ML041730175

Final Outlines (Change Summaries - Optional)

ML041730175
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: ML041730175 (14)

Text

ES-401 PWR Examination Outline Form ES-401-2 Tier Facilitv:

Salem Generating Station Date Of Exam:

06/12/2004 RO WA Category Point:

Group K I I K2 [ K3 I K4 [ K5 I K6 I AI [ A2 I A3 I A4 I G* (Tote Printed: 05/07/2004 1

1 4 ) 3 1 3 1 2 1 2 1 2 1 2 1 3 1 2 1 2 1 3 ) 28 I

2.

I I

I I

I I

I I

I I

I I

2 0

1 1

1 1

0 1

1 2

1 1

1 0

Systems 4

4 4

3 3

2 3

4 4

3 4

38 Tier Totals Plant

3. Generic Knowledge And Abilities Categories I

SRO-Only Points I 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 WAcategory 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 "Kt and "A".

Use duplicate pages for RO and SRO-only 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

PWR RO Examination Outline Facility:

Salem Generating Station E/AJ?E # / Name / Safety Function 000007 Reactor Trip - Stabilization - Recove 000008 Pressurizer Vapor Space Accident /

000009 Small Break LOCA / 3 Printed: 05/07/2004 K1 IC x

x ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-2

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00001 1 Large Break LOCA / 3 00001 1 Large Break LOCA / 3

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X 000015/000017 RCP Malfunctions / 4 000022 Loss of Rx Coolant Makeup / 2 000026 Loss of Component Cooling Water /

000026 Loss of Component Cooling Water /

000027 Pressurizer Pressure Control System 000027 Pressurizer Pressure Control System 000040 Steam Line Rupture - Excessive Hex 000055 Station Blackout / 6 000056 Loss of Off-site Power / 6 000057 Loss of Vital AC Inst. Bus / 6 000062 Loss of Nuclear Svc Water / 4 WE04 LOCA Outside Containment / 3 WE05 Inadequate Heat Transfer - Loss of St X

X X

I KIA Category Totals:

3 3

K3 -

A1 A2 G #

KA Topic EA1.02 - MFW System AK2.02 - Sensors and detectors 2.7*

I I

I I

EK2.03 - S/GS 3.0

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EZ.02 - Pumps 2.6*

EK3.06 - Actuation of Phase A and B 4.3*

during LOCA initiation AK3.01 - Potential damage from high winding and/or bearing temperatures AK1.03 - Relationship between 3.0 charging flow and PZR level I X I (AA2.01 -Location of a leakin the I 2.9 ccws 2.1.2 - Knowledge of operator responsibilities during all modes of plant operation.

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 3.0 2.4.3 1 - Knowledge of annunciators 3.3 2.8 AA2.03 - Difference between steam line rupture and LOCA a loss of instrument air system X

AA1.18 - Control room normal 3.2 ventilation supply fan system and integrated plant procedures during all modes of plant operation.

X AA1.06 - Control of flow rates to 2.9 components cooled by the SWS EK1.3 - Annunciators and conditions indicating signals, and remedial actions associated with the LOCA Outside Containment I

X 2.1.23 - Ability to perform specific 3.9 3.5 EKI.l - Components, capacity, and function of emergency systems 3.8 Group Point Total:

Point:

1 1

1 1 -

18 1

PWR RO Examination Outline Printed: 05/07/2004 Facility:

Salem Generating Station ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 2 Form ES-401-2 E/APE # I Name 1 Safety Function Points Imp.

3.4 KA Topic AK3.04 - Tech-Spec limits for inoperable rods 000005 InoperableIStuck Control Rod I 1 1 -

1 000032 Loss of Source Range NI / 7 2.6 2.9" 2.5 3.0 AA2.0 1 - Normal/abnormal power supply operation AKl.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 radiatior exposure levels AA1.05 - Plant and control room ventilation system 000037 Steam Generator Tube Leak 13 1

I 000060 Accidental Gaseous Radwaste Rel. /

000067 Plant Fire On-site / 9 1

AK2.03 - Controllers and positioners 2.9 1

300068 Control Room Evac. / 8 300068 Control Room Evac. / 8 I

AK2.01 - Auxiliary shutdown panel layout 3.9 3.4 -

1

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WE08 RCS Overcooling - PTS / 4 EK3.1 - Facility operating characteristics during transient conditions, including coolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics q/E 10 Natural Circ. / 4 2.2.22 - Knowledge of limiting conditions for operations and safety limits.

1 3.4 -

9 WA Category Totals:

Group Point Total:

1

PWR RO Examination Outline Facility:

Salem Generating Station TCS - 401.

Plant Systems - Tier 2 / Group 1 008 Component Cooling Water 008 Component Cooling Water 0 10 Pressurizer Pressure Control 01 0 Pressurizer Pressure Control 0 12 Reactor Protection 012 Reactor Protection 0 13 Engineered Safety Features Act 026 Containment Spray 039 Main and Reheat Steam 039 Main and Reheat Steam 059 Main Feedwater 059 Main Feedwater 06 1 AuxiliaryiEmergency Feedwate 062 AC Electrical Distribution 062 AC Electrical Distribution 063 DC Electrical Distribution 063 DC Electrical Distribution 064 Emergency Diesel Generator Printed: 05/07/2004 Form ES-401-2 of ECCS flowpaths X

K3.03 - RCP 4.1 1

X A4.01 - CCW indications 3.3 1

X K4.03 - Over pressure 3.8 1

X K6.03 - PZR sprays and 3.2 1

and controls control heaters X

K1.02 - 125V dc system 3.4 1

X K2.01 - RPS channels, 3.3 1

components, and interconnections depressurization system purpose and or function.

X K5.08 - Effect of steam 3.6 1

removal on reactivity steam dump X

A4.08 - Feed regulating 3.0*

1 valve controller X

K1.04 - S/GS water level 3.4 1

control system X

K6.01 - Controllers and 2.5 1

positioners X

A 1.O 1 - Significance of D/G 3.4 1

load limits X

A2.10 - Effects of switching 3.0 1

power supplies on instruments and controls X

A2.03 - Rapid 4.4 1

X 2.1.27 - Knowledge of 2.8 1

X A2.04 - Malfunctioning 3.4 1

X K2.01 - Major DC loads 2.9" 1

X K3.02 - Components using 3.5 1

X 2.1.28 - Knowledge of the 3.2 1

DC control power purpose and function of major system components and controls.

Sys/Evol # I Name 073 Process Radiation Monitoring 073 Process Radiation Monitoring 078 Instrument Air 078 Instrument Air K/A Category Totals:

2 K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G KATopic Imp. Points x

K1.O1 -Those systems 3.6 1

X A1.O1 - Radiation levels 3.2 1

K1.04 - Cooling water to 2.6 1

compressor X 2.1.32 - Ability to explain 3.4 1

and apply all system limits and precautions.

served by PRMs X

4 3

3 2

2 2

2 3

2 2

3 Group Point Total:

28

PWR RO Examination Outline Facility:

Salem Generating Station 2 1 Group 2 KA Topic A2.13 - ATWS Printed: 05/07/2004 Form ES-401-2 Imp. Points 4.4 1

A 1.1 1 - Relative level indications in the RWST, the refueling cavity, the PZR and the reactor vessel during preparation for refueling A3.03 - Pressure, temperatures, and flows A4.02 - Location and interpretation of containment pressure indications K3.02 - Area and ventilation radiation monitoring systems A3.01 - S/G water level control without reference to procedures those actions that require immediate operation of system components and Zontrols.

.ow-power reactor trips

limited to 25% power)

C4.02 - Fuel building solation C2.03 - Emergency/essential 2.4.49 - Ability to perform K5.18 - Purpose of SWS pumps 2.7 1

4.4 1

3.7*

1 2.8 1

4.0 1

4.0 1

2.7 1

3.2*

1 2.6*

1 1

Generic Knowledge and Abilities Outline (Tier 3)

PWR RO Examination Outline 2.1.10 2.1.28 2.1.32 Facility:

Salem Generating Station Generic Categorv KA KA Topic Knowledge of conditions and limitations in the facility license.

Knowledge ofthe purpose and function of major system components and controls.

Ability to explain and apply all system limits and precautions.

2.7 3.2

3.4 Printed

05/07/2004 Form ES-401-3 Imp. Points 2.2.2 2.2.12 Conduct of Operations Ability to manipulate the console controls as required to operate the facility between shutdown and designated power levels.

Knowledge of surveillance procedures.

Radiation Control I

I 2.3.1 Knowledge of 10 CFR: 20 and related facility 2.6 1

2.3.1 1 Ability to control radiation releases.

2.7 1

Category Total:

2 radiation control requirements.

Equipment Control 2.4.6 2.4.7 Knowledge symptom based EOP mitigation 3.1 1

Knowledge of event based EOP mitigation 3.1 1

strategies.

strategies.

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Emergency Procedures/Plan I

I I

2.4.3 I Ability to identify post-accident instrumentation. I 3.5 I 1

Generic Total:

10 1

ES-301 Administrative Topics Outline Form ES-301-1 Conduct of Operations Equipment Control Radiation Control 1 Facility:

SALEM 1 & 2 Date of Examination:

06/07/2004 Examination Level: RO N

M N

Administrative Topic see Note)

Code*

Conduct of Operations Emergency Plan 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)

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

==

Description:==

Prepare 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 Personnel Exposure WA:

radiation and guard against personnel exposure. (2.9, 3.3)

CFR:

55.45(10) 2.3.10 Ability to perform procedures to reduce excessive levels of 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.

II NUREG-1021, Draft Revision 9

ES-301 Ad minist ra t ive T ~ D ics Out tin e Form ES-301-1 Facility:

SALEM 1 & 2 Date of Examination:

06/07/2004 Examination Level: SRO Operating Test Number: - HOTEL Admin ist rat ive Topic Conduct of Operations Conduct of Operations

/I Equipment Control ll Radiation Control Radiation Control Emergency Plan Type Code*

N N

M N

M 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)

==

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

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 Facility:

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

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

HOTEL Control Room Systems (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U)

System / JPM Title

a.

Perform an RCS Dilution TY Pe Code*

Safety Function DS 1

I( b.

Respond to High Activity in the Reactor Coolant NS 2

11 c.

Transfer to Cold Leg Recirculation (RO Only)

DS 3

11 d.

Spurious Isolation of RCP Motor Bearing CCW ALNS 4

ADS 5

e.

f.

Respond to High Containment Sump Level (CFCU Leak)

Synchronize Main Generator to Grid ADS 6

ANS 7

g.

h.

In-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

Manually Actuate Control Room Accident Pressurized Mode Ops Start a Component Cooling Water Pump AS 8

Manually Isolate Seal Injection II J.

NR I

5 I

D l

11 k. Start and Synchronize an Emergency Diesel Generator

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11

• Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, 11 (S)imulator, (L)ow-Power, (R)CA NUREG-1021, Draft Revision 9

Amendix D Form ES-D-1 Event TY Pe*

N CRSlPO R

RO Facility:

SALEM 1 & 2 Scenario No.:

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

Operators:

Event Description Raise Reactor Power Initial Conditions:

Turnover:

Unit 2 is at 90% power with the following equipment is out of service: 2A 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.

90% Rated Thermal Power, MOL, Equilibrium Conditions C

CRSlPO 11 4 I VC0173A 21 SW Pump Trip With Failure of 25 Service Water Pump to Auto Start I/

5 I CN0086 I

CRSlRO Pressurizer Pressure Channel I Fails Low (TS CRS) 11 7

1 RP318G5 21 Cntmt Fan Coil Unit Trip (TS CRS) 6 BFOl05A&B RP0059A&B RP0058 PR0020A M

ALL C

1 Decreasing Condenser Vacuum ALL Mn Feed Pumps Trip on High Exh Hood Pressure, A M, Pzr Safety 2PR3 Fails Open C

CRSlPO I 23 Aux Building Exhaust Fan Fails to Start on SEC L

Terminate after SI flow reduction evaluation in LOCA-1 Page 1 of 12 NUREG-I 021, Draft Revision 9

ADDendix D Form ES-D-1 Facility:

SALEM 1 & 2 Scenario No.:

NRC #2 Op-Test No.: HOTEL ll Examiners:

Operators:

Initial Conditions:

Turnover:

magnetic disturbances have been occurring. Current SMD K3. 22 AFW Pump was taken 00s 1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-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 100% Rated Thermal Power, BOL, Equilibrium Conditions Unit 2 is at 100% power. Unit 1 and Hope Creek are also at 100% power. Solar

>wer.

Malf. No.

Event TvDe*

NlOI 93A CF81 (OVDI)

C CRSlPO DA033D (RF)

TU0081 G N

CRSlPO Event 1

2 3

4 5

6 I

R 1

RO VL0447 RP0058 RP0069 RP0073 RP0279A&B EL01 44 AFOI 83 C

ALL M

ALL Event DescriDtion PRNIS Channel N41 Fails High (TS CRS) 24MS10 Relief Fails Open (Pressure Setpoint Decrease)

Failure of RTB Shunt Trip Capability (TS CRS)

Main Turbine Governor Valve 23MS29 Fails Closed SG Fdwtr Control 22BF19 Fails Closed, Turbine Fails To Trip, Auto MSLIS Fails to Actuate Loss of 2A 4KV Vital Bus and 23 AFW Pump Trip Terminate when feed flow re-established to a SG (C)omponent, (M)ajor Page 1 of 10 NUREG-1021, Draft Revision 9

Appendix D Form ES-D-1 Event No.

I 2

3 Facility:

SALEM 1 & 2 Scenario No.:

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

Event Event TY pe*

Description N

Raise Reactor Power CRSlPO R

RO I

CRSlRO PRO01 7A SG0078A C

21 SG Tube Leak (5 gpm) (TS CRS)

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

Examiners:

Operators:

I ALL I

21 Main Feed Pump Trip I BF0105A I CRSlPO

1) 5 I RC0012C I C

1 23 RCP High Vibration CRSlRO SG0078A SGTR with Loss of Offsite Power II I EL01 34 11 7 I SJ0184A 21 SI Pump Fails to Auto Start 1

CRZlPO I Terminate scenario when depressurization criteria met (SGTR-1 Table F)

I

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor I

1 Page 1 of 10 NUREG-1021, Draft Revision 9

Appendix D Form ES-D-1

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Facility:

SALEM 1 & 2 Scenario No.:

NRC #4 Op-Test No.: HOTEL Examiners:

Operators:

Initial Conditions:

100% Rated Thermal Power Turnover:

two hours ago for pump 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.

Unit at 100% power. 22 SGFP has a control oil leak. 23 AFW Pump taken 00s

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Event DescriDtion Malf. No.

Event Type*

Event No.

1 N: CRS/PO R: RO Reduce Power to 60% To Repair SGFP Oil Leak 24 SG Lvl Xmtr (549) Ch II Fails Low (TS-CRS)

Letdown Hx CCW Outlet 2CC71 Fails Closed Cntmt Area Hi Rad Monitor 2R44B Fails High [TS-CRS]

2 SG0095D CV0029A 3

C CRSIRO 4

RM0241A 5

BFOI 05B RD0061 C

CRSlRO 22 Fd Pump Trip w/Rod Speed Control Program Failure to 8 Steps Per Minute 6

M ALL 24 MSL Break In Containment, 23 MSlV and 24 MSlV Fail to Close MS0088D MS0092G MS0092H AFOI 828 7

C CRSlPO 22 AFW Pump Override Protection Failure

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Phase B and Containment Spray Signas Fail to Automatically Actuate 9

RP0276A RP0276B RP0277A RP0277B C

CRS/PO I

(C)omponent, (M)ajor Page 1 of 12 NUREG-I 021, Draft Revision 9