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 Printed: 03/3 1/2008 Facility: Oyster Creek Nuclear Station ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 (RO / SRO) Form ES-401-1 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 Printed: 03/3 1/2008 Facility: Oyster Creek Nuclear Station ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 2 (RO / SRO) Form ES-401-1 EIAPE # I Name / Safety Function K1 K2 K3 KA Topic(s) IR #

29.5002 Loss of Main Condenser Vac 1 3 AA2.02 - Reactor power: Plant-Specific 3.2 I 295007 High Reactor Pressure / 3 X I I AK3.0 I - Isolation condenser operation:

Plant-Specific 4.0 4.0 1

29.50 I O High Drywell Pressure I 5 2.4.4 - Ability to recognize abnormal I indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

29.501 7 High Off-Site Release Rate 1 9 AA 1.07 - Process radiation monitoring 3.4 I system 29.5022 Loss of CRD Pumps / 1 X AKI .02 - Reactivity control 3.6 1 29.5034 Secondary Containment Ventilation X EKI .02 - TRadiation releases 4.1 1 High Radiation I 9 SO0000 High CTMT Hydrogen Conc. I 5 X 3. I I K/A Category Totals: I 2 1 1 Total: 7

BWIi RO Examination Outline Printed: 03/3 I /2008 Facility: Oyster Creek Nuclear Station Form ES-401-1 ES - 401 1 I tl Sys/Evol # I Name K l K2 K3 K4 K5 K6 A1 K5.02 - Valve operation 205000 Shutdown Cooling K5.03 - Heat transfer: 2.7 207000 Isolation (Emergency)

BWR-2, 3 Condenser A4.06 - Shell side makeup 3.8*

207000 Isolation (Emergency) valves: BWR-2,3 Condenser A2.09 - Low suppression 3. I 209001 LPCS pool level A4.1 I - System flow 3.7 ,

209001 LPCS 4.0" p i G L C I I A 1.09 - SBLC system lineup 2 I2000 RPS x K5.02 - Specific logic 3.3

- arrangements K6.03 - Detector drive 2.8 2 1 5003 IRM X motor K4.01 - Rod withdrawal 2 I5004 Source Range Monitor blocks 215005 APRMLPRM X KI .07 - Process computer, performance monitoring I system I 215005 APRMLPRM I A3.05 - Flow I 3.3 1 2 18000 ADS l l D.C. power to ADS valves 3.4*

223002 PCIS/Nuclear Steam I A 1.04 - Individual system relay status 2.6 4.2" 239002 SRVs X K3.02 - Reactor over pressunr.ation A3.06 - Reactor pressure 4.1*

239002 SRVs X K4. I0 - Three element 3.4 3-59002 Reactor Water Level control (main steam flab, Control reactor feedwater flow and reactor water level provide innut) 3.1

~ ~~

Y 2.4.6 - Knowledge symptom 259002 Reactor Water Level based EOP mitigation Control strategies.

K6.04 - Process radiation 2.9 K 1 .O 1 - Emergency 3.8 1

BWK RO Examination Outline Printed: 0313 I /200X Facility: Oyster Creek Nuclear Station

- Tier 2 /Group 1 (RO / SRO) Form ES-401-1 K4 K5 K6 A1 A2 KA Topic IR 2.4.49 - Ability to perform 4.0 without reference to procedures those actions tha require immediate operation of system components and controls.

X A2.02 - Over voltage 2.5 K3.03 - Systems with D.C. 3.4 components (i.e. valves, motors, solenoids, etc.)

K3.03 - Major loads 4.1" powered from electrical buses fed by the emergency generator(s)

X K4.01 - Manualhutomatic 2.8 transfers of control K2.02 - CCW valves 2.9 I A3.01 - Setpoints on 3 .0 I instrument signal levels for normal operations, warnings, and trips that are applicable to the CCWS Group Poi] Total: 26 2

BWR RO Examination Outline Printed: 03/3 1/2008 Facility: Oyster Creek Nuclear Station ES - 401 ~-

Form ES-401-1 I I I Svs/Evol # / Name IK1 IK2 4 4 G KATopic 1R #

A2.1 1 - Valve openings 2.6 1 sc1 A3.01 - Control rod position 3.7 I 55 Mechanism X 2.1.32 - Ability to explain 3.4 II 201006 RWM and apply system limits dnd 5b precautions.

I 202002 Recirculation Flow Control I I AI .03 - MG set generator current, power, voltage 2.5* 1

~

57 K4.06 - Pump motor 2 19000 RHlULPCI:Torus/Pool cooling: Plant-Specific 2.7 5%

223001 Primary CTMT and Aux.

II K2.09 - Drywell cooling fans: Plant-SDecific K5.06 - Vacuum breaker 226001 RHR/I,PCI: CTMT Spray operation I I A3.02 - thterlock operation I I

3.1 I

I 24 I000 Reactor/Turbine Pressure 1 I KI .24 - Main generator 1 2,7 I 1 b.2 4.0 29000 1 Secondary CTMT I I K3.01 - tOff-site radioactive release rates I53 290002 Reactor Vessel Internals K6.05 - SBLC 3.3 I b,y 1 290003 Control Room HVAC I I I A4.04 - Environmental conditions 1 2.a I I IL6 WA Category Totals: 1 1 I lI 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 Category KA# Topic IR I

___I Conduct of Operations 2. I . 1 Knowledge of conduct of operations requirements. 3.1 1

_c_

2 1.7 Ability to evaluate pldnt performance and make 3.7 I operaticma1judgments b a e d on operating characteristics, reactor 3ehdvior. and inatrumenl interpretation 2.1.25 Ability to obtain and interpret station reference materials 2.8 such as graphs, monographs, and tables which contain aerforinance data.

iubtotal:

Equipment Control 2.2. I3 Knowledge of tagging and clearance procedures. 3.6 1 h4 2.2.27 Knowledge of the refueling process. 2.6 I 7 0 Subtotal: 2 Radiation Control 2.3.9 Knowledge of the process for performing a containment 2.5 7' purge.

2.3.1 1 Ability 10 control radiation releases. 2.1 7 '2 Subtotal: 2 Emergency Plan 2.4.2 Knowledge of system set points, interlocks and automatic 73 actions ,issociated with EOP entry conditions.

2.4.24 I

Knowledge of loss of cooling water procedures.

I 3.3 I I

I 74 I I I 2.4.39 Knowledge of the RO's responsibilities in emergency plan implementation.

3.3 1 75 Tier 3 Point Total: 10 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 1: Fundamental Knowledge or Simple Memory (low cognitive level) 0 Bases or purpose (B) 0 Definitions (D) 0 Facts (F) 0 Interlocks, setpoints or system (singular) response (I)

Procedure steps or cautions (P) 0 Structures and locations (S) 0 Terminology (T)

Level 2: Comprehension (high cognitive level) 0 Describing or recognizing relationships (DR) 0 Showing differences and similarities (DS) 0 Recognizing interaction between systems (plural), including consequences and implications (RI) 0 Re-wording or re-phrasing information (DW)

Level 3: Application, Analysis, Synthesis (high cognitive level) 0 Create something new (CSN)

Predict an event or outcome (PEO) 0 Solve a problem using knowledge and its meaning (SPK) 0 Solve a problem using references (SPR)

Page 1 of 219

ES-401 BWR Examination Outline Form ES-401-1 Facility: Oyster Creek Nuclear Station Printed: 03/31/2008 Date Of Exam: 04/14/2008

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.
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 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' I 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.

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 E/APE # / Name / Safety Function K1 K2 K3 IR #

29500 1 Partial or Complete Loss of Forced 4. I Core Flow Circulation / I & 4 conditions for operations and safety I \

295003 Partial or Complete Loss of AC Pwr 3.6

/6 I2 295006 SCRAM / 1 3.8 I 3 I 295023 Refueling Acc / 8 I I I 4.6" I 295024 High Drywell Pressure / 5 I I I 1 4.4" 1 5 29.5025 High Reactor Pressure / 3 295030 Low Suppression Pool Wtr Lvl I 5 I I I X mitigation strategies.

EA2.03 - Reactor pressure 4.0 3.9 IC:

1 7 WA Category Totals: 0 0 0 01 4 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 A2 G KA Topic(s) IR #

295009 Low Reactor Water Level / 2 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.

I 295014 Inadvertent Reactivity Addition / I AA2.01 - Reactor power 295032 High Secondary Containment Area EA2 03 - Cause of high area Temperature / 5 temperature Group Point Total:

BWR SRO Examination Outline Printed: 03/3 1/2008 Facility: Oyster Creek Nuclear Station 3s - 401 Plant Systems - Tier 2 / Group 1 (RO / SRO) Form ES-401-1 I I Sys/Evol # / Name Kl K2 K3 A2 A3 IR #

20.5000 Shutdown Cooling X 2.6 I 2 I2000 RPS I l l X I A2.1 1 - Main steamline 4.I 3.3 26 1000 SGTS system status criteria which require the notification of plant personnel.

263000 DC Electrical Distribution 2.2.25 - Knowledge of bases 3.7 in technical specifications for limiting conditions for operations and safety limits.

300000 Instrument Air X A2.01 - Air dryer and filter 2.8 malfunctions WA Category Totals: 0 0 0 3 0 21 Group Point Total:

BWR SKO Examination Outline Printed: 03/3 1 /2008 Facility: Oyster Creek Nuclear Station Plant Systems - Tier 2 / Group 2 (RO / SRO)

ES - 401 --

Form ES-401-1 I

I I G KA Topic IR #

X 2.4.30 - Knowledge of 3.6 I which events related to system operations/status should be reported to outside agencies.

A2.07 - High fuel pool 3.2 I temperature IA2.01 - Pump trip 3.7 I I K/A Category Totals:

II Group Point Total: 3 I

Generic Knowledge and Abilities Outline (Tier 3)

UWR Sf30 Examination Outline Printed: 03/3 I /2008 Facility: Oyster Creek Nuclear Station Date of' Exam: Form ES-401-3 Category -

KA # Topic -

IR -#

Conduct of Operations chemistlv within allowable limits.

Subtotal: 2 1

~~ ~~ ~

Equipment Control 2.2.5 Knowledge of the process for making changes iri the 2.7 I 21 facility k s described in the safety analysis report.

2.2. I 1 Knowledge of the process for controlling temporary 3.4* I 22 changes.

Subtotal: 2 1 Radiation Control 2.3.1 Knowledge of I O CFR 20 and related facility radiation 3.0 1 z3 control requirements.

2.3.2 Subtotal

I Knowledge of facility ALARA program. 1 2 " ) I 2

2 "I

~ ~ ~

Emergency Plan 2.4.37 Knowledge of the lines of authority during an emergency. 3.5 1 25 I Subtotal: 1 1 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/ (18/25 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)

Level 2: Comprehension (high cognitive level) 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)

Level 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)

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

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

SRO 295008 AA2.01 295008 AA2.01 A valid operationally relevant SRO question for this KA 112 could not be constructed. KA 295014 AA 2.01 was randomly selected as a replacement.

  • RO 295001 AK3.03 295001 AK3.03 presents overlap with RO administrative JPM material. KA 111 I 295001 AK3.05 was randomly selected as a replacement.

RO 295034 EK1.01 295034 EK1.01 There is no relationship between the USAR design 112 function of the Standby Gas Treatment System and personnel protection.

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

RO 21 5004 K2.01 215004 K2.01 This KA was duplicated on the audit exam. KA 215004 211 K4.01 was randonly selected as a replacement.

RO 1 21 8000 A2.04 218000 A2.04 ADS is manually prevented from automatic operation in both 211 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 a replacement.

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

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

KA 262001 2.4.49 was randonly selected as a replacement.

RO 300000 K4.02 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.

RO 219000 K4.08 219000 K4.08 There is no design feature or interlock which provides for 2/2 I I suppression pool cooling that ensures adequate pump net positive suction I I head. KA 219000 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 not be constructed. KA 290003 A4.04 was randomly selected as a replacement.

  • RO 2.2.24 2.2.24 A valid operationally relevant RO question for this KA could not be 3 constructed. 2.2 13 was randomly selected as a replacement.
  • RO 2.4.50 2.4.50 This generic KA is best suited in the operating exam portion.

3 Generic 2.4.43 was randomly selected as a replacement.

RO 295026 2.4.31 295026 2.4.31 This generic KA is best suited in the operating exam 111 portion. 295026 2.2.22 was randomly selected as a replacement.

SRO 214000 A2.02 214000 A2.02 A valid operationally relevant SRO question for this KA could 212 not be constructed. KA 233000 A2.07 was randomly selected as a replacement.

  • SRO 2.4.9 2.4.9 A valid operationally relevant SRO question for this KA could not be 3 constructed. Generic 2.4.42 was randomly selected as a replacement.
  • RO 295024 EK1.01 295025 EKl.01 A valid operationally relevant RO question for this KA could 111 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 could not be constructed. 201001 2.4.30 was randomly selected as a replacement.

  • 2.4.43 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 I

Facility: Ovster Creek Date of Examination: 4/14/2008 Examination Level: RO SRO 0 Operating Test Number: OC 2008 Administrative Topic TYPe Describe activity to be performed (See Note) Code*

1 _ - - ~ _ _ _ - -

Complete the Technical Specification Log Sheet.

Conduct of Operations 2.1.18/2.9 (Admin R01)

Perform a Manual Core Heat Balance Calculation.

Conduct of Operations 2.1.20/4.3 (Admin R 0 2 )

~ _ __

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

Radiation Control Determine RPV Water Level Instrument Availability.

Emergency Plan R, M 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 (53 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 Date of Examination: 4/14/2008 Examination Level: RO 0 SRO Operating Test Number: OC 2008 Administrative Topic Describe activity to be performed (See Note)

. -~ - - - - - __ __ -

Review a Shift Turnover Checklist. 2.1.3/3.4 (Admin Conduct of Operations SRO1)

Plant Personnel Event Notification. 2.1 .,14/3.3 (Admin Conduct of Operations R. N SH02)

Review Acceptance Criteria for a Completed Surveillance.

Equipment Control R. M 2.:1.12/3.4 (Admin SR03)

Radiation Control Authorize Emergency Exposures. 2.3.413.1 (Adrnin SR04)

Determine Emergency Classification and Protective Action Emergency Plan 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 Facility: Ovster Creek Date of Examination: 4/14/2008 Exam Level: RO SRO-I c] SRO-U fl Operating Test Number: OC 2008 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 S, D 1 1

- - _ _ __ _ _ _ ~ - -

b. Respond to high Core Spray pump amps during surveillance (209001

- + - -A,- -S,N I 2 A4.01

~-__ ~

8/3.6) NRC JPM

_ _ _SIM2-

~.__ - - -_- - - _ _ _ --_ .~ --__ ~

c Perform Anticipatory Scram Turbine Stop Valve Closure Test with RPS A, S , D, P 3 a_ctuatlon_C241000K3.0141!311 N~5-JP-MsIM3- -- ___ ~~ __

d Control RPV pressure with the IC Tube Side Vents (207000 K1.02 4 40/4-2) NRC JPMSIM4 _ _ - -~ ~- _~

e Vent the Primary Containment through the Standby Gas Treatment A, S,D 5 S!@?!! L2230_01K1 0 9 4/3.6)_NP_C_L!MSIM5--_- _ _ _ _ - -_ --

f. Transfer 4160 VAC Busses in preperation fcr a manual scram (262001 A, S , D, P 6 K4.02 2 9/3.3) - ____

__ NRC JPM SIM6 - _ _ _ _ _ - - -- - _ _ - -__ _

g. Perform an APRM Gain Adjustment (215005 A4.03 3.2/3.3 NRC JPM S, N 7 SIM7 - .~
h. Swap Control Room Ventilation Fans (290003 A4.02 2.8/2.8) NRC JPM S,A 9 SIM8
  • Type Codes Criteria for RO / SRO-I / SRO-U

(A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank -

<91 1 5 4 (E)mergency or abnormal in-plant -

> 1 / 21 I 2 1 (L)ow-Power I Shutdown -

2 1 1 21 1 1 1 (N)ew or (M)odified from bank including 1(A) > 2 / 22 I21 (P)revious 2 exams - 3 15 3 I 5 2 (randomly selected)

( W A > l l 21 1 2 1 (S)imulator ES-30-, Page 23 of 27

-- _____ ~~ ~

ES-301 ..

Control Room/m-Plant

- Systems Outline Form ES-301-2 Facility: Ovster Creek Date of Examination: 4/14/2008 -

Exam Level: RO SRO-I SRO-U n Operating Test Number: OC 2008 I

I 1

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

Z M l -___-

A4

- 01 3 - 8/3.6lNRC System / JPM Tit13

a. Startup a Reactor Recirculation Pump (202001 A4.01 3.7/3 7) NRC JPM

~ _ _ -_ JPM SIM2 _ - _ _ - ~ -~-

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

~-

b Respond to high Core Spray pump amps dirring surveillance (209001

c. Perform Anticipatory Scram Turbine Stop Valve Closure Test with RPS d Control RPV pressure with the IC Tube Side Vents (207000 K1 02

- 40/4_12_NRCJPM%L- _ -________~

e Vent the Primary Containment through the Standby Gas Treatment

- System (223001 K1.09 3.413.6) NRC JPM SIM5 11 Type Code*

_ _A:S

_:D

_:I_

A, S , D 1

Sa'ety Functio 4

5 1

f . Transfer 4160 VAC Busses in preperation for a manual scram (262001 A, S, D,P 6 K4 02 2 9/3.3) NRC JPM_ SIM6 _ I

- 1 t g Perform an APRM Gain Adjustment (215005 A4 03 3 2/3 3 NRC ' 7 SIM7 h

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 J . Perform backup methods for critical functions in-plant (259001 K1 07 2 92

! 9) NRC-JPMPLANT2 - - ~-

k. Lineup Fire Water to Core Spray to raise torus water level (286000 K1.05 D, E, R, P 2

8 3.2/3.2)NRC JPM PLANT3

  • Type Codes Criteria for RO / SRO-I / SRO-U

(A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank <91

- sa 1 5 4 (E)mergency or abnormal in-plant >

- 1 / 2 1 121 (L)ow-Power I Shutdown -

>1/ 21 121 (N)ew or (M)odified from bank including 1(A) -

> 2 / z2 I 2 1 (P)revious 2 exams < 3 15 3

- I 5 2 (randomly selected)

( W A > 1 / 21 1 2 1 (S)imulator ES-30', Page 23 of 27

~~~~~~~- - S " L OC ILT 07-1 NHC Exam Scenario NRC SIM 2 Scenario Outline Facility: Ovster Creek Scenario No.: NRC SIM 2 Op Test No.: OC 2008 Examiners: Operators:

Initial Conditions:

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.

Turnover:

Complete 610.4.002, Core Spray Pump Operability Test for normal surveillance.

Event No.

Malf. No. 1 Event Type* I Event Description 1

SWI-RPS034 1 1 1 N

TS BOP SRO Perform Automatic Scram Contactor Test, 619.4.025 MAL-EDS003D 1 1 C BOP [ Sespond to a loss 480 VAC USS 181 with failure of TBCCW to auto start.

to loss of main generator isophase Fan #l.

GEA005B 4 to an upscale failure of APRM 4.

NIS020D 5

6 MAL-RCP003A ANN-H5c I1 I1 II I

C TS C

I BOP SRO ATC I

Respond to recirculation pump seal leak.

Responds to a high temperature control rod 46-15.

MAL-ICSO2B 1 1M Crew 1 Respond to an Isolation Condenser B tube leak with rising fuel failures.

MAL-CFW003A, C Crew Respond to the loss of all Feedwater/Condensate.

38,3C t (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Transient, (TS) Tech Specs NRC SIM 2 Page 1 of 27

tl*--p-xx' I_-x-OC ILT 07-1 NFC Exam Scenario NRC SIM 3 Scenario Outline Facility: Ovster Creek Scenario No.: NRC SIM 3 Op Test No.: OC 2008 Examiners: .- Operators:

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 Event Event Malf. No.

No. Description

-~ ~~ - ~

The BOP will place Feedwater Pump B in service IAW Procedure 1

317.

MAL-2 CRD008-2 C ATC Withdraw control rods and respond to uncoupled rod.

23 1 3 The ATC will raise rector power by raising reactor recirculationflow.

4 The BOP will respond to an EPR failure.

TCSOlO

~ ~~~ ~ ~ ~ -

5 ANN-T4b SRO The SRO will respond to loss of oil to EDG 1.

LOA-I 1 6

+ RBCOOg MAL-RCUO14 CRD002 &

MAL- -2 CRDOOG I 1 C

T"S BOP ATC SRO 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.

23 1 MAL-NSS025E 1 1M Crew The crew will respond to a leaking EMRV E and an electric ATWS.

PMP-9 SLCOOlN c Crew Respond to a SLC Pump shaft break.

SLC002A 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 Scenario Outline Facility: Ovster Creek Scenario No.: NRC SIM 4 Op Test No.: OC 2008 Examiners: -- Operators:

Initial Conditions:

The plant is at 95% power 0 EDG1 is 00s to replace a starting motor.

0 TBCCW Pump 2 and Air Compressor 3 are 00sfor maintenance.

The RWM is inoperable and bypassed.

Turnover:

Withdraw control rod 22-1 1 Perform 609.4.001, Isolation Condenser Valve Operability and In Service Test No.

1 I

Malf. No.

Event Type*

Event Description MAL-1 CRDOO7 3 C ATC Responds to control rod 22-11 stuck at 00 on withdrawal 21 1

- ~~

N BOP Performs 609.4.001, Isolation Condenser Valve Operability and 2 VLV-ICS06 In Service Test and responds to failure of V-14-31 (IC A) to re-TS SRO open.

MAL- C BOP 3 Responds to a failure of 480 VAC Bus USS 1A2.

EDSO036 TS SRO MAL-4 C BOP The BOP will respond to an oscillating reactor recirculation pump.

RFC003A MAL-1 5: ; ; T R ATC Responds to high turbine vibrations.

TSlOl8A MAN- Responds to a leak in RPV water level instruments common 6 C ATC NIS021E variable leg to ID13A and ID13C.

~-

MAL-7 NSSOl7A M Crew Responds to a primary leak in the Primary Containment.

MAL- Respond to a loss of offsite power and failure of all Core Spray 8 C Crew RPS007A Pumps.

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

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