ML063060180

Exam Oct. 2006 - Draft Outlines (Folder 2)

ML063060180
Person / Time
Site:	Oyster Creek
Issue date:	07/19/2006
From:	AmerGen Energy Co
To:	D'Antonio J Operations Branch I
Sykes, Marvin D.
References
Download: ML063060180 (35)

Text

Form ES-40 1-1 ES-401 BWR Examination Outline Facilitv:

Oyster Creek Nuclear Station Printed: 03/22/2006 8

Note:

1.

2.

3.

4.

5.

6.

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).

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 21 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.

Systemdevolutions 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 ES401, Attachment 2, for guidance regarding the elimination of inappropriate WA 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.

Absent a plant-specific priority, only those WAS 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.

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 WA Catalog, but the

8.

topics must be relevant to the applicable evolution or system.

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 KIA catalog, and enter the WA numbers, descriptions, IRs, and point totals (#) on Form ES401-3. Limit SRO selections to WAS that are linked to I O CFR 55.43.

Note: This form deviates from theNUREG-1021 Form ES-401-1 by theaddition oftheK and A column under the SRO Only Points. This allows sampling all Fuel Handling System KAs as required by ES-401.

1

BWR SRO Examination Outline Facility:

Oyster Creek Nuclear Station Printed: 03/22/2006 ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 (RO / SRO)

Form ES-401-1 1

BWR SRO Examination Outline

. Facility:

Oyster Creek Nuclear Station Printed: 03/22/2006 ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 (RO / SRO)

Form ES-401-1 criteria which require the notification of 1

BWR SRO Examination Outline Printed: 0312212006 Facility:

Oyster Creek Nuclear Station Plant Systems - Tier 2 I Group 1 (RO / SRO)

Form ES-401-1 ES - 401 I

I I

I SyslEvol # I Name 2 15004 Source Range Monitor 300000 Instrument Air I O 1 O 1 O WA Category Totals:

I IR 3.7 1

3.7 1

4.0 1

3.2 1

4.0 1

1

BWR SRO Examination Outline Printed: 03/22/2006

, Facilify:

Oyster Creek Nuclear Station Plant Systems - Tier 2 / Group 2 (RO / SRO)

Form ES-401-1 ES - 401

~

Generic Knowledge and Abilities Outline (Tier 3)

BWR SRO Examination Outline Printed: 03/22/2006 Facility:

Oyster Creek Nuclear Station Form ES-401-3 2.1.25 1

I f

Ability to obtain and interpret station reference 3.1 1

materials such as graphs, monographs, and tables which contain performance data.

Category Radiation Control Conduct of Operations 2.3.10 KA#

Topic m

i I

I I

Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure.

2.1.4 3.3 1

2.4.46 Knowledge of shift staffing requirements.

Ability to verify that the alarms are consistent 3.6 1

with the plant conditions.

I 3.4 1

2.2.9 2.2.3 1 i=

Knowledge of the process for determining if the proposed change, test or experiment increases the probability of occurrence or consequences of an accident during the change, test or experiment.

Knowledge of procedures and limitations involved in initial core loading.

Category Total:

3.3 1

2.9*

2 I

I I

Emergency Plan I 2.4.27 Knowledge of fire in the plant procedure.

I 3.5 I 1

Generic Total:

7 1

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

Oyster Creek Nuclear Station Printed: 03/22/2006 t

1' Date Of Exam:

0911 812006 RO WA Category Points I

SRO-Only Points Note:

1.

2.

3.

4.

5.

6.

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).

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 -+I from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.

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 K/A 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.

Absent a plant-specific priority, only those WAS 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.

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 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. 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.

Note: This form deviates from theNUREG-1021 Form ES-401-1 by the addition oftheK and A column under the SRO Only Points. This allows sampling all Fuel Handling System KAs as required by ES-401.

1

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~

~

_ _ ~

BWR RO Examination Outline Printed: 0312212006 Facility:.

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

Form ES-401-1 295025 High Reactor Pressure I 3 295026 Suppression Pool High Water Temp. I5 295028 High Drywell Temperature I 5 E/APE # / Name / Safety Function I K1 X

295001 Partial or Complete Loss of Forced Core Flow Circulation I 1 & 4 295003 Partial or Complete Loss of AC Pwr 295004 Partial or Complete Loss of DC Pwr 295004 Partial or Complete Loss of DC Pwr 295005 Main Turbine Generator Trip I 3 1

295006 SCRAM I 1 295016 Control Room Abandonment 17 295018 Partial or Total Loss of CCW I 8 295019 Partial or Total Loss of Instrument Air I 8 295021 Loss of Shutdown Cooling 14

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I 295023 Reheling Acc I 8 295024 High Drywell Pressure I 5 295030 Low Suppression Pool Wtr Lvl I 5 1

29503 1 Reactor Low Water Level / 2 295037 SCRAM Condition Present and Reactor Power Above APRh4 Downscale or unknown/ 1 I

295038 High Off-Site Release Rate I 9 600000 Plant Fire On Site 1 8 WA Category Tot=:

I 4-1

BWR RO Examination Outline Facility:, Oyster Creek Nuclear Station Printed: 03/22/2006 ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 (RO / SRO)

Form ES-401-1 1

BWR RO Examination Outline Facility:

Oyster Creek Nuclear Station Plant Systems - Tier 2 / Group 1 (RO / SRO) 5s - 401 I

I I

I I

Sys/Evol # / Name lK1 IK21K31K41K5(K6 205000 Shutdown Cooling I

I I

I I

I I

I I

I I

I 207000 Isolation (Emergency)

X Printed: 03/22/2006 Form ES-401-1 1

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BWR RO Examination Outline

, Facility:

Oyster Creek Nuclear Station Printed: 0312212006 ES - 401 SysIEvol # I Name 262001 AC Electrical Distribution 262002 UPS (ACIDC)

~~

263000 DC Electrical Distribution 264000 EDGs 264000 EDGs 300000 Instrument Air I 400000 Component Cooling Water K/A Category Totals:

I Plant Systems - Tier 2 I Group 1 (RO / SRO)

Form ES-401-1 2

BWR RO Examination Outline

, Facility Oyster Creek Nuclear Station Plant Systems - Tier 2 / Group 2 (RO / SRO) 3s - 401 I

Sys/Evol # I Name K1 20 100 1 CRD Hydraulic 201002 RMCS 20200 1 Recirculation

~~

202002 Recirculation Flow Control 204000 RWCU I

2 15001 Traversing In-Core Probe 223001 Primary CTMT and Aux.

233000 Fuel Pool Cooling/Clean-up 245000 Main Turbine GeneratorJAux 259001 Reactor Feedwater 286000 Fire Protection I

1 WA Category Totals:

Printed: 03/22/2006 Form ES-401-1 1

2.1.19 Ability to use plant computer to obtain and evaluate parametric information on system or comuonent status.

2.3.2 Knowledge of facility ALAFL4 program.

2.4.32 conditions.

Knowledge of operator response to loss of all 3.3 1

annunciators.

i Generic Knowledge and Abilities Outline (Tier 3)

BWR RO Examination Outline Printed: 03/22/2006 Facilitv:

Oyster Creek Nuclear Station Form ES-401-3 Category ToDic IR t!

Conduct of Operations I 3.8 I I

I 2.1.8 I Ability to coordinate personnel activities outside the control room.

3.0 1

I I

Category Total:

2 1

Equipment Control Ability to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivitv.

3.7 1

2.2.1 2.2.2 2.2.28 Ability to manipulate the console controls as required to operate the facility between shutdown and designated vower levels.

4.0 1

Knowledge of new and spent fuel movement urocedures.

2.6 1

~~

Category Total:

3 Radiation Control 2.5 2.3.4 Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized.

2.5 2.3.9 Knowledge of the process for performing a containment vursze.

2.5 Category Total:

Emergency Plan I

3.9 Knowledge of system set points, interlocks and I 2*4.2 I automatic actions associated with EOP entrv 1

Generic Total:

10 1

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

Oyster Creek Nuclear Station Printed : 07/28/2006 Date Of Exam:

09/18/2006 1

I RO w A Category Points I

SRO-Only Points Note:

1. Ensure that at least two topics from every WA category are sampled within each tier of the RO and SRO-only outlines (ie., except for one category in Tier 3 of the SRO-only artline, 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 kl 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,, 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. 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 WA Catalog, but the topics must be relevant to the applicable evolution or system.

8. On the following pages, enter the K/A 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 WA numbers, descriptions, IRs, and point totals (#) on Form ES401-3. Limit SRO selections to WAS that are linked to 10 CFR 55.43.

BWR RO Examination Outline Facility:

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

Printed : 07/2 8/200f Form ES-401-

'L

'L E/APE # / Name / Safety Function K1 K2 K3 295001 Partial or Complete Loss of Forced Core How Circulation I I & 4 295003 Partial or Complete Loss of AC Pwr 1 6 295004 Partial or Complete Loss of DC Pwr 1 6 295004 Partial or Complete Loss of DC Pwr X

X X

16 I I I 295005 Main Turbine Generator Trip / 3 X

295006 SCRAM I 1 X

295016 Control Room Abandonment / 7 I

I I 29501 8 Partial or Total Loss of CCW I 8 I

I I

29501 9 Partial or Total Loss of Instrument Air 1 8 295021 Loss of Shutdown Cooling / 4 I

I I 295023 Refueling Acc I 8 I I I 295024 High Drywell Pressure I 5 X

I x I I 295025 High Reactor Pressure I 3 I I I 295026 Suppression Pool High Water Temp. 1 5 295028 High Drywell Temperature I 5 X

295030 Low Suppression Pool Wtr Lvl 1 5 295031 Reactor Low Water Level 1 2 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown / 1 295038 High Off-Site Release Rate I 9 X

AK1.04 - -(Limiting cycle oscillation:

Plant-Specific AK1.02 - Load shedding for system operating parameters which are entry-level conditions for technical specifications.

AAI.05 - Reactor recirculation EA2.01 - Suppression pool level 2.4.3 1 - Knowledge of annunciators alarms and indications, and use of the response instructions.

EA2.02 - Reactor water level 3.2 1

3.2 1

3.6 1

4.2*

1 3.3 1

3.3 1

3.4 1 ;;

4.1 4.1* T I

I I

BWR RO Examination Outline Printed: 07/28/2001 Facility:

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

Form ES-401-

'W

BWR RO Examination Outline Facility:

Oyster Creek Nuclear Station Printed: 07/28/2006 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 (RO / SRO)

Form ES-401-ES - 401

BWR RO Examination Outline Facility:

Oyster Creek Nuclear Station Printed: 0712812 ES - 401 Sys/Evol # I Name 205000 Shutdown Cooling 207000 Isolation (Emergency)

Condenser 207000 Is01 ation (Emergency)

Condenser 209001 LPCS 21 1000 SLC 2 1 1000 SLC 2 12000 RPS 215003 IRM 215003 IRM 215004 Source Range Monitor 215005 AF'RMLPRM 2 15005 APRMLPRM 2 1 8000 ADS 223002 PCISINuclear Steam Sumlv Shutoff 239002 SRVs 259002 Reactor Water Level Control 261000 SGTS 26 1000 SGTS Plant Systems - Tier 2 / Group 1 (RO / SRO)

Form ES-41 IR 3.3 4.3" 3.8*

2.5 3.2 3.9 4.0 3.1 2.5 2.6 4.1 3.4 4.4*

2.8 3.2 3.1 2.7 3.2 1

BWR RO Examination Outline Facility:

Oyster Creek Nuclear Station 300000 Instrument Air 400000 Component Cooling Water K/A Category Totals:

X 2

2 2

3 2

Printed: 0712812 Form ES-41 2

B WR RO Examination Outline Facility:

Oyster Creek Nuclear Station Printed: 0712812 1

Generic Knowledge and Abilities Outline (Tier 3)

Conduct of Operations 2.1.8 Ability to coordinate personnel activities outside the control room.

2.1.19 Ability to use plant computer to obtain and evaluate parametric information on system or component status.

B W R RO Examination Outline Printed: 07/28/2006 3.8 1

3.0 1

Facility:

Oyster Creek Nuclear Station Form ES-401-3

-\\--

2.3.2 Knowledge of facility ALARA program.

Equipment Control Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized.

Knowledge of the process for performing a containment purge.

Radiation Control 2.5 1

2.5 1

2.2.1 2.4.2 2.4.32 2.2.2 Knowledge of system set points, interlocks and 3.9 1

automatic actions associated with EOP entry conditions.

Knowledge of operator response to loss of all 3.3 1

annunciators.

2.2.28 Ability to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity.

Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels.

Knowledge of new and spent fuel movement Drocedures.

3.7 4.0 2.6 1

1 1

Category Total:

3 I 2.5 I 1

2.3.4 2.3.9 Emergency Plan Generic Total:

10

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ES-401 Record of Rejected WAS Form ES-401-4 Tier /

Group 2/2 2/2 2/2 1 / I Randomly Selected KIA 234000 K4.03 292002 A2.06 293003 2.4.6 29501 9 2.2.25 Reason for Rejection The computer program used to generate the randomly selected KAs for the written exam erronously, automatically selects 234000 Fuel Handling Equipment as one of the three Tier 2IGroup 2 topics for the SRO exam. All three questions were de-selected and three new, manually, randomly selected KAs (from the Tier 2IGroup 2 pool) were inserted (201001/A2.03, 21 4000/2.2.22, 239001 /2.1.32).

The computer program used to generate the randomly selected KAs for the written exam erronously, automatically selects 234000 Fuel Handling Equipment as one of the three Tier 2/Group 2 topics for the SRO exam. All three questions were de-selected and three new, manually, randomly selected KAs (from the Tier 2IGroup 2 pool) were inserted (201001/A2.03, 21 4000/2.2.22. 239001 /2.1.32).

The computer program used to generate the randomly selected KAs for the written exam erronously, automatically selects 234000 Fuel Handling Equipment as one of the three Tier 2/Group 2 topics for the SRO exam. All three questions were de-selected and three new, manually, randomly selected KAs (from the Tier 2/Group 2 pool) were inserted (201001/A2.03, 214000/2.2.22, 239001/2.1.32).

Knowledge of bases in technical specifications for limiting conditions for operations and safety limits is not a required task for Reactor Operator candidates. A new, manually, randomly selected generic KA for 29501 9 was inserted (295019/2.1.33).

ES-401, Page 27 of 33

ES-301 Administrative ToDics Outline Form ES-301-1 Facility: Ovster Creek Examination Level: RO SRO 0 Operating Test Number: NRC 2006-1 Date of Examination: 9/18/2006 Administrative Topic (See Note)

Conduct of Operations Conduct of Operations Equipment Control I------

I Radiation Control Emergency Plan h

Type Code*

D, S N, S Describe activity to be performed Perform Manual Heat Balance Calculation (G2.1.7)

Perform Core Daily Checks (G2.1.2)

Plan a Clearance (Tagout) (G2.2.13)

Determine RadiationKontamination Area Access Requirements Based on Current Exposure, Survey Map, and Administrative Limits (G2.3.1)

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)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

ES-301 Ad m i n i st rat i ve Topics 0 ut I i ne Form ES-301-1 Facility: Ovster Creek Examination Level: RO SRO Date of Examination: 9/18/2006 Operating Test Number: NRC 2006-1 Administrative Topic (See Note)

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

N, R Describe activity to be performed Review/Approve Manual Heat Balance Calculation (G2.1.7)

Determine Shift Operating Compliment (G2.1.4)

Evaluate Surveillance Acceptance Criteria (Containment Spray System IST) (G2.2.12)

Determine if Plant Operator Can Acess Radiation Area Based on Current Exposure and Emergency Limits (G2.3.1)

Make an Emergency Plan Classification and Complete Notification Form (G2.4.41)

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.

(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)

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ES 301, Page 22 of 27

ES-301 Control Roomhn-Plant Systems Outline Form ES-301-2 Facility: Ovster Creek Exam Level: RO SRO-I 0 SRO-U 0 Date of Examination: 911 8/2006 Operating Test Number: NRC 2006-1 I Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety 1

1 Function System / JPM Title I In-Plant Systems* (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) 1 i. Align Core Spray to the CST for Emergency Operations (295030 EAl.01) 1 D, E, R 1

2 (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

, (R)CA 4-6 I' 4-6 I 2-3 ES-301, Page 23 of 27

ES-301 Control Roomhn-Plant Systems Outline Form ES-301-2 Facility: Ovster Creek Exam Level: RO SRO-I SRO-U 0 Date of Examination: 911 812006 Operating Test Number: NRC 2006-1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

I Safety System / JPM Title Type Code*

Function

a. Respond to a Power Oscillation (Recirc Flow Oscillations) w/ Recirc M, A, s 1

Pump Discharge Valve Failure to Close (202002 A2.01)

b.

I c. Perform EMRV Operability Test w/ Stuck Open EMRV (239002 A2.03)

[

N, A, S, L 1 3

d. Shutdown Core Spray After an Inadvertent Initiation w/ CS Booster

e. Vent the Torus for Hydrogen Control (500000 EA1.03)

D, A, s 4

N, S, L 5

Pump Failure to Trip (209001 A4.01)

f. Perform Emergency Diesel Generator Load Test w/ Engine High M, A, S 6

D, s 7

Temperature Alarm (264000 A4.04)

g. Bypass RPS Scram Logic Trips (295037 EA1.01)

h. Shutdown SGTS After Auto Initiation w/ Reactor Building Supply Fan 1

M, A, S 1

9 Trip (288000 A4.01) 1 1

In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i.

2

j. Remove Static Charger C1 From Service (263000 K1.02)

D, R 6

Align Core Spray to the CST for Emergency Operations (295030 EA1.01)

D, E, R riteria for RO / SRO-I / SRO-U (A) I tern ate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1 (A)

(P)revious 2 exams (WCA (S)im ulator 4-6 / 4-6 / 2-3 ES-301, Page 23 of 27

ES-301 Control Roomhn-Plant Systems Outline Form ES-301-2 Facility: Oyster Creek Exam Level: RO 0 SRO-I 0 SRO-U Date of Examination: 911 812006 Operating Test Number: NRC 2006-1 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

Safety Type Ode*

Function System / JPM Title

a.

b.

11 c. Perform EMRV Operability Test w/ Stuck Open EMRV (239002 A2.03)

I N, A, S, L I

3

d. Shutdown Core Spray After an Inadvertent Initiation w/ CS Booster

e.

D, A, S 4

Pump Failure to Trip (209001 A4.01)

I I

I I

h. Shutdown SGTS After Auto Initiation w/ Reactor Building Supply Fan M, A, S 9

Trip (288000 A4.01) 11 i. Align Core Spray to the CST for Emergency Operations (295030 EA1.01) I D, E, R I 2

j.

k. Lineup Firewater to A Isolation Condenser (286000 G2.4.35)

D, E, R 8

8 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 li

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

(P)revious 2 exams (S)im ulator

( W A Criteria for RO / SRO-I / SRO-U 4-6 / 4-6 / 2-3 c 9 / 5 8 1 5 4

> 1 / 21 / r l

> 1 / 2 1 / r l

> 2 / 2 2 1 2 1

> 1 / 2 1 / ? I

- 3 / 5 3 / 5 2 (randomly selected)

ES-301, Page 23 of 27

Appendix D Scenario Outline Event No.

1 2

Facility: Oyster Creek Malf. No.

Event Type*

Event Description N

R RO Withdraw control rods.

BOP Transfers from Low Flow Regulating Valve (LFRV) to the Main Feed Regulating Valve (MFRV).

Scenario No.: NRC 1 Op Test No.: NRC 2006-1 Examiners:

Operators:

Initial Conditions:

The reactor is starting up, after a 5-day forced outage, with the MODE SWITCH in STARTUP.

Cleanup Pump B is out of service for motor replacement, and is expected to return to service tomorrow.

Isolation Condenser System A was removed from service two hours ago and is isolated, due to motor operated valve torque switch replacement. Technical Specifications applicability has been reviewed.

The system is expected to return to an operable status in 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

IRM 14 failed during the control rod withdrawal to critical, and is BYPASSED. Technical Specifications applicability has been reviewed and an IR has been generated.

Surveillance test 607.4.004, Containment Spray and Emergency Service Water SystemlPump Operability and Comprehensive/Preservice/Post-Maintenance lnservice Test, is in progress at step 6.14 for a normal surveillance. The system has been in operation for 15 minutes.

Instrument Maintenance is calibrating the drywell wide range pressure transmitters IAW 604.3.01 8, Wide Range Drywell Pressure Calibration.

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

Total Malfunctions (5-8):

8 1

Malfunctions after EOP entry (1-2)

Abnormal Events (2-4) 3 Major Transients (1 -2) 2 EOP Contingencies w/ substantive actions (0-2)

Critical Tasks (2-3) 2 EOPs entered requiring substantive actions (I

-2) 2 0

Event 2

Type Position Description R

RO Withdraw control rods 4

6 C

RO Loss of CRD FCV C

RO Drifting low IRM 1 Event I Type 1 Position I Description Event Type Position I

N BOP 5

C BOP 7

C BOP 8

I M

I Crew I MPR failure plus ATWS Description LFRV to MFRV transfer ESW pump high amps EPR Fluctuations I

I I

9 l

M 1

Crew I Small steam LOCA in primary containment 3

5 I Event I Type I Position I Description TS SRO Loss of DW wide range pressure transmitter (3.13.E)

TS SRO Loss of ESW Pump (3.4.C.4)

NRC 1 Page 2 of 4

Scenario Summary The scenario will begin with the Containment Spray and Emergency Service Water System/Pump Operability and Comprehensive/Preserice/Post-Maintenance lnservice Test in progress (607.4.004). The test is at step 6.14, waiting for the system run time of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Also, Instrument Maintenance is calibrating the drywell wide range pressure transmitters PT-53 (IAW 604.3.01 8, Wide Range Drywell Pressure Calibration).

1. The BOP will successfully transfer from the LFRV to the MFRV per procedure (This will be directed by procedure 201, step 6.57, and performed in procedure 31 7, step 6.3.1 5) (NORMAL EVOLUTION)

2. The RO will withdraw control rods (a noticeable change in reactor power) IAW procedure 201, Plant Startup. (REACTIVITY MANIPULATION)

3. The SRO will receive a call from the field that drywell wide range pressure transmitter (PT-53) cannot be left in-spec per the calibration procedure. The SRO will declare the instrument inoperable and apply TS 3.13.E. (TS)

4. The CRD FCV (NC30A) will fail closed. Several panel indications are available to diagnose the problem. The RO will swap to the alternate FCV IAW procedure 302.1 (Control Rod Drive System), step 4.3.3. ABN-6, Control Rod Drive System may be entered. (COMPONENT FAILURE) (ABN)

5. The ESW pump will develop high amps (70 amps gives B6a alarm, and trip at 160 amps). It is expected that the BOP will secure the pump prior to the trip IAW the RAP. If not, the pump will trip. SRO applies Tech Specs 3.4.5C.4. The BOP is expected to shutdown the containment spray surveillance. (COMPONENT FAILURE) (TS) (ABN)

6. An IRM will fail low causing a rodblock (RAP-Gle, G2e). The IRM can be bypassed, and the rodblock cleared. The SRO will verify TS, and that no actions are required. (TS 3.1.I) (COMPONENT FAILURE)

7. Small oscillations in the EPR begins, which affect power, level and pressure.

(ABN-34, Power Oscillations, may be entered.) ABN-9, EPR Malfunctions, should be entered. It is expected that the BOP will transfer to the Mechanical Pressure Regulator (MPR) IAW 31 5.4, Transferring Pressure Regulators. (COMPONENT FAILURE) (ABN)

8. The MPR will fail causing all turbine bypass valves (TBVs) to go closed, causing RPV pressure to increase. The RO may attempt to scram prior to the NRC 1 Page 3 of 4

RPV high pressure scram setpoint, but an electrical ATWS will occur and no control rods will insert. The crew will enter RPV Control -With ATWS. The crew will insert control rods by venting the scram air header (IAW SP-21, Alternate Insertion of Control Rods). RPV pressure control will be available with one loop of isolation condensers and electromatic relief valves (EMRVs). (EOP) (MAJOR)

9. A small steam LOCA in the primary containment will require the Crew to enter the Primary Containment Control EOP. The operator will spray the containment (IAW SP-29, Initiation of the Containment Spray System for Drywell Sprays).

(EOP) (MAJOR)

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Scenario Outline Appendix D Event No.

Malf. No.

Event Type*

1 2

TS SRO R

RO 3

C BOP TS SRO Facility: Oyster Creek Scenario No.: NRC 2 Op Test No.: NRC 2006-1 Event Description Restore the amplidyne to service and transfer the main generator from manual voltage control to automatic voltage control.

Respond to Drywell-Torus vacuum breaker fail to close.

Respond to Reactor Recirculation Pump alarms.

Examiners :

Operators :

8 9

Respond to steam leak in the primary containment with failure of the Containment Spray system.

Respond to failure of primary containment to automatically isolate.

C Crew Respond to failure of RPV water level input to Feed Water Level I

I I I R 0 I Control System (LT ID1 3A and LT ID1 3C).

i L f

~

~~

~~

~

~

Respond to indications of low TBCCW pressure.

6 1

I C I RO I Respond to failure of Average Power Range Monitor (APRM).

7 1

I M I Crew I Respond to main generating overheating.

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Total Malfunctions (5-8):

8 Malfunctions after EOP entry (1 -2)

Abnormal Events (2-4) 4 Major Transients ( I -2) 2 EOP Contingencies w/ substantive actions (0-2)

Critical Tasks (2-3) 2 2

EOPs entered requiring substantive actions ( I -2)

I I

Event Type Position 3

R RO 4

I RO Description Respond to recirculation pump alarms Respond to failure of RPV level input to FWLC (LT 6

I Event I Type I Position 1 Description IDl3A and LT ID13C).

C RO Respond to failure of APRM.

7 8

M Crew Respond to main generating overheating M

Crew Respond to steam leak in the drywell with failure of valves to auto close on the primary containment isolation signal (V-22-1, V-22-2) 9 containment spray C

ROlBOP Respond to failure of drywell equipment drain isolation Scenario Summary Event Type Position 2

TS SRO 3

TS SRO The scenario will begin with field personnel continuing the drywell-torus vacuum breaker surveillance test. No actions are taken by control room operators except communicating with the field personnel and annunciation acknowledgement. The last valve is to be tested. Field personnel will continue with the surveillance after being notified by the control room that the test may reconvene (after placing the amplidyne in service).

Description Respond to vacuum breaker failure Respond to recirculation pump alarms

1. The BOP will swap from main generator manual voltage control to automatic voltage control IAW 336.1, 24 KV Main Generator Electrical System. (NORMAL EVO LUTlO N)

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2. Operators in the field are performing the DWflorus vacuum breaker exercise test. The last vacuum breaker tested, opens with a little more resistance than the others, makes a strange noise when fully opened, then remains open after being allowed to close. Alarms of the open valve are present in the control room. The SRO will declare the valve inoperable and applies TS 3.5.A.5 (TS)

3. The operators will respond to alarms for a recirculation pump. Alarms for low oil and high vibrations (RAP-E2d, RAP-E6d) will require an immediate pump trip by the BOP. The RO will make changes to power to ensure recirc pump limitations and power/flow considerations are met (recirc flow and/or CRAM rods). The SRO will apply TS 3.3.F, Recirc Loop Operability, and 3.10.A, Core Limits (as required by the Core Operating Limits Report). (COMPONENT FAILURE) (REACTIVITY MANIPULATION) (TS) (ABN)

4. The RO will respond to a leak in the common leg to RPV water level transmitters ID1 3A and ID1 3C which input to feed water level control. The crew will enter ABN-17, Feedwater System Abnormal Conditions. The RO will take manual control of feed water and return water level to the normal band. (The RO may swap level transmitters to Feedwater Level Control IAW procedure 317, Feedwater System (Feed Pumps to Reactor Vessel)). (INSTRUMENT FAILURE)

5. One of the operating TBCCW pumps will develop a sheared shaft, and the low system pressure switch to start the standby pump will not function. The H2 System Trouble annunciator will alarm. The BOP will deduct the reduced system pressure and start another TBCCW pump IAW ABN-20, TBCCW Failure Response. (COMPONENT FAILURE) (ABN)

6. The next event is a loss of an APRM causing the APRM to be INOP. The RO will bypass the APRM and reset the ?4 scram. The SRO will verify compliance with Tech Specs. (COMPONENT FAILURE)

7. The crew will receive the Generator Core Monitor annunciator (RAP-R8c).

Local indications will require tripping the generator (although the SRO may direct power reductions first). (MAJOR) (ABN)

8. A steam leak in the primary containment occurs and the crew will enter the Primary Containment Control EOP. Because a drywell-to-torus vacuum breaker is open, the pressure suppression function of the torus is lostheduced. The containment spray system will not function. The SRO will direct emergency depressurization (IAW Emergency Depressurization - No ATWS) as primary suppression pressure limits are approached. (MAJOR) (EOP) (COMPONENT FAILURE) (EOP CONTINGENCY)

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9. The Operators will recognize that the drywell equipment drain isolation valves failed to close on a primary containment isolation signal and will manually close the valves (V-22-1 and V-22-2) (COMPONENT FAILURE)

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