ML081330623

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Final - Outlines (Folder 3)
ML081330623
Person / Time
Site: Oyster Creek
Issue date: 03/28/2008
From: Ludlam G
AmerGen Energy Co
To: Caruso J
Operations Branch I
Hansell S
Shared Package
ML072851077 List:
References
50-219/08-301, U01688
Download: ML081330623 (24)
v • d • e


Text

ES-401 BWR Examination Outline Form ES-401-1 Facilitv:

Oyster Creek Nuclear Station Printed: 03/31 /2008 Note:

1. Ensure that at least two topics from every WA category are sampled within each tier of the RO and SRO-only 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 +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 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 WA statements.
4. Select topics from as many systems and evolutions as possible: sample every system or evolution in the group before selecting a second topic for any system or evolution.
5. Absent a plant-specific priority, only thcse K/As having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
6. Select SRO topics for Tiers 1 and 2 from the shaded systems and WA categories.

7.* The generic (G) WAS inTiers 1 and 2 shall be selected from Section 2 of the WA 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: if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). 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 WA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to WAS that are linked to 10 CFR 55.43.

I

BWR RO Examination Outline Facility:

Oyster Creek Nuclear Station Printed: 03/3 1/2008 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 (RO / SRO)

Form ES-401-1 ES - 401 conditions for operations and safety 295037 SCRAM Condition Present and Reactor Power Above APKM Downscale or 600000 Plant Fire On Site / 8 I

BWR RO Examination Outline Facility:

Oyster Creek Nuclear Station ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 2 (RO / SRO)

K2 X

Printed: 03/3 1/2008 K3 X

1 1

Form ES-401-1 IR 3.2 4.0 4.0 3.4 3.6 4.1

3. I I

1 I

I 1

1 I

EIAPE # I Name / Safety Function 29.5002 Loss of Main Condenser Vac 1 3 K1 SO0000 High CTMT Hydrogen Conc. I 5 295007 High Reactor Pressure / 3 29.50 IO High Drywell Pressure I 5 29.501 7 High Off-Site Release Rate 19 29.5022 Loss of CRD Pumps / 1 K/A Category Totals: I 2 X

29.5034 Secondary Containment Ventilation High Radiation I 9 KA Topic(s)

AA2.02 - Reactor power: Plant-Specific X

AK3.0 I - Isolation condenser operation:

I I

Plant-Specific 2.4.4 - Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

AA 1.07 - Process radiation monitoring system AKI.02 - Reactivity control EKI.02 - TRadiation releases Total:

7

BWIi RO Examination Outline K3 Facility:

Oyster Creek Nuclear Station ES - 401 1

I K4 Sys/Evol # I Name 205000 Shutdown Cooling 207000 Isolation (Emergency)

Condenser 207000 Isolation (Emergency)

Condenser 209001 LPCS Kl K2 209001 LPCS p i G L C I

I 2 I2000 RPS 2 1 5003 IRM 2 I5004 Source Range Monitor 215005 APRMLPRM X

215005 APRMLPRM 1 2 18000 ADS l

l 223002 PCIS/Nuclear Steam 239002 SRVs 239002 SRVs 3-59002 Reactor Water Level Control

~

~~

259002 Reactor Water Level Control X

X K5 K6 A1 tl x

X Printed: 03/3 I /2008 Form ES-401-1 K5.02 - Valve operation K5.03 - Heat transfer:

2.7 BWR-2, 3 A4.06 - Shell side makeup valves: BWR-2,3 A2.09 - Low suppression pool level 3.8*

3. I A4.1 I - System flow 3.7 4.0" '

A 1.09 - SBLC system lineup K5.02 - Specific logic 3.3 arrangements K6.03 - Detector drive 2.8 motor K4.01 - Rod withdrawal blocks KI.07 - Process computer, performance monitoring I system I

I A3.05 - Flow I

3.3 D.C. power to ADS valves A 1.04 - Individual system I relay status K3.02 - Reactor over pressunr.ation A3.06 - Reactor pressure K4. I0 - Three element control (main steam flab, reactor feedwater flow and reactor water level provide innut)

Y 2.4.6 - Knowledge symptom based EOP mitigation strategies.

K6.04 - Process radiation K 1.O 1 - Emergency 3.4*

2.6 4.2" 4.1*

3.4 3.1 2.9 3.8 1

BWK RO Examination Outline Facility:

Oyster Creek Nuclear Station

- Tier 2 /Group 1 (RO / SRO)

Printed: 0313 I /200X Form ES-401-1 K4 K5 K6 A1 A2 X

X KA Topic 2.4.49 - Ability to perform without reference to procedures those actions tha require immediate operation of system components and controls.

A2.02 - Over voltage K3.03 - Systems with D.C.

components (i.e. valves, motors, solenoids, etc.)

K3.03 - Major loads powered from electrical buses fed by the emergency generator(s)

K4.01 - Manualhutomatic transfers of control K2.02 - CCW valves A3.01 - Setpoints on instrument signal levels for normal operations, warnings, and trips that are applicable to the CCWS Group Poi]

IR 4.0 2.5 3.4 4.1" 2.8 2.9 3.0 Total:

I I

26 2

BWR RO Examination Outline Facility:

Oyster Creek Nuclear Station 44 ES - 401 I

I

~-

G KATopic 1R A2.1 1 - Valve openings 2.6 1 sc1 I Svs/Evol # / Name IK1 IK2 X

Mechanism A3.01 - Control rod position 3.7 I

55 2.1.32 - Ability to explain and apply system limits dnd precautions.

AI.03 - MG set generator 2.5*

1 5 7 current, power, voltage K4.06 - Pump motor cooling: Plant-Specific 5b 3.4

~

2.7 5%

201006 RWM K3.01 - tOff-site radioactive release rates K6.05 - SBLC I I I53 3.3 I

b,y 4.0 I

I I 202002 Recirculation Flow Control WA Category Totals:

2 19000 RHlULPCI:Torus/Pool 223001 Primary CTMT and Aux.

1 1

226001 RHR/I,PCI: CTMT Spray 24 I000 Reactor/Turbine Pressure 29000 1 Secondary CTMT I

I 290002 Reactor Vessel Internals I

I 1 290003 Control Room HVAC Printed: 03/3 1/2008 Form ES-401-1 K2.09 - Drywell cooling I I fans: Plant-SDecific K5.06 - Vacuum breaker operation I

I I I A3.02 - thterlock operation I 3.1 I 1 2,7 I 1 b.2 1 I KI.24 - Main generator 1 2.a I I

I L 6 A4.04 - Environmental I conditions I l I Group Point Total:

12 I I

Generic Knowlttdge and Abilities Outline (Tier 3)

BWR IiO Examination Outline Printed 03/3 112008 Facility:

Oyster Creek Nuclear Station Date of Exam:

Form ES-401-3

2. I. 1 Category Knowledge of conduct of operations requirements.

IR KA#

Topic I

2 1.7 Conduct of Operations Ability to evaluate pldnt performance and make operaticma1 judgments baed on operating characteristics, reactor 3ehdvior. and inatrumenl interpretation 3.7 2.1.25 3.1 Ability to obtain and interpret station reference materials such as graphs, monographs, and tables which contain aerforinance data.

Equipment Control 2.2. I3 Knowledge of tagging and clearance procedures.

3.6 1

2.2.27 Knowledge of the refueling process.

2.6 I

Subtotal:

2 2.8 2.4.2 2.4.24 iubtotal:

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

Knowledge of loss of cooling water procedures.

1

___I

_c_

I 2.4.39 Knowledge of the RO's responsibilities in emergency plan 3.3 1

implementation.

Radiation Control 2.3.9 2.3.1 1 Knowledge of the process for performing a containment purge.

Ability 10 control radiation releases.

2.5

2.1 Subtotal

2 h4 7 0 7 '

7 '2 Emergency Plan 3.3 I I

I I

I I

I I

Tier 3 Point Total:

10 7 3 74 75 I

OC ILT 07-1 RO NRC Exam KEY Coqnitive Level of Questions (Hiqh/Low) / Question TvPe (New, Modified, Bank):

Exam Construction Requirements:

0 RO Exam 50 - 60% high cog (38 - 45 questions): 41/75 = 54.6%

0 -

e 75% Bank/ 5 15% Modified/ 1. 10% New e 4 from 2 previous NRC exams * (1)

Cognitive Levels (from NUREG 1021, Appendix B)

Level 0

0 0

0 0

0 Level 0

0 0

0 Level 0

0 0

1 : Fundamental Knowledge or Simple Memory (low cognitive level)

Bases or purpose (B)

Definitions (D)

Facts (F)

Interlocks, setpoints or system (singular) response (I)

Procedure steps or cautions (P)

Structures and locations (S)

Terminology (T) 2: Comprehension (high cognitive level)

Describing or recognizing relationships (DR)

Showing differences and similarities (DS)

Recognizing interaction between systems (plural), including consequences and implications (RI)

Re-wording or re-phrasing information (DW) 3: Application, Analysis, Synthesis (high cognitive level)

Create something new (CSN)

Predict an event or outcome (PEO)

Solve a problem using knowledge and its meaning (SPK)

Solve a problem using references (SPR)

Page 1 of 219

ES-401 BWR Examination Outline Form ES-401-1 Facility:

Oyster Creek Nuclear Station Date Of Exam:

04/14/2008 Printed: 03/31/2008

1. Ensure that at least two topics from every WA category are sampled within each tier of the RO and SRO-only 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 +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.

Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate WA statements.

4. Select topics from as many systems and evolutions as possible: sample every system or evolution in the group before selecting a second topic for any system or evolution.
5. Absent a plant-specific priority, only those WAS having an importance rating (IR) of 2.5 or higher shall be selected. U s e the RO and SRO ratings for the RO and SRO-only portions, respectively.
6. Select SRO topics for Tiers 1 and 2 frorn the shaded systems and WA categories.

7.* The generic (G) WAS inTiers 1 and 2 shall be selected from Section 2 of the WA 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; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.
9. For Tier 3, select topics from Section 2 of the K/A catalog, and enter the WA numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to WAS that are linked to 10 CFR 55.43.
3.

I I

BWR SRO Examination Outline Printed: 03/3 1/2008 Facility:

Oyster Creek Nuclear Station ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group I (RO / SRO)

Form ES-401-1 IR

4. I 3.6 3.8 4.6" 1 4.4" 4.0 X

EA2.03 - Reactor pressure 3.9 I

\\

I 2 I

3 1 5 I C :

1 7

I I I

I 295023 Refueling Acc / 8 E/APE # / Name / Safety Function 29500 1 Partial or Complete Loss of Forced Core Flow Circulation / I & 4 295003 Partial or Complete Loss of AC Pwr

/ 6 295006 SCRAM / 1 I 295024 High Drywell Pressure / 5 I

I I

K1 K2 K3 29.5025 High Reactor Pressure / 3 295030 Low Suppression Pool Wtr Lvl I 5 WA Category Totals:

I I I 0

0 0

01 4 conditions for operations and safety mitigation strategies.

3 Group Point Total:

7 I

BWR SRO Examination Outline Printed: 03/3 1 /2008 Facility:

Oyster Creek Nuclear Station ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 (RO / SRO)

Form ES-401-1 E/APE # / Name / Safety Function 295009 Low Reactor Water Level / 2 I 295014 Inadvertent Reactivity Addition / I 295032 High Secondary Containment Area Temperature / 5 A2 G KA Topic(s)

IR X 2.4.4 - Ability to recognize abnormal 4.3 I

indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

AA2.01 - Reactor power EA2 03 - Cause of high area temperature Group Point Total:

BWR SRO Examination Outline Facility:

Oyster Creek Nuclear Station A2 X

X X

Printed: 03/3 1/2008 A3 3

0 3s - 401 Plant Systems - Tier 2 / Group 1 (RO / SRO)

I I

Form ES-401-1 Sys/Evol # / Name 20.5000 Shutdown Cooling Kl K2 K3 I

l l

2 I2000 RPS WA Category Totals:

26 1000 SGTS 263000 DC Electrical Distribution 300000 Instrument Air 0

0 0

I A2.1 1 - Main steamline system status criteria which require the notification of plant personnel.

2.2.25 - Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.

A2.01 - Air dryer and filter malfunctions IR 2.6

4.

I 3.3 3.7 2.8 -

2 1 Group Point Total:

I -

BWR SKO Examination Outline Facility:

Oyster Creek Nuclear Station X

Plant Systems - Tier 2 / Group 2 (RO / SRO)

ES - 401 I

I 2.4.30 - Knowledge of which events related to system operations/status should be reported to outside agencies.

A2.07 - High fuel pool temperature K/A Category Totals:

I Printed: 03/3 1 /2008 Form ES-401-1 G I KA Topic I A2.01 - Pump trip IR 3.6 3.2 3.7 -

Group Point Total:

II I

I I

3 -

I

Generic Knowledge and Abilities Outline (Tier 3)

UWR Sf30 Examination Outline Printed: 03/3 I /2008

~~

2.2.5 2.2. I 1 Facility:

Oyster Creek Nuclear Station Date of' Exam:

Form ES-401-3

~~

~

Knowledge of the process for making changes iri the Knowledge of the process for controlling temporary 3.4*

I 2.7 I

facility k s described in the safety analysis report.

changes.

Category Conduct of Operations 2.3.1 KA #

Topic chemistlv within allowable limits.

Knowledge of I O CFR 20 and related facility radiation 3.0 1

control requirements.

IR 2.4.37 Subtotal:

~

~

~

Knowledge of the lines of authority during an emergency.

3.5 1

25 2

1 Equipment Control Radiation Control Subtotal:

2 1

2.3.2 Knowledge of facility ALARA program.

1 2

)

I I

Subtotal:

2 Emergency Plan I Subtotal:

1 1

21 2 2 z3 2 "I Tier 3 Point Total:

7 I

OC ILT 07-1 PJRC SRO Exam KEY Coqnitive Level of Questions (Hiqh/Low) / Question Tvpe (New, Modified, Bank):

Exam Construction Requirements:

0 Cognitive level should match the level of the WA (16/25 High = 64% )

0 -

< 75% Bank/ 2 10% New / the rest Modified/ (1 8/25 New - 72%; 2/25 Bank - 8%; 5/25 modified - 20%; )

Cognitive Levels (from NUREG 1021, Appendix B)

Level 1 : Fundamental Knowledge or Simple Memory (low cognitive level)

Bases or purpose (B) 0 Definitions (D)

Facts (F)

Interlocks, setpoints or system (singular) response (I)

Procedure steps or cautions (P)

Structures and locations (S)

Terminology (T) 0 Describing or recognizing relationships (DR)

Showing differences and similarities (DS)

Recognizing interaction between systems (plural), including consequences and implications (RI)

Re-wording or re-phrasing information (DW)

Create something new (CSN)

Predict an event or outcome (PEO)

Solve a problem using knowledge and its meaning (SPK)

Solve a problem using references (SPR)

Level 2: Comprehension (high cognitive level)

Level 3: Application, Analysis, Synthesis (high cognitive level)

OC ILT 07-1 NRC SRO Exam KEY Page 1 of 74

ES-401 Record of Reiected WAS Form ES-401-4 Tier I Group SRO 111 SRO 1 12 RO 111 RO 1 12 RO 211 RO 211 Reason for Rejection Randomly Selected KIA Oyster Creek Nuclear Station Initial Exam April 14, 2008 295030 EA2.04 295030 EA2.04 A valid operationally relevant SRO question for this KA could not be constructed. KA 295030 EA 2.03 was randomly selected as a replacement.

295008 AA2.01 295008 AA2.01 A valid operationally relevant SRO question for this KA could not be constructed. KA 29501 4 AA 2.01 was randomly selected as a replacement.

  • 295001 AK3.03 295001 AK3.03 presents overlap with RO administrative JPM material. KA 295001 AK3.05 was randomly selected as a replacement.

295034 EK1.01 295034 EK1.01 There is no relationship between the USAR design function of the Standby Gas Treatment System and personnel protection.

KA 295034 EKl.02 was randomly selected as a replacement.

21 5004 K2.01 This KA was duplicated on the audit exam. KA 21 5004 K4.01 was randonly selected as a replacement.

21 8000 A2.04 ADS is manually prevented from automatic operation in both the RPV Control EOPs. A valid operationally relevant SRO question for this KA could not be constructed. KA 218000 A2.05 was raodomly selected as I

I 21 5004 K2.01 1 21 8000 A2.04 I

I a replacement.

RO I 262001 K1.05 I 262001 K1.05 A valid oDerationallv relevant RO auestion for this KA could 262001 2.4.4 RO 300000 K4.02 not be constructed. KA 262001 Ki.01 was randomly selected as a replacement.

  • 262001 2.4.4 This generic KA was previously selected in another question.

KA 262001 2.4.49 was randonly selected as a replacement.

300000 K4.02 There is no cross-over to other air systems from the instrument air system (ie., there is no other air system to supplement instrument air in the event of instrument air failures). KA 300000 K4.01 was randonly slsected as a replacement.

219000 K4.08 There is no design feature or interlock which provides for RO 219000 K4.08 2/2 I

I suppression pool cooling that ensures adequate pump net positive suction I

I head. KA 21 9000 K4.06 was randomly selected as a replacement.

RO I 290003 A4.02 I 290003 A4.02 A valid operationally relevant RO question for this KA could 2/2 RO 2.2.24 3

RO 2.4.50 3

RO 295026 2.4.31 111 SRO 21 4000 A2.02 212 SRO 2.4.9 3

RO 295024 EK1.01 111 not be constructed. KA 290003 A4.04 was randomly selected as a replacement.

  • 2.2.24 A valid operationally relevant RO question for this KA could not be constructed. 2.2 13 was randomly selected as a replacement.
  • 2.4.50 This generic KA is best suited in the operating exam portion.

Generic 2.4.43 was randomly selected as a replacement.

295026 2.4.31 This generic KA is best suited in the operating exam portion. 295026 2.2.22 was randomly selected as a replacement.

21 4000 A2.02 A valid operationally relevant SRO question for this KA could not be constructed. KA 233000 A2.07 was randomly selected as a replacement.

  • 2.4.9 A valid operationally relevant SRO question for this KA could not be constructed. Generic 2.4.42 was randomly selected as a replacement.
  • 295025 EKl.01 A valid operationally relevant RO question for this KA could not be constructed. 295024 EAl.17 was randomly selected as a ES-401, Page 27 of 33

valid operationally relevant RO question for this KA could ted. 295017 AA1.07 was randomly selected as a valid operationally relevant SRO question for this KA 2.4.43 I

could not be constructed. 201 001 2.4.30 was randomly selected as a replacement.

  • 2.4.43 A valid operationally relevant RO question for this KA could not be constructed. 2.4.39 was randomly selected as a replacement. *
  • Note: Many questions were rejected because a valid operationally relevant RO/SRO question could not be constructed. In fact, a new question for each of these KAs was initially developed. Review of the question by a independent reviewer revealed that the question was unsatisfactory for one or more reasons: the question did not directly relate to the KA; the question was of low difficulty; reference material did not directly support the answer; or, one/more distractors were not plausible. In all cases, the questions were re-worked but still noted as unacceptable. A new KA was then randomly selected for replacement.

I I

Facility: Ovster Creek Examination Level: RO SRO 0 1

Conduct of Operations Conduct of Operations Administrative Topic (See Note)

~

Equipment Control Radiation Control Emergency Plan TY Pe Code*

R, M Date of Examination: 4/14/2008 Operating Test Number: OC 2008 Describe activity to be performed

- - ~ _ _ _ -

Complete the Technical Specification Log Sheet.

2.1.18/2.9 (Admin R01)

Perform a Manual Core Heat Balance Calculation.

2.1.20/4.3 (Admin R02)

Perform APRM Drawer Count. 2.2.12/3.0 (Admin R03)

Determine RPV Water Level Instrument Availability.

2.4.21/3.7 (Admin R04)

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

  • Type Codes & Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (5 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, Page 22 of 27

Facility: Ovster Creek Examination Level: RO 0 SRO Date of Examination: 4/14/2008 Operating Test Number: OC 2008 Administrative Topic (See Note)

. -~

Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Plan R. N R. M Describe activity to be performed Review a Shift Turnover Checklist. 2.1.3/3.4 (Admin SRO1)

Plant Personnel Event Notification. 2.1.,14/3.3 (Admin SH02)

Review Acceptance Criteria for a Completed Surveillance.

2.:1.12/3.4 (Admin SR03)

Authorize Emergency Exposures. 2.3.413.1 (Adrnin SR04)

Determine Emergency Classification and Protective Action Recommendations. 2.4.29/4.0 (Admin SR05) 1 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

  • Type Codes & Criteria:

(C)ontrol room, (S)irnulator, or Class(R)oom (D)irect from bank (5 3 for ROs; 5 4 for SROs & RO retakes)

(N)ew or (Mjodifred from bank (2 1)

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

ES 301, Page 22 of 27

ES-301 Control Room/ln-Plant Systems Outline Form ES-301-2

  • Type Codes Facility: Ovster Creek Exam Level: RO Date of Examination: 4/14/2008 Operating Test Number: OC 2008 SRO-I c] SRO-U fl Criteria for RO / SRO-I / SRO-U Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF) 1 Typecode* I Function Satety a Startup a Reactor Recirculation Pump (202001 A4 01 3 7/3 7) NRC JPM 1
b. Respond to high Core Spray pump amps during surveillance (209001 S, D 1

1

~

2

- + - - - -

I A, S, N

A, S, D, P

.~ - - _ _

~

~-

A4.01

__ ~ 8/3.6) NRC JPM

_ _ _ ~ _

SIM2-c Perform Anticipatory Scram Turbine Stop Valve Closure Test with RPS a_ctuatlon_C241000K3.01 4 1!311 N~5-JP-M sIM3-

~~

40/4-2) NRC JPMSIM4

-~

~-

_~

d Control RPV pressure with the IC Tube Side Vents (207000 K1.02 e Vent the Primary Containment through the Standby Gas Treatment S!@?!! L2230_01 K1 0 9 4/3.6)_NP_C_L!MSIM5--

f. Transfer 4160 VAC Busses in preperation fcr a manual scram (262001 K4.02 2 9/3.3)

__ NRC JPM SIM6 - _

3 4

5 A, S, D

A, S, D, P 6

S, N 7

S, A 9

g. Perform an APRM Gain Adjustment (215005 A4.03 3.2/3.3 NRC JPM
h. Swap Control Room Ventilation Fans (290003 A4.02 2.8/2.8) NRC JPM SIM7 -

.~

SIM8

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

(P)revious 2 exams

( W A (S)im ulator 4-6 I 4-6 I 2-3

< 9 1 1 5 4

> 1 / 21 I 2 1 2 1 1 2 1 1 1 1

> 2 / 2 2 I 2 1

> l l 21 1 2 1 3 15 3 I 5 2 (randomly selected)

ES-30-, Page 23 of 27

~~

~

Form ES-301-2 Control Room/m-Plant Systems Outline ES-301 b Respond to high Core Spray pump amps dirring surveillance (209001

c. Perform Anticipatory Scram Turbine Stop Valve Closure Test with RPS d

A4

- 01 3

- 8/3.6lNRC

~

-_ JPM SIM2

~

-~

_ 1 A:S:D:I 1

actuation (241000 K3.01 4.1/4 1) NRC JPM SIM3

. - ~-

Control RPV pressure with the IC Tube Side Vents (207000 K1 02 4

- 40/4_12_NRCJPM%L-

_ _ _ _ _ _ _ _ ~

e Vent the Primary Containment through the Standby Gas Treatment A, S, D 5

System (223001 K1.09 3.413.6) NRC JPM SIM5

f. Transfer 4160 VAC Busses in preperation for a manual scram (262001 I

K4 02 2 9/3.3) NRC JPM SIM6 A, S, D, P 6

1 t

Facility: Ovster Creek Exam Level: RO SRO-I SRO-U n Date of Examination: 4/14/2008 -

Operating Test Number: OC 2008 in-Plant Systems@ (3 for RO); (3 for SRO-I), (3 or 2 for SRO-U)

I Perform in-plant actions during Station Blackout conditions (262001 K3.05 3 2/3 5) NRC JPM PLANT1

__ ~- - -

~_

I Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

k. Lineup Fire Water to Core Spray to raise torus water level (286000 K1.05 3.2/3.2)NRC JPM PLANT3 I

D, E, R, P 8

System / JPM Tit13

  • Type Codes 1 Type Code* 1 Sa'ety Functio Criteria for RO / SRO-I / SRO-U
a. Startup a Reactor Recirculation Pump (202001 A4.01 3.7/3 7) NRC JPM 1

Z M l -___-

g h

Perform an APRM Gain Adjustment (215005 A4 03 3 2/3 3 NRC SIM7 7

J. Perform backup methods for critical functions in-plant (259001 K1 07 2

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I 2 9!2

9) NRC-JPMPLANT2

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

(P)revious 2 exams (S)im ulator

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- S " L OC ILT 07-1 NHC Exam Scenario NRC SIM 2 MAL-

CFW003A, 38,3C Scenario Outline C

Crew Respond to the loss of all Feedwater/Condensate.

Facility: Ovster Creek Scenario No.: NRC SIM 2 Op Test No.: OC 2008 Examiners:

Operators:

Initial Conditions:

Turnover:

The plant IS at 100% power.

RWCU Pump B is out of service for repair.

Dilution Pump 2 is out of service for maintenance.

The RWM is inoperable and is bypassed.

Complete 61 0.4.002, Core Spray Pump Operability Test for normal surveillance.

Event No.

1 4

5 6

Event I

Malf. No. 1 Type*

Event Description Perform Automatic Scram Contactor Test, 61 9.4.025 SWI-N BOP RPS034 1 TS 1 SRO 1 Sespond to a loss 480 VAC USS 181 with failure of TBCCW to auto start.

MAL-1 C 1 BOP [

EDS003D to loss of main generator isophase Fan #l.

to an upscale failure of APRM 4.

GEA005B NIS020D Respond to recirculation pump seal leak.

MAL-C BOP RCP003A I TS I SRO I I

I I

ANN-H5c 1 C

1 ATC I Responds to a high temperature control rod 46-1 5.

Respond to an Isolation Condenser B tube leak with rising fuel failures.

MAL-ICSO2B 1

M 1 Crew 1 t

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Transient, (TS) Tech Specs NRC SIM 2 Page 1 of 27

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-x-OC ILT 07-1 NFC Exam Scenario NRC SIM 3 MAL-CRD008-2 23 1 Scenario Outline Facility: Ovster Creek Scenario No.: NRC SIM 3 Op Test No.: OC 2008 C

ATC Operators:

Examiners:

PMP-SLCOOlN SLC002A Initial Conditions:

The plant is at about 65% power.

EDG2 is 00s to replace a fuel pump.

0 TBCCW Pump 2 and RWCU Pump b3 are 00s for maintenance, The RWM is inoperable and bypassed.

0 Feedwater Pump B is off.

Turnover:

0 Start Feedwater Pump B.

Withdraw 4 control rods from position 40 to position 48.

I Event No.

c Crew Event Description 1

2 3

4 5

6 9

Event Malf. No.

TCSOlO ANN-T4b SRO LOA-RBCOOg I C 1 BOP MAL-RCUO14 +

ATC CRD002 &

CRDOOG MAL- -2 I T"S 1 SRO 23 1 MAL-1 M 1 Crew NSS025E

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~

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The BOP will place Feedwater Pump B in service IAW Procedure 31 7.

Withdraw control rods and respond to uncoupled rod.

The ATC will raise rector power by raising reactor recirculation flow.

The BOP will respond to an EPR failure.

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The SRO will respond to loss of oil to EDG 1.

Responds to a RWCU isolation with failure to auto triplisolate The ATC will respond to the trip of CRD Pump A, and an inward drifting control rod on the manual CRD pump start.

The crew will respond to a leaking EMRV E and an electric ATWS.

Respond to a SLC Pump shaft break.

t (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor Transient, (TS)

Tech Specs NRC SIM 3 Page 1 of 27

OC ILT 07-1 NRC Exam Scenario NRC SIM 4 1

2 3

4 Scenario Outline MAL-CRDOO7 3 21 1 VLV-I CS06 MAL-EDSO036 MAL-RFC003A MAL-Facility: Ovster Creek Scenario No.: NRC SIM 4 Op Test No.: OC 2008 Examiners:

Operators:

Initial Conditions:

0 0

Turnover:

The plant is at 95% power EDG1 is 00s to replace a starting motor.

TBCCW Pump 2 and Air Compressor 3 are 00s for maintenance.

The RWM is inoperable and bypassed.

Withdraw control rod 22-1 1 Perform 609.4.001, Isolation Condenser Valve Operability and In Service Test I

1 Malf. No.

No.

5 1

T TSlOl8A MAN-NIS021 E 6

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MAL-NSSOl7A 7

MAL-RPS007A 8

Event Type*

C N

TS C

TS C

R C

M C -

(N)ormal, (R)eactivity, ATC BOP SRO BOP SRO BOP ATC ATC Crew Crew Event Description Responds to control rod 22-1 1 stuck at 00 on withdrawal

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Performs 609.4.001, Isolation Condenser Valve Operability and In Service Test and responds to failure of V-14-31 (IC A) to re-open.

Responds to a failure of 480 VAC Bus USS 1 A2.

The BOP will respond to an oscillating reactor recirculation pump.

Responds to high turbine vibrations.

Responds to a leak in RPV water level instruments common variable leg to ID13A and ID13C.

Responds to a primary leak in the Primary Containment.

Respond to a loss of offsite power and failure of all Core Spray Pumps.

(I)nstrument, (C)omponent, (M)ajor Transient, (TS) Tech Specs NRC SIM 4 Page 1 of 27

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