ML090290221

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Final Outlines (Folder 3)
ML090290221
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 11/17/2008
From:
Exelon Generation Co
To: Todd Fish
Operations Branch I
Hansell S
Shared Package
ML081060602 List:
References
TAC U01776
Download: ML090290221 (20)
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Text

ES-401 BWR Examination Outline FORM ES-40171

acility Name: Peach Bottom Date of Exam: 12/08/2008 lote
1.
2.
3.
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6.

7.*

a.
9.

Ensure that at least two topics from every applicable 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 iri 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 fin RO exam must total 75 points and the SRO-only exam must total 25 points Systemslevolutions within each group are identified on the associated outline, systems or evolutions that do not apply at the facility should be deleted and justified, operationally important. site-specific systems that are not included on the outline should be added Refer to Section D 1 b of ES-401 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 selectin 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 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. Refer to Section D.l.b of ES-401 for the applicable WAS 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 ES-401-3. Limit SRO selections to WAS that are linked to 10 CFR 55.43.

ES-401 2

Form ES-401-9 ES-401 BWR Examination Outline Form ES-401 Ernerqency and Abnormal Plant Evolutions -Tier IIGrouD 1 (RO)

EJAPE # I Name I Safety Function ll 295001 Partial or Complete Loss of Forced Core Flow Circulation I 1 & 4 295003 Partial or Complete Loss of AC I 6 295004 Partial or Total Loss of DC Pwr I 6 i 295005 Main Turbine Generator Trip I 3 i 295006 SCRAM I 1 I I 295016 Control Room Abandonment I 7 (I

29501 8 Partial or Total Loss of CCW I 8 295019 Partial or Total Loss of Inst. Air I 8 295021 Loss of Shutdown Cooling I 4 295023 Refueling Acc I 8 295024 High Drywell Pressure I 5 295025 High Reactor Pressure I 3 295026 Suppression Pool High Water 295027 High Containment Temperature I 5 295028 High Drywell Temperature I 5 II 11295030 Low Suppression Pool Wtr Lvl I 5 I1 I

I 0

2 295031 Reactor Low Water Level I 2 I

295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or ll Unknown I 1 295038 High Off-site Release Rate I 9 600000 Plant Fire On Site I 8 700000 Generator Voltage and Electric Grid Disturbances I 6 WA Category Totals:

1 -

1 1

1 1

1 1

0 1

1 -

1 1

ES-401 3

Form ES-4014

ES-401 4

Form ES-401-1 ES-401 BWR Examination Outline Plant Svstems -Tier Z/GrouD 1 (RO)

Form ES-401-'

ES-401, Page 20 of 34

ES-401-1 5

Form ES-401-1 llES-401 BWR Examination Outline Form ian1 Systems - Tier 2lGroup 2 (RO)

ES-401-ES-401, Page 22 of 34

ES-401 2

Form ES-401-'

BWR Examination Outline Emeraencv and Abnormal Plant Evolutions - Tier IIGrouD 1 (SRO)

Form ES-401-K K

K EIAPE # I Name I Safety Function 1

295001 Partial or Complete Loss of Forced Core Flow Circulation I 1 & 4 295003 Partial or Complete Loss of AC I 6 95004 Partial or Total Loss of DC Pwr I 6 I

I t

295005 Main Turbine Generator Trip I 3 11295006 SCRAM I I I r i 295016 Control Room Abandonment I 7 295018 Partial or Total Loss of CCW I 8 295019 Partial or Total Loss of Inst. Air I 8 295021 Loss of Shutdown Cooling I4 295023 Refueling Acc I 8 295024 High Drywell Pressure I 5 295025 High Reactor Pressure I 3 Suppression Pool High Water Temp.

295027 High Containment Temperature I 5 295028 High Drywell Temperature I 5 295030 Low Suppression Pool Wtr Lvl I 5 295031 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 I 9 I I 600000 Plant Fire On Site I 8 700000 Generator Voltage and Electric Grid Disturbances I 6

@A Category Totals:

ES-401 3

Form ES-401-I ES-401 BWR Examination Outline Form ES-401 I1 Emergenc and Abnormal Plant Evolutions -

1 2

Tier /Group (SRO) 11 EIAPE # I Name I Safety Function 295002 Loss of Main Condenser Vac I 3 295007 High Reactor Pressure I3 295008 High Reactor Water Level I2 295009 Low Reactor Water Level I 2 295010 High Drywell Pressure I 5 29501 1 High Containment Temp I 5 295012 High Drywell Temperature I 5 295013 High Suppression Pool Temp. I 5 295014 Inadvertent Reactivity Addition I 1 295015 Incomplete SCRAM I 1 295017 High Off-site Release Rate I 9 295020 Inadvertent Cont Isolation I 5 & 7 295022 Loss of CRD Pumps I 1 ll 295029 High Suppression Pool Wtr Lvl I 5 emperature I 5 295033 High Secondary Containment Area Radiation Levels I 9 295034 Secondary Containment Ventilation High Radiation I9 295035 Secondary Containment High Differential Pressure I 5 295036 Secondary Containment High SumpIArea Water Level I 5 500000 High CTMT Hydrogen Conc I 5 WA Category Totals 0

ES-401, Page 19 of 34

4 Form ES-401-1 ES-401 Form ES-401 ES-401 BWR Examination Outline ES-401, Page 20 of 34

ES-401 5

Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 2 (SRO)

ES-401, Page 21 of 34

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

Form ES-401-3 acility Name:Peach Bottom Date of Exam:l2/08/2008 ES-401, Page 27 of 34

Form ES-401-4 ES-401 Record of Rejected WAS 295019 AK2.19 Tier I Group At Peach Bottom, there is no impact on RHRILPCI from loss of instrument air other than the inability to manually stroke testable check valves.

(Replaced with 295019 AK2.05)

R o l l 1 Q#46 R O I I I Q#48 R o l l 1 Q#52 R O I I I Q#57 RO 112 Q#65 RO211 Q#5 RO211 Q#8 RO211 Q#l7 RO211 Q#2 3 RO212 Q#33 R 0 2 1 2 Q#37 RO 3 Q#67 RO 3 Q#68 SRO211 Q#79 SRO 1 I 1 Q#85 Randomly Unable to construct an Fa0 question for this KIA that meets the 295023 2.2.42 I requirements of NUREG-1021. (Replaced with 295023 2.4.31)

Application of Technical Specifications is not an RO job function.

295028 2.4.40 I (Replaced with 295028 2.2.22) 600000 AK1.01 295036 EK2.02 Unable to construct an RO question for this KIA that meets the requirements of NUREG-1021. (Replaced with 600000 AK1.02)

Unable to construct an RO question for this KIA that meets the requirements of NUREG-1021. (Replaced with 295036 EK2.01) 209001 Unable to construct an RO question for this KIA that meets the K3 03 requirements of NUREG-1021 (Replaced with 209001 K3 02)

Unable to construct an RO question for this KIA that meets the K1 04 requirements of NUREG-1021 (Replaced with 215003 K1 02)

Unable to construct an RO question for this KIA that meets the K6 09 requirements of NUREG-1021 (Replaced with 261000 K6 03) 263000 Unable to construct an RO question for this KIA that meets the 2 4 18 requirements of NUREG-1022 (Replaced with 263000 2 1 23) 215003 261000 226001 A3.02 At Peach Bottom, there are no automatic operations associated with the I

Containment Spray mode of RHRlLPCl based on system pressure.

(Replaced with 226001 A3.01)

H Unable to construct an RO question for this KIA that meets the 245000 2.2.39 1 requirements of NUREG-1021. (Replaced with 245000 2.1.20)

A G2.1.4 Unable to construct an RO question for this KIA that meets the requirements of NUREG-1021. (Replaced with G2.1.5)

A G2.1.I7 Unable to construct an RO question for this KIA that meets the requirements of NUREG-1021. (Replaced with G2.1.7) 261000 2.2.38 I There are no conditions and limitations in the facility license associated 1 with the Standby Gas Treatment System. (Replaced with 261000 2.2.40) an SRO question for this WA that meets the (Replaced with 295016 AA2.06)

ES-401, Page 27 of 33

ES-301 Administrative Tooics Outline Form ES-301-1 Facility: Peach Bottom Examination Level: RO SRO 0 Date of Examination: 12/08/2008 Operating Test Number: 2008 NRC Administrative Topic (See Note)

Conduct of Operations I

N. S Describe activity to be performed G2.1.29 - Lineup Standby Gas Treatment System For Automatic Operation (New - SO 9A.1.A COL)

Conduct of Operations Equipment Control Radiation Control Emergency Plan NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they arc retaking only the administrative topics, when 5 are required.

Not Required G2.2.41 - Isolate the 2A Turbine Building Closed Coolir Water Heat Exchanger Due to a System Leak (New - P&ID M-316)

G2.3.11 - Perform PRO Duties For A Liquid Radwaste Discharge (2001 NRC)

G2.4.39 - Activate The Emergency Response Data System (PLOR-186C)

  • 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

Form ES-301-1 ES-301 Administrative Topics Outline Facility: Peach Bottom Examination Level: RO 0 SRO [XI Date of Examination: 12/08/2008 Operating Test Number: 2008 NRC Ik-Administrative Topic (See Note)

I Conduct of Operations Conduct of Operations Equipment Con trot Radiation Control

~~

~~

Emergency Plan TY Pe Code*

N, R Describe activity to be performed G2.1.34 - Review And Evaluate Reactor Coolant System Chemistry Limits - Condenser Tube Leak at Power (New - CH-10, ON-126, TRM 3.9)

G2.1.26 - Determine Minimum Required Personal Protective Equipment For Racking Out A 480 Volt Break1 (New - SA-AA-129)

G2.2.6 - Review And Approve A Temporary Procedure Change (PLOR-222C)

G2.3.13 - Review And Approve Primary Containment PurgeNent Isolation Valve Cumulative Hour Log (2007 NRC)

G2.4.40 - Make EAL Classification And State/Local Notifications For ALERT - High Winds With Visible Plant Damage (PLOR-234C)

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 (1. 1)

(P)revtous 2 exams (2 1, randomly selected)

~ _ _ _ _ _ -

~-

___-F ES 301, Page 22 of 27

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

i. 295037 G2.4.35 - Control Rod Drive Hydraulic System / Isolate And Vent The Scram Air Header - Unit 3 (PLOR-074P)
j. 217000 A2.04 - Reactor Core Isolation Cooling I Defeat Auto Open Signal
k. 295028 EA1.03 - Drywell Chilled Water Low Level (Alternate Path -

D, E, L, R E, N, R A, E, N, R of RClC Torus Suction Valves - Unit 2 (NEW - A 0 13.3-2)

Manual Makeup to Drywell Chilled Water System) - Unit 2 (NEW - ARC 217 H-5)

Facility: Peach Bottom Exam Level: RO Ix] SRO-I SRO-U 0 1

2 5

Date of Examination: 12/08/2008 Operating Test Number: 2008 NRC I

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

System / JPM Title

a. 202001 A4.01 - Recirculation System I Start a Recirc Pump (Alternate
b. 295031 EA1.02 - High Pressure Coolant Injection / Manually Initiate Path - Scoop Tube Lockup) (PLOR-309CA) - SET 4 HPCl (Alternate Path - Manual Initiation Pushbutton Fails To Operate)

(2007 NRC I PLOR-300CAI - SET I

c. 239001 A4.01 - Main Steam System / Open Main Steam Isolation Valves
d. 209001 A4.04 - Core Spray System / Perform Pump Capacity Test For
e. 223002 A4.03 - Primary Containment Isolation System / Perform a Group I PClS Isolation Reset (GP-8A) (PLOR-024C) - SET 1
f. 262001 A4.04 - AC Distribution / Excite The Main Generator
g. 212000 A4.14 - Reactor Protection System / Reset a Full Scram
h. 400000 A4.01 - Component Cooling Water / Verify Proper Isolation of

- Reactor Building Closed Cooling Water (RBCCW) (2005 NRC) - SET 3 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

After a Group-I Isolation (PLOR-083C) - SET 2 IST (Alternate Path - Minimum Flow Valve Fails To Open) - SET 3 (PLOR-03lC) - SET 4 (PLOR-004C) - SET 2 Type Code*

Safety 1

Function A, D, S 1

A, L, M, S 1

4 --

D, EN, S 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 (EN)gineered safety feature (L)ow-Power I Shutdown (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams

( W A (S)imulator E

~

Criteria for RO I SRO-I I SRO-U 4-6 I 4-6 I 2-3

< 9 1 5 8 1 5 4

> I I > 1 1 ~ 1 I 2 1 (control room system)

- >I

/ > I

> 2 1 2 1

< 3 I 5 2 (randomly selected)

- >I

/ > I 301, Page 23 of 27

~

ES-301 Control Room/ln-Plant Systems Outline FormES-301-2 Facility Peach Bottom Exam Level RO SRO-I [XI SRO-U 0 Date of Examination. 12/08/2008 Operating Test Number 2008 NRC

i. 295037 G2.4.35 - Control Rod Drive Hydraulic System / Isolate And Vent The Scram Air Header - Unit 3 (PLOR-074P)
j. 217000 A2.04 - Reactor Core Isolation Cooling / Defeat Auto Open Signal
k. 295028 EA1.03 - Drywell Chilled Water Low Level (Alternate Path -

of RClC Torus Suction Valves - Unit 2 (NEW - A 0 13.3-2)

Manual Makeup to Drywell Chilled Water System) - Unit 2 (NEW - ARC 217 H-5)

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

D, E, L, R 1

E, N, R 2

A, E, N, R 5

System / JPM Title a 202001 A4 01 - Recirculation System / Start a Recirc Pump (Alternate b 295031 EA1 02 - High Pressure Coolant Injection I Manually Initiate Path - Scoop Tube Lockup) (PLOR-309CA) - SET 4 HPCl (Alternate Path - Manual Initiation Pushbutton Fails To Operate) c 239001 A4 01 - Main Steam System / Open Main Steam Isolation Valves After a Group-I Isolation (PLOR-083C) - SET 2 d 209001 A4 04 - Core Spray System / Perform Pump Capacity Test For IST (Alternate Path - Minimum Flow Valve Fails To Open) - SET 3 e 223002 A4 03 - Primary Containment Isolation System / Perform a Group I PClS Isolation Reset (GP-8A) (PLOR-024C) - SET 1 (2007 NRC / PLOR300CA) - SET 1 f

  • Type Codes g 212000 A4 14 - Reactor Protection System / Reset a Full Scram h 400000 A4 01 - Component Cooling Water /Verify Proper Isolation of In-Plant Systems@ (3 for RO), (3 for SRO-I), (3 or 2 for SRO-U)

(PLOR-004C) - SET 2 Reactor Building Closed Cooling Water (RBCCW) (2005 NRC) - SET 3 Criteria for RO / SRO-I / SRO-U Type Code*

A, L, M, s D, EN, S D, EN, L, S Safety Function 1

2 3

4 5

7 8

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

(P)revious 2 exams (S)imulator

( R P 4-6 I 4-6 I 2-3 (9 I <a I 5 4 p 1 1 3 1 1 > 1

> 1 I > 1 1 ' 1 3 2 1 ' 2 1 ' 1

> 1 1 2 1 1 2 1

- I - I 2 1 (control room system)

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

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

_I__-

Facility Peach Bottom Exam Level RO 0 SRO-I 0 SRO-U Date of Examination 12/08/2008 Operating Test Number 2008 NRC SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title ll a N c.

d. 209001 A4.04 - Core Spray System / Perform Pump Capacity Test For I
f.
g. 212000 A4.14 - Reactor Protection System I Reset a Full Scram (PLOR-004C) - SET 2
h. 400000 A4.01 - Component Cooling Water / Verify Proper Isolation of Safety Type Ode*

1 Function D, EN, L, S 1 7

j. 217000 A2.04 - Reactor Core Isolation Cooling / Defeat Auto Open Signal

- of RClC Torus Suction Valves - Unit 2 (NEW - A 0 13.3-2)

k. 295028 EA1.03 - Drywell Chilled Water Low Level (Alternate Path - -

I Manual Makeup to Drywell Chilled Water System) - Unit 2 (NEW - ARC 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

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

(A)iternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power I Shutdown (Njew or (M)odified from bank including 1(A)

(P)revious 2 exams W C A (S)imulator 4-6

< 9

> 1 4-6 I 2-3

< 8 1 5 4

> 1 / 2 1

/ 2 1 (control room system)

- >I

/ > 1

> 1

> 2 1 2 2 I,I

< 3 I 5 3 / 5 2 (randomly selected)

> 1 1 2 1 / > 1 I

ES-301, Page 23 of 27 L

ES-0 Scenario Outline Simulation Facility Peach Bottom Scenario No.

  1. I (modified)

Op Test No.

2008 NRC C

URO TS PRO CRS Examiners Scenario Summary Initial Conditions Turnover Loss of MCC E224-R-B resulting in half scram and Group II outboard isolation I transfer RPS power supplies, reset half scram and isolatbns Operators CRS (SFiO)

URO (A-IC)

I URO PRO (BOP)

The scenario begins with a plant startup in progress at approximately 5% power following a r outage. During shift turnover, the crew is directed to swap CRD pumps due to a noisy beari A pump. Following the CRD pump swap, the 9 drywell chiller trips, requiring the crew to standby drywell chiller in service in accordance with the system operating procedure.

Next, a loss of MCC E224-R-B results in a loss of the B RPS MG set, a half scram and PClS outboard Group II isolation. The crew will investigate, transfer RPS to the alternate supply the half scram and PClS isolation. Following the Tech Spec evaluation, startup level contr 8091 will fail open, requiring the crew to manually restore and control RPV water level in a with OT-I 10 Reactor High Level. This event is further complicated by an inadvertent R initiation, requiring entry into OT-104 Positive Reactivity Insertion and manual shutdown Following this, an EHC failure will cause reactor pressure to rise, requiring entry into OT-102 Reactor High Pressure. The crew will be unable to reduce reactor pressure The reacto automatically scram on high pressure and the crew will be required to insert a manual scr after the scram, a leak will develop in the torus, requiring the crew to enter T-103 Secon Containment Control and 1-102 Primary Containment Control. A turbine bypass valve (remain) open and, due to a failure of the mode switch, will result in MSlVs closing when pressure decreases below 850 psig. As torus level continues to drop, the crew will be re perform T-I 12 Emergency Blowdown IC-71, -5% power See Attached Shift Turnover Sheet Startup level controller (LCV-8091) failure Swap CRD pumps 5

3 I

PRO Inadvertent RClC initiation TS CRS I

C URO CRS 4

1 EHC failure causes rising reactor pressure / reactor scram with mode switch failure (manual scram works) 7 M

ALL Torus leak into secondary containment (torus room) leading to emergency blowdown / turbine bypass valve fails open, causing MSlVs to close (due to failed mode switch)

Scenario Outline ES-D-1 II 11 Simulation Facility Peach Bottom Scenario No, #2 (modified)

Op Test No.

2008 NRC 11 Examiners Operators CRS (SRO)

URO ( A T )

PRO (BOP)

Scenario Summary The scenario begins with the reactor at approximately 76% power with power ascension on ho The crew will perform ST-0-001-200-2 Turbine Stop Valve Closure and EOC-RPT Function when an RPS failure will require the crew to make a Tech Spec declaration. This will be foll a trip of the in-service TBCCW pump with a failure of the standby pump to auto-start. The c be required to respond IAW ON-1 18 Loss of TBCCW and place the standby TBCCW pump i service. Following this, the A SRV will inadvertently open, requiring the crew to take actio OT-114 Inadvertent Opening of a Relief Valve. Power will be reduced in accordance wit Fast Power Reduction. The crew will be successful in closing the A SRV by directing plant operators to pull fuses for the valve A small steam leak inside the primary containment will occur next. The crew will be requi actions in accordance with OT-101 High Drywell Pressure. When the reactor is scrammed, a hydraulic ATWS will occur, requiring the crew to enter T-101 RPV Control and T-I 17 L Control. A failure of the Standby Liquid Control pump will require the crew to start the o order to successfully lower reactor power The crew will also be required to enter T-102 Primary Containment Control due to high drywell pressure. After diagnosing the inability to spray the containment due to an instrument failure, th crew will perform T-I 12 Emergency Blowdown. One ADS SRV will fail to open, requiring the opening of another SRV. The crew will need to implement T-216 Control Rod Insertion Scram Or Individual Scram Test Switches and T-220 Driving Control Rods During Failure To Scram to terminate the ATWS.

Initial IC-72, 76% power Conditions Turnover See Attached Shift Turnover Sheet Event No.

1 2

3 4

E

  • (N)orr Malfunction Event No.

Type*

N PRO TS CRS C

URO CRS I M ALL I I E al, (R)eactivity, (Qnstrument, (C)or Event DescriDtion Perform the main turbine stop valve functional test / RPS failure during functional test performance TBCCW pump trip w/ failure of standby pump to auto-start SRV inadvertently opens, requiring torus cooling to be maximized /

SRV closes when control power fuses are removed Fast power reduction due to SRV opening Steam leak in the primary containment / hydraulic ATWS I pressure.

instrument failure prevents using containment sprays Standby liquid control pump trips requiring manual start of the alternate pump

~

ADS SRV fails to open during emergency blowdown requiring an additional SRV to be opened Donent, (M)ajor, (TS) Tech Spec s=====

Scenario Outline ES-D 1 II Event No.

1 2

11 Simulation Facility Peach Bottom Scenario No. #3 (modified)

Op Test No.

2008 NRC Malfunction Event No.

Type*

N PRO CRS C

URO CRS 11 Examiners Operators CRS (SL?O)

M ALL 1

6 URO (Arc)

Scenario Summary The scenario begins with the reactor at 95% power. Immediately after shift turnover the crew place HPCl in service for data collection/troubleshooting While the test IS in progress, t Service Water pump will trip on overcurrent, requiring the crew to place the standby pu using the system operating procedure. The crew will then receive a report from the fie1 system cooling water leak, requiring HPCl to be shutdown and declared inoperable N DC power to an in-service RPS MG set output breaker will occur, requiring application of Tech Specs. When this IS complete, the A Condensate pump will trip without the expected runback. Power must be manually reduced using recirc flow to prevent a low-level scram When conditions have stabilized, #2 Auxiliary Bus will trip on overcurrent, removing the remaini Condensate pumps from service An RPS failure will prevent the automatic and manual scram requiring entry into T-101 RPV Control, T-I 17 LeveVPower Control, and the use of Insertion (ARI) to shutdown the reactor. The scram discharge volume will fail to comp and must be manually isolated. RClC will trip when either started manually or automa will remove the final source of high pressure feed As level deteriorates, the crew should start available low pressure ECCS pumps and when the crew determines level cannot be restored a maintained above -195 inches, the reactor will be depressurized in accordance with T-I 12 Emergency Blowdown, after terminating and preventing injection per T-240 (due to the six-rod ATWS). Low pressure ECCS will be available to recover reactor level Initial IC-73, 95% power Conditions Turnover See Attached Shift Turnover Sheet 1

3 1

C PRO TS CRS q

CRS Event Description Perform HPCI System startup (for data collection/troubleshooting)

Service Water pump trip, requiring manual start of standby pump HPCl cooling water leak requires HPCl shutdown Loss of DC power to RPS MG set output breaker Condensate pump trip with recirc runback failure / power reduction -

on over-speed during startup and cannot be reset Two in-series scram discharge volume (SDV) vent valves fail to automatically isolate --

Examiners Scenario Summary Initial Conditions Turnover Scenario Outline ES-D.1 Simulation Facility Peach Bottom Scenario No. #4 (modified)

Op Test No.

2008 NRC Operators CRS (S ?O)

URO prc)

PRO (BOP)

The scenario begins with the reactor at 82% power and a plant shutdown in progress.

lower reactor power using reactor recirculation flow and once below 80% power, the crew wi a condensate pump. Following the condensate pump shutdown, the 2SU-E feeder will trip.

bus will not fast transfer to the other startup feed, causing the E-I diesel to start and it automatically close onto the bus Automatic cooling to the diesel will not occur, requir establish cooling manually. The crew will be required to make a Tech Spec declarati electrical failure.

This will be followed by a trip of the B recirc pump due to a failed RPT breaker The c carry out the actions of OT-I 12 UnexplainedlUnexpected Change in Core Flow, whic establishing single loop operation and consulting Technical Specifications. A loss of occur next, requiring entry into SE-11 Loss of Off-Site Power. The crew should stabilize p parameters using T-100 Scram and should recognize and respond to a failure of the HPCl controller to operate in automatic. The E-4 dieselgenerator will fail to automatically start, and the diesel generator will not start at all. The crew will be required to manually start the E-4 diesel generator using the quick-start pushbutton in order to spray the Drywell later in the scenario.

Following this event, a steam leak will develop in the drywell, requiring the crew to take actions in accordance with OT-101 High Drywell Pressure, and execute T-101 RPV Control and T-102 Primary Containment Control. The high drywell pressure condition will prevent HPCl from beins used to control reactor pressure, resulting in further challenge to the primary containment.

IC-74,82% power See Attached Shift Turnover Sheet Event Event Type*

Description R

URO Lower reactor power with reactor recirculation flow CRS N

PRO Secure a condensate pump CRS Event Malfunction No.

No.

7 1

C TS C

URO Recirc RPT breaker trip / single loop operation TS CRS PRO CRS Loss of 2SU-E startup feed with failure of the E12 bus to fast transi E l EDG auto starts with failure of ESW cooling to diesel auxiliaries M

ALL I Loss of off-site power / steam leak in the drywell C

PRO E-4 diesel generator fails to auto start CRS I

URO HPCl flow controller fails in automatic CRS (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor. (TS) Tech Spec I

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