ML050350330

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Draft - Limerick Outlines (Folder 2)
ML050350330
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 11/15/2004
From: Jason White
Exelon Generation Co
To: Conte R
NRC/RGN-I/DRS/OSB
Conte R
References
50-352/05-301, 50-353/05-301 50-352/05-301, 50-353/05-301
Download: ML050350330 (21)
v • d • e


Text

ES-401 BWR Examination Outline FOIWI ES-401-I Note:

G* I Total

1. Ensure that at least two topics from every applicable WA category are sampled within each tier of the RO and SRO outlines (Le. except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each WA 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 2 1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.

3. Systemslevolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to ES-401,, for guidance regarding the elimination of inappropriate WA statements..
4. Select topics from as many systems and evolutions as possible; sample every system or evolution in
5. Absent a plant-specific priority, only those WAS having an importance rating (IR) of 2.5 or higher shall the group before selecting a second topic for any system or evolution.

be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

6. Select SRO topics for Tiers 1 and 2 from the shaded systems and WA categories.

7.* The generic (G) WAS 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 WA 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. Use duplicate pages for RO and SRO-only exams.

9. For Tier 3, select topics from Section 2 of the WA catalog, and enter the K/A numbers, descriptions, IRs. and point totals (#) on Form ES-401-3. Limit SRO selections to WAS that are linked to I O CFR ES-401, Page 16 of 33

ES-401 2

Form ES401-I 11 WAPE # I Name I Safety Function 95001 Partial or Complete Loss of Forced Flow Circulation I 1 & 4 295003 Partial or Complete LOSS of AC I 6

295004 Partial or Total Loss of DC Fwr I 6 295005 Main Turbine Generator Trip 13 295006 SCRAM I 1 295016 Control Room Abandonment I 7 295018 Partial or Total Loss of CCW / 8 29501 9 Partial or Total Loss of Inst. Air I 8

295021 LOSS of Shutdown Cooling I4 B IB 95023 Refueling Acc I 8 295024 High Drywell Pressure 15 295025 High Reactor Pressure I 3 295026 Suppression Pool High Water Temp. I 5 11295028 High Drywell Temperature I5 295030 Low Suppression Pool Wtr Lvl I 5 295031 Reactor Low Water Level I2 295037 SCRAM Condition Present and Power Above APRM Downscale or Unknown I 1 295038 High Off-site Release Rate I 9 600000 Plant Fire On Site I 8 WA Category Totals:

0 L.--

BWR Examination Outline Form ES401-17 of 33

ES401 3

Form ES-401-1 II D

Em IES4O1 L--

11 RAPE # I Name I Safety Function 295002 Loss of Main Condenser VaC I 3 295007 High Reactor Pressure 13 295008 High Reactor Water Level I 2 295009 Low Reactor Water Level I 2 295010 High Drywell Pressure I5 295012 High Drywell Temperature I5 95013 High Suppression Pool Temp. I5 295014 Inadvertent Reactivity Addition / 1 295015 Incomplete SCRAM I 1 D l 295017 High Off-site Release Rate I 9 v

295020 Inadvertent Cont. Isolation 15 & 7 295022 Loss of CRD pumps I 1 295029 High Suppression Pool Wtr Lvl 15 295032 High Secondary Containment Area Temperature I 5 295033 High Secondary Containment Area Radiation Levels I 9 295034 Secondary Containment Ventilation High Radiation / 9 295035 Secondary Containment High Differential Pressure I 5 295036 Secondary Containment High SumpIArea Water Level I5 500000 High CTMT Hydrogen Conc. I 5 01 K/A Category Totals:

I' c

BWR Examination Outline Form ES-401-'

18 of 33

ES-401 4

Form ES-401-1 Form ES-401-ES-401 BWR Examination Outline Plant Svsterns - Tier ZGrouD 1 (RO) 1 1

1 -

1 -

1 -

1 -

2 19 of 33

ES-401-I 5

Form ES-4014 BWR Examination Outline F O m ES401-1 bES-401 20 of 33

c ES-401 Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-3 26 of 33

ES-401 2

Form ES401-1 BWR Examination Outline F0t~l-1 ES-401-1 Emergency and Ab1 K

K K

B UAPE # I Name I Safely Function 95003 Partial or Complete Loss o 295004 Partial or Total Loss of DC Pwr I 6 295016 Control Room Abandonment / 7 95018 Partial or Total Loss of CCW 18 95021 Loss of Shutdown Cooling I 4 295023 Refueling Acc I 8

)I 95024 High Drywell Pressure I5

- I1 I l l 295025 High Reactor Pressure I 3

295026 Suppression Pool High Water Temp. I 5 295027 High Containment Temperature / 5 295028 High Drywell Temperature / 5 295030 Low Suppression Pool Wtr Lvl15 1)295031 Reactor Low Water Level I 2 I l l 295037 SCRAM Condition Present and Power Above APRM Downscale or Unknown / 1 295038 High.Off-site Release Rate I 9 600000 Plant Fire On Site I 8 WA Category Totals:

0 0

0 0

0 1 -

1 0

0 1

Revision 2 17 of 33

ES-401 3

Form ES401-I 95007 High Reactor Pressure / 3 9501 1 High Containment Temp / 5 95017 High Off-site Release Rate / 9 18 of 33

ES-401 4

Form ES401-1 300000 instrument Air 19 of 33 Revision 2

ES-401 5

Form ES401-I IlES-401 BWR Examination Outline Form ES-401-111 20 of 33

ES-401 Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-3 26 of 33

ES-401 Record of Rejected WAS Form ES401-4 L

Tier /

Group S R O 1 / 1 S R O 2 / 1 Randomly Selected WA 29 5024EA2.02 263000A2.01 Reason for Rejection K/A 295020AA2.01 (Existing WA) and WA29524EA2.02 (Replaced WA) test very similar topic areas. Writing questions on both very similar K/As will result in double jeopardy for both questions.

WA 295023AA2.02 was randomly selected to replace K/A 295024EA2.02 After many attempts to write an exam question on this WA, the exam team was unable to create a question that would satisfy the K/A requirements WA 206000A2.10 was randomly selected to replace W A 263000A2.01 ES401, Page 27 of 33

ES-301 Administrative Topics Out1 i ne Form ES-301-1 Facility: Limerick Generatinq Station Examination Level (circle one): RO Administrative Topic (See Note)

Conduct of Operations Conduct of Operations Equipment Control Type Code*

Date of Examination: 01/10/2005 Operating Jest Number:

Describe activity to be performed 2.1.10 Interpretation and Application of Overtime Limits 2.2.1 2 Review a Control Rod Exercise Test 2.3. I O Calculate Stay Time 2.4.27 Activate the Fire Brigade Emergency Plan P

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless

  • Type Codes & Criteria: (C)ontrol room they are retaking only the administrative topics, when 5 are required.

(D)irect from bank (I 3 for ROs; 5 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (2 1)

(P)revious 2 exams (5 1; randomly selected)

ES 301-1, Page 22 of 27

ES-301 Administrative ToDics Outline Form ES-301-1 Facility: Limerick Generatinq Station Examination Level (circle one): SRO Administrative Topic (See Note)

Conduct of Operations Conduct of Operations Equipment Control Radiation Control Type Code*

Date of Examination: 01/10/05 Operating Test Number:

~~

Describe activity to be performed 2.1.3 Complete a Turnover Checklist 2.1.10 Interpretation and Application of Overtime Limits 2.2.12 Review a Control Rod Exercise Test 2.3.10 Calculate Stay Time 2.4.41 ERP Classification and Reporting, Loss of DC Power (SRO)

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless

  • Type Codes & Criteria: (C)ontrol room 3

(D)irect from bank (r 3 for ROs; 5 4 for SROs & RO retakes)

(N)ew or (M)odified from bank (2 1)

(P)revious 2 exams (5 1 ; randomly selected)

ES 301-1, Page 22 of 27

ES-301 Control Roomlln-Plant Svstems Outline Form ES-301-2 Facility: Limerick Generating Station Exam Level (circle one): RO Date of Examination: 0111012005 Operating Test Number:

Control Room Systems@ (8 for RO, 7 for SRO-I, 2 or 3 for SRO-U)

System I JPM Title Type Safety Code*

Function

a. Reactor Recirc I Start MG Set - High Vibration occurs 1202001 A3.02 (A)(N)(S)(L) 1
b. Feedwater I Place 3rd RFP In Service 1259001 A4.02 (D)(S) 2
c. Main Turbine I ST-6-001-660-1 Main Turbine CIV, Stop Valve RPS (N)(S) 3 EOCIRPT Channel Functional Test 1241000 K4.05
d. RHR I Shutdown Cooling Flow Adjustments (RHRSW High Rad) I (A)(D)(S)(L) 4
e. Containment I T-228 Drywell lnerting with Nitrogen I 500000 EA1.07 (A)(N)(S) 5 205000 K1.I 5

(P)

f.

A. C. Power I Supplying Power to a 480 VAC Non-Safeguard Load (A)(N)(S) 6 Center from its alternate source 262001 A2.10

g. RPS / Scram Channel AI and A2 Functional Test 1212000 K4.05 7
h. MCR HVAC I Manually Initiate a Control Room Chlorine Isolation I (D)(S) 9 In-Piant Systems@ (3 for RO, 3 for SRO-I, 3 or 2 for SRO-U) 290003 A3.01
i.

HCU / Scram Discharge Volume Draining 29501 5 AA1.01 (R)(D)(E) 1

j.

UPS I Bypassing and Removing the *A RPS and UPS Static Inverter (R)(D) 6 from Service 262002 K6.02

k. SRV / Inadvertent Opening of a Relief Valve 239002 A2.03 (P)(R)(D) 3 (E)

@ All control room (and in-plant) systems must be different and serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

  • Type Codes Criteria for RO / SRO-l I SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (L)ow-Power (N)ew or (M)odified from bank including 1 (A)

(P)revious 2 exams 4-61 4-6 12-3 ES-301, page 23 of 27

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: Limerick GeneratinR Station Exam Level (circle one): SRO(I)

Date of Examination: 0111012005 Operating Test Number:

Control Room Systems@ (8 for RO, 7 for SRO-I, 2 or 3 for SRO-U)

System I JPM Title

a. Reactor Recirc I Start MG Set - High Vibration occurs 1202001 A3.02
b. Feedwater I Place 3 RFP In Service 1259001 A4.02
c. Main Turbine / ST-6-001-660-1 Main Turbine CIV, Stop Valve RPS EOCIRPT Channel Functional Test 1241000 K4.05
d. RHR I Shutdown Cooling Flow Adjustments (RHRSW High Rad) I 205000 K1.15
e. Containment I T-228 Drywell lnerting with Nitrogen 1500000 EA1.07
f. A. C. Power I Supplying Power to a 480 VAC Non-Safeguard Load Center from its alternate source 262001 A2.10
g. RPS I Scram Channel AI and A2 Functional Test 1212000 K4.05 Safety Code*

Function

h.

Implant Systems@ (3 for RO, 3 for SRO-I, 3 or 2 for SRO-U)

i.

HCU I Scram Discharge Volume Draining 295015 AA1.01 I

j.

UPS I Bypassing and Removing the *A RPS and UPS Static Inverter (R)(D) 6 from Service 262002 K6.02

k. SRV I Inadvertent Opening of a Relief Valve 239002 A2.03 (R)(D)(E) 3 (P)

~~

~

_ _ _ _ _ ~

@ All control room (and in-plant) systems must be different and serve different safety functions; in-plant systems and functions may overlap those tesl

  • Type Codes (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (L)ow-Power (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams d in the control room.

Criteria for RO I SRO-I / SRO-U 4-61 4-6 12-3 (randomly selected)

(R)CA

>I/ 21 1 2 1 (S)imulator ES-301, page 23 of 27

ES-301 Control Roomh-Plant Svstems Outline Form ES-301-2

i. HCU / Scram Discharge Volume Draining 295015 AA1.01
j.

SRV I Inadvertent Opening of a Relief Valve 239002 A2.03 1 Facility: Limerick Generatinn Station Exam Level (circle one): SRO(U)

(R)(D)(E) 1 3

(P)

Date of Examination: 0111012005 Operating Test Number:

  • Type Codes (A)lternate path (C)ontrol room (D)irect from bank Control Room Systems@ (8 for RO, 7 for SRO-I, 2 or 3 for SRO-U)

System I JPM Title Type Safety Code*

Function

a. RHR I Shutdown Cooling Flow Adjustments (RHRSW High Rad) I (A)(D)(S)(L) 4 205000 K1.15 (P)

Criteria for RO I SRO-I I SRO-U 4-61 4-6 12-3 e 9 1 ( 8 154 I

b. Containment I T-228 Drywell lnerting with Nitrogen I 500000 EA1.07
c. A. C. Power I Supplying Power to a 480 VAC Non-Safeguard Load Center from its alternate source 262001 A2.10
d.
e.
f.

I I

h.

(E)mergency or abnormal in-plant (L)ow-Power (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams (R)CA

> 1 / >I 121

> I I >I /?I

> 2 / 2 2 121 e 3 1 5 3 152

> I / 21 121 (randomly selected)

(S)imulator ES-301, page 23 of 27

Appendix D Scenario Outline Form ES-D-1 Initial Conditions: 4% power, Reactor Startup in progress, Y B" EHC pump blocked for maintenance Facility: Limerick Scenario No.: 1 Op-Test No.:

Examiners:

0 pera t ors:

Event 4

No.

N/A Override flow controller pot to 0 MED280B MRDOI 6F FIC46-1 R600 Type*

Description R (RO/

CRS)

I (RO/

Withdraw control rods until 4 bypass valves open CRD flow controller fails downscale in AUTO CRS)

I (ALL)

C (RO/

CRS)

Loss of 1 BY160 due to underfrequency trip of a series supply breaker (TS)

Control Rod 22-35 inadvertently scrams (TS)

E MRC465 MRC464A MRC464B MAD141D (04%)

Malf.

I Event 1

Event M (ALL)

C (PRO/

CRS)

C (PRO/

CRS)

Steam Leak from RClC piping RClC isolation valves fail to close YE" SRV fails to open I

I

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor APPENDIX D, Page 38 of 39

Appendix D Scenario Outline Form ES-D-I Event Facility: Limerick Scenario No.: 2 Op-Test No.:

Malf.

Examiners:

Operators:

Event Type*

N (ALL)

I (ALL)

Initial Conditions: 100% power, #3 APRM is inoperable and bypassed Event Description Perform ST-6-001-761-1 111 811 RECW pump trips, "IA" RECW pLmp fails to auto start Turnover: Reactor power is 100%. #3 APRM is inoperable and bypassed. I&C has been contacted to begin troubleshooting. The crew is to perform ST-6-001-761-1, Main Turbine Bypass Valve Exercising.

No.

1 No.

N/A 2

3 4

5 6

7 8

MCW483B MCW485A MED263D MRR433B MRR434B 50 gpm)

MRR440B MRHI71B MRHl74C MRR441 (0-I (PRO/

CRS)

D l 4 Bus Lockout relay fails, Loss of D14 Bus (TS)

C (ALL) I "1 B" Reactor Recirculation Pump seal failure (TS)

M (ALL)

C (ALL)

C (ALL)

Leakage past "1 B" Reactor Recirculation loop 1 isolation valves "1 B" Reactor Recirculation piping break "1 B" RHR Dum13 trit, C (PRO/

CRS)

" I C RHR LPCl injection valve fails to close after it opens I APPENDIX D, Page 38 of 39

Appendix D Scenario Outline Form ES-D-1 Type*

N (ALL)

Facility: Limerick Scenario No.: 3 Op-Test No.:

Description Perform ST-6-047-200-1 Examiners:

0 pera tors :

C (RO/

CRS)

I (PRO/

CRS)

I (RO/

CRS)

Initial Conditions: 100% power, *'I K SRV tailpipe temperature is elevated, and is being monitored using RT-6-041-230-1, MSRV Tailpipe Temperature Data Monitoring.

Scram discharge volume drain valve XV47-1 F181 fails closed/ SDV High Level (TS)

U/l RHRSW Radiation Monitor fails inoperable (TS)

Reactor Pressure Instrument fails high Turnover: Reactor power is 100%. "1 K SRV tailpipe temperature is elevated, and is being monitored using RT-6-041-230-1. The crew is to perform ST-6-047-200-1, SDV 3

4 5

Valve Exercise Test.

Event MCR414C MRMO19A MV1234A MRD556 I (ALL)

C (ALL) 6 I

MSL559 EHC Turbine Load Set runs back to minimum Main Turbine Bypass Valves fail closed Event I Event M (ALL)

ATWS - Control Rods fail to scram (Hydraulic I Lock)

C (RO/

SLC piping rupture CRS I I

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor APPENDIX D, Page 38 of 39

Appendix D Scenario Outline Form ES-D-1 Event No.

I.

2 3

4 5

6 Facility: Limerick Scenario No.: 4 Op-Test No.:

Malf.

Event No.

Type*

MV1231 B I (ALL)

MSW489B C (PRO/

CRS)

MHP452 C (PRO/

MHP453 CRS)

Override C (ALL)

HS05-102C to close MRR507A I (PRO/

MFW252B M (ALL)

CRS)

Examiners:

0 pe ra t o rs :

Initial Conditions: 83% power, ST-6-052-232-1, B Loop Core Spray Pump, Valve and Flow Test is in progress.

Turnover: Reactor power is 83% following a rod pattern adjustment. Reactor Engineering is completing a ReMA. Power restoration will resume within the next hour.

ST-6-052-232-1, B Loop Core Spray Pump, Valve and Flow Test is in progress and has been completed up to and including step 4.7.21. "1 D" Core Spray pump has been running for 20 minutes of its required 45 minutes for step 4.7.22.

7 8

9 (0-1 00%)

MADl46B MAD146E Override to fail "as-is" MAD151 D HS41-1 F032B C (PRO/

CRS)

C (ALL)

C (PRO/

CRS)

Event Description RPV instrument line break, XV42-1 F045B closes causing Division 2 LOCA signal (TS)

"OB" ESW Pump trip (TS)

HPCl Injection valves will fail to reopen after initial isolation/trip of HPCl "1 c" Condensate Pump Discharge Valve strokes closed due to a short in the control switch "IA" Reactor Recirculation MG Set fails to runback Feedwater line rupture inside Primary Containment "I

K" SRV opens "B" Feedwater line isolation valve fails to close "1 E" SRV downcomer leak

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor APPENDIX D, Page 38 of 39
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