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

Form ES-401-2 ES-401 PWR Examination Outline 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

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

ES-401-3.

1

Printed: 01/07/2004 PWR SRO Examination Outline 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 00001 5/000017 RCP Malfunctions / 4 000054 Loss of Main Feedwater / 4 000057 Loss of Vital AC Inst. Bus / 6 000058 Loss of DC Power / 6 000065 Loss of Instrument Air / 8 W/E04 LOCA Outside Containment / 3 W/E05 Inadequate Heat Transfer - Loss of St K/A Category Totals:

0 -

KA Topic 2.4.6 - Knowledge symptom based EOP mitigation strategies.

AA2.01 - Occurrence of reactor andlor turbine trip 2.2.25 - Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.

AA2.02 - 125V dc bus voltage, low/critical low, alarm AA2.08 - Failure modes of air-operated equipment 2.4.49 - Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.

EA2.2 - Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments Group Poin Imp.

4.0 4.4 3.7 3.6 3.3 4.0

4.3 Total

Points 1

1 1

PWR SRO Examination Outline Facility:

Salem 1 & 2 ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 2 K3 Printed: 01/07/2004 A1 0

0 Form ES-401-2 Imp.

4.3 4.1 4.0 3.8 I

I Point5 1

1 1

1 EIAPE ## I Name I Safety Function 000003 Dropped Control Rod / 1 W/E 14 Loss of CTMT Integrity / 5 W/E16 High Containment Radiation / 9 K/A Category Totals:

000024 Emergency Boration / 1 I

0 0

K1 -

K2 -

W/E07 Inad. Core Cooling 14 KA Topic 2.4.4 - Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

AA2.01 - Whether boron flow andor MOVs are malfunctioning, from plant conditions EA2.1 - Facility conditions and selection of appropriate procedures during abnormal and emergency operations EA2.2 - Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments 2.4.4 - Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

Group Poin I Total:

5 1

Sys/Evol # / Name 005 Residual Heat Removal K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KATopic X

A2.04 - RHR valve malfunction system status criteria which require the notification of plant personnel.

MFW in technical specifications for limiting conditions for operations and safety limits.

022 Containment Cooling X 2.1.14 - Knowledge of 06 1 AuxiliaryIEmergency Feedwate X

A2.06 - Back leakage of X 2.2.25 - Knowledge of bases 064 Emergency Diesel Generator 1

Imp. Points 2.9 1

3.3 1

3.0 1

3.7 1

WACategoryTotals:

0 0

0 0

0 0

0 2

0 0

2 roup Point Total:

4

Facility:

Salem 1 & 2 ES - 401 PWR SRO Examination Outline Plant Systems - Tier 2 / Group 2 Printed: 01/07/2004 Form ES-401-2 1

Generic Knowledge and Abilities Outline (Tier 3)

PWR SRO Examination Outline 2.1.1 1 Facility:

Salem 1 & 2 Knowledge of less than one hour technical 3.8 1

specification action statements for systems.

Printed: 01/07/2004 Form ES-401-3 Equipment Control Generic Category KA KA Topic Imp. Points I

I I

I I

2.2.17 Knowledge of the process for managing 3.5 1

2.2.33 Knowledge of control rod programming.

2.9 1

Category Total:

2 maintenance activities during power operations.

Conduct of Operations 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

~~~

~~

~~

during emergency operations.

Category Total:

1 1

2 Generic Total:

7 1

~~~

~

ES-401 PWR Examination Outline Form ES-401-2 Facility:

Salem I 8 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 *I from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.

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. 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

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

ES401-3.

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 AK2.02 - Sensors and detectors EK2.03 - S/GS 2.7*

3.0 2.1.2 - Knowledge of operator responsibilities during all modes of plant operation.

EA1.02 - MFW System E/APE # / Name / Safety Function I K1 Points 1

1 1

1 1

1 Imp.

3.8 I

000007 Reactor Trip - Stabilization - Recove 000008 Pressurizer Vapor Space Accident / 3 2.6*

4.3*

2.5 3.0 2.9 3.0 3.3 2.8 4.6 00001 1 Large Break LOCA I 3 000015/000017 RCP Malfunctions 14 000022 Loss of Rx Coolant Makeup / 2 I

000026 Loss of Component Cooling Water /

000026 Loss of Component Cooling Water I 000027 Pressurizer Pressure Control System 2.4.3 1 - Knowledge of annunciators alarms and indications, and use of the

~ response instructions.

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

1 EA2.01 - Existing valve positioning on a loss of instrument air system 3.4 3.2 3.9 2.9 3.5 3.8

Total:

000055 Station Blackout I 6 000056 Loss of Off-site Power / 6 AA 1.1 8 - Control room normal ventilation supply fan 2.1.23 - Ability to perform specific system and integrated plant procedures during all modes of plant operation.

1 000057 Loss of Vital AC Inst. Bus I 6 000062 Loss of Nuclear Svc Water 14 1

AA1.06 - Control of flow rates to components cooled by the SWS EK1.3 - Annunciators and conditions indicating signals, and remedial actions associated with the LOCA Outside Containment EK1.1 - Components, capacity, and function of emergency systems Group Poin W/E04 LOCA Outside Containment 13 X

1 WE05 Inadequate Heat Transfer - Loss of Sc X -

3 1

18 WA Category Totals:

1

PWR RO Examination Outline AA1.05 - Plant and control room ventilation systems AK2.03 - Controllers and positioners AK2.0 1 - Auxiliary shutdown panel EK3.1 - Facility operating layout 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 zonditions for operations and safety limits.

2.2.22 - Knowledge of limiting Printed: 01/07/2004 3.0 1

2.9 1

3.9 1

3.4 1

3.4 1

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 000005 Inoperable/Stuck Control Rod / 1 000032 Loss of Source Range NI / 7 000037 Steam Generator Tube Leak / 3 000060 Accidental Gaseous Radwaste Rel. /

000067 Plant Fire On-site / 9 000068 Control Room Evac. / 8 000068 Control Room Evac. / 8 W/EO8 RCS Overcooling - PTS / 4 W/E10 Natural Circ. / 4 K/A Category Totals:

K3 X -

X 2

KA Topic AK3.04 - Tech-Spec limits for inoperable rods AA2.01 - Normallabnormal power supply operation AK1.01 - Use of steam tables AK1.02 - Biological effects on humans 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 Imp.

3.4 2.6 2.9*

2.5 Pointt 1

1

Facility:

Salem 1 & 2 ES - 401 K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KATopic Sys/Evol # / Name 003 Reactor Coolant Pump X

K4.02 - Prevention of cold 003 Reactor Coolant Pump X

A3.01 - Seal injection flow 004 Chemical and Volume Control X

K5.26 - Relationship water accidents or transients between VCT pressure and NPSH for charging pumps K2.04 - BWST tank heaters 004 Chemical and Volume Control 005 Residual Heat Removal X

K3.05 - ECCS X

006 Emergency Core Cooling X

K5.05 - Effects of pressure 006 Emergency Core Cooling X

A3.08 - Automatic transfer 008 Component Cooling Water X

K3.03 - RCP 008 Component Cooling Water X

A4.01 - CCW indications on a solid system of ECCS flowpaths and controls control heaters

~

~~~

0 10 Pressurizer Pressure Control X

K4.03 - Over pressure 010 Pressurizer Pressure Control X

K6.03 - PZR sprays and 0 12 Reactor Protection X

K1.02 - 125V dc system 0 12 Reactor Protection X

K2.01 - RPS channels, components, and interconnections depressurization system purpose and or function.

K5.08 - Effect of steam removal on reactivity steam dump valve controller positioners load limits power supplies on instruments and controls 063 DC Electrical Distribution X

K2.01 - Major DC loads 013 Engineered Safety Features Act X

A2.03 - Rapid 026 Containment Spray X 2.1.27 - Knowledge of 039 Main and Reheat Steam X

039 Main and Reheat Steam X

A2.04 - Malfunctioning 059 Main Feedwater X

A4.08 - Feed regulating 06 1 AuxiliarylEmergency Feedwate X

K6.01 - Controllers and 062 AC Electrical Distribution X

A I.O 1 - Significance of DIG 062 AC Electrical Distribution X

A2.10 - Effects of switching 063 DC Electrical Distribution X

K3.02 - Components using 064 Emergency Diesel Generator X 2.1.28 -Knowledge of the DC control power PWR RO Examination Outline Plant Systems - Tier 2 / Group 1 Imp.

Point!

2.5 1

3.3 1

3.1 1

2.6 1

3.7*

1 3.4 1

4.2 1

4.1 1

3.3 1

1 3.8 3.2 1

3.4 1

3.3 1

4.4 1

2.8 1

3.6 1

3.4 1

3.0*

1 2.5 1

3.4 1

3.O 1

2.9*

1 3.5 1

3.2 1

Printed: 01/07/2004 Form ES-401-2 1

PWR RO Examination Outline Facility:

Salem 1 & 2 Sys/Evol # / Name 073 Process Radiation Monitoring 073 Process Radiation Monitoring 078 Instrument Air 078 Instrument Air WACategory Totals:

Printed: 01/07/2004 K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KATopic Imp. Points purpose and function of major system components and controls.

served by PRMs x

K1.O1 - Those systems 3.6 1

X A 1.O 1 - Radiation levels 3.2 1

X 2.1.32 - Ability to explain 3.4 1

and apply all system limits and precautions.

compressor X

K1.04 - Cooling water to 2.6 1

3 3

3 2

3 2

2 3

2 2

3 roup Point Total:

28 2

Facility:

Salem 1 & 2 ES - 401 Imp.

4.4 2.5 2.7 3.7*

2.8 4.0 4.0 2.7 3.2*

2.6*

Sys/Evol ## / Name 001 Control Rod Drive 002 Reactor Coolant 002 Reactor Coolant Point!

1 1

1 1

1 1

1 1

1 1

028 Hydrogen Recombiner and Purl 033 Spent Fuel Pool Cooling 035 Steam Generator 041 Steam DumpITurbine Bypass C 045 Main Turbine Generator 072 Area Radiation Monitoring 075 Circulating Water WA Category Totals:

PWR RO Examination Outline Plant Systems - Tier 2 / Group 2 Printed: 01/07/2004 Form ES-401-2 K A Topic K6.07 - Pumps A 1.1 1 - Relative level indications in the RWST, the refueling cavity, the PZR and the reactor vessel during preparation for refbeling A4.02 - Location and interpretation of containment pressure indications K3.02 - Area and ventilation radiation monitoring systems A3.01 - SIG water level control 2.4.49 - Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.

K5.18 - Purpose of low-power reactor trips (limited to 25% power)

K4.02 - Fuel building isolation K2.03 -

Emergencylessential SWS Pumps A2.13 - ATWS roup Point Total:

10 1

Generic Knowledge and Abilities Outline (Tier 3)

PWR RO Examination Outline

~

2.1.32 Printed: 01/07/2004 Ability to explain and apply all system limits and precautions.

Facility:

Salem 1 & 2

~~

2.2.2 2.2.12 Generic Category Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels.

Knowledge of surveillance procedures.

Conduct of Operations 2.3.1 Knowledge of 10 CFR 20 and related facility 2.6 2.3.11 Ability to control radiation releases.

2.7 radiation control requirements.

KA KA Topic 1

1 Form ES-40 1-3 Imp.

Points 2.4.3 Ability to identify post-accident instrumentation.

I 2.1.10 I Knowledge of conditions and limitations in the facility license.

3.5 1

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

2.4.6 2.4.7 Knowledge symptom based EOP mitigation strategies.

Knowledge of event based EOP mitigation strategies.

3 1

Equipment Control Radiation Control Emergency ProcedureslPlan 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 II II NUREG 1021, Draft Revision 9

ES-301 Administrative Topics Outline Form ES-30 1 -1 Administrative Topic I/

(see Notel Facility:

SALEM 1 & 2 Date of Examination:

06/07/2004 Type Code*

11 Examination Level: RO Describe activity to be performed Operating Test Number:

HOTEL M

==

Description:==

Prepare an Equipment Clearance WA:

CFR:

55.45(13) 2.2.13 Knowledge of tagging and clearance procedures. (3.6, 3.8)

Administrative Topic Conduct of Operations Conduct of Operations N

Conduct of Operations Conduct of Operations

==

Description:==

Determine Radiological Conditions for WA:

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)

Personnel Exposure

==

Description:==

WA:

graphs, monographs, and tables which contain performance data. (2.8,3.1)

CFR:

55.45(12)

Identify and Isolate Non-Essential Heat Loads 2.1.25 Ability to obtain and interpret station ref materials such as

==

Description:==

WA:

procedures during all modes of plant operation. (3.9,4.0)

CFR:

55.45(12)

Perform RCS Water Inventory Balance 2.1.23 Ability to perform specific system and integrated plant I

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 Administrative Topic (see Note)

Conduct of Operations Conduct of Operations Equipment Control Radiation Control Emergency Plan Type Code*

N N

M N

M Operating Test Number: - HOTEL Describe activity to be performed

==

Description:==

WA:

graphs, monographs, and tables which contain performance data. (2.8, 3.1)

CFR:

55.45( 12)

Identify and Isolate Non-Essential Heat Loads 2.1.25 Ability to obtain and interpret station ref materials such as

==

Description:==

WA:

procedures during all modes of plant operation. (3.9,4.0)

CFR:

55.45(12)

Review RCS Water Inventory Balance 2.1.23 Ability to perform specific system and integrated plant

==

Description:==

Review an Equipment Clearance WA:

CFR:

55.45(13) 2.2.13 Knowledge of tagging and clearance procedures. (3.6,3.8)

==

Description:==

Determine Radiological Conditions for 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)

Personnel Exposure

==

Description:==

Classify an Event 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 System / JPM Title

a.

Perform an RCS Dilution

b.

Respond to High Activity in the Reactor Coolant Transfer to Cold Leg Recirculation (RO Only)

Spurious Isolation of RCP Motor Bearing CCW Respond to High Containment Sump Level (CFCU Leak)

Synchronize Main Generator to Grid

c.

d.

e.

f.

g.

h.

Manually Actuate Control Room Accident Pressurized Mode Ops Start a Component Cooling Water Pump Facility:

SALEM 1 &2 Exam Level (circle one): RO / SRO(I) / SRO(U)

Type Safety Code*

Function DS 1

NS 2

DS 3

ALNS 4

ADS 5

ADS 6

ANS 7

AS 8

Date of Examination: -06/07/2004 Operating Test No.:

HOTEL

i. Locally Close MSlV and Operate Associated ARV D

4 I NR 11 j.

Manually Isolate Seal Injection 8

I DR I (1 k.

Initiate 21 CVCS Monitor Tank Release

• 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 Event No.

1 Facility:

SALEM 1 & 2 Scenario No.:

NRC #1 Op-Test No.: HOTEL Examiners:

Operators:

Initial Conditions:

Turnover:

Unit 2 is at 85% power with the following equipment is out of service: PA EDG taken 00s 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 00s 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.

85% Rated Thermal Power, BOL, Equilibrium Conditions Malf. No.

Event Event Type" Description N

Raise Reactor Power CRSlPO R

RO I

Decreasing Condenser Vacuum I

PRO01 6B CRSlRO CRSlPO 21 AFW Pump Fails To Auto Start I

' Terminate after SI flow reduction evaluation in LOCA-1 4

5 6

Pressurizer Pressure Channel 111 Fails Low (TS CRS)

CN0086 C

RP0073 M

RP0059A&B ALL RP0058 PR0020A ALL C

CRSlPO 23 SI Accumulator Gas Leak (TS CRS)

Spurious Turbine Trip, A M, Pzr Safety 2PR3 Fails Open I

I

• (N)ormal, (R)eactivity, (I)ns tru men t, (C)omponen t, (M)ajor Page 1 of 10 NUREG-1021, Revision 9

Appendix D Form ES-D-1 Event I

2 3

4 5

6 Facility:

SALEM I

& 2 Scenario No.:

NRC #2 Op-Test No.: HOTEL I

Examiners:

Operators:

I Initial Conditions:

100% Rated Thermal Power, BOL, Equilibrium Conditions Turnover:

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 Unit 2 is at 100% power. Unit 1 and Hope Creek are also at 100% power. Solar I

2 3

4 5

6 7

lower.

Malf. No.

Event I

N10193A TU0081 H CRSlPO VL0447 RP0058 RP0069 RP0279A RP0279B CRSlPO f RD0064 I C&RO EL0273A EL0260 CRS/PO AFOl83 EL01 61 I

, (R)eactivity, (1)nstrumen Event Description PRNIS Channel N41 Fails High (TS CRS)

NE0 Reports Broken Snubber in Aux Building (TS CRS)

Main Turbine Governor Valve 24MS29 Fails Closed 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 to auto connect with vital bus Loss of Heat Sink (23 AFW Pump Trip and Loss of 21 EDG)

Terminate when feed flow re-established to a SG (C)omponent, (M)ajor Page 1 of 11 NUREG-1021, Revision 9

Appendix D Form ES-D-1 Event No.

I Facility:

SALEM 1 & 2 Scenario No.:

NRC #3 Op-Test No.: HOTEL Malf. No.

Event Event Type*

Description N

Raise Reactor Power CRSlPO R

RO Examiners:

Operators:

2 Initial Conditions:

3% Rated Thermal Power, MOL PRO01 7A I

CRSlRO Pressurizer Level Channel I (LT459) Fails Low (TS CRS)

Turnover:

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.

Unit 2 is at 3% power, recovering from a 7 day forced outage to repair body to 4

5 6

7 BFOI 05A C

21 Main Feed Pump Trip RCOOI 2C C

23 RCP High Vibration SG0078A M

SGTR with Loss of Offsite Power EL0134 ALL CRSlPO CRSlRO C

CRSlRO Letdown Isolation Valve 2CV7 Fails to Close on Phase A Terminate when depress criteria met (SGTR-1 Table F) 21 SG Tube Leak (5 gpm) (TS CRS) 1 AfL I 3 I SG0078A Page I of 11 NUREG-1021, Revision 9

Appendix D Form ES-D-1 Event Type*

Facility:

SALEM 1 & 2 Scenario No.:

NRC #4 Op-Test No.: HOTEL ll Event DescriDtion Examiners:

Operators:

I 2

3 4

5 6

7 8

9 Initial Conditions:

Turnover:

two hours ago for motor bearing replacement. All required surveillances are complete.

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

100% Rated Thermal Power Unit at 100% power. 22 SGFP has a control oil leak. 22 AFW Pump taken 0 0 s S G 0 0 9 5 D CV0029A RM0241A BF0105B RD0045 MS0088D MS0092H SJO184A RP0276A RP0276B RP0277A RP0277B C

CRS/PO I

21 SI Pump Fails to Auto Start cRspo 1 Reduce Power to 60% To Repair SGFP Oil Leak R: RO 24 SG Lvl Xmtr (549) Ch I1 Fails Low (TS-CRS)

Letdown Hx CCW Outlet 2CC71 Fails Closed C

CRSlRO 1 Cntmt Area Hi Rad Monitor 2R44B Fails High [TS-CRS]

I I

22 Fd Pump Trip wlUncontrolled Rod Insertion in AUTO c;

CRSlRO 1

I I M

24 MSL Break In Containment, 24 MSIV Fails to Close ALL I

I I

~~

C CRSlPO Phase B Fails to Automatically Actuate C

CRSlPO Containment Spray Fails to Automatically Actuate Page I of 14 NUREG-1021, Revision 9