ML041620424

Draft Outlines

ML041620424
Person / Time
Site:	Salem
Issue date:	06/02/2004
From:	Conicella N Public Service Enterprise Group
To:	Conte R NRC/RGN-I/DRS/OSB
Conte R
References
50-272/04-301, 50-311/04-301
Download: ML041620424 (21)

Text

ES-401 PWR Examination Outline Form ES-401-2 Facility: Salem 1 & 2 Printed: 0 1/07/2004 Date Of Exam: 06/11/2004 RO WA Category Points I SRO-Only Points Note:

1. Ensure that at least two topics from every WA category are sampled within each tier of the RO outline (i.e., the 'Tier Totals" in each WA category shall not be less than two). Refer to Section D.1.c for additional guidance regarding the SRO sampling.

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 +1 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. Select topics from many systems and evolutions; avoid selecting more than two WA topics from a given system unless they relate to plant-specific priorities.

4. Systems/evolutions within each group are identified on the associated outline.

5. The shaded areas are not applicable to the category /tier.

6.* 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. The SRO WAS must also be linked to 10 CFR 55.43 or an SRO-level learning objective.

7. On the following pages, enter the WA numbers, a brief description of each topic, the topics' importance ratings (IR)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 columns labeled "K' and "A".

Use duplicate pages for RO and SRO+nly exams.

8. For Tier 3, enter the WA numbers, descriptions, importance ratings, and point totals on Form ES-401-3.

9. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate WA statements.

1

PWR SRO Examination Outline Printed: 01/07/2004 Facility: Salem 1 & 2 ES 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2 E/APE # / Name I Safety Function KA Topic Imp. Points 000015/000017 RCP Malfunctions / 4 2.4.6 - Knowledge symptom based EOP 4.0 mitigation strategies.

000054 Loss of Main Feedwater / 4 AA2.01 - Occurrence of reactor andlor 4.4 turbine trip 000057 Loss of Vital AC Inst. Bus / 6 2.2.25 - Knowledge of bases in 3.7 1 technical specifications for limiting conditions for operations and safety limits.

000058 Loss of DC Power / 6 AA2.02 - 125V dc bus voltage, 3.6 1 low/critical low, alarm 000065 Loss of Instrument Air / 8 AA2.08 - Failure modes of air-operated 3.3 equipment W/E04 LOCA Outside Containment / 3 2.4.49 - Ability to perform without 4.0 reference to procedures those actions that require immediate operation of system components and controls.

W/E05 Inadequate Heat Transfer - Loss of St EA2.2 - Adherence to appropriate 4.3 procedures and operation within the limitations in the facility's license and amendments K/A Category Totals: 0 Group Poin Total:

1

PWR SRO Examination Outline Printed: 01/07/2004 Facility: Salem 1 & 2 ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 2 Form ES-401-2 I I EIAPE ## I Name I Safety Function K1 K2 K3 A1 KA Topic Imp. Point5 000003 Dropped Control Rod / 1 2.4.4 - Ability to recognize abnormal 4.3 1 indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

000024 Emergency Boration / 1 AA2.01 - Whether boron flow andor 4.1 1 MOVs are malfunctioning, from plant conditions W/E07 Inad. Core Cooling 1 4 EA2.1 - Facility conditions and 4.0 1 selection of appropriate procedures during abnormal and emergency operations W/E 14 Loss of CTMT Integrity / 5 EA2.2 - Adherence to appropriate 3.8 1 I

procedures and operation within the limitations in the facility's license and amendments W/E16 High Containment Radiation / 9 2.4.4 - Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

I Total: 5 K/A Category Totals: 0 0 0 0 Group Poin 1

Sys/Evol # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KATopic Imp. Points 005 Residual Heat Removal X A2.04 - RHR valve 2.9 1 malfunction 022 Containment Cooling X 2.1.14 - Knowledge of 3.3 1 system status criteria which require the notification of plant personnel.

06 1 AuxiliaryIEmergency Feedwate X A2.06 - Back leakage of 3.0 1 MFW 064 Emergency Diesel Generator X 2.2.25 - Knowledge of bases 3.7 1 in technical specifications for limiting conditions for operations and safety limits.

WACategoryTotals: 0 0 0 0 0 0 0 2 0 0 2 roup Point Total: 4 1

PWR SRO Examination Outline Printed: 01/07/2004 Facility: Salem 1 & 2 ES - 401 -

Plant Systems Tier 2 / Group 2 Form ES-401-2 1

Generic Knowledge and Abilities Outline (Tier 3)

PWR SRO Examination Outline Printed: 01/07/2004 Facility: Salem 1 & 2 Form ES-401-3 Generic Category KA

- KA Topic Imp. Points I I I I I Conduct of Operations 2.1.1 1 Knowledge of less than one hour technical 3.8 1 specification action statements for systems.

Equipment Control 2.2.17 Knowledge of the process for managing 3.5 1 maintenance activities during power operations.

2.2.33 Knowledge of control rod programming. 2.9 1 Category Total: 2 Radiation Control Knowledge of the process for performing a containment purge.

Ability to perform procedures to reduce excessive levels of radiation and guard against I personnel exposure.

I Category Total: 2

~~~ ~~ ~~

Emergency Procedures/Plan 1 1

during emergency operations.

Category Total: 2 Generic Total: 7 1

~~~ ~

ES-401 PWR Examination Outline Form ES-401-2 Facility: Salem I8 2 Printed: 01/07/2004 Date Of Exam: 06/11/2004 7 - 1 ~ RO K/A Category Points I SRO-Only Points

3. Generic Knowledge And Abilities Categories Note:

1. Ensure that at least two topics from every WA category are sampled within each tier of the RO outline (i.e., the 'Tier Totals" in each W A category shall not be less than two). Refer to Section D.1.c for additional guidance regarding the SRO sampling.

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. Select topics from many systems and evolutions; avoid selecting more than two WA topics from a given system unless they relate to plant-specificpriorities.

4. Systemslevolutions within each group are identified on the associated outline.

5. The shaded areas are not applicable to the categoryhier.

6.* 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. The SRO WAS must also be linked to 10 CFR 55.43 or an SRO-level learning objective.

7. On the following pages, enter the WA numbers, a brief description of each topic, the topics' importance ratings (IR) 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 columns labeled "K' and "A".

Use duplicate pages for RO and SRO-only exams.

8. For Tier 3, enter the KIA numbers, descriptions, importance ratings, and point totals on Form ES401-3.

9. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate WA statements.

1

PWR RO Examination Outline Printed: 01/07/2004 Facility: Salem 1 & 2 ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2 E/APE # / Name / Safety Function I K1 Imp. Points EA1.02 - MFW System 3.8 1 000007 Reactor Trip - Stabilization - Recove I

000008 Pressurizer Vapor Space Accident / 3 AK2.02 - Sensors and detectors 2.7* 1 EK2.03 - S/GS 3.0 1 2.6* 1 00001 1 Large Break LOCA I 3 4.3* 1 000015/000017 RCP Malfunctions 1 4 2.5 1 000022 Loss of Rx Coolant Makeup / 2 3.0 2.9 000026 Loss of Component Cooling Water /

000026 Loss of Component Cooling Water I I 2.1.2 - Knowledge of operator 3.0 responsibilities during all modes of plant operation.

000027 Pressurizer Pressure Control System 2.4.3 1 - Knowledge of annunciators 3.3 alarms and indications, and use of the

~ response instructions.

000027 Pressurizer Pressure Control System AK3.04 - Why, if PZR level is lost and 2.8 then restored, that pressure recovers much more slowly 000040 Steam Line Rupture - Excessive Hea AA2.03 - Difference between steam 4.6 1 line rupture and LOCA 1

000055 Station Blackout I 6 EA2.01 - Existing valve positioning on 3.4 a loss of instrument air system 000056 Loss of Off-site Power / 6 AA 1.18 - Control room normal 3.2 ventilation supply fan 000057 Loss of Vital AC Inst. Bus I 6 2.1.23 - Ability to perform specific 3.9 1 system and integrated plant procedures during all modes of plant operation.

000062 Loss of Nuclear Svc Water 1 4 AA1.06 - Control of flow rates to 2.9 1 components cooled by the SWS W/E04 LOCA Outside Containment 1 3 X EK1.3 - Annunciators and conditions 3.5 1 indicating signals, and remedial actions associated with the LOCA Outside Containment WE05 Inadequate Heat Transfer - Loss of Sc X EK1.1 - Components, capacity, and 3.8 1 function of emergency systems WA Category Totals: 3 Group Poin : Total: 18 1

PWR RO Examination Outline Printed: 01/07/2004 Facility: Salem 1 & 2 FS - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 Form ES-401-2 E/APE # I Name / Safety Function K3 KA Topic Imp. Pointt 000005 Inoperable/Stuck Control Rod / 1 X AK3.04 - Tech-Spec limits for 3.4 1 inoperable rods 000032 Loss of Source Range NI / 7 AA2.01 - Normallabnormal power 2.6 supply operation 000037 Steam Generator Tube Leak / 3 AK1.01 - Use of steam tables 2.9*

000060 Accidental Gaseous Radwaste Rel. / AK1.02 - Biological effects on humans 2.5 of the various types of radiation, exposure levels that are acceptable for personnel in a nuclear reactor power plant; the units used for radiation intensity measurements and for radiation exposure levels 000067 Plant Fire On-site / 9 AA1.05 - Plant and control room 3.0 1 ventilation systems 000068 Control Room Evac. / 8 AK2.03 - Controllers and positioners 2.9 1 000068 Control Room Evac. / 8 AK2.0 1 - Auxiliary shutdown panel 3.9 1 layout W/EO8 RCS Overcooling - PTS / 4 X EK3.1 - Facility operating 3.4 1 characteristics during transient conditions, including coolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these aperating characteristics W/E10 Natural Circ. / 4 2.2.22 - Knowledge of limiting 3.4 1 zonditions for operations and safety limits.

K/A Category Totals: 2 1

PWR RO Examination Outline Printed: 01/07/2004 Facility: Salem 1 & 2 ES - 401 Plant Systems - Tier 2 / Group 1 Form ES-401-2 Sys/Evol # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KATopic Imp. Point!

003 Reactor Coolant Pump X K4.02 - Prevention of cold 2.5 1 water accidents or transients 003 Reactor Coolant Pump X A3.01 - Seal injection flow 3.3 1 004 Chemical and Volume Control X K5.26 - Relationship 3.1 1 between VCT pressure and NPSH for charging pumps 004 Chemical and Volume Control X K2.04 - BWST tank heaters 2.6 1 005 Residual Heat Removal X K3.05 - ECCS 3.7* 1 006 Emergency Core Cooling X K5.05 - Effects of pressure 3.4 1 on a solid system 006 Emergency Core Cooling X A3.08 - Automatic transfer 4.2 1 of ECCS flowpaths 008 Component Cooling Water X K3.03 - RCP 4.1 1 008 Component Cooling Water X A4.01 - CCW indications 3.3 1 and controls

~ ~~~

0 10 Pressurizer Pressure Control X K4.03 - Over pressure 3.8 1 control 010 Pressurizer Pressure Control X K6.03 - PZR sprays and 3.2 1 heaters 0 12 Reactor Protection X K1.02 - 125V dc system 3.4 1 0 12 Reactor Protection X K2.01 - RPS channels, 3.3 1 components, and interconnections 013 Engineered Safety Features Act X A2.03 - Rapid 4.4 1 depressurization 026 Containment Spray X 2.1.27 - Knowledge of 2.8 1 system purpose and or function.

039 Main and Reheat Steam X K5.08 - Effect of steam 3.6 1 removal on reactivity 039 Main and Reheat Steam X A2.04 - Malfunctioning 3.4 1 steam dump 059 Main Feedwater X A4.08 - Feed regulating 3.0* 1 valve controller 06 1 AuxiliarylEmergencyFeedwate X K6.01 - Controllers and 2.5 1 positioners 062 AC Electrical Distribution X A I .O 1 - Significance of DIG 3.4 1 load limits 062 AC Electrical Distribution X A2.10 - Effects of switching 3.O 1 power supplies on instruments and controls 063 DC Electrical Distribution X K2.01 - Major DC loads 2.9* 1 063 DC Electrical Distribution X K3.02 - Components using 3.5 1 DC control power 064 Emergency Diesel Generator X 2.1.28 -Knowledge of the 3.2 1 1

PWR RO Examination Outline Printed: 01/07/2004 Facility: Salem 1 & 2 Sys/Evol # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KATopic Imp. Points purpose and function of major system components and controls.

073 Process Radiation Monitoring x K1.O1 - Those systems 3.6 1 served by PRMs 073 Process Radiation Monitoring X A 1 .O 1 - Radiation levels 3.2 1 078 Instrument Air X 2.1.32 - Ability to explain 3.4 1 and apply all system limits and precautions.

078 Instrument Air X K1.04 - Cooling water to 2.6 1 compressor WACategory Totals: 3 3 3 2 3 2 2 3 2 2 3 roup Point Total: 28 2

PWR RO Examination Outline Printed: 01/07/2004 Facility: Salem 1 & 2 Plant Systems - Tier 2 / Group 2 ES - 401 Form ES-401-2 Sys/Evol ## / Name K A Topic Imp. Point!

001 Control Rod Drive A2.13 - ATWS 4.4 1 002 Reactor Coolant K6.07 - Pumps 2.5 1 002 Reactor Coolant A 1.11 - Relative level 2.7 1 indications in the RWST, the refueling cavity, the PZR and the reactor vessel during preparation for refbeling 028 Hydrogen Recombiner and Purl A4.02 - Location and 3.7* 1 interpretation of containment pressure indications 033 Spent Fuel Pool Cooling K3.02 - Area and ventilation 2.8 1 radiation monitoring systems 035 Steam Generator A3.01 - SIG water level 4.0 1 control 041 Steam DumpITurbine Bypass C 2.4.49 - Ability to perform 4.0 1 without reference to procedures those actions that require immediate operation of system components and controls.

045 Main Turbine Generator K5.18 - Purpose of 2.7 1 low-power reactor trips (limited to 25% power) 072 Area Radiation Monitoring K4.02 - Fuel building 3.2* 1 isolation 075 Circulating Water K2.03 - 2.6* 1 Emergencylessential SWS Pumps WA Category Totals: roup Point Total: 10 1

Generic Knowledge and Abilities Outline (Tier 3)

PWR RO Examination Outline Printed: 01/07/2004 Facility: Salem 1 & 2 Form ES-40 1-3 Generic Category KA

- KA Topic Imp. Points Conduct of Operations I 2.1.10 I Knowledge of conditions and limitations in the I I facility license.

2.1.28 Knowledge of the purpose and function of major system components and controls.

~

2.1.32 Ability to explain and apply all system limits and precautions.

3 1

~~

Equipment Control 2.2.2 Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels.

2.2.12 Knowledge of surveillance procedures.

Radiation Control 2.3.1 Knowledge of 10 CFR 20 and related facility 2.6 1 radiation control requirements.

2.3.11 Ability to control radiation releases. 2.7 1 Emergency ProcedureslPlan 2.4.3 Ability to identify post-accident instrumentation. 3.5 1 2.4.6 Knowledge symptom based EOP mitigation strategies.

2.4.7 Knowledge of event based EOP mitigation strategies.

Category Total: 3 Generic Total: 10 1

ES-401 Record of Rejected WAS Form ES-401-4 Salem 1 & 2 PWR Examination Outline for RO and SRO Exam Date of Exam: 6/10/04 I I I I NUREG 1021, Draft Revision 9

ES-301 Administrative Topics Outline ' Form ES-301-1 1 Facility: SALEM 1 & 2 Examination Level: RO Date of Examination:

Operating Test Number:

06/07/2004 HOTEL I/ Administrative Topic (see Notel Type Code*

Describe activity to be performed

Description:

Identify and Isolate Non-Essential Heat Loads WA: 2.1.25 Ability to obtain and interpret station ref materials such as Conduct of Operations graphs, monographs, and tables which contain performance data. (2.8,3.1)

CFR: 55.45(12)

Description:

Perform RCS Water Inventory Balance Conduct of Operations WA: 2.1.23 Ability to perform specific system and integrated plant procedures during all modes of plant operation. (3.9,4.0)

CFR: 55.45(12)

Description:

Prepare an Equipment Clearance M WA: 2.2.13 Knowledgeof tagging and clearance procedures. (3.6, 3.8)

CFR: 55.45(13)

I

Description:

Determine Radiological Conditions for Personnel Exposure N WA: 2.3.10 Ability to perform procedures to reduce excessive levels of radiationand guard against personnel exposure. (2.9,3.3)

CFR: 55.45(10)

I Note: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

NUREG-1021, Draft Revision 9

ES-301 Administrative Topics Outline Form ES-301-1 Facility: SALEM 1 & 2 Date of Examination: 06/07/2004 Examination Level: SRO Operating Test Number: - HOTEL Administrative Topic Type Describe activity to be performed (see Note) Code*

Description:

Identify and Isolate Non-Essential Heat Loads Conduct of Operations N WA: 2.1.25 Ability to obtain and interpretstation ref materials such as graphs, monographs, and tables which contain performance data. (2.8, 3.1)

CFR: 55.45( 12)

Description:

Review RCS Water Inventory Balance Conduct of Operations N WA: 2.1.23 Ability to perform specific system and integrated plant procedures during all modes of plant operation. (3.9,4.0)

CFR: 55.45(12)

Equipment Control M

Description:

Review an Equipment Clearance WA: 2.2.13 Knowledge of tagging and clearance procedures. (3.6,3.8)

CFR: 55.45(13)

Description:

Determine Radiological Conditions for Personnel Exposure Radiation Control N W A 2.3.10 Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure. (2.9.3.3)

CFR: 55.45(10)

Description:

Classify an Event Emergency Plan M WA: 2.4.41 Knowledge of the emergency action level thresholds and classifications. (2.3, 4.1)

CFR: 55.45(11)

Note: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

NUREG-1021.Draft Revision 9

ES-301 Control Room / In-Plant Systems Form ES-301-2 Outline Facility: SALEM 1 &2 Date of Examination: -06/07/2004 Exam Level (circle one): RO / SRO(I) / SRO(U) Operating Test No.: HOTEL System / JPM Title Type Safety Code* Function

a. Perform an RCS Dilution DS 1

b. Respond to High Activity in the Reactor Coolant NS 2

c. Transfer to Cold Leg Recirculation (RO Only) DS 3

d. Spurious Isolation of RCP Motor Bearing CCW ALNS 4

e. Respond to High Containment Sump Level (CFCU Leak) ADS 5

f. Synchronize Main Generator to Grid ADS 6

g. Manually Actuate Control Room Accident Pressurized Mode Ops ANS 7

h. Start a Component Cooling Water Pump AS 8

i. Locally Close MSlV and Operate Associated ARV D 4 1 j. Manually Isolate Seal Injection I NR (1 k. Initiate 21 CVCS Monitor Tank Release I DR I 8

• Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA NUREG-1021, Draft Revision 9

Anoendix D Form ES-D-1 Facility: SALEM 1 & 2 Scenario No.: NRC #1 Op-Test No.: HOTEL Examiners: Operators:

Initial Conditions: 85% Rated Thermal Power, BOL, Equilibrium Conditions Turnover: Unit 2 is at 85% power with the following equipment is out of service: PA EDG taken 0 0 s 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago for injector maintenance, 21 RHR Pump taken 0 0 s 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> ago for coupling alignment. Maintenance on both components expected to be completed 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> from now. All required surveillances are complete. Weather conditions are normal. Unit 1 is at 100% power. Hope Creek is in a refueling outage. Shift orders are to raise power to 100% at 10% per hour.

Event Malf. No. Event Event No. Type" Description 1 -------------- N Raise Reactor Power CRSlPO R

RO PRO016B Pressurizer Pressure Channel 111 Fails Low (TS CRS)

CRSlRO 23 SI Accumulator Gas Leak (TS CRS)

CRSlPO I

4 CN0086 C Decreasing Condenser Vacuum ALL I 5 RP0073 M Spurious Turbine Trip, A M , Pzr Safety 2PR3 Fails RP0059A&B ALL Open RP0058 PR0020A 6 C 21 AFW Pump Fails To Auto Start CRSlPO I

' Terminate after SI flow reduction evaluation in LOCA-1 I I

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 1 of 10 NUREG-1021, Revision 9

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

Initial Conditions: 100% Rated Thermal Power, BOL, Equilibrium Conditions Turnover: Unit 2 is at 100% power. Unit 1and Hope Creek are also at 100% power. Solar magnetic disturbances have been occurring. Current SMD K3. 22 AFW Pump was taken 0 0 s 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ago for motor bearing replacement. AFW pump maintenance is expected to be complete 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> from now. All required surveillances are complete. The crew is directed to maintain lower.

I Event Malf. No. Event Event Description I I I N10193A PRNIS Channel N41 Fails High (TS CRS) 2 NE0 Reports Broken Snubber in Aux Building (TS CRS) 3 TU0081H Main Turbine Governor Valve 24MS29 Fails Closed CRSlPO 4

5 6

VL0447 RP0058 RP0069 RP0279A RP0279B RD0064 EL0273A fI CRSlPO C&RO SG Fdwtr Control 22BF19 Fails Closed, Turbine Fails To Trip, Auto MSLIS Fails to Actuate 2 Control Rods Fail To Fully Insert On Reactor Trip Loss of 2A 4KV Vital Bus Offsite sources. 21 EDG fails EL0260 CRS/PO to auto connect with vital bus 7 AFOl83 Loss of Heat Sink (23 AFW Pump Trip and Loss of 21 EL0161 EDG)

I Terminate when feed flow re-established to a SG

, (R)eactivity, (1)nstrumen (C)omponent, (M)ajor Page 1 of 11 NUREG-1021, Revision 9

Appendix D Form ES-D-1 Facility: SALEM 1 & 2 Scenario No.: NRC #3 Op-Test No.: HOTEL Examiners: Operators:

Initial Conditions: 3% Rated Thermal Power, MOL Turnover: Unit 2 is at 3% power, recovering from a 7 day forced outage to repair body to bonnet leak on Prr Spray Bypass Valve 2PS4. Mode change is approved. Weather conditions are normal. Unit 1 and Hope Creek are at 100% power. Shift orders are to raise power to 50%

at <a% per hour.

Event Malf. No. Event Event No. Type* Description I -------------- N Raise Reactor Power CRSlPO R

RO 2 PRO017A I Pressurizer Level Channel I(LT459) Fails Low (TS CRS)

CRSlRO 3 I SG0078A 1 AfL I 21 SG Tube Leak (5 gpm) (TS CRS) 4 BFOI05A C 21 Main Feed Pump Trip CRSlPO 5 RCOOI2C C 23 RCP High Vibration CRSlRO 6 SG0078A M SGTR with Loss of Offsite Power EL0134 ALL 7 C Letdown Isolation Valve 2CV7 Fails to Close on Phase A CRSlRO Terminate when depress criteria met (SGTR-1 Table F)

Page Iof 11 NUREG-1021, Revision 9

Appendix D Form ES-D-1 l Facility:

Examiners:

SALEM 1 & 2 Scenario No.: NRC #4 Operators:

Op-Test No.: HOTEL Initial Conditions: 100% Rated Thermal Power Turnover: Unit at 100% power. 22 SGFP has a control oil leak. 22 AFW Pump taken 0 0 s two hours ago for motor bearing replacement. All required surveillances are complete.

Weather conditions are normal. Unit 1and Hope Creek are at 100% power. Shift orders are to reduce power to 60% at 10% per hour to repair SGFP oil leak.

Event Type* Event DescriDtion I

---

.------ cRspo R: RO 1

I Reduce Power to 60% To Repair SGFP Oil Leak 2 SG 0095D 24 SG Lvl Xmtr (549) Ch I1 Fails Low (TS-CRS) 3 CV0029A C CRSlRO 1 Letdown Hx CCW Outlet 2CC71 Fails Closed 4 RM0241A Cntmt Area Hi Rad Monitor 2R44B Fails High [TS-CRS]

- I I

5 BF0105B RD0045 c;

CRSlRO 1 I

22 Fd Pump Trip wlUncontrolled Rod Insertion in AUTO I

I 6 MS0088D M 24 MSL Break In Containment, 24 MSIV Fails to Close MS0092H ALL I

I 7 SJO184A C 21 SI Pump Fails to Auto Start CRS/PO

~~

8 RP0276A C Phase B Fails to Automatically Actuate RP0276B CRSlPO 9 RP0277A C Containment Spray Fails to Automatically Actuate RP0277B CRSlPO Page I of 14 NUREG-1021, Revision 9