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| {{#Wiki_filter:OC NRC Re-Take Exam 2008 Scenario Outline Event No. Facility: Ovster Creek Scenario No.: NRC 1 Op Test No.: NRC 2008-1 Malf. No. Event TY Pe* Examiners: Operators: | | {{#Wiki_filter:OC NRC Re-Take Exam 2008 Scenario Outline Facility: Ovster Creek Scenario No.: NRC 1 Op Test No.: NRC 2008-1 Examiners: Operators: S RO-Steve Johnston Initial Conditions: |
| S RO-Steve Johnston 1 Initial Conditions: | | 0 100% Power 0 RWCU Pump 9 00s 0 RWM is bypassed and 00s Turnover: |
| 0 100% Power 0 RWCU Pump "9" 00s 0 RWM is bypassed and 00s Turnover: | | 0 Perform 602.4.004, Main Steam Isolation Valve 10% Closure Test. |
| 0 Perform 602.4.004, Main Steam Isolation Valve 10% Closure Test. NIA N 2 I VLV-RPS004 TS 7 n MAL-EDS003B MAL-CFWO17 R /I 4 I MAL-NIS021F 8 9 1 1 %l05-22-15 1 MAL-SWSOOI B MAL-RCUO13 VLV-RCU001 M VLV-RCUOW MAL-CNS004A c or B or C or D SRO BOP SRO SRO BOP SRO RO SRO RO SRO BOP SRO RO ALL SRO BOP - Event Description Performs 602.4.004, Main Steam Isolation Valve 10% Closure Test. | | Event Malf. No. Event Event No. TY Pe* Description SRO Performs 602.4.004, Main Steam Isolation Valve 10% |
| MSlV NS04B sticks open during Closure Test TS 3.5.3. Respond to Loss of USS 1A2 480V bus. APRM 6 hop. Failure causes | | 1 NIA N BOP Closure Test. |
| % scram TS 3.7.B, ABN-45 "LOSS of USS 1A2" RAP-G2f Control Rod Drift Out ABN-6 "Control Rod Malfunctions" Respond to trip of Service Water Pump 1-2 ABN-18 "Service Water Failure Response Main Condenser Vacuum Leak Power Reduction required ABN-14 "Loss of Condenser Vacuum" 7. RWCU Leak in the Reactor Building RWCU fails to isolate Secondary Containment Control EOP Emergency Depressurization required A Containment Spray pump trips while in Torus Cooling (I)nstrument, (C)omponent, (M)ajor Transient (TS) Tech Spec NRC 1 Page 1 of 27 OC NRC Retake Exam 2008 Scenario Outline MAL-CRD005 MAL-RPSOOG
| | I MSlV NS04B sticks open during Closure Test n |
| | 2 VLV-RPS004 TS SRO TS 3.5.3. |
| | SRO Respond to Loss of USS 1A2 480V bus. |
| | MAL-EDS003B BOP TS 3.7.B, ABN-45 LOSS of USS 1A2 I |
| | 11 1 SRO APRM 6 hop. Failure causes % scram 4 MAL-NIS021F |
| | / I RO RAP-G2f SRO Control Rod Drift Out |
| | %l05-22-15 ABN-6 Control Rod Malfunctions RO SRO Respond to trip of Service Water Pump 1-2 MAL-SWSOOIB BOP ABN-18 Service Water Failure Response Main Condenser Vacuum Leak 7 MAL-CFWO17 R SRO Power Reduction required RO ABN-14 Loss of Condenser Vacuum 7 . |
| | RWCU Leak in the Reactor Building MAL-RCUO13 RWCU fails to isolate 8 VLV-RCU001 M ALL VLV-RCUOW Secondary Containment Control EOP Emergency Depressurization required 9 |
| | MAL-CNS004A c SRO A Containment Spray pump trips while in Torus Cooling or B or C or D |
| | - BOP (I)nstrument, (C)omponent, (M)ajor Transient (TS) Tech Spec NRC 1 Page 1 of 27 |
|
| |
|
| SWI-RPS006 MAL-NSSOI 78 MAL-PCN001 N MAL-RPS007C VLV-CNS008 PMP-CNS008A Facility: Oyster Creek Scenario No.: NRC 2 Op Test No.: NRC 2008-1 Examiners:
| | OC NRC Retake Exam 2008 Scenario Outline Facility: Oyster Creek Scenario No.: NRC 2 Op Test No.: NRC 2008-1 Examiners: Operators: SRO- Steve Johnston initial Conditions: |
| Operators: | | 90% Power R W M is bypassed and 00s lsophase Bus Fan A is 00s 0 Main Generator voltage control is in manual Turnover: |
| SRO- Steve Johnston C M C initial Conditions: | | Restore the amplidyne to service and transfer main generator voltage control to automatic IAW 336.1 24KV Main Gen Electrical System IAW the ReMA I |
| 90% Power RWM is bypassed and 00s lsophase Bus Fan "A" is 00s 0 Main Generator voltage control is in manual Turnover: | | Event Malf. No. I Event Event No. le* Description |
| Restore the amplidyne to service and transfer main generator voltage control to automatic IAW 336.1 "24KV Main Gen Electrical System" I Event No. I 2 Malf. No. I Event CRD008-34-11 x C SWI-ADS001C ANN-E6D ANN-E2D VLV-NSSOOG | | ~~ |
| * (N)ormal, (R)eactivity, le* SRO ATC SRO BOP SRO ATC SRO BOP SRO BOP SRO ATC ALL SRO BOP IAW the ReMA Event Description
| | Restore the amplidyne to service and transfer main SRO I generator voltage control to automatic IAW 336.1 ATC 24KV Main Gen Electrical System SRO 2 Increase reactor power with control rods BOP x |
| ~~ Restore the amplidyne to service and transfer main generator voltage control to automatic IAW 336.1 "24KV Main Gen Electrical System" Increase reactor power with control rods Uncoupled Control Rod ABN-6 "Control Rod Malfunction" EMRV "A Inadvertently Opens ABN-40 "Stuck Open EMRV'; TS 3.4.8 ~~ ~ ~ ~ Respond to Reactor Recirc Pump "A' Alarms, Pump Discharge Valve fails to close ABN-2 "Recirculation System Failures" TS 3.3.F. Multiple control rod drifts, Manual scram required and fails, ARI required ABNB "Control Rod Malfunction" Steam leak in Primary Containment, DWiTorus Vacuum Breaker fails open Failure of RWCU to Auto isolate, Containment Spray System failures (I)nstrument, (C)omponent, (M)ajor Transient (TS) Tech Spec NRC 2 Page 1 of 21 OC NRC Re-Take Exam 2008 Scenario Outline Event TY Pe* Facility: | | CRD008-34-11 SWI-ADS001C C |
| Oyster Creek Scenario No.: NRC 3 Op Test No.: NRC 2008-1 Event Description Examiners: Operators: | | SRO Uncoupled Control Rod ATC ABN-6 Control Rod Malfunction SRO EMRV A Inadvertently Opens BOP ABN-40 Stuck Open EMRV; TS 3.4.8 |
| RO- Steve Johnston ATC ATC ATC ALL Initial Conditions: | | ~~ ~ ~ ~ |
| 92%Power RWM bypassed and 00s TBCCW pump 2 00s Turnover: Increase reactor power to 100% IAW ReMA Increase Power with Rods | | ANN-E6D ANN-E2D Respond to Reactor Recirc Pump A Alarms, Pump SRO Discharge Valve fails to close VLV-NSSOOG BOP ABN-2 Recirculation System Failures TS 3.3.F. |
| & Recirc Flow to 100% Power Stuck Control Rod CRD Pump 1A Shaft Failure Condensate Pump B Motor Bearing Hi Temp requires power reduction with Recirculation Flow to approx. 65% power Small Steam leak in containment with Hydraulic ATWS Event Malf. No. No. 1 PMP- CRD002A 4 ICH-CW069A MAL- NSSOl7D CRD021A CRD021 B CRDOOI A MAL- MAL- MAL- ATC I CRD FIOW Control Valve fails to 0% i (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Transient (TS) Tech Spec NRC 3 Page 1 of 14}} | | MAL-CRD005 Multiple control rod drifts, Manual scram required and MAL-RPSOOG C SRO fails, ARI required SWI-RPS006 ATC ABNB Control Rod Malfunction MAL-NSSOI78 Steam leak in Primary Containment, DWiTorus MAL-PCN001N M ALL Vacuum Breaker fails open MAL-RPS007C SRO Failure of RWCU to Auto isolate, Containment Spray VLV-CNS008 C PMP-CNS008A BOP System failures |
| | * (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Transient (TS) Tech Spec NRC 2 Page 1 of 21 |
| | |
| | OC NRC Re-Take Exam 2008 Scenario Outline Facility: Oyster Creek Scenario No.: NRC 3 Op Test No.: NRC 2008-1 Examiners: Operators: RO- Steve Johnston Initial Conditions: |
| | 92%Power RWM bypassed and 00s TBCCW pump 2 00s Turnover: |
| | Increase reactor power to 100% IAW ReMA Event No. 1 Malf. No. Event TY Pe* |
| | Event Description Increase Power with Rods & Recirc Flow to 100% Power ATC Stuck Control Rod PMP-CRD002A ATC CRD Pump 1A Shaft Failure Condensate Pump B Motor Bearing Hi Temp 4 ICH-CW069A ATC requires power reduction with Recirculation Flow to approx. 65% power MAL-NSSOl7D MAL- Small Steam leak in containment with Hydraulic CRD021A ALL ATWS MAL-CRD021B MAL-CRDOOIA ATC I CRD FIOW Control Valve fails to 0% |
| | i (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Transient (TS) Tech Spec NRC 3 Page 1 of 14}} |
|
|---|
Category:License-Operator
MONTHYEARML18005A4202018-01-0303 January 2018
Announcement of Generic Fundamentals Examination Section of the Written Operator Licensing Examination for 2018
ML17156A5502017-06-0505 June 2017
Requalification Program Inspection - Oyster Creek Nuclear Generating Station
RS-17-070, Response to NRC Regulatory Issue Summary 2017-03, Preparation and Scheduling of Operator Licensing Examinations2017-05-0303 May 2017
Response to NRC Regulatory Issue Summary 2017-03, Preparation and Scheduling of Operator Licensing Examinations
ML17018A2822017-01-17017 January 2017
Announcement of Generic Fundamentals Examination Section of the Written Operator Licensing Examination for 2017
RS-16-156, Response to NRC Regulatory Issue Summary 2016-09, Preparation and Scheduling of Operator Licensing Examinations2016-07-18018 July 2016
Response to NRC Regulatory Issue Summary 2016-09, Preparation and Scheduling of Operator Licensing Examinations
ML17261B0602016-02-16016 February 2016
Final QA Related Forms (Folder 1)
ML16064A1772016-02-10010 February 2016
Final Written Examination with Answer Key (401-5 Format) (Folder 3)
ML17216A1722016-02-10010 February 2016
Draft Operating Exam (Sections a, B and C) (Folder 2)
ML17216A1742016-02-10010 February 2016
Draft Written Exam (Folder 2)
ML17261B1652016-02-10010 February 2016
Final Outlines (Folder 3)
ML17261B1672016-02-10010 February 2016
Draft - Outlines (Folder 2)
ML17261B1682016-02-10010 February 2016
NRC Comments on Draft Licensee-Developed Exam (Written) (Folder 2)
ML17261B1692016-02-10010 February 2016
NRC Comments of Draft Licensee-Developed Exam (Operating) (Folder 2)
ML16064A1712016-02-10010 February 2016
Final Operating Exam (Sections a, B, and C) (Folder 3)
ML16026A5812016-01-26026 January 2016
Initial Operator Licensing Operating Test and Written Examination Approval - Oyster Creek Nuclear Generating Station
ML14311A6622014-11-0303 November 2014
September 10, 2014, NRC Generic Fundamentals Examination Results - Oyster Creek Nuclear Generating Station Cover Letter
ML15016A1462014-06-0404 June 2014
Miscellaneous Exam Material (Folder 1)
ML14163A3872014-05-28028 May 2014
Handouts to Applicants, Summary of References (Folder 3)
ML14139A0052014-05-16016 May 2014
Initial Operator Licensing Operating Test and Written Examination Approval-Oyster Creek Nuclear Generating Station
ML15016A1522014-05-13013 May 2014
Final Outlines (Folder 3)
ML14163A3882014-05-13013 May 2014
Final Operating Exam (Sections a, B, and C) (Folder 3)
ML14163A3862014-05-13013 May 2014
Final Written Examination with Answer Key (405-5 Format) (Folder 3)
ML14167A3122014-05-0707 May 2014
NRC Comments on Draft Licensee-Developed Exam (Operating) (Folder 2)
ML14167A3232014-05-0505 May 2014
NRC Comments on Draft Licensee-Developed Exam (Written) (Folder 2)
ML14167A3842014-04-0202 April 2014
Draft Operating Exam (Sections a, B, and C) (Folder 2)
ML14167A2982014-04-0202 April 2014
Draft Outlines (Folder 2)
ML14167A3682014-04-0202 April 2014
Draft Written Exam (Folder 2)
RS-12-114, (EGC) - Response to NRC Regulatory Issue Summary 2012-07, Preparation and Scheduling of Operator Licensing Examinations2012-07-0505 July 2012
(EGC) - Response to NRC Regulatory Issue Summary 2012-07, Preparation and Scheduling of Operator Licensing Examinations
IR 05000219/20123012012-06-18018 June 2012
Er 05000219-12-301; 5/14/2012 - 5/24/2012; Oyster Creek Nuclear Generating Station; Initial Operator Licensing Examination Report
ML12172A0692012-06-13013 June 2012
Final Qa/Related Forms (Folder 1)
ML12165A6092012-06-0606 June 2012
Final Written Examination with Answer Key (401-5 Format) (Folder 3)
ML12165A6012012-06-0606 June 2012
Final Outlines (Folder 3)
ML12159A2442012-06-0101 June 2012
NRC Comments on Draft Licensee-Developed Exam (Written) (Folder 2)
ML12159A3912012-06-0101 June 2012
Draft Written Exam (Folder 2)
ML12159A2582012-06-0101 June 2012
Draft - Outlines (Folder 2)
ML12159A2522012-06-0101 June 2012
NRC Comments on Draft Licensee-Developed Exam (Operating) (Folder 2)
ML12165A6352012-06-0101 June 2012
Handouts to Applicants (Folder 3)
ML12128A2242012-05-0707 May 2012
Initial Operator Licensing Operating Test and Written Examination Approval - Oyster Creek Nuclear Generating Station,
ML1130000532011-10-27027 October 2011
Announcement of Generic Fundamentals Examination 2012 Administration Dates
IR 05000219/20113012011-08-11011 August 2011
Er 05000219-11-301, July 11-20, 2011, Oyster Creek Nuclear Generating Station; Initial Operator Licensing Examination Report
ML12017A1642011-07-30030 July 2011
Draft - Outlines (Folder 2)
ML1124903532011-07-28028 July 2011
Final Qa/Related Forms (Folder 1)
ML1121305252011-07-11011 July 2011
Final Outlines (Folder 3)
ML1121305282011-07-0606 July 2011
Final Written Examination with Answer Key (401-5 Format) (Folder 2)
ML1121305342011-07-0606 July 2011
Summary of Handouts to Applicants (Folder 3)
ML1121305412011-07-0606 July 2011
Final Operating Exam (Sections a, B, and C) (Folder 3)
ML1118101102011-06-30030 June 2011
Operator Licensing Examination Approval (Oyster Creek)
ML1118702612011-06-27027 June 2011
NRC Comments on Draft Licensee-Developed Exam (Operating) (Folder 2)
ML1118701862011-06-27027 June 2011
NRC Comments on Draft Licensee-Developed Exam (Written) (Folder 2)
ML1118702782011-05-27027 May 2011
Draft Operating Exam (Sections a, B, and C) (Folder 2)
2018-01-03
[Table view]
Category:Part 55 Examination Related Material
MONTHYEARML18005A4202018-01-0303 January 2018
Announcement of Generic Fundamentals Examination Section of the Written Operator Licensing Examination for 2018
RS-17-070, Response to NRC Regulatory Issue Summary 2017-03, Preparation and Scheduling of Operator Licensing Examinations2017-05-0303 May 2017
Response to NRC Regulatory Issue Summary 2017-03, Preparation and Scheduling of Operator Licensing Examinations
ML17018A2822017-01-17017 January 2017
Announcement of Generic Fundamentals Examination Section of the Written Operator Licensing Examination for 2017
RS-16-156, Response to NRC Regulatory Issue Summary 2016-09, Preparation and Scheduling of Operator Licensing Examinations2016-07-18018 July 2016
Response to NRC Regulatory Issue Summary 2016-09, Preparation and Scheduling of Operator Licensing Examinations
ML17261B0602016-02-16016 February 2016
Final QA Related Forms (Folder 1)
ML17261B1692016-02-10010 February 2016
NRC Comments of Draft Licensee-Developed Exam (Operating) (Folder 2)
ML17261B1682016-02-10010 February 2016
NRC Comments on Draft Licensee-Developed Exam (Written) (Folder 2)
ML17261B1672016-02-10010 February 2016
Draft - Outlines (Folder 2)
ML17261B1652016-02-10010 February 2016
Final Outlines (Folder 3)
ML17216A1742016-02-10010 February 2016
Draft Written Exam (Folder 2)
ML17216A1722016-02-10010 February 2016
Draft Operating Exam (Sections a, B and C) (Folder 2)
ML16064A1772016-02-10010 February 2016
Final Written Examination with Answer Key (401-5 Format) (Folder 3)
ML16064A1712016-02-10010 February 2016
Final Operating Exam (Sections a, B, and C) (Folder 3)
ML16026A5812016-01-26026 January 2016
Initial Operator Licensing Operating Test and Written Examination Approval - Oyster Creek Nuclear Generating Station
ML14311A6622014-11-0303 November 2014
September 10, 2014, NRC Generic Fundamentals Examination Results - Oyster Creek Nuclear Generating Station Cover Letter
ML15016A1462014-06-0404 June 2014
Miscellaneous Exam Material (Folder 1)
ML14163A3872014-05-28028 May 2014
Handouts to Applicants, Summary of References (Folder 3)
ML14139A0052014-05-16016 May 2014
Initial Operator Licensing Operating Test and Written Examination Approval-Oyster Creek Nuclear Generating Station
ML14163A3882014-05-13013 May 2014
Final Operating Exam (Sections a, B, and C) (Folder 3)
ML14163A3862014-05-13013 May 2014
Final Written Examination with Answer Key (405-5 Format) (Folder 3)
ML15016A1522014-05-13013 May 2014
Final Outlines (Folder 3)
ML14167A3122014-05-0707 May 2014
NRC Comments on Draft Licensee-Developed Exam (Operating) (Folder 2)
ML14167A3232014-05-0505 May 2014
NRC Comments on Draft Licensee-Developed Exam (Written) (Folder 2)
ML14167A3842014-04-0202 April 2014
Draft Operating Exam (Sections a, B, and C) (Folder 2)
ML14167A3682014-04-0202 April 2014
Draft Written Exam (Folder 2)
ML14167A2982014-04-0202 April 2014
Draft Outlines (Folder 2)
RS-12-114, (EGC) - Response to NRC Regulatory Issue Summary 2012-07, Preparation and Scheduling of Operator Licensing Examinations2012-07-0505 July 2012
(EGC) - Response to NRC Regulatory Issue Summary 2012-07, Preparation and Scheduling of Operator Licensing Examinations
IR 05000219/20123012012-06-18018 June 2012
Er 05000219-12-301; 5/14/2012 - 5/24/2012; Oyster Creek Nuclear Generating Station; Initial Operator Licensing Examination Report
ML12172A0692012-06-13013 June 2012
Final Qa/Related Forms (Folder 1)
ML12165A6012012-06-0606 June 2012
Final Outlines (Folder 3)
ML12165A6092012-06-0606 June 2012
Final Written Examination with Answer Key (401-5 Format) (Folder 3)
ML12159A2522012-06-0101 June 2012
NRC Comments on Draft Licensee-Developed Exam (Operating) (Folder 2)
ML12159A3912012-06-0101 June 2012
Draft Written Exam (Folder 2)
ML12159A2582012-06-0101 June 2012
Draft - Outlines (Folder 2)
ML12159A2442012-06-0101 June 2012
NRC Comments on Draft Licensee-Developed Exam (Written) (Folder 2)
ML12165A6352012-06-0101 June 2012
Handouts to Applicants (Folder 3)
ML12128A2242012-05-0707 May 2012
Initial Operator Licensing Operating Test and Written Examination Approval - Oyster Creek Nuclear Generating Station,
ML1130000532011-10-27027 October 2011
Announcement of Generic Fundamentals Examination 2012 Administration Dates
IR 05000219/20113012011-08-11011 August 2011
Er 05000219-11-301, July 11-20, 2011, Oyster Creek Nuclear Generating Station; Initial Operator Licensing Examination Report
ML12017A1642011-07-30030 July 2011
Draft - Outlines (Folder 2)
ML1124903532011-07-28028 July 2011
Final Qa/Related Forms (Folder 1)
ML1121305252011-07-11011 July 2011
Final Outlines (Folder 3)
ML1121305282011-07-0606 July 2011
Final Written Examination with Answer Key (401-5 Format) (Folder 2)
ML1121305342011-07-0606 July 2011
Summary of Handouts to Applicants (Folder 3)
ML1121305412011-07-0606 July 2011
Final Operating Exam (Sections a, B, and C) (Folder 3)
ML1118101102011-06-30030 June 2011
Operator Licensing Examination Approval (Oyster Creek)
ML1118702612011-06-27027 June 2011
NRC Comments on Draft Licensee-Developed Exam (Operating) (Folder 2)
ML1118701862011-06-27027 June 2011
NRC Comments on Draft Licensee-Developed Exam (Written) (Folder 2)
ML1118702672011-05-27027 May 2011
Draft - Outlines (Folder 2)
ML1118702782011-05-27027 May 2011
Draft Operating Exam (Sections a, B, and C) (Folder 2)
2018-01-03
[Table view] |
Text
OC NRC Re-Take Exam 2008 Scenario Outline Facility: Ovster Creek Scenario No.: NRC 1 Op Test No.: NRC 2008-1 Examiners: Operators: S RO-Steve Johnston Initial Conditions:
0 100% Power 0 RWCU Pump 9 00s 0 RWM is bypassed and 00s Turnover:
0 Perform 602.4.004, Main Steam Isolation Valve 10% Closure Test.
Event Malf. No. Event Event No. TY Pe* Description SRO Performs 602.4.004, Main Steam Isolation Valve 10%
1 NIA N BOP Closure Test.
I MSlV NS04B sticks open during Closure Test n
2 VLV-RPS004 TS SRO TS 3.5.3.
SRO Respond to Loss of USS 1A2 480V bus.
MAL-EDS003B BOP TS 3.7.B, ABN-45 LOSS of USS 1A2 I
11 1 SRO APRM 6 hop. Failure causes % scram 4 MAL-NIS021F
/ I RO RAP-G2f SRO Control Rod Drift Out
%l05-22-15 ABN-6 Control Rod Malfunctions RO SRO Respond to trip of Service Water Pump 1-2 MAL-SWSOOIB BOP ABN-18 Service Water Failure Response Main Condenser Vacuum Leak 7 MAL-CFWO17 R SRO Power Reduction required RO ABN-14 Loss of Condenser Vacuum 7 .
RWCU Leak in the Reactor Building MAL-RCUO13 RWCU fails to isolate 8 VLV-RCU001 M ALL VLV-RCUOW Secondary Containment Control EOP Emergency Depressurization required 9
MAL-CNS004A c SRO A Containment Spray pump trips while in Torus Cooling or B or C or D
- BOP (I)nstrument, (C)omponent, (M)ajor Transient (TS) Tech Spec NRC 1 Page 1 of 27
OC NRC Retake Exam 2008 Scenario Outline Facility: Oyster Creek Scenario No.: NRC 2 Op Test No.: NRC 2008-1 Examiners: Operators: SRO- Steve Johnston initial Conditions:
90% Power R W M is bypassed and 00s lsophase Bus Fan A is 00s 0 Main Generator voltage control is in manual Turnover:
Restore the amplidyne to service and transfer main generator voltage control to automatic IAW 336.1 24KV Main Gen Electrical System IAW the ReMA I
Event Malf. No. I Event Event No. le* Description
~~
Restore the amplidyne to service and transfer main SRO I generator voltage control to automatic IAW 336.1 ATC 24KV Main Gen Electrical System SRO 2 Increase reactor power with control rods BOP x
CRD008-34-11 SWI-ADS001C C
SRO Uncoupled Control Rod ATC ABN-6 Control Rod Malfunction SRO EMRV A Inadvertently Opens BOP ABN-40 Stuck Open EMRV; TS 3.4.8
~~ ~ ~ ~
ANN-E6D ANN-E2D Respond to Reactor Recirc Pump A Alarms, Pump SRO Discharge Valve fails to close VLV-NSSOOG BOP ABN-2 Recirculation System Failures TS 3.3.F.
MAL-CRD005 Multiple control rod drifts, Manual scram required and MAL-RPSOOG C SRO fails, ARI required SWI-RPS006 ATC ABNB Control Rod Malfunction MAL-NSSOI78 Steam leak in Primary Containment, DWiTorus MAL-PCN001N M ALL Vacuum Breaker fails open MAL-RPS007C SRO Failure of RWCU to Auto isolate, Containment Spray VLV-CNS008 C PMP-CNS008A BOP System failures
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Transient (TS) Tech Spec NRC 2 Page 1 of 21
OC NRC Re-Take Exam 2008 Scenario Outline Facility: Oyster Creek Scenario No.: NRC 3 Op Test No.: NRC 2008-1 Examiners: Operators: RO- Steve Johnston Initial Conditions:
92%Power RWM bypassed and 00s TBCCW pump 2 00s Turnover:
Increase reactor power to 100% IAW ReMA Event No. 1 Malf. No. Event TY Pe*
Event Description Increase Power with Rods & Recirc Flow to 100% Power ATC Stuck Control Rod PMP-CRD002A ATC CRD Pump 1A Shaft Failure Condensate Pump B Motor Bearing Hi Temp 4 ICH-CW069A ATC requires power reduction with Recirculation Flow to approx. 65% power MAL-NSSOl7D MAL- Small Steam leak in containment with Hydraulic CRD021A ALL ATWS MAL-CRD021B MAL-CRDOOIA ATC I CRD FIOW Control Valve fails to 0%
i (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Transient (TS) Tech Spec NRC 3 Page 1 of 14