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
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. DAntonio Chief Examiner Division of Reactor Safety US Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA. 19406-1415

Dear Mr. DAntonio,

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 11,2006. 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. Please note that when the latest version of the Random Exam Generation software was uploaded into our system, the previosly NRC approved suppressed WAs were un-suppressed, therefore ALL WAs 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 WAs rejected due to over sampling.

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. 19406-1415

Dear Mr. DAntonio,

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 11,2006. 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-301 Ad ministrative Topics Outline Form ES-301-1 Facility: SALEM Date of Examination: 1211I12006 Examination Level: 0 RO SRO Operating Test Number: INDIA ILT NRC Ad ministrative Describe activity to be performed Topic (See Note) Type Code*

Conduct of Review a completed surveillance to calculate the Quadrant Power Tilt Ratio.

R,M (WA 2.1.7 SRO-4.4)

Operations Conduct of Review a completed Shutdown Margin calculation.

Operations (K/A 2.1.25 SRO 3.1)

(WA 2.2.13SR0 3.8) - Knowledge of tagging and clearance procedures Equipment Control Evaluate a tagging request.

Determine Radiological Conditions For Personnel Exposure Using a Room Survey Map.

Radiation Control 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.

Emergency Plan (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.

T y p e 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 Facility: SALEM I& 2 Scenario No.: NRC #2 Op-Test No.: India Examiners: Operators:

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

, Event Malf. No. Event Type* Event

' No. Description i

- - - I -

N/R Raise power to 18% to place turbine on line 1 CRSIPOIRO REM:

MC12D Loss of Tripping Capability B Rx Trip Breaker (TS CRS)

CRS 3

1 CV0034 VL0245 I CIC CRSIRO 23 charging pump trips and Letdown valve fails to close (TS CRS) 1 I C CRS/RO/PO Failure of 3 Station Power Transformer (TS CRS) 1 RC0002 I M ALL Small Break LOCA 6

1 RP0'08 1 C CRSIRO 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 #3 Op-Test No.: India Examiners: Operators:

initial Conditions: 100% Rated Thermal Power BOL Turnover: Unit at 100% power, 21 AFW pump is tagged for emergent work to inboard bearing, 1-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 />.

Event Malf. No. Event Type* Event No. Description N/R EL12A Power Red to 80% due to Grid Disturbance(SMD) 1 CRS/PO/RO 2 I/R RCOOI4B 22 Loop Thot fails during downpower (TS CRS)

CRS/RO

~

3 C CCW leak on 21 CCW header (TS CRS)

CC0329 CRS/PO 4 C AN0529 Major Oil Leak at MPT CRS/RO 5 RP0069 C RP0073 ALL RP0279A Main Turbine fails to TriplManual MSLl required RP0279B 6 C AFOl81B CRS/PO 22 AFW pump trips after AFW throttled 7 AFOI 83 M/C 23 AFW pp trips, Loss of Heat Sink, CN pump recovery All

  • (N)orm , (R)eactivii (1)nstrumeni (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. 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).
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 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.
3. 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.

4 . 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.

5. 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.
6. Select SRO topics for Tiers 1 and 2 from the shaded systems and WA categories.

7.* The generic (G) WAS in Tiers 1 and 2 shall be selected from Section 2 of the WA Catalog, but the topics must be relevant to the applicable evolution or system.

8. 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.
3. 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 Printed: 09/01/2006 Facility: Salem Generating Station ES 401 -

Emergency and Abnormal Plant Evolutions Tier 1 / Group 1 Form ES-401-2 I ElAPE # / Name / Safety Function I K1 lK2 I K3 ( A A21 G I KATopic (Imp. 1 Point I Recovery 6 0 0 0 G e a c t o r Trip - Stabilization -

/1 1x1 I I EKl.03 - Reasons for closing the main turbine governor valve and the main 3.7 1 turbine stop valve after a reactor trip I1 r

~~

- Change in leak rate with I3 000008 Pressurizer Vapor Space Accident /

000009 Small Break LOCA I 3 X

X I I 1-change in pressure 1 z 1 . 0 2 - Use of steam tables

~~

3-1 1 3.5 I6 0 0 11 Large Break LOCA I 3 ~~

I 1x1 I I lEK2.02 - Pumps 1 2.6* 1 1 1 000015/000017RCP Malfunctions1 4 I 1 1 IX I (AAl.11 - RCP o d o f fand run indicators I 2.5 I 1 000022 Loss of Rx Coolant Makeup / 2 X 2.4.21 - Knowledge of the parameters 3.7 1 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.

000027 Pressurizer Pressure Control System Malfunction 13 I X 2.4.18 - Knowledge of the specific bases for EOPs. I I2.7 1 000029 ATWS / 1 000038 Steam Gen. Tube Rupture / 3 X EK2.06 - Breakers, relays, and disconnects EK3.03 Automatic actions associated 2.9*

3.6*

I 1 X

with high radioactivity in SIG sample lines 000040 Steam Line Rupture - Excessive Heat Transfer 1 4 AA2.02 - Conditions requiring a reactor hP I I '

4-6 000054 Loss of Main Feedwater / 4 l x AK3.03 - Manual control of AFW flow I I 1 1:;: 1 ;

control valves 3.8 000055 Station Blackout 1 6 I

X I EAI.06 - Restoration of power with one IED/G 000056 Loss of Off-site Power I 6 g 2 0 2 - ESF load sequencer status 000058 Loss of DC Power / 6 X AK3.01- Use of dc control power by ED/Gs WE04 LOCA Outside Containment / 3 X EA2.2 - Adherence to appropriate 3.6 procedures and operation within the limitations in the facility's license and amendments WE05 Inadequate Heat Transfer - Loss of X EAI. 1 - Components, and functions of 4.1 Secondary Heat Sink 1 4 control and safety systems, including insmentation, signals, interlocks, failure modes, and automatic and manual features W E 1 1 Loss of Emergency Coolant Recirc. / X EK2.1 - Components, and h c t i o n s of 3.6 1 4 control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features

PWR RO Examination Outline Printed: 09/01/2006 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G KATopic Imp. Points WE12 - Steam Line Rupture - Excessive X EAl.2 - Operating behavior 3.6 1 Heat Transfer / 4 characteristics of the facility WACategoryTotals: 3 3 3 4 3 2 Group Point Total: 18 2

PWR RO Examination Outline Printed: 09/01/2006 Facility: Salem Generating Station ES 401 -

Emergency and Abnormal Plant Evolutions Tier 1 I Group 2 Form ES-401-2 EIAPE # I Name I Safety Function K1 K2 K3 ]A1 A2 G KATopic Imp. Point!

000024 Emergency Boration / 1 X I I I I AK1.02 - Relationship between boron addition and reactor power I1 *13.6 I 000032 Loss of Source Range NI 1 7 17- IAA1.01 - Manual restoration of power

~~ ~~

3.1

~~~~

1 000033 Loss of Intermediate Range NI I 7 I IX I lAA2.01 Equivalency between

~ I 3.0 I 1 source-range, intermediate-range, and power-range channel readings 000069 Loss of CTMT Integrity I 5 AA1.01 - Isolation valves, dampers, 3.5 1 I I 1 1and electropneumatic devices I I I 000076 High Reactor Coolant Activity / 9 I I X I I I IAK2.01 -Process radiationmonitors 1 2.6 I 1 WE03 LOCA Cooldown - Depress. / 4 X EK1.l - Components, capacity, and 3.4 ' I fbnction of emergency systems W/E06 Inad. Core Cooling / 4 X EK2.1 - Components, and functions of 3.6 1 control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features WE07 Inad. Core Cooling I 4 X EK3.3 - Manipulation of controls 3.8 1 required to obtain desired operating results during abnormal, and emergency situations W/E13 Steam Generator Over-pressure 1 4 X EA2.2 - Adherence to appropriate 3.0 1 procedures and operation within the limitations in the facility's license and KIA Category Totals: 2 2 1 2 2 0 amendments Group Poh : Total:

1

PWR RO Examination Outline Printed: 09/01/2006 Facility: Salem Generating Station 1

PWR RO Examination Outline Printed: 09/01/2006 Facility: Salem Generating Station P1;ant ystems - Tier ! / G:I roup 1 ES 401 - - - Form ES-401-2 Sys/Evol # / Name K3 K4 A2 releases 076 Service Water A3.02 - Emergency heat loads I1 I 078 Instrument Air X

- transfers of control 103 Containment X 2.2.28 - Knowledge of new 3~andspenthelmovement procedures.

I I2.6 1 28 KIA Category Totals: 3 3 3 Group Point Total:

2

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

Generic Knowledge and Abilities Outline (Tier 3)

PWR RO ExaminationOutline Printed: 09/01/2006 Facilitv: Salem Generating Station Form ES-401-3 Generic Cateporv KA

_ I KA Topic ImD. Points Conduct of Operations 2.1.1 Knowledge of conduct of operations 3.7 1 requirements.

2.1.1 1 Knowledge of less than one hour technical 3.O 1 specification action statements for systems.

Category Total: 2 Equipment Control 2.2.4 (multi-unit) Ability to explain the variations in 2.8 1 control board layouts, systems, instrumentation and procedural actions between units at a facility.

2.2.26 Knowledge of refueling administrative 2.5 1 requirements.

~

Radiation Control 2.3.4 Knowledge of radiation exposure limits and 2.5 1 contamination control, including permissible levels in excess of those authorized.

2.3.10 Ability to perform procedures to reduce 2.9 1 excessive levels of radiation and guard against personnel exposure.

2.3.1 1 Ability to control radiation releases. 2.7 1 I Category Total: 3 1 Emergency ProceduresD'lan 2.4.27 Knowledge of fne in the plant procedure. 3.O 1 2.4.46 Ability to verify that the alarms are consistent 3.5 1 with the plant conditions.

2.4.48 Ability to interpret control room indications to 3.5 1 verify the status and operation of system, and understand how operator actions and directives affect plant and system conditions.

Generic Total: 10 1

ES-401 PWR Examination Outline Form ES-401-2 Facility: Salem Generating Station Printed: 09/01/2006 Date Of Exam: 12111/2020 RO K/A Category Points Tier I Group K1 K2 K3 K4 IK5 K6 A I A2 A31 A4 G* Total A2 G* Total

1. 1 0 0 0 0 0 0 0 5 2 7 mergenq 0 0 5 0 5

& 0 0 0 N/A N/A ibnormal Tier Plant Totals 0 0 0 0 0 0 0 10 2 12 iolutions 1 0 0 0 0 0 0 0 0 0 0 0 0 3 1 4 2.

2 0 0 0 0 0 0 0 0 0 0 0 0 0 2 0 2 Plant Systems Tier 0 0 0 0 0 0 0 0 0 0 0 0 5 1 6 Totals 1 2 3 4 1 2 3 4

3. Generic Knowledge And 7 0

Abilities Categories 0 0 0 0 2 2 1 2 Note:

1. 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).
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 *Ifrom 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.
3. 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.
4. 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.
5. 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.
6. Select SRO topics for Tiers 1 and 2 from the shaded systems and WAcategones.

7.* 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.

8. 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.
3. 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 Printed: 09/01/2006 Facility: Salem Generating Station

  • malPla olutions - Tier 1 I Group 1 Form ES-401-:

E / M E # I Name / Safety Function K1 K2 K3 A1 A2 ~ KATopic Imp. Points

- ~~

000011 Large Break LOCA / 3 X EA2.08 - Conditions necessary for 3.9* 1 recovery when accident reaches stable phase 000022 Loss of Rx Coolant Makeup 1 2 I I I X AA2.02 - Charging pump problems 3.7 1 000025 Loss of RHR System / 4 2.4.16 - Knowledge of EOP 4.0 1 implementation hierarchy and coordination with other support 1 procedures.

000038 Steam Gen. Tube Rupture I 3

' 2.3.4 - Knowledge of radiation 3.1 1 exposure limits and contamination I control, including permissible levels in excess of those authorized.

AA2.04 - Conditions requiring ESFAS 000040 Steam Line Rupture - Excessive Heat Transfer / 4 000056 Loss of Off-site Power / 6 I I I X X

initiation

~4A2.01- PORV controller indicator 4.7 3.4 1

1 1 and setpoint WE05 Inadequate Heat Transfer - Loss of X EA2.2 - Adherence to appropriate Secondary Heat Sink / 4 procedures and operation within the limitations in the facility's license and WACategory Totals: 0 0 0 0 5 Group Point Total: 7 1

PWR SRO Examination Outline Printed: 09/01/2006 Facility: Salem Generating Station ES - 401 E/APE ## I Name I Safety Function K1 K2 K3 A1 A2 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 G KATopic I

Form ES-401-2 Imp.

I Points 000024 Emergency Boration / 1 X AA2.05 - Amount ofboron to add to 3.9 1 achieve required SDM WE07 had. Core Cooling / 4 X EA2.2 - Adherence to appropriate 3.9 1 procedures and operation within the limitations in the facility's license and amendments WE08 RCS Overcooling - PTS 14 X EA2.1 - Facility conditions and 4.2 1 selection of appropriate procedures during abnormal and emergency overations WE09 Natural Circ. / 4 X E M . 1 - Facility conditions and 3.8 1 selection of appropriate procedures during abnormal and emergency ouerations W E 16 High Containment Radiation / 9 X EA2.2 - Adherence to appropriate 3.3 1 procedures and operation withm the limitations in the facility's license and amendments IUACategory Totals: 0 0 0 0 5 0 Group Point Total: 5 1

PWR SRO Examination Outline Printed: 0910112006 Facility: Salem Generating Station Plant Systems Tier 2 / Group 1 Form ES-401-2 Sys/Evol # / Name K1 41 A2 A3 G KATopic Imp. Points

~

005 Residual Heat Removal X A2.04 - RHR valve 2.9 1 malfunction 008 Component Cooling Water X A2.05 - Effect of loss of instrument and control air on the position of the CCW valves that are air operated 012 Reactor Protection X 2.2.26 - Knowledge of refbeling administrative requirements.

I 059 Main Feedwater I X A2.12 - Failure of feedwater 3.4" regulating valves WA Category Totals: 0 0 3 0 0 1 Group Point Total: 4 1

PWR SRO Examination Outline Printed: 09/01/2006 Facility: Salem Generating Station Plant Systems Tier 2 / Group 2 Form ES-401-2 I Imp. IPointsl 1

Generic Knowledge and Abilities Outline (Tier 3)

PWR SRO Examination Outline Printed: 09/01/2006 Facilitv: Salem Generating Station Form ES-401-3 Generic Cateeory -

KA Conduct of Operations I I

2.1.6 Ability to supervise and assume a management role during plant transients and upset conditions.

4.3 1 I

2.1.7 Ability to evaluate plant performance and make 4.4 1 operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

I

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Equipment Control Radiation Control t-I 2.2.20 2.2.22 2.3.6 I

Knowledge of the process for managing troubleshooting activities.

Knowledge of limiting conditions for operations and safety limits.

Knowledge of the requirements for reviewing I

3.3 4.1 3.1 I

1 1

1 I

and approving release permits.

Category Total: 1 Emergency ProceduresLF'lan 2.4.10

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Knowledge of annunciator response procedures. I 3.1 1 1 12.4.26 Knowledge of facility protection requirements including fire brigade and portable fire fighting 3.3 1 equipment usage.

~~ ~~~

Generic Total: 7 1

ES-401 Record of Rejected WAS Form ES-401-4 TierIGroup Randomly Selected WA Reason for Rejection 111 008 AK3.04 Oversampling, replaced with randomly selected 029 EK2.06 1I1 027 2.4.1 8 Oversampling, replaced with randomly selected 054 AK3.03 111 062 AA1.04 NIA to Salem, replaced with randomly selected 038 EK3.03 1I1 WE04 EK3.4 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 055 2.2.30 N/A to system, replaced with Manually selected 055 EA1.06 systemltier to i ncrease breadth of exam 211 004 K1.10 Oversampling, replaced with randomly selected 026 A4.05 211 005 K4.10 Oversampling, replaced with randomly selected 039 A4.01 211 006 2.2.13 Oversamalina. realaced with randomlv selected 073 K3.01 I

211 007 A4.10 Oversampling, replaced with randomly selected 011 K2.02 211 008 A4.05 NIA to Salem, replaced with randomly selected 003 2.4.20 211 010 K2.02 Oversamalina, replaced with randomlv selected 061 A2.04 211 012 K3.02 Oversampling, replaced with randomly selected 012 A2.07 211 013 K3.03 Oversampling, replaced with randomly selected 062 K3.01 211 059 2.2.34 Oversampling, replaced with randomly selected 064 2.2.22 211 022 K2.02 NIA to Salem. realaced with Manuallv selected 022 K4.02. same svstemltier to increase breadth of exam 2/1 025 K5.01 NIA to Salem, replaced with randomly selected 007 K1.01 211 064 A2.02 NIA to selected system, replaced with randomly selected 078 K4.01 211 076 A2.02 NIA to selected system, replaced with randomly selected 005 K1. I 2 212 075 K2.03 Oversamolina, realaced with randomlv selected 072 A4.01 I

212 014 A4.03 NIA to selected system, replaced with randomly selected 011 K2.02 212 075 K3.07 NIA to selected system, Manually replaced with 075 A2.02, same systemltier to increase breadth of exam 2/2 068 K6.10 Similar to System 073 K3.01, Manuallv replaced with 068 A2.02. same system to increase breadth of exam h

NUREG 1021, Revision 9

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 inistrative Describe activity to be performed Topic (See Note) Type Code*

Conduct of Review a completed surveillance to calculate the Quadrant Power Tilt Ratio.

Operations (2.1.7 SRO-4.4)

Conduct of Enter a Tech Spec Action Statement for an inoperable component and make a Log Operations entry IAW SHOP-108. (WA 004 2.1 .I 2 SRO-4.0)

I Equipment Control 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.

Radiation Control R,D 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.

S,N Classify Emergency I Non-Emergency Events. (WA 2.4.29 SRO-4.0)

I 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.

T y p e Codes and Criteria (C)ontrol Room, (S)imulator, or Class(R)oom

ES-30 1 Control Room Systemslln-Plant System Outline Form ES-30I-2 Facility: SALEM Date of Examination: 12/11/2006 Exam Level : R O O SRO-I x SRO-U 0 Operating Test No.: I ILT NRC 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 SGs using 21/22 AFW Pump.

1 j. TCAF Control Room Evacuation (Trip Turbine, Open Exciter Field Breaker, Trio SGFPs) I 6

k. Perform an Authorized Waste Gas Release
  • Type Codes: Criteria for RO I SRO-I I SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank 9 1 8 1 4 (E)mergency or abnormal in-plant l l l / l (L)ow-Power I Shutdown 1 1 1 1 1 (N)ew or (M)odified from bank including 1 (A) 2 1 2 1 1 (P)revious 2 exams 3 I 3 I 2 (randomly selected)

(R)CA 1 / 1 / 1 (S)imuIator

Appendix D Scenario Outline Form ES-D-4 Facility: SALEM 1 & 2 Scenario No.: NRC #I Op-Test No.: India Examiners: Operators :

Initial Conditions: 100% Rated Thermal Power Turnover: Unit at 100% power. 22 Heater Drain Pump has a Mech Seal leak and needs to be 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 1;

are to reduce power to 90% at 30% per hour to remove 22 Heater Drain pump from service.

Event Malf. No. Event Type* Event Description N/R CRS/PO Reduce Power to 90% To Repair Seal Leak on 22 HTR RO Drain Pump PRO016A I CH 1 Pzr Press fails HI (TS-CRS)

CRS/RO C

SWO216A CRS/PO Leak in SW Bay #2 (TS-CRS)

C SG0078A CRS/RO Steam Gen Tube Leak on 21 SG (TS-CRS) l SG0078A EL0134 M

ALL 21 SGTL progresses to Steam Generator Tube Rupture, with Loss of Off-Site Power (6bus deenergized)

VL0055 C 23SW20 fails to close on SEC CRSIRO OR: A106, I BIT Injection Meter Fails to 0 Flow GAIOGAFK CRSIRO

  • (N)ormi (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: 4% Rated Thermal Power Turnover: Unit at 4% power returning from a forced outage due to DEHC problems. All approvals and surveillances are complete and approval to proceed to mode 1 has been given. Orders to the shift is to raise power in preparationfor placing turbine on line L

Event Malf. No. Event Type* Event No. Description N/R 1 Raise power to 18% to place turbine on line CRS/PO/RO

~

REM:

2 MC12D TS Loss of Tripping Capability B Rx Trip Breaker (TS CRS)

CRS 3 CV0034 CIC 23 charging pump trips and Letdown valve fails to close (TS VL0245 CRSlRO CRS) 4 EL0102 C

Failure of 3Station Power Transformer (TS CRS)

CRSIROIPO 5 M RC0002 Small Break LOCA ALL 6 C RPOI08 Auto SI fails to actuate CRS/RO 7 EL01 34 C Loss of Off-Site Power ECCS restoration I CRS/RO/PO I

(R)eactivii (1)nstrumen (C)omponent, (M)ajor Appendix D.Page 38 of 39

Appendix D Scenario Outline Form ES-D-1 (I1/

Facility: SALEM 1 & 2 Scenario No.: NRC #3 Op-Test No.: India Examiners: Operators:

Initial Conditions: 100% Rated Thermal Power BOL Turnover: Unit at 100% power, 21 AFW pump is tagged for emergent work to inboard bearing, 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 />.

1: Event I

Malf. No. Event Type* Event Description Power Red to 80% due to Grid Disturbance(SMD) k-'

RC0014B IIR 22 Loop Thot fails during downpower (TS CRS)

CRSlRO

~~ ~~

CC0329 CCW leak on 21 CCW header (TS CRS)

CRS/PO

~~ ~

I CRS/RO

~~

C Major Oil Leak at MPT

~~ ~

RP0069 C RP0073 ALL Main Turbine fails to TripIManual MSLl required RP0279A RP0279B EXII AFOI 83 Loss of Heat Sink, 23 AFW pp trips 22 AFW pump trips after AFOI 816 AFVV throttled, CN pump recovery I'

j

  • (N)orm/ (R)eactivity, (Qnstrument, (C)omponent, (M)ajor Appendix D.Page 38 of 39

Appendix D Scenario Outline Form ES-D-1 Event Malf. No. Event Type* Event No. Description NlOl93 I

1 2N44 Fails Hi (TS CRS)

CRSIRO 2 swo222c C/I 23 SW strainer clogs/25 SW pump fails to Auto Start (TS SW0339E CRSIPO CRS) 3 CIFUN Turbine Gov Vlv Fails closed Tu0081H CRSIROIPO 4 RD0061 C Rod Speed Fails to 32 SPM CRSIRO 5 AN0137 C VL0049, CRSlRO 50,51, Inadvertent PH B (Loss of CCW to RCPs) 52,56,87 13 EL0134 M RP318Q1 All Loss of All AC Power EL0273A EL0146 AF0183 C Trip of 23 AFW pump CRS/PO (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D. Page 38 of 39

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