ML100670650

AN2-2009-08-Draft Operating Test

ML100670650
Person / Time
Site:	Arkansas Nuclear
Issue date:	08/07/2009
From:	Brian Larson Operations Branch IV
To:	Entergy Operations
References
Download: ML100670650 (256)

Text

A2JPM-RO-RWTMU Page 1 of 6 ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT: 2 REV #: 000 DATE:

SYSTEM/DUTY AREA: Conduct of Operations TASK: Determine volume of boric acid and DI water to makeup to RWT JTA#: ANO-2-RO-CHADD-NORM-110 KA VALUE RO: 4.3 SRO: KA

REFERENCE:

2.1.23 APPROVED FOR ADMINISTRATION TO: RO: X SRO:

TASK LOCATION: INSIDE CR: OUTSIDE CR: BOTH: X SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: SIMULATOR: Perform CLASSROOM: Perform POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: CLASSROOM:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 30 Minutes REFERENCE(S): OP 2104.003 Attachment E EXAMINEE'S NAME: Badge #:

EVALUATOR'S NAME:

THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:

SATISFACTORY: UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Time Stop Time Total Time SIGNED: DATE:

SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.

A2JPM-RO-RWTMU Page 2 of 6 ADMINISTRATIVE JOB PERFORMANCE MEASURE THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall review the "Briefing Checklist - System Walkthrough" portion of OP 1064.023 Attachment 6 with the examinee.

JPM INITIAL TASK CONDITIONS:

Initial RWT Level 92%

Initial RWT concentration 2700 ppm Final RWT level 95%

Final RWT Concentration 2725 ppm A BAMT concentration 5965 ppm TASK STANDARD: Determine that the amount of Boric Acid needed is 8516 gallons +/- 85 gallons and the amount of DI water needed is 5848 gallons +/- 58 gallons TASK PERFORMANCE AIDS: OP 2104.003 Attachment E.

A2JPM-RO-RWTMU Page 3 of 6 ADMINISTRATIVE JOB PERFORMANCE MEASURE INITIATING CUE:

The CRS directs: Given the information form initial conditions, determine the boric acid and DI water feed volumes required using OP 2104.003 Attachment E Step 3.0.

START TIME:

PERFORMANCE STANDARD (Circle One)

CHECKLIST N/A SAT UNSAT Enter initial RWT level. Entered 92% as initial RWT 1

level.

N/A SAT UNSAT Calculate initial RWT Calculated initial RWT volume volume as 466262 gallons and entered 466262 gals.

2 N/A SAT UNSAT Enter final RWT level. Entered 95% as final RWT 3

level.

N/A SAT UNSAT Calculate final RWT Calculated final RWT volume volume as 480626 gallons and entered 480626 gals.

4 N/A SAT UNSAT Determine total feed Calculated feed volume volume needed. Entered required to be added and (C) 5 14364 gallons +/- 100 entered 14364 gallons.

gallons.

N/A SAT UNSAT Calculate concentration of Calculated concentration of feed volume. Entered feed volume and entered 3536.5 ppm boron +/- 3536.5 ppm boron.

(C) 6 25ppm boron.

A2JPM-RO-RWTMU Page 4 of 6 ADMINISTRATIVE JOB PERFORMANCE MEASURE PERFORMANCE STANDARD (Circle One)

CHECKLIST N/A SAT UNSAT Calculate boric acid feed Calculate boric acid feed volume. Entered 8516 gal +/- volume. Entered 8516 gal.

(C) 7 100 gal.

N/A SAT UNSAT Calculate DI water feed Calculated DI water feed volume. Entered total feed volume and entered 5846 volume - boric acid feed gals.

(C) 8 volume. Entered 5848 gals

+/- 100 gal.

END STOP TIME:

A2JPM-RO-RWTMU Page 5 of 6 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINERS COPY JPM INITIAL TASK CONDITIONS:

Initial RWT Level 92%

Initial RWT concentration 2700 ppm Final RWT level 95%

Final RWT Concentration 2725 ppm A BAMT concentration 5965 ppm INITIATING CUE:

Determine the boric acid and DI water feed volumes required to raise the RWT from 92% to 95% and change boron concentration to 2725 ppm using OP 2104.003 Attachment E Step 3.0.

A2JPM-RO-RWTMU Page 6 of 6 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINEES COPY JPM INITIAL TASK CONDITIONS:

Initial RWT Level 92%

Initial RWT concentration 2700 ppm Final RWT level 95%

Final RWT Concentration 2725 ppm A BAMT concentration 5965 ppm INITIATING CUE:

Determine the boric acid and DI water feed volumes required to raise the RWT from 92% to 95% and change boron concentration to 2725 ppm using OP 2104.003 Attachment E Step 3.0.

ANO-2-JPM-NRC-ADMIN-PDIL Page 1 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT: 2 REV #: 001 DATE:

SYSTEM/DUTY AREA: Conduct of Operations TASK: Determine limits for CEA positions using the COLR PDIL.

JTA#: ANO-2-RO-OPROC-NORM-62 KA VALUE RO: 3.9 SRO: 4.2 KA

REFERENCE:

2.1.25 APPROVED FOR ADMINISTRATION TO: RO: X SRO:

TASK LOCATION: INSIDE CR: OUTSIDE CR: BOTH: X SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: SIMULATOR: Perform CLASSROOM: Perform POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: CLASSROOM:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 15 Minutes REFERENCE(S): OP-2102.004, Unit 2 Tech Specs, and Unit 2 COLR EXAMINEE'S NAME: Badge #:

EVALUATOR'S NAME:

THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:

SATISFACTORY: UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Time Stop Time Total Time SIGNED: DATE:

SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.

ANO-2-JPM-NRC-ADMIN-PDIL Page 2 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall review the "Briefing Checklist - System Walkthrough" portion of OP 1064.023 Attachment 6 with the examinee.

JPM INITIAL TASK CONDITIONS:

The plant has been at 100% since January 1st of this year with CEAs at the program insertion limit.

The following conditions were established on 8-1-09 at 12:00 which was 250 EFPD:

Plant power was lowered to 85% power due to A Main Feedwater pump outage for bearing replacement.

Group P CEAs are full out.

Group 6 CEAs are being used for ASI control and are 90 withdrawn.

COLSS ASI is -.07.

1. 1 CEAC is inoperable for Surveillance testing.

1. 2 CEAC is operable.

TASK STANDARD: Determine that CEA are inserted into the long term steady state insertion limits and that the 5 EFPD limit has not been exceeded.

TASK PERFORMANCE AIDS: OP-2102.004, Unit 2 Tech Specs, and Unit 2 COLR

ANO-2-JPM-NRC-ADMIN-PDIL Page 3 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE INITIATING CUE:

It is now 8-1-09 at 19:00 (250.25 EFPD) and the SM/CRS directs Using OP-2102.004A for the conditions stated above determine applicable CEA insertion limits (if any) and if any time limits for the current configuration have been exceeded.

START TIME:

PERFORMANCE CHECKLIST STANDARD (Circle One)

N/A SAT UNSAT

1. Using OP-2102.004 Examinee correctly derived determines that the COLR OP-2102.004 that the COLR must be referenced to must be referenced to determine if any limits are determine if any limits apply.

applicable.

N/A SAT UNSAT (C) 2. Using cycle 20 COLR figure 3 Examinee correctly derived determines that Group 6 from graph based on given CEAs are inserted into the values that Group 6 CEAs are long term steady state inserted into the long term insertion limit of operation. steady state insertion limits (LTSSIL).

(C) 3. Using Tech Spec 3.1.3.6 or Examinee determines that the N/A SAT UNSAT OP-2102.004 determines the current CEA configuration is limits for present CEA limited to < 5 EFPD per 30 configuration. EFPD and <14 EFPD per calendar year.

(C) 4. Using Tech Spec 3.1.3.6 or Examinee determines that .25 N/A SAT UNSAT OP-2102.004 determines if EFPD is less than 5 EFPD and any time limits have been no limits have been exceeded.

exceed for LTSSIL.

END STOP TIME:

ANO-2-JPM-NRC-ADMIN-PDIL Page 4 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINERS COPY JPM INITIAL TASK CONDITIONS:

The plant has been at 100% since January 1st of this year with CEAs at the program insertion limit.

The following conditions were established on 8-1-09 at 12:00 which was 250 EFPD:

Plant power was lowered to 85% power due to A Main Feedwater pump outage for bearing replacement.

Group P CEAs are full out.

Group 6 CEAs are being used for ASI control and are 90 withdrawn.

COLSS ASI is -.07.

1. 1 CEAC is inoperable for Surveillance testing.

1. 2 CEAC is operable.

INITIATING CUE:

It is now 8-1-09 at 19:00 (250.25 EFPD) and the SM/CRS directs Using OP-2102.004A for the conditions stated above determine applicable CEA insertion limits (if any) and if any time limits for the current configuration have been exceeded.

CEA Group 6 Long Term Steady State Insertion Limits Applicable CEA insertion limits (If any) ______________________________________

NO Have any time limits for the current configuration been exceeded? ___________________

ANO-2-JPM-NRC-ADMIN-PDIL Page 5 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINEES COPY JPM INITIAL TASK CONDITIONS:

The plant has been at 100% since January 1st of this year with CEAs at the program insertion limit.

The following conditions were established on 8-1-09 at 12:00 which was 250 EFPD:

Plant power was lowered to 85% power due to A Main Feedwater pump outage for bearing replacement.

Group P CEAs are full out.

Group 6 CEAs are being used for ASI control and are 90 withdrawn.

COLSS ASI is -.07.

1. 1 CEAC is inoperable for Surveillance testing.

1. 2 CEAC is operable.

INITIATING CUE:

It is now 8-1-09 at 19:00 (250.25 EFPD) and the SM/CRS directs Using OP-2102.004A for the conditions stated above determine applicable CEA insertion limits (if any) and if any time limits for the current configuration have been exceeded.

Applicable CEA insertion limits (If any) ______________________________________

Have any time limits for the current configuration been exceeded? ___________________

ANO-2-JPM-NRC-ADMIN-2P-35A Review Page 1 of 6 ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT: 2 REV #: 001 DATE:

SYSTEM/DUTY AREA: Equipment Control TASK: Identify Errors in a completed surveillance.

JTA#: ANO-2-RO-SPRAY-SURV-22 KA VALUE RO: 3.7 SRO: 4.1 KA

REFERENCE:

2.2.12 APPROVED FOR ADMINISTRATION TO: RO: X SRO:

TASK LOCATION: INSIDE CR: OUTSIDE CR: BOTH: X SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: SIMULATOR: CLASSROOM: Perform POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: CLASSROOM:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 15 Minutes REFERENCE(S): OP-2104.005 Supplement 1 completed form EXAMINEE'S NAME: Badge #:

EVALUATOR'S NAME:

THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:

SATISFACTORY: UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Time Stop Time Total Time SIGNED: DATE:

SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.

ANO-2-JPM-NRC-ADMIN-2P-35A Review Page 2 of 6 ADMINISTRATIVE JOB PERFORMANCE MEASURE THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall review the "Briefing Checklist - System Walkthrough" portion of OP 1064.023 Attachment 6 with the examinee.

JPM INITIAL TASK CONDITIONS:

The Containment Spray System 2P-35A QUARTERLY TEST WITH SDC SECURED has just been completed IAW Procedure 2104.005 Containment Spray Supplement 1.

TASK STANDARD: Review the marked up copy of the surveillance and find 3 of the 4 errors and determine that 2P-35A is not operable.

TASK PERFORMANCE AIDS: Marked up Copy of OP-2104.005 Supplement 1.

ANO-2-JPM-NRC-ADMIN-2P-35A Review Page 3 of 6 ADMINISTRATIVE JOB PERFORMANCE MEASURE INITIATING CUE:

The Control Room Supervisor/Shift Manager directs determination of the operability of the Train A Containment Spray System by performing a review of completed surveillance data and circle any errors or omissions found.

START TIME:

PERFORMANCE CHECKLIST STANDARD (Circle One)

N/A SAT UNSAT

1. Perform review of the Reviews the surveillance surveillance procedure procedure provided.

results.

(C) 2. Discover errors and omissions Pump D/P is out of LIMITING N/A SAT UNSAT RANGE FOR OPERABILITY.

Pump D/P is out of LIMITING RANGE FOR OPERABILITY. YES has been circled instead N/A SAT UNSAT of NO.

YES has been circled instead of NO. Axial Vibes Upper Motor Brg is N/A SAT UNSAT out of LIMITING RANGE FOR Axial Vibes Upper Motor Brg is OPERABILITY.

out of LIMITING RANGE FOR OPERABILITY. 2BS-1A is not marked as full N/A SAT UNSAT open 2BS-1A is not marked as full open. (Identification of three of the four errors required and two of the three must be the Pump D/P and the Axial Vibration)

(C) 3. Report that 2P-35A is Examinee determines that 2P- N/A SAT UNSAT inoperable. 35A is inoperable.

END STOP TIME:

ANO-2-JPM-NRC-ADMIN-2P-35A Review Page 4 of 6 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINERS COPY JPM INITIAL TASK CONDITIONS:

The Containment Spray System 2P-35A QUARTERLY TEST WITH SDC SECURED has just been completed IAW Procedure 2104.005 Containment Spray Supplement 1.

INITIATING CUE:

The Control Room Supervisor/Shift Manager directs determination of the operability of the Train A Containment Spray System by performing a review of completed surveillance data and circle any errors or omissions found.

ANO-2-JPM-NRC-ADMIN-2P-35A Review Page 5 of 6 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINEES COPY JPM INITIAL TASK CONDITIONS:

The Containment Spray System 2P-35A QUARTERLY TEST WITH SDC SECURED has just been completed IAW Procedure 2104.005 Containment Spray Supplement 1.

INITIATING CUE:

The Control Room Supervisor/Shift Manager directs determination of the operability of the Train A Containment Spray System by performing a review of completed surveillance data and circle any errors or omissions found.

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

PAGE: 70 of 106 2104.005 CONTAINMENT SPRAY CHANGE 56 SUPPLEMENT 1 PAGE 6 OF 7 3.0 ACCEPTANCE CRITERIA 3.1 Record values observed during 2P-35A operation AND compare against limiting range of values for operability.

TEST QUANTITY INSTRUMENT MEASURED VALUE ACCEPTABLE LIMITING IS DATA IN (INCLUDE NORMAL RANGE RANGE FOR LIMITING TEST INST. OPERABILITY RANGE?

Running Suction 2PI-5677 Pressure (local) 32.5 psig N/A > 6 psig YES NO 2PI-5678 Discharge (local) 245.5 psig N/A N/A N/A Pressure 2PI-5622 (2C17) 247.5 psig N/A N/A N/A 2PI-5678 - 214 to Pump P 2PI-5677 215 psid N/A 245.8 psid YES NO 2FIS-5610 Flow (1) (2C17) 2430.00 gpm N/A 2225 gpm YES NO Motor Running Ammeter at Amps 2A-304 N/A N/A N/A A 49 Amps 50 Amps (CR-1-96-0272-07 B

) Amps C 48 Upper Motor Brg Radial #1 0.105 in/sec 0.155 0.372 YES NO (North) Vibes in/sec in/sec Upper Motor Brg Radial #2 (West) 0.135 in/sec 0.162 0.390 YES NO Vibes in/sec in/sec Upper Motor Brg Axial Vibes 0.321 in/sec 0.107 0.258 YES NO in/sec in/sec 2BS-4A N/A ( ) if closed N/A Closed YES NO

( ) if Full Full Open YES NO 2BS-1A (2) N/A Open per N/A per Component Component N/A Engineer Engineer Initial 34.5 2BS-1B Closure N/A N/A N/A P5058

{4.3.4}

Final P5058 41.2 N/A N/A N/A Final - 6.7 Initial N/A > 4 psid YES NO

{4.3.2}

(1) 2225 gpm verifies partial stroke of 2BS-1A AND full stroke of 2BS-3A AND 2BS-4A (2) N/A if test not performed Vibration Instrument Number _____ VIB001__________ Cal Due Date ____09/30/2009______

Vibration Data Collected By ____________ Joe STA ____________________________

FOR TRAINING PURPOSES ONLY

A2JPM-RO-RWP PAGE 1 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT: 2 REV #: 002 DATE:

SYSTEM/DUTY AREA: Radiation Control TASK: Review RWP and determine requirements for tagging B LPSI pump.

JTA#: ANO-2-RO-ADMIN-NORM-62 KA VALUE RO: 3.5 SRO: 3.6 KA

REFERENCE:

2.3.7 APPROVED FOR ADMINISTRATION TO: RO: SRO:

X X TASK LOCATION: INSIDE CR: OUTSIDE CR: BOTH: X SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: Perform SIMULATOR: LAB: Perform POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: LAB:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 10 Minutes REFERENCE(S): 2009-2002; RWP and survey form for B HPSI pump room.

EXAMINEE'S NAME: Badge #:

EVALUATOR'S NAME:

THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:

SATISFACTORY: UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Time Stop Time Total Time SIGNED: DATE:

SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.

A2JPM-RO-RWP PAGE 2 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE INITIAL PLANT CONDITIONS

1. 100% power steady state.

2. B LPSI pump must be tagged out for repair of mechanical seal.

TASK STANDARD:

Using RWP and attached B HPSI pump room survey map:

Identify 5 of the 8 following requirements to control contamination:

Determine that a single set of anti-Cs are required.

Prior to draining or venting any potentially contaminated system or known contaminated systems, notify RP.

Or Notify RP when performing activities which could change plant radiological conditions. This includes venting/draining radioactive systems, performing degas or decay heat/shutdown cooling operations, or other non-routine system functions.

Use non-porous mats or pads when kneeling, sitting or laying in contaminated areas.

All joints between Anti-C gloves and sleeves must be taped.

Once gloves have made contact with any surface inside a Contamination Area boundary, the gloves are considered contaminated and must be removed PRIOR to crossing back into the clean area.

When using temporary hoses to vent or drain a radioactive system, ensure the hose is labeled for radioactive system use only. Contact RP to verify that radiological controls are adequate.

When venting or draining, monitor the rate of system drain to ensure the rate of drain does NOT exceed the capacity of the floor drain.

Upon exiting areas posted as "Contamination Area", perform a hand and foot frisk at the designated frisker location.

TASK PERFORMANCE AIDS: RWP 2009-2002 and survey map.

SIMULATOR SETUP: NA

A2JPM-RO-RWP PAGE 3 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE Initiating CUE:

The Shift Manager directs Use the attached RWP, 2009-2002 and the survey map for B HPSI room, and determine all radiological requirements to minimize the spread of contamination while hanging tags for maintenance on B LPSI pump mechanical seal.

START TIME:

PERFORMANCECHECKLIST STANDARD CIRCLE ONE NOTE: Provide RWP and survey sheet.

1. Review RWP. Reviews attached RWP for requirements. N/A SAT UNSAT (C) 2. Determine 5 of the 8 requirements N/A SAT UNSAT Using the survey report determined the listed in RWP 2009-2002 to minimize the spread of contamination. following :

The B LPSI area is a contamination area which requires a single set of anti-Cs per the RWP.

Prior to draining or venting any potentially contaminated system or known contaminated systems, notify RP.

Or Notify RP when performing activities which could change plant radiological conditions.

This includes venting/draining radioactive systems, performing degas or decay heat/shutdown cooling operations, or other non-routine system functions Use non-porous mats or pads when kneeling, sitting or laying in contaminated areas.

All joints between Anti-C gloves and sleeves must be taped.

Once gloves have made contact with any surface inside a Contamination Area boundary, the gloves are considered contaminated and must be removed PRIOR to crossing back into the clean area.

When using temporary hoses to vent or drain a radioactive system, ensure the hose is labeled for radioactive system use only.

Contact RP to verify that radiological controls are adequate.

When venting or draining, monitor the rate of system drain to ensure the rate of drain does NOT exceed the capacity of the floor drain.

Upon exiting areas posted as "Contamination Area", perform a hand and foot frisk at the designated frisker location.

END STOP TIME:

A2JPM-RO-RWP PAGE 4 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINERs COPY INITIAL PLANT CONDITIONS

1. 100% power steady state.

2. B LPSI pump must be tagged out for repair of mechanical seal.

Initiating CUE:

The Shift Manager directs Use the attached RWP, 2009-2002 and the survey map for B HPSI room, and determine all radiological requirements to minimize the spread of contamination while hanging tags for maintenance on B LPSI pump mechanical seal.

A2JPM-RO-RWP PAGE 5 OF 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINEEs COPY INITIAL PLANT CONDITIONS

1. 100% power steady state.

2. B LPSI pump must be tagged out for repair of mechanical seal.

Initiating CUE:

The Shift Manager directs Use the attached RWP, 2009-2002 and the survey map for B HPSI room, and determine all radiological requirements to minimize the spread of contamination while hanging tags for maintenance on B LPSI pump mechanical seal.

Entergy Arkansas Nuclear One RADIOLOGICAL WORK PERMIT RWP

Title:

OPERATIONS ACTIVITIES UNIT-2 RWP No.: 20092002 Rev. 00 1.16 Task: REACTOR OPERATION + SURVEIL

• 20092002*

Comments:

RWP Type: GENERAL RWP Status: Begin Date: Close On Date:

ACTIVE 1/1/2009 12/31/2009 Prepared By: LACY, RUSSELL S Job Supervisor: Randall Walters ALARA ID: Stay Time Alarm(hh:mm):

Estimated Dose: 880 mrem Estimated Hours: 20,512.00 Chirp Rate:

Actual Dose: 66 mrem Actual Hours: 3,563.88 Locations Buildings Elevations Rooms LOW LEVEL RADWASTE BUILDING 354 NON-LOCKED HIGH RADIATION AREA OLD RADWASTE BUILDING 354 OUTSIDE CONTROLLED ACCESS OUTSIDE CONTROLLED ACCESS ALL OUTSIDE CONTROLLED ACCESS UNIT 2 AUXILIARY BUILDING ALL NON-LOCKED HIGH RADIATION AREA Radiological Conditions Description Value Unit Smear data is in dpm/100 cm2 unless otherwise noted. <1-40K DPM/100CM2 General area gamma dose rates are in mrem/hour unless otherwise <1-200 MILLIREM/HOUR Tasks Task Description Status 1 OPERATIONS ACTIVITIES ANO-2 Active Requirements Requirement Groups Requirement Descriptions N/A Additional Instrutions Instructions 1:

Instructions 2:

Instructions 3:

Approvals Approver Title Name Date ALARA REVIEW NICKELS, THOMAS W 12/10/2008 RWP PREPARER NICKELS, THOMAS W 12/10/2008 RP SUPERVISOR MARVEL JR, STANLEY D 12/11/2008 Attachments N/A 3/3/2009 8:31:28PM Page 1 of 1

Entergy Arkansas Nuclear One RADIOLOGICAL WORK PERMIT Task Number: 1 RWP No.: 20092002 Rev.: 00 Task

Description:

OPERATIONS ACTIVITIES ANO-2 Task Status: Active 1.16 Task: REACTOR OPERATION + SURVEIL ALARA ID: Stay Time Alarm(hh:mm): 16:00 Estimate Dose: 880.00 Estimate Hours: 20,512.00 Chirp Rate:

Hi-Rad: Yes Hot Particle: No Locked Hi-Rad: No Hi-Contamination: No Alarm Settings Low Gamma Dose (mrem) Low Gamma Rate (mrem/hr) High Gamma Dose (mrem) High Gamma Rate (mrem/hr) 20.00 200.00 Low Beta Dose Low Beta Dose High Beta Dose High Beta Rate Low Neutron Dose Low Neutron Dose High Neutron Dose High Neutron Rate 3/3/2009 8:32:04PM Page 1 of 4

Entergy Arkansas Nuclear One RADIOLOGICAL WORK PERMIT Task Number: 1 RWP No.: 20092002 Rev.: 00 Requirements Requirement Groups Requirement Descriptions Contamination Control All materials are required to be surveyed in a small articles monitor or hand frisked by RP (with RP Supervisor approval) PRIOR TO unconditional release from a Radiologically Controlled Area.

Prior to draining or venting any potentially contaminated system or known contaminated systems, notify RP.

Use non-porous mats or pads when kneeling, sitting or laying in contaminated areas.

Dosimetry Requirements A blue dot on your Dosimeter of Legal Record (DLR) is used to identify a hearing impairment with regards to Electronic Alarming Dosimeter (EAD). IF you are designated as having a hearing impairment, THEN you must have an alarm amplifying device FOR WORK IN HIGH RADIATION AREAS- If your work conditions are in OR will cause hearing impairment (such as work in a high noise area, use of a communications headset, etc.) THEN the use of an EAD amplifying device (PAM) is required If an EAD dose alarm occurs: Secure Work, Immediately leave the RCA, Notify RP.

If an EAD dose rate alarm occurs: Secure Work, Back out of the immediate area until the alarm clears, Notify others in your work crew, Immediately notify RP for further instructions.

Periodically check your EAD. This check should be performed more frequently in areas where your ability to hear is diminished.

Whole body DLR and EAD required for entry Exposure Reduction Use Low Dose Waiting Areas whenever possible to minimize exposure.

Protective Requirements All joints between Anti-C gloves and sleeves must be taped.

Entry into Contamination Areas require Single Anti-Cs.

Entry into High Contamination Areas require Double Anti-Cs .

Notify RP prior to reaching across Contamination Area boundaries.

Once gloves have made contact with any surface inside a Contamination Area boundary, the gloves are considered contaminated and must be removed PRIOR to crossing back into the clean area Operations personnel may reach across a Contamination Area boundary without gloves ONLY for the purpose of using a flashlight to illuminate an item or using a mirror to enhance the ability to inspect PROVIDED that nothing is touched.

When using temporary hoses to vent or drain a radioactive system, ensure the hose is labeled for radioactive system use only. Contact RP to verify that radiological controls are adequate.

When venting or draining, monitor the rate of system drain to ensure the rate of drain does NOT exceed the capacity of the floor drain.

When work involves reaching across a Contamination Area boundary, and the only portion of the body that will make contact with a contaminated surface is the hands, THEN the use of cotton liners with rubber gloves or surgeon's gloves is permitted.

RP Coverage A "Cat 3 Advanced Radworker" may enter posted High Radiation Areas IF he/she is using a gamma sensitive RP instrument to monitor dose rates. (NOTE: An EAD is NOT an appropriate survey instrument).

Initial / Intermittent RP coverage is required for entry in to High Radiation Areas.

Notify RP when performing activities which could change plant radiological conditions.

This includes venting/draining radioactive systems, performing degas or decay heat/shutdown cooling operations, or other non-routine system functions 3/3/2009 8:32:04PM Page 2 of 4

Entergy Arkansas Nuclear One RADIOLOGICAL WORK PERMIT Task Number: 1 RWP No.: 20092002 Rev.: 00 Notify the Zone coverage RP or the on-duty shift RP of areas to be entered and work to be performed. RP is not required to be notified for entries to the Auxiliary Building to perform routine activities that do not involve HRA, CA, overhead entry or system breech.

Tech Spec monitoring is required for entry into High Radiation Areas and is accomplished by meeting the following criteria: A radiological brief from RP, AND an electronic alarming dosimeter (EAD).

Radiological Conditions Radiological conditions should be reviewed to ensure awareness of conditions in your work area. This information can be obtained from either a Status Board OR RP personnel Upon exit of an RCA, whole body monitoring is required utilizing a whole body contamination monitor. A whole body gamma monitor must also be cleared. IF the RCA is a satelite RCA with no whole body contaminaton monitor available, THEN the radworker should: a) perform a hand and foot frisk. b) IF the frisk indicates contamination is present, THEN contact RP. c) IF the frisk DOES NOT indicate the presence of contamination, THEN proceed to the nearest whole body contamination monitor Upon exiting areas posted as "Contamination Area" , perform a hand and foot frisk at the designated frisker location.

Respiratory Protection Based on historical and current data, the airborne radioactivity is less than 30 percent of a DAC. Respiratory protection is not required unless otherwise directed by RP Supervision.

Special Radiological Requirements Access to the overhead >8 feet is allowed with provisions specified by RP. When accessing overheads, then wear rubber gloves while operating valves but remove them prior to descending the ladder. Use a ladder to climb directly to the valve to be operated. DO NOT touch any interferences or components in the overhead without explicit permission by RP. Upon completion, perform a large area masslin survey of the ladder to determine if any cross contamination has occurred. Notify RP immediately if the ladder is contaminated. Use your survey meter to obtain dose rates of all areas entered.

Access to the top of partial walls separating Radiation/High Radiation areas from Locked High Radiation Areas or Very High Radiation Areas is NOT permitted on this RWP.

Prerequisites for a secondary resin transfer: A berm sufficient to contain the material being tranferred is required.The resin transfer fill head is to be secured such that changes in pressure will not cause a spill. Pre-transfer walkdowns must be done to ensure that hose connections and leak integrity is satisfactory. A resin sample must be taken and analyzed. If the total activity to be transferred is less than 5.389E02 microcuries, no further review is required.

Stop Work Criteria Work involving alpha contamination greater than or equal to 100 dpm/100cm2 cannot be worked on a General RWP Work involving beta/gamma contamination greater than 5 mrad/hour/100cm2 must have controls inplace to eliminate the potential of creating an airborne radioactivity area or the potential to cause "clean area" contamination Additional Instructions Instructions 1:

Instructions 2:

Instructions 3:

3/3/2009 8:32:04PM Page 3 of 4

Entergy Arkansas Nuclear One RADIOLOGICAL WORK PERMIT Task Number: 1 RWP No.: 20092002 Rev.: 00 Attachments N/A 3/3/2009 8:32:04PM Page 4 of 4

Radiation Area (RA)

High Radiation Area (HRA)

Locked High Radiation Area (LHRA) 5 - 10 mrem/hr CA Low Dose Waiting Area (LDWA)

LDWA RADS Telemetry Device Dose Rates may change due to current conditions.

2-5 mrem/hr 10- 15 mrem/hr RA This map is for your 2014 2013 information only. Contact a Radiation Protection Technician for answers to 2015 questions.

CA 6 - 12 mrem/hr

ANO-2-JPM-NRC-ADMIN-DNBRL Page 1 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT: 2 REV #: 001 DATE:

SYSTEM/DUTY AREA: Conduct of Operations TASK: Determine if COLR DNBR limit is being met during a loss of COLSS.

JTA#: ANO-2-SRO-EOPAOP-OFFNORM-233 KA VALUE RO: 3.9 SRO: 4.2 KA

REFERENCE:

2.1.25 APPROVED FOR ADMINISTRATION TO: RO: SRO: X TASK LOCATION: INSIDE CR: OUTSIDE CR: BOTH: X SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: SIMULATOR: Perform CLASSROOM: Perform POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: CLASSROOM:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 15 Minutes REFERENCE(S): Unit 2 Tech Specs and Unit 2 COLR EXAMINEE'S NAME: Badge #:

EVALUATOR'S NAME:

THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:

SATISFACTORY: UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Time Stop Time Total Time SIGNED: DATE:

SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.

ANO-2-JPM-NRC-ADMIN-DNBRL Page 2 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall review the "Briefing Checklist - System Walkthrough" portion of OP 1064.023 Attachment 6 with the examinee.

JPM INITIAL TASK CONDITIONS:

The plant is at 85% power, Steady State due to 2P-1A Feedwater pump is out of service for maintenance.

COLSS has been declared inoperable due to failed power supplies.

The CPC average DNBR is 2.35.

The CPC average ASI is .0001

1. 1 CEAC is inoperable for Surveillance testing.

1. 2 CEAC is operable.

TASK STANDARD: Determine that Technical Specifications LCO 3.2.4 action b is applicable.

TASK PERFORMANCE AIDS: Unit 2 Tech Specs and Unit 2 COLR

ANO-2-JPM-NRC-ADMIN-DNBRL Page 3 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE INITIATING CUE:

Determine if any Tech Specs LCOs are applicable and/or actions that are required for this condition.

START TIME:

PERFORMANCE CHECKLIST STANDARD (Circle One)

N/A SAT UNSAT

1. Using Tech Spec 3.2.4 Examinee correctly derived determines that the COLR from Tech Spec 3.2.4 that must be referenced to since COLSS is inoperable, determine if TS are satisfied. the COLR graph must be referenced to determine if Tech Spec 3.2.4 is met.

N/A SAT UNSAT (C) 2. Using cycle 20 COLR figure Examinee correctly derived determines DNBR is not in from graph based on given the acceptable region for values that DNBR is not in the operation and that Tech Spec acceptable region of operation LCO 3.2.4.c should be and determined that LCO entered. 3.2.4.c is applicable for the current condition.

(C) 3. Using Tech 3.2.4 determine Examinee correctly N/A SAT UNSAT that DNBR must meet the determines the DNBR must be requirements of T.S 3.2.4 restored to meet the action b requirements of the COLR graph within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to comply with Tech Spec 3.2.4 action b.

EXAMINER's NOTE: Examinee may discuss the Tech Spec applicability at this point stating that Tech Spec 3.2.4 LCO requires power to be lowered so that DNBR is restored to the acceptable region within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

END STOP TIME:

ANO-2-JPM-NRC-ADMIN-DNBRL Page 4 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINERS COPY JPM INITIAL TASK CONDITIONS:

The plant is at 85% power, Steady State due to 2P-1A Feedwater pump is out of service for maintenance.

COLSS has been declared inoperable due to failed power supplies.

The CPC average DNBR is 2.35.

The CPC average ASI is .0001

1. 1 CEAC is inoperable for Surveillance testing.

1. 2 CEAC is operable.

INITIATING CUE:

Determine if any Tech Specs LCOs are applicable and/or actions that are required for this condition.

T.S. LCO 3.2.4.c Applicable Tech Spec LCOs (if any) _________________________

T.S. LCO 3.2.4. Action b Actions required to comply with Tech Specs (if any) ______________________________

Tech Spec 3.2.4 LCO Action b requires power to be lowered so that DNBR is restored to the acceptable region within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

ANO-2-JPM-NRC-ADMIN-DNBRL Page 5 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINEES COPY JPM INITIAL TASK CONDITIONS:

The plant is at 85% power, Steady State due to 2P-1A Feedwater pump is out of service for maintenance.

COLSS has been declared inoperable due to failed power supplies.

The CPC average DNBR is 2.35.

The CPC average ASI is .0001

1. 1 CEAC is inoperable for Surveillance testing.

1. 2 CEAC is operable.

INITIATING CUE:

Determine if any Tech Specs LCOs are applicable and/or actions that are required for this condition.

Applicable Tech Spec LCOs (if any) _________________________

Actions required to comply with Tech Specs (if any) ______________________________

A2JPM-SRO-SFPMU PAGE 1 of 9 ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT: 2 REV #: 000 DATE:

SYSTEM/DUTY AREA: Conduct of Operations TASK: Review Spent Fuel Pool Makeup Calculation for Errors JTA#: ANO-SRO-SRO-ADMIN-NORM-197 KA VALUE RO: 4.3 SRO: 4.4 KA

REFERENCE:

2.1.23 APPROVED FOR ADMINISTRATION TO: RO: SRO:

X TASK LOCATION: INSIDE CR: OUTSIDE CR: BOTH:

X SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: SIMULATOR: LAB:

Perform POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: LAB:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 15 Minutes REFERENCE(S): OP 2104.006, Attachment F EXAMINEE'S NAME: Badge #:

EVALUATOR'S NAME:

THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:

SATISFACTORY: UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Stop Total Time Time Time SIGNED: DATE:

SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.

A2JPM-SRO-SFPMU PAGE 2 of 9 ADMINISTRATIVE JOB PERFORMANCE MEASURE THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall review the "Briefing Checklist - System Walkthrough" portion of OP 1064.023 Attachment 6 with the examinee.

JPM INITIAL TASK CONDITIONS:

Plant is at 100% power.

PMS computer is out of service.

Initial Spent Fuel Pool Level = 401 0 Tilt Pit Gate is installed Cask Loading Pit Gate is installed A BAM tank concentration is 5950 ppmb SFP boron concentration is 2964 ppmb Cask loading pit operations has lowered the SFP level CBOT has performed actions per OP 2104.006 step 10.3.

Final Spent Fuel Pool Level = 401 4 TASK STANDARD:

SRO candidates should identify the following:

1) Boron Concentration of the feed source should be 5950 NOT 4950. (CB)

2) The Feed volume (F) calculated previously was transposed into the feed volumes calc as 1788 gallons not the 1878 gallons correctly calculated. Therefore both the calculated Boric acid and DI water volumes are wrong.

And calculate the following correct feed volumes:

3) Boric acid volume calculated to be within 910 gallons to 960 gallons. (VB)

4) Determine DI water volume to be within 918 gallons to 968 gallons. (VW)

TASK PERFORMANCE AIDS:

OP 2104.006, Attachment F

A2JPM-SRO-SFPMU PAGE 3 of 9 ADMINISTRATIVE JOB PERFORMANCE MEASURE INITIATING CUE:

Chemistry has just notified the Control Room that when SPF level is raised, we need to make a single feed solution using a combination of boric acid from the A BAM tank and DI water maintaining SFP boron concentration 2964 PPM. The SM directs, Review for accuracy and correct any errors in the completed OP 2104.006, Attachment F.

START TIME:

PERFORMANCE CHECKLIST STANDARDS (Circle One)

1. Reviewed the completed form Reviewed the completed form N/A SAT UNSAT OP 2104.006, Attachment F. OP 2104.006, Attachment F.

2. Determined the calculated Calculated the feed volume to N/A SAT UNSAT volume of solution to be be added to the SFP, F, to be correct. 1878 gallons.

C 3. Determined that the boron Recognized the boron N/A SAT UNSAT concentration of the feed concentration of the feed source source was in error. was recorded as 4950 ppm instead of the given value of 5950 ppm.

C 4. Determined the calculated Recognized that the feed N/A SAT UNSAT volume of solution used in the volume to be added to the SFP, calculation of the feed F, was recorded in error as volumes of boric acid 1788 gallons NOT the 1878 gallons calculated on the previous page.

Examiners Note: the candidate may need to be prompted to calculate the volume of Boric acid and DI water.

C 5. Determined the Boron volume Recognized the Boron volume N/A SAT UNSAT to be added as calculated was to be added as calculated was in error and determined the in error and determined the correct volume to be 910 correct volume to be 935.5 gallons to 960 gallons. gallons instead of the 1070.6 gallons.

C 6. Determined the DI water Recognized the DI water N/A SAT UNSAT volume to be added as volume to be added as calculated was in error and calculated was in error and determined the correct volume determined the correct volume to be within 918 gallons to 968 to be 942.5 gallons instead of gallons. 717.4 gallons.

END STOP TIME:

A2JPM-SRO-SFPMU PAGE 4 of 9 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINERS COPY JPM INITIAL TASK CONDITIONS:

Plant is at 100% power.

PMS computer is out of service.

Initial Spent Fuel Pool Level = 401 0 Tilt Pit Gate is installed Cask Loading Pit Gate is installed A BAM tank concentration is 5950 ppmb SFP boron concentration is 2964 ppmb Cask loading pit operations has lowered the SFP level CBOT has performed actions per OP 2104.006 step 10.3.

Final Spent Fuel Pool Level = 401 4 INITIATING CUE:

Chemistry has just notified the Control Room that when SPF level is raised, we need to make a single feed solution using a combination of boric acid from the A BAM tank and DI water maintaining SFP boron concentration 2964 PPM. The SM directs, Review for accuracy and correct any errors in the completed OP 2104.006, Attachment F.

A2JPM-SRO-SFPMU PAGE 5 of 9 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINEES COPY JPM INITIAL TASK CONDITIONS:

Plant is at 100% power.

PMS computer is out of service.

Initial Spent Fuel Pool Level = 401 0 Tilt Pit Gate is installed Cask Loading Pit Gate is installed A BAM tank concentration is 5950 ppmb SFP boron concentration is 2964 ppmb Cask loading pit operations has lowered the SFP level CBOT has performed actions per OP 2104.006 step 10.3.

Final Spent Fuel Pool Level = 401 4 INITIATING CUE:

Chemistry has just notified the Control Room that when SPF level is raised, we need to make a single feed solution using a combination of boric acid from the A BAM tank and DI water maintaining SFP boron concentration 2964 PPM. The SM directs, Review for accuracy and correct any errors in the completed OP 2104.006, Attachment F.

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 1 of 9 2104.006 FUEL POOL SYSTEMS CHANGE:

ATTACHMENT F PAGE 1 of 4 BORIC ACID CONCENTRATION ADJUSTMENT VOLUME DATA REFERENCE NOTE If filling Tilt Pit, this attachment should only be used to estimate time needed to complete evolution because the Tilt Pit does NOT have installed level indication.

Initial level is only estimated and can result in inaccurate calculation.

Gal/Ft. Total Volume (Gal)

CASK LOADING PIT (CLP)

- Elev 358 to bottom of gate 722.4 13,726

- Bottom of gate to Elev 4016 795.6 19,493 FUEL TILT PIT (FTP)

- Elev 362 to bottom of gate 1,196.8 (1) 17,952 (1)

- Bottom of gate to Elev 4016 1,275.3 31,244 SPENT FUEL POOL (SFP)

- Elev 362 to top of racks 5,349.5 (2) 84,255 (2)

- Top of racks to Elev 4016 5,634.4 133,817 NOTES

1. Does NOT include volume occupied by tilt machine.

2. Does NOT include fuel. Includes ~ 600 ft3 allowance for fuel racks.

Fuel Pool Makeup Volume Calculation (N/A areas NOT hydraulically connected to SFP)

F = Feed Volume LI = Level Change (in inches)

F = [(LI)(SFP Level gal)(1 ft)]+[(LI)(CLP Level gal)(1 ft)]+[(LI)(FTP Level gal)(1 ft)]

(1 ft) (12 in.) (1 ft) (12 in.) (1 ft) (12 in.)

F = [( 4 in.)(5634.4 gal) + [( N/A in.)(795.6 gal) + [( N/A in.)(1275.3 gal) 12 in. 12 in. 12 in.

F = ____ 1878______gallons Cask Loading Pit Makeup/Fill Volume Calculation (Gate installed, N/A elevation NOT filled)

F = Feed Volume LB = Level change (in feet) below bottom of gate LA = Level change (in feet) above bottom of gate F = [(LB)(Volume below bottom of gate in gal/ft)] + [(LA)(Volume above bottom of gate in gal/ft)]

F = [__ N/A____ ft.)(722.4 gal/ft)] + [(___ N/A___ ft)(795.6 gal/ft)

F = _____ N/A ____gallons

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 2 of 9 2104.006 FUEL POOL SYSTEMS CHANGE:

ATTACHMENT F PAGE 2 of 4 Fuel Tilt Pit Makeup/Fill Volume Calculation (Gate installed, N/A elevation NOT filled)

F = Feed Volume LB = Level change (in feet) below bottom of gate LA = Level change (in feet) above bottom of gate F = [(LB)(Volume below bottom of gate in gal/ft)] + [(LA)(Volume above bottom of gate in gal/ft)]

F = [_N/A ft.)(1196.8 gal/ft)] + [(__N/A ft)(1275.3 gal/ft)

F = __ N/A _gallons Required Feed Solution Concentration Calculation CI = Initial Fuel Pool Boron Concentration = 2964 ppm CF = Final Desired Boron Concentration = 2964 ppm CW = Feed Solution Concentration = (VF x CF) - (VI x CI)

F CW = ( 217,133 gal x 2964 ppm) - ( 215255 gal x 2964 ppm)

( 1878 gal)

CW = 2964 ppm IF Feed Solution will be a combination of Boric Acid and demineralized water, THEN calculate feed volume as follows:

F = Feed Volume (from volume calculation)

VB = Volume of Boric Acid to Add VW = Volume of DI Water to Add CB = Boron Concentration of feed source = 4950 ppm Calculate Feed Volumes VB = (F) x (CF) = ( 1788 gal) x ( 2964 ppm)

CB ( 4950 ppm)

VB = 1070.6 gal Amount of Boric Acid to add VW = F - VB = ( 1788 gal) - ( 1070.6 gal)

VW = 717.4 gal Amount of DI Water to add

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 3 of 9 2104.006 FUEL POOL SYSTEMS CHANGE:

ATTACHMENT F PAGE 3 of 4 IF Feed Solution will be a combination of two Boric Acid solutions, THEN calculate feed volumes as follows:

F = Feed Volume (from volume calculation)

VB1 = Volume of 1st Boric Acid Solution to add VB2 = Volume of 2nd boric Acid Solution to add CB1 = Boron Concentration of 1st Boric Acid Solution = N/A ppm CB2 = Boron Concentration of 2nd Boric Acid Solution = N/A ppm CF = Boron Concentration of Feed Volume (F) = N/A ppm Calculate Feed Volumes VB1 = F x (CF - CB2)

(CB1 - CB2)

VB1 = ( N/A gal) x ( N/A ppm - N/A ppm)

( N/A ppm - N/A ppm)

VB1 = N/A gal Volume of Boric Acid of Concentration CB1 to add VB2 = F - VB1 = ( N/A gal) - ( N/A gal)

VB2 = N/A gal Volume of Boric Acid of Concentration CB2 to add Definition of terms:

I = Boron Concentration of Feed Solution desired VB = Boric Acid Volume CB = Boron Concentration of Boric Acid in BAM tank VW = Demineralized Water Volume To determine ratio of volumes of Demineralized Water and Boric Acid for makeup to maintain Specified Boron concentration:

VW = CB - CF = Ratio of demineralized water to Boric Acid VB CF to obtain desired feed concentration CF.

This ratio may be used to adjust the flowrate settings on Boric Acid Flow Controller (2FIC-4926) and RMW Flow Controller (2FIC-4927) to provide a Feed Solution of the desired concentration.

PROC./WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 1 of 9 2104.006 FUEL POOL SYSTEMS CHANGE:

ATTACHMENT F PAGE 4 OF 4 IF Feed solution boron concentration AND Feed volume is known, THEN calculate Final Spent Fuel Pool boron concentration as follows:

Definition of Terms CI = Initial Fuel Pool Boron Concentration CW = Feed Solution Concentration VF = Final Volume VI = Initial Volume F = Feed Volume Final Concentration Calculation CF = Final Boron Concentration = (CW x F) + (VI x CI)

VF CF = (CW 2964 ppm x F 1788 gal) + (VI 215,255 gal x CI 2964 ppm)

VF 217,133 gal CF = 2964 ppm Performed By Joe_Ro Date Todays Date Supervisor ___________________________________ Date____________________________

ANO-2-JPM-NRC-ADMIN MSSVINOP Page 1 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT: 2 REV #: 001 DATE:

SYSTEM/DUTY AREA: Equipment Control TASK: Verify RPS trip set point determination for inoperable MSSV JTA#: ANO-SRO-ADMIN-NORM-231 KA VALUE RO: 3.4 SRO: 4.7 KA

REFERENCE:

2.2.40 APPROVED FOR ADMINISTRATION TO: RO: SRO: X TASK LOCATION: INSIDE CR: OUTSIDE CR: BOTH: X SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: SIMULATOR: Perform CLASSROOM: Perform POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: CLASSROOM:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 15 Minutes REFERENCE(S): Unit 2 Tech Spec 3.7.1.1 EXAMINEE'S NAME: Badge #:

EVALUATOR'S NAME:

THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:

SATISFACTORY: UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Time Stop Time Total Time SIGNED: DATE:

SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.

ANO-2-JPM-NRC-ADMIN MSSVINOP Page 2 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall review the "Briefing Checklist - System Walkthrough" portion of OP 1064.023 Attachment 6 with the examinee.

JPM INITIAL TASK CONDITIONS:

The plant is at 90% power, 440 EFPD, Steady State.

MSSV testing is in progress.

One MSSV, 2PSV-1054 has been declared inoperable.

The value for MTC provide by Reactor Engineering for 440 EFPD is -2.6 k/k/°F.

TASK STANDARD: Determine the maximum High Linear Power Level and RPS trip set point to be 91.0% to comply with Technical Specification 3.7.1.1.

TASK PERFORMANCE AIDS: Unit 2 Tech Specs

ANO-2-JPM-NRC-ADMIN MSSVINOP Page 3 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE INITIATING CUE:

Determine the Maximum High Linear Power Level and RPS Trip Set point per Tech Specs allowed for this condition to remain at power.

PERFORMANCE CHECKLIST STANDARD (Circle One)

N/A SAT UNSAT

1. Using Tech Spec 3.7.1 Table Examinee correctly derived 3.7-1 determines new from table based on 1 MSSV maximum power and RPS inoperable, the maximum linear power trip set point to allowable linear power level be 79%. and RPS trip setpoint to be 79%.

N/A SAT UNSAT (C) 2. Using Tech Spec 3.7.1 figure Examinee correctly derived 3.7-1 determines new from graph based on MTC of maximum power and RPS -2.6 k/k/°F and knowing that linear power trip set point to one MSSV is inoperable be 91%. determined that maximum power and RPS linear power trip set point should be 91.0%.

EXAMINER's NOTE: Examinee should discuss the Tech Spec applicability at this point stating that Tech Spec 3.7.1.1 LCO to allow power operations to continue provided that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> power is reduced to the maximum power of 79% or as allowed by figure 3.7-1 (91%) and within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, the RPS trip set point adjusted to be less than the value of 79% or as allowed in figure 3.7-1 (91%).

END

ANO-2-JPM-NRC-ADMIN MSSVINOP Page 4 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINERS COPY JPM INITIAL TASK CONDITIONS:

The plant is at 90% power, 440 EFPD, Steady State.

MSSV testing is in progress.

One MSSV, 2PSV-1054 has been declared inoperable.

The value for MTC provided by Reactor Engineering for 440 EFPD is -2.6 k/k/°F.

INITIATING CUE:

Determine the Maximum High Linear Power Level and RPS Trip Set point per Tech Specs allowed for this condition to remain at power.

ANO-2-JPM-NRC-ADMIN MSSVINOP Page 5 of 5 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINEES COPY JPM INITIAL TASK CONDITIONS:

The plant is at 90% power, 440 EFPD, Steady State.

MSSV testing is in progress.

One MSSV, 2PSV-1054 has been declared inoperable.

The value for MTC provided by Reactor Engineering for 440 EFPD is -2.6 k/k/°F.

INITIATING CUE:

Determine the Maximum High Linear Power Level and RPS Trip Set point per Tech Specs allowed for this condition to remain at power.

ANO-2-JPM-NRC-KI Page 1 of 6 ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT: 2 REV #: 001 DATE:

SYSTEM/DUTY AREA: Radiation Controls (A.3)

TASK: Approve administration of Potassium Iodide.

JTA#: ANO-SRO-EPLAN-EMERG-292 KA VALUE RO: 3.4 SRO: 3.8 KA

REFERENCE:

2.3.14 APPROVED FOR ADMINISTRATION TO: RO: SRO: X TASK LOCATION: INSIDE CR: OUTSIDE CR: BOTH: X SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: SIMULATOR: Perform CLASSROOM: Perform POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: CLASSROOM:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 20 Minutes REFERENCE(S): 1903.035, Administration of Potassium Iodide EXAMINEE'S NAME: Badge #:

EVALUATOR'S NAME:

THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:

SATISFACTORY: UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Time Stop Time Total Time SIGNED: DATE:

SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.

ANO-2-JPM-NRC-KI Page 2 of 6 ADMINISTRATIVE JOB PERFORMANCE MEASURE THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall review the "Briefing Checklist - System Walkthrough" portion of OP 1064.023 Attachment 6 with the examinee.

JPM INITIAL TASK CONDITIONS:

The plant is tripped from 100% power.

300 gpm LOCA in progress.

Loss of Offsite power is in progress.

LOCA EOP is being implemented.

RDACS indicates an off site release in progress.

Data indicates I-131 concentration of 5.0 E-04 ci/cc in area of work in Upper South Piping Penetration room.

Whole body dose rates in area of work are 1Rem/hr.

General Emergency has just been declared.

Joe Mechanic has completed 1903.035C form, ANO Medical Questionnaire-Iodine Sensitivity.

RP estimates that it will take approximately 15 minutes to complete emergency actions and stop the release and all RP required controls/authorizations are complete.

Air Purifying Respirator with Iodine Canister having a protection factor of 1.0 will be used in place of a SCBA due to piping interference.

EOF, OSC and TSC have NOT been staffed.

TASK STANDARD: Determine that KI should be administered.

TASK PERFORMANCE AIDS: OP 1903.0035, Potassium Iodide Administration, completed form 1903.035C, ANO Medical Questionnaire-Iodine Sensitivity and 1903.035A, Potassium Iodide Administration.

ANO-2-JPM-NRC-KI Page 3 of 6 ADMINISTRATIVE JOB PERFORMANCE MEASURE INITIATING CUE:

Determine the need to issue KI, Potassium Iodide and complete necessary paperwork, using OP 1903.035.

START TIME:

PERFORMANCE CHECKLIST STANDARD (Circle One)

N/A SAT UNSAT

1. Review OP 1903.035, Examinee determined the Administration of Potassium criteria for administration of KI Iodide to determine criteria for is 25 REM exposure to administering KI. Thyroid committed dose equivalent or if concentration is unknown, the possibility exists for receiving large amounts of radioactive airborne iodine.

N/A SAT UNSAT (C) 2. Using graph on 1903.035 Determined that expected Attachment 1 and information exposure will exceed 25 REM provided in initial conditions, threshold.

determine that Joe Mechanic will exceed 25 REM during the maintenance evolution.

N/A SAT UNSAT (C) 3. Determine that Joe Mechanic Reviewed 1903.035C form is not sensitive to nor and determined that Joe experienced an allergic Mechanic was not sensitive to reaction to Iodide. nor experienced an allergic reaction to Iodide.

N/A SAT UNSAT

4. Complete form 1903.035A. Completed all areas of form 1903.035A, Potassium Iodide Administration, from initial conditions:

Estimated Thyroid dose commitment.

Date.

Respiratory protection.

Signature of Joe Mechanic that he chooses to receive KI.

ANO-2-JPM-NRC-KI Page 4 of 6 ADMINISTRATIVE JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARD (Circle One)

N/A SAT UNSAT (C) 5. Determine that KI may be Examinee approved approved for distribution to distribution of KI to Joe Joe Mechanic during the Mechanic by signing and Upper South Piping dating form.

penetration work.

END STOP TIME:

ANO-2-JPM-NRC-KI Page 5 of 6 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINERS COPY JPM INITIAL TASK CONDITIONS:

The plant is tripped from 100% power.

300 gpm LOCA in progress.

Loss of Offsite power is in progress.

LOCA EOP is being implemented.

RDACS indicates an off site release in progress.

Data indicates I-131 concentration of 5.0 E-04 ci/cc in area of work in Upper South Piping Penetration room.

Whole body dose rates in area of work are 1Rem/hr.

General Emergency has just been declared.

Joe Mechanic has completed 1903.035C form, ANO Medical Questionnaire-Iodine Sensitivity.

RP estimates that it will take approximately 15 minutes to complete emergency actions and stop the release and all RP required controls/authorizations are complete.

Air Purifying Respirator with Iodine Canister having a protection factor of 1.0 will be used in place of a SCBA due to piping interference.

EOF, OSC and TSC have NOT been staffed.

INITIATING CUE:

Determine if KI, Potassium Iodide should be issued and complete necessary paperwork, using OP 1903.035.

ANO-2-JPM-NRC-KI Page 6 of 6 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINEES COPY JPM INITIAL TASK CONDITIONS:

The plant is tripped from 100% power.

300 gpm LOCA in progress.

Loss of Offsite power is in progress.

LOCA EOP is being implemented.

RDACS indicates an off site release in progress.

Data indicates I-131 concentration of 5.0 E-04 ci/cc in area of work in Upper South Piping Penetration room.

Whole body dose rates in area of work are 1Rem/hr.

General Emergency has just been declared.

Joe Mechanic has completed 1903.035C form, ANO Medical Questionnaire-Iodine Sensitivity.

RP estimates that it will take approximately 15 minutes to complete emergency actions and stop the release and all RP required controls/authorizations are complete.

Air Purifying Respirator with Iodine Canister having a protection factor of 1.0 will be used in place of a SCBA due to piping interference.

EOF, OSC and TSC have NOT been staffed.

INITIATING CUE:

Determine if KI, Potassium Iodide should be issued and complete necessary paperwork, using OP 1903.035.

JOB PERFORMANCE MEASURE JPM-#-ANO-2-JPM-SRO- PAR3 PAGE 1 of 5 UNIT: 2 REV #: 003 DATE:

SYSTEM/DUTY AREA: Emergency Plan TASK: Issue Protective Action Recommendation to Offsite Authorities (Time Critical JPM)

JTA#: ANO-SRO-EPLAN-EMERG-301 KA VALUE RO: 2.4 SRO: 4.4 KA

REFERENCE:

2.4.44 APPROVED FOR ADMINISTRATION TO: RO: SRO: X TASK LOCATION: INSIDE CR: OUTSIDE CR: BOTH: X SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: SIMULATOR: Perform LAB:

POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: LAB:

TESTING METHOD: SIMULATE PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 5 Minutes - Read initial Conditions 15 Minutes - PAR Determination REFERENCE(S): OP-1903.011 EXAMINEE'S NAME: Badge #:

EVALUATOR'S NAME:

THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:

SATISFACTORY: UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Time Stop Time Total Time SIGNED: DATE:

SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.

JOB PERFORMANCE MEASURE JPM-#-ANO-2-JPM-SRO- PAR3 PAGE 2 of 5 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall review the "Briefing Checklist - System Walkthrough" portion of OP 1064.023 Attachment 6 with the examinee.

JPM INITIAL TASK CONDITIONS: (Time Critical JPM)

Unit 2 has experienced a LOCA.

A General Emergency has been declared and an Alert was previously declared.

Unit 2 had been at full power for 215 days.

Containment Building Pressure is 28 psia.

Containment Radiation Monitors 2RY-8925-1 and 2RY-8925-2 both read 1092 R/hr.

The reactor has been subcritical for 30 minutes.

Off site dose estimates are projected to be 1200 mRem TEDE and 6000 mRem Child Thyroid.

RDACS projects EPA Protective Action Guidelines will be exceeded in zones G and H.

Wind direction is from 190.

TASK STANDARD: (Time Critical 5 minutes for reading conditions 15 minutes for determining protective action recommendations)

A PAR 1 was declared.

A PAR 2 was declared.

Recommend evacuating Zones G H K M N O P R U.

Recommend zones I J L Q S T to go indoors and listen to the emergency broadcast for this event or remainder of the 10 mile EPZ to go indoors and listen to the Emergency Broadcasts for this event.

TASK PERFORMANCE AIDS: 1903.011; Attachment 6

JOB PERFORMANCE MEASURE JPM-#-ANO-2-JPM-SRO- PAR3 PAGE 3 of 5 INITIATING CUE:

The Shift Manager directs

1. Determine the appropriate PAR for the given conditions.

2. Determine the zones to be recommended for evacuation/sheltering to the State Health Department for the given conditions.

3. Determine the zones to be recommended to go indoors to the State Health Department for the given conditions.

START TIME:

PERFORMANCE CHECKLIST STANDARDS (Circle One)

(C) 1. Determine the correct PAR for the Using 1903.011 Attachments 6, N/A SAT UNSAT given conditions PAR 1 and 2 were determined.

(flowc hart)

(C) 2. Determine the zones that should Using 1903.011 Attachment 6 N/A SAT UNSAT be recommended for evacuation to Recommend evacuating Zones G, (PAR1 H, K, M, N, O, P, R, U.

the State Health Department.

Table)

(C) 3. Determine the zones that should Recommend zones I, J, L, Q, S, T N/A SAT UNSAT go indoors the State health go indoors to go indoors and listen (PAR1 Department. to the emergency broadcasts for this Table) event.

OR POSITIVE CUE: recommends remainder of the 10 None mile EPZ to go indoors and listen to the Emergency Broadcasts (C) 4. JPM complete in 15 minutes. JPM complete in 15 minutes with 5 N/A SAT UNSAT minutes to read conditions.

END STOP TIME:

JOB PERFORMANCE MEASURE JPM-#-ANO-2-JPM-SRO- PAR3 PAGE 4 of 5 Examiner's Copy This is a time critical JPM Initial Conditions:

Unit 2 has experienced a LOCA.

A General Emergency has been declared and an Alert was previously declared.

Unit 2 had been at full power for 215 days.

Containment Building Pressure is 28 psia.

Containment Radiation Monitors 2RY-8925-1 and 2RY-8925-2 both read 1092 R/hr.

The reactor has been subcritical for 30 minutes.

Off Site Dose estimates are projected to be 1200 mRem TEDE and 6000 mRem Child Thyroid.

RDACS projects EPA Protective Action Guidelines will be exceeded in zones G, and H.

Wind direction is from 190.

INITIATING CUE:

The Shift Manager directs:

1. Determine the appropriate PAR for the given conditions.

2. Determine the zones to be recommended for evacuation/sheltering to the State Health Department for the given conditions.

3. Determine the zones to be recommended to go indoors to the State Health Department for the given conditions.

Write Answer below:

A PAR 1 was declared.

1) PAR(s) declared A PAR 2 was declared.

Recommend evacuating Zones G H K M N O P R U.

2. Zones to be evacuated or sheltered (specify)

Recommend zones I J L Q S T to go indoors and listen to the

3) Zones to go indoors emergency broadcast for this event or remainder of the 10 mile EPZ to go indoors and listen to the Emergency Broadcasts for this event.

JOB PERFORMANCE MEASURE JPM-#-ANO-2-JPM-SRO- PAR3 PAGE 5 of 5 Examinee's Copy This is a time critical JPM Initial Conditions:

Unit 2 has experienced a LOCA.

A General Emergency has been declared and an Alert was previously declared.

Unit 2 had been at full power for 215 days.

Containment Building Pressure is 28 psia.

Containment Radiation Monitors 2RY-8925-1 and 2RY-8925-2 both read 1092 R/hr.

The reactor has been subcritical for 30 minutes.

Off site dose estimates are projected to be 1200 mRem TEDE and 6000 mRem Child Thyroid.

RDACS projects EPA Protective Action Guidelines will be exceeded in zones G, and H.

Wind direction is from 190.

INITIATING CUE:

The Shift Manager directs:

1. Determine the appropriate PAR for the given conditions.

2. Determine the zones to be recommended for evacuation/sheltering to the State Health Department for the given conditions.

3. Determine the zones to be recommended to go indoors to the State Health Department for the given conditions.

Write Answer below:

1. PAR(s) declared

2. Zones to be evacuated or sheltered (specify)

3. Zones to go indoors

ANO-2-JPM-NRC-EOP01 PAGE 1 OF 6 JOB PERFORMANCE MEASURE UNIT: 2 REV #: 09 DATE:

SYSTEM/DUTY AREA: Abnormal/Emergency Operations TASK: Secure Containment Spray JTA#: ANO2-RO-EOPAOP-EMERG-13 KA VALUE RO: 3.2 SRO: 3.7 KA

REFERENCE:

026 A2.03 APPROVED FOR ADMINISTRATION TO: RO: X SRO: X TASK LOCATION: INSIDE CR: X OUTSIDE CR: BOTH:

SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: SIMULATOR: Perform LAB:

POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: LAB:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 15 Minutes REFERENCE(S): OP 2203.012D 2K-04 ACA EXAMINEE'S NAME: Badge #:

EVALUATOR'S NAME:

THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:

SATISFACTORY: UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Stop Total Time Time Time SIGNED: DATE:

SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.

ANO-2-JPM-NRC-EOP01 PAGE 2 OF 6 JOB PERFORMANCE MEASURE THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall review the "Briefing Checklist - System Walkthrough" portion of OP 1064.023 Attachment 6 with the examinee.

JPM INITIAL TASK CONDITIONS: Containment spray actuation signal has actuated inadvertently and 2K04 D-1, CSAS ACT, is in Alarm. I&C has corrected the problem. No testing is currently in progress.

TASK STANDARD: CSAS is reset and CSAS actuated components are secured.

TASK PERFORMANCE AIDS: EOP 2203.012D Annunciator 2K04 D1, CSAS ACT SIMULATOR SETUP: Inadvertent containment spray actuated. Containment Temperature. < 140 ° F, Pressure < 22.5 psia.

ANO-2-JPM-NRC-EOP01 PAGE 3 OF 6 JOB PERFORMANCE MEASURE INITIATING CUE:

The CRS directs, "Reset CSAS and secure Containment Spray using ACA 2203.012D for annunciator 2D1, CSAS ACT.

START TIME:

PERFORMANCE CHECKLIST STANDARDS (Circle One)

1. Verify CSAS NOT valid. Determined that Containment N/A SAT UNSAT pressure less than 22.5 PSIA Step (PMS, SPDS or control board 2.1 indication).

EXAMINERS NOTE:

There is only one channel available on the simulator. Resetting B trip path will reset all the other channels also.

2. Place Spray Pumps in PTL. On panels 2C16/17, placed N/A SAT UNSAT handswitches for Containment Step Spray Pumps (2P35A and 2.3 2P35B) in Pull To Lock (PTL).

Examiners CUE: Observed green lights ON above handswitches.

CRS acknowledges TS entry into 3.0.3. Enter TS 3.0.3.

EXAMINERS NOTE:

There is only one channel available on the simulator. Resetting 2C23B actuation path will reset all the other channels also.

(C) 3. Reset CSAS on 2C23. On panel 2C23B, obtained key N/A SAT UNSAT and placed it in trip path to be Step reset.

Examiners Note:

Give examinee Key #15 when Placed trip path key switch to 2.6.1 asked. UNLK.

Depressed CSAS pushbutton for 2.6.2 trip path.

Verified Trip Path lights reset 2.6.3 (on 2C03) (Not a critical item) 2.6.4 Placed trip path key switch to LK.

ANO-2-JPM-NRC-EOP01 PAGE 4 OF 6 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

EXAMINERS NOTE:

There is only one channel available on the simulator. Resetting 2C40 actuation path will reset all the other channels also.

(C) 3. Reset CSAS on 2C40 On 2C40, depressed CSAS N/A SAT UNSAT lockout reset pushbutton.

Step On 2C40 verify reset lights are 2.6.6 ON.

2.6.7 (C) 4. Close Containment Spray On panels 2C16/17, placed N/A SAT UNSAT Header Isolation Valves. handswitches for Containment Step Spray Header Isolation valves 2.6.8 (2CV-5612-1 and 2CV-5613-2) in CLOSE.

Observed green lights ON above handswitches.

(C) 5. Remove CNTMT Spray On panels 2C16/17, removed N/A SAT UNSAT pumps from PTL: handswitches for Containment Step Spray Pumps (2P35A and 2.6.9 2P35B) from PTL and placed in normal after stop.

Observed green lights ON above handswitches.

6. Exit Tech Spec 3.0.3. Notify CRS to exit tech spec N/A SAT UNSAT 3.0.3 when both spray pumps Step are taken out of PTL.

2.6.10 EXAMINERs CUE: Exiting Tech Spec 3.0.3 has been entered into the station log.

END STOP TIME:

ANO-2-JPM-NRC-EOP01 PAGE 5 OF 6 JOB PERFORMANCE MEASURE EXAMINERS COPY JPM INITIAL TASK CONDITIONS:

Containment spray actuation signal has actuated inadvertently.

2K04 D-1, CSAS ACT, is in alarm.

I&C has corrected the problem.

No Testing is currently in progress.

INITIATING CUE:

The CRS directs, "Reset CSAS and secure Containment Spray using ACA 2203.012D for annunciator D1, CSAS ACT.

ANO-2-JPM-NRC-EOP01 PAGE 6 OF 6 JOB PERFORMANCE MEASURE EXAMINEES COPY JPM INITIAL TASK CONDITIONS:

Containment spray actuation signal has actuated inadvertently.

2K04 D-1, CSAS ACT, is in alarm.

I&C has corrected the problem.

No Testing is currently in progress.

INITIATING CUE:

The CRS directs, "Reset CSAS and secure Containment Spray using ACA 2203.012D for annunciator D1, CSAS ACT.

ANO-2-JPM-NRC-RCP04 PAGE 1 OF 5 JOB PERFORMANCE MEASURE UNIT: 2 REV #: 0 DATE:

SYSTEM/DUTY AREA: Reactor Coolant Pump TASK: Perform a normal RCP shutdown. (Alternate Path)

JTA#: ANO-2-RO-RCP-NORM-3 KA VALUE RO: 3.3 SRO: 3.1 KA

REFERENCE:

003 A2.02 APPROVED FOR ADMINISTRATION TO: RO: X SRO: X TASK LOCATION: INSIDE CR: X OUTSIDE CR: BOTH:

SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: SIMULATOR: Perform LAB:

POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: LAB:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 8 Minutes REFERENCE(S): OP 2103.006 Reactor Coolant Pump Operations EXAMINEE'S NAME: Badge #:

EVALUATOR'S NAME:

THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:

SATISFACTORY: UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Stop Total Time Time Time SIGNED: DATE:

SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.

ANO-2-JPM-NRC-RCP04 PAGE 2 OF 5 JOB PERFORMANCE MEASURE THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall review the "Briefing Checklist - System Walkthrough" portion of OP 1064.023 with the examinee.

JPM INITIAL TASK CONDITIONS:

The unit is in Mode 3.

TASK STANDARD:

All RCPs secured due to A RCP reverse rotation alarm.

TASK PERFORMANCE AIDS:

OP 2103.006 Section 8.0, OP-2203.012K for 2K11-C2 SIMULATOR SETUP:

Mode 3 all RCP running.

Insert Malfunction RCP2P32AREV the reverse rotation alarm will annunciate when the RCP is stopped.

ANO-2-JPM-NRC-RCP04 PAGE 3 OF 5 JOB PERFORMANCE MEASURE INITIATING CUE:

The CRS directs, "Shut down RCP "A" using OP 2103.006 Section 8.0."

Start Time:

PERFORMANCE CHECKLIST STANDARDS (Circle One)

(C) 1. Start RCP "A" bearing oil lift On panel 2C04, placed 2HS-6084 N/A SAT UNSAT pump (2P63A). for 2P63A to START.

(Step 8.1) Observed red light on; green light OFF above 2HS-6084.

(C) 2. Stop reactor coolant pump On panel 2C04, placed 2HS-4620 N/A SAT UNSAT (2P32A). for 2P32A to STOP.

(Step 8.2) Observed green light ON; red light OFF above 2HS-4620.

3 Acknowledges 2K11-C2 A RCP On panel 2K11 recognizes A RCP N/A SAT UNSAT reverse rotation alarm reverse rotation alarm (C) 4. IF RCP 2P-32A NOT operating, On panel 2C04, placed the N/A SAT UNSAT THEN trip all RCPs. handswitches for the following (Step RCPs in STOP:

2.2 of ACA) 2P-32B 2P-32C 2P-32D All RCPs must be stopped within 3 minutes of receiving reverse rotation alarm.

END Stop Time:

ANO-2-JPM-NRC-RCP04 PAGE 4 OF 5 JOB PERFORMANCE MEASURE EXAMINERS COPY JPM INITIAL TASK CONDITIONS:

The unit is in Mode 3 INITIATING CUE:

The SM/CRS directs, "Shut down RCP "A" using OP 2103.006 Section 8.0."

ANO-2-JPM-NRC-RCP04 PAGE 5 OF 5 JOB PERFORMANCE MEASURE EXAMINEES COPY JPM INITIAL TASK CONDITIONS:

The unit is in Mode 3 INITIATING CUE:

The SM/CRS directs, "Shut down RCP "A" using OP 2103.006 Section 8.0."

ANO-2-JPM-NRC-SIT01 PAGE 1 OF 7 JOB PERFORMANCE MEASURE UNIT: 2 REV #: 010 DATE:

SYSTEM/DUTY AREA: Safety Injection System TASK: Perform a high pressure fill of a SIT (SIT "A") (Alternate Success Path)

JTA#: ANO2-RO-ECCS-NORM-2 KA VALUE RO: 3.3 SRO: 3.7 KA

REFERENCE:

006 A2.03 APPROVED FOR ADMINISTRATION TO: RO: X SRO: X TASK LOCATION: INSIDE CR: X OUTSIDE CR: BOTH:

SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: SIMULATOR: Perform LAB:

POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: LAB:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 12 Minutes REFERENCE(S): OP-2104.001 Safety Injection Tank operations EXAMINEE'S NAME: Badge #:

EVALUATOR'S NAME:

THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:

SATISFACTORY: UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Stop Total Time Time Time SIGNED: DATE:

SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.

ANO-2-JPM-NRC-SIT01 PAGE 2 OF 7 JOB PERFORMANCE MEASURE THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall review the "Briefing Checklist - System Walkthrough" portion of OP 1064.023 with the examinee.

JPM INITIAL TASK CONDITIONS:

HPSI pump (2P89A) is running on minimum recirculation TASK STANDARD:

Safety Injection Tank (2T2A) level has been increased ~0.2% and fill is secured prior to 2T-2A pressure exceeding 624 psig (Hi Hi pressure) or level exceeding 89.5% (Hi Hi level)

TASK PERFORMANCE AIDS:

OP 2104.001 Section 8.0 SIMULATOR SETUP:

SIT A level low enough to accept a 0.2% water addition and Safety Injection Tank (2T2A) pressure is

<608 psig.

Setup overrides to deenergize the red and green lights for 2CV 5015-1 when the handswitch is is taken to the open position and have the valve open 1%.

HPSI pump (2P89A) is running on minimum recirculation. RCS PRESSURE > 1500psia.

Set trigger T4= of4r0151 (triggered when 2HS5015-1 red light is energized).

T4 - CV50151 = 0.1; fail HPSI injection MOV partially open.

T4 - DO_HS_5015_G = OFF; HPSI injection MOV green light off.

T4 - DO_HS_5015_R = OFF; HPSI injection MOV red light off.

ANO-2-JPM-NRC-SIT01 PAGE 3 OF 7 JOB PERFORMANCE MEASURE INITIATING CUE:

The CRS directs, "Raise Safety Injection Tank (2T2A) level 0.2% using OP 2104.001, beginning with step 8.3."

START TIME:

PERFORMANCE CHECKLIST STANDARDS (Circle One)

1. Monitor SIT level and While filling SIT A, monitored N/A SAT UNSAT pressure during fill. level to ensure level maintained Step 8.3 < 87.9%.

While filling SIT A, monitored SIT pressure closely to ensure pressure maintained < 624 psig.

(C) 2. Open SIT (2T2A) Drain On panel 2C17, placed N/A SAT UNSAT Valve (2SV-5001-1). handswitch for 2SV-5001-1 to Step OPEN.

8.4.1 Observed red light ON above handswitch.

(C) 3. Open SIT (2T2A) Check On panel 2C33, placed N/A SAT UNSAT Valve Bypass (2SV-5004). handswitch for 2SV-5004 to Step OPEN.

8.4.1 Observed red light ON above handswitch.

(C) 4. Throttle open HPSI Header 1 On panel 2C17, throttled N/A SAT UNSAT Injection to RCP A Discharge 2CV-5015-1 OPEN by placing Step (2CV-5015-1). handswitch to OPEN 8.4.2 momentarily as required to establish an SIT fill rate.

Observed red and green lights ON above handswitch.

Observed SIT (2T2A) control board level instrument(s):

2LIS-5008 (2C17) 2LI-5010 (2C17) 2LIS-5009 (2C16)

OR Observed SIT (2T2A) level on PMS, or SPDS computer point/trend display.

Examiners note:

The following step is the Alternate path portion of this JPM

ANO-2-JPM-NRC-SIT01 PAGE 4 OF 7 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

(C) 5. Attempts to close HPSI On panel 2C17, placed N/A SAT UNSAT Header 1 Injection to RCP A handswitch for 2CV-5015-1 to Step Discharge valve. CLOSE.

8.4.3.A Recognized that 2CV-5015-1 would NOT close and both red and green lights are deenergized.

(C) 6. Stop the level increase in On panel 2C17, placed N/A SAT UNSAT 2T2A SIT. handswitch for A HPSI pump (2P-89A) in stop Observed 2P89A stopped.

OR On panel 2C17 placed Step handswitch for SIT A Drain 8.4.3.B Valve (2SV-5001-1) to Step CLOSED.

8.4.3.C Observed green light ON above handswitch.

OR On panel 2C33, placed handswitch for SIT A Check Valve Bypass (2SV-5004) to CLOSED.

Observed green light ON above handswitch.

7. Inform CRS of failure of Informed CRS that 2CV-5015-1 N/A SAT UNSAT 2CV-5015-1 to close. failed to close.

Examiners Cue:

Acknowledge communication as CRS.

Direct Examinee to secure from filling A SIT.

8. Close SIT (2T2A) Drain On panel 2C17, placed N/A SAT UNSAT Valve. handswitch for SIT A Drain Step (if not closed previously.) Valve (2SV-5001-1) to CLOSE.

8.4.3.B Observed green light ON above handswitch.

ANO-2-JPM-NRC-SIT01 PAGE 5 OF 7 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

9. Close SIT (2T2A) Check On panel 2C33, placed N/A SAT UNSAT Valve Bypass. handswitch for SIT A Check Step (if not closed previously.) Valve Bypass (2SV-5004) to 8.4.3.C CLOSE.

Observed green light ON above handswitch.

(C) 10. On panel 2K07, Alarms C3, 2T2A SIT High High Pressure N/A SAT UNSAT SIT Press Hi Hi or C4 Level alarm NOT received (SIT Hi Hi NOT received. pressure > 624 psig) or High High level alarm NOT received (87.5%).

END STOP TIME:

ANO-2-JPM-NRC-SIT01 PAGE 6 OF 7 JOB PERFORMANCE MEASURE EXAMINERS COPY JPM INITIAL TASK CONDITIONS:

HPSI pump (2P89A) is running on minimum recirculation.

INITIATING CUE:

The CRS directs, "Raise Safety Injection Tank (2T2A) level 0.2% using OP 2104.001, beginning with step 8.3."

ANO-2-JPM-NRC-SIT01 PAGE 7 OF 7 JOB PERFORMANCE MEASURE EXAMINEES COPY JPM INITIAL TASK CONDITIONS:

HPSI pump (2P89A) is running on minimum recirculation.

INITIATING CUE:

The CRS directs, "Raise Safety Injection Tank (2T2A) level 0.2% using OP 2104.001, beginning with step 8.3."

ANO-2-JPM-NRC-PZR01 PAGE 1 OF 5 JOB PERFORMANCE MEASURE UNIT: 2 REV #: 001 DATE:

SYSTEM/DUTY AREA: Pressurizer Pressure control Operations TASK: Equalize RCS and Pressurizer Boron JTA#: ANO2-RO-PZR-NORM-3 KA VALUE RO: 3.7 SRO: 3.5 KA

REFERENCE:

010 A4.01 APPROVED FOR ADMINISTRATION TO: RO: X SRO: X TASK LOCATION: INSIDE CR: X OUTSIDE CR: BOTH:

SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: SIMULATOR: Perform LAB:

POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: LAB:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 10 Minutes REFERENCE(S): OP 2103.005 Pressurizer Operations EXAMINEE'S NAME: Badge EVALUATOR'S NAME:

THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:

SATISFACTORY: UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Time Stop Time Total Time SIGNED: DATE:

SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.

THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

ANO-2-JPM-NRC-PZR01 PAGE 2 OF 5 JOB PERFORMANCE MEASURE The examiner shall review the "Briefing Checklist - System Walkthrough" portion of OP 1064.023 with the examinee.

JPM INITIAL TASK CONDITIONS:

Chemistry reports that RCS Boron is 750 PPM and the PZR Boron is 805 PPM.

TASK STANDARD:

Establish boron equalization with backup heaters on and one PZR spray valve in manual with RCS pressure 2200 +/- 10 psia TASK PERFORMANCE AIDS:

OP 2103.005 section 7.1 SIMULATOR SETUP:

PZR pressure controller in automatic with setpoint at 2200 psia.

ANO-2-JPM-NRC-PZR01 PAGE 3 OF 5 JOB PERFORMANCE MEASURE INITIATING CUE:

The CRS directs, "Commence equalizing RCS and PZR boron concentration using OP 2103.005 section 7.1, A RCP spray valve, 2CV-4651."

Start Time:

PERFORMANCE CHECKLIST STANDARDS (Circle One)

1. Verify spray valve, 2CV-4651, On panel 2C04 verified red lights N/A SAT UNSAT isolation valves 2CV-4655 AND ON, green lights OFF for (Step 2CV-4656 are OPEN. 2CV-4655 and 2CV-4656.

7.1.1)

(C) 2. Place A RCP spray valve On panel 2C04, rotated 2HS-4651B N/A SAT UNSAT MAN/AUTO select switch in the CCW direction to (Step (2HS-4651B) to MANUAL. MANUAL.

7.1.2)

(C) 3. Energize all available Backup On panel 2C04 placed the N/A SAT UNSAT Heaters: following handswitches to ON:

(Step Place 2HS-4643 to ON Place 2HS-4643 to ON 7.1.3) Place 2HS-4644 to ON Place 2HS-4644 to ON Place 2HS-4645 to ON Place 2HS-4645 to ON Place 2HS-4646 to ON Place 2HS-4646 to ON AND Observed the red light ON and green light OFF above each of the above backup heater handswitches.

EXAMINERS NOTE:

The following action may take several attempts (cycling the spray valve open and then closed) until the proper valve position is obtained. When the handswitch is taken to the closed direction, 2CV-4651 will go completely closed.

Maintaining RCS pressure 2200 +/- 10 psia may also be accomplished by placing one backup heater to Auto.

The Critical portion of step 4 below is to maintain RCS pressure 2200 +/- 10 psia and this can be accomplished by either step 4 or 5.

This JPM should be stopped by examiner when determined satisfactory or unsatisfactory.

(C) 4. When PZR pressure begins On panel 2C 04, placed handswitch N/A SAT UNSAT increasing, Throttle open A for 2CV-4651 to the open position (Step RCP spray valve (2CV-4651) momentarily and then watched 7.1.4) enough to stabilize pressure 2200 PZR pressure stabilize at 2200 +/- 10

+/- 10 psia psia.

5. IF necessary to maintain pressure On panel 2C 04, placed handswitch N/A SAT UNSAT

+/- 10 psia of setpoint, for one backup heater to auto as (Step THEN place one Backup Heater necessary to maintain RCS pressure 7.1.5) bank in AUTO. 2200 +/- 10 psia.

END Stop Time:

ANO-2-JPM-NRC-PZR01 PAGE 4 OF 5 JOB PERFORMANCE MEASURE EXAMINERS COPY INITIAL CONDITIONS:

Chemistry reports that RCS Boron is 750 PPM and the PZR Boron is 805 PPM.

INITIATING CUE:

The CRS directs, "Commence equalizing RCS and PZR boron concentration using OP 2103.005 section 7.1, A RCP spray valve, 2CV-4651."

ANO-2-JPM-NRC-PZR01 PAGE 5 OF 5 JOB PERFORMANCE MEASURE EXAMINEES COPY INITIAL CONDITIONS:

Chemistry reports that RCS Boron is 750 PPM and the PZR Boron is 805 PPM.

INITIATING CUE:

The CRS directs, "Commence equalizing RCS and PZR boron concentration using OP 2103.005 section 7.1, A RCP spray valve, 2CV-4651."

ANO-2-JPM-NRC-VCTMU PAGE 1 OF 7 JOB PERFORMANCE MEASURE UNIT: 2 REV #: 010 DATE:

SYSTEM/DUTY AREA: Chemical and Volume Control System TASK: Perform Manual Makeup to the VCT JTA#: ANO2-RO-CHADD-NORM-111 KA VALUE RO: 3.6 SRO: 3.7 KA

REFERENCE:

004 A4.15 APPROVED FOR ADMINISTRATION TO: RO: X SRO: X TASK LOCATION: INSIDE CR: X OUTSIDE CR: BOTH:

SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: SIMULATOR: Perform LAB:

POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: LAB:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 20 Minutes REFERENCE(S): OP 2104.003 Chemical Addition EXAMINEE'S NAME: Badge #:

EVALUATOR'S NAME:

THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:

SATISFACTORY: UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Stop Total Time Time Time SIGNED: DATE:

SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.

ANO-2-JPM-NRC-VCTMU PAGE 2 OF 7 JOB PERFORMANCE MEASURE THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall review the "Briefing Checklist - System Walkthrough" portion of OP 1064.023 Attachment 6 with the examinee.

JPM INITIAL TASK CONDITIONS: Plant is operating at 100%.

OP 2104.003 Attachment L is completed through step 2.1. Boron 2 PMS program has been completed.

TASK STANDARD: Manual blended make-up to the VCT at the correct blend ratio has been established.

TASK PERFORMANCE AIDS: Copy of OP 2104.003 Attachment L and Plant Monitoring system print out of required boric acid and water SIMULATOR SETUP: VCT level at 60%. 2CVC-68 is throttled open(0.65) and 2CVC-83 is closed

ANO-2-JPM-NRC-VCTMU PAGE 3 OF 7 JOB PERFORMANCE MEASURE INITIATING CUE:

The SM/CRS directs, Raise VCT level to 75% using OP 2104.003 Attachment L beginning with step 2.2.

START TIME:

PERFORMANCE CHECKLIST STANDARDS (Circle One)

1. Verify 2CVC 68 is open and Contact WCO and direct N/A SAT UNSAT 2CVC83 is closed. OPENING of 2CVC68 and Step CLOSING of 2CVC83.

2.3 Examiner Cue:

WCO reports than 2CVC68 is OPEN and 2CVC83 is CLOSED.

Examiners note:

The Boric Acid and DI water flow rates should be set up to be approximately 1 to 5 ratio with 1 part Boric Acid and 5 parts DI water.

The actual blend ratio to maintain RCS boron concentration is 1 to 5.6 but the last 50 gallons of addition should be DI water to flush the makeup line and this will equate to a 1 to 5 ratio make up rate.

2. Set Boric Acid Makeup Flow On Panel 2C09, set Boric Acid N/A SAT UNSAT Controller (2FIC-4926) to Makeup Flow Controller Step desired flow rate. (2FIC-4926) to desired flow rate.

2.4 Flow rate adjusted to ~ 1 / 5 blend ratio.

3. Place 2FIC-4926 in either On Panel 2C09, placed N/A SAT UNSAT MANUAL or AUTOMATIC 2FIC-4926 to either MANUAL or Step mode. AUTOMATIC mode.

2.4

4. Set Reactor Makeup Water On Panel 2C09, set Reactor N/A SAT UNSAT Flow controller (2FIC-4927) to Makeup Water Flow Controller Step desired flow rate. (2FIC-4927) to desired flow rate.

2.5 Flow rate adjusted to ~ 1 / 5 blend ratio.

5. Place 2FIC-4927 in either On Panel 2C09, placed N/A SAT UNSAT MANUAL or AUTOMATIC 2FIC-4927 in either MANUAL or Step mode. AUTOMATIC mode.

2.5

ANO-2-JPM-NRC-VCTMU PAGE 4 OF 7 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

6. Reset Boric Acid Makeup Flow On Panel 2C09, on (2FQI-4926) N/A SAT UNSAT Totalizer (2FQI-4926) to zero. depressed the reset pushbutton.

Step (Function pushbutton F3) 2.6 Observed 2FQI-4926 indicating zero.

7. Reset Reactor Makeup Water On Panel 2C09, on (2FQI-4927) N/A SAT UNSAT Flow Totalizer (2FQI-4927) to depressed the reset pushbutton.

Step zero. (Function pushbutton F3) 2.6 Observed 2FQI-4927 indicating zero.

(C) 8. Open VCT Makeup Isol Valve. On Panel 2C09, placed N/A SAT UNSAT handswitch for VCT Makeup Isol Step Valve (2CV-4941-2) to OPEN.

2.7 Observed red light ON, green light OFF above handswitch for 2CV-4941-2.

9. Verify a Reactor Makeup On Panel 2C09, verified N/A SAT UNSAT Pump running. handswitch for one Reactor Makeup Pump (either 2P109A Step or 2P109B) in START.

2.8 Observed red light ON and green light OFF above handswitch for selected pump.

(C) 10. Start one BAM pump. On Panel 2C09, placed N/A SAT UNSAT handswitch for one BAM Pump Step (either 2P39A or 2P39B) to 2.9 START.

Observed red light ON and green light OFF above handswitch for selected pump

11. Open the associated BAM On Panel 2C09, opened the N/A SAT UNSAT pump recirc valve. BAM Pump recirc valve Step associated with the running BAM 2.10 pump (either 2CV-4903-2 or 2CV-4915-2).

Observed red light ON and green light OFF for valve opened.

ANO-2-JPM-NRC-VCTMU PAGE 5 OF 7 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

(C) 12. Place Boric Acid Makeup Mode On Panel 2C09, placed 2HS- N/A SAT UNSAT Selector switch (2HS-4928) to 4928 to MANUAL.

Step MANUAL.

2.11 (C) 13. Verify Boric Acid Makeup Flow On Panel 2C09, verified N/A SAT UNSAT Control Valve (2CV-4926) 2CV-4926 opens to control flow Step opens to maintain desired flow at ~ 1 / 5 of water flow rate.

2.12 rate.

Observed flow indicated on 2FIC-4926.

Critical step is the steady flow rate after adjustment of 1 to 4.6 to 5.4 of the water flow rate (C) 14. Verify Reactor Makeup Water On Panel 2C09, verified N/A SAT UNSAT Flow Control Valve (2CV-4927) 2CV-4927 opens to control flow Step opens to maintain desired flow at ~ 5 times acid flow rate.

2.13 rate.

Observed flow indicated on 2FIC-4927.

Critical portion is the steady water flow rate to 4.6 to 5.4 times the acid flow rate.

EXAMINERS NOTE: JPM may be terminated when above step is complete.

END

ANO-2-JPM-NRC-VCTMU PAGE 6 OF 7 JOB PERFORMANCE MEASURE EXAMINERS COPY JPM INITIAL TASK CONDITIONS:

Plant is operating at 100%.

OP 2104.003 Attachment L is completed through step 2.1. Boron2 program has been used to determine the correct amounts of Boric acid and water.

INITIATING CUE:

The SM/CRS directs, Raise VCT level to 75% using OP 2104.003 Attachment L beginning with step 2.2 using A Bamt.

ANO-2-JPM-NRC-VCTMU PAGE 7 OF 7 JOB PERFORMANCE MEASURE EXAMINEES COPY JPM INITIAL TASK CONDITIONS:

Plant is operating at 100%.

OP 2104.003 Attachment L is completed through step 2.1. Boron2 program has been used to determine the correct amounts of Boric acid and water.

INITIATING CUE:

The SM/CRS directs, Raise VCT level to 75% using OP 2104.003 Attachment L beginning with step 2.2 using A Bamt.

ANO-2-JPM-NRC-ELECXT PAGE 1 OF 7 JOB PERFORMANCE MEASURE UNIT: 2 REV #: 001 DATE:

SYSTEM/DUTY AREA: A. C. Electrical Distribution TASK: Perform Synchronized Cross Connect of 480 VAC load-centers 2B1 and 2B2 (Alternate Path)

JTA#: ANO2-RO-480VAC-NORM-15 KA VALUE RO: 3.3 SRO: 3.1 KA

REFERENCE:

062 A4.01 APPROVED FOR ADMINISTRATION TO: RO: X SRO: X TASK LOCATION: INSIDE CR: X OUTSIDE CR: BOTH:

SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: SIMULATOR: Perform LAB:

POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: LAB:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 12 Minutes REFERENCE(S): OP 2107.001 Electrical System Operation EXAMINEE'S NAME: Badge EVALUATOR'S NAME:

THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:

SATISFACTORY: UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Time Stop Time Total Time SIGNED: DATE:

SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.

ANO-2-JPM-NRC-ELECXT PAGE 2 OF 7 JOB PERFORMANCE MEASURE THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall review the "Briefing Checklist - System Walkthrough" portion of OP 1064.023 with the examinee.

JPM INITIAL TASK CONDITIONS:

Non-Vital 4160VAC busses energized. 2B1 and 2B2 are energized. Maintenance must be performed on 2B2 transformer.

TASK STANDARD:

Cross connect 480VAC non-vital busses 2B1 and 2B2 with 2B1 supplying and 2B2 supply breakers open. Maintain 2B1 amperage less than 130 amps.

TASK PERFORMANCE AIDS:

OP 2107.001 Section 12.0.

SIMULATOR SETUP:

Any power level or mode.

All Non-Vital 4160VAC and 480VAC Busses energized.

REMOTE malfunction 480CURR2B2 value = 15 REMOTE malfunctions 480CURR2B1 (value = 25) and 480CURR2B2 (value = 35) are set for trigger 2.

Conditional triggerT2 should be set for the handswitch to 2A-202 Normal after open (IC4G02CS)

ANO-2-JPM-NRC-ELECXT PAGE 3 OF 7 JOB PERFORMANCE MEASURE INITIATING CUE:

The SM/CRS directs, "Cross Connect 2B1 and 2B2 and separate 2B2 from 2A2 using OP 2107.001 section 12.0."

START TIME:

PERFORMANCE CHECKLIST STANDARDS (Circle One)

Examiners note:

If the initial plant conditions are in Mode 3, 4 or 5, then the first step is N/A.

1. Check that Operations Ask if Operations Manager has N/A SAT UNSAT (Step Manager approval obtained. given approval to cross connect 12.1) 2B1 and 2B2 at power.

EXAMINERS CUE:

The Operations Manager has given permission to perform Cross Connect of 2B1 and 2B2.

(C) 2. Determine combined load of On Panel 2C10, summed the N/A SAT UNSAT (Step 2B1 an 2B2 is less than 130 current reading of 2B1 and 2B2.

12.2) amps when cross connected.

Observed that the summed load is less than 130 amps.

Examiners Note Step 12.3 in procedure is not applicable for this JPM as both busses remained energized.

(C) 3. Synchroscope switch inserted On Panel 2C10, Placed N/A SAT UNSAT (Step in 2B1/2B2 cross-tie slot and Synchroscope switch into 12.4) placed in ON. 2B1/2B2 cross-tie slot and rotated clockwise to the ON position.

4. Observed that the On Panel 2C10, Observed that N/A SAT UNSAT (Step Synchroscope is at the 12 the Synchroscope is at the 12 12.5) oclock position. oclock position with the Synchroscope switch in the ON position.

ANO-2-JPM-NRC-ELECXT PAGE 4 OF 7 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

(C) 5. Close the 2B1/2B2 Cross Tie On panel 2C10, rotate the Cross N/A SAT UNSAT (Step breaker. Tie handswitch for 2B1/2B2 12.6) clockwise.

Observed that the Green light turns OFF and the Red light turns ON above the Cross Tie handswitch.

(C) 6. Open normal supply breaker On Panel 2C10, rotate the N/A SAT UNSAT (Step on 2B2, 480VAC bus. normal feeder supply breaker on 12.7.1) 2B2 counter clockwise to the open position. (2B212)

Observed that the RED light went OFF and the GREEN light went ON.

(C) 7. Open Transformer feeder On Panel 2C10, rotate the N/A SAT UNSAT breaker from 2A2 to 2B2. transformer feeder breaker on (Step 2A2 to 2B2 counter clockwise to 12.7.2) the open position. (2A202)

Observed that the RED light went OFF and the GREEN light went ON.

Examiners Note:

The following it the Alternate path portion of this JPM

ANO-2-JPM-NRC-ELECXT PAGE 5 OF 7 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

(C) 7. Verify that the amperage Observed that the summed load N/A SAT UNSAT (Step indicated on 2B1 is less than is greater than 130 amps.

12.8) 130 amps.

Direct the AO or inform CRS of EXAMINERS CUE: need to reduce non-essential loads on 2B1 and 2B2 so that AO has been directed to combined loading is less than secure non-essential loads 130 amps.

on 2B1 and 2B2 to reduce loading on 2B1 and 2B2 to less than 130 amps. OR EXAMINERS NOTE:

Un-crosstie 2B1 and 2B2 using Direct operator in simulator the appropriate section of instructors station to reduce 2107.001.

loading on 2B1 and 2B2 so that loading is less than 130 Either of the above must be amps (use REMOTE completed within 10 minutes malfunctions 480CURR2B1 of the crosstie of 2B-1 and 2B-and 480CURR2B2). 2.

8. Turn sync switch to OFF. On Panel 2C10, turn sync switch N/A SAT UNSAT (Step counter clockwise to the OFF 12.9) position.

Examiners Note:

Step 12.10 in procedure is not applicable for this JPM as both busses remained energized and the loads removed to reduce amperage on 2B1 will remain deenergized.

9. Notified AO to monitor 2B1 Notify AO to monitor 2B1 N/A SAT UNSAT (Step transformer during cross transformer during cross 12.11) connected operation and connected operation and maintain temperature less than maintain temperature less than 220°C. 220°C.

EXAMINERS CUE:

AO has been notified to monitor 2B1 transformer and notify the control room if temperature exceeds 220°C during cross connected operations.

END STOP TIME:

ANO-2-JPM-NRC-ELECXT PAGE 6 OF 7 JOB PERFORMANCE MEASURE EXAMINERS COPY JPM INITIAL TASK CONDITIONS:

Non-Vital 4160VAC busses energized. 2B1 and 2B2 are energized. Maintenance must be performed on 2B2 transformer.

INITIATING CUE:

The SM/CRS directs, "Cross Connect 2B1 and 2B2 and separate 2B2 from 2A2 using OP 2107.001 section 12.0."

ANO-2-JPM-NRC-ELECXT PAGE 7 OF 7 JOB PERFORMANCE MEASURE EXAMINEES COPY JPM INITIAL TASK CONDITIONS:

Non-Vital 4160VAC busses energized. 2B1 and 2B2 are energized. Maintenance must be performed on 2B2 transformer.

INITIATING CUE:

The SM/CRS directs, "Cross Connect 2B1 and 2B2 and separate 2B2 from 2A2 using OP 2107.001 section 12.0."

ANO-2-JPM-NRC-CPC02 PAGE 1 OF 6 JOB PERFORMANCE MEASURE UNIT: 2 REV #: 3 DATE:

SYSTEM/DUTY AREA: Core Protection Calculators/COLSS TASK: Determine DNBR/LPD limits with COLSS out of service JTA#: ANO2-RO-EOPAOP-OFFNORM-234 KA VALUE RO: 3.9 SRO: 3.9 KA

REFERENCE:

015 A3.03 APPROVED FOR ADMINISTRATION TO: RO: X SRO: X TASK LOCATION: INSIDE CR: X OUTSIDE CR: BOTH:

SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: SIMULATOR: Perform LAB:

POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: LAB:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 10 Minutes REFERENCE(S): OP-2203.043 Loss of COLSS EXAMINEE'S NAME: Badge EVALUATOR'S NAME:

THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:

SATISFACTORY: UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Time Stop Time Total Time SIGNED: DATE:

SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.

ANO-2-JPM-NRC-CPC02 PAGE 2 OF 6 JOB PERFORMANCE MEASURE THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall review the "Briefing Checklist - System Walkthrough" portion of OP 1064.023 with the examinee.

JPM INITIAL TASK CONDITIONS:

The plant is at 100%. COLSS has been declared inoperable due to MUX C and D failures.

TASK STANDARD:

DNBR/LPD limits have been calculated to within limits established.

TASK PERFORMANCE AIDS:

OP-2203.043 ATT A SIMULATOR SETUP:

Fail the COLSS program. Insert malfunction XSPCOLSSMXD (D MUX failure) and XSPCOLSSMXC (C MUX failure)

ANO-2-JPM-NRC-CPC02 PAGE 3 OF 6 JOB PERFORMANCE MEASURE INITIATING CUE: The CRS directs you to determine DNBR/LPD within limits by completing AOP 2203.043, Loss of COLSS, ATT A.

START TIME:

PERFORMANCE CHECKLIST STANDARDS (Circle One)

NOTES:

Steps may be performed in various orders. Examinee will

1. obtain data

2. derive average

3. derive limit To obtain readings on CPC B and C the CPC/CEAC selector button must be selected to CPC (backlit)

1. Obtain operable CPC channel At operable CPC modules on N/A SAT UNSAT values (PID 406) 2C03 obtained CPC channel (Step values (PID 406) by 1 A.)

MAIN MENU <ENTER>

CHANNEL CHECK (3) <ENTER>

EXAMINER NOTE:

OR Approximate 100% value for DNBR MAIN MENU <ENTER>

A-1.761 STANDARD O.M. (1) <ENTER>

B-1.730 POINT ID (P) <ENTER>

C-1.708 4 <ENTER D-1.737 0 <ENTER>

6 <ENTER>

AND Entered the 406 values for operable channels A-D on pg 1 step 1.A. of ATT A (C) 2. Determine DNBR Average On ATT A step 1.A. determined N/A SAT UNSAT DNBR Average by adding the (Step operable channel DNBR readings 1 A) previously obtained and dividing by # operable channels.

DNBR average calculated to be 1.7 to 1.8 (C) 3. Determine DNBR Limit On ATT A step 1.B. determined N/A SAT UNSAT DNBR limit by subtracting 0.12 (Step from average obtained in step 1 B) 1.A.

DNBR limit calculated to be 1.55 to 1.65

ANO-2-JPM-NRC-CPC02 PAGE 4 OF 6 JOB PERFORMANCE MEASURE PERFORMANCE CHECKLIST STANDARDS (Circle One)

4. Obtain operable CPC channel At operable CPC modules on N/A SAT UNSAT values (PID 179) 2C03 obtained CPC channel (Step values (PID 179) by 2 A)

MAIN MENU <ENTER>

EXAMINER NOTE:

CHANNEL CHECK (3) <ENTER>

Approximate 100% value for LPD OR A-14.69 MAIN MENU <ENTER>

B-14.41 STANDARD O.M. (1) <ENTER>

C-14.37 POINT ID (P) <ENTER>

D-14.26 1 <ENTER 7 <ENTER>

9 <ENTER>

AND Entered the 179 values for operable channels A-D on page 1 step 2.A. of ATT A (C) 5. Determine LPD average On ATT A step 2.A, determined N/A SAT UNSAT LPD Average by adding the (Step operable channel LPD readings 2 A) previously obtained and dividing by # operable channels.

LPD average calculated to be 14.3 to 14.6 (C) 6. Determine LPD limit On ATT A step 2.B. determined N/A SAT UNSAT LPD limit by adding 0.16 to (Step average obtained in step 2.A.

2 B)

LPD limit calculated to be 0.1 to 0.2 greater than the average.

END STOP TIME:

ANO-2-JPM-NRC-CPC02 PAGE 5 OF 6 JOB PERFORMANCE MEASURE EXAMINERS COPY JPM INITIAL TASK CONDITIONS:

The plant is at 100%. COLSS has been declared inoperable due to MUX C and D failures.

INITIATING CUE:

The CRS directs you to determine DNBR/LPD within limits by completing AOP 2203.043, Loss of COLSS, ATT A.

ANO-2-JPM-NRC-CPC02 PAGE 6 OF 6 JOB PERFORMANCE MEASURE EXAMINEES COPY JPM INITIAL TASK CONDITIONS:

The plant is at 100%. COLSS has been declared inoperable due to MUX C and D failures.

INITIATING CUE:

The CRS directs you to determine DNBR/LPD within limits by completing AOP 2203.043, Loss of COLSS, ATT A.

ANO-2-JPM-NRC-CCW02 PAGE 1 OF 5 JOB PERFORMANCE MEASURE UNIT: 2 REV #: 011 DATE:

SYSTEM/DUTY AREA: Component Cooling Water System TASK: Shift Running CCW pumps JTA#: ANO-2-RO-CCW-NORM-10 KA VALUE RO: 3.3 SRO: 3.1 KA

REFERENCE:

008 A4.01 APPROVED FOR ADMINISTRATION TO: RO: X SRO:

TASK LOCATION: INSIDE CR: X OUTSIDE CR: BOTH:

SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: SIMULATOR: Perform LAB:

POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: LAB:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 10 Minutes REFERENCE(S): OP-2104.028 Component Cooling Water System Operations EXAMINEE'S NAME: Badge #:

EVALUATOR'S NAME:

THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:

SATISFACTORY: UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Stop Total Time Time Time SIGNED: DATE:

SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.

ANO-2-JPM-NRC-CCW02 PAGE 2 OF 5 JOB PERFORMANCE MEASURE THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall review the "Briefing Checklist - System Walkthrough" portion of OP 1064.023 with the examinee.

JPM INITIAL TASK CONDITIONS:

2P-33B running in a normal configuration. Component Cooling water loops are cross tied.

Maintenance requests that 2P-33A be started and ran in single pump operation for PMT after pump rebuild.

TASK STANDARD:

2P33A running supplying CCW and 2P33B & 2P-33C in PULL-TO-LOCK.

TASK PERFORMANCE AIDS:

OP 2104.028 Section 18.2.5 SIMULATOR SETUP:

Any power level or mode.

2P-33B CCW pump in service with CCW loops cross tied.

ANO-2-JPM-NRC-CCW02 PAGE 3 OF 5 JOB PERFORMANCE MEASURE INITIATING CUE:

The CRS directs, "Start 2P-33A and secure 2P-33B for PMT run following maintenance using OP 2104.028 Step 18.2.5."

START TIME:

PERFORMANCE CHECKLIST STANDARDS (Circle One)

1. Contact AO to vent 2P-33A. Using telephone or radio, N/A SAT UNSAT contacted AO and directed him (Step Examiner CUE: to vent 2P-33A Casing, using 18.2.5 A 2CCW-1001.

& B) AO reports casing vented and 2CCW-1001 closed.

(C) 2. Verify 2P-33C handswitch On panel 2C14, placed 2P-33C N/A SAT UNSAT (2HS-5234) in PTL. handswitch in Pull-To-Lock.

(Step 18.2.5 C)

(C) 3. Start 2P-33A. On panel 2C14, took 2P-33A N/A SAT UNSAT handswitch to START and (Step 18.2.5 D) released handswitch.

Observed red light ON above handswitch.

(C) 4. Place 2P-33B handswitch On panel 2C14, placed 2P-33B N/A SAT UNSAT (2HS-5228) to PTL. handswitch in Pull-To-Lock.

(Step 18.2.5 E)

Observed 2K-12 PUMP 2P-33A/B/C LOCKED alarm.

5. Observe normal flow and On panel 2C14, observed CCW N/A SAT UNSAT discharge pressure. flow between 2000 to 3000 gpm.

(Step 18.2.5 F)

Directed operator to observe Examiner CUE: discharge pressure between 100 to 120 psig locally.

Operator reports discharge pressure 110 psig locally.

END STOP TIME:

ANO-2-JPM-NRC-CCW02 PAGE 4 OF 5 JOB PERFORMANCE MEASURE EXAMINERs COPY JPM INITIAL TASK CONDITIONS:

2P-33B running in a normal configuration.

Maintenance requests that 2P-33A be started and ran in single pump operation for PMT after pump rebuild.

INITIATING CUE:

The CRS directs, "Start 2P-33A and secure 2P-33B for PMT run following maintenance using OP 2104.028 Step 18.2.5."

ANO-2-JPM-NRC-CCW02 PAGE 5 OF 5 JOB PERFORMANCE MEASURE EXAMINEEs COPY JPM INITIAL TASK CONDITIONS:

2P-33B running in a normal configuration.

Maintenance requests that 2P-33A be started and ran in single pump operation for PMT after pump rebuild.

INITIATING CUE:

The CRS directs, "Start 2P-33A and secure 2P-33B for PMT run following maintenance using OP 2104.028 Step 18.2.5."

JOB PERFORMANCE MEASURE JPM# ANO-2-JPM-NRC-AACLS REV 08 PAGE 1 of 7 SYSTEM/DUTY AREA: Diesel Generator System (Alternate Success Path)

TASK: Start up the AAC diesel generator manually locally during a Loss of Offsite Power JTA # : ANO2-AO-AACDG-OFFNORM-18 KA VALUE RO: 4.0 SRO: 4.3 KA

REFERENCE:

064 A4.01 APPROVED FOR ADMINISTRATION TO: RO: X SRO: X TASK LOCATION: INSIDE CR: OUTSIDE CR: X BOTH:

SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: Simulate SIMULATOR: LAB:

POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT LAB:

SITE:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 20 minutes REFERENCE(S) OP 2104.037, Exhibit 1 EXAMINEES NAME: Badge #:

EVALUATORS NAME: DATE THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:

SATISFACTORY: UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Time: Stop Total Time:

Time:

Signature indicates this JPM has been compared to its applicable procedure by a qualified individual (not the examinee) and is current with that revision.

SIGNED: DATE:

JOB PERFORMANCE MEASURE JPM# ANO-2-JPM-NRC-AACLS REV 08 PAGE 2 of 7 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall review the "Briefing Checklist - System Walkthrough" portion of OP 1064.023 with the examinee.

This is an alternate success path JPM.

JPM INITIAL TASK CONDITIONS:

The following conditions exist:

The reactor has tripped due to a loss of off-site power.

Both emergency diesel generators are tied to their respective buses.

An attempt to start the AACDG from the Control Room to energize 4160v Non-vital bus 2A1 was unsuccessful.

TASK STANDARD:

The AAC Diesel has been started and is at 4160 V and 900 rpm with the output breaker (2A-1001) closed.

The 480V bus 2B16 has been powered from the AAC diesel generator.

TASK PERFORMANCE AIDS:

OP 2104.037 Exhibit 1

JOB PERFORMANCE MEASURE JPM# ANO-2-JPM-NRC-AACLS REV 08 PAGE 3 of 7 INITIATING CUE:

The CRS provides the following direction:

Start the AAC Diesel Generator using OP 2104.037 Exhibit 1 and bring the unit up to rated speed and voltage carrying house loads.

START TIME:

EXAMINERS NOTE:

Provide examinee with copy of 2104.037, Exhibit 1 If asked about the conditions of the alarms, tell the examinee that the only alarm in is H-3, GENERATOR CIRCUIT BREAKER OPEN.

If asked if 125 VDC is available, tell them that the indications for bus availability are as seen (assumes no actual maintenance in progress)

PERFORMANCE CHECKLIST STANDARDS (Circle One)

(C) 1. Place Local/Remote switch in On panel 2C-440, placed the N/A SAT UNSAT LOCAL. Local/Remote switch in (Step LOCAL.

1.1)

POSITIVE CUE:

Local/Remote switch indicates LOCAL.

2. Start the AAC Diesel using the On panel 2C-440 turned the N/A SAT UNSAT local start switch. local control switch CW to start.

(Step 1.2)

EXAMINERS NOTE:

Provide the following cue after ~ 35 seconds when the local start switch is taken to START.

EXAMINERS CUE:

There has been NO change in AAC diesel generator frequency or noise level.

Examiners NOTE:

Go to the AAC diesel engine room.

3. Open the pre-lube pump On the south side of the engine N/A SAT UNSAT solenoid (2SV-7224) for >10 at the generator end, rotated the (Step seconds. manual operator of 2SV-7224 2.1)

CW to open for >10 seconds.

EXAMINERS CUE:

Air noise is heard.

JOB PERFORMANCE MEASURE JPM# ANO-2-JPM-NRC-AACLS REV 08 PAGE 4 of 7 (C) 4. Open EITHER of the air start On the south side of the engine N/A SAT UNSAT solenoid valves: at the generator end, rotated the (Step manual operator of one of the air 2.2) - 2SV-7222 OR start solenoid valves CW to

- 2SV-7223 open.

EXAMINERS CUE: Looked for an increase in engine noise and/or discharge of oil and Engine speed and noise air from the air start motors.

level increases.

5. Close the air start solenoid On the south side of the engine N/A SAT UNSAT valve that was opened. at the generator end, rotated the (Step manual operator for the air start 2.3) solenoid valve CCW to close.

6. Close the pre-lube solenoid After > 10 seconds on the south N/A SAT UNSAT (2SV-7224). side of the engine at the (Step generator end, rotated the 2.3) manual operator of 2SV-7224 CCW to close.

7. Verify the AAC Diesel On panel 2C-440, observed N/A SAT UNSAT Generator is at rated speed generator frequency at 60 Hz (Step and voltage. and voltage at 4160V.

3)

EXAMINERS CUE:

Frequency indicates 60 Hz and voltage indicates 4160V.

JOB PERFORMANCE MEASURE JPM# ANO-2-JPM-NRC-AACLS REV 08 PAGE 5 of 7 EXAMINERS NOTE:

When the examinee inspects the condition of 2A-1001, provide the NEGATIVE CUE first to indicate that the breaker has NOT automatically closed. Once the action has been taken to close the breaker, provide the POSITIVE CUE.

(C) 8. Verify the AAC Generator Observed breaker position N/A SAT UNSAT Output Breaker (2A-1001) is indication on the door of 2A-(Step CLOSED 1001.

4.1)

EXAMINERS CUE: Rotated breaker local control switch for 2A-1001 to the The green breaker OPEN CLOSE position.

light is lit.

AND The white breaker spring charging light is lit.

EXAMINERS CUE:

The Red breaker CLOSED light is lit.

TRANSITION NOTE:

Go to the upstairs area of the switchgear room.

9. Verify the London Feed to Observed the mechanical N/A SAT UNSAT MCC 2B161 breaker 2B16-A1 position indicator breaker for (Step is OPEN. 2B16-A1 to show green open 4.2) and the green breaker position indication light is lit.

EXAMINERS CUE:

Green OPEN light is lit on 2B16-A1 and mechanical position indicator showing green open

10. Verify Load Center 2B16 Observed the mechanical N/A SAT UNSAT Supply from the AAC diesel position indicator breaker for (Step (2B16-B1) is CLOSED. 2B16-B1 to show red closed and 4.3) the red breaker position indication light is lit.

EXAMINERS CUE:

Red CLOSED light is lit on 2B16-B1 and mechanical position indicator showing red closed.

END STOP TIME:

JOB PERFORMANCE MEASURE JPM# ANO-2-JPM-NRC-AACLS REV 08 PAGE 6 of 7 Examiners Copy JPM INITIAL TASK CONDITIONS The following conditions exist:

The reactor has tripped due to a loss of off-site power.

Both emergency diesel generators are tied to their respective buses.

An attempt to start the AACDG from the Control Room to energize 4160v Non-vital bus 2A1 was unsuccessful.

INITIATING CUE:

The CRS provides the following direction:

Start the AAC Diesel Generator using OP 2104.037 Exhibit 1.

Bring the unit up to rated speed and voltage carrying house loads.

JOB PERFORMANCE MEASURE JPM# ANO-2-JPM-NRC-AACLS REV 08 PAGE 7 of 7 Examinees Copy JPM INITIAL TASK CONDITIONS The following conditions exist:

The reactor has tripped due to a loss of off-site power.

Both emergency diesel generators are tied to their respective buses.

An attempt to start the AACDG from the Control Room to energize 4160v Non-vital bus 2A1 was unsuccessful.

INITIATING CUE:

The CRS provides the following direction:

Start the AAC Diesel Generator using OP 2104.037 Exhibit 1.

Bring the unit up to rated speed and voltage carrying house loads.

JOB PERFORMANCE MEASURE JPM# ANO-2-JPM-NRC-XFCEA REV 10 PAGE 1 of 7 SYSTEM/DUTY AREA: Control Element Drive Mechanism Control System TASK: Transfer a CEA to the hold bus JTA # : ANO2-RO-CEDM-OFFNORM-12 KA VALUE RO: 3.7 SRO: 3.9 KA

REFERENCE:

001 A2.14 APPROVED FOR ADMINISTRATION TO: RO: X SRO: X TASK LOCATION: INSIDE CR: OUTSIDE CR: X BOTH:

SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: Simulate SIMULATOR: LAB:

POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT X LAB:

SITE:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 20 minutes REFERENCE(S) OP 2105.009, Exhibit 1 EXAMINEES NAME: Badge #:

EVALUATORS NAME: DATE THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:

SATISFACTORY: UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Time: Stop Total Time:

Time:

Signature indicates this JPM has been compared to its applicable procedure by a qualified individual (not the examinee) and is current with that revision.

SIGNED: DATE:

JOB PERFORMANCE MEASURE JPM# ANO-2-JPM-NRC-XFCEA REV 10 PAGE 2 of 7 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall review the "Briefing Checklist - System Walkthrough" portion of OP 1064.023 with the examinee.

PM INITIAL TASK CONDITIONS:

The following conditions exist:

1. The Plant is at 100% power.

2. 2K10-H1 CEDMCS COIL VOLTAGE HI is in alarm

3. 2K20-H3 CEDMCS TIMER FAILURE is locked in alarm TASK STANDARD:

CEA 47 held by Upper Gripper on the HOLD bus with CEDM power switch CKT BKR FOR CEA 47 OPENED TASK PERFORMANCE AIDS:

4. PowerPoint XFCEA Pictures.ppt located in In Plant JPM folder

5. OP 2105.009 Exhibit 1

6. Stop watch for timing subgroup transfer within 30 seconds.

JOB PERFORMANCE MEASURE JPM# ANO-2-JPM-NRC-XFCEA REV 10 PAGE 3 of 7 INITIATING CUE: The CRS provides the following direction:

1. Place the affected CEA subgroup on the hold bus using 2105.009, Exhibit 1 START TIME:

PERFORMANCE CHECKLIST STANDARDS (Circle One)

EXAMINERS NOTE:

Alarm lights may be either "RED" or "GREEN". POSITIVE CUES must be supplied to provide expected plant indications.

(C) 1. Check Timer Failure Alarm On CEDMCS Cabinet (2C72) Bay N/A SAT UNSAT (TFA) lamps. A and Bay B supervisory panels, (Step checked TFA lamps.

1)

EXAMINERS CUE:

Observed red light ON for CEA Red light "ON" for CEA #47

1. 47.

OR OR On CEDMCS Cabinets 2C71 and Check Card Status Monitor lights 2C72, checked CEA Card Status to determine affected Monitor lights.

subgroup/CEA.

Observed card status monitor light EXAMINERS CUE: for CEA #47 subgroup flashing Card status monitor light flashing for CEA #47 subgroup.

2. Locate the affected Subgroup On 2C71 identified the correct N/A SAT UNSAT Number and Subgroup subgroup number for CEA 47.

(Step Maintenance Switch 2.1)

On 2C72 located maintenance EXAMINERS CUE: switch #12 for that subgroup.

Maintenance switch #12 on 2C72 for CEA 047 is pointing down.

EXAMINERS NOTE:

Do not allow examinee to open the cabinet door to 2C-71. Once they have located the correct door, show them the picture of the voltage readings which indicate ~60 VDC.

3. Check positive and negative Hold AT back of panel 2C-71, observed N/A SAT UNSAT Bus voltages >50 VDC. Hold Bus Voltages (positive &

(Step negative) > 50 VDC on bus voltage 2.2) meters.

POSITIVE CUE:

Voltage meters indicate ~60 VDC

JOB PERFORMANCE MEASURE JPM# ANO-2-JPM-NRC-XFCEA REV 10 PAGE 4 of 7 Examiner Note:

When the CEA is transferred to the Upper Gripper start the timer for the 30 second critical time to complete the transfer to the Hold Bus.

Examiner Note:

Do not allow examinee to open the Card Status Monitor door. When the examinee has located the correct door, show them the picture of the ACTM cards.

4. Open the Card Status Monitor Opened door N/A SAT UNSAT door (Step 2.3) EXAMINERS CUE:

Observed the lower gripper light LG ENGD and ABNM VOLT and ABN VOLT light illuminated.

lights illuminated (C) 5. Operate the MAN TRANSFER Pushed up on the MANUAL N/A SAT UNSAT toggle switch on the ACTM card TRANSFER toggle switch (Step for CEA 47 to transfer it to the 2.4)

Upper Gripper.

Observed the Lower Gripper light extinguishes and the Upper Gripper EXAMINERS CUE: light illuminates & ABN VOLT light remains illuminated.

UG ENGD light illuminates and Lower Gripper light extinguishes when the MAN TRANS switch on the ACTM card is operated (C) 6. Operate Subgroup Maint Switch On front of 2C72 Bay B N/A SAT UNSAT to place CEA #47 on hold bus. Supervisory Panel, located and (Step raised subgroup maintenance 2.5) switch #12 to the ON position EXAMINERS CUE: within 30 seconds of completing Subgroup maintenance switch the previous step.

1. 12 is pointing up.

Within 30 seconds after operation of the MANUAL TRANSFER switch, operated subgroup maintenance switch.

EXAMINERS NOTE:

Do not allow examinee to open the cabinet door to 2C-71. Once they have located the correct door, show them the picture of the voltage readings which indicate ~45 VDC.

6. Check positive and negative Hold AT back of panel 2C-71, observed N/A SAT UNSAT Bus voltages. Hold Bus Voltages (positive &

(Step 2.6) negative) decreased 10 VDC from initial reading on bus voltage EXAMINERS CUE: meters.

Voltage meters indicate 44 VDC

JOB PERFORMANCE MEASURE JPM# ANO-2-JPM-NRC-XFCEA REV 10 PAGE 5 of 7 (C) 7. Open the disconnect switch for At front of panel 2C71 located and N/A SAT UNSAT CEA #47. pulled downward on CEA #47 (Step "Power Switch" disconnect.

2.7)

EXAMINERS CUE:

Observed green light ON, red light Green light ON, red light OFF.

OFF.

END STOP TIME:

JOB PERFORMANCE MEASURE JPM# ANO-2-JPM-NRC-XFCEA REV 10 PAGE 6 of 7 EXAMINERS COPY JPM INITIAL TASK CONDITIONS:

The plant is at 100%.

2K10-H1 CEDMCS COIL VOLTAGE HI is in alarm 2K20-H3 CEDMCS TIMER FAILURE is locked in alarm INITIATING CUE:

The CRS directs you to place the affected CEA subgroup on the hold bus using 2105.009, Exhibit 1

JOB PERFORMANCE MEASURE JPM# ANO-2-JPM-NRC-XFCEA REV 10 PAGE 7 of 7 EXAMINEES COPY JPM INITIAL TASK CONDITIONS:

The plant is at 100%.

2K10-H1 CEDMCS COIL VOLTAGE HI is in alarm 2K20-H3 CEDMCS TIMER FAILURE is locked in alarm INITIATING CUE:

The CRS directs you to place the affected CEA subgroup on the hold bus using 2105.009, Exhibit 1

40 60 20 40 60 20 D-C VOLTS 80 0

D-C VOLTS 80 0

NEGATIVE VOLTAGE 1 POSITIVE VOLTAGE 1 OUTPUT OUTPUT

F407 F408 F409 A B C 20 40 60 20 40 60 0 D-C VOLTS 80 0 D-C VOLTS 80 POSITIVE VOLTAGE 1 NEGATIVE VOLTAGE 1 OUTPUT OUTPUT POSITIVE OUTPUT NEGATIVE OUTPUT ADJUST CAUTION ADJUST HIGH VOLTAGE

JOB PERFORMANCE MEASURE ANO-2-JPM-NRC-69REL REV. 0 PAGE 1 of 7 UNIT: 2 REV #: 0 DATE:

SYSTEM/DUTY AREA: Liquid Radwaste and Boron Management System TASK: Perform a release of 2T-69A Boric Acid Condensate Tank JTA#: ANO2-WCO-LRWBMS-NORM-2 KA VALUE RO: 3.3 SRO: 3.1 KA

REFERENCE:

068 A4.02 APPROVED FOR ADMINISTRATION TO: RO: X SRO: X TASK LOCATION: INSIDE CR: OUTSIDE CR: X BOTH:

SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: Simulate SIMULATOR: LAB:

POSITION EVALUATED: RO: SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: LAB:

TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 20 Minutes REFERENCE(S): OP-2104.014 LRW and BMS Operations Sup. 3 EXAMINEE'S NAME: Badge#

EVALUATOR'S NAME:

THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:

SATISFACTORY: UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Stop Total Time Time Time SIGNED: DATE:

SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.

JOB PERFORMANCE MEASURE ANO-2-JPM-NRC-69REL REV. 0 PAGE 2 of 7 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall review the "Briefing Checklist - System Walkthrough" portion of OP 1064.023 Attachment 6 with the examinee.

JPM INITIAL TASK CONDITIONS:

1. 2T-69A Boric Acid Condensate Tank level is 90%.

2. 2104.014 Sup. 1 Liquid Radwaste Release permit for 2T-69A has been submitted and completed.

3. 2P-47A Boric Acid Condensate pump is running.

4. 2RE-2330 radiation monitor is OPERABLE.

5. Maximum flow rate from Pre-Release report based on number of Circ pumps running is 250 gpm.

6. 2CV-2330A and 2CV-2330B were both tested in Supplement 1 of 2104.014.

TASK STANDARD:

A 2T-69A Boric Acid Condensate Tank release has been commenced using OP-2104.014 Sup. 3.

TASK PERFORMANCE AIDS:

OP-2104.014 Sup. 3

JOB PERFORMANCE MEASURE ANO-2-JPM-NRC-69REL REV. 0 PAGE 3 of 7 INITIATING CUE:

The SM/CRS directs, Commence a 2T-69A Boric Acid Condensate Tank release using OP-2104.014 Sup. 3.

START TIME: _____________

PERFORMANCE CHECKLIST STANDARDS (Circle One)

TRANSITION NOTE:

Proceed to the 335 elevation of the Aux Bldg by the WCO desk.

1. Check 2CV-2312 closed and Observed red CLOSED magnetic tag N/A SAT UNSAT magnetic tag installed. installed on 2HS-2312.

(Step 3.1)

EXAMINERS CUE: AND EITHER:

Red light off, green light on. At 2C-112 panel, observed red light off, green light on.

Red CLOSED magnetic tag is installed on 2HS-2312. OR Valve stem is fully down. Locally, observed valve stem fully down.

2. Check 2CV-2318 closed and Observed red CLOSED magnetic tag N/A SAT UNSAT magnetic tag installed. installed on 2HS-2318.

(Step 3.1) AND EITHER:

EXAMINERS CUE: At 2C-112 panel, observed red light off, green light on.

Red light off, green light on.

OR Red CLOSED magnetic tag is installed on 2HS-2318. Locally, observed valve stem fully down.

Valve stem is fully down.

EXAMINERS NOTE:

Step 3.2 is not applicable due to using 2P-47A and Step 4 is not applicable due to releasing 2T-69A (C) 3. Verify 2P-47A pump is running. Either: N/A SAT UNSAT (Step At 2C-112 panel, observed red light on,

5) green light off.

EXAMINERS CUE:

OR Red light on, green light off.

At 2C-112 panel, observed pressure on OR 2PI-2317.

2PI-2317 indicates 65 psig.

4. Remove magnetic tag from 2CV- Removed red CLOSED magnetic tag N/A SAT UNSAT 2318. from 2HS-2318.

(Step 6.1)

EXAMINERS CUE:

Red CLOSED magnetic tag is removed from 2HS-2318.

JOB PERFORMANCE MEASURE ANO-2-JPM-NRC-69REL REV. 0 PAGE 4 of 7 PERFORMANCE CHECKLIST STANDARDS (Circle One)

(C) 5. Open 2P-47A discharge valve 2CV- At 2C-112 panel, placed 2HS-2318 to N/A SAT UNSAT 2318. OPEN.

(Step 6.2)

EXAMINERS CUE:

Red light on, green light off.

6. Place magnetic tag near 2CV-2318. Placed red OPEN-DUMP magnetic tag N/A SAT UNSAT near 2HS-2318.

(Step 6.3)

EXAMINERS CUE:

Red OPEN-DUMP magnetic tag is near 2HS-2318.

(C) 7. Verify tank release valves open. At 2C-112 panel, verified 2HS-2330 in N/A SAT UNSAT position 1 or 3 and Red light is (Step illuminated for 2CV-2330A and 2CV-7.1)

EXAMINERS CUE: 2330B.

2HS-2330 is position 1 or 3. Red light on, green light off for 2CV-2330A and 2CV-2330B.

8. Check no release flow exists. Contacted the Control room by radio or N/A SAT UNSAT phone to verify no flow exists on 2FR/RR-(Step 2331.

8)

EXAMINERS CUE:

Control room states, 2FR/RR-2331 recorder indicates 0 gpm.

TRANSITION NOTE:

Proceed to the 326 elevation area by the Squeeze valve.

(C) 9. Open 2BM-35. Opened valve by turning handwheel CCW N/A SAT UNSAT until resistance felt.

(Step 9)

EXAMINERS CUE:

Valve stem is fully extended.

(C) 10. Throttle 2BM-80A to one turn open. Closed valve by turning handwheel CW N/A SAT UNSAT until resistance felt.

(Step

10) Reopened valve ~ 1 turn.

EXAMINERS CUE:

Valve is one turn open.

Flow noise is heard.

JOB PERFORMANCE MEASURE ANO-2-JPM-NRC-69REL REV. 0 PAGE 5 of 7 PERFORMANCE CHECKLIST STANDARDS (Circle One)

11. Verify flow less than or equal to 75 Contacted Control room by radio or phone N/A SAT UNSAT gpm. to verify flow less than or equal to 75 (Step gpm.

10)

EXAMINERS CUE:

Flow is 60 gpm.

END STOP TIME: ______________

JOB PERFORMANCE MEASURE ANO-2-JPM-NRC-69REL REV. 0 PAGE 6 of 7 EXAMINERS COPY JPM INITIAL TASK CONDITIONS:

2T-69A Boric Acid Condensate Tank level is 90%.

2104.014 Sup. 1 Liquid Radwaste Release permit for 2T-69A has been submitted and completed.

2P-47A Boric Acid Condensate pump is running.

2RE-2330 radiation monitor is OPERABLE.

Maximum flow rate from Pre-Release report based on number of Circ pumps running is 250 gpm.

2CV-2330A and 2CV-2330B were both tested in Supplement 1 of 2104.014.

INITIATING CUE:

The SM/CRS directs, Commence a 2T-69A Boric Acid Condensate Tank release using OP-2104.014 Sup. 3.

JOB PERFORMANCE MEASURE ANO-2-JPM-NRC-69REL REV. 0 PAGE 7 of 7 EXAMINEES COPY JPM INITIAL TASK CONDITIONS:

2T-69A Boric Acid Condensate Tank level is 90%.

2104.014 Sup. 1 Liquid Radwaste Release permit for 2T-69A has been submitted and completed.

2P-47A Boric Acid Condensate pump is running.

2RE-2330 radiation monitor is OPERABLE.

Maximum flow rate from Pre-Release report based on number of Circ pumps running is 250 gpm.

2CV-2330A and 2CV-2330B were both tested in Supplement 1 of 2104.014.

INITIATING CUE:

The SM/CRS directs, Commence a 2T-69A Boric Acid Condensate Tank release using OP-2104.014 Sup. 3.

Appendix D Scenario 1 Form ES-D-1 Facility: ANO-2 Scenario No.: 1 (New) Op-Test No.: 2009-1 Examiners: Operators:

Initial Conditions:

100% MOL, All Engineered Safety Features systems are in standby. Gland Seal pressure control valve 2PCV-0231 is jacked closed. Green Train Maintenance Week. The B Charging pump seal water pump is in hand and has been running for 30 min.

Turnover:

100%. 260 EFPD. EOOS indicates Minimal Risk. 2PCV-0231 jacked closed, manually control seal steam pressure. Green Train Maintenance Week. C Charging pump will be removed from service for repack. Place B Charging pump in service and secure C Charging pump. Steps 8.1.1 and 8.1.2 are complete.

Event Malf. No. Event Event No. Type* Description 1 N (ATC) Place B Charging pump in service and secure C N (BOP) Charging pump.

N (SRO) 2 XSG2PT10411 I (BOP) A Steam generator safety channel pressure transmitter I (SRO) fails low. Tech Spec for SRO.

3 XCVLDNHXOU I (ATC) Letdown Temperature control valve input fails low.

I (SRO) 4 CVC2P36BFAL C (ATC) B Charging pump supply breaker trips due to a motor C (SRO) fault.

5 RCSLOCATCB N (BOP) Shutdown required due to15 gpm Reactor Coolant R (ATC) system leak on B cold leg. Tech Spec for SRO.

N (SRO) 6 MRGTRPLOCKO M (ALL) Main Turbine Generator trip causing a reactor trip and a FAILSU3 Startup #3 transformer lockout causing natural circulation of the RCS.

7 CV15042 C (BOP) #2 Emergency Diesel Generator service water outlet C (SRO) valve fails to open. This will result in de-energizing green train vital 4160VAC(2A-4) and vital 480VAC (2B-6).

8 RCSLOCATCB M (ALL) Reactor Coolant system B cold leg leakage ramps up to 225 gpm over 10 minutes.

9 HPISI10A C (BOP) 2P-89A Safety injection pump shaft shear.

C(SRO)

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Total malfunctions. = 8, Malfunctions after EOP entry = 2, Abnormal events = 4, Major transient = 2, EOPs with substantive actions =1, EOP Contingencies = 0, Critical tasks = 2.

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Appendix D Scenario 1 Form ES-D-1 Scenario #1 Objectives

1) Evaluate individual ability to operate safety related equipment.

2) Evaluate individual response to a failure of a Steam Generator Safety Channel Pressure detector.

3) Evaluate individual response to a failure of a Letdown temperature controller.

4) Evaluate individual response to a failure of a Coolant Charging pump.

5) Evaluate individual response to a small Reactor Coolant system leak.

6) Evaluate individual ability to perform a reduction in plant power.

7) Evaluate individual ability to respond to Degraded Electrical power.

8) Evaluate individual ability to mitigate a LOCA.

9) Evaluate individual response to a failure of cooling water to an Emergency Diesel Generator.

10) Evaluate individual ability to monitor operation of Emergency Core Cooling Equipment.

SCENARIO #1 NARRATIVE Simulator session begins with the plant at 100% power steady state Gland seal regulator, 2PCV-0231 is jacked closed.

When the crew has completed their control room walk down and brief, the ATC and BOP will shift lead charging pumps. The candidate will start the B Charging pump and secure C Charging pump using OP 2104.002 section 8.1.

After the B Charging pump is placed in service and C Charging pump is secured or cued by lead examiner, the A Steam Generator pressure safety channel pressure instrument, 2PT-1041-1, will fail low. This will trip one of the four PPS trip channels for low SG pressure trip and MSIS. Alarms for MSIS pre-trip, RPS channel trip/pre-trip, and channel A operator insert (2C03) trip and pre-trip lights will be lit. The SRO will refer to the ACA 2203.012D and tech specs 3.3.1.1, 3.3.2.1, 3.3.3.5 and 3.3.3.6 for guidance. The BOP will place Channel A PPS in bypass for point 11, SG pressure low, point 19, A SG delta-P for EFAS 1, and point 20, B SG delta-P for EFAS 2 for maintenance and trouble shooting. The crew will have one hour to place these points in bypass before exceeding the tech spec LCO.

After the A PPS channel is placed in bypass and cued by lead examiner, the Letdown heat exchanger temperature input will fail low. The ATC will report that LETDOWN HX 2E29 OUTLET TEMP HI alarm is in and the letdown heat exchanger temperature is reading low on the hand indicating controller but the computer point and control board indication are reading higher than normal. The SRO will direct the ATC to take manual control of the Letdown heat exchanger temperature control valve and manually control temperature. The SRO will also refer to the ACA for letdown radiation monitor flow low 2K12 J1 RADMONITOR FLOW LO and restore letdown radiation monitor flow.

After the ATC has taken manual control of the letdown temperature control valve, the B Coolant Charging Pump (CCP) will trip. The SRO will enter AOP 2203.036, Loss of Charging. The SRO will direct the ATC to manually start a standby CCP. The SRO should refer to the TRM and determine no LCOs are applicable.

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Appendix D Scenario 1 Form ES-D-1 SCENARIO #1 NARRATIVE (continued)

When a backup Charging pump has been started or at the lead examiners cue, a 15 gpm RCS leak will start. The SRO will enter the excess RCS leakage AOP, OP 2203.016. ATC and BOP will perform RCS Leak rate determinations. The SRO will enter Tech Spec 3.4.6.2. The SRO will direct to ATC to maintain pressurizer level within 5% of set point by starting additional charging pumps as needed. The SRO will also direct the ATC to isolate letdown to determine the leak location.

After the crew has determined the leak is not in letdown, they will restore letdown and the crew will perform a plant shutdown.

After the ATC has completed the required reactivity manipulation or cued by lead examiner, a Main Turbine Trip will occur and the crew will verify the reactor has tripped. When the reactor trips Start up transformer #3 will lock out. The RCPs and Circulating Water pumps lose power which will cause natural circulation conditions in the RCS and require steaming to atmosphere. During SPTAs, the BOP will report that #2 EDG service water outlet valve is not open requiring the #2 EDG to be secured locally.

The Crew will implement Standard Post Trip Actions (SPTA), OP 2202.001. After the reactor trips the RCS leakrate will ramp to 225 gpm over 10 minutes.

The SRO will diagnose a loss of coolant accident and enter EOP 2202.003, Loss of Coolant Accident (LOCA).

The ATC will cool down the RCS using the atmospheric dump valves. The BOP will override and open the Service Water to Component Cooling Water and Auxiliary Cooling Water valves. The ATC will control RCS pressure to recover pressurizer level. The BOP will take manual control of Emergency Feedwater flow and restore steam generator levels to normal.

Post SIAS, the A High Pressure Safety Injection (HPSI) pump will shear the shaft (red train) and the B high pressure safety injection pump (green train) will not be available due to loss of power.

The BOP will start the C HPSI pump to satisfy the required HSPI flow requirements.

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Appendix D Scenario 1 Form ES-D-1 Simulator Instructions for Scenario 1 Reset simulator to MOL 100% power IC steady state.

Ensure that AACG is secured and annunciators clear.

Place MINIMAL RISK and Green Train Maintenance Week signs on 2C11.

Ensure C HPSI pump in standby aligned to Red train Ensure C CCP is the lead charging pump and aligned to Green train.

Ensure 2PCV0231, Gland sealing steam pressure control valve failed closed.

Ensure T1, T2, T3, T4, & T5 set to false.

T6 = Reactor Trip Event Malf. No. Value/ Event No. Ramp Description Time 1 Place B Charging pump in service and secure C Charging pump.

2 XSG2PT10411 0 A Steam generator safety channel pressure transmitter Trigger = T1 fails low.

3 XCVLDNHXOU 80 Letdown Temperature control valve input fails low.

Trigger = T2 4 CVC2P36BFAL TRUE B Charging pump supply breaker trips due to a motor Trigger = T3 fault.

5 RCSLOCATCB 15.0 gpm Reactor Coolant system leak on B cold leg.

Trigger = T4 6 MRGTRPLOCKO TRUE Main Turbine Generator trip causing a reactor trip and a Trigger = T5 Startup #3 transformer lockout causing natural circulation of the RCS.

FAILSU3 TRUE Trigger = T6 7 CV15042 0 #2 Emergency Diesel Generator service water outlet valve Trigger = T5 fails to open.

8 RCSLOCATCB 225 Reactor Coolant system leak on B cold leg (225 gpm CUED RAMP= ramped over 10 Minutes).

10 MIN 9 HPISI10A 0 2P-89A Safety injection pump shaft shear.

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Appendix D Scenario 1 Form ES-D-1 Simulator Operator CUEs At T=0 BOP will place B Charging pump in service and secure C Charging pump.

CUE: When B charging pump is started, report as WCO that B Charging pump post start checks are satisfactory.

CUE: When C charging pump is secured, report as WCO that C Charging pump post stop checks are satisfactory.

Cued by Trigger T1 A Steam generator safety channel pressure transmitter fails low.

lead examiner CUE: When contacted as the WWM, then report that I & C planner will begin planning work on failed pressure instrument.

Cued by Trigger T2 Letdown Temperature control valve input fails low.

lead examiner CUE: If crew has taken manual control of 2TIC-4815, then WCO reports that CCW flow on 2FIS-5261 is indicating normal which is less than 200 gpm but not on the low peg. If the crew has not taken manual control of 2TIC-4815, then report there is no flow indicated on 2FIS-5261.

CUE: If crew has restored rad monitor flow, then report flow is 1 gpm other wise report 0 gpm.

CUE: When contacted as the WWM, then report that I & C planner will begin planning work on failed temperature controller.

Cued by Trigger T3 B Charging pump supply breaker trips due to a motor fault.

lead examiner Cue: When contacted as the WCO, then report that the breaker for B Coolant Charging Pump is in a tripped free condition.

Cue: If asked, then report that the motor for B Coolant Charging Pump is hot to touch and the paint is discolored, but no fire or smoke is evident.

Cue: If requested to vent B Charging pump, then report that a solid stream of water was observed when venting the suction to B Charging Pump from 2CVC-1099/1100.

Cue: If requested, then report that seal water pump is running for requested charging pump.

Cued by Trigger T4 15 gpm Reactor Coolant system leak on B cold leg.

lead examiner Cue: If requested, then report that seal water pump is running for requested charging pump.

Cued by Trigger T5 and Main Turbine trip and Startup #3 transformer lockout.

lead reactor trip examiner Revision 1 Page 5 of 27

Appendix D Scenario 1 Form ES-D-1 CUE: If requested, then report #2EDG is locked out locally.

CUE: If contacted, then act as Chemistry and respond as requested.

CUE: If contacted as WCO, then open the #2EDG SW outlet valve and report that 2CV-1504-2 is open.

CUE: If contacted as AO, then place #2 EDG back to AUTO and report action taken.

Reactor Trip Reactor Coolant system B cold leg leakage ramps up to 225 gpm over 10 minutes.

2P-89A Safety injection pump shaft shear.

CUE: if requested as WCO, then report that A HPSI pump shaft is sheared.

CUE: if requested as WCO, then report that C HPSI pump post start checks are satisfactory.

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Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2009-1 Scenario No.: 1 Event No.: 1 Event

Description:

ATC places B Charging pump in service and secure C Charging pump.

Time Position Applicant's Actions or Behavior T=0 SRO Direct the ATC to place B Charging pump in service and secure C Charging pump.

Refer to TRM 3.1.2.4 and determine entry is not required.

ATC Review OP 2104.0028 section 8.1.

ANY 8.1.3 IF shifting from 2P-36B to 2P-36C, OR shifting from 2P-36C to 2P-36B, THEN perform the following:

A. Refer to TRM 3.1.2.4.

ATC B. Place 2P-36A handswitch (2HS-4832-1) to STOP.

ATC 8.1.4 Place selected CCP handswitch in START.

CUE: When B charging pump is started, report as WCO that B Charging pump post start checks are satisfactory.

ANY 8.1.5 Check Charging Flow goes up 43 to 45 gpm (2FIS-4863).

ATC 8.1.6 Place CCP Select switch (2HS-4868) to position corresponding to selected lead pump:

2P-36A (PMP B&C) 2P-36B (PMP C&A) 2P-36C (PMP A&B)

ANY 8.1.7 Check Charging flow lowers 43 to 45 gpm (2FIS-4863).

CUE: When C charging pump is secured, report as WCO that C Charging pump post stop checks are satisfactory.

ATC 8.1.8 IF 2P-36A previously placed in STOP, THEN place 2P-36A handswitch (2HS-4832-1) in AUTO.

ATC 8.1.9 Place selected pump handswitch to AUTO.

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Appendix D Scenario 1 Form ES-D-2 ANY 8.1.10 Perform the following for off-going pump configuration:

A. Verify previous lead pump stops.

BOP B. Stop off-going pump Room cooler:

2P-36A (2VUC-7A) 2P-36B (2VUC-7B) 2P-36C (2VUC-7C)

BOP C. Close off-going pump Room cooler Service Water Inlet valve:

2P-36A (2CV-1500-1) 2P-36B (2CV-1502-2) 2P-36C (2CV-1501-5)

BOP D. Verify on-coming pump Room cooler in Normal-After-Start.

BOP E. Verify on-coming pump Room cooler Service Water Inlet valve open:

2P-36A (2CV-1500-1) 2P-36B (2CV-1502-2) 2P-36C (2CV-1501-5)

ANY Direct the WCO to perform the following:

8.1.11 WHEN CCP secured > 10 minutes, THEN perform ONE of the following:

Place associated Seal Water Pump handswitch in AUTO.

Verify associated Seal Water Pump handswitch in HAND.

- Verify handswitch status entered on Shift Relief Sheet.

Termination criteria: When B charging pump is placed in service and C charging pump is secured or at lead examiners discretion.

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Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2009-1 Scenario No.: 1 Event No.: 2 Event

Description:

A Steam Generator pressure transmitter, 2PT1041-1, on Channel A fails low.

Time Position Applicant's Actions or Behavior Cued by ANY Announce annunciators:

Lead Examiner 2K04-A4 CH A RPS/ESF/PRETRIP/TRIP 2K04-B3 PPS Channel TRIP 2K04-E4 MSIS PRETRIP ANY Report A SG low pressure pretrip/trip on PPS insert.

BOP Compare all four channels and report 2PI-1041-1 indicates zero.

SRO Implement Annunciator Corrective Action 2203.012D.

2K04-A4 CH A RPS/ESF/PRETRIP/TRIP applicable actions:

2.1 Refer to PPS insert on 2C03 to determine cause.

2.2 Compare all Channels to validate alarm.

2.6 IF channel failed, THEN refer to Tech Specs 3.3.1.1, 3.3.2.1, 3.3.3.5, 3.3.3.6, and TRM 3.3.1.1.

2K04-B3 PPS Channel TRIP applicable actions:

2.1 Determine which RPS or ESFAS trips have occurred on PPS inserts.

2.3 IF channel failed, THEN refer to Tech Specs 3.3.1.1 and 3.3.2.1 and TRM 3.3.1.1.

2K04-E4 MSIS PRETRIP applicable actions:

2.3 IF channel failed, THEN place in bypass using 2105.001, CPC/CEAC Operations.

2.4 Refer to Tech Spec 3.3.2.1.

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Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2009-1 Scenario No.: 1 Event No.: 2 Event

Description:

A Steam Generator pressure transmitter, 2PT1041-1, on Channel A fails low.

Time Position Applicant's Actions or Behavior SRO Enter Tech Spec 3.3.1.1, 3.3.2.1, 3.3.3.5, and 3.3.3.6.

Direct BOP to bypass bistable points for the associated functional units:

A SG PRESS low (Bistable 11)

A SG P - EFAS 1 (Bistable 19)

A SG P - EFAS 2 (Bistable 20)

SRO must enter Tech Specs 3.3.1.1, 3.3.2.1, 3.3.3.5, and 3.3.3.6.

BOP Bypass the points 11, 19, and 20 on Channel A:

11.1 Refer to Tech Spec 3.3.1.1, 3.3.2.1, 3.3.3.5, 3.3.3.6 and TRM 3.3.1.1.

11.2 Circle channel and functional units (points) to be bypassed below:

Channel to be bypassed: A B C D Points to be bypassed:

1 2 3 4 5 6 7 8 9 10 11 12 13 16 17 18 19 20 11.3 Enter appropriate Tech Spec/TRM actions.

11.4 Verify points to be bypassed NOT bypassed in ANY other channel.

11.5 Place desired points in BYPASS for selected channel on 2C23.

ANY Verify annunciator 2K04-C3 PPS CHANNEL BYPASSED Verify correct channels in bypass.

SRO Contact work management.

Cue: When contacted as the WWM, then report that I & C planner will begin planning work on failed pressure instrument.

Termination Criteria: Affected channel points placed in bypass or at lead examiner's discretion.

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Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2009-1 Scenario No.: 1 Event No.: 3 Event

Description:

Letdown Temperature control valve input fails low.

Time Position Applicant's Actions or Behavior ATC Announce alarm LETDOWN HX 2E29 OUTLET TEMP HI and report temperature.

SRO Implement Annunciator Corrective Action 2203.012L.

ANY 2.1 Check temperature on 2TIC-4815 and Computer Point (T4805).

Examiners note: Temperature is reading accurately on the control board indication and the computer point.

ATC 2.2 Verify letdown flow (2FIS-4801) within 10 gpm of charging flow (2FIS-4863).

ANY Direct WCO to locally perform the following:

2.3 Locally verify CCW flow through Letdown Heat Exchanger (2FIS-5261).

CUE: If crew has taken manual control of 2TIC-4815 then WCO reports that CCW flow on 2FIS-5261 is indicating normal which is less than 200 gpm but not on the low peg. If the crew has not taken manual control of 2TIC-4815 then report there is no flow indicated on 2FIS-5261.

ANY 2.4 IF Loop 2 CCW temperature high, THEN reduce temperature using Component Cooling Water System Operation (2104.028).

Examiners Note: Loop 2 CCW temperature is not expected to be high.

ATC 2.5 IF Letdown HX Temperature Controller (2TIC-4815) NOT controlling in AUTOMATIC, THEN perform the following:

2.5.1 Place 2TIC-4815 in MANUAL.

2.5.2 Raise CCW flow.

SRO Establish a control band for letdown heat exchanger outlet.

ANY Report 2K12 J1 RADMONITOR FLOW LO SRO Direct actions of 2K12 J1 RADMONITOR FLOW LO:

ANY Direct WCO to perform the following:

2.2 Locally check flow on 2FIS-4807.

CUE: If crew has restore rad monitor flow report flow is 1 gpm other wise report 0 gpm.

ANY 2.3 Verify letdown flow (2FIS-4801) > 28 gpm.

ANY 2.4 Verify L/D to Rad Monitor (2CV-4804) open.

Termination Criteria: When the letdown temperature controller has been placed in manual and temperature is in the directed band or at discretion of lead examiner.

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Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2009-1 Scenario No.: 1 Event No.: 4 Event

Description:

B Charging pump supply breaker trips due to a motor fault.

Time Position Applicant's Actions or Behavior Cued by ATC Announce 2K12-B3 Charging low flow alarm.

Lead Examiner Announce that B CCP has tripped and both red and green lights are out.

SRO Enter and direct the actions of AOP, OP-2203.036, Loss of charging.

ATC 1. Check Charging flow path as follows:

Suction source aligned to VCT, RWT, or BAMT.

Charging Header Isolation valve (2CV-4840-2) open.

ATC 2. IF lead Charging pump stopped AND green indicating light OFF, THEN start backup Charging pump.

ATC 3. Check for adequate Charging pump operation as follows:

Charging header flow 40 to 45 gpm.

Charging Pump Discharge header pressure greater than RCS pressure.

Charging Pump Discharge pressure and flow stable.

ANY 4. Check for indications of Charging header rupture:

VCT level drop.

Aux Building or CNTMT radiation level rise.

Waste Tanks 2T20A/B level rise.

CNTMT Sump level rise.

Aux Building sump level rise.

Examiner Note: There will be no indications of a Charging Header rupture and the SRO should proceed to step 9.

SRO Direct Waste Control Operator to vent the suction of B CCP.

9. Locally check affected Charging pump for gas binding using Attachment B, Charging Pump Venting.

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Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2009-1 Scenario No.: 1 Event No.: 4 Event

Description:

B Charging pump supply breaker trips due to a motor fault.

Time Position Applicant's Actions or Behavior Cue: If requested to vent B Charging pump, then report that a solid stream of water was observed when venting the suction to B Charging Pump from 2CVC-1099/1100.

Cue: If asked report that the motor for B Coolant Charging Pump is hot to touch and the paint is discolored, but no fire or smoke is evident.

Cue: When contacted as the WCO, then report that the breaker for B Coolant Charging Pump is in a tripped free condition.

SRO 10. IF Charging pumps were NOT gas bound, THEN GO TO Step 17.

(B charging pump will not be gas bound)

ATC Examiner Note: All of the following steps may be satisfied and only need to be checked by the ATC with exception of the following:

Recording charging header data and Restoring Letdown (which may need to be restored if it isolated on high temperature).

17. Restore Charging and Letdown as follows:

A. Verify Charging Pump Header Isolation valve (2CV-4840-2) open.

B. Verify VCT Outlet valve (2CV-4873-1) open.

C. Verify RWT to Charging Pump Suction valve (2CV-4950-2) closed.

D. Verify at least ONE Charging pump running, refer to 2104.002, Chemical and Volume Control.

1) Record charging header data using 2202.010, Standard Attachment 44, Charging Header Data.

E. Check for adequate Charging pump operation as follows:

Charging header flow 40 to 45 gpm.

Charging Pump Discharge header pressure greater than RCS pressure.

Charging Pump Discharge pressure and flow stable.

F. Restore Letdown, refer to 2104.002, Chemical and Volume Control.

Cue: If requested report that seal water pump is running for requested charging pump.

SRO G. Exit this procedure. (SRO will exit the loss of Charging Revision 1 Page 13 of 27

Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2009-1 Scenario No.: 1 Event No.: 4 Event

Description:

B Charging pump supply breaker trips due to a motor fault.

Time Position Applicant's Actions or Behavior procedure.)

SRO Refer to ACA 2K12 C2 Pumps not available from independent busses and/or ACA 2K04 A2 SIAS inop.

2.1 Refer to TRMs 3.1.2.3 and 3.1.2.4.

SRO Refer to TRM 3.1.2.4 and determine entry is not required IAW the TRM bases.

The SRO may direct the ATC to place C CCP on the GREEN side IAW 2104.002 CHEMICAL AND VOLUME CONTROL.

Termination Criteria: When backup CCP started or at discretion of lead examiner.

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Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2009-1 Scenario No.: 1 Event No.: 5 Event

Description:

15 gpm Reactor Coolant system leak on B cold leg.

Time Position Applicant's Actions or Behavior Cued by ANY Report the following indications:

Lead Examiner Containment dew point rising Pressurizer Level lowing.

Letdown flow lowering.

SRO Perform the following actions:

Assess Critical parameters Determine RCS leak is present and enter Excess RCS Leakage AOP.

SRO Enter and direct the actions of AOP, OP-2203.016 Excess RCS Leakage:

1. Open Placekeeping page.

ANY *2. Check PZR level controlled within 5% of setpoint.

(The SRO may direct the ATC to start Backup Charging pumps as necessary to maintain PZR level within 5% of setpoint)

Cue: If requested report that seal water pump is running for requested charging pump.

ANY *3. Check PZR level maintained within 10% of setpoint.

ATC *4. Maintain VCT level 60 to 75%, refer to 2104.003, Chemical Addition.

ANY *5. Determine RCS leakrate by ANY of the following:

Computer LKRT programs.

Check PZR level stable and use Charging and Letdown mismatch minus Controlled Bleed Off.

Check Letdown isolated and estimate RCS leak rate by total Charging flow minus Controlled Bleed Off.

CNTMT Sump level rate of rise.

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Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2009-1 Scenario No.: 1 Event No.: 5 Event

Description:

15 gpm Reactor Coolant system leak on B cold leg.

Time Position Applicant's Actions or Behavior ANY 6. IF RCS leakage greater than 44 gpm AND in Mode 1 OR 2, THEN perform the following:

A. Trip Reactor.

B. GO TO 2202.001, Standard Post Trip Actions.

SRO Direct the Shift Manager to perform the following step:

• 8. Refer to 1903.010, Emergency Action Level Classification.

SRO *9. IF location of leak is known, THEN perform the applicable following steps (10.A through 10.J):

CNTMT step 10.A Primary to Secondary Leakage step 10.B Quench Tank step 10.C RDT step 10.D RCP Seals step 10.E CCW System step 10.F CVCS step 10.G SIT inleakage step 10.H Vacuum Degasifier step 10.I RCS Sample step 10.J Examiners note: Leak location will be known and only step 10.A should be performed.

ANY Note: If this step entered from step 9, then only perform substep for identified leak path.

10.

A. Check the following CNTMT parameters stable or lowering:

Humidity (Dewpoint temperature)

Sump level Temperature Pressure BOP 10.

A. Perform the following:

1) Attempt to locate leak in CNTMT by monitoring CAMS suction points and CNTMT Area Radiation monitors.

Examiner note: This action is a long term action and they may not change CAMS suction points during this drill.

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Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2009-1 Scenario No.: 1 Event No.: 5 Event

Description:

15 gpm Reactor Coolant system leak on B cold leg.

Time Position Applicant's Actions or Behavior ATC 2) Verify leak NOT in Letdown line inside CNTMT by performing the following:

a) Isolate Letdown by verifying at least ONE Letdown Isolation valve closed:

• 2CV-4820-2

• 2CV-4821-1

• 2CV-4823-2 (least preferred) b) IF RCS leakage NOT stopped, THEN letdown may be restored at discretion of SM using 2104.002, Chemical and Volume Control.

Examiners Note: Isolating Letdown will not isolate the leak and Letdown should be restored to service.

SRO *11. Check leakage within allowable limits, refer to TS 3.4.6.2, Reactor Coolant System Leakage.

SRO must enter Tech Spec 3.4.6.2 ALL *11. Perform the following:

A. Continue efforts to locate and isolate leak.

B. IF plant shutdown required, THEN perform EITHER of the following using 2102.004, Power Operations:

1) IF leakage greater than 10 gpm, THEN perform RCS boration using 2104.003, Chemical Addition, Attachment R, RCS Boration from the RWT or BAMT.

2) IF RCS leakage less than 10 gpm, THEN perform RCS boration using 2104.003, Chemical Addition, Exhibit 3, Normal RCS Boration at Power.

Examiners Note: The ATC should start a shutdown using 2104.003, Chemical Addition, Attachment R Termination Criteria: When reactivity manipulations are satisfied or at the discretion of the lead examiner.

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Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2009-1 Scenario No.: 1 Event No.: 6,7,8 Event

Description:

Main Turbine Generator trip causing a reactor trip and a Startup #3 transformer lockout causing natural circulation of the RCS. #2 Emergency Diesel Generator service water outlet valve fails to open. And, the RCS LOCA ramps to 225 gpm over 10 min.

Time Position Applicant's Actions or Behavior Cued by ANY Report Reactor Tripped Lead Examiner SRO Enter and implement EOP 2202.001, Standard Post Trip Actions.

SRO 1. Notify Control Board Operators to monitor safety functions using Exhibit 7, CBO Reactor Trip Checklist.

2. Open Safety Function Tracking page.

ATC 3. Check Reactivity Control established as follows:

Reactivity control A. Reactor power lowering.

safety function _____B. ALL CEAs fully inserted.

BOP 4. Check Maintenance of Vital Auxiliaries satisfied:

A. Main Turbine tripped.

B. Generator Output breakers open.

C. Exciter Field breaker open.

D. At least ONE 6900v AC bus energized. (Not met)

Vital E. At least ONE 4160v Non-vital AC bus energized.

Auxiliaries safety function F. BOTH 4160v Vital AC buses energized.

G. BOTH DGs secured. (Both DGs will be running, perform contingency to secure #2 EDG)

H. At least ONE 125v Vital DC bus energized:

2D01 - SPDS point E2D01 2D02 - SPDS point E2D02 Revision 1 Page 18 of 27

Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2009-1 Scenario No.: 1 Event No.: 6,7,8 Event

Description:

Main Turbine Generator trip causing a reactor trip and a Startup #3 transformer lockout causing natural circulation of the RCS. #2 Emergency Diesel Generator service water outlet valve fails to open. And, the RCS LOCA ramps to 225 gpm over 10 min.

Time Position Applicant's Actions or Behavior SRO Direct Inside AO perform the following:

G. IF ANY DG running AND SW NOT aligned, THEN locally stop DG by unlocking and placing "ENGINE CONTROL" handswitch in LOCKOUT:

• 2E11

• 2E21 (#2 EDG will be locked out due to no service water Event #7)

Cue: If requested report #2EDG is locked out locally.

ATC 5. Check RCS Inventory Control established as follows:

RCS A. PZR level:

Inventory Control 10 to 80%.

Safety Trending to setpoint. (May not met due to LOCA Event function #8, perform contingency)

B. RCS MTS 30°F or greater.

SRO Direct the following as necessary:

RCS A. Perform as necessary:

Inventory Control 1) IF SIAS actuated on PPS inserts, THEN GO TO Step 6.

Safety function 2) Verify PZR Level Control system restoring level to setpoint.

RCS ATC 6. Check RCS Pressure Control:

Pressure

• 1800 to 2250 psia.

___

• Trending to setpoint. (May not met due to LOCA Event #8, Control Safety perform contingency) function Revision 1 Page 19 of 27

Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2009-1 Scenario No.: 1 Event No.: 6,7,8 Event

Description:

Main Turbine Generator trip causing a reactor trip and a Startup #3 transformer lockout causing natural circulation of the RCS. #2 Emergency Diesel Generator service water outlet valve fails to open. And, the RCS LOCA ramps to 225 gpm over 10 min.

Time Position Applicant's Actions or Behavior SRO Direct the following actions as necessary:

6. Perform as necessary:

D. IF RCP 2P32A or 2P32B stopped, THEN verify associated PZR Spray valve in MANUAL and closed. (This step should be directed)

E. IF RCS pressure lowers to 1650 psia or less, THEN perform the following: (This step may be directed)

1) Verify SIAS actuated on PPS inserts.

2) GO TO Step 7.

F. Verify PZR Pressure Control system restoring pressure to setpoint.

G. IF ALL RCPs stopped AND RCS pressure greater than 2250 psia, THEN initiate Aux spray using Attachment 27, PZR Spray Operation.

ATC D. IF RCP 2P32A or 2P32B stopped, THEN verify associated PZR Spray valve in MANUAL and closed.

ATC 7. Check Core Heat Removal by forced circulation:

A. At least ONE RCP running. (Not met due to SU #3 lockout, perform contingency)

Core Heat Removal ANY Perform contingency:

safety function.

A. IF ALL RCPs stopped, THEN perform the following:

1) Verify BOTH PZR Spray valves in MANUAL and closed.

2) GO TO Step 8.

Revision 1 Page 20 of 27

Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2009-1 Scenario No.: 1 Event No.: 6,7,8 Event

Description:

Main Turbine Generator trip causing a reactor trip and a Startup #3 transformer lockout causing natural circulation of the RCS. #2 Emergency Diesel Generator service water outlet valve fails to open. And, the RCS LOCA ramps to 225 gpm over 10 min.

Time Position Applicant's Actions or Behavior ANY 8. Check RCS Heat Removal:

A. Check SG available by BOTH of the following:

• At least ONE SG level 10 to 90%.

• FW maintaining SG level. (Not met due to SU #3 lockout, perform contingency)

B. Check MFW in RTO. (Not met due to SU #3 lockout, perform contingency)

RCS Heat Removal C. Check Feedwater line intact by the following:

Safety Function

• SG level stable or rising.

• NO unexplained step changes or erratic FW flow.

• NO unexplained step changes or erratic Condensate flow.

D. Check Condensate Pump discharge header pressure < 753 psig.

E. Check SG pressure 950 to 1050 psia.

F. Check RCS TC 540 to 555°F.

ANY A. Perform the following:

1) IF SG level lowering, THEN verify EFAS actuated.

ANY B. Verify EITHER of the following:

• BOTH MFW pumps tripped.

• SG levels controlling at setpoint Revision 1 Page 21 of 27

Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2009-1 Scenario No.: 1 Event No.: 6,7,8 Event

Description:

Main Turbine Generator trip causing a reactor trip and a Startup #3 transformer lockout causing natural circulation of the RCS. #2 Emergency Diesel Generator service water outlet valve fails to open. And, the RCS LOCA ramps to 225 gpm over 10 min.

Time Position Applicant's Actions or Behavior ATC 9. Check CNTMT parameters:

A. Temperature and Pressure:

• Temperature less than 140°F.

• Pressure less than 16 psia.

B. Check CNTMT Spray pumps secured.

C. NO CNTMT radiation alarms or unexplained rise in activity:

1) CAMS alarms:

• "CNTMT PART/GAS RAD HI/LO" annunciator (2K10-B6) clear.

2) RCS leakage alarms:

• "AREA RADIATION HI/LO" annunciator (2K11-B10)

Containment Safety clear.

Function * "PROC LIQUID RADIATION HI/LO" annunciator (2K11-C10) clear.

3) Check the following radiation monitors trend stable:

• CNTMT Area

• CAMS

• Process Liquid D. NO secondary system radiation alarms or unexplained rise in activity:

1) "SEC SYS RADIATION HI" annunciator (2K11-A10) clear.

2) Secondary Systems Radiation monitors trend stable:

• Main Steam lines

• SG Sample

• Condenser Off Gas SRO 10. Notify STA to report to control room.

11. Verify NLOs informed of Reactor trip.

12. Verify Reactor trip announced on Plant page.

13. Notify SM to refer to Technical Specifications and 1903.010, Emergency Action Level Classification.

Revision 1 Page 22 of 27

Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2009-1 Scenario No.: 1 Event No.: 6,7,8 Event

Description:

Main Turbine Generator trip causing a reactor trip and a Startup #3 transformer lockout causing natural circulation of the RCS. #2 Emergency Diesel Generator service water outlet valve fails to open. And, the RCS LOCA ramps to 225 gpm over 10 min.

Time Position Applicant's Actions or Behavior SRO 14. Direct control board operators to acknowledge ALL annunciators and announce ALL significant alarms.

SRO 15. Check ALL safety function acceptance criteria satisfied. (All safety functions are not satisfied, perform contingency)

15. IF ANY safety function acceptance criteria NOT satisfied, THEN perform the following:

A. Notify control room staff of safety functions NOT satisfied.

B. GO TO Exhibit 8, Diagnostic Actions.

SRO Diagnose Loss of Coolant Accident EOP, 2202.003 SRO Enter and Implement Loss of Coolant Accident EOP, 2202.003 SRO

• 1. Confirm diagnosis of LOCA as follows:

A. Check SFSC acceptance criteria satisfied every 15 minutes.(Normally performed by the STA)

B. Refer to Standard Attachment 20, Break Identification Chart.

C. Verify SG Sample valves open.

D. Direct Chemistry to sample BOTH SGs for activity.

E. IF SGs indicate primary to secondary leakage within TS limits, THEN continue with this procedure using SG with lowest leak rate for cooldown.

Cue: If contacted act as Chemistry respond as requested.

SRO

• 2. Notify SM to refer to Technical Specifications and 1903.010, Emergency Action Level Classification.

SRO 3. Open Placekeeping page.

SRO 4. Record present time:

Time __________

ANY 5. Verify SIAS and CCAS actuated on PPS inserts.

Revision 1 Page 23 of 27

Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2009-1 Scenario No.: 1 Event No.: 6,7,8 Event

Description:

Main Turbine Generator trip causing a reactor trip and a Startup #3 transformer lockout causing natural circulation of the RCS. #2 Emergency Diesel Generator service water outlet valve fails to open. And, the RCS LOCA ramps to 225 gpm over 10 min.

Time Position Applicant's Actions or Behavior ANY 6. Notify Control Board Operators to perform the following:

A. Monitor floating steps.

B. Verify actuated ESFAS components using 2202.010, Exhibit 9, ESFAS Actuation.

SRO Examiner note: The SRO should pull up the floating step for performing a cooldown and direct the actions of the cooldown step.

Step 1 of the unisolated LOCA section.

1. Perform controlled cooldown to 275°F TC as follows:

ANY A. Check RCS TC greater than 275°F.

ATC B. Reset Low PZR Pressure and Low SG Pressure setpoints during cooldown and depressurization.

CRITICAL STEP C. Verify maximum of ONE RCP running in EACH loop.

ANY Floating ATC D. IF RCP 2P32A or 2P32B stopped, step for a THEN verify associated PZR Spray valve in MANUAL and cooldown closed.

Must commence E. Monitor cooldown rate as follows:

a cooldown ATC

>40 degrees

• Record RCS TC and PZR temperature using Standard per hour Attachment 8, RCS Cooldown Table.

within 30 min. of

• Plot RCS pressure versus RCS TC using Standard entering LOCA Attachment 1, procedure P-T Limits every 15 minutes.

ATC F. Initiate RCS cooldown using SDBCS bypass valves or ADVs.

ANY G. Verify EFW or AFW capable of feeding SGs.

ANY H. Secure running MFW pump.

ANY I. Close ALL MFW Block valves.

Revision 1 Page 24 of 27

Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2009-1 Scenario No.: 1 Event No.: 6,7,8 Event

Description:

Main Turbine Generator trip causing a reactor trip and a Startup #3 transformer lockout causing natural circulation of the RCS. #2 Emergency Diesel Generator service water outlet valve fails to open. And, the RCS LOCA ramps to 225 gpm over 10 min.

Time Position Applicant's Actions or Behavior SRO Examiner note: The SRO should pull up the floating step for restoring ESF and Non/ESF systems and direct the actions of the step. Step 9 of the entry section for LOCA OP-2202.003.

9. Restore ESF/Non-ESF systems post-SIAS as follows:

ANY A. Verify at least ONE SW pump running on EACH loop.

ANY B. Verify DG SW Outlet valves open.(Not met on #2 EDG, perform contingency)

Examiner note: The Crew should have the WCO open the Service water outlet valve for #2EDG then have the AO remove the EDG from Lockout to allow it to start, but may elect to start the Alternate AC generator to supply 2A-4 vital 4160V bus or cross-tie 2B-5 and 2B-6 vital 480 volt busses using floating step 21 from the entry section of 2203.003 LOCA. One of these actions should be completed to restore auxiliary spray capability (RCS pressure control)

ANY Direct Non-licensed operators to perform the following:

B. IF SW Outlet valve can NOT be opened from Control Room, THEN locally perform the following for affected DG:

1) Open DG SW Outlet valve:

• "2DG-1 SW OUTLET" 2CV-1503-1

• "2DG-2 SW OUTLET" 2CV-1504-2

2) Monitor DG "SCAV AIR TEMP":

• 2TI-2931

• 2TI-2981

3) IF DG "SCAV AIR TEMP" rises to 170°F, THEN stop DG by unlocking and placing "ENGINE CONTROL" switch in LOCKOUT:

• 2E11

• 2E21 Cue: If contacted as WCO then open the #2EDG SW outlet valve and report that 2CV-1504-2 is open.

Cue: If contacted as AO, then place #2 EDG back to AUTO and report action taken.

ANY C. Verify SW pump suction aligned to Lake.

Revision 1 Page 25 of 27

Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2009-1 Scenario No.: 1 Event No.: 6,7,8 Event

Description:

Main Turbine Generator trip causing a reactor trip and a Startup #3 transformer lockout causing natural circulation of the RCS. #2 Emergency Diesel Generator service water outlet valve fails to open. And, the RCS LOCA ramps to 225 gpm over 10 min.

Time Position Applicant's Actions or Behavior ANY D. Check 4160v Non-vital bus 2A1 or 2A2 energized from offsite power.

ANY E. Check BOTH 4160v Vital buses 2A3 AND 2A4 energized from offsite. (Not met due to Startup

1. 3 lockout, perform contingency)

ANY E. Perform the following:

2) IF EITHER 4160v Vital bus energized from DG, THEN perform the following:

a) Verify ONE SW pump running on train supplied by DG.

b) GO TO Step 9.G.

ANY G. Check SW to CCW restored.(Not met, perform contingency)

ANY G. IF CCW available, THEN restore SW to CCW, refer to Exhibit 5, CCW/ACW/SW Alignment.

ANY H. Check ACW restored. (Not met, perform contingency)

ANY H. Restore SW to ACW, refer to Exhibit 5, CCW/ACW/SW Alignment.

ANY I. Maintain SW header pressure greater than 85 psig.

Termination criteria: When the Crew has commenced a cooldown or at discretion of lead examiner.

Revision 1 Page 26 of 27

Appendix D Scenario 1 Form ES-D-2 Op-Test No.: 2009-1 Scenario No.: 1 Event No.: 9 Event

Description:

2P-89A Safety injection pump shaft shear.

Time Position Applicant's Actions or Behavior ANY Recognizes and announces failure of A HPSI pump due to shaft shear.

Cue: As waste control operator if requested report that A HPSI pump shaft is sheared.

SRO Direct BOP start C HPSI pump (2P89C).

CRITICAL BOP On 2C17, remove the hand switch for C HPSI pump (2P89C) from STEP PTL and verified 2P-89C started and discharge pressure indicated (if pressure < 1450psia, verified flow to RCS) or #2 EDG restored and B HPSI pump (2P-89) is running.

2P-89C or 2P-89B must be started prior to reaching 100F Margin to Saturation.

Termination criteria: Termination criteria: When B or C HPSI pump is started or at the discretion of the lead examiner.

Revision 1 Page 27 of 27

Appendix D Scenario 2 Form ES-D-1 Facility: ANO-2 Scenario No.: 2 (New) Op-Test No.: 2009-1 Examiners: Operators:

Initial Conditions:

100% MOL, All Engineered Safety Features systems are in standby. Gland Seal steam pressure control valve 2PCV-0231 jacked closed. RED Train Maintenance Week. 2T-6A Boric Acid Make up tank is aligned for acid reducing shut down chemistry for Unit 1 Turnover:

100%. 260 EFPD. EOOS indicates Minimal Risk. 2PCV-0231 jacked closed, manually control seal steam pressure. RED Train Maintenance Week. 2T-6A Boric Acid Make up tank is aligned for acid reducing shut down chemistry for Unit 1 refueling outage that starts next week.

Evolution scheduled: Drain Containment Sump to 50% level. Steps 20.1.1 and 20.1.2 of OP-2104.014 have been completed.

Event Malf. No. Event Event No. Type* Description 1 CV20601 C (BOP) Containment sump drain valve breaker trips during DO_HS_2060_G C (SRO) normal drain evolution. Tech Spec for SRO DO_HS_2060_R 2 SW2P-4A C (BOP) 2P-4A Service water pump breaker trips C (SRO) 3 XRCCHAPLVL I (ATC) A Pressurizer level channel fails High. Tech Spec for I (SRO) SRO 4 R (ATC) System Dispatcher call with a request to reduce power N (BOP) to ~ 850MWe(~80%) within 30 min.

N (SRO) 5 CV10101 M (ALL) A Steam Generator MSIV 2CV-1010-1 fails closed.

SGAMSIVBEF Then 2 minutes after trip an Excess Steam Demand outside containment commences.

6 CEA38STUCK C (ATC) Control Element Assembly #38 remains fully CV48731 C (SRO) withdrawn when the reactor trips. The VCT outlet will not close and 2P-39B will trip when the reactor trips.

CVC2P39B 7 ESFCCAS2 C (BOP) Green train Containment coolers fail to automatically C (SRO) actuate.

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Total malfunctions. = 6, Malfunctions. after EOP entry = 2, Abnormal events = 3, Major transient = 1, EOPs with substantive actions =1, EOP Contingencies = 1, Critical tasks = 2.

Revision 1 Page 1 of 26

Appendix D Scenario 2 Form ES-D-1 Scenario #2 Objectives

1) Evaluate individual response to a failure of a containment isolation valve.

2) Evaluate individual ability to operate safety related equipment.

3) Evaluate individual response to a failure of a Service Water pump.

4) Evaluate individual response to a failure of a Pressurizer level control channel.

5) Evaluate individual ability to perform a reduction in plant power.

6) Evaluate individual response to a stuck out CEA after a Reactor Trip.

7) Evaluate individual response to a failed closed Main Steam Isolation Valve.

8) Evaluate individual ability to mitigate an Excess Steam Demand Outside containment.

9) Evaluate individual ability to monitor operation of Engineered Safety Features equipment.

SCENARIO #2 NARRATIVE Simulator session begins with the plant at 100% power steady state Gland seal regulator, 2PCV0231 is jacked closed and 2T-6A is aligned for acid reducing chemistry.

When the crew has completed their control room walk down and brief, The BOP will drain the Containment sump to the Auxiliary building sump using the normal drain method. When the BOP attempts to close 2CV-2060-1 its supply breaker will trip. The BOP should ensure the series sump drain valve 2CV-2061-2 is closed and sump level is stable. The SRO will determine that Tech Spec 3.6.3.1 is applicable and will enter Tech Spec 3.6.3.1.

After the Crew has entered the appropriate Tech Spec, verified sump level is stable or cued by lead examiner; the A Service Water Pump (2P-4A) breaker will trip open. The SRO will enter AOP, 2203.022 Loss of Service Water. The SRO will direct the BOP to start 2P-4B Service Water Pump.

After the B Service Water pump is placed in service or cued by lead examiner, the in service Pressurizer (PZR) control channel level instrument will fail high. This will result in letdown going to maximum flow, the two backup CCPs will automatically stop, all PZR heaters energizing and actual PZR level lowering. AOP 2203.028, PZR Systems Malfunctions, will be entered and actions directed by the SRO. The ATC will take the letdown flow controller to manual and control PZR level. The ATC will also verify that the other level control channel is reading correctly and select that channel for control and place the PZR low level cutoff switch to the unaffected channel. The SRO will enter Tech Spec 3.3.3.6 Post Accident Instrumentation. When the auto and manual signals are matched, the ATC will place the letdown flow controller to automatic.

Revision 1 Page 2 of 26

Appendix D Scenario 2 Form ES-D-1 SCENARIO #2 NARRATIVE (continued)

After the ATC has placed B Channel pressurizer level control in service and restored letdown to automatic, The Pine Bluff Systems Operations Center (SOC) will call the Control Room with a Transmission Loading Relief (TLR) to reduce plant output by 200MWe. The SOC will also report that all limits of EN-DC-199 are still met. If Contacted, Unit 1 will be unable to maneuver due to ICS maintenance.

After the ATC has completed the required reactivity manipulation or cued by lead examiner, 2CV-1010-1 A Steam Generator Main Steam Isolation Valve will fail closed. The crew will verify the reactor is tripped.

The Crew will implement Standard Post Trip Actions (SPTA), OP 2202.001. When the reactor trips one CEA will remain withdrawn which requires emergency boration. The VCT outlet will remain open and 2P-39B Boric Acid Makeup pump will trip when started. Reactivity control will not be satisfied. During SPTAs, an Excess Steam Demand event outside of Containment will commence. The Crew will manually actuate Main Steam Isolation Signal (MSIS) or verify that a Main Steam Isolation signal automatically actuates. The Crew will secure and/or verify that Emergency Feedwater (EFW) is not feeding A Steam generator. The ATC will secure two Reactor coolant Pumps when RCS pressure goes below 1400 psia.

The SRO will diagnose Functional Recovery due to reactivity control not being met and enter OP 2202.009, Functional Recovery.

The crew will manually control Reactor Coolant Temperature once the A SG boils dry using the upstream Atmospheric Dump Valve on B SG. The ATC will control RCS pressure using normal spray.

Revision 1 Page 3 of 26

Appendix D Scenario 2 Form ES-D-1 Simulator Instructions for Scenario 2 Reset simulator to MOL 100% power IC stead state.

Ensure that AACG is secured and annunciators clear.

Place MINIMAL RISK and RED Train Maintenance Week signs on 2C11.

Swing ESF equipment aligned to the RED train.

B CCP lead charging pump.

2PCV0231, Gland sealing steam pressure control valve failed closed.

2T-6A aligned for acid reducing shut down chemistry (CV49201 Value = 0, 2P-39A running with the recirc open, 2P-39A discharge valve closed CVC40A = 0)

Ensure CVC40A = 0 T1, T2, T3, T4, set to false.

T1 set to OE3C0601 T5 set to Reactor trip.

Event Malf. No. Value/ Event No. Ramp Description Time 1 CV20601 0.0 Containment isolation valve 2CV-2060-1 breaker trips.

DO_HS_2060_G DO_HS_2060_R Trigger = T1 2 SW2P-4A 0.0 2P-4A Service water pump breaker trips.

Trigger = T2 3 XRCCHAPLVL 100 Control Channel A Pressurizer Level fails High.

Trigger = T3 4 System Dispatcher call with a TLR to reduce power to ~

850MWe within 30 min.

5 CV10101 0 A Steam Generator MSIV 2CV-1010-1 fails closed.

SGAMSIVBEF 1.5/ Then 2 minutes after trip an Excess Steam Demand Delay = outside containment commences.

Trigger = T4 2 min.

6 CEA38STUCK 0% Control Element Assembly #38 remains fully withdrawn CV48731 1 when the reactor trips. The VCT outlet will not close and 2P-39B will trip when the reactor trips.

CVC2P39B True Trigger = 5 for CVC2P39B only 7 ESFCCAS2 True Green train Containment coolers fail to automatically or manually actuate.

Revision 1 Page 4 of 26

Appendix D Scenario 2 Form ES-D-1 Simulator Operator CUEs At T=0 Trigger T1 Containment isolation valve 2CV-2060-1 tripped its supply breaker during normal drain evolution Cue: When contacted as the WWM, then report that electrical planner will begin planning work trouble shoot 2CV-2060-1.

Cue: If asked report that the breaker for 2CV-2060-1 2B51-B2 is trip free and breaker 2B51-H3 is closed.

Cued by Trigger T2 2P-4A Service water pump breaker trips.

lead examiner Cue: If asked report that the motor for A Service Water Pump is hot to touch, but no fire or smoke is evident.

Cue: If requested when B Service Water pump is started, report as AO that B Service Water pump post start checks are satisfactory.

Cue: When contacted as the WWM, then report that the electrical planner will begin planning work on failed pump.

Cued by Trigger T3 Control Channel A Pressurizer Level fails High.

lead examiner Cue: When contacted as the WWM, then report that I & C planner will begin planning work on failed level instrument.

Cued by System Dispatcher call with a TLR to reduce power to ~ 850MWe lead within 30 min.

examiner Cue: Call as the Pine Bluff Systems Operations Center (SOC) with a Transmission Loading Relief (TLR) to reduce plant output to ~850 MWe (lower output by 200 MWe) within 30 min. The SOC will also report that all limits of EN-DC-199 are satisfied.

Cue: If contacted as Unit 1 report that the plant is within 60 days of a refueling outage and can not lower power.

Cued by Trigger T4 A Steam Generator MSIV 2CV-1010-1 fails closed.

lead examiner Reactor Trip Trigger T5 A Steam Generator Safety valve 2PSV-1002 sticks open Reactor Trip Control Element Assembly #38 remains fully withdrawn when the reactor trips. The VCT outlet will not close and 2P-39B will trip when the reactor trips.

Cue: If contacted as the AO to open 2CVC-40A (2P-39A discharge valve), then report that is stuck closed and will not open.

Cue: If contacted as the WCO to locally close 2CV-4873-1 VCT outlet valve, then delay locally closing the valve until after Functional recovery procedure has been entered.

Containment Green train Containment coolers fail to automatically or manually Cooling actuate.

actuation.

Revision 1 Page 5 of 26

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2009-1 Scenario No.: 2 Event No.: 1 Event

Description:

Draining the Containment sump beginning with step 20.1.3.

Time Position Applicant's Actions or Behavior BOP 20.1.3 Open the following valves to drain CNTMT sump:

Containment Sump Isolation valve (2CV-2060-1)

Containment Sump Isolation valve (2CV-2061-2)

ANY *20.1.4 Using level indication or corresponding computer points, monitor the following to prevent overflow:

Aux Building sump (2LIS-2000 or 2LIS-2000B)

In service Waste tank:

- 2T-20A (2LIS-2010)

- 2T-20B (2LIS-2012)

BOP *20.1.5 Cycle 2CV-2061-2 as necessary to prevent overflowing Aux Building sump.

BOP 20.1.6 WHEN draining is complete, THEN close the following valves:

2CV-2061-2 2CV-2060-1 BOP Report to the SRO that 2CV-2060-1 lights are out and suspect the breaker is tripped.

ANY Verify that Containment Sump level is not trending down.

Cue: If asked report that the breaker for 2CV-2060-1 2B51-B2 is trip free and breaker 2B51-H3 is closed.

SRO Refer to Tech Specs and enter Tech Spec 3.6.3.1 and determine that 2CV-2060-1 must be isolated within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Examiner note: SRO must Tech Spec 3.6.3.1 due to 2CV-2060-1 SRO Contact work management.

Cue: When contacted as the WWM, then report that electrical planner will begin planning work trouble shoot 2CV-2060-1.

Termination criteria: When Tech Spec 3.6.3.1 is entered and 2CV-2061-2 is closed or at lead examiners discretion.

Revision 1 Page 6 of 26

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2009-1 Scenario No.: 2 Event No.: 2 Event

Description:

2P-4A Service water pump breaker trips.

Time Position Applicant's Actions or Behavior Cued by ANY Report 2K06-B5 2P4A BREAKER TRIP lead examiner SRO Enter and direct actions of AOP, 2203.022 Loss of Service Water

• 1. Check the following criteria satisfied:

A. Breaker trip annunciators clear (2K06-B5/2K05-B4, B5).

(Perform contingency)

SRO A. GO TO Step 7.

SRO 7. Check "2P4A BREAKER TRIP" annunciator (2K06-B5) clear.

(Perform contingency)

BOP A. IF 2P4B aligned to Loop 1, THEN verify 2P4B running.

Examiner note: BOP will verify a suction source and start 2P-4B Cue: If asked report that the motor for A Service Water Pump is hot to touch, but no fire or smoke is evident.

Cue: If requested when B Service Water pump is started, report as AO that B Service Water pump post start checks are satisfactory.

SRO Contact work management.

Cue: When contacted as the WWM, then report that the electrical planner will begin planning work on failed pump.

Termination criteria: When B service water pump is placed in service or at lead examiners discretion.

Revision 1 Page 7 of 26

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2009-1 Scenario No.: 2 Event No.: 3 Event

Description:

A Pressurizer level channel fails High. Tech Spec for SRO Time Position Applicant's Actions or Behavior Cued by ANY Announce alarm 2K10-J6 CNTRL CH 1 LEVEL HIGH.

lead Report 2LI-4627-2 and 2LR-4625 indicate normal.

examiner Letdown flow high.

SRO Direct the ATC to place letdown flow controller to manual and lower flow to control pressurizer level.

ATC Place 2HIC-4817 to manual and lower letdown flow to control pressurizer level.

SRO Enter and implement PZR Systems Malfunctions AOP 2203.028 SRO 6. Check the following PZR level annunciators clear:

• "CNTRL CH 1/2 LEVEL LO" 2K10-G6/G7

• "CNTRL CH 1/2 LEVEL HI" 2K10-J6/J7 (Annunciators not clear, implement contingency)

ANY 6. Perform the following:

A. Compare PZR level instruments to determine the affected channel.

ATC C. IF selected control channel failed, THEN perform the following:

1) Place Letdown Flow controller (2HIC-4817) in MANUAL.

ATC 2) Place PZR Level Channel Select switch (2HS-4628) to unaffected channel.

ATC 3) Place PZR Low Level Cutoff select switch (2HS-4642) to unaffected channel.

ANY 4) Verify PZR heaters and Normal Spray operating to restore RCS pressure 2025 to 2275 psia.

ATC 5) WHEN Letdown Flow controller (2HIC-4817) automatic AND manual signals match, THEN place Letdown Flow controller in AUTO.

Revision 1 Page 8 of 26

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 2009-1 Scenario No.: 2 Event No.: 3 Event

Description:

A Pressurizer level channel fails High. Tech Spec for SRO Time Position Applicant's Actions or Behavior Examiner Note: The ATC may elect to take manual control of the pressurizer level controller (2LIC-4627), match the auto and manual signals then place the pressurizer level controller (2LIC-4627) to automatic.

SRO E. Refer to TS 3.3.3.5, Remote Shutdown Instrumentation and 3.3.3.6, Post-Accident Instrumentation.

Examiner note: SRO must enter Tech Spec 3.3.3.6 Post Accident Instrumentation.

SRO Contact work management.

Cue: When contacted as the WWM, then report that I & C planner will begin planning work on failed level instrument.

Termination Criteria: PZR level control selected to channel 2 in auto control or at lead examiner's discretion.

Revision 1 Page 9 of 26

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 4 Event

Description:

System Dispatcher call with a TLR to reduce power to ~ 850MWe within 30 min.

Crew will perform a plant shutdown Time Position Applicant's Actions or Behavior Cue: Call as the Pine Bluff Systems Operations Center (SOC) with a Transmission Loading Relief (TLR) to reduce plant output to ~850 MWe (lower output by 200 MWe) within 30 min.

The SOC will also report that all limits of EN-DC-199 are satisfied and the reliability of Offsite power is not impacted.

Cued by SRO Implement 2107.001 attachment S lead examiner SRO 1.1 IF notified by the SOC, TOC or Woodlands dispatcher that a TLR has been issued for ANO, THEN perform the following:

1.1.1 Conduct Reactivity Brief for requested downpower.

ALL 1.1.2 Unit designated to reduce power, commence power reduction using respective Power Operations procedure.

Cue: If contacted as Unit 1 report that the plant is within 60 days of a refueling outage and can not lower power.

SRO 1.1.3 Notify Operations Management.

Examiner note: 2107.001 attachments step 1.1.4 and 1.15 are normally completed by the Shift Manager and are not expected to be completed by the Control Room Supervisor.

1.1.4 IF power reduction requested is greater than 25 MWe, THEN inform Site Duty Manager to perform the following:

A. Perform required notifications per Notifications of Off-Normal Situations/Corporate Duty Manager responsibilities (EN-OM-128).

B. Notify NRC Resident.

1.1.5 IF notified by the Dispatcher of any off site disturbance that may affect the reliability of Offsite Power, THEN perform a Risk assessment using guidance in COPD-24.

1.1.6 Verify with Pine Bluff SOC that requirements of ENS-DC-199, Off-Site Power Supply Design Requirements, off-site post-trip voltage and frequency limits still met.

Examiner note: The following steps are the applicable steps from 2102.004 Power operation to perform a power reduction to 80%

Revision 1 Page 10 of 26

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 4 Event

Description:

System Dispatcher call with a TLR to reduce power to ~ 850MWe within 30 min.

Crew will perform a plant shutdown Time Position Applicant's Actions or Behavior SRO 11.6 Notify the following of intent to reduce power:

Chemistry Reactor Engineering Radiation Protection Little Rock Dispatcher Woodlands Dispatcher ATC 11.7 IF power reduction NOT rapid, THEN perform the following:

Determine amount of boric acid required for power reduction from Reactivity curves (located in Plant Data book) OR Unit 2 Shift Relief Sheet (1015.016).

IF NOT otherwise specified by Reactor Engineering, THEN determine desired rate of load change using Attachment A of this procedure.

Examiner note: This down power is not considered a rapid power reduction.

ATC 11.8 Commence Power reduction by performing the following as Power necessary:

reduction Boration using Normal Borate Mode to Charging pump suction (unless directed otherwise by Abnormal Operating Procedure) Refer to Chemical Addition (2104.003).

CEA insertion using CEDMCS Control System Operation (2105.009), Exhibit 3 CEDMCS Operations (normally for ASI control).

ANY *11.9 Lower Turbine load as necessary to hold Tave within +/- 2°F of program Tref using Exhibit 1, TAVE VS TREF.

ANY *11.10 Throttle Condensate recircs as necessary to maintain 650-750 psig Condensate Pump Discharge pressure:

2CV-0662 2CV-0663 ATC

• 11.12 Maintain ASI by performing the following:

IF power reduction rapid, THEN maintain ASI (PID 268) within Core Operating Limits Report (COLR) limits using CEA Group 6 or Group P.

IF power reduction NOT rapid, THEN maintain ASI at desired value using CEA Group 6 and Group P per Attachment A. (QASI trip setpoint +/- 0.48)

Revision 1 Page 11 of 26

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 4 Event

Description:

System Dispatcher call with a TLR to reduce power to ~ 850MWe within 30 min.

Crew will perform a plant shutdown Time Position Applicant's Actions or Behavior ANY

• 11.13 IF power change exceeds 15% within a one hour period, THEN notify Chemistry to obtain an RCS sample for Iodine Power between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following power change (TS 3.4.8).

reduction ANY Notify NLO to perform the following:

• 11.15 Monitor Secondary chemistry and adjust chemical feed as needed using Secondary System Chemical Addition (2106.028).

Termination Criteria: When reactivity manipulations are satisfied or at the discretion of the lead examiner.

Revision 1 Page 12 of 26

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 5, &6 Event

Description:

A Steam Generator MSIV 2CV-1010-1 fails closed. Then 2 minutes after trip an Excess Steam Demand outside containment commences. Control Element Assembly #38 remains fully withdrawn when the reactor trips. The VCT outlet will not close and 2P-39B will trip when the reactor trips.

Time Position Applicant's Actions or Behavior Cued by ANY Report Reactor Tripped lead examiner SRO Enter and implement EOP 2202.001, Standard Post Trip Actions.

SRO 1. Notify Control Board Operators to monitor safety functions using Exhibit 7, CBO Reactor Trip Checklist.

2. Open Safety Function Tracking page.

Reactivity ATC 3. Check Reactivity Control established as follows:

control safety A. Reactor power lowering.

function B. ALL CEAs fully inserted. (Not met due to Event #6, perform contingency)

SRO Direct ATC to perform emergency boration in progress using Exhibit 1, Emergency Boration.

_____B. Verify emergency boration in progress using Exhibit 1, Emergency Boration.

Examiner note: Emergency boration can not be established.

ATC 1. Select ONE of the following Emergency Boration flowpaths:

FLOWPATH ACTIONS REQUIRED A. Gravity Feed A. Verify at least ONE BAM Tank Gravity Feed valve open:

• 2CV-4920-1

• 2CV-4921-1 B. BAM pumps B. 1) Start at least ONE BAM pump.

2) Open Emergency Borate valve (2CV-4916-2).

3) Verify Boric Acid Makeup Flow Control valve (2CV-4926) closed.

C. RWT to Charging pumps C. Open Charging Pump Suction Source From RWT valve (2CV-4950-2).

Revision 1 Page 13 of 26

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 5, &6 Event

Description:

A Steam Generator MSIV 2CV-1010-1 fails closed. Then 2 minutes after trip an Excess Steam Demand outside containment commences. Control Element Assembly #38 remains fully withdrawn when the reactor trips. The VCT outlet will not close and 2P-39B will trip when the reactor trips.

Time Position Applicant's Actions or Behavior ATC 2. Close VCT Outlet valve (2CV-4873-1).

Examiner Note: The VCT outlet valve will not close and should perform step 3.

ATC 3. IF VCT Outlet valve does NOT close, THEN verify BAM Pumps Emergency Boration flowpath selected.

Examiner Note: 2P-39B breaker will trip when the pump is started and 2P-39A is not available due to the line up for acid reducing chemistry. Emergency boration can not be completed and should be reported to the SRO.

Examiner note: SRO may discuss Shutdown margin Tech Spec 3.1.1.1 due to one CEA withdrawn and inability to emergency borate. One CEA can be withdrawn without emergency boration and meet shutdown margin (SDM).

Cue: If contacted as the AO to open 2CVC-40A (2P-39A discharge valve), then report that it is stuck closed and will not open.

Cue: If contacted as the WCO to locally close 2CV-4873-1 VCT outlet valve, then delay locally closing the valve until after Functional recovery procedure has been entered.

BOP 4. Check Maintenance of Vital Auxiliaries satisfied:

A. Main Turbine tripped.

B. Generator Output breakers open.

C. Exciter Field breaker open.

D. At least ONE 6900v AC bus energized Vital Auxiliaries E. At least ONE 4160v Non-vital AC bus energized.

safety function F. BOTH 4160v Vital AC buses energized.

G. BOTH DGs secured.

H. At least ONE 125v Vital DC bus energized:

2D01 - SPDS point E2D01 2D02 - SPDS point E2D02 Revision 1 Page 14 of 26

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 5, &6 Event

Description:

A Steam Generator MSIV 2CV-1010-1 fails closed. Then 2 minutes after trip an Excess Steam Demand outside containment commences. Control Element Assembly #38 remains fully withdrawn when the reactor trips. The VCT outlet will not close and 2P-39B will trip when the reactor trips.

Time Position Applicant's Actions or Behavior ATC 5. Check RCS Inventory Control established as follows:

RCS A. PZR level:

Inventory Control 10 to 80%.

Safety Trending to setpoint. (May not be met due to ESD Event function #5 perform contingency if not met)

B. RCS MTS 30°F or greater.

SRO Examiners Note: This may or may not be performed depending on the PZR level trend at the time this safety function is assessed.

Direct the following as necessary:

A. Perform as necessary:

1) IF SIAS actuated on PPS inserts, THEN GO TO Step 6.

2) Verify PZR Level Control system restoring level to setpoint.

ATC 6. Check RCS Pressure Control:

• 1800 to 2250 psia.

• Trending to setpoint. (May not be met due to ESD Event #5.

Perform contingency if not met)

SRO Examiners Note: This may or may not be performed depending on the PZR level trend at the time this safety function is assessed.

Direct the following actions as necessary:

6. Perform as necessary:

RCS A. IF RCS pressure lowers to less than 1400 psia, Pressure THEN trip ONE RCP in EACH loop.

Control Safety B. IF NPSH requirements violated OR function RCS MTS less than 30°F, THEN verify ALL RCPs tripped.

D. IF RCP 2P32A or 2P32B stopped, THEN verify associated PZR Spray valve in MANUAL and closed.

E. IF RCS pressure lowers to 1650 psia or less, THEN perform the following:

1) Verify SIAS actuated on PPS inserts.

2) GO TO Step 7.

Revision 1 Page 15 of 26

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 5, &6 Event

Description:

A Steam Generator MSIV 2CV-1010-1 fails closed. Then 2 minutes after trip an Excess Steam Demand outside containment commences. Control Element Assembly #38 remains fully withdrawn when the reactor trips. The VCT outlet will not close and 2P-39B will trip when the reactor trips.

Time Position Applicant's Actions or Behavior F. Verify PZR Pressure Control system restoring pressure to setpoint.

G. IF ALL RCPs stopped AND RCS pressure greater than 2250 psia, THEN initiate Aux spray using Attachment 27, PZR Spray Operation.

ATC 7. Check Core Heat Removal by forced circulation:

A. At least ONE RCP running.

B. CCW flow aligned to RCPs.

C. Loop delta T less than 10°F.

D. RCS MTS 30°F or greater.

Core Heat E. Check SW aligned to CCW. (May not be aligned and should Removal perform contingency) safety function.

F. IF SIAS or MSIS actuated, THEN maintain SW header pressure greater than 85 psig.

SRO If required, direct the contingency for step 7. E BOP E. IF CCW available, THEN restore SW to CCW, refer to 2202.010 Exhibit 5, CCW/ACW/SW Alignment.

Revision 1 Page 16 of 26

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 5, &6 Event

Description:

A Steam Generator MSIV 2CV-1010-1 fails closed. Then 2 minutes after trip an Excess Steam Demand outside containment commences. Control Element Assembly #38 remains fully withdrawn when the reactor trips. The VCT outlet will not close and 2P-39B will trip when the reactor trips.

Time Position Applicant's Actions or Behavior ANY 8. Check RCS Heat Removal:

A. Check SG available by BOTH of the following:

• At least ONE SG level 10 to 90%.

• FW maintaining SG level. (Should not be met due to MSIS, perform contingency if necessary)

B. Check MFW in RTO. (Should not be met due to MSIS, perform contingency if necessary)

C. Check Feedwater line intact by the following:

• SG level stable or rising.

• NO unexplained step changes or erratic FW flow.

• NO unexplained step changes or erratic Condensate flow.

D. Check Condensate Pump discharge header pressure < 753 psig.

E. Check SG pressure 950 to 1050 psia. (Not Met, perform Contingency)

F. Check RCS TC 540 to 555°F.

ANY Perform step 8 contingency actions that are applicable:

A. Perform the following:

1) IF SG level lowering, THEN verify EFAS actuated. (To the B S/G only)

ANY B. Verify EITHER of the following:

• BOTH MFW pumps tripped.

• SG levels controlling at setpoint Revision 1 Page 17 of 26

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 5, &6 Event

Description:

A Steam Generator MSIV 2CV-1010-1 fails closed. Then 2 minutes after trip an Excess Steam Demand outside containment commences. Control Element Assembly #38 remains fully withdrawn when the reactor trips. The VCT outlet will not close and 2P-39B will trip when the reactor trips.

Time Position Applicant's Actions or Behavior ANY E. Perform as necessary:

1) IF SG pressure 751 psia or less, THEN perform the following:

a) Verify MSIS actuated on PPS inserts.

b) Maintain RCS post-cooldown conditions as follows:

Maintain RCS pressure within P-T limits with PZR heaters and spray using Attachment 27, PZR Spray Operation.

Maintain RCS temperature by steaming intact SG using Upstream ADV or Upstream ADV Isolation MOV.

c) GO TO Step 9.

Revision 1 Page 18 of 26

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 5, &6 Event

Description:

A Steam Generator MSIV 2CV-1010-1 fails closed. Then 2 minutes after trip an Excess Steam Demand outside containment commences. Control Element Assembly #38 remains fully withdrawn when the reactor trips. The VCT outlet will not close and 2P-39B will trip when the reactor trips.

Time Position Applicant's Actions or Behavior

9. Check CNTMT parameters:

A. Temperature and Pressure:

• Temperature less than 140°F.

• Pressure less than 16 psia.

B. Check CNTMT Spray pumps secured.

C. NO CNTMT radiation alarms or unexplained rise in activity:

1) CAMS alarms:

• "CNTMT PART/GAS RAD HI/LO" annunciator (2K10-B6) clear.

2) RCS leakage alarms:

• "AREA RADIATION HI/LO" annunciator (2K11-B10) clear.

• "PROC LIQUID RADIATION HI/LO" annunciator (2K11-C10) clear.

3) Check the following radiation monitors trend stable:

• CNTMT Area

• CAMS

• Process Liquid D. NO secondary system radiation alarms or unexplained rise in activity:

1) "SEC SYS RADIATION HI" annunciator (2K11-A10) clear.

2) Secondary Systems Radiation monitors trend stable:

• Main Steam lines

• SG Sample

• Condenser Off Gas SRO 10. Notify STA to report to control room.

11. Verify NLOs informed of Reactor trip.

12. Verify Reactor trip announced on Plant page.

13. Notify SM to refer to Technical Specifications and 1903.010, Emergency Action Level Classification.

Revision 1 Page 19 of 26

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 5, &6 Event

Description:

A Steam Generator MSIV 2CV-1010-1 fails closed. Then 2 minutes after trip an Excess Steam Demand outside containment commences. Control Element Assembly #38 remains fully withdrawn when the reactor trips. The VCT outlet will not close and 2P-39B will trip when the reactor trips.

Time Position Applicant's Actions or Behavior SRO 14. Direct control board operators to acknowledge ALL annunciators and announce ALL significant alarms.

SRO 15. Check ALL safety function acceptance criteria satisfied. (All safety functions are not satisfied, perform contingency)

15. IF ANY safety function acceptance criteria NOT satisfied, THEN perform the following:

A. Notify control room staff of safety functions NOT satisfied.

B. GO TO Exhibit 8, Diagnostic Actions.

SRO Diagnose Functional Recovery EOP 2202.009.

SRO Enter and implement Functional Recovery EOP 2202.009.

SRO 2. Record present time:

• Time .

SRO

• 3. Notify SM to refer to Technical Specifications and 1903.010, Emergency Action Level Classification.

ANY

• 4. Check RCS pressure greater than 1400 psia.

ANY If not performed in SPTAs, Then perform contingency to secure 2 RCPs

• 4. Perform the following:

A. IF RCS pressure less than 1400 psia, THEN perform the following:

1) Verify maximum of ONE RCP running in EACH loop.

2) IF RCP 2P32A or 2P32B stopped, THEN verify associated PZR Spray valve in MANUAL and closed.

Examiner Note:

The SRO may have directed the ATC and BOP actions for maintaining post-cooldown conditions from SPTAs and therefore may not implement the following floating step.

SRO Should pull up the floating step for maintain post-cooldown conditions.

HR-2 Step 33.

Revision 1 Page 20 of 26

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 5, &6 Event

Description:

A Steam Generator MSIV 2CV-1010-1 fails closed. Then 2 minutes after trip an Excess Steam Demand outside containment commences. Control Element Assembly #38 remains fully withdrawn when the reactor trips. The VCT outlet will not close and 2P-39B will trip when the reactor trips.

Time Position Applicant's Actions or Behavior BOP 33. Maintain RCS post-cooldown conditions as follows:

Maintain A. Maintain RCS temperature by steaming intact SG using post- EITHER of the following:

cooldown

• Upstream ADV.

conditions

• Upstream ADV Isolation MOV.

CRITICAL STEP RCS temperature must be maintained within 30°F of A Steam Generator Tc when generator boiled dry.

Maintain ATC B. Maintain RCS pressure within P-T limits using PZR heaters and post- 2202.010 Attachment 27, PZR Spray Operation.

cooldown conditions Maintain Post steam generator blow down pressure using attachment CRITICAL 27 within the Pressure-Temperature limits of 200°F and 30°F.

STEP ANY

• 5. IF SIAS or MSIS actuated, THEN perform the following:

A. Verify at least ONE SW pump running on EACH loop.

ANY B. Check EITHER DG running.

ANY C. Verify running DG SW Outlet valve open:

• 2CV-1503-1

• 2CV-1504-2 ANY D. Verify SW pump suction aligned to Lake.

ANY E. Check 4160v Non-vital bus 2A1 OR 2A2 energized from offsite power.

ANY F. Check 4160v Vital buses 2A3 AND 2A4 energized from offsite power.

ANY G. Start SW pumps as needed to maintain SW header pressure.

ANY H. Check SW to CCW restored.

ANY I. Check ACW restored. (ACW is not restored, perform contingency)

BOP I. Restore SW to ACW, refer to 2202.010 Exhibit 5, CCW/ACW/SW Alignment.

ANY J. Maintain SW header pressure greater than 85 psig.

ANY 6. Notify Chemistry to sample BOTH SGs for activity.

ANY 7. Verify SG Sample valves open.

Revision 1 Page 21 of 26

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 5, &6 Event

Description:

A Steam Generator MSIV 2CV-1010-1 fails closed. Then 2 minutes after trip an Excess Steam Demand outside containment commences. Control Element Assembly #38 remains fully withdrawn when the reactor trips. The VCT outlet will not close and 2P-39B will trip when the reactor trips.

Time Position Applicant's Actions or Behavior ANY 8. Check ALL available Hydrogen Analyzers in service, refer to 2104.044, Containment Hydrogen Control Operations - Exhibit 1, Hydrogen Analyzer Auto Start. (perform contingency)

ANY 8. Verify all available Hydrogen Analyzers in service within 70 minutes from start of event.

Record time from Entry Section step 2:

Time ______________

Examiner note: This step may not be performed due to70 minute allowance for start.

ANY 9. Open Functional Recovery Success Path Tracking page.

SRO 10. Notify Control Board Operators to perform the following:

A. Monitor floating steps.

B. Verify actuated ESFAS components using 2202.010 Exhibit 9, ESFAS Actuation.

ANY 11. Determine safety function status as follows:

A. Check Reactivity Control satisfied by EITHER of the following:

• Maximum of ONE CEA NOT fully inserted and Reactor power lowering.

• Reactor power less than 10-1% and stable or lowering.

Examiners note: Reactivity will be satisfied.

ANY B. Check Vital DC Auxiliaries satisfied:

1) At least ONE 125v Vital DC bus energized:

• 2D01-SPDS point E2D01

• 2D02-SPDS point E2D02

2) At least ONE 120v Vital AC bus energized:

• 2RS1 - SPDS point E2RS1 or E2RS1RS3

• 2RS2 - SPDS point E2RS2 or E2RS2RS4

• 2RS3 - SPDS point E2RS3 or E2RS1RS3 Revision 1 Page 22 of 26

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 5, &6 Event

Description:

A Steam Generator MSIV 2CV-1010-1 fails closed. Then 2 minutes after trip an Excess Steam Demand outside containment commences. Control Element Assembly #38 remains fully withdrawn when the reactor trips. The VCT outlet will not close and 2P-39B will trip when the reactor trips.

Time Position Applicant's Actions or Behavior

• 2RS4 - SPDS point E2RS4 or E2RS2RS4 ANY C. Check Vital AC Auxiliaries satisfied:

1) At least ONE 4160v Vital AC bus (2A3/2A4) energized.

ANY D. Check RCS Inventory Control satisfied:

1) CVCS maintaining PZR level 10 to 80% [40 to 70%] and level stable or trending to setpoint.

2) RCS MTS 30°F or greater.

3) RVLMS LVL 03 or higher elevation indicates WET.

ANY E. Check RCS Pressure Control satisfied:

1) RCS pressure maintained within P-T limits, refer to Attachment 1, P-T Limits.

ANY F. Check RCS and Core Heat Removal satisfied:

1) At least ONE intact SG available for Heat Removal by EITHER of the following:

• Level 10 to 90% [20 to 90%] with FW available.

• Level being restored with total FW flow of 485 gpm or greater.

2) IF ANY RCP operating, THEN RCS T less than 10°F and NOT rising.

3) IF ALL RCPs secured, THEN RCS T less than 50°F and NOT rising.

4) RCS TC less than 555°F and NOT rising.

5) RCS MTS 30°F or greater.

6) RVLMS LVL 01 indicates WET.

Revision 1 Page 23 of 26

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 5, &6 Event

Description:

A Steam Generator MSIV 2CV-1010-1 fails closed. Then 2 minutes after trip an Excess Steam Demand outside containment commences. Control Element Assembly #38 remains fully withdrawn when the reactor trips. The VCT outlet will not close and 2P-39B will trip when the reactor trips.

Time Position Applicant's Actions or Behavior ANY G. Check CNTMT Isolation satisfied:

1) CNTMT parameters normal:

a) "CNTMT RADIATION HI" annunciator (2K10-A6) clear.

b) NO unexplained rise in CNTMT radiation.

c) CNTMT pressure less than 18.3 psia.

2) "SEC SYS RADIATION HI" annunciator (2K11-A10) clear.

3) NO unexplained rise in Secondary Systems Radiation monitor trends:

• Main Steam lines

• SG Sample

• Condenser Off Gas ANY H. Check CNTMT Temperature and Pressure Control satisfied:

1) CNTMT pressure less than 16 psia.

2) CNTMT temperature less than 140°F.

ANY 12. Locally remove danger tags and close the following breakers.

2B51-E4 LTOP RELIEF ISOL 2CV-4730-1 2B51-K2 LTOP RELIEF ISOL 2CV-4741-1 ANY *13. Check ALL Safety Function acceptance criteria satisfied.

Revision 1 Page 24 of 26

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 5, &6 Event

Description:

A Steam Generator MSIV 2CV-1010-1 fails closed. Then 2 minutes after trip an Excess Steam Demand outside containment commences. Control Element Assembly #38 remains fully withdrawn when the reactor trips. The VCT outlet will not close and 2P-39B will trip when the reactor trips.

Time Position Applicant's Actions or Behavior SRO *13. Perform the following:

A. Determine appropriate success paths using Success Path Decision Trees.

B. Initiate success paths for ALL Safety Functions in the following order:

1) Jeopardized.

2) Challenged.

3) Satisfied.

C. IF higher priority Safety Function jeopardized AND lower priority safety function success path in progress, THEN GO TO appropriate success path for highest priority safety function in jeopardy.

D. WHEN success path implemented for EACH Safety Function, THEN RETURN TO Step 14 of Entry procedure.

Examiner Note: The SRO should complete the safety functions in order of hierarchy that are challenged first, and then the satisfied safety functions.

Examiner Note: The SRO may discuss Tech Spec 3.4.1.2 RCS loops and 3.4.9.1 RCS cooldown limits to due the excess steam demand event.

Termination criteria: When post-cooldown conditions have been stabilized and safety functions prioritized or at examiners discretion.

Revision 1 Page 25 of 26

Appendix D Scenario 2 Form ES-D-2 Op-Test No.: 1 Scenario No.: 2 Event No.: 7 Event

Description:

Green train Containment coolers fail to automatically or manually actuate.

Time Position Applicant's Actions or Behavior ANY Recognize the Green train Containment coolers failed to automatically actuate.

SRO Direct the CBOT to manually align the Green train Containment Coolers to the emergency mode using OP-2202.010 Standard Attachment, Exhibit 9

BOP Perform the following to align the Green train Containment Coolers to the emergency mode:

3.0 IF CCAS, THEN verify the following:

Red Train CNTMT Coolers in service.

Service Water aligned to Red Train CNTMT Coolers.

Red Train Bypass Dampers open.

Green Train CNTMT Coolers in service.

Service Water aligned to Green Train CNTMT Coolers.

Green Train Bypass Dampers open.

Examiner note: The SRO may discuss Tech Spec 3.3.2.1 ESFAS and 3.6.2.3 Containment Cooling due to the failure to automatically actuate.

Termination criteria: Green train Containment Coolers aligned IAW 2202.010 Exhibit 9 or at examiners discretion.

Revision 1 Page 26 of 26

Appendix D Scenario 3 Form ES-D-1 Facility: ANO-2 Scenario No.: 3 (Modified) Op-Test No.: 2009-1 Examiners: Operators:

Initial Conditions:

~60% MOL, Condenser outer waterboxes placed in service after tube plugging. All Engineered Safety Features systems are in standby. 2PCV-0231 jacked closed. RED Train Maintenance Week.

Turnover:

~60% power Condenser outer waterboxes placed in service after tube plugging. 260 EFPD. EOOS indicates Minimal Risk. 2PCV-0231 jacked closed, manually control seal steam pressure. RED Train Maintenance Week. The previous shift has completed steps 10.1.1 through 10.1.6 and section 10.2 of starting the second heater drain pump and B Heater drain pump needs to be placed in service. 2 Condensate pumps are running with Condensate recirculation valves in manual.

Commence power escalation using applicable 2104.002 step 9.1 through 9.11 are complete and steps 9.13 to 9.18 and 9.20 to 9.28 are not applicable or complete. Reactor engineering recommends a 12%

per hour rate.

Event Malf. No. Event Event No. Type* Description 1 (New) N (SRO) Power escalation following a forced outage.

R (ATC) 2 (New) N (BOP) Place the B Heater Drain pump in service.

N (SRO) 3 NIBLINEPWR I (BOP) B channel nuclear instrument fails high. Tech Spec for (Modified) I (SRO) SRO.

4 XRCCHBPCNT I (ATC) B Pressurizer control channel pressure fails high.

(New) I (SRO) 5 SGBTUBE M (ALL) B Steam Generator tube leakage ramps up to 275 gpm (Modified) over 25 minutes. Manual reactor trip criteria when greater than 44 gpm. Tech Spec for SRO 6 RPSRXMAN C (ATC) Failure of the reactor protection system to automatically RPSRXAUTO C (SRO) or manually trip the reactor.

(New) 7 OP5130 C (BOP) Generator output breakers fail to open automatically OP5134 (New) C (SRO) 8 CNDVACPPA C (BOP) 2C-5A Vacuum pump trip CND2C5B C (SRO) 2C-5B Vacuum pump fails to auto start.

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Total malfunctions. = 6, Malfunctions. after EOP entry = 2, Abnormal events = 2, Major transient = 1, EOPs with substantive actions =1, EOP Contingencies = 0, Critical tasks = 3.

Revision 1 Page 1 of 27

Appendix D Scenario 3 Form ES-D-1 Scenario #3 Objectives

1) Evaluate individual ability to perform a power escalation.

2) Evaluate individual ability to place the second heater drain pump in service.

3) Evaluate individual response to a failure of a Nuclear Instrumentation channel.

4) Evaluate individual response to a failure of a Pressurizer pressure control channel.

5) Evaluate individual response to a steam generator tube rupture.

6) Evaluate individual response to a failure of a RPS to manually or automatically trip the reactor.

7) Evaluate individual response to the generator output breakers failure to automatically open.

8) Evaluate individual ability to mitigate a steam generator tube rupture.

9) Evaluate individual response to a vacuum pump trip.

10) Evaluate individual response to a failure to the backup vacuum pump to auto start.

SCENARIO #3 NARRATIVE Simulator session begins with the plant at approximately 60% power and the Condenser outer waterboxes have been placed back in service after tube plugging. Gland seal regulator, 2PCV0231 is jacked closed. The previous shift has completed steps 10.1.1 through 10.1.6 of OP-2106.016 (Condensate and Feedwater operations) for placing the B Heater Drain pump in service.

When the crew has completed their control room walk down and brief, the ATC will commence a power escalation and the BOP will place the B Heater drain pump in service.

After the B Heater Drain pump is placed in service, the ATC has completed all required reactivity manipulations or cued by lead examiner, B nuclear instrumentation channel will fail high. This will result in a PPS channel trip and pre-trip, CPC sensor failure alarms and the NI linear and log power instruments on B channel failing to High. The SRO will enter the Nuclear Instrument Malfunction AOP, AOP 2203.026. The SRO will direct the BOP to bypass points 1, 2, 3, and 4 on B PPS. TS 3.3.1.1 and 3.3.3.5 will be entered due to the excore failure.

After the BOP has bypassed points 1, 2, 3, and 4 on B PPS or cued by lead examiner, the B channel Pressurizer (PZR) control channel will fail high. This will result in both main spray valves to automatically open and both proportional heater banks to go to minimum fire. Actual PZR pressure will drop and will result in an automatic reactor trip, if actions are not taken to mitigate the event. The SRO will enter Abnormal operating procedure OP 2203.028, PZR systems malfunctions.

The SRO will direct selecting the opposite control channel.

After the Crew has taken all actions of OP 2203.028 PZR systems malfunctions or cued by lead examiner, a primary to secondary leak will start. The SRO will enter the primary to secondary leakage AOP, OP 2203.038. ATC and BOP will perform RCS Leak rate determinations. The SRO will enter Tech Spec 3.4.6.2. The SRO will direct the NLOs to control secondary contamination using standard attachment 19 and direct the chemists to sample the SGs for activity. When the crew has determined that the primary to secondary leak is greater than 44 gpm, the ATC will trip the reactor.

Revision 1 Page 2 of 27

Appendix D Scenario 3 Form ES-D-1 SCENARIO #3 NARRATIVE (continued)

When the ATC attempts to manually trip the reactor RPS will not work and the SRO will direct the ATC to trip the reactor using the DSS system. The Crew will implement Standard Post Trip Actions (SPTA), OP 2202.001. During SPTAs the generator output breakers will fail to automatically open and require the BOP to manually open the breakers. The Crew should actuate safety injection (SIAS) and containment cooling actuation signal (CCAS) or verified that SIAS and CCAS automatically actuates. The Crew will lower Steam Dump master controller set point during SPTAs to aid in maintaining margin to saturation. The ATC will secure two Reactor coolant Pumps when RCS pressure goes below 1400 psia.

The SRO will diagnose a Steam Generator Tube Rupture event and enter OP 2202.004, Steam Generator Tube Rupture. The ATC will cool down the RCS to less than 535°F using the bypass valves to the condenser. The BOP will override SW to CCW and ACW. The BOP will isolate the B SG using standard attachment 10 when RCS Thot is less than 535°F.

After the EOP is entered, the RCS cooldown is started and at the lead examiners discretion, A vacuum pump will trip and B vacuum pump will NOT automatically start. The BOP will manually start B vacuum pump. If this vacuum pump is not started, the SDBCS bypass valves will close and the crew will have to steam the ruptured SG to atmosphere resulting in an off site radiological release.

Revision 1 Page 3 of 27

Appendix D Scenario 3 Form ES-D-1 Simulator Instructions for Scenario 3 Reset simulator to MOL ~60% power IC stead state.

Ensure that AACG is secured and annunciators clear.

Place MINIMAL RISK and RED Train Maintenance Week signs on 2C11.

Swing ESF equipment aligned to the RED train.

2PCV0231, Gland sealing steam pressure control valve failed closed.

T1, T2, T3, T4, set to false.

Event Malf. No. Value/ Event No. Ramp Description Time 1 No malfunctions inserted in event #1.

2 No malfunctions inserted in event #2.

3 NIBLINEPWR 200 B channel nuclear instrument fails high. Tech Spec for Trigger = T1, SRO.

4 XRCCHBPCNT 2500 / B Pressurizer control channel pressure fails high.

Trigger = T2, Ramp =

30 sec 5 SGBTUBE Value = B Steam Generator tube leakage ramps up to 275 gpm Trigger = T3 275gpm over 25 minutes. Manual reactor trip criteria when greater Ramp = than 44 gpm. Tech Spec for SRO 25 min.

6 RPSRXMAN TRUE Failure of the reactor protection system to automatically RPSRXAUTO or manually trip the reactor.

7 OP5130 NO_ Generator output breakers fail to open automatically OP5134 AUTO_

OPEN 8 CNDVACPPA True 2C-5A Vacuum pump trip CND2C5B 2C-5B Vacuum pump fails to auto start.

Trigger = T4 Revision 1 Page 4 of 27

Appendix D Scenario 3 Form ES-D-1 Simulator Operator CUEs At T=0 Power escalation following a forced outage.

At T=0 Place the B Heater Drain pump in service.

Cue: If contacted as the AO then report section 10.2 2P-8A/B Seal Water Pressure Controller Operation is complete.

Cue: If contacted as the AO then report pre-start check are satisfactory for the B Heater Drain Pump.

Cued by Trigger T1 B channel nuclear instrument fails high. Tech Spec for SRO.

lead examiner Cue: When contacted as the WWM, then report that I & C planner will begin planning work on nuclear instrument.

Cued by Trigger T2 B Pressurizer control channel pressure fails high.

lead examiner Cue: When contacted as the WWM, then report that I & C planner will begin planning work on failed pressure instrument.

Cued by Trigger T3 B Steam Generator tube leakage ramps up to 275 gpm over 25 lead minutes. Manual reactor trip criteria when greater than 44 gpm. Tech examiner Spec for SRO Cue: If contacted as the AO then report after 5 min that the local portions of Attachment 10 for B S/G are complete.

Cue: If contacted as the AO then report you are commencing Attachment 19 control of secondary contamination.

Failure of the reactor protection system to automatically or manually trip the reactor.

Generator output breakers fail to open automatically.

Triggered Trigger T4 2C-5A Vacuum pump trip during 2C-5B Vacuum pump fails to auto start.

SGTR brief.

If the brief is delayed then triggered 10 min after entering SGTR procedure.

Cue: If contacted as the AO then report that B vacuum pump is running satisfactory and A vacuum pump is secured.

Revision 1 Page 5 of 27

Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2009-1 Scenario No.: 3 Event No.: 1 Event

Description:

Plant power escalation from 60%.

Time Position Applicant's Actions or Behavior T=0 ALL Crew will conduct brief for power increase.

SRO Direct applicable actions of OP, 2102.004 Power Operations.

ATC 9.12 IF NOT specified otherwise by Reactor Engineering, THEN commence raising power using Attachment A of this procedure for ASI Control and power escalation limits:

Commence RCS dilution. [Refer to Chemical Addition (2104.003)]

Raise turbine load as necessary to maintain Tref within +/-

2°F of program Tave using Exhibit 1, TAVE VS TREF.

ANY Direct a NLO to perform the following:

• 9.19 Perform the following:

Monitor secondary chemistry during power escalation Adjust chemical feed as necessary using Secondary System Chemical Addition (2106.028).

BOP 9.29 WHEN ~ 50-55% power, THEN start second Heater Drain pump (2P-8A/B) using Condensate and Feedwater Operations (2106.016).

Termination criteria: When reactivity manipulations are satisfied or at the discretion of the lead examiner.

Revision 1 Page 6 of 27

Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2009-1 Scenario No.: 3 Event No.: 2 Event

Description:

Place the B Heater Drain pump in service starting at step 10.1.7.

Time Position Applicant's Actions or Behavior BOP 10.1.7 Verify associated Alarms clear for pump to be started:

2T-40A Low Pressure alarm (2K03-F1) 2T-40A Low Level alarm (2K03-E1) 2T-40B Low Pressure alarm (2K03-F2) 2T-40B Low Level alarm (2K03-E2)

BOP Note:

For cross-tied 2T-40 Tank operation, Recirc controllers are set up in lead/lag style of operation with Lead Recirc controller ~ 15% greater than lag. The Dump controllers can be set up this way if desired.

Normal Heater Drain Pump Recirc Controller set points are 85% on the Lead controller and 70% on the Lag controller.

10.1.8 Place the following valve controllers in desired position (auto or manual - refer to Attachment J) for Heater Drain Tank Level control:

2T-40A Recirc 2CV-0725 Level controller (2LIC-0812) 2T-40B Recirc 2CV-0719 Level controller (2LIC-0826) 2T-40A Hi Level Dump to 2E-11B controller (2LIC-0813) 2T-40B Hi Level Dump to 2E-11B controller (2LIC-0825)

ANY 10.1.9 Verify 2P-8A/B Seal Water pressure control established per Step 10.2.

Cue: If contacted as the AO then report section 10.2 2P-8A/B Seal Water Pressure Controller Operation is complete.

BOP 10.1.10 Verify Heater Drain Tank level 4 ft (~ 94% on Recirc Indicator) for selected pump to start.

ANY 10.1.11 IF pump casing warming performed, THEN verify Step 10.1.4 complete.

Cue: If contacted as the AO then report pre-start check are satisfactory for the B Heater Drain Pump.

BOP 10.1.12 Start selected Heater Drain pump (2P-8A/B).

BOP 10.1.13 Monitor 2T-40 levels on Recirc and HLD controllers.

Revision 1 Page 7 of 27

Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2009-1 Scenario No.: 3 Event No.: 2 Event

Description:

Place the B Heater Drain pump in service starting at step 10.1.7.

Time Position Applicant's Actions or Behavior BOP 10.1.14 Verify the following valves adjust as required to maintain Heater Drain Tank level:

2T-40A Hi Level Dump to 2E-11B (2CV-0813) 2T-40B Hi Level Dump to 2E-11B (2CV-0825) 2T-40A Recirc (2CV-0725) 2T-40B Recirc (2CV-0719)

Termination Criteria: When B Heater Drain pump is in service or at lead examiner's discretion.

Revision 1 Page 8 of 27

Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2009-1 Scenario No.: 3 Event No.: 3 Event

Description:

B channel nuclear instrument fails High. Tech Spec for SRO.

Time Position Applicant's Actions or Behavior Cued by ANY Announce annunciators:

lead 2K04-A5 CH B RPS/ESF/PRETRIP/TRIP examiner 2K04-B3 PPS Channel TRIP 2K04 H4 CPC channel sensor failure ANY Crew will recognize that B excore has failed High.

SRO Enter and Implement AOP 2203.026, NI malfunction .

ANY 1. Check at least TWO Linear Safety channels operable.

ANY 2. Check ALL Linear Safety channels operable. (Channel B will not be operable)

SRO 2. IF ALL Linear Safety channels NOT operable, THEN perform the following:

A. Refer to TS 3.3.1.1, Reactor Protective Instrumentation.

Examiner note: SRO must enter Tech Spec 3.3.1.1 action 2 BOP C. IF ONLY ONE channel failed, THEN verify the following trip functions bypassed:

Hi Linear Power {1}

High LPD {3}

Low DNBR {4}

SRO D. GO TO Step 4.

ANY 4. Check ALL Log Power channels operable. (Channel B will not be operable)

SRO 4. IF ALL Log Power channels NOT operable, THEN perform the following:

A. IF Log Power channel #2 failed, THEN refer to TS 3.3.3.5, Remote Shutdown Instrumentation.

B. Refer to TS 3.3.1.1, Reactor Protective Instrumentation.

Examiner note: SRO must enter Tech Spec 3.3.3.5 Revision 1 Page 9 of 27

Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2009-1 Scenario No.: 3 Event No.: 3 Event

Description:

B channel nuclear instrument fails High. Tech Spec for SRO.

Time Position Applicant's Actions or Behavior BOP D. IF ONLY ONE Log Power channel failed, AND associated Linear Safety channel failed, THEN verify the following trip functions bypassed:

Hi Linear Power {1}

Hi Log Power {2}

High LPD {3}

Low DNBR {4}

SRO 8. Notify I&C of Nuclear Instrument malfunctions.

Cue: When contacted as the WWM, then report that I & C planner will begin planning work on nuclear instrument.

Termination criteria: When points 1, 2, 3 and 4 are bypassed on B PPS or at the discretion of the lead examiner.

Revision 1 Page 10 of 27

Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2009-1 Scenario No.: 3 Event No.: 4 Event

Description:

Pressurizer control channel pressure fails high.

Time Position Applicant's Actions or Behavior Cued by ANY Announce annunciator 2K10-E7 Pressurizer Pressure Control Channel 2 lead Pressure HI / LO alarm is due to High pressure.

examiner ANY Determine that B control channel pressure has failed high and RCS pressure is actually lowering.

SRO Direct the ATC to place A Pressurizer pressure control channel in service.

SRO Enter and implement PZR Systems Malfunctions AOP 2203.028.

SRO 5. Check "CNTRL CH 1/2 PRESSURE HI/LO" annunciators (2K10-E6/E7) clear. (Annunciator is not clear, implement contingency)

ANY 5. Perform the following:

A. Compare PZR pressure instruments to determine affected channel.

ATC C. IF only the selected control channel affected, THEN perform the following:

1) Place PZR Pressure Channel Select switch (2HS-4626) to the unaffected channel.

2) Restore PZR Spray valves and Heater control to automatic.

ANY E. IF PZR Pressure Control Channel 2 failed, THEN perform the following:

1) Verify a maximum of ONE SDBCS 111/2% Bypass OR Downstream ADV Permissive switch in MANUAL:

• 2CV-0302

• 2CV-0306

• 2CV-0301

• 2CV-0305

2) Verify ALL other SDBCS Bypass and ADV Permissive switches in OFF.

SRO Exit PZR Systems Malfunctions AOP 2203.028.

Termination Criteria: PZR pressure control selected to channel A or at lead examiner's discretion.

Revision 1 Page 11 of 27

Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2009-1 Scenario No.: 3 Event No.: 5, 6, & 7 Event

Description:

B Steam Generator tube leakage ramps up to 275 gpm over 25 minutes. Manual reactor trip criteria when greater than 44 gpm. Tech Spec for SRO. Also failure of the reactor protection system to automatically or manually trip the reactor and Generator output breakers failure to open automatically.

Time Position Applicant's Actions or Behavior Cued by ANY Announce alarm SEC SYS RADIATION HI.

lead examiner SRO Enter and Implement AOP 2203.038, Primary to Secondary leakage.

ANY *2. Check PZR level stable or rising. (Not met, perform contingency)

ANY *2. Perform the following:

A. Start and stop Charging pumps as necessary to maintain level.

ANY *3. Check PZR level maintained within 10% of set point.

ANY 4. Notify Chemistry to sample Secondary system for activity using 1604.013, Measurement of Primary to Secondary Leak Rate.

ANY Direct NLO to perform the following:

5. Minimize secondary contamination using 2202.010 Attachment 19, Control of Secondary Contamination.

ANY 7. Determine Primary to Secondary leakrate by ANY of the following:

Computer RCS LKRT programs.

Check PZR level stable and use Charging and Letdown mismatch minus Controlled Bleed Off.

Check Letdown isolated and estimate RCS leak rate by total Charging flow minus Controlled Bleed Off.

Chemistry leakrate calculation using 1604.013, Measurement of Primary to Secondary Leakage.

SG Tube Leak N-16 monitors.

Manual leakrate calculation.

Revision 1 Page 12 of 27

Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2009-1 Scenario No.: 3 Event No.: 5, 6, & 7 Event

Description:

B Steam Generator tube leakage ramps up to 275 gpm over 25 minutes. Manual reactor trip criteria when greater than 44 gpm. Tech Spec for SRO. Also failure of the reactor protection system to automatically or manually trip the reactor and Generator output breakers failure to open automatically.

Time Position Applicant's Actions or Behavior SRO *8. Refer to TS 3.4.6.2, Reactor Coolant System Leakage.

Examiner note: SRO must enter Tech Spec 3.4.6.2 due to primary to secondary leakage.

ANY 10. Determine leaking SG by ANY of the following:

A. Secondary Systems Radiation Trend recorder:

2RR-1057 B. SG Sample Radiation monitors:

2RITS-5854 2RITS-5864 C. Main Steam Line Radiation monitors:

2RI-1007 2RI-1057 D. SG water sample results.

E. SG Tube Leak N-16 monitors.

ANY 11. Check SG Blowdown aligned to SU/BD DI.

SRO When the Leakrate is determined to be greater than 44 gpm the SRO will direct the Reactor trip.

12. IF RCS leakage greater than 44 gpm AND in Mode 1 OR 2, THEN perform the following:

A. Trip Reactor.

B. GO TO 2202.001, Standard Post Trip Actions.

ATC Recognize a failure of manual RPS trip.

CRITICAL ATC Trip the Reactor using the DSS pushbutton.

STEP Examiner note: DSS trip must be completed within 1 minutes of recognition of RPS failure.

SRO Enter and implement EOP 2202.001, Standard Post Trip Actions.

Revision 1 Page 13 of 27

Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2009-1 Scenario No.: 3 Event No.: 5, 6, & 7 Event

Description:

B Steam Generator tube leakage ramps up to 275 gpm over 25 minutes. Manual reactor trip criteria when greater than 44 gpm. Tech Spec for SRO. Also failure of the reactor protection system to automatically or manually trip the reactor and Generator output breakers failure to open automatically.

Time Position Applicant's Actions or Behavior SRO 1. Notify Control Board Operators to monitor safety functions using Exhibit 7, CBO Reactor Trip Checklist.

2. Open Safety Function Tracking page.

ATC 3. Check Reactivity Control established as follows:

A. Reactor power lowering.

B. ALL CEAs fully inserted.

BOP Manually align Gland Seal Steam using 2CV-0233.

BOP 4. Check Maintenance of Vital Auxiliaries satisfied:

A. Main Turbine tripped.

B. Generator Output breakers open. (Not met due to event #7, Perform contingency)

C. Exciter Field breaker open.

D. At least ONE 6900v AC bus energized.

E. At least ONE 4160v Non-vital AC bus energized.

F. BOTH 4160v Vital AC buses energized.

G. BOTH DGs secured. (May be running if SIAS is actuated, contingency is to verify service water outlet valve is open and the will both be open)

H. At least ONE 125v Vital DC bus energized:

2D01 - SPDS point E2D01 2D02 - SPDS point E2D02 BOP B. Open Generator Output breakers:

5130 5134 BOP Complete Post Trip contingencies to align gland seal steam.

Revision 1 Page 14 of 27

Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2009-1 Scenario No.: 3 Event No.: 5, 6, & 7 Event

Description:

B Steam Generator tube leakage ramps up to 275 gpm over 25 minutes. Manual reactor trip criteria when greater than 44 gpm. Tech Spec for SRO. Also failure of the reactor protection system to automatically or manually trip the reactor and Generator output breakers failure to open automatically.

Time Position Applicant's Actions or Behavior ATC 5. Check RCS Inventory Control established as follows:

A. PZR level:

10 to 80%.

Trending to set point. (Not met due to SGTR Event #5, perform contingency)

B. RCS MTS 30°F or greater.

SRO Direct the following as necessary:

A. Perform as necessary:

1) IF SIAS actuated on PPS inserts, THEN GO TO Step 6.

2) Verify PZR Level Control system restoring level to set point.

ATC 6. Check RCS Pressure Control:

• 1800 to 2250 psia.

• Trending to set point. (Not met due to SGTR Event #5, perform contingency)

Revision 1 Page 15 of 27

Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2009-1 Scenario No.: 3 Event No.: 5, 6, & 7 Event

Description:

B Steam Generator tube leakage ramps up to 275 gpm over 25 minutes. Manual reactor trip criteria when greater than 44 gpm. Tech Spec for SRO. Also failure of the reactor protection system to automatically or manually trip the reactor and Generator output breakers failure to open automatically.

Time Position Applicant's Actions or Behavior SRO Examiners Note: This may or may not be performed depending on the PZR level trend at the time this safety function is assessed.

Direct the following actions as necessary:

6. Perform as necessary:

A. IF RCS pressure lowers to less than 1400 psia, THEN trip ONE RCP in EACH loop.

B. IF NPSH requirements violated OR RCS MTS less than 30°F, THEN verify ALL RCPs tripped.

D. IF RCP 2P32A or 2P32B stopped, THEN verify associated PZR Spray valve in MANUAL and closed.

E. IF RCS pressure lowers to 1650 psia or less, THEN perform the following:

1) Verify SIAS actuated on PPS inserts.

2) GO TO Step 7.

F. Verify PZR Pressure Control system restoring pressure to set point.

G. IF ALL RCPs stopped AND RCS pressure greater than 2250 psia, THEN initiate Aux spray using Attachment 27, PZR Spray Operation.

ATC 7. Check Core Heat Removal by forced circulation:

B. At least ONE RCP running.

B. CCW flow aligned to RCPs.

C. Loop delta T less than 10°F.

D. RCS MTS 30°F or greater.

E. Check SW aligned to CCW. (IF SIAS actuated will not be aligned and should perform contingency)

F. IF SIAS or MSIS actuated, THEN maintain SW header pressure greater than 85 psig.

Revision 1 Page 16 of 27

Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2009-1 Scenario No.: 3 Event No.: 5, 6, & 7 Event

Description:

B Steam Generator tube leakage ramps up to 275 gpm over 25 minutes. Manual reactor trip criteria when greater than 44 gpm. Tech Spec for SRO. Also failure of the reactor protection system to automatically or manually trip the reactor and Generator output breakers failure to open automatically.

Time Position Applicant's Actions or Behavior SRO If required Direct the contingency for step 7. E BOP E. IF CCW available, THEN restore SW to CCW, refer to 2202.010 Exhibit 5, CCW/ACW/SW Alignment.

ANY 8. Check RCS Heat Removal:

A. Check SG available by BOTH of the following:

• At least ONE SG level 10 to 90%.

• FW maintaining SG level B. Check MFW in RTO.

C. Check Feedwater line intact by the following:

• SG level stable or rising.

• NO unexplained step changes or erratic FW flow.

• NO unexplained step changes or erratic Condensate flow.

D. Check Condensate Pump discharge header pressure < 753 psig.

(May not be met if manual actions have not already been taken)

E. Check SG pressure 950 to 1050 psia.

F. Check RCS TC 540 to 555°F.

Revision 1 Page 17 of 27

Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2009-1 Scenario No.: 3 Event No.: 5, 6, & 7 Event

Description:

B Steam Generator tube leakage ramps up to 275 gpm over 25 minutes. Manual reactor trip criteria when greater than 44 gpm. Tech Spec for SRO. Also failure of the reactor protection system to automatically or manually trip the reactor and Generator output breakers failure to open automatically.

Time Position Applicant's Actions or Behavior ANY Perform step 8 contingency actions that are applicable:

D. Perform EITHER of the following:

1) Throttle Condensate Pump Recirc Valves to maintain pressure:

2FIC-0662 for 2CV-0662 2FIC-0663 for 2CV-0663

2) Depress R/L button on tripped MFP Recirc Valve Controller:

2FIC-0735 for 2P-1A 2FIC-0742 for 2P-1B Revision 1 Page 18 of 27

Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2009-1 Scenario No.: 3 Event No.: 5, 6, & 7 Event

Description:

B Steam Generator tube leakage ramps up to 275 gpm over 25 minutes. Manual reactor trip criteria when greater than 44 gpm. Tech Spec for SRO. Also failure of the reactor protection system to automatically or manually trip the reactor and Generator output breakers failure to open automatically.

Time Position Applicant's Actions or Behavior ANY 9. Check CNTMT parameters:

A. Temperature and Pressure:

• Temperature less than 140°F.

• Pressure less than 16 psia.

B. Check CNTMT Spray pumps secured.

C. NO CNTMT radiation alarms or unexplained rise in activity:

1) CAMS alarms:

• "CNTMT PART/GAS RAD HI/LO" annunciator (2K10-B6) clear.

2) RCS leakage alarms:

• "AREA RADIATION HI/LO" annunciator (2K11-B10) clear.

• "PROC LIQUID RADIATION HI/LO" annunciator (2K11-C10) clear.

3) Check the following radiation monitors trend stable:

• CNTMT Area

• CAMS

• Process Liquid D. NO secondary system radiation alarms or unexplained rise in activity: (Not met due to SGTR Event #5)

1) "SEC SYS RADIATION HI" annunciator (2K11-A10) clear.

2) Secondary Systems Radiation monitors trend stable:

• Main Steam lines

• SG Sample

• Condenser Off Gas Revision 1 Page 19 of 27

Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2009-1 Scenario No.: 3 Event No.: 5, 6, & 7 Event

Description:

B Steam Generator tube leakage ramps up to 275 gpm over 25 minutes. Manual reactor trip criteria when greater than 44 gpm. Tech Spec for SRO. Also failure of the reactor protection system to automatically or manually trip the reactor and Generator output breakers failure to open automatically.

Time Position Applicant's Actions or Behavior SRO 10. Notify STA to report to control room.

11. Verify NLOs informed of Reactor trip.

12. Verify Reactor trip announced on Plant page.

13. Notify SM to refer to Technical Specifications and 1903.010, Emergency Action Level Classification.

SRO 14. Direct control board operators to acknowledge ALL annunciators and announce ALL significant alarms.

SRO 15. Check ALL safety function acceptance criteria satisfied. (All safety functions are not satisfied, perform contingency)

15. IF ANY safety function acceptance criteria NOT satisfied, THEN perform the following:

A. Notify control room staff of safety functions NOT satisfied.

B. GO TO Exhibit 8, Diagnostic Actions.

SRO Diagnose Steam Generator Tube Rupture EOP 2202.004.

SRO Enter and implement Steam Generator Tube Rupture EOP 2202.004.

SRO

• 1. Confirm diagnosis of SGTR:

A. Check SFSC acceptance criteria satisfied every 15 minutes.

B. Refer to 2202.010 Attachment 20, Break Identification Chart.

C. Verify SG Sample valves open.

D. Notify Chemistry to perform BOTH of the following:

• Sample BOTH SGs for activity.

• Monitor RDACS for off site dose releases.

SRO

• 2. Notify SM to refer to Technical Specifications and 1903.010, Emergency Action Level Classification.

ANY 4. Verify SIAS and CCAS actuated on PPS inserts.

Revision 1 Page 20 of 27

Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2009-1 Scenario No.: 3 Event No.: 5, 6, & 7 Event

Description:

B Steam Generator tube leakage ramps up to 275 gpm over 25 minutes. Manual reactor trip criteria when greater than 44 gpm. Tech Spec for SRO. Also failure of the reactor protection system to automatically or manually trip the reactor and Generator output breakers failure to open automatically.

Time Position Applicant's Actions or Behavior SRO 5. Notify Control Board Operators to perform the following:

A. Monitor floating steps.

B. Verify actuated ESFAS components using 2202.010, Exhibit 9, ESFAS Actuation.

ANY *6. Check CCW aligned to RCPs.

SRO May elect to pull up the floating step for commencing a cooldown. Step

11. It is possible that the SRO will implement step 11 at the same time he implements step 7.

ATC 11. Commence RCS cooldown to less than 535°F TH as follows:

A. Reset Low SG Pressure set points during cooldown and depressurization.

B. Commence RCS depressurization to maintain RCS MTS 30 to 45°F.

C. Monitor cooldown rate as follows:

• Record RCS TC and PZR temperature using Attachment 8, RCS Cooldown Table.

• Plot RCS pressure versus RCS TC using 2202.010 Attachment 1, P-T Limits every 15 minutes.

D. IF ANY RCPs running, THEN initiate RCS cooldown using EITHER of the following:

1) SDBCS Bypass valves (condenser available) - most preferred.

2) SDBCS ADV from intact SG to atmosphere - least preferred.

IF necessary, THEN supplement with SDBCS ADV from ruptured SG to atmosphere as needed.

ANY F. IF SDBCS Bypass valves available for RCS cooldown, THEN place ALL ADV Permissive switches in OFF.

Revision 1 Page 21 of 27

Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2009-1 Scenario No.: 3 Event No.: 5, 6, & 7 Event

Description:

B Steam Generator tube leakage ramps up to 275 gpm over 25 minutes. Manual reactor trip criteria when greater than 44 gpm. Tech Spec for SRO. Also failure of the reactor protection system to automatically or manually trip the reactor and Generator output breakers failure to open automatically.

Time Position Applicant's Actions or Behavior BOP G. Verify EFW or AFW capable of feeding SGs.

ANY H. Secure running MFW pump.

BOP I. Close ALL MFW Block valves.

ANY 7. Restore ESF/Non-ESF systems post-SIAS as follows:

A. Verify at least ONE SW pump running on EACH loop.

ANY B. Verify DG SW Outlet valves open.

ANY C. Verify SW pump suction aligned to Lake.

ANY D. Check 4160v Non-vital bus 2A1 or 2A2 energized from offsite power.

ANY E. Check 4160v Vital buses 2A3 AND 2A4 energized from offsite power.

BOP F. Start SW pumps as needed to maintain SW header pressure.

ANY G. Check SW to CCW restored.

ANY H. Check ACW restored. (Not met, perform contingency)

BOP H. Restore SW to ACW, refer to 2202.010 Exhibit 5, CCW/ACW/SW Alignment.

BOP I. Maintain SW header pressure greater than 85 psig.

ANY *8. Verify Safety Injection flow to RCS as follows:

A. Check total HPSI flow acceptable using 2202.010 Exhibit 2, HPSI Flow Curve.

B. Check total LPSI flow acceptable using 2202.010 Exhibit 3, LPSI Flow Curve.

ANY 9. Check RCS pressure greater than 1400 psia. (Not met, perform contingency)

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Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2009-1 Scenario No.: 3 Event No.: 5, 6, & 7 Event

Description:

B Steam Generator tube leakage ramps up to 275 gpm over 25 minutes. Manual reactor trip criteria when greater than 44 gpm. Tech Spec for SRO. Also failure of the reactor protection system to automatically or manually trip the reactor and Generator output breakers failure to open automatically.

Time Position Applicant's Actions or Behavior ANY 9. Perform the following:

A. IF RCS pressure less than 1400 psia, THEN perform the following:

1) Verify maximum of ONE RCP running in EACH loop.

2) IF RCP 2P32A or 2P32B stopped, THEN verify associated PZR Spray valve in MANUAL and closed.

B. IF NPSH requirements violated OR RCS MTS less than 30°F, THEN perform the following:

1) Stop ALL RCPs.

3) Verify BOTH PZR Spray valves in MANUAL and closed.

ANY 10. Check IA pressure greater than 65 psig.

ANY *12. Minimize primary to secondary break flow as follows:

A. Check ANY RCP running.

B. Maintain RCS pressure within the following criteria:

• Within 100 psia above minimum RCP NPSH requirement, refer to 2202.010 Attachment 1, P-T Limits.

• Less than 1000 psia as conditions allow.

• Within 50 psi of ruptured SG pressure as RCP NPSH requirements allow.

Examiners note: The criteria to minimize break flow can not be established until HPSI is overridden. Then the crew should establish these limits.

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Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2009-1 Scenario No.: 3 Event No.: 5, 6, & 7 Event

Description:

B Steam Generator tube leakage ramps up to 275 gpm over 25 minutes. Manual reactor trip criteria when greater than 44 gpm. Tech Spec for SRO. Also failure of the reactor protection system to automatically or manually trip the reactor and Generator output breakers failure to open automatically.

Time Position Applicant's Actions or Behavior ANY C. Use EITHER of the following to depressurize RCS:

1) 2202.010 Attachment 27, PZR Spray Operation.

2) IF HPSI termination criteria met, THEN cycle Charging pumps or throttle HPSI flow to lower PZR pressure.

ANY D. IF RCS pressure less than ruptured SG pressure, THEN sample RCS Boron concentration every 30 minutes.

ANY 13. Determine ruptured SG by comparing ANY of the following:

A. Secondary Systems Radiation Trend recorder (2RR-1057).

B. Main Steam Line Radiation Monitors:

• 2RI-1007

• 2RI-1057 C. SG Sample Radiation Monitors:

• 2RITS-5854

• 2RITS-5864 D. SG Tube Leak N-16 monitor history trends.

E. SG levels.

1) Level rising faster in ONE SG with similar FW flow rates and steaming rates in BOTH SGs.

2) Rising SG level with ALL FW isolated.

F. Steam flow and FW flow prior to Reactor trip.

G. SG water sample results.

H.

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Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2009-1 Scenario No.: 3 Event No.: 5, 6, & 7 Event

Description:

B Steam Generator tube leakage ramps up to 275 gpm over 25 minutes. Manual reactor trip criteria when greater than 44 gpm. Tech Spec for SRO. Also failure of the reactor protection system to automatically or manually trip the reactor and Generator output breakers failure to open automatically.

Time Position Applicant's Actions or Behavior ANY Direct the NLOs to perform the following:

14. Minimize secondary contamination by performing BOTH of the following:

A. Commence isolation of ruptured SG by performing local actions ONLY of 2202.010 Attachment 10, SG Isolation.

B. 2202.010 Attachment 19, Control of Secondary Contamination.

Cue: If contacted as the AO then report after 5 min that the local portions of Attachment 10 for B S/G are complete.

Cue: If contacted as the AO then report you are commencing Attachment 19 control of secondary contamination.

ANY 15. Isolate ruptured SG Steam Supply to EFW pump 2P7A as follows:

ANY A. Verify EFW pump 2P7B running.

B. IF 2P7B NOT running, THEN verify AFW pump 2P75 running.

C. Stop EFW pump 2P7A:

1) Override and close Steam Supply to 2P7A valve (2CV-0340-2).

2) Close Main Steam Supply valve from ruptured SG to EFW pump 2P7A:

• "SG A TO EMER FW PMP TURB" 2CV-1000-1

• "SG B TO EMER FW PMP TURB" 2CV-1050-2 Examiners note: SRO must enter Tech Spec 3.7.1.2 for Emergency Feedwater.

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Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 2009-1 Scenario No.: 3 Event No.: 5, 6, & 7 Event

Description:

B Steam Generator tube leakage ramps up to 275 gpm over 25 minutes. Manual reactor trip criteria when greater than 44 gpm. Tech Spec for SRO. Also failure of the reactor protection system to automatically or manually trip the reactor and Generator output breakers failure to open automatically.

Time Position Applicant's Actions or Behavior CRITICAL ALL 18. Isolate ruptured SG as follows:

STEP A. Monitor RCS TH during cooldown with ANY of the following:

• PMS point T4614

• PMS point T4714

• SPDS display B. WHEN RCS TH less than 535°F, THEN isolate ruptured SG using 2202.010 Attachment 10, SG Isolation.

C. Maintain ruptured SG less than 1050 psia with ONE of the following:

• MSIV Bypass valve

• Upstream ADV Examiner note: 2202.010 Attachment 10 must be complete within 30 minutes of entering the EOP.

Examiners note: SRO may enter Tech Spec 3.4.5 for Steam generator integrity.

Termination criteria: RCS Cool down to less than 535°F Th and A SG isolated or at the discretion of the lead examiner.

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Appendix D Scenario 3 Form ES-D-2 Op-Test No.: 1 Scenario No.: 3 Event No.: 8 Event

Description:

2C-5A Vacuum pump trip and 2C-5B Vacuum pump fails to auto start..

Time Position Applicant's Actions or Behavior Triggered ANY Announce alarm VACUUM PUMP 2C5A TRIP during SGTR brief.

If the brief is delayed then triggered 10 min after entering SGTR procedure.

SRO Enter and implement ACA 2203.012C, Annunciator 2K03 corrective action.

BOP 2.1 Verify Vacuum Pump (2C-5B) running properly per Condenser Vacuum System (2106.010)

CRITICAL BOP Start the B vacuum pump and dispatch a NLO to verify it is running STEP properly.

Start the B Vacuum pump prior to a condenser interlock which would require steaming to atmosphere.

Cue: If contacted as the AO then report that B vacuum pump is running satisfactory and A vacuum pump is secured.

Termination criteria: When B Vacuum pump has been started or at examiners discretion.

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