Text

Seabrook - Draft Operating Exam (Sections a, B, and C) (Folder 2)
	ML103490490
Person / Time
Site:	Seabrook
Issue date:	09/15/2010
From:	Silk D M; Operations Branch I
To:	Momm E; NextEra Energy Seabrook
	Hansell S
Shared Package
ML101870654	List: ML101940088; ML103190314; ML103490482; ML103490486; ML103490487; ML103490490; ML103490597; ML103490620; ML103490635; ML103490648;
References
	TAC U01694
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---SEABROOK SRO ADMIN JOB PERFORMANCE MEASURE-VERIFY QPTR Rev. Student Name: LMS#: Evaluator Name: SAT UNSAT OFFICIAL NRC EXAMINATION MATERIAL ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2010 INITIAL EXAM SECURITY PREPARED BY: ________ DATE: APPROVED BY: DATE:

JOB PERFORMANCE Task Number and

Description:

Position:

RO 0150200501 Perform A Manual QPTR Calculation Conditions:

A Plant is now at 100% power after recovering from a dropped rod at EOL. The main plant computer has been inoperable since yesterday (It was inoperable when the rod dropped). The seven day QPTR surveillance has been performed by an RO. Incore/Excore calibration was performed yesterday (before the rod dropped). Standards:

Verify the results of the manual QPTR surveillance per RX1703, QPTR Surveillance. Student Materials:

Copy of the Directions Tear-Off RX1703, QPTR Surveillance, Rev. 7, Chg. Completed Form A: Quadrant Power Tilt Calculation Limitations on performance:

Simulate/Perform all steps.

References:

Procedures RX1703, QPTR OS1000.05 , Power ON1251.01 , Loss Of Plant Page 2 of 11 JOB PERFORMANCE

7.0 Setting

Classroom

1. Use values listed in RE-17. 2. Give the student the completed copy of Form A: Quadrant Power Tilt Calculation Sheet. 8.0 Safety Considerations:

None 9.0 Approximate Completion Time: 20 minutes 10.0 Directions to the Student(s):

Initial Conditions:

1. Plant is now at 100% power following the recovery of a dropped rod at EOL. 2. The main plant computer has been inoperable since yesterday.

3. The QPTR surveillance has been performed by an RO. 4. The time is 0800, today's date. I : Detector Current N41 184 TOP (A) DETECTORS N42 I N43 182 181 N44 179 i micoamps I I ! I ! I ! BOTTOM (B) DETECTORS i N41 I N42 N43 N44 I I I Current I 177 197 191 187 mlcoamps I J Page 3 of 11 JOB PERFORMANCE 11.0 Initiating Cue: Verify the results of the completed QPTR Surveillance per RX1703. The alarm surveillance work order has been Provide your results to Page 4 of 11 PERFORMANCE D::;Discuss ELEMENT/STEP STANDARD EVALUATION P::;Perform

denotes a *denotes critical S::;Simulate critical step standard SAT UNSAT Start time _____P Initiating cue read. If the student requests a Peer Check at any time during the JPM, respond: "No one is available to peer check your actions. Please continue with the task". For performance of JPM in a classroom setting the student is provided with a copy of RX1703, Quadrant Power Tilt Ratio Surveillance.

2 RECORD the Figure RE-17 Records today's date and the revision revision and the date and time number of the RE-17 curve used the operable power range currents were taken. Detector current data for upper & lower detectors are provided.

Detector Current value units are microamps.

Student should be able to determine that all Power Range Detectors are operable when given the detector current data. P VERIFY that the current output Verifies outputs. from the top (A) and bottom (8) detector of each channel was correctly recorded on Form A, Quadrant Power Tilt Calculation Sheet Row 1. N41 top (A) detector N42 top (A) detector N43 top (A) detector N44 top (A) detector N41 bottom detector N42 bottom detector N43 bottom detector N44 bottom (8) detector Page 5 of 11 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform

denotes a *denotes critical S=Simulate critical step standard SAT UNSAT If the student asks for independent verification of the values recorded in Row 1 of Form A, cue, evaluator to student, " Form A Detector currents have been independently verified." The student is provided with a copy of RE-17. P Using data from Technical Data Book Figure RE-17, VERIFY that the 100% power, 0% AFD detector current, for the top (A) and bottom (B) detector of each channel was recorded correctly on Form A, Quadrant Power Tilt Calculation Sheet Row 2. P VERIFY that the normalized detector current was calculated correctly by dividing each detector current by its 100% power, 0% AFD current. VERIFY the results from Form A, Quadrant Power Tilt Calculation Sheet Row 3. From Technical Data Book fig RE-17, Records 100% power, 0% AFD values: 4 Top (A) Detectors From Technical Data Book fig RE-17, Records 100% power, 0% AFD values: 4 Bottom (B)Detectors Page 6 of 11

PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform

denotes a *denotes critical S=Simulate critical step standard SAT UNSAT *6. VERIFY that the average normalized detector current for the top detectors and for the bottom detectors was calculated correctly.

VERIFY the results from Form A, Quadrant Power Tilt Calculation Sheet Row 4. a. Calculates and verifies Normalized Detector Currents:

4 Top (A) Detectors

b. Calculates and verifies Normalized Detector Currents:

4 Bottom (B)Detectors Calculates and records average normalized detector currents:

Top (A) Detectors

Candidate identify that normalized current for the / /detectors is incorrect. Calculates and records average normalized detector currents:

Bottom (B) Detectors Page 7 of 11 PERFORMANCE D=Discuss P=Perform S=Simulate ELEMENT/STEP

denotes a critical step STANDARD *denotes critical standard EVALUATION SAT UNSAT *7. P VERIFY that the Quadrant Power Tilt Ratio for each detector was calculated correctly by dividing each normalized detector current by its associated average normalized detector current. VERIFY the results from Form A, Quadrant Power Tilt Calculation Sheet. *a. Calculates and records QPTR for each detector:

4 Top (A) Detectors

The student should identify that the calculated QPTR for each top detectors is incorrect.

b. Calculates and records QPTR for each detector:

4 Bottom (B)Detectors

8. P VERIFY that the maximum QPTR was circled on Form A Row 5. Verifies (circled) the maximum power tilt ratio on Form A Row 5.

The student should identify that the calculated maximum QPTR should be from top detector N-42. If the student asks for independent verification of the Form A calculations, cue, evaluator to student, " Form A calculations have been independently verified." Page 8 of 11 PERFORMANCE D=Discuss P=Perform S=Simulate

9. P ELEMENT/STEP

denotes a critical step Determine if LC03.2.4 is/is not met based on maximum QPTR STANDARD *denotes critical standard *a. Identify in step 6 of Form A that LeO 3.2.4 is/is not met *b. In Row 6 Form A circle YES/NO

The student should identify that the QPTR value for channel N-41 and N-42 top detectors exceed 1.02 and that Tech. Spec. 3.2.4 LCO is NOT met. NOTE: See answer key for the correct item to circle in row 6 on Form A CUE: "The JPM is complete." Stop time _____ Evaluator calculates the time to complete the task. Obtain from student: Tear Off Sheets and any other training materials used in the performance of the JPM Time to complete the task s;: 20 minutes. Page 9 of 11 SAT PERFORMANCE Provide comments on unsatisfactory performance of an element/step or for deviation from performance as stated. Record interruptions in performance such as retraining, shift change, and processing of procedure changes. Recommend remedial training, if necessary.

Page 10 of 11 TEAR-OFF SHEET FOR JPM 2009 RO-ADMIN#1 Initial Conditions:

1. Plant is now at 100% power following the recovery of a dropped rod at EOL. 2. The main plant computer has been inoperable since yesterday.

3. The QPTR surveillance has been performed by an RO. 4. The time is 0800, today's date. TOP (A) DETECTORS J I ! N41 N42 N43 I N44 I Detector Current I 184 182 181 179 I I I micoamps I BOTTOM(B}

DETECTORS N41 N42 N43 Detector Current 177 197 I 191 i 187 micoamps I I I Initiating Cue: Verify the results of the completed QPTR Surveillance.

The QPTR alarm surveillance work order has been generated. Provide your results to me. Page 11 of 11 RE-17 NIS CHANNEL and LOOP DELTA-T Channel N41 N42 N43 N44 Loop 1 2 3 4 Channel N35 N36 RE Dept. Supervisor Operations Manager Revision 01-14-05 Values Shown Below Indicate 100% Values Top (ramps) Bottom (/lamps) MPCS Constant Amp. Gain ) 192.76 205.70 18.30 2.000 187.64 230.97 18.30 2.000 204.85 227.05 18.30 2.000 195.84 215.50 18.30 2.000 T AVG Dev. Full Power AT Gain AT Alarm Alarm AT (C*-0223)

Time Delay 61.705 1.2965 60 sec. 60 sec. 61.891 1.2926 60 sec. 60 sec. 60.314 1.3264 60 sec. 60 sec. 61.340 1.3042 60 sec. 60 sec. rR Full Power Current (!lamps) 337.613 325.517 -: -/...-w Signature Revision Summary: tilt! //0 Date Update 100% Currents and MPCS Constant for Quarterly In/Ex Normalization Ro Form A: Quadrant Power Tilt Calculation Detector Current at: TIME 1rc:J'I DATE ?;dt/ RE-17Revision , . CAUTION Record all detector currents in units of microamps.

TOP (A) DETECTORS BOTTOM (B) DETECTORS N41 N42 N43 N44 N41 N42 N43 N44 f(i). DETECTOR CURRENT J<?Z-Jt3( J 111-19,} }q I 0-500 MICRO (2) 100% RTP, 0% AFD DETECTOR CURRENT lq2,i-{, let.6Y 2d1.8-S-ltXto '2.s0.q'1-Z2r. O!; 2/S:C;O ' FROMRE-17 (3) NORMALIZED DETECTOR CURRENT ." C[SS-/969

.. q/4 , <{60 ClLl I , ?6<6 (1)/(2) (4) AYE. NORMALIZED o 9$ t (;,p DETECTOR CURRENT (5) QUADRANT POWER L O'ZS-(t -_. TILT RATIO I. a?S-1Cf1£ ,982-(1.eo?) '(J:-I cry?;(3)/(4) (6) LCO 3.2.4 YES 1 Detector Current Obtained by: Date: _________Detector Current Independently Verified by: Calculations Performed by: Date: __________Calculations Independently Verified by: _______________

_ RX1703 Rev. 07 Chg.02 Page 11 of 12 V/J-iy}-'>H£{ Form A: Quadrant Power Tilt Calculation Sheet Detector Current at: TIME DATE\ocle{

Revision Of-J -tJ S-' W CAUTION Record all detector currents in units of microamps.

TOP (A) DETECTORS BOTTOM (B) DETECTORS N41 N42 N43 N44 N41 N42 N43 N44 (1) DETECTOR CURRENT t cr I 10:r 0-500 MICRO I'BY 102__ /91

} i-1-(2) 100% RTP, 0% AFD DETECTOR CURRENT \92/1-6 101-.6'1 ,gs-\q s-. '1>'1 265,,)-0 z.:56)/11-211: os FROMRE-17 (3) NORMALIZED DETECTOR CURRENT elY 09 SS-,969 i .BED 1 <6<;3 "= (1)1(2) (4) AVE. NORMALIZED (j o( I g-S'£DETECTOR CURRENT (5) QUADRANT POWER TILT RATIO (QPTR) \ I 00 L02 J .Q6/ \,DOS-/1qb ,'182 (3)/(4) (6) LCO 3.2.4 Met? (YES) / NO Detector Current Obtained by: Date: __________ Detector Current Independently Verified by: Date: __________ Calculations Performed by; Date: __________ Calculations Independently Verified by: Date: __________

_ RX1703 Rev. 07 Chg.02 11 of 12

SEABROOK SRO ADMIN JOB PERFORMANCE MEASURE-VERIFY SHUTDOWN MARGIN (MODE Rev. Student Name: LMS#: Evaluator Name: SAT UNSAT OFFICIAL NRC EXAMINATION ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2010 INITIAL EXAM SECURITY PREPARED BY: DATE: APPROVED BY: TRAINING JOB PERFORMANCE

1. Task Number and Description Position RO SBK 0010100401 Perform Shutdown Margin Calculation

2. Conditions: The plant is in Mode 1, MOL at 100% RTP and stable. RCS boron concentration is 1300 ppm. During performance of OX1410.02 , Quarterly Rod Operability Surveillance, rod H-2 dropped to the bottom of the core. Rod H-2 cannot be moved. OS1210.05 , Dropped Rod actions are being performed. The RO has completed RX1707, "Shutdown Margin Surveillance.

3. Standards:

Verify that results of the shutdown margin calculation are correct within +/-0.035%.6.KlK.

4. Student Materials:

Copy of Tear Off Copy of RX1707, Shutdown Margin Surveillance Rev 7 Copy of Primary TDB, Figure RE-8 Total Power Defect vs. Power And Concentration Rev.

Copy of Primary TDB, Figure RE-18 Shutdown Margin Values, Rev.

Copy of Primary TDB, Figure RE-19 Control Bank Worth At RIL vs. Power Rev. Copy of Core Operating Limit Report SSTR Rev.

Copy of completed Form C: Shutdown Margin Determination Immovable, Untrippable Dropped 5. Limitations On Performance:

Perform all steps. Verbalize all actions to the evaluator.

6.

References:

Procedures: OS1210.05 , Dropped Rod RX 1707, Shutdown Margin Surveillance Page 2 of 9 JOB PERFORMANCE Curves: Primary TDB, Figure RE-8 Total Power Defect vs. Power And Boron Concentration Primary TDB, Figure RE-18 Shutdown Margin Values

Primary TDB, Figure RE-19 Control Bank Worth At RIL vs. Power Technical SpecificationslTRM: 3.1.3.1 Moveable Control assemblies Group Height 3.1.3.6 Control Rod Insertion Limits 3.1.1.1 Shutdown Margin >200°F Core Operating Limit Report Setting: Classroom. Safety Considerations:

None. Approximate Completion Time: 15 minutes Directions To The Student: The following information is provided to you: The plant is in Mode 1, MOL at 100% RTP and stable. RCS boron concentration is 1300 ppm. During performance ofOX1410.02, Quarterly Rod Operability Surveillance, rod H-2 dropped to the bottom of the core. Rod H-2 cannot be moved. OS1210.05 , Dropped Rod actions are being performed. The RO has completed RX1707, "Shutdown Margin Surveillance. Perform the task using RX1707, Shutdown Margin Surveillance.

Page 3 of 9 JOB PERFORMANCE

11. Initiating Cue: Evaluator to student (or student's name). "Make sure we are in compliance with Tech Spec 3.1.1.1 by verifying the shutdown margin calculation using RX1707." Page 4 of 9

PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform S=Simulate

denotes a critical step

denotes a critical step SAT UNSAT When the student demonstrates the ability to obtain controlled copies of RX1707, Shutdown Margin Surveillance, Primary TDB, Figure RE-8 Total Power Defect vs. Power And Boron Concentration, Primary TDB, Figure RE-18 Shutdown Margin Values, Primary TDB, Figure RE-19 Control Bank Worth At RIL vs. Power, and Core Operating Limit Report, provide the student with the required documents when requested.

1. Start time _____ Initiating cue read If the student requests a Peer Check at any time during the JPM respond, "No one is available to Peer Check your actions. Please continue with the task." P Refer to section 4.4 of RX 1707 Refers to section 4.4 of Shutdown Margin Surveillance to Shutdown Margin Surveillance complete Form C Shutdown Margin complete Form C Shutdown Determination Immovable, Determination Untrippable, Or Dropped Rod(s) Part Untrippable, Or Dropped Rod(s) 1. See key for all values that student should enter on Form D. P Verify the correct number of Verifies the correct number immoveable,untrippable or dropped immoveable,untrippable or rod(s) were entered on Form C block rod(s) were entered on Form C (a). P Verify that the correct value for Verifies that the correct value maximum worth of individual maximum worth of immoveable,untrippable or dropped immoveable,untrippable or rod(s) was entered on Form C block rod(s) (using Primary TDB figure (b). 18) was entered on Form C block P Verify that the calculation of total Verifies that the calculation of unavailable rod worth was performed unavailable rod worth was correctly and entered on Form C block correctly (by multiplying (a) by (c). and entered on Form C block Page 5 of 9 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform S=Simulate

denotes a critical step

denotes a critical step SAT UNSAT If student requests boron concentration, reply, "RCS boron concentration is 1300 ppm." 6. P Verify that the correct value for total power defect is entered on Form C block (d). 7. P Verify that the correct value of "worth of the control banks inserted to the rod insertion limit for current relative power" is entered on Form C block (e). 8. P Verify that the correct value of "total control and shutdown rod worth minus stuck rod and less 10% uncertainty" is entered on Form C block (f). *9. P Verify that the shutdown margin calculation was performed correctly:

[f -(c + d + e)l /1,000. Verifies that the correct value for power defect for current power using Primary TDB figure and enters on Form C block Verifies that the correct value "worth of the control banks inserted the rod insertion limit for relative power" (using Primary figure RE-19) is entered on Form block Verifies that the correct value of control and shutdown rod worth stuck rod and less 10% (using using Primary TDB figure 18) is entered on Form C block Verifies shutdown margin performed

[f -(c + d + e)l

Student should identify that the shutdown margin calculation was NOT performed correctly.

Student should provide corrected calculation of shutdown margin. (See answer key for correct answer). If student fails to report the shutdown margin adequacy determination, provide the cue, "Is shutdown margin adequate?" P Notify SM/US .if the shutdown margin Notifies SM/US if the is less than the limit specified in the margin is less than the limit Core Operating Limits Report. in the Core Operating Limits Page 6 of9 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform S=Simulate

denotes a critical step

denotes a critical step SAT UNSAT CUE: "The JPM is complete." Stop time ____ Time to complete task S 15 minutes Evaluator calculates time to Obtain from Tear Off sheets and any other materials used in performance of Page 7 of 9 PERFORMANCE Provide comments on unsatisfactory performance of an element/step or for any deviation from performance as stated. Record interruptions in performance such as retraining, shift change, and processing of procedure changes. Recommend remedial training, if necessary.

Page 8 of 9 TEAR OFF Directions To The Student: The following information is provided to you: The plant is in Mode 1, MOL at 100% RTP and stable. ReS boron concentration is 1300 ppm. During performance ofOX1410.02 , Quarterly Rod Operability Surveillance, rod H-2 dropped to the bottom of the core. 10. Rod H-2 cannot be moved. 11. OS1210.05 , Dropped Rod actions are being performed.

12. The RO has completed RX 1707, "Shutdown Margin Surveillance. Perform the task using RX1707, Shutdown Margin Surveillance.

Initiating Cue: Evaluator to student (or student's name), "Make sure we are in compliance with Tech Spec 3.1.1.1 by verifying the shutdown margin calculation using RX1707." Page 9 of 9

Form C: Shutdown Margin Determination Immovable, Untrippable Or Dropped Rod(s) (Sheet 1 PART Shutdown Margin Determination

-MODEs 1 and 2 (Step Number of Immovable, Untrippable I I Dropped Rod(s) (a) Maximum Worth Individual of Untrippable or Dropped Rod (Primary 1(b)Technical Data Book Figure RE-18) I Total Unavailable Rod Worth = I x iO'?'1-pem :::: I pem (al (b) (e)

Total Power Defect -For Current Relative Power \-:t 00 pem (d)(Primary Technical Data Book Figure RE-8) Worth of the Control Banks Inserted to the Insertion Limit -For Current Relative Power '3YO (el (Primary Technical Data Book Figure RE-19) ! Total Control and Shutdown Rod Worth Minus , Stuck Rod and less 10% uncertainty (Primary pem -(f)Techmcal Data Book FIgure RE Shutdown Margin [f-(c + d + e)] / I

Notify the SMIUS ifthe Shutdown Margin is less than the limit specified in the Core Operating Limits Report. Completed By Date Independently Date Verified By US Review Date SM Review Date RXI707 Rev. 07 Chg. 07 Page 17 of19 Form C: Shutdown Margin Immovable, Untrippable Or Dropped (Sheet 1 of2) PART I Shutdown Margin Determination

-MODEs 1 and 2 (Step 4.4.1.1) Number of Immovable, Untrippable Dropped Rod(s) Maximum Worth Individual of Immovable, Untrippable or Dropped Rod (primary pcm (b)Technical Data Book Figure RE-18) Total Unavailable Rod Worth x pcm pcm (a) (b) /' -....... (e) Total Power Defect -For Current Relative Power (1980) pcm (Primary Technical Data Book Figure RE-S) " (d) ...-/ Worth of the Control Banks Inserted to the Rod Insertion Limit -For Current Relative Power pem ! (primary Technical Data Book Figure RE-19) (e) Total Control and Shutdown Rod Worth Minus Stuck Rod and less 10% uncertainty (Primary pcm Technical Data Book Figure RE-lS) (t) / --.....

Shutdown Margin [f-(c + d + e)] 11,000 \. ,if 2. Y °6.&Wkj

...... f .,...", NotifY the SMIUS if the Shutdown Margin is less than the limit specified in the Core Operating LImits Report. Completed By . Date Independently Date Verified By US Review Date SMReview Date RX1707 Rev. 07 Chg.07 Page 17 of 19

ENERG_. ..'-":'.""""., ,",-".Y,'

'" SRO ADMIN JOB PERFORMANCE MEASURE-TECHNICAL DETERMINATION AND REQUIRED OFF-SITE Rev. 0 Student Name: ___________

LMS#: Evaluator Name: SAT UNSAT OFFICIAL NRC EXAMINATION MATERIAL ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2010 INITIAL EXAM SECURITY PREPARED BY: APPROVED BY:

JOB PERFORMANCE 1.0 Task Number and

Description:

Position:

SRO Conditions: The plant is operating at full power. The Shift Manager informs you that both centrifugal charging pumps are INOPERABLE. Standards:

Identify the correct TS determination and identify the required off-site notifications and time periodicities in accordance with the Regulatory Compliance Manual (NARC). Student Materials:

Copy of the Tear-Off Seabrook Technical Regulatory Compliance Manual limitations on performance:

Perform all steps. Verbalize all actions to the evaluator.

References:

Seabrook Technical Regulatory Compliance Manual Emergency Response Manual OS1000.06 , POWER Setting: Classroom Safety Considerations:

None. Note to Evaluator

-Obtain Tear-Off Sheets from student following JPM completion (Ops only). Page 2 of 7 JOB PERFORMANCE Approximate Completion Time: 20 minutes Directions to the Student: You are the Work Control Supervisor. The following information is provided to you: The plant is operating at full power. The Shift Manager informs you that both centrifugal charging pumps are INOPERABLE. Initiating Cue: Shift Manager to Work Control Supervisor (or name), "Based on the stated plant conditions, determine the required Technical SpeCification action, if any, and inform me of your results".

Note to Evaluator

-Obtain Tear-Off Sheets from student following JPM completion (Ops only). Page 3 of 7 PERFORMANCE ELEMENT/STEP STANDARD EVALUATION

denotes a *denotes critical critical step standard SAT UNSAT 1. Start time ____ Initiating cue read. *2. Obtains a copy of Technical

Determines that there is no Specifications and references statement for two inoperable applicable T8 based on given pumps (TS 3.5.2) and therefore plant conditions.

3.0.3 Continue

with this JPM only if the correct T8 call was made above, otherwise CUE that this JPM 8M to WC8, "Using the Immediate Notifications Tab in Section 3 of the Regulatory Compliance Manual (NARC), identify the required offsite notifications and time limits. The required shutdown (TS 3.0.3 action) began at 0200 this morning." The student may refer to ER-1.1A to confirm there is no E-Plan implication.

NARC ACTIONS Outlined Below *3. Refer to the IMMEDIATE Refers to the NOTIFICATION tab and NOTIFICATION tab and reporting requirements table in requirements table in the the NARC to identify NOTE: If student asks if the shutdown has begun state "The required shutdown began at 0200." NRC Operations Center -Identifies notification to NRC within four Operations Center is required within 4 Hrs (Initiation of a TS required Shutdown)

CUE: If student wants to reference the OPMM or NAP-402, inform him it is not necessary. Note to Evaluator

-Obtain Tear-Off Sheets from student following JPM completion (Ops only). Page 4 of 7

D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform

denotes a *denotes critical S=Simulate critical step standard SAT UNSAT NOTE: The student may also determine that the following on-site notifications should be made: Ops/Asst.

Ops. Mgr, Licensing Department, FPLE Communications.

NRC Resident ASAP/1 hour OPS.! ASST. OPS. ASAP/1 hour Licensing

-ASAP FPLE Communications ASAP/1 hour CUE: The * .lPM is complete.

4. Stop time Evaluator calculates the time to complete the task. Identifies NRC Resident Inspector ASAP (when any 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months notification or less is reported to the NRC or due to the additional notification section within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ) Identifies OPS.! ASST. OPS. ASAP (any transient event/major equipment failure or due to the additional notifications section within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ) Identifies Regulatory Compliance ASAP (when any 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months notification or less is reported to the NRC) Identifies FPLE Communications ASAP (any off-normal condition or due to the additional notifications section within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ) Start -Stop time is 25 minutes. Note to Evaluator

-Obtain Tear-Off Sheets from student following ,IPM completion (Ops only). Page 5 of 7 PERFORMANCE Provide comments on unsatisfactory performance of an element/step or for deviation from performance as stated. Record interruptions in performance such as retraining, shift change, and processing of procedure changes. Recommend remedial training, if necessary.

Note to Evaluator Obtain Tear-Off Sheets from student following ,IPM completion (Ops only). Page 6 of 7 TEAR-OFF SHEET Directions to the Student: You are the Work Control Supervisor. The following information is provided to you: The plant is operating at full power. The Shift Manager informs you that both centrifugal charging pumps are INOPERABLE.

Initiating Cue: Shift Manager to Work Control Supervisor (or name), "Based on the stated plant conditions determine the required Technical Specification action, if any, and inform me of your results".

Note to Evaluator Obtain Tear-Off Sheets from student following JPM completion (Ops only). Page 7 of 7

SEABROOK SRO ADMIN JOB PERFORMANCE MEASURE-EMERGENCY DOSE LIMIT Rev. Student Name: LMS#: Evaluator Name: SAT UNSAT OFFICIAL NRC EXAMINATION ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2010 INITIAL EXAM SECURITY PREPARED BY: APPROVED BY:

JOB PERFORMANCE Task Number and

Description:

Position:

SRO SBK 1190402303 Direct Emergency Response as Short Term Emergency Director. Conditions:

1) The plant has suffered a LOP due to a Winter 2) Emergency Diesel Generator "A" and "B" failed to 3) Bus 6 has been energized using the SEPS

4) The "D" Reactor Coolant pump seal has failed completely causing a LOCA containment.

5) The core has uncovered.

6) COP-V-3 and COP-V-4 have lost indication.

7) Local Airborne radiation readings in the PAB are elevated.

8) A General Emergency has been declared on EAL: AG1; Actual or projected offsite dose> 1,000 mRem TEDE or 5,000 mRem Thyroid CDE. 9) The TSC is dispatching a team to the PAB Mechanical Penetration Area to determine if COP-V-4 can be closed. 10) Radiation readings taken at the doorway to the Mechanical Penetration Area are 2 REM/Hr. Dose at COP-V-4 is conservatively estimated at 15 REM/Hr 11) The OSC conservatively estimates

1.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months s

to assess any damage to the valve and make repairs. Standards:

Authorize an Emergency Dose Limit Extension per ER 4.3, Radiation Protection During Emergency Conditions. Student Materials:

Copy of the Directions Tear-Off ER 4.3, Radiation Protection During Emergency Limitations on performance:

Even if requested no Peer Checks will be provided during the JPM. Page 2 of 8 JOB PERFORMANCE 6.0

References:

Procedures ER 4.3, Radiation Protection During Emergency Conditions.

7.0 Setting

Classroom

8.0 Safety

Considerations:

None 9.0 Approximate Completion Time: 20 minutes Page 3 of 8 JOB PERFORMANCE 10.0 Directions to the Student(s):

Initial Conditions:

1) The plant has suffered a LOP due to a Winter Storm. 2) Emergency Diesel Generator "An and "B" failed to start. 3) Bus 6 has been energized using the SEPS Diesels. 4) The "D" Reactor Coolant pump seal has failed completely causing a LOCA in containment.

5) The core has uncovered.

6) COP Valves COP-V-3 and COP-V-4 have lost indication.

7) Local Airborne radiation readings in the PAB are elevated.

8) A General Emergency has been declared on EAL: AG1; Actual or projected offsite dose> 1,000 mRem TEDE or 5,000 mRem Thyroid CDE. 9) The TSC is dispatching a team to the PAB Mechanical Penetration Area to determine if COP-V-4 can be closed. 10) Radiation readings taken at the doorway to the Mechanical Penetration Area are 2 REM/Hr. Dose at COP-V-4 is conservatively estimated at 15 REM/Hr 11) The OSC conservatively estimates

1.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months s

to assess any damage to the valve and make repairs. 11.0 Initiating Cue: You are the Short Term Emergency Director (STED). Emergency Dose Limit Extensions have been requested for a three person to enter the Mechanical Penetration Area to attempt closing Review the Emergency Dose limit Extensions and provide approval if Provide the completed Forms to Page 4 of 8 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform

denotes a *denotes critical S=Simulate critical step standard SAT UNSAT 1. P Start time _____ Initiating cue read. If the student requests a Peer Check at any time during the JPM, respond: "No one is available to peer check your actions. Please continue with the task". Provide the student with the 3 completed Emergency Dose Limit Extension sheets and a copy ER 4.3, Radiation Protection During Emergency Conditions.

Students will evaluate and authorize the completed dose extensions. JPM task is approval of a task that is administrative in nature. Student may perform steps in any order, provided that critical tasks are all accomplished.

2 ER 4.3, step 5.1.2, 2a: a Dose extension for NSO 24000 mrem Verifies dose extension for all workers exceeds 4500 mrem/yr (minimum level requiring STED approval) Dose extension for Maintenance Mechanic 24000 mrem Dose extension for HP Technician 24000 __ mrem 3 ER 4.3, Step 5.1.2, 2b, and a Dose extension for NSO 24000 mrem Figure 2 Verifies dose extension is 25 rem or less for "Protection of large Populations" category Dose extension for Maintenance Mechanic 24000 mrem Dose extension for HP Technician 24000 __ mrem 4 ER 4.3, Step 5.1.2, 2c, and a NSO has signed figure 4. Figure 3 Verifies dose extension is up to 25 rem only for Volunteers fully aware of risks for "Protection of large Populations" category, Page 5 of 8 PERFORMANCE D=Discuss P=Perform S=Simulate 5 ELEMENT/STEP

denotes a critical step and signified by employee signature on figure 4. Authorizes Dose Extensions CUE: "The JPM is complete." 6. Stop time ______ Evaluator calculates the time to complete the task. 7 Obtain from student: Tear Off Sheets and any other training materials used in the performance of the JPM STANDARD EVALUATION

denotes critical standard SAT UNSAT b Maintenance Mechanic has signed figure __ 4. c HP Technician has signed figure 4. *a Dose extensions signed. Time to complete the task :; 20 minutes. Page 6 of 8 PERFORMANCE Provide comments on unsatisfactory performance of an element/step or for deviation from performance as stated. Record interruptions in performance such as retraining.

shift change. and processing of procedure changes. Recommend remedial training.

if necessary.

Page 7 of 8 TEAR-OFF Initial Conditions:

1) The plant has suffered a LOP due to a Winter 2) Emergency Diesel Generator "A" and "B" failed to 3) Bus 6 has been energized using the SEPS

4) The "D" Reactor Coolant pump seal has failed completely causing a LOCA in

5) The core has

6) COP-V-3 and COP-V-4 have lost

7) Local Airborne radiation readings in the PAS are

8) A General Emergency has been declared on EAL: AG1; Actual or projected offsite 1,000 mRem TEDE or 5,000 mRem Thyroid CDE. 9) The TSC is dispatching a team to the PAS Mechanical Penetration Area to determine if 4 can be closed. 10) Radiation readings taken at the doorway to the Mechanical Penetration Area are 2 REM/Hr. Dose at COP-V-4 is conservatively estimated at 15 REM/Hr 11) The OSC conservatively estimates

1.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months s

to assess any damage to the valve and make repairs. Initiating Cue: You are the Short Term Emergency Director (SlED). Emergency Dose Limit Extensions have been requested for a three person team to enter Mechanical Penetration Area to attempt closing Review the Emergency Dose limit Extensions and provide approval if Provide the completed Forms to ER 43 Page 21 Rev. 28 Figure Emergency Dose Limit

1) Name Age ,)JSO for Dose Request (Be specific): -it Cc>P-v-q I understand the consequences ofthe proposed exposure:

Note 1: The signature of the employee may be authorized by verbal reply. RADlA nON PROTECTION USE __________________

mrem.4) Current TEDE: YTD -/:i 5) Individual dose estimate for required work: _____Z_2-:-5(c:-.

O_O_ mrem. 6) Emergency Dose Limit Requested:

__

mrem. SHORT TERM EMERGENCY DIRECTOR/SITE EMERGENCY DIRECTOR A. Individual I authorize the above-named individual an emergency dose extension not to exceed This extension is necessary to perform emergency functions for plant/personnel safety, and is valid only for the task specified above. Short Term Emergency Director/Site Emergency Director B. Blanket Extension All emergency center personnel are authorized a blanket extension, not to exceed mrem. ttJ(d Short Term Emergency Director/Site Emergency Director ER 4.3 Page 21 Rev. 28 Figure 4 Emergency Dose Limit Extension

1) Name geV& Me:ck(tYlLL I understand the consequences of the proposed exposure:

Note 1: The signature of the employee may be authoriz RADIATION PROTECTION USE 4) Current TEDE: YTD -mrem. 5) Individual dose estimate for required work: 225C1O mrem. 6) Emergency Dose Limit Requested:

___---'2=--4 WO_ mrem. SHORT TERM EMERGENCY DIRECTOR/SITE EMERGENCY DIRECTOR A. Individual Extension I authorize the above-named individual an emergency dose extension not to exceed 2 Lf Cbo mrem. This extension is necessary to perform emergency functions for plantipersonnel safety, and is valid only for the task specified above. Short Term Emergency Director/Site Emergency Director B. Blanket Extension All emergency center personnel are authorized a blanket extension, not to exceed ,A/iA Short Term Emergency Director/Site Emergency Director ER 4.3 Page 21 Rev. 28 Figure 4 Emergency Dose Limit Extension

1) Name Age

_H--=--=--P

_ 3) Rd."!' for Dose E,::t sion Request (Be specific):

e\eVMlvLe...

t --V-Y I understand the consequences of the proposed exposure:

Note 1: The signature of the employee may be authorized by verbal reply. RADIA nON PROTECTION USE 4) Current TEDE: YTD -'::j'1 mrem.

5) Individual dose estimate for required work: 22. ';00 mrem.

6) Emergency Dose Limit Requested:

____

mrem. SHORT TERM EMERGENCY DIRECTOR/SITE EMERGENCY DIRECTOR A. Individual Extension I authorize the above-named individual an emergency dose extension not to exceed lLJct:t::?

mrem. This extension is necessary to perform emergency functions for plant/personnel safety, and is valid only for the task specified above. Short Term Emergency Director/Site Emergency Director B. Blanket All emergency center personnel are authorized a blanket extension, not to exceed Short Term Emergency Director/Site Emergency Director

SEABROOK SRO ADMIN JOB PERFORMANCE MEASURE-POST SCENARIO EMERGENCY CLASSIFICATION AND Rev. Student Name: _____________

LMS#: Evaluator Name: SAT UNSAT OFFICIAL NRC EXAMINATION MATERIAL ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2010 INITIAL EXAM SECURITY PREPARED BY: DATE: APPROVED BY: ________::--____------:__-----TRAINING JOB PERFORMANCE Task Number and

Description:

Position:

SRO 1190402003 Perform required notifications of on-site and off-site personnel for emergency events. Conditions:

A As applicable to associated simulator scenario. Standards:

Classify the emergency condition and make the required notifications of on-site and state personnel for this event Student Materials:

Copy of the Tear-Off E-Plan folder drawer or copies of the ER-1.1, Classification of ER-1.1A, Emergency Classification Flow ER-1.2, Emergency Plan Limitations On Performance:

Simulate/Perform all steps. Verbalize all actions to the evaluator.

References:

Procedures: RE-1.1, Classification of Emergencies ER-1.2, Emergency Plan Activation Setting: Simulator, post scenario in Notes To

Because this JPM is done with the simulator in freeze the Control Board clock

cannot be used to track time. The digital clock on the Communications Console or a wristwatch must be used. There is a reminder cue in the of the JPM. Note to Evaluator

-Obtain Tear Off Sheets from student following JPM completion (Ops only). Page 2 of 11 JOB PERFORMANCE Safety Considerations:

None Approximate Completion Time: 30 minutes 10.0 Directions To The Student(s):

A You are the Work Control Supervisor. The following information is provided to 1) The plant was initially in Mode The evaluator will act as the Shift Manager and provide the cues and communications for this ..IPM. Do you have any questions?

11.0 Initiating Cue: Shift Manager to Work Control Supervisor, "Work Control Supervisor, classify the Emergency Condition based on the most severe condition experienced during the scenario and activate the Emergency Plan for this event." Note to Evaluator

-Obtain Tear Off Sheets from student following JPM completion (Ops only). Page 3 of 11

D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform S=Simulate

denotes a critical step

denotes a critical step SAT UNSAT 1. P Start time Initiating cue read.

2. Performs ER-1.1 Section 5.1 Emergency Classification for Post Scenario Evaluation NOTE: ER-1 1, Step 2, Dose Projection is not applicable.

P Review applicable forms: ER-1.1A: Emergency Initiating Condition Matrix Modes 1, 2, 3 and 4. ER-1.1 C, Fission Product Barrier Degradation Matrix Modes 1, 2, 3 and 4. ER-1.1 B, Emergency Initiating Condition Matrix, Modes 5,6, and Defueled Reviews applicable forms. P Circle the potential emergency initiating condition(s) on each form. Circles the potential emergency initiating condition.

P For category A, E, H, Sand C events, refer to initiating condition EAL(s) in Figure 1 and verify that the EAL is met or the intent is met. Verifies that the EAL is met or the intent is met. P Identify the most severe (highest) emergency classification for which the *Identifies the most severe (highest) emergency classification.

EAL(s) is met or the intent of the initiating condition is met. P If an emergency classification is warranted, immediately implement Station Emergency Response Procedure ER 1.2, Emergency Plan Activation.

Implements procedure ER-1.2. Note to Evaluator

-Obtain Tear Off Sheets from student following JPM completion (Ops only). Page 4 of 11 PERFORMANCE D=Oiscuss ELEMENT/STEP STANDARD EVALUATION P=Perform S=Simulate

denotes a critical step

denotes a critical step SAT UNSAT NOTE: The student is expected to use the applicable Emergency Plan binder from the drawer. INSTRUCTOR CUE: DO NOT RESET THE SIMULATOR UNTIL THE CANDIDATE HAS AQUIRED THE DATA TO DETERMINE THE E-PLAN CLASSIFICATION!

CUE: If the sim is in freeze, when the student looks at the MCB clock, inform them that "The MCa clock is not running. Please use the Communications Console clock or your wristwatch to determine the time." *3. P Acquires applicable binder. Acquires binder. NOTE: Expected emergency classification is identified at the end of each simulator exam scenario description.

CUE: Shift Manager to Work Control Supervisor, "There is no Code Yellow condition imminent or in progress". Determine if a Code Yellow

Determines if a Code Yellow condition condition exists. exists. Declare emergency via a crew *Declares emergency and records time of update. update. Time of Declaration____

When student performs the update. NOTE: Determination of Schiller Station Activation is made at the Alert level or higher. 4 P DETERMINE Schiller Station Use flow chart: Activation:

Is there a WRGM high alarm?

Chooses appropriate path .

Is there a Main Steam line

Chooses appropriate path. monitor high alarm with an open ASDV or Safety Relief Valve on the affected line? Note to Evaluator

-Obtain Tear Off Sheets from student following JPM completion (Ops only). Page 5 of 11

D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform S=Simulate

denotes a critical step

denotes a critical step SAT UNSAT

Select appropriate procedure step?

Determines Schiller Station is/is not activated and goes to applicable step. EVALUATOR Ask the candidate if they still need the simulator for data for this JPM. If not then direct the simulator operator to reset the simUlator.

EVALUATOR If the student inquires about safety hazards, respond: "There are no safety hazards within the site boundry to evacuate personnel." *5. NOTIFY Station Personnel (Using message in applicable ER procedure).

Ensures night muting is off.

Sounds the plant emergency alarm. Makes Gaitronics announcement. Repeats the plant emergency alarm.

Using the Gaitronics override, repeat the announcement.

Proceed to step for notifying guard island security.

Notifies station personnel:

Ensures muting is *. Sounds the emergency *. Makes the over the

Repeats the emergency

Repeats

Goes to step for notifying guard island security.

Note to Evaluator

-Obtain Tear Off Sheets from student following JPM completion (Ops only). Page 6 of 11 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform S=Simulate

denotes a critical step

denotes a critical step SAT UNSAT NOTE: An instructor must be in the instructor booth to answer the phone and provide necessary feedback.

6. P NOTIFY Guard Island Security Notifies Guard Island

Contact the Guard Island at

Contacts the Guard ext. 4006 or 4008. Island supervisor.

Provide the following information:

A (applicable emergency plan *. (Applicable emergency plan classification) has been classification}

has been declared.

declared.

Time of declaration.

. Time when update was performed per ER-1.2A.

The emergency initiating

. Provides EAL. condition.

Schiller Station is/is not being *. Schiller Station is/is not activated.

activated (as determined above).

Direct implementation of *. Directs that procedure GN1332.00, Security GN1332.00 be Response To A Declared implemented.

Radiological Emergency.

Proceed to next step. Goes to next step. *7. P Complete ER-2.0B, State Completes ER-2.0B: Notification Fact Sheet.

Block 1-Leave Blank

Block 1-Leaves blank. Note to Evaluator

-Obtain Tear Off Sheets from student following JPM completion (Ops only), Page 7 of 11 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform S=Simulate

denotes a critical step ,;, denotes a critical step SAT UNSAT CUE: If asked, STED to WCS, "Time of declaration was _____ based on your update."

Block 2-Check

. Block 2-emergency plan "Declared" classification) checks (applicable emergency plan classification) and enters time declared.

Block 3-Enter

. Enters appropriate initiating condition.

initiating condition.

Block 4-Use applicable

. Checks applicable PARS. protective NOTE: The candidate should determine if there has been a release based upon scenario conditions.

Determines if a release has *

Block 5-checks a release has/has not occurred.

NOTE: When student presents form for authorization:

Make no comments of any sort on the information recorded.

Evaluator should sign form as STED

Block 6-Self

Block 6-authorizes by and dating the Time State Notification Fact Sheet completed,_____ *Time State Notification Fact Sheet Completed

-Time of Declaration

= ____ {Must be <15 minutes) CUE: "The JPM is complete." 9. Stop Time to complete the task::; 30 minutes. Note to Evaluator

-Obtain Tear Off Sheets from student following JPM completion (Ops only). Page 8 of 11 PERFORMANCE D=Discuss ELEMENTfSTEP STANDARD EVALUATION P=Perform S=Simulate

denotes a critical step

denotes a critical step SAT UNSAT Evaluator calculates time complete Note to Evaluator

-Obtain Tear Off Sheets from student following JPM completion (Ops only). Page 9 of 11 PERFORMANCE Provide comments on unsatisfactory performance of an element/step or for deviation from performance as stated. Record interruptions in performance such as retraining, shift change, and processing of procedure changes. Recommend remedial training, if necessary.

Note to Evaluator Obtain Tear Off Sheets from student following JPM completion (Ops only). Page 10 of 11 TEAR-OFF SHEET Directions to the Student: Evaluator gives Tear-Off sheet to the student. You are the Work Control Supervisor.

You are going to activate the emergency plan based on the following information. The following information is provided to you: The plan was initially in Mode 1. The evaluator will act as the Shift Manager and provide the cues and communications for this JPM. Do you have any questions?

Initiating Cue: Shift Manager to Work Control Supervisor, "Work Control Supervisor, classify the Emergency Condition based on the most severe condition experienced during the scenario, and activate the Emergency Plan for this event." Note to Evaluator

-Obtain Tear Off Sheets from student following JPM completion (Ops only). Page 11 of 11

Seabrook Station State Notification Fact Sheet Time Notification Initiated:

NH _____ MA _____ Block 1: Tbis is: _________at Seabrook Station. Name Title ,-------------------

, .------

Time Declared:

M Unusual Event : Time Terminated:

,: ,[ 1 Alert : I I Site Area Emergency I I General Emergency Block 4: We recommend the fonowing protective actions: [ I As follows New Hampshire Massachusetts ERPA Town Shelter Evacuate ERPA Town Shelter Seabrook [ I I ] B. Amesbury [ J I ] Hampton Falls [ 1 I ) Salisbury ( J I J Kensington I ) ( ) E. Merrimac I 1 I J S. Hampton r ) ( ) Newburyport

[ ] ( Newbury I 1 [ D. I J I ] West Newbury ( 1 ( ) N. Hampton I J ( Brentwood [ J I ] Evacuate E. Kingston [ I ( ) [ I Seabrook Beacb Exeter [ I I ) ( J Hampton Beach Newfields ( 1 I ] Newton [ ) I ) Kingston I ) I ) ( ) Parker River National Wildlife Refuge I Plum Island Beach Greenland II I ] ( ] Salisbury Beach Stratham I ] I I Rye ( J I ] Potassium Iodide (General Emergency only) New Castle [ ] I 1 ( ) Implement KI plans for the general public Portsmouth ( I Block 5: A radiological II Has not occurred I ] Has occurred and is continuing

[ } Occurred but has been terminated Block 6: Authorized by:

STED I SED I RM Date Time Block 7: Acknowledge receipt of this message with your name. New Hampshire:

__-:--_--,--

_______ Massachusetts:

__Name of Dispatcher Name of Dispatcher ER2.0B Rev. 31 Page I of 1 Seabrook Station State Notification Fact Sheet Time Notification Initiated:

NH _____ MA _____ Block 1: This is: __________

_ ______at Seabrook Station. Name Title i---_ ... -------... ---...... --......

Time Declared:

I J Unusual Event : : Time Terminated:

I I I I

I I l...tSite Area Emergency:

.I ,

I I General Emergency

,___________________

t Block 3: The Block 4: We recommend t7hf<lowing protective actions: I ( I As follows New Hampshire Massach usetts ERPA Town Shelter Evacuate EBrA Town Shelter Evacuate Seabrook I J [ J B. Amesbury [ I I I Hampton Falls , I [ ) Salisbury [ J ,] Kensington ( ) I I E. Merrimac I I r I S. Hampton ( I I I Newburyport ( J Newbury ( I ( Hampton ( I ( I West Newbury ,) I ] N. Hampton ( I ( Brentwood , I ( ) Evacuate E. Kingston I J I I ( I Seabrook Beach Exeter , J ( ] I 1 Hampton Beach Newfields I ) ( ) Newton I I ( I Close Kingston II [ ) ( 1 Parker River National Wildlife Refuge ( Plum Island Beach Greenland I J ( ) ( ] Salisbury Beach Stratham I 1 I I Rye ( I I J Potassium Iodide (General Emergency only) New Castle ( J II ( I Implement KI plans for the general public Portsmouth I I , J Block 5: A radiological ,,/ Has not occurred ( I Has occurred and is continuing I I Occurred but has been terminated Block 6: Authorized by: __________ STED I SED I RM Date Time Block 7: Acknowledge receipt of this message with your name. New Hampshire: ___________

_ Massachusetts:

_--::-::--_-:-=--:----::--

_____ Name of Dispatcher Name of Dispatcher ER2.0B Rev. 31 Page 1 of 1 Seabrook Station State Notification Fact Sheet Time Notification Initiated:

NH _____ MA _____ Block 1: This is: __________

_ _ _________at Seabrook Station. Name Title j-------------------,---------------------------.I ] Unusual Event : Time I l\t'Site Area I I J General Emergency I I

______I Block 3: The emergency initiating condition is __----'S=-<;.=...::1.

___, Block 4: We recommend the ,..owin g protective actions: I J As follows New Hampshire Massachusetts ERPA Town Shelter EVacuate ERPA Town Shelter Evacuate Seabrook [ I [ ] B. Amesbury I ] [ ] Hampton Falls I I [ I Salisbury [ ] I I Kensington ( I I J E. Merrimac I ) I I S. Hampton I J [ ] Newburyport I I ( Newbury [ I [ Hampton I I I I West Newbury I ) I I N. Hampton ( J ( Brentwood [ J ( ) Evacuate E. Kingston ( I ( J I ] Seabrook Beach Exeter I I [ I I ] Hampton Beach Newfields [ I ( ) Newton I ] [ I Close Kingston I I ( I I I Parker River National Wildlife Refuge I Plum Island Beach Greenland (I ( I I ) Salisbury Beach Stratham I ) I ) Rye ( ) ( ) Potassium Iodide (General Emergency only) NewCastle

[ ] I I ( ] Implement KI plans for the general public Portsmouth I ) [ I Block 5: A radiological V Has not occurred I ) Has occurred and is continuing [ I Occurred but has been terminated Block 6: Authorized by: ______STED I SED I RM Date Block 7: Acknowledge receipt of this message with your name. New Hampshire:

____....,.."..

________ Massachusetts:

_--::::--_=:----:

__Name of Dispatcher Name of Dispatcher ER2.0B Rev. 31 Page 1 of 1 ER 1.2 Page 14 Rev. 54 Figure Site Area Emergency Protective Action (PAR) (Sheet 1 of2)

IS BETWEEN MAY SEPTEMBER ? No Yes S.RED, C-ORANGE, WAS THE STA noN H-RED, P-RED, Z-ORANGE, IN MODE 1,2. 3, OR 4, >---v.. --... OR PRIOR TO THE EVENT Z-RED EXIST? ? See NOTE 1 No GO TO "A" ON

______ RECOMMEND:

EVACUATION OF SEABROOK AND HAMPTON BEACHES. CLOSURE OF SALISBURY AND PlUM ISlAND ;BEACHES, AND PARKER RIVER NA nONAl WIlDLIFE REFUGE.NOTE 1: H Red -after the actions to establish a'bleed and feed' cooIdown have been initiated P Red -with ReS pressure greater !han 300 psg Z Orange -after transitioning out of Procedure FR-Z.1 with no CBS pump running p:\aluoAvisloler1*2fg1.vsd PIli ..

Seabrook Station State Notification Fact Sheet Time Notification Initiated:

NH _____ MA _____ This is: ____________

_ _ _________at Seabrook Station. Name Title 1------....... ------------:-

[-----1 : Time Terminated:

I It.I'Alert I I I I I I I I Site Area Emergency:

I I : I 1 General Emergency

, , ______________

t The Block 4: We recommend the following protective actions: ./ [ ] As follows New Hampshire Massach usetts ERPA* Town Shelter Evacuate ERPA Town Shelter Evacuate Seabrook I I ( ) B. Amesbury [ ] ( I Hampton Falls [ ] [ ] Salisbury r ] ( J Kensington I ] r 1 E. Merrimac ( J I ) S. I J [ ] Newburyport ( J I Newbury ( I [ Hampton [ ] I I West Newbury ( ] [ J N. Hampton I ] I Brentwood [ J ( ] Evacuate E. Kingston ( I ( ] ( ) Seabrook Beach Exeter I J [ I ( ] Hampton Beach Newfields

[ ] [ I Newton [ ) [ I Close Kingston I J [ ] [ J Parker River National Wildlife Refuge [ Plum Island Beach Greenland ( ) ( ] [ ] Salisbury Beach Stratham I ] I I Rye [ J [ ] Potassium Iodide (General Emergency only) New Castle [ J ( ] I 1 Implement KI plans for the general public Portsmouth [ I (J/ Block 5: A radiological Has not occurred [I Has occurred and is continuing [ ] Occurred but has been terminated Block 6: Authorized by: __________

_ STED J SED I RM Date Time Block 7: Acknowledge receipt orth!s message with your name. New Hampshire:

____________

_ Massachusetts:

_----:::-_-=:-:-_..,-

_____ Name of Dispatcher Name of Dispatcber ER2.0B Rev. 31 Page 1 ofl

SEABROOK RO ADMIN JOB PERFORMANCE MEASURE-CALCULATE BORON CHANGE Rev. 0 Student Name: ___________

LMS#: Evaluator Name: SAT UNSAT OFFICIAL NRC EXAMINATION MATERIAL ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2010 INITIAL EXAM SECURITY PREPARED BY: DATE: APPROVED BY: ______----:-__-__----TRAINING JOB PERFORMANCE

1. Task Number and Description Position RO SBK 0040100601 Perform Boron Concentration Change Calculation

2. Conditions:

A Plant is in Mode 3. B. The RCS is 557"F and 2235 psig. C. The crew is making preparations to go critical per OS1000.07.

D. RCS born sample is 1500 ppm. E. The ECP boron concentration is 1120 ppm. F. The MPCS Boron/Dilution program is not available.

3. Standards:

Calculate total volume required to lower RCS boron concentration

(+/- 100 gals) per RS 1735, Reactivity Calculations.

4. Student Materials:

Copy of Tear Off Copy of RS1735, Reactivity Calculations Rev 4 Copy of Primary TDB, Figure RE-14 Boration/Dilution Tables Rev.

Copy of Primary TDB, Figure RE-15 Boration/Dilution Temperature Correction, Rev. 5. Limitations On Performance:

Perform all steps. Verbalize all actions to the evaluator.

6.

References:

Procedures:

OS1000.07 , Approach To Criticality

RS 1735, Reactivity Calculations

Primary TDB, Figure RE-14 Boration/Dilution Tables

Primary TDB, Figure RE-15 BorationlDilution Temperature Correction Page 2 of 7 JOB PERFORMANCE Setting: Simulator or Classroom. Safety Considerations:

None. Approximate Completion Time: 15 minutes Directions To The Student: A. You are the Primary Operator.

You are going to perform a boron change calculation.

B. The following information is provided to you: 1. Plant is in Mode 3. 2. The RCS is 557"F and 2235 psig. 3. The crew is making preparations to go critical per OS1000.07.

4. RCS born sample is 1500 ppm. 5. The ECP boron concentration is 1120 ppm. 6. The MPCS BoronlDilution program is not available.

C. Perform the task using RS1735, Reactivity Calculations. Initiating Cue: US to Primary Operator, "Primary Operator (or student's name), using RS1735, calculate the total volume required to lower RCS boron concentration from the present boron concentration to that required for the ECP." Page 3 of 7 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform S=Simulate

denotes a critical step

denotes a critical step SAT UNSAT When the student demonstrates the ability to obtain controlled copies of RS 1735, Reactivity Calculations, Primary TDB, Figure RE-14 BorationlDilution Tables, and Primary TDB, Figure RE-15 BorationlDilution Temperature Correction provide the student with the required documents. P Start time _____ Initiating cue read If the student requests a Peer Check at any time during the JPM respond, "No one is available to Peer Check your actions. Please continue with the task." 2. Obtain Form D, Dilution worksheet for Obtains Form D, Dilution worksheet manual calculation of dilution amount. for manual calculation of dilution amount from RS1735, Reactivity Calculations. See key for values that student should enter on Form D. P Enter expected T avg at the time when Enters expected T avg at the time concentration change is to be made concentration change is to be on Form D item 1. on Form D item P Enter the present and desired boron Enter the present and desired concentration on Form D item 2. concentration on Form D item Item 3A requires a set of numbers (FROM, TO, and RMW). A value will be entered for each reading set of RE-14. For instance, changing from and would require four sets of numbers. See key for values that student should enter on Form D for item 3A. RE-14 has dilution (RMW makeup) values in the upper right and boration values in the lower left (not used for this JPM) for each boron concentration change made of 100 ppm or less. Page 4 of 7 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform S=Simulate

denotes a critical step

denotes a critical step SAT UNSAT NOTE: See key for values that student should enter on Form D. 5. P Using TSD Figue Re-14 obtain the total required volume of Reactor Makeup Water (RMW) and enter on Form D item 3a. 6. P Temperature correction for dilutions.

Perform one of the following:

If T avg is greater than or equal to 55rF then enter 1.0 on Form D item 3b. OR If T avg is less than 55rF then use TDS Figure RE-15 to obtain the value to enter on Form D item 3b. Using TSD Figue Re-14 obtains total required volume of Makeup Water (RMW) and enter Form D item Temperature correction for Performs one of the If Tavg is greater than or equal 55rF then entes 1.0 on Form D item 3b. OR If Tavg is less than 55rF then uses TDB Figure RE-15 to obtain the value to enter on Form D item 3b. NOTE: See key for values that student should enter on Form D. *7. P Calculate the corrected Total Volume of RMW required in units of gallons as the product of items 3a and 3b and enters on Form D item 3c. CUE: "The JPM is complete." 8. Stop time ____ Evaluator calculates time to complete task 9. Obtain from student: Tear Off sheets and any other training materials used in performance of this JPM. *Calculate the corrected Total Volume of RMW required in units of gallons as the product of items 3a and 3b and enters on Form D item 3c. Time to complete task S 15 minutes Page 5 of7 PERFORMANCE Provide comments on unsatisfactory performance of an elemenUstep or for any deviation from performance as stated. Record interruptions in performance such as retraining, shift change, and processing of procedure changes. Recommend remedial training, if necessary, Page 6 of 7 TEAR OFF SHEET Directions To The Student: A. You are the Primary Operator.

You are going to perform a boron change calculation.

B. The following information is provided to you: 1. Plant is in Mode 3. 2. The RCS is 55rF and 2235 psig. 3. The crew is making preparations to go critical per OS1000.07.

4. RCS born sample is 1500 ppm. 5. The ECP boron concentration is 1120 ppm. 6. The MPCS Boron/Dilution program is not available.

C. Perform the task using RS1735, Reactivity Calculations.

Initiating Cue: US to Primary Operator, "Primary Operator (or student's name), using RS1735, calculate the total volume required to lower RCS boron concentration from the present boron concentration to that required for the ECP." Page 7 of 7 Form D:, Dilution Worksheet (Sheet 1 of 1) 1. RCS Temp. (T AVO) ,5" 51-O F 2. Desired Boron Change: From IS 00-ppm To I I 2. 0 3. Gallons Required 3a. Gallons ofRMW at 557°F RCS Temperature.

ppm From From From From From 1500 I(0C? 3cu 12ao ppm ppm ppm ppm ppm To To To To To IYDO l'sQO ZOO ll2,C? ppm ppm ppm ppm ppm Total a RMW 4Zqy LiblS L}i8L LJ2QY Jt; l B-z, gals. gals. gals. gals. gals. gals. NOTE If Res temperature is greater than or equal to then parameter "b" = 1.0 3b. 3c. Temperature Correction for T AVG less than 557°F TDB Figure RE-15 Correction Factor b =__,_._D_,__ Corrected Total Gallons Required (a 18 IS3 g als.) x (b_-=-cL,--,-O_,-J) 181£53 gallonsofRMW.

Calculated By: ______________________

Date: Independently Verified By: Date: RS1735 Rev. 04 Chg.08 Page 25 of26

1# SEABROOK RO ADMIN JOB PERFORMANCE MEASURE-QPTR Rev. Student Name: LMS#: Evaluator Name: SAT UNSAT OFFICIAL NRC EXAMINATION ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2010 INITIAL EXAM SECURITY PREPARED BY: DATE: APPROVED BY: TRAINING JOB PERFORMANCE Task Number and

Description:

Position:

RO 0150200501 Perform A Manual QPTR Calculation Conditions:

A Plant is now at 100% power after recovering from a dropped rod at EOL The main plant computer has been inoperable since yesterday (It was inoperable when the rod dropped). The seven day QPTR surveillance is scheduled to be done this shift. Incore/Excore calibration was performed yesterday (before the rod dropped). Standards:

Perform the manual QPTR surveillance per RX1703, QPTR Surveillance. Student Materials:

Copy of the Directions Tear-Off RX1703, QPTR Surveillance, Rev. 7, Chg. Limitations on performance:

Simulate/Perform all steps.

References:

Procedures RX1703, QPTR OS1000.05 , Power ON1251.01 , Loss Of Plant Page 2 of 11 JOB PERFORMANCE Examiner must prepare a completed RX 1703A in advance. It shall reflect the JPM values for NI cabinet detector currents and the RE-17 100% power, 0% AFD values. Use values listed in RE-17. Safety Approximate Completion 20 10.0 Directions to the Initial Plant is now at 100% power following the recovery of a dropped rod at EOL. The main plant computer has been inoperable since yesterday. The QPTR surveillance is scheduled to be done this shift. Incore/Excore calibration was performed yesterday (before the rod dropped). Detector current readings have been taken by the Control Board Monitor. The time is 0800, today's date. TOP (A) DETECTORS i N41 N42 N43 N44 i Detector Current 184 182 181 179 i micoamps I BOTTOM (B)

I N42 N43 N44 i I Detector Current 177 197 187 i micoamps : Page 3 of 11 JOB PERFORMANCE 11.0 Initiating Cue: Perform the QPTR Surveillance per RX1703. The QPTR alarm surveillance work order has been generated.

All independent verifications of calculations will be performed after you are completed.

Provide your results to me. Page 4 of 11 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform

denotes a *denotes critical S=Simulate critical step standard SAT UNSAT P Start time _____ Initiating cue read. If the student requests a Peer Check at any time during the JPM, respond: "No one is available to peer check your actions. Please continue with the task". For performance of JPM in classroom setting the student is provided with a copy of RX1703, Quadrant Power Tilt Ratio Surveillance.

Student should refer to section 4.1 Surveillance With QPTR Alarm Inoperable.

2 RECORD the Figure RE-17 Records today's date and the revision revision and the date and time number of the RE-17 curve used the operable power range currents were taken. Detector current data for upper & lower detectors are provided.

Detector Current value units are microamps.

Student should be able to determine that all Power Range Detectors are operable when given the detector current data. P RECORD the current output Records detector from the top (A) and bottom detector of each channel Form A, Quadrant Power Calculation Sheet Row N41 top (A) detector N42 top (A) detector N43 top (A) detector N44 top (A) detector N41 bottom (8) detector N42 bottom detector N43 bottom detector N44 bottom (8) detector Page 5 of 11

D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform

denotes a *denotes critical S=Simulate critical step standard SAT UNSAT CUE: If the student asks for independent verification of the values recorded in Row 1 of Form A, cue, evaluator to student, " Form A Detector currents have been independently verified." NOTE: The student is provided with a copy of RE-17. 4. P Using data from Technical Data Book Figure RE-17, RECORD the 100% power, 0% AFD detector current, for the top (A) and bottom (B) detector of each channel on Form A, Quadrant Power Tilt Calculation Sheet Row 2. *5. P CALCULATE the normalized detector current by dividing each detector current by its 100% power, 0% AFD current. RECORD the results on Form A, Quadrant Power Tilt Calculation Sheet Row 3. a. From Technical Data Book fig RE-17, Records 100% power, 0% AFD values: 4 Top (A) Detectors

b. From Technical Data Book fig RE-17, Records 100% power, 0% AFD values: 4 Bottom (B) Detectors Page 6 of 11

PERFORMANCE D=Discuss P=Perform S=Simulate

6. ELEMENT/STEP

denotes a critical step CALCULATE the average normalized detector current for the top detectors and for the bottom detectors.

RECORD the results on Form A, Quadrant Power Tilt Calculation Sheet Row 4. STANDARD EVALUATION

denotes critical standard SAT UNSAT *Calculates and records Detector 4 Top (A) Detectors *Calculates and records Detector 4 Bottom (B) Detectors *Calculates and records normalized detector Top (A) Detectors *Calculates and records normalized detector Bottom (B) Detectors Page 7 of 11

D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform

denotes a *denotes critical S=Simulate critical step standard SAT UNSAT *7. CALCULATE the Quadrant Power Tilt Ratio for each detector by dividing each normalized detector current by its associated average normalized detector current. COMPLETE Form A, Quadrant Power Tilt Calculation Sheet. *Calculates and records QPTR for each detector:

4 Top (A) Detectors *Calculates and records QPTR for each detector:

4 Bottom (B) Detectors

8. Indicate the maximum QPTR *Identifies (circles) the maximum power tilt by circling on Form A Row 5. ratio on Form A Row 5. CUE: If the student asks for independent verification of the Form A calculations, cue, evaluator to student, " Form A calculations have been independently verified." Page 8 of 11 PERFORMANCE O=Oiscuss P=Perform S=Simulate

9. P ELEMENT/STEP

denotes a critical step Determine if LCO 3.2.4 is/is not met based on maximum QPTR. STANDARD *denotes critical standard *a. Identify in step 6 of Form A that LCO 3.2.4 is/is not met *b. In Row 6 Form A circle YES/NO NOTE: See answer key for the correct item to circle in row 6 on Form A CUE: "The JPM is complete." Stop time ______ Evaluator calculates the time to complete the task. Obtain from student: Tear Off Sheets and any other training materials used in the performance of the JPM Time to complete the task s 20 minutes. Page 9 of 11 SAT PERFORMANCE Provide comments on unsatisfactory performance of an element/step or for deviation from performance as stated. Record interruptions in performance such as retraining, shift change, and processing of procedure changes. Recommend remedial training, if necessary.

Page 10 of 11 TEAR-OFF SHEET FOR 2009 Initial Conditions:

1. Plant is now at 100% power following the recovery of a dropped rod at EOL. 2. The main plant computer has been inoperable since yesterday.

3. The QPTR surveillance is scheduled to be done this shift. 4. Incore/Excore calibration was performed yesterday (before the rod dropped).

5. Detector current readings have been taken by the Control Board Monitor. The time is 0800, today's date. TOP (A) DETECTORS I N41 N42 N43 N44 i Detector Current 184 182 179I micoamps I : BOTTOM (B) DETECTORS N41 N42 N43 N44 Detector Current 177 197 191 187 micoamps i Initiating Cue: Perform the QPTR Surveillance per RX1703. The QPTR alarm surveillance work order has been generated.

All independent verifications of calculations will be performed after you are done. Provide your results to me. Page 11 of 11 KO Detector Current at: TIME (1) DETECTOR CURRENT 0-500 MICRO (2) 100% RTP, 0% AFD DETECTOR CURRENT FROMRE-17 (3) NORMALIZED DETECTOR CURRENT = (1)/(2) (4) AVE. NORMALIZED r------DETECTOR CURRENT QUADRANT TILT RATIO = (6) LCO 3.2.4 Met? YES Form A: Quadrant Power Tilt Calculation Sheet 17 Revision w CAUTION W Record all detector currents units of microamps.

TOP (A) DETECTORS BOTTOM (B) DETECTORS N41 N42 N43 N44 N41 N42 N43 N44 1 c) y (9 Z 18 { 11 C l I1-T r-ll-jcr I t 8 r 91.16 ,

1'1S: 8'-1 2oS'. '"to 250.(1"1-27..7, oS-

,-0 9 95.5-, 9 b (l JB!)3 08 Lt I ;;JU Q 6 S 9 I ,8 5 6 .. Cry '-1 /B2 L, 0 9 9£ LOIY L02' :JOYD I Detector Current Obtained by: _____________

_ Date: Detector Current Independently Verified by: Date: __________ Calculations Performed by: _____________

_ Date: __________ Calculations Independently Verified by: _______________

_ Date: __________ RX1703 Rev. 07 Chg. 02 Page 11 of 12 i RE-17 NIS CHANNEL and LOOP DELTA-T Channel N41 N42 N43 N44 Loop 1 2 3 4 Channel N35 N36 RE Dept. Supervisor Operations Manager Revision 01-14-05 Values Shown Below Indicate 100% Values Top ()lamps) 192.76 187.64 204.85 195.84 Full 61.705 61.891 60.314 61.340 Bottom MPCS ()lamps) Constant 205.70 18.30 230.97 18.30 227.05 18.30 215.50 18.30 AT Gain AT Alarm (C*-0223)

Time Delay 1.2965 60 sec. 1.2926 60 sec. 1.3264 60 sec. 1.3042 60 sec. IR Full Power Current (!lamps) 337.613 325.517 Revision Summary: Amp. Gain (C*-0231) 2.000 2.000 2.000 2.000 T AVG Dev. Alarm Time Delay 60 sec. 60 sec. 60 sec. 60 sec. ...&/1'1 //(J Date Update 100% Currents and MPCS Constant for Quarterly In/Ex Normalization

RO ADMIN JOB PERFORMANCE MEASURE-SHUTDOWN MARGIN (MODE 1) Rev. 0 Student Name: ____________

LMS#: Evaluator Name: SAT UNSAT OFFICIAL NRC EXAMINATION MATERIAL ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2010 INITIAL EXAM SECURITY PREPARED BY: DATE: APPROVED BY: TRAINING JOB PERFORMANCE

1. Task Number and Description Position SBK 0010100401 Perform Shutdown Margin

2. Conditions: The plant is in Mode 1, MOL at 100% RTP and stable. RCS boron concentration is 1300 ppm. During performance ofOX1410.02, Quarterly Rod Operability Surveillance, rod H-2 dropped to the bottom of the core. Rod H-2 cannot be moved. OS1210.05 , Dropped Rod actions are being performed.

3. Standards:

Determine the shutdown margin within +/-0.035%i1K1K.

4. Student Materials:

Copy of Tear Off Copy of RX1707, Shutdown Margin Surveillance Rev 7 Copy of Primary TDB, Figure RE-8 Total Power Defect vs. Power And Concentration Rev.

Copy of Primary TDB, Figure RE-18 Shutdown Margin Values, Rev.

Copy of Primary TDB, Figure RE-19 Control Bank Worth At RIL VS. Power Rev. Copy of Core Operating limit Report SSTR Rev.

5. Limitations On Performance:

Perform all steps. Verbalize all actions to the evaluator.

6.

References:

Procedures: OS1210.05 , Dropped Rod RX1707, Shutdown Margin Surveillance Page 2 of 9 JOB PERFORMANCE Curves: Primary TOB, Figure RE-8 Total Power Defect vs. Power And Boron Concentration Primary TOB, Figure RE-18 Shutdown Margin Values Primary TOB, Figure RE-19 Control Bank Worth At RIL vs. Power Technical SpecificationslTRM: 3.1.3.1 Moveable Control assemblies Group Height 3.1.3.6 Control Rod Insertion Limits 3.1.1.1 Shutdown Margin >200°F Core Operating Limit Report 7. Setting: Classroom.

8. Safety Considerations:

None. 9. Approximate Completion Time: 15 minutes 10. Directions To The Student: The following information is provided to you: The plant is in Mode 1, MOL at 100% RTP and stable. RCS boron concentration is 1300 ppm. During performance of OX1410.02, Quarterly Rod Operability Surveillance, rod H-2 dropped to the bottom of the core. Rod H-2 cannot be moved. OS1210.05 , Dropped Rod actions are being performed. Perform the task using RX1707, Shutdown Margin Surveillance.

11. Initiating Cue: Page 30f9 JOB PERFORMANCE WORKSHEET US to student (or student's name), "Make sure we are in compliance with Tech Spec 3.1.1.1 by calculating shutdown margin using RX1707." Page 4 of 9

--PERFORMANCE D=Oiscuss ELEMENT/STEP STANDARD EVALUATION P=Petform S=Simulate

denotes a critical step

denotes a critical step SAT UNSAT When the student demonstrates the ability to obtain controlled copies of RX1707, Shutdown Margin Surveillance, Primary TDB, Figure RE-8 Total Power Defect vs. Power And Boron Concentration, Primary TDB, Figure RE-18 Shutdown Margin Values, Primary TDB, Figure RE-19 Control Bank Worth At RIL vs. Power, and Core Operating Limit Report, provide the student with the required documents when requested.

1. Start time _____ Initiating cue read If the student requests a Peer Check at any time during the JPM respond, "No one is available to Peer Check your actions. Please continue with the task." P Refer to section 4.4 of RX1707 Refers to section 4.4 of Shutdown Margin Surveillance to Shutdown Margin Surveillance complete Form C Shutdown Margin complete Form C Shutdown Determination Immovable, Determination Untrippable, Or Dropped Rod(s) Part Untrippable, Or Dropped Rod(s) 1. See key for all values that student should enter on Form D. P Determine number of Determines number immoveable,untrippable or dropped immoveable,untrippable or rod(s) and enter on Form C block (a). rod(s) and enters on Form C block P Determine maximum worth of Determines maximum worth individual immoveable,untrippable or individual immoveable,untrippable dropped rod(s) using Primary TDB dropped rod(s) using Primary figure RE-18 and enter on Form C figure RE-18 and enters on Form block (b). block P Calculate total unavailable rod worth Calculates total unavailable rod by multiplying (a) by (b) and enter on by multiplying (a) by (b) and enters Form C block (c). Form C block Page 5 of9 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform S=Simulate

denotes a critical step

denotes a critical step SAT UNSAT If student requests boron concentration, reply, "RCS boron concentration is 1300 ppm." P Determine total power defect for current relative power using Primary TDB figure RE-8 and enter on Form C block (d). P Determine worth of the control banks inserted to the rod insertion limit for current relative power using Primary TDB figure RE-19 and enter on Form C block (e). P Determine total control and shutdown rod worth minus stuck rod and less 10% uncertainty using Primary TDB figure RE-18 and enter on Form C block (t). *9. Calculate shutdown margin: [f -(c + d + e)] /1,000. Determines total power defect for current relative power using Primary TDB figure RE-8 and enters on Form C block (d). Determines worth of the control banks inserted to the rod insertion limit for current relative power using Primary TDB figure RE-19 and enters on Form C block (e). Determines total control and shutdown rod worth minus stuck rod and less 10% uncertainty using Primary TDB figure RE-18 and enters on Form C block (t). Calculates shutdown margin: [f -(c + d + e)] /1,000. If student asks for independent verification, provide the following cue, "Form C Part 1 has been independently verifed. Please continue." If student fails to report the shutdown margin adequacy determination, provide the cue, "Is shutdown margin adequate?" P Notify SM/US if the shutdown margin Notifies SM/US if the is less than the limit specified in the margin is less than the limit Core Operating Limits Report. in the Core Operating Limits Page 6 of 9

D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform S=Simulate

denotes a critical step

denotes a critical step SAT UNSAT CUE: "The JPM is complete." 11. Stop time ____ Time to complete task S 15 minutes Evaluator calculates time to complete task 12. Obtain from student: Tear Off sheets and any other training materials used in performance of this JPM. Page 7 of 9 PERFORMANCE Provide comments on unsatisfactory performance of an element/step or for any deviation from performance as stated. Record interruptions in performance such as retraining, shift change, and processing of procedure changes. Recommend remedial training, if necessary.

Page 8 of 9 TEAR OFF SHEET Directions To The Student: You are going to calculate shutdown margin in Mode 1. The following information is provided to you: The plant is in Mode 1, MOL at 100% RTP and stable. ReS boron concentration is 1300 ppm. During performance of OX1410.02, Quarterly Rod Operability Surveillance, rod H-2 dropped to the bottom of the core. Rod H-2 cannot be moved. OS1210.05 , Dropped Rod actions are being performed. Perform the task using RX1707, Shutdown Margin Surveillance.

Initiating Cue: US to student (or student's name), "Make sure we are in compliance with Tech Spec 3.1.1.1 by calculating shutdown margin using RX1707." Page 9 of9

I 7 Form C: Shutdown Margin Immovable, Untrippable Or Dropped (Sheet 1 of2) PART I Shutdown Margin Determination

-MODEs 1 and 2 (Step 4.4.1.1) Number of Immovable, Untrippable and i Dropped Rod(s) Ca) Maximum Worth Individual of Untrippable or Dropped Rod (primary 1-031-Technical Data Book Figure RE-18) Total Unavailable Rod Worth 1. x :1 0'3--:r pem = i03':f-pem (a) (b) (c) Total Power Defect -For Current Relative Power _____ pem i1BO (primary Technical Data Book Figure RE-8) (d) Worth-of the Control Banks Inserted to the Rod Insertion Limit -For Current Relative Power 3YO pcm (primary Technical Data Book Figure RE-19) Total Control and Shutdown Rod Worth Minus ) L!)Stuck Rod and less 10% uncertainty (primary pem Technical Data Book Figure RE-18) (f)

Shutdown Margin [f-(c +d +e)] / 1,000 f§625'-(ioq*+ i 9 CZo t'31?!J!Iat 7 %AKfK Notify the SMJUS if the Shutdown Margin is less than the limit specified in the Core Operating Limits Report. Completed By Date Independently Verified US Review Date SMReview Date -rfl'tb C*:iJjJ.*;1 tuvst IJe *t /OC1 a & ;1,LjD'6

2. ,12 %ld</K +0 2

%4" I K RX1707 Rev. 07 Chg.07.--.. Page 17 of 19

SEABROOK RO ADMIN JOB PERFORMANCE MEASURE-COP Exhaust RM Setpoints Rev. 0 Student Name: LMS#: Evaluator Name: SAT UNSAT OFFICIAL NRC EXAMINATION MATERIAL ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2010 INITIAL EXAM SECURITY PREPARED BY: APPROVED BY:

JOB PERFORMANCE 1.0 Task Number and

Description:

RO/SRO 0290100401 Adjust Containment Pressure Using the COP 0290100401 Start-Up the COP 0710101302 Authorize Release of Gaseous Conditions: Plant is in Mode 1. B. The previous shift has made preparations to place COP in service per OS 1 023.69 section 4.2. Standards:

Verify COP Exhaust Radiation Monitors' Alert and Alarm setpoints prior to gaseous effluent release per OS1023.69 section 4.2. Student Materials:

Copy of the Tear-Off Copy of CS0917.02C GEW Containment Purge Release Copy of OS 1023.69, Containment On-Line Purge System Limitations On Performance:

Perform all steps. Verbalize all actions to the evaluator.

References:

Procedures: CS0917.02 , Gaseous Effluent Releases, Rev. 10, Chg. 12. OS1023.69 , Containment On-Line Purge System Operation, Rev. 11. CP-4.1 Effluent Surveillance Program MA-4.6, RDMS Data Base Item Control I Sys KA Description Value RO/SRO Generic A2.3.11 Ability to Control Radiation Releases 2.7/3.2 Setting: Classroom Safety Considerations:

Note to Evaluator

-Obtain Tear Off Sheets from student following .IPM completion (Ops only). Page 2 of 8 JOB PERFORMANCE None 9.0 Approximate Completion Time: 20 minutes 10.0 Directions To The Student{s): You are the Primary Operator.

You are going to verify the alert and alarm setpoints of the COP Exhaust Radiation Monitors prior to placing COP in service. The following information is provided to you: Plant is in Mode 1. The previous shift has made preparations to place COP in service per OS1023.69, section 4.2. Perform the task per OS1023.69 Containment On-Line Purge Operation, section 4.2. 11.0 Initiating Cue: US to Primary Operator, "Primary Operator (or student's name), after reviewing the Gaseous Effluent Waste Containment Purge Release Permit, continue with preparations to place COP in service per OS1023.69 step 4.2. Note to Evaluator Obtain Tear Off Sheets from student following ,IPM completion (Ops only). Page 3 of 8 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform S=Simulate

denotes a critical step

denotes a critical step SAT UNSAT P Start time Initiating cue read. If the student requests a Peer Check at any time during the ..IPM respond: "No one is available to peer check your actions. Please continue with the task." Provide student with a copy of OS1023.69 (steps 4.2.1 and 4.2.2 complete) and CS0917.02C GEW Containment Purge Release Permit. "Prerequisites for performance of OS1023.69 section 4.2 have been verified met by the previous crew. If the student asks for US approval for CS0917.02C respond "The release permit has already been approved by a chemistry supervisor

-no further approval is required." *2. RECORDS the expected *RECORDS the value 31.2 as Expected radiation monitor response Radiation Monitor Response per from the Gaseous Effluent step 4.2.3. Waste (GEW) Containment Purge Release Permit, L524. *3. DETERMINES the New COP Per step 4.2.4, ADDs the Monitor Background Levels Expected Radiation Monitor (CPM) Response value to the Current COP radiation monitor background levels recorded in step 4.2.2 * *RECORDS 4.39E+01 (+1-4 CPM) for RM-6527A-1

*RECORDS 4.30E+01 (+I-4 CPM) for RM-6527A-2 *RECORDS 4.44E+01 (+1-4 CPM) for RM-6527B-1 Note to Evaluator

-Obtain Tear Off Sheets from student following JPM completion (Ops only). Page 4 of 8 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform S=Simulate

denotes a critical step

denotes a critical step SAT UNSAT *RECORDS 4.17E+01 (+/-4 CPM) for RM-6527B-2 CUE: After student determines that it is necessary to make RDMS data base changes, "Step 4.2.6.1 will be performed by the BOP operator and is in progress.

Continue with step 4.2.6.2" NOTE: If the student determines that it is not necessary to perform step 4.2.6, then the JPM is complete and the ...IPM is a failure. *4. DETERMINES the Need to Make RDMS Data Base Changes. *5. CALCULATES the New ALERT ALARM setpoint for each Channel. *DETERMINES that is necessary to perform step 4.2.6 Per step 4.2.6.2, multiplies the New COP Monitor Background Level recorded in step 4.2.4 by 1.5 *RECORDS 6.59E+01 (+/-6 CPM) for RM-6527A-1 *RECORDS 6.45E+01 (+/-6 CPM) for RM-6527A-2 *RECORDS 6.66E+01 (+/-6 CPM) for RM-6527B-1 *RECORDS 6.26E+01 (+/-6 CPM) for RM-6527B-2 Note to Evaluator

-Obtain Tear Off Sheets from student following ,IPM completion (Ops only). Page 5 of 8 PERFORMANCE D=Discuss ELEMENT/STEP P=Perform S=Simulate

denotes a critical step *6. CALCULATES the New HIGH ALARM setpoint for each Channel. CUE: "The JPM is complete." Stop time Evaluator calculates time to complete task.

EVALUATION

denotes a critical SAT UNSAT Per step 4.2.6.3, multiplies the New COP Monitor Background Level recorded in step 4.2.4 by 1.95 *RECORDS 8.56E+01 (+/-8 CPM) for *RECORDS 8.39E+01 (+/-8 CPM) for RM-6527A-2 *RECORDS 8.66E+01 (+/-8 CPM) for RM-6527B-1 *RECORDS 8.13E+01 (+/-8 CPM) for RM-6527B-2 Time to complete the task s 30 minutes. Note to Evaluator

-Obtain Tear Off Sheets from student following JPM completion (Ops only). Page 6 of 8 PERFORMANCE Provide comments on unsatisfactory performance of an element/step or for deviation from performance as stated. Record interruptions in performance such as retraining, shift change, and processing of procedure changes. Recommend remedial training, if necessary.

Note to Evaluator Obtain Tear Off Sheets from student following JPM completion (Ops only). Page 7 of 8 TEAR-OFF SHEET Directions to the Student: You are the Primary Operator.

You are going to verify the alert and alarm setpoints of the COP Exhaust Radiation Monitors prior to placing COP in service. The following information is provided to you: The plant is in Mode 1. The previous shift has made preparations to place COP in service per 081023.69 section 4.2. Perform the task per per 081023.69 Containment On-Line Purge Operation, section 4.2. Initiating Cue: U8 to Primary N80, "Primary Operator (or student's name), after reviewing the Gaseous Effluent Waste Containment Purge Release Permit, continue with preparations to place COP in service per 051023.69 step 4.2.3." Note to Evaluator

-Obtain Tear Off Sheets from student following JPM completion (Ops only). Page 8 of 8 Form C: GEW Containment Purge Release Permit -CH-L524 RELEASE PERMIT 1

______ SAMPLE DATEffIME:

Tod(l"-'-y/'-"O-"'-'OO""'o'--

_____ PURGE RELEASE RATE _

_____CFM EXPECTED CONTAINMENT PURGE RADIATION MONITOR RESPONSE 31.2 CPM The Containment Building purge requires Chemistry to sample as follows: SAMPLE the containment atmosphere prior to the start ofthe release. SAMPLE the Plant Vent 30 minutes after the start of the release. SAMPLE the Plant Vent within four hours after the release is terminated by Operations, or when two containment building volumes have been released (5.43E+06 cubic feet). Initiation of purge shall occur within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of sample date/time (see above). This permit assumes the purge will be at the Release Rate indicated above provided no startup, shutdown, or a thermal power change >15% in one hour has occurred.

If a startup, shutdown, or a thermal power change>15% in one hour has occurred during this purge, notify the Duty Chemistry Technician.

It is not necessary to stop the actual purge, but a new permit will have to be issued after new samples are collected and analyzed.

The purge may be interrupted (stopped and restarted) without obtaining new samples or issuing a new permit, provided one of the following conditions are met: For up to two hours, provided no startup, shutdown, or power change greater than 15% in one hour has occurred, with no factor of 3 increase in RCS DEI and PV Noble Gas. For up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , provided the purge is reinitiated within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ofthe sample date and time, with no factor of 3 increase in RCS DEI and PV Noble Gas. At any time after 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from the sample date and time for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , provided no startup, shutdown, or power change greater than 15% in one hour has occurred, and a two containment volume (5.43 E+06 cubic feet) has been released.

Chemistry Technician

______

___________________

_ Chemistry Supervision/SMIUS

________________

_ NOTIFY Chemistry of all purge interruptions.

Operations RECORD the following information: PURGE START DATE & TIME ____'---____ _ ____INITIALS PURGE FLOW RATE ______CFM CHEMISTRY TECH NOTIFIED OF PURGE STATE ._________INITIALS PURGE STOP DATE & TIME INITIALS CS0917.02 Rev. 10 Chg.12 Page 47 of 47

JOB PERFORMANCE MEASURE Sa Rev. 0 FR-H.1 BLEED AND FEED Student Name: LMS#: Evaluator Name: SAT UNSAT OFFICIAL NRC EXAMINATION ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2010 INITIAL EXAM SECURITY PREPARED BY: ___________________

DATE: _______ APPROVED BY: ____________________ TRAINING JOB PERFORMANCE Task Number and

Description:

Position:

RO 0060401501 Monitor The Safety Injection System When Activated 0060501201 Feed And Bleed The RCS During Inadequate Core Cooling Conditions: A reactor trip has occurred. A loss of all feedwater capability has forced a transition to FR-H.1, Response to loss of Secondary Heat Sink. Standards:

Initiate bleed and feed per FR-H.1, Response To loss Of Secondary Heat Sink. Student Materials:

Copy of the Tear-Off FR-H.1, Response to loss Of Secondary Heat Sink, Rev. Limitations on performance:

Perform all steps. Verbalize all actions to the Even if requested, no Peer Checks will be provided during the ..

References:

Procedures:

FR-H.1, Response To loss Of Secondary Heat Sys KA Description i ROISRO EPE 074 EK3.04 Tripping RCPs. 3.9/4.2 I EPE 074 EK3.05 Activating HPI system. 4.2/4.5 i EPE 074 Guidance contained in EOP for inadequate core 4.0/4.4 cooling I Sa Page 2 of 8 JOB PERFORMANCE

7.0 Setting

If performed as a pair with JPM Sh, Reset to IC # 81 or IC For stand alone, reset the simulator to IC #382 or any 100% IC which contains Initialize to the 100% IC and place simulator in RUN. Insert malfunctions mfRPS001 and mfRPS002 failure of automatic reactor trip Train A &B. In panel graphics section PCF07 insert override for RC-PCV-456B control switch to AUTO. Insert remote function rmvMSV129 Value=O Insert malfunctions mfFW039 and mfFW041 FW-P113 trip (faulty 86 device) Bus 4&5. Insert component remote function bkFW37B RF: rack-out, Rack out breaker for FW-P37B and mvFW347 RF: open breaker to deenergize breaker for FW-V347 EFW mini-floW valve. Place FW-P37B control switch in PTL. Insert malfunctions mfFW038 and mfFW054 Delay 10 seconds to trip both MFPs on low LO pressure. Complete all actions of FR-S.1 and when S/G WR levels <30% trip the reactor. Place the simulator in FREEZE. Place simulator in RUN (only as long as needed) to ensure all alarms are prior to start of Ensure 3 S/G WR levels <30%, conditions for immediate Bleed and Feed Place danger tags on the motor-driven EFW pump and mini-floW valve control

8.0 Safety

Considerations:

None 9.0 Approximate Completion Time: 15 minutes 10.0 Directions to the Student(s):

Evaluator gives Tear-Off sheet to the student You are the Secondary Operator.

You are going to evaluate the need for RCS bleed and feed, and perform the appropriate actions. The following information is provided to you: An ATWS and loss of both Main Feedwater pumps has occurred. FR-S.1 has just been successfully completed. The motor-driven EFW pump is tagged out. A transition from FR-S.1 to FR-H.1, Response To Loss Of Secondary Heat Sink, has occurred, and steps 1 & 2 are complete.

Sa Page 3 of 8 JOB PERFORMANCE You are the only Operator in the control room and you must perform all control board operations.

11.0 Initiating Cue: US to Secondary Operator: "Secondary Operator (or student's name), we will continue performing FR-H.1, beginning with the step 3 Caution." Sa Page 4 of 8 PERFORMANCE D=Discuss P=Perform S=Simulate ELEMENT/STEP

denotes a critical step STANDARD *denotes critical standard SAT NOTE: Ensure that student is ready to begin the "IPM before placing simulator in run. Start time _____ Initiating cue read. CUE: If the student requests a Peer Check at any time during the JPM, respond: "No one is available to peer check your actions. Please continue with the task". P Student identifies need RCS bleed and feed described in Step 3,

3. Check RCP status: All RCPs -STOPPED. (RNO) Stop all RCPs. *4. Actuate SI. 5. Verifies RCS Feed Path: Check pump status: CCPs -AT LEAST ONE RUNNING SI pumps -AT LEAST ONE RUNNING Check valve alignment for operating pumps PROPER EMERGENCY ALIGNMENT ON STATUS PANEL TRAIN A -Cold Leg Injection TRAIN B -Cold Leg Injection

6. Establish RCS Bleed Path: Verify power to PZR PORV block valves -AVAILABLE Verify PZR PORV block Sa Identifies 3 SG wide range levels <30%.

Verifies RCPs all running

Stops all RCPs *Actuates SI Verifies at least one CCP or SI Verifies proper valve alignment operating pumps on both Establishes RCS bleed path: Verifies power to PORV block Verifies PORV block valves both open. Page 5 of 8 PERFORMANCE D=Discuss P=Perform S=Simulate

7. P *8 P ELEMENT/STEP

denotes a critical step valves -BOTH OPEN Open both PZR PORVs Verify Adequate RCS Bleed Path: PORVs -BOTH OPEN PZR PORV block valves BOTH OPEN Perform the following: Open reactor head vent isolations: RC-FV-2881 RC-V323 CUE: "The JPM is complete." Stop time _____ Evaluator calculates the time to complete the task. Obtain from student: Tear Off Sheets and any other training materials used in the performance of the JPM STANDARD *denotes critical standard Performs the

. Opens

. Attempts to open PORV-455B. Verifies A PORV is open. Recognizes B PORV is closed. Verifies both block valves open Opens reactor head vents isolations:

.

. Time to complete the task s; 15 minutes.

SAT Sa Page 6 of 8 PERFORMANCE Provide comments on unsatisfactory performance of an element/step or for deviation from performance as stated. Record interruptions in performance such as retraining, shift change, and processing of procedure changes. Recommend remedial training, if necessary.

Sa Page 7 of 8 Directions to the Student: You are the Secondary Operator.

You are going to evaluate the need for ReS bleed and feed, and perform the appropriate actions. The following information is provided to you: An ATWS and loss of both Main Feedwater pumps has occurred. FR-S.1 has just been successfully completed. The motor driven EFW pump is DTO'd. A transition from FR-S.1 to FR-H.1, Response To Loss Of Secondary Heat Sink, has occurred, and steps 1 &2 are complete. You are the only operator in the control room, and you must perform all control board operations.

Initiating Cue: US to Secondary Operator: "Secondary Operator (or student's name), we will continue performing FR-H.1, beginning with the step 3 Caution." Sa Page 8 of 8

JOB PERFORMANCE MEASURE JPM Sb Rev. 0 RECOVER FROM A CRFRM ACTUATION Student Name: ___________

LMS#: Evaluator Name: SAT UNSAT OFFICIAL NRC EXAMINATION ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2010 INITIAL EXAM SECURITY PREPARED BY: _____________

DATE: _____ APPROVED BY: TRAINING JOB PERFORMANCE 1.0 Task Number and

Description:

Position:

RO 1050400301 Remove the control room ventilation system from the filter recirculation mode. 2.0 Conditions: The plant is at 100% power. I&C was performing maintenance on control room east air intake rad monitor 6506A2. It was in HIGH alarm due to this maintenance procedure.

The appropriate paperwork and Tech. Specs. were in place for performance of this maintenance. A spurious ROMS HIGH radiation alarm was subsequently received on control room east air intake rad monitor RM-6506A 1. This resulted in an "A" train CRFRM ESF actuation. F7009, CTL RM MAKEUP AIR FL TR RECIRC MODE, is in alarm. While the US was executing OS1252.02, AIRBORNE HIGH RADIATION, based on the HIGH rad signal on RM-6506A 1, I&C reported that the HIGH rad signals on 6506A 1 & RM-6506A2 were due to the maintenance activities.

After consultation with HP, the US has determined that the CRFRM Actuation was spurious. The US is now executing step 11 of OS1223.01 , LOSS OF CONTROL ROOM VENTILATION OR AIR CONDITIONING.

3.0 Standards

Secure from the CRFRM per OS1023.51, CONTROL ROOM VENTILATION AND AIR CONDITIONING SYSTEM OPERATION. Align control room ventilation to the normal makeup mode per OS1023.51, CR VENTILATION AND AIR CONDITIONING SYSTEM OPERATION.

4.0 Student

Materials:

Copy of the Tear-Off OS1023.51 , Control Room Ventilation and Air Conditioning System Operation, Rev Pages 1-5 and 5.0 Limitations on performance:

Simulate/Perform all steps. Verbalize all actions to the evaluator.

JPM Sb Page 2 of 9 JOB PERFORMANCE 6.0

References:

Procedures OS1223.01 , Loss of Control Room Ventilation or Air OS1023.51 , Control Room Ventilation and Air Conditioning System Technical Specifications 3.3.3.1, RAD MONITORING FOR PLANT 3.7.6, Sys KA Value 013 K1.13 HVAC. 013 K1.18 Premature Reset of ESF actuation. 1013 K4.10 Safeguards eq uip control reset. 3.3/3.7 1013 A3.02 Operation and actuated equipment.

4.1/4.2 2.1 2.1.30 Ability to locate and operate components.

4.3/4.4 2.1 2.1.23 Ability to perform integrated specific plant 4.4/4.0 procedures a" 072 K1.04 Control Room Ventilation. 7.0 Setting: If performed as a pair with JPM Sd, Reset to Ie # For stand alone, reset the simulator to IC #398 or any 100% IC which contains Initialize to the 100% IC Train A of normal CBA running and Train B of normal CBA in standby per OS1023.51 , CR VENTILATION AND AIR CONDITIONING SYSTEM Operation. Insert malfunctions mfRM014 RM-6506A-1 Final Value=200and mfRM015 6506A-2 Final Value=200 to actuate HIHI alarm Place the simulator in RUN. Ensure this 2 of 2 "A" train CRFRM signal resulted in the following CBA line-up: CBA-FN-27A is OFF. CBA-DP-53A remains OPEN (closes on "B" train CRFRM signal). CBA-FN-27B remains OFF. CBA-DP-53B remains CLOSED. CBA-DP-27A OPENS and CBA-FN-16A STARTS. CBA-DP-27B remains CLOSED and CBA-FN-16B remains OFF. CBA-DP-28 shuts. CBA-FN-15 is tripped. CBA-DP-1058 remains OPEN Delete the high rad malfunctions on RM-6506A 1 &RM-6506A2.

Acknowledge CP-295 to ensure rad monitors are "green". Place the simulator in FREEZE. Place the simulator in RUN. Acknowledge a" alarms. JPM Sb Page 3 of 9 JOB PERFORMANCE

8.0 Safety

Considerations:

None 9.0 Approximate Completion Time: 25 minutes 10.0 Directions to the Student(s):

Evaluator gives Tear-Off sheet to the student Initial Conditions: You are the Primary Operator.

You are going shutdown Train A of control room ventilation from filter recirculation mode and place Train A of the control room normal makeup and ventilation supply system in service per. 051023.51. The following information is provided to you: The plant is at 100% power. I&C was performing maintenance on control room east air intake rad monitor RM-6506A2.

It was in HIGH alarm due to this maintenance procedure.

The appropriate paperwork and Tech. Specs. were in place for performance of this maintenance. An RDMS HIGH radiation alarm was subsequently received on control room east air intake rad monitor RM-6506A 1. This resulted in an "Alpha" train CRFRM ESF actuation. F7009, CTL RM MAKEUP AIR FL TR RECIRC MODE, is in alarm. While the US was executing OS1252.02, AIRBORNE HIGH RADIATION, based on the HIGH rad signal on RM-6506A 1, I&C reported that the HIGH rad signals on RM-6506A 1 & RM-6506A2 were due to the maintenance activities.

After consultation with HP, the US has determined that the CRFRM Actuation was spurious. The US is now executing step 11 of OS 1223.01, LOSS OF CONTROL ROOM VENTILATION OR AIR CONDITIONING.

11.0 Initiating Cue: US to Primary Operator, "Primary Operator (or student's name), Shutdown the "An train of control room ventilation from filter recirculation mode and place the "An train of the control room normal makeup and ventilation supply system in service per. 051023.51.

All procedural Prerequsites have been completed.

JPMSb Page 4 of 9 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform

denotes a *denotes critical S=Simulate critical step standard SAT UNSAT 1. Start time _____ Initiating cue read. NOTE: Student should use OS1023.51 , sections 4.17 and 4.18. P CHECK/PLACE the following Checks the following switches in control switches to CR MAKE-UP AIR

CR MAKE-UP AIR TRAIN A FILTER TRAIN A FILTER RECIRC MODE. RECIRC MODE CR MAKE-UP AIR

CR MAKE-UP AIR TRAIN B FILTER TRAIN B FILTER RECIRC MODE. RECIRC MODE Both control switches should be in AUTO. When CBA-DP-27A goes full closed, CBA-FN-16A stops. When CBA-FN-16A stops, the CRFRM actuation signal resets. If the student does not wait until CBA-DP-27 A is closed, which in turn stops CBA-FN-16A, the "An train CRFRM actuation will reinitiate, causing CBA-DP-27A to re-open. *3. PLACE the following control Performs the following:

switches to STOP. and HOLD until the exhaust damper CLOSES: CBA-DP-27 A EMER MU Positions and holds CBA-DP-27 A *. FL TR control switch in STOP until the damper closes CBA-DP-27B EMER MU

Observes CBA-DP-27B already closed. FL TR DAMPER (Placing switch to close not required) US to student: "Use 051023.51 , section 4.18 to place Train A CBA Normal Ventilation In Service.". CHECK CLOSED/CLOSE Verifies CBA-DP-53B CBS-DP-53B, CR MU JPM Sb Page 5 of 9 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform

denotes a *denotes critical S=Simulate critical step standard SAT UNSAT P CHECK OPEN/OPEN CBA-Verifies open DP-53A, CR MU AIR *6. START CBA-FN-27 A, Control *Starts CBA-FN-27 A. Room makeup air fan CTL RM STATIC PRESS CONTROLLER is on CP-23. CP-23 is not simulated. When the student identifies actions for the CTL RM STATIC PRESS CONTROLLER on CP-23, Evaluator to student, "CTL RM STATIC PRESS CONTROLLER is in AUTO and set at 0.3 inches." S At CP-23, CHECK or PLACE Checks the CTL RM STATIC the CTL RM STATIC PRESS CONTROLLER in auto set at 0.3 CONTROLLER to AUTO at 0.3 P CHECK OPEN/OPEN Verifies CBA-DP-1058 is CBA-DP-1058, Control exhaust isolation P CHECK/PLACE the control Verifies CBA-FN-15 switch is in switch for CBA-FN-15, Room exhaust fan in When the student identifies actions for the CTL RM STATIC PRESS CONTROLLER on CP-23, Evaluator to student, "CTL RM STATIC PRESS CONTROLLER is in auto with input pressure indication at 0.3 inches WC." S At CP-23, CHECK or PLACE Checks the CTL RM STATIC the CTL RM STATIC PRESS CONTROLLER in auto set at 0.3 CONTROLLER to AUTO at 0.3 *11. PLACE and MAINTAIN the *Places CBA-DP-28 to open until control switch for CBA-DP-28, intermediate is indicated, and then releases Control Room exhaust to auto. modulate damper to OPEN until intermediate position of the damper is indicated, then allow the switch to spring return to AUTO JPM Sb Page 6 of 9 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform

denotes a *denotes critical S=Simulate critical step standard SAT UNSAT P VERIFY CBA-FN-15, Control Verifies CBA-FN-15 Room exhaust fan Since the simulator does not model the "Modulate" function, When the student monitors CBA-DP-28 position indication, provide the cue: "Both the Red and Green position indication lights are lit." S VERIFY CBA-DP-28, Control Verifies CBA-DP-28 modulates to Room exhaust modulate damper MODULATES control (If required)

Evaluator to student, "CTL RM STATIC PRESS CONTROLLER input pressure indication is 0.3 inches WC and stable. II "The JPM is complete." Stop time _____ Time to complete the task s 25 minutes. Evaluator calculates the time complete the Obtain from Tear Off Sheets and any training materials used in performance of the JPM Sb Page 7 of 9 PERFORMANCE Provide comments on unsatisfactory performance of an element/step or for deviation from performance as stated. Record interruptions in performance such as retraining, shift change, and processing of procedure changes. Recommend remedial training, if necessary.

JPM Sb Page 8 of 9 TEAR-OFF SHEET FOR LOIT ..IPM Sb RECOVER FROM A CRFRM Directions to the Student: You are the Primary Operator.

You are going shutdown Train A of control room ventilation from filter recirculation mode and place Train A of the control room normal makeup and ventilation supply system in service per OS1023.51. The following information is provided to you: The plant is at 100% power. I&C was performing maintenance on control room east air intake rad monitor RM-6506A2.

It was in HIGH alarm due to this maintenance procedure.

The appropriate paperwork and Tech. Specs. were in place for performance of this maintenance. An RDMS HIGH radiation alarm was subsequently received on control room east air intake rad monitor RM-6506A 1. This resulted in an "Alpha" train CRFRM ESF actuation. F7009, CTL RM MAKEUP AIR FL TR RECIRC MODE, is in alarm. While the US was executing OS1252.02, AIRBORNE HIGH RADIATION, based on the HIGH rad signal on RM-6506A1, I&C reported that the HIGH rad signals on RM-6506A 1 & RM-6506A2 were due to the maintenance activities.

After consultation with HP, the US has determined that the CRFRM Actuation was spurious. The US is now executing step 11 of OS1223.01 , LOSS OF CONTROL ROOM VENTILATION OR AIR CONDITIONING.

Initiating Cue: US to Primary Operator, "Primary Operator (or student's name), Shutdown the "A" train of control room ventilation from filter recirculation mode and place the "A" train of the control room normal makeup and ventilation supply system in service per. OS1023.51.

All procedural Prerequsites have been completed.

JPM Sb Page 9 of 9

SEABROOK JOB PERFORMANCE MEASURE JPM New Sc Rev. Loss of Containment Instrument Student Name: LMS#: Evaluator Name: SAT UNSAT OFFICIAL NRC EXAMINATION ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2010 INITIAL EXAM SECURITY PREPARED BY: DATE: APPROVED BY: DATE:

PERFORMANCE D=Discuss ELEMENT/STEP EVALUATION P=Perform S=Simulate

denotes a critical step

denotes a critical SATUNSAT Task Number and

Description:

NA Conditions:

A The plant is at about 95% power. S. SA-C-4B is tagged out of service for motor replacement.

C. SA-C-4A has just tripped. D. The US has directed performance of OS1242.02 , Loss Of Containment Instrument Air. Standards:

Restore containment instrument air pressure. Student Materials:

Copy of the Tear-Off sheet. OS1242.02 , Rev 11 Limitations on performance:

Simulate all steps. Verbalize all actions to the evaluator.

Even if requested, no Peer Checks will be provided during the JPM.

References:

Procedures:

OS1242.02 , Loss Of Containment Instrument Air Sys KA 078 Knowledge of the physical connections andlor cause-effect relationships between the lAS Containment 078 K3.01 Knowledge of the effect that a loss or malfunction of the lAS will have on the Containment air 078 A3.012 Ability to mnonitor automatic operation of the lAS, including Air JPM Sc Page 2 of7 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform S=Simulate

denotes a critical step

denotes a critical step SATUNSAT 7. Setting: If performed as a pair with JPM Sg, Reset the simulator to IC# For stand alone performance, reset the simulator to IC #30 or any IC which contains the Initialize to any 100% IC and place the simulator in RUN. Reduce power to 95% C. Place SA-C-4B control switch to OFF and Tag D. Rack out the breaker for SA-C-4B as SELECT Component Remote SELECT SERVICE AIR DOUBLE CLICK cSAC4B, SA Compressor 4b 460V MCC E631 SELECT Trip SA-C-4A as SELECT Component Remote SELECT SERVICE AIR DOUBLE CLICK cSAC4A, SA Compressor 4A 460V MCC E531 SELECT Place the simulator in FREEZE. 8. Safety Considerations:

None. 9. Approximate Completion Time: 10 mins 10. Directions to the Student: Evaluator gives Tear-Off sheet to the student Initial Conditions: You are the Secondary Operator SA-C-4B is tagged out due to a motor replacement. SA-C-4A has just tripped. 11. Initiating Cue: US to Secondary Operator, "Secondary Operator (or student's name), Due to the loss of the only operating Containment Air Compressor, perform the required actions of ON1242.02 , Loss Of Containment Instrument Air. JPM Sc Page 30f7 DATA SHEET FOR JPM Sc CUE: If the student requests a Peer Check at any time during the JPM, respond: "No one is available to peer check your actions. Please continue with the task". 1. Start time _____ Initiating cue read 2. P Check Containment Instrument Air System: NOTE: The performance of either bulleted step below will allow transition to the RNO. Containment instrument air pressure -GREATER THAN 95 PSIG AND INCREASING OR Containment instrument air compressors

-BOTH RUNNING *3. Perform The following:

a. Cross connect containment instrument air system with instrument air by opening the following valve:

IA-V530 Checks Containment instrument air pressure GREATER THAN 95 PSIG AND INCREASING, answer is; No Checks Containment instrument air compressors BOTH RUNNING, answer is; None running. Student refers to Step 1 RNO *a. Opens IA-V530 The following step is a long-term action and is met by determining instrumentation/MPCS points that will be used Monitor containment

Monitors containment pressure pressure for instrument air for instrument air header header leakage. leakage. When directed to cycle breaker, respond: "Understand, cycle the breaker for SA-C-4A at MCC 531, Node <093>." Verify that the control switch for SA-C-4A is in OFF. *4. I F a compressor has tripped, reset the compressor by cycling the supply breaker: SAC-4A MCC-531,Node

<093> *Directs NSO to cycle the supply breaker for SAC-4A at MCC 531, Node <093> Page 4 of 7 DATA SHEET FOR ..IPM Sc CUE: Simulator Operator:

Following verification that the control switch is in off; Delete Component Malfunction; csAC4A SA Compressor 4a 460V MCC E531 093 IF a compressor has tripped, reset the compressor by cycling the supply breaker: SAC-4B MCC-631 ,Node <095>

Recognizes that SAC-4B is tagged out. Breaker cannot be cycled. NOTE: With low IA header pressure indicated, the compressor will start when the control switch is taken to the AUTO position.

Manually restart compressor.

*Places the SA-C-4A control switch to AUTO. CUE: "The JPM is complete." 5. Stop time _____ Evaluator calculates the time to complete the task. Time to complete the task minutes. 10 6. Obtain from student: Tear Off Sheets and any other training materials used in the performance of the JPM ..IPM Sc Page 5 of 7 PERFORMANCE Provide comments on unsatisfactory performance of an element/step or for deviation from performance as stated. Record interruptions in performance such as retraining, shift change, and processing of procedure changes. Recommend remedial training, if necessary.

JPM Page 6 of 7 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform S=Simulate

'" denotes a critical step '" denotes a critical step SAT UNSAT Directions to the Student: Initial Conditions:

1. You are the Secondary Operator 2. SA-C-4B is tagged out due to a motor replacement.

3. SA-C-4A has just tripped. Initiating Cue: US to Secondary Operator, "Secondary Operator (or student's name), Due to the loss of the only operating Containment Air Compressor, perform the required actions of ON1242.02 , Loss Of Containment Instrument Air . ..IPM Sc Page 70f7

JOB PERFORMANCE MEASURE JPM Sd Rev. TRANFER SERVICE WATER FROM THE COOLING TOWER TO THE Student Name: LMS#: Evaluator Name: SAT UNSAT OFFICIAL NRC EXAMINATION ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2010 INITIAL EXAM SECURITY PREPARED BY: DATE: APPROVED BY:

DATE: ________ TRAINING SUPERVISOR JOB PERFORMANCE

1. Task Number and Description RO SBK Switch From SW To Cooling Tower Operation

2. Conditions: The plant is operating at 100% power. On line maintenancelretests are complete on the Service Water system Train A pump house valves. The SM has directed that Train A Service Water be transferred back to the ocean from the cooling tower. All pre-starts are complete for the "A" Service Water pump (SW-P-41A).

3. Standards:

Return Service Water operation to the ocean per OS1016.05.

4. Student Materials:

Copy of Tear Off Copy of OS1016.05 Service Water Cooling Tower Operation, Rev. 10. Section 2 and pages 5-9, Section 4.4 pages 26-28, Figures 1-5 pages 55-61, and Form 001-05 Pump Pre-start guidelines SW-P-41A page 49, Rev. 5. Limitations On Performance:

Perform all steps. Verbalize all actions to the Even if requested no Peer Checks will be provided during the 6.

References:

Procedures: OS1016.05 Service Water Cooling Tower Operation Value Sys Description RO/SRO 076 Ability to predict the impacts of loss of SW 3.5/3.7 and use procedures to correct, control, or mitigate the consequences of those malfunctions or operations.

076 Knowledge of the effect that a loss of SW 3.4/3.6 will have on closed cooling water. JPMSd Page 2 of 8 i i JOB PERFORMANCE

7. Setting: If performed as a pair with JPM Sb, Reset to IC # For stand alone, Reset the simulator to IC #363 or any 100% IC which contains Initialize to any 100% IC and place the simulator in RUN. Place Train A Service Water on the cooling tower per OS1016.05, Service Water Cooling Tower Operation. Insert component malfunction cSWV22 460V MCC E514 CR7 fail closed. Place SW-P-41C control switch in PTL Insert component remote function cSWP41 C 4.16KV Bus E5 AQ4 RF:rackout. Insert component remote function cSWV22 460V MCC E514 CR7 RF:open breaker. Insert malfunction mfSW001 SW-P-41A OC trip. Place the simulator in RUN. Acknowledge all alarms. Place tags on SW-P-41 C and V-22 control switches.

8. Safety Considerations:

None. 9. Approximate Completion Time: 20 minutes 10. Directions To The Student: Evaluator gives Tear Off sheet to the student. Initial Conditions: You are the Secondary Operator. The following information is provided to you: The plant is operating at 100% power. On line maintenance/retests are complete on the Service Water system Train A pump house valves. The SM has directed that Train A Service Water be transferred back to the ocean from the COOling tower. All pre-starts are complete the "A" Service Water purnp (SW-P-41A).

JPM Sd Page 3 of 8 JOB PERFORMANCE

11. Initiating Cue: US to Secondary Operator, "Secondary Operator (or student's name), using OS1016.05 , section 4.4, transfer Train A Service Water from the Cooling Tower to the ocean. All prerequisites, limitations, and pre-starts for SW-P-41A are complete." JPM Sd Page 4 of 8 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform S=Simulate

denotes a critical step

denotes a critical step SAT UNSAT 1. Start time _____ Initiating cue read CUE: If the student requests a Peer Check at any time during the JPM respond, "No one is available to Peer Check your actions. Please continue with the task." NOTE: Student may re-verify prerequisites, precautions

&limitations and pre-starts.

CUE: If student asks, state: "The fire protection system has not been used to fill the cooling tower, no chemistry sampling is required." CUE: Inform student: "Form L, Cooling Tower Flush NPDES Tracking Sheet has been recorded and tracked by US." NOTE: Student may put up color graphic on the MPCS for Service water. P Check SW Train B is aligned to the Checks SW Train B is aligned to ocean. *3 Record initial Cooling tower level from *Records initial Cooling tower either SW-Ll-6139 or A1537 and from either SW-Ll-6139 or A1537 record on Form L. record on Form When student attempts to determine the position of SW-V-44, provide cue, "SW-V-44 is open/' P If SW-V-44, SW isolation from the Investigates the position of intake structure is closed, perform If the student begins to perform pump pre-start checks, provide cue, "All pre-starts are complete." If the student inquires about the prestart checklist requiring SW-V-20, 34, and 54 in a different position, respond: "SW-V-20, 34, and 54 are repositioned by the performance of the procedure, continue with the procedure." P Perform SW ocean pump pre-starts Inquires / Determines that the as determined by the Us. room pre-start checks are P Open SW-V-20, SW Train A to *Opens SW-V-20, SW Train A discharge structure.

discharge JPM Sd Page 5 of 8

D=Discuss ELEMENT/STEP P=Perform S=Simulate

denotes a critical step *7. P Close SW-V-34, SW Train A return to cooling tower. *8. p Simultaneously place and hold control switch for SW-V54, cooling tower pump A discharge to throttle close and control switch for SW-V-56, cooling tower Train A spray header test to open until valves reposition EVALUATION

denotes a critical SATUNSAT *Closes SW-V-34, SW Train A return to cooling tower. *Simultaneously manipulate switches until valves reposition as follows: SW-V-54 control switch to throttle close SW-V-56 control switch to open CUE: If requested to make a plant announcement, inform the student; "The announcement for starting Service Water pump 41A has been made." CUE: If informed that the COOling tower basin low level alarm has been received, inform student; "Copy, low cooling tower basin level. I will dispatch a field operator to initiate fill of the COOling tower basin." *9. P Start the desired Train A ocean SW pump. *Starts SW-P-41A.

CUE: If student informs US that SW-P41A tripped, respond; "Continue with the procedure." 10. P Verify the selected SW pump discharge valve opens. *11. P In accordance with caution prior to step 4.4.9: Reopen SW-V-54 CUE: "The JPM is complete." 12. Stop time ____ Evaluator calculates time to complete task 13. Obtain from student: Tear Off sheets and any other training materials used in performance of this JPM. JPMSd Recognizes SW-V-2 not open and SW-P-41A tripped *Re-opens SW-V-54 Time to complete task :5 20 minutes Page 6 of 8 PERFORMANCE Provide comments on unsatisfactory performance of an element/step or for any deviation from performance as stated. Record interruptions in performance such as retraining, shift change, and processing of procedure changes. Recommend remedial training, if necessary.

JPMSd Page 7 of 8 TEAR OFF SHEET FOR LOIT JPM Sd Directions To The Student: Initial Conditions: You are the Secondary Operator. The following information is provided to you: The plant is operating at 100% power. On line maintenancelretests are complete on the Service Water system Train A pump house valves. The SM has directed that Train A Service Water be transferred back to the ocean from the cooling tower. All pre-starts are complete for the "Aft Service Water pump (SW-P-41A).

Initiating Cue: US to Secondary Operator, "Secondary Operator (or student's name), using OS1016.05 , section 4.4, transfer Train A Service Water from the Cooling Tower to the ocean. All prerequisites, limitations, and for SW-P41A are complete.

JPM Sd Page 8 of 8

JOB PERFORMANCE MEASURE JPM Se Rev. LOWER SI ACCUMULATOR Student Name: ____________

LMS#: Evaluator Name: SAT UNSAT OFFICIAL NRC EXAMINATION ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2010 INITIAL EXAM SECURITY PREPARED BY: DATE: APPROVED BY: __

DATE: ______ TRAINING SUPERVISOR JOB PERFORMANCE Task Number and Description Position RO SBK 0060100201 Monitor The Safety Injection System Conditions:

2.1 The "An Accumulator Level has increased to above the Technical Specification Limit due to containment 1 system temperature increase. Standards:

Decrease the "A" Accumulator level to within the limitations of Technical Specifications.

(6121 to 6596 gallons at 585 to 664 psig) Student Materials:

Copy of Tear Off Copy of OS1005.05 Safety Injection System Operation Rev. 12, Pages Limitations On Performance:

Perform all steps. Verbalize all actions to the Even if requested no Peer Checks will be provided during the

References:

Procedures:

OS1005.05 Safety Injection System Technical

3.5.1.1 ECCS Accumulators

-Hot Standby, Startup, and Power Operation Drawings 1-SI-820455 Safety Injection System Value Sys Description RO/SRO 006 Ability to predict andlor monitor (to 3.5/3.7 prevent exceeding design basis limits) accumulator pressure, level, boron concentration.

JPM Se Page 2 of 8 JOB PERFORMANCE Setting: If performed as a pair with JPM Sf, Reset to IC # For stand alone, Reset the simulator to any 1 OO%IC which contains the Initialize to an IC at 100% power. Raise "A" Accumulator level to > 6473 Gallons. Verify F5498, SI Accumulator Level High alarm is in. Use "GD ACCUMS" on MPCS to view Accumulator level and pressure "A" points. Verify "A" Accumulator pressure is 640-660 psig., or adjust as necessary. Using Safety Injection Local Panel, OPEN SI-V-67. Freeze the simulator. Safety Considerations:

None. Approximate Completion Time: 20 minutes Directions To The Student: Evaluator gives Tear Off sheet to the student. Initial Conditions: You are the Primary Operator and you are going to the lower the "A" Accumulator level to within limits of Tech. Specs. You may use MPCS Group Display "GD ACCUMS" to view Accumulator level and pressure "A" points or SVD A0413 for "A" Accumulator level. The following information is provided to you: The "A" Accumulator level has increased due to normal system heatup. All applicable prerequisites of OS1005.05 Safety Injection System Operation are complete. The Primary NSO is standing by to support local valve manipulations. Initiating Cue: US to PSO "Primary Operator (or student's name), lower the 'A' Accumulator level to 6400 gals., +/-50 gals., using 081005.05 , "8afety Injection System Operation." ..'PMSe Page 3 of 8 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform S=Simulate

denotes a critical step

denotes a critical step SAT UNSAT Start time _____ Initiating cue read If the student requests a Peer Check at any time during the JPM respond, "No one is available to Peer Check your actions. Please continue with the task." If the student inquires about consideration for initially raising accumulator pressure, respond; "Pressure appears to be sufficient, continue with lowering level and monitor pressure as appropriate." P If desired, PRESSURIZE the Determines that accumulator to be drained per Section pressure is sufficient to support 4.4, Pressurizing an Accumulator.

drain-down If student requests leak testing status, respond, "Check valve leak testing is not in progress." P VERIFY that check valve leak testing VERIFIES that check valve is not in progress.

testing is not in P CHECK CLOSED/CLOSE SI-V-157, CHECKS CLOSED SI-V-157, SI accumulator fill. accumulator P CHECK CLOSED/CLOSE SI-V-62, CHECKS CLOSED SI-V-62, test test line header isolation ORC. header isolation 6 CHECK CLOSED/CLOSE SI-V-131, CHECKS CLOSED SI-V-131, test iso for SI cold legs 1,2,3,4 iso for SI cold legs If the student indicates that they would use an electronic database to determine valve locations for the following step. respond; "The Primary NSO is standing by to perform local actions for SI*V*67 and 69." *7. ALIGN the SI test header to the by performing the When the Primary NSO is directed to check open/open SI-V-67, provide repeat-back and respond: "SI*V-67 has been opened." CHECK OPEN/OPEN SI-V-67, * *Directs local actions to CHECK isolation for PDT and boron OPEN/OPEN SI-V-67, isolation for recovery storage tanks 66A and PDT and boron recovery storage JPM Se Page 4 of 8 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Petiorm S=Simulate

denotes a critical step

denotes a critical step SAT UNSAT tanks 66A and 668. CUE: When the Primary NSO is directed to check closed/close SI-V-69, provide repeat-back and respond: "SI-V-69 is closed." CHECK CLOSED/CLOSE SI-V-69, test line isolation for RWST. Directs local actions to CHECK CLOSED/CLOSE SI-V-69, test line isolation for RWST. CUE: If student inquires respond, "51 test header pressure will not be monitored at this time." 8. P If SI test line pressure is to be monitored, then UNLOCK and OPEN SI-V-61, SI-PI-929/PT-2491 isolation.

9 P OPEN SI-V-70, test line header isolation IRC. *10 P OPEN the valve for the accumulator to be drained:

SI-V-1S, accumulator A drain/fill isolation

11 P CYCLE OPEN and CLOSED SI-V-62, test line header isolation ORC and MONITOR accumulator level and pressure.

12 P When accumulator has been drained to the desired level, CLOSE the valve opened in step 4.6.9:

SI-V-1S, accumulator A drain/fill isolation CUE: "The JPM is complete." 9. Stop time ____ Evaluator calculates time to complete task JPM Se Inquires / determines that SI test line pressure will not be monitored.

OPENS SI-V-70, test line header isolation IRC. *OPENS SI-V-1S, accumulator A drain / fill isolation.

CYCLES OPEN and CLOSED SI-V-62, test line header isolation ORC and MONITORS accumulator level and pressure.

When "An accumulator level is 6400 gals, +/-SO gals, CLOSES SI-V-1S, accumulator A drain/fill isolation.

Time to complete task S; 20 minutes Page S of 8 PERFORMANCE D=Discuss P=Perform S=Simulate ELEMENT/STEP

denotes a critical step STANDARD

denotes a critical step EVALUATION SAT UNSAT 10. Obtain from student: Tear Off sheets and any other training materials used in performance of this ..IPM. JPM Se Page 6 of 8 PERFORMANCE Provide comments on unsatisfactory performance of an elemenUstep or for any deviation from performance as stated. Record interruptions in performance such as retraining, shift change, and processing of procedure changes. Recommend remedial training, if necessary.

JPM Se Page 7 of 8 TEAR OFF SHEET FOR ..IPM Se Directions To The Student: Initial Conditions: You are the Primary Operator and you are going to the lower the "A" Accumulator level to within limits of Tech. Specs. You may use MPCS Group Display "GO ACCUMS" to view Accumulator level and pressure "A" points or SVD A0413 for "A" Accumulator level. The following information is provided to you: The "A" Accumulator level has increased due to normal system heatup. All applicable prerequisites of OS1005.05 Safety Injection System Operation are complete. The Primary NSO is standing by to support local valve manipulations.

Initiating Cue: US to PSO "Primary Operator (or student's name), lower the 'A' Accumulator level to 6400 gals., +/*50 gals., using OS1005.05 , "Safety Injection System Operation." ..IPMSe Page 8 of 8

JOB PERFORMANCE MEASURE JPM Sf Rev. 0 EMERGENCY TRIP OF DIESEL GENERATOR 1 B Student Name: ___________

LMS#: Evaluator Name: SAT UNSAT OFFICIAL NRC EXAMINATION ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2010 INITIAL EXAM SECURITY PREPARED BY: DATE: APPROVED BY: ____________

DATE: _______ TRAINING SUPERVISOR JOB PERFORMANCE Task Number and

Description:

Position:

RO 0640402501 Restore off-site power to Bus E5/E6 Conditions: Bus E6 was being supplied by the RAT (Reserve Auxiliary Transformer) to support a scheduled UAT (Unit Auxiliary Transformer) breaker inspection.

The tagging clearance for the UAT breaker had not been started. A failure on the Bus 6 RAT breaker caused the breaker to trip open. DG "B" started and restored power to bus E6. Plant conditions have stabilized.

The Shift Manager has directed the Unit Supervisor to transfer bus E6 to the UAT and shutdown DG "B". The SM and US have decided to use Attachment L of OS1246.01 , LOSS OF OFFSITE POWER-PLANT SHUTDOWN, as guidance in restoring off-site power to bus E6. Standards:

Attempt to restore off-site power to bus E6 and respond to degraded DG "B" condition as necessary. Student Materials:

Copy of the Tear-Off Attachment L of OS1246.01 , LOSS OF OFFSITE POWER-PLANT SHUTDOWN, Rev. limitations On Performance:

Simulate/Perform all steps. Verbalize all actions to the evaluator.

Even if requested, no peer checks will be provided during the JPM.

References:

Procedures:

Attachment L of OS1246.01 , LOSS OF OFFSITE POWER-PLANT SHUTDOWN Sys KA Description Value RO/SRO 064 A4.07 Ability to manually operate and/or monitor in the 3.4/3.4 control room: Transfer EDG with load to grid. Setting: JPMSf Page 2 of 9 JOB PERFORMANCE Simulator If performed as a pair with JPM Se, Reset to IC # For stand alone, Initialize the simulator to any 100% power IC with the following Place the simulator in RUN. Transfer Bus E6 to the RAT. Place the UAT breaker in Normal After Stop. Remove CS-P-2B from service by placing Danger Tags and racking out the breaker. CS-P-2B is removed from service so it does not interfere with the JPM. The CCP's start on a LOP. SELECT: Component Remote SELECT: bkCS1 P2B_52 Insert component malfunction:

bkEDE6RAT, 4160V Bus E6 A72 trip. Check for the following:

EPS sequenced loads start, as applicable with the plant remaining at power.

SGBD isolated.

SW-V-5 closed. Clear RAT amber light and PLACE RAT breaker in PTL 8.0 Safety Considerations:

None 9.0 Approximate Completion Time: 20 minutes 10.0 Directions To The Student(s):

JPM Sf Page 3 of 9 JOB PERFORMANCE Evaluator gives Tear-Off sheet to the student. Initial Conditions: You are the Secondary Operator. The following information is provided to you: Bus E6 was being supplied by the RAT (Reserve Auxiliary Transformer) to support a scheduled UAT (Unit Auxiliary Transformer) breaker inspection.

The tagging clearance for the UAT breaker had not been started. A failure on the Bus 6 RAT breaker caused the breaker to trip open. DG "B" started and restored power to bus E6. Plant conditions have stabilized.

The Shift Manager has directed the Unit Supervisor to transfer bus E6 to the UAT and shutdown DG "B". The SM and US have decided to use Attachment L ofOS1246.01 , LOSS OF OFFSITE POWER-PLANT SHUTDOWN, as guidance in restoring off-site power to bus E6. 11.0 Initiating Cue: Unit Supervisor to Secondary Operator, "Restore offsite power to bus E6, via the UAT, using Attachment L of 051246.01 , LOSS OF OFFSITE POWER-PLANT SHUTDOWN." JPM Sf Page 4 of 9 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform S=Simulate

denotes a critical step

denotes a critical step SAT UNSAT Start time Initiating cue read. Evaluator CUE: If the student asks if the grid is stable, respond: "The grid is stable." 2 IF AC emergency bus is Recognizes that Bus 6 is energized and deenergized, THEN restore continues with step 2. offsite power as follows: 3 Raise DG frequency to 60.2 to Raises "B" DG frequency to 60.2 to 60.4 Hz. 60.4 Hz. *3 Place the DG synch. Selector *Places the Bus 6 synch. Selector switch in switch in the RAT or UA T the UA T position.

position.

4 Reset RMO (Remote Manual *Resets "B" Train RMO. Override).

5 Adjust EDG voltage to match Matches "B" EDG voltage .+/-..1 0 INCOMING VOL TS RUNNING *6 Adjust EDG frequency so that

Adjusts "B" EDG speed as required.

the synch meter is going slowly in the fast direction.

7 Close the RAT or UA T *Closes the Bus 6 UA T breaker when Transformer breaker when synchronized.

synchronized.

8 Place the synch selector switch Places the Bus 6 synch selector switch in in OFF. OFF. Instructor NOTE: The DB B Lube Oil Pressure Low and DG B Aux. Lube Oil Pump Running alarms should be initiated before the EDG can be unloaded.

JPM Sf Page 50f9 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform S=Simulate

denotes a critical step

denotes a critical step SAT UNSAT Evaluator NOTE: Wait for the associated low lube oil pressure alarms to go into alarm prior to providing the following CUE. Evaluator CUE: Before the student starts unloading the EDG, the NSO makes an urgent report to the Control Room via the radio, " Control Room this is the Rover NSO at the Bravo Emergency Diesel. There is a large amount of lube oil spraying from the Bravo diesel engine." Instructor CUE: Run scenario:

Len, DG Test Insert malfunction:

svo6608DGB f: Insert malfunction:

svo6611 DGB f: NOTE: On a low lube oil condition the emergency diesel engines should automatically trip. This scenario simulates failure of the automatic trip. Based on the VAS (Video Alarm System) alarm and report from the field, it is expected that the candidate will perform a manual emergency shutdown of the diesel generator.

9 Acknowledge the report from Acknowledges the report from the field. the field and the MPCS VAS (Video Alarm System) alarm Acknowledges the MPCS VAS alarm condition.

condition.

Evaluator NOTE: The intention of the JPM is for the student to identify and recommend/perform an emergency shutdown of EDG 1 B. Evaluator CUE: If the student recommends stopping the diesel generator, say: "Perform an emergency shutdown of EDG 1 B." *10 Perform emergency shutdown *Performs an emergency of DG-1 B by simultaneously shutdown of DG-1 B by simultaneously pressing BOTH Emergency pressing BOTH Emergency Stop Stop pushbuttons.

push buttons. Evaluator CUE: "The JPM is complete." Stop time Start-Stop is minutes. Evaluator calculates the time to complete the task. "IPM Sf Page 6 of 9 12 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform S=Simulate

denotes a critical step

denotes a critical step SAT UNSAT Obtain from Tear Off sheets and any training materials used performance of this JPM Sf Page 7 of 9 PERFORMANCE Provide comments on unsatisfactory performance of an element/step or for deviation from performance as stated. Record interruptions in performance such as retraining, shift change, and processing of procedure changes. Recommend remedial training, if necessary.

JPM Sf Page 8 of 9 TEAR-OFF SHEET FOR JPM Sf Directions to the Student: Initial Conditions: 1 You are the Secondary Operator. The following information is provided to you: 8us E6 was being supplied by the RAT (Reserve Auxiliary Transformer) to support a scheduled UAT (Unit Auxiliary Transformer) breaker inspection.

The tagging clearance for the UAT breaker had not been started. A failure on the 8us 6 RAT breaker caused the breaker to trip open. DG "8" started and restored power to bus E6. Plant conditions have stabilized.

The Shift Manager has directed the Unit Supervisor to transfer bus E6 to the UAT and shutdown DG "8". The SM and US have decided to use Attachment L of OS1246.01 , LOSS OF OFFSITE POWER-PLANT SHUTDOWN, as guidance in restoring off-site power to bus E6. Initiating Cue: Unit Supervisor to Secondary Operator, "Restore offsite power to bus E6, via the UAT, using Attachment L of OS1246.01 , LOSS OF OFFSITE POWER-PLANT SHUTDOWN." JPM Sf Page 9 of 9 JOB PERFORMANCE MEASURE JPM Sg Rev. RECOVER A DROPPED ___________ Student Name: Evaluator Name: SAT UNSAT OFFICIAL NRC EXAMINATION ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2010 INITIAL EXAM SECURITY PREPARED BY: ____________

DATE: APPROVED BY: ____________

DATE: _____ TRAINING SUPERVISOR JOB PERFORMANCE Task Number and Description Position RO SBK 0010400301 Operate single full length control rod (misalignment) Conditions: The plant is at approximately 95% power following a dropped rod in control bank D (CBD) group 2, identified as H-8. The plant has been stabilized using turbine load control, with rod control in manual. I&C has completed replacing a blown fuse on the stationary gripper. Standards:

Align the dropped rod with its bank per OS1210.05 Dropped Rod. Student Materials:

Copy of Tear Off Copy of OS121 0.05 Dropped Rod Rev Limitations On Performance:

Perform all steps. Verbalize all actions to the Even if requested no Peer Checks will be provided during the

References:

Procedures:

OS1210.05 Dropped Technical 3.1.1.1 SDM Tavg Greater Than 200 0 3.1.3.1 Moveable Control Assemblies Group height 3.1.3.2 Moveable Control Assemblies Position Indication Systems 3.1.3.5 Shutdown Rod Insertion Limit 3.1.3.6 Control Rod Insertion Limit 3.2.1 Axial Flux Difference

3.2.4 Quadrant power Tilt 1-NHY-509049 Rod Control ..IPM Page 2 of JOB PERFORMANCE Value Sys Description ROISRO 001 Knowledge of CRDS design features 3.9/4.1 and/or interlocks which provide for recovery of a dropped rod Setting: Simulator:

If performed as a pair with JPM Sc, Reset the simulator to IC# For stand alone, Reset the simulator to IC# 300 or any 100% IC and reduce power -95% power. Complete simulator setup by performing the Insert malfunction mfCP01B, Dropped Rod Place the simulator in RUN and stabilize the plant per Place rods in MANUAL. Match TavelTref by reducing turbine load. Acknowledge alarms. Verify Bank Demand Counters reflect expected plant conditions. Delete malfunction mfCP01B, Dropped Rod H-B. Place the simulator in RUN as long as needed to ensure all alarms are acknowledged prior to start of the JPM. Safety Considerations:

None Approximate Completion Time: 20 minutes Directions To The Student(s):

Evaluator gives Tear Off sheet to the student. Initial Conditions: You are the Primary Operator.

You are going to recover a dropped rod. The following information is provided to you: The plant is at approximately 95% power following a dropped rod in control bank D (CBD) group 2, identified as H-B. The plant has been stabilized using turbine load control, with rod control in manual. I&C has completed replacing a blown fuse on the stationary gripper. JPM Sg Page 3 of 10 JOB PERFORMANCE

11. Initiating Cue: US to Primary Operator, "Primary Operator (or student's name), we are at step 4 of 051210.05 , Dropped Rod. Continue with the procedure and recover the dropped rod." JPM 8g Page 4 of 10

--PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform S=Simulate

denotes a critical step

denotes a critical step SAT UNSAT Start time _____ Initiating cue read If the student requests a Peer Check at any time during the JPM respond, "No one is available to Peer Check your actions. Please continue with the task." Note prior to step 4 should be reviewed, if student contacts SM or RE for rod recovery recommendation, respond: "Recover the dropped rod in an expeditious manner." P Check rod control urgent failure alarm -RESET 07746 Local power cabinet Local logic cabinet Checks rod control urgent failure alarm -RESET D7746 Contacts NSO and Inquires about Local power cabinet alarm. Contacts NSO and Inquires about Local logic cabinet alarm CUE: When student requests the NSO to locally verify logic and power cabinet alarms, respond, "There are currently no alarms on the logic or power cabinets." *3. Align rod control system for dropped rod recovery: Place the rod bank selector switch to -Affected Bank Position Except for the dropped rod, place all the lift coil disconnect switches for the affected bank to -Rod Disconnected Record the affected group step counter position. Place the rod bank selector switch to -CBD Places all the lift coil disconnect switches for the Control Bank D to -Rod Disconnected except for rod H-8 Records the CBD group 2 counter JPMSg Page 5 of 10 PERFORMANCE D=Discuss ELEMENTISTEP STANDARD EVALUATION P=Perform S=Simulate

denotes a critical step

denotes a critical step SATUNSAT CUE: Due to differences between the simulator and the plant if student asks for direction on how to reset counter position, respond, "Depress step counter reset pushbutton:'

d. Reset the affected group step counter to zero *d. Resets the CBD group 2 step counter position to zero e. Hold and maintain the pulse to analog converter Auto-Man switch in Man until rod withdrawal is complete *e. Directs NSO to hold and maintain the pulse to analog converter Auto-Man switch in Man until rod withdrawal is complete CUE: When directed NSO to Primary Operator, "I copy, hold the PIA converter switch to Man until rod withdrawal is complete." NOTE: Simulator Operator Place PIA converter switch in Man as follows: Select Local Panels Select Rod Drive System Select Pulse to Analog Converter Select Hold in Manual CUE: NSO to Primary Operator, "The PIA converter Auto-Man switch is beil1g held in Man." *4. P Withdraw the dropped rod until the step counter reaches the previously recorded position:

a. Verify that the dropped rod is the only rod moving by DRPI *a. Verifies that only rod H-8 is withdrawing.

CUE: When asked for method of maintaining Tavg on program, US to Primary Operator, "The Secondary Operator will maintain Tavg with turbine load adjustments while you withdraw the control rod." b. Maintain programmed Tavg using boration and/or turbine loading as recommended by Reactor Engineering.

b. Discusses controlling Tavg with the US. JPMSg Page 6 of 10 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform S=Simulate

denotes a critical step

denotes a critical step SAT UNSAT Withdraw rod to previously

c. Withdraws rod H-8 to previously recorded position.

recorded position.

5. Align rod control system for Return the Pulse to Analog *a. Directs NSO to return the Pulse Converter Auto-Man switch to to Analog Converter Auto-Man Auto. switch to Auto. CUE: NSO to Primary Operator, "I copy, return The PIA converter Auto-Man switch to Auto." Simulator Operator Place PIA converter switch in Auto as follows: Select Local Panels Select Rod Drive System Select Pulse to Analog Converter Select Hold in Automatic CUE: NSO to Primary Operator, "The PIA converter Auto-Man switch is in Auto." Reset the rod control urgent *b. Depresses the rod control alarm failure alarm by depressing the reset pushbutton.

rod control alarm reset pushbutton. Place all the lift coil disconnect

c. Places all the lift coil disconnect switches to Rod Connect. switches for Control Bank D to Rod Connect. Return Rod Bank Selector Switch *d. Returns Rod Bank Selector to Man. Switch to Man. If necessary, reset the power e. If necessary, rotates rate mode range rate reset switch to reset for affected Nls. JPM Sg Page 7 of 10 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform S=Simulate

denotes a critical step

denotes a critical step SAT UNSAT 6. Check the dropped rod is aligned with Checks that rod H-8 is realigned to affected CBD group 2 rod height within allowable tolerances

(+/-12 steps). CUE: "The JPM is complete." Stop time ____ Time to complete task S 20 minutes Evaluator calculates time to Obtain from Tear Off sheets and any other materials used in performance of JPM Sg Page 8 of 10 PERFORMANCE Provide comments on unsatisfactory performance of an elemenUstep or for any deviation from performance as stated. Record interruptions in performance such as retraining, shift change, and processing of procedure changes. Recommend remedial training, if necessary.

JPM Sg Page 9 of 10 TEAR OFF SHEET FOR JPM Directions To The Student: Initial Conditions: You are the Primary Operator.

You are going to recover a dropped rod. The following information is provided to you: The plant is at approximately 95% power following a dropped rod in control bank D (CBD) group 2, identified as H-8. The plant has been stabilized using turbine load control, with rod control in manual. I&C has completed replacing a blown fuse on the stationary gripper. Initiating Cue: US to Primary Operator, "Primary Operator (or student's name), we are at step 4 of 051210.05 , Dropped Rod. Continue with the procedure and recover the dropped rod." JPM Sg Page 10 of 10

JOB PERFORMANCE MEASURE JPM Sh Rev. 0 START HYDROGEN RECOMBINERS Student Name: __________________

LMS#: Evaluator Name: SAT UNSAT OFFICIAL NRC EXAMINATION ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2010 INITIAL EXAM SECURITY PREPARED BY: DATE: APPROVED BY: ___________

--___--__-----DATE: ________ TRAINING SUPERVISOR JOB PERFORMANCE 1.0 Task Number and

Description:

Position:

RO 0280500201 Start 'A' H2 Recombiner From The Main Control Room. 2.0 Conditions:

A. A reactor trip with SI occurred from 100% power due to a large break LOGA. B. The US transitioned through E-O, E-1, ES-1.3, and back to E-1 and is now at step 17. C. Hydrogen concentration in containment is 3.4% 3.0 Standards:

Place a hydrogen recombiner in service. 4.0 Student Materials:

Copy of the Tear-Off Copy of OS1023.40 , Hydrogen Recombiner Operation, Rev. 7, Chg.

5.0 Limitations

On Performance:

Simulate/Perform all steps. Verbalize all actions to the Even if requested, no Peer Checks will be provided during the 6.0

References:

Procedures:

E-1, Loss of Reactor or Secondary Coolant

OS1023.40 , Hydrogen Recombiner Operation.

Sys Description Value RO/SRO 028 A2.02 LOCA condition and concern over hydrogen.

3.5/3.9 028 A2.03 The hydrogen/air concentration in excess of limit 3.4/4.0 flame propagation or detonation with resulting equipment damage in containment. 2.1.23 Ability to perform specific system and integrated plant procedures during all modes of 2.1.8 Ability to coordinate personnel activities outside the control 2.1.31 Ability to locate control room switches, controls, and indications, and determine that they are reflecting the desired plant JPM Sh Page 2 of 9 JOB PERFORMANCE

7.0 Setting

If performed as a pair with JPM Sd, reset the simulator to IC-82. When run as a pair, simulator conditions will not reflect the conditions identified below. If running as a stand alone ...IPM, Reset the simulator to IC #356 or any 100% IC which contains the following: Initialize to the 100% IC and place simulator in RUN. Insert malfunction mfRC024A RCS Cold leg 12l0CA (double ended shear). Run the simulator while performing the following per E-O and E-1: Trip RCPs. Reset SI. Throttle EFW back to approximately 150 gpm per generator. Shutdown both EDGs. Close SW-V16, and 18. Reset both engines. Swap to cold leg recirculation when RWST level decreases to 120,478 gallons lAW ES-1.3. Insert component remote function mvCS 1lCV112D 460V MCC-512 breaker open and mvCS1lCV-112E 460V MCC-612 breaker open when required in ES-1.3. Complete the actions of E-1 through step 17. Using panel graphics display sections PGR06A and PGR06B insert overrides on Hydrogen Analyzer A meter AND Hydrogen Analyzer B meter. Override to 3.4 for both meters. Insert the following overrides Safety Injection Analog outputs for Containment pressure:

IOOZMAOSIPI2576 Final Value=4 IOOZMAOSIPI2577 Final Value=4 IOOZMAOSIPR934B Final Value=4 IOOZMAOSIPR934R Final Value=4 IOOZMAOSIPR935B Final Value=4 IOOZMAOSIPR935R Final Value=4 IOOZMAOSIPI934 Final Value=4 IOOZMAOSIPI935 Final Value=4 IOOZMAOSIPI936 Final Value=4 IOOZMAOSIPI937 Final Value=4 Place the simulator in FREEZE. The simulator must be in RUN to allow the PWR OUT meter to respond to Verify the "PWR OUT" potentiometer is at MINIMUM prior to beginning the 8.0 Safety Considerations:

None 9.0 Approximate Completion Time: 20 minutes JPM Sh Page 3 of 9 JOB PERFORMANCE 10.0 Directions To The Student(s):

Evaluator gives Tear-Off sheet to the student. Initial Conditions: You are the Secondary Operator.

You are going to place Hydrogen Recombiner

'A' in service. The following information is provided to you: A reactor trip with SI occurred from 100% power due to a large break LOCA. The US transitioned through E-O, E-1, ES-1.3, and back to E-1. The crew is presently at step 17 of E-1 Loss of Reactor or Secondary Coolant and they have checked containment H2 concentration, which is 3.4 %. 11.0 Initiating Cue: US to Secondary Operator, "Secondary Operator (or student's name), we are in E-1, and containment hydrogen concentration is presently 3.4%. Place Hydrogen Recombiner

'A' in service per OS1023.40 , Hydrogen Recombiner Operation.

Report to me when the recombiner is in service." JPM Sh Page 4 of 9 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform S=Simulate

denotes a critical step

denotes a critical step SAT UNSAT When the student is ready to begin place the simulator in run. Start time _____ Initiating cue read. If the student request a Peer Check at any time during the JPM, respond: "No one is available to peer check your actions. Please continue with the task". If asked by the student, "The electrical lineup has been completed". P Verify the white PWR. IN Verifies the PWR. IN AVAIL. light AVAIL. light is energized. P Set the PWR. ADJ. Turns PWR ADJ pot to potentiometer to *4. Place the PWR. OUT SW. *

Moves switch to ON position.

switch to the ON position and VERIFY that the red light on the switch plate comes on.

Verifies the red light is on. At each power level, inform the student; "The stated time has elapsed." Energize the Hydrogen Energizes the recombiner:

Recombiner heater by PERFORMING the following:

P TURN the PWR. ADJ. *a. Tums the PWR ADJ pot clockwise until 5 __ Potentiometer clockwise kW is indicated.

until 5 kW is indicated on the PWR. OUT meter. MAINTAIN the 5 kW value for at least 10 minutes. P TURN the PWR. ADJ. *b. Turns the PWR ADJ pot clockwise Potentiometer clockwise 10 kW is until 10 kW is indicated the PWR. OUT MAINTAIN the 10 kW for at least 10 JPMSh Page 5 of 9

--PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform S=Simulate

denotes a critical step

denotes a critical step SAT UNSAT P TURN the PWR. ADJ. *c. Turns the PWR ADJ pot clockwise Potentiometer clockwise 20 kW is until 20 kW is indicated the PWR. OUT MAINTAIN the 20 kW for at least 5 P DETERMINE the d. Refers to Form recombiner power per Form A, Power Setpoint P Calculate the H2 power setpoint performing the ClIE: When the student locates any of the required pressure instruments, cue the student: "Containment pressure is 4 psig.JJ DETERMINE the current

Determines the current cntmnt pressure containment pressure from from SI-PI-934 or 935. SI-PI-934 or SI-PI-935, MCB containment pressure indicators. Current Containment *

Converts cntmnt pressure to psia Pressure + 14.7 psi = psia records on data sheet (= 18.7 Using containment absolute *. Determines C p and Records on data

pressure, pre-accident sheet -(C p :;: 1.17 -containment temperature and Figure 2, Enter student C p Recombiner Power C p Correction Factor determine the Factor (C pMULTIPLY the Pressure *. Multiplies C p by the reference power.

Factor (C p) by Reference Records on data sheet -(52.9 -54.3 Power (45.24 kW). kW). (C p) x 45.24 = Power Enter Setting kW KW JPM Sh Page 6 of 9 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform S=Simulate

denotes a critical step

denotes a critical step SAT UNSAT If the student requests a second person verification, respond: "For the purpose of this evaluation, a second verification will not be performed.

Please continue with the procedure." Have a second person

Requests second person verification.

VERI FY the power setting calculation.

P f. Turn the PWR. ADJ. *1. Turns the PWR ADJ pot clockwise potentiometer clockwise the power setpoint is indicated on until the power setpoint, as PWR OUT calculated in Step 4.2.4.4, indicated on the PWR When student mentions that conference with the TSC is necessary to determine recombiner effectiveness, inform the student, "The SM is aware of this and in contact with the TSC on this matter." P CONFER with the TSC to g. Attempts to confer with the determine effectiveness and the to make adjustments recombiner "The JPM is complete." Stop time _____ Time to complete the task 20 minutes. Evaluator calculates the time complete the Obtain from Tear Off Sheets and any training materials used in performance of the JPMSh Page 7 of9 PERFORMANCE Provide comments on unsatisfactory performance of an element/step or for deviation from performance as stated. Record interruptions in performance such as retraining, shift change, and processing of procedure changes. Recommend remedial training, if necessary.

JPM Sh Page 8 of 9 TEAR-OFF SHEET FOR LOIT JPM Sh Directions to the Student: Initial Conditions: You are the Secondary Operator.

You are going to place Hydrogen Recombiner

'A' in service. The following information is provided to you: A reactor trip with SI occurred from 100% power due to a large break LOCA. The US transitioned through E-O, E-1, ES-1.3, and back to E-1. The crew is presently at step 17 of E-1 Loss of Reactor or Secondary Coolant and they have checked containment H2 concentration, which is 3.4 %. Initiating Cue: US to Secondary Operator, "Secondary Operator (or student's name), we are in E-1, and containment hydrogen concentration is presently 3.4%. Place Hydrogen Recombiner

'A' in service per 051023.40 , Hydrogen Recombiner Operation.

Report to me when the recombiner is in service." JPMSh Page 9 of 9

IN-PLANT JOB PERFORMANCE MEASURE 'A LOCAL REACTOR TRIP Student Name: LMS #: Evaluator Name: LMS #: SAT UNSAT OFFICIAL NRC EXAMINATION ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2010 INITIAL EXAM SECURITY PREPARED BY: APPROVED BY:

JOB PERFORMANCE

1. Task Number and Description SBK 0010101604 Locally Operate Reactor Trip Breaker SBK 0010150204 Trip Rod Drive Motor Generator Sets SBK 0120100104 Locally Trip Reactor trip Breaker and Bypass Breaker Conditions: The reactor has a trip demand and should have tripped but both reactor trip breakers are still closed and control rods are withdrawn. The reactor trip bypass breakers are open and racked out. The Primary Operator has unsuccessfully tried to manually trip the reactor from both reactor trip switch locations on the MCB. The control room is executing FR-S.1 and they are using the Operator Action Summary page to have you locally trip the reactor. Standards:

Simulate locally tripping the reactor. Student Materials:

Copy of Tear Off Sheet. Limitations On Performance:

Simulate all steps. Verbalize all actions to the Even if requested no Peer Checks will be provided during the

References:

Procedures: FR-S.1 Response To Nuclear Power Generation/ATWS. NAP-402 Conduct Of Operations Value Sys/Proc Description RO/SRO I 007-EA2.04 If the reactor should have tripped but has 4.4/4.6 I Reactor Trip not, carry out actions in A TWS EOP. 2.4-2.4.35 I Knowledge of local NSO tasks during 3.8/4.0 Emergency emergency operations.

i Proc.lPlan In-Plant 'A' Page 2 of 8 JOB PERFORMANCE Setting: In-Plant.

Train 'A' Essential Switchgear Room. Safety Considerations:

Do NOT permit opening of reactor trip breaker cubicles or rod drive MG set cubicles. Approximate Completion Time: 5 minutes Directions To The Student: Evaluator gives Tear Off sheet to the student. Initial Conditions: You are the Secondary NSO. You are going to simulate locally tripping the reactor. The following information is provided to you: The reactor has a trip demand and should have tripped but both reactor trip breakers are still closed and control rods are withdrawn. The reactor trip bypass breakers are open and racked out. The Primary Operator has unsuccessfully tried to manually trip the reactor from both reactor trip switch locations on the MCB. The control room is executing FR-S.1 and they are using the Operator Action Summary page to have you locally trip the reactor. Initiating Cue: US to Secondary NSO, "Secondary NSO (or student's name), locally open the reactor trip breakers." In-Plant 'A' Page 3 of 8 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform S=Simulate

denotes a critical step

denotes a critical step SATUNSAT P Start time -----Initiating cue read If the student requests a Peer Check at any time during the JPM respond, "No one is available Peer Check your actions. Please continue with the If required upon arrival at the reactor trip breakers, US to Secondary NSO, "Secondary NSO, locally open the reactor trip breakers." CAUTION DO NOT allow the student to depress the trip plate because this will cause an actual reactor trip. Evaluator to student, "The reactor trip breakers indicate closed." 2. Open the reactor trip breakers locally: Depress red trip plate for reactor a. Simulates depressing red trip trip breaker RTA. plate for reactor trip breaker RT A. When student simulates depressing red trip plate for reactor trip breaker RTA, evaluator to "The reactor trip breaker does not Depress red trip plate for reactor b. Simulates depressing red trip trip breaker RTB. plate for reactor trip breaker RTB. When student simulates depressing red trip plate for reactor trip breaker RTB, evaluator to "The reactor trip breaker does not S Inform the control room that the Inform the control room that reactor trip breakers will not open. reactor trip breakers will not US to Secondary NSO, "I copy, the reactor trip breakers will not open. Open the A & B rod drive MG set motor and generator breakers." In-Plant 'A' Page 4 of 8 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform S=Simulate

denotes a critical step

denotes a critical step SAT UNSAT CAUTION DO NOT allow the student to actually open or jar the MG set breakers. The order in which the breakers are opened is not critical.

At least one breaker being opened (motor or generator) for each MG set is critical.

4. Open the input (motor) and/or (generator) for both MG Open "A" MG set motor and/or *a. Simulates opening "A" MG set generator breaker. motor and/or generator breaker. When student simulates rotating each breaker handle switch to TRIP, evaluator to student,"Red light extinguishes and green light illuminates.

The breaker opens." Open "8" MG set motor and/or *b. Simulates opening "8" MG set generator breaker. motor and/or generator breaker. When student simulates rotating each breaker handle switch to TRIP, evaluator to student,"Red light extinguishes and green light illuminates.

The breaker opens." S Inform the control room that the input Informs the control room that the and output breakers for both rod drive and output breakers for both rod MG sets are open. MG sets are US to Secondary NSO,"I copy, the input and output breakers for both rod drive MG sets are open. All control rods are inserted." In-Plant 'A' Page 5 of 8 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform S=Simulate

denotes a critical step

denotes a critical step SAT UNSAT CUE: "The JPM is complete." 6. Stop time ____ Time to complete task s 20 minutes Evaluator calculates time to complete task 7. Obtain from student: Tear Off sheets and any other materials used. I n-Plant 'A' Page 6 of 8 PERFORMANCE Provide comments on unsatisfactory performance of an element/step or for any deviation from performance as stated. Record interruptions in performance such as retraining, shift change, and processing of procedure changes. Recommend remedial training, if necessary.

I n-Plant 'A' Page 7 of 8 TEAR OFF SHEET FOR JPM In-Plant 'A' Directions To The Student: You are the Secondary NSO. You are going to simulate locally tripping the reactor. The following information is provided to you: The reactor has a trip demand and should have tripped but both reactor trip breakers are still closed and control rods are withdrawn. The reactor trip bypass breakers are open and racked out. The Primary Operator has unsuccessfully tried to manually trip the reactor from both reactor trip switch locations on the MeS. The control room is executing FR-S.1 and they are using the Operator Action Summary page to have you locally trip the reactor. Initiating Cue: US to Secondary NSO, "Secondary NSO (or student's name), locally open the reactor trip breakers." In-Plant 'A' Page 8 of 8

SEABROOK IN-PLANT JOB PERFORMANCE MEASURE 'B' Rev. HYDROGEN ANALYZER LOCAL Student Name: __________________

LMS#: Evaluator Name: SAT UNSAT OFFICIAL NRC EXAMINATION ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2010 INITIAL EXAM SECURITY PREPARED BY: APPROVED BY:

JOB PERFORMANCE Task Number and Description SBK 0280101104 Align Hydrogen Analyzer to the Analyze Mode Conditions: The reactor tripped from 100% power due to an LOP. SI has actuated. The US transitioned from ECA-O.O to ECA-O.2 after energizing both emergency buses from the EDGs. Step 9 of ECA-0.2 is complete, permitting implementation of FRPs as necessary. Core exit thermocouples are 1150°F; therefore we have a valid red path on core cooling. The crew transitioned to FR-C.1, Response to Inadequate Core Cooling. 80th hydrogen analyzers have been in standby for> 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . Standards:

Simulate placing the hydrogen analyzer in the ANALYZE mode per OS1023.71, Operation of the H2 Analyzers. Student Materials:

Copy of Tear Off Copy of OS 1023.71, Operation of the H2 Limitations On Performance:

Simulate all steps. Verbalize all actions to the Even if requested no Peer Checks will be provided during the

References:

Procedures: OS1023.71 , Operation of the H 2 Analyzers FR-C.1, Response to Inadequate Core Cooling ECA-O.2 Loss Of All AC Power Recovery With SI Required Technical Specifications: 3.6.1.1 Containment Integrity In-Plant '8' Page 2 of 8 JOB PERFORMANCE Value Sys Description RO/SRO 028-HRPS Ability to manually operate/monitor H2 3.1/3.3 sampling and analysis of containment atmosphere Setting: Plant. H 2 Analyzer Room. Safety Considerations:

Hearing protection. Approximate Completion Time: 15minutes Directions To The Student: Evaluator gives Tear Off sheet to the student. Initial Conditions: You are the NSO on a team being dispatched from the OSC. You are going to simulate placing the hydrogen analyzer in the ANALYZE mode using 081023.71, Operation of the H2 Analyzers. The following information is provided to you: Core exit thermocouples are 1150"F; therefore we have a valid red path on core cooling. The crew transitioned to FR-C.1, Response to Inadequate Core Cooling. 80th hydrogen analyzers have been in standby for> 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . Initiating Cue: OSC Coordinator to NSO, "NSO (or student's name), simulate placing Train A H2 analyzer in the ANALYZE mode per OS1 023.71, Operation of the H2 Analyzers.

I am sending the Chemistry tech to verify the sample vessel is installed and an HP tech to monitor radiation levels in the area." In-Plant '8' Page 3 of 8 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform S=Simulate

denotes a critical step

denotes a critical step SAT UNSAT When student demonstrates the ability to obtain a controlled copy of OS1023.71, Operation of the H2 Analyzers provide the student with a copy of OS 1023.71, Operation of the H2 Analyzers

1. P Start time ___Initiating cue read If the student requests a Peer Check at any time during the JPM respond, "No one is available to CUE: Peer Check your actions. Please continue with the task." S Notify HP and Chemistry Simulates notifying HP HP to NSO, "General dose rates are 10 mr/hr and no indications of radiation streaming present. It is safe to enter the hydrogen analyzer room and SCBA is not Chemist to NSO, "I understand, you are placing Train A H2 analyzer in the ANALYZE mode. We have a half inch non-sparking wrench if needed." The requirements of OS1090.05 shall be waived during the implementation of EOPs. Configuration control will be re-established during recovery operations. If student requests permission to unlock and open CGC-V3 and V10, provide cue, "you permission to unlock and open CGC-V3 and V10 per step 4.3.1.2 of OS1023.71S Unlock and open the following valves: Simulates unlocking and opening __ a. CGC-V3 When student simulates unlocking and opening CGC-V3, evaluator to NSO, "The valve is unlocked, the handwheel turns and the valve opens." Simulates unlocking and opening CGC-V10 When student simulates unlocking and opening CGC-V10, evaluator to NSO, "The valve unlocked, the handwheel turns and the valve In-Plant 'B' Page 4 of 8

D=Discuss ELEMENT/STEP EVALUATION P=Perform S=Simulate

denotes a critical step

denotes a critical SAT UNSAT *4. S Open CGC-V-12 hydrogen analyzer A *Simulates opening train supply ORC isolation.

hydrogen analyzer A train ORC When student simulates opening CGC-V12, evaluator to NSO, "The handwheel turns and the valve opens." NOTE: DO NOT allow the student to open the cabinet when simulating alignment of the sample vessel. When asked, the Chemistry Tech reports, "The sample vessel is installed in the Train A analyzer. If the student inquires about gloves for operation of potentially hot sample vessel isolation valves, then provide cue, "Gloves have been obtained." *5 S Open the following *a. Simulates opening hydrogen analyzer A sample vessel inlet When student simulates opening CGC-V58, evaluator to NSO, "The handwheel turns and the valve opens." Simulates opening CGC-V59 hydrogen analyzer A Train sample vessel outlet isolation. When student simulates opening CGC-V59, evaluator to NSO, "The handwheel turns and the valve opens." *6. S Place the main power switch on Simulates informing control room CP-173A to ANALYZE main power switch at CP-173A be placed to When NSO calls the control room, US to NSO, "The main power switch has been placed ANALYZE.In-Plant '8' Page 5 of 8 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform S=Simulate

denotes a critical step

denotes a critical step SAT UNSAT CUE: "The JPM is complete." 7. Stop time ____ Time to complete task S 15 minutes Evaluator calculates time to complete task 8. Obtain from student: Tear Off sheets and any other training materials used in performance of this JPM. In-Plant 'B' Page 6 of 8 PERFORMANCE Provide comments on unsatisfactory performance of an element/step or for any deviation from performance as stated. Record interruptions in performance such as retraining, shift change, and processing of procedure changes. Recommend remedial training, if necessary.

In-Plant '8' Page 7 of 8 TEAR OFF SHEET FOR In-Plant '6' Directions To The Student: You are the NSO on a team being dispatched from the OSC. You are going to simulate placing the hydrogen analyzer in the ANALYZE mode using OS1023.71, Operation of the H2 Analyzers. The following information is provided to you: Core exit thermocouples are 1150°F; therefore we have a valid red path on core cooling. The crew transitioned to FR-C.1, Response to Inadequate Core Cooling. Both hydrogen analyzers have been in standby for> 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . Initiating Cue: OSC Coordinator to NSO, "NSO (or student's name), simulate placing Train A H2 analyzer in the ANALYZE mode per OS1 023.71, Operation of the H2 Analyzers.

I am sending the Chemistry tech to verify the sample vessel is installed and an HP tech to monitor radiation levels in the area." In-Plant 'B' Page 8 of 8

t. .,f ,/ SEABROOK IN-PLANT JOB PERFORMANCE MEASURE 'C' Rev. PERFORM LOCAL OPS TO SWAP CC Student Name: DATE: Evaluator Name: DATE: SAT UNSAT OFFICIAL NRC EXAMINATION ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2010 INITIAL EXAM SECURITY PREPARED BY: DATE: APPROVED BY: DATE:

JOB PERFORMANCE Task Number and Description SBK 0080102304 Perform local OPS To Swap CC Pumps Conditions: Plant is at 100% power. CC-P-11A outboard motor bearing is making a squealing noise and is progressively worsening. The decision has been made to swap to CC-P-11C. Standards:

Simulate valve manipulations and component checks to support start up of CC-P-11 C and shutdown of CC-P-11 A. Student Materials:

Copy of Tear Off Copy of 0015 Pump Starts From MCB Or Other Remote Page 15 Pre-start Checklist PCCW pump CC-P-11 Limitations On Performance:

Simulate all steps. Verbalize all actions to the Even if requested no Peer Checks will be provided during the

References:

Procedures: OS1012.03 , PCCW Loop A Operation. OS1212.01 , PCCW System Malfunction. 0015 Pump Starts From MCB Or Other Remote Locations Value Sys Description ROISRO 008 K4.01 Automatic start of standby pump. 3.1/3.3 191001 K1.08 Operation of valves and verification of 3.4/3.4 position.

In-Plant 'C' Page 2 of 8 JOB PERFORMANCE Setting: Plant. PAB 25 ft. Safety Considerations:

Health Physics postings and Rotating machinery Approximate Completion Time: 15 minutes Directions To The Student: Evaluator gives Tear Off sheet to the student. Initial Conditions: You are the Primary NSO. You are going to simulate the actions required to swap PCCW pumps. The following information is provided to you: Plant is at 100% power. CC-P-11A outboard motor bearing is making a squealing noise and is progressively worsening. The decision has been made to swap to CC-P-11C. Initiating Cue: US to Primary NSO, "Primary NSO (or student's name), we are swapping from the A to the C PCCW pump. Perform the local pre-start checks on CC-P-11C." In-Plant 'C' Page 3 of 8 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform S=Simulate

denotes a critical step

denotes a critical step SAT UNSAT P Start time ____ Initiating cue read If the student requests a Peer Check at any time during the JPM respond, "No one is available Peer Check your actions. Please continue with the Student may perform the pre-starts in any order. The pre-start checklist is provided to the student by the evaluator. S Verify open CC-V-6 suction isolation.

Simulates verifying open suction When student simulates verifying open CC-V-6 suction isolation, evaluator to student, "CC-V-6 If student contacts the control room regarding the "procedure determined position" of discharge isolation, US to NSO, "CC-V-2 is required to be 3. Verify open CC-V-2 Simulates verifying open CC-V-2 S discharge isolation. When student simulates verifying open CC-V-2 discharge isolation, US to student, "CC-V-2 is open." S Verify pump is filled and vented. Simulates verifying pump is filled When student simulates verifying pump is filled and vented, evaluator to student, "Pump is filled and vented." S Verify both pump bearing oil cups Simulates verifying both pump levels are normal. oil cups levels are When student simulates verifying both pump bearing oil cups levels are normal, evaluator to student, "Both pump bearing oil cup levels are normal." In-Plant 'C' Page 4 of 8 PERFORMANCE D=Discuss ELEMENT/STEP STANDARD EVALUATION P=Perform S=Simulate

denotes a critical step

denotes a critical step SAT UNSAT S Verify both motor bearing bulls eye Simulates verifying both levels are normal. bearing bulls eye levels are When student simulates verifying both motor bearing bulls eye levels are normal, evaluator to student, "Both motor bearing bulls eye levels are normal." CC-PI-2165 CC-P-11A1C Train A Return Pressure is located on side of column, 17 ft from North wall and 8 ft from West wall. S Verify suction pressure is greater than Simulates verifying suction pressure 15 psig on CC-PI-2165.

greater than 15 psig on When student simulates verifying suction pressure is greater than 15 psig on CC-PI-2165, to student, "Suction pressure is greater than 15 S Inform US that pre-start checks for Simulates informing US that CC-P-11 C completed.

checks for CC-P-11C When control room is informed that pre-start checks for CC-P-11C completed., US to NSO, "I pre-start checks for CC-P-11C completed.

Stand by for starting of Provide the following cue, "The announcement for the starting of CC-P-11C is heard, moments later CC-P-11C starts. All indications show CC-P-11C is running US to Primary NSO, "We are preparing to stop CC-P-11A.

Unlock and close CC-V-5, discharge Primary NSO carries the required key (BEST key)on his key ring. *9. Unlock and close CC-V-5, CC-P-11A *Simulates unlocking and closing discharge valve. V-5, CC-P-11A discharge When student simulates unlocking and closing CC-V-5, CC-P-11A discharge valve, evaluator student, "CC-V-5 is unlocked and In-Plant 'c' Page 5 of 8 PERFORMANCE D='oiscuss ELEMENT/STEP STANDARD EVALUATION P=Perform S=Simulate

denotes a critical step

denotes a critical step SAT UNSAT S Inform US that CC-V-5 is unlocked Simulates informing US that CC-V-5 and closed. unlocked and US to Primary NSO, "I copy, CC-V-5 is unlocked and closed." After US is informed that CC-V-5 is closed, the control room stops CC-P-11A.

Provide the necessary cues that CC-P-11A is stopped. Us to Primary NSO, "We have secured CC-P11A. Open and lock open CC-V-5." *11. Open and lock open CC-V-5, CC-P-*Simulates opening and locking 11A discharge valve. CC-V-5, CC-P-11A discharge When student simulates opening and locking open CC-V-5, CC-P-11A discharge valve, evaluator to student, "CCN-5 is open and locked." S Inform US that CC-V-5 is locked open. Simulates informing US that CC-V-5 locked US to Primary NSO, "I copy, CC-V-5 is locked open." "The JPM is complete." Stop time ____ Time to complete task S 20 minutes Evaluator calculates time to Obtain from Tear Off sheets and any other materials used in performance of In-Plant 'c' Page 6 of 8 PERFORMANCE Provide comments on unsatisfactory performance of an element/step or for any deviation from performance as stated. Record interruptions in performance such as retraining, shift change, and processing of procedure changes. Recommend remedial training.

if necessary.

In-Plant 'C' Page 7 of 8 TEAR OFF SHEET FOR JPM L0052J Directions To The Student: You are the Primary NSO. You are going to simulate the NSO actions required to swap PCCW pumps. The following information is provided to you: Plant is at 100% power. CC-P-11A outboard motor bearing is making a squealing noise and is progressively worsening. The decision has been made to swap to CC-P-11C.

Initiating Cue: US to Primary NSO, "Primary NSO (or student's name), we are swapping from the A to the C PCCW pump. Perform the local pre-start checks on CC-P-11C." In-Plant IC' Page 8 of 8 ODI.05 Page IS Rev. 01 PRIMARY COMPONENT COOLING WATER PUMP CC-P-llC 1) SUCTION PATH CC-V-6 HEAD TANK LEVEL 2) DISCHARGE PATH CC-V-2 IN PROCEDURE DETERMINED POSITION CC-TK-2171: -WI CC-P-IIA SHUTDOWN -WI CC-P-I1A RUNNING 3) COOLING MEDIUM PAB NORMAL VENTILATION PAH-FN-42A OR B OR PAH-FN-42A ORB 4) OTHER SUPPORT PUMP FILLED AND VENTED PUMP BEARING OIL CUPS (2) MOTOR BEARING BULLS EYES (2) PUMP SUCTION PRESSURE COLOR GRAPHICS FOR CC-P-IIC PREVIOUS PUMP STARTS -TWO IN LAST HOUR (W. MOTOR STATOR AT AMBIENT TEMP.) -ONE IN LAST 112 HOUR (WI MOTOR STATOR AT OPERATING TEMPERATURE GAITRONICS ANNOUNCEMENT MADE MCB >45% MAN. 0% AUTO RUNNING AUTO AUTO DISPLAYED NO NO YES LOCAL OPEN YES YES (Note 1) NORMAL 112 +1-1I4 >15# Note 1: If the pump is being started for surveillance testing, it should not be vented unless the pump was drained to support maintenance.

This is to prevent preconditioning the pump prior to testing.

2009*2010 LOIT NRC SIMULATOR EXAMINATION

01 Rev. 0 OFFICIAL NRC EXAMINATION ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2010 INITIAL EXAM SECURITY PREPARED BY: DATE: APPROVED BY: _________------_____--------DATE: TRAINING SUPERVISOR REVIEWED BY: DATE: SME (OPTIONAL)

SCENARIO The Scenario begins with the plant at 55% power. SW-P-41C is danger tagged out for motor replacement Both Main feed Pumps and one Heater Drain pump are in service. After the crew begins to increase power, FW-PT-505 fails low, which is addressed in Abnormal Procedure OS1235.05, "Turbine Impulse Pressure PT-505 or PT-506 Instrument Failure." RC-L T -459 will fail high the crew should take manual control of charging flow. This failure is addressed with Abnormal Procedure OS1201.07, "PZR Level Instrument Failure." Also during this failure, a 20 gpm RCS leak will develop on the instrument sensing line. After initially addressing, or in parallel with the instrument failure, it is expected that the crew will address the RCS leak using Abnormal Procedure OS1201.02, "RCS Leak." The running EHC pump will trip and the standby EHC pump will start The standby pump will have a sheared shaft and EHC pressure will continue to decrease.

The crew will need to recognize the decreasing EHC pressure and manually trip the reactor or respond to an automatic turbine trip/reactor trip demand. The #2 turbine stop and control valves will stick is" on the trip. Automatic Main Steam Isolation (MSI) will fail to actuate, requiring the crew to manually close the main steam isolation valves to prevent an excessive cooldown.

When the Main Steam Isolation Valves are shut, one safety valve on each of "C" & "D" Steam Generators will open and subsequently stick open, requiring a manual or an automatic Safety Injection.

SI-P-6A and SI-P-6B will fail to start on the Safety Injection, requiring a manual start. The crew will enter E-O, "Reactor Trip or Safety Injection" and may enter ES-0.1, "Reactor Trip Response" before transitioning back to E-O and then to E-2, "Faulted Steam Generator", to address the depressurization of the "C" &"D" Steam Generators.

Anticipated AOP/EOP flow-path:

OS1235.05, OS1201.07, OS1201.02, E-O, E-2, ES 1.1 Page 2 of 15 2010 LOIT Rev. 0 SIMULATOR SETUP D Reset the simulator to 50-55 % power with both MFPs in service, Middle of Core Life condition.

This setup has been snapped to a password protected IC with the below conditions.

Alternately, any other 55% IC can be used, and conditions established using Scenario Sim test EV1 or individually as described below. 2. Set Protected Train as "B" on MPCS and MCB. Tag out SW-P-41C by inserting the D Override cSWP41C SW-P-41C breaker racked D Remote Function cSWV22 SW-V-22 breaker D Tag the Control Switch for

4. Verify Pressurizer Level Channel LT-459 is Selected for control. Actuate the following scenario to insert malfunctions and activate triggers the exam D SELECT:

D SELECT: Demo D SELECT: Exam #01 D SELECT: Verify the following were inserted and activated:

D mfS1003, SI PUMP 6A FAILS TO AUTO START D mfS1004, SI PUMP 6B FAILS TO AUTO START D avMSVSV2, t:1 d:O, MT STOP VLV#2 FAILS OPEN D mfRPS019, MS ISOLATION FAILS TO ACTUATE (TRN A) D mfRPS020, MS ISOLATION FAILS TO ACTUATE (TRN B) Verify the following event trigger that will insert malfunctions to fail open SG safety valves on two Steam Generators when Main Steamline Isolation Train "B" switch is turned to ACTUATE has been Activated:

D SELECT: Event Triggers (Top D SELECT: Demo Exams/Exam 01 D VERIFY:

SHIFT TURNOVER

Plant is at 50-55% power.

Procedure OS1000.05 is being performed and is completed to step 4.3.10.

Maintain AFD on target.

Increase power to 75% at 5%/hour.

SW-P-41 C tagged out for motor replacement.

Page 3 of 15 2010 LOIT Rev. 0 SCENARIO OUTLINE EVENT INSTRUCTION Shift Turnover Shift turnover information as stated. Event 1 5%/hr. power increase PSO (R), US (N), BOP Crew Begins the Power increase lAW MPE OS1000.05 , Power The crew should prepare for and initiate a increase at Unit Supervisor:

A brief reactivity review will take discussing the temperature limits for Tave to be used the power increase.

The temperature band will be + 1.5°F with rods in Auto or +/- 3 of with rods manual. Dilution will be used for temperature during the power increase.

Control rods will be used AFD and temperature Turbine Operations:

The BOP will increase turbine using automatic DEHC operations.

Using the sheets, Figure 9 of OS1000.05 , The basic steps Check the Load Set is in Hold mode. Insert the desired loading Rate. Insert the desired Power Level. When RCS temperature begins to Increase, Select "Load." Monitor turbine loading using "Load Status" is Loading and "Load Actual" increases.

The BOP should verify the change with control valve position change, temperature change and power change. At any time during the automatic loading, the power increase can be stopped by activating the "Hold" function.

Page 4 of 17 2010 LOIT Rev. 0 EVENT COMMENTS Reactor Power change: The crew will use dilution to increase temperature during the turbine load increase.

A dilution value will be determined to change the boron concentration and increase power/temperature.

If control rods are used in manual to control AFD / temperature, the operator will verify rod speed, place the Rod Motion Selector (In*Hold*Out) switch to the OUT direction and withdraw the rods a maximum of three steps. The PSO will monitor temperature and power as confirmation of actions. Using the laminated sheets OS1008.01, Figure 2, Dilution Check List, the PSO will set up the controllers for the required dilution volume and rate. The high level steps are: Verify the pumps in AUTO Verify the makeup valves are in AUTO Place Blender Mode Start Switch to STOP Place the Mode Selector Switch to DILUTE or ALT DILUTE Set the quantity and flow rate on CIS*FIQ*111 controller If not desired, select OFF for the "Stepback Feature" Set the Mode Start Switch to START Verify the pumps and valves respond Verify Plant Response. Restore System to Automatic control Allow the crew to demonstrate a power increase or at Chief Examiners discretion, enter the next Event: Page 5 of 17 2010 LOIT 01 INSTRUCTION Event 2 FW-PT-505 Enter the Turbine Impulse Press Channel FW-PT-505 fails low Failure as follows: o '-S-E-L-E-C-T-:SELECT: FEEDWATER (Component)

D SELECT:

D Double SELECT: Fails SELECT: 0 COMMENTS PSO(I), US(I, TS), Turbine Impulse Pressure FW-PT-505 fails low. Control Rods are selected to auto, automatic insertion B7457 Rod Motion US may direct termination of the dilution and rods in Crew Enters OS1235.05, Turbine Impulse Pressure 505 or PT -506 Instrument Step 1: Check FW-PT-505 The BOP checks FW-PT-505 Failed using FW-PI-505 or Tref indication. PSO places rods in manual. PSO/BOP monitor Tavg at program temp., using Tavg indication or RCS cold leg temperature.

The Crew will likely withdraw rods in 3-step increments or reduce turbine load to restore temperature.

Step 2: BOP Checks Condenser Steam Dumps: Checks Steam dump valves closed. Transfers Steam dump control to the STM Press Mode. Adjust Steam dump controller output, places in AUTO. Verifies interlock switches in NA RESET Page 6 of 17 2010 LOIT Rev. 0 Place FW-PT-505 in Bypass as follows: I SELECT: Panel Overview D I SELECT: AMSAC CP-519 D SELECT: TB IMP 505 Step 3: PSO verifies P-13 Status Light for Power above Step 4: US verifies TS compliance and T.S. 3.3.1, Table 3.3-1, Item 18.f, Action 8, is applicable.

Step 5: Crew verifies ATWAS Mitigation Input Status:

US directs I&C to place the failed channel in Operate Bypass. Alarm: D7899 ATWAS Mitigation Sys Byp/Trouble BOP verifies UL-28 B-1, Turbine power above 20% -status light energized.

US may contact Ops. Management with regards to continuing with the power increase.

Instructor Cue: If Ops. Management contacted the power increase, respond to continue the Allow the crew to complete ON1235.05 or at Chief Examiners discretion prior to entering the next Event: Page 7 of 17 2010 LOIT 01 INSTRUCTION Event 3 RC-L T-459 Failure Enter the pressurizer Level Channel failure over 5 minutes as follows: SELECT: MF List SELECT: REACTOR COOLANT (Component)

D I SELECT: ItRCL T459 D Double Click D SELECT: FAIL TO SPECIFIED VALUE D ENTER: 100% ENTER: Ramp Rate of 300 secs SELECT: INSERT D I Input Event 4 as a simultaneous failure. Rev. 0 COMMENTS PSO(I),

RC-Ll-459, PZR Level, channel 1 , fails high, manual control of charging and letdown. No loss letdown occurs due to the failure of the channel Crew may take manual control of charging letdown flow using Skill Of The 04436 PZR L VL Deviation High &BU Htrs On

F7861 PZR Level High Channel trip Crew Enters OS 1201.07, PZR Level Instrument Failure. Step 1: PSO checks Pressurizer controlling channel failed. Step 2: PSO Realigns PZR Level Instruments: Manually controls level using Letdown and Charging Selects an alternate level channel for control

Selects an alternate level channel for recorder Step 3: PSO will not need to Reset heaters Step 4: PSO checks letdown NOT isolated, US goes to '---___________________

---', step Step 7: PSO aligns pressurizer level control by controller setpoint and placing RC-LK-459 and 121 in Auto. (Time Step 8: PSO verifies redundant bistables on Pressurizer Level High, NOT Page 8 of 17 2010 LOIT 01 EVENT INSTRUCTION To place LB459A in Bypass perform the following: !SELECT: CP1 Bypass Cabinet o I SELECT: Door Open SELECT: Enable SELECT: Panel Overview SELECT: BTl CP1 Position the following switches to bypass: LB. 459, High Reactor Trip BS-1 SELECT: CP1 Bypass Cabinet SELECT: Door Closed D I SELECT: Enable Shortly after initiating Event 3, Insert malfunctions for Event 4. Rev. 0 COMMENTS Step 9: US verifies TS compliance and determines the following are applicable: T .S. 3.3.1. Reactor Trip System Instrumentation; Table 3.3-1, Item 11. Action 6 is applicable T.S. 3.3.3.6, Accident Monitoring Instrumentation; Table 3.3.10, Item 5, Action A for PAM indication T.S. 3.3.3.5, Remote Shutdown Systems; Table 3.3-9, Item 5, Action A for RSSD indication US Coordinates with I&C to place bistables in bypass or tripped. Page 9 of 17 2010 LOIT Rev. 0 EVENT Event 20 gpm RCS Leak INSTRUCTION Shortly after initiating Event 3, insert the following malfunction for a 20 gpm leak ramped in over 5 minutes, simulating a leak on the pressurizer instrument sensing line: D I Select: MF List D Select: Reactor Coolant D Select: mfRC049C D Select: Final Value = 20 Select: Ramp = 300 D I Select: Insert PSO(C),

Supports E-Plan UE call on SU5 (End of Crew responds to a 20 gpm RCS leak lAW Procedure OS1201.02, RCS ROMS Containment Particulate High and High High Containment Gaseous High and High High

Containment Backup Gas High and High High Step 1: PSO Checks If Pressurizer Level Can Be Maintained by controlling charging and letdown and checking level stable or increasing.

Step 2: US refers to ER1.1, Classification Of '---___________________

---', Emergencies, SU5. If an NSO is sent to sent to the RSSD panel to check indication, after 2 minutes, Inform the control room that RC-LT*7334 indicates off-scale high. (common instrument sensing line) Step 3: US determines step 4 is the appropriate Transition for a suspected RCS Step 4: PSO Isolates Potential RCS Leakage Checks Safety or PORV leakage using PORV tailpipe temps, and Acoustic monitor alarms Checks reactor head vents isolated, RC-FV-2881 and RC-V323 Checks Excess Letdown isolated, CS-V175 and CS-V176 Checks Phase A Status lights for RCS sample lines indicate valves are closed Checks reactor vessel flange leakoff temperature Normal Checks valve stem leakoff header temperature, D7805 and D7804 not in alarm. BOP checks SG tubes intact using rad monitors for MS line, SG blowdown, and Condenser air evacuation.

Calls Chemistry for sample. PSO checks SI discharge header pressure<

800 Page 10 of 17 2010 LOIT Rev. 0 EVENT COMMENTS psig US determines RCS leakage is NOT isolated and goes to step 16. Step 16: US continues efforts to determine leak source by considering plant walk-downs or containment entry. Step 17: Estimate RCS Leak Rate: Crew stabilizes Tavg PSO maintains Pzr level stable Crew estimates leak rate using VCT level, Containment sump levels, and/or PZRNCT mass balance. Step 18: US verifies TS Compliance and determines the following apply: T.S. 3.4.6.2, Reactor Coolant System Leakage, Action b. Action a will have to be evaluated once the exact leak location is determined. T.S. 3.4.10, Structural Integrity, will have to be evaluated once the exact leak location is determined.

Allow the crew to estimate the leak size and determine Tech. Spec. Compliance or at Chief Examiners discretion, enter the next sequence of Events: Page 11 of 17 2010 LOIT 01 EVENT Event 5 EHC Pumps Trip INSTRUCTION Insert the following to fail Turbine control valve #2 As-Is, partially open, following the impending turbine trip. I SELECT: Sim Diagram SELECT: SELECT: Fail As SELECT: RUN the following scenario to initiate loss of both EHC pumps: I SELECT: Scenario D I SELECT: Demo exams D I SELECT: Exam #01 EHC D SELECT: RUN Malfunction mfHF001, HF-P-54A, "A" EHC Pump Over Current Trip will actuate. IF the crew does not start the standby EHC pump, it will start automatically at 1300 psig. Rev. 0 Crew Responds to sequential loss of EHC pumps eventual complete loss producing an Turbine/Reactor trip 07185 EHC PUMP A TROUBLE. Crew is expected monitor HF pressure and dispatch an NSO to the The crew may choose to have the BOP start the pump using "skill of the 07180, EHC HEADER PRESSURE 07183, EHC STANDBY PUMP AUTO Page 12 of 17 2010 LOIT Rev. 0 Following the loss of the "A" EHC pump, three minutes into Event 5, a combination of 1/0 overrides and malfunctions will make it appear that there is a "problem" with the "B" EHC pump. The scenario first simulates internal pump mechanical problems (loss of load and low amps) that eventually lead to the pump binding and tripping on over current. Event 6 EOP entry COMMENTS The Crew should refer to 07185 VPRO for additional guidance: Verify startedlstart EHC Pump B and leave control switch in run. Stop EHC Pump A. Verify EHC system operation per ON1031.10, Operation of Electro-Hydraulic control system. Have an NSO check HF-P-54A or the breaker on MCC-141 <C66> The BOP should determine that HF pressure is decreasing.

It is expected that the crew will trip the plant based on continuously lowering EHC pressure.

Alarms: 07186 EHC PUMP B TROUBLE will alarm. PSO(M),US(M),BOP(M)

A turbine trip -Reactor trip will occur when EHC pressure decays below 1100 psig or when MANUALLY tripped by the crew. The #2 turbine stop & control valves stick open requiring the crew to manually close the MSIVs to stop the cooldown.

When the MSIVs are shut, two SG safeties, one on C and one on 0 steam lines will fail open. The steam flow I cooldown will cause a safety injection (automatic or manual). US will transition to E-2 at step 9 of E-O after SI has actuated.

The Crew will enter E-O: Step 1: PSO verifies Reactor Trip Page 13 of 17 2010 LOIT 01 INSTRUCTION Event 7 Turbine trip failure Event 8 SI pumps A &B start failure Rev. 0 COMMENTS Step 2: BOP verifies Turbine Trip BOP(C). CCT: #2 Stop and #2 Control valves are stuck as-is. The BOP will have to recognize this from valve position and/or excessive cooldown, attempt a manual turbine trip, and then isolate steam by using MSIVs. Step 3: BOP verifies power to emergency busses Step 4: PSO verifies SI is NOT actuated, and checks if SI is required: RCS pressure <1800 Pressurizer Level < 7% Containment Pressure>

4 psig RCS subcooling<

40 degrees

SG pressure < 585 PSO manually actuates SI, if automatic SI has not yet occurred.

NOTE: Normally the PSO will be assigned actions to complete Attachment "An of E-O, while the BOP continues processing of E-O. It is possible that these roles could be reversed.

Step 5: PSO completes ESF Attachment A: Verifies Phase A actuation by Status Panel Verifies Safeguard Equipment alignment by Status Panel. Uses RNO to manually start SI pumps. SI pumps A &B will fail to auto-start on the SI signal require manual actions to Verifies Feedwater isolation by Status Panel Verifies both trains of PCCW Pumps running Verifies ECCS flow (Based upon timing, if RCS pressure has decreased to <1700 psig, this step Page 14 of 17 2010 lOIT Rev. 0 EVENT provides an additional opportunity to start SI pumps if not previously done, to meet CCT) Verifies MS-V129 open Verify both trains of Service Water Pumps operating Verifies Service Water flow to EDGs > 900 GPM Checks if Main Steam lines should be isolated.

This should have been completed earlier based upon turbine control valve stuck open. Goes to next step. Checks Containment pressure < 18 psig Verifies EFW flow total> 500 gpm Reset of RMO is not required Notifies US of verification status including manual actions to start SI pumps. Step 6: BOP monitors RCS temperature NOT stable, US refers to RNa: Stops dumping steam Checks MSR steam isolated Monitors cooldown and adjust EFW flow to above 500 gpm Throttles to maintain SG levels> 6% Narrow range in at least 1 SG. With cooldown continuing, verifies MSIVS and Bypasses closed, and closes Upstream drain valves MSD-V-44 and 45. Step 7: BOP Checks RCS Step 8: BOP Checks if RCPs should be stopped based upon subcooling

> 40 degs. US Goes to step Step 9: BOP determines SG pressure boundary is intact, based upon C & D SG pressures decreasing an uncontrolled Page 15 of 17 2010 LOIT 01 EVENT INSTRUCTION Terminate Terminate the examination when the crew transitions to ES-1.1, Exam SI Termination, or at Lead Examiner's discretion.

R-Reactivity, N-Normal, I-Instrument, C-Component, M-Major Rev. 0 COMMENTS US proceeds to E-2, Faulted Steam Generator Step 1: BOP checks MSIVS and Bypasses Step 2: BOP checks A &B SG pressure boundaries Step 3: BOP identifies C & D SGs are Step 4: BOP checks C &D SGs are Step 5: BOP checks CST level> 250,000 Step 6: BOP checks secondary radiation is Step 7: PSO checks if ECCS flow can be

Subcooling

> 40 deg.

Secondary heat sink> 65 % SG wide range level

RCS pressure stable or increasing

PZR level> 7%

US transitions to ES-1.1 SI Termination, Step 1 During the post-scenario JPM, the US will evaluate correct Emergency Response classification based SU5, RCS Anticipated AOP/EOP flow-path:

OS1201.07 , OS1201.02, E-O, E-2, ES Possible brief transition may be from E-O to ES-O.1 back to E-O, based upon Page 16 of 17 DEMONSTRATIVE EXAM # Rev. 0 CREW CRITICAL TASKS MANUALLY actuate main steamline isolation or close MSIVs before a severe (Orange Path) challenge develops to either the subcriticality or the integrity CSF or before transition to ECA-2.1, whichever happens first.{CCT E-O,O) Isolate the faulted Steam Generators before transition out of E-2, Faulted Steam Generator Isolation, or ECA-2.1, Uncontrolled Depressurization of All Steam Generators.(CCT E-2,A) Page 17 of 17

SEABROOK 2009-2010 LOIT NRC SIMULATOR EXAMINATION

03 Rev. 0 OFFICIAL NRC EXAMINATION ACCESS IS LIMITED TO NRC EXAMINERS AND PERSONNEL FULLY UNDERSTAND AND HAVE SIGNED ON TO THE 2010 INl"rlAL EXAM SECURITY PREPARED BY: DATE: ____ REVIEWED BY: DATE: ____ SME (Optional)

APPROVED BY: DATE: ____ TRAINING SUPERVISOR 2007 *2009 LOIT NRC Examination Scenario 3 SCENARIO The simulator is initialized at 100% power. SW -P-41 C is danger tagged out for motor replacement.

'A" ASDV is tagged out of service due to seat leakage. The A Main Feed Pump has a small control system oil leak that cannot be repaired with the pump operating.

The crew will start a 10% per hour downpower to 45% power. Before starting the power decrease, the Loop 1 Tcold instrument (TE-411) will fail high. The crew responds with OS1201.08, "Tave/Delta T Instrument Failure".

The downpower will be continued.

A leak in the letdown line at the inlet to the Reactor Coolant Filter will be initiated.

Letdown flow will be reduced approximately 50%, causing VCT level to decrease.

The crew responds using OS1201.02, "RCS Leak". The "D" ASDV controlling pressure channel will fail high causing "D" ASDV to open. The BOP operator should recognize the "D" ASDV opening is due to a failed pressure channel. The ASDV controller is placed in MANUAL and the valve is closed to prevent an uncontrolled power/reactivity increase.

A Loss of Offsite Power will occur. The 'B' EDG will start and then trip on low lube oil pressure caused by a lube oil leak. The 'A' EDG fails to start.

The crew will recover power to Bus E6 via the Supplemental Emergency Power System (SEPS). The EFW Turbine Trip Throttle valve will close for unknown reasons. Recovery of the EFW turbine will be delayed until later in the scenario.

Upon restoration of power to Bus E6, the "B' train 8W pump will not Auto restart and action must be taken to start a pump to restore 8W flow. The crew will enter E-O and ECA-O.O for these events. During the recovery of Bus E6, the Motor Driven EFW Pump will trip on Overcurrent requiring the use of the Turbine driven EFW pump to restore EFW flow to the 8Gs. Anticipated AOP/EOPflow-path:

081201.08, 081201.02, E-O, ECA-O.O, E-O, ES-0.1 Page 2 of 21 2007-2009 LOIT NRC Examination Scenario 3 SIMULATOR Reset the simulator to a 100%, Middle of Core Life condition.

This setup has been snapped to password protected IC92 with the below conditions.

Alternately, any other 100% IC (IC-30) can be used, and conditions established using Scenario Sim test EV3 or individually as described below. D Set Protected Train as "8" on MPCS and MC8 If EV3 is to be used, establish the exam setup by running the following scenario:

D Select: Scenario D Select: Len D Select: Sim test EV3 D Select Run D Verify the following conditions were entered: Insert the following Malfunction and Overrides to fail the Auto Start of "An EDG; Electrical Distribution:

D IMF mfED031, DG-1A Auto Start Failure D Override the DG-1A Emergency Start pushbutton to RELEASE. On Panel Graphic PHF09, Override the CIA" EDG Emergency Stop Pushbuttons to STOP Insert the following Malfunction to Trip the "8" EDG on Low Lube Oil Pressure, Electrical Malfunctions:

D IIMF mfED034, DG-1 8 Low Lube Oil Press Trip Set up the ASDV "A" Closure and Isolation with MS-V5: D On Sim Diagram MS1, for MS-V5 Select the Remote Function, rfMS009, and Set Final value to 0 D On MS-PK-3001, place the controller to Manual and Minimum Output D On Sim Diagram MS1, MS-PV-3001, Component Malfunction D SELECT: FAIL CLOSED D SELECT: INSERT D PLACE MC8 jog switch to CLOSED for MS-PV-3001 and place a Control 80ard

Tag. Continued on next page. Page 3 of 21 2007-2009 LOIT NRC Examination Scenario 3 Using Malfunctions, Service Water, Insert the following malfunctions to prevent Auto Start of SW-P-41B, 41D and P-110B IMF mfSW013. SW-P-41B Fails to Auto Start IMF mfSW015, SW-P-41D Fails to Auto Start IMF mfSW017, SW-P-110B Fails to Auto Start Activate trigger for FW-P-37A Overspeed.

D I LOIT, L30591, Loss of FW-P-37A on Overspeed Setup the Malfunction for FW-P-37B to Trip on Overcurrent after starting in ECA-O.O. Malfunctions, Feedwater SELECT: mfFW055, FW-P-37B Overcurrent Trip SELECT: INSERT Tag out SW-P-41 C by inserting the following: Override cSWP41 C, SW-P-41 C breaker racked out Remote Function cSWV22, SW-V-22 breaker open Tag the Control Switch for SW -P-41 C Page 4 of 21 2007*2009 LOIT NRC Examination Scenario 3 SHIFT TURNOVER The plant is at 100% power. Decrease plant power at 1 O%/hr to 45% power to allow for repairs of FW-P-32A oil leak. Main Steam Atmospheric Steam Dump ("A" ASDV), MS-PV-3001 is Danger Tagged closed due to excessive seat leakage. MS-V-5 is closed and tagged. Tech. Spec. 3.7.1.6 and 3.6.3 were entered 4 days ago. SW-P-41C tagged out for motor replacement.

Page 5 of 21 Examination 03 Rev. 0 SCENARIO OUTLINE EVENT Shift Turnover Shift turnover information as At the Chief Examiners discretion initiate the first Event RCS Loop 1 T fails Initiate the instrument failure as follows: D I SELECT Malfunction:

Reactor Coolant SELECT Component:

ttRCTT411 SELECT: FAIL HIGH SELECT: INSERT COMMENTS Operators should review alarms and indications PSO (I) US RCS Loop 1 Tcold will fail high causing inward control Control Rods step in based on TavglTref The crew should diagnose that rods are stepping in due to instrument failure. The PSO should recommend and/or the Supervisor should direct the PSO to place rods in manual "skill of the F529a, OTDT Chan D4422, Average Tavg 04421, Tavg-Tref 87457, Rod Motion UL-6, A3, RC Loop 1, T8-411 C OTDT, momentarily transient The crew responds using OS1201.0a, TavglDelta T

Step 1: The PSO should identify that Loop 1 Tave has Step 2: The US should direct the PSO to place rods MANUAL. This action may already have taken place prior to procedure step as a "skill of the operator" Page 6 of 22 Examination 03 EVENT INSTRUCTION Rev. 0 COMMENTS BOP checks condenser steam dumps closed. PSO adjusts charging and letdown flow as necessary to restore PZR level. Step 3: The PSO defeats the Loop 1 LlT input, Loop 1 Tavg input, and selects a non-effected loop for the Ll T,OT,OP recorder.

The following Alarms Reset: F5298, OTDT Chan Trip 04422, Average Tavg High The following alarms will have occurred and will remain VAS F8115, RC Loop 1 Tavg VAS F8119, RC Loop 1 Delta T Step 4: The PSO verifies that Tavg is within 1°F of If not, the US directs PSO to manually withdrawer rods or BOP to reduce turbine load to restore PSO places rods back in automatic. PSO checks PZR level at program, and restores level control to automatic BOP checks steam dumps in NA RESET NOTE; As a power decrease is planned rods may remain in MANUAL Step 5: The RO should verify that there are no redundant stable lights lit for the following: UL-1, T Avg La Loop To FW Iso UL-1, T Avg La-La Loop Stm Dmp Iso UL-6, RCS Loop OTLlT UL-6, RCS Loop OPLlT UL-12, Tavg La Loop To FW Iso Page 7 of 22 Examination 03 EVENT INSTRUCTION If I&C is directed to bypass the failed instrument, RCS Loop 1 Tcold, RC-TI-411, perform the following:

CP1 Bypass Cabinet SELECT: Door Open D SELECT: Enable D I SELECT: Panel Overview SELECT: BTl CP1 Position the following switches to bypass: D I TB411G D I TB411C TB412G I TB412C D SELECT: CP1 Bypass Cabinet D SELECT: Door Closed D SELECT: Enable Rev. 0 COMMENTS Step 6: The Unit Supervisor should identify Tech. Spec. 3.3.1, Reactor Trip System Instrumentation, Item 7, Overtemperature AT is applicable. Requires affected bistables to be placed in the trip condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . T.R 19, Feedwater Isolation On Low Tavg Coincident With Reactor Trip is not applicable due to 3 other channels available.

The Unit Supervisor may coordinate with I&C to place the affected bistables to bypass, using BTl, for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . Allow the crew to complete the abnormal procedure or at Chief Examiners discretion prior to entering the next Event. Page 8 of 22 Examination Rev. 0 EVENT Event 2: Decrease plant power @ 10%/hr. PSO (R) BOP (N) US (N) The crew should prepare for and initiate a plant shutdown at 10%/hr. The US should use OS1000.06, Power Decrease procedure and reference Figure 6, Rapid Power Decrease Guidelines.

Unit Supervisor:

A brief reactivity review will take place discussing the temperature limits for Tave to be used in the power decrease.

The temperature band will normally be -3°F to +3°F. Boration will be used for temperature control during the power decrease.

Control rods will be used for AFD and temperature control. Turbine Operations:

The BOP will decrease turbine load using automatic DEHC operations.

Using the laminated sheets, Figure 12 of OS1000.06 , The basic steps are: Insert the desired loading Rate. Insert the desired Power Level. Monitor turbine loading using "Load Status" is Unloading and "Load Actual" decreases.

The BOP should verify the change with control valve position change, temperature change and power change. At any time during the automatic unloading, the power increase can be stopped by activating the "Hold" function.

Reactor Power change: The crew will use control rods in automatic to control temperature during the turbine load decrease.

Using 001-56, a boration value will be determined to change the boron concentration and decrease power/temperature.

If control rods are used in manual the operator will verify rod speed, place the Rod Motion Selector (in-Hold-Out) switch to the "IN" direction and insert the rods a maximum of three steps. He will monitor temperature and power as confirmation of his actions. Using the laminated sheets for Figure 3 of OS1008.01 , Page 9 of 22 Examination 03 EVENT INSTRUCTION Rev. 0 COMMENTS Boration Check List, the RO will set up the controllers for the required boration volume and rate. The high level steps are: Verify the pumps in AUTO Verify the makeup valves are in AUTO Place Blender Mode Start Switch to STOP Place the Mode Selector Switch to Borate Set the quantity on CIS-FIQ-111 and CIS-FIQ-11 0 controllers Set the Mode Start Switch to START Verify the pumps and valves respond

Verify Plant Response.

Restore System to Automatic control. Allow the crew to commence the downpower or at Chief Examiners discretion prior to entering the next Event. Page 10 of 22 Examination 03 Rev. 0 EVENT INSTRUCTION o I SELECT: Malfunctions Event Initiation of a o I SELECT: Chemical and Volume letdown o I SELECT: mfCS012, Letdown Line Leak At Filter leak. Inlet To Reactor Coolant o INPUT Value: 0.5 o SELECT: INSERT COMMENTS PSO (C), US (C,TS) Alarms: ROMS High Alarm, RM6541, PA8 7 ft North 87399, RCS Unidentified Leak Rate High 88266, RCS Unidentified Leak Rate Warning ROMS High Alarm, RM6508-2, High Range PA8 North El-7 RO should identify decrease in VCT level. The crew responds with OS1201.02, RCS Leak: The Unit Supervisor should alert the crew to the Caution Statement prior to step 1: If the plant is in Mode 1 ,2,or 3 with SI accumulators aligned for injection and pressurizer level can not be maintained greater than 7% using normal charging lineup, then perform the following:

1) Trip reactor 2) When the reactor trip is verified, then actuate SI 3) Go to E-O, REACTOR TRIP OR SAFETY INJECTION.

Step 1: The PSO will control charging and letdown flow as necessary to maintain pressurizer level, and verify that pressurizer level is stable or increasing.

This is a continuous action step. The RNO response for this step reflects the information contained in the procedure caution as described above. Step 2: The US may refer to ER-1.1, Classification of Emergencies for potential E-Plan classification.

Step 3: The crew should identify that a CVCS leak is suspected.

The US should proceed to Step 6. Step 6: The Unit Supervisor will direct the PSO to isolate letdown.

The PSO will close the following valves: o CS-HCV-189 Page 11 of 22 Examination 03 EVENT INSTRUCTION Instructor CUE: After completion of Step 7, have the NSO report that the leak appears to be from the inlet to the reactor coolant filter, CS-F-1. Rev. 0 COMMENTS CS-HCV-190 CS-V-145 RC-V-81 PSO isolates charging to the loops: Closes CS-HCV-182 Maintains seal inj. flow 6-13 gpm utilizing FCV-121 in manual. Closes Charging Line isolation valves CS-V-142 and CS-V-143.

Alarms: When letdown flow is isolated the following alarms occur: VAS B8166, Pzr Stm/Chg Line AT Approach When the charging line isolation valves are closed the following alarms will occur: VAS 07853, Chg Pmp Disch Combined Hdr Flow Low VAS 07872, Chg Header Contm Iso VLV-142 Closed VAS 07873, Chg Header Contm Iso VLV-143 Closed When a VCT auto makeup occurs at 30% level the following alarm will occur" VAS 04660, BA Makeup VLV-110B to Chg Pmp Open Step 7: The crew should identify that the leak is isolated by verifying the following parameters: Pressurizer level-Increasing at a rate equal to the difference between seal injection and seal return. Containment air particulate and gas monitor. Stable or Decreasing.

Since the leak was in the PAB, the US may also reference PAB monitors. Containment temperature and pressure.

Stable or Decreasing Containment sump A and B levels. Normal or Page 12 of 22 Examination 03 Rev. 0 EVENT INSTRUCTION COMMENTS Decreasing Step 8: The crew will be checking charging and letdown system integrity based on: VCT level decrease-Equal to the difference between seal injection and seal return. PAS radiation levels-Stable or decreasing.

NOTE: The outcome of these verifications is time dependant.

The RNO step directs dispatching HP/NSO's to determine the source of the leak. If the source cannot be identified the step directs entering 051202.02 , Charging System Failure. The crew could also enter procedure 051252.03 , Area High Radiation abnormal.

Step 9: The Unit Supervisor should direct the PSO to establish excess letdown. Excess letdown is necessary to remove the inventory being added to the RCS via seal injection flow. NOTE: Do not exceed Excess Letdown Heat Exchanger outlet temperature of 175°F. Do not exceed Excess Letdown Heat Exchanger outlet pressure of 150 psig. The PSO establishes excess letdown as follows: Opens CC-V-434, Excess Letdown Heat Exchanger Cooling Water isolation valve Checks open CS-V-167 and 168, Excess Letdown Containment Isolation valves Checks closed CS-HCV-123, Excess Letdown flow control valve. Opens CS-V-175 and 176, Excess Containment Isolation Flushes Excess Letdown to RCDT, Aligns CS-V-170 to RCDT, Slowly opens CS-HCV-123 to flush for greater than 5 minutes, then closes CS-HCV-123. Aligns CS-V-170 to Seal Return Header. Page 13 of 22 Examination Rev. 0 EVENT Establish Excess letdown flow via CS-HCV-123.

The RO should limit flow such that excess letdown heat exchanger outlet temp is <175°F and outlet pressure is <150 psig. Using the MPCS, the PSO will remove data point A0620, letdown Outlet Flow, from the plant calorimetric calculation.

Step 10: PSO confirms RCS leakage has stopped by verifying: VCT level stable Containment radiation particulate

&gas stable Containment temperature and pressure stable Containment sump A &B level trends decreasing or normal Step 11: US Minimizes effect of loss of Normal letdown: Contacts Chemistry

& HP regarding loss of demin. flow and RCS hydrogen maintenance, Verify Tech. Spec. Compliance:

These T.S. 's are not currently applicable however, follow up will be needed if RCS chemistry samples indicate limits exceeded. T.S. 3.4.7, Chemistry o T.S. 3.4.8, Specific Activity US goes to step 18 Step 18: US verifies Tech. Spec. Compliance: T.S. 3.4.6.2, Reactor Coolant System leakage

T.S. 3.4.10, Structural Integrity Since the leak was on the letdown System, this is not considered RCS leakage and T.S. does not apply. Following US review of Tech. Specs. At step 18 or at Chief Examiners discretion continue with the next Event. Page 14 of 22 Examination 03 EVENT INSTRUCTION Event 4: D I SELECT: ASOV D SELECT: Main Steam Failure D SELECT: ptMSPK3004 D SELECT: Fail to Specified Value D INSERT FINAL VALUE: 1500 D INPUT RAMP TIME: 45 D SELECT: INSERT Rev. 0 COMMENTS BOP (C), US (TS) "0" ASOV controlling pressure channel will fail high causing ASOV to 05217, ASOV 0 Not Full BOP operator recognizes "0" ASOV opening due to a pressure Using "Skill of the Operator" the US will direct taking control of the ASOV and closing the The BOP will place the ASOV controller in MANUAL and the valve to stop uncontrolled power/reactivity The BOP/Crew should also refer to the Alarm Procedure for 05217 to verify Verify S/G pressure and compare to ASOV controllers setpoint. (instrument failure) Adjust ASOV controller setpoint and/or transfer steam load the condenser as required. (Not required) If an ASOV has failed open: PlacesNerifies ASOV control switch in close Locally isolates ASOV as necessary by closing MS-V-49. (Not necessary) PlacesNerifies controller for the ASOV in manual minimum Page 15 of 22 Examination Rev. 0 EVENT COMMENTS The US evaluates Tech. Specs: TS 3.7.1.6, Atmospheric Relief Valves. The crew is already in Action A due to the "An ASOV being tagged out. The US should determine that the "0" ASOV is operable, based upon the availability to control the valve using the "Jog" switch. No additional actions are required. TS 3.6.3, Containment Isolation Valves. The valve remains operable as a containment isolation valve, no additional actions are required.

Following US review of Tech. Specs. or at Chief Examiners discretion continue with the next series of Events. Page 16 of 22 Examination 03 EVENT INSTRUCTION Initiate the loss of power as follows: Event 5: SELECT: Malfunctions The plant has a loss of SELECT: Electrical Distributionpower. 0 SELECT: mfED038, Loss of Offsite SELECT: INSERT Trip the Turbine Driven EFW um as follows: o SELECT: Sim Diagram: FW3 LEFT Click on MS-V129 o SELECT: MANUAL ADJUST o SELECT: Final Position =0 o SELECT: INSERT NOTE: This pump will not be restored until after the power restoration in ECA-O.O. Provide delay statements to control room if asked about status, i.e., can not reset valve, having difficulty with washer and need maintenance assistance.

Rev. 0 COMMENTS PSO (M), BOP (M), US (M) The Crew enters E-O and performs the Immediate Actions steps and exits at step 3 to ECA-O.O. ECA*O.O, LOSS OF ALL AC POWER Step 1: The RO verifies that the reactor is tripped: -Checks reactor trip and bypass breakers open. -Checks neutron flux decreasing.

Step 2: The BOP verifies that the turbine is tripped: -Checks all stop valves closed. -Checks generator breaker open. NOTE: The 'A' DG fails to start and no actions will recover the 'A' DG. The 'B' EDG will trip on Low Lube Oil Pressure.

Step 3: The PSO checks the RCS Isolated. -Pressurizer PORVs closed -Letdown isolation valves closed CS-V-145 Or RC-LCV-459 Or RC-LCV-460 -Excess Letdown valve CS-V-175 and 176 are closed -RCS Sample Valves closed Page 17 of 22 Examination 03 EVENT Event 6 SW pump does not auto-start INSTRUCTION Instructor CUE: NSO will find a large quantity of oil on the "B" EDG skid. Finds oil line to engine oil pressure switches ruptured. NSO finds nothing obviously wrong with "A" EDG. If directed by crew to prevent uncontrolled start, use DG Local Panels to set LOCAL on the LOCAL/REMOTE switch. If previously directed by the crew, as time allows, report as HP that steam lines show no change in radiation levels. Instructor Delay restoration of EFW flow from the driven pump until Bus E6 is re-energized and EFW pump trips on This satisfies Rev. 0 COMMENTS Step 4: The BOP should identify that there is no EFW flow. MS-V-129 is tripped closed but no indication due to LOP. The crew should utilize Step 4 RNO, and direct an NSO to locally start the steam driven EFW pump per OS1036.03, RESETTING THE STEAM DRIVEN EFW PUMP TRIP VALVE. Step 5: The crew should continue efforts to restore power. SEP's is available BOP place UAT and RAT breaker switches in Lock. BOP should attempt an emergency start of EDG 'A'. Instructor Cue; A Slave relay start at K603 test switch S909 is unsuccessful.

Neither EDG will be able to function.

The RNO for this step is to use the SEP's diesel generator.

SEP's is available.

Upon Bus 6 power restoration from SEPs no water pump will start. The Motor Driven EFW Pump on US directs Step 5 RNO: B: BOP performs the lESEPS bus feeder breaker is aligned to Bus 6, Places the following equipment control switches in PULL TO LOCK position: DG 1 B output breaker CBS-P-9B

SI-P-6B 2) Manually closes SEPS Bus 6 breaker. 3) US goes to Step 5f. Page 18 of 22 Examination 03 EVENT Event 7 EFW pump trip Event 6 (Continued)

Restoration of SW When the crew dispatches an NSO to the field to reset the EFW pump, perform the following ( d 5 f ECA 0 0 . aroun ste 0 -.. Using Panel Graphic FW3: Open FW-V-346 SELECT' C t RtF f . omponen emo e unc Ions Summary SELECT:

SELECT' M I Ad' . anua SELECT: SELECT' INSERT . Rev. 0 COMMENTS Step 5f: Verifies EPS -ACTUATED AND SEQUENCING Step5g: Crew checks equipment loaded: Charging pump Thermal barrier cooling pumpPCCW pump EFW pump BOP (C): The EFW Pump will trip on Overcurrent when the Bus is re-energized, requiring the Turbine Driven EFW Pump to be restored to recover feedwater flow and SG level. SW or cooling tower pump NOT running, BOP must Reset RMO and manually start SW-P-41D.

BOP (C), CCT 1: Sub step g. has the operator verify one ocean SW pump or cooling tower pump running. The crew should identify that Train 'B' has no pumps running. The RNO for the step directs manually starting a SW pump. The RMO relay needs to be reset to restart the SWpump. BOP Checks AC emergency busses -AT LEAST ONE ENERGIZED BOP Checks AC emergency busses -BOP Checks emergency bus -NOT POWERED BY EMERGENCY DIESEL. US refers to Step 5j. RNO: If Emergency Bus is powered by SEPS, then maintain SEPS load limit per ATTACHMENT A while performing actions in other procedures in effect. Page 19 of 22 Examination Rev. 0 EVENT If SI was actuated, the crew will continue with E-O step 5. Page 20 of 22 COMMENTS

US returns to procedure and step in effect. FRPs shall now be implemented as required.

If a RED path exists at this time for Heat Sink, the crew will transition to FR-H.1 f Response to loss of Secondary Heat Sink, and verify actions to recover the turbine driven EFW pump are successful to restore >500 gpm EFWflow. Crew Returns to E-O Step 3 as the procedure and step in effect: Step 3A: BOP verifies AC emergency busses -AT LEAST ONE ENERGIZED Step 38: BOP responds AC emergency busses -BOTH NOT ENERGIZED.

US refers to 3B RNO: Try to restore power to other train from emergency diesel generator or offsite source as time permits. Do NOT use SEPS. SEPS is supplying Bus E6. Step 4: PSO Checks If SI Is Actuated:

Checks SI annunciators NOT lit for train A and US Refers to RNO to Check if SI is RCS pressure -LESS 1800

Pressurizer level -LESS THAN 7%

Containment pressure -GREATER THAN 4 PSIG

RCS subcooling

-LESS THAN 40°F

Any SG pressure -LESS THAN 585 PSIG SI should NOT be IF 81 is required, THEN manually Examination Rev. 0 EVENT COMMENTS SI should not be required and crew IE SI is NOT required, THEN go to ES-0.1, REACTOR TRIP transitions to ES-0.1, Reactor Trip Response.

RESPONSE, Step 1 Anticipated AOP/EOP flow-path:

OS 1201.08, OS 1201.02, E-O, ECA-O.O, E-O, ES-0.1 Terminate examination when the crew transitions to ES-0.1 and stabilizes RCS temperature with the ASDVs, or processes past step 5 of E-O or at Chief Examiner direction.

Instructor NOTE: restore A-Point A0620, Letdown Outlet Flow, to scan at the end of the scenario.

Emergency Plan: The charging system leak does not qualify as an RCS leak, so no e-plan call is made based on this event. Post scenario JPM-Alert E-plan classification on: Alert based upon EAL SA4, Unplanned Loss of most or all safety system annunciation or indication in Control Room (RDMS) with a significant transient in progress. Alert based upon EAL SA5, Power to AC emergency buses reduced to a single power source for >15 minutes such that additional single failure would result in station blackout. (as IF 15 minutes had elapsed from the start of Event 5 (LOP Event) until the SEPS breaker was closed at ECA 0.0 step 5.b RNO, then SAE on EAL SS1,Both AC buses E5 and E6 de-energized for> 15 minutes Page 21 of 22 Examination Scenario REV.O CREW CRITICAL TASKS Manually start an ocean Service Water Pump or a Cooling Tower Pump. Energize at least one AC Emergency bus before transition out of E-O, Reactor trip or Safety Injection, unless the transition is to ECA 0.0, in which case the critical task must be performed before placing safeguards equipment in the pull to lock position as directed by Step 6 of ECA-O.O. Paqe 22 of 22

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1.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />s

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1.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />s

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