ML082730779

Draft - Operator Licensing Exam Outlines (Folder 2)

ML082730779
Person / Time
Site:	Salem
Issue date:	07/02/2008
From:	Public Service Enterprise Group
To:	Operations Branch I
Hansell S
Shared Package
ML080030005	List: ML081060248 ML082350047 ML082470469 ML082730736 ML082730775 ML082730779 ML082730784 ML082730786 ML082730790 ML082820486 ML082820496 ML082820517 ML082820534 ML082820540 ML082820562 ML082970764 ML082970767
References
50-272/08-301, 50-311/08-301
Download: ML082730779 (24)

Text

P\YE E;:an!r;atior Outline Form ES-401-? E Si-43 1 - Facu Salem i G 2 Printed 05!22/2008 Note: 1. Ensure that at least two topics from every applicable KiA category are sampled within each tier of the RO and SRO-only outlines (;.e., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each WA category shall not be less than two). The point total for each group and tier in the proposed outline must match that specified in the table.

The final point total for each group and tier may deviate by k1 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 Systemdevolutions 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 systemdevolutions that are not included on the outline should be added. Refer to Section D.1 .b of ES-401 for guidance regarding the elimination of inappropriate K/A 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 prtority, 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

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

Refer to Section D.l .b of ES-401 for the applicable WAS. On the following pages, enter the WA numbers a brief description of each topic, the topics' importance ratings (IRs) for the applicable license level. and the point totals

(#J 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 M or 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 K/A catalog. and enter the WA numbers. descriptions, IRs, and point totals (#) on Form ES401-3. 10 CFR 55.43. 2. 3. 4. 5. 8. 9. Limit SRO selections to K/AS..that are linked to I KA Topic EA 1.09 - CVCS EK1.02 - Use of steam tables EA I .07 - Containment isolation system Imp. 3.2 3.5 4.4 1 EIAPE # I Name I Safety Function

~~ 000055 Station Blackout 16 ~ AA2.01 - Cause of RCP failure AA2.05 - Limitations on LPI flow and temperature rates of change AA 1.07 - Flow rates to the components and systems that are serviced by the CCWS; interactions among the components AI(2.03 - Controllers and positioners EK3.06 - Actions contained in EOP for RCS water inventory balance, S/G tube runture, and plant shutdown procedures 3 .O 3.1

• 2.9 2.6 4.2 3.6 - 3.4 000054 Loss of Main Feedwater 14 X - ~~ AA2.82 - Temperatures displayed on plant computer CRT monitor AK3.02 -Actions contained in EOP for loss of dc power bases for EOPs.

2.4. I8 - Knowledge of the specific 2.6 4.0 3.3 Printed: OiK!i2008 PM'R RO Examination Outline Facility:

Salem I & 2 ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 1 Form ES-401-2 K1 000007 Reactor Trip - Stabilization - Recovery 1 Ix 000009 Small Break LOCA

/ 3 0000 1 1 Large Break LOCA / 3 I 00001 5IOO0017 RCP Malfunctions i 4 000025 Loss of RHR System 14 000026 Loss of Component Cooling Water I 8 I 000027 Pressurizer Pressure Control System Malfunction

' 3 00003s Steam Gen. Tube Rupture / 3 AKl.02 - Effects of feedwater introduction on dry SIG 2.4.23 - Knowledge of the bases for prioritizing emergency procedure implementation during emergency operations.

000056 Loss of Off-site Power / 6 000058 Loss of DC Power ii 6 I 000065 Loss of Instrument Air

/ 8 ~ 2.4.50 - Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 4.2 3.5 000077 Generator Voltage and Electric Grid Disturbances

/ 6 EKl.2 - Normal, abnormal and emergency operating procedures associated with LOCA Outside Containment

~~ EK.2 - Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the Dperation of the facility 3.9 05/22/2008 2:53:12 pm 1 Facility:

Sillem 1 & 2 ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 1 Form ES-401-2 E/APE #I Name I Safety Function 14 WE 12 - Steam Line Rupture - Excessive Heat Transfer

/ 4 K/A Category Totals: A2 I G 1 KA Topic I/ EK2.2 - Facility's heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility ~ EK3.2 - Normal, abnormal and emergency operating procedures associated with Uncontrolled Depressurizaiton of all Steam Generators Imp. 3.9 3.3 -1 I 31 31 Group Point Total:

Points 1 1 18 05/22/2008 2:53:12 pm 2 PWR RO Examination Outline KA Topic AK2.01 - Rod bank step counters AA2.14 - Actions to be taken if S/G goes solid and water enters steam lines Printed: 05/2.'2008 Imp. Points 2.9 1 4.0 1 Facility:

Salem 1 & 2 ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 2 Form ES-401-: 000001 Continuous Rod Withdrawal

/ 1 000037 Steam Generator Tube Leak / 3 EIAPE # / Name I Safety Function X X 00005 1 Loss of Condenser Vacuum I 4 X 1 I I lxI I I 000059 Accidental Liquid RadWaste Rel.

/ 9 1x1 I I I I 000067 Plant Fire On-site

/ 9 1x1 I I I I 000069 Loss of CTMT Integrity

/ 5 ~ AK3 .O 1 - Loss of steam dump capability upon loss of condenser vacuum 2.8* 1 AK3.03 - Iniplementation of E-plan I1 3.2* AKl.01 - Fire classifications, by type I 2.9 I 1 AKl.01 - Effect of pressure on leak rate I 2.6 I 1 EA2.03 - Availability of turbine bypass valves for cooldown Em. 1 - Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features 3.8 3.6 2. I. 14 - Knowledge of criteria or conditions that require plant-wide announcements, such as pump starts, reactor trips, mode changes, etc. 3.1 1 Group Point Total: 9 05/22/2008 253: 19 pm 1 Printed: 05 '12'3008 PM'R RQ Examination Outline Facility:

Salem 1 B 2 05/22/2008 2:53:26 pm 1 Printed: 05/22,'2008 PM'R RO Examination Outline 05/22/2008 2:53:26 pm 2 1 SyslEvol # / Name 1K1 Iu2 IK3 X 2.4.23 - Knowledge of the 3.4 1 37 bases for prioritizing emergency procedure implementation during emergency operations.

0 1 1 Pressurizer Level Control 014 Rod Position lndication 01 5 Nuclear Instrumentation 0 16 Non-nuclear Instrumentation I 07 1 Waste Gas Disposal 072 Area Radiation Monitoring 086 Fire Protection WA Category Totals: 1 1 0 I I I I 05/22/2008 2:53:33 pm 1 Facilitv:

Salem 1 f2 2 3.9 Conduct of Operations 2.1.17 Ability to make accurate, clear, and concise verbal reports. PWR RO Examination Outline Printed: 0512212008 1 Form ES-401-3 2.1.27 2.1.40 1 $6;. 68 3.9 Knowledgt of system purpose and/or function.

2.8 Knowledge nf refueling administrative requirements.

2.2.23 2.2.36 Equipment Control 3.1 1 Ability to track Technical Specification limiting conditions for operations.

Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations.

3.1 1 L 3.2 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.

Ability to control radiation releases.

3.8 2.3.1 1 2.3.14 Knowledge of radiation or contamination hazards 3.4 that may arise during normal, abnormal, or emergencq conditions or activities.

Radiation Control 1 1 1 I I Emergency ProceduresPlan 2.4.14 Knowledge of general guidelines for EOP usage. 3.8 3.3 2.4.25 Knowledge of fire protection procedures.

1 1 I 73 Generic Total:

10 0512212 008 2:53:39 pm 1 ES-401 PWR Examinatiori Outline Form ES-401-2 Facilitv:

Salem 1 8, 2 Printed: 04/15/2008 Tier 1. I me rg en cl & Abnormal Plant Evolutions

2. Plant Systems Date Of Exam: 08/25/2008 RO WA Category Points SRO-Only Points 1 Io1 01 0 Totals 3. Generic Knowledge And Abilities Categories G* Total K4 (~5 IK6 AI A2 A3(A4 G* Total A2 00 00 3 3 6 00 2 2 4 NIA 00 5 5 io Note: 1. Ensure that at least two topics from every applicable WA category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each WA category shall not be less than two). The point total for each group and tier in the proposed outline must match that specified 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 poi& do not apply at the facility should be deleted and justified; operationally important, sitespecific systemdevolutions that are not included on the outline should be added. Refer to Section D.l .b of ES91 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.

1 2. 3. Systemdevolutions within each group are identified on the associated outline; systems or evolutions that 1 /Q \ 4. a' 7.- a -3 5. Absent a plant-specific priority, only those WAS having an importance rating (IR) of 2.5 or higher Select SRO topics for Tiers 1 and 2 from the shaded systems and WA categories.

shall be selected.

Use the RO and SRO ratings for the RO and SRO-only portions, respective1 jl . d I u 6. ,/ ii .Q Y 7

• The generic (G)

WAS in Tiers 1 and 2 shall be selected from Section 2 of the WA Catalog, bdt the topics must be relevant to the applicable evolution or system. Refer to Section D.l.b of ES-401 for the applicable WAS. On the following pages, enter the WA numbers, a brief description of each topic, the topics'

\ importance ratings (IRs) for the applicable license level, and the point totals

(#) for each syst$m 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 ES401-3. Limit SRO selections to WAS that are linked to 10 CFR 55.43. , i i 8. and category. Enter the group and tier totals for each category in the table above; if fuel handhng ,-- .-___..#.-

3. 0411 5/2008 1 1 :07:43 am

• " ".l --**-(*I-*-."*.

E -___, _I_ I-IIu ~x-I^_LxI

~~-~ _____^- ~~-wI PM'R SRO Examination Outline Printed 03'1 5 '2006 Facility:

Salem 1 & 2 ES - 401 Emergent) arid Abnormal Plant Evolutions - Tier I I Group I Form ES-40 1-2 KA Topic 3.1.37 - Knowledge of procedures, guidelines, or limitations associated with reactivity management.

AA2.02 - Charging pump problems AA2.03 - The cause of possible CCW AA1.07 - Makeup flo~. indication loss Imp. Points 4.6 1 3 .I 1 3.6 1 3.1 1 000027 Pressurizer Pressure Control System Malfunction

/ 3 EIAPE #I Name / Safety Function 000007 Reactor Trip - Stabilization - Recovery / 1 000022 Loss of Rx Coolant Makeup

/ 2 000026 Loss of Component Cooling Water 1 8 Kl 2.1.45 - Ability to identifi and interpret diverse indications to validate the response of another indication.

2.2. I4 - Knowledge of the process for controlling equipment configuration or status. 4.3 4.3 1 000040 Stearn Line Rupture - Excessive Heat Transfer 14 000056 Loss of Off-site Power / 6 WA Category Totals:

I 0 Group Point Total:

6 In 7 04/15/2008 1 1 :07: 15 am 1 PWR SRO Examination Outline Printed: 04/15/2008 Facility:

Salem 1 & 2 ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 2 Form ES-401-2 E/APE # I Name I Safety Function I K1 I* II 000033 Loss of Intermediate Range NI / 7 160059 Accidental Liquid RadWaste Rel.

I I I ~ ~ 000059 Accidental Liquid RadWaste Rel.

I 9 000069 Loss of CTMT Integrity

/ 5 WE02 SI Termination I 3 KIA Category Totals: reactor coolant system integrity, containment conditions, radioactivity Imp. 3.5 4.6 4.4 4.7 0121 21 Group Point Total:

Points 1 5 5 q CD 0411 512008 11 :07:20 am 1 Facility:

Salem 1 & 2 K1 ES - 401 Sys/Evol ## / Name 026 Containment Spray K2 00 059 Main Feedwater 064 Emergency Diesel Generator 073 Process Radiation Monitoring 078 Instrument Air ~~ WA Category Totals:

Printed: 04/15/2008 PWR SRO Examination Outline Plant Systems - Tier 2 / Group 1 Form ES-401-2 II I I 1 0411 5/2008 11 :07:26 am 1

Printed: 04/15/2008 PWR SRO Examination Outline Facility:

Salem 1 &: 2 ES - 401 I Sys/Evol # / Name 0 1 1 Pressurizer Level Control 029 Containment Purge I 068 Liquid Radwaste WA Category Totals: Plant Systems - Tier 2 / Group 2 Form ES-401-2 Imp. 3.7 3.8 - 2.8* 01 XI Group Point Total:

3 04/15/2008 1 1 :07:32 am 1 Generic Knowledge and Abilities Outline (Tier

3) PWR SRO Examination Outline Printed: 0411 512008 Conduct of Operations 2.1.34 Knowledge of primary and secondary plant 3.5 chemistry limits.

2.1.39 Knowledge of conservative decision making 4.3 1 Category Total: 2 practices.

19 Lo Equipment Control 2.2.18 Radiation Control Knowledge of the process for managing 3.9 1 maintenance activities during shutdown operations, such as risk assessments, work prioritization, etc. Emergency Procedures/Plan 2.3.4 Knowledge of radiation exposure limits under Knowledge of radiation monitoring systems, such normal or emergency conditions.

as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

2.3.15 3.7 1 3.1 1 2.4.26 Knowledge of facility protection requirements, including fire brigade and portable fire fighting equipment usage. event (non-safeguards information).

2.4.28 Knowledge of procedures relating to a security 3.6 1 4.1 1 22 z3 0411 5/2008 11 :07:38 am 1 TierIG rou p RO 111 RO 112 RO 112 Reason for Rejection Randomly Selected KIA 022 AKI .01 WE01 2.1.1 5 024 AAI .08 Sampled on CERT Exam NA to WE01 (Rediagnosis) Pump speed control is for recirc (slow) and boration (high) and is not related to seal nrotection. ~ ~ RO 112 RO 211 007 K3.01 Sampled on CERT Exam RO 211 RO 211 068 K3.16 008 AI .01 010 K5.02 Salem does not have fail open control room access doors. Too similar to RO Tier 1 Group 1 KIA for 006 AI .07 Too similar to RO Tier 1 Group 1 KIA FOR 008 AKI .01 on CERT Exam( constant NOTE: All rejected WAS were deleted from Outline. Replacement WAS were then selected by generating a random exam with the remaining WAS still inserted.

All deleted WAS were replaced with randomly selected WAS by the Exam Generation software. WA's removed or changed from exam per NRC direction were manually replaced with WA's approved by the NRC. Manually replaced KIA's are identified as such on this form, all others were randomly replaced.

ES-401 , Page 27 of 33 RO 211 RO 211 RO 211 RO 211 RO 211 RO 212 SRO 112 SRO 211 SRO 211 SRO 212 RO 112 RO 212 RO 112 SRO 212 SR03 enthalpy throttling characteristics Salem does not have Ice Condenser Not specific to Main Feedwater (knowledge of fire in the plant procedure) Oversampling of Generic 2.2.23 (Ability to track - TSAS) (also in Tier 3) Sampled on CERT Exam No physical connection or causeleffect relationship between service water and Fire Protection systems Sampled on CERT Exam Chemistry limits NA to Loss of SR Nls Over sampling of ECCS system (3 on entire exam) Security event NA to RPI system. Manually replaced with same system, AKI .03 to match question developed per NRC direction. Manually replaced with same system, AKI .01 , to allow a question to be written that is not Level of difficulty 5 as originally submitted. Manually replaced with same system EA1.3 to allow a question to be written. Manually replaced with same system, A2.21 to allow for SRO question to be written. Manually replaced with 2.3.13 to allow SRO level question to be selected.

025 K1.O1 059 2.4.27 062 2.2.23 073 AI .01 076 K1 .I 5 055 K3.01 032 2.1.34 103 2.3.5 Not SRO level 006 A2.11 014 2.4.28 001 AK2.01 059 AK3.02 EO9 2.1 .I 4 064 A2.10 I 2.3.1 5 ES-301 Ad mi n ist ra t ive To Bics Outline Form ES-301 -I Date of Examination: - Facility:

SALEM - Examination Level:

Administrative Topic (See Note) Conduct of Opera ti ons Conduct of 0 pera ti ons Equipment Control Radiation Control 0 RO SRO Operating Test Number: 07-01 NRC TY Pe Code* R,M 0812 512008 NS NA Describe activity to be performed Calculate Shutdown Margin 2.1.25 Ability to obtain and interpret station reference materials such as graphs, monographs, and tables which contain performance data. RO 2.8 Verify qualifications prior to assuming Licensed Operator Duties.

2.1.3 Knowledge of Shift turnover practices. RO 3.0

~ Respond to loss of Source Range Nuclear Instrumentation during refueling operations.

2.2.30 operations such as alarms from the fuel handling area, . . . . Knowledge of RO duties in the Control Room during Fuel Handling RO 3.5 NA Perform the duties of the Secondary Communicator during an Alert 2.4.39 Knowledge of the ROs responsibilities in Emergency Plan implementation.

RO 3.3 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)

ES-30 1 Ad mi n ist rat ive Topics Out I i ne Form ES-301-1 Facility:

SALEM Date of Examination:

08/25/2008 Examination Level:

I RO SRO Operating Test Number:

07-01 NRC Administrative Topic (See Note) I Conduct of Operations Conduct of Operations Equipment Control Equipment Control Radiation Control TY Pe Code* Describe activity to be performed Verify shift operators are qualified to perform specified duties (From list of operators assigned to shift, which of them can take vibration data.)

2.1.5 Ability to locate and use procedures and directives related to shift staffirg and activities. SRO 3.4 Review calculated head vent time in FRCI-3 2.1.20 Ability to perform procedure steps SRO 4.2 Initiate an OTSC to an Implementing Procedure 2.2.6 in the safety analysis report. SRO 3.3 Knowledge of the process for making changes in procedures as described Review a radioactive gaseous waste release form. 2.3.6 Knowledge of the requirements for reviewing and approving release permits.

SRO 3.1 Classify Emergency

/ Non-Emergency Events, and complete the ICMF 2.4.29 Knowledge of the Emergency Plan 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)

ES-301 Control Room SystemsAn-Plant System Outline Form ES-301-2 Facility:

SALEM Exam Level : RO X S RO- I S RO-U Date of Examination:

08/25/08 Operating Test No.:

07-01 ILT NRC Exam ~~ Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U, including 1 ESF) System I JPM Title I Type Code*

I Safety Function

a. Respond to Main Turbine Runback with malfunctioning Auto Rod Control I S,N,A I 1 b. Perform a manual makeup to the VCT SD 2 c. Respond to PZR spray valve failure S,L,D,A 3 d. Swap operating RHR loops with one loop aligned for ECCS injection in MODE 4 SLN 4 (Pro Alternate Source In-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

i. Locally manually isolate seal injection during LOPA D,P 2 j. Locally start 23 AFP and feed SGs during CR evacuation RD,E 4 (sec) k. Commence a liquid waste release, and respond to high activity during the release R,M,A 9 @ All RO and SRO-I control room (and in plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions

in-plant systems and functions may overlap those tested in the control room. *Type Codes

Criteria for RO I SRO-I I SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power I Shutdown (N)ew or (M)odified from bank including 1 (A) (P)revious 2 exams (R)CA 4-6 I 4-6 I 2 e9 150 154 - >I I 21 121 - I - I z 1 (control room system)

>I I21 I 21 c 3 1 5 3 7 5 2 (randomly selected) - >I I z1111 >? I L2121 -

ES-301 Control Room Systems/ln-Plant System Outline Form ES-301-2 a. R.espond to Main Turbine Runback with malfunctioning Auto Rod Control Perform a manual makeup to the VCT b. Facility:

SALEM S,N,A 1 SD 2 Exam Level: RO SRO-1 x SRO-U k. Commence a liquid waste release, and respond to high activity during the release Date of Examination:

08/25/08 R,MA 9 Operating Test No.: 07-01 ILT NRC Exam Control Room Systems@

(8 for RO; 7 for SRO-I; 2 or 3 for SRO-U, including 1 ESF) System I JPM Title

c. Respond to PZR spray valve failure 3 d. Swap operating RHR loops with one loop aligned for ECCS injection in MODE 4 1 SLN e. Perform a CFCU Operability and Service Water Flow Verification 5 f. Failure of 2C 4KV Vital Bus to Transfer to the Altermte Source 6 8 I g. Start 21 CCW pump IAW APPX-1 I S,L,D,A h. NA for SRO-I n-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U) i. Locally manually isolate seal injection during LOPA 2 j. Locally start 23 AFP and feed SGs during CR evacuation i RD,E (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power I Shutdown (N)ew or (M)odified from bank including 1 (A) (P)revious 2 exams (WCA 4-6 I 4-6 I 2-3 ~9 158 154 - - >I I 21 111 - / - I 2 1 (control room system) - >I I 21 I ?I >2 / 22/11 - >I / 21/?1 - < 3 I 5 3 7 5 2 (randomly selected)

Appendix D Scenario Outline Form ES-D-1 Facility: SALEM 1 & 2 Scenario No.: -NRC ESG-1 Op-Test No.: 07-01 NRC 11 Examiners: Operators:

11 Initial Conditions: 100% Rated Thermal Power Turnover:

preparation for removing a Condensate Pump from service. Unit at 100% power. 22 AFW pp is C/T. Lower power to 85% at 20% per hour in Event 1 2 3 4 * (N)orm: Malf. No.

N/A 1 2 3 4 5 Event Type* N,R CRSIROIPO I CRSIROIPO C CRS/RO/PO M CRSIROIPO C CRS/PO C CRSIPO Event Description Power reduction for Condensate Pump emergent maint.

EDG oil leak (TS)

PZR level channel failure, letdown isolation, letdown re establish (TS)

Note: The RO will provide the PZR level channel failure initial response, the PO will restore letdown) Steam Generator Tube Leak Steam Generator Tube Rupture SEC activated equipment fails to start ~~~ SG Atmospheric relief fails partially open (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D, Page 38 of 39 Aooendix D Scenario Outline Form ES-D-1 I (N)ormal, (R)eactivity, Facility: SALEM 1 & 2 Scenario No.: _NRC ESG-2 Op-Test No.: 07-01 NRC I (I)nstrument, (C)omponent, (M)ajor Examiners: Operators:

1 Initial Conditions:

1X108 Amps for critical data. 1 Turnover: Raise power to 3-4%. C CRS/RO D VIB deenergizes causing no Auto or Manual rod control just as Rx is entering POAH (TS) 2 21 C CRSIROIPO l3 Various SEC initiated components malfunction (RHR pp fail to start, no auto CS) 4 31 5 41 + Event Type* Raise Rx power to 3-4% R, N CRS/RO I Event Description I I IR NI fails low (TS) 1 of 2 operating MDAFW pps trip on Rx trip. C PO RCS leak progressing to LBLOCA w Auto SI failure. M CRS/RO I Loss of Emergency Recirc b CRS/RO/PO I Appendix D, Page 38 of 39 Appendix D Scenario Outline Form ES-D-1 M CRSIROIPO l3 3 Facility:

SALEM 1 & 2 Scenario No.:

_N_KC ESG-3 Op-Test No.:

07-01 NRC Examiners: Operators:

Initial Conditions:

80% power for last 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Turnover:

Raise power to 90% @ 3% per hour. (Power ascension ramp limit is 3%/hr) 11 I N,R I CRSIROIPO CRSIROIPO CRSIROIPO I C CRSIPO 4 II I L 51 I CRSIROIPO Event Description Raise Rx power MT Steamline Inlet Pressure Transmitter fails high (TS)

SGFP oil leak, trip with no auto MT runback Feedwater rupture on common SGFP discharge header, MSLl failure SG Code Safety fails open post trip Single 4KV Group bus fails to transfer (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 ESG-4 Op-Test No.: 07-01 NRC Examiners: Operators:

Malf. No. 1 2 3 Initial Conditions: 100% power Turnover: Maintain 100%

power Event 1 2 3 4 6 * (N)orm; 4 5 6 Event Type*

I CRSIRO C,R CRSIROIPO R CRSIROIPO C CRSIPO C, M CRSIROIPO C CRSIRO (R)eactivity, (1)nstrumen Event Description Power range NI fails high (TS)

B 4KV vital loads in Blackout, power reduction to required ESO predicted voltage level e493 KV (TS) ESO directed rapid load reduction.

100% Loss of 23A CW bus (3 circulators)

Loss of 4th circulator requiring Rx trip LOCA outside containment (200 gpm in RHR pp room) (C)omponent, (M)ajor Appendix D, Page 38 of 39 Appendix D Scenario Outline Form ES-D-1 1 2 3 4 5 Facility:

SALEM 1 & 2 Scenario No.: NRC ESG-5 (Spare) Op-Test No.: 47-01 NRC 1 2 3 4 4 5 Examiners:

Operators:

Initial Conditions:

40% power Turnover:

23 charging pump CIT for scheduled maint. Event Type*

I CRSIRO C CRS/RO/PO C,R CRSIROIPO M C CRSIROIPO Event Description VCT level transmitter fails 2C SEC loss of power (TS) ~ ~ ~~~ ~ Centrifugal charging pump trip (TS) Loss of Main Turbine Lube Oil (Rx trip not required)

Steam Rupture (unisolable) outside containment.

FRHS with no centrifugal charging pps available (Bleed and Feed required, one PZR PORV won't open, RC head vents required.) LOOP. AFP recovery. (C)omponent, (M)ajor Appendix D, Page 38 of 39