ML050330272

Initial Exam 09-2004 - Final Exam Outlines

ML050330272
Person / Time
Site:	Columbia
Issue date:	09/20/2004
From:	Gody A Operations Branch IV
To:	Parrish J Energy Northwest
Shared Package
ML040840180	List: ML050240347 ML050330226 ML050330272 ML050330287 ML050330300 ML050330365 ML050330438 ML050340094 ML050690424
References
50-397/04-301
Download: ML050330272 (17)

Text

ES-401 BWR Examination Outline Form ES-401-1 Facility: Columbia Generating Station (CGS) Date of Exam: September 2004 Tier Group RO K/A Category Points SRO-Only Points K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

Total K

A A

2 G

Total 1.

Emergency Abnormal Plant Evolutions 1

3 4

3 3

4 3

20 4

2 1

1 8

2 1

1 1

1 1

2 7

1 1

0 2

4 Tier Totals 4

5 4

4 5

5 27 5

3 1

3 12 2.

Plant Systems 1

2 2

2 3

2 2

2 3

2 3

3 26 1

1 0

2 4

2 1

1 1

1 1

1 1

1 1

2 1

12 1

0 1

0 2

Tier Totals 3

3 3

4 3

3 3

4 3

5 4

38 2

1 1

2 6

3. Generic Knowledge and Abilities Categories 1

2 3

4 10 1

2 3

4 7

3 2

2 3

2 2

1 2

Note:

1.

Ensure that at least two topics from every K/A category are sampled within each tier of the RO outline (i.e., the Tier Totals in each K/A category shall not be less than two). Refer to Section D.1.c for additional guidance regarding SRO sampling.

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 100 75 points and the SRO-only exam must total 25 points.

3.

Select topics from many systems and evolutions; avoid selecting more than two or three K/A topics from a given system or evolution unless they relate to plant-specific priorities.

4.

Systems/evolutions within each group are identified on the associated outline.

5.

The shaded areas are not applicable to the category/tier.

6.*

The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. The SRO K/As must also be linked to 10 CFR 55.43 or an SRO-level learning objective.

7.

On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings (IR) for the SRO applicable license level, and the point totals for each system and category. K/As below 2.5 should be justified on the basis of plant-specific priorities. Enter the group and tier totals for each category in the table above; summarize all the SRO-only knowledge and non-A2 ability categories in the columns labeled K and A. Use duplicate pages for RO and SRO-only exams.

h.

For Tier 3, enter the K/A numbers, descriptions, importance ratings, and point totals on Form ES-401-3.

i.

Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate K/A statements.

ES-401 CGS BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO / SRO)

E/APE # / Name / Safety Function K

1 K

2 K

3 A

1 A

2 G

K/A Topic(s)

IR 295001 Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 S

R S

AK3.02 Reactor Power Response (R)

AK1.03 Thermal Limits (S)

AA1.02 RPS (S) 3.7 4.1 3.3 Q43 Q25 Q7 295003 Partial or Complete Loss of AC / 6 R

S AK2.01 Station Batteries (R)

AA1.02 Emergency Diesel Generators (S) 3.2(R) 4.3(S)

Q59 Q06 295004 Partial or Total Loss of DC Pwr / 6 R

AK1.05 Loss of Breaker Protection (R) 3.3(R)

Q62 295005 Main Turbine Generator Trip / 3 R

AA1.01 Recirculation System: Plant Specific (R) 3.1(R)

Q44 295006 SCRAM / 1 R

AA2.02 Control Rod Position 4.3*

Q45 295016 Control Room Abandonment / 7 R

S 2.4.49 Ability to perform without reference to procedures those actions that require immediate operation of system components and controls. (R) 2.4.29 Knowledge of the Emergency Plan (S) 4.0(R) 4.0(S)

Q36 Q09 295018 Partial or Total Loss of CCW / 8 R

AA2.03 Cause for partial or complete loss 3.2 Q46 295019 Partial or Total Loss of Inst. Air / 8 R

AK2.01 Control Rod Hydraulics 3.8 Q47 295021 Loss of Shutdown Cooling / 4 R

AK1.01 Decay Heat 3.6 Q48 295023 Refueling Acc Cooling Mode / 8 S

R AA1.04 Radiation Monitoring Equipment (R)

AK 3.02 Interlocks Associated with Fuel Handling Equipment (S) 2.9 3.7 Q49 Q02 295024 High Drywell Pressure / 5 R

2.1.32 Ability to apply system limits and precautions.

3.4 Q50 295025 High Reactor Pressure / 3 S

R EK3.08 Reactor/Turbine pressure regulating system operation EK2.08 Reactor/Turbine pressure regulating system 3.5 3.7 Q51 Q08 295026 Suppression Pool High Water Temp. / 5 R

EA1.01 Suppression Pool Cooling 4.1 Q63 295027 High Containment Temperature / 5 Deleted - Not applicable to CGS XXX 295028 High Drywell Temperature / 5 S

R 2.4.4 Ability to recognize abnormal indications for system operating parameters which are entry level conditions for emergency and abnormal operating procedures. (R)

EA2.03 Reactor Water Level (S) 4.0(R) 3.9(S)

Q73 Q13 295030 Low Suppression Pool Wtr Lvl / 5 R

R EK1.03 Heat Capacity EK2.02 RCIC: Plant Specific 3.8 3.7 Q16 Q35 295031 Reactor Low Water Level / 2 R

EK3.03 Spray Cooling 4.1 Q52 295037 SCRAM Condition Present and Power Above APRM Downscale or Unknown / 1 S

R EA2.05 Control Rod Position (R)

EK2.03 ARI/RPT/ATWS: Plant Specific (S) 4.2 4.2 Q53 Q14 295038 High Off-site Release Rate / 9 R

EK2.03 Plant ventilation systems.

3.6(R)

Q54 600000 Plant Fire On Site / 8 R

AA2.13 Need for emergency plant shutdown (R) 3.2 Q64 (19 Total E/APs)

(20 RO & 8 SRO Required)

K/A Category Totals (R) 3 4

3 3

4 3

=20 K/A Category Totals (S) 1 2

1 2

1 1

=8 Group Point Total:

20/8

ES-401 CGS BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO / SRO)

E/APE # / Name / Safety Function K

1 K

2 K

3 A

1 A

2 G

K/A Topic(s)

IR 295002 Loss of Main Condenser Vac / 3 R

AA1.05 Main Turbine 3.2 Q60 295007 High Reactor Pressure / 3 R

S 2.4.1 Knowledge of EOP Entry Conditions and Immediate Action Steps 2.2.22 Knowledge of LCOs and safety limits 4.3 Q17 Q22 295008 High Reactor Water Level / 2 S

AA1.03 Main Steam System 3.1 Q21 295009 Low Reactor Water Level / 2 295010 High Drywell Pressure / 5 295011 High Containment Temp / 5 Deleted - Not applicable to CGS xxx 295012 High Drywell Temperature / 5 R

AK1.01 Pressure/Temperature Relationship (R) 3.3(R)

Q42 295013 High Suppression Pool Temp. / 5 295014 Inadvertent Reactivity Addition / 1 R

AA2.03 Cause of Reactivity Addition 4.0 Q75 295015 Incomplete SCRAM / 1 R

AK3.01 Bypassing Rod Insertion Blocks 3.4 Q58 295017 High Off-site Release Rate / 9 295020 Inadvertent Cont. Isolation / 5 & 7 295022 Loss of CRD Pumps / 1 R

AK2.02 CRD Mechanism 3.1 Q61 295029 High Suppression Pool Wtr Lvl / 5 295032 High Secondary Containment Area Temperature / 5 295033 High Secondary Containment Area Radiation Levels / 9 S

2.4.1 Knowledge of EOP entry conditions and immediate action steps.

4.6 Q20 295034 Secondary Containment Ventilation High Radiation / 9 295035 Secondary Containment High Differential Pressure / 5 295036 Secondary Containment High Sump/Area Water Level / 5 S

EK3.01 Emergency Depressurization 2.8 Q23 500000 High CTMT Hydrogen Conc. / 5 R

2.4.20 Knowledge of Operational Implications of EOP Warnings/Cautions/and notes.

3.3 Q13 (19 Total E/APs)

(7 RO & 4 SRO Required)

K/A Category Point Totals (R) 1 1

1 1

1 2

OK K/A Category Point Totals (S) 0 0

1 1

0 2

OK Group Point Total:

7/4

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

System # / Name K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

K/A Topic(s)

IR 203000 RHR/LPCI: Injection Mode R

A2.17 Keepfill System Failure 3.3 Q41 205000 Shutdown Cooling R

R K5.03 Heat Removal Mechanisms A3.01 SDC/Valve Operation 2.8 3.2 Q07 Q18 206000 HPCI Deleted - Not applicable to CGS XXX 207000 Isolation (Emergency)

Condenser Deleted - Not applicable to CGS XXX 209001 LPCS R

R A1.07 Emergency Generator Loading 2.1.12 Ability to Apply Technical Specifications for a System 3.0 2.9 Q33 Q02 209002 HPCS R

A4.05 Manual Initiation Controls 3.8 Q31 211000 SLC R

A4.06 RWCU Isolation 3.9 Q05 212000 RPS R

K2.01 RPS Motor Generator Sets 3.3 Q19 215003 IRM R

K2.01 IRM Channels/Detectors 2.5 Q74 215004 Source Range Monitor R

R S

K4.03 Rod Withdrawal Blocks (R)

K6.05 Trip Units (R)

A3.04 Control Rod Block Status (S) 3.7(R) 2.6(R) 3.1(S)

Q03 Q27 Q01 215005 APRM / LPRM R

K1.04 LPRM Channels 3.6 Q26 217000 RCIC R

R S

K5.02 Flow Indications 2.4.20 Knowledge of operational implications of EOP warnings/cautions/

and notes.

2.1.12 Ability to apply technical specifications for a system. (S) 3.3 4.0 Q09 Q15 Q16 218000 ADS R

R K1.06 Safety/Relief Valves K6.07 Primary Containment Instrumentation 3.9 3.4 Q28 Q29 223002 PCIS/Nuclear Steam Supply Shutoff R

K3.21 Traversing in-core probe system 2.5 Q12 239002 SRVs R

A2.04 ADS Actuation 4.1*

Q04 259002 Reactor Water Level Control R

S A2.03 Loss of Reactor Level Input (R)

G2.4.1 Knowledge of EOP entry conditions and immediate action steps 3.6(R) 4.6(S)

Q34 Q24 261000 SGTS R

S K4.05 Fission Product Gas Removal (R)

K4.01 Automatic System Initiation (S) 2.6(R) 3.9(S)

Q08 Q03 262001 AC Electrical Distribution R

A1.02 Breaker Lineups 3.2 Q40 262002 UPS (AC/DC)

R A4.01 Transfer From Alternative Source To Preferred Source 2.8 Q06 263000 DC Electrical Distribution R

2.2.13 Knowledge of Tagging and Clearance Procedures (R) 3.6(R)

Q32 264000 EDGs R

K4.02 Emergency Generator Trips (emergency/LOCA) 4.0 Q01 300000 Instrument Air R

K3.02 Systems having pneumatic valves and controls 3.3 Q30 400000 Component Cooling Water R

K3.01 Setpoints on instrument signal levels for normal operations, warnings, and trips that are applicable to the CCWS.

3.0 Q67 K/A Category Point Totals (R):

2 2

2 3

2 2

2 3

2 3

3 (26 RO & 4 SRO Required)

K/A Category Point Totals (S):

0 0

0 1

0 0

0 0

1 0

2 Group Point Total:

26/4

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

System # / Name K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

K/A Topic(s)

IR 201001 CRD Hydraulic 201002 RMCS S

A2.02 Rod Drift Alarm 3.3 Q 04 201003 Control Rod and Drive Mechanism 201004 RSCS R

A4.02 RSCS console switches and indicators: BWR 4,5 3.5 Q11 201005 RCIS 201006 RWM 202001 Recirculation 202002 Recirculation Flow Control 204000 RWCU R

2.1.29 Knowledge of How to Conduct and Verify Valve Lineups 3.4 Q37 214000 RPIS R

A2.01 Failed Reed Switches 3.1 Q10 215001 Traversing In-core Probe 215002 RBM 216000 Nuclear Boiler Inst.

219000 RHR/LPCI: Torus/Pool Cooling Mode R

K2.02 Pumps 3.1 Q39 223001 Primary CTMT and Aux.

226001 RHR/LPCI: CTMT Spray Mode R

K4.12 Prevention of inadvertent containment spray activation 2.9 Q38 230000 RHR/LPCI: Torus/Pool Spray Mode 233000 Fuel Pool Cooling/Cleanup 234000 Fuel Handling Equipment R

K5.05 Fuel Orientation 3.0 Q23 239001 Main and Reheat Steam 239003 MSIV Leakage Control 241000 Reactor/Turbine Pressure Regulator R

S K3.01 Reactor Power K6.10 Bypass Valves 4.1 3.7 Q25 Q05 245000 Main Turbine Gen. / Aux.

R A4.08 Turbine Oil Pressure 2.7 Q21 256000 Reactor Condensate R

K6.06 Reactor Feedwater System 3.3 Q24 259001 Reactor Feedwater R

A3.04 Reactor Water Level 3.8 Q14 268000 Radwaste R

K1.06 Drywell Floor Drains 2.9 Q20 271000 Offgas R

A1.12 Process Radiation Monitoring Indicators 3.1 Q22 272000 Radiation Monitoring 286000 Fire Protection 288000 Plant Ventilation 290001 Secondary CTMT 290003 Control Room HVAC 290002 Reactor Vessel Internals (33 Total Systems)

(12 RO & 2 SRO Required)

K/A Category Point Totals (R) 1 1

1 1

1 1

1 1

1 2

1

K/A Category Point Totals (S):

0 0

0 0

0 1

0 1

0 0

0 Group Point Total (R/S):

12/2

ES-401 Record of Rejected K/As Form ES-401-104 Columbia Generating Station September 2004 Exam Tier / Group Randomly Selected K/A Reason for Rejection RO/SRO 2/1 206000 Not applicable to CGS.

RO/SRO 2/1 207000 Not applicable to CGS.

RO/SRO 1/1 295027 Not applicable to CGS.

RO/SRO 1/2 295011 Not applicable to CGS.

RO 2/1 218000 K6.07 Initial question was rejected by the initial reviewer based on not matching the K/A. A suitable question could not be written so a second K/A from the same K/A section was randomly selected. The new K/A selected was 218000 K 6.02 instead of K6.07.

SRO 2/2 239001 K4.06 Initial question was rejected by the reviewer based on not matching the K/A. A suitable SRO level question could not be constructed from this KA category. Another category and K/A was selected at random from the same tier/group and a new question developed.

SRO 1/1 295004 A2.02 The initial question was rejected by the review based on not being an SRO level question. A suitable SRO question could not be developed from the same K/A category. Therefore a new K/A was randomly selected from the same tier/group and a new question developed.

ES-301 ADMINISTRATIVE TOPICS OUTLINE FORM ES-301-1 Facility: Columbia Generating Station Date of examination: September2004 Examination level: SRO Operating test number:

Administrative (see Note below)

Describe the activity to be performed A1. Conduct of Operations 2.1.18 Ability to make accurate / clear and concise logs /

records / status boards / and reports.

Given information on an inoperable technical specification component, complete an INOP EQUIP/LCO/RFO STATUS SHEET. New A2. Conduct of Operations 2.1.24 - Ability to obtain and interpret station electrical and mechanical drawings. 2.8/3.1 Explain failure of ROA-FN-1A indications from a blown fuse in the trip circuit. CGS LER 88-07 1999 NRC Exam B. Equipment Control 2.2.13 - Knowledge of tagging and clearance procedures.

Given a tagging scenario with mistakes, find and correct errors.

1998 NRC Exam C. Radiation Control 2.3.11 - Ability to control radiation release. 2.7/3.2 Calculate projected dose using QEDPS and information given.

2002 NRC Exam D. Emergency Plan 2.4.41 - Knowledge of Emergency action level thresholds and classifications. 2.3/4.1 After participating in an event on the simulator, determine the E-Plan classification and PAR. New 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.

Page 1

ES-301 ADMINISTRATIVE TOPICS OUTLINE FORM ES-301-1 Page 2 Facility: Columbia Generating Station Date of examination:

Examination level: RO Operating test number:

Administrative (see Note below)

Describe the activity to be performed A1. Conduct of Operations 2.1.7 - Ability to evaluate plant performance and make operational judgments based on operation characteristics/

reactor behavior/and instrument interpretation. 3.7/4.4 Determine actions needed when criticality occurs outside of the ECP. 1999 NRC Exam A2. Conduct of Operations 2.1.12 - Ability to apply Tech Specs for a system.

Given a section of OSP-INST-H101, Shift and Daily Inst.

Checks (Modes 1, 2, and 3), determine SLC operability from the information provided. 1999 NRC Exam B. Equipment Control 2.2.13 - Knowledge of tagging and clearance procedure. (S)

Prepare a tagout for CRDH Pump A without the use of the tagout computer. New C. Radiation Control 2.3.1 - Knowledge of 10CFR20 and related facility radiation control requirements.

Given a valve lineup to perform in the RCA, determine which RWP to use, any applicable limits, and time allowed to complete the task. (S) New Emergency Plan 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.

INDIVIDUAL WALK-THROUGH TEST OUTLINE FORM ES-301-2 Columbia Generating Station September 2004 Facility: Columbia Generating Station Date of examination: September 2004 Exam level: RO / SRO-I B.1 Control Room Systems System / JPM Title Type Code*

Safety Function

a.

Startup RRC Pump A (Alternate Path)

N, A, S 1

R, I

b.

RFPT Startup D, S 2

R, U

c.

Bypass a control rod in Rod Sequence Control System M, S 7

R, I

d.

Shift Shutdown Cooling from RHR A to RHR B N, L, S 4

R, I

e.

Raise Suppression Pool Level Using HPCS System ESF, D, S 5

R, I

f.

Transfer SM-1 from TR-N to TR-S (Faulted)

D, A, S 6

R, I

g.

RPV Depressurization N, L, S 3

R, I, U

h.

Prepare for Emergency Wetwell Venting (Alternate Path)

D, A, L, E, RCA 9

R, I, U B2. Facility Walkthrough

i.

Restore RPS to a Normal Alignment Starting With RPS MG A shutdown (Alternate Path)

Plant N, A, RCA 7

R, I, U

j.

Shift CAS Air Dryers D, RCA, A 8

R, I

k.

Vent Overpiston Area for Control Rod Insertion D, RCA, L, E 1

R, I, U Page 1 JPMOUTR2

INDIVIDUAL WALK-THROUGH TEST OUTLINE FORM ES-301-2 Columbia Generating Station September 2004 Facility: Columbia Generating Station Date of examination: October 2004 Exam level: RO / SRO-I Spare JPMs System / JPM Title Type Code*

Safety Function

1.

Perform Jet Pump Operability Surveillance (Alternate Path)

N, A, RCA 1

m.

Remove Decay Heat from SBGT Carbon Bed D, S, E 9

n.

Restore Control of RPV Level from the Remote Shutdown Panel D, RCA, L, E 2

• Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (L)ow power, (S)imulator, (E)mergency or Abnormal, (R)CA Indicates spare JPMs Page 2 JPMOUTR2

INDIVIDUAL WALK-THROUGH TEST OUTLINE FORM ES-301-2 Columbia Generating Station September 2004 Page 3 JPMOUTR2 Facility: Columbia Generating Station Date of examination: October 2002 Exam level: SRO-U B.1 Control Room Systems System / JPM Title / Type Codes Type Code Safety Function

g.

RPV Depressurization N, L, S 3

R, I, U

h.

Prepare for Emergency Wetwell Venting (Alternate Path)

D, A, L, E, RCA 9

R, I, U

b.

RFPT Startup D, S 2

R, I, U In-Plant Systems

i.

Restore RPS to a Normal Alignment Starting With RPS MG A shutdown N, A, RCA 7

R, I, U

k.

Vent Overpiston Area for Control Rod Insertion D, RCA, L, E 1

R, I, U Spare JPMs System / JPM Title / Type Codes

• Type Code Safety Function

l.

Perform Jet Pump Operability Surveillance (Alternate Path)

N, A, RCA, S 1

m.

Remove Decay Heat from SBGT Carbon Bed D, S, E 9

n.

Restore Control of RPV Level from the Remote Shutdown Panel Plant D, RCA, L, E 2

• Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (L)ow power, (S)imulator, (E)mergency or Abnormal, (R)CA Indicates spare JPMs

Appendix D Scenario Outline Form ES-D-1 No.

Type*

1. Initiated by turnover T=0 N (BOP) Place RWCU-P-1B in service and secure RWCU-P-1A.

2. Initiated by turnover T=0 N (RO)

Perform rod over travel surveillance OSP-CRD-W701.

3.

Active at start T=15 min C (RO)

The third rod tested fails the overtravel surveillance. The control rod is driven full in, withdrawn, and recoupled successfully.

4.

Trigger 1 T=25 I (BOP)

Main steam line flow instrument MS-DPIS-10B fails high.

5.

Trigger 2 T=45 min C (BOP) RWCU-P-1B trips.

6.

Trigger 3 T=55 min M (All)

Fire alarm in the HPCS DG Room. SM-2 and SM-4 ground fault alarms and lockout of SM-2 and SM-4.

7.

Active at start of scenario C (BOP) Failure of SM-1, SM-2 and SM-3 to close in Startup Power on Main Turbine Trip.

8.

Active at start of scenario C (BOP/

RO)

RCIC turbine over speed trip on startup. (Loss of all high pressure injection systems.)

9.

Active at start C (BOP/

RO)

MS-RV-5B will not close when initially opened.

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Scenario 1, 2004 exam NUREG 1021, Revision 8, Supplement 1 Page 2

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station September 2004 Facility: Columbia Scenario Set No: 1 Scenario No: 5 Examiners: _______________ Operators: _______________

Initial conditions:

Plant is at approximately 20% with the main turbine generator synchronized and a startup in progress. Reactor feedwater control is in 3 element on feedpump speed control.

Turnover:

RCC-P-1A is OOS for motor replacement. BPA is selling power to CA. and power should be increased as soon as possible following turnover. The reactivity brief has been given and the power increase is to begin immediately.

Event No.

Timeline Event Type*

Event Description

1.

T=0 N

SRO RO Power increase with rods to 24%.

2.

T=5 I

ALL LPRM 08-41A fails upscale.

TRG-1

3.

T=15 C

SRO BOP Failure of RB exhaust fan requires entry into PPM 5.3.1.

TRG-2

4.

I SRO RO Failure of RFW-LIC-600 to manual.

OVERRIDE TO MANUAL DURING POWER INCREASE.

5.

T=30 M

ALL Loss of SL-81 results in a loss of RCC and subsequent trip of RWCU, RRC, and a manual reactor scram.

TRG 3

6.

M ALL Failure of enough rods to insert such that reactor power is GT 5%.

Active at the beginning of the scenario.

7.

C SRO RO SLC fails - neither squib valve fires.

Active at the beginning of the scenario.

8.

Termination Cue: Power is being controlled with level less than LL>

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station October, 2004 Facility: Columbia Scenario Set No: 1 Scenario No: 10 Examiners: _______________ Operators: _______________

Initial conditions:

The plant is operating at 90% power due to economic dispatch. Power is to be increased to 100% immediately following shift turnover.

Turnover Information: HPCS-P-1 is OOS for motor bearing replacement. It is expected to be returned to service in two days. Tech. Spec. 3.5.1, condition B, was entered four hours ago. A reactivity brief for the power increase has been held and power is to be increased to 100% immediately following shift turnover. There are no pre-conditioning limits.

Event No.

Timeline Event Type*

Event Description

1.

T=0 R

SRO RO Increase power with flow.

2.

When power =

95%

I SRO RO APRM-A fails upscale Tech Spec TRG 1

3.

T=7 C

SRO BOP DEH-P-1A shaft break with a fail to auto start of DEH-P-1B.

TRG 2

4.

T=12 C

RO SRO ASD Channel A2 alarm and fault TRG 3 5/6.

T=20 C

ALL ASD UPS trouble alarm TRG 4 Trip of E-PP-ASD1/4 and ASD CH A1 and B1 fault which results in a manual scram by the crew.

TRG 5

7.

T=30 M

ALL OBE and RHR-B Suction Break with a trip of both RFW pumps.

TRG 6

8.

T=31 C

ALL RCIC trips on initiation and cannot be re-started Automatic upon RCIC initiation.

9.

Termination cue: The scenario can be terminated when the ED has been performed and reactor level is being controlled in the band from

+13 inches to +54 inches.

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Appendix D SCENARIO OUTLINE FORM ES-D-1 Columbia Generating Station October, 2004 Event No. 1

==

Description:==

increase reactor power with flow to 100% power.

Time Position Applicants Actions or Behavior T=0 SRO Directs the RO to increase reactor power to 100% power with RRC flow at the rate of 10 mwe/minute.

RO Increases reactor power with RRC flow as directed.

BOP Monitors plant equipment.

COMMENTS: