Text

Final Operation Exam (Sections a, B, and C) (Folder 3)
	ML113340065
Person / Time
Site:	Salem
Issue date:	09/09/2011
From:	; Public Service Enterprise Group
To:	; Operations Branch I
	JACKSON D RGN-I/DRS/OB/610-337-5306
Shared Package
ML110030673	List: IR 05000272/2011301; ML111610244; ML112590037; ML112650617; ML113330710; ML113330734; ML113330777; ML113330798; ML113330805; ML113340036; ML113340040; ML113340044; ML113340065; ML113500280; ML12167A076;
References
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OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Admin TASK: Respond to a Void in the Reactor Vessel TASK NUMBER: N1150410501 JPM NUMBER: 09-01 NRC RO Admin A 1-1 ALTERNATE PATH: D ~ANUMBER: _____E_P_E_1_0_E_A_1_.1____~

IMPORTANCE FACTOR: 3.8 3.6 APPLICABILITY: RO SRO EOD ROCK] STAD SROCK]

EVALUATION SETTING/METHOD: Classroom

REFERENCES:

2-FRCI-3 Rev. 25 Response to Void in Reactor Vessel TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 8 min TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: NfA

! Developed By: G Gauding Date: 07-20-11 Instructor Validated By: J Pierce, Jr Date: 07-28-11 SME or Instructor J~;~

Approved By: Date: ,:£_L- ,I Approved By: ~.~ Date: gil/'I operationTIepres~

ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION TIME:

. PERFORMED BY:

GRADE: D SAT D UNSAT

. REASON, IF UNSATISFACTORY:

I EVALUATOR 1S SIGNATURE: DATE:

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM: Admin TASK: Respond to a Void in the Reactor Vessel TASK NUMBER: N1150410501 SIMULATOR SETUP INITIAL CONDITIONS:

Unit 2 is performing 2-EOP-FRCI-3, Response to Void in Reactor Vessel, due to an unexpected void formation in the Rx Vessel following a LOCA.

- Containment temperature is 220 degrees F.

- Containment hydrogen concentration is 1.0%.

- RCS pressure is 800 psig.

INITIATING CUE:

The CRS directs you to calculate the maximum Rx Vessel Head venting time using Attachment 1 of FRCI-3.

Successful Completion Criteria:

1. All critical steps completed.

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made (and NRC concurrence is obtained).

Task Standard for Successful Completion:

1. Calculate maximum head vent time to be 20-24 minutes.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM NAME: __________________

JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM Admin TASK: Respond to a Void in the Reactor Vessel STEP COMMENTS STEP (*Denotes a Critical Step) EVAL (Required for

NO. STANDARD S/U UNSAT Once operator has read Initial Condition and Initiating Cue, provide them with FRCI-3 Attachment 1 and Figure 1.

Att. 1 --Record the following data: Operator records the following data given Step 1 in Initial Conditions:

1.1 Containment temperature: 220 1.2 Containment hydrogen concentration (H): 1.0 1.3 RCS pressure: 800

Att.1 Determine containment air volume at Step 2 standard temperature and pressure Operator calculates containment 2.1 Calculate containment absolute absolute temperature. 220 + 460= 680 temperature, Tabs Tabs =Containment temperature (oF)

+460=

Operator calculates containment air 2.2 Calculate containment air volume volume at STP. 1.28E09/680=1.88E6 (V) at STP: (actual value of 1.882353E6 will be used V=1.28E09/Tabs= for bounding number, and can be used by operator)

~

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OPERATOR TRAINING PROGRAM NAME: ___________________

JOB PERFORMANCE MEASURE DATE: ___________________

SYSTEM Admin TASK: Respond to a Void in the Reactor Vessel STEP COMMENTS STEP (*Denotes a Critical Step) EVAL (Required for

NO. STANDARD S/U UNSAT

AU. 1 Determine maximum hydrogen vent Step 3 volume 3.1 Record containment hydrogen Operator records 1.0 concentration (from Step 1.2) 3.2 Record containment air volume at Operator records 1.88E6 (or STP (from Step 2.2) 1.882353E6) 3.3 Calculate maximum vent volume (M) Operator calculates maximum vent volume M= (3.0%-H) x V 100% M= {3.0%-1.0%} x 1.88E6{or 1.882353E6}

100%

M= 37600 (or 37647)

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OPERATOR TRAINING PROGRAM NAME: __________________

JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM Admin TASK: Respond to a Void in the Reactor Vessel STEP COMMENTS STEP (*Denotes a Critical Step) EVAL (Required for

NO. STANDARD S/U UNSAT

AU. 1 Determine maximum vent time Step 4 4.1 Record RCS pressure (from Step Operator records 800 1.3)

Operator records 37600 (or 37647) 4.2 Record calculated maximum vent volume (from Step 3.3) Operator records 1600-1800 (allowed extrapolation) 4.3 Record hydrogen vent flow rate (from Figure 1) Operator calculates maximum vent time Tv= 37600/1600 4.4 Calculate maximum vent time (Tv) Tv= 23.5 minutes Tv=M/F Note: Using the 37647 (M) value and the 1600-1800 allowed extrapolation from Figure 1, the bounding correct answers for Tv are 20.89 minutes and 23.53 minutes.

The allowable answer for this JPM is 20-24 minutes.

Once operator has provided maximum head vent time, state JPM is complete.

Page 5 of 7 PSEG Restricted - Possession Requires Specific Permission Nuclear Training

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 and 11 below.

4-- 1. Task description and number, JPM description and number are identified.

~ 2. Knowledge and Abilities (KIA) references are included.

l' 3. Performance location specified. (in-plant, control room, or simulator)

J 4. Initial setup conditions are identified.

r 5. Initiating and terminating Cues are properly identified.

_-.:./1/;c...-_ 6. Task standards identified and verified by SME review.

/

~

7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

_--i(f/,-_ 8. Verify the procedure referenced by this JPM m~~h.?s the most current revision of I that procedure: Procedure Rev. ). 5 Date '-lAY'jgi

_""'"y'---_ 9. Pilot test the JPM:

/ a. verify Cues both verbal and visual are free of conflict, and

b. ensure performance time is accurate.

_-FV__ 10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

I

_,I-fi'-V__ 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

SME/lnstructor: ,17 b::s-= Date: _?-f-?_~2._9+A_'_,_ _

SME/lnstructor:_ _ _ _ _ _ _ _ _ _ _ __ Date: _ _ _ _ __

SMEllnstructor:_ _ _ _ _ _ _ _ _ _ _ __ Date: - - - - -

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 6 of 7

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

Unit 2 is performing 2-EOP-FRCI-3, Response to Void in Reactor Vessel, due to an unexpected void formation in the Rx Vessel following a LOCA.

- Containment temperature is 220 degrees F.

- Containment hydrogen concentration is 1.0%.

- RCS pressure is 800 psig.

INITIATING CUE:

The CRS directs you to calculate the maximum Rx Vessel Head venting time using Attachment 1 of FRCI-3.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 7 of 7

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Admin TASK: TCAF a Loss of Spent Fuel Pool Cooling (Calculate the time at which SFP temperature will exceed Design Bases)

TASK NUMBER: N1140900401 JPM NUMBER: 09-01 NRC RO Admin A 1-2 ALTERNATE PATH: D KIA NUMBER: 2.4.47

~

I IMPORTANCE FACTOR: 3.8 3.6!

APPLICABILITY: RO SRO EOO ROm STAO SROm EVALUATION SETTING/METHOD: Classroom S1.0P-AB.SF-0001, Rev. 7 Loss of Spent Fuel Pool Cooling S1.0P-AR.ZZ-0003, Rev. 17, Overhead Annunciator Window C

REFERENCES:

Salem UFSAR Section 9.1.3 Spent Fuel Pool Cooling System (pg 9.1-13)

TOOLS AND EQUIPMENT: Calculator VALIDATED JPM COMPLETION TIME: 10 min TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 07*20*11 Instructor Validated By: J Pierce, Jr Date: 07*28*11 SME or Instructor

/~nt Date: ~-2.--

I t Approved By:

Approved By:

opli~ Date:

~t!J ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION TIME:

PERFORMED BY:

GRADE: D SAT D UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM: Admin TASK: TCAF a Loss of Spent Fuel Pool Cooling (Calculate the time at which SFP temperature will exceed Design Bases)

TASK NUMBER: N114090040 1 SIMULATOR SETUP INITIAL CONDITIONS:

Salem Unit 1 is defueled during a regular refueling outage.

Spent Fuel Pool temperature is stable at 121°F.

On November 30 th at 0100, the operating Spent Fuel Pool Cooling pump trips, and cannot be re-started.

The standby Spent Fuel Pool Cooling pump cannot be started.

At0115, OHAC-19, SFPTEMP HI alarms.

INITIATING CUE:

At 0200, the CRS directs you to calculate the time of day at which the Unit 1 Spent Fuel Pool will reach its Design Temperature, lAW S1.0P-AB.SF-0001, if no operator actions are taken.

Assume the heat-up rate has been linear from 0100 to 0200.

Successful Completion Criteria:

1. All critical steps completed.

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Task Standard for Successful Completion:

1. Calculates that SFP temp will exceed Design Temp (180) @ 0436-0442. See bases for range on page 5.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM NAME: __________________

JOB PERFORMANCE MEASURE DATE:

SYSTEM Admin TASK: TCAF a Loss of Spent Fuel Pool Cooling (Calculate the time at which SFP temperature wi" exceed Design Bases)

STEP COMMENTS STEP NO. (*Denotes a Critical Step) EVAL {Required for

STANDARD S/U UNSAT Provide candidate with blank copy of IF asked, provide a copy of S2.0P S1.0P-AB.SF-0001, Loss of Spent Fuel AR.ZZ-0003, Overhead Annunciator Pool Cooling. WindowC.

Cue: IF asked by candidate if the OHA C-19 has been adjusted to a temporary setpoint, THEN state" OHA C-19 has not been adjusted to a temporary setpoint.

-~~-~ -~~

AB.SF-1 INITIATE Attachment 5, Spent Fuel Refers to S1.0P-AB.SF-0001, Loss of Step 3.3 Pool Heatup Trending, for Unit 1 Spent Spent Fuel Pool Cooling, Attachment 5,

.fuel Pool, as directed by the CRS. Spent Fuel Pool Heatup Trending .

-~

~-~-

.~~

AB.SF-1 Enters 121 as Initial SFP TEMP (A) on Att.5 Attachment 5.

~

AB.SF-1 Refers to S1.0P-AR.ZZ-0003, Overhead Att.5 Annunciator Window C, and determines the alarm setpoint is 125°F.

~_~ L~~~ ~_~ ~-~

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OPERATOR TRAINING PROGRAM NAME: __________________

JOB PERFORMANCE MEASURE DATE: ___________________

SYSTEM Admin TASK: TCAF a Loss of Spent Fuel Pool Cooling (Calculate the time at which SFP temperature will exceed Design Bases)

STEP COMMENTS STEP NO. (*Denotes a Critical Step) EVAL (Required for

STANDARD S/U UNSAT

AB.SF-1 Determines the SFP TEMP (A) at "+1 AU. 5 HR" is 137 based on the temperature rise from 0100 (121°) to the alarm at0115 (125°) over 15 minutes, and multiplies by 4 to get heatup for the hour of 16°.

-~

AB.SF-1 Determines the 11TEMP/HR (B) at +1 HR AU. 5 is 16.

--~ - ~-~

AB.SF-1 Performs calculation to determine the Att. 5 time to 180°F:

(180-A)/B

=

(180-137)/16 2.6875 HRS L_ ~-

Note: 2.6875 hrs= 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , 41.25 min.

Page 4 of 7 PSEG Restricted Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM NAME: ___________________

JOB PERFORMANCE MEASURE DATE: ___________________

SYSTEM Admin TASK: TCAF a Loss of Spent Fuel Pool Cooling (Calculate the time at which SFP temperature will exceed Design Bases)

STEP COMMENTS STEP NO. (*Denotes a Critical Step) EVAL (Required for

STANDARD S/U UNSAT Calculates the time of day at which SFP temp will reach Design Temp:

Time of calculation: 0200 Time to reach 180: 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , 41.25 min 04:41:15 Determination to the second is not required. The Task Standard states the band is 0436 (if rounded down to 2.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and 0442 (if round up to 2.7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months ) r---..

Terminate the JPM when all paperwork has been returned to the evaluator.

Page 5 of 7 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist shoiJld be performed upon initial validation, Prior to JPM usage, revalidate JPM using steps 8 and 11 below,

~ 1. Task description and number, JPM description and number are identified,

~ 2, Knowledge and Abilities (KIA) references are included, 9L' 3. Performance location specified. (in-plant, control room, or simulator)

_ ~L 4. Initial setup conditions are identified.

__!}~V"'-_ 5, Initiating and terminating Cues are properly identified,

--.:.;,f'-V- 6. Task standards identified and verified by SME review.

--}/-F----- 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*),

--4~- 8. Verify the procedure referenced by this JPM matches the most current revision of

/' that procedure: Procedure Rev. _7_ _ Date _7:.<../.;,..;z..'fr+A,;,:...'I_ __

_ ...!:/'---_ 9. Pilot test the JPM:

a. verify Cues both verbal and visual are free of conflict, and

b. ensure performance time is accurate.

~ 10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

____ 11. When JPM is revalidated, SME or Instructor sign and date ...IPM cover page.

SMEIlnstructor: ~

)'

SMEflnstructor: Date:

SME/lnstructor:_ _ _ _ _ _ _ _ _ _ _ __ Date: _______

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OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

Salem Unit 1 is defueled during a regular refueling outage.

Spent Fuel Pool temperature is stable at 121°F.

On November 30 th at 0100, the operating Spent Fuel Pool Cooling pump trips, and cannot be re-started.

The standby Spent Fuel Pool Cooling pump cannot be started.

At 0115, aHA C-19, SFP TEMP HI alarms.

INITIATING CUE:

At 0200, the CRS directs you to calculate the time of day at which the Unit 1 Spent Fuel Pool will reach its Design Temperature, lAW S1.0P-AB.SF-0001, if no operator actions are taken.

Assume the heat-up rate has been linear from 0100 to 0200.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 7 of 7

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Admin TASK: Prepare a Manual Tagout TASK NUMBER: N3130060301 JPM NUMBER: 09-01 NRC RO Admin A2 ALTERNATE PATH: KIA NUMBER: 2.2.13

~

IMPORTANCE FACTOR: 4.1 4.3 APPLICABILITY:

- -RO--- SRO EoD ROm STAD SROm EVALUATION SETIING/METHOD: Classroom

REFERENCES:

OP-AA-109-115, Rev. 2, Safety Tagging Operations TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 30 min TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 07-20-11 Instructor Validated By: J. Pierce Date: 07-28-11 SME or Instructor

~~

- I (

Approved By: Date: ~

. Approved By: 45=~l___- Date:

I, 8 j. I Operations Representative I

ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION TIME:

PERFORMED BY:

GRADE: D SAT D UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE: _________________________

SYSTEM: Admin TASK: Prepare a Manual Tagout TASK NUMBER: N3130060301 SIMULATOR SETUP INITIAL CONDITIONS:

Unit 1 is operating at 100% power.

While performing a surveillance on 11 Safety Injection Pump, a leak was observed on the pump outlet flange discharge piping.

The Work Clearance Module is not available due to an emergent power outage.

INITIATING CUE:

You are directed to perform the following:

1. Determine the correct blocking points which will allow repair of the 11 SI pump.

2. Sequence those blocking points in the correct order.

3. Determine the correct tag type for each blocking point.

4. Determine the required positions necessary to allow repair on 11 SI pump.

5. Enter all the above information on the provided OP-AA-1 09-115, Safety Tagging Operations Form 4.

Specific WCM identifiers are NOT required.

Successful Completion Criteria:

1. All critical steps completed.

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made (and NRC concurrence is obtained).

Task Standard for Successful Completion:

1. Identifies correct blocking points.

2. Sequence tagging in order by 1: Bezels, 2: Electrical, 3: Mechanical isolation, 4: Vents and drains.

3. Identifies correct tag types for components.

4. Identifies desired positions.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM NAME: __________________

JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM Admin TASK: Prepare a Manual Tagout STEP COMMENTS STEP (*Denotes a Critical Step) EVAL (Required for

NO. STANDARD S/U UNSAT Provide candidate with package Note: If requested, provide extra blank copies of containing several blank Form 4's, Form 4 Tagging/Untagging Work List (Tagging/Untagging Worklist), a copy of OP-AA-109-115, Safety Tagging Operations, drawings 205234 sheets 1-4, 203002, 207910-207912, and 207931-207933. Several of these drawings are not required.

Determines Blocking Points as per key.

Sequences Blocking Points in following order:

1. Bezels

2. Electrical Isolation Mechanical Isolation

4. Vents and Drains

Determines correct tag type for each Blocking Point as per key.

Determines position required for each Blocking Point as per key.

Page 3 of 6 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM NAME: ___________________

JOB PERFORMANCE MEASURE DATE: ___________________

SYSTEM Admin TASK: Prepare a Manual Tagout STEP COMMENTS STEP (*Denotes a Critical Step) EVAL (Required for

NO. STANDARD S/U UNSAT Notes for Evaluators:

Attachment 2. Component Tagging Rules, contains information which allows for the following:

1. "A minimum of 1 vent or drain is required to be RBT opened, there is no limit to how many can be used inside boundaries." (This is why all the vents and drains are sequenced #16)

2. MOV's are allowed to be used as Blocking Points. It would be acceptable procedurally if the 11SJ113 AND 12SJ113 were used as Blocking Points instead of the single manual valve 1S.J 114. I F used as blocking points, the 11/12SJ113 breakers (RBT-OFF), bezels (INFO). and valve handwheels (RBT

-~

SHUT)would also be required to be tagged. ~-~

Note for Evaluators: The electrical power to a component must be cleared and tagged before that components manual operator is tagged, but may be sequenced within the tagout after other manual valves have been tagged.

~-~

Note: Actual WCD 4278552 (CRTE) used as the bases for the blocking points in JPM, with addition of vents and drains.

Page 4 of 6 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to ,JPM usage, revalidate JPM using steps 8 and 11 below.

_":I1'.?r,--_1. Task description and number, JPM description and number are identified.

--:.J~.c,-- 2. Knowledge and Abilities (KIA) references are included.

,J~,...- 3. Performance location specified. (in-plant, control room, or simulator)

--?J:£-/- 4. Initial setup conditions are identified.

--J'-¥-c'- 5. Initiating and terminating Cues are properly identified.

_~y,--_ 6. Task standards identified and verified by SME review.

_....,7~_7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

_....;I'Y:7F-_ 8. Verify the procedure referenced by this JPM rna ches the most current revision of r that procedure: Procedure Rev. .2. Date "'f/) II j/ 9. Pilot test the JPM:

a . verify Cues both verbal and visual are free of conflict, and

b. ensure performance time is accurate.

-,J.,...-- 10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

-."..1:-- 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

SME/lnstructor:_~~~ _______ J_._,?_,.:..-~.:..-~-=-::~;;;...

I' SME/lnstructor:_ _ _ _ _ _ _ _ _ _ _ __ Date: -----

SME/lnstructor: Date: _______

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 5 of 6

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

Unit 1 is operating at 100% power.

While performing a surveillance on 11 Safety Injection Pump, a leak was observed on the pump outlet flange discharge piping.

The Work Clearance Module is not available due to an emergent power outage.

INITIATING CUE:

You are directed to perform the following:

1. Determine the correct blocking points which will allow repair of the 11 SI pump.

2. Sequence those blocking points in the correct order.

3. Determine the correct tag type for each blocking point.

4. Determine the required positions necessary to allow repair on 11 SI pump.

5. Enter all the above information on the provided OP-AA-1 09-115, Safety Tagging Operations Form 4.

Specific WCM identifiers are NOT required.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 6 of 6

OP-AA-109*115 Revision 2 Page 94 of 97 FORM 4 TAGGING / UNTAGGING WORK LIST o REQUEST RELEASE TYPE (circle one) FULL PARTIAL TEMPORARY DISCIPLINE REVIEWS:

WORK CLEARANCE DOCUMENT NUMBER This Worksheet: Page_ of Tag Current Desired Apply/Release QO Verified QO Seq. WCM Identifier Tagging Point Description Tvpe Position Position Date/Time Initials DateITime Initials 1 S1SJ -11SIPP-BZL 11 81 Pump Bezel INFO 2 S1SJ -11SJ33-BZL 118J33 Bezel INFO 3 S18J -11SJ113-BZL 11SJ113 Bezel INFO 4 S1SJ -12SJ113-BZL 12SJ113 Bezel INFO 5 S14KV-1Ao1AX5o 11 81 Pump 4KV breaker RBT 01 6 S 1230-1 A Y2AX3E 11 SJ33 Valve Motor RBT OFF 7 S1230-1AY2AX31 11 SJ 113 Valve Motor RBT OFF 8 S 1230-1 BY2AX8A 12SJ 113 Valve Motor RBT OFF 9 81SJ -11SJ35 11 SI Pump Discharge valve RBT X I 10 S1SJ -11SJ65 11 SI Pump mini flow isolation RBT X 11 S1SJ -11SJ922 11 81 Pump mini flow isolation RBT X 12 S1SJ-11SJ33 11 81 Pump Suction valve RBT X 13 S18J -1SJ114 SJ-CHG pump x-over isolation vlv RBT X 14 S1SJ -11SJ113 11 SJ113 Cross over RBT X 15 S1SJ -12SJ113 12SJ 113 Cross over RBT X 16 S1SJ -1 SJ181 SJ-CHG pump x-over drain vlv RBT 0 16 S1SJ -18J326 SJ-CHG pump x-over vent vlv RBT 0 16 S1SJ -11SJ102 11 SI Pump drain RBT 0 16 S1SJ -11SJ106 11 SI Pump drain RBT 0 16 S1SJ -11SJ104 11 SI Pump drain RBT 0 16 S1SJ -11SJ103 11 SI Pump vent RBT 0 16 81SJ -11SJ105 11 SI Pump vent RBT 0 TAGGED BY: DATEITIME: VERIFIED BY: _ _ _ _ DATE/TIME: _ _ __

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: ADMINISTRATIVE TASK: Perform Duties of Secondary Communicator During an Alert TASK NUMBER: N1240100501 JPM NUMBER: 09-01 NRC RO Admin A4 ALTERNATE PATH: KJANUMBER: 2.4.39

~

IMPORTANCE FACTOR: - - 3.9 APPLICABILITY: RO SRO EoD ROCK]

EVALUATION SETIING/METHOD: Simulator

REFERENCES:

Salem ECG, Attachment 8 Secondary Communicator Log, Rev. 24 TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 8 min TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 7-19-11 Instructor Validated By: J Pierce, Jr Date: 07 11 SME or Instructor Approved By:

fP./7 afning Department Date: <'7_" -

'0 L.

II Approved By: f.3~--

Operations Representative Date:

ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION TIME:

PERFORMED BY:

GRADE: SAT D UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 1 of 8

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM: Administrative TASK: Perform Duties of Secondary Communicator During an Alert.

TASK NUMBER: N1240100501 SIMULATOR OPERATOR CALL THE NRC OPERATIONS CENTER ON LAND LINE 1-301-951-0550 BEFORE STARTING JPMS TO INFORM THEM EROS WILL BE ACTIVATED DURING EXAM. PLACE FOLLOWUP CALL AFTER LAST RO HAS PERFORMED JPM.

ENSURE modem in simulator computer room, by 3 monitors is turned ON.

Reset simulator to MODE 3 HSB IC, and place simulator in RUN.

INITIAL CONDITIONS: An ALERT was declared at Salem due to the Unit 2 reactor failing to trip when a manual trip signal was initiated. The Rx tripped when the second trip handle was used.

The unit is currently stable in MODE 3.

INITIATING CUE: You are the Secondary Communicator. You are directed to perform Salem ECG Attachment 8, Secondary Communicator Log.

Successful Completion Criteria:

1. All critical steps completed

2. All sequential steps completed in order

3. All time-critical steps completed within allotted time

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made (and NRC concurrence is obtained).

Task Standard for Successful Completion:

1. Activate EROS.

2. Does NOT provide plant information to outside caller.

3. Terminate EROS.

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OPERATOR TRAINING PROGRAM NAME:_ _ _ _ _ _ _ _ __

JOB PERFORMANCE MEASURE DATE:

System: ADMINISTRATIVE -----------

Task: Perform Duties of Secondary Communicator During an Alert I

STEP STEP STANDARD EVAL COMMENTS NO. (* Denotes a Critical Step) StU (Required for UNSAT evaluation)

Provide a copy of ECG Attachment 8.

Fills out ECG Attachment 8 by:

1. Printing name

2. Circles ALERT and circles CM2.

A.1 OBTAIN a copy of Attachment 6 and ASSIST Primary Communicator with Cue: Primary Communicator does not 15-minute notifications, as necessary.

require assistance.

A.2 DIRECT the Shift Rad Pro Tech (SRPT) (2644) to implement SC.EP- Cue: Shift Rad Pro Tech (Matt EP.ZZ-0301(Q) Shift Radiation Hassler) has been notified to Protection Technician Response. implement SC.EP-EP.ZZ-0301(Q)

(N/A for Common Site) Shift Radiation Protection Technician Response. I

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

A.3 For an ALERT or higher Emergency;

a. an on-shift SRO is not available to fill the OSC Operations Supervisor Cue: The WCC Supervisor is the OSC position, CALLOUT an Supervisor.

additional SRO and have

~---~"---~

him/her report to the OSC.

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OPERATOR TRAINING PROGRAM NAME:_ _ _ _ _ _ _ _ _ __

JOB PERFORMANCE MEASURE DATE:_____________

System: ADMINISTRATIVE Task: Perform Duties of Secondary Communicator During an Alert

STEP STEP STANDARD EVAL COMMENTS NO. (* Denotes a Critical Step) S/U (Required for UNSAT evaluation)

A.3

b. ACTIVATE EROS within 60 Uses SPDS display to activate EROS

minutes from the affected unit's by:

SPDS terminal:

1. CLICK <EROS> button 1. Clicking <EROS> button

2. CLlCK<lnitiate> button 2. Clicking<lnitiate> button

3. CHECK for the following 3. Checking for the following status: status:

EROS Active EROS Active LINK Dialing Modem -~ Link LINK Dialing Modem - t Link Active Active A.3 c. IF ERDS Activator is not Determines EROS Activator was successful, CONTACT IT Support: successful.

Network Operations (DID 7008),

EOF IT Supervisor (NETS 5009), or the IT Help Desk (Ext. 5555) for assistance. I A.4 ENSURE FAXed or FAX the ICMF to Cue: The ICMF has been FAXed to Group A. Group A.

I

_ _ L _____ ----- I PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 4 of 8

OPERATOR TRAINING PROGRAM NAME:_ _ _ _ _ _ _ _ __

JOB PERFORMANCE MEASURE DATE:._ _ _ _ _ _ _ _ __

System: ADMINISTRATIVE Task: Perform Duties of Secondary Communicator During an Alert

STEP STEP STANDARD EVAL COMMENTS NO. (* Denotes a Critical Step) S/U (Required for UNSAT evaluation)

Simulator O(!erator: After candidate has performed step A.4 above, call the desk phone and say the following:

'This is Anderson Cooper calling Does NOT give plant information to from CNN headquarters in Atlanta. caller.

We have received a report that the Salem 2 reactor has experienced a Attachment 8, Section C, INCOMING Rx accident and the core is melting. CALLS, MEDIA, CAUTION, states, Can you give me an update on the "Communicators are NOT authorized current condition of Salem Unit 2?" to release any information to the News Media."

May read either Attachment 8, section C, Incoming Calls, 3B, OR tell them he cannot provide any information.

CUE: If asked, state the ENG is activated.

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

CUE: Once EROS is activated AND Media call action is complete, then state, 'The Station Event has been terminated. The NRC Operations Center directs you to terminate EROS transmission."

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OPERATOR TRAINING PROGRAM NAME:_ _ _ _ _ _ _ _ __

JOB PERFORMANCE MEASURE DATE:_ _ _ _ _ _ _ _ __

System: ADMINISTRATIVE Task: Perform Duties of Secondary Communicator During an Alert

STEP STEP STANDARD EVAL COMMENTS NO. (* Denotes a Critical Step) S/U (Required for UNSAT evaluation)

CA WHEN directed by the NRC to TERMINATE ERDS transmission, THEN GO TO any SPDS terminal of the affected unit AND PROCEED as Uses SPDS display to activate ERDS follows:

by:

a. CLICK <ERDS> button

b. CLlCK<Terminate> button *1. Clicking <ERDS> button

c. CHECK for the following 2. Clicking<TERMINATE> button status: 3. Checking for the following ERDS Inactive status:

LINK Not Connected EROS Inactive

d. WHEN completed, NOTIFY LINK Not Connected the SM L ______________

Cue: SM notified, JPM is complete.

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OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate ,JPM using steps 8 and 11 below.

--J-#L--1. Task description and number, JPM description and number are identified.

_-¥11~_2. Knowledge and Abilities (KIA) references are included.

/'

-J-+,,-v-_3. Performance location specified. (in-plant, control room, or simulator)

_-'-J~~_4. Initial setup conditions are identified.

_~~ _ _ 5. Initiating and terminating Cues are properly identified.

_~..,;.-___ 6. Task standards identified and verified by SME review.

_..::.~_ _ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

__'). ..."",,:..:..-_ 8. Verify the procedure referenced by this JPM m?tches the most current revision of that procedure: Procedure Rev. "2..'1 Date?/z..'t/{/

-r/-"'---77~---

~~rr,--- 9. Pilot test the JPM:

a. verify Cues both verbal and visual are free of conflict, and

b. ensure performance time is accurate.

-1:...v-c~_10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

_/j/:.-.p..__ 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

SME/lnstructor: #-<= J,?(~ Date: ---,7~t=--~'f-h.j...L..'_

I /

SME/lnstructor:_ _ _ _ _ _ _ _ _ _ _ __ Date: _ _ _ _ __

SMEflnstructor: Date: _ _ _ _ __

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OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

An ALERT has been declared at Salem due to the Unit 2 reactor failing to trip when a manual trip signal was initiated. The Rx tripped when the second trip handle was used.

The unit is currently stable in MODE 3.

INITIATING CUE:

You are the Secondary Communicator. You are directed to perform Salem ECG , Secondary Communicator Log.

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OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEIVI: Administrative TASK: Determine the required actions based on abnormal Secondary Plant chemistry conditions .

TASK NUMBER: .;\1 II L/t) s1CYo 2 JPM NUMBER: 09-01 NRC SRO Admin A1-1 ALTERNATE PATH: KIA NUMBER: 2.1.34 IMPORTANCE FACTOR: 3.5 APPLICABILITY: RO SRO EO RO STA SRO EVALUATION SETIING/M ETHOD: Classroom

REFERENCES:

S2.0P-AB.CHEM-0001, Rev. 21 TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 10 minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 7*21*11 Instructor Validated By: C Recchione Date: 07*28*11 SIVIE or Instructor Approved By:

~a-ment Date: 1, - L. - II Approved By: -:g ~~- Date: g{, {ll opera~~'Department ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION TIME:

PERFORMED BY:

GRADE: SAT UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

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OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM: Administrative TASK: Determine the required actions based on abnormal Secondary Plant chemistry conditions.

TASK NUMBER: N1140530402 INITIAL CONDITIONS:

While operating at 100% power, Salem Unit 2 has experienced a rise in Sodium levels in 22B main condenser hotwell. Chemistry samples have been reported at 0800 on September 11th:

S/G Blowdown pH: 10.1 S/G Slowdown cr: 38 ppb S/G Blowdown Na: 40 ppb S/G blow down Cation Conductivity: 0.9 uS/cm.

Feedwater DO: 0.25 ppb INITIATING CUE:

Using the assumption that the Secondary Chemistry conditions cannot be corrected, develop a timeline that describes required actions, starting at 0800 on September 11th.

Assume that any plant power changes will only be the minimum required.

Successful Completion Criteria:

1. All critical steps completed.

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. ..JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Task Standard for Successful Completion:

1. Calculates that Unit 2 must be < 30% power by 1600 on September 18th *

2. Calculates that Unit 2 must be <5% power by 1600 on September 22 nd

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OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: Administrative TASK: Determine the required actions based on abnormal Secondary Plant chemistry conditions.

STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD StU evaluation)

When asked, provide a clean copy of S2.0P-AB.CHEM-0001, Abnormal Secondary Chemistry.

Note: Once entered, the AB would not be exited until the conditions cause were found and isolated.

I-- ----

Note: Action Levels are found on Attachment 4.

S/G blowdown CI- and S/G blowdown Cation Conductivity both meet Action Level 1 at 0800 on September 11th.

Operation in Action Level 1 for 7 days is the escalation to Action Level 2, which is entered at 0800 on September 18th .

Action Level 2 actions are directed at Step 3.28, which requires initiation of actions and reduce power ,530 % in the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , by 1600 on September 18th . I

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

100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months of operation at Action Level 2 is the escalation to Action Level 3, which is entered at 1200 on September 22 od

I PSEG Restricted - Possession Requires Specific Approval from Nuclear Training Page 30f6

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Administrative TASK: Determine the required actions based on abnormal Secondary Plant chemistry conditions.

STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD Stu evaluation) I Action Level 3 actions are directed at Step 3.18, which requires initiation of actions and reduce power <5% in the next four hours, by 1600 on September 22 nd

Terminate JPM when operator turns in paperwork.

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JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 and 11 below.

____ 1. Task description and number, JPM description and number are identified.

--""f--- 2. Knowledge and Abilities (KIA) references are included.

_--=-~_3. Performance location specified. (in-plant, control room, or simulator)

_ _-=-_ 4. Initial setup conditions are identified.

__Ci-,,-_ 5. Initiating and terminating Cues are properly identified.

__Lt-,,-_ 6. Task standards identified and verified by SME review.

__Q _ _ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

_~-+-__ 8. Verify the procedure referenced by this JPM matc~es the most current revision of that procedure: Procedure Rev. ~ Date I 'vII,,' P

__V_\_ 9. Pilot test the JPM:

a. verify Cues both verbal and visual are free of conflict, and

/ b. ensure performance time is accurate.

~ 10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

_--"fl_/t/_LL_11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

SME/lnstructor:_. ,.: ,C~J. . : .-.",-

_ _ _ _ _ _ __ Date: _I-,-,-~",--'-"-'~

1_1-,--1_

SME/lnstructor: Date: ------

SME/lnstructor: Date: - - - - - -

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INITIAL CONDITIONS:

While operating at 100% power, Salem Unit 2 has experienced a rise in Sodium levels in 22B main condenser hotwell. Chemistry samples have been reported at 0800 on September 11th:

SIG Blowdown pH: 10.1 SIG Blowdown cr: 38 ppb S/G Blowdown Na: 40 ppb S/G blow down Cation Conductivity: 0.9 uS/cm.

Feedwater DO: 0.25 ppb INITIATING CUE:

Using the assumption that the Secondary Chemistry conditions cannot be corrected, develop a timeline that describes required actions, starting at 0800 on September 11 tho Assume that any plant power changes will only be the minimum required.

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OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Administrative TASK: Determine the TSAS(s) for a dropped rod and complete the appropriate log TASK NUMBER: 1120700302 JPM NUMBER: 09-01 NRC SRO A 1-2 ALTERNATE PATH: I I KIA NUMBER: 2.1.18

~

IMPORTANCE FACTOR: 3.8 APPLICABILITY: ----=R-==-O- SRO EOD ROD STAD SROW EVALUATION SETTING/METHOD: Classroom Salem Tech Specs

REFERENCES:

OP-SA-1 08-115-1001, Rev. 2 TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 20 min TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 07*21*11 Instructor Validated By: C Recchione Date: 07*28*11 SME or Instructor Approved By: ij~ Date: -g-2-- 11

~&1ning.DePartment

Approved By: -,:s Date: ~J I II 1 Operatio s Representative ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION TIME:

PERFORMED BY:

GRADE: D SAT D UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

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OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM: ADMINISTRATIVE TASK: Determine the TSAS(s) for a dropped rod and complete the applicable log TASK NUMBER: 1120700302 INITIAL CONDITIONS:

1. Unit 2 is at EOL in a 300 day run at 100% power.

2. Control Rod 2SA4 dropped fully into the core at 1015, the reactor did not trip.

3. The crew has implemented S2.0P-AB.ROO-0002, Dropped Rod.

4. Control Rod 2SA4 has been declared inoperable, and Reactor Engineering reports it will be at least 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months before they determine how to recover the rod.

5. The 3rd NCO has just completed a QPTR at 1025. The highest reading quadrant is 1.031.

6. Computerized LCO tracking is not being used.

INITIATING CUE:

As CRS, determine ALL TSAS( s) that apply and make the appropriate log entries on OP-SA-108-115 1001, Operability Assessment and Equipment Control Program, Attachment 4-1, and Form 1, Section 1.0.

Creation or documentation of notifications is not required.

Successful Completion Criteria:

1. All critical steps completed.

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Task Standard for Successful Completion:

1. Identifies TSAS 3.1.3.4.b, 3.1.3.1.c, and 3.2.4.a are applicable with correct action times identified .

. 2. Fills out Attachment 4-1 and Form 1's as per Standard in JPM body.

!I PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 2 of9

OPERATOR TRAINING PROGRAM NAME: ___________________

JOB PERFORMANCE MEASURE DATE: ___________________

SYSTEM: ADMINISTRATIVE

_ ,_, T*. , , .. .. ~

COMMENTS STEP STEP EVAL (Required for UNSAT

NO. (*Denotes a Critical Step) STANDARD StU evaluation)

Provide candidate package consisting of Note to Evaluator: Completed Form 1's for blank copy of OP-SA-108-115-1001, each of the 3 TSAS's are included as keys Operability Assessment and Equipment with this JPM.

Control Program, marked up copy of Attachment 4-1, and blank Form 1'so

Obtains a copy of Plant Technical Determines the following LCO's apply:

Specifications and reviews for LCO 3.1.3.4.b , 3.1.3.1.c, 3.2.4.a applicability.

Refers to Section 5.2, Entry into an Active/Tracking Technical Specification (TIS)

LCO Action Statements of OP-SA-1 08-114 1001, Operability Assessment and Equipment Control Program.

5.2.2 DETERMINE if the TIS LCO Action Determines the LCOs are ACTIVE.

Statement is ACTIVE or TRACKING based on the following criteria:

5.2.3 lE the cause of the SSC being Determines the cause of the SSC being INOPERABLE is a planned .... evolution ... INOPERABLE it is NOT a planned evolution.

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

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OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: ADMINISTRATIVE TASK: Determine the TSAS(s) for a dropped rod and complete the applicable log COMMENTS STEP STEP EVAL (Required for UNSAT

NO. (*Denotes a Critical Step) STANDARD S/U evaluation) 5.2.4 For activities that cause a TECH SPECS SSC to be INOPERABLE that do not meet the criteria of Section 5.2.3, DOCUMENT the condition as follows:

5.2.4.A For SAP LCO tracking, REFER TO Determines computerized SAP LCO tracking guidance provided in OP-SH-108-115- is not being used as per stem.

1001, LCO Entry/Exit & Operability Determination SAP Guidance.

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OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: ADMINISTRATIVE TASK: Determine the TSAS(s) for a dropped rod and complete the applicable log COMMENTS STEP STEP EVAL (Required for UNSAT

NO. (*Denotes a Critical Step) STANDARD S/U evaluation) 5.2.4.B For LCO tracking using Attachment 4 and CUE: Provide copies of Attachment 4-1 and Form 1, PERFORM the following: Form 1. On Att. 4-1, the first LCO Index No. should is filled in so the candidate can number sequentially.

1. ASSIGN the next consecutive LCO

Makes entries on Att. 4-1:

Index Number obtained from the Action Statement Log Index (Attachment 4) and

Next LCO Index No. is11-234 LOG the TIS LCO ACTION Statement on the Index.

TS No's. 3.1.3.4.b. 3.1.3.1.c, 3.2.4.a

Active

Summary Descriptions

Planned? NO

Entry Date/Time

Expiration: 3.1.3.1.c- 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , 3.2.4.a- 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , 3.1.3.4.b 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

2. UPDATE Unit Status Board for the Technical Specification Action Statement. CUE: Another operator will update the Unit Status Board.

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

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OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE: ___________________

SYSTEM: ADMINISTRATIVE TASK: Determine the TSAS( s) for a dropped rod and complete the applicable log COMMENTS STEP STEP (Required for UNSAT EVAL

NO. (*Denotes a Critical Step) STANDARD S/U evaluation)

3. COMPLETE Sections 1 and 2 of Form Makes entries on Form 1, Section 1.0 as per

5.2.4.B 1 by performing the following: initiating cue:

Note: Separate Form 1's should be filled out for each Tech Spec, listing the other 2 Tech Specs in the "Other Applicable TIS" section.

RECORD the LCO Index Number

LCO Index No: same as Att. 4 (from Attachment 4)

RECORD the LCO Status (Active

LCO Status: Active I Tracking)

RECORD the applicable Technical

TS No.: 3.1.3.1.c (3.2.4.a)( 3.1.3.4.b)

Specification LCO number. When an INOPERABLE TECH SPECS/SSC affects multiple LCO Action Statements, RECORD the LCO number with the most limiting Action Time.

RECORD the DatelTime entered.

DatelTime entered: Same as Att. 4

RECORD the Mode Applicability for

Applicability: MODES 1 & 2 (MODE 1 the LCO. above 50% RTP)(MODES 1&2)

RECORD the DatelTime Action

DatelTime Action Required: Within one Required, When recording the date hour from entry and time that Action is required for an LCO Action Statement that has multiple actions, use the most limiting Action time. For Tracking Action Statements, record 'N/A'.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 6 of9

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: ADMINISTRATIVE TASK: Determine the TSAS(s) for a dropped rod and complete the applicable log COMMENTS STEP STEP EVAL (Required for UNSAT

NO. (*Denotes a Critical Step) STANDARD evaluation)

I S/U

Other Applicable TS: 3.1.3.1.c, 3.2.4, 5.2.4.B

RECORD Other Applicable TIS.

3.1.3.4.b (whichever 2 were not listed List only active LCO's. Applicable as "Tech Spec Number" in Section 1.0 ~

Tracking LCOs should be listed top section.)

seperately in the Summary Description of the Log Sheet.

RECORD the Equipment

Equipment: Shutdown Rod 2SA4 description.

Briefly STATE the reason for the

Summary: Brief summary of TS and required action for that TSAS.

SSC condition in the Summary See provided keys (3) for Summary Description section and include a Desription for each Active Tech Spec.

brief summary of actions required, including submittal of any special Note to Evaluators: Providing the LCO reports to the NRC. NOTIFY the Action number, i.e, "3.1.3.1 actions SOS of any reporting c.1,2,3a-d is acceptable in lieu of writing requirements.

all the required actions.

When candidate returns all paperwork terminate JPM. '

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TQ-AA-106-0303 Revision 4 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 and 11 below.

_....\,,-__ 1. Task description and number, JPM description and number are identified.

__y+.__ 2. Knowledge and Abilities (KIA) references are included. +-- 3. Performance location specified. (in-plant, control room, or simulator)

__q-,-_ 4. Initial setup conditions are identified.

_-""fA,-~'--_ 5. Initiating and terminating Cues are properly identified.

__y-\--_ 6. Task standards identified and verified by SME review.

C1

____ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

/\ ~ T <I .dzS:. I}

__ VJ-\-,_ _ 8. Verify the procedure reference~y {his JPM m~r?es the most current revision of that procedure: Procedure Rev.~ Date ~

'& gil I oc~

_ - l . . - _ 9. Pilot test the JPM:

a. verify Cues both verbal and visual are free of conflict, and

b. ensure performance time is accurate .

1t .

. ' 10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

~ 11. When JPM is revalidated, SME or Instructor sign and date ..!PM cover page.

SMElinstructor:__ oL_'_,_t'1-_'_,_____, Date: _'7_(_z-=.~- =-/. .:. J{I~_

SMEllnstructor:_ _ _ _ _ _ _ _ _ _ _ __ Date: _ _ _ _ __

SMEllnstructor: Date: _ _ _ _ __

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INITIAL CONDITIONS:

1. Unit 2 is at EOl in a 300 day run at 100% power.

2. Control Rod 2SA4 dropped fully into the core at 1015, the reactor did not trip.

3. The crew has implemented S2.0P-AB.ROD-0002, Dropped Rod.

4. Control Rod 2SA4 has been declared inoperable, and Reactor Engineering reports it will be at least 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months before they determine how to recover the rod.

5. The 3rd NCO has just completed a QPTR at 1025. The highest reading quadrant is 1.031.

6. Computerized leO tracking is not being used.

INITIATING CUE:

As CRS, determine ALL TSAS(s) that apply and make the appropriate log entries on OP-SA 108-115-1001, Operability Assessment and Equipment Control Program, Attachment 4-1, and Form 1, Section 1.0.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 9 of 9

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: ADMINISTRATIVE TASK: Review a completed surveillance to calculate Shutdown Margin TASK NUIVIBER: 1200030301 JPM NUMBER: 09-01 NRC SRO Admin A2 ALTERNATE PATH: KJA NUMBER: 2.2.12

~

IMPORTANCE FACTOR: 4.1 APPLICABILITY: RO SRO EoD ROO STAD SROm EVALUATION SETTING/METHOD: Classroom

REFERENCES:

SC.RE-ST.ZZ-0002, Rev. 19 Shutdown Margin Calculation S1.RE-RA.ZZ-0016, Rev. 3 Figures (Cycle 21)

Salem Unit 1 Technical Specifications TSAS 3.1.3.1 Movable Control Assemblies TOOLS AND EQUIPMENT: Calculator VALIDATED JPM COMPLETION TIME: 20 minutes A ,g.17-fl TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: 30 ~inutes Developed By: G Gauding Date: 07 11 Instructor Validated: C Recchione Date: 07-28-11 SME or Instructor Approved By: /1 ~~ Date:

~::/f~ning DePartment Approved By: --:P- \\.

Operatidn~ Re"-p-r-es-e-n-ta-t-ive Date:

S f II J I

ACTUAL JPM COMPLETION TIME:

ACTUAL TIIVIE CRITICAL COMPLETION TIME:

PERFORMED BY:

GRADE: D SAT D UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 1 of 7

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAIIIIE:

DATE:

SYSTEM: Ad mi nistrative TASK: Review a completed surveillance to calculate Shutdown Margin TASK 1200030301 NUMBER:

INITIAL CONDITIONS:

Control Rod 105 was declared INOPERABLE at 2210 today due to not moving during a rod exercise test A NCO has completed a SDM as required by Tech Spec 3.1.3.1 lAW SC.RE-ST.ZZ-0002, Shutdown Margin Calculation, and reports that SDM is SAT.

Unit 1 Reactor Power is 70%. Control Bank 0 is at 174 steps.

Current boron concentration is 300 ppm.

Current core burnup is 10,000 EFPH.

INITIATING CUE:

1. Review the attached SDM calculation procedure SC.RE-ST.ZZ-0002 for completeness and accuracy.

2. Note any discrepancies found by the review on Attachment 7.

3. Determine if SDM is SAT.

The current time is 2240. This is a time critical JPM. Time will start when procedures are given to you. Time will stop when procedures are given to proctor.

Successful Completion Criteria:

1. All critical steps completed.

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. ,-'PM completed within validated time. Completion time may exceed the validated time if satisfactor ro ress is bein made and NRC concurrence is obtained .

Task Standard for Successful Completion:

1. Operator identifies incorrect Total Control Bank Worth at Step 4.2.1 of Att. 3.

2. Operator identifies incorrect Total Shutdown Bank Worth at Step 4.2.2 of AU. 3.

3. Operator identifies incorrect Integral Rod Worth inserted at Step 4.2.5 of AU. 3

4. Operator identifies incorrect value of Power Defect at Step 4.3.3 of Att. 3.

5. Operator determines SDM is SAT.

6. Operator completes review within 30 minutes.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 2 of 7

OPERATOR TRAINING PROGRAM NAME:_ _ _ _ _ _ _ _ __

JOB PERFORMANCE MEASURE DATE:_ _ _ _ _ _ _ _ __

System: ADMINISTRATIVE Task: Review a completed surveillance to calculate Shutdo\iV11 rvli3!fl1n STEP COMMENTS STEP (*Denotes a Critical Step) STANDARD EVAL (Required for UNSAT

NO. stu Evaluation)

Note to Evaluator: The actions contained in this JPM do not require the SRO candidate to perform the Shutdown Margin, only to identify the portions that have been performed incorrectly. All the actual numbers are more conservative than the errors, and the SDM can be determined from this conclusion, or recalculation of correct numbers can be performed to determine SAT SDM.

The time critical aspect refers to the time required when the Shutdown Margin requirement of TSAS 3.1.3.1.c must be met.

1 Provide the candidate with the marked I Ensures Sections 3 and 4 are completed.

up copy of SC.RE-ST.ZZ-0002 and copy of S2.RE-RA.ZZ-0016, Curve Book.

Time Start: - - - - -

2 I Review Section 5 to ensure the correctl Reviews Section 5 and determines the correct Attachment was performed. Attachment (3) was performed.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 3 of 7

OPERATOR TRAINING PROGRAM NAME:_ _ _ _ _ _ _ _ __

JOB PERFORMANCE MEASURE DATE:_ _ _ _ _ _ _ _ __

System: ADMINISTRATIVE Task: Review a completed surveillance to calculate ShLltcjown Margin STEP COMMENTS STEP (*Denotes a Critical Step) STANDARD EVAL (Required for UNSAT

NO. S/U Evaluation) 3 Review the completed Shutdown Margin Calculation:

4.1.1 Power Level Verifies power is 70% from stem initial 4.1.2 Boron Concentration conditions.

Verifies 300 ppm from initial conditions 4.1.3 Control Bank Position Verifies Bank D at 174 from initial conditions.

4.1.3 Burnup Verifies burnup 10,000 EFPH from initial conditions.

Step 4.1.5 Verifies 1 from stem.

Step 4.2.1 Determines Total Control Bank Worth is incorrect from Figure 15/Table G (Should be -3018)

Step 4.2.2 Determines Total Shutdown Bank Worth is incorrect from from Figure 16fTable H (Should be -3743)

Step 4.2.3 Verifies 722 from Figure 14/Table I Step 4.2.4 Verifies 722 for 1 control rod.

Step 4.2.5 Determines Integral Rod Worth Inserted is incorrect from Figure 2CfT able 1-7 or Figure 2A1Table 1-8.

(Should be 221)

__1___

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 4 of 7

OPERATOR TRAINING PROGRAM NAME:_ _ _ _ _ _ _ _ __

JOB PERFORMANCE MEASURE DATE:_ _ _ _ _ _ _ _ __

System: ADMINISTRATIVE k R . ,- d '11 Iculate Shutd M STEP COMMENTS STEP (*Denotes a Critical Step) STANDARD EVAL (Required for UNSAT

NO. S/U Evaluation)

Step 4.2.6 Determines errors carried forward.

~

(Should be -5096)

Step 4.3.1 Determines errors carried forward. (Should be -5096)

Step 4.3.2 Determines errors carried forward. (Should be 604)

Step 4.3.3 Determines incorrect Power Defect is used.

(Should be 1937)

Step 4.3.4 Determines SDM is incorrect. (Should be 2555)

4 Acceptance Criteria Determines Acceptance Criteria are met.

Turns in procedures within 30 minutes of start time.

Time Stop:

Total time to complete JPM MUST be 30 minutes or less.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 5 of 7

OPERJ\TOR TRAh'lING PROGRAl'VI JOB PERFORl"fANCE MEASlJRE TQ-AA-I06-0303 Revision 4 JOB PERFORMANCE ;:VIEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 and 11 below.

~ 1. Task description and number, JPM description and number are identified.

C.iL

_-,,-_2. Knowledge and Abilities (KiA) references are included .

._ _-\-_3. Performance location specified. (in-plant, control room, or simulator)

__.. .~ 4. Initial setup conditions are identified.

_ C\~ 5. Initiating and terminating Cues are properly identified.

___C_i_ 6. Task standards identified and verified by SME review.

__--'~_7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

8. Verify the procedure referenced by this JPM matche~ the most current revision of that procedure: Procedure Rev. J.t__ Date ~\~'tjL~

9. Pilot test the JPM:

a. verifY Cues both verbal and visual are free of conflict, and

b. ensure performance time is accurate.

~ 10. If"" JPM orumo! be p"fonned " writteo with pwp" poo"" then revi" the JPM.

- - ~C 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

Date: 1\1~~_

Date:

Date: _ _ _ _ __

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 6 of 7

OPERATOR TRAINING PROGRAM JOB PERFORl'\1ANCE MEASURE INITIAL Name: __________________________

CONDITIONS:

Control Rod 1D5 was declared INOPERABLE at 2210 today due to not moving during a rod exercise test.

A NCO has completed a SDM as required by Tech Spec 3.1.3.1 lAW SC.RE-ST.ZZ-0002, Shutdown Margin Calculation, and reports that SDM is SAT.

Unit 1 Reactor Power is 70%. Control Bank D is at 174 steps.

Current boron concentration is 300 ppm.

Current core burnup is 10,000 EFPH.

INITIATING CUE:

1. Review the attached SDM calculation procedure SC.RE-ST.ZZ-0002 for completeness and accuracy.

2. Note any discrepancies found by the review on Attachment 7.

3. Determine if SDM is SAT.

The current time is 2240. This is a time critical JPM. Time will start when procedures are given to you. Time will stop when procedures are given to proctor.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 7 of 7

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Waste Liquid TASK: Select Release Path for Radioactive Liquid Waste Release TASK NUMBER: N0680070302 JPM NUMBER: 09-01 NRC SRO Admin A3 ALTERNATE PATH: D KiA NUMBER:_ _ _ _2_.3_.6_ _ _---1 IMPORTANCE FACTOR: 3.8 APPLICABILITY: RO SRO Ece=J STpO SRc())

EVALUATION SETTING/METHOD: Classroom

REFERENCES:

S1.0P-SO.WL-0002, Rev.25, 205209 (CW), 205242 (SW)

TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 30 minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS:

Developed By: G Gauding Date: 06-24-11 Instructor Validated By: A Crampton Date: 06-30-11 SME or Instructor Approved By: ~v-;?- Date: ?] I I afning De(fartment Approved By: ~~ rl Date:

Operations Department ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION TIME:

PERFORMED BY:

GRADE: D SAT D UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

Page 1 of 6 PSEG Restricted - Possession requires Specific Permission From Nuclear Training

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE: ________________

SYSTEM: Waste Liquid TASK: Select Release Path for Radioactive Liquid Waste Release TASK NUMBER: N0680070302 INITIAL CONDITIONS:

Salem Unit 2 is on day 25 of a scheduled 45 day refueling outage.

11 and 12 CCHX's are in service.

21 CCHX is in service, 22 CCHX is removed from service and drained.

All Unit 2 Circulators are O/S.

Salem Unit 1 is operating at 75% power.

12A Circulator is OIS for waterbox cleaning.

The Non-Rad Waste Treatment System is in service performing a release, and must remain in service.

Unit 1 is NOT in any active Tech Specs.

12 CVCS Monitor Tank is in Recire using 11 CVCS Monitor Tank Pump, and Chemistry has granted permission to release the tank with a minimum dilution flow rate of 100,000 gpm.

INITIATING CUE: You are the Unit 1 CRS. Select the release path for 12 CVCS Monitor Tank lAW S1.0P-SO.WL-0002, Attachment 2, Section 2.2 Release Verification AND provide marked up drawings of the flow path from 12 CVCS Monitor tank to its ultimate release point.

Successful Completion Criteria:

1. All critical steps completed.

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made (and NRC concurrence is obtained).

Task Standard for Successful Completion:

1. Candidate determines the release path as 21 CCHX to 12A AND/OR 12B CW Pump liS (Att. 2 Step 2.2.3)

2. Provides release flow path drawing of 12 CVCS MT to 21 CCHX, (via Unit x-conn) to discharge of 12AJ12B Circulators.

Page 2 of 6 PSEG Restricted - Possession requires Specific Permission From Nuclear Training

OPERATOR TRAINING PROGRAM NAME: __________________

JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: Waste Liquid TASK: Select Release Path for Radioactive Liquid Waste Release STEP COMMENTS STEP (*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD stu Evaluation)

Provide marked up copy of S1.0P- Note: Drawings 205229-2 SO.WL-0002., and blank copies of 205242-4 drawings: 205342-5 205230 are not needed for flowpath but are 205239-1 included to ensure an incorrect 205229-2 alternate flowpath could be selected.

205242-4 205339-1 205342-3,4,5,6 205209-2 and a colored marker.

Have a blank copy of S1.0P-SO.CW 0001 Circulating Water System Operation available if asked for.

Uses S2.0P-SO.WL-0002,

Attachment 2, Section 2.2, to select the release flow path based on CCHX's available and Circulators in service, as 12 CVCS Monitor Tank to 21 CCHX, to 12A and/or 128 CW pumps I/S.

Page 3 of 6 _

PSEG Restricted - Possession requires Specific Permission From Nuclear Training

OPERATOR TRAINING PROGRAM NAME: ___________________

JOB PERFORMANCE MEASURE DATE: ___________________

SYSTEM: Waste Liquid TASK: Select Release Path for Radioactive Liquid Waste Release STEP COMMENTS STEP (*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD S/U Evaluation)

Candidates mark the appropriate drawings, from the 12 CVCS MT on drawing 205230 to 205239 Sheet 1, to 205339 Sheet 1 via x-connect line, to 205342 Sheet 4, to 205342 Sheet 3, through 21 SW222, to 205342 Sheet 6, to 205342 Sheet 3, to 205209 Sheet Terminate JPM when candidate has returned procedures and marked up drawings.

Page 4 of 6 PSEG Restricted Possession requires Specific Permission From Nuclear Training

JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 and 11 below.

~ 1. Task description and number, JPM description and number are identified.

A 2. Knowledge and Abilities (KIA) references are included.

il< 3. Performance location specified. (in-plant, control room, or simulator) ft 4. Initial setup conditions are identified.

A 5. Initiating and terminating Cues are properly identified.

/L 6. Task standards identified and verified by SME review.

L 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*) .

.---!.f.--'----_ _ 8. Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. ZS" Date 5[cd IIi.:.

---!./Lc.......;;;;..

__ 9. Pilot test the JPM:

a. verify Cues both verbal and visual are free of conflict, and

b. ensure performance time is accurate.

_/V....!.~_A_ _ 1O. If the JPM cannot be performed as written with proper responses, then revise the JPM.

At I;L 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

SMElinstructor:---;Y£::1~td..._~~~~_ __ Date: _=c.+-f-=-~..::;O-l-!..LJI',--

SME/lnstructor: Date: _ _ _ _ __

SMEllnstructor: Date: _ _ _ _ __

Page 5 of 6 PSEG Restricted - Possession requires Specific Permission From Nuclear Training

, '\

INITIAL CONDITIONS:

Salem Unit 2 is on day 25 of a scheduled 45 day refueling outage.

11 and 12 CCHX's are in service.

21 CCHX is in service, 22 CCHX is removed from service and drained.

All Unit 2 Circulators are O/S.

Salem Unit 1 is operating at 75% power.

12A Circulator is OIS for waterbox cleaning.

The Non-Rad Waste Treatment System is in service performing a release, and must remain in service.

Unit 1 is NOT in any active Tech Specs.

12 CVCS Monitor Tank is in Recirc using 11 CVCS Monitor Tank Pump, and Chemistry has granted permission to release the tank with a minimum dilution flow rate of 100,000 gpm.

INITIATING CUE:

You are the Unit 1 CRS. Select the release path for 12 evcs Monitor Tank lAW S1.0P-SO.WL-0002, Attachment 2, Section 2.2 Release Verification AND provide marked up drawings of the flow path from 12 cves Monitor tank to its ultimate release point.

Page 6 of 6 PSEG Restricted - Possession requires Specific Permission From Nuclear Training

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Emergency Plan TASK: Classify an event and complete an ICMF within the regulatory committed time limit (ESG~1)

TASK NUMBER: 1240020502 JPM NUMBER: 09-01 NRC SRO Admin A4-1 (ESG-1)

ALTERNATE PATH: L-I_--,I KIA NUMBER: _ _ _---=2.:.....:.4"--.4.:....;1_ _ _-1 IMPORTANCE FACTOR: 4.6 APPLICABILITY: --=R-'-O- SRO EOO ROO STAO SROm EVALUATION SETTING/METHOD: Simulate (Simulator or Classroom)

REFERENCES:

Salem ECG TOOLS AND EQUIPMENT: Inform Simulator Operators - DO NOT ERASE ANY PROCEDURES UNTIL THE SRO EVALUATOR APPROVES VALIDATED JPM COMPLETION TIME: 12 minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: 15 minutes Developed By: G Gauding Date:

Instructor Validated By: B Boos Date:

SME or Instructor Approved By: j)/~ Date:

Cf7atning De¢lrtment

Approved By:

F ~I'~R aCI Ity epresentatlve .

Date:

ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION TIME:

PERFORMED BY:

GRADE: D SAT UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

PSEG Restricted - Possession Requires Specific Approval from Nuclear Training

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Emergency Plan TASK: Classify an event and complete an ICMF within the regulatory committed time limit (ESG-1)

STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD S/U evaluation)

Provide candidate with "Tear-off sheet" Reviews initial conditions and EOP's (as I necessary - 5 minute limit prior to starting)

-~ ~- -~

START TIME: I

Start time begins when candidate Cue: The regulatory commitment time reports he/she is ready to assume SM clock has started.

duties

~-~

I 1 Reviews ECG to classify event Note: It is acceptable to use the laminated tables in the simulator, rather than the ECG I

~ t---~

2 Classifies the event Determines the classification of the event and refers to ECG Attachment 2 (ALERT) t-----~ r---. - --- -

3 Fills out Section A of Emergency Unit: 2 Coordinator Log Sheet, Attachment 2 EAL#(s):EALs 3.2.2.a (or 3.2.l.b if subcooling is OaF)

I Declared at: Current Time and Date I

Initials as EC

,---~~- ~~.-~

4 CALL communicators to the Control Pages communicators and initials as 8M Room Cue: I am the Primary Communicator

-~

PSEG Restricted - Possession Requires Specific Approval from Nuclear Training

OPERATOR TRAINING PROGRAM NAME: __________________

JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: Emergency Plan TASK: Classify an event and complete an ICMF within the regulatory committed time limit (ESG-1)

STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD S/U evaluation) 5 ACTIVATE "ERO Emergency Callout" per Cue: Activation of ERO Emergency posted instructions titled: "Emergency Callout is not required for this JPM.

Callout Activation (EP96-003) 6 COMPLETE the INITIAL CONTACT MESSAGE FORM (ICMF) (last page of

Fills out Section II of ICMF:

this attachment).

TimelDate: Time/date filled in on Attachment 2 EAL#(s): 3.2.2.a (or 3.2.2.b if subcooling is OaF)

Description of Event:

Potential Loss of the Reactor Coolant System Barrier (or Loss of the Reactor Coolant System Barrier)

Note: Description of Event is found in Section IV of the ECG.

Fills out Section III:

Checks No Radiological Release is in progress Fills out Section IV:

Retrieves wind speed and direction data from SPDS Initials for aQQroval to transmit PSEG Restricted - Possession Requires Specific Approval from Nuclear Training

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Emergency Plan TASK: Classify an event and complete an ICMF within the regulatory committed time limit (ESG-1)

STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD S/U evaluation)

7 PROVIDE the ICMF to the Primary Provides (CMF to Primary Communicator Communicator and DIRECT the within 15 minutes of START TIME Communicator to implement ECG COMPLETION TIME:

Attachment 6. -_._.......... --_ ........... --_._.......... _- -

PSEG Restricted - Possession Requires Specific Approval from Nuclear Training

ECG ATT2 Pg 2 of2 INITIAL CONTACT MESSAGE FORl\1

1. THIS IS _ _ _ _ _ _ . . . _ _ _ _, COMMUNICATOR IN THE 0 CONTROL ROOM (NAME) DTSC AT THE SALEM :NUCLEAR GENERATING STATION, IJNIT(s) NO. _ _ _-____.._"

II.

o THIS IS NOTIFICATION OF A ALERT WHICH WAS DECLARED AT ON _ _ _TODAYS DATE .

(Time-24 HR CLOCK) (DATE)

EAL #(s) 3.2.2.a (or 3.2.2.b if subcooling is OOF)

DESCRIPTION OF EVENT: Potential Loss of the Reactor Coolant System Barrier (Loss of the Reactor Coolant System Barrier

m. ~--------------------------------------------~

NOTE:

Radiological Release is defilled as: Plant Effluent> Federal Limit of 2.42E+05 uCiisec Noble Gasor2.1E+Ol uCi/secI-131.

NO RADIOLGICAL RELEASE IS IN PROGRESS. see NOTE for release o THERE IS A RADIOLOGICAL RELEASE IN PROGRESS definition IV. 0 33 FT. LEVEL WIND DIRECTION _ ***I "_ _ _ ~-_ _-WINDSPEED:---------

(From MET Computer ISPDS) (DEGREES) (NIPH)

V. 0 NO PROTECTNE ACTIONS ARE RECOl\tIMENDED AT TIDS TIME SMINITIALS EC Initials (Approval to Transmit ICMF)

SGS Rev. 08 PSEG Restricted - Possession Requires Specific Approval from Nuclear Training

TQ-AA-l 06-0303 Revision 4 JOB PERFORlVIANCE MEASURE V ALIDA nON CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to ]PM usage, revalidate JPM using steps 8 and 11 below.

- 1. Task description and number, JPM description and number are identified.

M- 2. Knowledge and Abilities (KiA) references are included.

-M-- 3. Performance location specified. (in-plant, control room, or simulator)

~ 4. Initial setup conditions are identified.

&_ 5. Initiating and terminating Cues are properly identified.

M-- 6. Task standards identified and verified by SME review.

~ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

jt_ 8. Verify the procedure referenced by ~hiS JPM match~) the most current revision of that procedure: Procedure Rev. Date!:d..;3()L1O J.. 9. Pilot test the JPM: *

a. verify Cues both verbal and visual are free of conflict, and

b. ensure performance time is accurate.

N..Lt..!-A=--__ 10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

1L....1.'-I_/>._ _ 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

sME/lnstruc~"""'iil""""",,-+_....q""""__ d'-_-6.uc--v-SMEiInstructor:_ _ _ _ _ _ _ _ _ _ _ __ Date: - - - - - -

Date: _ _ _ _ __

INITIAL CONDITIONS:

1. You have a maximum of 5 minutes to review the Emergency Operating Procedures used during this scenario to refresh your memory of all events/paths. At the end of your review you will become the Shift Manager (SM). Inform the Evaluator when you are ready to assume SM duties.

You may continue to reference the procedures or to look at the control board but "the clock will be running."

INITIATING CUE:

You are the Duty SM. Classify the event, complete the correct ECG Attachment and provide an ICMF to the Primary Communicator.

This is a Time Critical JPM.

PSEG Restricted - Possession Requires Specific Approval from Nuclear Training

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Emergency Plan TASK: Classify an event and complete an ICMF within the regulatory committed time limit (ESG-2)

TASK NUMBER: 1240020502 JPM NUMBER: 09-01 NRC SRO Admin A4-2 (ESG-2)

ALTERNATE PATH: KIA NUMBER: 2.4.41

=~~----~

IMPORTANCE FACTOR: 4.6 APPLICABILITY:

---=-::::---

RO SRO EoD ROD STAD SROW EVALUATION SETTING/METHOD: Simulate (Simulator or Classroom)

REFERENCES:

Salem ECG TOOLS AND EQUIPMENT: Inform Simulator Operators DO NOT ERASE ANY PROCEDURES UNTIL THE SRO EVALUATOR APPROVES VALIDATED JPM COMPLETION TIME: 12 minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: 15 minutes Developed By: G Gauding Date: 07-05-11 Instructor Validated By: B Boos Date: 07-28-11 SME or Instructor Approved By: u./'~ Date: "1_1..-- 11

~rling Department Approved By:

Fa~J~entatwe Date:

8 f' /1 I ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION TIME:

PERFORMED BY:

GRADE: D SAT D UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

PSEG Restricted - Possession Requires Specific Approval from Nuclear Training

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM: Emergency Plan TASK: Classify an event and complete an ICMF within the regulatory committed time limit (ESG-2)

TASK NUMBER: 1240020502 INITIAL CONDITIONS:

1. You have a maximum of 5 minutes to review the Emergency Operating Procedures used during this scenario to refresh your memory of all events/paths. At the end of your review you will become the Shift Manager (SM). Inform the Evaluator when you are ready to assume SM duties. You may continue to reference the procedures or to look at the control board but "the clock will be running." If there are multiple ECG calls, classify the most severe.

INITIATING CUE:

You are the Duty SM. Classify the event, complete the correct ECG Attachment and provide an ICMF to the Primary Communicator.

This is a Time Critical JPM.

Successful Completion Criteria:

1. All critical steps completed.

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Task Standard for Successful Completion:

1. Complete the ICMF with the classification of SAE under EAL 5.1.3. and provide it to the Primary Communicator within 15 minutes of Start Time.

PSEG Restricted - Possession Requires Specific Approval from Nuclear Training

OPERATOR TRAINING PROGRAM NAME: -------------------

JOB PERFORMANCE MEASURE DATE: -------------------

SYSTEM: Emergency Plan TASK. Classify an event and complete an ICMF within the regulatory committed time limit (ESG-2)

STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD StU evaluation)

Provide candidate with 'Tear-off sheet" Reviews initial conditions and EOP's (as necessary - 5 minute limit prior to starting)

START TIME:

Start time begins when candidate Cue: The regulatory commitment time reports he/she is ready to assume SM clock has started.

duties 1 Reviews ECG to classify event Note: It is acceptable to use the laminated tables in the simulator, rather than the ECG 2 Classifies the event Determines the classification of the event and refers to ECG Attachment 3 (SAE) 3 Fills out Section A of Emergency Unit: 2 Coordinator Log Sheet, Attachment 3 EAL#(s):EALs 5.1.3 Declared at: Current Time and Date Initials as EC 4 CALL communicators to the Control Pages communicators and initials as SM Room Cue: I am the Primary Communicator PSEG Restricted - Possession Requires Specific Approval from Nuclear Training

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: Emergency Plan Classify an event and complete an ICMF within the regulatory committed time limit (ESG~2)

TASK STEP COMMENTS STEP (Required for UNSAT

(*Denotes a Critical Step) EVAL

NO. STANDARD S/U evaluation) 5 ACTIVATE "ERO Emergency L.:allout" per Cue: Activation of ERO Emergency posted instructions titled: "Emergency Callout is not required for this JPM.

Callout Activation (EP96~003)

~------------------------------+-----~ ~

6 COMPLETE the INITIAL CONTACT MESSAGE FORM (ICMF) (last page of

Fills out Section" of ICMF:

this attachment).

TimelDate: Time/date filled in on Attachment 3 EAL#(s): 5.1.3 Description of Event:

Reactor Trip Failure with power above 5%

Note: Description of Event is found in Section IV of the ECG.

Fills out Section III:

Checks No Radiological Release is in progress Retrieves wind speed and direction data from SPDS Initials for approval to transmit

7 PROVIDE the ICMF to the p ... ","""" Provides ICMF to Primary Communicator Communicator and DIRECT 15 minutes of START TIME Communicator to implement ECG COMPLETION TIME: ______

Attachment 6.

PSEG Restricted - Possession Requires Specific Approval from Nuclear Training

ECG ATT3 Pg 2 of2 INITIAL CONTACT MESSAGE FORl"l L THIS IS _ _ _ _ _ _ _ _ _ _, COMMUNICATOR IN THE 0 CONTROL ROOM (NAME) [J TSC o EOF AT THE SALEM NUCLEAR GENERATING STATION, VNIT(s) NO. ~__- _____.

II.

o THIS IS NOTIFICATION OF A SITE AREA EMERGENCY WlIICH WAS DECLARED AT TIME ON _ _ _TODAYS DATE (Time-24 fiR CLOCK) (DATE)

EAL #(s) 5.

1.3 DESCRIPTION

OF EVENT: Reactor Trip Failure with power above 5%

III.,---_ _~_~_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __,

NOTE:

.l.'-"'.UVJ.V);:,J.,- Federal Limit of 2.42E+05 uCiJsec Noble NO RADIOLGICAL RELEASE IS IN PROGRESS. see NOTE for release o THERE IS A RADIOLOGICAL RELEASE IN PROGRESS definition IV. 33 FT. LEVEL WIND DIRECTION (From): WIND SPEED:

(From MET Computer iSPDS) (DEGREES) (1-fPH)

V. 0 NO PROTECTIVE ACTIONS ARE RECO\,ThIENDED AT TIDS TIME SMINITIALS EC Initials (Approval to Transmit ICMF)

SGS Rev. 09 PSEG Restricted - Possession Requires Specific Approval from Nuclear Training

TQ-AA-I06-0303 Revision 4 JOB PERFOMIA.NCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be perfonned upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 and 11 below.

M- 1. Task description and number, JPM description and number are identified.

M 2. Knowledge and Abilities (KJ A) references are included .

.~ 3. Perfonnance location specified. (in-plant, control room, or simulator) 4. Initial setup conditions are identified.

~ 5. Initiating and tenninating Cues are properly identified.

L 6. Task standards identified and verified by SME review.

& 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

&AO 8. Verify the procedure referenced bY)fll.'55 JPM matches the most current revision of that procedure: Procedure Rev. ~'1-- Date

~ 9. Pilot test the JPM:

a. verify Cues both verbal and visual are free of connict, and

b. ensure performance time is accurate.

____ 10. If the JPM cannot be performed as written ,\lith proper responses, then revise the JPM.

__~__ 11. When JPM is revalidated, SME or Instructor and date JPM cover page.

SME/lnst Date: o7""8-~ 1)

SME/lnstructor: Date: ------

SME/lnstructor: Date: .~---- ...........

INITIAL CONDITIONS:

1. You have a maximum of 5 minutes to review the Emergency Operating Procedures used during this scenario to refresh your memory of all events/paths. At the end of your review you will become the Shift Manager (SM). Inform the Evaluator when you are ready to assume SM duties.

You may continue to reference the procedures or to look at the control board but "the clock will be running."

INITIATING CUE:

You are the Duty SM. Classify the event, complete the correct ECG Attachment and provide an ICMF to the Primary Communicator.

This is a Time Critical JPM.

PSEG Restricted - Possession Requires Specific Approval from Nuclear Training

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Emergency Plan TASK: Classify an event and complete an ICMF within the regulatory committed time limit (ESG-3)

TASK NUMBER: 1240020502 JPM NUMBER: 09-01 NRC SRO Admin A4-3 (ESG-3)

ALTERNATE PATH: I I KIA NUMBER: 2.4.41

~

IMPORTANCE FACTOR: 4.6

=-R~O---

APPLICABILITY: SRO EOD ROO STAD SROm EVALUATION SETTING/METHOD: Simulate (Simulator or Classroom)

REFERENCES:

Salem ECG TOOLS AND EQUIPMENT: Inform Simulator Operators - DO NOT ERASE ANY PROCEDURES UNTIL THE SRO EVALUATOR APPROVES VALIDATED JPM COMPLETION TIME: 12 minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: 15 minutes Developed By: G Gauding Date: 07-05-11 Instructor Validated By: B Bonner Date: 07-28-11 SME or Instructor J4~nt Approved By: Date: '9 - 1.... - I I Approved By:

~~e Date: g /. /1 I ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION TIME:

PERFORMED BY:

GRADE: 0 SAT D UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM: Emergency Plan TASK: Classify an event and complete an ICMF within the regulatory committed time limit (ESG-3)

TASK NUMBER: 1240020502 INITIAL CONDITIONS:

1. You have a maximum of 5 minutes to review the Emergency Operating Procedures used during this scenario to refresh your memory of all events/paths. At the end of your review you will become the Shift Manager (SM). Inform the Evaluator when you are ready to assume SM duties. You may continue to reference the procedures or to look at the control board but "the clock will be running." If there are multiple ECG calls, classify the most severe.

INITIATING CUE:

You are the Duty SM. Classify the event, complete the correct ECG Attachment and provide an ICMF to the Primary Communicator.

This is a Time Critical JPM.

Successful Completion Criteria:

1. All critical steps completed.

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

114. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress IS being made.

Task Standard for Successful Completion:

1. Complete the ICMF with the classification of ALERT under EAL 5.1.2.a and provide it to the Primary Communicator within 15 minutes of Start Time.

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Emergency Plan TASK: Classify an event and complete an ICMF within the regulatory committed time limit (ESG-3)

STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD S/U evaluation)

I Provide candidate with 'Tear-off sheet" Reviews initial conditions and EOP's (as necessary 5 minute limit prior to starting)

START TIME:

Start time begins when candidate Cue: The regulatory commitment time reports he/she is ready to assume SM clock has started.

duties 1 Reviews ECG to classify event Note: It is acceptable to use the laminated tables in the simulator, rather than the ECG r-----~~

2 Classifies the event Determines the classification of the event i and refers to ECG Attachment 2 (ALERT)

I r-- ~

3 Fills out Section A of Emergency Unit: 2 Coordinator Log Sheet, Attachment 2 EAL#(s):EALs 5.1.2.a Declared at: Current Time and Date Initials as EC

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

4 CALL communicators to the Control Pages communicators and initials as SM Room Cue: I am the Primary Communicator

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE: -------------------

SYSTEM: Emergency Plan TASK: Classify an event and complete an ICMF within the regulatory committed time limit (ESG-3)

STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD S/U evaluation) 5 ACTIVATE "ERO Emergency Callout" per Cue: Activation of ERO Emergency posted instructions titled: "Emergency Callout is not required for this JPM.

Callout Activation (EP96-003) 6 COMPLETE the INITIAL CONTACT MESSAGE FORM (ICMF) (last page of

Fills out Section II of ICMF:

this attachment).

Time/Date: Time/date filled in on Attachment 2 EAL#( s): 5.1.2.a Description of Event:

Reactor Trip Failure Note: Description of Event is found in Section IV of the ECG.

Fills out Section III:

Checks No Radiological Release is in progress Fills out Section IV:

Retrieves wind speed and direction data from SPDS Initials for am2roval to transmit

7 PROVIDE the ICMF to the Primary Provides ICMF to Primary Communicator Communicator and DIRECT the within 15 minutes of START TIME Communicator to implement ECG COMPLETION TIME:

Attachment 6.

ECG ATT2 Pg 2 of2 INITIAL CONTACT MESSAGE FORt"I L THIS IS ------:c-::--:----:c-::----' COMMUNICATOR IN THE 0 CONTROL ROOM (NAME) 0 TSC AT THE SALEM NUCLEAR GEr..'ERATING STATION, VNIT(s) NO. _ _2_ _ _.

TI.

o THIS IS NOTIFICATION OF A ALERT WHICH WAS DECLARED AT ON _ _ _TODAYS DATE_ _

(Time-24 HR CLOCK) (DATE)

EAL #(s) 5.1.2.a DESCRIPTION OF EVENT: Reactor Trip Failure III.,--_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _-,

Radiological Release is defmed as: Plant Effluent> Federal Limit of2.42E+05 uCiisec Noble RADIOLGICAL RELEASE IS IN PROGRESS. see NOTE for release o THERE A RADIOLOGICAL RELEASE IN PROGRESS defInition IV. 0 33 FT. LEVEL WIND DIRECTION (From): WIND SPEED: _ _ _ _ __

MET Computer ISPDS) (DEGREES) (MPH)

V. NO PROTECTIVE ACTIONS ARE RECOMMENDED AT THIS TIME SM INITIALS EC Initials (Approval to Transmit ICMF)

SGS Rev. 08

TQ-AA-I06-0303 Revision 4 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be perfonned upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 and 11 below.

-hihlo<c---- 1. Task description and number, JPM description and number are identified.

-7"'!T-- 2. Knowledge and Abilities (KIA) references are included.

--'-:1-..--- 3. Perfonnance location specified. (in-plant, control room, or simulator)

---'\~'=-_ 4. Initial setup conditions are identified.

--:~c-- 5. Initiating and terminating Cues are properly identified.

~ 6. Task standards identified and verified by SME review.

~ 7. Critical steps meet the criteria for critical sfeps and are identified with an asterisk (*).

18. Verify the procedure referenced by this JPM'matches the most current revision of that procedure: Procedure Rev. ~ Date '71-ki 10 o

-1J!f----

9. Pilot test the JPM:

a. verify Cues both verbal and visual are free of conflict, and

b. ensure perfonnance time is accurate.

(Q) 10. If the JPM cannot be perfonned as written with proper responses, then revise the JPM.

-..fl>>- 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

n,re 7h~

SME/Instructor:_ _ _ _ _ _ _ _ _ _ _ __ Date: - - - - - -

SME/Instructor:_ _ _ _ _ _ _ _ _ _ _ __ Date:

INITIAL CONDITIONS:

1. You have a maximum of 5 minutes to review the Emergency Operating Procedures used during this scenario to refresh your memory of all events/paths. At the end of your review you will become the Shift Manager (8M). Inform the Evaluator when you are ready to assume SM duties.

You may continue to reference the procedures or to look at the control board but "the clock will be running."

INITIATING CUE:

You are the Duty 8M. Classify the event, complete the correct ECG Attachment and provide an ICMF to the Primary Communicator.

This is a Time Critical JPM.

OPERATOR TRAINING PROGRAM

- - - -JOB - -PERFORMANCE MEASURE STATION: SALEM l

SYSTEM: Rod Control TASK: Take corrective actions for a dropped control rod(s)

TASK NUMBER: 1140330401 JPM NUMBER: 09-01 NRC Sim a ALTERNATE PATH: IXI KIA NUMBER: 003 AA2.03 IMPORTANCE FACTOR: 3.6 3.8 APPLICABILITY: RO SRO EO RO jX] STA SRO EVALUATION SETIING/METHOD: Simulator

REFERENCES:

S2. OP-AS. ROO-0002 Rev. 10 (checked 6/30/11 )

TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 5 minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 06*17*11 Instructor i Validated By: K Riedmuller Date: 06-30-11 SME or Instructor Approved By:

~~

Approved By:

o~~ Department Date: ..., /b/' I ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION TIME:

PERFORMED BY:

GRADE: SAT UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

PSEG Restricted - Possession Requires Specific Approval from Nuclear Training Page 1 of 8

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE: _________________________

SYSTEM: Rod Control TASK: Take corrective actions for 2 dropped control rods TASK NUMBER: 1140330401 SIMULATOR SETUP IC-251 Insert RT-1, RD0267, ANY ROD DROPS INTO RX, Final Severity 5 after candidate has assumed the watch.

Modify RD0267 ANY ROD DROPS INTO RX, to Final Severity 53 when candidate has completed step 3.10 of S2.0P-AB.ROD-0002 OR if candidate attempts to change Main Turbine load due to Tavg being >1.5 degrees lower than Tref.

INITIAL CONDITIONS:

40% power, BOl.

A power reduction to bring the Main Turbine off-line is on hold.

INITIATING CUE: You are the Reactor Operator. Respond to all alarms and indications.

Successful Completion Criteria:

1 All critical steps completed .

. 2. All sequential steps completed in order.

i 3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Task Standard for Successful Completion:

1. Candidate places Rod Control in Manual following 1st dropped rod.

2. Candidate trips the reactor upon discovery of 2nd dropped rod.

PSEG Restricted - Possession Requires Specific Approval from Nuclear Training Page 2 of 8

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: ROD CONTROL TASK: Take corrective actions for a dropped control rod( s)

STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD S/U evaluation)

SIMULATOR OPERATOR:

Insert RT-1 RD0267, ANY ROD DROPS Candidate announces cluster of rod related INTO RX, Final Severity 5, when "E" Window OHAs as unexpected alarms.

candidate assumes the watch. Announces indications of rod 2SA 1 dropped into the core.

Enters S2.0P-AB.ROD-0002, Dropped Rod.

2.1 IF more than one rod is verified to be Verifies only 1 rod has dropped into core.

tripped, THEN Manually TRIP Reactor AND GO TO 2-EOP-TRIP-1, Reactor Trip OR Safety Injection.

3.1 PLACE Rod Bank Selector Switch in Places Rod Bank Selector Switch in MAN.

MAN.

3.2 IF a Turbine load change is in progress ... Verifies no turbine load change in progress.

PSEG Restricted - Possession Requires Specific Approval from Nuclear Training Page 3 of 8

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE: ___________________

SYSTEM: ROD CONTROL TASK: Take corrective actions for a dropped control rod(s)

STEP COMMENTS STEP EVAL (Required for UNSAT

(*Denotes a Critical Step)

NO. STANDARD StU evaluation) 0 3.3 ADJUST Tave to within 1.50 of program as Verifies Tave is within 1.5 of program.

follows:

IF Main Turbine is operating, Simulator Operator: IF operator THEN adjust Turbine load.

attempts to lower turbine load, then

IF Main Turbine is NOT operating, change RT-1 as described on next page THEN ADJUST Steam Dumps now.

OR 21-24MS10 valves.

3.4 Is Reactor subcritical as a result of the Answers NO, GOES TO step 3.9 dropped rod?

3.9 IF AT ANY TIME a power reduction Determines no power reduction is becomes necessary, THEN BORATE necessary.

AND ADJUST Turbine load or Steam Dump System flowrate to maintain T ave within 1.50 F of program.

3.10 Is power above 50% of RATED Answers NO, and GOES TO Step 3.12 THERMAL POWER?

SIMULATOR OPERATOR:

Modify malfunction RD0267, ANY ROD DROPS INTO RX, to Final Severity 53, when candidate has completed step 3.10 of S2.0P-AB.ROD-0002.

PSEG Restricted - Possession Requires Specific Approval from Nuclear Training Page 4 of 8

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: ROD CONTROL TASK: Take corrective actions for a dropped control rod(s)

STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD S/U evaluation)

1 IF more than one rod is verified to be Candidate should observe a second rod tripped, THEN Manually TRIP Reactor bottom light by direct observation, or by AND GO TO 2-EOP-TRIP-1, Reactor Trip depressed power in the region of the 2 OR Safety Injection. dropped rods, Terr or Tavg lowering, or OHA 0-32 TAVE LO, and MANUALLY TRIP the Reactor lAW Step 2.1.

Evaluator: See next step if candidate does not recognize the second dropped rod and continues in the procedure. (This will allow the candidate to continue in the JPM until the 2 times validation time has been reached and the JPM is terminated.)

3.12 REQUEST Maintenance to determine if Candidate contacts Maintenance or an Individual Rod Position Indicator requests CRS to contact Maintenance to (IRPI) malfunction has occurred. determine if an IRPI malfunction has occurred.

Cue: Maintenance has been contacted.

3.13 Has an IRPI malfunction occurred? Candidate answers NO based on rod bottom, OHAs, and primary plant parameter changes, and GOES TO Step 3.15.

3.15 INITIATE a power reduction to <75% Candidate recognizes power is 40%.

Rated Thermal Power ...

PSEG Restricted - Possession Requires Specific Approval from Nuclear Training Page 5 of 8

OPERATOR TRAINING PROGRAM NAME: __________________

JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: ROD CONTROL TASK: Take corrective actions for a dropped control rod(s)

STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD S/U evaluation) 3.16 REQUEST Reactor Engineering Candidate contacts Reactor Engineering or assistance to recover rod. requests CRS to contact Reactor Engineering for assistance in recovering dropped rod.

Cue: Reactor Engineering has been contacted.

3.17 Is dropped rod to be recovered, per Cue: Reactor Engineering will be Reactor Engineering? performing a flux map to aid in determination of whether a recovery will be made of the dropped rod.

Terminate the JPM once the candidate has inserted a manual Reactor Trip or reaches two times the validation time.

PSEG Restricted - Possession Requires Specific Approval from Nuclear Training Page 6 of 8

JOB PERFORl'VIANCE MEASl.JRE VALIDATION CHECKLIST NOTE: All steps ofthis checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 and 11 below.

\lCv-- 1. Task description and number, JPM description and number are identified.

\lC/--- 2. Knowledge and Abilities (KiA) references are included.

\~ 3. Performance location specified. (in-plant, control room, or simulator)

\~ 4. Initial setup conditions are identified.

It.(r.- 5. Initiating and terminating Cues are properly identified.

\f...Cr- 6. Task standards identified and verified by SME review.

\If..t-- 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

v...tv- 8. Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. Date '-10' II

\1..Cr-__ 9. Pilot test the JPM:

a. verify Cues both verbal and visual are free of conflict, and

b. ensure performance time is accurate.

~___ 10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

____ 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

SME/Instructor:_f+-~=-=-_*--Ln-..:..:\'-t-'aCL~='-'---"-----'__ (.*30*"

Date: . _ ----

SME/Instructor: Date: - - - - - -

SME/Instructor:__________. _ _~. Date: ._ _ _ _ __

PSEG Restricted - Possession Requires Specific Approval from Nuclear Training Page 7 of 8

INITIAL CONDITIONS:

40% power, BOL A power reduction to bring the Main Turbine off-line is on hold.

INITIATING CUE:

You are the Reactor Operator. Respond to all alarms and indications.

PSEG Restricted - Possession Requires Specific Approval from Nuclear Training Page 8 of 8

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: Salem Generating Station SYSTEM: Emergency Core Cooling Systems TASK: Raise ECCS Accumulator Level with a Safety Injection Pump TASK NUMBER: 0065010101 JPM NUMBER: 09-01 NRC Sim b ALTERNATE PATH: 0 KIA NUMBER: 006 A4.07

~

IMPORTANCE FACTOR: - - 4.4 4.4 APPLICABILITY: RO SRO EoD ROW STAD SROW EVALUATION SETTING/METHOD: Simulator / Perform

REFERENCES:

S2.0P-SO.SJ-0002, Accumulator Operations, Rev. 22 TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 8 minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 07-09-11 Instructor Validated By: S Harris Date: 07-28-11 SME or Instructor Approved By: ~C:-~ Date: '2-2-- 1

/raPnin g Depsvtment Approved By:

Operatlons

~jRepresentative . Date: ~ {*id ACTUAL ...IPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION TIME:

PERFORMED BY:

GRADE: D SAT D UNSAT

. REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

PSEG Restricted Possession Requires Specific Approval from Nuclear Training Page 1 of 8

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME: __________________________

DATE:

SYSTEM: Emergency Core Cooling Systems TASK: Raise ECCS Accumulator Level with a Safety Injection Pump TASK 006501 01 01 NUMBER:

INITIAL IC-254 CONDITIONS:

1. The plant is at 100% power with all systems in their normal alignment with control systems in automatic.

2. 24 Accumulator is at 57.9% level.

3. The Safety Injection System is available.

4. RWST Boron Concentration is 2400 ppm.

INITIATING CUE:

Raise 24 ECCS Accumulator to 60% using 21 SI pump lAW S2.0P-SO.SJ-0002, Accumulator Operations, Section 5.2.

Successful Completion Criteria:

1. All critical steps completed.

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made (and NRC concurrence is obtained).

Task Standard for Successful Completion:

1. Raise 24 Accumulator to 60% using 21 SI pump, and return system to normal lineup.

PSEG Restricted - Possession Requires Specific Approval from Nuclear Training Page 2 of 8

OPERATOR TRAINING PROGRAM NAME: __________________

JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: Emergency Core Cooling Systems TASK: Raise ECCS Accumulator Level with a Safety Injection Pump STEP COMMENTS STEP (*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD S/U Evaluation}

I Provide copy of S2.0P-SO.SJ-0002(Q), Reviews procedure, and initials all Accumulator Operations, with Prerequisites Precautions and Limitations.

signed off.

5.2.1 ENSURE either of the following conditions exist:

ALL RCS Cold Leg Temperatures Determines ALL RCS Cold Leg

>312°F Temperatures >312°F.

OR

The Reactor Vessel Head is Removed.

--- r-- - -

5.2.2 IF RCS Pressure <2000 psig, THEN Determines RCS pressure is >2000 ENSURE CLOSED 21SJ134, COLD LEG psig and marks step NtA..

DISCHARGE.

r------

5.2.3 START 21 Safety Injection Pump. Operator depresses 21 Safety Injection Pump START PB.

Cue if required: IF operator asks for a Field Operator to do pre-start checks on 21 SI pump, THEN report as NEO that 21 SI Pump is ready for start.

PSEG Restricted - Possession Requires Specific Approval from Nuclear Training Page 3 of 8

OPERATOR TRAINING PROGRAM NAME: __________________

JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: Emergency Core Cooling Systems TASK: Raise ECCS Accumulator Level with a Safety Injection Pump STEP COMMENTS STEP (*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD stu Evaluation)

5.2.4 OPEN 2SJ53, 21 SI PUMP DISCHARGE Pushes and holds 2SJ53 21 SI PUMP TEST LINE VALVE. DISCHARGE TEST LINE VALVE OPEN PB until open light illuminates.

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

5.2.5 OPEN 2SJ123, TEST LINE TO CVCS HUT. Depresses 2SJ123 TEST LINE TO CVCS HUT OPEN PB and notes change in light status.

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

'Ii 5.2.6 OPEN associated Accumulator fill valve: Depresses 24SJ20 24 ACCUMULATOR FILL OPEN PB;

21SJ20, 21 ACCUMULATOR FILL notes change in light status, and monitors level on the applicable level

22SJ20, 22 ACCUMULATOR FILL channels.

23SJ20, 23 ACCUMULATOR FILL

24SJ20, 24 ACCUMULATOR FILL

- --_.- ---_.- ~----.- -----_.

PSEG Restricted Possession Requires Specific Approval from Nuclear Training Page 4 of 8

OPERATOR TRAINING PROGRAM NAME: __________________

JOB PERFORMANCE MEASURE DATE: ___________________

SYSTEM: Emergency Core Cooling Systems TASK: Raise ECCS Accumulator Level with a Safety Injection Pump STEP COMMENTS STEP (*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD stU Evaluation) I

5.2.7 When desired level is reached, CLOSE the Cue: After level starts to rise in 24 associated Accumulator fill valve: Accumulator, state: "24 Accumulator level has risen to 60%."

21SJ20, 21 ACCUMULATOR FILL

22SJ20, 22 ACCUMULATOR FILL After acknowledging cue, depresses

23SJ20, 23 ACCUMULATOR FILL 24SJ20 24 ACCUMULATOR FILL CLOSE PB.

24SJ20, 24 ACCUMULATOR FILL 5.2.8 If required, REPEAT Steps 5.2.6 and 5.2.7 Determines no other Accumulators will to fill additional Accumulators. be filled.

5.2.9 CLOSE 2SJ53. Depresses 2SJ53 CLOSE PB.

e--- ----- -- -- ----- -----

5.2.10 CLOSE 2SJ123. Operator depresses 2SJ123 CLOSE PB.

PSEG Restricted - Possession Requires Specific Approval from Nuclear Training Page 5 of 8

OPERATOR TRAINING PROGRAM NAME: __________________

JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: Emergency Core Cooling Systems TASK: Raise ECCS Accumulator Level with a Safety Injection Pump STEP COMMENTS STEP (*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD S/U Evaluation)

5.2.11 STOP 21 Safety Injection Pump. Depresses 21 SI Pump STOP PB.

TERMINATING CUE: Terminate after 21 SI pump is stopped.

PSEG Restricted Possession Requires Specific Approval from Nuclear Training Page 6 of 8

OPERATOR TRAINING PROGRAM JOB PERFOR.!.vIANCE MEAS1JRE JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 and 11 below.

__h__ 1. Task description and number, JPM description and number are identified.

__h-->-_2. Knowledge and Abilities (KIA) references are included .

.....,L~C'\4-- 3. Performance location specified. (in-plant. control room, or simulator)

__\'""/\~_ 4. Initial setup conditions are identified.

---tLr o,-",..- 5. Initiating and terminating Cues 'are properly identified.

k 6. Task standards identified and verified by SME review.

___k_7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

~ 8. Verify the procedure referenced b.l this JPM matches t most current revision of that procedure: Procedure Rev. d:t Date 2-- (}

- 4 9 . Pilot test the JPM:

. a. verify Cues both verbal and visual are free of conflict, and

b. ensure performance time is accurate.

10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

SME/lnstructor:___.... ~dz:}~~-+-t~"-"::::::""---='_ ___ Date: -..!-f--=--=--f--..A..1..

SME/lnstructor: Date: _ _ _ _ __

SME/lnstructor:_ _ _ _ _ _ _ _ _ _ _ __ Date: _ _ _ _ ___

PSEG Restricted - Possession Requires Specific Appronal from NuciearTraining Page 7 of 8

OPERATOR TRAINING PROGRA1VI JOB PERFORMA1~CE MEASURE INITIAL CONDITIONS:

1. The plant is at 100% power with all systems in their normal alignment with control systems in automatic.

2. 24 Accumulator is at 57.9% level.

3. The Safety Injection System is available.

4. RWST Boron Concentration is 2400 ppm.

INITIATING CUE:

Raise 24 ECCS Accumulator to 60% using 21 SI pump lAW S2.0P-SO.SJ-0002, Accumulator Operations, Section 5.2.

PSEG Restricted - Possession Requires Specific Approval from Nuclear Training Page 8 of 8

OPERATIONS TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Pressurizer Pressure and Level TASK: TCAF Pressurizer Pressure Malfunction (Failed open Pressurizer Spray Valve)

TASK NUMBER: 1140240401 JPM NUMBER: 09-01 NRC Sim c ALTERNATE PATH: m KIA NUMBER:

IMPORTANCE FACTOR:

010 A4.01

~

3.7 3.5 APPLICABILITY: RO SRO EoD ROm STAD SROm EVALUATION SETTING/METHOD: Simulator

REFERENCES:

S2.0P-AB.PZR-0001, Rev. 18 (Rev. checked 6-30-11)

TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 4 min TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A- - -

Developed By: G Gauding Date: 6-17-11 Instructor Validated By: W. Neiheiser Date: 6-30-11 SME or Instructor Approved By: /1cJ-G Date: 7- 2( - if

~ningDe~t Approved By: -S~--

Operaflons Department Date: 7 lsI I ,

ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION TIME:

PERFORMED BY:

GRADE: D SAT D UNSAT REASON, IF UNSATISFACTORY:

. EVALUATOR'S SIGNATURE: DATE:

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 1 of9

OPERATIONS TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM: Pressurizer Pressure and Level TASK: TCAF Pressurizer Pressure Malfunction (Failed open Pressurizer Spray Valve)

TASK 1140240401 NUMBER:

SIMULATOR SETUP: IC-253 4% power, BOL.

110 B304 OVLO Pressurizer Relief Valve Outlet Temperature- Value: 98.6 MALF: PR018A PZR PORV 2PR1 develops leak Value:40000 Tied to ET-1 RT-1 PR0019A PZR Spray Valve 2PS1 fails open ET-1 kal06tph 23 RCP Stop INITIAL CONDITIONS:

Reactor power is stable at 4.0% power. The power ascension is on hold temporarily.

INITIATING CUE:

You are the Reactor Operator. Respond to all indications and alarms.

Successful Completion Criteria:

1. All critical steps completed.

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made (and NRC concurrence is obtained).

Task Standard for Successful Completion:

1. Trip Rx.

2. Stops 21 and 23 RCP.

3. Stop 22 OR 24 RCP.

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OPERATIONS TRAINING PROGRAM NAME: ___________________

JOB PERFORMANCE MEASURE DATE: ___________________

SYSTEM: Pressurizer Pressure and Level TASK: TCAF Pressurizer Pressure Malfunction (Failed open Pressurizer Spray Valve)

STEP COMMENTS STEP (* Denotes a Critical Step) EVAL (Required for UNSAT NO. STANDARD S/U Evaluation) .

Simulator Operator: Note: The time between the 2PS1 I failing open and RCS pressure Insert RT-1 on direction of evaluator. reaching 2,000 psig is - 4 minutes and 15 seconds.

MALF: PR0019A, 2PS1 fails open Recognizes lowering PZR Pressure and/or alarm and/or change in 2PS1 position.

Acknowledges OHA E-28 PZR HTR ON PRESS LO. Recognizes 22 PZR B/U heaters energized. If candidate refers to ARP for OHA E-28, it directs entry into S2.0P-AB.PZR-0001, Pressurizer Pressure Malfunction.

Enters S2.0P-AB.PZR-0001 directly or via OHA E-28 ARP.

Note: It is acceptable for the candidate to attempt closing 2PS1 prior to entering S2.0P-AB.PZR-001.

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OPERATIONS TRAINING PROGRAM NAME: __________________

JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: Pressurizer Pressure and Level TASK: TCAF Pressurizer Pressure Malfunction (Failed open Pressurizer Spray Valve)

STEP COMMENTS STEP (* Denotes a Critical Step) EVAL (Required for UNSAT NO. STANDARD stU Evaluation) 3.1 INITIATE Attachment 1 Continuous Initiates Attachment 1 Continuous Action Summary. Action Summary.

Note: There is a CAS action to trip the Rx if RCS pressure lowers to 2,000 psig and continues to drop. IF the candidate were to trip the Rx during this JPM based on that CAS action and not at step 3.24.A on page 6 as expected, THEN AFTER the candidate has tripped the Rx, verified the Main Turbine is tripped, verified SI not actuated or required and all 4KV I

vital buses energized, the following cue must be given:

Cue: The immediate actions of TRIP-1 have been verified by the CRS and RO. The CRS directs you to continue actions of S2.0P AB.PZR-0001, while the remaining crew members will continue to perform TRIP-1.

"-~r 3.2 Is POPS in service? Determines POPS is not in service by initial conditions or console indications.

L"_,--_ "

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OPERATIONS TRAINING PROGRAM NAME: ___________________

JOB PERFORMANCE MEASURE DATE: ___________________

SYSTEM: Pressurizer Pressure and Level TASK: TCAF Pressurizer Pressure open Pressurizer Spray Valve)

STEP COMMENTS STEP (* Denotes a Critical Step) EVAL (Required for UNSAT NO. STANDARD S/U Evaluation) 3.3 Is the controlling Pressurizer Pressure Determines Pressurizer Pressure Control Channel (lor III) failed? Control Channel (lor III) is not failed and GOES TO Step 3.11 3.11 Is the Master Pressure Controller Determines Master Pressure failed? (Refer to Attachment 2 for Controller is not failed and GOES TO guidance) Step 3.17 (may not refer to Attachment 2 if 2PS1 has been noted open with pressure below closing setpoint.)

3.17 Is a Spray Valve(s) failed? (Refer to Determines 2PS1 is failed open.

Attachment 2 for guidance) 3.18 PLACE the Spray Valve(s) in MANUAL Depresses MANUAL PB for 2PS1 and verifies AUTO light extinguished and MANUAL light illuminates.

3.19 OPERATE the Spray Valves to control Depresses the CLOSE PB for 2PS1 pressure consistent with Attachment 2. and recognizes that 2PS1 remains open.

3.20 PLACE all Pressurizer heaters in Determines all PZR heaters are in MANUAL and ON MANUAL and ON.

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OPERATIONS TRAINING PROGRAM NAME: ___________________

JOB PERFORMANCE MEASURE DATE: ___________________

SYSTEM: Pressurizer Pressure and Level TASK: TCAF Pressurizer Pressure Malfunction (Failed open Pressurizer Spray Valve)

STEP COMMENTS STEP (* Denotes a Critical Step) EVAL (Required for UNSAT NO. STANDARD S/U Evaluation) 3.21 Has pressure control been regained? Determines pressure control has not been regained since 2PS1 remains open.

3.22 Is RCS pressure dropping rapidly? Determines RCS pressure is dropping rapidly from console indication.

3.23 Are Reactor Trip Breakers CLOSED? Determines Reactor Trip Breakers are closed by initial conditions or console indication.

3.24 PERFORM the following:

A

A. TRIP the Reactor. Initiates a Reactor Trip using either MANUAL TRIP handle.

3.24 B. Is Reactor Trip Confirmed? Determines Reactor Trip is confirmed B after identifying PRNI reading < 5%

and IR NI indication dropping.

3.24 STOP 21 AND 23 RCPs: Depresses STOP PBs for 21 and 23 C RCP and verifies start lights extinguish and stop lights illuminates.

Simulator Operator: Ensure ET-1 is TRUE when RCP stop PB is depressed.

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OPERATIONS TRAINING PROGRAM NAME: __________________

JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: Pressurizer Pressure and Level TASK: TeAF Pressurizer Pressure Malfunction (Failed open Pressurizer Spray Valve)

STEP COMMENTS STEP (* Denotes a Critical Step) EVAL (Required for UNSAT NO. STANDARD StU Evaluation)

3.24 IF Pressurizer Pressure continues to Determines Pressurizer Pressure D drop, THEN STOP all but one RCP. continues to drop, and depresses STOP PB on 22 OR 24 RCP and verifies start light extinguishes and stop light illuminates.

3.24 E GO TO 2-EOP-TRIP-1, Reactor Trip or Begins performing Immediate Actions Safety Injection, AND CONTINUE with of 2-EOP-TRIP-1, Reactor Trip or this procedure. Safety Injection.

Cue: When candidate begins performing Immediate Actions of 2 EOP-TRIP-1, Reactor Trip or Safety Injection, state JPM is complete.

I PSEG Restricted - Possession Requires Specific Permission from Nuclear Training Page 7 of 9

OPERATIONS TRAINING PROGRAM JOB PERFORMANCE MEASURE JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to "PM usage, revalidate JPM using steps 8 and 11 below.

__W __ 1. Task description and number, JPM description and number are identified.

__0_ _ 2. Knowledge and Abilities (KIA) references are included.

__W __ 3. Performance location specified. (in-plant, control room, or simulator)

_->[,J<<---_4. Initial setup conditions are identified.

__(,J __ 5. Initiating and terminating Cues are properly identified.

__{)J __ 6. Task standards identified and verified by SME review.

_c....&J__ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

_-"vJ~_ 8. Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. -LL Date "~30 -I (

_...;..0__ 9. Pilot test the JPM:

a. verify Cues both verbal and visual are free of conflict, and

b. ensure performance time is accurate.

____ 10. If the JPM cannot be performed as written with proper responses, then revise the ~IPM.

____ 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

@j./lnstructor: w::QE) ~ Date: _{o_-3_D_-_\\_

SMEllnstructor:_ _ _ _ _ _ _ _ _ _ _ __ Date: _ _ _ _ __

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OPERATIONS TRAINING PROGRAM JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

Reactor power is stable at 4.0% power. The power ascension is on hold temporarily.

INITIATING CUE: You are the Reactor Operator. Respond to all indications and alarms.

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OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM 1 & 2 SYSTEM: Emergency Operating Procedures TASK: Respond to a Loss of Heat Sink (Initiate Bleed and Feed with SI pumps and Rx Head Vents)

TASK NUMBER: N1150290501 JPM NUMBER: 09-01 NRC Sim d ALTERNATE PATH: I X I KIA NUMBER: EPE E05 EA 1.1

~~~~~~--~

IMPORTANCE FACTOR: 4.1 4.0 APPLICABILITY: RO SRO EOD ROW STAD SROW EVALUATION SETTING/METHOD: Simulator - Perform

REFERENCES:

2-EOP-FRHS-1, Loss of Secondary Heat Sink, Rev. 24 (checked 6/20/11)

TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 5 minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS:

Developed By: G Gauding Date: 06-17-11 Instructor Validated By: J Klein Date: 06-30-11 SME or Instructor Jf~~ent Date: -; -2.-. I~ V Approved By:

Approved By:

~t.

Operati ns Department Date: B/I/"

ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION TIME:

PERFORMED BY:

GRADE: D SAT D UNSAT REASON, IF UNSATISFACTORY:

i EVALUATOR'S SIGNATURE: DATE:

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OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM: Emerqency Operatinq Procedures TASK: TCAF a Loss of Heat Sink (Initiate Bleed and Feed with 81 pumps and Rx Head Vents)

TASK NUMBER: N1150290501 SIMULATOR SETUP:

IC-252 developed by : MSL rupture downstream of MSIVs. Fail auto MT trip. Fail all MSIVs open. All AFW pumps failed. Fail2PR2 shut. 21 CVCS pp CIT. Performed TRIP-1 through Step 20. 22 CVCS pp tripped during TRIP-1.

INITIAL CONDITIONS:

Unit 2 initiated a Rx trip from 100% power in response to a Main Steamline break at the mixing bottle.

An automatic Safety Injection initiated.

The Main Turbine failed to trip automatically, and was manually tripped from the control console.

MSLI faiied, and all MSIV's remain open.

All AFW flow has been lost.

21 charging pump is CIT.

22 charging pump tripped 3 minutes ago.

EOP-TRIP-1 was performed and a transition to FRHS-1, Loss of Secondary Heat Sink was made at Step 20.

INITIATING CUE:

You are the Reactor Operator. Perform FRHS-1 starting at Step 1.

Successful Completion Criteria:

1. All critical steps completed.

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Task Standard for Successful Completion:

1. Stop ALL Reps.

2. Open 2PR1.

3. Open Rx Head Vent Valves 2RC40*2RC43.

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OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Emergency Operating Procedures TASK: Respond to a Loss of Heat Sink (Initiate Bleed and Feed with SI pumps and Rx Head Vents)

STEP COMMENTS STEP

(* Denotes a Critical Step) EVAL (Required for UNSAT I

NO. STANDARD S/U evaluation)

Operator states he has the watch.

'r-- -

1 IS TOTAL AFW FLOW LESS THAN Determines it was not operator action which 22E04 LB/HR DUE TO OPERATOR caused total AFW flow to be less than 22E04 ACTIONS Ib/hr.

--- r----

2 tE AT LEAST ONE INTACT OR Recognizes ALL SGs are faulted.

RUPTURED SG IS AVAILABLE, THEN DO NOT FEED A FAULTED SG 3 IS RCS PRESSURE GREATER THAN Checks RCS pressure on control console ANY INTACT OR RUPTURED SG and determines it is greater than all SG PRESSURE pressures checked on control console.

3.1 ARE RCS T-HOTS GREATER THAN Checks RCS That indication on control 350°F console and determines that ReS Thots are greater than 350°F.

4 IS 21 OR 22 CHARGING PUMP Determines neither 21 nor 22 charging pump AVAILABLE is available based on initial conditions and/or control console indications.

--- I------- ---

GOTOSTEP23 Goes to Step 23.

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OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Emergency Operating Procedures TASK: Respond to a Loss of Heat Sink (Initiate Bleed and Feed with SI pumps and Rx Head Vents)

STEP COMMENTS STEP

(* Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD S/U evaluation) 23 CAUTION TO ESTABLISH RCS HEAT REMOVAL Reads Step.

BY RCS BLEED AND FEED, STEPS 24 THRU 29 MUST BE PERFORMED QUICKL Y AND WITHOUT INTERRUPTION

23 STOP ALL RepS Depresses STOP PB for 21-24 RCPs and verifies green stop light illuminates and red start light extinguishes.

24 INITIATESI Uses Safeguards key and initiates Sian at least one train of Safeguards initiation.

25 ARE SI VALVES IN SAFEGUARDS Checks 2RP4 and/or console indication to POSITION' determine that all valves listed in Table Bare in Safeguards position.

Table B valves are:

2SJ4 OPEN BIT INLET 2SJ5 OPEN BIT INLET 2SJ12 OPEN BIT OUTLET 2SJ13 OPEN BIT OUTLET 2CV68 CLOSED CHARGING DISCHARGE 2CV69 CLOSED CHARGING DISCHARGE (continued next paqe)

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OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Emergency Operating Procedures TASK: Respond to a Loss of Heat Sink (Initiate Bleed and Feed with SI pumps and Rx Head Vents)

STEP COMMENTS STEP

(* Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD S/U evaluation)

Table B Valves (can't):

21~24SJ54 OPEN ACCUMULATOR OUTLET 2SJ1 OPEN RWST TO CHARGING 2SJ2 OPEN RWST TO CHARGING 2CV40 CLOSED DISCHARGE STOP 2CV41 CLOSED DISCHARGE STOP 25.1 IS 21 OR 22 CHARGING PUMP Checks control console and determines RUNNING neither 21 nor 22 charging pump is running.

f- -----

25.2 IS ANY SI PUMP RUNNING Checks control console and determines both 21 and 22 SI pumps are running.

25.2 ARE VALVES IN TABLE C OPEN FOR Checks control console indication for valves AT LEAST ONE RUNNING SI PUMP listed in Table C and determines the valves are open for at least one running 81 pump.

Table C valves are:

21/22 SI PUMPS 2SJ30 (FROM RWST) 21/22SJ33 (SI PUMP SUCTION) 2SJ135 (COLD LEG DISCHARGE) 21/22SJ134 (COLD LEG DISCHARGE) 26 OPEN BOTH PZR PORV STOP VALVES Checks control console and determines BOTH 2PR6 and 2PR7 PORV STOP VALVES are open.

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OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE DATE: - - - - - - - - - - - - - - - -

SYSTEM: Emergency Operating Procedures TASK: Respond to a Loss of Heat Sink (Initiate Bleed and Feed with SI pumps and Rx Head Vents)

STEP COMMENTS STEP

(* Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD S/U evaluation)

OPEN BOTH PZR PORVS Depresses 2PR1 PZR PORV open PB and

26 verifies green closed light extinguishes and red open light illuminates.

Depresses 2PR2 PZR PORV open PB and reports that 2PR2 will not open.

26.1 ARE BOTH PZR PORV STOP VALVES Checks control console and determines BOTH OPEN 2PR6 and 2PR7 PORV STOP VALVES are open.

ARE BOTH PZR PORVS OPEN Determines 2PR2 PZR PORV is not open.

Inserts key into each 2RC40 THRU 2RC43

26.1 OPEN 2RC40 THRU 2RC43 (REACTOR HEAD VENTS) (REACTOR HEAD VENTS) switch on 2RP3, turns to open, and verifies each valve opens.

Terminate JPM when operator has opened 2RC40 thru 2RC43 Reactor Head Vents.

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JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPIV1 usage, revalidate JPM using steps 8 and 11 below.

~ 1. Task description and number, JPM description and number are identified.

cw...- 2. Knowledge and Abilities (KIA) references are included.

~ 3. Performance location specified. (in-plant, control room, or simulator)

~ 4. Initial setup conditions are identified.

01L 5. Initiating and terminating Cues are properly identified.

Q}t< 6. Task standards identified and verified by SME review.

~ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

~ 8. Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. )(..1 Date k 3,0 ( l \.

~ 9. Pilot test the JPM:

a. verify Cues both verbal and visual are free of conflict, and

b. ensure performance time is accurate.

____ 10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

____ 11. When JPM is revalidated, SME or Instructor sign and date ..IPM cover page.

SMEll nstructor:_Q_-t--LeK~,c\;;;L"",QkytUol"'----!..>.-"./'--_ _ _ __ Date:

SMElinstructor:_ _ _ _ _ _ _ _ _ _ _ __ Date: _ _ _ _ __

Date: _ _ _ _ __

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INITIAL CONDITIONS:

Unit 2 initiated a Rx trip from 100% power in response to a Main Steam line break at the mixing bottle.

An automatic Safety Injection initiated.

The Main Turbine failed to trip automatically, and was manually tripped from the control console.

MSLI failed, and all MSIV's remain open.

All AFW flow has been lost.

21 charging pump is CIT.

22 charging pump tripped 3 minutes ago.

EOP-TRIP-1 was performed and a transition to FRHS-1, Loss of Secondary Heat Sink was made at Step 20.

INITIATING CUE:

You are the Reactor Operator. Perform FRHS-1 starting at Step 1.

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OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Main Turbine TASK: TCAF Main Turbine Trip < P-9 (Loss of Turbine Auxiliaries Cooling Expansion Tank Level)

TASK NUMBER: N1140420401 JPM NUMBER: 09-01 NRC Sim e ALTERNATE PATH: I X KIA NUMBER: 2.4.31 IMPORTANCE FACTOR: 4.2 4.1 APPLICABILITY: RO SRO EO RO STA SRO EVALUATION SETTING/METHOD: Simulator - Perform S2.0P-AR.ZZ-0007, Rev. 46, Overhead Window G

REFERENCES:

S2.0P-AB.TRB-0001, Rev. 14, Turbine Trip <P-9 (Both rev checked 6-21-11)

TOOLS AND EQUIPMENT: None VALIDATED "IPM COMPLETION TIME: 5 min TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 06-17-11 Instructor Validated By: J. Klein Date: 06-30-11 SME or Instructor Approved By:

~~ent Date: ~ ~ II Approved By:

o~ment Date: 7J 6/ J I ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION TIME:

PERFORMED BY:

GRADE: SAT UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

Page 1 of 10 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM: Main Turbine TASK: TCAF Main Turbine Trip < P-9 (loss of Turbine Auxiliaries Cooling Expansion Tank level)

TASK NUMBER: N1140420401 SIMULATOR SETUP IC-255 RT-1 MAlF AN010S SER 105 Fails-: G8 Turbine Auxiliary Cooling MAlF TU0118A 21 MS28 Turb Stop Valve Fails Open Override CK23 Turbine Trip-Trip INITIAL CONDITIONS:

40% power, BOl.

A power reduction to bring the Main Turbine off-line is on hold.

INITIATING CUE: You are the Reactor Operator. Respond to all alarms and indications.

Successful Completion Criteria:

1. All critical steps completed.

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Task Standard for Successful Completion:

1. Trip the Main Turbine.

2. Trip the Rx.

Page 2 of 10 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM NAME:

DATE: __________________

JOB PERFORMANCE MEASURE SYSTEM: Main Turbine TASK: TCAF Main Turbine Trip < P-9 {Loss of Turbine Auxiliaries Cooling Expansion Tank Level}

STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD StU evaluation)

SIMULATOR OPERATOR:

Insert RT~1 after candidate assumes the Announces unexpected OHA G~8 TAC watch. EXP TK LVL HI OR LO.

Refers to S2.0P-AR.ZZ-0007, Overhead WindowG.

ARP Reviews causes and determines there are 1.0/2.0 no automatic actions associated with this alarm.

ARP DETERMINE if level alarm is high or low Determines CRT point 105 Turbine 3.1 from the Annunciator CRT: Auxiliary Cooling Expansion Tank Level CRT Point Description Low is in alarm.

104 Turbine Auxiliary Cooling Expansion Tank Level High 105 Turbine Auxiliary Cooling Expansion Tank Level Low Page 3 of 10 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM NAME:

DATE: __________________

JOB PERFORMANCE MEASURE SYSTEM: Main Turbine TASK: TCAF Main Turbine Trip < P-9 (Loss of Turbine Auxiliaries Cooling Expansion Tank Level)

STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD S/U evaluation) I 3.2 IF level is high, THEN: Determines level is not high, and continues to next step.

3.3 IF level is low, THEN:

A. Send an operator to MAKEUP to Dispatches an operator to makeup to tank, tank. and identify and isolate any leaks.

B. Send an operator to IDENTIFY AND ISOLATE any leaks.

I 1,------- ,--------- -- I--

Simulator Operator: 2 minutes after being dispatched, call control room and report:

"This is the Secondary Operator. The Unit 2 TAC expansion tank level is 7" and lowering one inch per minute. The auto makeup valve is stuck shut, and I can't get the bypass valve open."

Page 4 of 10 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE: ___________________

SYSTEM: Main Turbine TASK: TCAF Main Turbine Trip < P-9 (Loss of Turbine Auxiliaries Cooling Expansion Tank Level)

STEP COMMENTS STEP EVAL (Required for UNSAT

(*Denotes a Critical Step) STANDARD

NO. S/U evaluation) 3.4 IF unable to maintain tank level above 6 I inches, THEN:

A. LE >P-9 (49% power), THEN TRIP the Reactor, AND GO TO 2-EOP- Determines tank level cannot be TRIP-1, Reactor Trip or Safety maintained above 6 inches, and attempts

Injection. to trip the Main Turbine with the Turbine Trip handle, and reports the Main Turbine

B. IF <P-9 (49% power) THEN TRIP did not trip.

the Turbine, AND GO TO S2.0P- Depresses the Turbine Trip PB and AB.TRB-0001(Q), Turbine Trip determines the Turbine has tripped.

Below P-9. Goes to S2.0P-AB.TRB-0001.

Note: LE the candidate observes the 21 MS28 remaining open at this point, THEN they may determine the turbine is not tripped, and perform a MSLI by depressing all 4 MSLI PBs on either Safeguards bezel. Initiating a MSLI before the Rx is tripped is an incorrect action which may challenge SG safeties if they lift.

Initiating a MSLI renders the Main Steam Dumps inoperable and prematurely isolates the SGFPs. With Rx power >P-10 (10%)

and steam dumps not available, a Rx trip is required lAW CAS actions 1.0 and 2.0.

See page 8 for complete discussion. Go to page 7 for required actions IF a Rx trip is performed here.

Page 5 of 10 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Main Turbine TASK: TCAF Main Turbine Trip < P-9 (Loss of Turbine Auxiliaries Cooling Expansion Tank Level)

STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD StU evaluation)

AB.TRB INITIATE Attachment 1, Continuous Initiates Attachment 1, Continuous Action 3.1 Action Summary. Summary.

3.2 VERIFY the Turbine is tripped. Note: IF the candidate observes the 21 MS28 remaining open at this point, THEN they may determine the turbine is not tripped, and perform a MSLI by depressing all 4 MSLI PBs on either Safeguards bezel. Initiating a MSLI before the Rx is tripped is an incorrect action which may challenge SG safeties if they lift.

Initiating a MSLI renders the Main Steam Dumps inoperable and prematurely isolates the SGFPs. With Rx power >P-10 (10%)

and steam dumps not available, a Rx trip is I required lAW CAS actions 1.0 and 2.0.

See page 8 for complete discussion.

See next page for required actions IF a Rx trip is performed here.

Page 6 of 10 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM NAME:

DATE: __________________

JOB PERFORMANCE MEASURE SYSTEM: Main Turbine TASK: TCAF Main Turbine Trip < P-9 (Loss of Turbine Auxiliaries Cooling Expansion Tank Level)

STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD stu evaluation) I IF candidate initiates a Rx trip prior to EOP initiating a MSLI based on CAS actions 1.0 TRIP-1 and 2.0 which would occur if they initiated a MSLI, then successful performance of TRIP-1 immediate actions must be performed as follows:

1 TRIP REACTOR Trips the Rx using either Trip handle.

2 IS REACTOR TRIP CONFIRMED Confirms Rx trip

3 TRIP TURBINE Attempts to trip the Main Turbine using the Trip handle.

Determines the Trip handle did not close all Main Turbine Stop Valves.

Depresses Turbine Trip bezel.

Determines the Trip handle did not close all Main Turbine Stop Valves.

EOP Initiates a MSLI.

TRIP-1 TRIP TURBINE (MSLI step) Terminate JPM after MSLI has been 3 performed.

.. ~ -_.

3.3 Are all Turbine Stop Valves closed? Determines all Turbine Stop Valves are NOT closed from 2RP4.

Goes to Step 3.7.

r*

3.7 TRIP the Reactor, GO TO 2-EOP-TRIP Trips the Reactor using either of the 1, Reactor Trip or Safety Injection. Reactor Trip handles.

r* .__.r - - -_. , . . _-_.

Begins performing immediate actions of 2 EOP-TRIP-1, Reactor Trip or Safety Injection.

' - - - ... ~.

Page 7 of 10 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM NAME:

DATE: __________________

JOB PERFORMANCE MEASURE SYSTEM: Main Turbine TASK: TCAF Main Turbine Trip < P-9 (Loss of Turbine Auxiliaries Cooling Expansion Tank Level)

STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD S/U evaluation)

Terminate JPM when Reactor has been tripped.

Turbine Trip requirements- During performance of this JPM, the candidate will receive direction from the Alarm Response Procedure S2.0P-ARZZ 0007, Overhead Window G, OHA G-8, page 18-19, which states "TRIP the Turbine and GO TO S2.0P-AB.TRB-0001, Turbine Trip <P-9."

When outside the EOP network, initiating a MSLI to perform a Turbine Trip is NOT an appropriate action, since in TRIP-1 the steps for tripping the Rx precede the steps for tripping the Turbine, and the MSLI would only be performed AFTER all attempts to trip the Rx from the control room have already been performed. IF the Rx trip were NOT confirmed, then the Turbine trip steps would include the MSLI since the overriding concern at that point would be reduction of Rx power by removing the Main Turbine from service.

After entering the EOP Network, actions for tripping the Reactor and tripping the Turbine have special definitions as described in OP-AA-1 01-111-1003, Use of Procedures, which ONLY apply while in the EOP network. When defining turbine trip while in EOP-TRIP-1, it states on page 13,

" Steps 2.2 and 3, TRIP TURBINE, are defined as, "Operate the turbine trip switch" IF turbine trip NOT confirmed, THEN trip the turbine using the Turbine Trip bezel.

IF turbine trip NOT confirmed, THEN initiate main steam isolation.""

For these reasons, initiating a MSLI during this JPM prior to initiating a Rx trip will be considered failure criteria due to the possible challenge to SG safeties which may occur due to this action, and which otherwise would not occur in the JPM.

Page 8 of 10 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate '"'PM using steps 8 and 11 below.

~ 1. Task description and number, JPM description and number are identified.

4.. ~"'".-- 2. Knowledge and Abilities (KIA) references are included.

-41.. . .".--- 3. Performance location specified. (in-plant, control room, or simulator)

.....ca'+'A-\i.---4. Initial setup conditions are identified .

. . C. fh'-l"--"'-'--- 5. Initiating and terminating Cues are properly identified.

-!0j1"""",,,,--_6. Task standards identified and verified by SME review.

_CtA--",-,,,--_7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

~ 8. Verify the procedure referenced !w try~ JPM m,atc~~s the most current revision of that procedure: Procedure Rev. ~ Date ", .. ~ ... \ I

.......:Q\~,__ 9. Pilot test the JPM:

a. verify Cues both verbal and visual are free of conflict, and

b. ensure performance time is accurate.

~ 10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

~ 11. When JPM is revalidated, SME or Instructor sign and date JPM COver page.

SMEIlnstructor: ~ Date: &; -sO -/1 SMEllnstructor: Date: _______

SME/lnstructor: Date: _______

Page 9 of 10 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

INITIAL CONDITIONS:

40% power, BOL.

A power reduction to bring the Main Turbine off-line is on hold.

INITIATING CUE:

You are the Reactor Operator. Respond to all alarms and indications.

Page 10 of 10 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE

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

STATION: SALEM SYSTEM: AC Electrical Distribution TASK: Transfer A 4 KV Group Bus To The Alternate Power Supply (SPT to APT)

! TASK NUMBER: N062011 01 01 JPM NUMBER: 09-01 NRC Sim f ALTERNATE PATH: KIA NUMBER: 062 A4.01 IMPORTANCE FACTOR: 3.3 3.1 APPLICABILITY: RO SRO EO RO STA SRO EVALUATION SETTING/METHOD: Simulator - Perform S2.0P-IO.ZZ-0003, Rev. 35, Hot Standby to Minimum Load

REFERENCES:

S2.0P-S0.4KV-0008, Rev. 12, 4KV Group Buses Power Supply Transfer TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 12 min TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 06-17-11 Instructor Validated By: J Klein Date: 06-30-11 SME or Instructor

~~

Approved By: Date: 7-2/- /1 Approved By:

Date: 7 1'6/ I I ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION TIME:

PERFORMED BY:

GRADE: SAT UNSAT I REASON, IF UNSATISFACTORY:

. SIGNATURE: DATE:

Page 1 of7 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM: AC Electrical Distribution TASK: Transfer A 4 Kv Group Bus To The Alternate Power Supply (SPT to APT)

TASK NUMBER: N0620110101 SIMULATOR SETUP IC-256 19.2% power BOl.

MALFS: AN0637 SER 63? Fails-: J14 21 ESD Breaker Failure tied to ET-1 RP0058 Failure of Automatic Reactor Trip Overrides: C308 OVDI 2AEGD 2E GROUP BUS FEEDER -CLOSE OFF All tied C308 OVDI 2AEGD 2E GROUP BUS FEEDER-OPEN ON to ET-1 C312 OVDI21ESD 2E GROUP BUS FEEDER-OPEN ON C312 OVDI 21 ESD 2E GROUP BUS FEEDER-CLOSED OFF C30? OVDI 21 HSD 2H GROUP BUS FEEDER-OPEN ON C307 OVDI 21 HSD 2H GROUP BUS FEEDER-CLOSED OFF C601 OVDI 13 KV SECTION 1-6-0PEN ON C601 OVDI13 KV SECTION 1-6-CLOSED OFF Check APT voltage the same as the Group bus voltage pre-req 2.3.3 Note to Evaluator: The bus transfer sequence - H,E,F,G corresponds to RCPs 21, 22, 23. AND 24.

INITIAL CONDITIONS:

19.2% power, BOL.

The Main Turbine was synchronized 10 minutes ago.

Steam Dumps are in Tavg Mode-Auto.

Rod Control is in Manual until Group Buses are transferred.

Group Buses are powered from the Station Power Transformers.

INITIATING CUE: You are the NCO assigned to transfer the 4KV Group Buses. The CRS directs you to transfer all 4KV Group buses from their respective Station Power Transformers to the Aux Power Transformers, starting with H Group Bus, lAW S2.0P-SOAKV-0008, 4KV Group Buses Power Supply Transfer. All pre-requisites are complete SAT.

The CRS directs you to transfer the buses in this order: H, E, F, G Successful Completion Criteria:

1. All critical steps completed.

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Task Standard for Successful Completion:

1. Transfer 2H 4KV Group bus from SPT to APT.

2. Trip Rx upon ATWT while transferring 2E 4KV Group bus from SPT to APT Page 2 of 7 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Electrical TASK: Transfer A 4 Kv Group Bus To The Alternate Power Supply (SPT to APT)

STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD S/U evaluation)

Reviews Precautions and Limitations.

5.4.1 ENSURE all Overhead Annunciators for Checks OHA Windows and determines all 2 APT are clear. Overhead Annunciators for 2 APT are clear.

5.4.2 ENSURE 2B APT voltage is 4.22 Checks 2B APT reading on 2CC3 and 4.36KV. determines 2B APT voltage is 4.22 4.36KV.

r--~ ,----~

~-~

5.4.3 IF Auxiliary Power Unit Isolation Transfer Determines Auxiliary Power Unit Isolation is tripped, Transfer is not tripped from control console THEN RESET Auxiliary Power Unit indication.

Isolation Transfer (UIT).

5.4.4 PRESS the Mimic Bus 2H GROUP BUS Depresses Mimic Bus 2H GROUP BUS INFEED 2AHGD BREAKER pushbutton, INFEED 2AHGD BREAKER pushbutton AND ENSURE console bezel 2AHGD and checks console bezel2AHGD MIMIC MIMIC BUS INTLK CLOSE SELECTION BUS INTLK CLOSE SELECTION illuminates. Illuminates.

~-~

Page 3 of7 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM NAME:

DATE: __________________

JOB PERFORMANCE MEASURE SYSTEM: Electrical TASK: Transfer A 4 Kv Group Bus To The Alternate Power Supply (SPT to APT)

STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD S/U evaluation)

5.4.5 PRESS control console 2AHGD CLOSE Depresses control console 2AHGD CLOSE I pushbutton, pushbutton, and checks the following:

AND ENSURE the following:

A. 21 HSD is OPEN. A. 21 HSD is OPEN.

B. 2AHGD is CLOSED. B. 2AHGD is CLOSED.

C. 2H 4KV Group Bus voltage is C. 2H 4KV Group Bus voltage is from from 4.22 - 4.36KV. 4.22 - 4.36KV.

D. Console bezel 2AHGD MIMIC D. Console bezel 2AHGD MIMIC BUS BUS INTLK CLOSE SELECTION INTLK CLOSE SELECTION is is extinguished. extinguished.

5.1.1 ENSURE all Overhead Annunciators for Checks OHA Windows and determines all 2 APT are clear. Overhead Annunciators for 2 APT are clear.

5.1.2 ENSURE 2B APT voltage is 4.22 - Checks 2B APT reading on 2CC3 and .

4.36KV. determines 2B APT voltage is 4.22 4.36KV.

r---- I 5.1.3 IF Auxiliary Power Unit Isolation Transfer Determines Auxiliary Power Unit Isolation is tripped, Transfer is not tripped from control console THEN RESET Auxiliary Power Unit indication.

Isolation Transfer (UIT).

5.1.4 PRESS Mimic Bus 2E GROUP BUS Depresses Mimic Bus 2E GROUP BUS INFEED 2AEGD BREAKER pushbutton, INFEED 2AEGD BREAKER pushbutton, AND ENSURE console bezel 2AEGD AND checks console bezel 2AEGD MIMIC MIMIC BUS INTLK CLOSE SELECTION BUS INTLK CLOSE SELECTION I illuminates. illuminates.

~----~---- --r- I Page 4 of7 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Electrical TASK- Transfer A 4 Kv Group Bus To The Alternate Power Supply (SPT to APT)

STEP COMMENTS I STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD S/U evaluation)

5.1.5 PRESS control console 2AEGD CLOSE pushbutton, AND ENSURE the following: Determines 2E Group bus did not transfer A. 21 ESD is OPEN. and recognizes a Rx trip demand signal is B. 2AEGD is CLOSED. present by First Out Annunciator F-10, RC C. 2E 4KV Group Bus voltage is 4.22 LO FLO OR Rep BKR OPEN & P-7.

- 4.36KV.

Recognizes the Rx did not trip.

D. Console bezel 2AEGD MIMIC Announces ATWT.

BUS INTLK CLOSE SELECTION

is extinguished.

1----. I---

Tr!Qs the Rx using either trip handle.

Terminate the JPM when a Rx trip has been initiated.

Page 50f7 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate ~IPM using steps 8 and 11 below.

1. Task description and number, JPM description and number are identified.

2. Knowledge and Abilities (KiA) references are included.

3. Performance location specified. (in-plant, control room, or simulator)

~ 4. Initial setup conditions are identified.

---t:w-- 5. Initiating and terminating Cues are properly identified.

~ 6. Task standards identified and verified by SME review.

Litk 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

~

Au that procedure: Procedure Rev.3~ /(L. Date ,,-~o . \\.

8. Verify the procedure referenced by this JPM matches the most current revision of

~ 9. Pilot test the JPM:

a. verify Cues both verbal and visual are free of conflict, and

b. ensure performance time is accurate.

____ 10. If the ..IPM cannot be performed as written with proper responses, then revise the JPM.

_ _ _ _ 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

SME/'nstructor:_ _ C1K;"'--b~.l-JI-Q1

. . .....Aw£..'~_ ____ Date: _19_"_30_'_\\_

SME/lnstructor: _ _ _ _ _ _ _ _ _ _ _ __ Date: - - - - -

SME/lnstructor: Date: - - - - - - -

Page 6 of 7 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

INITIAL CONDITIONS:

19.2% power, BOL.

The Main Turbine was synchronized 10 minutes ago.

Steam Dumps are in Tavg Mode*Auto.

Rod Control is in Manual until Group Buses are transferred.

Group Buses are powered from the Station Power Transformers.

INITIATING CUE:

You are the NCO assigned to transfer the 4KV Group Buses. The CRS directs you to transfer all 4KV Group buses from their respective Station Power Transformers to the Aux Power Transformers, starting with H Group Bus, lAW S2.0P*SOAKY*0008, 4KY Group Buses Power Supply Transfer. All pre-requisites are complete SAT.

The CRS directs you to transfer the buses in this order: H, E, F, G Page 7 of7 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Emergency Procedures TASK: Take Corrective Action For A Nuclear Instrumentation System Malfunction (Energize Source Range NIS lAW TRIP-2 wlone under compensated IR channel)

TASK NUMBER: N1140230401 JPM NUMBER: 09-01 NRC Sim g ALTERNATE PATH: W KIA NUMBER: EPE 007 EA1.05

~

IMPORTANCE FACTOR: 4.0 4.1 APPLICABILITY: RO SRO EoD ROm STAD SROm EVALUATION SETTING/METHOD: Simulator I Perform

REFERENCES:

2-EOP-TRIP-2, Rev. 27 Reactor Trip Response (rev checked 6-17-11)

TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 10 Minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 05-04-2011 Instructor Validated By: K Reidmuller Date: 06-30-11 SME or Instructor Approved By:

~~ent Date: 7~z 1- 1/

'7/ ~ /1 I Approved By:

~~nt Date:

ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION TIME:

PERFORMED BY:

GRADE: D SAT D UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

PSEG Restricted- Possession Requires Specific Approval from Nuclear Training Page 1 of 7

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME: __________________________

DATE:

SYSTEM: Emergency Procedures TASK: Take Corrective Action For A Nuclear Instrumentation System Malfunction (Energize Source Range NIS lAW TRIP-2 One under compensated IR channel)

TASK NUMBER: 1150030501 SIMULATOR SETUP: IC-257 on 2011 Flash Drive MALF: NI0195D IR CH N36 Compensating Volts Lo - TRUE IC setup by tripping both SGFP's and initiating a MANUAL Rx trip Perform EOP's through up to Step 19 of TRIP-2 Ensure audio count rate monitor selected to 10K scale INITIAL CONDITIONS:

A MANUAL reactor trip from full power was initiated 15 minutes ago when both SGFP's tripped automatically. Operators performed the immediate actions of EOP-TRIP-1, Reactor Trip or Safety Injection, then transitioned to 2-EOP-TRIP-2, Reactor Trip Response. Operators have performed TRIP-2 up to Step 19, Steam Dump Mode Shift.

INITIATING CUE:

You are the board operator. Starting at Step 19. perform 2-EOP-TRIP-2 Reactor Trip Response Successful Completion Criteria:

1. All critical steps completed.

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPIVI completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Task Performance for Successful Completion:

1. Transfers Main Steam Dumps to MS Pressure Control - Auto

2. Energizes BOTH SRNI Channels

3. Adjusts audio count rate monitor to 1 K scale PSEG Restricted- Possession Requires Specific Approval from Nuclear Training Page 2 of 7

OPERATOR TRAINING PROGRAM NAME: ___________________

JOB PERFORMANCE MEASURE DATE: ___________________

SYSTEM: Emergency Procedures TASK: Take Corrective Action For A Nuclear Instrumentation System Malfunction COMMENTS STEP STEP (Required for

(""Denotes a Critical Step) EVAL

NO. STANDARD UNSAT

(#Denotes a Sequential Step) StU evaluation) 19 Are Condenser Steam Dumps Available? Checks Condenser Steam Dumps are reports they are available based on circulators in service and condenser vacuum established, I'

Place Steam Dumps in "Manual" Depresses Steam Dumps Manual PB on control console and verifies Manual light illuminates and Auto light extinguishes,

~

Align Steam Dump Valve demand "Press Uses Increase Demand (Open Vlv) PB on

%" and "Tavg %" to align Steam Dump Valve demand "Press

%" and "Tavg %",

-~

'* Place Steam Dumps in "MS Pressure Depresses "MS Pressure Control" PB on Control" control console and verifies light illuminates and Tavg Control light extinguishes.

'* Place Steam Dumps in "Auto" Depresses Steam Dumps Auto PB on control console and verifies Auto light illuminates and Manual light extinguishes.

PSEG Restricted- Possession Requires Specific Approval from Nuclear Training Page 3 of 7

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: Emergency Procedures TASK: Take Corrective Action For A Nuclear Instrumentation System Malfunction COMMENTS STEP STEP {Required for

(*Denotes a Critical Step) EVAL

NO. STANDARD UNSAT

(#Denotes a Sequential Step) S/U evaluation}

Adjust Steam Pressure Valve Demand to Adjusts Steam Pressure Valve Demand to maintain SG Pressure at 1005 psig. maintain SG Pressure at 1005 psig.

Note: Steam dumps may be placed in Manual for adjustment then returned to auto.

IF candidate takes additional time to monitor steam pressure (preventing them from continuing to next step) THEN CUE:

The Crew will continue monitoring steam pressure to ensure it stabilizes at 1005 psig.

r--

20 Is any RCP running Checks RCP status and determines all RCP's are running.

22 Are both IR Channels less than 7E-11 Checks IRNI Channel 1 and Channell!

Amps indication and determines 2N36 reads

>7E-11 Amps.

I Is undercompensation preventing proper Determines undercompensation of channel IR operation? 2N36 is preventing proper IR operation by:

Elapsed time since trip

- SUR 0 on affected channel with power above minimum display PSEG Restricted- Possession Requires Specific Approval from Nuclear Training Page 4 of 7

OPERATOR TRAINING PROGRAM NAME: __________________

JOB PERFORMANCE MEASURE DATE: ___________________

SYSTEM: Emergency Procedures TASK: Take Corrective Action For A Nuclear Instrumentation System Malfunction COMMENTS STEP STEP (Required for

(*Denotes a Critical Step) EVAL

NO. STANDARD UNSAT

(#Denotes a Sequential Step) S/U evaluation)

22.1 Energize Source Range Channels Energizes Source Range Channel I by depressing RESET SOURC RANGE A

Energizes Source Range Channel II by depressing RESET SOURC RANGE B 22.2 Transfer NR-45 (Nuclear Power Transfers NR-45 (Nuclear Power Recorder) to Source Range Channels Recorder) to Source Range Channels by I selecting Source Range Channel I on Pen 1 or 2, and selecting Source Range Channel II on the other Pen.

I r---

- - 22.3 Adjust Audio Count Rate Circuit Scale Adjusts Audio Count Rate Circuit Scale so that SR counts can be heard in the control r----~

room.

~--

I Terminate JPM after audio count rate scale adjustment has been verified in the control room.

'----- -~ --- -~-

PSEG Restricted- Possession Requires Specific Approval from Nuclear Training Page 5 of 7

JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage. revalidate JPM using steps 8 and 11 below.

_~_ _ _ 1. Task description and number. JPM description and number are identified.

_\L_r _ _ 2. Knowledge and Abilities (KIA) references are included.

\l~

_"_ _ _ 3. Performance location specified. (in-plant. control room. or simulator)

-'-_ _ _ 4. Initial setup conditions are identified.

\c.v

--'-~_ _ _ 5. Initiating and terminating Cues are properly identified.

\l(,r"""

_~_ _ _ 6. Task standards identified and verified by SME review.

---'\'-(}-

_ _ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

_\_lQ--

___ 8. Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. ~ Date , .')u* q

- - - - 9. Pilot test the JPM:

a. verify Cues both verbal and visual are free of conflict. and

b. ensure performance time is accurate.

____ 10. If the JPM cannot be performed as written with proper responses. then revise the JPM.

_ _ _ _ 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

SME/lnstructor:--I1_~=-_'_n __ , ....:..~

_ _ _ _ _ __ Date: _'_'_3_ 0

_'1_'_ _

SMEllnstructor: Date:

SMEllnstructor: Date: ___________

PSEG Restricted- Possession Requires Specific Approval from Nuclear Training Page 6 of 7

INITIAL CONDITIONS:

A MANUAL reactor trip from full power was initiated 15 minutes ago when both SGFP's tripped automatically. Operators performed the immediate actions of EOP-TRIP-1, Reactor Trip or Safety Injection, then transitioned to 2-EOP-TRIP-2, Reactor Trip Response. Operators have performed TRIP-2 up to Step 19, Steam Dump Mode Shift.

INITIATING CUE:

You are the board operator. Starting at Step 19, perform 2-EOP-TRIP-2 Reactor Trip Response.

PSEG Restricted- Possession Requires Specific Approval from Nuclear Training Page 7 of 7

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE -------

STATION: SALEM SYSTEM: Component Cooling System TASK: Take Corrective Action For A Component Cooling Water System Abnormality TASK NUMBER: N1140080401 JPM NUMBER: 09-01 NRC Sim h ALTERNATE PATH: KIA NUMBER: 008 A4.01 IMPORTANCE FACTOR: 3.3 3.1 APPLICABI L1TY: RO SRO EO c:::=J RO STA SRO [LJ EVALUATION SETTING/METHOD: Simulator - Perform S2.0P-AB.CC-0001, Rev. 14 Component Cooling Abnormality S2.0P-AB.RCP-0001, Rev. 21 Reactor Coolant Pump Abnormality

REFERENCES:

S2.0P-AR.ZZ-0004, Rev. 26, Overhead Window 0 (all rev checked 6-22-11)

TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 10 minutes TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 06-17-11 Instructor Validated By: K Reidmuller Date: 06-30-11 SME or Instructor

,~~

Approved By: Date: Y.- 2.. - I I Approved By: -:g;~

Operations Department Date: ~ sf /11 ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION TIME:

PERFORMED BY:

GRADE: SAT UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

Page 1 of 17 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM: Component Cooling System TASK: Take Corrective Action For A Component Cooling Water System Abnormality TASK NUMBER: 1\J1140080401 SIMULATOR SETUP IC-258 100% power EOL.

RT-1 MALF: CC0172B 22 Component Cooling Water Pump Trip MALF: CC0172A 21 Component Cooling Water Pump Trip DELAY: 4 minutes OVLO 23 CC Pump Auto - ON OVLO 23 CC Pump Manual OFF (23 CCW pump placed in manual before OVLOs inserted, pump is in manual but looks like it is in auto.)

OVDI 23 CC Pump-Start OFF ET-S and ET-6 delete the OVLO's for 23 CC pp and allow the pump indication to swap to manual, but the 23 CCW pump start PB does not start the pump.

INITIAL CONDITIONS:

100% power, EOL.

INITIATING CUE: You are the Reactor Operator. Respond to all alarms and indications.

Successful Completion Criteria:

1. All critical steps completed.

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. ...IPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Task Standard for Successful Completion:

1. Trip the Reactor.

2. Trip 21-24 RCPs.

3. Isolate Letdown and swap Charging Pump suction to the RWST.

Page 2 of 17 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM NAME:

DATE: __________________

JOB PERFORMANCE MEASURE SYSTEM: Component Cooling System TASK: Take Corrective Action For A Component Cooling Water System Abnormality STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD S/U evaluation)

Note for Simulator Operator: The Note to Evaluator: The end result of this remaining CCW pump must be tripped JPM will be the same whether the PRIOR to the determination that the Rx Component Cooling or Reactor Coolant must be tripped and RCPs stopped in Pump Abnormal Procedure is used. The either the Reactor Coolant Pump or Attachment in each procedure for Stopping Component Cooling System Abnormal RCPs is the same.

Procedures.

S2.0P-AB.RCP-0001 steps start on page 8 lE required, THEN remove the delay S2.0P-AB.CC-0001 steps start on page 13 from 22 CCW pump trip prior to the candidate tripping the reactor.

Page 3 of 17 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Component Cooling System TASK: Take Corrective Action For A Component Cooling Water System Abnormality STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD Stu evaluation)

Simulator Operator:

Insert RT-1 after candidate assumes the Reports 22 CCW pump has tripped.

watch.- The following alarms will annunciate:

MALF: CC0172B 22 Component

OHAs 020-02321/22/23/24 RCP Coaling Water Pump Trip BRG CLG WTR FLO LO.

MALF: CC0172A 21 Component

RCP Thermal Barrier Return La Cooling Water Pump Trip Flow.

DELAY: 4 minutes

21 and 22 CCW Header Lo Pressure Console alarms.

Note: Each of the Alarm Response actions Note: IF candidate announces intention is contained here, as well as the actions to trip the Rx before the remaining CCW contained in both S2.0P-AB.RCP-0001, pump has tripped, then remove Reactor Coolant Pump Abnormality, and remaining delay time from the 21 CCW S2.0P-AB.CC-0001, Component Cooling pump trip. Abnormality. Either of the Abnormal Procedures may be entered directly, or through the Alarm Response Procedure to get to ASs.

Determines that the standby CCW pump has failed to auto start, and attempts to manually start it here or when directed by Abnormal Procedure.

I ARP Refers to S2.0P-AR.ZZ-0004, Overhead 020-23 Window O.

Page 4 of 17 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE: ___________________

SYSTEM: Component Cooling System TASK: Take Corrective Action For A Component Cooling Water System Abnormality STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD S/U evaluation)

ARP Determines there are no automatic actions 020-23 associated with these alarms.

2.0 ARP CHECK OPEN the following Component Determines the following Component 020-23 Cooling Water valves: Cooling Water valves are open on CC1:

3.1 A. 2CC117, RCP CC MOT OP A. 2CC11 RCP CC MOT OP INLET INLETV. V.

B. 2CC118, RCP CC MOT OP B. 2CC118, RCP CC MOT OP INLET INLET VALVE VALVE C. 2CC136, RCP BRG MOT OP C. 2CC136, RCP BRG MOT OP OUTLET VALVE OUTLET VALVE D. 2CC187, RCP MOTOR CC D. 2CC187, RCP MOTOR CC MOTOR OPERATED OUTLET MOTOR OPERATED OUTLET VALVE. VALVE.

ARP MONITOR 21 RCP Motor Bearing Monitors 21 RCP Motor Bearing 020-23 temperatures. (T0413A, T0414A T0415A, temperatures. (T0413A, T0414A T0415A, 3.2 and T0416A) and T0416A) using P-250 computer on the Reactor Coolant Pumps screen, which has 21-24 RCP bearing temperatures.

Note: OHA 020-23 are identical except for bearing temperature instrument numbers.

Only OHA 0-20 for 21 RCP is listed here, but all RCP bearing temperatures should be monitored.

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

Page 5 of 17 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Component Cooling System TASK: Take Corrective Action For A Component Cooling Water System Abnormality STEP COMMENTS STEP EVAL (Required for UNSAT

(*Denotes a Critical Step)

NO. STANDARD S/U evaluatiof!l ARP !E either of the following conditions exist, 020-23 GO TO S2.0P-AB.RCP-0001(Q) Reactor 3.3 Coolant Pump Abnormality:

21 RCP Motor Bearing Determines 21 RCP Motor Bearing Temperature reaches 175°F, or Temperature has not reached 175° reach maximum of - 157 OF)

CCW flow can NOT be Determines that RCP Motor Bearing established within 5 minutes AND temperatures are not trending up. (The 21 RCP Motor Bearing temps will rise from -141 to 157 quickly, temperatures are trending within 3 minutes, and the curve of the line flattens out quickly. There IS still CCW flow going to the RCPs, and it WILL keep them from reaching required pump trip temperatures. !E pace of JPM performance results in it being determined that temperatures are trending up, THEN will go to S2.0P-AB.RCP-001 here.

ARP MONITOR CC Surge Tank and Determines CC Surge Tank and 020-23 Containment Sump Pump runs for Containment Sump Pump runs do not 3.4 leakage indication. indicate leakage.

ARFl** IF CC Console alarms header pressure Initiates S2.0P-AB.CC-0001, Component 020-23 low, OR Surge Tank Level High Low, Cooling Abnormality based on CC header 3.5 THEN INITIATE S2.0P-AB.CC-0001, Pressure low console alarms.

Component Cooling Abnormality.

ARP 21 (22) CC HDR PRESSURE LO Determines there are no automatic actions CC1 associated with these alarms.

2.0 Page 6 of 17 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE: __________________

SYSTEM: Component Cooling System TASK: Take Corrective Action For A Component Cooling Water System Abnormality STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD S/U evaluation)

ARP ENSURE Seal Injection Flow to each Checks seal injection to each RCP CC1 RCP is between 6-12 gpm NOT to between 6-12 gpm, and total seal injection 3.1 exceed 40 gpm total seal injection. flow less than 40 gpm.

ARP IF 2CC131 closed due to momentary Determines 2CC131 did not close on high CC1 high flow while balancing CC flow or flow while balancing CC flow or pump 3.2 pump shifting ... shifting.

ARP IF the High flow alarm also occurs ... Determines the High flow alarm is not CC1 alarmed.

3.3 ARP ENSURE OPEN: Determines the following valves are open CC1

2CC190, RCP THERM BAR CC on 2CC1:

3.4 OUTLETV.

2CC190, RCP THERM BAR CC

2CC117, RCP CC MOT OP OUTLETV.

INLETV.

2CC117, RCP CC MOT OP INLET

2CC118, RCP CC MOT OP V.

INLET VALVE.

2CC118, RCP CC MOT OP INLET

2CC131, RCP THERM BAR CC VALVE.

CO NT VALVE.

2CC131, RCP THERM BAR CC CONT VALVE. -_._.......... _

Page 7 of 17 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Component Cooling System TASK Take Corrective Action For A Component Cooling Water System Abnormality STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD S/U evaluation)

ARP IF the low flow alarm does NOT clear, CC1 THEN:

3.5 A. SEND an operator to:

1. MONITOR CC flow from each RCP seal locally.

2. ENSURE CC valve positions to/from each RCP.

B. GO TO S2.0P-AB.RCP-0001, Reactor Coolant Pump Abnormality.

i ABRCP INITIATE Attachment 1, Continuous Initiates Attachment 1. Continuous Action 3.1 Action Summary. Summary.

Note: The first 2 bulleted CAS actions for

1) losing CCW flow to ALL RCPs

2) not restoring CCW flow within 5 minutes of initial loss are based on a loss of ALL CCW flow.

However. if a conservative decision is made that the actions of Attachment 2.

Stopping Reactor Coolant Pumps are applicable, then CUE: The CRS directs you to dispatch an operator to 23 CCW pump breaker first to see if there is any apparent reason why 23 CCW pump breaker did not close.

~

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

Page 8 of 17 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM NAME:

DATE: __________________

JOB PERFORMANCE MEASURE SYSTEM: Component Cooling System TASK: Take Corrective Action For A Component Cooling Water System Abnormality STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD S/U evaluation)

ABRCP MONITOR AND COMPARE RCP Monitors and compares RCP parameters in 3.2 parameters in Attachment 3 to determine Attachment 3 on the Plant Computer, affected RCP(s) until malfunction is Control Console, and RP Panels, and corrected or as directed by SM/CRS. determines that all RCPs are affected.

I-- ----- ---- ~ ------

ABRCP !E Component Cooling Water supply is 3.3 causing the RCP(s) abnormal condition, THEN:

A. ENSURE the following automatic CC valves supplying RCP( s) are OPEN.

2CC117 AND 2CC118, RCP Determines 2CC117 AND 2CC118, RCP COOLING INLET COOLING INLET, 2CC131 AND 2CC190,

2CC131 AND 2CC190, RCP RCP THERMAL BARRIER VALVE. and THERMAL BARRIER VALVE 2CC136 AND 2CC187, RCP BEARING OUTLET valves are all open on control

2CC136 AND 2CC187, RCP console.

BEARING OUTLET Determines that CCW system operation B. ENSURE CCW Heat prior to the event was normal, and CCW I exchanger(s) in service lAW HX( s) are in service.

S2.0P-SO.CC-0002(Q), 21 & 22 Component Cooling Heat Cue if required: verification of CCW HX Exchanger Operation. operation is begun using S2.0P-SO.CC 0002, THEN cue: "21 & 22 CCW HX's are in service."

Page 9 of 17 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: Component Cooling System TASK: Take Corrective Action For A Component Cooling Water System Abnormality STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD Stu evaluation)

C. ENSURE RCP Sea! Injection Checks RCP Seal Injection flows are 6-12 flows are 6-12 gpm per pump, gpm per pump, total RCP Seal Injection NOT to exceed 40 gpm total RCP Flow adds up to < 40 gpm.

Seal Injection Flow.

i r- ------- ~~~~- f~~~ ------- ~~~~~~- I~~~ ----------

ABRCP any RCP Motor winding temperature, Determines all RCP Motor winding 3.4 indicated on 2RP4 recoder, is >235°F for temperatures, indicated on 2RP4 recoder, Hot Loop Conditions (Modes 1-4), OR are <235° for Hot Loop Conditions (Modes

>248°F for Cold Loop Conditions (Mode 1-4).

5) THEN:

Note: 2RP4 Motor winding temperature recorder is broken, so the following cue is required.

Cue: All RCP Motor winding temperatures, indicated on 2RP4 recoder, are <235° ABRCP IE Loss of Seal Injection is causing Determines Loss of Seal Injection flow is 3.5 RCP{s) abnormal condition, AND RCP not causing RCS(s) abnormal condition.

Seal Leakoff is <2.5 gpm on any RCP, THEN:

r-~~~~

ABRCP IF affected RCP Seal Water Leakoff is Determines affected RCP Seal Water 3.6 <0.8 gpm or is slowly appraoching 6 Leakoff is >0.8 gpm and is not slowly gpm, AND affected Pump bearing/sea approaching 6 gpm from console inlet temperatures are stable or indications.

lowqering, THEN:

Page 10 of 17 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

~---------

SYSTEM: Component Cooling System TASK: Take Corrective Action For A Component Cooling Water System Abnormality STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD S/U evaluation)

Note: 22 CCW pump will trip 4 minutes after 21 CCW pump trips.

Determines last remaining Component Cooling water has tripped.

-r-. - -

ABRCP IF AT ANY TIME, any of the validated Determines Component Cooling Water flow RCP conditions exist, THEN GO TO has been lost to all RCPs and goes to CAS 1.0 Attachment 2, Stopping Reactor Coolant Attachment 2, Stopping Reactor Coolant Pumps: pumps.

Page 11 of 17 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE: ___________________

SYSTEM: Component Cooling System TASK: Take Corrective Action For A Component Cooling Water System Abnormality STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD S/U evaluation)

AB.RCP lE Reactor Trip Breakers are CLOSED, Att.2 THEN:

1.0 1.1 TRIP the Reactor. Trips the Reactor using either trip handle.

1.2 STOP affected RCP(s). Depresses stop PBs for 21-24 RCPs.

1.3 IF RCP shutdown was due to RCP Determines RCP shutdown was not due to seal Leakoff flow> 6gpm, THEN RCP seal Leakoff flow> 6gpm.

simultaneously PERFORM the following:

1.4 IF RCP shutdown was due to a Determines RCP shutdown was due to a TOTAL LOSS of Component Cooling TOTAL LOSS of Component Cooling Water (including loss of CCW to the Water and simultaneously performs the CVCS Letdown Heat Exchanger), following:

THEN simultaneously PERFORM the following:

ISOLATE RCS letdown AND SWAP charging pump suction to the RWST by performing the following:

a) CLOSE 2CV2 AND Depresses the close PB for 2CV2 AND 2CV277 to isolate letdown. 2CV277 to isolate letdown.

b) OPEN 2SJ1 AND 2SJ2 to Depresses the open PB for 2SJ 1 AND swap charging pump 2SJ2 to swap charging pump suction to the suction to the RWST. RWST.

c) CLOSE 2CV40 AND Depresses the close PB for 2CV40 AND 2CV41 to isolate the VCT. 2CV41 to isolate the VCT.

GO TO 2-EOP-TRIP-1, Reactor Goes to 2-EOP-TRIP-1, Reactor Trip or Trip or Safety Injection AND Safety Injection.

RETURN to this attachment, at Terminate JPM when TRIP-1 immediate the SM/CRS discretion. actions begin to be performed.

Page 12 of 17 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM NAME:

DATE: __________________

JOB PERFORMANCE MEASURE SYSTEM: Component Cooling System TASK: Take Corrective Action For A Component Cooling Water System Abnormality STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD S/U evaluation)

AB.CC INITIATE Attachment 1, Continuous Initiates Attachment 1, Continuous Action 3.1 Action Summary. Summary.

~---

~~ ~-

Is CCW Surge Tank level >58% and Determines CCW Surge tank level is AB.CC rising? < 58% and stable from console indication, 3.2 goes to Step 3.13.

- ~- ~-

Is CCW Surge Tank level <42% and Determines CCW Surge tank level is AB.CC dropping? >42% and stable from console indication, 313 goes to Step 3.40.

~-~

AB.CC Is either of the following annunciators in 3.40 alarm?

21CCHDRPRESSURELO Determines both 21 and 22 CC HDR

-~

22 CC HDR PRESSURE LO PRESSURE LO annunciators are in alarm .

-~

.~-

AB.CC START available CC Pumps as Determines no CCW pumps are available 3.41 necessary to clear CC HDR PRESSURE to be started to clear CC HDR PRESSURE LO alarms(s). LO alarms(s).

Note: 22 CCW pump will trip 4 minutes after 21 CCW pump trips.

Determines last remaining Component Cooling water has tripped.

-- ~-~ ~ --

Page 13 of 17 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM NAME:

DATE: ___________________

JOB PERFORMANCE MEASURE SYSTEM: Component Cooling System TASK: Take Corrective Action For A Component Cooling Water System Abnormality STEP COMMENTS STEP

(*Denotes a Critical Step) EVAL (Required for UNSAT

NO. STANDARD S/U evaluation)

AB.CC IF AT ANY TIME, any of the validated Determines Component Cooling Water flow CAS conditions exist, THEN STOP RCP's has been lost to all RCPs and goes to lAW Attachment 2, Stopping Reactor Attachment Stopping Reactor Coolant 1.0 Coolant Pumps: pumps.

I Page 14 of 17 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE: ___________________

SYSTEM: Component Cooling System TASK Take Corrective Action For A Component Cooling Water System Abnormality STEP COMMENTS STEP EVAL (Required for UNSAT

(*Denotes a Critical Step)

NO. STANDARD S/U evaluation)

IF Reactor Trip Breakers are CLOSED, THEN:

A. TRIP the Reactor. Trips the Reactor using either trip handle.

B. STOP affected RCP( s). Depresses stop PBs for 21-24 RCPs.

C. Simultaneously PERFORM the following:

IF a total loss of Component Cooling Water was the initiating event (including loss of CCW to the evcs Letdown Heat Exchanger), THEN ISOLATE RCS letdown AND SWAP Charging Pump suction to the RWST as follows:

a. CLOSE 2CV2 AND 2CV277 to Depresses the close PB for 2CV2 AND isolate letdown. 2CV277 to isolate letdown.

b. OPEN 2SJ1 AND 2SJ2 to swap Depresses the open PB for 2SJ 1 AND charging pump suction to the 2SJ2 to swap charging pump suction to the RWST. RWST.

c.CLOSE 2CV40 AND 2CV41 to Depresses the close PB for 2CV40 AND isolate the VCT. 2CV41 to isolate the VCT.

IF a Component Cooling Water Detemines CCW leak in containment was LEAK in Containment with not the initiating event.

2CC 113 AN D 2CC215 closed was the initiating event, THEN CLOSE the following valves:

GO TO 2-EOP-TRIP-1, Reactor Goes to 2-EOP-TRIP-1, Reactor Trip or Trip or Safety Injection. Safety Injection.

Terminate JPM when TRIP-1 immediate actions begin to be performed.

Page 15 of 17 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to ...IPM usage, revalidate JPM using steps 8 and 11 below,

\t..(}I..r 1. Task description and number. JPM description and number are identified.

v.rJI- 2. Knowledge and Abilities (KIA) references are included.

\Ut- 3, Performance location specified. (in-plant, control room, or simulator) lto-- 4. Initial setup conditions are identified. _ _ _ 5. Initiating and terminating Cues are properly identified.

\lC;---- 6. Task standards identified and verified by SME review.

--=-___ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

\Ui-- 8. Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. 1'1 Date 6*10. "

~

\Lv 9. Pilot test the JPM: 1.. 6

a. verify Cues both verbal and visual are free of conflict, and

b. ensure performance time is accurate.

_ _ _ _ 10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

____ 11. When JPM is revalidated, SME or Instructor sign and date ..IPM cover page, SME/lnstructor:_1+-~-=---_*_n---=.-,~>-==,-'

'-'-'--_ _ __ Date: _{_'_30_"_1_'_ _

SMEllnstructor: Date: _ _ _ _ __

SME/lnstructor:_ _ _ _ _ _ _ _ _ _ _ ___ Date: _______

Page 16 of 17 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

INITIAL CONDITIONS:

100% power, EOL.

INITIATING CUE:

You are the Reactor Operator. Respond to all alarms and indications.

Page 17 of 17 PSEG Restricte~ - Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Control Room Evacuation TASK: Control charging flow after Control Room evacuation.

TASK NUMBER: 1130070501 JPM NUMBER: 09-01 NRC IP-i ALTERNATE PATH: KIA NUMBER: APE 068 AA1.22

~

IMPORTANCE FACTOR: 4.0 4.3 APPLICABILITY: RO SRO EOL] ROm STAL] SROm EVALUATION SETTING/IVIETHOD: In Plant/Simulate

REFERENCES:

S2.OP-AB.CR-0001, Rev. 22 Att.5 TOOLS AND EQUIPMENT: JAM Key VALIDATED JPM COMPLETION TIME: 10 min TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 06-30-11 Instructor Validated By: J Pierce, Jr Date: 07-28-11 SIVIE or Instructor

/.~nt Approved By: Date: :(-"2-- I I Approved By:

~~Departmen; Date: g If /11 ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION TIME:

PERFORMED BY:

GRADE: D SAT 0 UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

Page 1 of7

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:

DATE:

SYSTEM: CVCS TASK: Control charging flow after Control Room evacuation.

TASK NUMBER: 1130070501 INITIAL CONDITIONS:

1. The Control Room has been evacuated in accordance with S2.0P-AB.CR-0001, Control Room Evacuation.

2. A reactor trip from 100% was initiated prior to evacuating the Control Room.

INITIATING CUE:

You have been directed to take local control of charging flow per S2.0P-AB.CR-0001, Control Room Evacuation Att. 5, starting at Step 8.0. Steps 1.0-7,0 have been completed.

Successful Completion Criteria:

1. All critical steps completed.

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPIVI completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made.

Task Standard for Successful Completion:

1. Take local control of 2CV55.

2, Adjust air operator to change charging flow from current reading to 70 gpm.

Page 2 of7

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: CVCS TASK: Control charging flow after Control Room evacuation.

STEP COMMENTS STEP (Required for

(*Denotes a Critical Step) EVAL NO. STANDARD UNSAT S/U evaluation)

-~

r-Operator reviews a copy of Evaluator provides copy of Attachment 5, S2.0P-AB.CR-0001, Att. 5, and proceeds to and a JAM Key.

Charging Pump Alley, EI. 84.

Note: If operator inquires why steps 1.0 7.0 are not signed off, state that another operator performed those steps and still has the procedure with him in the field.

Proceeds to Panel 216-2, Chg Pmps FL

& PR Inst Pnl.

Note: Panel 216-2 will alarm in the Control Room. The Control Room must be notified prior to opening this panel, and when it is secured.

8.0 TAKE local control of 2CV55, Cent Chg Pmp Flow Cont Valve, by performing the following:

8.1 RECORD the charging flow as indicated on Records charging flow from 2FI-128A, 2FI-128A. Charging Pump Flow Indication.

Locates local E/P Bypass Line Selector

8.2 PLACE local E/P Bypass Line Selector Valve Valve and discusses turning valve to in Manual.

Manual.

Page 3 of7

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM: CVCS TASK: Control charging flow after Control Room evacuation.

STEP COMMENTS i STEP (Required for

(*Denotes a Critical Step) EVAL NO. STANDARD UNSAT StU evaluation) 8.3 Using the MANUAL hand air operator, Reads flowrate from 2FI-128A, Charging ENSURE that the flow rate as noted in Step Pump Flow Indication to ensure the flow 8.1 is being maintained with 2CV55. rate is maintained with 2CV55.

Cue: Flow rate is the same as that recorded in Step 8.1.

[ 8.4 OBSERVE local air pressure indicator to verify local control.

Points out local air pressure indicator.

Cue: Air pressure on local air pressure indicator is 8 psig.

Page 4 of7

OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE: - - - - - - -

SYSTEM: CVCS TASK: Control charging flow after Control Room evacuation.

COMMENTS STEP STEP (Required for

NO.

(*Denotes a Critical Step)

STANDARD EVAL UNSAT S/U evaluation) 9.0 NOTIFY the CRS and STA that Steps 1.0-8.0 Locates page or states that they would of Att. 5 are completed. walk to HSD Panel, to inform CRS and STA that steps 1-8 of Attachment 5 are completed.

Note: May inform CRS and STA that Step 8 is completed, since they didn't perform Steps 1-7.

Cue: The CRS directs you to adjust charging flow to 70 gpm (Evaluator: or a value not currently read on FI-128A).

~ --- ----

Discusses adjusting flow using MANUAL hand air operator. Raises air pressure to

lower flow or lowers air pressure to raise flow. (2CV55, Cent Chg Pmp Flow Cant Valve is fail open valve)

Cue: If candidate states they would LOWER air pressure, then provide feedback that charging flow indicated on FI-128A has risen to 5 gpm above that recorded in Step 8.1. When candidate RAISES air pressure, then provide feedback that charging flow indicated on FI-128A has lowered to 70 gpm.

--- i Terminating Cue: Adjusts air pressure to match new requested flow rate. $tate "this JPM is terminated".

Page 5 of 7

JOB PERFORl'VlANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 and 11 below.

7- 1. Task description and number, JPM description and number are identified.

'Y 2. Knowledge and Abilities (KIA) references are included.

/

!J/" 3. Performance location specified. (in-plant, control room, or simulator) 7 1/ 4. Initial setup conditions are identified.

7 JL"

5. Initiating and terminating Cues are properly identified.

6. Task standards identified and verified by SME review.

~ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

8. Verify the procedure referenced by this JPM matches the most current revision of that procedure: Procedure Rev. 1..'1.- Date 1!-,..Kf' I

9. Pilot test the JPM:

a. verify Cues both verbal and visual are free of conflict, and

+-

b. ensure performance time is accurate.

10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

l' 11. \\Then JPM is revalidated, SME or Instructor sign and date JPM cover page.

SME/Instructor: ff/L~

t/

~.>>I ~£.. Date:

SME/Instructor:_ _ _ _._ _ _ _ _ _ _ _ __ Date: - - - - - -

SME/Instructor: Date: _ _ _ _ __

Page 6 of 7

INITIAL CONDITIONS:

1. The Control Room has been evacuated in accordance with S2.0P-AB.CR-0001, Control Room Evacuation.

2. A reactor trip from 100% was initiated prior to evacuating the Control Room.

INITIATING CUE:

You have been directed to take local control of charging flow per S2.0P-AB.CR-0001, Control Room Evacuation Att. 6, starting at Step 8.0. Steps 1.0-7.0 have been completed.

Page 7 of 7

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Auxiliary Feedwater TASK: Reset Auxiliary Feedwater Pump Turbine Trip Valve MSS2 TASK NUMBER: 113004 OS 01 JPM NUMBER: 09-01 NRC IP-j ALTERNATE PATH: I I KIA NUMBER: APE 068 AA1.02

~

IMPORTANCE FACTOR: 4.3 4.S APPLICABILITY: RO SRO EoD ROm STAD SROm EVALUATION SETTING/METHOD: In Plant 51 i7

REFERENCES:

rSrOP-AB.CR-0001, Control Room Evacuation, Rev~ Att. 13 A~hC;-t! ).}g,j"l-IJ TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 8 min TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 06-24-11 Instructor Validated By: J Pierce, Jr. Date: 07 11 SME or Instructor K~~

Approved By: Date: .r:z,- 1 I Approved By:

~Operations Department Date: 8}, JI' ACTUAL JPM COMPLETION TIME:

ACTUAL TIIVIE CRITICAL COMPLETION TIME:

PERFORMED BY:

GRADE: D SAT D UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

Page 1 of 7 PSEG Restricted- Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM NAME______________

JOB PERFORMANCE MEASURE DATE_____________

SYSTEM: AUXILIARY FEEDWATER SYSTEM TASK: Reset an Auxiliary Feedwater Turbine Trip Valve (MS52)

TASK NUMBER: 1130040501 INITIAL CONDITIONS: Unit 1 reactor has been tripped and the Unit 1 control room has been evacuated due to a bomb threat. 13 AFW Pump has tripped on over speed.

INITIATING CUE: You have been directed to reset 13 AFW Pump Turbine Trip Valve (1 MS52) lAW S1.0P-AB.CR-0001, Control Room Evacuation, Attachment 13, Turbine - Driven AFW Pump Restoration. Maintenance has corrected the cause of the overspeed trip, and there are no AUTO start signals present for 13 AFW pump.

SUCCESSFUL COMPLETION CRITERIA:

1. ALL critical steps completed

2. ALL sequential steps completed in order

3. ALL time-critical steps completed within the allotted time JPM completed within validated time.

Completion may exceed the validated time if satisfactory progress is being made (and NRC concurrence is obtained).

Task Standard for Successful Completion:

1. Perform Attachment 13 in correct sequence.

Page 2 of 7 PSEG Restricted- Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:_ _ _ _ _ _ _ __

DATE:_ _ _ _ _ _ _ __

SYSTEM: Auxiliary Feedwater TASK: Reset MS52 STEP STEP STANDARD EVAL COMMENTS

No. (*Denotes Critical Step) S/U Provide operator with the correct procedure, Operator obtains procedure.

I S1.0P-AB.CR-0001, Rev. 17, Att.13.

I ---

Contacts Control Room and reports that they will be entering 13 AFP Room.

Note: 13 AFP Room is a High Energy Line Break (HELB) area, and the Control Room must be contacted prior to opening door or access panel to room.

1.0 RESETTING 1MS52

1.1 SEAT tappet nut by slightly pulling Head Lever Verifies tappet nut seated and EMERGENCY away from trip linkage AND CHECK that the TRIP LEVER in reset position.

Emergency Trip Lever is in its RESET position (horizontal). Cue: Tappet nut seated and EMERGENCY TRIP LEVER is reset.

1.2 ROTATE 1 MS52 handwheel in the closed Simulates rotating 1MS52 13 AFW Pp Turbine direction (clockwise). This will cause the Latch- Trip Valve handwheel clockwise and verifies Up Lever to move up toward the Trip Hook. Latch-Up Lever moving toward Trip Hook.

Cue: Lever is moving towards trip hook.

~----- ---

Page 3 of 7 PSEG Restricted- Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:_ _ _ _ _ _ _ __

DATE:_ _ _ _ _ _ _ _ __

SYSTEM: Auxiliary Feedwater TASK: Reset MS52 STEP STEP STANDARD EVAL* COMMENTS

No. (*DenotesCritical Step) S/U 1.3 CHECK that the Latch-Up Lever moves up into position, that it moves to and engages the Trip

Hook. Verifies Trip Hook engages.

Cue: Trip Hook is engaged.

Points out Hand Trip Lever to ensure full 1A PULL UP on the Hand Trip Lever to ensure full engagement of the Trip Hook and Latch-up engagement of the Trip Hook and Latch-up Lever.

Lever.

Cue: Trip Hook and Latch-up Lever are fully engaged. ------ ,

I CAUTION:

Extra caution is advised while in the Turbine Driven AFW Pump Room when resetting the AFW Pump with AUTO Start signals locked in.

In this condition, the pump will start Leaving 1MS52 backseated may impose more reaction loading on the Trip Hook than the Trip Linkage can overcome, thus rendering the 1MS52 trip function INOPERABLE.

._---------J

1.5 Slowly ROTATE 1MS52 handwheel in the Simulates rotating Handwheel counter-OPEN direction (counter-clockwise) until the clockwise and verifies Split Coupling makes Split Coupling raises and makes contact with contact with Sliding Nut OR the valve comes to the bottom of the Sliding Nut OR the valve rest on the backseat.

comes to rest on the backseat.

Cue: Split Coupling makes contact with Sliding Nut.

Page 4 of 7 PSEG Restricted- Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME:_________________

DATE:_____________

SYSTEM: Auxiliary Feedwater TASK: Reset MS52

,~~

STEP STEP STANDARD EVAL COMMENTS

No . (*DenotesCritical Step) *.. S/U

1.6 ROTATE 1MS52 handwheel clockwise Simulates rotating 1MS52 Handwheel clockwise approximately one turn until handwheel moves one turn and verifies Handwheel moves freely freely AND Latch-up lever is in full contact with AND Latch-up lever is in full contact with Trip Trip Hook. Hook.

Cue: Handwheel moves freely and Latch-up lever is in full contact with Trip Hook.

-~~ -~~~~

1.7 ENSURE turbine stops spinning (indicates Determines shaft is not spinning.

1MS 132 is seated) ~-~

1.8 ENSURE proper engagement of tappet nut and Ensures proper engagement of tappet nut and head lever lAW Alt. 13, page 2, 13 AF Pump head lever lAW AU. 13, page 2.

TriplThrottle Valve & Overspeed Trip Mechanism, Overspeed Trip Mechanism Reset.

TERMINATING CUE: When report is made that 1MS52 is reset; state JPM is complete. Ensure Control Room is contacted after 13 AFW pump room access door/panel is shut.

Page 5 of 7 PSEG Restricted- Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate ...IPM using steps 8 and 11 below.

F 1. Task description and number, JPM description and number are identified.

_---j~1<--_2. Knowledge and Abilities (KIA) references are included.

/

--7.,.9r~- 3. Performance location specified. (in-plant. control room, or simulator)

JL 4. Initial setup conditions are identified.

~ 5. Initiating and terminating Cues are properly identified.

-_;Y~_6. Task standards identified and verified by SME review.

,Ij/ 7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

)L 8. Verify the procedure referenced by this JPM manh%theP i t cur,:,nt revision of that procedure: Procedure Rev. z.. '2- Date 'I 1.(.'Z 7..1")

L} 9. Pilot test the JPM:

-;- a. verify Cues both verbal and visual are free of conflict, and

b. ensure performance time is accurate.

/: 10. If the JPM cannot be performed as written with proper responses, then revise the ...IPM.

~ 11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

SME/lnstructor:--;tf--~,-- _ _ _ _-=-J-,-*_5>-,,--_\~

__ Date: _?+-h_)...--""f,+-/r..:....:{(~_

I 7 SMEll Date: _ _ _ _ __

SME/lnstructor:_ _ _ _ _ _ _ _ _ _ _ __ Date: - - - - -

i l7

""" O. A Pag&6-6f1J:/,J.. S-f7~ II PSEG Restricted- Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

Unit 1 reactor has been tripped and the Unit 1 control room has been evacuated due to a bomb threat. 13 AFW Pump has tripped on over speed.

INITIATING CUE:

You have been directed to reset 13 AFW Pump Turbine Trip Valve ('I MS52) lAW S1.0P-AB.CR-0001, Control Room Evacuation, Attachment 13, Turbine - Driven AFW Pump Restoration. Maintenance has corrected the cause of the overspeed trip, and there are no AUTO start signals present for 13 AFW pump.

Page 7 of 7 PSEG Restricted- Possession Requires Specific Permission from Nuclear Training

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE STATION: SALEM SYSTEM: Control Room Evacuation TASK: TCAF Control Room Evacuation (Trip Turbine, Open Exciter Field Breaker, Trip SGFP's)

TASK NUMBER: 1140130401 JPM NUMBER: 09-01 NRC IP-k ALTERNATE PATH: D KIA NUMBER:

IMPORTANCE FACTOR:

APE 068 AA 1.04, AA 1.23, All >2.5 AA1.27 All >2.5 APPLICABI LlTY: RO SRO EOO ROW* STAO SROW EVALUATION SETTING/METHOD: In Plant! Simulate

REFERENCES:

S2.0P-AB.CR-0001, Rev. 22 Att.8 (checked 6-24-11)

TOOLS AND EQUIPMENT: None VALIDATED JPM COMPLETION TIME: 10 min TIME PERIOD IDENTIFIED FOR TIME CRITICAL STEPS: N/A Developed By: G Gauding Date: 06-24-11 Lead Regulatory Exam Author Validated By: ~. -P.CY':'~ Date: i *ZJ?*/l SME or Instructor Approved By: p~ Date: /? - \,

c:YfflIning Department Approved By: ~ * ~ Date: s/l/II Opera~ Dep~-rt~ent ACTUAL JPM COMPLETION TIME:

ACTUAL TIME CRITICAL COMPLETION TIME:

PERFORMED BY:

GRADE: D SAT UNSAT REASON, IF UNSATISFACTORY:

EVALUATOR'S SIGNATURE: DATE:

PSEG Restricted- Possession Requires Specific Approval from Nuclear Training Page 1 of 6

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE NAME: __________________________

DATE: __________________________

SYSTEM: Control Room Evacuation TASK: TCAF Control Room Evacuation (Trip Turbine, Open Exciter Field Breaker, Trip SGFP's)

TASK 1140130401 NUMBER:

INITIAL CONDITIONS:

The control room has been evacuated due to a bomb threat.

INITIATING CUE:

You are assigned to carry out the actions of S2.0P-AB.CR-001, Control Room Evacuation, Attachment 8, Steps 2.0-4.0: Trip the Main Turbine, open the Exciter Field Breaker, Trip both SGFP's. Assume you have the equipment required by the procedure.

I Successful Completion Criteria: I

1. All critical steps completed.

2. All sequential steps completed in order.

3. All time-critical steps completed within allotted time.

4. JPM completed within validated time. Completion time may exceed the validated time if satisfactory progress is being made (and NRC concurrence is obtained).

Task Standard for Successful Completion:

1. Locate and describe TRIP operation of Reset-Normal-Trip Lever at Turbine Front standard.

2. Locate and describe opening of Exciter Field Breaker.

3. At SGFP area, locate and describe at least one method of locally tripping SGFPs.

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OPERATOR TRAINING PROGRAM N~E: __________________________

JOB PERFORMANCE MEASURE DATE:

SYSTEM ABNORMAL PROCEDURES TASK: TCAF Control Room Evacuation: Trip MT, Open Exciter Field Breaker, Trip SGFP's STEP COMMENTS

STEP (*Denotes a Critical Step) EVAL (Required for UNSAT

NO. (#Denotes a Sequential Step) STANDARD StU Evaluation) 1 Evaluator provides copy of S2.0P Operator reviews procedure. AB.CR-1, Control Room Evacuation AU. 8.

2 Proceed to Turbine Front Standard, and place the Reset-Normal-Trip Lever in the Proceeds to turbine front standard, TRIP position. locates Reset-Norma/-Trip lever and points out TRIP position.

3 Proceed to Excitation System Control Cubicle and open Generator Exciter Field Proceeds to Turb. Bldg., EI. 120, Breaker. (North End) locates Generator Exciter Field Breaker and discusses opening.

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OPERATOR TRAINING PROGRAM NAME:

JOB PERFORMANCE MEASURE DATE:

SYSTEM ABNORMAL PROCEDURES TASK: TeAF Control Room Evacuation: Trip MT, Open Exciter Field Breaker, SGFP's STEP COMMENTS

STEP (*Denotes a Critical Step) EVAL (Required for UNSAT

NO. (#Denotes a Seauential Step) STANDARD S/U Evaluation)

4 Locally, trip the following:

21 SGFP Proceeds to Turb. Bldg., EI. 100, and

SGFP discusses operation of at least one of the ways to locally trip the SGFPs.

1. Pulling out the OS trip plunger

2. Depressing the "Local Emergency TRIP" button under glass on side of SGFP.

3. Depressing the Emergency Stop PB on the Woodward 505 Digital Control panel.

4. Opening Thrust Oil drain valves 21 PL73 or 22PL73.

(21 SGFP Trip Test Loading Oil ISLN VL V behind panel; same for

22) (!.f..they select a different method such as de-energizing COPU, evaluate after JPM complete)

CUE: JPM is complete PSEG Restricted- Possession Requires Specific Approval from Nuclear Training Page 4 of 6

OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation. Prior to JPM usage, revalidate JPM using steps 8 and 11 below.

jc: 1. Task description and number, JPM description and number are identified.

~ 2. Knowledge and Abilities (KIA) references are included.

~ 3. Performance location specified. (in-plant, control room, or Simulator)

_--;y,-_ 4. Initial setup conditions are identified.

-_7"'Y,-- 5. Initiating and terminating Cues are properly identified.

~ 6. Task standards identified and verified by SME review.

_-+-,,,c-_7. Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

'-t>'--- 9. Pilot test the JPM:

a. verify Cues both verbal and visual are free of conflict, and

b. ensure performance time is accurate.

_-r:-__ 10. If the JPM cannot be performed as written with proper responses, then revise the JPM.

_--f..,.c-_11. When JPM is revalidated, SME or Instructor sign and date JPM cover page.

SMEIlnstructor. /~.:> "',~ . Date: _7-r-t_'2..._R-f-6_---.f_

I I Date: - - - - - -

Date: _ _ _ _ __

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OPERATOR TRAINING PROGRAM JOB PERFORMANCE MEASURE INITIAL CONDITIONS:

The control room has been evacuated due to a bomb threat.

INITIATING CUE: You are assigned to carry out the actions of S2.0P-AB.CR-001, Control Room Evacuation, Attachment 8, Steps 2.0-4.0: Trip the Main Turbine, open the Exciter Field Breaker, Trip both SGFP's. Assume you have the equipment required by the procedure.

PSEG Restricted- Possession Requires Specific Approval from Nuclear Training Page 6 of 6

Appendix D Scenario Outline Form ES-D-1 Facility: SALEM 1 & 2 Scenario No.: ESG-1 Op-Test No.: 09-01 NRC Examiners: Operators:

Initial Conditions: 100% power, BOL. 21 AFW pp CIT for oil leak repair. 21 CFCU is CIT. PZR Pressure channel II is O/S for calibration.

Turnover: Maintain 100% power.

Event No.

Malf. No.

Event Type*

Event Description I

1 PR0017A I I Controlling PZR level ch failure (TS)

CRS/RO C

2 RCOO02 RCS leak (TS)

ALL N

3 Power Reduction (directed based on RCS leak)

ALL M

4 RCOOO2 ALL SBLOCA (-100 gpm) I RP0342 C 5 Failure of automatic High Head injection RP0343 CRS/RO AF0182A C

6 RP318E2 AFW fails to automatically actuate CRS/PO O/R B606 C

7 O/R C206 SEC fails to reset CRS/PO C

8 RCOO02 SBLOCA escalation (ECCS flow re-initiation in TRIP-3)

I CRS/RO I

crs 1. Establish hi head ECCS. 2. Initiate AFW flow.

3.Re-start ECCS pps

.. I

(N)ormal, (R)eactlvlty, (I)nstrument, (C)omponent, (M)aJor O/R = Override Appendix D, Page 38 of 39

TQ~AA~1 06~0204 Page 1 of 30 SIMULATOR EXAMINATION SCENARIO GUIDE SCENARIO TITLE: Res Leak, Escalating SBLOCA SCENARIO NUMBER: 09-01 NRC ESG-1 EFFECTIVE DATE: See Approval Date EXPECTED DURATION: 77 minutes REVISION NUMBER: 00 PROGRAM: '------'----'

L.O. REQUAL X I INITIAL LICENSE L...::......;..~"'-.J STA

'---~---J OTHER Revision Summary New Issue for 09-01 NRC Exam PREPARED BY: G Gauding Lead Regulatory Exam Author Date O~~~

APPROVED BY:

Manager Date APPROVED BY: B~ III ate PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 3 of 30 A. Given a situation with an OHA alarm, the crew will perform action(s) to investigate and correct the cause of the alarm, lAW approved station procedures.

B. Given the unit with multiple OHAs in alarm, the crew will prioritize, validate and then determine a course of action when provided with additional information, lAW approved station procedures.

C. Given the order or indications of a charging system malfunction, perform actions as the nuclear control operator to RESPOND to the loss or malfunction of the charging system in accordance with the approved station procedures.

D. Given indication of a loss or malfunction of the Charging system DIRECT corrective action for a Charging System malfunction in accordance with the approved station procedures.

E. Given the indications of a reactor coolant system (RCS) malfunction or leak, perform actions as the nuclear control operator to RESPOND to the malfunction in accordance with the approved station procedures.

F. Given the indications of a reactor coolant system (RCS) malfunction or leak, DIRECT the response to the malfunction in accordance with the approved station procedures.

G. Given the unit at power with an RCS leak greater than the Tech. Spec. limit, take corrective action lAW AB.RC-0001.

H. Given the order or indications of a reactor trip, perform actions as the nuclear control operator to RESPOND to the reactor trip in accordance with the approved station procedures.

I. Given indication of a reactor trip, DIRECT the response to the reactor trip in accordance with the approved station procedures.

J. Given the order or indications of a safety injection perform actions as the nuclear control operator to RESPOND to the safety injection in accordance with the approved station procedures.

K. Given indication of a safety injection DIRECT the response to the safety injection in accordance with the approved station procedures.

L. Given the order or indications of a loss of coolant accident (LOCA), complete actions as the nuclear control operator to PERFORM the immediate response to the LOCA in accordance with the approved station procedures.

M. Given indication of a loss of coolant accident (LOCA), DIRECT the immediate response to the LOCA in accordance with the approved station procedures.

N. During performance of emergency operating procedures, monitor the critical safety function status trees in accordance the EOP in effect.

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TQ-AA-106-0204 Page 4 of 30 A, Controlling PZR level channel fails low B, 17 gpm RCS leak C. 100 gpm SBLOCA D, 1800 gpm SBLOCA A. The crew takes the watch with the unit at 100% power, BOL 21 AFW pump is CIT for oil bubbler repair. 21 CFCU is CIT after it tripped 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ago, I&C is performing a channel calibration of PZR Pressure Channel II. 2PR7 is shut with power removed to comply with TSAS 3.4.5,b. All bistables associated with PZR Pressure Channell! are tripped lAW S2.IC.

CC.RCP-0018, 2PT-456 Pressurizer Pressure Protection Channel II. Orders for the shift are to maintain 100% power.

B, Shortly after taking the watch the controlling PZR level channel will fail low, and a 17 gpm RCS leak will commence ramping in over 12 minutes. The CRS will enter S2.0P-AB.CVC-0001, Loss of Charging. The crew will respond and take manual control of the Master Flow Controller, swap to an operable level channel, restore letdown and PZR level, and return the system to auto. The CRS will enter the appropriate Tech Spec.

C. The crew will diagnose the RCS leak based on indications and alarms. The CRS will enter S2.0P-AB.RC-0001, Reactor Coolant System Leak. The crew will swap to a centrifugal charging pump and quantify the leak. The CRS will identify that the Unidentified RCS leak rate exceeds Tech Spec limits, and a unit shutdown is required.

D. During the power reduction, the RCS leak will worsen to a 100 gpm SBLOCA The crew will identify that the RCS leak rate exceeds the capacity of the CVCS makeup system. The CRS will direct a Rx trip and Safety Injection be initiated.

E. The High Head ECCS injection valves 2SJ12 and 2SJ13 fail to open on the Safety Injection signal. The crew opens the valves from the control room to establish High Head ECCS injection.

F. AFW fails to initiate based on: 21 AFW pump CIT, 22 AFW pump fails to start on the SEC initiation signal, and 23 AFW pump governor fads to minimum speed. The crew establishes AFW flow by blocking and resetting 2B SEC and starting 22 AFW pump. 23 AFW pump remains unavailable for the remainder of the scenario.

G. The crew performs diagnostics in EOP-TRIP-1, Rx Trip Response, and transitions to EOP TRIP-3, Safety Injection Termination based on the size of the RCS LOCA. The 2C SEC cannot be reset, and will be deenergized to establish control over C bus equipment.

H. Once ECCS equipment has been removed from service, the SBLOCA will increase in size.

The crew will diagnose the inability to maintain PZR level, and start ECCS pumps to maintain PZR and RCS subcooling.

I. The scenario will be terminated when the crew has started sufficient ECCS pumps to maintain PZR level and RCS subcooling .

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TQ-AA-106-0204 Page 5 of 30 IC-241 100% power, BOL 1 RH1 and RH2 crr 2 RH18s crr 3 VC1 and VC4 crr 4 RCPs (SELF CHECK)

_ 5 RTBs (SELF CHECK)

_ 6 MS167s (SELF CHECK)

_ 7 500 KV SWYD (SELF CHECK)

_ 8 SGFP Trip (SELF CHECK) 9 23 CV PP (SELF CHECK)

_ 10 21 AFW pump CIT.

11 21 CFCU CIT.

_ 12 2PR7 shut and deenergized.

13 S2.1C-CC-RCP-0018, 2PT-456 Pressurizer Pressure Protection Channel II, Exhibit 1 signed and on NCO desk or provided to crew for turnover.

14 SGBD directed to Condenser placard on 2CC3.

15 Complete Attachment 2 "Simulator Ready-for-Training/Examination Checklist."

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TQ-AA-106-0204 Page 6 of 30 Note: Tables with blue headings may be populated by external program, do not change column name without consulting Simulator Support group Description EVENT MONP254 <10 /1 CONT ROD BANK C < 10 ( RX TRIP)

ACTION:

1 COMMAND: <update as needed>

PURPOSE:

04 06

.AN0328 SER 328 FAILS - :A12 REACTOR PROT.SYS 07 N/A CHANNEL II INSTRUMENT LOOP IN TEST PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 7 of 30 SELF CHECK 01 6606 F 01 23 AUX FEED PUMP-SPEED 02 i 6606 E 0123 AUX FEED PUMP-SPEED INCREASE

. C206 A 01 2C SFGD EMER OPR-EMERG LOADING 03 N!A N/A OFF RESET

1. !\Jone PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106*0204 Page 8 of 30 A. State shift job assignments and review scenario objectives.

Hold a shift briefing, detailing instruction to the shift: (provide crew members a copy of the shift turnover sheet).

C. Inform the crew "The simulator is running. You may commence panel walkdowns at this time.

CRS please inform me when your crew is ready to assume the shift".

D. Allow sufficient time for panel walk-downs. When informed by the CRS that the crew is ready to assume the shift, ensure the simulator is cleared of unauthorized personnel.

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TQ-AA-106-0204 Page 9 of 30

1. PZR Level Controlling Channel (LT4S9) Fails Lo

. 'ondirection.froni*;te s.*:. -. m..9.'.a.,t.or:.p. '. p.'~. r. . a..*. .!.pr:)rll

~:>> :",:-:': ",

i.

,<':,-,y::->"

RO announces OHA E-36, PZR HTR OFF LVL LO, and console alarm PZR LO LVL as unexpected, and diagnoses failure of PZR controlling level channel.

'RO may place Master Flow Controller in manual and reduce flow to minimize level rise in PZR prior to Abnormal Procedure entry.

CRS enters S2.0P-AB.CVC-0001, Loss of Charging.

CRS directs initiation of Attachment 1, Continuous Action Summary.

RO reports letdown is isolated.

RO reports 23 charging pump is running.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 p

RO reports there is no indication of cavitation.

RO reports PZR level channel I has failed low.

Note: RCP seal injection flow RO takes manual control of charging flow if not lower as charging flow is lowered, previously done, and lowers charging flow to and CV71 may have to be adjusted minimize level rise in PZR.

to maintain at least 6 gpm seal injection flow to each RCP.

RO selects channel III for control, and reports expected clearing of OHA E-36, PZR HTR OFF LVL LO, and console alarm PZR LO LVL.

RO reports OHA E20, PZR HTR ON LVL HI as expected due to no letdown flow.

RO places control heaters and one group of backup heaters in ON.

Note: An auto makeup to the VCT PO restores letdown by:

may occur depending on how - Ensuring open 2CV7 quickly crew restores letdown flow, - Placing 2CV18 in Manual closed and is an expected condition. - Opening 2CV18 until close PB extinguishes.

Opening 2CV2 and 2CV277 and placing in auto.

- Ensure charging flow 85-90 gpm.

- Open a 75 gpm orifice while adjusting 2CV18 to maintain letdown pressure -300 psig.

When selected orifice is open, place 2CV18 in auto.

CRS directs RO to restore charging flow PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 11 of 30 controller to auto when PZR level is restored to program.

Note: Charging flow should not be RO manually lowers charging flow to restore lowered lower than -65 gpm to PZR level is restored to program.

ensure adequate cooling of letdown flow through the Regen HX and prevent flashing in the Letdown CRS directs PO to remove PZR level channel I from service lAW S2.0P-SO.RPS-0003.

CRS enters TSAS 3.3.1.1 action 6.

PO verifies PZR Level channel III selected for control, Channel II selected for alarm, and selects PZR level recorder to channel II or III.

PO informs CRS that IC support is required to perform remainder of procedure.

Note: Crew may identify rising 2R11 A prior to RMS alarm. CRS should enter S2.0P-AB.RC-0001, Reactor Coolant System Leak, or S2.OP-AB.RAO-0001, Abnormal Radiation upon indication that containment radiation level is rising.

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TQ-AA-106-0204 12 of 30

2. Res leak Note: The 2R11A monitor, RO announces unexpected OHA A-5, RMS Containment Particulate, will go Trouble.

into warning at -8 minutes from leak onset. Warning does not provide annunciation. 2R11A will go into Alarm - 11 minutes after leak onset, and will cause OHA A-6 to annunciate.

RO reports 2R11A is in alarm.

Note: Master Flow Controller may be in auto or manual at this point.

CRS enters S2.0P-AB.RC-0001, Reactor Coolant System Leak, or S2.0P-AB.RAD 0001, Abnormal Radiation.

Note: OHA C-2 will annunciate RO reports unexpected OHA C-2, CNTMT

-13 minutes after RT-1 insertion. SUMP PMP START.

CRS directs initiation of Attachment 1, Continuous Action Summary.

RO reports RCS temperature is >350°F, and the unit is in MODE 1.

RO raises charging flow to determine if PZR level can be maintained stable or rising, and reports that with maximum charging flow, PZR level is dropping slowly.

RO reports a centrifugal charging pump is not running.

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TQ-AA-106-0204 13 of 30 PO places 2 CFCUs in slow speed and 2 CFCUs in fast speed lAW CAS Step 4.0.

RO transfers to a centrifugal charging pump as follows:

Ensures Master Flow Controller in auto.

Shuts 2CV55.

Starts a centrifugal charging pump Place 23 charging pump speed controller in manual and lowers 23 charging pump speed to minimum while adjusting 2CV55.

Stops 23 charging pump when at minimum flow.

Adjusts 2CV55 to stabilize PZR level.

Maintains RCP seal injection flow 6-12 gpm per pump not to exceed 40 gpm total seal injection flow.

RO swaps to 45 gpm letdown orifice if required to stabilize PZR level.

Note: Alarm is due to the letdown RO reports 2CC131 Discharge Flow La HX CCW TCV 2CC71 opening due console alarm when second letdown orifice is to the increased letdown flow, and placed in service, and reports its clearing will clear when 2 nd orifice is shut when 2 nd orifice is removed from service.

Note: With RCS leak fully ramped RO stabilizes PZR level and estimates RCS in the leakrate is 20 gpm. leak rate.

RO reports PZR level can be maintained stable or rising.

RO ensures CVCS makeup system in service.

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TQ-AA-106-0204 Paae 14 of 30 CRS directs initiation of S2.0P-ST.RC-0008, RCS Water Inventory Balance.

CRS identifies Tech Spec 3.4.7.2.b for RCS unidentified leakage.

Role Play: When directed by Lead Evaluator, call the CRS as the Operations Director. State" This is John Garecht. The Shift Manager has just updated me on the status of the Unit 2 RCS leak rate. I want you to have Unit 2 Rx shutdown within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . Commence the Unit 2 shutdown expeditiously."

3. Power Reduction CRS briefs crew on load reduction.

CRS enters S2.0P-AB.LOAD-0001, Rapid Load Reduction.

CRS directs initiation of Attachment 1, Continuous Action Summary..

CRS directs RO and PO to coordinate and initiate a Turbine Load Reduction (at least 1%

per minute.)

RO calculates boratlon required for load reduction.

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TQ-AA-106-0204 15 of 30 Note: Digital EHC is set up for a PO initiates load reduction at rate directed by SGFP trip to 66% turbine power at CRS, and ensures load reduction starts.

15% per minute. PO must change rate to the rate directed by the CRS.

RO maintains Tavg on program during load reduction by ensuring control rods automatically insert when Tavg-Tref deviation reaches +1.5°F.

RO energizes all PZR heaters.

Proceed to next event after sufficient power reduction has been performed at direction of Lead Evaluator.

4. SBLOCA STrnlJlat§rOp(;;r~tor;:JVlO~,it

"*MiJ\4~*'**'RCOOO~i;!rpm:~Z',t()'i1~,O',~:iil)',,':;

with 'no. rarnp,oridelaY5rl;~: ~r,e=ti9?;;!,':

"from Lead "EYaJuatqr,';' ,,' ,ii'?' ,";;,::

'"' -,:-' .,:';,:,~::>" "-,,'/":.,';

RO reports OHAs E-28 PZR HTR ON PRESS LO and C-38 CFCU LK DET PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Paae 16 of 30

'~~;;;-~~4

~~{~",i RO reports PZR level dropping faster than expected for the down power.

RO reports PZR level cannot be maintained on program.

5. Rx Trip, failure of High Head CRS directs RO to trip the Rx, confirm the trip, ECCS injection. initiate Safety Injection, then perform immediate actions of EOP-TRIP-1.

RO trips the Rx using either Trip handle.

RO confirms the Rx trip and initiates Safety Injection with either key switch.

RO performs Immediate Actions for TRIP-1:

- Trip reactor

- Confirms reactor trip

- Trips turbine

- Verifies at least one 4KV vital bus energized Reports SI initiated CRS and RO verify performance of immediate actions.

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TQ-AA-106-0204 Paae 17 of 30 PO reports AFW status:

- 21 AFW pump not available.

22 AFW pump not running.

- 23 AFW pump coasting down with speed demand at zero.

RO announces Unit 2 Rx trip. Safety Injection on plant page.

PO reports SEC loading is not complete for energized vital buses. and determines 22 AFW pump did not start.

Note: When the 28 SEC is reset. PO blocks and resets 2B SEC.

22 AFW pump will start due to the 10-10 SG NR signal which is present.

PO reports 22 AFW pump is running.

PO throttles AFW flow to no less than 22E4 lbm/hr.

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TQ-AA-106-0204 Page 18 of 30 RO reports 2SJ12 and 2SJ13 have not opened as expected.

,.CT#2:.* ".(~~O-~.I) *.,.* *.*.* .*.* .* ,*'...* ..... ;:i*:.*~" . . . . . . . . > RO opens 2SJ12 and 2SJ13 to establish high Estt;l~1 is.!:-** f! Q""fr.!?~y:~,;!~~.~~;:,~ '. head ECCS injection flow .

.rHighHe<:ldjEPC~mUfl'lpl?~.fo

,iransition!6utdf--.... -_._,

RO reports 21/22CA330's are shut.

RO reports containment pressure has remained less than 15 psig, and will report to CRS if it exceeds 15 psig.

RO reports no indication of high steam flow coincident with low steam pressure or 10-10 Tavg.

PO reports all 4KV vital busses are energized.

RO reports control room ventilation is in Accident Pressurized mode.

RO runs 2 switchgear supply and one exhaust fans.

RO reports 2 CCW pumps in operation.

RO reports cold leg recirc has not been established.

RO reports greater than 100 gpm charging flow SI systems charging flowmeter.

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TQ-AA-106-0204 Paae 19 of 30 RO reports Res pressure is >1540 psig.

PO reports AFW flow is > 22E4 Ibm/hr.

PO receives permission to throttle AFW flow <

22E4 Ibm hr when at least one SG NR level is

> 9%, and maintains intact SG NR levels between 9-33%.

RO reports all Reps are running.

RO reports Res Tavg is stable at or trending to 54rF.

RO reports both reactor trip breakers are open.

RO reports both PZR PORVs are shut and both PORV block valves are open.

RO reports all Reps running and spray valves shut.

RO reports RCS pressure is > 1350 psig.

RO maintains seal injection flow to all RCPs.

PO reports no SGs are depressurizing in an uncontrolled manner or completely depressurized.

RO reports no indications of any SGTR.

RO reports no radiation monitors in Table F are in warning, alarm, or rising.

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TQ-AA-106-0204 20 of 30 RO reports containment pressure remains < 4 psig.

RO reports containment sump is <46%.

RO reports RCS subcooling is >O°F.

PO reports AFW flow is either >22E4 Ibm/hr or at least one SG NR level is >9%.

RO reports RCS pressure is stable or rising.

Note: If PZR level is <11% at this RO reports PZR level is > 11%.

point, it should be rising due to ECCS injection flow. CRS will loop back to step 29 until PZR level is >

11%.

CRS transitions to EOP-TRIP-3, Safety Injection Termination.

RO resets SI and Phase A isolation.

RO opens 21 122CA330s.

RO reports neither spray valve is failed open.

PO resets A SEC, and reports C SEC will not reset.

Note: 2C SEC will not block PO attempts to block 2C SEC, or reports that because there is no SI present to the block function is unavailable due to SI block. reset actions already performed.

PO reports 2C SEC will not reset.

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TQ-AA-106-0204 21 of 30 CRS dispatches an operator to deenergize 2C SEC.

I.Vlt;:;~\.i' ';) RO reports OHAs A-29 SEC 2A-2C TEST OR TRBL and A-41 AUX ALM SYS PRINTER as expected due to deenergizing 2C SEC.

PO reports all 230V control centers are reset.

RO stops all but one centrifugal charging pump.

RO reports RCS pressure is rising slowly.

RO reports charging pump suction is aligned to the RWST.

RO reports 2CV139 and 2CV140 are open.

RO closes BIT isolation valves 2SJ4, 2SJ5, 2SJ12, and 2SJ13.

RO closes Charging Flow Control Valve 2CV55.

RO opens Charging Discharge Valves 2CV68 and 2CV69.

RO maintains PZR level >25% by adjusting 2CV55, while maintaining RCP seal injection flow to RCPs.

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TQ-AA-106-0204 Paae 22 of 30 RO reports PZR level is stable or rising.

RO reports RCS pressure> 1540 psig and stable or rising.

RO stops 21 and 22 SI pumps, and 21 and 22 RHR pumps.

RO reports RCS subcooling >O°F.

RO reports PZR level >11 %.

RO reports RCS pressure and PZR level are lowering rapidly.

RO raises charging flow to maintain PZR level

>11 RO reports that PZR level not be able to be maintained >11 %.

CRS should start the idle CRS directs starting of ECCS pumps.

centrifugal charging pump and both SI pumps. RHR pumps may be started since the RCS leak rate not have been determined. SI pumps may not be started until it is determined that RCS pressure PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 23 of 30 lower below the shutoff head of the pumps (-1560 psi g).

RO starts the idle centrifugal charging pump and both SI pumps.

Terminate scenario when the idle centrifugal charging pump and both SI pumps have been started.

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TQ-AA-106-0204 Page 24 of 30 A. Alarm Response Procedures (Various)

B. Technical Specifications C. Emergency Plan (ECG)

D. Salem FSAR E. OP-AA-101-111-1003, Use of Procedures F. S2.0P-AB.CVC-0001, Loss of Charging G. S2.0P-AB. RC-0001, Reactor Coolant System Leak H. 2-EOP-TRIP-1, Rx Trip or Safety Injection I. 2-EOP-TRIP-3, Safety Injection Termination PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

. TQ*AA*106*0204 Page 30 of 30 09*01 NRC ESG*1 CT #1: (E-O--F) Establish the minimum required AFW flow rate (22E4 Ibm/hr) to the SGs before transition out of EOP-TRIP-1.

BASIS: Failure to establish the minimum required AFW flow rate, under the postulated plant conditions, results in "adverse consequence(s) or a significant degradation in the mitigative capability of the plant."

CT #2: (E-O--I) Establish flow from at least one High Head ECCS pump before transition out of EOP-TRIP-1 BASIS: Failure to manually start at least one high head EGCS pump under the postulated conditions constitutes "mis-operation or incorrect crew performance which leads to degraded EGGS capacity. .

CT #3: (FSAR) Start ECCS pumps to restore/maintain RCS subcooling and PZR level.

BASIS: Salem FSAR assumes a minimum of one train of ECCS pumps available for a SBLOGA. When EGGS pumps are secured in EOP-TRIP-3 and a subsequent SBLOGA causes a loss of PZR level (and eventually subcooling),

operator action to start EGGS pumps is required to restore the minimum complement of EGGS pumps assumed in the Accident Analysis.

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.. TQ-AA-106-0204 P 31 of 30

~==~~~~~~~

EVENTS LEADING TO CORE DAMAGE YIN Event YIN Event N TRANSIENTS with PCS Unavailable N Loss of Service Water N Steam Generator Tube Rupture N Loss of CCW N Loss of Offsite Power N Loss of Control Air N Loss of Switchgear and Pen Area Ventilation N Station Black Out Y LOCA COMPONENT/TRAIN/SYSTEM UNAVAILABILITY THAT INCREASES CORE DAMAGE FREQUENCY YIN COMPONENT, SYSTEM, OR TRAIN YIN COMPONENT. SYSTEM, OR TRAIN N Containment Sump Strainers N Gas Turbine N SSWS Valves to Turbine Generator Area N Any Diesel Generator N RHR Suction Line valves from Hot Leg Y Auxiliary Feed Pump N CVCS Letdown line Control and Isolation Valves N SBO Air Compressor OPERATOR ACTIONS IMPORTANT IN PREVENTING CORE DAMAGE YIN OPERATOR ACTIOI\l N Restore AC power during SSO N Connect to gas turbine N Trip Reactor and RCPs after loss of component cooling system N Re-align RHR system for re-circulation N Un-isolate the available CCW Heat Exchanger' N Isolate the CVCS letdown path and transfer charging suction to RWST N Cooldown the RCS and depressurize the system N Isolate the affected Steam Generator that has the tube rupture(s)

N Early depressurize the RCS N Initiate feed and bleed Complete this evaluation form for each ESG.

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Appendix D Scenario Outline Form ES-D-1 Facility: SALEM 1 & 2 Scenario No.: ESG-2 Op-Test No.: 09-01 NRC Examiners: Operators:

Initial Conditions: 85% power, MOL. 25 Service Water pump is CIT for strainer work.

Turnover: Raise power to 100% at 10% per hour.

Event Malf. No. I Event Event Type* I No. Description I

N 1 Raise Power ALL I

C 2 O/RAG04 In service ABV Exhaust fan trip (TS)

CRS/PO I

I i I 3 NI0193B PR NI Channel II fails (TS)

ALL I

i 4 8F0105A C 21 SGFP oil leak 21 SGFP trip, MT fails to auto runback (PO manually EH0327 R 5 initiates turbine runback, RO uses manual rod control or O/R B433 ALL boration)

M 6 SG0078B 22 SG Tube leak I tube rupture ALL i RP0058 RPOO59A RP0059B 7 C O/R 8440 ATWT/FRSM ALL O/R B441 O/R C310 O/R C510 CNOO86 C 8 Loss of condenser vacuum during SGTR cooldown MSOO93 I CRS/PO i

3 CT, insert neg reactivity, isolate rupt SG, cool down to target temp

(N)ormal, (R)eactlvlty, (I)nstrument, (C)omponent, (M)8Jor Appendix 0, Page 38 of 39

TQ-AA-106-0204 Page 1 of 36 SIMULATOR EXAMINATION SCENARIO GUIDE SCENARIO TITLE: SGFP trip, ATWT/FRSM, SGTR SCENARIO NUMBER: 09-01 NRC ESG-2 (Modified ESG-905)

EFFECTIVE DATE: See Approval Date EXPECTED DURATION: 75 minutes REVISION NUMBER: 01 PROGRAM: '---_--' L.O. REQUAL X I INITIAL LICENSE STA OTHER Revision Summary Modified ESG-0905 as follows:

Initial power level is now 69.5% vs. 90%.

Changed initial conditions so that only 22 Condensate pump is O/S.

Added additional Tech Spec component failure.

Added Main turbine runback failure.

Added 25 SW CIT.

PREPARED BY: G Gauding 1 Lead Regulatory Exam Author APPROVED BY: _L...- I'

~r ons Traifl9Manager Date APPROVED BY: 3 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 3 of 36 A. Given a situation with an OHA alarm, the crew will perform action(s) to investigate and correct the cause of the alarm, lAW approved station procedures.

B. Given the unit with multiple OHAs in alarm, the crew will prioritize, validate and then determine a course of action when provided with additional information, lAW approved station procedures.

C. Given the unit at power with the generator synchronized to the grid, the crew will perform a power increase to 100% at 10%/hr, lAW S2.0P-IO.ZZ-0004(Q).

D. Given a failure of a power range detector, take corrective action for a power range instrument failure lAW AB.NIS-0001.

E. Given the unit at power and a trip of an operating main feedwater pump, take corrective action lAW AB.CN-0001.

F. Given the order or indications of a feedwater or condensate system malfunction, perform actions as the nuclear control operator to RESPOND to the malfunction in accordance with the approved station procedures.

G. Given indication of a feedwater or condensate system malfunction, DIRECT the response to the malfunction in accordance with the approved station procedures.

H. Given a steam generator tube leak, take corrective action, lAW S2.0P-AB.SG-0001.

I. Given the order or indications of a steam generator tube leak (SGTL), perform actions as the nuclear control operator to RESPOND to the tube leak in accordance with the approved station procedures.

J. Given the order or indications of a steam generator tube leak (SGTL), DIRECT the response to the tube leak, in accordance with the approved station procedures.

K. Given the order or indications of an anticipated transient without trip (ATWT), complete actions as the nuclear control operator to PERFORM the immediate response to the ATWT in accordance with the approved station procedures.

L. Given indication of an anticipated transient without trip (ATWT) , DIRECT the immediate response to the A TWT in accordance with the approved station procedures.

M. Given the order or indications of a steam generator tube rupture (SGTR), perform actions as the nuclear control operator to RESPOND to the tube rupture in accordance with the approved station procedures. Given indication of a steam generator tube rupture (SGTR), DIRECT the response to the SGTR in accordance with the approved station procedures.

N. Given the order or indications of a reactor trip, perform actions as the nuclear control operator to RESPOND to the reactor trip in accordance with the approved station procedures.

O. Given indication of a reactor trip, DIRECT the response to the reactor trip in accordance with the approved station procedures.

P. During performance of emergency operating procedures, monitor the critical safety function status trees in accordance the EOP in effect.

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TQ-AA-106-0204 Page 4 of 36 A. 22 ABV fan trips B. Raise power C. PRNI fails high D. 21 SGFP oilleakl trip MT fails to auto runback F. 22 SG Tube leak I rupture G. ATWT/FRSM H. Loss of Condenser vacuum during cooldown A. The crew takes the watch with the unit at 85% power, MOL. 25 SW pump is CIT for strainer work. A Tech Spec 3,0.3 required power reduction was in progress due to declaring both ECCS trains inoperable based on discovery of non 1E rated bearings installed on both Safety Injection pumps during the last refueling outage. The correct documentation paperwork showing that the bearings were actually qualified was found, and the load reduction stopped at 85%.

B. The crew will perform a power ascension at 10% per hour.

C. After the crew performs sufficient power ascension for evaluation, 22 Auxiliary Building Exhaust fan will trip. The crew will start the standby exhaust fan, and the CRS will identify the appropriate Tech Spec.

D. Power Range Nuclear Instrument 2N42 fails high. The crew will determine a load rejection has not occurred and place rod control in manual. The crew will perform actions to remove the failed channel from service. The CRS will identify the appropriate Tech Specs.

After the PRNI failure has been addressed, 21 SGFP will develop an oil leak which will lead to its tripping. The Main Turbine will fail to automatically runback, and the crew will manually lower Main Turbine load.

F. A large SGTR will ramp in over 10 minutes following a six minute delay from 21 SGFP trip. The crew will diagnose the tube rupture, and the CRS will order a Rx trip and Safety Injection.

G. The Rx will not trip from the control room, and the crew will enter and perform 2-EOPFRSM-1, response to Nuclear Power Generation. The crew will establish rapid boration and the Rx will be tripped locally.

H. The crew will transition to 2-EOP-TRIP-1, and initiate a Safety Injection if an automatic SI has not yet occurred. The crew will transition to 2-EOP-SGTR-1, Steam Generator Tube Rupture.

I. The crew will identify and isolate the 22 SG. The crew will perform a cooldown to target temperature. During the cooldown, Main Condenser vacuum will be lost, and steam dumping will be shifted from the Main Steam Dumps to the intact SG MS10's.

J. The scenario will be terminated when the crew has demonstrated the ability to maintain RCS temperature below the target temperature.

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TQ-AA-106-0204 Page 5 of 36

__ IC-242 85.2% power, MOL 1 RH1 and RH2 CIT 2 RH18s CIT 3 VC1 and VC4 CIT 4 RCPs (SELF CHECK)

_ 5 RTBs (SELF CH ECK)

_ 6 MS167s (SELF CHECK) 7 500 KV SWYD (SELF CHECK)

_ 8 SGFP Trip (SELF CHECK) 9 23 CV PP (SELF CHECK) 10 25 SW pump CIT

_ 11 IOP-4 out and marked up to 5.1.26 12 Complete Attachment 2 "Simulator Ready-for-Training/Examination Checklist."

NOTE for simulator setup: Minimize time simulator is in RUN during setup. Xenon is building in and temperature is lowering. Excessive Tavg - Tref deviation will make scenario run longer if dilution is initiated and then the crew waits for substantial temperature rise before beginning load ascension PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ*AA*106-0204 Page 6 of 36 Note: Tables with blue headings may be populated by external program, do not change column name without consulting Simulator Support group Description EVENT monp187 < 540 /I HOTTEST TEMP.O ACTION:

4 COMMAND: <update as needed>

PURPOSE:

EVENT monp187 < 518 /1 HOrrEST INCORE TIC TEMP.O ACTION:

6 COMMAND: <update as needed>

PURPOSE:

EVENT monp299 < SPEED ACTION:

7 COMMAND: <update as needed>

PURPOSE:

EVENT /I TURBINE TRIP-TRIP ACTION:

10 COMMAND: <update as needed>

PURPOSE:

SELF . Description Delay Initial Ramp Trigger Severity CHECK Time Value Time RP318G4 22 Aux Bldg Exhaust Fan Fails to Start on 01 SEC i'Ji,'\ NiA N/A NIA CONTROL OIL 02 BF0105A 21 STM GEN FEED PUMP TRIP N/A NfA NiA RT-5 PRESSURE LOW 03 I EH0327 TURBINE FAILS TO RUNBACK ON SGFP NfA N/A NJA N!A TRIP 04 TUBE RUPTURE 00:06:00 0 00:10:00 ET-7 900 AAS POINT 05 NJA N!A RT-10 FAILS/OVRD TO ON AAS POINT 06 AAS 736 FAILS - :22 TGA SUMP LEVEL HIGH 00:00:10 N/A N/A RT-10 FAILS/OVRD roaN AAS POINT 07 AAS 737 FAILS - :23 TGA SUMP NIA N/A RT-10 FAILS/OVRD PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 P age 7 0 f36 MSPOINT I 08 AN3738 MS 738 FAILS - :24 TGA SUMP LEVEL HIGH 00:00:27 N/A N/A RT-10 FAILS/OVRD TO ON MSPOINT 09 I AN3739 MS 739 FAILS - :25 TGA SUMP LEVEL HIGH 00:00:35 N/A N/A RT-10 FAILS/OVRD TO ON 10 MS0093 LOSS OF STM DMP VAC PERMISSIVE N!A I'liA HiA ET-6 11 ! CN0086 LOSS OF MAIN CONDENSER VACUUM....... - -.. ~

N/,<\ N/A N/A ET-4 100 12 RP0058 FAILURE OF AUTOMATIC RX TRIP f\JiA N!A NfA N/A 13 RP0059A FAILURE OF MAN! IAI RX TRIP NJA N!A N/A NiA 14 RP0059B FAILURE OF MANUAL .......

SI/RX TRIP

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

NiA NJA NfA ~~iA 15 I-NI0193B PR CH N42 FAILS HIILO .. ~

N/A N/A NiA RT-3 200 SELF*

CHECK 01 02 03 04 Nf.M 05 N!A 01 N!A N!A 02 Ni/\ N/A, 03 NfA. Nip. NiA NfA OFF 04 NiP" N!/\ N/A OFF 05 NlA NiA OFF 06 N!p~ ET-10 OFF PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106*0204 Page 8 of 36 1.

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TQ-AA-106-0204 Page 9 of 36 A. State shift job assignments and review scenario objectives.

B. Hold a shift briefing, detailing instruction to the shift: (provide crew members a copy of the shift turnover sheet).

C. Inform the crew "The simulator is running. You may commence panel walkdowns at this time.

CRS please inform me when your crew is ready to assume the shift".

D. Allow sufficient time for panel walk-downs. When informed by the CRS that the crew is ready to assume the shift, ensure the simulator is deared of unauthorized personnel.

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TQ*AA*106-0204 Page 10 of 36

1. Raise Power Note: RCS Tavg-Tref when simulator is taken out of freeze is

-+0.75 degrees. The rate at which Tavg is lowering is .0rFJmin.

Note: 60 pcm will be added per CRS briefs crew on power ascension.

700 gallons of dilution. Xenon is building in at 60 pcm/hr. An additional 1.185 gallons is required for 10% per hour load ascension, assuming % from dilution and Yz from control rods.

RO initiates a 900 gallon RO reports console alarm VCT Pressure Hi-Lo when it alarms.

RO operates 2CV243 DEGAS as necessary to lower VCT pressure < 50 psig and maintain <

50 psig.

PO sets up Digital EHC for 10% per hour load change.

PO initiates turbine load ascension and verifies turbine load rises.

RO monitors Tavg and announces expected control rod movement when it occurs PSEG Restricted Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 11 of 36 581;)0' .

frOGl,j

2. 22 ABV Exhaust Fan stops

~imul~tor OperatoF:-'n$ertRTa'~p:;:,:,

o"d.irectronfr()mteadEvaHia~?r;;~~;;;~d duringcpower change,""Y~<' ";;i!"';":";0/;~~

---:~~:' , \. ,~;;.. ~ '\'

o"~~k1DE:,AGo~~,,61~i~.

BLDG EXHAust FAN STOP ."'-------'

RO reports AIR FLOW LO for 22 ABV Exhaust fan.

RO reports 22 ABV Exhaust fan was running, but is now stopped.

CRS dispatches an operator to check the status of 22 ABV Exhaust Fan breaker 2BX1AX12X.

Role Play: 2 minutes after being dispatched, report as the NEO breaker 2BX1AX12X is open, and there is nothing abnormal with the breaker, and there is no indication that the breaker tripped.

Note: CRS may direct PO to CRS directs PO to start 23 ABV Exhaust Fan attempt to restart 22 ABV Exhaust lAW S2.0P-SO.ABV-0001, Auxiliary Building Fan since no apparent reason for it Ventilation System Operation.

to stop running is present, but it will not start.

Note: P&L 3.6 identifies that TSAS 3.7.7 is applicable.

RO starts 23 ABV Exhaust fan and ensures AIR FLOW LO alarm clears.

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TQ-AA-106-0204 Page 12 of 36

~Pla'i1tl$fu\dentRespbnse . Comment:

SY'iZ%L\'trA" /.',W CRS enters TSAS 3.7.7 action a for not having three ABV exhaust fans operable.

Proceed to next event on direction from Lead Evaluator.

3. PRNI Channel II fails Simul~tor6perator: . lnserntf:a;;-~-

on 'directibhfromLead;E;valuator:~;(('<

'./ ,. ": :'. 't~:;:'i"':">" :,.'.",~' ,'(;<~',i'<: :'. " ," ::','i::i'~~~:~~i~~F ':'; :.!'. .>." ',: '~~':~::.~;}'

MAEF:.NJ0193BPRcArr FAlfs':t;**

.' HI/Lqi;~;~(~~z *.. .*. .*. * ." .1i.*;~0:* . , .

i<Final"Value:**200 *. .:,.,~!..,;;,.

RO announces control rods inserting at 72 steps per minute with no load rejection in progress, requests permission and places Rod Control in manual, and reports rod motion stopped.

CRS directs PO to place load ascension on hold.

PO depresses Hold PB on digital EHC and ensures the load ascension stops.

RO announces OHA E-28 PZR HTRS ON PRESS LO (if it alarms depending on how much rod insertion) as expected due to rod insertion and acknowledges bezel indication of 22 B/U htr group energizing in auto.

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TQ-AA-106-0204 13 of 36 Direct entry into S2.0P-AB.NIS CRS enters S2.0P-AB.ROD-0003, Continuous 0001 may be performed. Steps are Rod Motion or S2.0P-AB.NIS-0001, Nuclear below. Instrumentation System Malfunction.

CRS verifies with RO that placing rod control in manual stopped rod movement.

RO reports PRNI channel II has failed high.

Note: There is no direction in RO reports outward rod motion is blocked by S2.0P-AB.ROD-0003 to lower Overpower Rod Stop.

load to restore Tavg.

RO reports rod was in direction.

RO reports PRNI channel II has failed high.

S2.0P-AB.NIS-0001 steps CRS enters S2.0P-AB.NIS-0001, Nuclear Instrumentation System Malfunction.

CRS ensures rod control is in manual.

If not performed earlier, CRS directs PO to place the turbine load change on hold.

RO reports indications of 2N42 PRNI failed high.

CRS directs PO to remove failed channel from service lAW S2.0P-SO.RPS-0001, Nuclear Instrumentation Channel Trip/Restoration.

S2.0P-SO.RPS-0001 Steps PO verifies tripping of associated bistables will not result in an ESF or RPS actuation.

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TQ*AA*106*0204 14 of 36 PO ensures 2N42 is not selected on 2N45 recorder.

CRS enters 3.3.1.1, Actions 2 and 6 if not entered previously.

PO informs crew prior to taking any action that will cause alarm status change.

PO places Detector Current Comparator, Upper Section switch in PRN42 and ensures the Channel Defeat Jight illuminates and OHA is clear.

PO places Detector Current Comparator, Lower Section switch in PRN42 position and verifies Channel Defeat light illuminates and OHA E-46 is clear.

PO places Power Mismatch Bypass switch in Bypass PRN42.

PO places Rod Stop Bypass switch in Bypass PRN42 and ensures the overpower rod stop for channel I on 2RP4 is illuminated and OHA E-31 is clear.

PO places Comparator Channel Defeat switch in N42 and ensures the Comparator Defeat lamp illuminates and OHA E-39 is clear.

PO reports to CRS that S2.0P-SO.RPS-001 is complete with the exception of actions required to be taken by I&C technician to trip the associated bistables.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 15 of 36 m~n~~~~~:'

Note: CRS may elect to leave rods CRS directs RO to withdraw control rods to in manual due to step 3.6 of restore Tavg to within +/- 1.5 degrees of Tref.

S2.0P-AB.NIS-0001 not being complete until I&C trips bistables.

Continue to next event if this is the case.

RO withdraws control bank D rods in a slow and deliberate manner, and places rod control in Auto when Tavg is within +/- 1.5 degrees of Tref.

Proceed to next event after rods Crew updates AFD penalty minutes acquired if are restored to auto or at direction AFD went out of target band.

of Lead Evaluator.

4. 21 SGFP Trip on Low Control Oil Pressure Simulator2perator: Insert RT*5 PO announces unexpected 21 SGFP Turb Oil on cue fronlithe!LeadEvaluator. Res Lvi HI-LO alarm and refers to ARP.

MAI..F:

c"/IV** I;~

F!Oa. a . . . . ' .>i X

,,7k;

{1(Will"take;~;90,seco'nasJor*

reserVOir 10 levelalarnitoEome No report from the field will be CRS dispatches an NEO to investigate the made prior to 21 SGFP trip. SGFP low oil pressure.

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TQ-AA-106-0204 Page 16 of 36 CRS briefs crew on required actions for a SGFP trip if Rods are in manual.

Note: This alarm will occur approx PO reports OHA G-23, 21/22 SGFP Deviation 5 min after RT-5 insertion. and 21 SGFP speed decreasing CRS directs of 21 SGFP to initiate auto runback.

iSiml.llatorOperator:E:nslJre,ET';'7.,~l PO trips 21 SGFP.

'Jsfrue.when 21.~GP:Pspe~a,.

lo~ersto<250q.rp~.Thjs~iin:serts" .

theSGTRon a 10 minuteramp' '

after.fI6 rnihute delE1Y'~;':~;'

''\>, ~~ :,,:~'; ;,'Z7',"V Note: If Crew trips Reactor proceed to Event 7.

It would take over 4 minutes until the trip requirement CAS at 16%

NR level would occur if NO operator action to initiate the runback were taken.

CRS enters S2.0P-AB.CN-0001, Main Feedwater/Condensate System Abnormality.

PO reports the automatic Main Turbine runback has not occurred.

PO performs immediate actions by initiating Main Turbine runback by:

Adjusting ramp rate to :::15%/MIN Adjusting SETTER-SETTER: :::66%

Selecting SETTER GO PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ~AA-1 06-0204 Paae 17 of 36 RO performs immediate actions by ensuring control rods insert if in auto when required, or manually inserts rods to maintain Tavg on program lAW Attachment Section 3.0.

CRS initiates Attachment 1, Continuous Action Summary for S2.0P-AB.CN-0001.

PO reports 21 SGFP tripped.

RO reports power is > P-10.

RO initiates boration as required to maintain control rods above the RIL and restore AFD.

PO verifies 22 SGFP speed has risen and is maintaining SG levels.

PO reports the Polisher Bypass valves, 21 23CN108s, are open.

PO opens the CN47, Heater String Bypass Valve, opens, and shuts 21-24GB4 SG Blowdown Isolation Valves, and 21-24GB185 Blowdown Throttle Valves.

PO presses 21 SGFP trip PB if not performed previously and ensures AFP AUTO ARMED bezel lit for 21 SG FP.

RO energizes PZR heaters.

Note: Proceed to next event on RMS alarm for 22 Steam Generator Tube Leak.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 18 of 36

,,'- <l'~f'J~

6. 22 Steam Generator Tube Leak RO reports 2R53B for 22 SG in warning.

followed shortly by 2R15 alarm.

Note: CRS will order Rx trip and SI CRS enters S2.0P-AB.SG-0001, Steam when it is apparent that the tube Generator Tube Leak.

leak is larger than the capacity of the RCS makeup system.

CRS initiates Attachment 1, Continuous Action Summary.

RO reports 2R19B when it alarms.

Si mtllatQr(j~~t~tor&;"3:ro18MWs . ";>'W: CRS directs NEO to deenergize the Turbine

/affe(bf3i9~9jf3P~t¢hed;':lQ~~~~I}T:.-:' . z Generator Area and Condensate Polishing 10.10de~hergjzeTGA~sumps;:* .:...... Sumps.

CRS directs swapping to a centrifugal charging pump, but orders Manual Rx Trip and SI when PZR level cannot be maintained lAW CAS.

Note: Proceed to next event when CRS direct RO to trip the Rx. confirm the Rx CRS orders a reactor trip. trip. then initiate SI lAW CAS of S2.0P AB.SG-0001.

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TQ~AA-1 06~0204 Page 19 of 36

7. ATWT I FRSM RO attempts to trip the Rx and reports the Rx did not trip.

Crew ATWT.

RO attempts to trip the Rx handle and reports the Rx did not trip.

RO attempts to trip the Rx by opening both Rx trip breaker PBs and reports the Rx did not trip.

RO attempts to trip the Rx by opening PZR heater bus infeed breakers and reports the Rx did not trip.

RO reports not confirmed.

S:imula~()r()perator~,,,"~\~;E(lsure I RO trips the Main Turbine.

ET-1 Oita:rRUEwhen,t?eturblrie~Is<

'ktripped~This fails' auto'rodcontrQI RO identifies rods not inserting in auto and initiates rod insertion in manual.

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TQ-AA-106-0204 20 of 36 CRS/RO verify immediate actions of EOP TRIP-1 are complete.

lCT#1(~B,:S.1..C),fiJs~rtl1egi\tjye ." CRS enters EOP-FRSM-1, Response to

.rea~tiyitxi!lto1~to the5(}re:~y,~f\:: Nuclear Power Generation.

<Je~st9n~(}'thEtf()no~ing*"':~*. "";;1'

. '~~l~()d~\pr!<c>;r~();~.rjmpletlog ,.. ,iYY step;r4'1~""'"

FRsM.

PO starts/ensures 21 and 22 AFW Pumps running.

Note: The earliest AFW should be PO reports AFW flow <44E04 Ib/hr.

isolated to 22 SG is at Step 10 of FRSM-1, and then only if at least 1 SG NR level is >9%.

PO starts 23 AFW pump.

RO starts 21 and 22 charging pumps.

RO reports no SI has occurred.

RO initiates Rapid Boration

- Starting both Boric Acid Pumps in Fast PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 21 of 36

.";;Comrnent .

TEvalliator/lnstructor'Activity :ExpecteciPlant/StLidEu1t

"-~ '".: ~{:c~(::*;;>,,,, ','

Response

.., ' t>;~g~'

Speed;

- Opening 2CV175 Rapid borate Stop Valve;

- Closing 21/22CV160 BAT Recirc Valves;

- Verifies Rapid Boration flow indicated on Rapid Borate flowmeter;

- Maintaining charging flow >87 gpm.

RO reports PORVs operating as expected for current RCS pressure, and that both PORV block valves are open.

RO reports containment isolation valves 2VC5 and 2VC6 are shut.

PO performs APPX-3 SI verification when SI occurs.

Simulator Operator: Open the, CRS sends NEO to open RTBs, Rod Drive MG reactor, trip breakers 3 minutes Motor and Generator breakers.

after the order is given but no*,

sooner than completion of the

Rapid Bbration decision step in FRSM-1.

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TQ-AA-106-0204 22 of 36

',PlantIStlideri('Re$pons~:~r";;tg~:/

"' ,~:}: ~~~~:;:):t;1~;~{< * <.~!:t};-t~~~77f;fo~~'

.Delet~'*MALF$:~~()058;~

RP0059~

i'sndRP00598.

I, ""',,."',"" .. :'"

f\J169J{¥~!t0 Overrid~s S:440 E:l441:~g,ON (open$ RI6s) .

.'" ,:')1:;:' *..L*':' .' ',"'",' ",',' '.' .', ,,'>~i~<""i "!~9~,;~~\i~,~;~',::: '

D~~energ"l':z;ei'~OdO~ivefV1G:Sets~~;"

!;1;;~~~~~tt,;f;: ,~;:;:,f;5f(;;'<~~

PO reports Stop Valves closed.

RO reports when the Reactor is tripped.

PO maintains AFW flow >44E4 Ibm/hr until at least one SG NRlevel is > 9%, then throttle AFW flow to maintain SG NR levels 9-33%.

CRS sends NEO to isolate dilution paths and PO checks no primary water flow on FI111 A.

PO reports no faulted SG or uncontrolled cooldown.

RO reports no CETs are >1200°F.

RO confirms reactor trip by 3 PRNls <5% and IRNls SUR negative.

CRS directs Chemistry to sample RCS boron.

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TQ-AA-106-0204 Page 23 of 36

Evaluator/lnstructor Activity \Expectedplarit/$tudent Response *SErr:~ Comment*******

3;;~;,~~~\~' );, . .LOG .

CRS directs performance of Shutdown Margin.

CRS transitions back to TRIP-1 after completing FRSM-1.

Note: Proceed to next event after transition back to TRIP-1

5. Steam Generator Tube Rupture Evaluators: Log reentry time RO verifies reactor and turbine trip.

into TRIP-1 to start clock for critical tasks:

TIME: - - -

RO reports all 4kV Vital Buses energized.

RO reports either:

- SI has actuated OR

- SI has not actuated, and SI is required by plant conditions.

RO initiates SI if auto SI has not occurred.

RO announces Unit 2 Reactor Trip, Safety Injection (twice) on PA.

CT #2 (E..;3-A): Isolate AFWtothe I PO closes 22AF11 and 22AF21 to isolate AFW ruptured SG within 1o minutes of.. flow into 22 SG.

reentry intoTRIP-1and.

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TQ-AA-106-0204 24 of 36 PO identifies aU SG NR levels >9% and throttles AFW to SGs.

PO verifies SEC loading complete for all available equipment on energized 4kV Vital Buses.

PO reports proper safeguards valve alignments.

PO reports MSLI not required.

PO reports all 4KV vital buses are energized.

RO reports Control Room Ventilation in Accident Pressurized Mode.

RO runs 2 Switchgear Room Supply fans and one exhaust RO reports 2 CCW pumps running.

RO reports cold leg recirc has not been established.

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TQ-AA-106-0204 Page 25 of 36 RO reports greater than 100 gpm charging flow SI systems charging flowmeter.

RO reports RCS pressure is >1540 psig.

RO/PO verifies AFW flow >22E04 orSG level> 9%.

RO reports all RCPs are running.

RO reports RCS Tavg is stable at or trending to 54rF.

RO reports both reactor breakers are open.

RO reports both PZR PORVs are shut and PORV block valves status.

RO reports all RCPs running and spray valves shut.

RCS pressure is < 1350 psig and ECCS flow is established, then RO stops all RCPs.

RO maintains seal injection flow to all RCPs.

RO reports no faulted SGs.

PO reports 22 SG NR level is risina in an uncontrolled manner.

CRS transitions to EOP-SGTR-1, Steam Generator Tube Rupture.

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TQ~AA~1 06~0204 26 of 36 PO reports 22 SG NR level is rising in an uncontrolled manner.

PO sets 22MS1 0 to 1045 psig. and reports 22MS10 is SEE CT#2 PREVIOUS PAGE PO shuts 22MS167, and reports 22MS18, 22MS7, and 22GB4 are shut PO reports 21 or 23 is not the ruptured SG.

Role Play: 5 minutes after CRS dispatches an operator to close 2SS327.

requested, report 2SS327 closed.

PO reports 22 SG is isolated from intact SGs.

PO reports 22 SG NR level >9% and that feedwater flow is isolated to 22 SG.

RO reports power is available to both PORV Block valves RO verifies PORV status is correct for current RCS pressure.

RO reports both PORV Block valves are open.

PO reports no SGs are faulted.

PO adjusts AFW flow to maintain at least 1 SG NR level> 9%, and all SG NR levels 9-33%.

RO/PO reset Safeguards Actuations:

Resets SI

Resets Phase A

Opens 21 & 22CA330 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ~AA-1 06-0204 Page 27 of 36

~,valuatotrl~~~ruct~r~C!i:ylt~:&(:$;;\~~~:<~'~:~:';i~~~pecte~ir~~.~.t/Student*.*Respon~i~;::**;*:;':t**:):Eg~ .* i'Comm'erif:'"

Resets each SEC

Resets each 230V Control Center.

RO stops 21 & 22 RHR pumps.

PO reports 22 SG is isolated and >375 psig.

CRS dispatches NEO to shift Gland Sealing Steam to Unit 1.

PO notifies CRS when 22MS1 0 starts to open.

Simulator Operator: Ensure ET~4 . CREW commences RCS cooldown with the inserts when highest incore . Steam Dumps using intact SGs to value thermocouple is less than 540°. determined from Table D (503 deg)

MALF: CN0086 Loss Of Cond Vacuum* '.

PO places Steam Dumps in manual.

PO adjusts steam pressure valve demand to zero.

PO places steam dumps to MS Pressure Control.

PO adjusts steam pressure valve demand to 25%.

Proceed to next event when When Tavg low-low is reached, PO bypasses highest incore thermocouple is less Tavg and verifies steam dumps reopen.

than 540°.

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TQ-AA-10.6-0.20.4 Page 28 of 36

8. Loss of Condenser Vacuuml Steam Dumps RO reports "DO HI" in alarm as not expected.

Note: Crew should monitor steam PO reports OHA G-5 Condenser Vac La.

dumps but not swap to MS10s early as this is an increased release to the public.

Note: CRS may implement S2.0P CRS briefs crew on potential loss of steam AB-COND-1 for loss of vacuum. dumps with degrading vacuum.

CRS dispatches an NEO to look for vacuum leaks.

_ *. :,,;,,'.1 PO reports Steam Dump valves have closed.

" "f,t,:;;jy:;"'"

.,/>:,:" \\~'~i0~:i:G:'i>'"r;\;;~::-?-::<-r}' ;.:;

. MJ%LF:}IVI.~009~.LOSS'

.Vac'permissi~e; ...

CRS returns to step 15.2 and answers "Steam Dumps not available" PO re-commences cooldown by fully opening 21,23, and 24MS10.

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TQ-AA-106-0204 29 of 36

~T.#~~;{E*;3~B).;,~~ta~'is~/; . .* . .*., RO reports hottest CET is < 503°F .

.~.aintain:~g~:'t~ri1p~raturetoi*

'maintai nlmi nimtlm>requ ired:""": PO stops the cooldown and dumps steam as

. . su ~C~~.I!.t~~~<;i>~:";i;i~::*'*** ;"iii;';'{§::;Z0"~' ... ,.;dJ required to maintain temperature < target temperature.

,. 'SAT ;.;,."

~; . '\."

Terminate scenario when crew has demonstrated the ability to maintain temperature at target temperature.

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TQ-AA-106-0204 Page 30 of 36 A. Alarm Response Procedures (Various)

B. Technical Specifications C. Emergency Plan (ECG)

D. OP-AA-101-111-1003, Use of Procedures E. S2.0P-AB.ROD-0001, Continuous Rod Motion F. S2.0P-AB.NIS-0001, Nuclear Instrumentation System Malfunction G. S2.0P-AB.CN-0001, Main Feedwater/Condensate System Abnormality H. 2-EOP-TRIP-1, Rx Trip or Safety Injection I. 2-EOP-FRSM-1, Response to Nuclear Power Generation J. 2-EOP-SGTR-1, Steam Generator Tube Rupture PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Revision 2 Page 31 of 36 ATTACHMENT 1 UNIT TWO PlANTSTATUS

. TODAY MODE: 1 POWER: 85.2% RCS BORON: 920 MWe 1050 SHUTDOWN SAFETY SYSTEM STATUS (5,6 & DEFUELED):

NA REACTIVITY PARAMETERS Power reduction from 100% to 85% at 1% per minute was completed 30 minutes ago due to TS 3.0.3 for both SI pumps being declared inoperable due to possible unqualified bearings installed. TS 3.0.3 was exited when proper documentation was found for bearing qualification.

A Power ascension to 100% power will be performed at 10% per hour.

Xenon is building in at 60 pcm per hour.

Reactivity plan for the power ascension is to perform 900 gallon batch dilutions every 30 minutes, while using rod control to maintain AFD and Tavg on program.

Rx fuel is conditioned to 100% power.

MOST LIMITING LCO AND DATErnME OF EXPIRATION:

EVOLUTIONS/PROCEDURES/SURVEILLANCES IN PROGRESS:

IOPA, Power Operation Step 5.1.25 is complete.

ABNORMAL PLANT CONFIGURATIONS:

CONTROL ROOM:

Unit 1 and Hope Creek at 100% power.

No penalty minutes in the last 24 hrs, PRIMARY:

SECONDARY:

RADWASTE:

No discharges in progress CIRCULATING WATER/SERVICE WATER:

25 SW pump CIT for strainer work.

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TQ-AA-106-0204 Revision 2 Page 32 of 36 ATTACHMENT 2 SIMULATOR READY FOR TRAINING CHECKLIST

1. Verify simulator is in "TRAIN" Load

2. Simulator is in RUN

3. Overhead Annunciator Horns ON

4. All required computer terminals in operation

5. Simulator clocks synchronized

6. All tagged equipment properly secured and documented

7. TSAS Status Board up-to-date

8. Shift manning sheet available

9. Procedures in progress open and signed-off to proper step

10. All OHA lamps operating (OHA Test) and burned out lamps replaced

11. Required chart recorders advanced and ON (proper paper installed)

12. All printers have adequate paper AND functional ribbon 13, Required procedures clean

14. Multiple color procedure pens available

15. Required keys available

16. Simulator cleared of unauthorized material/personnel

17. All charts advanced to clean traces and chart recorders are on.

18. Rod step counters correct (channel check) and reset as necessary

19. Exam security set for simulator

20. Ensure a current RCS Leak Rate Worksheet is placed by Aux Alarm Typewriter with Baseline Data filled out

21. Shift logs available if required

22. Recording Media available (if applicable)

23. Ensure ECG classification is correct

24. Reference verification performed with required documents available

25. Verify phones disconnected from plant after drill.

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TQ-AA-106-0204 Revision 2 Page 33 of 36 I

ATTACHMENT 3

CRITICALTASK METHODOLOGY In reviewing each proposed CT, the examination team assesses the task to ensure, that it is essential to safety. A task is essential to safety if, in the judgment of the examination team, the improper performance or omission of this task by a licensee will result in direct adverse consequences or in significant degradation in the mitigative capability of the plant.

The examination team determines if an automatically actuated plant system would have been required to mitigate the consequences of an individual's incorrect performance. If incorrect performance of a task by an individual necessitates the crew taking compensatory action that would complicate the event mitigation strategy, the task is safety significant.

I. Examples of CTs involving essential safety actions include those for which operation or correct performance prevents ...

degradation of any barrier to fission product release

degraded emergency core cooling system (ECCS) or emergency power capacity

a violation of a safety limit

a violation of the facility license condition

incorrect reactivity control (such as failure to initiate Emergency Boration or Standby Liquid Control, or manually insert control rods)

a significant reduction of safety margin beyond that irreparably introduced by the scenario II. Examples of CTs involving essential safety actions include those for which a crew demonstrates the ability to ...

effectively direct or manipulate engineered safety feature (ESF) controls that would prevent any condition described in the previous paragraph.

recognize a failure or an incorrect automatic actuation of an ESF system or component.

take one or more actions that would prevent a challenge to plant safety.

prevent inappropriate actions that create a challenge to plant safety (such as an unintentional Reactor Protection System (RPS) or ESF actuation.

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TQ-AA-106-0204 Revision 2 Page 34 of 36 Note: Attach a separate copy of this form to each scenario reviewed. This form is used as guidance for the examination team as they conduct their review for the proposed scenarios.

SCENARIO IDENTIFIER: 09-01 NRC ESG-2 RE~EWER: ~~ ~ ~

Initials Qualitative Attributes

{,

~y 1. The scenario has clearly stated objectives in the scenario.

r 2.

3.

The initial conditions are realistic, in that some equipment and/or instrumentation may be out of service, but it does not cue crew into expected events.

The scenario consists mostly of related events.

t 4. Each event description consists of:

the point in the scenario when it is to be initiated

the malfunction(s) that are entered to initiate the event

the symptoms/cues that will be visible to the crew

the expected operator actions (by shift position) 1

the event termination point

~ 5. No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event.

~

6. The events are valid with regard to physics and thermodynamics.

7. Sequencing/timing of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectives.

t 8.

9.

The simulator modeling is not altered.

All crew competencies can be evaluated.

~(

10. The scenario has been validated.

11. If the sampling plan indicates that the scenario was used for training during the requalification cycle, evaluate the need to modify or replace the scenario.

12. ESG-PSA Evaluation Form is completed for the scenario at the applicable facility.

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TQ-AA-106-0204 Revision 2 Page 35 of 36 Note: The quantitative attribute target ranges that are specified on the form are not absolute limitations; some scenarios may be an excellent evaluation tool, but may not fit within the ranges. A scenario that does not fit into these ranges shall be evaluated to ensure that the level of difficulty is appropriate. (ES-301 Section D.5.d)

Initial Quantitative Attributes (as per ES-301-4, and ES-301 Section D.5.d)

-t1 7 Total malfunctions inserted: 5-8

-iL 1 Malfunctions that occur after EOP entry: 1-2

-1L 2 Abnormal Events: 2-4

-1L 1 Major Transients: 1-2 1=

2 EOPs entered/requiring substantive actions: 1-2 1 EOP contingencies requiring substantive actions: 0-2 jL 3 Crew Critical Tasks: 2-3 COMMENTS:

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TQ-AA-106-0204 Page 36 of 36 09-01 NRC ESG-2 CT#1: (FR-S.1-C) Insert negative reactivity into the core by at least one of the following methods prior to completing the immediate actions of FR-S.1 (FRSM)

BASIS: Failure to insert negative reactivity under the postulated plant conditions, results in an unnecessary situation in which the reactor remains critical or returns to a critical condition. Performance of this critical task would make the reactor subcritical and provide sufficient shutdown margin to prevent (or at least minimize the power excursion associated with) any subsequent return to criticality. Since Salem employs flow charts vice the standard Westinghouse two-column format, there are no immediate actions associated with FRSM. The immediate actions of FRSM are contained in step 2 of EOP TRIP-1 and steps 1-4 of FRSM. Thus the time limit of this critical task is extended to step 4 of FRSM to maintain alignment.

CT #2: (E-3-A) Isolate AFW to the ruptured SG within 10 minutes of entry into TRIP-1 and subsequently close 22MS167, 22MS18, 22MS7 and 22GB4 prior to initiating cooldown in SGTR-1.

BASIS: Failure to isolate the ruptured SG causes a loss of differential pressure between the ruptured SG and the intact SGs. Upon a loss of differential pressure, the crew must transition to a contingency procedure that constitutes an incorrect performance that" ... necessitates the crew taking compensating actions which complicates the event mitigation strategy ... "

CT #3: (E-3-B) Establish/Maintain RCS temperature so a transition from SGTR-1 does not occur because Tave is too high to maintain minimum subcooling, OR below the RCS temperature that causes an extreme challenge (Red) or severe (Purple) challenge to the subcriticality and/or the integrity CSF.

BASIS: Failure to establish and maintain the correct RCS temperature during a SGTR leads to a transition from E-3 to a contingency procedure, which constitutes an incorrect performance that " ... necessitates the crew taking compensating actions which complicates the event mitigation strategy ... "

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TQ-AA~1 06~0204 37 of 36 EVENTS LEADING TO CORE DAMAGE YIN Event YIN Event N TRANSIENTS with PCS Unavailable N Loss of Service Water Y Steam Generator Tube Rupture N Loss ofCCW N Loss of Offsite Power N Loss of Control Air N Loss of SWitchgear and Pen Area Ventilation N Station Black Out N LOCA COMPONENT/TRAIN/SYSTEM UNAVAILABILITY THAT INCREASES CORE DAMAGE FREQUENCY YIN COMPONENT, SYSTEM, OR TRAIN YIN COMPONENT, SYSTEM, OR TRAIN N Containment Sump Strainers N Gas Turbine N SSWS Valves to Turbine Generator Area N Any Diesel Generator N RHR Suction Line valves from Hot Leg N Auxiliary Feed Pump N CVCS Letdown line Control and Isolation Valves N SBO Air Compressor OPERATOR ACTIONS IMPORTANT IN PREVENTING CORE DAMAGE YIN OPERATOR ACTION N Restore AC power during SBO N Connect to gas turbine N Trip Reactor and RCPs after loss of component cooling system N Re-align RHR system for re-circulation N Un-isolate the available CCW Heat Exchanger N Isolate the CVCS letdown path and transfer charging suction to RWST Y Cooldown the RCS and depressurize the system Y Isolate the affected Steam Generator that has the tube rupture(s)

N Early depressurize the RCS N Initiate feed and bleed Complete this evaluation form for each ESG.

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Appendix D Scenario Outline Form ES-D-1 Facility: SALEM 1 & 2 Scenario No.: ESG-3 Op-Test No.: 09-01 NRC Examiners: Operators:

Initial Conditions: 100%, EOL. 21 CFCU is CIT.

Turnover: Secure the Containment Pressure Relief in progress. Maintain current power.

Event Malf. No. Event Event Type*

No. Description N 2VC5 (CIV) fails to shut when securing containment 1 CC0172B CRS/PO pressure relief. (TS)

O/R C808 C Loss of 2B 4KV bus (TS) and subsequent failure of 22 AFW 2

O/R C805 ALL pump to stop.

R 3 Power reduction to <100%.

ALL 4 MS0088Cr M Steam Leak in containment.

C 5 RP0058 ATWT, (auto demand-no trip-manual trip works)

RO MS0090Cr M

6 VL0420 MSLI fails, Multiple SG depressurization, ALL 423 RP0276A,B C 7 Auto CS & Phase B isolation fails.

RP0277A,B CRS RO Recovery of single SG in LOSC-2.

CTs man init trip, man inti phase B, lower AFW flow to nit 1 E41bm/hr

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

TQ-AA-106-0204 Page 1 of 34 SIMULATOR EXAMINATION SCENARIO GUIDE SCENARIO TITLE: Loss of 2B 4KVl460V, Steam leak in containment SCENARIO NUMBER: 09-01 NRC ESG-3 EFFECTIVE DATE: See Approval Date EXPECTED DURATION: 80 minutes REVISION NUMBER: 00 PROGRAM: L....----..:..--l L.O. REQUAL X . I INITIAL LICENSE L....-_--l STA L...c.--'-----ll OTH ER Revision Summary New Issue for 09-01 NRC Exam PREPARED BY: G Gauding 07-10-11 Lead Regulatory Exam Author Date o~nager APPROVED BY: '~~2..- if Date

{

APPROVED BY:

~ve ~ , ,I PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 3 of 33 A. Given a situation with an OHA alarm, the crew will perform action(s) to investigate and correct the cause of the alarm, lAW approved station procedures.

B. Given the unit with multiple OHAs in alarm. the crew will prioritize, validate and then determine a course of action when provided with additional information, lAW approved station procedures.

C. Given a loss of a 4 Kv vital bus, take corrective action. lAW S2.0P-AB.4KV-0002.

D. Given the order or indications of a loss or malfunction of a safety related electrical distribution system. perform actions as the nuclear control operator to RESPOND to the loss or malfunction in accordance with the approved station procedures.

Given indications of a loss or malfunction of a safety related electrical distribution system, DIRECT the response to the loss or malfunction in accordance with the approved station procedures.

F. Given the unit at 100% power with a steam leak, the crew will take corrective aCtion for a steam leak, lAW S2.0P-AB.STM-0001 G. Given the indication of excessive steam flow, perform actions as the nuclear control operator to RESPOND to excessive flow in accordance with the approved station procedures.

H. Given the indication of excessive steam flow, DIRECT the response to excessive flow in accordance with the approved station procedures.

I. Given the order or indications of a reactor trip. perform actions as the nuclear control operator to RESPOND to the reactor trip in accordance with the approved station procedures.

J. Given indication of a reactor trip, DIRECT the response to the reactor trip in accordance with the approved station procedures.

K. Given the order or indications of a safety injection perform actions as the nuclear control operator to RESPOND to the safety injection in accordance with the approved station procedures.

L. Given indication of a safety injection DIRECT the response to the safety injection in accordance with the approved station procedures.

M. Given the order or indications of a loss of secondary coolant, perform actions as the nuclear control operator to RESPOND to the coolant loss in accordance with the approved station procedures.

N. Given indication of a loss of secondary coolant, DIRECT the response to the loss of secondary coolant, in accordance with the approved station procedures.

O. Given the order or indications of a multiple steam generator depressurization. perform actions as the nuclear control operator to RESPOND to the generator depressurization in accordance with the approved station procedures.

P. Given indication of a multiple steam generator depressurization, DIRECT the response to the generator depressurization in accordance with the approved station procedures.

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TQ*AA*106*0204 Page 4 of 33 Q. Given the order or indications of excessive containment pressure, perform actions as the nuclear control operator to RESPOND to the excessive pressure in accordance with the approved station procedures.

R. Given indication of excessive containment pressure, DIRECT the response to the excessive pressure in accordance with the approved station procedures.

S. During performance of emergency operating procedures, monitor the critical safety function status trees in accordance the EOP in effect.

A. 2VC5 cannot be shut securing from Containment Pressure Relief.

B. Loss of 2B 4KV/460V bus (EDG energizes)

C. Steam leak in containment D. Steam rupture in containment with failure of MSLI.

E. Recovery of single SG in LOSC-2 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 5 of 33 A. The crew takes the watch with the unit at 100% power, EOl. 21 CFCU is crr after it tripped two hours ago. A normal Containment Pressure Relief was initiated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ago lAW S2.0P SO.CBV-0002, Containment Pressure-Vacuum Relief System Operation. Orders for the shift are to maintain 100% power and to secure the Containment Pressure Relief in progress.

B. After assuming the watch, the crew will secure the Containment Pressure relief in progress.

Containment Isolation Valve (CIV) 2VC5 (outside containment) will fail to shut after the Pressure Relief Damper and 2VC6 (inside containment) have been shut. The CRS will enter TSAS 3.6.3 Action 1.

C. Once the CIV Tech Spec has been identified, 2B 4KV vital bus infeed breakers will open, along with the 4KV-460V tie breaker. 2B EDG will start and load 2B Vital bus in SEC MODE 11*,

Single Vital Bus Undervoltage. The crew will respond to stabilze the plant lAW S2.0P-ABAKV 0002, loss of 2B 4KV Vital Bus. 22 AFW pump will start, and Rx power will rise above 100%

power.. 22 AFW pump will not be able to be stopped from the control room, nor will the 21 or 22 AF21 valves respond if AFW flow from 22 AFW pump is attempted to be lowered. The crew will perform a power reduction to less than 100% power. The CRS will identify the appropriate Tech Spec.

D. Once power has been reduced to < 100% power, a small steam leak in containment will ramp in over 5 minutes. The crew will identify changing containment conditions, and respond lAW S2.0P-AB.STM-0001, Excessive Steam Flow. Once the need for a unit shutdown is made, the steam line will rupture in containment.

E. The Rx will not automatically trip, and will be tripped by the crew. Auto and manual MSLI fails to shut the MSIV's. Containment Spray and Phase B isolation fail to actuate and will be manually initiated.

F. The crew will transition to 2-EOP-lOSC-1, Steam Generator Depressurization, then 2-EOP lOSC-2 for Multiple Steam Generator Depressurization.

G. The crew will perform 2-EOP-FRCE-1, Response to Excessive Containment Pressure to ensure containment cooling systems are in correct lineup.

H. While in 2-EOP-lOSC-2, a single SG MS167 will be locally shut, and the crew will take the CAS action to transition to EOP-lOSC-1.

I. The scenario will be terminated when the crew has transitioned back to 2-EOP-lOSC-1.

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TQ*AA*106*0204 Page 6of33

__ IC-243 100% power, EOl 1 RH1 and RH2 CIT 2 RH18s CIT 3 VC1 and VC4 CIT 4 RCPs (SELF CHECK)

_ 5 RTBs (SELF CHECK) 6 MS167s (SELF CHECK)

_ 7 500 KV SWYD (SELF CHECK) 8 SGFP Trip (SELF CHECK) 9 23 CV PP (SELF CHECK) 10 21 CFCU CIT.

11 2VC5, 2VC6, and Pressure Relief Damper open, with marked up S2.0P-SO.CBV-0002 provided to crew with turnover sheet.

12 Complete Attachment 2 "Simulator Ready-for-Training/Examination Checklist."

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TQ*AA*106*0204 Page 7 of 33 Note: Tables with blue headings may be populated by external program. do not change column name without consulting Simulator Support group Description

-~--~------.----------------------'~-~-------------------~------- -~------ - ------------

EVENT MONP254 <10 ROD BANK C < 10 ( TRIP)

ACTION: DOR KB515LCP -1 0 9

COMMAND: <update as needed>

PURPOSE:

- - - j - - - ~-----__:=___=____:=:=-+--=--:-::-:c-c_=-:-'c___:_________ -:__:-:-__:::-=c__::=:_::::- =~=:-____=----c-_:_:__:-=----__:_::_- -:-==--:-=:=--::-~=--:---------------------;

EVENT MONP254 <10 II ROD BANK C < 10 RX TRIP)

ACTION: DOR KB515PNP 11 COMMAND: <update as needed>

PURPOSE:

01 i\,lfl\

l Jjn N/A RT-3 MS0088Cr 23 Main Steam Line Leak Inside Cont 02 BEFORE orifice N/A. 0 00:05:00 RT-5 MS0090Cr 23 Main Steam Line Leak Inside Cont 03 N/A N/A RTc7. 80 AFTER orifice 04 RP0058 FAILURE OF AUTOMATIC RX TRIP NfA NJA NJA 05 VL0420 21MS167 Fails to Position N!A 06 VL0421 22MS167 Fails to Position N/A 07 23MS167 Fails to Position Ni/\"

08 i VL0423 24MS167 Fails to Position NiA 09 N/A 10 NtA NUl. N/A 11 N!A 12 N/A 13 81B22AUX N!A SELF CHECK 01 02 03 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 8 of 33 SELF CHECK 01 RT-3 ON 02 RT-3 ON 03 N!A OFF 04 NfA OFF 05 NiA OFF 06 NlA OFF

1. None PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ*AA*106*0204 Page 9 of 33 A. State shift job assignments and review scenario objectives.

B. Hold a shift briefing, detailing instruction to the shift: (provide crew members a copy of the shift turnover sheet).

C. Inform the crew 'The simulator is running. You may commence panel walkdowns at this time.

CRS please inform me when your crew is ready to assume the shift".

D. Allow sufficient time for panel walk-downs. When informed by the CRS that the crew is ready to assume the shift, ensure the simulator is cleared of unauthorized personnel.

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TQ-AA-106-0204 Page 10 of 33

1. Containment Isolation Valve 2VC5 fails to shut PO shuts Containment Pressure Relief damper.

PO shuts Containment Isolation valve 2VC6.

PO attempts to shut Containment Isolation valve 2VC5, and reports 2VC5 remains open.

Note: PO may swap bezel control units to determine if the close PB is what is keeping the 2VC5 from closing.

CRS contacts personnel to investigate 2VC5 failure.

CRS enters TSAS 3.6.3 Action 1.

Continue to next event on direction from Lead Evaluator.

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TQ-AA-106-0204 Paae 11 of 33

2. UV on 28 4KV vital bus with loss of 28 460/230V vital bus.

RO/PO announce multiple OHA and Console alarms.

Note: The Full Core Display Rod Bottom lights will all illuminate and IRPI indication will go to zero.

Crew diagnoses the loss of 28 4KV vital bus, and 2B EDG is loading in MODE 11* (Single Vital Bus UV).

Note: The 2B4D 460V breaker open bezel will flash continuously, and is unable to be silenced control power is removed from the breaker.

Note: The 2840 460V breaker should have remained shut during the SEC loading sequence, but has PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Paae 12 of 33 tripped open.

CRS enters S2.0P-AB.4KV-0002, Loss of 2B 4KV Vital Bus.

Note: Rx power rises above 100%

with the addition of cold AFW.

When the crew determines a power reduction must be performed, go to steps on page 16 of this guide.

CRS directs initiation of Attachment 1, Continuous Action Summary.

CRS dispatches an operator to monitor 2B EOG.

RO reports 2SW26 is open based on having no power to close it, and Main Turbine and TGA parameters related to SW cooling water are stable, and dispatches an operator to locally check position.

IF dispatched to remove control power from breaker 2B40, call control room 2 minutes after being dispatched for a first check, then use REMOTE E0530 to OFF to deenergize breaker 2B40 control power.

RO reports 21 charging pump was not supplying seal injection and charging flow.

RO reports 22 RHR pump was not providing core cooling.

PO reports 2B vital bus is energized from 2B PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Paae 13 of 33 EDG.

RO reports OHA E-20 PZR HTR ON LVL HI when it annunciates due to 21 charging pump running.

PO resets emergency loading for 28 EDG.

PO resets 28 230V control center.

PO reports 2SW26 is open based on having no power to close it, and Main Turbine and TGA parameters related to SW cooling water are stable.

CRS directs stopping of loads being powered from 28 EDG:

PO stops 24 SW pump based on 4 SW pumps in service.

RO stops 21 charging pump based on 23 charging pump in service.

Note: Charging flow will lower to RO adjusts charging flow as required to

- 65 gpm when 21 charging pump maintain 6-12 gpm seal injection flow to each is secured. RCP, and not exceed 40 gpm total seal injection flow.

RO reports letdown did not isolate.

PO reports stable SG levels.

PO depresses 22 AFW pump start P8.

RO opens21-24SS94s.

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TQ-AA-106-0204 14 of 33 CRS determines if SGBD is to be restored.

PO restores SGBD to service if required.

RO/PO depresses 22 AFW pump stop PB and reports 22 AFW pump remains in service.

If CRS directs PO to close 21AF21 and 22AF22, PO reports 21AF21 and 22AF22 remain open.

IF directed to locally open 22 AFW CRS dispatches personnel to 22 AFW pump pump breaker, do NOT open it breaker.

unless the power reduction has been performed. IF power reduction to < 100% power has been performed, AND direction to locally open breaker has been given, then:

1. Delete 110 8512 for 22 AFW pump Stop PB.

2. Open 22 AFW pump breaker with REMOTE AF28D to TRIP.

3. Power Reduction to less than CRS directs PO to initiate a power reduction.

100% power.

RO calculates boration required for power reduction, and initiates boration.

PO initiate turbine load reduction to power specified by CRS at directed rate, and ensures load reduction starts.

PO ensures load reduction stops at the PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 15 of 33

'iEvahJ;atorJlnstructdr~Acti.vit

~~'~~~'T:!~*~~~~;;i~~~ ,~~~:i~':'~;}*~: ~~" ,',( ':~~~c > : ~. :':it ,( ,>~~'~Z~~~,:;~~~~~ti;Plr~~~j~~~nt'R;~~~~'~;5~T;;~;~1i~;f~~~'eg~"t'!.~'; i~;~~Fo:~~:~nt :,~~:;~.: .

specified level, and sets digital EHC up for the SGFP runback (66% @15%lminute).

Note: Time considerations may CRS enters TSAS 3.6.2.3 action b for 3 preclude identification of all Tech CFCUs inoperable (21 CIT, 22 and 24 have no Specs associated with the B Bus power.) 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months probable. Post scenario query may CRS enters TSAS 3.6.1.1 for Containment I, be necessary for all Tech Spec Integrity based on 2SW26 being inoperable. 1 identifications. Action times for each Tech Spec listed in bold.

hour CRS enters TSAS 3.8.1.1 for off-site power to 4KV vital bus. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months II CRS enters TSAS 3.8.2.1 for loss of power to 4KV/460V vital buses. 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months CRS enters TSAS 3.4.5 for loss of power to I

PORV Block valve 2PR7. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months CRS enters 3.8.2.3 and 3.8.2.5 for 125V and 28VDC battery chargers. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Continue to next event at lead Evaluators direction. ~

I

4. Steam Leak in Containment lI Silllulaior Operator::lnsertRT';5 ','

ort direction from Lead Evaruator. I

'MA~F:M~0088Cr M<lin Steam.

"Line Leak InsideContainrnent .

i::Ramp:5:rninufes.

Fil1aIVah... e': 1.5"( ,

RO reports CFCU leak detection HI, as unexpected.

RO reports rising level on 23 and 25 CFCU PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ*AA*106-0204 e16of33 leak detection.

RO reports rising containment pressure, and Containment Pressure High console alarm.

PO determines no rise in CNTMT radiation and that a steam leak is inside containment based on rising containment pressure.

CRS enters S2.0P.AB.STM-0001, Excessive Steam Flow.

CRS directs initiation of Attachment 1 Continuous Action summary.

PO verifies EHC system operating correctly, and MS 1Os and Steam Dumps are closed.

CRS determines a shutdown is required and plans rate and reactivity management.

RO calculates boration required.

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TQ-AA-106-0204 17 of 33 Note: It takes - 8 seconds from the insertion of RT-7 for the Rx trip signal to be generated.

RO reports demand for RX trip F Window annunciates, and initiates a manual reactor trip and informs CRS of ATWT.

CRS directs MSLI and verification of Safety when RX trio is confirmed.

RO reports MSLI failed and reports SI has auto initiated, and backs up SI initiation.

RO continues with Immediate Actions of EOP-TRIP-1, Rx Trip or Safety Injection:

- Trips Turbine

- Reports all Vital AC buses energized

- Reports SI actuated After Immediate Actions of EOP-TRIP-1 are completed, CRS may order PO to attempt MSLI isolation at 2CC3 and 2CC2 controls (fast and slow close).

CRS/RO verify immediate actions of EOP TRIP-1 are complete by performing PSEG Restricted - Possession Requires Specific Permission from Nuclear

TQ-AA-106-0204 Paae 18 of 33 verification of immediate action steps.

Note: STA will arrive in the control RO announces Rx trip and Safety injection.

room 10 minutes after being called initiate monitoring of CFSTs.

Note: With all SGs faulted, AFW PO throttles AFW flow to no less than 22E4 should not be isolated to any Ibm/hr with CRS concurrence.

SG.

PO reports SEC loading is not complete for A and B vital bus. 21 CFCU is CIT. Reports B bus is 2B4D breaker and 22 ABV Supply fan.

PO reports all available equipment started.

PO reports 21 and 23 AFW pumps are operating.

RO reports numerous safeguards valves have failed to realign due to no power available from 2B 460/230V buses, but reports that all valves have a redundant valve in the flowpath that has shut.

CRS dispatches personnel to realign safeguards valves which have not aligned to their safeguards positions.

RO reports 21 and 22CA330s are shut.

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TQ-AA-106-0204 Paae 19 of 33 RO reports containment pressure is > 15 psig.

RO reports Phase B and Containment Spray have not automatically initiated.

RO manually initiates CS and Phase B, stops RCPs, and verifies Phase B valve alignments.

RO reports High Steam Flow SI status and failure of MSLI to shut MS167s.

Role Play: Respond when CRS contacts WCC to assist in closing contacted that you will assemble a MS167s locally.

team of operators and mechanics and attempt to shut the valves you were directed to shut.

If CRS dispatches an NEO directly to attempt closure of any MS167, state that you will report to the WCC to pick up a Safety Man.

PO reports all 4KV vital busses are energized.

RO reports CAV is in Accident Pressurized mode.

Note: The 2C SEC must be RO runs 2 switchgear room supply fans and blocked and reset to allow start 1 exhaust fan.

of 23 switchgear supply fan.

RO reports 2 CCW pumps are running.

RO reports correct ECCS pump alignment and PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Paae 20 of 33 expected flows for RCS conditions.

Note: PO should have lowered PO reports AFW flow is >22E4 Ibm/hr, and AFW flow to as close to 22E4 maintains total AFW flow >22E4Ibm/hr.

Ibm/hr as possible.

RO reports all RCPs are stopped.

PO reports RCS temperature is not being controlled, and MSLI has failed to close any MS167.

RO reports both reactor trip breakers are open.

RO reports both PZR PORVs are shut and Block valves are open.

PO reports all SG pressures lowering in an uncontrolled manner or completely depressurized.

CRS transitions to EOP-LOSC-1, Loss of Secondary Coolant.

Timing of scenario will determine STA reports Red or Purple path on when FRCE Red or Purple path is Containment environment.

reported by the STA. When FRCE transition is made, go to FRCE steps on page 24.

CRS transitions to EOP-FRCE-1, Response to Excessive Containment Pressure.

LOSC-1 steps begin here. PO reports all MS167s are open.

Role Play if not previously CRS dispatches personnel to 21 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 21 of 33 performed: Respond when 24MS167s if not previously performed.

contacted that you will assemble a team of operators and mechanics and attempt to shut the valves you were directed to shut.

!f CRS dispatches an NEO directly to attempt closure of any MS167, state that you will report to the WCC to pick up a Safety Man.

PO reports all SG pressures lowering in an uncontrolled manner or completely depressurized.

CRS transitions to EOP-LOSC-2, Multiple Steam Generator Depressurization.

LOSC-2 steps begin here PO ensures all BF19s, BF40s, BF13s, MS10's, MS7s, MS18s, and GB4s are shut, and reports all MS167s remain open.

CRS dispatches operators to close MS167s one loop at a time if not previously dispatched.

Note: When SGs are completely CRS determines 23 AFW pump is needed to depressurized, 23 AFW pump will maintain SG levels.

slow down due to inadequate steam supply. If 23AF21 and 24AF21 were shut earlier in scenario, they will have to be opened to establish AFW flow.

CRS directs performance of Shutdown Margin monitoring.

RO reports RCS cooldown rate is > 100°F/hr.

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TQ-AA-106-0204 Paae 22 of 33 PO minimizes AFW flow to all SGs while maintaining a minimum of 1E4 Ibm/hr to each SG.

RO reports ReS That status.

Note: Once the SGs have RO reports all Reps stopped.

completely depressurized, ReS pressure will rapidly rise to the PZR PORV setpoint.

RO reports when ReS pressure is being controlled by automatic PZR PORV cycling.

PO reports selected MS167 valve is shut.

Note: IF step 8 is reached prior to PO reports selected SG pressure is rising.

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TQ-AA-106-0204 Paae 23 of 33 identification of MS 167 shut and SG pressure rising, the crew will perform SI reduction steps 8-20 before transitioning to LOSC-i.

CRS transitions to LOSC-1 based on a single SG pressure rise.

FRCE-1 Steps begin here. PO verifies Phase A isolation valves shut with 2VC5 open and 2VC6 shut.

RO reports:

- Containment pressure> 15 psig

- LOCA-5 not in effect

- Containment Spray in service

- Phase B isolation valves shut RCPs stopped.

RO reports CFCU status:

- 21 CFCU CIT.

- 22 and 24 CFCU have no power to fans, but SEC shut the respective 460V Low Speed breakers, and SW is being supplied to CFCUs.

- 23 and 25 CFCU running normally in Low Speed.

RO reports MSIVs remain open.

PO minimizes AFW to all SGs while maintaining at least 1E4 Ibm/hr per SG.

SImldato .. ope~atqn:~pnCE?'~B"J.,~ PO verifies all BF19s, BF40s, and BF13s are

~j;.JI8}o/.s,.ba.,~;~~.~~'~i~.~,t~.i. ~.'~~'.,.?~.g~i Y./).~1,

. . the*MAt:F aSSoclated.wlththe"')h'J'j them.

. f. .* . shut or dispatches operators to locally shut d ......

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TQ-AA-106-0204 Paae 24 of 33 PO reports selected MS167 valve is shut PO reports selected SG pressure is rising.

PO maintains at least 1E4 Ibm/hr to each SG.

CRS transitions to procedure in effect (LOSC-1 or 2)

STA reports RED path on Heat Sink CSF after PO reduces AFW flow.

CRS transitions to EOP-FRHS-1, Response to Loss of Secondary Heat Sink, and verifies it was operator action that lowered AFW flow less than 22E4 Ibm/hr, and returns to procedure in effect (LOSC-1 or LOSC-2).

Terminate scenario after the transition to LOSC-1 on rising SG pressure has been made.

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TQ-AA-106-0204 Paae 25 of 33 PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Page 26 of 33 A. Alarm Response Procedures (Various)

B. Technical Specifications C. Emergency Plan (ECG)

D. Salem FSAR E. OP-AA-101-111-1003, Use of Procedures F. S2.0P-SO.CBV-0002, Containment Pressure-Vacuum Relief System Operation G. S2.0P-AB.4KV-0002, Loss of 2B 4KV Vital Bus H. S2.0P-AB.STM-0001, Excessive Steam Flow I. 2-EOP-TRIP-1, Rx Trip or Safety Injection J. 2-EOP-LOSC-1. Loss of Secondary Coolant K. 2-EOP-LOSC-2, Multiple Steam Generator Depressurization L. 2-EOP-FRCE-1, Response to Excessive Containment Pressure M. 2-EOP-FRHS-1, Loss of Secondary Heat Sink N. 205338-2, Reactor Containment - Ventilation.

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TQ-AA-106-0204 Revision 2 Page 27 of 33 MODE: 1 POWER: 100% RCS BORON: 19 MWe 1230 SHUTDOWN SAFETY SYSTEM STATUS (5.6 & DEFUELED):

NA' REACTIVITY PARAMETERS MOST LIMITING LCO AND DATEHIME OF EXPIRATION:

21 CFCU CIT after its high speed breakers tripped 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ago. TSAS 3.6.2.3 action a.

EVOLUTIONS/PROCEDURES/SURVEILLANCES IN PROGRESS:

Containment Pressure Relief in progress lAW S2.0P-SO.CBV-0002. Containment Pressure-Vacuum Relief System Operation. Terminate the pressure relief lAW S2.0P SO.CBV-0002 upon assuming the watch.

ABNORMAL PLANT CONFIGURATIONS:

CONTROL ROOM:

Unit 1 and Hope Creek at 100% power.

No penalty minutes in the last 24 hrs.

PRIMARY:

SECONDARY:

RADWASTE:

No discharges in progress CIRCULATING WATER/SERVICE WATER:

None PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ*AA*106*0204 Revision 2 Pa e 28 of 33

1. Verify simulator is in "TRAIN" Load

2. Simulator is in RUN

3. Overhead Annunciator Horns ON

4. All required computer terminals in operation

5. Simulator clocks synchronized

6. All tagged equipment properly secured and documented

7. TSAS Status Board up-to-date

8. Shift manning sheet available

9. Procedures in progress open and signed-off to proper step

10. All aHA lamps operating (aHA Test) and burned out lamps replaced

11. Required chart recorders advanced and ON (proper paper installed)

12. All printers have adequate paper AND functional ribbon

13. Required procedures clean

14. Multiple color procedure pens available

15. Required keys available

16. Simulator cleared of unauthorized material/personnel

17. All charts advanced to clean traces and chart recorders are on.

18. Rod step counters correct (channel check) and reset as necessary

19. Exam security set for simulator

20. Ensure a current RCS Leak Rate Worksheet is placed by Aux Alarm Typewriter with Baseline Data filled out

21. Shift togs available if required

22. Recording Media available (if applicable)

23. Ensure ECG classification is correct

24. Reference verification performed with required documents available

25. Verify phones disconnected from plant after drill.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 In reviewing each proposed CT, the examination team assesses the task to ensure, that it is essential to safety. A task is essential to safety if, in the judgment of the examination team, the improper performance or omission of this task by a licensee will result in direct adverse consequences or in significant degradation in the mitigative capability of the plant.

The examination team determines if an automatically actuated plant system would have been required to mitigate the consequences of an individual's incorrect performance. If incorrect performance of a task by an individual necessitates the crew taking compensatory action that would complicate the event mitigation strategy, the task is safety significant.

I. Examples of CTs involving essential safety actions include those for which operation or correct performance prevents ...

degradation of any barrier to fission product release

degraded emergency core cooling system (ECCS) or emergency power capacity

a violation of a safety limit

a violation of the facility license condition

incorrect reactivity control (such as failure to initiate Emergency Boration or Standby Liquid Control, or manually insert control rods)

a significant reduction of safety margin beyond that irreparably introduced by the scenario II. Examples of CTs involving essential safety actions include those for which a crew demonstrates the ability to ...

effectively direct or manipulate engineered safety feature (ESF) controls that would prevent any condition described in the previous paragraph.

recognize a failure or an incorrect automatic actuation of an ESF system or component.

take one or more actions that would prevent a challenge to plant safety_

prevent inappropriate actions that create a challenge to plant safety (such as an unintentional Reactor Protection System (RPS) or ESF actuation.

PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

TQ-AA-106-0204 Revision 2 Page 31 of 34 Note: Attach a separate copy of this form to each scenario reviewed. This form is used as guidance for the examination team as they conduct their review for the proposed scenarios.

SCENARIO IDENTIFIER: 09-01 NRC ESG-3 REVIEWER: 1t~lvf a/uYl, Initials Qualitative Attributes The scenario has clearly stated objectives in the scenario.

The initial conditions are realistic, in that some equipment and/or instrumentation may be out of service, but it does not cue crew into expected events.

The scenario consists mostly of related events.

Each event description consists of:

the point in the scenario when it is to be initiated

the malfunction{s) that are entered to initiate the event

the symptoms/cues that will be visible to the crew

the expected operator actions (by shift position)

the event termination point No more than one non-mechanistic failure (e.g., pipe break) is incorporated into the scenario without a credible preceding incident such as a seismic event.

The events are valid with regard to physics and thermodynamics.

Sequencing/timing of events is reasonable, and allows for the examination team to obtain complete evaluation results commensurate with the scenario objectives.

The simulator modeling is not altered.

All crew competencies can be evaluated.

The scenario has been validated.

If the sampling plan indicates that the scenario was used for training during the requalification cycle, evaluate the need to modify or replace the scenario.

ESG-PSA Evaluation Form is completed for the scenario at the applicable facility.

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TQ-AA-106-0204 Revision 2 Page 32 of 34 Note: The quantitative attribute target ranges that are specified on the form are not absolute limitations; some scenarios may be an excellent evaluation tool, but may not fit within the ranges. A scenario that does not fit into these ranges shall be evaluated to ensure that the level of difficulty is appropriate. (ES-301 Section D.5,d)

Quantitative Attributes (as per ES-301-4, and ES-301 Section D,5.d) 6 Total malfunctions inserted: 5-8 1 Malfunctions that occur after EOP entry: 1-2 3 Abnormal Events: 2-4 2 Major Transients: 1-2 1 EOPs entered/requiring substantive actions: 1-2 1 EOP contingencies requiring substantive actions: 0-2 3 Crew Critical Tasks: 2-3 COMMENTS:

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TQ-AA*106*0204 Page 32 of 33 09-01 NRC ESG*3 CT#1 (E-O-A) Manually trip the reactor from the control room prior to SG dryout Basis: Failure to manually trip the reactor causes a challenge to the subcriticality CSF beyond that irreparably introduced by the postulated conditions. Additionally, it constitutes an "incorrect performance that necessitates the crew taking compensating action which complicates the event mitigation strategy and demonstrates the inability of the crew to recognize a failure of the automatic actuation of the RPS."

For a specific scenario, select a parameter that is related to the initial trip initiation signal and that is supported by analysis as being safety significant. .. a candidate for a safety significant parameter that can be developed into a performance standard is SG wide range water level. (Footnote 3.d)

CT#2 (E-O-E) Manually initiate Phase 8 and Spray Actuation before transition from Step 11 of 2-EOP-TRIP-1.

Basis: Failure to actuate the minimum required complement of containment cooling equipment under the postulated conditions constitutes a "demonstrated inability by the crew to recognize a failure/incorrect auto actuation of an EFS system or component." In this case, the minimum required complement of containment cooling equipment can be manually actuated from the control room. Therefore, failure to manually actuate the minimum required complement of containment cooling equipment also represents a "demonstrated inability by the crew to effectively direct/manipulate ESF controls that would lead to violation of the facility license condition."

Note: There is no time limit associated with this critical task (specifically stopping RCPs on isolation of CCW cooling)other than performing it before finishing step 11 in EOP-TRIP-1.

If an automatic Phase B and Spray initiation occurred, there is no time limit associated with getting to Step 11 perfomance in TRlp-1 bases, so no time limit can be imposed if the operator manually initiates Phase B and Spray when auto Spray fails to initiate.

CT#3 (FRCE Basis) Reduce AFW to no less than 1 E4 Ibm/hr per SG prior to exiting FRCE-1.

Basis: Failure to control the AFW flow rate to the SGs leads to an unnecessary and avoidable severe challenge to the integrity CSF. Also failure to perform the critical task increases the challenges to the subcriticality and the containment CSFs beyond those irreparably introduced by the postulated plant conditions. Thus, failure to perform the critical task constitutes "demonstrated inability by the crew to take an action or combination of actions that would prevent a challenge to plant safety" (con't next page)

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TQ-AA-106-0204 Page 33 of 33 The standard which has been applied to this CT in this scenario encompasses the reason for minimizing AFW flow to 1E4 Ibm/hr in FRCE with multiple faulted SGs. The reason this is done is to prevent thermal shock conditions to SG components if the SG was allowed to dry out, and then subsequently have AFW flow reinitiated. This meets the definition given on of Examples of CTs involving essential safety actions include those for which operation or correct performance prevents ...

degradation of any barrier to fission product release.

Not maintaining verifiable minimum AFW flow (1 E4th) when it is possible to do so could result in a SGTR when cold feedwater is subsequently reinitiated.

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TQ-AA-106-0204 34 of 33 EVENTS LEADING TO CORE DAMAGE YIN Event YIN N TRANSIENTS with PCS Unavailable N Loss of Service Water N Steam Generator Tube Rupture N Loss ofCCW N Loss of Offsite Power N Loss of Control Air N Loss of Switchgear and Pen Area Ventilation N Station Black Out N LOCA COMPONENTITRAIN/SYSTEM UNAVAILABILITY THAT INCREASES CORE DAMAGE FREQUENCY YIN COMPONENT, SYSTEM, OR TRAIN YIN COMPONENT, SYSTEM, OR TRAIN N Containment Sump Strainers N Gas Turbine N SSWS Valves to Turbine Generator Area N Any Diesel Generator N RHR Suction Line valves from Hot Leg Y Auxiliary Feed Pump N CVCS Letdown line Control and Isolation Valves N SBO Air Compressor OPERATOR ACTIONS IMPORTANT IN PREVENTING CORE DAMAGE YIN OPERATOR ACTION N Restore AC power during SBO N Connect to gas turbine N Trip Reactor and RCPs after loss of component cooling system N Re-align RHR system for re-circulation N Un-isolate the available CCW Heat Exchanger N Isolate the CVCS letdown path and transfer charging suction to RWST N Cool down the RCS and depressurize the system N Isolate the affected Steam Generator that has the tube rupture(s)

N Early depressurize the RCS N Initiate feed and bleed Complete this evaluation form for each ESG, PSEG Restricted - Possession Requires Specific Permission from Nuclear Training

ML113340065

Contents

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1.3 DESCRIPTION

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1.3 DESCRIPTION

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