NTD-06-074, Draft - Outlines (Folder 2)

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Draft - Outlines (Folder 2)
ML070120472
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 09/27/2006
From: Kafantaris M
Public Service Enterprise Group
To: D'Antonio J M
Operations Branch I
Sykes, Marvin D.
Shared Package
ML060800083 List:
References
50-272/06-301, 50-311/06-301, ES-301, ES-301-1, NTD-06-074 50-272/06-301, 50-311/06-301
Download: ML070120472 (26)
v • d • e


Text

September 27,2006 NTD-06-074 Mr. Joseph M. D'Antonio Chi e f Examiner Division of Reactor Safety US Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA. 19406- 141 5

Dear Mr. D'Antonio,

Salem Initial License Examination Outline Enclosed is our proposed outline for the initial license examination to be conduc :d for S lem candidates during a-two-week period beginning on December 1 1,2006. These materials should be witheld from public disclosure until after the examinations are complete.

Included are: Form ES-20 1-2, Examination Outline Oualitv Checklist. Form ES-301-1, Administrative Topics Outline.

Form ES-301-2, Control Room Systems

/ In-Plant System Outline.

Form ES-301-5, (2 pages), Transient and Event Checklist.

Form ES-D-1,14 uages), Appendix D, Scenario Outline. Form ES-401-2, PWR Examination Outline:

Separate forms are completed for the RO and SRO sections of the examinations.

Form ES-401-4, Record of Rejected WAS. the Random Exam Generation software was uploaded into our system, the previosly NRC approved suppressed WA's were un-suppressed, therefore ALL WA's were subject to selection. Additionally, the RO examination was generated with a previous version of the Exam Generation software, (prior to the release of the current version), hence the relatively high number of WA's rejected due to over sampling.

Please note that when the latest version of The examination team is currently drafting all portions of the examination.

If you have any questions or comments, please call me at 856-339-2215. The Lead Exam Author, Gerry Gauding, may be contacted as needed at 856-339-1554.

Sincerely, Salem Operations Training Manager October 18,2006 Mr. Joseph M. DAntonio Chief Examiner Division of Reactor Safety US Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA.

19406-1 41 5

Dear Mr. D'Antonio,

Salem Initial License Examination Outline Enclosed is OUT revised outline for the initial license examination to be conducted for Salem candidates during a two-week period beginning on December 1 1,2006. These materials should be witheld fi-om public disclosure until after the examinations are complete. Included are:

0 Form ES-301-1, Administrative Topics Outline. 0 Form ES-301-5, (2 pages), Transient and Event Checklist.

0 Form ES-D-1, (2 pages). Appendix D, Scenario Outline.

Additionally, there is also: 1. An explanation of the random selection process used in conjunction with deleted K/A replacement.

2. Explanation for ESG #1, Event # 7, Instrument Failure.

The examination team is currently drafting all portions of the examination.

If you have any questions or comments, please call me at 856-339-2215.

The Lead Exam Author, Gerry Gauding, may be contacted as needed at 856-339-1554.

Sincerely, Salem Operations Training Manager ES-30 1 Ad ministrative Topics Outline Form ES-301-1 Facility:

SALEM Date of Examination:

1211 I12006 Examination Level: 0 RO SRO Operating Test Number: INDIA ILT NRC Ad mi nistrative Topic (See Note) Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Plan Type Code* R, M Describe activity to be performed Review a completed surveillance to calculate the Quadrant Power Tilt Ratio. (WA 2.1.7 SRO-4.4) Review a completed Shutdown Margin calculation. (K/A 2.1.25 SRO 3.1) (WA 2.2.1 3SR0 3.8) - Knowledge of tagging and clearance procedures Evaluate a tagging request. Determine Radiological Conditions For Personnel Exposure Using a Room Survey Map. 2.3.1 0 Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure. (SRO 3.1) Classify Emergency

/ Non-Emergency Events, and complete the ICMF. (WA 2.4.29 SRO-4.0) 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 and Criteria (C)ontrol Room, (S)imulator, or Class(R)oom (D)irect from bank, (3 for ROs; 4 for SROs & RO retakes) (N)ew or (M)odified from bank (1) (P)revious 2 exams (1 ; randomly selected)

Appendix D Scenario Outline Form ES-D-1 , Event Malf.

No. Event Type* ' No. i Facility:

SALEM I & 2 Scenario No.: NRC #2 Op-Test No.: India Examiners: Operators:

initial Conditions:

Turnover:

and surveillances are complete and approval to proceed to mode I has been given. Orders to the shift is to raise power in preparation for placing turbine on line 4% Rated Thermal Power Unit at 4% power returning from a forced outage due to DEHC problems. All approvals N/R ---I- 1 CRSIPOIRO REM: MC12D CRS 3 CV0034 CIC 1 VL0245 I CRSIRO C 1 I CRS/RO/PO M 1 RC0002 I ALL 6 C 1 RP0'08 1 CRSIRO Event Description Raise power to 18% to place turbine on line Loss of Tripping Capability B Rx Trip Breaker (TS CRS) 23 charging pump trips and Letdown valve fails to close (TS C RS) Failure of 3 Station Power Transformer (TS CRS) Small Break LOCA Auto SI fails to actuate 2SJ12-BIT Outlet Valve fails to Auto open on SEC signal ~ Loss of Off-Site Power ECCS restoration I I Appendix D. Page 38 of 39 Appendix D Scenario Outline Form ES-D-1 Facility:

SALEM 1 8.2 Scenario No.: NRC

  1. 3 Op-Test No.: India Examiners:

Operators:

initial Conditions:

100% Rated Thermal Power BOL Turnover: Solar Magnetic Disturbances have been occurring currently at K-3, river grass loading very heavy at Unit at 100% power, 21 AFW pump is tagged for emergent work to inboard bearing, 11 last tide change, high tide in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. - Event No. 1 2 3 4 5 6 7 * (N)orm Malf. No. EL12A RCOOI 4B CC0329 AN0529 RP0069 RP0073 RP0279A RP0279B AFOl81 B AFOI 83 , (R)eactivii Event Type* N/R CRS/PO/RO I/R CRS/RO C CRS/PO C CRS/RO C ALL C CRS/PO M/C All (1)nstrumeni Event Description Power Red to 80% due to Grid Disturbance(SMD) 22 Loop Thot fails during downpower (TS CRS) ~ CCW leak on 21 CCW header (TS CRS) Major Oil Leak at MPT Main Turbine fails to TriplManual MSLl required 22 AFW pump trips after AFW throttled 23 AFW pp trips, Loss of Heat Sink, CN pump recovery (C)omponent, (M)ajor Appendix D. Page 38 of 39

/ ES-401 PWR Examination Outline Form ES-401-2 Facility: Salem Generating Station Printed: 09/01/2006 Date Of Exam: 12/11/2020 Note: 1. 2. 3. 4. 5. 6. 7 .* 8. 3. Ensure that at least two topics from every WA category are sampled within each tier of the RO and SRO-only outlines (Le., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each WA category shall not be less than two). The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by 21 from that specified in the table based on NRC revisions.

The final RO exam must total 75 points and the SRO-only exam must total 25 points. 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.

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 ES-401-3.

Limit SRO selections to WAS that are linked to 10 CFR 55.43. 1 PWR RO Examination Outline 000009 Small Break LOCA I 3 Printed: 09/01/2006 X Facility:

Salem Generating Station ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2 000022 Loss of Rx Coolant Makeup

/ 2 000027 Pressurizer Pressure Control System Malfunction 13 000029 ATWS / 1 000038 Steam Gen. Tube Rupture / 3 000040 Steam Line Rupture - Excessive Heat Transfer 14 A21 G I KATopic (Imp. 1 Point X X I ElAPE # / Name / Safety Function I K1 lK2 I K3 (A lx X I X X X I 6000Geactor Trip - Stabilization - 1x1 I I EKl.03 - Reasons for closing the main turbine governor valve and the main turbine stop valve after a reactor trip 3.7 1 Recovery / 1 ~~ - Change in leak rate with change in pressure 3-1 I 000008 Pressurizer Vapor Space Accident

/ X I3 II ~~ 1- 1z1.02 - Use of steam tables 1 3.5 1 r ~~ I 6001 1 Large Break LOCA I 3 I 1x1 I I lEK2.02 - Pumps 1 2.6* 1 1 1 000015/000017 RCP Malfunctions 14 I 1 1 I X I (AAl.11 - RCP odoff and run indicators I 2.5 I 1 X 2.4.21 - Knowledge of the parameters and logic used to assess the status of safety functions including:

1. Reactivity control;
2. Core cooling and heat removal;
3. Reactor coolant system integrity; 4. Containment conditions;
5. Radioactivity release control. 3.7 1 I 2.7 I 1 X 2.4.18 - Knowledge of the specific I bases for EOPs. 2.9* I EK2.06 - Breakers, relays, and disconnects 3.6* 1 EK3.03 - Automatic actions associated with high radioactivity in SIG sample lines I 4-6 I ' AA2.02 - Conditions requiring a reactor hP I 3.8 I AK3.03 - Manual control of AFW flow control valves 000054 Loss of Main Feedwater

/ 4 000055 Station Blackout 16 EAI.06 - Restoration of power with one I IED/G 000056 Loss of Off-site Power I 6 g202 - ESF load sequencer status 1 1:;: 1 ; AK3.01- Use of dc control power by ED/Gs 000058 Loss of DC Power / 6 WE04 LOCA Outside Containment

/ 3 X - EA2.2 - Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments 3.6 EAI. 1 - Components, and functions of control and safety systems, including insmentation, signals, interlocks, failure modes, and automatic and manual features 4.1 WE05 Inadequate Heat Transfer - Loss of Secondary Heat Sink 14 WE1 1 Loss of Emergency Coolant Recirc. / 4 3.6 EK2.1 - Components, and hctions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features 1 PWR RO Examination Outline E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G KATopic WE12 - Steam Line Rupture - Excessive X EAl.2 - Operating behavior Heat Transfer / 4 characteristics of the facility Printed: 09/01/2006 Imp. Points 3.6 1 WACategoryTotals:

3 3 3 4 3 2 2 Group Point Total: 18 PWR RO Examination Outline Facility:

Salem Generating Station A2 G Printed: 09/01/2006 KATopic Imp. Point!

ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 2 Form ES-401-2 EIAPE # I Name I Safety Function 000024 Emergency Boration / 1 000032 Loss of Source Range NI 17 000033 Loss of Intermediate Range NI I 7 000069 Loss of CTMT Integrity I 5 K1 K2 X I 000076 High Reactor Coolant Activity

/ 9 I I X source-range, intermediate-range, and power-range channel readings AA1.01 - Isolation valves, dampers, 3.5 1 K3 ]A1 : Total: 'I 1 1 I 3.6 I AK1.02 - Relationship between boron IIII addition and reactor power WE03 LOCA Cooldown - Depress. / 4 W/E06 Inad. Core Cooling

/ 4 WE07 Inad. Core Cooling I 4 W/E13 Steam Generator Over-pressure 14 KIA Category Totals: ~~ ~~ ~~~~ 1 7- I AA1.01 - Manual restoration of power 1 3.1 *1 1 X X 2 2 I I X I lAA2.01 ~ Equivalency between I 3.0 I 1 X 12 I I 1 1 and electropneumatic devices I I X I I I IAK2.01 -Process radiationmonitors 1 2.6 I 1 20 EK1.l - Components, capacity, and fbnction of emergency systems EK2.1 - Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features EK3.3 - Manipulation of controls required to obtain desired operating results during abnormal, and emergency situations EA2.2 - Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments Group Poh 3.4 3.6 3.8 3.0 1 PWR RO Examination Outline Facility: Salem Generating Station Printed: 09/01/2006 1

Facility:

Salem Generating Station ES - 401 Sys/Evol # / Name 076 Service Water 078 Instrument Air 103 Containment KIA Category Totals:

PWR RO Examination Outline Printed: 09/01/2006 P K3 - 3 1; ant K4 - X - 3 ystems - Tier !/G A2 - 3 :I roup 1 Form ES-401-2 releases A3.02 - Emergency heat loads transfers of control X 2.2.28 - Knowledge of new 2.6 1 I 1 3~andspenthelmovement I I 28 I procedures.

Group Point Total:

2 PWR RO Examination Outline Facility: Salem Generating Station Printed: 09/01/2006 Plant Systems - Tier 2 / Group 2 Form ES-401-2 1 Generic Knowledge and Abilities Outline (Tier

3) PWR RO ExaminationOutline Conduct of Operations Facilitv: Salem Generating Station

2.1.1 Knowledge

of conduct of operations 3.7 1 2.1.1 1 Knowledge of less than one hour technical 3 .O 1 Category Total: 2 requirements.

specification action statements for systems. Generic Cateporv

_I KA KA Topic 2.2.4 2.2.26 Printed: 09/01/2006 Form ES-401-3 ImD. Points (multi-unit)

Ability to explain the variations in 2.8 1 control board layouts, systems, instrumentation and procedural actions between units at a facility. Knowledge of refueling administrative 2.5 1 requirements.

2.3.4 2.3.10 2.3.1 1 Equipment Control Knowledge of radiation exposure limits and 2.5 1 contamination control, including permissible levels in excess of those authorized. Ability to perform procedures to reduce 2.9 1 excessive levels of radiation and guard against personnel exposure.

Ability to control radiation releases.

2.7 1 Emergency ProceduresD'lan 2.4.27 Knowledge of fne in the plant procedure.

2.4.46 Ability to verify that the alarms are consistent Ability to interpret control room indications to with the plant conditions.

2.4.48 verify the status and operation of system, and understand how operator actions and directives affect plant and system conditions.

~ Radiation Control 3 .O 1 3.5 1 3.5 1 I Category Total: 31 Generic Total:

10 1 ES-401 PWR Examination Outline Form ES-401-2 Tier 1. mergenq & ibnormal Plant iolutions

2. Plant Systems Facility:

Salem Generating Station Printed: 09/01/2006 Date Of Exam: 1211 1 /2020 Group K1 K2 K3 K4 IK5 I K6 AI A2 A31 A4 G* Total A2 G* Total 1 000 00 00 5 2 7 00 5 0 5 000 N/A N/A Tier Totals 0 0 0 00 00 10 2 12 1000000000000 3 1 4 2 000000000000 02 0 2 Tier 0 0 0 0 0 0 0 0 0 0 0 0 5 1 6 Totals RO K/A Category Points 1 2 3 4 0 0 0 0 0 3. Generic Knowledge And Abilities Categ ories 1234 2212 7 Note: 1. 2. 3. 4. 5. 6. 7 .* 8. 3. Ensure that at least two 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 WAcategory 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 WAcategones.

The generic (G) WAS in Tiers 1 and 2 shall be selected from Section 2 of the WACatalog, 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 #1 does not apply). Use duplicate pages for RO and SRO-only exams. For Tier 3, select topics from Section 2 of the K/A 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 PWR SRO Examination Outline Facility: Salem Generating Station *mal A1 Pla A2 X X X X X 05 000022 Loss of Rx Coolant Makeup 12 I I I E/ME # I Name / Safety Function K1 K2 00001 1 Large Break LOCA / 3 000025 Loss of RHR System / 4 K3 000038 Steam Gen. Tube Rupture I3 000056 Loss of Off-site Power / 6 WE05 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 WACategory Totals: I II 000040 Steam Line Rupture - Excessive Heat Transfer / 4 0 0 0 Printed: 09/01/2006 olutions - Tier 1 I Group 1 Form ES-401-: ~ KATopic Imp. Points ~~ - EA2.08 - Conditions necessary for 3.9* 1 AA2.02 - Charging pump problems 3.7 1 2.4.16 - Knowledge of EOP 4.0 1 recovery when accident reaches stable phase implementation hierarchy and coordination with other support 1 procedures.

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

initiation 1 and setpoint 3.1 1 AA2.04 - Conditions requiring ESFAS 4.7 1 ~4A2.01 - PORV controller indicator 3.4 1 EA2.2 - Adherence to appropriate procedures and operation within the limitations in the facility's license and Group Point Total: 7 1 PWR SRO Examination Outline Printed: 09/01/2006 Facility:

Salem Generating Station ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 Form ES-401-2 A1 A2 X X X X X 05 E/APE ## I Name I Safety Function 000024 Emergency Boration

/ 1 WE07 had. Core Cooling / 4 WE08 RCS Overcooling - PTS 14 WE09 Natural Circ. / 4 WE 16 High Containment Radiation

/ 9 IUACategory Totals:

-- I I K1 K2 K3 0 0 0 G KATopic Imp. Points AA2.05 - Amount ofboron to add to 3.9 1 achieve required SDM EA2.2 - Adherence to appropriate 3.9 1 procedures and operation within the limitations in the facility's license and amendments selection of appropriate procedures during abnormal and emergency overations EA2.1 - Facility conditions and 4.2 1 EM. 1 - Facility conditions and selection of appropriate procedures during abnormal and emergency ouerations 3.8 1 1 EA2.2 - Adherence to appropriate procedures and operation withm the limitations in the facility's license and amendments 3.3 1 0 Group Point Total: 5 Facility:

Salem Generating Station G X KATopic A2.04 - RHR valve malfunction A2.05 - Effect of loss of instrument and control air on the position of the CCW valves that are air operated 2.2.26 - Knowledge of refbeling administrative requirements.

A2.12 - Failure of feedwater regulating valves ~ 005 Residual Heat Removal 008 Component Cooling Water 012 Reactor Protection 41 I I 059 Main Feedwater A2 A3 X X X 030 Sys/Evol # / Name PWR SRO Examination Outline Plant Systems - Tier 2 / Group 1 K1 Printed: 0910 1 12006 Form ES-401-2 Imp. 2.9 Points 1 WA Category Totals:

0 3.4" Group Point Total:

4 01 1 PWR SRO Examination Outline Facility: Salem Generating Station Printed: 09/01/2006 Plant Systems - Tier 2 / Group 2 Form ES-401-2 I Imp. IPointsl 1 Generic Knowledge and Abilities Outline (Tier 3) Ability to supervise and assume a management Ability to evaluate plant performance and make role during plant transients and upset conditions.

operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

PWR SRO Examination Outline Printed: 09/01/2006 4.3 1 4.4 1 Facilitv:

Salem Generating Station Form ES-401-3 Knowledge of the process for managing Knowledge of limiting conditions for operations troubleshooting activities.

and safety limits. Generic Cateeory - KA I 3.3 1 4.1 1 Conduct of Operations Radiation Control I 2.1.6 2.3.6 Knowledge of the requirements for reviewing 3.1 1 Category Total: 1 and approving release permits.

I Emergency ProceduresLF'lan 2.1.7 2.4.10 Knowledge of facility protection requirements including fire brigade and portable fire fighting equipment usage. ~ ~~~ Equipment Control 3.3 1 2.2.20 t- 2.2.22 I I I I I I 12.4.26 ~ Knowledge of annunciator response procedures.

I 3.1 1 1 ~~ ~~~ Generic Total:

7 1 ES-401 Record of Rejected WAS Form ES-401-4 TierIGroup 111 1 I1 111 1 I1 Randomly Selected WA 008 AK3.04 027 2.4.1 8 062 AA1.04 WE04 EK3.4 Reason for Rejection Oversampling, replaced with randomly selected 029 EK2.06 Oversampling, replaced with randomly selected 054 AK3.03 NIA to Salem, replaced with randomly selected 038 EK3.03 Oversamalina, replaced with randomlv selected E05 EK3.2 N I/1 I WE08 2.4.24 I NIA to Salem. redaced with randomlv selected 024 AKI.02 n 1 /I 211 211 211 055 2.2.30 004 K1.10 005 K4.10 006 2.2.13 N/A to system, replaced with Manually selected 055 EA1.06 systemltier to i ncrease breadth of exam Oversampling, replaced with randomly selected 026 A4.05 Oversampling, replaced with randomly selected 039 A4.01 Oversamalina. realaced with randomlv selected 073 K3.01 I 211 Oversampling, replaced with randomly selected 01 1 K2.02 211 NIA to Salem, replaced with randomly selected 003 2.4.20 211 010 K2.02 Oversamalina, replaced with randomlv selected 061 A2.04 007 A4.10 008 A4.05 211 211 211 211 012 K3.02 01 3 K3.03 059 2.2.34 022 K2.02 Oversampling, replaced with randomly selected 012 A2.07 Oversampling, replaced with randomly selected 062 K3.01 Oversampling, replaced with randomly selected 064 2.2.22 NIA to Salem. realaced with Manuallv selected 022 K4.02. same svstemltier to increase breadth of exam 2/1 211 211 212 NUREG 1021, Revision 9 025 K5.01 064 A2.02 076 A2.02 075 K2.03 NIA to Salem, replaced with randomly selected 007 K1.01 NIA to selected system, replaced with randomly selected 078 K4.01 NIA to selected system, replaced with randomly selected 005 K1 .I2 Oversamolina, realaced with randomlv selected 072 A4.01 I 212 212 2/2 014 A4.03 075 K3.07 068 K6.10 NIA to selected system, replaced with randomly selected 01 1 K2.02 NIA to selected system, Manually replaced with 075 A2.02, same systemltier to increase breadth of exam Similar to System 073 K3.01, Manuallv replaced with 068 A2.02. same system to increase breadth of exam h ES-301 Administrative Topics Outline Form ES-301-1 Facility:

SALEM Date of Examination:

12/11/2006 Examination Level:

0 RO SRO Operating Test Number: INDIA ILT NRC Adm in istrative Topic (See Note) Conduct of Operations Conduct of Operations I Equipment Control Radiation Control Type Code* R,D S,N Describe activity to be performed Review a completed surveillance to calculate the Quadrant Power Tilt Ratio. (2.1.7 SRO-4.4) Enter a Tech Spec Action Statement for an inoperable component and make a Log entry IAW SHOP-108. (WA 004 2.1 .I 2 SRO-4.0) 2.2.1 3 (3.8) - Knowledge of tagging and clearance procedures Evaluate a tagging request.

~ 2.3.2 (2.9) - Knowledge of facility ALARA program QUESTION:

Evaluate an airborne and whole-body exposure scenario and apply station ALARA principles regarding use of a respirator.

2.3.4 (3.1) - Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized QUESTION: Given an exposure history and an emergency situation, determine stay time. Classify Emergency I Non-Emergency Events. (WA 2.4.29 SRO-4.0) NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unlss they are retaking only the administrative topics, when 5 are required.

I Type Codes and Criteria (C)ontrol Room, (S)imulator, or Class(R)oom ES-30 1 Control Room Systemslln-Plant System Outline Form ES-30 I -2 Facility:

SALEM Date of Examination:

12/11/2006 Operating Test No.: "I" ILT NRC Exam Level : ROO SRO-I x SRO-U 0 System I JPM Title a. Perform actions for two stuck out rods post trip IAW EOP-TRIP-2 A,C,D,L,S 1 b. Swap ECCS from Injection Mode to Cold Leg Recric MODE IAW EOP- LOCA-3. C,D,L,P,S, 2 c. Respond to Pressurizer PORV failure failure.

1 i. TCAF Control Room Evacuation-Feed SG's using 21/22 AFW Pump. 1 j. TCAF Control Room Evacuation (Trip Turbine, Open Exciter Field Breaker, Trio SGFP's) I 6 k. Perform an Authorized Waste Gas Release

  • 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 1 (A) (P)revious 2 exams (S)im u I ator (R)CA Criteria for RO I SRO-I I SRO-U 4-6 I 4-6 I 2-3 91 814 lll/l 11111 21 211 3 I 3 I 2 (randomly selected) 1/1/1 Appendix D Scenario Outline Form ES-D-4 Event 1; Facility:

SALEM 1 & 2 Scenario No.: NRC #I Op-Test No.: India Examiners: Opera tors : Initial Conditions:

Turnover:

removed from service.

2B EDG is tagged for repair of governor linkage. All required surveillances are complete.

Weather conditions are normal. Unit 1 and Hope Creek are at 100% power.

Shift orders are to reduce power to 90% at 30% per hour to remove 22 Heater Drain pump from service. 100% Rated Thermal Power Unit at 100% power. 22 Heater Drain Pump has a Mech Seal leak and needs to be ll * (N)ormi Malf. No. PRO01 6A SWO216A SG0078A SG0078A EL01 34 VL0055 OR: A106, GAIOGAFK Event Type* N/R CRS/PO RO I CRS/RO C CRS/PO C CRS/RO M ALL C CRSIRO I CRSIRO Event Description Reduce Power to 90% To Repair Seal Leak on 22 HTR Drain Pump CH 1 Pzr Press fails HI (TS-CRS)

Leak in SW Bay #2 (TS-CRS) Steam Gen Tube Leak on 21 SG (TS-CRS) 21 SGTL progresses to Steam Generator Tube Rupture, with Loss of Off-Site Power (6 bus deenergized) 23SW20 fails to close on SEC BIT Injection Meter Fails to 0 Flow (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D, Page 38 of 39 Appendix D Scenario Outline Form ES-D-1 Facility:

SALEM 1 & 2 Scenario No.: NRC #2 Op-Test No.: India Examiners

Operators:

initial Conditions:

Turnover:

and surveillances are complete and approval to proceed to mode 1 has been given. Orders to the shift is to raise power in preparation for placing turbine on line 4% Rated Thermal Power Unit at 4% power returning from a forced outage due to DEHC problems.

All approvals L Event No. 1 2 3 4 5 6 7 I I Malf. No. REM: MC12D CV0034 VL0245 EL0102 RC0002 RPOI 08 EL01 34 (R)eactivii Event Type* N/R CRS/PO/RO TS CRS CIC CRSlRO C CRSIROIPO M ALL C CRS/RO C CRS/RO/PO (1)nstrumen Event Description Raise power to 18% to place turbine on line ~ Loss of Tripping Capability B Rx Trip Breaker (TS CRS) 23 charging pump trips and Letdown valve fails to close (TS C RS) Failure of 3Station Power Transformer (TS CRS) Small Break LOCA Auto SI fails to actuate Loss of Off-Site Power ECCS restoration (C)omponent, (M)ajor Appendix D. Page 38 of 39 Appendix D Scenario Outline Form ES-D-1 XII (R)eactivity, (Qnstrument, Facility:

SALEM 1 & 2 Scenario No.: NRC #3 Op-Test No.: India I/ (C)omponent, (M)ajor (1 Examiners: Operators:

Malf. No. Initial Conditions:

Turnover:

Solar Magnetic Disturbances have been occurring currently at K-3, river grass loading very heavy at last tide change, high tide in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. 100% Rated Thermal Power BOL Unit at 100% power, 21 AFW pump is tagged for emergent work to inboard bearing, Event Type*

Event 1: RC0014B IIR CRSlRO E k- j/ * (N)orm ~~ ~ RP0069 RP0073 RP0279A RP0279B ~~ C ALL I CRS/PO CC0329 ' C I CRS/RO AFOI 83 AFOI 81 6 I' Event Description Power Red to 80% due to Grid Disturbance(SMD) 22 Loop Thot fails during downpower (TS CRS) ~~ ~~ CCW leak on 21 CCW header (TS CRS) Major Oil Leak at MPT ~~ ~ Main Turbine fails to TripIManual MSLl required Loss of Heat Sink, 23 AFW pp trips 22 AFW pump trips after AFVV throttled, CN pump recovery Appendix D. Page 38 of 39 Appendix D Scenario Outline Form ES-D-1 Event No. 1 2 3 4 5 13 (N)ormal, Event Type* Malf. No. NlOl93 swo222c SW0339E Tu0081 H RD0061 AN01 37 VL0049, 50,51, 52,56,87 EL0134 RP318Q1 EL0273A EL01 46 AF0183 (R)eactivity, (I)nstrument, (C)omponent, (M)ajor I CRSIRO C/I CRSIPO CIFUN CRSIROIPO C CRSIRO C CRSlRO M All C CRS/PO Event Description 2N44 Fails Hi (TS CRS) 23 SW strainer clogs/25 SW pump fails to Auto Start (TS CRS) Turbine Gov Vlv Fails closed Rod Speed Fails to 32 SPM Inadvertent PH B (Loss of CCW to RCPs) Loss of All AC Power Trip of 23 AFW pump Appendix D. Page 38 of 39

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