for a Station Blackout.

f.

Main Turbine Shutdown 245000 A2.01 Ability to predict impacts of a turbine trip on the Main Turbine Generator and Auxiliary Systems; and based on those predictions, use procedures to correct, control or mitigate consequences of those abnormal conditions.

This is a new simulator JPM that will require the examinee to shutdown the turbine. As an alternate path one of the PCBs will fail to auto open and the examinee will have to open the PCB manually.

g. SULCV in service after scram 295001 A4.02 Ability to manually start/control a RFP in the control room.

This is a banked low power simulator JPM that will require the examinee to place the Startup Level Control Valve in service, restart a Reactor Feed Pump and restore RPV water level.

h. (RO only) Restart CRD 201001 A2.01 Ability to predict the impact of a CRD pump trip on the CRD Hydraulic System and use procedures to correct, control or mitigate the consequences.

This is a banked simulator JPM that will require the examinee to restart the CRD system.

i.

LEP-01 Alternate Coolant Injection, SLC wI Fire Water 295031 EA 1.08 Ability To Operate/Monitor Alternate Coolant I njection Systems.

This is an in-plant JPM that will require the examinee to simulate aligning Fire Water to the SLC pumps for alternate coolant injection per LEP-01. This JPM is performed in the RCA. This JPM was modified due to a plant modification incorporating a new connector to the fire water hose.

j.

Fire Pump power supply to alternate 286000 A 1.05 Ability to predict and/or monitor changes in parameters associated with operating the Fire Protection System controls including: System lineups.

k. SAMA DG 295003 AA 1.02 This is a banked in-plant JPM that will require the examinee to simulate the transfer of the Electric Fire Pump to its alternate power supply and start the Electric Fire Pump locally.

Ability to Operate and/or Monitor Emergency Generators as it applies to a Station Blackout This is a banked in-plant JPM that will require the examinee to simulate aligning the SAMA Diesel to a battery charger. This JPM is performed in the RCA. This JPM was modified due to a plant modification to the equipment. This JPM contains actions for a Station Blackout.

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