Text

Final Operating Exam (Sections a, B, and C) (Folder 3)
	ML111010411
Person / Time
Site:	Pilgrim
Issue date:	01/24/2011
From:	; Entergy Nuclear Generation Co
To:	; NRC Region 1
	Hansell S
Shared Package
ML102210114	List: IR 05000293/2011301; ML102780057; ML110450647; ML110620474; ML110620479; ML111010402; ML111010406; ML111010409; ML111010411; ML111870176; ML111870178;
References
	TAC U01833
	Download: ML111010411 (241)
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PILGRIM 2011 NRC RO .ADMIN JPM C001 TITLE: Perform a Short Form Heat Balance Comparison OPERATOR: DATE:

EVALUATOR: EVALUATOR SIGNATURE: _ _ _ _ _ _ _ _ __

CRITICAL TIME FRAME: Required Time (min): N/A Actual Time (min): N/A

PERFORMANCE TIME: Average Time (min): 15 Actual Time (min):

JPM RESULTS: SAT UNSAT (Circle one)

COMMENT SHEET ATTACHED: Not Required for NRC JPMs SYNOPSIS: Perform a Short Form Heat Balance TASK Attachment 4 of PNPS 2.1.10 is completed with no errors.

STANDARD:

EVALUATION METHOD: EVALUATION LOCATION:

x Perform Plant Simulate x Simulator Control Room Prepared: Date:

Reviewed: Date:

Approved: Date:

Superintendent, Operations Training (or Designee)

TASK

Title:

Task Number K&A: K&A RATING:

Perform a Short Form Heat Balance 356-01-07-004 2.1.7 - Ability to evaluate 4.4 Comparison plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation

REFERENCES:

1. PNPS 2.1.10 SIMULATOR CONDITIONS:

1. IC-30 set at about 95% power (Recirc Speeds at 70.8%)

2. Turn OFF EPIC displays GENERAL TOOLS AND EQUIPMENT:

1. Steam Tables

2. Calculator CRITICAL ELEMENTS:

Critical elements are within the body of this document.

INITIAL CONDITIONS:

The plant was at approximately 80% power.

The plant process computer has been out of service for 2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .

An OPER-20 is in progress lAW PNPS 2.1.10 Section 7.5

PNPS Section 7.4 has been completed

The RE and Nuclear Computer Applications are attempting to restart the process computer.

The previous Short Form Heat Balance was performed one hour ago.

INITIATING CUE:

Perform a Short Form Heat Balance lAW PNPS 2.1.10 Att.4.

PERFORMANCE:

EXAMINER NOTE: Provide candidate with the previously completed Short Form Heat Balance NOTE: If the candidate notices the higher Indicated reactor power on the APRMs or Generator output and asks about these indications report that rising APRMs and Generator output have been noticed and that is why the Heat Balance is required to validate these indications.

START TIME:

1. Procedure Step Operator reviews the applicable sections of the procedure.

I Standard Reviews the following in PI\IPS 2.1.10:

Precautions and Limitations I

Section 7.5 reviewed i

AttA i I

I Comments Results SAT D UNSAT D

2. Procedure Step 1Fills out date/time and performed by on Attachment 4.

Standard . Date/time and performed by recorded on Attachment 4.

J Comments I I Results SAT UNSAT I I

3. Procedure Step Find and record reading for Feedwater Flow A from FI-640-24A on Panel C905.

i i

Standard FI-640-24A reading recorded.

I Comments Approximately 3.75 Mlb/hi I

Results SAT UNSAT I .~

I D I I

i 4. Procedure Step Find and record reading for Feedwater Flow B from FI-640-24B on Panel C90S.

Standard FI-640-24B reading recorded.

Comments Approximately 3.85 Mlb/hr.

Results SAT UNSAT r 1 I I

5. Procedure Step Find and record reading for Feedwater Temperature A from TR-3496A on Panel C1.

Standard TR-3496A reading recorded (RED pen).

Comments Approximately 360°F.

I Results I SAT UNSAT I D D

6. Procedure Step Find and record reading for Feedwater Temperature B from TR-3496B on Panel C1.

Standard TR-3496B reading recorded (BLUE pen).

Comments Approximately 360°F.

Results I

SAT D UNSAT D

7.

PrOOedlre Step Calculate Total Feedwater flow by adding the A and B Feedwater Flows.

Stamfard Total Feedwater flow calculated.

' . i

...... ~'."

,**:;:*:)C~"

APProximately 7.6 Mlb/hr.

Results SA I

UNSAT D

8. Procedure Step Average the A and B Feedwater Temperatures loops together.

Standard Average Feedwater temperature calculated.

I Comments Approximately 360°F.

Results SAT r UN SAT r l I

I~~.*..** . :"".'

."""'" i: . ';; .. , Using steam tables, determine Feedwater enthalpy.

Standard Feedwater enthalpy is recorded .

.'7 Cue

". ;/*~ts

... H1 310°F,. 332 BTU/lb* I Results SAT I I UNSAT r I

10. 'Pro~Step Determine Core Thermal Power 7.6 X (1189.6 - 332) + 9.02 = 1918 !

...... . I 3.413

$tllnd""ct Core Thermal Power is calculated at approximately 1918 MWth C~t$ the oaIoulatedCore Thermal Power depends on how the candidate reads Feedwater Flow Indications assuming a one division range of the meter scale.

'. Core Thermal Power should be In a range between approximately

.' 1892 and 1942MWth Rs&t11tC SAT I I UNSAT D

Terminating Cue: ONCE candidate discusses their findings the JPM can be terminated STOP TIME:

INITIAL CONOrnONS:

The plant was at approximately 80% power.

The plant process computer has been out of service for 2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .

An OPER-20 is in progress lAW PNPS 2.1.10 Section 7.5

PNPS Section 7.4 has been completed

The RE and Nuclear Computer Applications are attempting to restart the process computer

The previous Short Form Heat Balance was performed one hour ago INITIATING CUE:

Perform a Short Form Heat Balance lAW PNPS 2.1.10 Att.4.

PILGRIM 2011 NRC RO ADMIN JPM C002 TITLE: Operator License Status Verification OPERATOR: DATE:

EVALUATOR: EVALUATOR SIGNATURE: ---------------------

CRITICAL TIME FRAME: Required Time (min): N/A Actual Time (min): N/A PERFORMANCE TIME: Average Time (min): 15 Actual Time (min):

JPM RESULTS: SAT UNSAT (Circle one)

COMMENT SHEET ATTACHED: Not Required for NRC JPMs SYNOPSIS: Given a table containing watch standing, medical and, requal training information for 3 operators, determine if the requirements for maintaining an active license have been met TASK Determines that 2 of 3 operators have failed to meet 10 CFR 55 and utility STANDARD: requirements for maintaining an active license.

EVALUATION METHOD: EVALUATION LOCATION:

X Perform Plant Simulate Simulator/Classroom x Classroom Prepared: Date:

Reviewed: Date:

Approved: Date:

Superintendent, Operations Training (or Designee)

PILGRIM 2011 NRC RO ADMIN JPM C002 1 February 2011

TASK

Title:

Task Number K&A: K&A RATING:

Operator License Status XXXX 2.1.4 - Knowledge of 3.3 Verification individual licensed operator responsibilities related to shift staffing, such as medical requirements, "no-solo" operation, maintenance of active license status, 10CFR55, etc.

REFERENCES:

1. 10CFR55.53

2. PNPS 1.3.34 SIMULATOR CONDITIONS: N/A GENERAL TOOLS AND EQUIPMENT: N/A CRITICAL ELEMENTS:

Critical elements are within the body of this document.

INI1"IAL CONDITIONS:

The plant is operating at 100% power.

Today is January 20,2011.

You are the RO.

You must leave shift.

Three replacement operators are available.

INITIATING CUE:

Using the given information on Handout #1, determine which of the three operators, if any, are qualified to relieve you lAW procedural requirements of PNPS 1.3.34, Operations Administrative Policies and Processes.

Record your findings on Handout #2.

PILGRIM 2011 NRC RO ADMIN JPM C002 2 February 2011

PERFORMANCE:

EXAMINER NOTE: Provide candidate with Handout #1 START TIME:

aOl:lHCElDle sections of the' procedures.

of the operators in accordance with the below key Terminating Cue: ONCE candidate discusses their findings the JPM can be terminated Answer Key If No. whatrequl,ement Is not bel . ,mel.

Does not have a medical exam within the* past! years NO License has expired (>6 yrs 01 Does not meet the required number of hours performing NO dutl. . as a licensed operator for the last quarter (Because Work Control hours do NOT count - This reason Is NOT Crltlca VES NIA PILGRIM 2011 NRC RO ADMIN JPM C002 3 February 2011

HANDOUT #1 RO#1 RO#2 Hours Performing Operator Duties in Last Quarter Hours Performing Operator Duties in Last Quarter

. 10/16/10: 0700 - 1900 - ATC 11/21/10: 0700 - 1900 - Work Control 10/17/10: 0700 1900 ECCS Operator 11/30/10: 0700 - 1900 - ATC 10/25/10: 0700 - 1900 - ATC 12/14/10: 0700 - 1900 - ECCS Operator 11/5/10: 0700 - 1900 - Work Control 12/15/10: 0700 - 1900 Work Control 11/6/10: 0700 - 1900 - BOP 12/24/10: 0700 - 1900 - BOP 11/7/10: 0700 - 1900 - BOP 12/25/10: 0700 - 1900 - BOP 12/4/10: 0700 - 1900 - ATC 12/26/10: 0700 1900 - Work Control 12/5/10: 0700 1900 - Work Control Date of Most Recent Medical Exam - 12/10/2008 Date of Most Recent Medical Exam - 2/14/2009 License Issue Date 1/16/2005 License Issue Date - 3/27/2005 RO#3 Hours Performing Operator Duties in Last Quarter 10/6/10: 0700 - 1900 - BOP 11/8/10: 0700 - 1900 - ATC 11/9/10: 0700 - 1900 - ECCS Operator 11/15/10: 0700 - 1900 - Work Control 12/1/10: 0700 - 1900 - BOP 12/21/10: 0700 - 1900 - BOP Date of Most Recent Medical Exam - 6/5/2009 I

License Issue Date - 5/10/2005 PILGRIM 2011 NRC RO ADMIN JPM C002 4 February 2011

HANDOUT #2 Qualified for Relief? I'f No, what requirement(s)

(Yes/No) is/are not being met.

RO#1 RO#2 RO#3 PILGRIM 2011 NRC RO ADMIN JPM C002 5 February 2011

INITIAL CONDITIONS:

The plant is operating at 100% power.

Today is January 20,2011.

You are the RD.

You must leave shift.

Three replacement operators are available.

INITIATING CUE:

Using the given information, determine which of the three operators, if any, are qualified to relieve you lAW PNPS 1.3.34, Operations Administrative Policies and Processes.

Record your findings on Handout #2.

PILGRIM 2011 NRC RO ADMIN JPM C002 6 February 2011

Pilgrim NRC 2011 RO ADMIN JPM EC TITLE: Identify the tagging/clearance pOints for a shaft seal replacement on the "E" RBCCW pump OPERATOR: DATE:

EVALUATOR: EVALUATOR SIGNATURE: - - -

CRITICAL TIME FRAME: I ....

. ....ime (min): N/A Actual Time (min):

I N/A I

PERFORMANCE TIME: ime (min): 30 Actual Time (min):

I JPM RESLILTS: SAT UNSAT (Circle one)

COMMENT SHEET ATTACHED:

SYNOPSIS: Candidate must use plant prints to determine the blocking points for a shaft seal replacement on the liE" RBCCW pump, and then determine the position of the blocking point and the type of clearance tag required.

TASK Identify the blocking points, tag type and sequence for a clearance for a shaft seal STANDARD: replacement on the "E" RBCCW pump EVALUATION METHOD: EVALUATION LOCATION:

X Perform Plant Simulate x Simulator/Classroom Control Room Prepared: Date:

Reviewed: Date:

Approved: Date:

Superintendent, Operations Training (or Designee)

NRC 2011 RO ADMIN JPM EC 1 February 2011

TASK

Title:

Task Number K&A: K&ARATING:

CONDUCT EQUIPMENT TAGOUTS 299-03-01-012 2.2.13, Knowledge RO 4.1 SRO 4.3 CLEARANCE AND SWITCHING. of tagging and clearance procedures.

REFERENCES:

RBCCW P &10 M-215, Sheet 2 EN-OP-102-02, Fleet Tagging Assessments EN-OP-102, Protective and Caution Tagging SIMULATOR CONDITIONS: None None GENERAL TOOLS AND EQUIPMENT:

Ensure RBCCW P&IDs are available CRITICAL ELEMENTS:

Critical elements are within the body of this document.

INITIAL CONDITIONS:

The plant is at rated power. A tagouVclearance is required for maintenance work to replace the mechanical shaft seal on the HE" RBCCW pump INITIATING CUE:

Identify the components required to be tagged, the type of tags and the position of clearance pOints required for a shaft seal replacement on the HE" RBCCW pump NRC 2011 RO ADMIN JPM EC 2 February 2011

PERFORMANCE:

START TIME:

1. Procedure Step: Reference P&ID M-215, !

Standard Candidate determines correct P&ID and reviews it to determine the blocking points for the E RBCCW Pump.

Comments l

Results SAT D UNSAT I I

2. Pr~Step: Identifies isolations necessary to replace the seal on the E RBCCW Pump

. From EN-OP-102; and P&ID M-215 Using controlled documents, determine hazardous energy sources and isolations necessary to provide a safe work boundary for each work actiVity.

Stlf1dard See attached key C'*'~'" ..... "ems' Results SAT D UNSAT D

3. PfaIIMIure;Step: Identifies valves necessary to open to replace the seal on the E RBCCW Pump

[1] From EN-OP-102; Isolation Boundaries - Those components (isolation valves, vents, drains, electrical breakers, fuses, and/or switches, for example.) that are required to be pOSitioned to provide eqUipment protection and personnel safety during work actMty/procedural performance. One vent or drain should normally be tagged open to depressurize systems and to prevent it from re pressurizing .

. ......... . , Itfmdard S_attached ke~

Corftffl$nts SAT Ftesults D UNSAT D

NRC 2011 RO ADMIN JPM EC 3 February 2011

4. .......1d'St.~ Identifies the type of tags required to replace the seal on the E RBCCW Pump Standard See attached key Comme Aesults SAT D UNSAT D

Terminating Cue: ONCE candidate discusses their findings the JPM can be terminated KEY Com anent Ta T e Position 1.'RIeOW'PumpE Suction Valve 30-HO-46 Danger Closed RED 2; Pump Et>ischarge Valve 30-HO-49 Danger Closed RED

3. RBCCW Pump E Discharge PI-4004 Root Valve Caution - Open/Close as 30-HO-240E Yellow necessary to vent/drain NOTE: This isolation point is NOT required but may be chosen.

4. RII60W Pump E Discharge Casing Vent Valve CAUTION Open 30-HO-S2 Yellow OR DANGER Red Pump E (P-202E) Power Supply AUX Danger Off (Removed or Red OPEN itumpE (P-202E) Control Switch Danger Pull To Lock Red STOP TIME: _ _ _ _ _ _ __

NRC 2011 RO ADMIN ..IPM EC 4 February 2011

HANDOUT r---_ _ _ _ _ _ C_o_m-'-p_o"_e_"_t_______-+-_T_a9' p_e--+__P_o_s~

.....---T-"-y.......

i i I !

i I

I I

i i I I I

I

,..----...... I I

Stop time: _ _ _ _ __

NRC 2011 RO ADMIN JPM EC 5 February 2011

INITIAL CONDITIONS:

The plant is at rated power. A tagout/clearance is required for maintenance work to replace the mechanical shaft seal on the liE" RBCCW pump INITIATING CUE:

Identify the components required to be tagged, the type of tags and the position of clearance points required for a shaft seal replacement on the liE" RBCCW pump NRC 2011 RO ADMIN JPM EC 6 February 2011

Pilgrim 2011 NRC RO Admin JPM RC TITLE: Determine personnel available to perform a High Rad Area task OPERATOR: DATE:

EVALUATOR: EVALUATOR SIGNATURE: _ _ _ _ _ _ _ _ __

CRITICAL TIME FRAME: Required Time (min): N/A Actual Time (min): N/A PERFORMANCE TIME: Average Time (min): 15 Actual Time (min):

JPM RESULTS: SAT UNSAT (Circle one)

COMMENT SHEET ATTACHED:

SYNOPSIS: Candidate will determine the appropriate individual(s) to perform the task lAW EP-IP-440, the reasons for those selections and exclusions and whether an Extended Exposure authorization is required.

TASK Candidate will determine the appropriate individual(s) to perform the task lAW STANDARD: EP-IP-440 and the reasons for those selections and exclusions.

EVALUATION METHOD: EVALUATION LOCATION:

x Perform Plant Simulate x Simulator/Classroom Control Room Prepared: Date:

Reviewed: Date:

Approved: Date:

Superintendent, Operations Training (or Designee)

Pilgrim 2011 NRC RO ADMIN JPM RC 1 February 2011

TASK

Title:

Task Number K&A: K&ARATING:

Determine personnel available to XXX 2.3.4 - Knowledge of 3.2 perform a High Rad Area task radiation exposure limits under normal or emergency conditions.

REFERENCES:

10 CFR 20.1206 EP-IP-440 SIMULATOR CONDITIONS:

N/A GENERAL TOOLS AND EQUIPMENT:

Calculator CRITICAL ELEMENTS:

Critical elements are within the body of this document.

INITIAL CONDITIONS:

1. An event has occurred at the plant and the E-Plan has been entered.

2. A RCIC steam leak into the Reactor Building cannot be isolated without manually shutting the MO 1301-61 RCIC Steam Admission valve.

3. Radiation levels at the valve are 15 R/hr.

4. Rad Pro has determined the following:

A. Time to complete the task for an experienced Licensed Reactor Operator will be 12 minutes.

B. Time to complete the task for a recently Licensed Reactor Operator will be 25 minutes

5. Four (4) individuals are available to perform the task.

Worker A is a volunteer who is an experienced Licensed Reactor Operator and has previously received a Planned Special Exposure of 1R at a.nother facility this year. This individual has also received a dose of 1200 mR this year at Pilgrim

Worker B is a volunteer who is an experienced Licensed Reactor Operator and is a declared pregnant adult worker and has received a dose of 15 mR this year at Pilgrim

Worker C is a volunteer who is an experienced Ucensed Reactor Operator that has received a dose of 1200 mR this year at Pilgrim, as well as a dose of 2400 mR during this event on another task.

Worker D is a volunteer who is a recently Licensed Reactor Operator that has received a dose of 1400 mR this year at Pilgrim Pilgrim 2011 NRC RO ADMIN JPM RC 2 February 2011

INITIATING CUE:

1. Determine the worker(s) available to perform the task lAW EPIP-440, Emergency Exposure Controls, WITHOUT exceeding Emergency Exposure Limit AND why you chose the worker(s).

2. Determine the reason why you would not choose any particular worker to perform the task.

(Assume that dose rates remain at the level noted above throughout the task and it is completed.)

Pilgrim 2011 NRC RO ADMIN JPM RC 3 February 2011

START TIME:

1. L p~o.~ce_d_u_re Step Operator will review the task conditions and obtain EP-IP-440 J tl--*-------= ~t_a_nd_a~~ I op_e-,-ra-,-t_or_r_e_Vi_ew_s_th_e_t_as_k_c_on_di~o_n_s_a~_d_o_bt~i:S_~:~I:~~~ __~ ~=J COJllmert!s Provide the candidate with? copy of EP-IP-440 if requested I

L-L__

r-I Results SAT 0 _._..

UNSAT 0

__.___~._~._.~_.~_._.____J I'

~rator determines the worker that may be assigned to perform the 10k

\Al1"\1~WtAII"G may be chosen for reasons noted:

A may b, assigned to the task.

indMduafwUl result .in the lowest total dose for the job of 3R.

)( 15 R/hr = 3R) and will not exceed Emergency Exposure Limit of 5 Afor this event.

AiPl8ftlrMKI* SpecIal: ExJ*IUFe*t8.ICCounted for separately from

.,.. . .Ild.td dUri.,.anyotherplanMd special exposure and year 10 .eexp08ur. Ie not Included during Emergency Conditione.

UNSAT Pilgrim 2011 NRC RO ADMIN JPM RC 4 February 2011

1\;Op._~detenTfines worker(s) that may be NOT be assigned to perform the

" ...n .... TF_ reasonS")

reasons noted:

Worker B may NOT be a§igned to the task because she is a declared pr",nant adult and can not receive emergency exposure during emergency

~es.

1:'WOrKl!Jf' C may not be assigned to the task.

ChoOsillfthis im:iividual will result in a total dose to this person during this evt.mt of 5.4R. (0.2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months X.15 R/hr = 3R plus the additional dose of 2.4R in performing. another task during this event.)

Worker 0 may NOT be assigned to the task.

Choosing this individual will result in a total dose of 3.75R for the task. (0.42

~X 15~/hr =6.25R farthls task.).

D D Terminating Cue: ONCE candidate discusses their findings the JPM can be terminated STOP TIME:

Pilgrim 2011 NRC RO ADMIN JPM RC 5 February 2011

HANDOUT INITIAL CONDITIONS:

4. An event has occurred at the plant and the E-Plan Ilas been entered.

5. A RCIC steam leak into the Reactor Building cannot be isolated without manually shutting the MO 1301-61 RCIC Steam Admission valve.

6. Radiation levels at the valve are 15 R/hr.

4. Rad Pro has determined the following:

A. Time to complete the task for an experienced Licensed Reactor Operator will be 12 minutes.

C. Time to complete the task for a recently Licensed Reactor Operator will be 25 minutes

6. Four (4) individuals are available to perform the task.

Worker A is a volunteer who is an experienced Licensed Reactor Operator and has previously received a Planned Special Exposure of 1R at another facility this year. This individual has also received a dose of 1200 mR this year at Pilgrim

Worker B is a volunteer who is an experienced Licensed Reactor Operator and is a declared pregnant adult worker and has received a dose of 15 mR this year at Pilgrim

Worker C is a volunteer who is an experienced Licensed Reactor Operator that has received a dose of 1200 mR this year at Pilgrim, as well as a dose of 2400 mR during this event on another task.

Worker D is a volunteer who is a recently Licensed Reactor Operator that has received a dose of 1400 mR this year at Pilgrim INITIATING CUE:

1. Determine the worker(s) available to perform the task lAW EPIP-440, Emergency Exposure Controls, WITHOUT exceeding Emergency Exposure Limit AND why you chose the worker(s).

2. Determine the reason why you would not choose any particular worker to perform the task.

(Assume that dose rates remain at the level noted above throughout the task and it is completed.)

Pilgrim 2011 NRC RO ADMIN JPM RC 6 February 2011

PILGRIM 2011 NRC SRO ADMIN JPM C001 TITLE: Perform a Short Form Heat Balance Comparison OPERATOR: DATE:

EVALUATOR: _______________ EVALUATORSIGNATURE: _____________

F'nc.;;:..: TIME FRAME: Tf;uired Time (~i~): - N/Al Actual Time (min): ~,. N/~

,1'-_

PERFORMANCE TIME:

_ _ _ _ _ _~_~ _

Average Time (min): ~ ~ Actu;1 Time (min):

____'__ _ _ _ _ _ _ _ _---'-___---'-._ _ _ _ ~________ ___1 __________ j JPM RESULTS: SAT UNSAT (Circle one)

COMMENT SHEET ATTACHED: Not Required for NRC JPMs SYNOPSIS: Perform a Short Form Heat Balance Comparison and determine that reactor power has changed then take the corrective action.

TASK Attachment 4 of PNPS 2.1.10 is completed with no errors. A power reduction is STANDARD: required based on data comparison which indicates a power change greater than 10%.

EVALUATION METHOD: EVALUATION LOCATION:

x Perform Plant Simulate x Simulator Control Room Prepared: Date:

Reviewed: Date:

Approved: Date:

Superintendent, Operations Training (or Designee)

TASK

Title:

Task Number K&A: K&A RATING:

Perform a Short Form Heat Balance 356-01-07 -004 2.1.7 - Ability to evaluate 4A Comparison plant performance and make operational judgments based on operating characteristics, reactor behavior and instrument interpretation

REFERENCES:

1. PNPS 2.1.10 SIMULATOR CONDITIONS:

1. IC 30, set at about 95% power (Recirc Speeds at 70.8%)

2. A completed Short Form Heat Balance with MWth indicating about 290 MWth lower than the current conditions.

3. The thermal power difference between the handout and the current conditions must be greater than 10%.

4. Turn OFF EPIC displays GENERAL TOOLS AND EQUIPMENT:

1. Steam Tables

2. Calculator CRITICAL ELEMENTS:

Critical elements are within the body of this document.

INITIAL CONDITIONS:

The plant was at approximately 80% power.

The plant process computer has been out of service for 2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .

An OPER-20 is in progress lAW PNPS 2.1.10 Section 7.5

PNPS Section 7A has been completed

The RE and Nuclear Computer Applications are attempting to restart the process computer.

The previous Short Form Heat Balance was performed one hour ago.

INITIATING CUE:

Perform a Short Form Heat Balance lAW PNPS 2.1.10 AttA and take actions as specified in Section 7.5 of PNPS 2.1.10, Computer Data and Alarms.

EXAMINER NOTE: Provide candidate with the previously completed Short Form Heat Balance

PERFORMANCE:

NOTE: If the candidate notices the higher indicated reactor power on the APRMs or Generator output and asks about these Indications report that rising APRMs and Generator output have been noticed and that is why the Heat Balance is required to validate these indications.

START'rlME:

1. Procedure Step Operator reviews the applicable sections of the procedure.

Standard Reviews the following in PNPS 2.1.10:

Precautions and Limitations

Section 7.5 reviewed

AttA Comments Results SAT D UNSAT D

2. Procedure Step Fills out date/time and performed by on Attachment 4. I Standard Date/time and performed by recorded on Attachment 4.

Comments Results SAT UNSAT I I I D

3. Procedure Step Find and record reading for Feedwater Flow A from FI-640-24A on Panel C9OS.

Standard FI-640-24A reading recorded.

Comments Approximately 3.75 Mlb/hr.

Results SAT LlNSAT i D I I

4. Procedure Step Find and record reading for Feedwater Flow B from FI-640-24B on Panel C90S.

Standard FI-640-24B reading recorded.

Comments Approximately 3.85 Mlb/hr Results SAT UNSAT D I I

5. Procedure Step Find and record reading for Feedwater Temperature A from TR-3496A on Panel C1.

Standard TR-3496A reading recorded (RED pen).

Comments Approximately 360°F.

Results SAT UNSAT I I D I I

6. Procedure Step Find and record reading for Feedwater Temperature B from TR-3496B on Panel C1.

Standard TR-3496B reading recorded (BLUE pen).

Comments Approximately 360°F.

Results SAT D UNSAT I I

.p ***Cafcutate Total Feedwaterflow by adding the A and B Feedwater Flows.

T"'aterflow calculated.

UNSAT D

8. Procedure Step Average the A and B Feedwater Temperatures loops together.

i Standard Average Feedwater temperature calculated.

I i

Comments Approximately 360°F.

Results SAT I I UNSAT I I i

~ng _am tables, determtne Feedwater enthalpy.

Feedwater enthalpy is recorded.

UNSAT De1temttneCore Thermal Power 7.6 X (1189.6 ~ 332) + 9.02 = 1918 3.413 Thermal Power is calculated at approximately 1918 MWth

.".....latetCICOr. Thermal Power depends on how the eandldate

.iP.","1t1' Flowlndlcatl..... anumIn, a one division rante of the UNSAT

~,~oml.r~~8 data obtained above with the previously provided Short Form Balance. Baseline data will showthat CTP was 1628 MWth iii~I01tl.r_ data and determines that reactor power change greater than 10%

ha&~ped which requires lowering reactor power with recirc flow. PNPS

. *p7.'&II1(e)

'.~'Hm the candidate compares the Short Form Heat Balance just completed

_mat the provided form, they should note the increase in core thermal power. A recommendation must be made for a reduction in power lAW PHPS8tep 7.5[2](b).4)

In this situation, lAW STEP 7.5(2)(b)(4), a >10% power change has occurred od tt1erefore'apower reduction is required.

J~18 -1828= 290), 290MWtH change is >10% change. A 10% change WUI~ .have been 162.8 MWth.

Terminating Cue: ONCE candidate discusses their findings the JPM can be terminated STOP TIME:

INITIAL CONDITIONS:

The plant was at approximately 80% power.

The plant process computer has been out of service for 2.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months .

An OPER*20 is in progress lAW PNPS 2.1.10 Section 7.5

PNPS Section 7.4 has been completed

The RE and Nuclear Computer Applications are attempting to restart the process computer

The previous Short Form Heat Balance was performed one hour ago INITIATING CUE:

Perform a Short Form Heat Balance lAW PNPS 2.1.10 Att.4 and take actions as specified in Section 7.5 of PNPS 2.1.10, Computer Data and Alarms. Here is the previous hours heat balance which did not deviate from the initial baseline data.

HANDOUT ATTACHMENT 4 Sheet 1 of 1 SHORT fORM HEAT BALANCE Date/Time _Today_l_" HOUf Ago_ __

Performed By __SXD_ _ _ _ _ _ __

OPERATING DATA:

Item Panel Instrument Reading Units (I) Feedwater Flow A C905 FI-640-24A 3.10 Mib/hr Feedwater Flow B C905 FI-640-24B 3.23 Mlblhr feedwate" Temp A C1 TR-3496A 345 of

@ Feedvlater Temp B C1 TR-3496B 345 ~F CALCULATION:

The circled numbers are item numbers; Le., Total Feedwater Flmv is equal to Item (Feedwater Flow A) plus Item ,~) (Feedwater Flow B).

T etal Feedwater Flow: +@ 3.10 + 3.2J = 6.33 Mlblhr Ave. Feedwater Temp: 1f2(@+ @) .5 (34!:; +3450) =345 OF Feedwater Enthalpy: Stm. Tables, @ 3165 Btullb Core Thermal PO'#er: X (1189.6 - tJ)) + 9.02 =

3.4 13 6.33 XE6 X (1189.6 - 316.5)13.4 13 + 9.02 =1628.3 MWth Comments:

NRC 2011 SRO ADMIN JPM C002 TITLE: Perform a Review of the Control Room Daily Logs OPERATOR: DATE:

EVALUATOR: EVALUATOR SIGNATURE:

CRITICAL TIME FRAIl~:;:: Required Time (min): I N/A Actual Time (min): N/A PERFORMANCE TIME: Average Time (min): ual Time (min):

I JPM RESULTS: SAT UNSAT (Circle one)

COMMENT SHEET ATTACHED: Not Required fm NRC JPMs SYNOPSIS: Perform a Review of the Control Room Daily Logs TASK Attachment 1 of PNPS 2.1.15 is reviewed with OOS items identified, TS/FSAR STANDARD: applicability determined and other notifications made as required EVALUATION METHOD: EVALUATION LOCATION:

X Perform Plant Simulate Simulator X Classroom Prepared: Date:

Reviewed: Date:

Approved: ~---------------------- Date:

Superintendent, Operations Training (or Designee)

NRC 2011 SRO ADMIN JPM C002 1 February 2011

TASK

Title:

Task Number K&A: K&A RATING:

Perform a Review of the Control XX 2.1.18 - Ability to make 3.8 Room Daily Logs clear, accurate and concise logs, records, status boards, and reports.

REFERENCES:

1. PNPS 2.1.15, Att.1 SIMULATOR CONDITIONS:

1. None required GENERAL TOOLS AND EQUIPMENT:

Partially completed Att.1 of PNPS 2.1.15 - Daily Log Tests Tech Specs FSAR Section 10.8 CRITICAL ELEMENTS:

Critical elements are within the body of this document.

INITIAL CONDn"IONS:

The plant is at approximately 100% power.

INITIATING CUE:

Perform a review of the Attachment 1 of the Control Room Daily Logs beginning at Daily Log Test #8. When the review is completed through Daily Log Test #37, inform the examiner of findings and any Technical Specification, FSAR and/or procedural required actions, if any, from your review.

NRC 2011 SRO ADMIN JPM C002 2 February 2011

PERFORMANCE:

EXAMINER NOTE: Provide candidate with the Handout - Partially completed Att.1 of PNPS 2.1.15 - Daily Log Tests DO NOT PROVIDE FSAR SECTION UNLESS REQUESTED START TIME:

1. '<~:aep Dally Log Test #1 a (Step 2) - Sheet 21 of 66

~es th. Aecirc Flow Converter readings are not within 6% as required

-determines that a work request must be issued.

IIUie candidate states*that they must initiate a work request state. "Another operator will issue the work requesf'.

If the operator reports that they are notifying the Shift Manager. as the Shift Manager reply, "I understand. Determine required T.S., FSAR and/or procedural requirements".

UNSAT NRC 2011 SRO ADMIN JPM C002 3 February 2011

Baity log Test #31 - Sheet 41 of 66 tdentifles that boron concentration is OOS LOW - (Step 1. - 8.16%)

determines that TS 3.4.A. applies and that concentration must be restored to within limits WIthin 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

AIao,natifies Chemistry.

The notification to Chemistry is NOT CRITICAL for this step. The TS appttcation Is critical The candidate ma reference TS 3.4.C which refers to T8 3A.A.

SAT UNSAT

3. ~. Step 9lilyLog Test #35 - Sheet 45 of 66

'$umlllfidentifies that FireWater Storage tank Levets are OOS LOW. Refers to FSAA Section 10.8.4.2.1 sAd determines that levels must be restored WIthin 7 days.

FSAR Section if requested.

UNSAT D

Terminating Cue: ONCE candidate discusses their findings the JPM can be terminated STOP TIME:

NRC 2011 SRO ADMIN JPM C002 4 February 2011

INITIAL CONDITIONS:

The plant is at approximately 100% power.

INITIATING CUE:

Perform a review of the Attachment 1 of the Control Room Daily Logs beginning at Daily Log Test #8. When the review is completed through Daily Log Test #37, inform the examiner of findings and required actions, if any, from your review.

NRC 2011 SRO ADMIN JPM C002 5 February 2011

NRC 2011 SRO ADMIN JPM EC TITLE: Analyze a Solomon case from 3D Monicore and determine the appropriate action.

OPERATOR: DATE:

EVALUATOR: EVALUATOR SIGNATURE:

CRITICAL TIME FRAME: Required Time (min): N/A I Actual Time (min):

PERFORMANCE TIME: Average Time (min): 15

Actual Time (min):

JPM RESULTS: SAT UNSAT (Circle one)

COMMENT SHEET ATTACHED: Not Required for NRC JPMs SYNOPSIS: With the plant operating in the Buffer Zone on the Pilgrim Power/Flow Map analyze a Solomon case from 3D Monicore and determine the appropriate action.

TASK Following a dual Recirculation Pump runback the candidate will review a Solomon STANDARD: Case and determine that the Hot Channel Decay Ratio is higher than allowable, then determine power must be lowered using the RPR array instruction sheet.

EVALUATION METHOD: EVALUATION LOCATION:

x Perform Plant Simulate Simulator x Classroom Prepared: Date:

Reviewed: Date:

Approved: Date:

Superintendent, Operations Training (or Designee)

NRC 2011 SRO ADMIN JPM EC 1 February 2011

TASK

Title:

Task Number K&A: K&ARATING:

3D Monicore review 2.2.38 - Knowledge of 4.5 conditions and limitations in the facility license.

REFERENCES:

1. PNPS 2.4.20, Reactor Recirculation System Speed or Flow Control System Malfunction

2. Solomon Case

3. PNPS 2.1 .14, Station Power Changes

4. PNPS 2.4.165 Reactor Core Instability SIMULATOR CONDITIONS: N/A GENERAL TOOLS AND EQUIPMENT:

Solomon Stability Evaluation Report (attached)

CRITICAL ELEMENTS:

Critical steps are within the body of this document.

INITIAL CONDITIONS:

Both Recirculation Pumps have run back due to a 'flow control system malfunction

The plant has entered PNPS 2.4.20 and Immediate actions completed including the lock up of both Recirculation Pump Scoop Tubes

Maintenance has requested that Recirculation Pump speed NOT be changed.

Reactor operation is in the Buffer Zone

Operation is above the 60% Rod Line

There are no LPRM alarms

There are no APRM or LPRM oscillations occurring

A Solomon Case has been printed and will be provided INITIATING CUE:

Evaluate plant conditions in accordance with PNPS 2.4.20, and determine required actions, if any.

Examiner Note: provide the candidate with the Solomon Case Handout NRC 2011 SRO ADMIN JPM EC 2 February 2011

PERFORMANCE:

Examiner Note: Provide Solomon Stability Evaluation (attached).

START TIME:

1. Performance Step Reviews 2.4.20 Reactor Recirculation System Speed or Flow Control System Malfunction, step 4.0 [1] (a) 4.0 SUBSEqUENT OPERATOR ACTIONS

[1J ASSESS operating conoitions by plotting power versus core flow on the Pilgrim PoweriFlow Map.

(a) !f operating in a region of instability (Exclusion Region or Buffer Zone), !l:it!l REFER TO PNPS 2,4,165 8.t!Q PERFORM CONCURRENTLY.

[NRC GL.94-02 (ElWROG-9407811 Standard Operator reviews 2.4.20 -step 4.0 [1] (a) and enters 2.4.165 Reactor Core Instability step 4.0 [4]

Comment Results SAT D UNSAT D

2. Performance Step Enters and Reviews 2.4.165 - Reactor Core Instability step 4.0

[4]

[5] JE operating in the Buffer Zone AtiI2. SOLOMON is available, (a) II:iiJi DEMAND a SOLOMON case from 3D Monicore AUQ. VERIFY the following:

Core Decay Ratio (DR) is <: 0,70, Hot Channel Decay Ratio is" 0,55.

Standard Operator reviews 2.4.165 - Reactor Core Instability step 4.0 [4]

and obtains and the Solomon Case Cue Comment:

Results SAT D UNSAT D

NRC 2011 SRO ADMIN "IPM EC 3 February 2011

Reviews the Solomon Case Printout (a) II::IE.t:l DEMAND a SOLOMON case from 3D Monicore At:U:!. VERIFY the following:

Core Decay Ratio (DR) is < 0.70.

Hot Channel Decay Ratio is <. 0.55.

(b) 1E the Core Decay Ratio (DR) is ::: 0.70.Q.B. the Hot Channel Decay Ratio is 0.55, I!:iEt! IMMEDIATELY EXIT the Buffer Zone by either:

Raising core flow, unless restricted by another Off-Normal Operating Procedure.

Inserting control rods in accordance with PNPS 2.1.14 Section 7.9.

Operator reviews the Solomon Case and determines that Core Decay Ratlo Is <0.70 and Hot Channel Decay Ratlo is >0.55 and theoperetor must immediately exit the Buffer Zone.

The oritical/portion of this step Is determining the Hot Channel DeeayRatio Is greater than the allowable value.

UNSAT D

4. Performance Step Enters and Reviews 2.1.14 Station Power Changes section 7.9 7.9 POWER DECREASE EFFECTED BY RPR ARRAY/ROPS

[1] WHEN power reduction below that achieved by executing Section 7.11 is required, THEN PERFORM the following steps until the desired power level is attained:

Standard Candidate may go to section 7.11 to determine the correct actions.

Comment Candidate may know that 2.1.14, Section 7.11 is for lowering power using recirculation flow and not required and skip the next step Results SAT UNSAT NRC 2011 SRO ADMIN ..IPM EC 4 February 2011

5. Performance Step Reviews 2.1.14 Station Power Changes section 7.11, Power Reductions during Abnormal Conditions.

Standard Identifies that 7.11, Power Reductions during Abnormal Conditions, does not apply since flow has already been lowered and operation is above the 60% Rod Line.

Comment Results SAT UNSAT D

Enters and Reviews 2.1.14 - Station Power Changes section 7.9 Greater than or equal to 60% load line (1) VERIFY/REDUCE total core flow to achieve as close to. but less than 43 Mlblhr.

(2) This method shall only be utilized during events that require rapid power reduction, when directed by Off-Normal Procedures, or as directed by the SMleRS, OTHERWISE, REDUCE power in accordance with Step 7,9[1](b), "ROPS",

(3) INSERT control rods as specified by the RPR array instruction sheet, as required, to the desired load line (REFER TO PNPS 9.13),

Identifies that that core flOw is less than 43 Mtb/hr by reviewing the power flow map (Att 1A of the procedure) Also determines tbat2.4.16S requires immediate exit from the Buffer Zone and

. inserts control rods. as specified ,by the APR array instruction

Itt_t.

SAT D UNSAT Terminating Cue: ONCE candidate discusses their findings the JPM can be terminated STOP TIME:

NRC 2011 SRO ADMIN JPM EC 5 February 2011

INITIAL CONDITIONS:

Both Recirculation Pumps have run back due to a flow control system malfunction

The plant has entered 2.4.20 and Immediate actions completed including the lock up of both Recirculation Pump Scoop Tubes

Maintenance has requested that Recirculation Pump speed NOT be changed.

Reactor operation is in the Buffer Zone

Operation is above the 60% Rod Line

There are no LPRM alarms

There are no APRM or LPRM oscillations occurring

A Solomon Case has been printed INITIATING CUE:

Determine the required action(s), if any.

NRC 2011 SRO ADMIN JPM EC 6 February 2011

PLANT NAME: PILGRIM CYCLE 18 PAGE 1 OF2 SOLOMON STABILITY EVALUATION REPORT XX-JAN-201112:00 CALCULATE XX-JAN-2011 12:01 PRINTED CORE DECAY RATIO 0.69 CASE ID FMLDll01018120004 HOT CHANNEL DECAY RATIO = 0.60 RESTART FMLDl101018110004 CORE POWER MWT = 912 LOAD LINE

SUMMARY

CORE FLOW MLB/HR = 29.643 CORE POWER 44.9%

CORE FLOW 42.0%

INITIATED BY: 3D MONICORE LOAD LINE 80%

CORRECTION FACTORS: MFLCPR= 1.001 MFLPD=: 0,999 MAPRAT= 0.999 zpp= 3.25 f OPTION: ARTS 2 LOOPS ON MANUAL FLOW MCPRLIM= 1.5.10 FCBB= N/A VALUE LOCATION MFLCPR 0.880 23-26 MFLPD 0.676 25-32-17 MAP RAT 0.704 23-26-18 PC RAT 0.994 27-20-17 STABILITY ANALYSIS TYPE: OFFICIAL SEQ.A2 C=MFLCPR D=MFLPD M=MAPRAT P=PCRAT '" MULTIPLE CORE AVE AXIAL 51 NOTCH RELPW LOC 00 0.187 24 47 02 0.138 L 04 0.802 43 08 06 0.936 08 1.058 39 00 00 10 1.108 L 12 1.136 35 00 00 14 1.189 D 16 1.168 31 18 1.195 L 20 1.311 27 08 08 22 1.315

'" 24 1.328 23 26 1.320 L P 28 1.246 19 00 00 30 1.193 32 1.177 15 34 1.121 L 36 1.055 11 08 38 1.021 40 0.959 07 42 0.858 L 44 0.730 03 46 0.269 L

02 06 10 14 18 22 26 30 34 38 42 46 50 CORE AVERAGE RADIAL POWER DISTRIBUTION RING # 1 2 3 4 5 6 7 RELPW 1.269 1.449 1.372 1,274 1.305 1.171 0.466 NRC 2011 SRO ADMIN JPM EC 7 February 2011

NRC 2011 SRO ADMIN JPM RC TITLE: Determine the ODCM requirements for both Reactor Building Effluent Monitoring Systems inoperable.

OPERATOR: DATE:

EVALUATOR: EVALUATOR SIGNATURE:

CRITICAL TIME FRAME: Required Time (min): N/A Actual Time (min): N/A PERFORMANCE TIME: Average Time (min): 15 Actual Time (min):

JPM RESULTS: SAT UNSAT (Circle one)

COMMENT SHEET ATTACHED: Not Required for' NRC JPMs SYNOPSIS: Candidate will determine the actions required when both channels of the Reactor Building Effluent Monitoring System become inoperable the ODCM TASK With Reactor Building Effluent Monitoring System "AU RM-1705-32A out of service the STANDARD: control room will must determine the ODCM 3.1 requirements when the "B" monitor becomes inoperable. This includes that grab samples are taken, that auxiliary sampling equipment is operable and flow rates are estimated.

EVALUATION METHOD: EVALUATION LOCATION:

x Perform Plant Simulate Simulator x Classroom Prepared: Date:

Reviewed: Date:

Approved: Date:

Superintendent, Operations Training (or Designee)

NRC 2011 SRO ADMIN JPM RC 1 February 2011

TASK

Title:

Task Number K&A: K&A RATING:

Determine and apply ODCM 2.3.11 - Ability to 4.3 requirements control radiation releases.

REFERENCES:

aDCM Section 3.1 and 3.3 SIMULATOR CONDITIONS:

1. N/A GENERAL TOOLS AND EQUIPMENT:

1. None CRITICAL ELEMENTS:

Critical steps are within the body of this document.

INITIAL CONDITIONS:

The plant is at 100% power

Reactor Building Effluent Monitoring System "An RM-1705-32A became inoperable due to a vacuum pump failure at 20:00 yesterday.

INITIATING CUE:

As the SM you have just been told that the vacuum pump on the "B" Reactor Building Effluent Monitoring System, RM-1705-32B failed. Determine the ODCM 3.1 requirements for continued operation including the times when actions must occur.

NRC 2011 SRO ADMIN JPM RC 2 February 2011

START TIME:

1. Performance Step Obtain and review ODCM Section 3.1.2, Radioactive Gaseous Effluent Monitoring Instrumentation Standard Obtains and reviews aDCM Section 3.1.2, Radioactive Gaseous Effluent Monitoring Instrumentation Comment Results SAT UNSAT

2. Performance Step Determines from aDeM Table 3.1-2 past 2 that the minimum number of Reactor Building Effluent Monitoring System channels is NOT met.

Standard Determines from ODCM Table 3.1*2 past 2 that the minimum of one channel of the Reactor Building Effluent Monitoring System channels is required, with both "A" and "B" inoperable there are no channels available.

Comment Results SAT UNSAT D NRC 2011 SRO ADMIN JPM RC 3 February 2011

3. Performance Step Evaluates how the instrument inoperability effects the five required functions of the Reactor Building Effluent Monitoring System are inoperable.

Standard Determines from aDCM Table 3.1-2 part 2 that all five functions of the Reactor Building Effluent Monitoring System are inoperable. That notes (1) (2) and (3) are applicable.

Comment Results SAT D UNSAT D

4. P~.nce Step Action 1. With the number of OPERABLE channels less than required by the minimum channels OPERABLE reqUirement, effluent releases via this pathway may continue provided grab samples are taken at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and these samples analyzed for activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

~ard Determines that grab samples must be taken within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and analyzed for activity within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Comment Results SAT D UNSAT D NRC 2011 SRO ADMIN "IPM RC 4 February 2011

5. PerfOrmance Step Action 2. With the number of OPERABLE channels less than required by the minimum channels OPERABLE requirement, effluent releases via this pathway may continue provided samples are continuously collected wit auxiliary sampling equipment as required in table 4.3 1.

w Standard: Candidate goes to Table 4.3~1 and determines the following continuous sampling is required:

Weekly Charcoal Sample for Iw131

Weekly Particulate Sample for Principal Gamma Emitters

Monthly Composite Particulate Sample for Gross Alpha

Quarterly Composite Particulate Sample for Sr-89, Sr-90

Continuous Noble Gas Monitor for Noble Gas Gross Gamma Comment:

Results SAT D UNSAT

6. Performance Step Action 3. With the number of OPERABLE channels less than required by the minimum channels OPERABLE requirement, effluent releases via this pathway may continue provided the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Standard Determines that the flow rate is estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Comment Results SAT D UNSAT D

Terminating Cue Determines that grab samples are taken, that auxiliary sampling equipment is operable and flow rates are estimated.

STOP TIME:

NRC 2011 SRO ADMIN JPM RC 5 February 2011

INITIAL CONDITIONS:

The plant is at 100% power

Reactor Building Effluent Monitoring System "AU RM-1705-32A became inoperable due to a vacuum pump failure at 20:00 yesterday.

INITIATING CUE:

As the SM you have just been told that the vacuum pump on the "B" Reactor Building Effluent Monitoring System, RM-1705-32B failed. Determine the aDCM 3.1 requirements for continued operation including the times when actions must occur.

NRC 2011 SRO ADMIN JPM RC 6 February 2011

NRC 2011 SRO ADMIN JPM EP - Scenario #2 TITLE: Evaluate Plant Event and Determine Appropriate EAL Classification (Scenario #2)

OPERATOR: DATE:

EVALUATOR: EVALUATOR SIGNATURE:

CRITICAL TIME FRAME: Required Time (min): N/A Actual Time (min): N/A PERFORMANCE "riME: Average Time (min): 15 Actual Time (min):

JPM RESULTS: SAT UNSAT (Circle one)

COMMENT SHEET ATTACHED: Not Required for NRC JPMs SYNOPSIS: Evaluate Plant Event and Determine Appropriate EAL Classification TASK Candidate will review the plant events and conditions at the end of NRC Scenario #2 STANDARD: and determine the Emergency Classification as a Site Area Emergency due to EAL:

2.3.1.3, Reactor power> 3% and boron injection into the RPV intentionally initiated.

EVALUATION METHOD: EVALUATION LOCATION:

X Perform Plant Simulate X Simulator OR X Classroom Prepared: Date:

Reviewed: Date:

Approved: Date:

Superintendent, Operations Training (or Designee)

TASK

Title:

Task Number K&A: K&A RATING:

Evaluate Plant Event and Determine XXXX 2.4.41 - Knowledge of 4.6 Appropriate EAL Classification the emergency action level thresholds and classifications.

NRC 2011 SRO ADMIN JPM EP - Scenario #2 1 February 2011

REFERENCES:

EALs SIMULATOR CONDITIONS: N/A GENERAL TOOLS AND EQUIPMENT:

EAL Chart CRITICAL ELEMENTS:

Critical steps are within the body of this document.

INITIAL CONDITIONS:

The plant was operating at 90% power

A Recirc pump outboard seal failure occurred and the pump was tripped and isolated

The other recirc pump tripped

The reactor was scrammed and several control rods failed to insert

Boron was injected to the vessel

EOP-3 was entered due to Suppression Pool Temperature >80°F

Injection to the RPV was terminated and prevented lAW EOPs

All Control Rods were inserted using methods in PNPS 5.3.23 INITIATING CUE:

Determine the EAL classification based on the scenario events.

NRC 2011 SRO ADMIN JPM EP - Scenario #2 2 February 2011

PERFORMANCE:

START TIME:

Performance Step: 1 Review scenario events Standard: Operator scenario events Comment:

Terminating Cue: ONCE candidate discusses their findings the JPM can be terminated STOP TIME: _ _

NRC 2011 SRO ADMIN JPM EP - Scenario #2 3 February 2011

INITIAL CONDITIONS:

The plant was operating at 90% power

A Recirc pump outboard seal failure occurred and the pump was tripped and isolated

The other recirc pump tripped

The reactor was scrammed and several control rods failed to insert

Boron was injected to the vessel

EOP-3 was entered due to Suppression Pool Temperature >80°F

Injection to the RPV was terminated and prevented lAW EOPs

All Control Rods were inserted using methods in PNPS 5.3.23 INITIATING CUE:

Determine the EAL classification based on the scenario events.

NRC 2011 SRO ADMIN JPM EP - Scenario #2 4 February 2011

NRC 2011 SRO ADMIN JPM EP - Scenario #3 TITLE: Evaluate Plant Event and Determine Appropriate EAL Classification (Scenario #3)

OPERATOR: DATE:

EVALUATOR: EVALUATOR SIGNATURE:

CRITICAL TIME FRAME: Required Time (min): N/A Actual Time (min): N/A PERFORMANCE TIME: Average Time (min): 15 Actual Time (min):

JPM RESULTS: SAT UNSAT (Circle one)

COMMENT SHEET ATTACHED: Not Required for NRC JPMs SYNOPSIS: Evaluate Plant Event and Determine Appropriate EAL Classification TASK Candidate will review the plant events and conditions at the end of NRC Scenario #3 STANDARD: and determine the Emergency Classification as a Site Area Emergency due to EAL 3.4.1.3: Torus bottom pressure cannot be maintained below the "Pressure Suppression Pressure" (PSP) EOP Figure 6.

EVALUATION METHOD: EVALUATION LOCATION:

x Perform Plant Simulate X Simulator OR X Classroom Prepared: Date:

Reviewed: Date:

Approved: Date:

Superintendent, Operations Training (or Designee)

TASK

Title:

Task Number K&A: K&ARATING:

Evaluate Plant Event and Determine XXXX 2.4.41 Knowledge of 4.6 Appropriate EAL Classification the emergency action level thresholds and NRC 2011 SRO ADMIN JPM EP Scenario #3 1 February 2011 2011

classifications.

REFERENCES:

EALs SIMULATOR CONDITIONS: N/A GENERAL TOOLS AND EQUIPMENT:

EAL Chart CRITICAL ELEMENTS:

Critical steps are within the body of this document.

INITIAL CONDITIONS:

The plant was operating at 90% power

An SRV stuck and a manual scram was inserted

All Control Rods inserted Full In

EOP-3 was entered due to High Suppression Pool temperature

Torus Bottom pressure exceeded 16 psig

Drywell Sprays could not maintain containmemt pressure below the PSP curve

An Emergency Depressurization was performed INITIATING CUE:

Determine the EAL classification based on the scenario events.

NRC 2011 SRO ADMIN JPM EP - Scenario #3 2 February 2011 2011

PERFORMANCE:

START TIME:

Performance Step: 1 Review scenario events Standard: Operator scenario events Comment:

'Sfte NeaErn. . . .

be~'_,

EOPFiijU"i~. '.

Terminating Cue: ONCE candidate discusses their findings the JPM can be terminated STOP TIME: _ __

NRC 2011 SRO ADMIN ...IPM EP - Scenario #3 3 February 2011 2011

INITIAL CONDITIONS:

The plant was operating at 90% power

An SRV stuck and a manual scram was inserted

All Control Rods inserted Full In

EOP-3 was entered due to High Suppression Pool temperature

Torus Bottom pressure exceeded 16 psig

Drywell Sprays could not maintain containment pressure below the PSP curve

An Emergency Depressurization was performed INITIATING CUE:

Determine the EAL classification based on the scenario events.

NRC 2011 SRO ADMIN JPM EP - Scenario #3 4 February 2011 2011

PILGRIM 201"1 NRC JPM S-1 NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE (RO/SRO)

TITLE: CONTROL ROD EXCERCISING lAW 8.3.2 CALTERNATE PATH)

OPERATOR: DATE: ____________________

EVALUATOR: EVALUATOR SIGNATURE: _ _ _ _ _ _ _ _ __

I CRITICAL TIME FRAME: Required Time (min): N/A Actual Time (min): N/A PERFORMANCE TIME: Average Time (min): 20 Actual Time (min):

JPM RESULTS*: SAT UNSAT NEEDS IMPROVEMENT (Circle one) *Refer to Grading Instructions at end of JPM COMMENT SHEET ATTACHED: Yes / No (circle one) (Required for Unsat, Needs Improvement or Follow-Up Questions)

SYNOPSIS: The reactor is at power. The weekly control rod exercising in accordance with procedure 8.3.2 is required. When a coupling check is performed on a rod being withdrawn, the rod will go into an overtravel condition. The operator is expected to recouple the rod per off-normal procedure 2.4.11. The JPM will end when the rod is recoupled.

TASK Control rod exercising will be performed lAW procedure 8.3.2, Station Power STANDARD: Changes. When an uncoupled rod is discovered the rod will be recoupled lAW off normal procedure 2.4.11. There shall be no failure of critical elements EVALUATION METHOD: EVALUATION LOCATION:

x Perform Plant Simulate x Simulator Control Room Prepared: Date:

Reviewed: Date:

Approved: Date:

Superintendent, Operations Training (or Designee)

PILGRIM 2011 NRC JPM S-1 -1

PILGRIM 201"1 NRC JPM 8-1 REVISION LOG ision Number Date Description I 1 08/19/10 Revised a control rod movement JPM to reflect new format and different procedure for 2011 LOT NRC Exam PILGRIM 2011 NRC JPM 8-1 -2

PILGRIM 2011 NRC JPM 8-1 TASK

Title:

Task Number K&ASYSTEM: K&ARATING:

RESPOND TO A DRIFTING 201-04-01-010 201002 201002 CONTROL ROD

REFERENCES:

2.4.11, Rev 21 8.3.2, Rev 54 SIMULATOR CONDITIONS:

1. Initialize the simulator to an Exam full power IC 30 and start Lesson Plan 30. Perform the following:

2. Verify control rods 14-51 and 18-51 are at position 48 and that 18-51 will be uncoupled, by inserting malfunction RD10, Rod Uncoupled when it is exercised.

3. Condition RD10 to DELETE when the "right dig if' on the 4-rod display for control rod 18-51 is TRUE for position 4.

GENERAL TOOLS AND EQUIPMENT:

1. Printout of the current Control Rod positions (00-3)

2. Applicable sections of 8.3.2 filled out; Section 7 and 8 (check the Normal Surveillance box)

3. 8.3.2, Attachments 1, 2, 3, and 5 (Multiple copies of Att.3)

CRITICAL ELEMENTS:

Critical elements are shaded in gray within the body of this document.

PILGRIM 2011 NRC JPM 8-1 -3

PILGRIM 2011 NRC JPM S-1 OPERATOR BRIEF:

1. State the following paragraph IF this is the first performance in this setting:

a) "All actions associated with this job performance measure are to be performed. You will be provided access to any tools or equipment you determine necessary to perform the task. When a second checker is called for, the evaluator will perform the role of second checker and will always be in agreement with your actions. Before you start, the evaluator will state the task conditions and answer any questions, then provide a cue to begin."

2. Always state the following two paragraphs:

a) "The title of this JPM is: CONTROL ROD EXCERCISING lAW 8.3.2 a) "The task conditions are as follows:

i) The reactor is at 100 % power.

ii) Weekly Control Rod exercising shall be performed lAW procedure 8.3.2, Section 8.1.

Starting with control rod 14-51, proceeding to 18-51 then working across the top of the core from the left to the right continuing down each subsequent row of control rods.

iii) Reactor Engineering has directed that single notch exercising is required for this surveillance.

iv) Reactor Engineering has determined there are no control rods that have demonstrated excessive movement speeds.

v) Sections 7.0 and 8.0 of 8.3.2 already been completed.

vi) A current control rod printout has just been printed vii) A Reactivity Manager has been stationed and reactivity brief conducted.

viii) An operator (state the individual's/evaluator's name) has been assigned to verify control rod withdraw.

3. Solicit and answer any questions the operator may have. (Step 1 of the JPM has answers to some anticipated questions. Refer to step 1 as necessary.)

INITIATING CUE:

"[State the operator's name], commence the weekly control rod exercising lAW procedure 8.3.2, Section 8.1."

PILGRIM 2011 NRC JPM S-1 -4

PILGRIM 201*1 NRC JPM S-1 PERFORMANCE:

Notes This task is covered in procedure 8.3.2 and 2.4.11 All controls associated with this JPM are located on C905.

All critical steps must be performed in order written unless otherwise noted START TIME:

1. Procedure Step: Obtains procedure 8.3.2 and goes to section 4.1 Control Rod Exercise at 1

power. Reviews procedure: I Standard Obtains current revision of PNPS 8.3.2 and enters section 4.1, reviews procedure Cue Notes I i Results SAT D UNSAT D

1

2. Procedure Step: [2] PRIOR to rod exercise, OBTAIN a control rod printout [Format 500 or 3D MonicorE Control Rod Position Log (F9 key)].

Standard Operator obtains control rod printout of Control Rod Positions.

i I

Cue Role playas second operator and provide a control rod printout of the current Control Rod Positions Notes Printout of the current Control Rod Positions was made prior to starting the JPM.

i Results SAT D I I PILGRIM 2011 NRC JPM S-1 -5

PILGRIM 201'1 NRC JPM S-1

3. Procedure Step: [3] ENSURE a second licensed Reactor Operator is stationed at Panel C905 to verify proper control rod movement.

Standard Operator verifies a second operator is available at the C905 Panel as a verifier.

Cue State you will act as second operator and perform verifications Role playas verifier, read from the sequence sheet and communicate to the operator the following:

- rod number

- initial rod position

- final rod position.

Notes These steps are to be repeated prior to each rod withdrawn.

I Results SAT D UNSAT D

4. Procedure Step: [4] ENSURE the Rod Select Power Switch is ON.

Standard Operator verifies Rod Select Power switch is in the ON position.

Cue Notes Results SAT D UNSAT I I

5. Procedure Step: !

NOTES

1. Attachments 1 and 2 are provided as placekeeping aids for Control Room Operators.

Use of either Attachments 1 and/or 2 is at the discretion of the CRS. Neither Attachment is required to be maintained with the completed copy of this Procedure.

2. If the selected rod does not withdraw using normal drive water differential pressure, then elevating drive water differential pressure is preferred to "double clutching" the rod. Refer to PNPS 2.4.11.1 Attachment 1, This will lessen the potential for a rod mispositioning.

3. At the discretion of the SM/CRS, control rods may be exercised in sequence provided that the core conditions and limitations "fJ",... ifii:u by Reactor En\:l''''''''\:1 are met.

Standard Operator may select to use Attachments 1 and 2 during this evolution.

The order of control rod selection for testing was stated in the initial conditions.

Cue Notes I I Results SAT I I UNSAT D

PILGRIM 2011 NRC JPM S-1 -6

PILGRIM 201'1 NRC JPM S-1

6. Procedure Step: CAUTIONS

1. For control rods that have previously demonstrated excessive movement speeds and have the potential to "double notch", it is permissible to reduce the CRD System drive water differential pressure setpoint to 200 psid as indicated by dPI-340-4 In order to mitigate the possibility of a mlspositlonlng event. The CRD System drive water differential pressure setpolnt shall be returned to 250 psld immediately following the movement of the control rod In question to its intended position.

2. During the control rod exercise, only the control rods specified by Reactor Engineering on Attachment 6 are to be left inserted one notch.

Standard Operator recalls from the initial conditions that there are NO control rods that have demonstrated excessive movement speeds.

Cue Notes Results SAT D UNSAT D

7. Procedure Step: [5] EXERCISE the fully withdrawn, operable control rods as follows:

(a) VERIFY OR ADJUST MO-302-8 to obtain a CRD drive water differential pressure setpoint as indicated on dPI-340-4 of:

200 psid for control rods that have previously demonstrated excessive:

movement speeds. !

OR

250 psid for all other control rods .

Standard Operator maintains CRD Drive pressure at 250 psid.

Cue i

Notes Results SAT D UNSAT D i PILGRIM 2011 NRC JPM S-1 -7

PILGRIM 201'1 NRC JPM S-1 s'~ *PWMtJllre8tep: (b) INSERT the rod to be exercised to position 46 or, as evaluated by Reactor Engineering, to position 44 in accordance with Attachment 1 Step (1).

From Attachment 1:

a. MOMENTARILY TURN the ROD CONTROL switch to the "ROD OUT NOTCH" position

!tiQ. RELEASE the control switch.

b. OBSERVE the control rod IS latched in an even-numbered positi,on and that it is in the latched position before the SETTLE light goes off.

c. IF performing two notch exercise, OBSERVE control rod movement AND IF movement speed appears fast, AOJ UST MO-302-B to obtain a CRD drive water differential setpoint as indicated on dPI-340-4 of 200 psid.

d. If the control rod is at position 48, I.I:15!i PERFORM a control rod coupling check in accordance with Attachment 2.

e. !E. performing two notch exercise in accordance with base document Step 8.2[6](b), REPEAT Steps [3](b)(1)a and b above.

~aId Operator selects Control Rod 14-51 and inserts the control rod to position 46 and observes the SETTLE light OFF.

Cue Rote playas verifier "i*:

Not.

~ults SAT D UNSAT D

9;, RroOeCkn

.," ".' , . ",.p.. . ** (d) WITHDRAW the rod to position 48 unless otherwise instructed by Reactor Engineering. Rod withdrawal to be in accordance with Attachment 1 Steps [3)(a) and [3](b)(1).

"'.rd Qperatorwithdraws Control Rod 14-51 to position 48 and observes the SETTLE light OFF.

CUe Role playas verifier,

' .. , This step Is redundant to the step in PNPS 8.3.2 Attachment 1 Results SAT D UNSAT D

PILGRIM 2011 NRC JPM S-1 -8

PILGRIM 201'1 NRC JPM S-1 til, " . . .r.:IIep: (e) PERFORM a control rod coupling test in accordance with Attachment 2 (PNPS 2.2.88 Section 7'.6). [SR4.3.B.1.3]

Verifies (a) Position indication on the four rod display momentarily goes "BLACK/BLACK" and returns to indicate position 48.

(b) The FULL OUT red indicating light on the futl core display wU! momentarily go off and then re-illuminate.

(c) Alarm "ROO OVERTRAVEL" (C90SL-B3) does NOT actuate, Standard Operator may either attempt to withdraw Control Rod 14-51 or attempt a continuous control rod withdrawal from position 48.

Verifies coupling check is satisfactory:

Cue , Role playas verifier I

NOleI i

"AesttltS SAT D UNSAT I I

11. Procedure Step: [6] INITIAL (two persons' initials required) the appropriate square on the Control Rod Exercise Signoff Sheet (Attachment 3). These initials indicate that the control rod has been placed in its correct position.

Standard Operator initials Attachment 3 for Control Rod 14-51 .

Cue i Role playas verifier and also initial Control Rod that candidate initialed.

i Notes I

Results SAT D UNSAT D

i 12. Procedure Step: [7] !E. the coupling test was satisfied, INITIAL the appropriate square on the Control ROd~~

Coupling Test Signoff Sheet (Attachment 5). A second person's verification is require if the coupling test will be used to support the implementation of an alternate BPWS

sequence for shutdown.

Standard Operator initials Attachment 5 for Control Rod 14-51.

Cue Role playas verifier and also initial Control Rod that candidate initialed.

Notes I

Results SAT D UNSAT I J PILGRIM 2011 NRC JPM S-1 -9

PILGRIM 201"1 NRC JPM S-1

18. ~.""'.,"'p: (b) INSERT the rod to be exercised to position 46 or, as evaluated by Reactor Engineering, to position 44 in accordance with Attachment 1 Step [1].

From Attachment 1 :

a. MOMENTARILY TURN the ROD CONTROL switch to the "ROD OUT NOTCH" position Af:!Q. RELEASE the control switch.

"" b. OBSERVE the control rod is latched in an even-numbered position and that it is in the latched position before the SETTLE light goes off.

c. IF performing t\vo notch exercise, OBSERVE control rod movement AND IF movement speed appears fast, ADJ UST MO-302-8 to obtain a CRD drive ".,'ater differential setpoint as indicated on dPI-340-4 of 200 psid.

',. [;

d. if the control rod is at position 48, ll:i&.t:l PERFORM a control rod coupling check in accordance with Attachment 2.

e. IF performing t\vo notch exercise in accordance with base document Step 8.2[6](b), REPEAT Steps [3](b)(1)a and b above .

Operator selects Control Rod 18-51 and inserts the control rod to position 46

.' .and observes the SETTLE light OFF Cue Role playas verifier

Notes Ae$ults SAT D UNSAT I I

14. P. . . . . . . .p: (d) WITHDRAW the rod to position 48 unless otherwise instructed by Reactor Eng ineering. Rod withdrawal to be in accordance with Attachment 1 Steps [3](a) and [3](b)( 1).

~rd Operator withdraws Control Rod 18-51 to position 48 and observes the

< SETTLE Ught OFF Que..... Role playas verifier,

\' ..';,

Notfi Thl$ step is redundant to the step in PNPS 8.3.2, Attachment 1 i Rlluftl SAT D UNSAT D

PILGRIM 2011 NRC JPM S-1 - 10

PILGRIM 2011 NRC JPM S-1

15.: . . . p~ . .: (e) PERFORM a control rod coupling test in accordance with Attachment 2 (PNPS 2.2.88 Section 7.6). (SR4.3.B.1.3]

Verifies (a) Position indication on the four rod display momentarily goes "BLACK/BLACK" and returns to indicate position 48.

(b) The FULL OUT red indicating light on the full core display will momentarily go off and then re*illuminate.

(c) Alarm "ROD OVERTRAVEL" (C905L*B3) does NOT actuate.

Standard Operator may either attempt to withdraw Control Rod 18-51 or attempt a continuous control rod withdrawal from position 48.

Verifies acknowledges (C905L-B3), ROD OVERTRAVEL alarming and observes blank position indication for Control Rod 18-51, determines coupling check is Unsatisfactory and Control Rod 18-51 is uncoupled Announces control rod overtravel and rod drift alarms and refers to ARPs.

.... Cue Role playas verifier I

_sutts SAT D UNSAT D

! 16. Procedure Step: [4] IF any control rod coupling test has failed, THEN REFER TO PNPS 2.4.11, "Control Rod Positioning Malfunctions",

Standard Operator refers to PNPS 2.4.11, Attachment 1 Cue Notes I I Results SAT D I I PILGRIM 2011 NRC JPM S-1 - 11

PILGRIM 2011 NRC JPM 8-1 11, j~l.p: (a) ATTEMPT TO RECOUPLE the drive by inserting it two notches.

Standard Operator selects Control Rod 18-51 and inserts the control rod to position 46, waits for settle step then inserts the control rod to position 44.

i Cue Role playas verifier Notes Results SAT D UNSAT D I

18. P. . . .ur. . .p: (b) WITHDRAW the rod by notching it out.

S~ Operator withdraws Control Rod 18-51 to position 46, waits for settle step then withdraws the control rod to position 48. I Cue Role pfay as verifier j .,

j,'

Notes Resul*' SAT D UNSAT I J 1'. ~edurep: (c) ~ the drive is withdrawn to position 48, I!::I.5.ti PERFORM a rod coupling check in accordance with Attachment 5.

[1 J PERFORM a control rod coupling check as follows:

(a) With a control rod at position 48, PERFORM the following:

(1 ) SELECTIVERIFY SELECTED the control rod for coupling test.

I (2) ATTEMPT TO NOTCH WITHDRAW QB CONTINUOUSLY WITHDRAW i

, the selected control rod from position 48.

Stedard Operator may either attempt to withdraw Control Rod 18-51 or attempt a continuous control rod withdrawal from position 48.

Verifies coupling check is satisfactory:

Cue Role pfay as verifier Notes Resuk$' SAT I D UNSAT D

PILGRIM 2011 NRC JPM 8-1 - 12

PILGRIM 2011 NRC JPM S-1

! 20. Procedure Step: (d) !E. the drive has recoupled, THEN RESET the "ROD DRIFT" (C905L-A3) alarm AND RETURN TO normal operation.

Standard Operator resets "ROD DRIFT" and verifies Rod Drift Annunciator clears then returns to the performance of Control Rod ExercisinQ per PNPS 8.3.2 Cue Notes i

Results SAT D UNSAT I I I

21. Procedure Step: [6] INITIAL (two persons' initiclls required) the appropriate square on the Control Rod EXercise Signoff Sheet (Attachment 3). These initials indicate that the control rod has been placed in its correct position.

Standard Operator initials Attachment 3 for Control Rod 18-51.

Cue Role playas verifier and also initial Control Rod that candidate initialed.

Notes Results SAT D UNSAT D

22. Procedure Step: [7] IF the coupling test was satisfied, INITIAL the appropriate square on the Control Rod Coupling Test Signoff Sheet (Attachment 5). A second person's verification is require if the coupling test will be used to support the implementation of an alternate BPWS sequence for shutdown.

Standard Operator initials Attachment 5 for Control Rod 18-51 .

Cue Role playas verifier and also initial Control Rod that candidate initialed.

Inform the operator that this ,JPM is completed. I Notes Results SAT D I I Cue: This completes this JPM.

STOP TIME:

PILGRIM 2011 NRC JPM S-1 - 13

PILGRIM 2011 NRC JPM S-1 JPM GRADING INSTRUCTIONS CRITERIA FOR SATISFACTORY EVALUATION

1. 100% of critical elements/steps identified in the JPM successfully completed.

2. Critical Time Frame is met if applicable

3. 1\10 actual safety violation (radiological or industrial) requiring evaluator intervention.

CRITERIA FOR UNSAT EVALUATION

1. Any critical element/step is graded as "UNSAT"

2. Critical Time Frame is not met if applicable. *

3. Actual safety violation (radiological or industrial) requiring evaluator intervention.

4. Operator's actions would have damaged plant equipment, created a personnel safety hazard, or otherwise reduced the level of safety of the plant CRITERIA FOR NEEDS IMPROVEMENT EVALUATION

1. One or more non-critical elements/ steps evaluated as UNSAT which indicate the need for remediation.

2. Any relevant Management Expectation/Standard missed a majority of the opportunities.

ADMINISTRATIVE REQUIREMENTS Any performance deficiencies resulting in an UNSAT or NEEDS IMPROVEMENT evaluation shall be documented on the JPM comment sheet.

Documentation for Satisfactory evaluations need only consist of the cover sheet and any applicable comment sheet(s) provided that a Master Copy of the JPM is on file or captured.

Documentation for UNSAT evaluations shall consist of the entire, as administered ..IPM, with associated comment sheets.

Documentation for NEEDS IMPROVEMENT evaluations need only consist of the cover sheet and the associated comment sheet(s) describing the operator deficiencies noted, provided that a Master Copy of the JPM is on file or captured and the deficiencies are involving only management expectations. Otherwise, the entire JPM shall be retained.

PILGRIM 2011 NRC JPM S-1 - 14

PILGRIM 201'1 NRC JPM S-1 JPM COMMEt--lT SHEET REQUIREMENTS:

Any operator deficiencies resulting in an UNSAT or NEEDS IMPROVEMENT evaluation shall be documented.

Any follow-up questions asked and the operator's response must be documented.

Any operator deficiencies which, in themselves, would not result in an UNSAT evaluation of this JPM but may, when coupled with performance on other JPMs, result in an OVERALL FAILING evaluation for the JPM exam should also be documented below.

Any other comments, positive or negative, that the evaluator determines is worth noting.

COMMENTS:

PILGRIM 2011 NRC JPM S-1 - 15

PILGRIM 2011 NRC JPM S-1 INITIAL CONDITIONS:

The reactor is at 100 % power.

Weekly Control Rod exercising shall be performed lAW procedure 8.3.2, Section 8.1. Starting with control rod 14-51, proceeding to 18-51 then working across the top of the core from the left to the right continuing down each subsequent row of control rods.

Reactor Engineering has directed that single notch exercising is required for this surveillance.

Reactor Engineering has determined there are no control rods that have demonstrated excessive movement speeds.

Sections 7.0 and 8.0 of 8.3.2 have already been completed.

A current control rod printout has just been printed

A Reactivity Manager has been stationed and reactivity brief conducted.

An operator (state the individual's/evaluator's name) has been assigned to verify control rod withdraw.

INITIATING CUE:

"[State the operator's name], commence the weekly control rod exercising lAW procedure 8.3.2, Section 8.1."

PILGRIM 2011 NRC JPM 8-1 - 16

PILGRIM 201*1 NRC JPM S-:;:~

NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE (RO/SRO)

HPCI SWAPOVER FROM PRESSURE CON"rROL TO INJECTION CALTERNATE PATH)

OPERATOR: DATE: ____________________

EVALUATOR: EVALUATOR SIGNATURE:

I CRITICAL TIME FRAME: Required Time (min): N/A Actual Time (min): N/A I PERFORMANCE TIME: Average Time (min): B Actual Time (min):

JPM RESULTS*: SAT UNSAT NEEDS IMPROVEMENT (Circle one) *Refer to Grading Instructions at end of JPM COMMENT SHEET ATTACHED: Yes / No (circle one) (Required for Unsat, Needs Improvement or Follow-Up Questions)

SYNOPSIS: HPCI is operating in pressure control mode and must be swapped to injection mode.

When HPCI is placed in injection mode and the candidate attempts to raise injection flow the HPCI Flow Controller FIC-2340-1 fails high, the operator must place the controller in manual to raise flow.

TASK HPCI injecting to the RPV. The HPCI System shall be operated in accordance with all STANDARD: applicable precautions and limitations. The HPCI procedure shall be followed and there shall be no failure of critical elements.

EVALUATION METHOD: EVALUATION LOCATION:

x Perform Plant Simulate x Simulator Control Room Prepared: Date:

Reviewed: Date:

Approved: Date:

Superintendent, Operations Training (or Designee)

PILGRIM 2011 NRC JPM S-2 -1

PILGRIM 201"1 NRC JPM 8-~~

REVISION LOG Revision Number: 5 Date Originated: 7/20/2005 Pages Affected: All

Description:

New template Revision Number: 6 Date Originated: 8/10/2010 Pages Affected: All

Description:

Revised for NRC exam and faulted JPM PILGRIM 2011 NRC JPM 8-2 -2

PILGRIM 201'1 NRC JPM S-2 TASK

Title:

Task Number K&ASYSTEM: K&A RATING:

HPCI Swapover from Pressure 206-01-01-005 206000 A4.02 4.0/3.8 Control to Injection

REFERENCES:

Procedure 5.3.35.1, Attachment 23 SIMULATOR CONDITIONS:

1. Exam IC-54, this will:

Trip all three feed pumps

Trip RCIC

Initiate HPCI in full'flow test for pressure control

Reactor water level is about -20"

Insert malfunction HPCI Flow Controller FIC-2340-1 fails high with the controller in AUTO occurs when the full flow test valve MO-2301-1 0 is fully closed as indicated by the red light going OFF.

GENERAL TOOLS AND EQUIPMENT:

1. N/A CRITICAL ELEMENTS:

Critical elements are shaded in gray within the body of this document.

OPERATOR BRIEF:

1. State the following paragraph IF this is the first performance in this setting:

a) "All actions associated with this job performance measure are to be performed. You will be provided access to any tools or equipment you determine necessary to perform the task. When a second checker is called for, the evaluator will perform the role of second checker and will always be in agreement with your actions. Before you start, the evaluator will state the task conditions and answer any questions, then provide a cue to begin".

2. Always state the following two paragraphs:

a) "The title of this JPM is: HPCI SWAPOVER FROM PRESSURE CON"rROL TO INJECTION" b) "The task conditions are as follows:

i) The reactor has scrammed on low level following a loss of feed.

ii) RCIC has tripped.

iii) HPCI is presently operating in pressure control mode and has been manually initiated in accordance with PI\lPS 2.2.21.5.

iv) Current RPV level is approximately -20 inches."

3. Solicit and answer any questions the operator may have.

PILGRIM 2011 NRC JPM S-2 -3

PILGRIM 201'1 NRC JPM S-2 INITIATING CUE:

State the following:

"[Operator's name], swap HPCI from pressure control to injection in accordance with procedure 5.3.35.1, Attachment 23. Restore and maintain level-20" to +45". Inform me when HPCI is aligned for injection and maintaining RPV level -20" to +45".

PILGRIM 2011 NRC JPM S-2 -4

PILGRIM 2011 !\IRC JPM S-2 PERFORMANCE:

Notes This task is covered in 5.3.35.1, Attachment 23.

All controls are located on control room panel C903/904.

All critical steps must be performed in order unless otherwise noted.

START TIME:

1 Procedure Step: I 1 .

Standard Review the applicable sections of the Qrocedure. I Cue None I Notes i i

Results SAT D UNSAT D I D

(J)lMT D PILGRIM 2011 NRC JPM S-2 -5

PILGRIM 201'1 NRC JPM 8-2 UNSAT D necessary UNSAT D Cue: This completes this JPM.

STOP TIME:

PILGRIM 2011 NRC JPM 8-2 -6

PILGRIM 201'1 NRC JPM S-2 JPM GRADING INSTRUCTIONS CRITERIA FOR SATISFACTORY EVALUATION

1. 100% of critical elements/steps identified in the ...IPM successfully completed.

2. Critical Time Frame is met if applicable

3. No actual safety violation (radiological or industrial) requiring evaluator intervention.

CRITERIA FOR UNSAT EVALUATION

1. Any critical element/step is graded as "UNSAT"

2. Critical Time Frame is not met if applicable. *

3. Actual safety violation (radiological or industrial) requiring evaluator intervention.

4. Operator's actions would have damaged plant equipment, created a personnel safety hazard, or otherwise reduced the level of safety of the plant CRITERIA FOR NEEDS IMPROVEMENT EVALUATION

1. One or more non-critical elements/ steps evaluated as UNSAT which indicate the need for remediation.

2. Any relevant Management Expectation/Standard missed a majority of the opportunities.

ADMINISTRATIVE REQUIREMENTS Any performance deficiencies resulting in an UNSAT or NEEDS IMPROVEMENT evaluation shall be documented on the JPM comment sheet.

Documentation for Satisfactory evaluations need onlY consist of the cover sheet and any applicable comment sheet(s) provided that a Master Copy of the JPM is on file or captured.

Documentation for UNSAT evaluations shall consist of the entire, as administered JPM, with associated comment sheets.

Documentation for NEEDS IMPROVEMENT evaluations need only consist of the cover sheet and the associated comment sheet(s) describing the operator deficiencies noted, provided that a Master Copy of the JPM is on file or captured and the deficiencies are involving only management expectations. Otherwise, the entire JPM shall be retained.

PILGRIM 2011 NRC JPM S-2 -7

PILGRIM 2011 NRC JPM 8-2 JPM COMMENT SHEET REQUIREMENTS:

Any operator deficiencies resulting in an UNSAT or NEEDS IMPROVEMENT evaluation shall be documented.

Any follow-up questions asked and the operator's response must be documented.

Any operator deficiencies which, in themselves, would not result in an UN8AT evaluation of this JPM but may, when coupled with performance on other JPMs, result in an OVERALL FAILING evaluation for the JPM exam should also be documented below.

Any other comments. positive or negative, that the evaluator determines is worth noting.

COMMENTS:

PILGRIM 2011 NRC JPM 8-2 -8

PILGRIM 2011 NRC JPM S-2 INITIAL CONDITIONS:

The reactor has scrammed on low level following a loss of feed.

RCIC has tripped.

HPCI is presently operating in pressure control mode and has been manually initiated in accordance with PNPS 2.2.21.5.

Current RPV level is approximately -20 inches."

INITIATING CUE:

State the following:

"[Operator's name], swap HPCI from pressure control to injection in accordance with procedure 5.3.35.1, Attachment 23. Restore and maintain level -20" to +45". Inform me when HPCI is aligned for injection and maintaining RPV level -20" to +45".

PILGRIM 2011 NRC JPM S-2 -9

PILGRIM 2011 NRC JPM s-a NUCLEAR PLANT OPERATOR JOB PERFORMANCE MEASURE (RO/SRO)

TITLE: RE-OPEN AN MSIV FOLLOWING CLOSURE OPERATOR: DATE: ___________________

EVALUATOR: EVALUATOR SIGNATURE:

CRITICAL TIME FRAME: Required Time (min): N/A Actual Time (min): N/A PERFORMANCE TIME: Average Time (min): 15 Actual Time (min):

JPM RESULTS*: SAT UNSAT NEEDS IMPROVEMENT (Circle one) *Refer to Grading Instructions at end of JPM COMMENT SHEET ATTACHED: Yes / No (circle one) (Required for Unsat, Needs Improvement or Follow-Up Questions)

SYNOPSIS: The plant is at 50% power. The "D" outboard MSIV inadvertently closed early on the previous shift due to a broken airline which has since been repaired.

TASK MSIVs shall be opened without causing inadvertent actuations and shall be STANDARD: accomplished in accordance with all system precautions and limitations. 2.2.92 shall be followed without failure of any critical elements.

EVALUATION METHOD: EVALUATION LOCATION:

X Perform Plant Simulate X Simulator Control Room Prepared: Date:

Reviewed: Date:

Approved: Date:

Superintendent, Operations Training (or Designee)

PILGRIM 2011 NRC JPM S-3 -1

PILGRIM 201'1 NRC JPM 8<1 REVISION LOG Revision Number: 0 Date Originated: 8/10/2010 Pages Affected: All

Description:

Revised for NRC exam and faulted JPM PILGRIM 2011 NRC JPM 8-3 -2

PILGRIM 201"1 NRC JPM S-3 TASK

Title:

Task Number K&ASYSTEM: K&ARATING:

RESPOND TO MSIV CLOSURE 200-05-01-003 239001 A2.03 4.0/

4.2 REFERENCES

Procedure 2.2.92, Revision 52 SIMULATOR CONDITIONS:

1. Exam IC: 37, Reactor power -50%

2. Initialize the simulator.

3. Close Main Steam Line 0 Outboard and Inboard MSIVs.

4. Complete PNPS 2.2.92 section 7.2 Steps [1] thru [4]

a) MO-220-1 and MO-220-2 closed b) Open MO-220-3 and jog open MO-220-4 to establish and maintain a Main Steam Line low point drain temperature (TE-3604) as close to BUT NOT GREATER THAN 520°F.

GENERAL TOOLS AND EQUIPMENT:

1. N/A CRITICAL ELEMENTS:

Critical elements are shaded in gray within the body of this document.

OPERATOR BRIEF:

1. State" the following paragraph IF this is the first performance in this setting:

a) "All actions associated with this job performance measure are to be performed. You will be provided access to any tools or equipment you determine necessary to perform the task. When a second checker is called for, the evaluator will perform the role of second checker and will always be in agreement with your actions. Before you start, the evaluator will state the task conditions and answer any questions, then provide a cue to begin".

2. Always state the following two paragraphs:

a) "The title of this "IPM is: RE-OPEN AN MSIV FOLLOWING CLOSURE b) "The task conditions are as follows:

i) The plant is at 50% power ii) The "0" outboard MSIV inadvertently closed early on the previous shift due to a broken airline which has since been repaired

3. Solicit and answer any questions the operator may have.

INITIATING CUE:

"[State the operator's name] reopen the outboard and inboard "0" MSIVs lAW PNPS 2.2.92 Section 7.2 beginning at step [5]."

PILGRIM 2011 NRC JPM S-3 -3

PILGRIM 2011 NRC JPM S-3 PERFORMANCE:

Notes START TIME:

1. Procedure Step: Verify drainage of the Main Steam Line through MO-220-3 (MAIN STEAM LINE DRN VLV) and MO-220-4 (MAIN STEAM LlI\JE DRN TO CONDR) according to the table below:

15 mi nute~

> Ih minutes ::; 1101.,

Standard Operator determines that the limitations of the table have been met.

Cue As the CRS inform the Operator that MO-220-3 and MO-220-4 have been I . open for 30 minutes.

. ---t---------:--------1 Notes Initiating cue states the MSIV closed on the previous shift. Operator determines that the limitations of the table have been met. MSIV closed on the previous shift (less than 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ago) and MO-220-3 and MO-220-4 have been open for greater than 10 minutes.

Results SAT c===J UNSAT c===J

2. ~.Step: WHEN the above time limitations are satisfied, THEN CLOSE the Main Steam Line drain valve, MO-220-4, MAIN STEAM LINE DRN TO CONDR

.: ;'\.

Stadatd Operator CLOSES MO-220-4 Cue Notes Operator observes green indicating lights on and red lights off for MO-220-4 on the PCIS status board or apron section of C904.

R_ults SAT UNSAT I c===J c===J PILGRIM 2011 NRC JPM S-3 -4

PILGRIM 2011 NRC JPM S-3

3. PJVCIdure'atep: OPEN the following valves:

MO-220*1, MSIV DRNS INBD ISOL VLV

MO*220*2, MSIV DRNS OUTBD ISOL VLV

, StanGarei Operator OPENS MO*220*1 and MO-220-2.

... Cue Notes Operator observes red indicating lights on and green lights off for MO-220-1, and MO-220-2 on the PCIS status board or apron section of C904.

Results SAT D UNSAT D

4. . , . ..... ltep: SLOWLY JOG OPEN, until FULLY OPEN, MO-220-4, (MAIN STEAM LINE DRN TO CONDR).

(1) DRAIN the Main Steam Une for 10 minutes.

\

Standard Operator Jogs MO-22G-4 FULL OPEN and marks time .

Cue Wait until annunciator C905R, Ea, MAIN STM LINE TO TURBINE STM FLOW MISMATCH. alarms (-30 sees after MO-220-4 is opened) After operator confirms alarm inform Operator that 10 minutes has elapsed.

Notes Operator observes red light on and green light off for MO-220-4.

R.ulta SAT I I UNSAT D

15. Procedure Step: Annunciator 905R, E-8, MAIN STM LINE TO TURBINE STM FLOW MISMATCH may alarm.

1. Confirm Alarm a) Compare main steam flow (PR/FR-640-27, RX WIDE RANGE PRESSURE RX STEAM FLOW) and Turbine steam flow (PR/FR/LR-640-28, RX STM FLOW/NARROW RANGE WTR LVL RX NARROW RANGE PRESSURE) on PanelC905 Standard Operator determines that this is an expected alarm because of the steam flow being diverted to the condenser by the open steam line drain valve.

Cue After operator confirms alarm inform Operator that 10 minutes has elapsed.

Notes I

i I Results SAT D UNSAT D

PILGRIM 2011 NRC JPM S-3 -5

PILGRIM 2011 NRC JPM S<~

6. P....U... Step: OPEN all outboard MSIV's that are currently closed:

I

AO-203-2A, Main Steam Line A Outboard Isolation Valve

AO-203-2B, Main Steam Line B Outboard Isolation Valve

AO-203-2C, Main Steam Line C Outboard Isolation Valve

AO-203-20, Main Steam Line 0 Outboard Isolation Valve i i

Standard Operator selects and OPENS AO-203-20. i Cue Notes Operator observes green indicating light off, red indicating light on.

D i

I Results SAT D UNSAT 7.

I Procedure Step: Open MO-220-3. (MAIN STEAM LINE DRN VLV).

Standard Operator locates and verifies open MO-220-3.

NOTE The following cue should be given for time compression to permit continuing the task in atimely manner.

Cue AFTER MO-220-3 is OPEN, STATE that "10 minutes have elapsed".

Notes Operator observes GREEN indicating light OFF, RED indicating light LIT.

Results I SAT UNSAT D D I

~p~8tep:

8. OPEN, one at a time, all inboard MSIVs that are currently closed: I

AO-203-1 A, Inboard Main Steam Isolation Valve A )

AO-203-1 B, Inboard Main Steam Isolation Valve B

AO-203-1C, Inboard Main Steam Isolation Valve C

AO-203-1 D, Inboard Main Steam Isolation Valve D stindard Operator selects and OPENS AO-203-10.

Cue Notel Operator observes GREEN indicating light OFF, RED indicating light LIT.

Resutts

SAT i D UNSAT D

PILGRIM 2011 NRC JPM S-3 - 6

PILGRIM 201 '1 NRC

JPM S-~I

9. Procedure Step: CLOSE the following lives: I (1) MO-220-4 (MAIN STEAM LINE DRN TO CONDR)

(2) MO-220-2 (MSIV DRNS OUTBD ISOL VLV)

(3) MO-220-1 (MSIV DRNS INBD ISOL VLV)

Standard Operator locates and closes MO-220-4, MO-220-2 and MO-220-1 .

Cue Notes Operator observes GREEN indicating lights LIT, RED indicating lights OFF.

i Results SAT UNSAT I I I I I I This JPM is complete.

STOP TIME:

PILGRIM 2011 NRC JPM S-3 7

PILGRIM 2011 t\IRC

JPM S-3 JPM GRADING INSTRUCTIONS CRITERIA FOR SATISFACTORY EVALUATION

1. 100% of critical elements/steps identified in the ,JPM successfully completed.