Text

Draft - Section a Operating Exam (Folder 2)
	ML070820563
Person / Time
Site:	Nine Mile Point
Issue date:	10/24/2006
From:	Shortell T; Constellation Energy Group
To:	Caruso J; Operations Branch I
Shared Package
ML060800077	List: IR 05000220/2007301; ML070610189; ML070820469; ML070820475; ML070820484; ML070820520; ML070820529; ML070820535; ML070820542; ML070820551; ML070820557; ML070820563; ML070820570; ML070820573; ML070871016; ML071030148; ML071340128;
References
	Download: ML070820563 (69)
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ES-301, Rev. 9 Administrative Topics Outline Form ES-301-1 Facility: Nine Mile Point 1 Examination Level: RO Date of Examination:

Operating Test Number:

NA December 11, 2006 Administrative Topic (see Note) Conduct of Operations Plant parameter Verification RO ADMIN 1 Conduct of Operations Configuration Control RO ADMIN 2 Equipment Control Use of Electrical Prints RO ADMIN 3 Radiation Control Radiation Hazards RO ADMIN 4 Type Code* D N N M, P NRC 2004 Describe activity to be performed Perform N1-ST-DO, Daily Checks (Partial)

Record control room instrument readings for recirc loop temperatures, reactor water level instruments and hotwell level. With tech spec readings out of spec for RPV water level and hotwell level, identify impact on Tech Spec related equipment.

Readings are taken in the simulator and entered into the applicable sections of the Daily Checks.

2.1 .I8 (2.9) Ability to make accurate / clear and concise logs I records I status boards I and reports. GAP-OPS-01; 3.10, N1-ST-DO section 6.0, 7.0 and 8.0 Determine Plant Impact of Mispositioned Liquid Poison Components Evaluate system lineup, determine both Liquid Poison Pumps are not available to inject. Identify the Tech Spec impact. 2.1 .I 1 (3.0) Knowledge of less than one hour technical specifications for systems. DWG C-18019-C; N1-OP-12, Tech Spec 3.1.2 RPS Logic Operation with EOP-3.1 RPS Jumpers Installed Identify and locate electrical drawings related to RPS circuits.

Use the drawings to describe the effect of installing RPS jumpers on how scram signal is reset prior to initiating another manual scram, with the jumpers installed under failure to scram conditions. (Perform in simulator and supply with copies for candidate to mark-up).

2.1 24 (2.8) Ability to obtain and interpret station electrical and mechanical drawings.

N1-EOP-3.1; Drawincl C-19859-C SH 4 and 7 Radiological Requirements Related Entry Into High Radiation Areas Given radiological conditions and a survey map related to an area to be inspected, ensure the appropriate radiological aspects of the job are met prior to performance of the inspection. 2.3.10 (2.9) Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure.

GAP-RPP-02; 3.1, 3,3.

GAP-RPP-08; 3.2, 3.3 N0TE:All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

Type Codes & Criteria (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs, ~ 4 for SROs & RO retakes) (N)ew or (M)odified from bank (- 1) (P)revtous 2 exams ( 1, randomly selected) 1 012412006 10:29:08 AM 1of1 2006 Unit 1 NRC RO Admin Outline Submittal Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE Title: Perform N1 -ST-DO DAILY CHECKS (Partial)

Task Number: Amrovals: Genpral Supervi6or Date Operations Training (Designee)

Revision:

NRC 2006 NA EXAM SECURITY I General Supervisor Date Operations (Designee) NA EXAM SECURITY I Configuration Control Date Performer: (ROISRO) TrainerIEvaluator: Evaluation Method:

X Perform Simulate Evaluation Location: Plant X Simulator or other location Expected Completion Time: 20 min Time Critical Task: NO Alternate Path Task:

NO Start Time: Stop Time: Completion Time: JPM Overall Rating: Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment.

Comments:

Evaluator Signature:

Date: NRC RO ADMIN JPM 1 October 2006 Recommended Start Location: (Completion time based on the start location)

If actual readings are to be taken, Simulator must be setup and used, otherwise perform in other designated area. Simulator Set-up:

IC-238 contains setup conditions for Admin JPMs

1. TURN OFF PI MONITOR. JPM readings are taken with simulator in FREEZE. Establish 70% reactor power, 40 mlb/hr total recirc flow, align Feedwater Level Column to 72, and override reactor water level and hotwell level instruments as necessary to read those indicated in the Attachment. Override both hotwell indication to 55 inches and activate crywolf for alarms H2-2-7 and 3-7 for low level, Directions to the Instructor/Evaluator: Prior to performance of this JPM, obtain SM / CSO general permission to open equipment cabinets and inspection covers. If opening the equipment cabinet or inspection cover will affect Tech. Spec. Operability, operational status, or the effects are unknown, obtain specific SM I CSO permission.

Directions to Operators: Read Before Every JPM Performance: For the performance of this JPM, I will function as the SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

With the exception of accessing panels, NO plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues. Read Before Each Evaluated JPM Performance: This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional I concurrent verification will not be provided; therefore, it should not be requested. Read Before Each Traininq JPM Performance: During this Training JPM, the use of applicable methods of verification and checking are expected. Therefore, either another individual or I will act as the independent verifier or peer checker. Notes to Instructor

/ Evaluator:

1. Critical steps are identified in grading areas PasslFail.

All steps are sequenced critical unless denoted by a "e". 2. During Evaluated JPM:

0 3. During Training JPM: Self checking shall be demonstrated. Self checking shall be demonstrated. Peer checking shall be demonstrated. NRC RO ADMlN JPM 1 October 2006

References:

1. GAP-OPS-01; 3.10. 2. N1-ST-DO; 6.0, 7.0 and 8.0. 3. 2.1 .I8 (2.9) Ability to make accurate / clear and concise logs

/ records / status boards

/ and reports.

Tools and Equipment:

1. None Task Standard:

Control room readings are taken. Out of spec readings are identified to SRO and inoperable equipment is identified by the candidate.

Initial Conditions:

1. 2. 3. 4. The plant is operating at 75% power. Surveillance test N1 -ST-DO, DAILY CHECKS, is in progress ALL computer point readings are consistent with control room panel instrument readings.

Ask the operator for any questions.

Initiating cue: "(Operator's name), obtain the instrument readings needed from control room panels to complete N1 -ST-DO, DAILY CHECKS Attachment I sections 6.0, 7.0 and 8.0 only. When completed, report findings and provide completed sections to SRO". 1. Provide repeat back of initiating cue. Evaluator A ckn o wle dge rep eat back providing correction if necessary RECORD START TIME 1. 2. 3. *Obtain a copy of the reference procedure and review/utilize the correct section. *Records section 6.0 Reactor Recirc Pump Inlet Temperature readings Compares reading and determines readings within 15°F Proper communications used for repeat back (GAP-OPS-01 ) N-ST-DO obtained. - Section 6.0, 7.0 and 8.0 referenced. NOTE: Completed N1-ST-DO is provided as an Attachment 2 to this JPM. Records Reactor Recirc Pump Inlet Temperature readings. Compares reading and determines readings within 15°F of each other.

Checks YES block in Section 6.0, indicating the maximum difference in loop temperatures is < 15°F. Sat/Unsat SatlUnsat Sa tlU nsat PasslFail PasslFail NRC RO ADMIN JPM 1 October 2006

4. .Records section 7.0 readings.

5. .Compares YARWAY Chll - Ch12 (RPS Level Column) instrument readings to guide values. 6. .Performs GEMAC Chll - Ch12 variance check per Section 7.1. 7. .Records section 8.0 Condensate readings

8. Provides completed sections to SRO. Informs of out of spec readings. Recorded Section 7.0 "LOW-Low Level alarm" and "Feedwater Level Column selected to" checks agree with Attachment 1 without error. Recorded Section 7.0 instrument readings agree with Attachment 1 within k 1 inch. Record Total Recirc Flow per step 7.1.2 for GEMAC variance check. Determines YARWAY (RPS Level Column) instrument readings differ by 5" which is above the guide value of 4". Determines YARWAY (RPS Level Column) instruments OPERABLE. Indicates an ACR is required to have the calibration checked. Determines GEMAC variance is 6" Compares GEMAC variance to total recirc flow and determines on line between ALERT RANGE and INOP. Determines that GEMAC I1 or GEMAC 12 must be declared inoperable.

Reports out of specification readings to SRO. Records Condensate readings Determines Hotwell level is below 57 inches (Tech Spec Minimum)

Informs SRO Hotwell level is below 57 inches (Tech Spec Minimum).

<Ref 2> is TS 3.1.8, HPCl is inoperable.

SRO informed of out of spec readings.

PasslFail PasslFail Sat/Unsat Sat/Unsat PasslFail Sat/Unsat SatlUnsat SatlUnsat PasslFail PasslFail Sat/Unsat PasslFail PasslFail PasslFail Sat/Unsat End of JPM TERMINATING CUE: Control room readings are taken. Out of spec readings are identified to SRO and inoperable equipment is identified by the candidate.

RECORD STOP TIME NRC RO ADMIN JPM 1 October 2006 Initial Conditions:

1. The plant is operating at 75% power. 2. Surveillance test N1-ST-DO, DAILY CHECKS, is in progress 3. ALL computer point readings are consistent with control room panel

4. Ask the operator for any questions. instrument readings.

Initiating cue: "(Operator's name), obtain the instrument readings needed from control room panels to complete N1 -ST-DO, DAILY CHECKS Attachment 1 sections 6.0, 7.0 and 8.0 only. When completed, report findings and provide completed sections to SRO". NRC RO ADMlN JPM 1 October 2006 I Setup Attachment Override Value Settings Panel Meter Meter Reading Obtained K-Panel Flange Level Indicator (K Panel: ta ~ig~~ of ~$-~$~ Reactor Vessel Level Recorder (F Panel: 36-SSJ I 70'5 1 k:hes 1 E-Panel Vessel Level Indicator (E Panel iD59~) ~~ ~ ~ None Below -3 72.5 74 ft inches 1 75 1 k:hes K-Panel Vessel Level Indicator (K Panel: 36-96 ID5 Wide Range Level Indicator (FPane/: 36-94) I Ch 11 7.2 6 ft Ch 12 11 12 GEMAC Level Column (F ane el: 36-76A, I 77.5 I 69.5 1 79-80; 73 1 ~6~~~A} ~ RPS Level Column <Ref 1 > (F Panel: 36-76 ~~ 1 F NRC RO ADMIN JPM 1 October 2006

- ATTACHMENT 1 (Cont) -- ANSWER KEY. DO NOT PROVIDE TO APPLICANT Reactor Recirc Pump Inlet Temperature RRP 11 Inlet Temp RRP 12 Inlet Temp RRP 13 Inlet Temp RRP 14 Inlet Temp RRP 15 Inlet Temp Maximum difference in loop temperatures 15°F 7.0 Control Room Reactor Water Level Checks Low-Low Level Alarms IF YES, provide reason in Remarks Feedwater Level Column selected to (E Pane!] 520 OF 525 OF 520 OF 530 OF 520 OF YES No OYES BNO El11 12 I E-Panel Vessel Level Indicator

(*Panel) I 73 I inches I I K-Panel Vessel Level Indicator (K Panel: 36-96) I 76 I inches I I c-3 vet- 1 K-Panel Flange Level Indicator (K Panel: to ~ig~~ of I Reactor Vessel Level Recorder (F Pane/: 36-98) I 74 1 inches I I Wide Range Level Indicator (f Pane/: 36-94] I 6 I feet I If reading difference is greater than the guide valve, review previous readings for the instrument(s). If a single reading is the cause for the recorded value being greater than the guide value, verify that reading.

If reading difference is still greater than guide value, consider the indicator OPERABLE and generate an ACR to have the calibration checked. If reading difference is grossly greater than guide value, consider the indicator INOPERABLE, enter applicable Tech Spec action and generate an ACR. See Section 7.1 ** If the difference between Yarway indicators Ll-36-09 and LI-36-10 is 6" or greater, *** THEN declare the following instruments inoperable and initiate the required Technical Specification actions (ESA for DER 1-2001-3027):

LT-36-03C, LT-36-03D LT-36-04C, LT-36-04D LT-36-216, LT-36-21 D NRC RO ADMlN JPM 1 October 2006 ATTACHMENT 1 (Cont) ANSWER KEY.

DO NOT PROVIDE TO APPLICANT 7.1 GEMAC Variance Check 7.1 .I Calculate Variance Between Ch 12 and Ch 11 GEMAC Level Recorders.

73 6 / / - Ch 12 Ch 11 Variance (in.) Ind. Verif 7.1.2 Record Total Recirc Flow 40 MllblHr {E init / date 7.1.3 Verify GEMAC 1111 2 Variance as a function of Total Recirc Flow is in the Acceptable Range as determined in the Graph below. (Note, ignore negative sign, if any.) 0 Yes (Sat) 4 No (Unsat), DER Required init / date If results are in ALERT range, generate DER for Engineering Evaluation.

If results are in INOP range, declare GEMAC 11 and/or 12 INOP. GEMAC LEVEL COLUMN 11 / 12 VARIANCE 10 9 8 v) w7 I 0 F6 55 -14 x3 n > 0, crr - 2 1 0 0 5 10 15 20 25 30 35 40 45 50 55 60 65 70 Total Recirc Flow wlb/Hr) NRC RO ADMIN JPM 1 October 2006

Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE Title: Determine Plant Impact of Mispositioned Liquid Poison Components Revision: NRC 2006 Task Number:

Ap prova Is : NA EXAM SECURITY I Operations (Designee)

G e n $a I S u pe rvi sqfr Date General Supervisor Date Operations Training (Designee)

/,&3b!mc.

NA EXAM SECURITY I Configuration Control Date Performer: (RO) TrainerIEvaluator: Evaluation Method:

X Perform Simulate Eva I ua t ion Location : Plant X Simulator or other location Expected Completion Time:

15 min Time Critical Task: NO Alternate Path Task: NO Start Time: Stop Time: Completion Time:

JPM Overall Rating: Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment. Comments:

Evaluators Signature:

Date: NRC RO ADMIN JPM 2 October 2006 Simulator or other designated location with prints and procedures available Simulator Set-up (if required):

NA Directions to the Instructor/Evaluator: Prior to performance of this JPM, obtain SM / CSO general permission to open equipment cabinets and inspection covers. If opening the equipment cabinet or inspection cover will affect Tech. Spec. Operability, operational status, or the effects are unknown, obtain specific SM / CSO permission. Directions to Operators: Read Before Every JPM Performance:

For the performance of this JPM, I will function as the SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

With the exception of accessing panels, NO plant equipment will be physically manipulated.

Repositioning of devices will be simulated by discussion and acknowledged by my cues. Read Before Each Evaluated JPM Performance: This evaluated JPM is a measure of your ability to perform this task independently.

The Control Room Supervisor has determined that a verifier is not available and that additional

/ concurrent verification will not be provided; therefore, it should not be requested. Read Before Each Traininq JPM Performance:

During this Training JPM, the use of applicable methods of verification and checking are expected.

Therefore, either another individual or I will act as the independent verifier or peer checker.

Notes to Instructor

/ Evaluator: 1. Critical steps are identified in grading areas Pass/Fail.

All steps are sequenced critical unless denoted by a 0. 2. During Evaluated JPM:

3. During Training JPM: Self checking shall be demonstrated.

Self checking shall be demonstrated. Peer checking shall be demonstrated.

References:

1. P&ID C-18019-C

2. N1-OP-I 2, Attchment2

3. Tech Spec 3.1.2 Tools and Equipment:

NRC RO ADMIN JPM 2 October 2006

1. None Task Standard: Determines both Liquid Poison subsystems are inoperable and one must be restored within one hour or an orderly shutdown is required. Initial Conditions:

1. The plant is in operating at 100% power.

2. Red clearance is being applied to Liquid Poison Pump 12 for corrective maintenance on the pump. 3. You are the Independent Verifier for the red clearance. 4. The first clearance tag is found on Power Board 17B Breaker 42-38 and the breaker is disconnected and open.

5. The next clearance tag is found on valve 41-07 and the valve is unlocked and closed. Initiating cue:

"(Operator's name), determine plant impact of this configuration." Performance Steps Standard Grade

1. Provide repeat back of initiating cue. Evaluator Acknowledge repeat back providing correction if necessary. RECORD START TIME 2. 2. 3. 4. 5. Consults reference documents to determine effect of the given component lineup. Identifies LP Pump 12 is unable to inject (inoperable), with PI3 178 42-38 open.

Identifies LP Pump 11 is unable to inject (inoperable), with 41 -07 closed. Identifies tag applied to incorrect component.

Informs Control Room per GAP-OPS-01.

Determines Tech Spec LCO conditions Proper communications used for repeat back (GAP-OPS-O1/

CNG-HU-1 .Ol-1001)

Refers to any of the following documents to determine function of PB 17B breaker 42-38 and 41-07 N1-OP-12 P & ID C-18019-C Any other document that indicated power supply for LP Pump 12 and suction valve for LP Pump 11 are the affected com ponen ts Determines that with PB 17B BKR 42- 38 open and disconnected, LP Pump 12 is deenergized and inoperable.

Determines that with 41-07 closed LP Pump 11 is inoperable because of loss of suction path.

Determines that 41-1 1 should have been closed. Notifies CRS of improperly positioned com pone n ts and incorrect application of red clearance tag. Determines that these conditions SatlUnsat Sat/Unsat Pass/Fail Pass/Fail Sat/Unsat Sat/Unsat Sat/Unsat NRC RO ADMIN JPM 2 October 2006 I Performance Steps Standard for liquid Poison are exceeded.

6. Refers to LCO 3.1.2 result in Tech Spec entry for the Liquid Poison system.

Grade o Identifies LCO 3.1.2 Specification

b. Sat/Unsat applies because the redundant component is also inoperable.

If a single pump was inoperable 7 days would be allowed to restore the inop Pump Since both are inoperable, specification e applies and an orderly shutdown must be initiated within one hour. 7. Determines that one subsystem must be Identifies the requirement to restore Pass/Fail restored to operable.

one of the redundant components to OPERABLE within one hour or an orderly shutdown is required End of JPM Terminating Cue: restored within one hour or an orderly shutdown is required. Determines both Liquid Poison subsystems are inoperable and one must be RECORD STOP TIME NRC RO ADMIN JPM 2 October 2006

a. Com m u nications

b. Verification of Actions Per CNG-HU-1.01-1001 Per GAP-OPS-0 1 Per CNG-HU-1.01-1001 Per GAP-OPS-01

c. Procedural CompliancelPlacekeeping Per CNG-HU-1.01-1001 Per N IP-PRO-01 Per GAP-OPS-01

d. Safety Compliance Per N I P-OSH-01 Per Personnel Safety Manual

e. Radiation Protection Compliance Per GAP-RPP-01 Per GAP-RPP-02 Sat/Unsat SatlUnsat SatlUnsat Sat/Unsat Sat/Unsat Overall Work Practice Competency Result PasslFail NOTE: 1. UNSAT in any competency area requires oral remediation of unsat area. 2. Fail in Overall Work Practice Competency Results requires review and evaluation of work practices using the Work Practices JPM (U1 using 01-REQ-SJE-WPJ-1-00 and U2 using 02-REQ-SJE-WPJ-2-00).

NRC RO ADMIN JPM 2 October 2006 InGI Conditions:

1. 2. 3. 4. 5. The plant is operating at 100% power. Red clearance is being applied to LP PUMP 12 for corrective maintenance on the pump.

You are the Independent Verifier for the red clearance.

The first clearance tag is found on PB 17B Breaker 42-38 and the breaker is disconnected and open. The next clearance tag is found on valve 41-07 and the valve is closed. Initiating cue: "(Operator's name), determine plant impact of this configuration."

NRC RO ADMIN JPM 2 October 2006 JPM 2 Scorecard For Applicant Use - Determine plant impact of this configuration. Impact of Configuration on c System Impact on plant operation NRC RO ADMIN JPM 2 October 2006 Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE Title: N1 -EOP-3.1 RPS Jumper Operation Electrical Print Reading Revision:

NRC 2006 Task Number: N/A NA EXAMINATION SECURITY General Supervisor Operations Training (Designee) Operations (Designee)

NA EXAMINATION SECURITY Configuration Control Date Performer: (RO) Trai ne r/Eval ua tor: Evaluation Method:

X Perform Simulate Eva1 ua t ion Location : Plant X Simulator or other location Expected Completion Time: 20 min Time Critical Task: NO Alternate Path Task:

NO Start Time: Stop Time: Completion Time: JPM Overall Rating:

Pass Fail NOTE: A JPM overall rating of fail shall be given if grade of unsat or individual competency area unsat requires a comment. critical step is graded as fail. Any Comments: Evaluator Signature: Date: NRC RO ADMIN JPM 3 Draft October 2006 Recommended Start Location: (Completion time based on the start location) For NRC Exam 2006, This Admin JPM is performed in Simulator.

Simulator Set-up: None Directions to the Instructor/Evaluator:

Directions to Operators: Read Before Every JPM Performance: For the performance of this JPM, I will function as the SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

Read Before Each Evaluated JPM Performance: This evaluated JPM is a measure of your ability to perform this task independently.

The Control Room Supervisor has determined that a verifier is not available and that additional

/ concurrent verification will not be provided; therefore it should not be requested. Read Before Each Training JPM Performance:

During this Training JPM, applicable methods of verification are expected to be used. Therefore, either another individual or I will act as the additional

/ concurrent verifier.

Notes to Instructor I Evaluator:

1. 2. During Evaluated JPM:

3. During Training JPM:

Critical steps are identified as PasslFail.

All steps are sequenced critical unless denoted by a "0". 0 Self-verification shall be demonstrated.

0 Self-verification shall be demonstrated.

0 No other verification shall be demonstrated.

References:

1. Drawing C-19859-C Sheet 4 and 7 2. N1-EOP-3.1, Alternate Control Rod Insertion

3. K/A 2.1.24 (2.8) Ability to obtain and interpret station electrical and mechanical drawings. Tools and Equipment:

1. None. Task Standard: Relays and contacts used to install RPS jumpers and reset scram signal are identified on station electrical drawings and operation is explained.

NRC RO ADMIN JPM 3 Draft October 2006 Initial Conditions:

1. The plant is experiencing a failure to scram. 2. N1-EOP-3 has been entered. 3. EOP Director directs execution of EOP-3.1.

4. Repeated manual scrams will be attempted.

5. Ask the operator for any questions. Initiating cue: "(Operator's name), Using station procedures and drawings, explain the effect of installing the RPS jumpers for RPS Channel 12 on RPS Channel 12 circuits, including identifying the signals defeated when jumpers are installed AND electrical component (relays, contacts and switches) operation necessary to reset the RPS Channel 12 scram logic."

1. Provide repeat back of initiating cue. Evaluator Acknowledge repeat back providing correction if necessary RECORD START TIME 1. Obtain a copy of the necessary procedures and drawings 2. Using C-I 9859-C Sheet 7, locates trip circuits and jumpers. 3. Using C-19859-C Sheet 7, identifies the signals defeated when jumpers are installed. Proper communications used for repeat back (GAP-OPS-01)

Sat/Unsat Obtains the following documents, as needed: N1-EOP-3.1 Sat/Unsat/NA Drawing Index, if needed Sat/Unsat/NA 0 Drawing C-I 9859-C Sheet 7 PasslFail Locates SCRAM BYPASS jumper PasslFail (EOP jumper 12) at drawing coordinate A-I to A-5, in REACTOR TRIP #I circuit. Locates SCRAM BYPASS jumper (EOP jumper 13) at drawing coordinate B-1 to B-5, in REACTOR TRIP #2 circuit. PasslFail Identifies that ALL AUTOMATIC PasslFail scram signal relay trip contacts are bypassed when jumper is installed. NOTE: The manual scram circuit is not bypassed by the jumpers. NRC RO ADMIN JPM 3 Draft October 2006

4. Using C-19859-C Sheet 7, describes electrical component operation necessary to reset the scram. Indicates when jumper is installed in REACTOR TRIP

I circuit, relay 12K51A (coordinate B-5) energizes and closes the following contacts:

0 PasslFail 12K51A L1-TI for GROUP 1 (coordinate D-2) 12K51A L2-T2 for GROUP 2 (coordinate E-2) 12K51A L3-T3 for GROUP 3 (coordinate F-2) 12K51A L4-T4 for GROUP 4 (coordinate G-2) 12K51A 7-8 for Backup Scram circuitry (coordinate H-2) 0 0 0 0 Indicates when jumper is installed in REACTOR TRIP

2 circuit, relay 12K52A (coordinate C-5) energizes and closes the following contacts:

0 PasslFail 12K52A L1-TI for GROUP 1 (coordinate D-2) 12K52A L2-T2 for GROUP 2 (coordinate E-2) 12K52A L3-T3 for GROUP 3 (coordinate F-2) 12K52A L4-T4 for GROUP 4 (coordinate G-2) 12K52A 7-8 for Backup Scram circuitry (coordinate H-2) 0 0 0 Indicates that depressing switch 1 S3, RESET REACTOR TRIP (SCRAM) pushbutton (coordinate C- 4), closes its 1 S3 7-8 contact and energizes relay 12K53 (coordinate C-5) (while reset button is depressed).

SaVUnsat NRC RO ADMIN JPM 3 Draft October 2006 Indicates that Relay 12K53 Sat/Unsat energizing closes its 7-8 contact (coordinate D-4) and energizes relay 12K55 and 12K56 (coordinate D-5) in REACTOR MANUAL SCRAM circuit Indicates that Relay 12K55 energizing and closes the following contacts:

0 12K55 L1-TI for GROUP 1 (coordinate D-2) 12K55 L2-T2 for GROUP 2 (coordinate E-2) 12K55 L3-T3 for GROUP 3 (coordinate F-2) 12K55 L4-T4 for GROUP 4 (coordinate G-2) 12K55 7-8 for Backup Scram circuitry (coordinate H-2) 0 0 0 PasslFail Indicates that Relay 12K56 provides SatlUnsat a seal-in to keep 12K55 energized when 12K53 drops out after the scram reset pushbutton is released. Indicates that when all three contacts PasslFail in the four GROUP 1 through 4 circuits for 12K51A, 12K52A and 12K55 are closed the scram is reset (for channel 12). Four white lights on F and M panels are ON and the scram pilot solenoids are energized for RPS Channel 12.

10. Reports JPM complete Reports JPM complete Sat/Unsat NRC RO ADMIN JPM 3 Draft October 2006 TERMINATING CUE: Relays and contacts used to install RPS jumpers and reset scram signal are identified on station electrical drawings and operation is explained. RECORD STOP TIME October 2006 NRC RO ADMIN JPM 3 Draft Initial Conditions:

1. The plant is experiencing a failure to scram. 2. N1-EOP-3 has been entered. 3. EOP Director directs execution of EOP-3.1.

4. Repeated manual scrams will be attempted.

5. Ask the operator for any questions.

Initiating cue: "(Operator's name), Using station procedures and drawings, explain the effect of installing the RPS jumpers for RPS Channel 12 on RPS Channel 12 circuits, including identifying the signals defeated when jumpers are installed AND electrical component operation necessary to reset the RPS Channel 12 scram logic." NRC RO ADMIN JPM 3 Draft October 2006

Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE Title: Radiological Requirements Related to Entry Into Revision: NRC 2006 High Radiation Areas Task Number: N/A NA EXAMINATION SECURITY

-- Genefal Supervisal/

Datd General Supervisor Date Operations Training (Designee) Operations (Designee)

NA EXAMINATION SECURITY Configuration Control Date Performer: (RO)

Trainer/Evaluator:

Evaluation Method: X Perform Simulate Evaluation Location: Plant X Simulator or other location Expected Completion Time: 10 minutes Time Critical Task: NO Alternate Path Task:

NO Start Time: Stop Time:

Completion Time: JPM Overall Rating:

Pass Fail NOTE: A JPM overall rating of fail shall be given if unsat or individual competency area unsat requires a comment.

critical step is graded as fail. Any grade of Comments: Evaluator Signature: Date:

NRC RO ADMIN JPM 4 October 2006 Recommended Start Location: (Completion time based on the start location)

Simulator or other designated location. Simulator Set-up:

N /A Directions to the InstructodEvaluator:

RWPs and survey maps are to be provided.

Directions to Operators: Read Before Everv JPM Performance: For the performance of this JPM, I will function as the SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

Read Before Each Evaluated JPM Performance:

This evaluated JPM is a measure of your ability to perform this task independently.

The Control Room Supervisor has determined that a verifier is not available and that additional I concurrent verification will not be provided; therefore, it should not be requested.

Read Before Each Traininq JPM Performance:

During this Training JPM, the use of applicable methods of verification and checking are expected.

Therefore, either another individual or I will act as the independent verifier or peer checker. Notes to Instructor

/ Evaluator:

1. 2. 3. Critical steps are identified in grading areas PasslFail.

All steps are sequenced critical unless denoted by a ".". During Evaluated JPM:

0 During Training JPM: 0 Self checking shall be demonstrated.

Self checking shall be demonstrated. Peer checking shall be demonstrated.

References

1. GAP-RPP-01; 3.5. 2. GAP-RPP-02; 3.3. 3. GAP-RPP-08; 3.2. 4. GAP-RPP-07; 3.2.5 5. KIA 2.3.10 (2.9) Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure.

Tools and Equipment:

1. None. Task Standard: Radiological requirements related to the entry into Contaminated High radiation Area are evaluated and recorded. NRC RO ADMIN JPM 4 October 2006 Initial Conditions:

1. Unit 1 is operating at 100% power.

2. Entry into SHUTDOWN COOLING ROOM is required to hang clearance on BV 38-03 SDC Pump 11 suction handwheel.

3. Current exposure is 1800 mrem TEDE.

4. RWP and survey map are provided.

5. Ask the operator for any questions.

Initiating cue: "(Operator's name), you will be performing an entry into the SHUTDOWN COOLING ROOM to hang clearance on BV 38-03 SDC Pump 11 suction handwheel.

RWP and survey maps are provided. Address the radiological aspects of performing this job and record findings on scorecard."

1. Provide repeat back of initiating cue. Evaluator Acknowledge repeat back providing correction if necessary RECORD START TIME 2. 3. 4. 5. 6. Classify the area. Determine highest on contact and general area dose rates and location, based on survey map Determines highest contamination levels in the room. Determine RWP and Task Number required for entry. Determines insufficient delta exposure to enter without additional approval. Proper communications used for repeat back (GAP-OPS-01)

NOTE: A score card is attached to this JPM identifying the items for the performer to identify. Determines the area is a HIGH RADIATION AREA. Determines highest on contact dose rate to be 500 mremlhr at 12 SDC Pump. Determines highest general area dose rate to be 100 mrem/hr near BV 38-03, 12 SDC Pump and 11 SDC Heat Exchanger. Determines highest contamination level to be 8000 dpm/lOO cm2 at 12 SDC Pump, smear location

7. Determines RWP I06001 Task 2 is correct for the job. Determine within delta exposure of 300 mrem and additional approvals required prior to performing the inspection. (GAP-RPP-08 3.2.2, minimum delta exposure of 300 mRem needed to enter HRA). Admin limit of 2000 mr, from GAP-RPP-07.

2000 - 1800 = 200 mrem delta 300 mrem delta is required.

SatlUnsat PasslFail PasslFail PasslFail PasslFail PasslFail PasslFail NRC RO ADMIN JPM 4 October 2006 End of JPM TERMINATING CUE: Radiological requirements related to the entry into Contaminated High radiation Area are evaluated and recorded.

RECORD STOP TIME NRC RO ADMIN JPM 4 October 2006 Initial Conditions:

1. Unit 1 is operating at 100% power. 2. Entry into SHUTDOWN COOLING ROOM is required to hang clearance

3. Current exposure is 1800 mrem TEDE. 4. RWP and survey map are provided.

5. Ask the operator for any questions.

on BV 38-03 SDC Pump 11 suction handwheel.

Initiating cue: "(Operator's name), you will be performing an entry into the SHUTDOWN COOLING ROOM to hang clearance on BV 38-03 SDC Pump 11 suction handwheel.

RWP and survey maps are provided. Address the radiological aspects of performing this job and record findings on scorecard."

NRC RO ADMlN JPM 4 October 2006 I Answer the following when performing this task:

I 0 High Radiation Area 0 Locked High Radiation Area 0 Very High Radiation Area

2. Designate the highest on contact dose rate in the area and the location AND the I highest general area dose rate and location:

0 Acceptable 0 Additional approval(s) required NRC RO ADMIN JPM 4 October 2006 NOTE: THIS IS THE EXAMINER SCORECARD.

DO NOT PROVIDE TO THE CANDIDATE.

Answer the following when performing this task:

J High Radiation Area Locked High Radiation Area 500 mrem/hr on contact at 12 SDC Pump I00 mrem/hr near BV38-03 and I1 SDC Pump, 12 SDC Pump and I1 SDC Heat Exchanger (east side of HX). 3. PasslFail Designate the highest contamination levels in the room and location:

8,000 dpm/lOOcmZ at 12 SDC Pump at smear location #7 4. Pass/Fail 1 Designate the RWP and task number required to be used: RWP # 106001 Task 2 (because task is in Contaminated High Radiation Area) 5. PasslFail Evaluate delta exposure for entry into the area: (check one): 0 Acceptable

/Additional approval(s) required NRC RO ADMlN JPM 4 October 2006 Map No. 1 RB 261' Shut-Down Cooling Room 1 25b Nine Mile Point 1 Unit One I WORK ON HTX 202-84 / WO 051895400

'I L Rx Power 100 % I H, lnj. Rate 6 scfrn I 1 Floor <400 4K e20 1K 1K 2K V - U (PMP-3 149) FCV-3809 (o/h) I /I I / I / I I *250 75 @ 38-05 PIPE TAPS - 50 @ DO NOT LINGER SIGN, WHICH IS ALSO AT BOTTOM OF LADDER TO SCAFFOLD (SHIELDED)

I I INSULATED PIPES WITHIN REACH OF THE LADDER TRAVEL PATH 3, A = General Area Unless Noted

4. .* = $~~~~t 2. @ =SmearLocation

= Rope/Area " - Boundary 5. A = Neutron (rnRemlhr)

6. IA/sI =Air Sample 7. @ = LargeArea Wipe 8. =Area Rad Monitor 9. v#I = VAMP Number 7 = Readings in mRernlhr.

p = Readings in mRadlhr. Remarks: All overhead doserates were by use of the teletector Survevor:

i HENRY Dose:

9 mRem I Reviewed Bv:

Date I 10/24/2006 8: 19:28AM Page 1 of2 Radiation Work Permit: 106001 Perform Minor Maintenance in High Radiation Areas. Low Radiological Risk. Inspections, Maintenance and Surveillances in High Radiation Areas. TASK: 1 High Radiation Area (HRA) 7391 Dose Alarm 50 mRem Dose Rate Alarm 500 mRemlHr Backoff Dose 40 mRem Protective Clothing Requirements:

No Protective Clothing Required.

TLD, Electronic Dosimeter If entry to a Contaminated Area is required on this RWP, Contact Radiation Protection for Protective Clothing Requirements.

Instructions:

1) RPS approval and survey required for system breech.

2) Pre-job briefing by RP required.

Work crew will provide work area locations

3) HEPA Vacuums

& Ventilation Units are radiological engineering instruments:

To be used on approved work, not to be opened, not to be relocated to another work area without RP approval, no water or oil vacuuming. All direct users must recieve a pre-job brief. Contact RP for any changes to these instructions.

4) If High Radiation Area is within a High Noise Area a PEA MUST be used. Obtain PEA prior to RCA Entry

5) Leave area if radiation monitor or dosimeter alarms and contact Radiation Protection.

ALARA Review Number:

Survey Data: Radiation Levels: Turbine Building HRAs Reactor Building HRAs Rad Waste Buiding HRAs Off Gas Building HRAs 2 - 200mRem/hr 2 - 250mRemlhr 2 - GOOmRem/hr 2 - 120mRem/hr Contamination Levels: ~400 - 10,000 dpm/lOOcm2 Airborne Levels: ~0.3 DAC SDecific areas as Der RP briefina and / or survev maw. Scanning or entering RWP and Task number signify that I have read, understand and will comply with the RWP More Information On Back 1 OI2412OO6 8: 19:28AM Page 2 of2 Radiation Work Permit: 106001 Perform Minor Maintenance in High Radiation Areas.

Low Radiological Risk. Inspections, Maintenance and Surveillances in Contaminated High Radiation Areas. TASK: 2 High Radiation Area (HRA) 7391 Dose Alarm 50 mRem Backoff Dose 40 mRem Dose Rate Alarm 500 mRem/Hr Protective Clothing Requirements:

Single Full Set Of Protective Clothing Hood, Cotton Liners, Rubber Gloves (I), Cotton Boots (I), Rubbers (1) Coveralls (I), TLD, Electronic Dosimeter Radiation Protection Tech. may change protective clothing, respirator, or other requirements as work locations and conditions change. Leather gloves may be worn instead of rubber gloves for safety reasons.

When Leather gloves are worn, SURGEON gloves or RUBBER MUST be worn underneath them. Instructions:

1) RPS approval and survey required for system breech.

2) Pre-job briefing by RP required.

Work crew will provide work area locations

3) HEPA Vacuums

& Ventilation Units are radiological engineering instruments:

To be used on approved work, not to be opened, not to be relocated to another work area without RP approval, no water or oil vacuuming. All direct users must recieve a pre-job brief. Contact RP for any changes to these instructions.

4) If High Radiation Area is within a High Noise Area a PEA MUST be used. Obtain PEA prior to RCA Entry. 5) Leave area if radiation monitor or dosimeter alarms and contact Radiation Protection.

ALARA Review Number:

Survey Data: Radiation Levels:

Turbine Building HRAs Reactor Building HRAs Rad Waste Buiding HRAs Off Gas Building HRAs 2 - 200mRem/hr 2 - 250mRem/hr 2 - GOOmRem/hr 2 - 120mRem/hr Contamination Levels:

~400 - 10,000 dpm/lOOcrn2 Airborne Levels:

~0.3 DAC Specific areas as per RP briefing and / or survey maps.

Scanning or entering RWP and Task number signify that I have read, understand and will comply with the RWP More Information On Back c Conduct of Operations SRO ADMIN 1 ES-301, Rev. 9 Administrative Topics Outline Form ES-301-1 N Conduct of Operations SRO ADMIN 2 I N Equipment Control SRO ADMIN 3 I N Radiation Control SRO ADMIN 4 D Emergency Plan SRO ADMIN 5 Date of Examination:

Operating Test Number:

NA December 11, 2006 Describe activity to be performed 9ssess Reportability Requirements For Transient Plant Conditions Given a series of plant events, determine the verbal reporting requirements per 10CFR50.72. (CR NM-2006-4134) 2.1 .I8 (3.0) Ability to make accurate/ clear and concise logs/ records/ status boards1 and reports. 10CFR50.72, NUREG 1022 REV 2 Reactivity Management Events and RMR Review Given plant conditions review an RMR. RMR is not to be approved, based on predicted power/flow map operating point. Determine the reactivity event severity level and the appropriate compensatory actions and notifications.

2.1.7 (4.4) Ability to evaluate plant performance and make operational judgments based on operating characteristics I reactor behavior I and instrument interpretation.

GAP-OPS-05 section 3.13 Determine Thermal Limits with Inoperable Pressure Regulator Given plant parameters including an inoperable reactor pressure regulator, determine the adjusted thermal limit values. Core Operating Limit Report graphs and 3D Monicore printout is used to evaluate conditions against the adjusted thermal limits. 2.2.22 (4.1) Knowledge of limiting conditions for operations and safety limits. N1-RESP-1, Core Operating Limits Report and Tech Spec 3.1.7 Determine Actions Required For an Inoperable Effluent Radiation Monitor Given plant conditions, determine operability of an effluent radiation monitor and apply action statements contained in the station ODCM. 2.3.1 1 (3.2) Ability to control radiation releases.

ODCM (CR NM-2004-976)

~ Classify Emergency Event and Perform PARs Given plant conditions at an existing Site Area Emergency, determine the plant conditions now meet General Emergency conditions. Reclassify the event and determine PARs, based on conditions provided. (Time Critical)

NRC 2002 SRO JPM A4 2.4.44 (4.0)

Knowledge of emergency plan protective action recommendations.

EAL Matrix NOTE All items (5 total) are required for SROs RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required

Type Codes & Criteria (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs, (N)ew or (M)odifred from bank

(- 1) (P)revious 2 exams 1 randomlv selected) 4 for SROs & RO retakes) 10123/2006 3: 19:02 PM 2006 Unit 1 NRC SRO Admin Outline Submittal 1 of1 Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE Title: Assess Reportability Requirements Revision:

NRC 2006 Task Number: NA NA EXAMINATION SECURITY Date General Supervisor Date Operations Training (Designee) Operations (Designee)

NA EXAMINATION SECURITY Configuration Control Date Pe dormer: (SRO) Tra i ne r/Eval ua tor: Evaluation Method:

X Perform Simulate Evaluation Location: Plant X Simulator or other location Expected Completion Time:

25 min Time Critical Task: NO Alternate Path Task: NO Start Time: Stop Time: Completion Time: JPM Overall Rating: Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment. Comments: Evaluator Signature: Date:

NRC SRO ADMIN JPM 1 1 October 2006 Recommended Start Location: (Completion time based on the start location) Simulator or other designated area.

Simulator Set-up: NIA Directions to the InstructorIEvaluator:

None Directions to Operators: Read Before Everv JPM Performance: For the performance of this JPM, I will function as the SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

With the exception of accessing panels, NO plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues. Read Before Each Evaluated JPM Performance: This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional I concurrent verification will not be provided; therefore, it should not be requested.

Read Before Each Traininq JPM Performance:

During this Training JPM, the use of applicable methods of verification and checking are expected. Therefore, either another individual or I will act as the independent verifier or peer checker.

Notes to Instructor I Evaluator: 1. Critical steps are identified in grading areas PasslFail.

All steps are sequenced critical unless denoted by a "0. 2. During Evaluated JPM:

0 3. During Training JPM:

0 0 Self checking shall be demonstrated. Self checking shall be demonstrated. Peer checking shall be demonstrated.

References:

1. NIP-IRG-01

2. 10CFR50.72

3. NUREG 1022 Rev 2, Section 3.2.6 4. EAL Matrix

5. CR NM-2006-4134 Plant Event Unit 2 Log Entry 9/5/06 1130 Tools and Equipment:

1. None Task Standard:

Determine notification requirements.

NRC SRO ADMlN JPM 1 2 October 2006

- Initial Conditions:

The plant is operating at 100% power. Containment purge is in progress Maintenance is using an approved work order (WO) to perform a maintenance activity on containment purge isolation logic WO identifies that the activity has the potential to cause containment purge isolation, due to the possibility of causing an electrical short. While the WO is being performed, the worker does create an electrical short and an automatic isolation of the containment purge system occurs.

No other systems are affected. After conditions are stabilized, Drywell Floor Drain leakage rate rises to 12 gpm. Drywell pressure stabilizes below the scram setpoint Actions to comply with Tech Specs as a result of the leakage are initiated and Nl-OP-43C, Plant Shutdown is being implemented. Reactor power is now at 50%. Drywell Floor Drain leak rate is at Igpm and Tech Spec LCO is exited. After conditions are stabilized, a spurious MSlV isolation occurs and the reactor automatically scrams All rods fully insert Emergency Condensers are manually placed in service to control RPV pressure 600 to 800 Feedwater shift to HPCl mode and RPV level is being maintained 53 inches to 95 inches. Plant conditions are stabilized and a normal cool down occurs.

Psig Initiating cue: "(Operator's name), identify the applicable verbal notification requirements, the reason that they apply and the associated time limitations for reporting under that category".

1. Provide repeat back of initiating Proper communications used for repeat Sat/Unsat cue. Evaluator Acknowledge back (GAP-OPS-01) repeat back providing correction if necessary RECORD START TIME 2 *Obtain a copy of the any of the 0 Reference materials obtained. reference documents related to regulatory notifications.

These are likely to include the following:

NIP-IRG-01 10CFR50.72 and 73 NUREG1022 EAL Matrix Note: Invalid isolation during maintenance is illustrated in NUREG 1022, Rev 2, section 3.2.6 System Actuation on page 52, example 7. NRC SRO ADMIN JPM 1 3 October 2006

3. Locate and identify applicability of 0 50.72 (b)(3)(iv)(B)(2) Determines actuation of isolation logic is not reportable under 50.72 (b)( 3)( iv)( B)( 2) because the actuation is not due to a valid signal.

LER is not a verbal reporting 0 requirement.

4. Locate and identify applicability of 0 50.72(a)(I

)(i). Declaration of an Emergency Class. 5. Locate and identify applicability of 0 50,72(b)(Z)(i).

Non-emergency four hour report. Initiation of a plant shutdown required by Tech Specs. (If not already reported with the 50,72(a)(l)(i).

0 6. Locate and identify applicability of 0 50.72(b)(2)( iv)( B) Non- emergency four hour report. Actuation of RPS when the reactor is critical. 7. Locate and identify applicability of 50.72(b)(3)( iv)( B)(5) Non- emergency eight hour report.

Event or condition results in valid actuation of BWR isolation condenser system and feedwater coolant injection. LER is required under 50.73 (b)(Z)(iv). Identification of this requirement is not required. Identifies leak rate above 10 gpm requires EAL 2.1.1 UNUSUAL EVENT must be declared. Identify reportability per 50.72(a)(I

)(i) and (a)(3), within 15 minutes of declaration, immediately after notifying State and local agencies and not later than one hour after the time of declaration. Refer to Tech Spec 3.2.5.a.1 and determines that with specification not being met, the required action to comply with Tech Spec is to be cold shutdown within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . The plant shutdown being performed is required by Tech Specs. Identify reportability per 50.72(b)( 2)(i) within four hours, if not already reported. Identify reportability per 50.72(b)(Z)(iv)(B) within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , if not already reported. Identify reportability per 50.72(b)(3)(iv)(B)(S) within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , if not already reported. End of JPM TERMINATING CUE: Determine notification requirements. RECORD STOP TIME PasslFail SatlUnsatlNA PasslFail SatlUnsat PasslFail PasslFail PasslFail NRC SRO ADMIN JPM 1 4 October 2006 Applicant Cue Sheet Initial Conditions:

e 0 e e e e e e e e e 0 0 e e The plant is operating at 100% power. Containment purge is in progress Maintenance is using an approved work order (WO) to perform a maintenance activity on containment purge isolation logic WO identifies that the activity has the potential to cause containment purge isolation, due to the possibility of causing an electrical short. While the WO is being performed, the worker does create an electrical short and an automatic isolation of the containment purge system occurs.

No other systems are affected.

After conditions are stabilized, Drywell Floor Drain leakage rate rises to 12 gpm. Drywell pressure stabilizes below the scram setpoint Actions to comply with Tech Specs as a result of the leakage are initiated and N 1 -0P-43C, Plant Shutdown is being implemented.

Reactor power is now at 50%. Drywell Floor Drain leak rate is at Igpm and Tech Spec LCO is exited. After conditions are stabilized, a spurious MSlV isolation occurs and the reactor automatically scrams All rods fully insert Emergency Condensers are manually placed in service to control RPV pressure 600 to 800 psig Feedwater shift to HPCl mode and RPV level is being maintained 53 inches to 95 inches. Plant conditions are stabilized and a normal cool down occurs. Initiating cue: "(Operator's name), identify the applicable verbal reportability requirements, the reason that they apply and the associated time limitations for reporting under that category".

NRC SRO ADMlN JPM 1 5 October 2006 Attachment 1 JPM Scorecard KEY Identify the applicable verbal reportability requirements, the reason that they apply and the associated time limitations for reporting under that category Reporta bil ity Rea u i rernen t 50.72 (b)(3)(iv)(B)(2). General containment isolation signals.

50.72(a)(l)(i) and (a)(3). Declaration of an Emergency Class 50.72(b)(2)(i). Initiation of a plant shutdown required by Tech Specs 50.72( b)(2)(iv)(B).

Actuation of RPS when the reactor is critical.

50.72( b)(3)(iv)(B)(5).

Event or condition results in valid actuation of BWR isolation condenser system and feedwater coolant injection.

Time Limit NOT REPORTABLE Within 15 minutes of declaration, immediately after notifying state and local agencies and not later than one hour after the time of declaration Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , if not previously reported.

Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , if not previously reported.

Within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , if not previously reported.

Reason (Event) Category Amlies Containment Purge Isolation during maintenance activity. Also, only affects one system.

Declaration of UE 2.1 .I Initiation of a plant shutdown required by Tech Specs 3.2.5.a.1. Unidentified leakage is above 5 gpm. Automatic reactor trip when the reactor is critical.

Manual initiation of Emergency Condensers to control pressure.

Intentional manual actions are valid initiations. Also, the HPCl mode (feedwater coolant injection) is actuated.

NRC SRO ADMIN JPM 1 6 October 2006 Attachment 2 JPM Scorecard For Applicant Use dentify the applicable verbal reportability requirements, the reason that :hey apply and the associated time limitations for reporting under that :at eg o ry Re porta b i I i ty Reau iremen t Time Limit qeason (Event) Category 4pplies NRC SRO ADMIN JPM 1 7 October 2006 Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE Title: Review Reactivity Maneuver Request and Classify Reactivity Events Revision:

NRC 2006 Task Number: NA Approvals:

NA EXAMINATION SECURITY General Supervisor Date Operations Training (Designee)

Operations (Designee)

NA EXAMINATION SECURITY Configuration Control Date Pe rfo r me r : Trainer/Evaluator: Evaluation Method:

X Perform Simulate Evaluation Location: Plant X Simulator or other location Expected Completion Time:

20 min Time Critical Task: NO Alternate Path Task: NO (SW Start Time: Stop Time: Completion Time:

JPM Overall Rating:

Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment. Comments: Evaluator Signature: Date:

NRC SRO ADMIN JPM 2 1 October 2006 Recommended Start Location: (Completion time based on the start location) Simulator or other designated area. Simulator Set-up:

NIA Directions to the Instructor/Evaluator:

Applicant is to be provided with 3D Monicore printout data and RMR for review and approval.

A 5 Loop Power to Flow Map is also required.

Directions to Operators: Read Before Every JPM Performance:

For the performance of this JPM, I will function as the SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

With the exception of accessing panels, NO plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues. Read Before Each Evaluated JPM Performance: This evaluated JPM is a measure of your ability to perform this task independently.

The Control Room Supervisor has determined that a verifier is not available and that additional

/ concurrent verification will not be provided; therefore, it should not be requested. Read Before Each Traininq JPM Performance:

During this Training JPM, the use of applicable methods of verification and checking are expected. Therefore, either another individual or I will act as the independent verifier or peer checker.

Notes to Instructor I Evaluator:

1. Critical steps are identified in grading areas PasslFail.

All steps are sequenced critical unless denoted by a "*". 2. During Evaluated JPM:

3. During Training JPM: Self checking shall be demonstrated. Self checking shall be demonstrated. Peer checking shall be demonstrated.

References:

1. GAP-OPS-05 Tools and Equipment:

1. None Task Standard:

Identify approval of RMR would result in operation outside acceptable area of the Power/Flow map. Applicant does not approve the RMR.

Identifies and initiates actions for Reactivity Events. NRC SRO ADMIN JPM 2 2 October 2006 Initial Conditions:

PART 1 0 The plant is operating at rated power.

An intended plant maneuver to raise rod line is being planned.

A Reactivity Maneuver request is provided for review. Initiating cue: PART 1 "(Operator's name), review and approve the RMR and initiate any required actions. Document and explain findings and conclusions on scorecard provided.

PART 2 (After actions are complete for RMR) The following events occur: Loud abnormal noises are reported from the Main Turbine.

Power is rapidly reduced to 75% with Recirc Flow. After power is reduced to 75% the Main Turbine automatically trips. EOPs are entered and implemented. ERVs actuate. Turbine Bypass Valves were observed to remain closed throughout the transient. Control Rod 18-19 is at position 04. All other control rods are at position 02. PART 2 "(Operator's name), based on the plant events that occur identify any internal classification and administrative actions related to the events. Document findings and conclusions on scorecard provided".

1. Provide repeat back of initiating Proper communications used for repeat Sat/Unsat cue. Evaluator Acknowledge back (GAP-OPS-01) repeat back providing correction if necessary RECORD START TIME 02. Obtain a copy of the any of the 0 Reference materials obtained. reference documents.

PART 1 03. Reviews RMR and supporting 3D 0 Determines predicted results cause PasslFail Monicore predictor case. operation outside ELLLA Operating Limit (PFR Line) of Power Flow Map. (PFR is > 1 .O) Does NOT approve the RMR based on failure to maintain plant operation within allowable regions of the power to flow map. (PFR is > 1 .O) NRC SRO ADMIN JPM 2 3 October 2006 PasslFail Grade PART 2 04. Refer to GAP-OPS-05 section 0 Identifies the emergency power PasslFail 3.13 to classify reactivity event severity levels. reduction OR unplanned scram as Severity Level 4 (4-1 Rapid Downpower 10.5% RTP or shutdown due to emergent issues)

OR 4-9 Unplanned Reactor Scram While Critical.

May also identify other SL-4 Sat/Unsat events, such as 4-1 1, with rods at 02 and 04, following the scram. Identifies the Main Turbine Trip with PasslFail Bypass Valve failure to operate as Severity Level 2 (2-1 Main Turbine Trip With Bypass System failure). NOTE: SL-1 (ATWS) would not apply, with rods at 04 and 02 after the scram. All rods not inserted to at least 04 requires entry into EOP-3, Failure to Scram. Sat/Unsat u Identifies CR (DER) is required for severity level 1,2,3 and 4 events. 13. Report completion.

u Reports completion. Sat/Unsat TERMINATING CUE: Identify approval of RMR would result in operation outside acceptable area of the Power/Flow map. Applicant does not approve the RMR.

Identifies and initiates actions for Reactivity Events. RECORD STOP TIME NRC SRO ADMIN JPM 2 4 October 2006 Applicant Cue Sheet Initial Conditions PART 1 The plant is operating at rated power.

An intended plant maneuver to raise rod line is being planned.

A Reactivity Maneuver request is provided for review. Initiating cue:

PART 1 "(Operator's name), review and approve the RMR and initiate any required actions. Document and explain findings and conclusions on scorecard provided".

PART 2 (After actions are complete for RMR) The following events occur:

Loud abnormal noises are reported from the Main Turbine. Power is rapidly reduced to 75% with Recirc Flow. After power is reduced to 75% the Main Turbine automatically trips. EOPs are entered and implemented.

ERVs actuate. Turbine Bypass Valves were observed to remain closed throughout the transient . Control Rod 18-19 is at position 04. All other control rods are at position 02. PART 2 "(Operator's name), based on the plant events that occur identify any internal classification and administrative actions related to the events. Document findings and conclusions on scorecard provided".

NRC SRO ADMIN JPM 2 5 October 2006 Attachment 1 JPM Scorecard KEY Document any findings and conclusions for PART 1 and PART 2 events. ACTIONS Determines predicted results cause operation outside ELLLA Operating Limit (PFR Line > 1 .O) of Power Flow Map. Does NOT approve the RMR based on failure to maintain plant operation within allowable regions of the power to flow map. Identifies the emergency power reduction or unplanned scram as Severity Level 4. Identifies the Main Turbine Trip with Bypass Valve failure to operate as Severity Level 2 NOTE: SL-1 (ATWS) would not apply, with rods at 04 and 02 after the scram.

All rods not inserted to at least 04 requires entry into EOP-3, Failure to Scram. Identifies CR (DER) is required for severity level 1,2,3 and 4 events. Explanation 100% power and 83.9% core flow (1 12.3% rod line) results in operation above ELLLA. (PFR

>I .O) GAP-OPS-05 Attachment 1 Item 2 evaluates the RMR for maintaining operation within allowable regions of the power to flow map. Since this maneuver does not accomplish this, the RMR should not be approved.

GAP-OPS-05 section 3.1 3 SL 4. Example 4-1 Rapid Downpower 2 0.5% RTP or shutdown due to emergent issues OR 4-9 Unplanned Reactor Scram While Critical.

GAP-OPS-05 section 3.13 Example 2-1 Main Turbine Trip With Bypass System failure. GAP-OP-05 section 3.13.2 NRC SRO ADMIN JPM 2 6 October 2006 Attachment 2 JPM Scorecard For Applicant Use 3ocument any findings and conclusions for PART 1 and PART 2 events. 4ct ions Exdanation NRC SRO ADMIN JPM 2 7 October 2006

10. Determine "Adjusted LHGR limit" 0 Determines adjusted value to be PasslFail value for step 9.2.10, with pressure regulator out of service and thermal power between 45% and 90% from the COLR. 0.860, from COLR Section 3.1 and Figure 3, as follows: For 70% 5 P < 90% MFLPD Limit

= FRTP = 1591/1850

= 0.8600 0 Enters 0.860 as "Adjusted LHGR Sat/Unsat limit" value for step 9.2.10. 11. Determine "Actual MFLPD Value" Determines actual MFLPD value to PasslFail from 3D Monicore printout. be 0.735, from printout. Enters 0.735 as "Actual Sat/Unsat MFLPDValue" for step 9.2.10 12. Determines COLR thermal limit Evaluates actual MFLPD value to be PasslFail restriction for MCPR is met. less than adjusted limit and that the MFLPD thermal limit is met. 0 Records MFLPD and location in step SatlUnsat 9.2.1 1 as 0.735 and 41-38. Records FPAPDR in step 9.2.12 as Sat/Unsat 0.855 from printout.

0 Records step 9.2.13 as NA, since Sat/Unsat FPAPDR is < 1 .O. 13. Report completion. Reports completion. Sat/Unsat TERMINATING CUE: Determine and evaluate adjusted thermal limits with an inoperable pressure regulator.

Identify COLR MCPR limit is exceeded and Tech Spec 3.1.7 actions required.

RECORD STOP TIME NRC SRO ADMIN JPM 3 5 October 2006 Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE Title: Determine Thermal Limits with Inoperable Pressure Regulator Revision:

NRC 2006 Task Number:

NA NA EXAMINATION SECURITY Da General Supervisor Date Operations Training (Designee) Operations (Designee)

NA EXAMINATION SECURITY Configuration Control Date Trai ne r/Eval uator: Evaluation Method:

X Perform Simulate Evaluation Location: Plant X Simulator or other location Expected Completion Time:

25 min Time Critical Task: NO Alternate Path Task: NO Start Time: Stop Time: Completion Time:

JPM Overall Rating: Pass Fail NOTE: A JPM overall rating of fail shall be given if any critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment. Comments: Evaluator Signature:

Date: NRC SRO ADMIN JPM 3 1 October 2006 Recommended Start Location: (Completion time based on the start location)

Simulator or other designated area. Simulator Set-up:

N /A Directions to the Instructor/Evaluator:

Applicant is to be provided with NI-RESP-1 for recording data. Applicant must have access to Core Operating Limits Report, Tech Specs, 3D Monicore printout data and N1-OP-31 Directions to Operators: Read Before Everv JPM Performance: For the performance of this JPM, I will function as the SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.

During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

With the exception of accessing panels, NO plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues. Read Before Each Evaluated JPM Performance: This evaluated JPM is a measure of your ability to perform this task independently. The Control Room Supervisor has determined that a verifier is not available and that additional

/ concurrent verification will not be provided; therefore, it should not be requested. Read Before Each Traininq JPM Performance:

During this Training JPM, the use of applicable methods of verification and checking are expected. Therefore, either another individual or I will act as the independent verifier or peer checker.

Notes to Instructor

/ Evaluator:

1, 2. During Evaluated JPM:

3. During Training JPM:

Critical steps are identified in grading areas PasslFail.

All steps are sequenced critical unless denoted by a "*". 0 Self checking shall be demonstrated. Self checking shall be demonstrated. Peer checking shall be demonstrated.

References:

1. Core Operating Limits Report (COLR)

2. N1 -RESP-1 Daily Thermal Limit Surveillance

3. Tech Spec 3.1.7 4. N1-OP-31, H.5.0 and H.3.0 Tools and Equipment:

1. None Task Standard NRC SRO ADMIN JPM 3 2 October 2006 limit is exceeded and Tech-Spec 3.1.7 actions required.lnitial Cond'itions:

The plant is operating at power Current core thermal power and flow are indicated on 3D Monicore printout The Mechanical Pressure Regulator is out of service for repairs MPR linkage is disconnected at the Front Standard Initiating cue: "(Operator's name), using the 3D Monicore printout provided complete N1-RESP-1, Daily Thermal Limit Surveillance section 9.2, up to and including step 9.2.13". 1. Provide repeat back of initiating cue. Evaluator Acknowledge back (GAP-OPS-01) Proper communications used for repeat I NRC SRO ADMIN JPM 3 3 October 2006 repeat back providing corr&tion if necessary RECORD START TIME *2. Obtain a copy of the any of the 0 reference documents.

03. Candidate may reference N 1

-0P- 0 31, H.3.0. 4. Record data in N1-RESP-1 by 0 obtaining information from 3D Monicore printout. Reference materials obtained. Refers to N1-OP-31, H.3.0 for direction for operation with one pressure regulator inoperable.

Refer to Core Operating Limits Report for applicable MFLPD and MFLCPR thermal limit restrictions.

IF unable to meet COLR thermal limit restrictions, THEN perform the following: Enter applicable Tech Spec (3.1.7) Notify Reactor Engineering to obtain direction to achieve compliance with applicable thermal limit restrictions. Records Core Thermal Power in step 9.2.2 as 1591 MWth and 86.0%. Records Total Core Flow in step 9.2.3 as 48.023 Mlbm/hr and 71 .I % Records step 9.2.4 as NA, since all RRPs are operating.

Sat/Unsat Sat/Unsat/NA Sat/Unsat PasslFail PasslFail Sat/Unsat SatlUnsat Sat/Unsat

5. Determine "Adjusted MCPR limit" value for step 9.2.6.1, with pressure regulator out of service and thermal power between 45%

and 90% from the COLR.

6. Determine "Actual MCPR Value" from 3D Monicore printout.

7. Determines COLR thermal limit restriction for MCPR is not met. 8. Enter Tech Spec 3.1.7.c 9. Record data in N1-RESP-I by obtaining information from 3D Monicore printout.

0 0 0 0 0 0 0 0 0 0 Records MAPRAT and location in step 9.2.5 as 0.775 and 41-38 Records step 9.2.6 as NA, since all RRPs are operating. Determines adjusted value to be 1.809, from COLR Section 2.1 and Figure 2b, as follows: For 70% 5 P < 90% MCPR Limit = (Rated 0 L M C P R)/F RTP Rated OLMCPR= MCPRlim*Kf

= 1.53*1.017

= 1.556 = 1.5561.860

= 1.809 Enters 1.809 as "Adjusted MCPR limit" value for step 9.2.6.1 Determines actual MCPR value to be 1.753, from printout. Enters 1.753 as "Actual MCPR Value" for step 9.2.6.1 Evaluates actual MCPR value to be less than adjusted limit and that the MCPR thermal limit is NOT met. Recognize entry into Tech Spec 3.1.7 specification

c. Identifies "action shall be initiated within 15 minutes to restore operation to the prescribed limit. If all operating MCPRs are not returned within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , reactor power reductions shall be initiated at a rate not less than 10% per hour until MCPR is within the prescribed limit". Notifies Reactor Engineering to obtain direction to achieve compliance with applicable limits. (OP-31 H.3.2.2) Records MFLCPR and location in step 9.2.7 as 1.032 and 29-14. Records step 9.2.8 as NA, since all RRPs are operating. Records Power to Flow Ratio (PFR) step 9.2.9 as 0.933.

Sat/Unsat PasslFail SaVUnsat PasslFail Sa t/U n sa t PasslFail PasslFail PasslFail PasslFail SatlUnsat Sat/Unsat NRC SRO ADMIN JPM 3 4 October 2006 Grade 10. Determine "Adjusted LHGR limit" Determines adjusted value to be PasslFail value for step 9.2.10, with pressure regulator out of service and thermal power between 45% and 90% from the COLR. 0.860, from COLR Section 3.1 and Figure 3, as follows:

For 70% 5 P < 90% MFLPD Limit = FRTP = 1591/1850

= 0.8600 Enters 0.860 as "Adjusted LHGR Sat/Unsat limit" value for step 9.2.10.

11. Determine "Actual MFLPD Value" Determines actual MFLPD value to PasslFail from 3D Monicore printout.

be 0.735, from printout. Enters 0.735 as "Actual MFLPD Sat/Unsat Value"for step 9.2.10

12. Determines COLR thermal limit Evaluates actual MFLPD value to be PasslFail restriction for MCPR is met. less than adjusted limit and that the MFLPD thermal limit is met. Records MFLPD and location in step SatlUnsat 9.2.1 1 as 0.735 and 41-38. Records FPAPDR in step 9.2.12 as Sat/Unsat 0.855 from printout. Records step 9.2.13 as NA, since Sat/Unsat FPAPDR is

< 1.0. 13. Report completion. Reports completion. Sat/Unsat TERMINATING CUE: Determine and evaluate adjusted thermal limits with an inoperable pressure regulator. Identify COLR MCPR limit is exceeded and Tech Spec 3.1.7 actions required.

RECORD STOP TIME NRC SRO ADMlN JPM 3 5 October 2006 Applicant Cue Sheet Initial Conditions: The plant is opera ing a : power 0 Current core thermal power and flow are indicated on 3D Monicore printout The Mechanical Pressure Regulator is out of service for repairs MPR linkage is disconnected at the Front Standard Initiating cue: "(Operator's name), using the 3D Monicore printout provided complete N1 -RESP-1 , Daily Thermal Limit Surveillance section 9.2, up to and including step 9.2.1 3". NRC SRO ADMIN JPM 3 6 October 2006 H. OFF-NORMAL PROCEDURE (Cont) 3.0 c. Operation With One Pressure Requlator Inoperable 3.1 IF operating without a backup pressure regulator, see the Core Operating Limits Report (COLR) section for operation without a backup pressure regulator for IF unable to meet the COLR thermal limit restrictions, THEN perform the following:

3.2.1 .............................................

applicable MFLPD and MFLCPR thermal limit restrictions

(-1 :t 3.2 Enter applicable Tech Spec LCO for Fuel Rod Thermal Limits

..........................

3.2.2 Notify Reactor Engineering to obtain direction to achieve compliance with ..............................................................

the applicable thermal limit restrictions

(-) 4.0 This Section Deleted. Page 66 N 1 -0 P-31 Rev 21 PAGE 1 CORE PARAMETERS 3 DM/ P11 20-OCT-2006 13:39 CALCULATED PREDICTOR LOG 20-OCT-2006 13:40 PRINTED POWER MWT CASE ID FTFF1061020133947 RESTART FMLD1061020084721 FIT - FULL CORE 1.0034 FLOW MLB/HR FPAPDR SUBC BTU/LB PR PSIa 1012.63 XE WORTH % -2.33 LOAD LINE

SUMMARY

CORE MWD/sT 26190.6 XE/RATED 1.01 CORE POWER 86. Os CYCLE MWD/sT AVE VF 0.371 CORE FLOW 71.1%@ MCPR ff:":;: PFR @ 0.933 LOAD LINE 107.5% T STEP HOURS CORRECTION FACTORS: MFLCPR=

1.017 MFLPD= 1.000 MAPRAT= 1.000 OPTION: PRE-ARTS 5 LOOPS ON MANUAL FLOW MCPRLIM= 1.530 0.887 4 9-14 0.735 @1 4 y;E@41%- 4 0.862 37 7 :F:11bl-12 0.732 37 4 0.772 37 5 0.859 23 5 Q 0-7 KfZ MOST LIMITING LOCATIONS (NON-SYMMETRIC)

LOC MFLPD LOC PCRAT LOC 0.879 0.878 0.868 0.868 0.863 0.863 0.862 0.861 51 L 47 43 39 35 31 27 L L L 23 19 15 11 L L 07 03 0.772 37 4 0.859 29 7 33-14 0.726 39 4 31-16 0.723 35 4 0.764 39 4 0.859 43 9 27-18 0.723 37 4 0.760 33 5 0.859 43-24-11 39-24 0.722 41 9 0.756 33 5 0.857 37 5 41-22 0.721 27 9 0.755 35 4 0.857 33 5 39-20 0.720 33 4 0.751 43 5 0.856 41 7 37-22 0.716 43 9 0.751 27 8 0.856 29 5 35-26 0.715 33 4 0.750 43 5 0.855 33 7 08 00 06 C=MFLCPR D=MFLPD M=MAPRAT P=PCRAT

=MULTIPLE CORE AVE AXIAL NOTCH REL PW LOC 00 0.154 24 02 0.276 23 04 0.574 22 36 06 0.737 21 P 08 0.840 20 10 0.928 19

12 0.976 18 06 14 0.982 17 16 1.107 16 18 1.160 15 20 1.178 14 00 00 36 22 1.217 13 24 1.253 12 26 1.262 11 28 1.255 10 30 1.285 09 32 1.293 08 34 1.271 07 C 36 1.292 06 36 38 1.304 05 40 1.272 04 42 1.171 03 44 0.928 02 46 0.285 01 L L L L L L 08 02 06 10 14 18 22 26 30 34 38 42 46 50

Constellation Energy Group OPERATOR JOB PERFORMANCE MEASURE Title: Determine Actions for Service Water Radiation Monitor Low Flow Revision: NRC 2006 Task Number:

NA NA EXAMINATION SECURITY General Supervisor Date Operations (Designee) NA EXAMINATION SECURITY Configuration Control Date Performer: (SRO)

TrainedEvaluator: Evaluation Method:

X Perform Simulate Evaluation Location: Plant X Simulator or other location Expected Completion Time: 20 min Time Critical Task: NO Alternate Path Task:

NO Start Time:

Stop Time: Completion Time: JPM Overall Rating: Pass Fail NOTE: A JPM overall rating of fail shall be given if or individual competency area unsat requires a comment. critical step is graded as fail. Any grade of unsat Comments: Evaluator Signature: Date:

NRC SRO ADMIN JPM 4 1 October 2006 Recommended Start Location: (Completion time based on the start location) Simulator or other designated area. Simulator Set-up:

N/A Directions to the InstructorlEvaiuator:

None Directions to Operators:

Read Before Everv JPM Performance:

For the performance of this JPM, I will function as the SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions. During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary.

With the exception of accessing panels, NO plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues. Read Before Each Evaluated JPM Performance: This evaluated JPM is a measure of your ability to perform this task independently.

The Control Room Supervisor has determined that a verifier is not available and that additional

/ concurrent verification will not be provided; therefore, it should not be requested. Read Before Each Traininq JPM Performance:

During this Training JPM, the use of applicable methods of verification and checking are expected. Therefore, either another individual or I will act as the independent verifier or peer checker.

Notes to Instructor

/ Evaluator:

1. 2. During Evaluated JPM:

3. During Training JPM:

Critical steps are identified in grading areas PasslFail.

All steps are sequenced critical unless denoted by a "*". 0 Self checking shall be demonstrated.

Self checking shall be demonstrated. Peer checking shall be demonstrated.

References:

1. 2. 3. 4. 5. 6. ARP HI; HI-4-5. ODCM 3.6.14.a and TBL 3.6.14-1 Inst. 16. DER NM-2003-5168, ODCM Entry Due to SW RM Low Flow. DER NM-2004-976, Unplanned LCO - SW RM Low Flow.

K/A 2.3.1 1 (3.2) Ability to control radiation releases.

2.4.45 (3.6) Ability to prioritize and interpret the significance of each annunciator or alarm. Tools and Equipment:

1. None Task Standard: Determine actions per ARP HI-4-5 and ODCM in response to service water radiation monitor low flow condition. NRC SRO ADMIN JPM 4 2 October 2006 Initial Conditions:

1. 2. 3. 4. 5. 6. 7. 8. The plant is operating at 100°/~ power. High wind conditions (20-25 mph with higher gusts) are present and are expected to continue for the next twelve (1 2) hours. HI-4-5, LQ PROCESS RAD MON, has alarmed.

Computer Point F172, SERVICE WATER SKID FAILURE, is in alarm.

Operator reports an EQUIP FAIL Light is shown for the Service Water Discharge Monitor at the J Panel. Chemistry reports alarm is caused by low sample flow. Flows are reading 0.98 gpm on the east side (TB) and 0.99 gpm on the west side (RB). Sample flow cannot be adjusted.

Ask the operator for any questions.

Initiating cue: "(Operator's name), determine the appropriate actions in response to these conditions." 1. Provide repeat back of initiating cue. Evaluator Acknowledge repeat back providing correction if necessary RECORD START TIME 1. .Obtain a copy of the reference procedure and reviewlutilize the correct section. 2. .Per ARP HI 5, if service water monitor alarm, and monitor EQUIP FAIL light is lit, then: a. *Notify Radiation Protection Instrument Support for repair. b..lnitiate LCO sampling (C h em is try). 3. .Reference ODCM and takes appropriate actions. Proper communications used for repeat back (GAP-OPS-01)

ARP HI-4-5 obtained. Operator Actions referenced. ODCM obtained. DLCO 3.6.14 referenced.

TBL D3.6.14-1 referenced. Notifies Radiation Protection Instrument Support to initiate repairs. Directs Chemistry to perform DLCO sampling per TBL D 3.6.14-1 InstrumentlB action (d); twelve (12) hour grab samples to be collected/analyzed for SW effluent. Determines SW Radiation Monitor is inoperable.

References ODCM DLCO 3.6.14.a and TABLE D 3.6.14-1 Instrument 1 B and note (d) applies. Determines less than the minimum number of radioactive liquid effluent monitoring channels for service water effluent and takes action Sat/Unsat SatlUnsat Sat/Unsat PasslFail PasslFail SatlUnsat PasslFail NRC SRO ADMIN JPM 4 3 October 2006 shown in TBL D 3.6.14-1. Determines action (d) applies. PasslFail Effluent releases via this pathway can continue provided that at least once per twelve (12) hours grab samples are collected and analyzed SW effluent.

Initiates CR for unplanned LCO entry. Sat/Unsat End of JPM TERMINATING CUE:

SW Radiation Monitor flow adjusted and restored to operable status. RECORD STOP TIME NRC SRO ADMIN JPM 4 4 October 2006 Initial Conditions:

1. The plant is operating at 100% power. 2. High wind conditions (20-25 mph with higher gusts) are present and are

3. HI-4-5, LQ PROCESS RAD MON, has alarmed.

4. Computer Point F172, SERVICE WATER SKID FAILURE, is in alarm.

5. Operator reports an EQUIP FAIL Light is shown for the Service Water

6. Chemistry reports alarm is caused by low sample flow. Flows are reading

7. Sample flow cannot be adjusted.

8. Ask the operator for any questions. expected to continue for the next twelve (12) hours. Discharge Monitor at the J Panel. 0.98 gpm on the east side (TB) and 0.99 gpm on the west side (RB). Initiating cue: "(Operator's name), determine the appropriate actions in response to these conditions . " NRC SRO ADMIN JPM 4 5 October 2006 Attachment 1 JPM Scorecard KEY 1 Determine the appropriate actions in response to these conditions.

I Action Direct Chemistry to initiate required LCO sampling Determines SW Radiation Monitor is inoperable.

Determines less than the minimum number of radioactive liquid effluent monitoring channels for service water effluent and takes action shown in TBL D 3.6.14-1.

Determines action identified in note (d) applies. Effluent releases via this pathway can continue provided that at least once per twelve (1 2) hours grab samples are collected and analyzed SW effluent.

Required By (Document)

ARP H 1-4-5 ODCM DLCO 3.6.14 TABLE D 3.6.14-1.

ODCM DLCO 3.6.14 TABLE NOTE (d) NRC SRO ADMIN JPM 4 6 October 2006 I Attachment 2 JPM Scorecard For Applicant Use Determine the appropriate actions in response to these conditions.

Action qequired By (Document) 7 October 2006 NRC SRO ADMlN JPM 4

CONSTELLATION ENERGY GROUP OPERATOR JOB PERFORMANCE MEASURE Title: Emergency Classification With PARS Task Number: N/A Revision:

NRC 2006 NA EXAMINATION SECURITY I Genejal Supervisor

/ Date ' General Supervisor Date Operations Training (Designee) Operations (Designee)

V4-z &k3& NA EXAMINATION SECURITY Configuration Control Date Performer:

PRO) Trainer/Evaluator:

Evaluation Method: X Evaluation Location:

Plant X Simulator or other location Expected Completion Time: 20 min Time Critical Task: YES Alternate Path Task: NO Perform Simulate Start Time: Stop Time: Completion Time: JPM Overall Rating: Pass Fail - NOTE: A JPM overall rating of fail shall be given if critical step is graded as fail. Any grade of unsat or individual competency area unsat requires a comment. Comments:

Evaluators Signature: Date:

SRO ADMIN JPM 5 October 2006 Recommended Start Location: (Completion time based on the start location)

Any appropriate location with proper references. Simulator Set-up (if required):

None Directions to the Instructor/Evaluator:

None Directions to Operators: Read Before Every JPM Performance: For the performance of this JPM, I will function as the SM, CSO, and Auxiliary Operators. Prior to providing direction to perform this task, I will provide you with the initial conditions and answer any questions.

During task performance, I will identify the steps to be simulated, or discuss and provide cues as necessary. With the exception of accessing panels, NO plant equipment will be physically manipulated. Repositioning of devices will be simulated by discussion and acknowledged by my cues. Read Before Each Evaluated JPM Performance: This evaluated JPM is a measure of your ability to perform this task independently.

The Control Room Supervisor has determined that a verifier is not available and that additional I concurrent verification will not be provided; therefore, it should not be requested. Read Before Each Traininq JPM Performance:

During this Training JPM, the use of applicable methods of verification and checking are expected. Therefore, either another individual or I will act as the independent verifier or peer checker.

Notes to Instructor

/ Evaluator:

1. 2. During Evaluated JPM:

3. During Training JPM: Critical steps are identified in grading areas PasslFail.

All steps are sequenced critical unless denoted by a ".". 0 Self checking shall be demonstrated. Self checking shall be demonstrated. Peer checking shall be demonstrated.

References

1. EPIP-EPP-08, Offsite Dose Assessment And Protective Action Recommendations

2. EPIP-EPP-20, Emergency Notifications

3. EAL Matrix SRO ADMIN JPM 5 October 2006 Tools and Equipment:

1. EAL Matrix Task Standard:

Given a set of plant conditions, classify the emergency (within 15 min.), and complete the Part 1 Notification Fact sheet including PARS (within 15 min.) Initial Conditions:

1. 2. 3. The plant is under accident conditions.

A Site Area Emergency has been declared based on plant conditions. The Chemistry Technician has reported the following release data:

0 0 0 Dose assessment for ground level release rate is 58 Curies per second (Ci/second)

Dose assessment for elevated level release rate is 502 Cilsecond Wind speed is 8 mph Wind direction is from the East South East (1 50") Pascal Stability Class is E Initiating Cues : "(Operator's name), Take the required actions as the Emergency Director."

Grade Performance Steps Standard Evaluator Note: Inform the Candidate that this is a Time-Critical task

1. Provide repeat back of initiating cue. Evaluator Acknowledge repeat back providing correction if necessary.

RECORD TASK 1 CRITICAL START TIME

2. Obtain a copy of the reference procedure and reviewhtilize the correct section of the procedure.

3. Using given plant data and EPIP-EPP-08 Attachment 1 Table 1 .I and Table 1.2, determine that a General Emergency exists based upon calculated total release (ground release + elevated release).

RECORD TASK 1 CRITICAL STOP/

TASK 2 CRITICAL START TIME 4. Review meteorological data and EPIP- EPP-08 and/or EPIP-EPP-20 to determine SRO ADMIN JPM 5 Proper communications used for repeat back (GAP-OPS-Ol/Operations Manual) The candidate may reference anylall of the following: EAL Matrix obtained. Section 5.0 EPIP-EPP-08 Att. 1 EPIP-EPP-18 EPIP-EPP-20 Att. 1A General Emergency is declared, within 15 minutes of recorded start time for Task 1. PAR'S made and indicated on Part I Notification Fact Sheet to evacuate ERPA's 1, 2, 3, 26, and 27 and shelter all October 2006 Sat/Unsat SaVUnsat PasslFail PasslFail PAR's. remaining ERPA's, within 15 minutes of recorded start time for Task 2. RECORD TASK 2 CRITICAL STOP TIME Terminating Cue: RECORD STOP TIME The event is classified as a General Emergency and PAR's are made. SRO ADMIN JPM 5 October 2006 Initial Conditions:

1. 2. 3. The plant is under accident conditions. A Site Area Emergency has been declared based on plant conditions.

The Chemistry Technician has reported the following release data:

Dose assessment for ground level release rate is 58 Curies per second (Cilsecond)

Dose assessment for elevated level release rate is 502 Cilsecond. Wind speed is 8 mph Wind direction is from the East South East (1 50') Pascal Stability Class is E Initiating Cues: "(Operator's name), Take the required actions as the Emergency Director."

SRO ADMIN JPM 5 October 2006

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