Text

Draft - Outlines (Folder 2)
	ML101130328
Person / Time
Site:	Salem
Issue date:	03/29/2010
From:	; Public Service Enterprise Group
To:	David Silk; Operations Branch I
	Hansell S
Shared Package
ML092470038	List: IR 05000272/2010301; ML101130322; ML101130328; ML101130338; ML101130402; ML101520331; ML101520347; ML101520364; ML101520414; ML101880243; ML102520088; ML111730058;
References
	TAC U01764, 50-272/10-301, 50-311/10-301
	Download: ML101130328 (24)
	v • d • e

ES-4C'1 PWR Examination Outline Form ES-401-2 Facilit,l!:

Salem Printed: 01/17/2010 Date Of Exam 05/14/2010 RO KIA Category Points SRO-Only Points Tier Group K1 K2 K3 K4 lK5 K6 P.1 P\\2 A3 A4 G* Total P\\2 G*

Total

1.

1 0

0 0

3 3

6

Emergenc, 2

0 0

0 1

2 4

N/A N/A Abnormal I

Tier I

Plant Tota!s (I I 0 0

0 0

5 5

10 Evolutions I

1 0

0 0

(I 0

0 0

0 3

2 5

2.

2 0

0 0

2 I

3 I

Plant Tier

°i 0

Systems 5

3 8

0 0

Totals 1

2 3

4 1

2 3

4

3. Generic Knowledge And 0

7 Abilities Categories 0

0 0

0 2

2 I

2 Note

1.

Ensure that at least two topics from every applicable KJA 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 KJA 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 jor 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.

Systems/evolutions 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 systems/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for!;; uidance regarding the elimination of inappropriate KJA 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 Elvolution.

5.

Absent a plant-specific priority, only those KlAs having an importance rating (IR) of 2.5 or higher shail 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 KIA categories.

7.' The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable KiAs.

8.

On the following pages, enter the KIA numbers; a brief description of each topic, the topics' importance ratings (IRs) for the applicable license level, and the pOint totals (#) for each system anci category Enter the group and tier totals for each category in the table above; jf fuel handling equipment js sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column 1'.\\2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-onlyexams.

9.

For Tier 3, select topics from Section 2 of the KIA catalog, and enter the KIA numbers, descriptions, IRs, and pOint totals (#) on Form ES-401-3.

Limit SRO selections to KJAs that are linked to 10 CFR 55,43.

01/17/2010 10:04:13 am

.PWR SRO Lxamination Outline Printed: O1,'J 7:2010 Facility:

Salem ES - 401 Emergenc)' and Abnormal Plant Evolutions - Tier 1 I Group I Form ES-401-2 EiAPE # / Name / Safety Function Kl K2 K3 Al A2 G

KATopic Imp.

Points 000008 Pressurizer Vapor Space Accident I X 2.3.11-Ability to control radiation 4.3 1

3 releases.

000009 Small Break LOCA / 3 X

EA2.13 - Charging pump flow 3.6 1

I indication 00001 I Large Break LOCA / 3 X

EA2.02 Consequences to RHR ofnot 3.7*

1 I

resetting safety injection 000022 Loss ofRx Coolant Makeup;' 2 X

AA2.02 - Charging pump problems 3.7 1

000054 Loss of Main Feedwater / 4 X 2.4.46 - Ability to verifY that the alarms 4.2 I

are consistent with the plant conditions.

W/E12 - Steam Line Rupture - Excessive X 2.4.18 - Knowledge of the specific 4.0 I

Heat Transfer / 4 bases for EOPs.

KIA Category Totals:

0 0

3 3

Group Point Total:

6 01/17/2010 10:03:42 am

Printed: 01/17/2010 Facility:

Salem ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 I Group 2 Form ES-401-2 E!APE # / Name / Safet) Function KI K1 K3 Al A2 G

KA. Topic Imp.

Points 000001 Continuous Rod Withdrawal / 1 X

AA2.02 - Position of emergency 4.2 1

boration val ve 000076 High Reactor Coolant Activity 19 X 2.4.41-Knowledge ofthe emergency 4.6 1

action level thresholds and classifications.

W!E06 Inad. Core Cooling! 4 X

EA2.2 - Adherence to appropriate 4.1 1

procedures and operation within the limhations in the facility's license and amendments W/E14 Loss ofCTMT Integrity / 5 X 2.1.7 - Ability to evaluate plant 4.7 I

performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

KIA Category Totals:

0 0

0 I 0 2

2 Group Point Total:

4 01/17/2010 10:03:48 am

PWR SRO Examination Outline Printed:

0 L!J 7'2010 Facility:

Salem Plant Systems - Tier 2 I Group 1 Form ES-401-2 ES - 401 S)'s/Evo\\ # I Name Kl K2 K3 K4 K5 K6 A.l A2 A3 A4 G KA Topic Imp.

Points 006 Emergency Core Cooling X

A2.12 - Conditions 4.8 I

requiring actuation of ECCS 022 Containment Cooling X

A2.01-Fan motor 2.7 1

over-current 026 Containment Spray X 2.3.11 - Ability to control 4.3 I

radiation releases.

061 Auxiliary/Emergency X 2.4.20 - Knowledge of 4.3 1

Feedwater operational implications of EOP warnings, cautions. and notes.

)(

064 Emergency Diesel Generator A2.04 - Unloading prior to 3.0 1

securing an EDIG KIA Category Totals:

0 0

0 3

()

0 2

Group Point Total:

5 01/17/2010 10:03:54 am

P\\VR SRO Examination Outltine Printed:

01/1720 j ()

Facility:

Salem ES - 401

~

Plant Systems Tier 21 Group 2 Form ES-401-2 Sys/Evol # I Name Kl K2 K3 K4 K5 K6 AI A2 A3 A4 G KA Topic Imp.

Points 016 Non-nuclear Instmmentation 033 Spent Fuel Pool Cooling X

X A2.02 - Loss of power supply A2.03 - Abnormal spent fuel pool water level or loss of water level

~ 'J*

3.5 I

]

07J Waste Gas Dispm.al X 2.2.18 - Knowledge ofthe process for managing maintenance activities 3.9

]

during shutdo'Wll operations, such as risk assessments, work prioritization, etc.

KIA Category Totals:

0 0

0 2

0 0

1 Group Point Total:

3 01/17/2010 10:04:01 am

Genernc Know]edge and A bilities Outline (Ticr 3)

P\\VR SRO Examination Outline Printed: 0 I 117/2010 Facility:

Salem Qeneric Cate~ory KA Topic Conduct of Operations 2.].20 Ability to interpret and execute procedure steps.

4.6 1

2.1.25 Ability to interpret reference materials, such as 4.2 1

graphs. curves. tables, etc.

Category Total:

2.

Equipment Control 2.2.1 Ability to perform pf<;~-startup procedures for the 4.4 I

facility. including operating those controls associated with plant equipment that could affect reactivity.

2.2.25 Knowledge of the bases in Technical 4.2

]

Specifications for limiting conditions for operations and safety limits.

Category Total:

2 Radiation Control I 2.3.4 Knowledge of radiation exposure limits under 3.7 1

nonnal or emergency conditions.

I Category Total:

1 Emergency PI'oc(~dures/Plan 2.4.27 Knowledge of "fire m the plant" procedure.

3.9 1

2.4.49 Ability to perform without reference to 4.4 I

procedures those actions that require immediate operation of system components and controls.

I Category Total:

2 Generic Total:

7 01/17/2010 10:04:07 am

4 ES-4J1 PWR Exammatlon Outline Form ES-401-2 Facilit:C Salem Printed: 01/17/2010 Date Of Exam:

05/14/20'10 RO KIA Category Points SRO-Only Points Tier Group K1 K2 K3 K4 IK5 IK6 A1 A2 A:3 A4 G* Total A2 G*

Total

1.

1

~

J 3

3 I,., !..,

18 0

0 0

Emergency 2

Abnormal Tier Plant Evolutions Totals 2

5 5

5 N/A ffi 4

5 I

I N/A 0

,)

9 27 0

(I 0

0 0

0 2,

Plant 1

2 3

I 2

I I

.., I 3 I I I

3 I

I !

3 I !

.)

I I

~

0 J

()

28 10 0

0 I 0 0

0 0

0 Systems Tier Totals 4

3 I

I 4

I I

l 4

4

.)

4 I I

4 4

2 38 0

0 0

3. Generic Knowledge And Abilities Categories 1

>J 2

3 3

.)

4 2

10 1

0 2

0 3

0 4

0 0

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 (Le., except for one category in Tier 3 of the SRO-only outline, the "Tier Totals" in each KIA 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 poinl total for each group and tier may deviate by ::1 from that specified in the table basl~d on NRC revi~iions. The final RO exam must lotal 75 points and the SRO-only exam must total 25 pOints, 3,

Syslemslevolutions 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 systems/evolutions :hat are not included on the outline should be added. Refer to Section D.1.b of ES-401 for £Iuidance regarding the elimination of inappropriate KIA statements, Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.

5.

Absent a plant*specific priority, only those KlAs having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for thE R.C and SRO-only portions, respectively.

6.

Select SRO topics for Tiers 1 and 2 from the shaded systems end KIA categories.

7.* The generic (G) KlI\\s in Tiers 1 and 2 shall be selected from Section 2 of the KIA Catalog. but the topics must be relevant to the applicable evolution or system.

I~efer to Section D.1.b of ES-401 for the applicable KlAs.

8.

On the following pages, enter the KiA numbers, a brief description of each topic, the topics' importance ratings (IRs) for the applicable license level, and the pOint totals (#) for each system and category. Ente~ the group and tier totals for each category in the table above; if fuel handling 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, Grou,:; 2 (Note #1 does not appl>/). Use duplicate pages for RO and SRO*onlyexams.

9.

For Tier 3, select topics from Section 2 of the KIA catalo~l, and enter the KIA numbers, descriptions, IRs, and pOint totals (#) on Form ES-401-3, Limit SRO selections to KlAs that are linked to 10CFR 55.43.

01/17/2010 9:58:58 am

PWR RO Ex.amin~ition Outline Prm(~d: 0 t / 17 i 20 !0 Form ES-401-2 Facility:

Salt'm ES - 401 Emergency and Abnormal Plant [yolutions Tier 1 i Group 1

[/APE # I Namt' / Safety Function K3 A1 A2

(;

KIIK2 I

000007 Reactor Trip - Stabilization -

Ix Recovery! I 000008 Pressurizer Vepor Space Accident!

3 000009 Small Break LOCA / 3 0000 II Large Break LOeA / 3 0000 1510000 17 RCP 'v1alfullctions '4 X

000022 Loss of Rx Coolant Makeup / ::

000025 Loss of RHR System; 4 000026 Loss of Component Cooling Water!

8 000029 A TWS / 1 000038 Steam Gen. Tube Rupture 3 000040 Steam Line Rupture - Excessive Heat Transfer: 4 000055 Station Blackout! 6 000056 Loss of OfC-site Power / 6 000065 Loss oflnstrument Air! 8 000077 Generator Voltage and Electric Grid Disturbances. 6 WiE04 LOeA Outside Containment / ::;

I I

!WlE05lnadequate heat Transfer Loss of ISecondar) Heat Sin\\. " 4 X

X X

'\\' "

X X

X I

X X

I X

i I

I I

X KA Topic EK::>.02 - Breakers. relays and disconnects AK I.0 I - Thermodynamics and flow characteristics of open or leaking valves EA 1. J4 - Secondary pressure contraI EAL]:; Safet) injection components AK*2.07 - RCP seals AA2.()2 - Charging pump problems AA 1.09 - LPI pump switches, anuneteL discharge pressure gauge, flow meter, and indicators 2.1.45 - Ability to idemifY and interpret diverse indications to validate the response of another indication.

2.4. J4 - Knowledge of general guidelines for EOP usage.

EK3.06 - Actions contained in EOP for ReS water inventory balance, S/G tube rupture. and plam shutdo"m procedures AK3.03 - Steam line non-return valves EA2.03 - Actions necessary to restore power AA2.35 - Reactor trip alaml AK3.04 - Cross-over to bach.'l1p air supplies AK 1.02 - Over-excitation EKI.2 NomlaL abnormal and emergency operating procedures associated with LOeA Outside Containment EK2.1 - Components. and functions of control and safety systems. including instrumentation. signals. interlocks.

failure modes. and automatic and manual features Imp.

2.6

'" ')

3.4 4.1

1.9

'" ')

.J.~

3.2 4.3 3.8 4.2 3.2*

3.9 I 4.1 3.0 3.3 3.5

~), '7!

Points 1

J J

I 1

I I

1 1

I 1 I 1

I 1

1 I

1 01/17/2010 9:58:20 am

P\\iTR RO Examination Outline Primed: 01 172010 Facility:

Salem ES - 401 Emergency and Abnormal Plant [\\'olutions - Tier I (Group I Form ES-401-2 I. EJAPE # I Name / Safety Function KJ K2 K3 Al A2 G

KA Topic Imp.

Points WlE II Loss of Emergency Coolant Recire. j X 1.4.5 - Knowledge ofthe organization 3.7 I

A ofthe operating procedures network for

'"t normal, abnormaL and emergency evolutions.

KJA Categof)' Totals:

3 3

Group Point Total:

18 01/17/2010 9:58:20 am 2

PV{R RO l~xaminntion Outline Printed: 0 I/] 7/2010 Facility:

Salem ES - 401 Emergenc)' and Abnormal Plant Eyolutions - Tier 1 j Group 2 Form ES-40l-2 EIAPE # ! Name I Sa fet~ Function Kl K2 K3 Al A2 G

).;.,\\ Topic limp.

Points 000001 Continuous Rod Withdrawal! I X

AK2.06 T-ave.lref. deviation meter 3.0*

J 000003 Dropped Control Rod / 1 X

AK3.04* Actions contained in EOP for 3.8*

I dropped control rod 000005 lnoperabJI~/Stllck Control Rod. / 1 X

AK3,02 Rod insertion limits 3.6 I

000032 Loss of Source Range Nl ! 7 X

AA2.03 - Expected values of source 2.8 I

range indication when high voltage is I

automatically removed 000036 Fuel Handling Accident / 8 X

AA2.0 I - ARM system indications 3.2 I

I 000068 Control Room Evac. i 8 X

AK2.01 - Auxiliary shutdown panel 3.9 1

layout 000076 High Reactor Coolant Activity! 9 X

AA 1.04 - F ailed fuel-monitoring 3.2 1

equipment W/E02 SI Termination / 3 X

EK 1,2 - Normal. abnormal and 3.4 1

emergency operating procedures associated with SI Termination W/E06 Inad. Core Cooling. 4 X

EK1.2 - NormaL abnormal and 3.5 1

emergency operating procedures I

associated with Degraded Core Cooling I

i I

KiA Categorl Totals:

2 2

2 1

2 0

Group Point Total:

9 01/17/2010 9:58:28 am

PWR RO Lxamination OutUn<'

Primed:

01 *17'20 I 0 FHdlit~:

Salem Plant Systems - Tier:! / Group I Form ES-401-2

[S - 401 I

1 I Sys/Evol # " Name I KJ Ie K3 )(4 K5 K6 AI !A:~ A3 A4 C I KA Topic Imp.

Points 003 Reactor Coolant Pump X

K5.05 - The dependency of 2.8*

1 ReS How rates upon the numher of operating RCPs 003 Reactor Coolant Pump X

K-l.04 - Adequate cooling of 2.8 I

RCP motor and seals 004 Chemical and VOlume Control X

A 1. 1 0 - Reactor power 3.7 1

005 Residual Heat Removal X

I K2J)] - RHR pumps 3.0 1

006 Emergency Core Cooling X

K4.16 - Interlocks between

~

).-'1 1

I 006 Emergency Core Cooling X

A4.0 I - Pumps 4.1 I

I RHR valves and ReS 007 Pressurizer Relief/Quench X

K3.0J - Containment 3.3 I

I Tank 008 Component Cooling Water X

A2.04 - PRMS alarm 3.3 1

icator for PORV 2.8*

1

() I 0 Pressurizer Pressure Control Ix I K1.03 - RCS 3.6 I

010 Pressurizer Pressure Control i

X IK2.03 - Ind I

posmon 1

012 Reactor Protection I

X A2.03 - Incorrect channel 3.4 1

bypassing 012 Reactor Protection X

KI.02 - 125V de system 3.4 I

013 Engineered Safety F earures X

K5.02 - Safety system logic 2.9 I

Actuation and reliabili!)

013 Engineered Safety Features X I K6.0 1 - Sensors and 2.7*

1 I

Actuation I

derecTOrs 022 Containment Co)ling X

A3.01 lnitiation of 4.1 1

~.I.

safeguards mode of I

Ioperation 026 Contammem Spray X

IA2.05 - Failure of chemical 1

addition tanks to inject 039 Main and Reheat Steam X

i K3.04 - MFV,i pumps 2.5*

1 059 Main Feedwater lX I

' K3.03 - S/Gs 3.5 1

06 J Auxi liary.IE:mergenc)

X 2.2.42 - Abili!)' to recognize 3.9 1

Feedwater system parameters that are entry-level conditions for Technical Specifications.

061 Auxiliary/Emergency X

K5.03 - Pump head effects 2.6 J

Feedwater when control valve is shut 062 AC Electncal Distribution X

A4.03 Synchroscope, 2.8 1

including an understanding of running and incoming voltages I

'\\

, 063 DC Electrical Distribution IAl.0 I - Bauery capacity as J

I I

xl iT i, affected bv dischare.e f

I Irate

I

'I "'7 I

I

_.1 064 Emergency Diesel Generator X

I I

I K6.07 - Air receivers I

I I

01/17/2010 9:58:36 am

P\\VR RO rxaminatior. Outline PriHtt?d' o]n 7'::.,010 F acilit)':

Salerr Plant S~'stems - Tier 2 i Group 2 Form ES-40J-2 ES - 401 I Sys/Evol # / Name Kl K2 1(3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp.

Points 001 Controi Rod Driv.:

X K2.0 1 - One-line diagram of 3.5 1

power supply to MIG sets 002 Reactor Coolant X

K3.03 - Containment 4.2 J

011 Pressurizer Level Control OJ 5 Nuclear Instrumentation 027 Containment Iodine Removal 028 Hydrogen Recombiner and Purge Control 033 Spent Fuel Pool Cooling 034 Fuel Handling Equipment 035 Steam Generator X

086 Fire Protection I

KIA CategorJ Totals:

J I

X Al.l1-Failure ofPZR level 3.4 1

instrument - low X

Al.06 - Fuel bumup 2.5*

1 X

A4.03 - CIRS fans

~ ~*

.J *.J I

X K5.03 - Sources of hydrogen 2.9 1

within containment X

A3.02 - Spent fuel leak or 2.9 I

rupture X

K6.02 - Radiation 2.6 1

monitoring systems Kl.I2 - RPS 3.7 1

X K 4.02 - Maintenance of fire 3.0 I

header pressure 1

I 1

1 1

1 t

1 0

Group Point Total:

10 01/17/2010 10:06:48 am

I GeneI'ic Knowledge and Abmtic:; Outline (Tier 3)

P\\\\'R RO Examination Outline Printed: 01/17/2010 FadIitv..

Salem Generic Cate~ory Conduct of Ollerations Equipment Control

'I Radiation Control Emergency ProcedureslPlan 2.1.1 2.1.18 2.2.39 2.2.43 I

2.3.4

'! ~ ~

...:.._'. J 2.3.14 2.4.12 2.4.46 Form ES-401-3 Knowledge of condu(:( of operations 3.8 I

requirements.

Ability to make accurate. clear. and concise logs, 3.6 I

records. status boards. and reports.

Category Total:

2 Ability to manipulate the console contTols as 4.6 I

required to operate the facility between shutdown and designated power levels.

Knowledge of less than or equal to one hour 3.9 I

Technical Specificanon action statements for systems.

Knowledge ofthe process used to track 3.0 1

inoperable alarms.

Categor) Total:

3 I

Knowledge ofradiation exposure limits under J"'!

I nonnal or emergency conditions.

I Ability to comply with radiation work permit 3.5 1

t requirements during normal or abnormal conditions.

Knowledge or radiation or contamination hazards 3.4 I

tila: may arise during non11a!. abnormaL or emergenc; conditions or activities.

Category Total:

3 Knowledge ofgeneral operating crew 4.0 1

responsibiliti,;:s during emergency operations.

Ability to verify that tile alarms are consistent 4.2 1

with the plan: conditions.

Category Total:

2 Generic TotaJ:

10 01/17/2010 9:58:51 am

I ES-401 ITier/Group I Randomly t Selected KIA rito 111 054 Gen 2.2.22 r --

-~-,80,

.2.4

-~-

003 Gen 2.1.6 r-------~

R021I 004 K5.37 R02/I

-~-

068 A3.0l R0211 076 K1.21 078 A3.0J

~.~~~/;-

2.3.15

-~-

f-----

r-----

-~-

I-----~~--

-~-

r-----

Record of Reiected KlAs Form ES-401-4 Reason for Rejection Generic KIA for LCO status is poor match for Loss of Main Feedwater category.

~

A~utomatically/randomly reQlaced with 057 2.4.6 There is no difference between the units for DC power systems. Automatically/randomly replaced with 029 2.4.14 Not an RO function to manage control room crew. Automatically/randomly replaced with 010 Kl.03 Concept of ion exchangerlboron concentration effect sampled on CERT exam.

Automatically/randomly reQlaced with 061 Gen 2.2.42 Liquid radwaste evaporators no longer used at Salem. Automatically/randomly replaced with 033 A3.02 Salem does not have an auxiliary backup SW system. Automatically/randomly replaced with 076 A4.02 Sampled on CERT exam. Automatically/randomly replaced with 076 K1.20

~

SamQled on CERT exam. Automatically/randomly reQlaced with Generic 2.4.27

~

ES-401, Page 27 of 33

ES-301 Ad ministrative Outline Form ES-30 1-1 Facility:

_~A_L_E:;.;;;*M~_________~ __~ ___

Date of Examination:

05/10/10 Examination Level:

RO SRO Operating Test Number:

08-01 NRC Describe activity to be performed Perform a RCS Manual Leakrate calculation 2.1.18 Ability to make accurate, clear, and concise logs, records, status boards, and reports. RO-3.6 Calculate Quadrant Power Tilt Ratio 2.1.43 Ability to use procedures to determine the effects on reactivity of plant I

changes, such as reactor coolant temperature, secondary plant, fuel depletion, etc. I i R04.1 Perform a peer check of an EGC using Nuclear Design Data.

2.2.1 Ability to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity. RO 4.5 Perform Stay Time calculation for Emergency condition.

[adiatiOn Controlt, 2.3.4 Knowledge of radiation expost.Jre limits under normal and emergency conditions. RO-3.2 I

I I

Emergency Plan I

N/A N/A i

I I NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the I

administrative topics, when 5 are required.

Type Codes and Criteria (C)ontrol Room, (S)imulator, or (D)irect from bank, (3 for ROs; 4 for

& RO retakes)

(N)ew or (M)odified from bank (1)

(P)revious 2 exams (1; randomly selected)

ES-301 Administrative Outline Form ES-301-1 Facility:

SALEM Date of Examination:

05/10/10 Examination Level:

RO

SRO Operating Test Number:

08-01 NRC i

I Adm inistrative Describe activity to be performed Type I

Topic (See Note) I Code*

=

Conduct of Operate the Chilled Water System (Identify and Isolate Non-Essential Heat Loads)

R,D Operations 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.

I Evaluate a shift staffing situation and take corrective action lAW administrative Conduct of procedures R,M Operations 2.1.5 Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.

i Walkdown control console and determine most limiting LCO for current Mode of operation.

Equipment Control S,N

2.2.42 Ability to recognize system parameters that are entry level conditions for I

Technical Specifications SRO 4.6 I

I Review Radioactive Liquid Waste Release preparations and select release path Radiation Control R,N 2.3.6 Ability to approve release permits SRO-3.B I

Classify Emergency! Non-Emergency Events, and complete the ICMF.

Emergency Plan S,M,P i

2.4.29 Knowledge of the Emergency Plan SRO 4.4 II l

Ii 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 Systemslln-Plant System Outline Form ES-301-2 Facility:

SALEM Date of Examination:

05/10/10 Operating Test No.:

08-01 NRC Exam Level:

SRO-I SRO-U Control Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U, including 1 ESF)

System I JPM Title Type Code*

Safety Function

a.

Respond to successive dropped control rods at power (003 AA2.03 RO-3.6 SRO-3.8)

D,S,A 1

b.

Perform EOP-TRIP-1 Immediate Actions and initiate Safety Injection based on board indication after auto SI fails to actuate (Normal Rx trip from 20%

power entering an outage and fail steam dumps open with no first out of SI)

A,EN,N 2

(EPE 007 EA2.02 RO-4.3 SRO-4.6)

c.

Respond to an unwarranted PZR Overpressure Protection System (POPS) actuation. (010 A4.03 RO-4.0 SRO-3.8)

A,N, L 3

d.

Respond to a Shutdown LOCA (2.4.9 RO-3.8 SRO-.:1 !)

D,S,L 4 (pri)

e.

Perform stroke time testing of 21 MS 167 (Main Steam line Isolation Valve)

(039 A4.01 RO-2.9 SRO-2.8)

D,EN,S 4 (sec)

f.

Perform a CFCU Operability and Service Water Flow Verification (022 A4.01 RO-3.6 SRO-3.6)

D,S,P 5

I

g.

Start an EDG from the control room and energize an isolated vital bus (064 A4.01 RO-4.0 SRO-4.3)

L,N,S 6

Failure of Permissive P-6 to block Source Range Hi Flux trip during Rx S/U (012 A4.03 RO-3.6 SRO-3.6)

A, D, L, S 7

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

i.

Reset TDAFW pump steam inlet trip valve 2MS52 (APE 068 AA1.02 RO-4.3 SRO-4.5)

D,E,R 4 (sec)

j.

Start the SSO Air Compressor (2.1.23 RO-4.3 SRO-4.4)

D,E 8

k.

Commence a liquid waste release, and respond to high activity during the release (2.3.11 RO-3.8 SRO-4.3)

D,R,A,P 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, SRO-U (A)lternate path 4-6 / 4-6 I 2-3 (C)ontrol room (D)irect from bank

~9 I ~8 1~4 (E)mergencyor abnormal in-plant

.?:1 I.?:1/.?:1 (EN)gineered safety feature

- I - I.?: 1 (control room system)

(L)ow-Power I Shutdown

.?:1 I.?:1 I.?:1 (N)ewor (M)odified from bank including 1 (A)

.?:2 /.?:2/.?:1 (P)revious 2 exams

~3 I ~3 1 ~2 (randomly selected)

(R)CA

.?:1

/

.?: 11.?: 1 (S)imulator

ES-301 Control Room Systems/In-Plant System Outline Form ES-301-2

--~----------------------------------

Facility:

SALEM Date of Examination:

05/10/10 Operating Test No.:

08-01 NRC Exam Level:

SRO-I SRO-U Control Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U, including 1 ESF)

System I JPM Title Type Code*

Safety Function

a.

Respond to successive dropped control rods at power (003 AA2.03 RO-3.6 SRO-3.8)

D,S,A 1

b.

Calculate actual RCS subcooling during performance of LOCA-1(Static)

(2.1.45 RO-4.3 SRO-4.3)

A,M,L 2

c.

Perform EOP-TRIP-1 Immediate Actions and initiate Safety Injection based on board indication after auto SI fails to actuate (Normal Rx trip from 20%

I power entering an outage and fail steam dumps open with no first out of SI)

A,EN,N 3

(EPE 007 EA2.02 R0-4.3 SRO-4.6)

d.

Respond to a Shutdown LOCA (2.4.9 RO-3.8

'RO-4.2)

I D,S,L I

4 (pri)

e.

Perform stroke time testing of 21 MS167 (Main Steamline Isolation Valve)

(039 A4.01 RO-2.9 SRO-2.8)

D,EN,S 4 (sec)

f.

Perform a CFCU Operability and Service Water Flow Verification (022 A4.01 RO-3.6 SRO-3.6)

D,S,P 5

g.

Start an EDG from the control room and energize an isolated vital bus (064 A4.01 RO-4.0 SRO-4.3)

L,N,S I

6 II

h.

Failure of Permissive P-6 to block Source Range Hi Flux trip during Rx S/U (012 A4.03 RO-3.6 SRO-3.6)

A, D, L, S 7

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

i.

Reset TDAFW pump steam inlet trip valve 2MS52 (APE 068 AA1.02 RO-4.3 k5)

D, R

4 (sec)

j.

Start the SBO Air Compressor (2.1.2~1 RO-4.3 SRO-4.4)

D,E 8

k.

Commence a liquid waste release, and respond to high activity during the release (2.3.11 RO-3.8 SRO-4.3)

D,R,A I

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-II SRO-U (A)lternate path 4-6 I 4-6 I 2-3 (C)ontrol room (D)irect from bank

~ 9 I <8 I ~ 4 (E)mergency or abnormal in-plant

> 1 I

~ 1 / ~ 1 (EN)gineered safety feature

- I -

I ~ 1 (control room system)

(L)ow-Power I Shutdown

~1 I ~11 ~1 (N)ewor (M)odified from bank including 1 (A)

~2 I

> 2 / > 1 (P)revious 2 exams

<3/~3 1~2 (randomly selected)

(R)CA

> 1 I

> 1/ ~ 1 (S)imulator Rev

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

SALEM Date of Examination:

05/10/10 Operating Test No.:

08-01 NRC Exam Level: RO SRO-I Control Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U, including 1 ESF)

Safety Function System / JPM Title I Type Code*

a.

c.-tC I

,K:'

.i?

Perform EOP-TRIP-1 Immediate Actions and initiate Safety Injection based on board indication after auto SI fails to actuate (Normal Rx trip from 20%

power entering an outage and fail steam dumps open with no first out of SI) I A,EN,N

>-2 (EPE 007 EA2.02 R0-4.3 SRO-4.6)

I

d.

Respond to a Shutdown LOCA I

(2.4.9 RO-3.8 SRO-4.2)

D,S,L I

4 (pri)

I

e.

I

f.

g.

I

h. Failure of Permissive P-6 to block Source Range Hi Flux trip during Rx S/U (012 A4.03 RO-3.6 SR.o-3.6)

I A,D,L,S I 7

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

I I

i.

j.

Start the SSO Air Compressor (2.1.23 RO-4.3 SRO-4.4)

D,E 8

k. Commence a liquid waste release, and respond to high activity during the release D,R,A 9

(2.3.11 RO-3.B SRO-4.3~

I @ 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 contro' room.

I I!

Type Codes:

I Criteria for RO I SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C}ontrol room (D)irect from bank

< 9 / :s8 /:s 4 (E)mergency or abnormal in-plant

> 1 I

> 1 / '?. 1 (EN)gineered safety feature

- I - I '?. 1 (control room system)

(L)ow-Power / Shutdown

'?.1 I '?.1 I '?.1 (N)ewor (M)odified from bank including 1 (A)

'?. 2 /

'?. 2 I> 1 (P)revious 2 exams

,::::3/<3/<2 (randomly selected)

(R)CA

> 1 I

'?. 1 / '?. 1 (S)imulator I

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

SALEM Date of Examination:

05110110 Operating Test No.:

08-01 NRC Exam Level : RO SRO-U

! Control Room Systems@ (8 for RO; 7 for SRO-I; 2 or 3 for SRO-U, including 1 ESF)

System 1JPM Title

a.

Respond to successive dropped control rods at power 1*~~_(cO~03~Arl;A;2~.0~3~R~O~-3c*6iiS[R~O~-m3*m8)~~~~~~~DC~~~~-T--~V---r-------~I I 6 A:f.

Calm:rlate actual ~cs sabcoollng elurlng perieFmaAOG QU.QCA::1(Stat~

1f---__--;-:-(6~.4J:j RQA 3 SRO~ {see r{O '30{-2. 1'f"1 '~-------+---'------I--------il

,Y Perform EOP-TRIP-1 Immediate Actions and initiate Safety Injection based on board indication after auto SI fails to actuate (Normal Rx trip from 20%

.b power entering an outage and fail steam dumps open with no first out of SI)

(EPE 007 EA2.02 RO-4.3 SR0-4.6)

d.

Respond to a Shutdown LOCA (2.4.9 RO-3.8 SR0-4.2)

e.

f.

Perform a CFCU Operability and Service Water Flow Verification (022 A4.01 RO-3.6 SRO-3.6)

I D,S,P 5

g.

Start an EDG from the control room and energize an isolated vital bus (064 A4.01 RO-4.0 SR0-4.3)

L,N,S 6

!i (012 A4.03 RO-3.6 SRO-3.6)

II

h.

Failure of Permissive P-6 to block Source Range Hi Flux trip during Rx Stu I

A, D, L, S 7

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

1*

i.

R_~TDAFW~mp-s-~-~-m-in-le-t-tr-ip-v-a-lv-e-2-M-S-~-----------~----~-----~

(APE 068 AA1.02 RO-4.3 SRO-4.5)

D, E, R 4 (sec)

j.

Start the SBO Air Compressor (2.1.23 RO-4.3 SRO-4.4)

D,E 8

j/------::-

k. Commence a liquid waste release, and respond to high activity during the release D, R,A 9

(2.3.11 RO-3.8 SRO-4.3)

@ 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.

T pe Codes:

Criteria for RO I SRO-It SRO-U (A)lternate path 4-6 I 4-6 / 2-3 (C)ontrol room (D)irect from bank

~9 I ~8 /<4 (E)mergenGy or abnormal in-plant

~1 /

~1 />1 (EN)gineered safety feature I -

I ~ 1 (control room system)

(L)ow-Power I Shutdown I ~1 /

~1 (N)ewor (M)odified from bank including 1 (A)

>2 /

>2/~1 (P)revious 2 exams

~ 3 I < 3 I ~ 2 (randomly selected)

{R)CA

~ 1 I

~ 11 > 1 Simulator

Appendix 0 Scenario Outline Form ES-D-1 Facility:

SALEM 1 & 2 Scenario No.:

ESG-1 Op-Test No.: 08-01 NRC Examiners:

Operators:

-~..

Initial Conditions: 90% power, MOl. 23 SW pp CIT for strainer repair.

Turnover: Raise Rx power to 100%

Event Malf. No.

Event Event Type*

No.

Description N ~ (i(J{"O 1

Raise power R.- ((C )d::t t

I 2

Tavg channel fails high (Tech Specs)

CRS/RO C

4 SW Bay leak, leak isolation requires isolating all #4 Bay 3

CRS/PO SW pps, with 23SW pp CIT (TS 3.0.3 entry)

W&

4 RCP #1 seal degradation leading to failure CRS/RO C

2A 4KV vital bus de-energizes on Rx trip, EDG output bkr 5

CRS/PO does not shut, no SW pumps are running I

,Q"'M 6

SBLOCA ALL I

7 C

SEC controlled equipment fails to start (22 SI pp)

ALL 8

C Loss of Off-Site power after SI reset ALL

(N)ormal,

{R)eactlVlty, (I)nstrument, (C)omponent, (M)aJor Appendix D, Page 38 of 39

Appendix D Scenario Outline Form ES-D-1 Facility: _~AlEM 1 _£2~__

Scenario No.: ESG-2 Op-Test No: 08-01 NRC Examiners:

Operators:

--.-~~.--~-----

-~-.

Initial Conditions: 100% power, BOl, PZR level CH III selected fa control due to CH I indication problem. Rod Control in manual due to PT-505 channel calibration in progress. 21 Heater Drain Tank pump OIS due to oil leak. 22 Condensate pump has elevated vibration.

Turnover: Reduce power at 30% per hour to 79% in preparation for removing 22 Condensate Pump from service.

Event Malf. No.

Event Event Type*

No.

Description R- ~D 1

N- ~5/~

Perform power reduction

~

C 2

CFCU trip (Tech Specs)

CRS I

3 VCT level ch fails high CRS/RO I

C 4

Operating charging pump cavitation (Tech Specs)

CRS/RO M

5 22 Cond pump trip, loss of SGFP suction pressure All C

6 MainTurbine fails to trip initially, MSLI successful I

RO 21 AFW pump will not start, 22 AFW pp pressure override 7

C defeat failure, 23 AFW pp trips. FRHS with condensate pump CRS/PO I

recovery.

I Ii

'" (N)ormal, (R)eactlvlty, (I)nstrument, (C)omponent, (M)aJor Appendix D, Page 38 of 39

Appendix 0 Scenario Outline Form ES-0-1 Facility: __SALEM 1 &2~__

Scenario No.:

ESG-3 Op-Test No.: 08-01 NRC Examiners:

Operators:

~.

Initial Conditions: 4.8% power, MOL, Main Turbine is on the Turning Gear. Rx startup by Control Rods was performed. 21 AFW pp is CIT. 2PR'1 PZR PORV is leaking, 2PR6 is shut with power applied to comply with Tech Specs.

Turnover: Raise Rx power to 17% over the next 30 minutes in preparation for rolling the Main Turbine.

Reactivity plan developed by Rx Engineering directs raising power with control rods only Event Malf. No.

Event Event Type*

No.

Description N~'-~

~ Ac 1

/'.,-

AU..

Raise Rx power 2

I PZR pressure instrument fails high (Tech Spec)

CRS/RO 3

C ECCS Accumulator low pressure (Tech Specs)

CRS/PO 4

M Rapid degradation of condenser vacuum/loss of steam ALL dumps with power above capacity of SG Atmospheric reliefs.

C'815C;t Rod Control failure results in no inward rod movement or Rx

~ '(0 trip available - A TWT I FRSM i

C 6

Rapid Borate Stop valve fails to open CRS/RO I

C 7

PZR PORV fails open.

CRS/RO

(N)ormal, (R)eactlvity, (I)nstrument, (C)omponent, (M)aJor Appendix D, Page 38 of 39

~~~~~

1_~ft_._,_,____

Appendix D Scenario Outline Form ES-D-1 Facility: _ SALEM 1 &2 Scenario No_: ESG-4 (Spare)

Op-Test No_: 08-01 NRC Examiners:

Operatclrs:

Initial Conditions: Rx power is 67%, BOl. Power is reduced clue to 21 MS29 Main Turbine Governor Valve failed shut 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> ago. 2PS1 is leaking and its manual isolation valve is shut. 2PR1 is leaking and its block valve is shut with power applied Turnover:

Maintain current power while 21 MS29 failure is investigaed.

Event Malf. No.

Event Event Type*

No.

Description I

1 Controlling PZR level channel fails low (Tech Specs)

ALL

.2'3 C

2nd turbine governor valve (23MS29) fails closed PO N

3 Power reduction to <30% power (Tech Spec-AFD)

ALL C

4 f-o Steam leak downstream of MSIVs

~

M Steam rupture with failed open MSIV 5

ALL C

6 SGTR following affected SG de-pressurzation CRS/PO i

(N)ormal, (R)eactlvlty, (I)nstrument, (C)omponent, (M)aJor Appendix 0, Page 38 of 39

v t e Letter Sequence Draft Other
TAC:U01764, (Open)
Initiation Acceptance... Administration Questions Answers Results Approval... Other: ML101520347, ML101880243, ML102520088, ML111730058
MONTHYEAR2010-04-20 [Table View]

ML101130328

Text

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