ML101590071

From kanterella
Jump to navigation Jump to search
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.

E8-401 Rev. 99 BWR examination BWR Examination Outline Outline Form Form ES-401-1 ES-401-1 1

Facility:

Facility: BRUNSWICK BRUNSWICK Date of Date of Exam:

Exam: APRIL APRIL 20102010 RO KIA RO K/A Category Category Points Points SRO-Only SROOnIy Points Points Tier Tier Group Group KKKKKKKAK K K K K A AAAG A A A G A2 A2 G*

G* Total Total 11 22 33 44 55 66 11 22 33 44 ** Total Total

= =

1.1. 11 4 3 3 44 33 3 20 20 33 44 77 Emergency &&

Emergency Abnormal 22 1 1 T 1 22 11 1 77 11 22 33 Abnormal Plant Plant N/A NIA N/A NIA Evolutions Evolutions TierTotals Tier Totals 5 4 4 66 4 4 27 27 4 66 10 10

, = = = = - = =- = -= = =

11 3323 2 3 222333 2 3 3 3 212 2 1 2 26 26 22 33 55 2.

2.

22 11 11 11 1111 11 2211 11 11 11 12 12 00 11 22 33 Plant Plant Systems Systems Tier Totals 4 3 4 3 3 4 55 4 3 22 3 38 3 5 8 Tier

= = = = =

Generic Knowledge and Abilities

3. Generic 11 22 3 4 10 10 11 22 3 4 7 Categories Categories 3 3 2 2 2 2 11 2 1
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 of the SRO-only outline, the "Tier Tier Totals" Totals in each KIA 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 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/evo Systemslevolutions lutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; 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 elimination of inappropriate K/A KIA statements.

statements.

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

5.

5. Absent aa plant-specific Absent plant-specific priority, priority, only those K/As only those KIAs having having an an importance importance rating (IR) (IR) of of 2.5 2.5 or or higher higher shall shall be be selected. Use Use the RO and and SRO SRO ratings for the RO and and SRO-only portions, respectively. respectively.

6.

6. Select Select SROSRO topics topiCS forfor Tiers Tiers I1 and and 22 from the shaded shaded systems systems and and K/AKIA categories.

7,

7. *The generic The generic (G) (G) K/As KIAs in in Tiers Tiers I1 andand 22 shall shall be be selected selected from SectionSection 22 of of the the K/A KIA Catalog, Catalog, but but thethe topics must must be be relevant relevant to to the the applicable applicable evolution evolution or or system.

system.

8.

8. On the following On the following pages, pages, enter enter thethe K/A KIA numbers, numbers, aa brief brief description description of of each each topic, topic, the the topics topics' importance importance ratings (IRs) for ratings (IRS) the applicable for the applicable license license level,level, and the point and the totals (#)

point totals for each

(#) for each system system and and category.

category. EnterEnter the group the group and tier totals and tier totals forfor each each category category in in the table above; the table abovej ifif fuel fuel handling handling equipment equipment is is sampled sampled in in other other than Category than Category A2 A2 oror G*

G* on the SRO-only on the SRO-only exam, exam, enter enter itit on on the the left left side side of of Column Column A2 A2 for for Tier Tier 2,2, Group Group 22 (Note (Note

    1. I1 does does not not apply).

apply). Use Use duplicate duplicate pages pages for for RORO and and SRO-only SRO-only exams. exams.

9.

9. For For TierS, Tier 3, select topics from select topics from Section Section 22 of the KIA of the KIA catalog, catalog, andand enter enter the the K1A KIA numbers, numbers, descriptions, descriptions, IRs, IRs, and point totals and point totals (U) on Form

(#) on Form ES-401-3.

ES-401-3. Limit limit SROSRO selections selections to to K/As KIAs thatthat are are linked linked to to 1010 CFR CFR 55.43.

55.43 .

,.. _0._.. .. -----------.. _. -

ES-401, REV ES-401, REV 99 TIG1 BWR T1G1 BWR EXAMINATION EXAMINATION OUTLINE OUTLINE FORM FORM ES-401-1 ES-401-1 KA KA NAME IISAFETY NAME FUNCTION:

SAFETY FUNCTION: IR IR 1(1 K2 K1 K2 K3 K4 K5 K3 K4 K5 K6K6 A1Al A2 A2 A3 A3 A4 A4 G G TOPIC:

TOPIC:

RO RO SRO SRO 295001AK1. 03 Partial or or Complete Complete Loss Loss of of Forced Forced 295001AK1.03 Partial Flow Circulation Core Flow Circulation I/ 11 &

3.6 3.6 4.1 4.1 ~ 0fl 0E 0E 0fl 0 0000 Thermal Thermal limits limits....................................... .

Core & 44 295003AA2. 05 Partial or or Complete Complete Loss Loss of AC AC 16

/6 3.9 295003AA2.05 Partial 3.9 4.2 4.2 0 0 0 0 [] 0 0 0 ~ 0 0 0 Whether aa partial partial oror complete complete loss loss ofof AC.

AC. power power has has occurred ............................................. .

295004AA10 2 Partial or Total Loss of DC Pwr 16 or Total /6 3.8 4.1 295004AA1.02 Partial 3.8 4.1 0 DOC [] 0 0 ~ 0 0 0 0 fl Systems necessary necessary to to assure assure safesafe plant plant shutdown shutdown .......

295005AA1.07 Main 295005AA1.07 Main Turbine Turbine Generator Generator Trip 13 3.3 3.3 3.3 3.3 0 D 0 0 0 H fl H 0 H 0 ~ 0 0 0 0 Li AC. electrical A.C. electrical distribution distribution ......................... .

295006AK1. 02 SCRAM /111 SCRAM 3.4 3.7 295006AK1.02 3.4 3.7 ~ 0 U LiDOCLI H LI COO Li H LI0 H 0 fl 0 Shutdown margin ...................................... .

Shutdown 295016G2.4. 1 Control Control Room Abandonmentt 17 Room Abandonmen 295016G2.4.1 17 46 4.6 4.8 4.8 0 0 H 0 0 [] 0 r COO 0 ~ Knowledge of Kno1edge of EOP EOP entryentry conditions conditions and and immediate immediate action steps.

action steps.

295018AA1.02 Partial 295018AA1.02 Partial or or Total Total Loss Loss of CCW /8 of CCW 18 3.3 3.3 3.4 3.4 0 0 0 0 0 fl [] ~ 0 0 0 0 System loads System loads ......................................... .

295019G2.2. 37 PartialorTota Partial or TotallLossoflnst.A irI8 295019G2.2.37 Loss of Inst. Air I8 3.6 3.6 4.6 4.6 0 H 0 H 0 H0 H0 0 0 0 0 0 ~ Ability to Ability to determine determine operability operability and/or andlor availability of safety availability of safety related equipment related equipment 295021AA2. 02 LossofShutd ownCooling/

Loss of Shutdown Cooling I44 3.4 295021AA2.02 3.4 3.4 H0 H 0 H 0 H0 H0 H 0 H [] ~ 0 LI fl 0 H0 RHRlshutdown RHRlshutdo cooling system wn cooling system flow flow 295023AK3. 03 Refueling RefuelingAccAceCooling Mode/I 88 Cooling Mode 3.3 295023AK3.03 3.3 3.63.6 H0 H 0 1 ~ H0 H0 H 0 fl 0 fl[] H

[] H0 LI 0 Ventilation isolation Ventilation isolation ................................ .

295024G2.2. 37 High HighOrywell OrywellPressure Pressure/ I55 3.6 295024G2.2.37 3.6 4.64.6 H0 H0 H 0 H0 H0 H 0 H0 H ODDH H ~ Abilitytotodetermine Ability determineoperability operabilityand/orandloravailability availabilityofofsafety safety relatedequipment related equipment Page Page1 1ofof2 2 0611812009 8:52 06/18/2009 8:52AMAM

ES-401, REV ES-401, REV 99 TIGI BWR T1G1 BWR EXAMINATION EXAMINATION OUTLINEOUTLINE FORM FORM ES-401-1 ES-401-1 KA KA NAME II SAFETY NAME SAFETY FUNCTION:FUNCTION: IR IR Ki K2 K1 K3 K4 K2 K3 K4 KS K5 K6 K6 A1 Al A2 A2 A3 A3 A4 A4 G G TOPIC:

TOPIC:

RO RO SRO 295025EA2.05 295025EA2.05 High Reactor High Reactor Pressure Pressure 13 I 3 3.4 3.4 3.6 3.6 0 0 [] 0 0 0 0 ~ 0[] 0fl 0 Decay Decay heat heat generation generation ................................ .

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

295026EA1.

295026EA1.0101 Suppression Pool Suppression High Water Pool High Water Temp. I/ 4.1 4.1 0 0 0 0 0 0 ~ 0 [] 0 n

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

fl Suppression Suppression pool cooling ............................. .

55 295028EK3.05 295028EK3.05 High Drywell Temperature High Drywell Temperature 15 /5 3.6 3.7 0 0 ~ 0 0 0 0 0 [] 0 [] Reactor SCRAM ........................................ .

295030EK2.09 295030EK2.09 Low Suppression Low Suppression Pool Pool WtrWtr Lvl /5 Lvl/S 2.5 2.S 2.8 0 ~ 0 0 0 [] 0 0 0 [] 0 SPDS/ERIS/CRIDS/GDS:

SPDSIERISICRIDS/GDS: Plant-SpecifiPlant-Specific c ................. .

295031 EK3.03 Reactor Reactor Low Low Water Water Level 295031EK3.03 Level/2I2 4.14.4 4.1 4.4 0 []

0 ~ 0 0 D [] E 0 0 fl [] El 0 fl

[] Spray cooling ........................................ .

Spray 295037EK1 .03 SCRAM SCRAM Condition Condition Present Present andand Power 4.2 4.4 295037EK1.03 Above Power 4.2 4.4 ~O[]OD[]OOOOO Boron effects Boron effects onon reactor reactor power power (SBLC)(SBLC).................

Above APRM APRM Downscale Downscale or or Unknown Unknown

/1 11 295038EK2. 12 High High Off-site Off-site Release Release RateRate /199 3.5 3.8 295038EK2.12 3.5 3.8 []~OOOOOO[][]O E fl flfl Feedwater leakage Feedwater leakage control:

control: BWR-6 BWR-6 .....................

600000AK2. 01 Plant 600000AK2.01 Plant Fire Fire On Site II 88 On Site 2.6 2.6 2.7 2.7 O~[]DODDO[]DO Sensors /I detectors Sensors detectors andand valves valves 700000AK1 .02 Generator 700000AK 1.02 Generator Voltage Voltage andand Electiic Electric Grid Grid 3.3 3.3 3.4 3.4 ~OOOOOOOOOO Over-excitation Over-excitati on Distrurbance Distrurbancecscs Page Page22ofof2 2 06/18/2009 8:52 06/18/2009 8:52AM AM

ES-401 ES-401, ,REVREV9 T1G2BWR BWREXAMINATION EXAMINATIONOUTLINE FORM 9 T1G2 OUTLINE FORMES-401-1ES-401 -1 KA NAMEI /SAFETY SAFETYFUNCTION:

FUNCTION: IR IR Ki K2 K1 k2 K3 K3 K4 K4 K5 K5 K6K6 A1 Al A2 A2 A3 A3 A4 A4 GG TOPIC:

KA NAME TOPIC:

RO RO SRO SRO 295008AK1 .01 HighReactor ReactorWater WaterLevell Level 12 295008AK1.01 High 2 3.0 3.2 3.0 3.2 ~ 0 0 0 0 0 0 0 0 0 0 Moisture Moisturecarryover.

carryover.................................. .

295014AA203 InadvertentReactivity ReactivityAddition Addition /1 Inadvertent II 4.0 4.34.3 0 COD 0 0 0 ~ 0 0 0 Cause Causeofofreactivity reactivityaddition 295014AA2.03 4.0 addition......................... .

295015AK3.01 Incomplete SCRAM SCRAM11 / I 295015AK3.01 Incomplete 3.4 3.7 0 0 ~ 0 0 0 0 0 0 0 0 Bypassing Bypassing rod rod insertion insertion blocks blocks....................... .

295020G24.1 Inadvertent Cont. Isolation 15 & 7 Inadvertent Cont. Isolation /5 & 7 4.6 4.8 0 [] 0 0 0 0 0 0 0 0 ~ Knowledge of of EOP 295020G2.4.1 4.6 4.8 Knowledge EOP entry entry conditions conditions and and immediate immediate action action steps.

steps.

295032EK2.02 High Secondary Containment Area 3.6 3.7 0 0 0 0 0 0 0 0 0 0 Secondary Secondary containment 295032EK2.02 High Secondary Temperature! 5 Containment Area 3.6 3.7 ~ containment ventilation ventilation.................... .

Temperature 15 295033EA1 .05 High Secondary Containment Area High Secondary Containment Area 3.9 4.0 0 0 0 0 0 0 ~ 0 0 0 0 Affected Affected systems systems so 295033EA1.05 Radiation Levels I 9 3.9 4.0 so as as to to isolate isolate damaged damaged portions ....

portions....

Radiation Levels I9 295035EA1 .01 Secondary 295035EA1.01 Secondary Containment Containment High High 3.6 3.6 3.6 3.6 0 0 0 0 0 0 ~ 0 0 0 0 Secondary containment Secondary containment ventilation ventilation system system ............. .

Differential Pressure / 5 Differential Pressure I 5 Page1 1ofof1 1 Page 06/18/2009 8:52 AM 06/18/2009 8:52 AM

ES-401, REV ES-401, REV 99 T2GI BWR T2G1 BWR EXAMINATION EXAMINATION OUTLINE FORM OUTLINE FORM ES-401-1 ES-401-1 KA KA NAME II SAFETY NAME SAFETY FUNCTION:

FUNCTION: IR IR Ki K2 K1 K2 K3 K3 K4 K4 K5 K5 K61(6 A1Al A2 A2 A3 A3 A4 A4 G G TOPIC:

TOPIC:

RO RO SRO SRO 203000K1.01 RHRJLPCI: Injection Injection Mode Mode 203000K1.01 RHRlLPCI: 2.8 2.8 2.8 2.8 ~ 0 0El 0 0fl 0fl 0 0 0[] 0 0 Cendensate Condensate storage storage and and transfer transfer system:

system: Plant-Specific Plant-Specific 205000G2.4. 21 Shutdown Cooling Cooling 205000G2.4.21 Shutdown 4.0 4.0 4.6 4.6 0 0 0 0 0 0 0 0 0 0 ~ Knowledge of Knowledge of the the parameters parameters andond logic logic used used to to assess assess the status of the status of safety safety functions functions 206000K4.02 HPCI 206000K4.02 HPCI 3.9 3.9 44 DDD~ODDDDDD fl System System isolation:

isolation: BWR-2.3,4 BWR-2,3,4 209001K3.O 1 LPCS LPCS 3.8 3.9 209001K3.01 H H DD~DD[JDDDDDH H El H H H H H Reactor water levellevel 209001K3.03 LPCS LPCS 209001K3.03 2.9 3.0 H H DD~DDODDDDD H H H H H H H H Emergency generators generators 211000K101 SLC SLC 3.0 3.3 211000K1.01 3.0 3.3 ~DDDDDDDDDD H H H H H El H H H H Cere spray line Corespraylin break detection:

ebreakdetect Plant-Specific ion: Plant-Specift 211000K1.09 SLC SLC 3.2 3.4l 211000K1.09 3.2 3.4 ~DDDDDDDDDD H H H H H H H H El H Core spray Core spray system:

system: Plant-Specifi Plant-Specificc 212000K2.O 1 RPS RPS 3.2 3.3 212000K2.01 3.2 3.3 D~DDDDDDDDD El H H H H H H E H H RPS motor-genera RPS motor-generator sets tor sets 215003A2.02 IRM IRM 35 3.7 215003A2.02 3.5 3.7 H DDDDDDD~DDD H H fl H H H H H IRM mop IRM inop condition condition 2150041<5.0 3 Source 215004K5.03 Source Range Range Monitor Monitor 2.8 2.8 2.8 2.8 n El El [J 0 H El 0 ~ 0 H H 0 H 0 H0 H0 H0 Changing detector Changing detector position position 215005A2.05 APRM 215005A2.05 APRM /I LPRM LPRM 3.5 3.5 3.6 3.6 0 El H 0 El0 H 0 H0 H 0 H 0 ~ 0 0 ofrecirculation Loss of Loss recirculation flow flowsignal signal Page1 1ofof33 Page 8:52AM 06/18/2009 8:52 06/18/2009 AM

ES-401, REV ES-401, REV 99 T2GI BWR T2G1 BWR EXAMINATION EXAMINATION OUTLINE OUTLINE FORM FORM ES-401*1 ES-401-1 KA KA NAME II SAFETY NAME SAFETY FUNCTION:

FUNCTION: IR IR Ki K2 K1 K2 K3 K3 K4 K5 K6 K4 K5 K6 A1Al A2A2 A3 A3 A4 A4 G G TOPIC:

TOPIC:

RO RO SRO SRO 215005A2.07 APRM /I LPRM LPRM 215005A2.07 APRM 3.2 3.2 3.4 3.4 El DOC 0 0 0fl 0[] 21 0fl 0 0 Recirculation Recirculation flowflow channels channels flow flow mismatch mismatch 217000A1,01 RCIC 3.7 217000A1.01 RCIC 3.7 f 000000210000 J LI LI LI [ RCICflow RClCflow 217000A1 .04 RCIC 217000A 1.04 RCIC 3.6 3.6 000000210000 LI Reactor pressure LI pressure 218000K3,01 218000K3.01 ADS ADS 4.4 4.4 002100000000 Restoration of of reactor reactor water water level level after after aa break break that that does does not depressurize depressunze the the reactor when required reactor when required 223002A3.03 -

PCIS/Nuclea PCIS/Nuclearr Steam Steam Supply Supply Shutoff 2.5 2.8 223002A3.03 LI LI LI LI LI 000000002100 LI LI i LI LI SPDS/ERIS/CRIDS/GDS:

SPDS/ERIS/ Plant-Specific CRIDS/GDS: Plant-Specifi c 239002A404 SRVs 4.3 239002A4.04 SRVs 4.3 4.3 4.3 0 LI LI 0 LI0 LI 0 LI0 LI0 LI [] LI0 LI0 21 LI0 Suppression pool Suppression pool temperature temperature 2590021(6.0 4 Reactor Reactor Water Water Level Level Control 3.1 259002K6.04 Control 3.1 3.1 3.1 0 LI LI 0 LI0 LI 0 LI0 21 LI 0 LI 0 LI0 LI 0 LI0 Reactor feedwater Reactor feedwater flow flow input input 261000A3.01 SGTS SGTS 3.2 261000A3.o1 3.2 3.3 3.3 0 LI LI 0 LI0 LI 0 LI0 LI0 LI 0 LI 0 21 LI0 LI0 System flow System flow 262001K6.01 AC 262001K6.01 AC Electrical Electrical Distribution Distribution 3.1 3.1 3.4 3.4 0 LI LI 0 LI0 LI 0 LI0 21 LI 0 LI 0 LI 0 fl 0 LI0 D.C. power D.C. power 2620011(6.0 2 AC AC Electrical Electrical Distribution 262001K6.02 Distribution 3.6 3.6 3.93.9 COD fl fl LI 0 LI0 21 LI LI 0 LI 0 LI DOCLI LI Off-sitepower Off-site power 262002G2.4. 3 UPS UPS(AC/DC) 3.7 262002G2.4.3 (AC/DC) 3.7 39 3.9 0 LI LI 0 LI0 LI0 LI 0 LI0 LI0 LI ODDLI LI 21 Abilitytotoidentify Ability identifypost-acciden post-accident instrumentation.

t instrumentat ion.

Page22ofof3 Page 3 06/18/2009 8:52 06/18/2009 8:52AMAM

ES-401, REV ES-401, REV99 T2G1 BWR T2G1 BWR EXAMINATION EXAMINATION OUTLINE FORM OUTLINE FORM ES-401-1 ES-401-1 KA KA NAME IISAFETY NAME SAFETY FUNCTION:

FUNCTION: IR IR Ki K2 K1 K3 K4 K2 K3 K4 K5 K5 K6 K6 A1Al A2 A2 A3 A3 A4 A4 GG TOPIC:

TOPIC:

RO RO SRO SRO 263000K2.01 DC Electrical Electrical Distribution Distribution 3.1 3.4 263000K2.01 DC 3.1 3.4 0 ~ 0 0 0 0 0 0 0 0 0[] Major MajorD.C.

D.C. loads loads 264000A1 .01 EDGs 3.0 3.0 264000A1.01 EDGs 3.0 3.0 0 0 0 0 0 0 ~ 0 0 0 0 Lube Lube oiloil temperature temperature 300000K5.13 Instrument Air Air 2.9 2.9 3OOO00K5.13 Instrument 2.9 2.9 0 U 0 0 ~ 0D 0 0 0 0 0 Filters Filters 400000K4.01 Component Coolin9 Cooling Water Water 3.4 3.9 400000K4.01 Component 3.4 3.9 0 0 0 ~ 0E 0 0 0 0 0 0 Automatic Automatic startstart of of standby standby pump pump Page Page33ofof33 06/18/2009 8:52 06/18/2009 8:52AM AM

ES-401 ES*401, ,REV REV99 T2G2BWR BWREXAMINATION EXAMINATIONOUTLINE FORM T2G2 OUTLINE FORMES-401*1 ES-401-1 KA NAMEf ISAFETY NAME SAFETYFUNCTION:

FUNCTtON: IR IR Kl K2 K1 K3 K4 K2 K3 K4 K5 KS K6K6 A1Al A2 A2 A3 A3 A4 A4 GG TOPIC:

KA TOPIC:

RO RO SRO SRO 201001A1.03 CRD Hydraulic 2.9 2.82.8 201001A1.03 CRD Hydraulic 2.9 DODDOO~OOOD CRD CR0system systemflow flow 201002K6.O1 RMCS 2.5 2.6 201002K6.01 RMCS 2.5 2.6 OODOO~DDDOO Select Selectmatrix matrixpower power 201006K5.01 RWM 3.3 3.7 Minimize Minimize clad clad damage 201006K5.01 RWM 3.3 3.7 OOOO~OODODD fl fl damage ififaa control control rod rod drop drop accident accident (CRDA)

(CRDA) occurs:

occurs: P-Spec(Not-BWR6)

P-Spec(Not-BWR6) 214000A3.04 RPIS 3.5 3.8 j D J 214000A3.04 RPIS 3.5 3.8 DOOODDDD~OD RCIS:

RCIS: Plant-Specific Plant-Specific 216000K2.O1 Nuclear Boiler Inst. 2.8 2.8 Analog Analog triptrip system:

system: Plant-Specific 216000K2.01 Nuclear Boiler Inst. 2.8 2.8 O~DOOOOODDO El Plant-Specific 230000A1.06 RHRJLPCI: TonislPool Spray Mode 3.3 3.3 230000A 1.06 RHRlLPCI: ToruslPool Spray Mode 3.3 3.3 OOOOOO~DODD Suppression Suppression pool pool level level 234000A4.02 Fuel Handling Equipment 14 3.7 234000A4.02 Fuel Handling Equipment 3.4 3.7 OODODDOOO~O E Control rod Control rod drive drive system system 259001A2.06 259001A2.06 Reactor Feedwater Reactor Feedwater 3.2 3.2 3.2 3.2 o []0 E0 [30 [30 [30 [30 j~ fln [30 D Ef~ Loss of Loss of AC.

AC. electrical electrical power power 272000K305 Radiation Monitoring 3.5 3.7 272000K3.05 Radiation Monitoring 3.5 3.7 [3 [3 DC~DOOOODDD[3 [] [3 [3 [3 [3 [3 [3 Offgas system Offgas system _______________

2880001(1.04 Plant Ventilation 2.62.6 288000K1.04 Plant Ventilation 2.6 2.6 [3 [3 [3 [3 [3 [3 [3 [3 [3 [3

~OOCODOODOO Applicable component Applicable component cooling cooling water watersystem:

system: Plant-Plant-Specific Specific 290002G2.4.46 Reactor Vessel Internals 4.2 290002G2.4.46 Reactor Vessellntemals 4.2 4.24.2 ODOOOOOOOO~ Abilitytotoverify Ability verifythat thatthe thealarms alarmsare areconsistent consistent with the with the plantconditions.

plant conditions.

Page Page1 1ofof22 06/18/2009 8:52 AM 06/18/2009 8:52 AM

ES-401, ES-401,REV REV99 T2G2 T2G2BWR BWREXAMINATION EXAMINATIONOUTLINE OUTLINE FORMES-401-1 ES-401-1 FORM KA KA NAME NAMEI ISAFETY SAFETYFUNCTION:

FUNCTION: JRIR K1K1 K2 K2 K3 K3 K4 K4 K5 K5 K6K6AlA1 A2 A2 A3 A3 A4 A4 GG TOPIC:

TOPIC:

RO RO SRO SRO 290003K401 Control 290003K4.01 ControlRoom RoomHVAC HVAC 3.13.1 3.23.2 0 0 LI0 ~ LI0 LI0 LI0 LI0 LI0 LI0 LI0 Systeminitiations/reconfiguration:

System initiations/reconfiguration:Plant-Specific Plant-Specific Page 2 of22of 2 Page 8:528:52 06/18/2009 06/18/2009 AMAM

ES-401, REV ES-401, REV99 T3 BWR T3 BWR EXAMINATION EXAMINATION OUTLINE FORM OUTLINE FORM ES-401-1 ES-401-1 KA KA NAME II SAFETY NAME SAFETY FUNCTION:

FUNCTION: IR JR Ki K2 K1 K3 K4 K2 K3 K4 K5 K5 K6 K6 A1 Al A2 A2 A3 A3 A4 A4 GG TOPIC:

TOPJC:

RO RO SRO SRO G2.1 .27 Conduct ofof operations operations 3.9 44 G2.1.27 Conduct 3.9 D D D D D DOD D D ~ Knowledge Knowledge of of system system purpose purpose and and ororfunction.

function.

G2.1 31 Conduct ofof operations operations 4.6 G2.1.31 Conduct 4.6 4.3 4.3 D D D DOD ,

fl 0 D D D ~ Ability Ability to to locate locate control control room room switches, switches, controls controls and and indications indications andand toto determine determine that that they they are are correctly correctly reflecting the desired plant reflecting the desired plant lineup.lineup.

G2.1 .39 Conduct of of operations operations G2.1.39 Conduct 3.6 3.6 4.3 4.3 D DOD DOD [] 0 0 [] ~ Knowledge of Knowledge of conservative conservative decision decision making making practices practices G2.2.1 5 Equipment Control Control G2.2.15 Equipment 3.9 3.9 4.3 0E 0fl 0 0 ODD D [] 0 D 0 ~ Ability Ability to to determine determine the the expected expected plantplant configuration configuration using using design design andand configuration configuration control control documentaion documentaion G2.2.25 Equipment Control Control G2.2.25 Equipment 3.2 3.2 4.2 4.2 DOD 0 D [] D DOD [] [ D ~ Knowledge of of the the bases bases in in Technical Technical Specifications Specifications forfor limiting limiting conditions conditions for for operations operations and and safety safety limits.

limits.

G2.2.39 Equipment Control Control G2.2.39 Equipment 3.9 3.9 4.5 4.5 0 0 ODD D 0 0 0 0 0 ~ Knowledge Knowledgeo of flessthanoneh less than one hour technical peciflcation ourtechnicals specification action statements for for systems.

systems.

G2.3.14 Radiation Control G2.3.14 Radiation Control 3.4 3.4 3.8 3.8 0 0 0 0 0 El 0 [] D 0 ~ Knowledge of of radiation radiation or contamination or contaminatio hazards that n hazards that may arise arise during during normal, abnormal, or normal, abnormal, emergency or emergency conditions or activities or activities G2.3.6 Radiation G2.3.6 Radiation Control Control 2.0 3.8 ODD

[] [] 0 D [] [] [] ODD ~ to aprove aprove release release permits permits 2.0 3.8 [] [ Ability to G2.4.1 Emergency G2.4.1 -

Emergency Procedures/P lans Procedures/Plans 4.6 4.6 4.8 4.8 0 0 0 0 0 0 [1 [] El 0 El[] 0 ~ Knowledge of Knowledge of EOP EOP entry entry conditions conditions and and immediate immediate action steps.

action steps.

02.4.9 Emergency G2.4.9 Emergency Procedures/P lans Procedures/Plans 3.8 3.8 4.2 4.2 0 El El 0 El0 ElODD El El El D El u LI

[] El 0 I ~ Knowledge of Knowledge of low low power power I/ shutdown shutdown implications implications inin accident (e.g.

accident (e.g. LOCA LOCA or or loss loss ofof RHR)

RHR) mitigation mitigation strategies.

strategies.

Page 11of Page of 11 06/1812009 8:52 06/1812009 8:52AM AM

ES-401, REV ES-401, REV99 SRO T1G1 SRO TIGI BWR BWR EXAMINATION EXAMINATION OUTLINE OUTLINE FORM FORM ES-401*1 ES-401-1 KA KA NAME /I SAFETY NAME SAFETY FUNCTION:

FUNCTION: IR IR Ki K2 K1 K2 K3 K3 K4 K4 K5 K5 K6 K6 A1 Al A2 A2 A3 A3 A4 A4 GG TOPIC:

TOPIC:

RO RO SRO SRO 295006G2.2.22 SCRAM/i 4.0 4.7 295006G2.2.22 SCRAM 11 4.0 4.7 0EED 0 0 0DDD 0 0 0 E1D 0 0 0 E ~ Knowledge Knowledge of oflimiting limiting conditions conditions forforoperations operations andand safety safety limits.

limits.

295021AA2.03 Loss of of Shutdown Shutdown Cooling Cooling /4

/4 3.5 295021AA2.03 Loss 3.5 3.5 3.5 0 0 0 0 0 0 0 ~ [] 0 0 Reactor Reactor water water level level 295023G2.4.46 Refueling Acc Cooling Mode Acc Cooling Mode 1/ 88 4.2 295023G2.4.46 Refueling 4.2 4.2 4.2 0 0 0 0 0 0 0 0 0 0 ~ Ability Ability to to verify verify that that the the alarms alarms areare consistent consistent with with the the plant plant conditions.

conditions.

295026EA2.03 Suppression Pool 295026EA2.03 Suppression Pool High High Water Water Temp.

Temp. 1/ 3.9 3.9 4.0 4.0 0 0 0 [J 0 0 0 21 0 0 0 Reactor Reactor pressure pressure..................................... .

55 295028EA2.05 High Orywell Drywell Temperature 295028EA2.05 High Temperature /5 /5 3.6 3.6 3.8 0 0 [] 0 0 0 0 21 0 0 0 Torus/suppression Torus/suppression chamber chamber pressure:

pressure: Plant-Specific ...

Plant-Specific...

295038G2.2.42 High Off-site Off-site Release Release Rate Rate!1 9 3.9 295038G2.2.42 High 3.9 4.6 4.6 0 0 0 [] [] 0 0 0 0 0 ~ Ability to recognize recognize system system parameters parameters that that are are entry-entry-level conditions conditions for for Technical Technical Specifications Specifications 6OtJ000G2.2.37 Plant Fire 600000G2.2.37 Plant Fire On On Site / 88 Site 1 3.6 3.6 4.6 4.6 0 0 0 0 0 0 0 0 0 0 ~ to determine Ability to determine operability operability and/or and/or availability of safety availability of safety related equipment equipment Page Pagei 1ofof1 1 06/1812009 8:52 06/i8!2009 8:52AM AM

ES-401, REV ES-401, REVS9 SRO T1G2 SRO TIG2 BWR BWR EXAMINATION EXAMINATION OUTLINE OUTLINE FORM FORM ES-401-1 ES-401-1 KA KA NAME!I SAFETY NAME SAFETY FUNCTION:

FUNCTION: IR IR Ki K2 K1 K2 K3 k3 K4 k4 KS K5 K6K6 A1Al A2 A2 A3 A3 A4 A4 G G TOPIC:

TOPIC:

RO RO SRO SRO 295008AA2.05 High Reactor Reactor Water Water Levell Level 1 22 2.9 295008AA2.05 High 2.9 3.1 3.1 0 0 0 0 0 0 0 ~ [] 0 0 Swell..

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

295014G2.1.19 Inadvertent Reactivity Reactivity Addition Addition/i 3.9 295014G2.1.19 Inadvertent 11 3.9 3.8 3.8 0 0 0 0 0 0 0 CJ 0 [] ~ Ability Ability to to use use plant plant computer computer to to evaluate system or evaluate system or component component status.

status.

295029G2.1 .7 High Suppression Suppression Pool Pool Wtr Wtr LvllS Lvi / 5 4.4 4.7 295029G2.1.7 High 4.4 4.7 0 0 0 0 0 0 0 0 0 0 ~ Ability Ability to to evaluate evaluate plant plant performance performance and and make make operational judgments judgments based based on on operating operating characteristics, characteristics, reactor reactor behavior behavior and and instrument instwment interpretation.

interpretation.

Page Page1 1ofof 1 06118/2009 8:52 06/18/2009 8:52AMAM

ES.401, REV ES-401, REV 99 SRO T2G1 SRO T2G1 BWR BWR EXAMINATION EXAMINATION OUTLINE OUTLINE FORM FORM ES-401-1 ES-401-1 KA KA NAME II SAFETY NAME SAFETY FUNCTION:

FUNCTION: IR IR Kl K2 K1 K2 K3 K4 K5 K3 K4 K5 K6 K6 A1 Al A2 A2 A3 A3 A4 A4 GG TOPIC:

TOPIC:

RO RO SRO SRO 212000A2.12 RPS 212000A2.12 RPS 4.0 4.0 4.1 4.1 0 0 0 0 0 0 0 2J 0 0 0 Main Main turbine turbine stop stop control control valve valve closure closure 217000G2.4.8 RCIC 217000G2.4.8 RCIC 3.8 3.8 4.5 4.5 0 0 0 0 0 0 0 0 0 0 ~ Knowledge Knowledge of of how how abnormal abnormal operating operating procedures procedures are are used used inin conjunction conjunction with with EOPs.

EOPs.

2.39002G2.2.25 SRVs 239002G2.2.25 SRVs 3.2 3.2 4.2 4.2 0 0fl 0 0fl 0 0 0 0 0 0 ~ Knowledge of Knowledge of the the bases bases in in Technical Technical Specifications Specifications for for limiting limiting conditions conditions forfor operations operations and and safety safety limits.

limits.

262002G2.1 .23 UPS (ACIDC)

(AC/DC) 262002G2.1.23 UPS 4.3 4.3 4.4 4.4 0 0 0 0 0 0 0 0 0 0 ~ Ability toto perform perform specific specific system system and and integrated integrated plant plant procedures procedures during during all modes of all modes of plant plant operation.

operation.

300000A2.OllnstrumentA ir 300000A2.01 Instrument Air 2.9 2.9 2.8 2.8 0 0 0 0 0 0 0 2J 0 0 0 Air dryer and iltermalfunct Airdryerandf filter malfunctions ions Page 11of Page of11 06118/2009 8:52 AM 06118/2009 8:52 AM

ES-401, REV ES-401, REV 99 EXAMINATION OUTLINE SRO T2G2 BWR EXAMINATION FORM FORM ES-401-1 ES-401-1 KA KA NAME II SAFETY NAME SAFETY FUNCTION:

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

RO SRO 204000G223 RWCU 204000G2.2.3 RWCU 3.8 3.8 3.9 3.9 0LI 0LI 0LI 0 0 0 0LI 0LI 0 0 ~ (multi-unit license) license) Knowledge Knowledge ofof the the design, design, procedural procedural operational differences and operational differences between between units.

units.

214000A2.03 RPIS 214000A2.03 RPIS 3.6 3.6 3.9 3.9 nOD LI LI LI LI 0 LI 0 LI 0 [] 0 ~ 0 [lfljOvertrav 0 0 Overtravellin-out el/in-out 233000G2.4. 34 Fuel Fuel Pool Pool CoolinglClea nup 233000G2.4.34 Cooling/Cleanup 4.2 4.2 4.1 4.1 0 LI LI 0 LI0 LI 0 LI 0 LI 0 LI 0 LI 0 LI 0 LI 0 ~ Knowledge of of RO RO tasks tasks performed performed outside outside the the main main control room control room during during an an emergency emergency andand the the resultant resultant operational effects operational effects Page1 1ofof1 1 Page 8:52AM 06/1812009 8:52 06/18/2009 AM

ES-401, REV ES-401. REV 99 SRO T3 SRO T3 BWR BWR EXAMINATION EXAMINATION OUTLINE OUTLINE FORM FORM ES-401*1 ES-401-1 KA KA NAME II SAFETY NAME SAFETY FUNCTION:

FUNCTION: ER IR Ki K2 K1 K2 K3 1<3 K4 K4 K5 1<5 K6 K6 A1 Al A2 A2 A3 A3 A4 A4 G G TOPIC:

TOPIC:

RO RO SRO SRO G2.1 42 Conduct of of operations operations 3.4 G2.1.42 Conduct 2.5 2.5 3.4 0 0fl 0 0El 0fl 0fl 0 0 0 0 ~

i Knowledge Knowledge of of new new and and spent spent fuel fuel movement movement procedures procedures G2.1 .5 Conduct of of operations operations 2.9 G2.1.5 Conduct 2.9 3.9 3.9 0 0 0 0 0 0 0 0 0 0 ~ Ability to to locate and and use use procedures procedures related related to to shift shift staffing.

staffing, such such as as minimum minimum crew crew complement.

complement, overtime overtime limitations.

limitations, etc.

etc.

G2.2.15 EquipmentC ontrol 3.9 G2.2.15 Equipment Control 3.9 4.3 4.3 DOD 0 0 0 [] 0 0 0 0 ~ Ability to determine Abilitytodete the expected rminetheexpe plant configuration ctedplantcon flguration using design andand configuration configuration control control documentaion documentaion G2.222 Equipment Equipment Control 4.0 G2.2.22 Control 4.0 4.7 4.7 0 0 fl 0 DOD fl 0 0 0 0 El, ~ Knowledge of of limiting conditions for limiting conditions for operations operations and and safety limits.

limits.

02.3.1 G2.3.111 Radiation Radiation Control Control 3.8 3.8 4.3 4.3 0 E0 El 0 El0 El 0 El 0 El 0 El0 El 0 El 0 ~ to control Ability to control radiation radiation releases releases G2.4.17 Emergency G2.4.17 Emergency Procedures/P lans Procedures/Plans 3.9 3.9 4.3 4.3 0 0 0 0 0 0 0 0 0 {] 0 ~ Knowledge of Knowledge of EOP EOP terms terms and and definitions.

definitions.

02.4.35 Emergency G2.4.35 Emergency Procedures/P lans Procedures/Plans 3.8 3.8 4.0 4.0 0 El El 0 El 0 El0 El 0 El 0 El 0 El0 El 0 El 0 ~ Knowledge of Knowledge of local local auxiliary auxiliary operator operator tasks tasks during during emergency and emergency and the the resultant resultant operational operational effects effects Page1 1ofof1 1 Page 06/18/2009 8:52 06/18/2009 8:52AMAM

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

Facility: Brunswick Brunswick Date of Examination:

Date Examination: April April 2010 Examination Level:

Examination Level: RO Administrative Topic

  • SRO-i SRO-J Type
  • Operating Test Number: DRAFT Describe activity to be performed DRAFT (see Note) Code*

Code*

R, M, D R,M,D Core Performance Check - APRM parameter check Conduct of Operations R, M, P R,M,P Drywell Average Air Temperature Calculation Conduct of Operations R, P R,P (SRO-l only) Refueling Technical Specifications (SRO-I R, D R,D RCC Clearance Equipment Control R, M R,M Calculation of Stay Times Radiation Control R, M R,M (5R0-l only) Emergency Action Level (SRO-I 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 (

(::; 33 for ROs; ::; 4 for SROs & RO retakes)

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

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

\k

Conduct of Operations Core Performance Check RO/SROIROISROI R, M, D K/A 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 11PT-O1.i1 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 K/A KIA 2.1.20 Ability to interpret and execute procedure steps This is a modified classroom Administrative JPM that will require the examinee OPT-i 6.2. Modified to allow performance in a classroom setting and perform OPT-16.2.

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 (SRO-l Only) R, P Evaluate Refueling Technical Specifications (SRO-I P K/A 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 K/A 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 OPS-NGGC-i 301.

of OPS-NGGC-1301.

Radiation Control Calculation of Stay Times M R, M K/A KIA 2.3.7 Ability to comply with radiation work permit requirements during normal and abnormal conditions This is aa 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 Procedures/Plan Emergency Action Level Determinations (SRO-l (SRO-I Only) R, M M

K/A KIA 2.4.29 Knowledge of the Emergency Plan This is aa modified banked classroom Administrative JPM that will require the examinee to classify an emergency per PEP-02.1. Modified to incorporate NEI 99-0 99-011 EAL5.

EALs.

ES-301 Roomlln-Plant Systems Outline Control Room/In-Plant Form ES-301-2 Facility: Brunswick Date of Examination: April 2010 Exam Level: RO

  • SRO-I.

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

Control Room Systems@

System I/ JPM Title Type Code*Code* Safety Function

a. Bypass a LPRM S, 5, D 7
b. Restart RBHVAC with Failure to Isolate 5, A, D S,A, 9 B Loop RHR in SPC lAW hard card - NSW header failure
c. Place BLoop 5, A, P S,A, 5
d. Place HPCI in Pressure control 5, A, P S,A, 3
e. 230 kV Bus in Service 5, D S, 6
f. Secure Main Turbine with failure of PCB to open 5, A, N S,A, N 4
g. SULCV in service after scram S, L, D 2
h. (RO only) Restart CRD S, D S,D 11 Systems@ (3 for RO/SRO-I)

In-Plant Systems@

i. LEP-01 LEP-Ol Alternate Coolant Injection, SLC wI w/ Fire Water R, M, E R,M,E 2
j. Fire Pump power supply to alternate D 8 k.SAMADG
k. SAMA DG R,P,M,E R,P,M, E 6

@ All RO and SRO-l SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 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-I / SRO-U (A)lternate path 4-6 I/ 4-6 I/ 2-3 (C)ontrol room (D)irect from bank 9I 8I 4
59/:58/:54 (E)mergency or abnormal in-plant 2:1/2:1/2:1 1 I 1 I 1 (EN)gineered safety feature - / - I/ 1

- - 2:1 (control room system)

(L)ow-Power / Shutdown 1 / 1 I 1 2:1/2:1/2:1 (N)ew or (M)odified from bank including 1 1 (A) 2:2/2:2/2:1 2/ 2I 1 (P)revious 22 exams :5 33 / :5 33 I/ :5 22 (randomly selected)

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

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

abnormal conditions.

This isis aa banked This banked simulator simulator JPM JPM that that will require the will require the examinee examinee toto bypass an bypass an LPRM.

LPRM.

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

and the examinee B Loop RHR in SPC lAW hard card - NSW header failure

c. Place BLoop 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 .04 EA11.04 Ability to operate and/or monitor the following as they apply to High Reactor Pressure: HPCI (plant specific)

This is a a banked simulator JPM that will require the examinee to place HPCI into pressure control mode of operation. As an alternate path there is aa 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 aa banked simulator JPM that will require the examinee energize 230 kV Bus 2B.

f. Main Turbine Shutdown 245000 A2.01 a turbine trip on the Main Turbine Ability to predict impacts of a 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 aa 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 aa banked simulator JPM that will require the examinee to restart the CRD system.

i. LEP-Ol Alternate Coolant Injection, SLC wI Fire Water LEP-01 EA11.08 295031 EA .08 Ability To Operate/Monitor Alternate Coolant IInjection 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 LEP-Ol. This JPM is performed in the RCA. This JPM was per LEP-01.

modified due to a plant modification incorporating a a new connector to the fire water hose.

j.j. Fire Pump power supply to alternate Al1.05 286000 A .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 AAI1.02 295003 AA .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 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 a Station Blackout.
Retrieved from "https://kanterella.com/w/index.php?title=ML101590071&oldid=2557562"