ML093430219

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Initial Exam 2009-302 Draft Administrative Documents
ML093430219
Person / Time
Site: Hatch  Southern Nuclear icon.png
Issue date: 12/07/2009
From: Bruno Caballero
NRC/RGN-II/DRS/OLB
To:
Southern Nuclear Operating Co
References
50-321/09-302, 50-366/09-302
Download: ML093430219 (33)
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Text

{{#Wiki_filter:FACILITY NAME: _...:..H.:.:.,.A.:..:.T..=C;.:..:H:.....-________ Section 1 REPORT NUMBER: 05000321/2009302 AND 05000366/2009302 DRAFT ADMINISTRATIVE DOCUMENTS CONTENTS: o Draft Written Exam sample plan (ES-401-1/2/3) o Draft Administrative Topics Outline (ES-301-1) o Draft Control Room Systems & Facility Walk-Through Test Outline (ES-301-2) Location of Electronic Files: O:\\Hatch Examinations\\lnitial Exam 2009-302 Submitted By: Bruno Caballero Verified By:1I!J / ~ FACILITY NAME: _.....;;.H.;.;;..A....;;..;T""""'C;..;;..H~ _________ Section 1 REPORT NUMBER: 05000321/2009302 AND 05000366/2009302 DRAFT ADMINISTRATIVE DOCUMENTS CONTENTS: o Draft Written Exam sample plan (ES-401-1/2/3) o Draft Administrative Topics Outline (ES-301-1) o Draft Control Room Systems & Facility Walk-Through Test Outline (ES-301-2) Location of Electronic Files: O:\\Hatch Examinations\\lnitial Exam 2009-302 Submitted By: Bruno Caballero

ES-401 1 Rev. 9 BWR Examination Outline Form ES-401-1 Facility: HATCH Date of Exam: OCT/NOV 2009 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 4 3 7 Emergency & 2 1 1 1 2 1 1 7 2 1 3 Abnormal Plant N/A N/A Evolutions Tier Totals 5 4 4 6 4 4 27 6 4 10 1 3 2 3 2 2 3 3 3 2 1 2 26 3 2 5 2.- 1 1 1 1 1 1 2 1 1 1 1 12 0 I 2 1 3 Plant 2 Systems Tier Totals 4 3 4 3 3 4 5 4 3 2 3 38 5 3 8

3. Generic Knowledge and Abilities 1

2 3 4 10 I 1 I 2 I 3 I 4 I 7 I 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 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.

Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do v 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 KIA statements. 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. 0* 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 ofthe KIA Catalog, but the topics V

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 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 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. ES-401& Rev. 9 BWR Examination Outline Form ES-401-1 Facility: HATCH Date of Exam: OCT/NOV 2009 RO K/A 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 4 3 7 Emergency & 2 1 1 1 2 1 1 7 2 1 3 Abnormal Plant N/A N/A Evolutions Tier Totals 5 4 4 6 4 4 27 6 4 10 1 3 2 3 2 2 3 3 3 2 1 2 26 3 2 5 2.* 1 1 1 1 1 1 2 1 1 1 1 12 0 2 1 3 Plant 2 Systems Tier Totals 4 3 4 3 3 4 5 4 3 2 3 38 5 3 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 (Le., 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.

Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do v 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 KIA statements. /. 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. V 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 v'/ ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; iffuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note

  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, v' and point totals (#) on Form ES-401-3. Limit SRO selections to KIAs that are linked to 10 CFR 55.43.

ES-401 E/APE # I Name I Safety Function 295001 Partial or Complete Loss of Forced Core Flow Circulation I 1 & 4 295003 Partial or r.",,,nIAtA Loss of AC I 6 295004 Partial or Total Loss of DC Pwr I 6 295005 Main Turbine Generator Tri 13 295006 SCRAM I 1 295016 Control Room Abandonment I 7 295018 Partial or Total Loss of CCW I 8 295019 Partial or Total Loss of Ins!. Air 18 295021 Loss of Shutdown 14 295026 Suppression Pool High Water 15 295027 H 295028 H 295030 Low Su~-*~~~*;~~ 295031 Reactor Low Water Level I 2 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown I 1 295038 H Off-site Release Rate I 9 600000 Plant Fire On Site I 8 700000 Generator Voltage and Electric Grid Disturbances I 6 KIA Totals: 2 Form ES-401-1 BWR Examination Outline Form ES-401-1 and Abnormal Plant Evolutions - Tier 1

==~==~~~~~~~=========r==~==~1 IR ES-401 2 Form ES-401-1 ES-401 BWR Examination Outline ~I Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group <<(RO V ~J E/APE # I Name I Safety Function K K K A A G KIA Topic(s) IR 1 2 3 1 2 295001 Partial or Complete Loss of Forced R R~q5 A, ';:), ~3l(- Core Flow Circulation I 1 & 4 295003 Partial or Complete Loss of AC I 6 K RaQSOD3A-K [,04-f<-3./ 295004 Partial or Total Loss of DC Pwr I 6 R if<, ~ q S 004-G ';2. Lf~, c:r R3,t? 295005 Main Turbine Generator Trip I 3 tZ (Z;(qgoos A, \\L, 3( o? R3.g 295006 SCRAM I 1 K rz Jtf5()()b A A I. DJ-(?? q v', 295016 Control Room Abandonment I 7 R fJ.q 5 t)1 (p 1'1, A ;;(J)b ~:?3 295018 Partial or Total Loss of CCW I 8 K RJq 6 018,/< K3,D~ ((5.3 295019 Partial or Total Loss of Inst. Air 18 A Relq 5 DI q /\\ft-* I:)!, OJ. f< ],1, 295021 Loss of Shutdown Coolina I 4 f{ R~q 50J./ G,C;{,JA-b R3,4 295023 Refueling Acc I 8 A R';{q 50d-5AAI* 04* 1:3.4-295024 High Drywell Pressure I 5 R R ;;'Cf5 OC2/LFA d,a;}. ~:1,'1 295025 High Reactor Pressure I 3 !< lZ;;a50J~[" ' J" .. I .:::>.:oroe '/'0<-5 R43 295026 Suppression Pool High Water R R(lQ500lb EI< 31~1 ((3,g Temp. I 5 295027 High Containment Temperature I 5 295028 High Drywell Temperature I 5 !~. R2~ SrXJS 6A f,05 ~3}1 295030 Low Suppression Pool Wtr Lvi I 5 P R~q'5()30 £KI,oJ. 1<3.5 295031 Reactor Low Water Level I 2 {<, R~Cf5031 GAl,£)5 R1-,s 295037 SCRAM Condition Present f~; R~q5D37E K;t., 07 R,Llo and Reactor Power Above APRM Downscale or Unknown I 1 295038 High Off-site Release Rate I 9 rz II<.;<q 5D3$ Ek {, ['g RJ,y 600000 Plant Fire On Site I 8 R ,R bOt)[}(J 0 A f< I, 0;;' AJ{9 700000 Generator Voltage and Electric Grid f( IZ 70{)(}OD AJ< J.,,D? /(3.h Disturbances I 6 KIA Category Totals: f :3 12 4--3 3 Group Point Total: ~I (

ES-401, REV 9 (ro) T1G1 BWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 295003AK1.04 Partial or Complete Loss of AC 16 3.1 3.2 ~ D D D D D D D D D D 295004G2.4.9 Partial or Total Loss of DC Pwr 16 3.8 4.2 D D D D D D D D D D ~ 295005AK3.07 Main Turbine Generator Trip I 3 3.8 3.8 D D ~ D D D D D D D D 295006AA 1.02 SCRAM 11 3.9 3.8 D D D D D D ~ D D D D 295018AK3.06 Partial or Total Loss of CCW 18 3.3 3.3 D D ~ D D D D D D D D 295019AA2.02 Partial or Total Loss of Inst. Air 18 3.6 3.7 D D D D D D D ~ D D D 295021G2.2.40 Loss of Shutdown Cooling 14 3.4 4.7 D D D D D D D D D D ~ 295023AA 1.04 Refueling Acc Cooling Mode I 8 3.4 3.7 D D D D D D ~ D D D D 295025G2.1.23 High Reactor Pressure I 3 4.3 4.4 D D D D D D D D D D ~ 295026EK3.01 Suppression Pool High Water Temp. I 3.8 4.1 D D ~ D D D D D D D D 5 295028EA1.03 High Drywell Temperature 15 3.9 3.9 D D D D D D ~ D D D D Page 1 of 2 FORM ES-401-1 TOPIC: Electrical bus divisional separation.................. Knowledge of low power I shutdown implications in accident (e.g. LOCA or loss of RHR) mitigation strategies. Bypass valve operation............................... Reactor water level control system.................... Increasing cooling water flow to heat exchangers...... Status of safety-related instrument air system loads (see AK2.1 - AK2.19).................................. Ability to apply technical specifications for a system. Radiation monitoring equipment........................ Ability to perform specific system and integrated plant procedures during all modes of plant operation. Emergencylnormal depressurization..................... Drywell cooling system................................ 4129/2009 1 :47 PM ES-401, REV 9 (~D) T1 G1 BWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 295003AK1.04 Partial or Com plete Loss of AC / 6 3.1 3.2 ~ D D D D D D D D D D 295004G2.4.9 Partial or Total Loss of DC Pwr / 6 3.8 4.2 D D D D D D D D D D ~ 295005AK3.07 Main Turbine Generator Trip / 3 3.8 3.8 D D ~ D D D D D D D D 295006AA1.02 SCRAM / 1 3.9 3.8 D D D D D D ~ D D D D 295018AK3.06 Partial or Total Loss of CCW / 8 3.3 3.3 D D ~ D D D D D D D D 295019AA2.02 Partial or Total Loss of Inst. Air / 8 3.6 3.7 D D D D D D D ~ D D D 295021 G2.2.40 Loss of Shutdown Cooling / 4 3.4 4.7 D D D D D D D D D D ~ 295023AA 1.04 Refueling Acc Cooling Mode / 8 3.4 3.7 D D D D D D ~ D D D D 295025G2.1.23 High Reactor Pressure / 3 4.3 4.4 D D D D D D D D D D ~ 295026EK3.01 Suppression Pool High Water Temp. / 3.8 4.1 D D ~ D D D D D D D D 5 295028EA1.03 High Drywell Temperature / 5 3.9 3.9 D D D D D D ~ D D D D Page 1 of 2 FORM ES-401-1 TOPIC: Electrical bus divisional separation.................. Knowledge of low power / shutdown im plications in accident (e.g. LOCA or loss of RHR) mitigation strategies. Bypass valve operation............................... Reactor water level control system.................... Increasing cooling water flow to heat exchangers...... Status of safety-related instrument air system loads (see AK2.1 - AK2.19}.................................. Ability to apply technical specifications for a system. Radiation monitoring equipment........................ Ability to perform specific system and integrated plant procedures during all modes of plant operation. Emergency/normal depressurization..................... Drywell cooling system................................ 4/29/2009 1 :47 PM

ES-401, REV 9 (RD) T1Gl BWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION: IR* K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 295030EK1.02 Low Suppression Pool Wtr LviI 5 3.5 3.8 ~ 0 0 0 0 0 0 0 0 0 0 295031 EA 1.05 Reactor Low Water Levell 2 4.3 4.3 0 0 0 0 0 0 ~ 0 0 0 0 295037EK2.07 SCRAM Condition Present and Power 4.0 4.0 0 ~ 0 0 0 0 0 0 0 0 0 Above APRM Downscale or Unknown 11 700000AK2.07 Generator Voltage and Electric Grid 3.6 3.7 0 ~ 0 0 0 0 0 0 0 0 0 Distrurbancecs 295001AK2.07 Partial or Complete Loss of Forced 3.4 3.4 0 ~ 0 0 0 0 0 0 0 0 0 Core Flow Circulation 11 & 4 295016AA2.06 Control Room Abandonment 17 3.3 3.5 0 0 0 0 0 0 0 ~ 0 0 0 295024EA2.02 High Dryweli Pressure I 5 3.9 4.0 0 0 0 0 0 0 0 ~ 0 0 0 295038EK1.03 High Off-site Release Rate I 9 2.8 3.8 ~ 0 0 0 0 0 0 0 0 0 0 600000AK1.02 Plant Fire On Site I 8 2.9 3.1 ~ 0 0 0 0 0 0 0 0 0 0 Page 2 of 2 FORM ES-401-1 TOPIC: Pump NPSH............................................. Reactor core isolation system: Plant-Specific........ Neutron monitoring system............................. Turbine I Generator control Core flow indication.................................. Cooldown rate......................................... Dryweli temperature................................... Meteorological effects on off-site release............ Fire Fighting 4/29/2009 1 :47 PM ES-401, REV 9 (g,D) T1G1 BWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 295030EK1.02 Low Suppression Pool Wtr Lvi 1 5 3.5 3.8 ~ D D D D D D D D D D 295031 EA1.05 Reactor Low Water Levell 2 4.3 4.3 D D D D D D ~ D D D D 295037EK2.07 SCRAM Condition Present and Power 4.0 4.0 D ~ D D D D D D D D D Above APRM Downscale or Unknown 1 1 700000AK2.07 Generator Voltage and Electric Grid 3.6 3.7 D ~ D D D D D D D D D Distrurbancecs 295001AK2.07 Partial or Complete Loss of Forced 3.4. 3.4 D ~ D D D D D D D D D Core Flow Circulation 1 1 & 4 295016AA2.06 Control Room Abandonment 1 7 3.3 3.5 D D D D D D D ~ D D D 295024EA2.02 High Drywell Pressure 1 5 3.9 4.0 D D D D D D D ~ D D D 295038EK1.03 High Off-site Release Rate/9 2.8 3.8 ~ D D D D D D D D D D 600000AK1.02 Plant Fire On Site 1 8 2.9 3.1 ~ D D D D D D D D D D Page 2 of 2 FORM ES-401-1 TOPIC: Pump NPSH............................................. Reactor core isolation system: Plant-Specific........ Neutron monitoring system............................. Turbine 1 Generator control Core flow indication.................................. Cooldown rate......................................... Drywell temperature................................... Meteorological effects on off-site release............ Fire Fighting 4/29/2009 1:47 PM

ES-401 3 Form ES-401-1 ES-401 BWR Examination Outline ~ Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 RO)SR6j Form ES-401-1 EIAPE # I Name I Safety Function K K K A I,d KIA Topic(s) IR 1 2 3 1 295002 Loss of Main Condenser Vac I 3 i Ii' 295007 High Reactor Pressure I 3 295008 High Reactor Water Levell 2 295009 Low Reactor Water Levell 2 295010 High Drywell Pressure I 5 R /'.., ;JiS 0 I !) A III / ',?5-J?;:U 295011 High Containment Temp 15 j'f 295012 High Drywell Temperature 15 '~~I !iT 295013 High Suppression Pool Temp./5 .. /) 15~\\ 1 RJqS* Of;?*C[ Oi:, -t}, j f(A~ 295014 Inadvertent Reactivity Addition 11 Ix /'i: 1 K,;;'}ti 5 at 5 A p,;, f)~2 I<::.:,{ 1) 295015 Incomplete SCRAM 11 K 295017 High Off-site Release Rate I 9 295020 Inadvertent Cont. Isolation 15 & 7 Iq5D'{~vAA.;;?, p.;~ 1;11"3, 7 295022 Loss of CRD Pumps 11 !\\;' 295029 High Suppression Pool Wtr LviI 5 I L 295032 High Secondary Containment t: R (X1Q ~ /:1 3;;;' R,{;leI If~:~lh Area Temperature 15 I. 295033 High Secondary Containment Area Radiation Levels I 9 295034 Secondary Containment Ventilation High Radiation I 9 295035 Secondary Containment High R (J IR33 Differential Pressure I 5 I( 295036 Secondary Containment High SumplArea Water Levell 5 500000 High CTMT Hydrogen Conc. I 5 JI t\\ . r?':: (,,> An"" E:/(l. .",,,~, I', 1 !f'3~i'j ~ KIA Category Point Totals: I I ~ ~"' PO;O! Tota; r;;S,~ ES-401 3 Form ES-401-1 ES-401 BWR Examination Outline ~~_ Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 RO ~ EIAPE # I Name I Safety Function K K K A A G KIA Topic(s) IR 1 2 3 1 2 295002 Loss of Main Condenser Vac 13 295007 High Reactor Pressure 13 295008 High Reactor Water Levell 2 295009 Low Reactor Water Levell 2 295010 High Drywell Pressure 15 I< fZ~1SOI{) AAI,{)5' R3./ 295011 High Containment Temp 15 295012 High Drywell Temperature 15 295013 High Suppression Pool Temp. I 5 ~ R ;2q5 {;liZ (i" C)" /i<-.! 1i4,b 295014 Inadvertent Reactivity Addition 11 295015 Incomplete SCRAM 11 fZ R ;;;<; 5' 0'/ S" A A/, DJ. V?4. D 295017 High Off-site Release Rate 19 295020 Inadvertent Cont. Isolation 15 & 7 f<

<;ZQ5ot?vAcA;Y, ~

I? 3. '1 ( 295022 Loss of CRD Pumps 11 295029 High Suppression Pool Wtr LviI 5 295032 High Secondary Containment I<. R :;q 5 () 32. [~~ F I, OJ, ~3b Area Temperature I 5 295033 High Secondary Containment Area Radiation Levels I 9 295034 Secondary Containment Ventilation High Radiation I 9 295035 Secondary Containment High R, R ~H51) 35 r£k 3,(}(;r. 1(33 Differential Pressure I 5 295036 Secondary Containment High SumplArea Water Levell 5 500000 High CTMT Hydrogen Conc. 15 A r<50f)~t)O £I<'cl.{)&' R3tJ KIA Category Point Totals: I I I d. I I Group Point Total: I~ (

ES-401, REV 9 CRo) T1G2 BWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION: 29501 OAA 1.05 High Drywell Pressure 1 5 295013G2.4.1 High Suppression Pool Temp. 15 295015AA1.02 Incomplete SCRAM 11 295020AA2.03 Inadvertent Cont. Isolation 1 5 & 7 295032EK1.02 High Secondary Containment Area Temperature 1 5 295035EK3.02 Secondary Containment High Differential Pressure 1 5 500000EK2.06 High CTMT Hydrogen Cone. 1 5 IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.1 3.4 0 0 0 0 0 0 ~ 0 0 0 0 4.6 4.8 0 0 0 0 0 0 0 0 0 0 ~ 4.0 4.2 0 0 0 0 0 0 ~ 0 0 0 0 3.7 3.7 0 0 0 0 0 0 0 ~ 0 0 0 3.6 4.0 ~ 0 0 0 0 0 0 0 0 0 0 3.3 3.5 0 0 ~ 0 0 0 0 0 0 0 0 3.0 3.4 0 ~ 0 0 0 0 0 0 0 0 0 Page 1 of 1 FORM ES-401-1 TOPIC: Dryweil/suppression vent and purge.................... Knowledge of EOP entry conditions and immediate action steps. RPS................................................... Reactor power......................................... Radiation releases.................................... (e'3'~ T~ ~ f1~ $C-C-. ftaW~'lZMih \\l.;V~C- ~t'DYl If ~ ~ ~~) Secondary containment ventilation response............ Wetwell Spray system 4/29/2009 1 :47 PM ES-401, REV 9 CRo) T1 G2 BWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION: 295010AA1.05 High Drywell Pressure 1 5 295013G2.4.1 High Suppression Pool Temp. 1 5 295015AA1.02 Incomplete SCRAM 11 295020AA2.03 Inadvertent Cont. Isolation 1 5 & 7 295032EK1.02 High Secondary Containment Area Temperature 1 5 295035EK3.02 Secondary Containment High Differential Pressure 1 5 500000EK2.06 High CTMT Hydrogen Conc. 1 5 IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.1 3.4 D D D D D D ~ D D D D 4.6 4.8 D D D D D D D D D D ~ 4.0 4.2 D D D D D D ~ D D D D 3.7 3.7 D D D D D D D ~ D D D 3.6 4.0 ~ D D D D D D D D D D 3.3 3.5 D D ~ D D D D D D D D 3.0 3.4 D ~ D D D D D D D D D Page 1 of 1 FORM ES-401-1 TOPIC: Dryweil/suppression vent and purge.................... Knowledge of EOP entry conditions and immediate action steps. RPS................................................... Reactor power......................................... Radiation releases.................................... (e'3.)T~ L4j 6/, ScC. f(oWC~' !Z\\Mih \\\\\\Jf\\C-or0:ttk,'OV\\.if nw- ~5' Fse4) Secondary containment ventilation response............ Wetwell Spray system 4/29/2009 1 :47 PM

ES-401 4 Form ES-401-1 BWR Examination OLJ!lLne Form ES-401-1 Plant Systems - Tier 2/Group;;",1~' (!O,;RR,;;;,Q)0!f:'~~;f~)-==========;r====;====l1 li=sy=s=te=m=#=1 =Na=m=e=====r=K=r=K=r=K=r=K=FK=r="'=K FA= A =;t KIA Topic(s) 1~ ________________ ~~1~2~3~4~5~6~~1 r3-r4-r~-r;--------------------____ -r __ +-__ ~1 IR 203000 RHRlLPCI: Injection Mode 205000 Shutdown Cooling 206000 HPCI 207000 Isolation (Emergency) Condenser ~t<! () '1 "-Z"() A. ':" "" '~,' ~~S' ~ "of. t~.,) Go' () 1;,..";lti,:;i,

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,
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209002 HPCS ......~;~? --~, 215005 APRM I LPRM 217000 RCIC 218000 ADS 223002 PCIS/Nuciear Steam Supply Shutoff 239002 SRVs 259002 Reactor Water Level Control 261000 SGTS 262001 AC Electrical Distribution 262002 UPS (AC/DC) 263000 DC Electrical Distribution 264000 EDGs 300000 Instrument Air 400000 Component Cooling Water KIA Category Point Totals: t' K l< s ~g f( t" I~ :2 5111'/:) J,~ A4. i;i3" R,;( 5 '}tM~i k.'(;,tltt I< 3. J I R i ',,' i/1~

  • ===============~=~

Group Point Total: ES-401 4 Form ES-401-1 ES-401 BWR Examination o~~ Form E'",n, Plant Systems - Tier 2/Group 1 0 System # / Name K K K K K K A A A A G KIA Topic(s) IR 1 2 3 4 5 6 1 2 3 4 203000 RHRlLPCI: Injection R Rc20~~OOOG\\~,1,1t R4l:; Mode 205000 Shutdown Cooling I< R d'D '5t}tYCJ ~~ £, R:{,g 206000 HPCI R IZ~ O~ OOl' 1<5 < I?£" 1<3.3 207000 Isolation (Emergency) Condenser 209001 LPCS ~ f!. 'd.of OD I /-(1, OJ R ~ 01001/<1, 13 1~3,;L 2.rl 209002 HPCS 211000SLC R R,)) J () [)l) R3.£; 212000 RPS ~ R. ~IJ. D~{) A i!,J6 J R. dl /, POD A(;" If 1'<.4-.D fU.% 2150031RM R f!..;?150fJ3 A t.£!4 R3.4 215004 Source Range Monitor P.. <<;</ S()04 kC?OI ~g,;;?: ( 215005 APRM / LPRM ~ /( 2./6:(1)5AI.D1* f!..:u5()& SA I. t}:; ~4'/ 3,:/' 217000 RCIC I<. A. C< 17 () 00 K;(dJ':5 R;(*7 218000 ADS P..cxl<6000 /{l.OG. IR3,r 223002 PCIS/Nuclear Steam R Supply Shutoff f? ~~" !}~ - K,5,;'i( 1?2.b " (,( ;;13,r/ cl",,;,, 239002 SRVs A j( 2s'/!)()d 143,1,0' R4.1 R3,g 259002 Reactor Water Level Control f< ~ R 259r?OiJ: 1'14.03 R?5'}OtQ k~/b4 R3.J 261000 SGTS ~ I<. ;l (,pI {}()O k 3,tJ I I<;;(fp/()!)() J< 3.1)~ ~3.3 3.0 262001 AC Electrical f( Distribution R. ';J6;lOO(lfii;{' ;;',44 fJ,4,J. 262002 UPS (AC/DC) R. j{ ;2&:it iJO,J., A 3,0/ ~2,.? 263000 DC Electrical Distribution I< '21., S f)() 0 A:?, () I t,Z!5 264000 EDGs R fi" 2bL'J-IH)[) K4J)4 <<U~ 300000 Instrument Air P, R 3000{)0 K6,tJ7 R)S 400000 Component Cooling f< A Lj(){)OOO K d, O;:L ~;(, r Water \\, KIA Category Point Totals: '3 ? "3 ~ ;1. '3 3-3 I~ I cl Group Point Total: {~

ES-401, REV 9 e/<.D) T2Gl BWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 203000G2.1.31 RHRlLPCI: Injection Mode 4.6 4.3 0 0 0 0 0 0 0 0 0 0 ~ 205000K5.03 Shutdown Cooling 2.8 3.1 0 0 0 0 ~ 0 0 0 0 0 0 . 206000K5.05 HPCI 3.3 3.3 0 0 0 0 ~ 0 0 0 0 0 0 209001 K1.09 LPCS 3.2 3.4 ~ 0 0 0 0 0 0 0 0 0 0 209001K1.13 LPCS 2.8 3.0 ~ 0 0 0 0 0 0 0 0 0 0 211000K4.03 SLC 3.8 3.9 0 0 0 ~ 0 0 0 0 0 0 0 212000A2.16 RPS 4.0 4.1 0 0 0 0 0 0 0 ~ 0 0 0 212000A2.19 RPS 3.8 3.9 0 0 0 0 0 0 0 ~ 0 0 0 215003A1.04 IRM 3.4 3.4 0 0 0 0 0 0 ~ 0 0 0 0 215004K6.01 Source Range Monitor 3.2 3.3 0 0 0 0 0 ~ 0 0 0 0 0 215005A1.04 APRM 1 LPRM 4.1 4.1 0 0 0 0 0 0 ~ 0 0 0 0 Page 1 of 3 FORM ES-401-1 TOPIC: Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup. Heat removal mechanisms Turbine speed control: BWR-2,3,4 Nuclear boiler instrumentation Leak detection Keeping sodium pentaborate in solution Changing mode switch position Partial system activation (half-SCRAM) Control rod block status RPS \\ SCRAM and rod block trip setpoints 4/29/2009 1 :47 PM ES-401, REV 9 (I<D) T2G1 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC: RO SRO 203000G2.1.31 RHRlLPCI: Injection Mode 4.6 4.3 DDDDDDDDDD~ Ability to locate control room switches, controls and indications and to determine that they are correctly reflecting the desired plant lineup. 205000K5.03 Shutdown Cooling 2.8 3.1 DDDD~DDDDDD Heat removal mechanisms . 206000K5.05 HPCI 3.3 3.3 DDDD~DDDDDD Turbine speed control: BWR-2,3,4 209001K1.09 LPCS 3.2 3.4 ~DDDDDDDDDD Nuclear boiler instrumentation 209001K1.13 LPCS 2.8 3.0 ~DDDDDDDDDD Leak detection 211000K4.03 SLC 3.8 3.9 DDD~DDDDDDD Keeping sodium pentaborate in solution 212000A2.1 6 RPS 4.0 4.1 DDDDDDD~DDD Changing mode switch position 212000A2.19 RPS 3.8 3.9 DDDDDDD~DDD Partial system activation (half-SCRAM) 215003A1.04 IRM 3.4 3.4 DDDDDD~DDDD Control rod block status 215004K6.01 Source Range Monitor 3.2 3.3 DDDDD~DDDDD RPS 215005A1.04 APRM 1 LPRM 4.1 4.1 DDDDDD~DDDD SCRAM and rod block trip setpoints Page 1 of 3 4/29/2009 1:47 PM

ES-401, REV 9 KA NAME / SAFETY FUNCTION: 215005A1.05 APRM/LPRM 217000K2.03 RCIC 218000K1.06 ADS 223002K3.21 PCIS/Nuclear Steam Supply Shutoff 239002A3.05 SRVs 259002A4.03 Reactor Water Level Control 259002K6.04 Reactor Water Level Control 261000K3.01 SGTS 261000K3.06 SGTS 262001G2.2.44 AC Electrical Distribution 262002A3.01 UPS (AC/DC) (FD2 T2G1 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.3 3.2 DDDDDD~DDDD 2.7 2.8 D~DDDDDDDDD 3.9 3.9 ~DDDDDDDDDD 2.6 2.7 DD~DDDDDDDD 4.1 4.2 0 0 0 0 0 0 0 0 ~ 0 0 3.8 3.6 0 0 0 0 0 0 0 0 0 ~ 0 3.1 3.1 0 0 0 0 0 ~ 0 0 0 0 0 3.3 3.6 0 0 ~ 0 0 0 0 0 0 0 0 3.0 3.3 0 0 ~ 0 0 0 0 0 0 0 0 4.2 4.4 0 0 0 0 0 0 0 0 0 0 ~ 2.8 3.1 0 0 0 0 0 0 0 0 ~ 0 0 Page 2 of 3 FORM ES-401-1 TOPIC: Lights and alarms RCIC flow controller Safety/relief valves Traversing in-core probe system Suppression pool temperature All individual component controllers when transferring from manual to automatic modes Reactor feedwater flow input Secondary containment and environment differential pressure Primary containment oxygen content: Mark-I&II Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions Transfer from preferred to alternate source 4/29/2009 1 :47 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION: 215005A1.05 APRM / LPRM 217000K2.03 RCIC 218000K1.06 ADS 223002K3.21 PCIS/Nuclear Steam Supply Shutoff 239002A3.05 SRVs 259002A4.03 Reactor Water Level Control 259002K6.04 Reactor Water Level Control 261000K3.01 SGTS 261000K3.06 SGTS 262001 G2.2.44 AC Electrical Distribution 262002A3.01 UPS (AC/DC) ~D) T2G1 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.3 3.2 D D D D D D ~ D D D D 2.7 2.8 D ~ D D D D D D D D D 3.9 3.9 ~ D D D D D D D D D D 2.6 2.7 D D ~ D D D D D D D D 4.1 4.2 D D D D D D D D ~ D D 3.8 3.6 D D D D D D D D D ~ D 3.1 3.1 D D D D D ~ D D D D D 3.3 3.6 D D ~ D D D D D D D D 3.0 3.3 D D ~ D D D D D D D D 4.2 4.4 D D D D D D D D D D ~ 2.8 3.1 D D D D D D D D ~ D D Page 2 of 3 FORM ES-401-1 TOPIC: Lights and alarms RCIC flow controller Safety/relief valves Traversing in-core probe system Suppression pool temperature All individual component controllers when transferring from manual to automatic modes Reactor feedwater flow input Secondary containment and environment differential pressure Primary containment oxygen content: Mark-I&II Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions Transfer from preferred to alternate source 4/29/2009 1 :47 PM

ES-401, REV 9 (RO,) T2G1 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC: RO SRO 263000A2.01 DC Electrical Distribution 2.8 3.2 DDDDDDD~DDD Grounds 264000K4.04 EDGs 2.6 2.7 DDD~DDDDDDD Field flashing 300000K6.07 Instrument Air 2.5 2.6 DDDDD~DDDDD Valves 400000K2.02 Component Cooling Water 2.9 2.9 D~DDDDDDDDD CCWvalves Page 3 of 3 4/29/2009 1 :47 PM ES-401, REV 9 (Rq) T2G1 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC: RO SRO 263000A2.01 DC Electrical Distribution 2.8 3.2 D D D D D D D ~ D D D Grounds 264000K4.04 EDGs 2.6 2.7 D D D ~ D D D D D D D Field flashing 300000K6.07 Instrument Air 2.5 2.6 D D D D D ~ D D D D D Valves 400000K2.02 Component Cooling Water 2.9 2.9 D ~ D D D D D D D D D CCW valves Page 3 of 3 4/29/2009 1:47 PM

ES-401 201003 Control Rod and Drive Mechanism 201004 RSCS 5 Form ES-401-1 Form ES-IR ES-401 5 Form ES-401-1 ES-401 BWR Examination ou~ Form ES-401-1 P System # / Name K K K K K K A A A A G KIA Topic(s) IR 1 2 3 4 5 6 1 2 3 4 V 201001 CRD Hydraulic R i<.C2o 100 t 1<5,a;L RU. 201002 RMCS 201003 Control Rod and Drive Mechanism 201004 RSCS 201005 RCIS 201006 RWM V 202001 Recirculation If f<2o(}.oo/ A3,04 P'j.::l. V 202002 Recirculation Flow Control I< A ~();J. {)JJ ~ J<';;{,02. 1<2,b V 204000 RWCU R R ;;;'I)+~()D ~;z, 4,4, ((4,l V 214000 RPIS R P. 'Q14L?{)/) KI,p/j lig.] 215001 Traversing In-core Probe 215002 RBM V 216000 Nuclear Boiler Inst. 1< f( ;).;(PO{)!) A CJ.. /1'0 /(3.3 219000 RHRfLPCI: Torus/Pool Cooling Mode ( 223001 Primary CTMT and Aux. 226001 RHRfLPCI: CTMT Spray Mode 230000 RHRfLPCI: Torus/Pool Spray Mode !/ 233000 Fuel Pool Cooling/Cleanup K. I< ;;Z -33IJ'.::;';) k 4-, O/;, R2.cl / 234000 Fuel Handling Equipment P.

p. 234000 1<3. ()4 R2/1 f,..

239001 Main and Reheat Steam 239003 MSIV Leakage Control i/ 241000 ReactorlTurbine Pressure R. I<. ~41 DIJOAI, J4.- 1<2.1:. Regulator 245000 Main Turbine Gen. / Aux. 256000 Reactor Condensate 259001 Reactor Feedwater 268000 Radwaste 271000 Offgas 272000 Radiation Monitoring v 286000 Fire Protection f k oZg?; DbD /14. oa. /(;(S 288000 Plant Ventilation 290001 Secondary CTMT V 290003 Control Room HVAC I< ",;;(q'0 (if) '3 AI. 04 Rc(S V 290002 Reactor Vessel Internals I< ;<q fl DO;2. ;.<,. 0'% I<Z,r KIA Category Point Totals: I I \\ I 1 ( I :2 I I \\ I Group Point Total:

ES-401, REV 9 CRO) T2G2 BWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 201001 K5.02 CRD Hydraulic 2.6 2.6 DDDD~DDDDDD 202001 A3.04 Recirculation 3.2 3.1 DDDDDDDD~DD 202002K2.02 Recirculation Flow Control 2.6 2.6 D ~ D D D D D D D D D 204000G2.4.46 RWCU 4.2 4.2 D D D D D D D D D D ~ 214000K1.04 RPIS 3.2 3.2 ~ D D D D D D D D D D 216000A2.10 Nuclear Boiler Inst. 3.3 3.5 D D D D D D D ~ D D D 233000K4.06 Fuel Pool Cooling/Cleanup 2.9 3.2 D D D ~ D D D D D D D 234000K3.04 Fuel Handling Equipment 2.9 3.8 D D ~ D D D D D D D D 241 OOOA 1.24 ReactorlTurbine Pressure Regulator 2.6 2.7 D D D D D D ~ D D D D 286000A4.02 Fire Protection 2.5 2.5 D D D D D D D D D ~ D 28W02K6.08 Reactor Vessel Internals 2.9 3.2 D D D D D ~ DOD D D Page 1 of 2 FORM ES-401-1 TOPIC: Flow indication Lights and alarms ~~o;~ ~~fi~~~tsl> Ability to verify that the alarms are consistent with the plant conditions. RMCS: Plant-Specific Rapid vessel depressurizations Maintenance of adequate pool level core modifications/alterations Main turbine eccentricity Applicable component cooling water system: Plant-

  • .. Il Specific (e..g ') Dre.uR-Rre.. :Puvwr ~

~'~ ~~~~w~~~) Nuclear boiler instrumentation 4/29/2009 1 :47 PM ES-401, REV 9 (RO) T2G2 BWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 201 001 K5.02 CRD Hydraulic 2.6 2.6 0 0 0 0 ~ 0 0 0 0 0 0 202001A3.04 Recirculation 3.2 3.1 0 0 0 0 0 0 0 0 ~ 0 0 202002K2.02 Recirculation Flow Control 2.6 2.6 0 ~ 0 0 0 0 0 0 0 0 0 204000G2.4.46 RWCU 4.2 4.2 0 0 0 0 0 0 0 0 0 0 ~ 214000K1.04 RPIS 3.2 3.2 ~ 0 0 0 0 0 0 0 0 0 0 216000A2.10 Nuclear Boiler Inst. 3.3 3.5 0 0 0 0 0 0 0 ~ 0 0 0 233000K4.06 Fuel Pool Cooling/Cleanup 2.9 3.2 0 0 0 ~ 0 0 0 0 0 0 0 234000K3.04 Fuel Handling Equipment 2.9 3.8 0 0 ~ 0 0 0 0 0 0 0 0 241000A1.24 ReactorlTurbine Pressure Regulator 2.6 2.7 0 0 0 0 0 0 ~ 0 0 0 0 FORM ES-401-1 TOPIC: Flow indication Lights and alarms Ability to verify that the alarms are consistent with the plant conditions. RMCS: Plant-Specific Rapid vessel depressurizations Maintenance of adequate pool level core modifications/alterations Main turbine eccentricity .---------------------------------------------------------~--~=-~~~--~~~------~--~------~--~~----- ?>36000M.02 Fire Protection 2.5 2.5 0 0 0 0 0 0 0 0 0 ~ 0 Applicable component cooling water system: Plant-Specific (e..g') D/'t,sve-h're.--PUWtf ~ J.e.J,i~ ~D~ ~~ wi~ Y1~) Nuclear boiler instrumentation 28i;002K6.08 Reactor Vessel Internals 2.9 3.2 0 0 0 0 0 ~ 0 0 0 0 0 Page 1 of 2 4/29/2009 1:47 PM

ES-401, REV 9 (Rc>> T2G2 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC: RO SRO 290003A1.04 Control Room HVAC 2.5 2.8 D D D D D D ~ D D D D Control room pressure Page 2 of 2 4/29/2009 1 :47 PM ES-401, REV 9 ( R D) T2G2 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC: RO SRO 290003A1.04 Control Room HVAC 2.5 2.8 D D D D D D ~ D D D D Control room pressure Page 2 of 2 4/29/2009 1 :47 PM

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Date of Exam: Category KIA # Topic IR

1.

2.1. Conduct of Operations 2.1.-- 2.1. 2.1. 2.2.

2.

2.2. Equipment Control 2.2. --~ 2.2.- 2.3. '

3.

2.3. Radiation Control 2.3. 2.3. 2.3. 2.4.

4.

2.4. Emergency 2.4. Procedures I Plan 2.4. 2.4. 2.4. Subtotal Tier 3 Point Total -yo ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: /1x+tb.. Date of Exam: (}d/N()v' :::<.OCJ1 Category KIA # Topic ,,_RO ) ..cu::>.=.r>o IR IR 2.1.11 V(/&/r1/J2 rep cn;( 's; R3,q

1.

2.1. b rn aA/~.e C/;~f) clu/L<~;': i:Cj' 7rtiYPc 1;;;:1.1: S ~3,g Conduct 2.1. Z &rnJlA'M~Je ac4j\\1i1:i-{~[ z57S' U":!y,,.l?'rJ!i}C; R34 of Operations f 2.1.- 2.1.-' 2.1.- Subtotal I(j) 2.2. I PeA~ff7;Jv;'t p n:; ':::+tVctt*,fP p nrl.ecfAA/~.:L '1c-R -'0 2.2.31 /).{'/1C/J/'/CI:)~2 ~yzJ?<tl,h/r/"j /a (h{t; i(:J'$~, /' :['l 1<3,0

2.

2.2.44 Pvt.j(,.~ <p,tc4 ~~ trJ;A1 f ~7r":eiCi!/,AI,acvr.S' P, 4, ~ Equipment I Control 2.2.- 2.2.- ( 2.2.- Subtotal (1) 2.3. ! 3 ?vr,/sv,J-f,uIJje fYt, t'!?!£;,r{(J;)t,it&.O jJ F',;:>:c:;'>r. ~ x3,4 2.3. r: A?! /1 fI' cJ,1 YLa.e f//lAJ;'a:::f:';\\1 (; /rJ.'Fy1 ~} ~:~j:::c;:,;;,<,." /?):Jl i 1

3.

2.3. Radiation Control 2.3. 2.3. 2.3. Subtotal (9;) 2.4. :2c, F.~ 16 r 14 11c:J,~, r {&'i' tl//{( Wi f/11.::(S AS,/

4.

2.4.*1~r ~ f//udi 11//t:;~{) f"'~~ tTfi,1' j<'c;:!:,'Jir/:: (i11?f4#"i) f.?4?> Emergency 2.4. Procedures / Plan 2.4. 2.4. 2.4. Subtotal (.2) Tier 3 Point Total /D 00) -=r-(

ES-401, REV 9 KA NAME / SAFETY FUNCTION: G2.1.17 Conduct of operations G2.1.6 Conduct of operations G2.1.8 Conduct of operations G2.2.1 Equipment Control G2.2.37 Equipment Control G2.2.44 Equipment Control G2.3.13 Radiation Control G2.3.5 Radiation Control G2.4.26 Emergency Procedures/Plans G2.4.49 Emergency Procedures/Plans T3 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.9 4.0 D D D D D D D D D D ~ 3.8 4.8 D D D D D D D D D D ~ 3.4 4.1 D D D D D D D D D D ~ 4.5 4.4 D D D D D D D D D D ~ 3.6 4.6 D D D D D D D D D D ~ 4.2 4.4 D D D D D D D D D D ~ 3.4 3.8 D D D D D D D D D D ~ 2.9 2.9 D D D D D D D D D D ~ 3.1 3.6 D D D D D D D D D D ~ 4.6 4.4 D D D D D D D D D D ~ Page 1 of 1 FORM ES-401-1 TOPIC: Ability to make accurate, clear and concise verbal reports. Ability to manage the control room crew during plant transients. Ability to coordinate-p-ersonnel activities outside the control room. Ability to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity. Ability to determine operability and/or availability of safety related equipment Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions Knowledge of radiological safety procedures pertaining to licensed operator duties Ability to use radiation monitoring systems Knowledge of facility protection requirements including fire brigade and portable fire fighting equipment usage. Ability to perform without reference to procedures those actions that require immediate operation of system components and controls. 5/6/2009 6:20 AM ES-401, REV 9 KA NAME / SAFETY FUNCTION: G2.1.17 Conduct of operations G2.1.6 Conduct of operations G2.1.B Conduct of operations G2.2.1 Equipment Control G2.2.37 Equipment Control G2.2.44 Equipment Control G2.3.13 Radiation Control G2.3.5 Radiation Control G2.4.26 Emergency Procedures/Plans G2.4.49 Emergency Procedures/Plans T3 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.9 4.0 0 0 0 0 0 0 0 0 0 0 Ii'l 3.8 4.8 0 0 0 0 0 0 0 0 0 0 Ii'l 3.4 4.1 0 0 0 0 0 0 0 0 0 0 Ii'l 4.5 4.4 0 0 0 0 0 0 0 0 0 0 Ii'l 3.6 4.6 0 0 0 0 0 0 0 0 0 0 Ii'l 4.2 4.4 0 0 0 0 0 0 0 0 0 0 Ii'l 3.4 3.8 0 0 0 0 0 0 0 0 0 0 Ii'l 2.9 2.9 0 0 0 0 0 0 0 0 0 0 Ii'l 3.1 3.6 0 0 0 0 0 0 0 0 0 0 Ii'l 4.6 4.4 0 0 0 0 0 0 0 0 0 0 Ii'l Page 1 of 1 FORM ES-401-1 TOPIC: Ability to make accurate, clear and concise verbal reports. Ability to manage the control room crew during plant transients. Ability to coordinate-personnel activities outside the control room. Ability to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity. Ability to determine operability and/or availability of safety related equipment Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions Knowledge of radiological safety procedures pertaining to licensed operator duties Ability to use radiation monitoring systems Knowledge of facility protection requirements including fire brigade and portable fire fighting equipment usage. Ability to perform without reference to procedures those actions that require immediate operation of system components and controls. 5/6/2009 6:20 AM

ES-401 2 Form ES-401-1 ES-401 BWR Examination Outline Form ESA01-1 E;""'-~-"'J and_Abnormal Plant Evolutions - Tier 1/Group 1 ~ ~ ~ ~ E/APE # I Name I Safety Function KIA Topic(s) IR 295001 Partial or Complete Loss of Forced /1£ I~' v Core Flow Circulation I 1 & 4 t1' 5.00 l ~il A Ql ~ '4-j 295003 Partial or Complete Loss of AC I 6 v 295004 Partial or Total Loss of DC Pwr 16

', IS ;5
215 ()()4*~' ;Z, /. ;':3 1~:44

,/' 295005 Main Turbine GeneratorIrip I 3 j~% .::: ;;?f 5~ () () s:~ A-i; ;l..,;'1 ;;!. i;5~:l 295006 SCRAM I 1 ~- E~i! 295016 Control Room Abandonment! 7 295018 Partial or Total Loss of CCW I 8 v' 295019 Partial or Total Loss of Inst. Air 18 IS' ;;;'1 [,{' t'! filA ;;.',1,1;,2-1(3,'? 295021 Loss of Shutdown Cooling I 4 295023 Refueling Acc I 8 295024 HighDrywell Pressure I 5 i"'" 295025 High Reactor Pressure I 3 295026 Suppression Pool High Water i'e Temp. I 5 295027 High Containment Tb"'fJ"rature I 5

  • ..*.,~ i,',

295028 High Drywell I ""'fJ",rature I 5 v/ 295030 Low SL Pool Wtr Lvi 15 it ~l. iS~';:FfS* 0 3* t) GJ..,. l, ;20 I;:;'i",, )// 295031 Reactor Low Water Level I 2 1;5,;n,<; '31 <1 2, L, 41-1;0: 1;tl 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown I 1 295038 High Off-site Release Rate I 9 ~ 600000 Plant Fire On Site I 8 v 700000 Generator Voltage and Electric Grid ~.~ Ii )$ ,£{

S3!t.~

Disturbances I 6 I,~i~ ,"', Ii}' i"iJ I',.: I KIA Category Totals: E Gro" Po;"lTol" -~ ES-401 2 Form ES-401-1 ES-401 BWR Examination Outline ~ Form E'",n1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 f ,SRO. E/APE # / Name / Safety Function K K K A A G KIA Topic(s) IR 1 2 3 1 2 v 295001 Partial or Complete Loss of Forced

3

$;215 ()O I,1\\ A O!, )f'

3,1 Core Flow Circulation / 1 & 4 295003 Partial or Complete Loss of AC / 6 v

295004 Partial or Total Loss of DC Pwr /6 ,s S ;)15&O1-~:2, /,;l:J <£:44- ,/ 295005 Main Turbine Generator Trip / 3 t2l {} ;;. q S"f'lt) 5"' Ii It ;;;;, C';;;t.

f;1.,7 295006 SCRAM / 1 295016 Control Room Abandonment / 7 295018 Partial or Total Loss of CCW /8

( ,$ C21'5N f AA.<, 0;; r:3,? v 295019 Partial or Total Loss of Ins!. Air /8 ? 295021 Loss of Shutdown Cooling / 4 295023 Refueling Acc / 8 295024 High Drywell Pressure / 5 295025 High Reactor Pressure /3 ( 295026 Suppression Pool High Water Temp. / 5 295027 High Containment Temperature / 5 295028 High Drywell Temperature / 5 ,/" 295030 Low Suppression Pool Wtr Lvi /5 ~ ~ tf--'()';;f)~- /;)() .]"';;'

> J

<>I, S1,' V 295031 Reactor Low Water Level / 2 IS

01.

~ 61

5 "q5'O~' t ~ 2,- 4-1*

",c., f, 4.4-295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown / 1 295038 High Off-site Release Rate / 9 600000 Plant Fire On Site / 8 t.// 700000 Generator Voltage and Electric Grid ~

}, 7 f)()OoO A A';(, (J 3

~3!~ Disturbances / 6 KIA Category Totals: 4 3 Group Point Total: -@Ii) (

ES-401, REV 9 KA NAME / SAFETY FUNCTION: 295001AA2.04 Partial or Complete Loss of Forced Core Flow Circulation 1 1 & 4 295004G2.1.23 Partial or Total Loss of DC Pwr 1 6 295005AA2.02 Main Turbine Generator Trip 1 3 295019AA2.02 Partial or Total Loss of Inst. Air 1 8 295030G2.1.20 Low Suppression Pool Wtr Lvi 15 295031 G2.2.44 Reactor Low Water Levell 2 700000AA2.03 Generator Voltage and Electric Grid Distrurbancecs SRO T1G1 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.0 3.1 D D D D D D D ~ D D D 4.3 4.4 D D D D D D D D D D ~. 2.4 2.7 D D D D D D D ~ D D D 3.6 3.7 D D D D D D D ~ D D D 4.6 4.6 D D D D D D D D D D ~ 4.2 4.4 D D D D D D D D D D ~ 3.5 3.6* D D D D D D D ~ D D D Page 1 of 1 FORM ES-401-1 TOPIC: Individual jet pump flows: Not-BWR-1 &2............... Ability to perform specific system and integrated plant procedures during all modes of plant operation. Turbine vibration..................................... Status of safety-related instrument air system loads (see AK2.1 - AK2.19).................................. Ability to execute procedure steps. Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions Generator current outside the generator capability curve 4/29/2009 1 :47 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION: 295001AA2.04 Partial or Complete Loss of Forced Core Flow Circulation 1 1 & 4 295004G2.1.23 Partial or Total Loss of DC Pwr 1 6 295005AA2.02 Main Turbine Generator Trip 1 3 295019AA2.02 Partial or Total Loss of Inst. Air 1 8 295030G2.1.20 Low Suppression Pool Wtr Lvi 15 295031 G2.2.44 Reactor Low Water Levell 2 700000AA2.03 Generator Voltage and Electric Grid Distrurbancecs SRO T1 G1 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 3.0 3.1 0 0 0 0 0 0 0 ~ 0 0 0 4.3 4.4 DDDDDDDDDD~ 2.4 2.7 DDDDDDD~DDD 3.6 3.7 DDDDDDD~DDD 4.6 4.6 DDDDDDDDDD~ 4.2 4.4 DDDDDDDDDD~ 3.5 3.6 0 0 0 0 0 0 0 ~ 0 0 0 Page 1 of 1 FORM ES-401-1 TOPIC: Individual jet pump flows: Not-BWR-1&2............... Ability to perform specific system and integrated plant procedures during all modes of plant operation. Turbine vibration..................................... Status of safety-related instrument air system loads (see AK2.1 - AK2.19).................................. Ability to execute procedure steps. Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions Generator current outside the generator capability curve 4/29/2009 1:47 PM

ES-401 3 Form ES-401-1 ES-401 BWR Examination Outline ~ ~/~~ Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 EIAPE # I N,me I S,fely '",cl,,, KKK I KIA Toplc(,) IR 1 2 3 1', 295002 Loss of Main Condenser Vac /3 I,:, /' 295007 High Reactor Pressure / 3 {!} O{, f5'(Y'O ~7 !lAd? ' () I ~¢,/ 295008 High Reactor Water Level / 2 295009 Low Reactor Water Level / 2 295010 High Drywell Pressure / 5 295011 High Containment Tel'1l[li 5 ,/ 295012High DI}'\\'IIJlIITemperature / 5 i~ ',"I "',. 1"" / I ~q$"{} !,',~,,-" -;1. Ii

54..2 v' 295013 High Su Pool Temp. / 5

$ ;(1()' 0/3,4A (2.01 '$.~1" /,I 295014 Inadvertent D. .i+, Addition / 1 295015 Incomplete SCRAM /1 295017 High Off-site Release Rate / 9 'i 295020 Inadvertent Cont. Isolation / 5 & 7 295022 Loss of CRD Pumps /1 L~ 295029 High Suppression Pool Wtr Lvi / 5 '~; 'J 295032 High Secondary Containment ~' Area Temperature /5 295033 High Secondary Containment 'i Area Radiation Levels / 9 iii 295034 Secondary Containment Ventilation High Radiation / 9 295035 Secondary Containment High ,/i Differential Pressure / 5

'i 295036 Secondary Containment High I~f\\

Sump/Area Water Level / 5 500000 High CTMT fUI UYCI Conc. / 5 I Iii I*} Itl' l,>, KIA _Category Point Totals: II mop PolotTolel, fit:) ES-401 3 Form ES-401-1 ES-401 BWR Examination Outline ~ Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 ~/

SRO,

""~-- E/APE # / Name / Safety Function K K K A A G K/A Topic(s) IR 1 2 3 1 2 295002 Loss of Main Condenser Vac /3 /' 295007 High Reactor Pressure / 3 ,5 PCJ.'fSth?7AA;) IN {4'; 295008 High Reactor Water Level / 2 295009 Low Reactor Water Level / 2 295010 High Drywell Pressure /5 295011 High Containment Temp / 5 ,/ 295012 High Drywell Temperature / 5 (~ S C2 q 6'0 !;.{ G::( 4 li I, F f iiU

54,2 v 295013 High Suppression Pool Temp, / 5 S

/~,21'6 DI3 AA'pt.OI '[14, f) 295014 Inadvertent Reactivity Addition /1 295015 Incomplete SCRAM / 1 295017 High Off-site Release Rate / 9 295020 Inadvertent Cont. Isolation / 5 & 7 ( 295022 Loss of CRD Pumps / 1 295029 High Suppression Pool Wtr Lvi / 5 295032 High Secondary Containment Area Temperature /5 295033 High Secondary Containment Area Radiation Levels / 9 295034 Secondary Containment Ventilation High Radiation / 9 295035 Secondary Containment High Differential Pressure / 5 295036 Secondary Containment High Sump/Area Water Level /5 500000 High CTMT Hydrogen Conc, /5 KIA Category Point Totals: 0<- { Group Point Total: .-rJ;3} (

ES-401, REV 9 SRO T1G2 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC: RO SRO 295007AA2.01 High Reactor Pressure 1 3 4.1 4.1 D D D D D D D ~ D D D Reactor pressure...................................... 295012G2.4.11 High Drywell Temperature 1 5 4.0 4.2 D D D D D D D D D D ~ Knowledge of abnormal condition procedures. 295013AA2.01 High Suppression Pool Temp. 15 3.8 4.0 D D D D D D D ~ D D D Suppression pool temperature.......................... Page 1 of 1 4/29/2009 1 :47 PM ES-401, REV 9 SRO T1G2 BWR EXAMINATION OUTLINE FORM ES-401-1 KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G TOPIC: RO SRO 295007AA2.01 High Reactor Pressure 1 3 4.1 4.1 D D D D D D D ~ D D D Reactor pressure...................................... 295012G2.4.11 High Drywell Tem perature 1 5 4.0 4.2 D D D D D D D D D D ~ Knowledge of abnormal condition procedures. 295013AA2.01 High Suppression Pool Temp. 1 5 3.8 4.0 D D D D D D D ~ D D D Suppression pool temperature.......................... Page 1 of 1 4/29/2009 1 :47 PM

ES-401 4 Form ES-401-1 ES-401 BWR Examination o~~_~(~ Form ES-401-1 Plant Systems - Tier 2/Grou 0 1 System # / Name ~ ~ ~ ~ ~ ~ ~ ~ ~ i'b KIA Topic(s) IR 203000 RHR/LPCI: Injection I***. Mode I:" 'e 205000 Shutdown Cooling 1'1

t5~"

Ii" 206000 HPCI 1:. 207000 Isolation (Emergency) I~' L;~ Condenser 209001 LPCS I~I "0'1' 209002 HPCS I:'~i '.~ ,/ 211000SLC F.**'.*. ** '$ S C2 ! I () Cit) C-1 7~} -po,,!

4,1..1 1"';7

4!.~ f i!'Jl~~"1:f Ij~ 212000 RPS

-.l.

v' 2150031RM li~~

s *,t,,;(1 lS-{},93 L:;; ;f', /, ;2 'J'

$~O 215004 Source Range Monitor ~,~, ( 215005 APRM / LPRM ~'J,. ~~ *.*

  • .l.

217000 RCIC t *.' 218000 ADS

\\

t! 223002 PCIS/Nuclear Steam '.~~. Supply Shutoff 239002 SRVs i~~'? i ; I 259002 Reactor Water Level Control v 261000 SGTS '1,;5 ocl;" I () 0 0 A;Z ' l;:Z I,S34 262001 AC Electrical I; *. ~ Distribution ~ 262002 UPS (AC/DC)

(i.

263000 DC Electrical .,..... ~. 1.< Distribution I~;~' ,/ 264000 EDGs ~! ~,r:!;,,:{ 64 (l(N} 101;::7, (;;1

4, l 300000 Instrument Air

"~ ~~7£ v'" 400000 Component Cooling ie"~ (54J){}lJ,,() It;;, 153,t) Water I: if', I KIA Category Point Totals: m Grn"p Po;otTota; ( ES-401 4 Form ES-401-1 ES-401 BWR Examination OUtlin~~ Form PI C', '=. System # / Name K K K K K K A A A A G KIA Topic(s) IR 1 2 3 4 5 6 1 2 3 4 203000 RHR/LPCI: Injection Mode 205000 Shutdown Cooling 206000 HPCI 207000 Isolation (Emergency) Condenser 209001 LPCS 209002 HPCS v 211000 SLC is.:f ell! () ?o~ ~ '1 ~l1: ( d.o/, $4,0 212000 RPS V 2150031RM IS ~~~ -'G;;(

2'/

'iD rx:!':;;' ()03.,I. : 1;;1,0 215004 Source Range Monitor ( 215005 APRM / LPRM 217000 RCIC 218000 ADS 223002 PCIS/Nuclear Steam Supply Shutoff 239002 SRVs 259002 Reactor Water Level Control v 261000 SGTS {3

5;(&/DV o !';?,!;;].

t,24 262001 AC Electrical Distribution 262002 UPS (AC/DC) 263000 DC Electrical Distribution 264000 EDGs

5 S~64C1(!O A,;),l?j
iiI 300000 Instrument Air

/' 400000 Component Cooling ~

4(){)O(JO A;;(, O,;}_

.53,1: Water ? KIA Category Point Totals: 3

2 Group Point Total

.2fJ/5)

ES-401, REV 9 KA NAME / SAFETY FUNCTION: 211000G2.2.44 SLC 215003G2.1.27 IRM 261000A2.12 SGTS 264000A2.09 EDGs 400000A2.02 Component Cooling Water SRO T2G1 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4,KS K6 A1 A2 A3 A4 G RO SRO 4.2 4.4 D D D D D D D D D D ~ 3.9 4 D D D D D D D D D D ~ 3.2 3.4 D D D D D D D ~ D D D 3.7 4.1 D D D D D D D ~ D D D 2.8 3.0 D D D D D D D ~ D D D Page 1 of 1 FORM ES-401-1 TOPIC: Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions Knowledge of system purpose and or function. High fuel pool ventilation radiation: Plant-Specific. Loss of A.C. power High/low surge tank level 4129/2009 1 :47 PM ES-401, REV 9 SRO T2G1 BWR EXAMINATION OUTLINE KA NAME / SAFETY FUNCTION: IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 211000G2.2.44 SLC 4.2 4.4 D D D D D D D D D D ~ 215003G2.1.27 IRM 3.9 4 D D D D D D D D D D ~ 261000A2.12 SGTS 3.2 3.4 D D D D D D D ~ D D D 264000A2.09 EDGs 3.7 4.1 D D D D D D D ~ D D D 400000A2.02 Component Cooling Water 2.8 3.0 D D D D D D D ~ D D D Page 1 of 1 FORM ES-401-1 TOPIC: Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions Knowledge of system purpose and or function. High fuel pool ventilation radiation: Plant-Specific. Loss of A.C. power High/low surge tank level 4/29/2009 1 :47 PM

ES-401 5 Form ES-401-1 ES-401 BWR Examination Outline 'I!~) Form PI; Int ~ ystems -JJ~. ~/Gn~ System # / Name ~ ~ ~ ~ ~ ~ ~ ,'I ~ KIA Topic(s) IR '2~ 4 201001 CRD Hydraulic 201002 RMCS (,' I--I-- 201003 Control Rod and Drive 1< Mechanism 201004 RSCS ,;>i 201005 RCIS 201006 RWM \\,/ 202001 Rpr;rr"l"t;fJn ~, 202002 Rp";rr"I"tion Flow Control !ill:,;: 204000 RWCl,L ~> 214000 RPIS I~f~ 215001 raversmg In-core Probe ~: Ie!; 215002 RBM IS~.\\:*i v 216000 Nuclear Boiler Ins!. Ii. ",j f1 a lh C;NJf;1 /4;{. /4 ,,::?,9 Ii 219000 RHRlLPCI: Torus/Pool Cooling I", Mode 223001 Primar),CTMT ~Aux. ---.~, 226001 RHRlLPCI: CTMT Spray Mode 1i:.;'JI 230000 RHRlLPCI: Torus/Pool Spray J Mode 233000 Fuel PJlClL Cooling/Cleanup ,/ 2340()0 Fuel H?_ndling Equipment ~X,, ",:/.: Ii :;.~.,; * ';,!.",' I~~ "", ~l,8 _It'? 2~( 3.4-{)O lJ G/ /;Z, ;;,:1.' 5-

1i.2.

239001 Main and Reheat Steam I~[~ 239003 MSIV Leakage Control Im~i 241000 ReactorlTurbine Pressure [;~ ReglJ@.tor 245000 Main Turbine Gen. / Aux. I"".*,,' 256000 Reactor Condensate ',;5 ~.., 259001 Reactor Feedwater r'J~'; ~ 268000 R"rlw""jF! I:'*~-, '1 271000 Offgas ~ v~ 272000 Radiation Monitoring ~~S,;z?.'J t'oo A;'!, ij ~t3,7 286000 Fire 288000 Plant v' "". i ii, li~ 290001 CTMT ,i! 1::11 290003 Control Room HVAC fF 290002 Reactor Vessel Internals

'r KIA

-T. I!:.~ I: 1'If3) ES-401 5 Form ES-401-1 ES-401 BWR Examination Outline /~) Form ES-401-1 Plant Systems - Tier 2/Group 2 1'R1~ / R System # / Name K K K K K K A A A A G KIA Topic(s) IR 1 2 3 4 5 6 1 2 3 4 201001 CRD Hydraulic 201002 RMCS 201003 Control Rod and Drive Mechanism 201004 RSCS 201005 RCIS 201006 RWM 202001 Recirculation 202002 Recirculation Flow Control 204000 RWCU 214000 RPIS 215001 Traversing In-core Probe 215002 RBM V 216000 Nuclear Boiler Ins!. S rt!Zlb~t)~ A;?,I,f $,;;,1 219000 RHRlLPCI: Torus/Pool Cooling Mode ( 223001 Primary CTMT and Aux. 226001 RHRlLPCI: CTMT Spray Mode 230000 RHRlLPCI: Torus/Pool Spray Mode 233000 Fuel Pool Cooling/Cleanup V 234000 Fuel Handling Equipment t ;S 0( 31-ootJG.0? :1. ;),:) ~ 1,.2_ 239001 Main and Reheat Steam 239003 MSIV Leakage Control 241000 ReactorlTurbine Pressure Regulator 245000 Main Turbine Gen. / Aux. 256000 Reactor Condensate 259001 Reactor Feedwater 268000 Radwaste 271000 Offgas ./ 272000 Radiation Monitoring t5 $,;; '7 :l O()O AO? 1/ /,3*7 286000 Fire Protection 288000 Plant Ventilation 290001 Secondary CTMT 290003 Control Room HVAC 290002 Reactor Vessel Internals ~ I Group Point Total: ( \\

ES-401, REV 9 KA NAME / SAFETY FUNCTION: 216000A2.14 Nuclear Boiler Inst. 234000G2.2.25 Fuel Handling Equipment 272000A2.11 Radiation Monitoring SRO T2G2 BWR EXAMINATION OUTLINE IR K1 K2 K3"K4 K5 K6 A1 A2 A3 A4 G RO SRO 2.9 2.9 D D D D D D D ~ D D D 3.2 4.2 D D D D D D D D D D ~ 3.4 3.7 D D D D D D D ~ D D D Page 1 of 1 FORM ES-401-1 TOPIC: Recirculation flow: Design-Specific Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits. Leakage andlor breaks from contaminated systems to atmosphere or to other process systems 4/29/2009 1 :47 PM ES-401, REV 9 KA NAME / SAFETY FUNCTION: 216000A2.14 Nuclear Boiler Inst. 234000G2.2.25 Fuel Handling Equipment 272000A2.11 Radiation Monitoring SRO T2G2 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 2.9 2.9 D D D D D D D Ii'l D D D 3.2 4.2 D D D D D D D D D D Ii'l 3.4 3.7 D D D D D D D Ii'l D D D Page 1 of 1 FORM ES-401-1 TOPIC: Recirculation flow: Design-Specific Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits. Leakage andlor breaks from contaminated systems to atmosphere or to other process systems 4/29/2009 1 :47 PM

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 II tl J ,t~ Date of Exam: ()~'r/A/ ;1 iF' ,;;; tJ~)r Category KIA # Topic -Re-- cSRO~Only IR IR 2.1. ;;;:3 rVt<lf,i CFt $qf;-fC,IV'tM!P': i/' i'~;; /<c..,,II.,'(;;rt!!FC':; 1$4,/

1.

2.1.37 12'":~i~'.("J8 ;""8, :(",<5 YJ!1.,tV',,(!A A!e' * '41.t..~i":;( Is4d~ i ,4 Conduct 2.1.- of Operations 2.1.'-- 2.1.--- 2.1. ~ 1:4c:j Subtotal 2.2. I f'r.e .. S:-(;z/l't1A.4J<,p,A,*,*t/* A'};",i~41(j.", 2.2.J3 n?rr..,w*:k:J !t:rl t~l5~ (11:;i1/:' j,1,af de C;jj \\r*c::. LC/),j 1,:s4il~

2.

2.2. -. !I G Equipment 2.2. '-- Control 2.2.- 2.2. '- Subtotal 2.3. 1,t<a.:::ei:;;lc>z;rtC<!lP ,C:;;~,(:~,~;t::t !Pr;rci{"~*:C/;'A!.;jL

3,8

',I U 2.3.-

3.

2.3.-- Radiation Control 2.3.-- 2.3.... - 2.3. --.. Subtotal I;;:':<i;l;:' 2.4.37 LiJ1fio 1~1,f "~l/f:;t~th'd,rul~l rdlA;/;:4;:,vt~~ E'. P/;;:l ft;1' I,~! '4~ l

4.

2.4.4l £";j fAl;:<1..

  • ll1,n'J;/urt~;tJ* t (;id ~L,tJ'~it:p~.:ft,.Jj"'~J l,s4, I' Emergency 2.4.--

Procedures I Plan 2.4. "-.-. 2.4. --- 2.4.- Subtotal B-Tier 3 Point Total ) ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Hal eli Date of Exam: OC,1 / iii () if' ('1 (I() '1" Category KIA # Topic -Re-- (sRO-Only IR IR 2.1. ;;:(3 flf1etjOY 9-vrfj*te-'V>t I!A' ~'k'&'1vr;fS /'~l/~!:i!£}(5 $4,/

1.

2.1. 37 tJ,;;t~~ofij't' t'L., j)/'4i,tf,/V!0'1 if~CPi [1:::( 1:;4,(;' f Conduct 2.1.- of Operations 2.1.- 2.1.- 2.1. ~ Subtotal ((}~ 2.2. I rre. 5-1;v"d/44fJ /pAiTU cJt-VW.t- ,s4~1 2.2.J3 Phr[~<k2 fin v . tA ';:[c:tl LCi):

rv{5"Y1 t my i yt Ie

~. Is4,b

2.

2.2. -. 1/ a Equipment 2.2. - Control 2.2.- ( 2.2. - Subtotal (;)) 2.3. 13 l<aC£;!)u,2YiI:vjJ Citr)tj Pnr: c,:t;a/Lf-~ eI?8 ?,""" ' v ~ U 2.3.--

3.

2.3.- Radiation Control 2.3.- 2.3.- 2.3.- Subtotal (V 2.4.37 LiJllM &,(aif4liunA'f/ ?:~,u~:,i /i,~ I~~' P/r'? n $4,}

4.

2.4.41 v ",,--!O~ -f/trecsUds t ei&/hck?<fi;,lirlS f!,d./ 1Jfft'2' Emergency 2.4.- Procedures I Plan 2.4.- 2.4.~ 2.4.- Subtotal

0)

Tier 3 Point Total '(7 (7) (

ES-401, REV 9 KA NAME / SAFETY FUNCTION: G2.1.28 Conduct of operations G2.1.37 Conduct of operations G2.2.1 Equipment Control G2.2.23 Equipment Control G2.3.13 Radiation Control G2.4.37 Emergency Procedures/Plans G2.4.41 Emergency Procedures/Plans SRO T3 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 KS K6 A1 A2 A3 A4 G RO SRO 4.1 4.1 D D D D D D D D D D ~ 4.3 4.6 D D D D D D D D D D ~ 4.S 4.4 D D D D D D D D D D ~ 3.1 4.6 D D D D D D D D D D ~ 3.4 3.8 D D D D D D D D D D ~ 3.0 4.1 D D D D D D D D D D ~ 2.9 4.6 D D D D D D D D D D ~ Page 1 of 1 FORM ES-401-1 TOPIC: Knowledge of the purpose and function of major system components and controls. Knowledge of procedures, guidelines or limitations associated with reactivity management Ability to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity. Ability to track Technical Specification limiting conditions for operations. Knowledge of radiological safety procedures pertaining to licensed operator duties Knowledge of the lines of authority during implamentation of an emergency plan. Knowledge of the emergency action level thresholds and classifications. 4/29/2009 1 :47 PM ES-401, REV 9 KA NAME / SAFETY' FUNCTION: G2.1.28 Conduct of operations G2.1.37 Conduct of operations G2.2.1 Equipment Control G2.2.23 Equipm ent Control G2.3.13 Radiation Control G2.4.37 Emergency Procedures/Plans G2.4.41 Emergency Procedures/Plans SRO T3 BWR EXAMINATION OUTLINE IR K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G RO SRO 4.1 4.1 0 0 0 0 0 0 0 0 0 0 ~ 4.3 4.6 0 0 0 0 0 0 0 0 0 0 ~ 4.5 4.4 0 0 0 0 0 0 0 0 0 0 ~ 3.1 4.6 0 0 0 0 0 0 0 0 0 0 ~ 3.4 3.8 0 0 0 0 0 0 0 0 0 0 ~ 3.0 4.1 0 0 0 0 0 0 0 0 0 0 ~ 2.9 4.6 0 0 0 0 0 0 0 0 0 0 ~ Page 1 of 1 FORM ES-401-1 TOPIC: Knowledge of the purpose and function of major system components and controls. Knowledge of procedures, guidelines or limitations associated with reactivity management Ability to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity. Ability to track Technical Specification limiting conditions for operations. Knowledge of radiological safety procedures pertaining to licensed operator duties Knowledge of the lines of authority during implamentation of an emergency plan. Knowledge of the emergency action level thresholds and classifications. 4/29/2009 1 :47 PM

ES-301 Facility: HATCH Examination Level: RO X Administrative Topic (see Note) Conduct of Operations Conduct of Operations Equipment Control Equipment Control Radiation Control Emergency ProcedureslPlan Emergency Procedures/Plan NRC Draft Administrative Topics Outline Form ES-301-1 Date of Examination: Oct 262 2009 SRO X Operating Test Number: 2009-302 Type Describe activity to be performed Code* D;R Determine-ifa Recirc Pump Quick Restart is Allowed 2.1.20 (4.6/4.6)ALL I D,R Determine Minimum Crew Staffing SRO Only 2.1.4 (3.3/3.8) n,R Determine Drywell Floor Drain Leak Rate 2.2.12 (3.7) ROOnly N,R Review/Approve Equipment Danger Tagout 2.2.13 (4.3) SRO Only N,R Evaluate a Radiation Work Permit (RWP) and Survey Map 2.3.7 (3.5/3.6) ALL D,R Perform a Prompt Offsite Dose Assessment 2.4.39 (3.9) RO Only D,R Determine a Protective Action Recommendation (PAR) 2.4.9 (4.0) SRO Only 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 (::s 3 for ROs; ::s 4 for SROs & RO retakes) (N)ew or (M)odified from bank (2: 1) (P)revious 2 exams (::s 1; randomly selected) ( ES-301 Facility: HATCH Examination Level: RO X r~ .allve; l.u!-,ic II ~~e;e; Note) Conduct of Operations Conduct of Operations Equipment Control Equipment Control Radiation Control Emergency ProcedureslPlan Emergency Procedures/Plan NRC Draft Administrative Topics Outline Form ES-301-1 Date of Examination: Oct 26,2009 SRO X Operating Test Number: 2009-302 Type Describe activity to be performed Code* D~R Determine if a Recirc Pump Quick Restart is Allowed 2.1.20 (4.6/4.6)ALL D,R Determine Minimum Crew Staffing SRO Only 2.1.4 (3.3/3.8) n,R Determine Drywell Floor Drain Leak Rate 2.2.12 (3.7) RO Only N,R Review/Approve Equipment Danger Tagout 2.2.13 (4.3) SRO Only N,R Evaluate a Radiation Work Permit (RWP) and Survey Map 2.3.7 (3.5/3.6) ALL D,R Perform a Prompt Offsite Dose Assessment 2.4.39 (3.9) RO Only D,R Determine a Protective Action Recommendation (PAR) 2.4.9 (4.0) SRO Only 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 (:S 3 for ROs; :S 4 for SROs & RO retakes) (N)ew or (M)odified from bank (~ 1) (P)revious 2 exams (:S 1; randomly selected)

ADMIN DRAFT JPM

SUMMARY

1. Determine if a Recirc Pump Quick Restart is Allowed Determines RPV saturation temperature from table - Critical Task Records Recirc suction temperature Records bottom head temperature Calculates delta T for loop to RPV - Critical Task Calculates delta T for bottom head and steam dome - Critical Task Reports to Shift Supervisor that Recirc can NOT be restarted - Critical Task
2. Determine Minimum Crew Staffing SRO ONLY Determines an HP is needed per Tech Specs - Critical Task Determine required action time/ time limit - Critical Task Determines staffing met per 30AC-OPS-003-0 Determines SO is needed per DI-OPS-8I-0501 - Critical Task Determines required action for missing SO - Critical Task.
3. Determine Drywell Floor Drain Leak Rate RO ONLY Record total leakage from meter Determine 24 hour leakage - Critical Task Determine 8 hour leakage-Critical Task Determine differential leakage-Critical Task
4. Review/Approve Equipment Danger Tagout SRO ONLY Determines incorrect sequence on tagout (component isolated before being electrically isolated) - Critical Task Determines component has incorrect noun name on tag - Critical Task Determines component has incorrect tagged position (opened instead of closed) -

Critical Task

5. Evaluate a Radiation Work Permit (RWP) and Survey Map Operator determines that lab coat, booties, and gloves are required when entering this area - Critical Task Operator determines the max stay time is 2 hours before the DAD alarms-Critical Task Operator determines that immediate exit and HP notification is required if DAD alarms-Critical Task Operator determines a dose of >.1 Remlhr (100 mrlhr) requires an HP brief.-

Critical Task 3 ( ADMIN DRAFT JPM

SUMMARY

1. Determine if a Recirc Pump Quick Restart is Allowed Determines RPV saturation temperature from table - Critical Task Records Recirc suction temperature Records bottom head temperature Calculates delta T for loop to RPV - Critical Task Calculates delta T for bottom head and steam dome - Critical Task Reports to Shift Supervisor that Recirc can NOT be restarted - Critical Task
2. Determine Minimum Crew Staffing SRO ONLY Determines an HP is needed per Tech Specs - Critical Task Determine required action time/ time limit - Critical Task Determines staffing met per 30AC-OPS-003-0 Determines SO is needed per DI-OPS-81-0501 - Critical Task Determines required action for missing SO - Critical Task
3. Determine Drywell Floor Drain Leak Rate RO ONLY Record total leakage from meter Determine 24 hour leakage - Critical Task Determine 8 hour leakage-Critical Task Determine differential leakage-Critical Task
4. Review/Approve Equipment Danger Tagout SRO ONLY Determines incorrect sequence on tagout (component isolated before being electrically isolated) - Critical Task Determines component has incorrect noun name on tag - Critical Task Determines component has incorrect tagged position (opened instead of closed) -

Critical Task

5. Evaluate a Radiation Work Permit (RWP) and Survey Map Operator determines that lab coat, booties, and gloves are required when entering this area - Critical Task Operator determines the max stay time is 2 hours before the DAD alarms-Critical Task Operator determines that immediate exit and HP notification is required if DAD alarms-Critical Task Operator determines a dose of >.1 Rem/hr (100 mrlhr) requires an HP brief.-

Critical Task 3 /

DRAFT JPM

SUMMARY

6. Perform a Prompt Offsite Dose Assessment RO ONLY Operator logs onto the MIDAS software - Critical Task Records the needed information - Critical Task Determines off-site dose rates and dose projections - Critical Task Determines duration of release - Critical Task Determines release is in progress and notifies SMIED - Critical Task Determines peak 1EDE greater than.057 mrthr and notifies SMIED - Critical Task
7. Determine a Protective Action Recommendation (PAR) SRO ONLY Determines the dose to the population is greater than 1 REM 1EDE and 5 REM CDE Thyroid Determines the dose at 5 miles and 10 miles is greater than 1 REM 1EDE and 5 REM CDE Thyroid Determines a PAR 3 is required - Critical Task Obtains 15 minute average wind direction - Critical Task Record affected zones - Critical Task Determine PAR is based on dose projections - Critical Task 4

(r ( DRAFT JPM

SUMMARY

6. Perform a Prompt Offsite Dose Assessment RO ONLY Operator logs onto the MIDAS software - Critical Task Records the needed information - Critical Task Determines off-site dose rates and dose projections - Critical Task Determines duration of release - Critical Task Determines release is in progress and notifies SMIED - Critical Task Determines peak TEDE greater than.057 mr/hr and notifies SMIED - Critical Task
7. Determine a Protective Action Recommendation (PAR) SRO ONLY Determines the dose to the population is greater than I REM TEDE and 5 REM CDE Thyroid Determines the dose at 5 miles and 10 miles is greater than 1 REM TEDE and 5 REM CDE Thyroid Determines a PAR 3 is required - Critical Task Obtains 15 minute average wind direction - Critical Task Record affected zones - Critical Task Determine PAR is based on dose projections - Critical Task 4

\\

NRC Draft ES-301 Control RoomlIn-Plant Systems Outline Form ES-301-2 Facility: HATCH Date of Examination: Oct 26,2009 Exam Level: RO X SRO-l X SRO-U Operating Test No.: 2009-302 Control Room Systems@ (8 for RO); (7 for SRO-l); (2 or 3fbr SRO-U, including 1 ESF) System / JPM Title TypeCode* Safety Function Normal Start of Recirc ASD A,D,L,M,S SF-l 202001 Recirc - System A4.01 (3.7/3.7) Restore RWL With RHRSW D,S SF-2. 295031 Reactor Low Water Level Al.08 (3.8/3.9) ED Using Head Vents M,S SF-3* 295025 High* Reactor Pressure Al.Ol (2.9/3.0) Roll the Main Turbine A,L,M,S SF-4 245000 Main Turbine Gen. A4.06 (2.712.6) Purge the Drywell with Air for Hydrogen Control D,S SF-5 500000 High CTMT Hydrogen Al.03 (3.4/3.2) Re-Energize Bus with Diesel Generator A,M,S SF-6 295003 Partial or Complete Loss of AC Al.02 (4.2/4.3) Rod Worth Minimizer Functional Test (RO ONLY) D,L,S SF-7 201006 Rod Worth Minimizer System A3.02 (3.5/3.4) Loss of Air Actions for Rx Bldg Ventilation A,N,S SF-8 295019 Partial or Total Loss of lnst. Air K2.08 (2.8/2.9) 1 ( NRC Draft ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: HATCH Date of Examination: Oct 26,2009 Exam Level: RO X SRO-I X SRO-U Operating Test No.: 2009-302 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF) System / JPM Title Type Code* Safety Function Normal Start of Recirc ASD A, D, L, M, S SF-l 202001 Recirc System A4.01 (3.7/3.7) Restore RWL With RHRSW D,S SF-2 295031 Reactor Low Water Level A1.08 (3.8/3.9) ED Using Head Vents M,S SF-3 295025 High Reactor Pressure A1.01 (2.9/3.0) ( Roll the Main Turbine A,L,M,S SF-4 245000 Main Turbine Gen. A4.06 (2.7/2.6) Purge the Drywell with Air for Hydrogen Control D,S SF-5 500000 High CTMT Hydrogen A1.03 (3.4/3.2) Re-Energize Bus with Diesel Generator A,M,S SF-6 295003 Partial or Complete Loss of AC A1.02 (4.2/4.3) Rod Worth Minimizer Functional Test (RO ONLY) D,L,S SF-7 201006 Rod Worth Minimizer System A3.02 (3.5/3.4) Loss of Air Actions for Rx Bldg Ventilation A,N,S SF-8 295019 Partial or Total Loss of Inst. Air K2.08 (2.8/2.9) ( 1 ~.: /;' \\

In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 Of 2 for SRO-U) Vent the Scram Air Header D,E,R SF-l 295015 Incomplete SCRAM K2.11 (3.5/3.:]) Locally Start 1B PSW Pump Breaker Without Control Power A,E,M SF 295004 Partial or Total Loss of DC A1.07 (3.3/3.3) Start RPS MG Set D SF-7 212000 Reactor Protection System A1.01 (2.812.9) All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

  • Type Codes Criteria for RO / SRO-I / SRO-U (A)ltemate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank S9/S8/S4 (E)mergency or abnormal in-plant 2:1/2:112:1 (EN)gineered safety featnre

- / - / 2:1 (control room system) (L)ow-Power / Shutdown 2:112:1/2:1 (N)ew or (M)odified from bank including l(A) 2:2/2:2/2:1 (P)revious 2 exams S 3 / S 3 / S 2 (randomly selected) (R)CA 2:1/2:1/2:1 (S)imulator 2 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) Vent the Scram Air Header D,E,R SF-l 295015 Incomplete SCRAM K2.11 (3.5/3)) Locally Start 1B PSW Pump Breaker Without Control Power A,E,M SF 295004 Partial or Total Loss of DC A1.07 (3.3/3.3) Start RPS MG Set D SF-7 212000 Reactor Protection System A1.01 (2.8/2.9) All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

  • Type Codes Criteria for RO 1 SRO-I 1 SRO-U (A)ltemate path 4-6/4-6/2-3 (C)ontrol room

( (D)irect from bank

9/
:;8/::;4 (E)mergency or abnormal in-plant
lJ::::: 11::::: 1 (EN)gineered safety feature 1 :::::1 (control room system)

(L)ow-Power 1 Shutdown

11:::::11:::::1 (N)ew or (M)odified from bank including l(A)
2/:::::2/:::::1 (P)revious 2 exams
3 1
:; 3 I::; 2 (randomly selected)

(R)CA

11:::::11:::::1 (S)imulator 2

SIMULATOR

1. Normal Start of Recirc ASD
  • 'Depress ASD fault reset DRAFT JPM

SUMMARY

Confirm ASD cooling normal Verify Suction Valve open Verify Reactor Water level Confirm ASD room cooler running Close Recirc Discharge Valve - Critical Task Start ASD - Critical Task ASD Cooling Annunciators Alarm Confirm ASD Shutdown Trip ASD Recirc Input Breaker - Critical Task

2. Restore RWL With RHRSW Verify RHR pumps stopped Verify 5 RHR valves closed Open RHR Inboard Injection Valve - Critical Task Open 2 RHRSW valves - each one a Critical Task Override RHRSW valve close logic - Critical Task Open RHRSW valve - Critical Task Override RHRSW pump trip - Critical Task Start RHRSW pump - Critical Task Open RHR Outboard Injection Valve - Critical Task
3. ED Using Head Vents Restart DW Chillers by overriding LOCA signal-Critical Task Open 6 DW vent valves - each one a Critical Task (note: valves are not the same as in below JPM #5)

Pull to lock for DW floor and equipment drains Open 2 Head Vent valves - each one a Critical Task

4. Roll the Main Turbine Turbine at 800 rpm Select 1800 rpm - Critical Task Tum off lift pumps at 900 rpms Respond to Quill Shaft failure annunciator Depress "All valves closed" - Critical Task Verify SV, CV, CNs closed Start Turning Gear Oil Pump - Critical Task Verify Motor Suction Pump running 1

( ( SIMULATOR

1. Nonnal Start of Recirc ASD Depress ASD fault reset DRAFT JPM

SUMMARY

Confinn ASD cooling normal Verify Suction Valve open Verify Reactor Water level Confinn ASD room cooler running Close Recirc Discharge Valve - Critical Task Start ASD - Critical Task ASD Cooling Annunciators Alarm Confinn ASD Shutdown Trip ASD Recirc Input Breaker - Critical Task

2. Restore RWL With RHRSW Verify RHR pumps stopped Verify 5 RHR valves closed Open RHR Inboard Injection Valve - Critical Task Open 2 RHRSW valves - each one a Critical Task Override RHRSW valve close logic - Critical Task Open RHRSW valve - Critical Task Override RHRSW pump trip - Critical Task Start RHRSW pump - Critical Task Open RHR Outboard Injection Valve - Critical Task
3. ED Using Head Vents Restart DW Chillers by overriding LOCA signal-Critical Task Open 6 DW vent valves - each one a Critical Task (note: valves are not the same as in below JPM #5)

Pull to lock for DW floor and equipment drains Open 2 Head Vent valves - each one a Critical Task

4. Roll the Main Turbine Turbine at 800 rpm Select 1800 rpm - Critical Task Tum off lift pumps at 900 rpms Respond to Quill Shaft failure annunciator Depress "All valves closed" - Critical Task Verify SV, CV, CIVs closed Start Turning Gear Oil Pump - Critical Task Verify Motor Suction Pump running I

DRAFT JPM

SUMMARY

5. Purge the Drywell with Air for Hydrogen Control Open 6 containment vent/purge valves - each one a Critical Task (note: valves are not the same as in above JPM #3)

Start purge fan - Critical Task

6. Re-Energize Bus with Diesel Generator Push Shutdown Relay Pushbutton - Critical Task Start the diesel - Critical Task Raise frequency to auto sync diesel - Critical Task
7. Rod Worth Minimizer Functional Test (RO ONLY)

Select a rod in Group 2 (6 &10) and verify rod block-each one a Critical Task Attempt to move rod the rod - each one a Critical Task

8. Loss of Air Actions for Rx Bldg Ventilation Attempt start of one SBGT-doesn't start Start second SBGT - Critical Task Trip each running Rx, TB, Refuel fan - each one a Critical Task PLANT
1. Vent the Scram Air Header Close air isolation valve - Critical Task Remove pipe cap - Critical Task Open vent valve - Critical Task
2. Locally Start IB PSW Pump Breaker Without Control Power Attempt to start pump with local control switch - doesn't start Selects another pump to start*

Trips the pumps control power breaker Insert Spring ChargeiMaintenance Handle - Critical Task Charge breaker - Critical Task Disable under voltage trip - Critical, Task Close breaker - Critical Task Close control power breaker

3. Start RPS MG Set Confirm output breakers tripped and fuses installed Start MG set - Critical Task Confirm output voltage Close in 2 output breakers - each one a Critical Task 2

( DRAFT JPM

SUMMARY

5. Purge the Drywell with Air for Hydrogen Control Open 6 containment vent/purge valves - each one a Critical Task (note: valves are not the same as in above JPM #3)

Start purge fan - Critical Task

6. Re-Energize Bus with Diesel Generator Push Shutdown Relay Pushbutton - Critical Task Start the diesel - Critical Task Raise frequency to auto sync diesel - Critical Task
7. Rod Worth Minimizer Functional Test (RO ONLY)

Select a rod in Group 2 (6 &10) and verify rod block-each one a Critical Task Attempt to move rod the rod - each one a Critical Task

8. Loss of Air Actions for Rx Bldg Ventilation Attempt start of one SBGT-doesn't start Start second SBGT - Critical Task Trip each running Rx, TB, Refuel fan - each one a Critical Task PLANT
1. Vent the Scram Air Header Close air isolation valve - Critical Task Remove pipe cap - Critical Task Open vent valve - Critical Task
2. Locally Start 1B PSW Pump Breaker Without Control Power Attempt to start pump with local control switch - doesn't start Selects another pump to start Trips the pumps control power breaker fusert Spring ChargeiMaintenance Handle - Critical Task Charge breaker - Critical Task Disable under voltage trip - CriticaL Task Close breaker - Critical Task Close control power breaker
3. Start RPS MG Set Confirm output breakers tripped and fuses installed Start MG set - Critical Task Confirm output voltage Close in 2 output breakers - each one a Critical Task 2}}
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