ML070610478

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Final Outlines (Folder 3)
ML070610478
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 01/29/2007
From: Vanwyen T
Exelon Generation Co
To: Todd Fish
Operations Branch I
Sykes, Marvin D.
Shared Package
ML060800089 List:
References
ES-401, ES-401-1
Download: ML070610478 (23)
v • d • e


Text

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

Peach Bottom Printed: 01/24/2007 Date Of Exam:

02/05/2007 Note:

1.
2.
3.
4.
5.
6.

Ensure that at least iwo 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 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; 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 # I 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 ES401-3. Limit SRO selections to WAS that are linked to 10 CFR 55.43.

1

BWR RO Examination Outline Printed: 0 1 /24/2007 Form ES-401-1 Facility:

Peach Bottom ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 /Group 1 (RO I SRO)

' "/APE # / Name / Safety Function K1 K2 K3

,4500 1 Partial or Complete Loss of Forced Core Flow Circulation I 1 & 4 295003 Partial or Complete Loss of AC Pwr 16 295026 Suppression Pool High Water 295028 High Drywell Temperature / 5 295030 Low Suppression Pool Wtr Lvl 1 5 Temp. 15

~~

~

I l x l 295004 Partial or Complete Loss of DC Pwr I 6 X

X X

295005 Main Turbine Generator Trip / 3 I I 1

29503 1 Reactor Low Water Level I 2 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown I 1 295038 High Off-Site Release Rate 19 295006 SCRAM / 1 I

I I x X

2950 16 Control Room Abandonment I 7 1

I I X 600000 Plant Fire On Site / 8 WA Category Totals:

I I I x 29501 8 Partial or Total Loss of CCW I 8 3

3 4

2950 18 Partial or Total Loss of CCW / 8 2950 19 Partial or Total Loss of Instrument Air 1 8 I

I I 295021 Loss of Shutdown Cooling 14 I X I I

5023 Refueling Acc I 8 1'

295024 High Drywell Pressure I 5 1 x 1 I 295025 High Reactor Pressure 13 1

BWR RO Examination Outline Facility:

Peach Bottom Printed: 0 1/24/2007 1

BWR RO Examination Outline Printed: 0 1 /24/2007 Facility:

Peach Bottom 1

2

BWR RO Examination Outline Printed: 0 1 /24/2007 Facility:

Peach Bottom 2.4.3 1 - Knowledge of annunciators alarms and 1

Generic Knowledge and Abilities Outline (Tier 3)

BWR RO Examination Outline Printed: 0 1 /24/2007 Facility:

Peach Bottom Date of Exam:

Form ES-401-3 KA#

Topic IR E

L-4 CatePory 2.1.1 2.1.20 Conduct of Operations Knowledge of conduct of operations requirements.

3.7 1

Ability to execute procedure steps.

4.3 1

Knowledge of the process for determining the internal and external effects on core reactivity.

Subtotal:

2 2.8 1

~

~

~

~~~

Equipment Control 2.3.2 Knowledge of facility ALARA program.

2.2.24 2.5 1

2.2.28 2.2.34 Subtotal:

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

Ability to analyze the affect of maintenance activities on LCO status.

2.5 1

Knowledge of new and spent fuel movement procedures. 1 2.6 1

1 I 2.4.2 Knowledge of system set points, interlocks and automatic Ability to prioritize and interpret the significance of each actions associated with EOP entry conditions.

2.4.45 annunciator or alarm.

3.9 1

3.3 1

Radiation Control I Emergency Plan P 2.3.4 2.3.1 1 Ability to control radiation releases.

I 2.7 I 1

Tier 3 Point Total:

10 1

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

volu tions
2.

Plant Systems Totals 0

0 0

0 0

0 0

7 3

10 1

0 0

0 0

0 0

0 0

0 0

0 0

3 2

5 2

0 0

0 0

0 0

0 0

0 0

0 0

0 2

1 3

Totals Tier 0

0 0

0 0

0 0

0 0

0 0

0 5

3 8

1.
2.
3.
4.
5.
6.

7.*

8.
9.
3. Generic Knowledge And Abilities Categories Ensure that at least Wo topics from every WA category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each 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 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 I and 2 from the shaded systems and WA categories.

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.

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 # I does not apply). Use duplicate pages for RO and SRO-only exams.

For Tier 3, select topics from Section 2 of the WA catalog, and enter the WA numbers, descriptions, IRs, and point totals (#) on Form ESllOl-3, Limit SRO selections to WAS that are linked to 10 CFR 55.43.

1 2

3 4

1 2

3 4

0 0

0 0

2 2

1 2

0 7

1

BWR SRO Examination Outline Printed: 0 1/24/2007 Facility:

Peach Bottom ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 1 (RO I SRO)

Form ES-401-1 I SIAPE # I Name I Safety Function

~ 5 0 0 3 Partial or Complete Loss of AC Pwr

/ 6 295004 Partial or Complete Loss of DC Pwr

/ 6 29501 8 Partial or Total Loss of CCW / 8 2950 19 Partial or Total Loss of Instrument Air I 8 295023 Refueling Acc 1 8 29503 1 Reactor Low Water Level / 2 600000 Plant Fire On Site 1 8 KIA Category Totals:

1 7

BWR SRO Examination Outline Facility:

Peach Bottom Printed: 0 1 12412007 ES - 401 Emergency and Abnormal Pian I I I 295036 Secondary Containment High SumpIArea Water Level 1 5 I

WA Category Totals: I 0 I 0 I 0 Evolutions - Tier 1 / Group 2 (RO / SRO)

Form ES-401-1 1

Printed: 0 1/24/2007 BWR SRO Examination Outline Facility:

Peach Bottom 1

Printed: 0 1 /24/2007 Form ES-401-1 BWR SRO Examination Outline Facility:

Peach Bottom ES - 401 Plant Systems - Tier 2 / Croup 2 (RO / SRO) stem limits and c-'

I

Generic Knowledge and Abilities Outline (Tier 3)

BWR SRO Examination Outline Date of Exam:

KA #

Took 2.1.4

2.1.6 Facilitv

Peach Bottom

'ii' CatePory Knowledge of shift staffing requirements.

3.4 1

Ability to supervise and assume a management role 4.3 1

during plant transients and upset conditions.

Printed: 0 1 I2412007 Form ES-401-3 IR

!?

Equipment Control Conduct of Operations 2.2.18 Knowledge of the process for managing maintenance 3.6 1

2.2.29 Knowledge of SRO fuel handling responsibilities.

3.8 1

activities during shutdown operations.

Subtotal:

2 2.3.1 Knowledge of 10 CFR 20 and related facility radiation 3.O 1

control requirements.

Radiation Control 2.4.22 2.4.33 Knowledge of the bases for prioritizing safety functions 4.0 1

Knowledge ofthe process used track inoperable alarms.

2.8 1

during abnormallemergency operations.

Emergency Plan

.~

-- I

~

~

Tier 3 Point Total:

7 I

ES-401 Record of Rejected WAS Form ES-401-4 Tier I Group RO 211 RO 212 SRO 111 SRO 1 12 SRO 211 SRO 111 RO 1 I 1 RO 211 SRO 1 I 1 Reason for Rejection Peach Bottom uses static inverters for uninterruptable power supplies, not

~

Randomly Selected KIA 262002 A I.02 motor-generators.

290003 A3.02 At Peach Bottom, there is no direct association between the Control Room HVAC System and the Fire Protection System.

295024 A205 Peach Bottom has no direct indication or procedural guidance for determining suppression chamber air space temperature.

295008 G2.4.49 Unable to construct an SRO question for this KA that meets the requirements of NUREG-1023.

259002 G2.1.I4 Unable to construct an SRO question for this KA that meets the requirements of NUREG-1023.

G2.3.2 This KA was already sampled on the RO portion of the exam. Unable to construct an additional question at the SRO level.

295026 EK2.06 Unable to construct an RO question for this KA that meets the requirements of NUREG-1023.

21 1000 K5.05 Unable to construct an RO question for this KA that meets the requirements of NUREG-1023.

295026 G2.4.30 Unable to construct an SRO level quesiton for this KA that also meets the criteria of 10CFR55.43(b).

ES-401, Page 27 of 33

r -

ES-301 Administrative Topics Outline Form ES-301-1 acility: Peach Bottom tamination Level: RO [7 SRO Date of Examination: 2/5/2007 Operating Test Number: 2007 NRC Administrative Topic (See Note)

Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Plan TY Pe Code*

N, R M. R Describe activity to be performed G2.1.4 - Evaluate Shift Staffing H

G2.1.7 - Evaluate A PI Edit And Take Corrective Action For A Thermal Limit Violation [PLOR-218C]

G2.2.21 - Determine Post Maintenance Test Requirements For Valve Operability [NEW]

G2.3.9 - Review And Approve Primary Containment PurgeNent Isolation Valve Cumulative Hour Log [NEW]

G2.4.38 - Review And Authorize Issuance Of Thyroid Blocking Agent (KI) [PLOR-215C]

OTE: 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 Administrative Topics Outline Form ES-301-1 3cility: Peach Bottom xamination Level: RO [XI SRO 0 Date of Examination: 2/5/2007 Operating Test Number: 2007 NRC Administrative Topic (See Note)

Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Plan TY Pe Code*

Describe activity to be performed G2.1.7 - Calculate Drywell Bulk Average Temperature

[2005 NRC]

G2.1.25 - Perform Reactor Coolant Leakage Surveillance

[NEW G2.2.11 - Prepare A Partial Procedure [PLOR-205C]

G2.4.43 - Perform Personnel Notifications During A Security Threat [PLOR-217C]

OTE: 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

4,'

a. 295037 EA1.04 - Inject Boron Into RPV (Alternate Path - RWCU Fails To Isolate) [PLOR-301 CAI - SET 1 ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2 Facility: Peach Bottom Exam Level: RO SRO-I 0 SRO-U 0 Date of Examination: 2/5/2007 Operating Test Number: 2007 NRC A, D, S Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
d. 209001 A4.04 - Perform Core Spray B Pump Capacity Test For IST
e. 219000 A4.13 - HPSW Injection Into The Torus [PLOR-O81C] - SET 1

[NEW] - SET 4 System / JPM Title N, s D, s Type Code*

f. 262001 A4.04 - Synchronize Turbine Generator Output With Grid At
g. 295018 AA1.01 - Emergency Cooling Water System Startup [PLOR-
h. 261 000 A2.10 - PRO Scram Actions (Alternate Path - SBGT Fails To Minimum Load [PLOR-O17C] - SET 4 028Cl-SET 3 Automatically Initiate) [NEW] - SET 2 D, s M, s A, L, N, s
b. 295031 EA1.02 - Manually Initiate HPCl (Alternate Path - Manual Initiation Pushbutton Fails To Operate) [PLOR300CA] - SET 2
c. 218000 A4.03 - ADS Reset Following Blowdown [PLOR-O23C / 2005 NRC] - SET 3
i. 201001 A2.09 - Low CRD Scram Air Header Pressure - Unit 3 (Alternate
i. 295031 EA1.05 - Defeat RClC Low Pressure Isolation - Unit 2
k. 264000 A2.10 - Diesel Generator Air Start Solenoid Override Path - Place Standby Regulator In Service) [PLOR-316PA / 2002 NRC]

[PLOR-O86P]

[PLOR-O49P]

A, D, E, p, R D, E, R D, E Safety Function 1

2 3

4 5

6 8

9 1

2 6

All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

I

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

4 (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)imulator 4-6 I 4-6 I 2-3 ES-301, Page 23 of 27

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2

a. 295037 EA1.04 - Inject Boron Into RPV (Alternate Path - RWCU Fails To
b. 295031 EA1.02 - Manually Initiate HPCl (Alternate Path - Manual
c. 218000 A4.03 -ADS Reset Following Blowdown [PLOR-O23C I2005 Isolate) [PLORdOl CAI - SET I Initiation Pushbutton Fails To Operate) [PLOR300CA] - SET 2 NRCl - SET 3 Facility: Peach Bottom Exam Level: RO 0 SRO-I SRO-U [7 A, D, S 1

A, D, L, s 2

D, L, P, s 3

Date of Examination: 21512007 Operating Test Number: 2007 NRC

d. 209001 A4.04 - Perform Core Spray 6 Pump Capacity Test For IST
e. 219000 A4.13 - HPSW Injection Into The Torus [PLOR-O81C] - SET 1

[NEW] - SET 4 Control Room Systems* (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

N, s 4

D, s 5

System I JPM Title

g. 295018 AA1.01 - Emergency Cooling Water System Startup [PLOR-028Cl-SET 3
h. 261000 A2.10 - PRO Scram Actions (Alternate Path - SBGT Fails To Automatically Initiate) [NEW] - SET 2 Safety I

1 Function M, s 8

A, L, N, s 9

i. 201001 A2.09 - Low CRD Scram Air Header Pressure - Unit 3 (Alternate Path - Place Standby Regulator In Service) [PLOR-316PA 12002 NRC]
j. 295031 EA1.05 - Defeat RClC Low Pressure Isolation - Unit 2

[ PLOR-086Pl

k. 264000 A2.10 - Diesel Generator Air Start Solenoid Override A, D, E, 1

D, E, R 2

p, R D, E 6

  • Type Codes (A)lternate path (C)ontrol room (D)irect from bank (Epergency or abnormal in-plant Criteria for RO I SRO-I I SRO-U 4-6 I 4-6 I 2-3

< 9 / ( 8 1 5 4

> I / 21 1 2 1 (L)ow-Power / Shutdown (N)ew or (M)odified from bank including I(A)

(P)revious 2 exams (S)imulator (R)CA

< 3 11 3 I ( 2 (randomly selected)

> I 1 >I

/ > I

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2

a.
b. 295031 EA1.02 - Manually Initiate HPCl (Alternate Path - Manual Initiation Pushbutton Fails To Operate) [PLOR-300CA] - SET 2
c. 218000 A4.03 - ADS Reset Following Blowdown [PLOR-O23C / 2005 NRC] - SET 3
d. 209001 A4.04 - Perform Core Spray B Pump Capacity Test For IST

[NEW] - SET 4

e.
f.

Facility: Peach Bottom Exam Level: RO 0 SRO-I 0 SRO-U [XI A, D, L, S ESF D, L, p, s ESF N, s ESF Date of Examination: 2/5/2007 Operating Test Number: 2007 NRC Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System I JPM Title I Type Code*

h.

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

i. 201001 A2.09 - Low CRD Scram Air Header Pressure - Unit 3 (Alternate Path - Place Standby Regulator In Service) [PLOR316PA 12002 NRC]
i.
k. 264000 A2.10 - Diesel Generator Air Start Solenoid Override Safety Function 2

3 4

A, D, E,

[PLOR-O49P]

All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

  • Type Codes (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 I(A)

(P)revious 2 exams (S)imulator

( W A Criteria for RO I SRO-I / SRO-U 4-6 I 4-6 I 2-3 ES-301, Page 23 of 27

Scenario Outline ES-D-1 1

Event No.

I 2

Simulation Facility Peach Bottom Scenario No.

  1. 1 Op Test No.

2007 NRC Examiners Operators CRS (SRO)

Malfunction Event No.

Type*

R URO CRS C

ALL TS URO (ATC)

PRO (BOP)

~~

~

~~

Control rod drifts out Scenario Summary The scenario begins with the reactor at approximately 5% power during a reactor startup. Following shift turnover, the crew should continue with the reactor startup, pulling control rods in accordance with the approved startup sequence. A control rod will drift out, requiring the crew to execute ON-I21 Drifting Control Rod and declare the affected control rod inoperable.

~~

~~

~

Inadvertent RClC initiation Following the control rod drift, the crew should secure drywell purge in preparation for inerting the drywell. Once drywell purge is secured, an inadvertent RClC initiation will occur, requiring the crew to perform a RClC shutdown and declare it inoperable. This event will be followed by a failure of the in-service CRD flow control valve, which will require the crew to enter ON-1 07 Loss of CRD Regulating Function and shift to the alternate flow control valve.

5 C

URO CRD flow control valve failure CRS 1

6 M

ALL Recirculation system leak in the drywell C

URO Seven rods stick full out during the scram CRS l

7 8

C PRO Drywell spray valve failures - prevents drywell spray C RS Next, a Recirc system leak will develop in the drywell requiring entry into OT-101 High Drywell Pressure. The crew should take actions for the rising drywell pressure and should manually scram the reactor and enter T-100 Scram. During the scram, seven rods will fail to insert resulting in an ATWS. When drywell pressure reaches 2 psig, the crew should enter T-101 RPV Control and T-102 Primary Containment Control. Multiple failures of drywell spray valves will prevent spraying the drywell, requiring the crew to perform T-I12 Emergency Blowdown when drywell temperature cannot be restored and maintained below 281 degrees F. With several rods stuck out, the crew should terminate and prevent injection in accordance with T-240 prior to the emergency depressurization.

Initial IC-70, 5% power Conditions Turnover See Attached Shift Turnover Sheet Event Description Power ascension with control rods Secure drywell purge

Scenario Outline ES-D-1.

Simulation Facility Peach Bottom Scenario No.

  1. 2 Op Test No.

2007 NRC Event Malfunction No.

No.

11 Examiners Operators CRS (SRO)

Event Type*

URO (ATC) 2 3

4 5

6 PRO (BOP)

TS CRS C

URO CRS I

URO TS CRS M

ALL I

URO CRS Scenario Summary The scenario begins with the plant at 76% power and the B RHR pump blocked for motor replacement. Following turnover the crew will perform a main turbine master trip solenoid valves routine test. Following this test, the SBO line will fail, requiring a Tech Spec (TRM) entry. A loss of feedwater heaters will require the crew to respond to a positive reactivity addition and reduce reactor power to ensure thermal limits are not exceeded. The crew will then receive an RPS half scram due to a failed low vacuum pressure transmitter (blown fuse). This will require a Tech Spec entry.

Troubleshooting and repairs will be time-compressed, allowing the crew to reset the half scram.

8 7

8 After RPS is reset, a steam leak will develop in the Turbine Building. As the steam leak grows in magnitude, the crew should recognize the need to shutdown the plant. During the manual scram, a reactor mode switch failure will require the crew to use the manual pushbuttons or Alternate Rod Insertion (ARI) to terminate the ATWS.

C PRO CRS isolate PRO CRS pressure control I depressurization Group I failure to auto isolate /failure of the D MSL to manually C

Unable to restore drywell nitrogen I only ADS SRVs available for A failure of the Group I isolation will require a manual isolation but the D MSL will fail to isolate. The crew should enter T-104 Radioactive Release to evaluate and control the release. The inability to restore instrument nitrogen to the SRVs wi!l result in a loss of all non-ADS SRVs.

When the release exceeds the General Emergency level, the crew should perform an Emergency Blowdown in accordance with T-112 Emergency Blowdown.

I I I I N PRO 1

CRS Event Descrintion Perform the main turbine master trip solenoid valves routine test SI30 line failure (TRM)

Loss of extraction steam to feedwater heaters I power reduction

~~

Failure of a vacuum transmitter I RPS half scram & reset Steam leak in the turbine building

~~

~~~~~~

Reactor mode switch failure (manual scram I ARI work)

Scenario Outline ES-D-1 Simulation Facility Peach Bottom Scenario No.

  1. 3 Op Test No.

2007 NRC Exam i ners Operators CRS (SRO)

URO (ATC)

PRO (SOP)

Event No.

1 2

3 Scenario Summary The scenario begins with the reactor at 100% power. The 25 EHC Pump is blocked out of service for filter replacement. Following shift turnover, the crew should transfer RPS bus B to the alternate supply to facilitate repairs for a failed trip coil on the B RPS bus feeder breaker. The failed B RPS feeder breaker will already be inoperable when the crew takes the shift.

Malfunction Event Event No.

Type*

Description N

TS breaker)

TS CRS RClC 250 VDC bus failure C

URO Lossof RBCCW ALL Transfer RPS bus to alternate supply (failed trip coil on B RPS feeder CRS Following the RPS bus transfer, the RCIC 250 VDC bus will de-energize, rendering RClC inoperable and requiring a Tech Spec entry. Next, the running RBCCW pump will trip and the standby pump will fail to start, resulting in a complete loss of RBCCW. The crew should reduce RBCCW loads (e.9.

RWCU) and reactor power as directed by ON-113 Loss of RBCCW.

4 5

The crew should perform a GP-4 manual scram due to the inability to restore RBCCW to the recirculation pump motors. An ATWS will occur requiring the crew to execute T-101 RPV Control and T-I 17 LeveVPower Control. Shortly after SLC is initiated the SLC pump will trip, requiring the URO to place the alternate SLC pump in service. A drywell vent valve will fail to isolate on low RPV level and the PRO should manually isolate the valve.

I I

M ALL ATWS (hydraulic)

A failure of the only available EHC pump will cause the turbine to trip and the turbine bypass valves to close, requiring the crew to utilize SRVs for reactor pressure control. The crew should perform T-216 Control Rod Insertion By Manual Scram or Individual Scram Test Switches to bypass ARI and RPS, drain the scram discharge volume and initiate another scram.

C URO Standby liquid control pump trips URO Reduce reactor power 1

CRS 1 7

I PRO Drywell vent valve (AO-2509) fails to isolate CRS I

CRS 1 (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS) Tech Spec

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