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

E Si-431 P\YE E;:an!r;atior Outline Form ES-401-?

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F a c u 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).

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 k1from 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. 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

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 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 W A 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.

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 (#Jfor 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.

9. 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 K/AS..thatare linked to 10 CFR 55.43.

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PMR RO Examination Outline Printed: OiK!i2008 Facility: Salem I & 2 ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 1 Form ES-401-2 1 EIAPE # I Name I Safety Function K1 K A Topic Imp.

000007 Reactor Trip - Stabilization - EA 1.09 - CVCS 3.2 Recovery 1 EK1.02 - Use of steam tables 000009 Small Break LOCA / 3 Ix 3.5 0000 1 1 Large Break LOCA / 3 I EA I .07 - Containment isolation system 4.4

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00001 5IOO0017 RCP Malfunctions i 4 AA2.01 - Cause of RCP failure 3 .O 000025 Loss of RHR System 1 4 AA2.05 - Limitations on LPI flow and 3.1

• temperature rates of change 000026 Loss of Component Cooling Water I AA 1.07 - Flow rates to the components 2.9 8 and systems that are serviced by the CCWS; interactions among the components 000027 Pressurizer Pressure Control System Malfunction 3 00003s Steam Gen. Tube Rupture / 3 I AI(2.03 - Controllers and positioners EK3.06 - Actions contained in EOP for 2.6 4.2 RCS water inventory balance, S/G tube runture, and plant shutdown procedures 000054 Loss of Main Feedwater 14 X AKl.02 - Effects of feedwater 3.6

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introduction on dry SIG

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000055 Station Blackout 1 6 2.4.23 - Knowledge of the bases for 3.4 prioritizing emergency procedure implementation during emergency operations.

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000056 Loss of Off-site Power / 6 AA2.82 - Temperatures displayed on 2.6 plant computer CRT monitor 000058 Loss of DC Power ii 6 AK3.02 -Actions contained in EOP for 4.0 loss of dc power 000065 Loss of Instrument Air / 8 I 2.4. I8 - Knowledge of the specific bases for EOPs.

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3.3 000077 Generator Voltage and Electric Grid 2.4.50 - Ability to verify system alarm 4.2 Disturbances / 6 setpoints and operate controls identified in the alarm response manual.

EKl.2 - Normal, abnormal and 3.5 emergency operating procedures associated with LOCA Outside Containment

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E K . 2 - Facilitys heat removal systems, 3.9 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 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 A2 IG 1 KA Topic Imp. Points I /

EK2.2 - Facilitys heat removal systems, 3.9 1 including primary coolant, emergency 14 coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility

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W E 12 - Steam Line Rupture - Excessive EK3.2 - Normal, abnormal and 3.3 1 Heat Transfer / 4 emergency operating procedures associated with Uncontrolled Depressurizaiton of all Steam Generators

-1 I K/A Category Totals: 31 3 1 Group Point Total: 18 05/22/2008 2:53:12 pm 2

PWR RO Examination Outline Printed: 05/2.2008 Facility: Salem 1 & 2 ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 2 Form ES-401-:

EIAPE # / Name I Safety Function KA Topic Imp. Points 000001 Continuous Rod Withdrawal / 1 X AK2.01 - Rod bank step counters 2.9 1 000037 Steam Generator Tube Leak / 3 X AA2.14 - Actions to be taken if S/G 4.0 1 goes solid and water enters steam lines

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00005 1 Loss of Condenser Vacuum I 4 X AK3 .O 1 - Loss of steam dump 2.8* 1 capability upon loss of condenser vacuum 1

000059 Accidental Liquid RadWaste Rel. /

9 I I lxI I I AK3.03 - Iniplementation of E-plan I

3.2*

II 1 000067 Plant Fire On-site / 9 1x1 I I I I AKl.01 - Fire classifications, by type 2.9 1 AKl.01 - Effect of pressure on leak rate I I 000069 Loss of CTMT Integrity / 5 1x1 I I I I 2.6 1 EA2.03 - Availability of turbine bypass 3.8 valves for cooldown E m . 1 - Components, and functions of 3.6 control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features 2 . I . 14 - Knowledge of criteria or 3.1 1 conditions that require plant-wide announcements, such as pump starts, reactor trips, mode changes, etc.

Group Point Total: 9 05/22/2008 253: 19 pm 1

PM'R RQ Examination Outline Printed: 05 '12'3008 Facility: Salem 1 B 2 05/22/2008 2:53:26 pm 1

PMR RO Examination Outline Printed: 05/22,2008 05/22/2008 2:53:26 pm 2

1 SyslEvol # / Name 1K1 Iu2 IK3 0 1 1 Pressurizer Level Control X 2.4.23 - Knowledge of the 3.4 1 bases for prioritizing emergency procedure 37 implementation during emergency operations.

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

PWR RO Examination Outline Printed: 0512212008 Facilitv: Salem 1 f2 2 Form ES-401-3 Conduct of Operations 2.1.17 Ability to make accurate, clear, and concise 3.9 1 verbal reports.

2.1.27 Knowledgt of system purpose and/or function. 3.9 1 $6;.

2.1.40 Knowledge nf refueling administrative requirements.

2.8 68 I I Equipment Control 2.2.23 Ability to track Technical Specification limiting 3.1 1 conditions for operations.

L 2.2.36 Ability to analyze the effect of maintenance 3.1 1 activities, such as degraded power sources, on the status of limiting conditions for operations.

Radiation Control 2.3.4 Knowledge of radiation exposure limits under 3.2 1 normal or emergency conditions.

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

I Emergency ProceduresPlan 2.4.14 Knowledge of general guidelines for EOP usage. 3.8 1 73 2.4.25 Knowledge of fire protection procedures. 3.3 1 Generic Total: 10 0512212008 2:53:39 pm 1

ES-401 PWR Examinatiori Outline Form ES-401-2 Facilitv: Salem 1 8, 2 Printed: 04/15/2008 Date Of Exam: 08/25/2008 RO WA Category Points SRO-Only Points Tier K4 ( ~ I K5 6 A I A2 A 3 ( A 4 G* Total A2 G* Total

1. 0 0 0 0 3 3 6 Imergen cl 0 0 2 2 4

& NIA Abnormal Plant 0 0 5 5 io Evolutions

2. 1 Io1 01 0 Plant Systems Totals

3. Generic Knowledge And Abilities Categories 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 W A 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 +I from that specified in the table 1 3.

based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 poi&

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, sitespecific 1

systemdevolutions that are not included on the outline should be added. Refer to Section D . l .b of E S 9 1 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 /

/Q \

a' in the group before selecting a second topic for any system or evolution.

7.-

5. Absent a plant-specific priority, only those WAS having an importance rating (IR) of 2.5 or higher 6.

shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respective1 .

Select SRO topics for Tiers 1 and 2 from the shaded systems and WA categories. ,/

I jl -3 u

d a

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• The generic (G) WAS in Tiers 1 and 2 shall be selected from Section 2 of the WA Catalog, bdt the i .Q topics must be relevant to the applicable evolution or system. Refer to Section D . l . b of ES-401for Y the applicable WAS. ,

i i

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 syst$m and category. Enter the group and tier totals for each category in the table above; if fuel handhng 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.

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3. For Tier 3, select topics from Section 2 of the WA catalog, and enter the W A numbers, descriptions, IRs, and point totals (#) on Form ES401-3. Limit SRO selections to WAS that are linked to 10 CFR 55.43.

04115/2008 11:07:43 am

.l --**-(*I-*-.*. E -___,_I_ I-IIu

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• PMR SRO Examination Outline Printed 031 5 2006 Facility: Salem 1 & 2 ES - 401 Emergent) arid Abnormal Plant Evolutions - Tier I I Group I Form ES-40 1-2 EIAPE # I Name / Safety Function Kl KA Topic Imp. Points 000007 Reactor Trip - Stabilization - 3.1.37 - Knowledge of procedures, 4.6 1 Recovery / 1 guidelines, or limitations associated with reactivity management.

000022 Loss of Rx Coolant Makeup / 2 AA2.02 - Charging pump problems 3 .I 1 000026 Loss of Component Cooling Water 1 AA2.03 - The cause of possible CCW 3.6 1 8 loss 000027 Pressurizer Pressure Control System AA1.07 - Makeup f l o ~indication

. 3.1 1 Malfunction / 3 000040 Stearn Line Rupture - Excessive 2.1.45 - Ability to identifi and interpret 4.3 1 Heat Transfer 14 diverse indications to validate the In response of another indication.

000056 Loss of Off-site Power / 6 2.2. I4- Knowledge of the process for 4.3 I controlling equipment configuration or 7 status.

WA Category Totals: 0 Group Point Total: 6 04/15/2008 11:07:15 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 I I*

E/APE # I Name I Safety Function Imp. Points K1 II 000033 Loss of Intermediate Range NI / 7 3.5 1 5

I I

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160059 000059 Accidental Liquid RadWaste Rel. I 4.6 9

5 reactor coolant system integrity, containment conditions, radioactivity 000069 Loss of CTMT Integrity / 5 4.4 q

W E 0 2 SI Termination I 3 4.7 CD KIA Category Totals: 0 1 2 1 21 Group Point Total:

0411512008 11:07:20 am 1

PWR SRO Examination Outline Printed: 04/15/2008 Facility: Salem 1 & 2 Plant Systems - Tier 2 / Group 1 Form ES-401-2 ES - 401 I I I I Sys/Evol ## / Name K1 K2 026 Containment Spray 059 Main Feedwater 064 Emergency Diesel Generator 1 073 Process Radiation Monitoring 078 Instrument Air

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WA Category Totals: 0 0 04115/2008 11:07:26 am 1

PWR SRO Examination Outline Printed: 04/15/2008 Facility: Salem 1 &: 2 ES - 401 Plant Systems - Tier 2 / Group 2 Form ES-401-2 I

Sys/Evol # / Name

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Imp.

0 1 1 Pressurizer Level Control 3.7 029 Containment Purge 3.8 I 068 Liquid Radwaste 2.8*

WA Category Totals: 01 XI Group Point Total: 3 04/15/2008 11:07:32 am 1

Generic Knowledge and Abilities Outline (Tier 3)

PWR SRO Examination Outline Printed: 0411512008 Conduct of Operations 2.1.34 Knowledge of primary and secondary plant chemistry limits.

3.5 19 2.1.39 Knowledge of conservative decision making 4.3 1 Lo practices.

Category Total: 2 Equipment Control 2.2.18 Knowledge of the process for managing 3.9 1 maintenance activities during shutdown operations, such as risk assessments, work prioritization, etc.

Radiation Control 2.3.4 Knowledge of radiation exposure limits under 3.7 1 2 2 normal or emergency conditions.

2.3.15 Knowledge of radiation monitoring systems, such 3.1 1 as fixed radiation monitors and alarms, portable z3 survey instruments, personnel monitoring equipment, etc.

Emergency Procedures/Plan 2.4.26 Knowledge of facility protection requirements, 3.6 1 including fire brigade and portable fire fighting equipment usage.

2.4.28 Knowledge of procedures relating to a security 4.1 1 event (non-safeguards information).

04115/2008 11:07:38am 1

TierIG roup Randomly Reason for Rejection Selected KIA RO 111 022 AKI .01 Sampled on CERT Exam RO 112 WE01 2.1.15 NA to WE01 (Rediagnosis)

RO 112 024 AAI .08 Pump speed control is for recirc (slow) and boration (high) and is not related to seal

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nrotection.

RO 112 068 K3.16 Salem does not have fail open control room access doors.

RO 211 007 K3.01 Sampled on CERT Exam RO 211 008 A I .01 Too similar to RO Tier 1 Group 1 KIA for 006 A I .07 RO 211 010 K5.02 Too similar to RO Tier 1 Group 1 KIA FOR 008 AKI .01 on CERT Exam( constant enthalpy throttling characteristics RO 211 025 K1.O1 Salem does not have Ice Condenser RO 211 059 2.4.27 Not specific to Main Feedwater (knowledge of fire in the plant procedure)

RO 211 062 2.2.23 Oversampling of Generic 2.2.23 (Ability to track-TSAS) (also in Tier 3)

RO 211 073 A I .01 Sampled on CERT Exam RO 211 076 K1.I 5 No physical connection or causeleffect relationship between service water and Fire Protection systems RO 212 055 K3.01 Sampled on CERT Exam SRO 112 032 2.1.34 Chemistry limits NA to Loss of SR Nls SRO 211 103 2.3.5 Not SRO level SRO 211 006 A2.11 Over sampling of ECCS system (3 on entire exam)

SRO 212 014 2.4.28 Security event NA to RPI system.

RO 112 001 AK2.01 Manually replaced with same system, AKI .03 to match question developed per NRC direction.

RO 212 059 AK3.02 Manually replaced with same system, AKI .01, to allow a question to be written that is not Level of difficulty 5 as originally submitted.

RO 112 EO9 2.1 .I4 Manually replaced with same system EA1.3 to allow a question to be written.

SRO 212 064 A2.10 Manually replaced with same system, A2.21 to allow for SRO question to be written.

SR03 I 2.3.1 5 Manually replaced with 2.3.13 to allow SRO level question to be selected.

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. WAs removed or changed from exam per NRC direction were manually replaced with WAs approved by the NRC. Manually replaced KIAs are identified as such on this form, all others were randomly replaced.

ES-401, Page 27 of 33

ES-301 Ad ministrat ive To Bics Outline Form ES-301-I Facility: SALEM - Date of Examination: - 0812512008 Examination Level: 0 RO SRO Operating Test Number: 07-01 NRC Administrative Describe activity to be performed Topic (See Note) TY Pe Code*

Calculate Shutdown Margin Conduct of R,M 2.1.25 Ability to obtain and interpret station reference materials such as graphs, Operati ons monographs, and tables which contain performance data. RO 2.8 Conduct of Verify qualifications prior to assuming Licensed Operator Duties.

0perations 2.1.3 Knowledge of Shift turnover practices. RO 3.0

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

Equipment Control NS 2.2.30 Knowledge of RO duties in the Control Room during Fuel Handling operations such as alarms from the fuel handling area, .... RO 3.5 Radiation Control NA 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-301 Ad ministrative Topics OutIine Form ES-301-1 I

Facility: SALEM Date of Examination: 08/25/2008 Examination Level: RO SRO Operating Test Number: 07-01 NRC I Administrative Topic (See Note) 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.)

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

Radiation Control 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 Date of Examination: 08/25/08 Exam Level : RO X S RO-I S RO-U Operating Test No.: 07-01 ILT NRC Exam

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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 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank e9 1 5 0

- 154 (E)mergency or abnormal in-plant > I I

- 21 1 2 1 (EN)gineered safety feature z

- I - I 1 (control room system)

(L)ow-Power I Shutdown >II 2 1 I 21 (N)ew or (M)odified from bank including 1 (A) >? I L 2 1 2 1 (P)revious 2 exams c3 1 53

- 7 5 2 (randomly selected)

(R)CA ->II z 1 1 1 1

ES-301 Control Room Systems/ln-Plant System Outline Form ES-301-2 Facility: SALEM Date of Examination: 08/25/08 Exam Level: RO SRO-1 x SRO-U 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

a. R.espond to Main Turbine Runback with malfunctioning Auto Rod Control S,N,A 1

b. Perform a manual makeup to the VCT SD 2

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

g. Start 21 CCW pump IAW APPX-1 II S,L,D,A 8

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

k. Commence a liquid waste release, and respond to high activity during the release R,MA 9 (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank ~9 1 5 8 1 5 4

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(E)mergency or abnormal in-plant > II

- 21 1 1 1 (EN)gineered safety feature - / - I 2 1 (control room system)

(L)ow-Power I Shutdown >I I 21 I ?I

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(N)ew or (M)odified from bank including 1 (A) >2 / 2 2 / 1 1 (P)revious 2 exams <3 I 53

- 7 5 2 (randomly selected)

(WCA >I/ 2 1 / ? 1

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

1 Initial Conditions: 100% Rated Thermal Power Turnover: Unit at 100% power. 22 AFW pp is C/T. Lower power to 85% at 20% per hour in preparation for removing a Condensate Pump from service.

Event Malf. No. Event Event Type*

Description N/A N,R Power reduction for Condensate Pump emergent maint.

1 CRSIROIPO 1 EDG oil leak (TS)

PZR level channel failure, letdown isolation, letdown r e I

2 2 establish (TS) Note: The RO will provide the PZR level CRSIROIPO channel failure initial response, the PO will restore letdown)

C 3 3 Steam Generator Tube Leak CRS/RO/PO M

Steam Generator Tube Rupture CRSIROIPO C

4 SEC activated equipment fails to start CRS/PO

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C 4 5 SG Atmospheric relief fails partially open CRSIPO

• (N)orm: (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Appendix D, Page 38 of 39

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

Initial Conditions: 1X108Amps for critical data.

Turnover: Raise power to 3-4%.

Event Event Type*

Description R,N CRS/RO I Raise Rx power to 3-4%

1 1 I IR NI fails low (TS)

I 2 1 C D VIB deenergizes causing no Auto or Manual rod control 2

CRS/RO just as Rx is entering POAH (TS) l 3 C PO 1 of 2 operating MDAFW pps trip on Rx trip.

3 1 4 M

CRS/RO I RCS leak progressing to LBLOCA w Auto SI failure.

C Various SEC initiated components malfunction (RHR pp fail CRSIROIPO to start, no auto CS) 4 1 5 b I Loss of Emergency Recirc

+

CRS/RO/PO I I (N)ormal, (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.: _N_KC E S G - 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 /> 1 Turnover: Raise power to 90% @ 3% per hour. (Power ascension ramp limit is 3%/hr)

Event I

Description N,R I CRSIROIPO Raise Rx power MT Steamline Inlet Pressure Transmitter fails high (TS)

CRSIROIPO SGFP oil leak, trip with no auto MT runback CRSIROIPO l 3 I 3 M CRSIROIPO Feedwater rupture on common SGFP discharge header, MSLl failure C

4 SG Code Safety fails open post trip CRSIPO II I 51 I L CRSIROIPO 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.: N R C ESG-4 Op-Test No.: 07-01 NRC Examiners: Operators:

Initial Conditions: 100% power Turnover: Maintain 100% power Event Malf. No. Event Event Type*

Description 1 1 I Power range NI fails high (TS)

CRSIRO B 4KV vital loads in Blackout, power reduction to 100%

2 2 C,R CRSIROIPO required ESO predicted voltage level e493 KV (TS)

R 3 3 ESO directed rapid load reduction.

CRSIROIPO C

4 4 Loss of 23A CW bus (3 circulators)

CRSIPO 5 C, M Loss of 4thcirculator requiring Rx trip CRSIROIPO C

6 6 LOCA outside containment (200 gpm in RHR pp room)

CRSIRO

• (N)orm; (R)eactivity, (1)nstrumen (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-5 (Spare) Op-Test No.: 4 7 - 0 1 NRC Examiners: Operators:

Initial Conditions: 40% power Turnover: 23 charging pump CIT for scheduled maint.

Event Event Type*

Description 1 1 I VCT level transmitter fails CRSIRO 2 2C SEC loss of power (TS)

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2 C 3 Centrifugal charging pump trip (TS)

CRS/RO/PO 3 4 C,R Loss of Main Turbine Lube Oil (Rx trip not required)

CRSIROIPO Steam Rupture (unisolable) outside containment.

4 4 M FRHS with no centrifugal charging pps available (Bleed and C

5 5 Feed required, one PZR PORV won't open, RC head vents CRSIROIPO required.) LOOP. AFP recovery.

(C)omponent, (M)ajor Appendix D,Page 38 of 39