ML022660536

Init Exam - 09/2002 - as Run Operating Examiantion

ML022660536
Person / Time
Site:	Fort Calhoun
Issue date:	03/07/2002
From:	Koske J Omaha Public Power District
To:	Office of Nuclear Reactor Regulation
References
50-285/02-301 50-285/02-301
Download: ML022660536 (159)

Text

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: ADM RO A.1.a JPM

Title:

Estimated Critical Condition Page 1 of 5 Approximate Time:

15 minutes Actual Time: _________________

Reference(s):

Fort Calhoun Technical Data Book K/A 2.1.25 (RO 2.8)

JPM Prepared by:

Jerry Koske Date:

JPM Reviewed by:

Date:

JPM Approved by:

Date:

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: ADM RO A.1.a JPM

Title:

Estimated Critical Condition Page 2 of 5 Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment:

TDB, Calculator Safety Considerations:

None Comments:

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: ADM RO A.1.a JPM

Title:

Estimated Critical Condition Page 3 of 5 INITIATING CUE:

The plant has been shutdown as the result of a reactor trip and is planning a reactor startup at 1400 on 9/9/02.

You are directed to determine the estimated critical boron concentration for this startup.

The following information has been provided:

• Shutdown from 100% power occurred at 2300 on 9/8/02

• Plant was operating with all rods out prior to the trip

• Boron concentration prior to the trip was 610 ppm

• Average core burnup is 4500 MWD/MTU

• Criticality should occur with group 4 at 85 inches

• Boron concentration has not been changed since the trip

• DEN-Nuclear states that no correction is needed for boron depletion Critical Steps shown in gray STEP ELEMENT STANDARD 1

Obtains TDB-V.1.B, Estimated Critical Conditions Worksheet from the Technical Data Book.

Locates TDB-V.1.B NOTE: Provide procedure copy after it is located in TDB.

2 Completes worksheet through step D.3.d.

See attached completed worksheet 3

Determines critical boron concentration.

Critical boron concentration is determined to be 686 ppm +/- 20 ppm CUE: Stop after step D.3.D is completed.

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: ADM RO A.1.a JPM

Title:

Estimated Critical Condition Page 4 of 5 Termination Criteria:

Critical boron concentration has been determined

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: ADM RO A.1.a Page 5 of 5 INITIATING CUE:

The plant has been shutdown as the result of a reactor trip and is planning a reactor startup at 1400 on 9/9/02.

You are directed to determine the estimated critical boron concentration for this startup.

The following information has been provided:

• Shutdown from 100% power occurred at 2300 on 9/8/02

• Plant was operating with all rods out prior to the trip

• Boron concentration prior to the trip was 610 ppm

• Average core burnup is 4500 MWD/MTU

• Criticality should occur with group 4 at 85 inches

• Boron concentration has not been changed since the trip

• DEN-Nuclear states that no correction is needed for boron depletion

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: RO ADM JPM A.1.b JPM

Title:

Determine Operational Mode Page 1 of 4 Approximate Time:

10 minutes Actual Time: _________________

Reference(s):

Fort Calhoun Tech Specs COLR K/A 2.1.22 (RO 2.8)

JPM Prepared by:

Jerry Koske Date:

JPM Reviewed by:

Date:

JPM Approved by:

Date:

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: RO ADM JPM A.1.b JPM

Title:

Determine Operational Mode Page 2 of 4 Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment:

None Safety Considerations:

None Comments:

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: RO ADM JPM A.1.b JPM

Title:

Determine Operational Mode Page 3 of 4 INITIATING CUE:

The following plant conditions exist:

RCS is intact and on shutdown cooling.

One shutdown cooling pump is in operation.

RCS temperature is 190F RCS pressure is 18 psia RCS boron concentration is 1975 PPM.

Burnup is 3800 MWD/MTU Determine the plants operational mode.

Critical Steps shown in gray STEP ELEMENT STANDARD 1

Refer to technical specifications For mode definitions Refers to Technical Specification Definitions section, page 2 and determines that the plant is either in mode 4 or 5 depending on the boron concentration.

2 Refer to COLR to determine shutdown boron concentration.

Refers to TDB-VI (COLR) Table 2 and determines that the required refueling boron concentration is 2023 ppm.

3 Determine plant operational mode The plant is in Mode 4, Cold Shutdown Condition.

Termination Criteria:

Operational mode has been determined

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: RO ADM JPM A.1.b Page 4 of 4 INITIATING CUE:

The following plant conditions exist:

RCS is intact and on shutdown cooling.

One shutdown cooling pump is in operation.

RCS temperature is 190F RCS pressure is 18 psia RCS boron concentration is 1975 PPM.

Burnup is 3800 MWD/MTU Determine the plants operational mode.

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: RO ADM JPM A.2 JPM

Title:

Time to boil determination Page 1 of 4 Approximate Time:

10 minutes Actual Time: _________________

Reference(s):

AOP-19 K/A 2.1.24 (RO 2.6)

JPM Prepared by:

Jerry Koske Date:

JPM Reviewed by:

Date:

JPM Approved by:

Date:

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: RO ADM JPM A.2 JPM

Title:

Time to boil determination Page 2 of 4 Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment:

AOP-19 Safety Considerations:

None Comments:

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: RO ADM JPM A.2 JPM

Title:

Time to boil determination Page 3 of 4 INITIATING CUE:

It is 0600 on 5/12/02. The Plant has shutdown for a refueling outage. The reactor was shutdown on 5/6/02 at 1800. The RCS level is at the vessel flange. The pressurizer manway is removed. RCS pressure is 15 psia and CET temperatures indicate 120°F. A loss of shutdown cooling has just occurred and the CRS has directed you to use AOP-19 to determine the time to boil and report the results to him.

Critical Steps shown in gray STEP ELEMENT STANDARD 1

Obtain copy of AOP-19 Obtains AOP-19 and goes to attachments B and C.

2 Record time shutdown cooling was lost and temperature.

Attachment B form. Enter 0600 and 120F in blanks 1 and 2.

3 Determine remaining time to boil Calculate that 5.5 days have elapsed since shutdown. Use graph on page 19 to interpolate time to boil.

4 Record time to boil on time to boil worksheet.

Determines that there are 39 minutes +/- 4 minutes to boil.

5 Report time to boil Communicate results of the time to boil determination to the CRS.

Termination Criteria:

Time to boil reported to the CRS

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: RO ADM JPM A.2 Page 4 of 4 INITIATING CUE:

It is 0600 on 5/12/02. The Plant has shutdown for a refueling outage. The reactor was shutdown on 5/6/02 at 1800. The RCS level is at the vessel flange. The pressurizer manway is removed. RCS pressure is 15 psia and CET temperatures indicate 120°F. A loss of shutdown cooling has just occurred and the CRS has directed you to use AOP-19 to determine the time to boil and report the results to him.

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: ADM RO A.3 JPM

Title:

RCA Entry and Exit with PCM Alarms Page 1 of 6 Approximate Time:

12 minutes Actual Time: _________________

Reference(s):

GET-Radiation Worker Training Standing Order G-101 K/A 2.3.1 (RO 2.6)

JPM Prepared by:

Jerry Koske Date:

JPM Reviewed by:

Date:

JPM Approved by:

Date:

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: ADM RO A.3 JPM

Title:

RCA Entry and Exit with PCM Alarms Page 2 of 6 Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment:

None Safety Considerations:

None Comments:

This JPM is conducted during RCA entry and exit for the RCA JPMs

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: ADM RO A.3 JPM

Title:

RCA Entry and Exit with PCM Alarms Page 3 of 6 INITIATING CUE:

A plant procedure that you are performing requires entry into the RCA.

Critical Steps shown in gray STEP ELEMENT STANDARD 1

Review the RWP RCA Access Control Reads RWP 2

Determine Radiological Conditions Checks survey maps or discusses radiological conditions with RP personnel.

3 Obtains Dosimetry Verify TLD attached to security badge. Obtain EAD.

4 Sign on to appropriate RWP.

Insert EAD in reader. Scan PID and RWP number.

5 Enter RCA RCA Entered 6

Performs procedure Performs RCA JPMs 7

Exits RCA Returns to RCA access point 8

Monitor for personnel contamination prior to exiting RCA Monitor for contamination using PCM-1.

CUE: After examinee has completed counting on a PCM-1, tell him to assume that the PCM-1 alarmed-zone 6

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: ADM RO A.3 JPM

Title:

RCA Entry and Exit with PCM Alarms Page 4 of 6 STEP ELEMENT STANDARD 9

Monitor for contamination a second time.

Monitor for contamination again using a different PCM-1.

CUE: After examinee has completed counting on another PCM-1, tell him to assume that this PCM-1 also alarmed-zone 6 10 Contact RP RP Contacted CUE: RP directs that you to monitor for contamination using frisker.

11 Uses Frisker to monitor for contamination.

Slowly moves pancake probe over hands, shoes and body surface.

CUE: Frisker cpm as read.

Termination Criteria:

RCA has been exited

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: ADM RO A.3 JPM

Title:

RCA Entry and Exit with PCM Alarms Page 5 of 6 NOTE to RP Tech As a part of this candidates NRC license exam, he must enter and exit the RCA.

During RCA exit, he has been given verbal Cues that he has received a zone 6 alarm on two separate PCM-1 monitors.

As a part of this JPM, we would like you to direct him to perform a whole body frisk on himself.

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: ADM RO A.3 Page 6 of 6 INITIATING CUE:

A plant procedure that you are performing requires entry into the RCA.

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: RO ADM JPM A.4 JPM

Title:

EP Questions Page 1 of 5 Approximate Time:

5 minutes Actual Time: _________________

Reference(s):

GET Training EPIPs K/A 2.4.29 (RO 2.6)

JPM Prepared by:

Jerry Koske Date:

JPM Reviewed by:

Date:

JPM Approved by:

Date:

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: RO ADM JPM A.4 JPM

Title:

EP Questions Page 2 of 5 Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment:

None Safety Considerations:

None Comments:

This Administrative JPM consists of two questions

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: RO ADM JPM A.4 JPM

Title:

EP Questions Page 3 of 5 Question One:

You are the RO in the control room during an event when an Accountability Determination is performed per the Emergency Plan. What do you do with your Accountability card?

Answer:

Place your accountability card in the control room accountability box.

Question Two:

You are escorting two individuals inside the protected area when an ALERT is declared. What action do you take?

Answer:

Take the escorted individuals to the security building and ensure that they exit the protected area.

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: RO ADM JPM A.4 Page 4 of 5 Question One You are the RO in the control room during an event when an Accountability Determination is performed per the Emergency Plan. What do you do with your accountability card?

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: RO ADM JPM A.4 Page 5 of 5 Question Two:

You are escorting two individuals inside the protected area when an ALERT is declared. What action do you take?

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: ADM SRO A.1.a JPM

Title:

Review of faulty Estimated Critical Condition Worksheet Page 1 of 5 Approximate Time:

Actual Time: _________________

Reference(s):

Fort Calhoun Technical Data Book K/A 2.1.25 (SRO 3.1)

JPM Prepared by:

Jerry Koske Date:

JPM Reviewed by:

Date:

JPM Approved by:

Date:

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: ADM SRO A.1.a JPM

Title:

Review of faulty Estimated Critical Condition Worksheet Page 2 of 5 Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment:

Calculator Safety Considerations:

None Comments:

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: ADM SRO A.1.a JPM

Title:

Review of faulty Estimated Critical Condition Worksheet Page 3 of 5 INITIATING CUE:

The plant has been shutdown as the result of a reactor trip and is planning a reactor startup at 1400 on 9/9/02.

You are directed to review the calculation of the estimated critical boron concentration for this startup through step D.3.d.

The following information has been provided:

• Shutdown from 100% power occurred at 2300 on 9/8/02

• Plant was operating with all rods out prior to the trip

• Boron concentration prior to the trip was 610 ppm

• Average core burnup is 4500 MWD/MTU

• Criticality should occur with group 4 at 85 inches

• Boron concentration has not been changed since the trip

• DEN-Nuclear states that no correction is needed for boron depletion Critical Steps shown in gray STEP ELEMENT STANDARD 1

Reviews the ECC worksheet 2

Identifies first error The wrong sign is used for the change in reactivity due to xenon in step C.3.c.

3 Identifies second error The HFP inverse boron worth was used in step D.1 rather than the HZP inverse boron worth as specified in the worksheet. (The wrong curve was used when reading TBD Figure II.A.4)

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: ADM SRO A.1.a JPM

Title:

Review of faulty Estimated Critical Condition Worksheet Page 4 of 5 STEP ELEMENT STANDARD 4

Determines correct critical boron concentration after making corrections Critical boron concentration is 686 ppm +/- 20 ppm Termination Criteria:

Both worksheet errors have been identified and the correct estimated critical boron concentration has been determined

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: ADM SRO A.1.a Page 5 of 5 INITIATING CUE:

The plant has been shutdown as the result of a reactor trip and is planning a reactor startup at 1400 on 9/9/02.

You are directed to review the calculation of the estimated critical boron concentration for this startup through step D.3.d.

The following information has been provided:

• Shutdown from 100% power occurred at 2300 on 9/8/02

• Plant was operating with all rods out prior to the trip

• Boron concentration prior to the trip was 610 ppm

• Average core burnup is 4500 MWD/MTU

• Criticality should occur with group 4 at 85 inches

• Boron concentration has not been changed since the trip

• DEN-Nuclear states that no correction is needed for boron depletion

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: SRO ADM JPM A.1.b JPM

Title:

Armed Security Attack Page 1 of 6 Approximate Time:

15 minutes Actual Time: _________________

Reference(s):

AOP-37 K/A 2.1.13 (SRO 2.9)

JPM Prepared by:

Jerry Koske Date:

JPM Reviewed by:

Date:

JPM Approved by:

Date:

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: SRO ADM JPM A.1.b JPM

Title:

Armed Security Attack Page 2 of 6 Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment:

None Safety Considerations:

None Comments:

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: SRO ADM JPM A.1.b JPM

Title:

Armed Security Attack Page 3 of 6 INITIATING CUE:

You are the CRS. You have just been notified by the Central Alarm Station Operator that an armed security attack is in progress. An armed force has attacked via the river and occupied the intake structure.

Take the appropriate actions.

CRITICAL STEP ELEMENT STANDARD 1

Enter AOP-37 Obtains copy of AOP-37 and enters it.

2 Confirm the report of the armed attack.

Call back on extension 6991 or 6188 using 800Mhz radio subfleet 1 or 2 CUE: Attack is confirmed 3

Make plant announcement Make the following announcement Attention all Personnel. Attention all Personnel. The Plant is in a Security Emergency. Take cover and do not move:

4 Direct Installation of Ultra Dogs CUE: Ultra Dogs have been installed on both Control Room Doors.

5 Initiate a reactor shutdown.

Directs RO to trip the reactor and implement EOP-00, Standard Post-Trip actions.

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: SRO ADM JPM A.1.b JPM

Title:

Armed Security Attack Page 4 of 6 CRITICAL STEP ELEMENT STANDARD CUE: The reactor has been tripped and Standard Post Trip Actions completed. All EOP-00 safety functions are met.

5 Directs entry into EOP-01 Refers to diagnostic actions and enters EOP-01 6

Directs that both Control room ventilation Mode selector switches placed in recirc.

Directs RO to place HC-VA-46A-1 and HC-VA-46B-1 in RECIRC.

CUE: RO reports that CR ventilation mode selector switches are in RECIRC 7

Ensure S/G levels 85-95% NR Direct RO to maintain S/G levels 85-95% NR (94-98%

WR) 8 Monitor CR panels and security radio for indication of potentially compromised equipment.

Directs ROs to monitor panels and security radio.

9 CUE: RO reports trip of CW-1A 10 Refer to AOP-37 attachment A Refers to AOP-37 attachment A and determines that no alternate safety function equipment is required.

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: SRO ADM JPM A.1.b JPM

Title:

Armed Security Attack Page 5 of 6 CRITICAL STEP ELEMENT STANDARD 11 CUE: Central Alarm station Operator reports that the armed security attack has been terminated. All intruders have been captured by FCS security.

12 Exit AOP-37 Exits AOP-37 and continues with procedure EOP-01.

Termination Criteria:

Armed attack is terminated and AOP-37 exited.

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No:

Page 6 of 6 INITIATING CUE:

You are the CRS. You have just been notified by the Central Alarm Station Operator that an armed security attack is in progress. An armed force has attacked via the river and occupied the intake structure.

Take the appropriate actions.

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: SRO ADM JPM A.2 JPM

Title:

Review a faulty clearance for AC-1A Page 1 of 5 Approximate Time:

15 minutes Actual Time: _________________

Reference(s):

SO-G-20A K/A 2.2.13 (SRO 3.8)

JPM Prepared by:

Jerry Koske Date:

JPM Reviewed by:

Date:

JPM Approved by:

Date:

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: SRO ADM JPM A.2 JPM

Title:

Review a faulty clearance for AC-1A Page 2 of 5 Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment:

P&IDs Safety Considerations:

None Comments:

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: SRO ADM JPM A.2 JPM

Title:

Review a faulty clearance for AC-1A Page 3 of 5 INITIATING CUE:

The plant is at 100% power when it is noticed during a surveillance test that RW/CCW heat exchanger AC-1A has a high DP which requires that the RW side of the heat exchanger be opened and cleaned. You have been provided a clearance for this work, that was prepared by an equipment operator, for review and approval.

Critical Steps shown in gray STEP ELEMENT STANDARD 1

May obtain a copy of Procedure SO-O-20A and determine review responsibilities Note: Provide copy of clearance 2

Reviews clearance References P&IDs to verify equipment that should be included in clearance and desired status..

3 Clearance approval Does not approve clearance as written.

HCV-2880A and HCV-2880B must be handjacked closed because they fail open on a loss of air.

NOTE: The proposed clearance treats these valves as fail-closed valves by isolating instrument air to them. As written, this clearance would likely result in flooding.

Termination Criteria:

Clearance review complete and error identified.

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: SRO ADM JPM A.2 Page 4 of 5 INITIATING CUE:

The plant is at 100% power when it is noticed during a surveillance test that RW/CCW heat exchanger AC-1A has a high DP which requires that the RW side of the heat exchanger be opened and cleaned. You have been provided a Clearance for this work, that was prepared by an equipment operator, for review and approval.

FOR TRAINING USE ONLY Page 5 of 5 FCS Clearance AC-1A MECH ISOL AC-RW-001 AC-RW

==

Description:==

Complete isolation of ac-1a for maintenance Reason:

Tube cleaning on AC-1A Hazards:

flooding Notes:

Tagged Component Description Location Tag Type Pl.

Seq Rest Seq Tagged Position Restoration Position Tag Placement Notes Tag Removal Notes HC-2880C CONTROL SWITCH FOR HCV-2880A AND HCV-2880B AUX 77 1036 Cb-1,2,3 Caution 1

5 CLOSED CLOSED IA ISOLATED TO VALVES HC-489 CONTROL SWITCH FOR HCV-489A AND HCV-489B AUX 77 1036 Cb-1,2,3 Caution 1

5 CLOSED CLOSED VALVES HJ CLOSED HC-2880A COMP CLNG HT EXCH AC-1A;RAW WATER INLET VALVE; HAND CONTROLLER AUX 18 0993 13WC-26N5B Danger 2

4 DO NOT USE CLOSED HC-2880B COMP CLNG HT EXCH AC-1A;RAW WATER OUTLET VALVE; HAND CONTROLLER AUX 4 0995 9WD-1N5B Danger 2

4 DO NOT USE CLOSED IA-HCV-2880A-B HCV-2880A INSTRUMENT AIR SUPPLY ISOLATION VALVE AUX 18 0994 13ED-6S6D Danger 3

3 CLOSED OPEN IA-HCV-2880B-B HCV-2880B INSTRUMENT AIR SUPPLY ISOLATION VALVE AUX 4 0991 7WD-4N5B Danger 3

3 CLOSED OPEN HCV-489A COMP COOLING HT EXCH AC-1A; CCW INLET VALVE AUX 4 0995 10WD-11N5B Danger 3

3 HJ CLOSED HJ REMOVED HCV-489B COMP COOLING HT EXCH AC-1A; CCW OUTLET VALVE AUX 4 0992 10WD-1N6D Danger 3

3 HJ CLOSED HJ REMOVED RW-156 COMP COOLING HT EXCH AC-1A OUTLET WATER BOX FLUSH VALVE AUX 4 0992 6WD-4N5B Danger 4

2 CLOSED CLOSED RW-130 RW/CCW HT EXCH AC-1A AIR SPARGING INLET ISOLATION VALVE AUX 4 0990 4WD-33N5B No Tag 5

1 SM DISCR CLOSED RW-213 CCW HEAT EXCHANGER AC-1A DRAIN VALVE AUX 4 0991 3WD-15S7A No Tag 5

1 SM DISCR CLOSED RW-152 COMP COOLING HT EXCH AC-1A RAW WATER OUTLET VENT VALVE AUX 4 0999 8WD-4N5B No Tag 5

1 SM DISCR CLOSED RW-189 RAW WATER HEAT EXCH AC-1A DWNSTREAM OF VALVE HCV-2880A VENT VLV AUX 18 1001 20WC-30N5B No Tag 5

1 SM DISCR CLOSED Level Verified by Verification Date/Time Verification Description Status 1

2

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: SRO ADM A.3 JPM

Title:

Approve a Containment Pressure Reduction Release Page 1 of 5 Approximate Time:

12 min Actual Time: _________________

Reference(s):

OI-VA-1 FC-212 K/A 2.3.6 (SRO 3.1)

JPM Prepared by:

Jerry Koske Date:

JPM Reviewed by:

Date:

JPM Approved by:

Date:

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: SRO ADM A.3 JPM

Title:

Approve a Containment Pressure Reduction Release Page 2 of 5 Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment:

None Safety Considerations:

None Comments:

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: SRO ADM A.3 JPM

Title:

Approve a Containment Pressure Reduction Release Page 3 of 5 INITIATING CUE:

You are acting as the Shift Manager. A Containment Pressure Reduction is planned for your shift. You must review the paperwork and authorize the release before it can be performed.

OI-VA-1-CL-B has been completed per OP-1.

Critical Steps shown in gray STEP ELEMENT STANDARD Provide the applicant with OI-VA-1 attachment 6 and the FC-212.

1 Verify at least one VA-40 fan is running.

AI-44 At least one fan has control switch in AFTER START and RED light ON.

2 Verify at least one noble gas monitor in service on AB stack.

AI-31 Verify RM-062 or RM-052 in service on the stack 3

Verify one Iodine/Particulate Sampler or aux sample collection equipment in service on AB stack.

CUE: One Iodine/Particulate sampler is in service on the AB stack 4

Verify required recorders are operable AI-33E - RR-049A AI FR-758 AI PR-745 5

Verify Room 60 items CUE:EONA reports the following:

• VA-366 is open

• VA-367 is open

• VA-368 is closed

• DPI-729 reads zero

• FI-729 reads zero

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: SRO ADM A.3 JPM

Title:

Approve a Containment Pressure Reduction Release Page 4 of 5 STEP ELEMENT STANDARD 6

Reviews FC-212 Determines that 75 scfm was used as the containment release rate in FC-212 resulting in non-conservative setpoint.

DOES NOT AUTHORIZE RELEASE Termination Criteria:

Release permit reviewed and release authorization refused.

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: SRO ADM JPM A.3 Page 5 of 5 INITIATING CUE:

You are acting as the Shift Manager. A Containment Pressure Reduction is planned for your shift. You must review the paperwork and authorize the release before it can be performed.

OI-VA-1-CL-B has been completed per OP-1.

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: SRO ADM JPM A.4 JPM

Title:

Emergency Plan Classification of an Armed Attack Page 1 of 5 Approximate Time:

10 minutes Actual Time: _________________

Reference(s):

EPIP-OSC-1 EPIP-EOF-7 K/A 2.4.41 (SRO 4.1)

K/A 2.4.44 (SRO 4.4)

JPM Prepared by:

Jerry Koske Date:

JPM Reviewed by:

Date:

JPM Approved by:

Date:

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: SRO ADM JPM A.4 JPM

Title:

Emergency Plan Classification of an Armed Attack Page 2 of 5 Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment:

None Safety Considerations:

None Comments:

Do not perform this JPM before SRO ADM JPM A.1.b

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: SRO ADM JPM A.4 JPM

Title:

Emergency Plan Classification of an Armed Attack Page 3 of 5 INITIATING CUE:

An armed security attack has been confirmed. The control room has entered AOP-37.

The armed attack came from the river. The armed intruders have occupied the intake structure. AC-10A tripped unexpectedly.

The meteorological indications are as follows:

• Indicated 10m wind speed - 12 mph, 14 mph

• Indicated wind direction - 120°, 128°

• Indicated ?T is -1.8°C/100m, -1.6°C/100m

• It is raining, 0.4 inches daily total You are directed to enter the Emergency Plan, classify the event and determine offsite Protective Action Recommendations.

Complete page 1 of form FC-1188.

Critical Steps shown in gray STEP ELEMENT STANDARD 1

Refer to Emergency Plan Refer to EPIP-OSC-1 2

Classify the event The event should be classified as a Site Area Emergency per EAL 9.10 (Confirmed Vital Attack occurs inside a vital area) on form FC-1188 Note: The area in the intake structure where AC-10A is located is a vital area.

3 Determine Protective Action Recommendations Refer to EPIP-EOF-7 and determine that there are no PARs for this situation. Document on form FC-1188

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: SRO ADM JPM A.4 JPM

Title:

Emergency Plan Classification of an Armed Attack Page 4 of 5 STEP ELEMENT STANDARD 4

Document other items on form FC-1188 Wind from - 120° - 128° Wind Speed - 12 mph Precipitation - yes Stability class - C There is no radioactive release Termination Criteria:

Event has been classified and PARs determined

Fort Calhoun Station - Operations Training ADMINISTRATIVE JOB PERFORMANCE MEASURE JPM No: SRO ADM JPM A.4 Page 5 of 5 INITIATING CUE:

An armed security attack has been confirmed. The control room has entered AOP-37.

The armed attack came from the river. The armed intruders have occupied the intake structure. AC-10A tripped unexpectedly.

The meteorological indications are as follows:

• Indicated 10m wind speed - 12 mph, 14 mph

• Indicated wind direction - 120°, 128°

• Indicated ?T is -1.8°C/100m, -1.6°C/100m

• It is raining, 0.4 inches daily total You are directed to enter the Emergency Plan, classify the event and determine offsite Protective Action Recommendations.

Complete page 1 of form FC-1188.

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: B.1.a JPM

Title:

Emergency Boration from the Control Room Page 1 of 5 Location:

Simulator Approximate Time:

7 minutes Actual Time: _________________

Reference(s):

EOP-00 K/A 000001 K4.05 (RO 3.9 / SRO 3.9)

K/A 000001 A4.02 (RO 4.1 / SRO 3.9)

JPM Prepared by:

Jerry Koske Date:

JPM Reviewed by:

Date:

JPM Approved by:

Date:

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: B.1.a JPM

Title:

Emergency Boration from the Control Room Page 2 of 5 Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment:

None Safety Considerations:

None Comments:

Simulator Dynamic JPM Override HCV-268 closed [COP RBAH268 0%] and LCV-218-2 open

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: B.1.a JPM

Title:

Emergency Boration from the Control Room Page 3 of 5 INITIATING CUE:

A reactor trip has occurred during a reactor startup and while performing EOP-00, you find that all shutdown rods have stuck out. All attempts to trip or insert control rods have failed. You are directed to commence emergency boration.

No procedures are allowed for this JPM Critical Steps shown in gray STEP ELEMENT STANDARD 1

Close FCV-269X and FCV-269Y Note: The following steps may be performed out of sequence.

CB-4 Control switches for FCV-269X&Y in CLOSED and GREEN lights lit 2

Open all of the following valves:

a. HCV-268

b. HCV-265

c. HCV-258 CB-4

a. Control switch for HCV-268 to OPEN until only RED light lit

[ HCV-268 will not open]

b. Control switch for HCV-265 to OPEN until only RED light lit

c. Control switch for HCV-258 to OPEN until only RED light lit 3

Start All of the following pumps:

a. Both Boric Acid Pumps

b. All Charging Pumps CB-4

a. Control switches to START CB-1,2,3

b. Control switches to START and RED lights lit

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: B.1.a JPM

Title:

Emergency Boration from the Control Room Page 4 of 5 STEP ELEMENT STANDARD 4

Close LCV-218-2 CB-1,2,3 Control Switch to CLOSE until only GREEN light lit

[LCV-218-2 will not close]

5 Ensure all of the following valves are closed:

a. LCV-218-3

b. HCV-257

c. HCV-264 CB-1,2,3

a. GREEN lights lit CB-4

b. GREEN light lit

c. GREEN light lit 6

Locally open HCV-268 and/or close LCV-218-2.

Direct EONA to manually open HCV-268 and/or close LCV-218-2; Note: Only one of these actions is required to establish emergency boration CUE: Simulator Operator will perform requested manual action and report as EONA.

Termination Criteria:

Borated water is being injected into the RCS

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: B.1.a Page 5 of 5 INITIATING CUE:

A reactor trip has occurred and while performing EOP-00, you find that all shutdown rods have stuck out. All attempts to trip or insert control rods have failed. You are directed to commence emergency boration.

No procedures are allowed for this JPM

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: B.1.b JPM

Title:

Perform Monthly RAS Surveillance Test Page 1 of 8 Location:

Simulator Approximate Time:

15 minutes Actual Time: _________________

Reference(s):

OP-ST-ESF-0009 7.4 (R38)

K/A 000013 K4.06 (RO 4.0 / SRO 4.3)

JPM Prepared by:

Jerry Koske Date:

JPM Reviewed by:

Date:

JPM Approved by:

Date:

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: B.1.b JPM

Title:

Perform Monthly RAS Surveillance Test Page 2 of 8 Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment:

None Safety Considerations:

None Comments:

Simulator Operator will perform the dedicated operator functions referred to in the procedure. (Override LCV-383-2 and HCV-386 control switches in open position)

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: B.1.b JPM

Title:

Perform Monthly RAS Surveillance Test Page 3 of 8 JPM Setup:

1 Use a Mode 1 IC 2

Place HC-AI-43A in TEST position 3

Place CS-A1/SP-A (Derived Cutoff switch) in OFF 4

Place Channel A load shed switch in OFF 5

Place HC/344 in TEST 6

Place HC/345 in TEST 7

Place all S1-1 sequencer isolation switches (key switches) in OFF 8

RFP DSG10F LOCAL (simulator operator) 9 Place RM050/51 sample pump switch OFF 10 Place RM-065 sampel pump switch OFF 11 Place PPLS test switch in TEST and release

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: B.1.b JPM

Title:

Perform Monthly RAS Surveillance Test Page 4 of 8 INITIATING CUE:

OP-ST-ESF-0009 is in progress and complete through section 7.3. You are directed to perform RAS testing per section 7.4.

You will double as the Dedicated Operator for. (step 7.4.1)

Critical Steps shown in gray STEP ELEMENT STANDARD 1

Verify the following alarm windows are clear:

• TESTING (A-6)

• STLS A SAFEGUARD SIGNAL (B-3)

• SAFETY INJECTION RECIRCULATION COMMAND (C-3)

AI-30A Listed alarm windows are CLEAR 2

Verify the following ERF Computer CRT displays are clear:

• STLS

• RAS ERF Computer Screen STLS and RAS have GREEN background 3

Ensure HCV-386 is open AI-30A HCV-386 is OPEN and RED light ON 4

Log into Tech Spec 2.3(2)I and Tech Spec 2.4(i)b CUE: Tech Spec logging is complete 5

Place HCV-383-3 in PULL-TO-OVERRIDE AI-30A Switch to PULL-TO-OVEERRIDE position 6

Verify SIRWT HDT#1 RECIRC VALVES OFF NORMAL alarm AI-30A, A33-1, G-2 is ON

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: B.1.b JPM

Title:

Perform Monthly RAS Surveillance Test Page 5 of 8 STEP ELEMENT STANDARD 7

Station a dedicated operator at LCV-383-2 to maintain switch open CUE: a dedicated operator is stationed at LCV-383-2 holding the switch in open (Note: Simulator operator will override switch open)

[COP RSIL3832 100%]

8 Station a dedicated operator at HCV-386 to maintain switch open CUE: a dedicated operator is stationed at HCV-386 holding the switch in open (Note: Simulator operator will override switch open)

[COP RSIH386 100%]

9 Place 86A/STLS test switch in TEST and verify TESTING in alarm, then release.

AI-30A Hold 86A/STLS test switch in test until TESTING alarm received, then release.

10 Verify the following relays have actuated:

• 86-A/STLS

• 86-A/RAS

• 86-AX/RAS AI-30A Lockout relays tripped and AMBER lights OFF (Note: 86-AX/RAS has no light) 11 Verify the following alarms:

• STLS A SAFEGUARD SIGNAL (B-3)

• SAFETY INJECTION RECIRCULATION COMMAND (C-3)

AI-30A Listed alarm windows are ON 12 Verify the following ERF computer points printout:

• 86-A/STLS TRIPPED

• 86-A/RAS TRIPPED ERF Printer Tripped printout

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: B.1.b JPM

Title:

Perform Monthly RAS Surveillance Test Page 6 of 8 STEP ELEMENT STANDARD 13 Verify the following ERF CRT displays are in alarm:

• STLS

• RAS ERF Display Screen STLS and RAS have RED background 14 Sequentially reset the following Lockout Relays:

• 86-A/STLS

• 86-A/RAS

• 86-AX/RAS AI-30A Reset lockout relays in order given.

Lockout relays in RESET and AMBER lights ON (Note: 86-AX/RAS has no light) 15 Direct dedicated operator at LCV-383-2 to release control switch and ensure Red light remains on.

CUE: LCV-383-2 control switch released and RED light on.

(Note: Simulator Operator will clear override) 16 Direct dedicated operator at HCV-386 to release control switch and ensure Red light remains on.

CUE: HCV-386 control switch released and RED light on.

(Note: Simulator Operator will clear override) 17 Notify Dedicated Operators assigned to LCV-383-2 and HCV-386 that they are no longer needed.

CUE: Dedicated operators assigned to LCV-383-2 and HCV-386 have left.

18 Place Control switch HCV-383-3 in auto then ensure valve remains closed.

AI-30A HCV-383-3 Control switch in AUTO and GREEN light ON 19 Verify SIRWT HDR#1 RECIRC VALVES OFF NORMAL alarm is clear (G-2)

AI-30A,A33-1, G-2 Alarm Window is OFF 20 Place control switch HCV-481 in CLOSE, Then release and verify valve is closed.

CB-1,2,3 Place control switch to CLOSE, then release. HCV-481 GREEN light is ON.

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: B.1.b JPM

Title:

Perform Monthly RAS Surveillance Test Page 7 of 8 STEP ELEMENT STANDARD 21 Place control switch HCV-480 in CLOSE, Then release and verify HCV-484 is closed.

CB-1,2,3 Place control switch to CLOSE, then release. HCV-484 GREEN light is ON.

CUE: Electrician has completed step 7.4.24. Measured voltage is 125 VDC.

22 Notify Dedicated operator assigned to attachment 4 that RAS testing is complete.

CUE: Dedicated operator assigned to attachment 4 has left.

23 Exit tech specs CUE: Tech specs have been exited Termination Criteria:

RAS test using 86A/STLS test switch is complete

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: B.1.b Page 8 of 8 INITIATING CUE:

OP-ST-ESF-0009 is in progress and complete through section 7.3. You are directed to perform RAS testing per section 7.4.

You will double as the Dedicated Operator for. (step 7.4.1)

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RO B.1.c JPM

Title:

Transfer Pressurizer Pressure Control to Manual to support Maintenance Page 1 of 5 Location:

Simulator Approximate Time:

5 minutes Actual Time: _________________

Reference(s):

OI-RC-7 K/A 000010 K4.03 (RO 3.8 / SRO 4.1)

K/A 000010 A1.07 (RO 3.7 / SRO 3.7)

JPM Prepared by:

Jerry Koske Date:

JPM Reviewed by:

Date:

JPM Approved by:

Date:

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RO B.1.c JPM

Title:

Transfer Pressurizer Pressure Control to Manual to support Maintenance Page 2 of 5 Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment:

None Safety Considerations:

None Comments:

Select PRC-103 Y as the controlling channel

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RO B.1.c JPM

Title:

Transfer Pressurizer Pressure Control to Manual to support Maintenance Page 3 of 5 INITIATING CUE:

RCS pressure is at a nominal 2110 psia. All four RCPs are in operation.PRC-103Y is the controlling pressure channel. The Shift Manager directs you to make PRC-103X the controlling pressure channel and to shift PRC-103Y to Manual for I&C maintenance.

All prerequisites are met Critical Steps shown in gray STEP ELEMENT STANDARD 1

Refers to attachment 8:

Ensure both Pressure Controllers are in Automatic:

• PC-103X

• PC-103Y CB-1,2,3 Both controllers in AUTO with GREEN lamp ON 2

Adjust the setpoint pushbutton(s) on the non-selected controller to obtain same output indicated on selected controller CB-1,2,3 Adjust setpoint as necessary 3

Transfer the controlling channels by placing HC-103, Pressurizer Pressure Selector Switch to the opposite channel CB-1,2,3 HC-103 to the X channel 4

Ensure the selected controller is acting as follows:

• Controller in AUTO

• Controller is controlling pressure at the desired setpoint CB-1,2,3 Controller in AUTO, GEEN light is ON, Pressure at nominal 2100 psia 5

Refers to attachment 7:

Press Manual pushbutton on the selected controller CB-1,2,3 Press M on PC-103Y, AMBER light ON

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RO B.1.c JPM

Title:

Transfer Pressurizer Pressure Control to Manual to support Maintenance Page 4 of 5 STEP ELEMENT STANDARD 6

Move the Manual Control lever as necessary to obtain desired reading on the output meter CB-1,2,3 May make adjustment to match PC-103X CUE: When PC-103Y is placed in manual, PC-103X fails high.

[COP T:P103X 2500 120 sec ramp]

7 Shift HC-103 to PC-103Y for pressure control in manual CB-1,2,3 HC-103 to PC-103Y 8

Adjust Output Meter as necessary to control pressure Return Pressurizer Pressure to 2100 psia +/- 10 psi.

TM/LP trip must not occur Termination Criteria:

Pressurizer pressure at 2100 psia in Manual Control

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RO B.1.c Page 5 of 5 INITIATING CUE:

RCS pressure is at a nominal 2110 psia. All four RCPs are in operation.PRC-103Y is the controlling pressure channel. The Shift Manager directs you to make PRC-103X the controlling pressure channel and to shift PRC-103Y to Manual for I&C maintenance.

All prerequisites are met

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: SRO B.1.c JPM

Title:

Fuel Handling Incident Page 1 of 6 Location:

Simulator or Control Room Approximate Time:

12 minutes Actual Time: _________________

Reference(s):

AOP-08 K/A 000034 A2.01 (RO 3.6 / SRO 3.4)

JPM Prepared by:

Jerry Koske Date:

JPM Reviewed by:

Date:

JPM Approved by:

Date:

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: SRO B.1.c JPM

Title:

Fuel Handling Incident Page 2 of 6 Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment:

None Safety Considerations:

None Comments:

This is a static JPM

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: SRO B.1.c JPM

Title:

Fuel Handling Incident Page 3 of 6 INITIATING CUE:

The plant is in a refueling shutdown. Fuel movement is in progress. RM-050, RM-051 and RM-073 have just alarmed and VIAS has actuated.

The Control Room has been notified that a fuel bundle has dropped in the transfer canal inside the containment. You have been directed to take appropriate actions.

Critical Steps shown in gray STEP ELEMENT STANDARD 1

Enters AOP-08 Enters AOP-08 2

Notify plant personnel of event Announce over Gaitronics 3

Direct RP to survey affected area Cue: RP in containment is checking area 4

Initiate Emergency Plan per EPIP-OSC-1 Cue: Shift Manager will initiate Emergency Plan.

5 Direct Security Shift Manager to close Room 66 Roll-up Doors Contact Security Shift Manager.

Cue: Security Shift Manager reports that roll-up doors are closed.

6 Direct Shift Outage Manager to close all containment penetrations open to the outside atmosphere.

Contact Shift Outage manager.

Cue: Shift Outage Manager reports that all containment penetrations open to the outside atmosphere are closed.

7.

Direct EONA to close at least one PAL door Contact EONA.

Cue: EONA report that a PAL door is closed.

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: SRO B.1.c JPM

Title:

Fuel Handling Incident Page 4 of 6 STEP ELEMENT STANDARD 8

Verify VIAS actuation Goes to AOP-08, attachment A 7

Ensure Both of the following Containment Vent Fans are operating:

• VA-3A

• VA-3B AI-30A/B Control Switches in After-Start (RED FLAG) and RED lights lit 8

Ensure containment vent fans have switched to filtered mode.

AI-30A/B Check HCV-724 and HCV-725 in filter mode with RED lights lit 9

Ensure that All of the Containment Purge Fans are stopped:

• VA-24A/B

• VA-32A/B

• VA-76

• VA-77 AI-44 Fans stopped and GREEN lights lit or switch placed in Pull-To-Lock 10 Ensure ALL of the following are closed:

• PCV-742A/B/C/D

• PCV-742E/F/G/H

• HCV-746A/B AI-44 Valves closed and GREEN lights lit.

11 Ensure RM-050/051 Sample pump is stopped AI-33 Pump switch in STOP position 12 Ensure FCV-532C, Header Isolation Valve is closed Contact EONA Cue: EONA reports from AI-100 that FCV-532C is Closed 13 Stop proper Control Room Ventilation Fan AI-106A/B Cue: When at AI-106A/B, provide the following information:

VA-63B, VA-46A and VA-46B are running.

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: SRO B.1.c JPM

Title:

Fuel Handling Incident Page 5 of 6 STEP ELEMENT STANDARD 13 cont Stop VA-46A AI-106A Place Control switch in After-Stop position. GREEN light lit 14 Place Control Room Ventilation Mode switch in Filtered Air Position AI-46A HC-VA-46A-1 switch in FILT-AIR AI-46B HC-VA-46B-1 switch in FILT-AIR 15 Ensure RM-065 is operating AI-106A HC-RM-65 RED light lit 16 If directed by RP, don respirator protection Cue: RP reports that respirator protection is not required in Control Room.

Termination Criteria:

Ventilation systems are properly aligned.

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: SRO B.1.c Page 6 of 6 INITIATING CUE:

The plant is in a refueling shutdown. Fuel movement is in progress. RM-050, RM-051 and RM-073 have just alarmed and VIAS has actuated.

The Control Room has been notified that a fuel bundle has dropped in the transfer canal inside the containment. You have been directed to take appropriate actions.

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: B.1.d JPM

Title:

Restore Shutdown Cooling following an Instrument Failure Page 1 of 6 Location:

Simulator Approximate Time:

20 minutes Actual Time: _________________

Reference(s):

OI-SC-1 OI-SC-2 K/A 005000 A4.01 (RO 3.6 / SRO 3.4)

AOP-19 JPM Prepared by:

Jerry Koske Date:

JPM Reviewed by:

Date:

JPM Approved by:

Date:

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: B.1.d JPM

Title:

Restore Shutdown Cooling following an Instrument Failure Page 2 of 6 Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment:

None Safety Considerations:

None Comments:

This will be a dynamic JPM in the simulator. The simulator operator will fail P-118 high which will result in HCV-347 and HCV-348 closing.

[Ensure LI-197, LIS-119 enabled]

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: B.1.d JPM

Title:

Restore Shutdown Cooling following an Instrument Failure Page 3 of 6 INITIATING CUE:

The plant is on shutdown cooling on LPSI SI-1A. The RCS is intact and time to boil is 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />. No refueling outage is in progress. Both SI-1A and SI-1B are lined up for shutdown cooling.

You are directed to respond to the alarms on panel CB-1,2,3.

Critical Steps shown in gray STEP ELEMENT STANDARD Note: The following alarms will come in:

SHUTDOWN COOLING VALVES CLOSED SIG FAIL OR VIOLATION SHUTDOWN COOLIN FLOW HI-LO 1

Respond to annunciators Reviews ARP for alarms and transitions to AOP-19.

2 Implement the Emergency Plan CUE: Shift Manager has entered Emergency Plan 3

Verify RCS water level above hot leg centerline.

CB-1,2,3 LI-197 al least 1006.5 feet LIS-119 at least 1006.5 feet ERF Computer PVLMS > 29%

In containment Sight glass LI-199 at least 1006.5 feet

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: B.1.d JPM

Title:

Restore Shutdown Cooling following an Instrument Failure Page 4 of 6 STEP ELEMENT STANDARD 4

Verify RCS water level constant or rising Verifies level trend from, at least, one of the following:

CB-1,2,3

• LI-106

• LI-197

• LI-119 5

Verify proper LPSI pump operation by meeting all of the following criteria:

• LPSI Pump current stable

• LPSI flow greater than or equal to 200 gpm AI-30A Ammeter for SI-1A, current is varying CB-1,2,3 FI-326 shows low flow 6

Determines that pump current is not stable and shuts down SI-1A AI-30A SI-1A control switch to AFTER-STOP, GREEN light lit CUE: LPSI discharge header is operable 7

Determines that RCS pressure instrument P-118 has failed high 8

Ensures that the following valves are open:

a. FCV-326

b. HCV-335

c. HCV-341

d. HCV-348

e. HCV-347

a. RED light lit on CB-1,2,3

b. RED light lit on AI-30B

c. Verify controller signal

d. Place P-118 Pressurizer pressure PC-118 auto signal override HC-347/348 switch to OVERRIDE. Verify RED light lit as valve opens

e. Hold HCV-347 to OPEN.

Verify RED light lit.

Cue: LPSI pump venting not required

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: B.1.d JPM

Title:

Restore Shutdown Cooling following an Instrument Failure Page 5 of 6 STEP ELEMENT STANDARD 9

Place FCV-326 in manual CB-1,2,3 Select MANUAL on FCV-326 controller 10 If RCS level is above hot leg centerline, start one LPSI pump, SI-1A or SI-1B.

AI-30A/B Pump control switch in AFTER START and RED light lit 11 Adjust FCV-326 to obtain 1500 gpm flow CB-1,2,3 Operate controller in manual until FI-326 reads approximately 1500 gpm 12 Place FCV-326 in automatic CB-1,2,3 Select AUTO on FCV-326 Termination Criteria:

Shutdown Cooling Reestablished

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: B.1.d Page 6 of 6 INITIATING CUE:

The plant is on shutdown cooling on LPSI SI-1A. The RCS is intact and time to boil is 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />. No refueling outage is in progress. Both SI-1A and SI-1B are lined up for shutdown cooling.

You are directed to respond to the alarms on panel CB-1,2,3.

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: B.1.e JPM

Title:

Shift 4160V Buses 1A3 and 1A4 from 345KV to 161 KV Page 1 of 6 Location:

Simulator Approximate Time:

6 minutes Actual Time: _________________

Reference(s):

OI-EE-1, attachment 1 K/A 000062 K1.04 (RO 3.7 / SRO 4.2)

K/A 000062 A2.01 (RO 3.4 / SRO 3.9)

JPM Prepared by:

Jerry Koske Date:

JPM Reviewed by:

Date:

JPM Approved by:

Date:

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: B.1.e JPM

Title:

Shift 4160V Buses 1A3 and 1A4 from 345KV to 161 KV Page 2 of 6 Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment:

None Safety Considerations:

None Comments:

Dynamic JPM on the simulator Insert then clear malfunction [MFP SWD02B]

[RFP SWD03D DISABLE]

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: B.1.e JPM

Title:

Shift 4160V Buses 1A3 and 1A4 from 345KV to 161 KV Page 3 of 6 INITIATING CUE:

A loss of 161 KV has occurred due to a grid problem.

Busses 1A3 and 1A4 transferred to 345 KV. AOP-31, section II has been entered and appropriate actions taken The 161 KV grid problem has been fixed and 161 KV is available.

You are directed to restore normal power to busses 1A3 and 1A4 beginning with AOP-31, section II, step 10.

Critical Steps shown in gray STEP ELEMENT STANDARD 1

Ensure Lockout Relay 86/161 is reset AI-22 86 Relay RESET 2

Ensure all of the following Lockout Relays are reset:

• 86-1/T1A-4

• 86-2/T1A-4

• 86-1/T1A-3

• 86-2/T1A-3

• 86X/FT161 AI-24, AI-25, AI-46 Relays RESET 3

Synchronize and Close at least one of the following breakers:

• Breaker 110

• Breaker 111 CB-20 Insert Sync switch handle and turn to ON Breaker switch to AFTER CLOSE RED light lit 4

Enter OI-EE-1, Attachment 1 5

Ensure both fast Transfer switches in manual:

• 43/1A1-1A3

• 43/1A2-1A4 CB-20 Both switches in MANUAL 6

Turn 1A33 Synchroscope ON CB-20 Insert Sync switch handle and turn

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: B.1.e JPM

Title:

Shift 4160V Buses 1A3 and 1A4 from 345KV to 161 KV Page 4 of 6 STEP ELEMENT STANDARD to ON 7

Verify incoming and running voltages are matched CB-20 Verify voltages within 25 volts 8

Verify Synchroscope at 12 o,clock CB-20 Indicator at 12 o,clock 9

Close Breaker 1A33 CB-20 Breaker 1A33 in AFTER CLOSE, RED light lit 10 Open Breaker 1A13 CB-20 Breaker 1A13 in AFTER TRIP.

GREEN light lit 11 Turn Off Synchroscope Sync switch handle to OFF Verify loads still energized 12 Turn 1A44 Synchroscope ON CB-20 Insert Sync switch handle and turn to ON 13 Verify incoming and running voltages are matched CB-20 Verify voltages within 25 volts 14 Verify Synchroscope at 12 o,clock CB-20 Indicator at 12 o,clock 15 Close Breaker 1A44 CB-20 Breaker 1A44 in AFTER CLOSE, RED light lit 16 Open Breaker 1A24 CB-20 Breaker 1A24 in AFTER TRIP.

GREEN light lit 17 Turn Off Synchroscope Sync switch handle to OFF Verify loads still energized

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: B.1.e JPM

Title:

Shift 4160V Buses 1A3 and 1A4 from 345KV to 161 KV Page 5 of 6 STEP ELEMENT STANDARD 18 Verify conditions for fast transfer met:

• Lock-out relays amber lights on

• Appropriate 4160V breakers not in pull-to-lock

• Power is available CB-20

• AMBER lights lit (vertical panel)

• Control Switches not in PULL-TO-LOCK

• Voltmeters show proper voltages 19 Place Fast Transfer switches in AUTO

• 43/1A1-1A3

• 43/1A2-1A4 CB-20 Both Switches in AUTO Termination Criteria:

Busses 1A3 and 1A4 powered from 161 KV

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: B.1.e Page 6 of 6 INITIATING CUE:

A loss of 161 KV has occurred due to a grid problem.

Busses 1A3 and 1A4 transferred to 345 KV. AOP-31, section II has been entered and appropriate actions taken The 161 KV grid problem has been fixed and 161 KV is available.

You are directed to restore normal power to busses 1A3 and 1A4 beginning with AOP-31, section II, step 10.

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: B.1.f JPM

Title:

Perform DSS Matrix Channel Trip Manual Actuation Relay Test Page 1 of 8 Location:

Simulator Approximate Time:

10 minutes Actual Time: _________________

Reference(s):

IC-FT-DSS-0002, sections 7.6 and 7.7 LER 95-005 K/A 012000 A4.03 (RO 3.6 / SRO 3.6)

JPM Prepared by:

Jerry Koske Date:

JPM Reviewed by:

Date:

JPM Approved by:

Date:

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: B.1.f JPM

Title:

Perform DSS Matrix Channel Trip Manual Actuation Relay Test Page 2 of 8 Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment:

None Safety Considerations:

None Comments:

Dynamic simulator JPM Simulator operator will need to run files to override matrix light status

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: B.1.f JPM

Title:

Perform DSS Matrix Channel Trip Manual Actuation Relay Test Page 3 of 8 INITIATING CUE:

I&C is testing the DSS system using IC-FT-DSS-0002.

Sections 7.6 and 7.7 of this procedure are conducted by licensed operators.

You have been directed to perform section 7.6 and 7.7 of IC-FT-DSS-0002.

Critical Steps shown in gray STEP ELEMENT STANDARD 1

Verify the following alarm windows are clear:

• DSS 86A/DSS ACTUATED

• TEST SWITCH A1/TS-DSS OFF NORMAL

• DSS MATRIX A BLOCKED AI-66A Listed Alarm Windows CLEAR

[SIM OP File #1]

2 Place switch CHAN A DSS TEST OR BYPASS SW A1/TS-DSS in test AI-66A Insert key in switch and place in TEST position

3.

Verify alarms:

• TEST SWITCH A1/TS-DSS OFF NORMAL

• DSS MATRIX A BLOCKED AI-66A Listed Alarm Windows LIT 4

Verify DSS Lockout relay 86A/DSS is reset AI-66A Relay in RESET position 5

Turn DSS Manual Trip Switch A/TS-DSS to trip position AI-66A Turn A/TS-DSS to TRIP position and release

[SIM OP File #2]

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: B.1.f JPM

Title:

Perform DSS Matrix Channel Trip Manual Actuation Relay Test Page 4 of 8 STEP ELEMENT STANDARD 6

Verify Clutch power Supply breakers are closed:

• CB-AB

• CB-CD AI-57 Breakers CLOSED (Full Up) 7 Verify the following parameters:

a. DSS 86A/DSS ACTUATED alarm

b. DSS Trip relay 94-A1-DSS white light is on

c. DSS Trip relay 94-A2-DSS white light is on

d. DSS lockout relay 86A/DSS amber light is off

e. All four DSS Matrix supervisory amber lights are off

f. Lockout relay 86A/DSS is tripped AI-66A

a. Alarm Window LIT

b. WHITE light is ON

c. WHITE light is ON

d. AMBER light is OFF

e. AMBER lights are OFF

f. Lockout Relay is TRIPPED 8

Reset DSS Lockout Relay 86A/DSS AI-66A Lockout relay RESET

[SIM OP File #1]

9 Verify the following:

a. All four DSS Matrix supervisory amber lights are on

b. DSS lockout relay 86A/DSS amber light is on

c. DSS Trip relay 94-A2-DSS white light is off

d. DSS Trip relay 94-A1-DSS white light is off

e. DSS 86A/DSS ACTUATED alarm is clear AI-66A

a. AMBER lights ON

b. AMBER light ON

c. WHITE light OFF

d. WHITE light OFF

e. Alarm window CLEAR

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: B.1.f JPM

Title:

Perform DSS Matrix Channel Trip Manual Actuation Relay Test Page 5 of 8 STEP ELEMENT STANDARD 10 Place CHAN A DSS TEST OR BYPASS SW switch in normal AI-66A Switch to NORMAL 11 Verify the following:

• DSS MATRIX A BLOCKED alarm window is clear

• TEST SWITCH A1/TS-DSS OFF NORMAL alarm window is clear AI-66A Both alarm windows CLEAR 12 Verify the following alarm windows are clear:

• DSS 86B/DSS ACTUATED

• TEST SWITCH B1/TS-DSS OFF NORMAL

• DSS MATRIX B BLOCKED AI-66B Listed Alarm Windows CLEAR 13 Place switch CHAN B DSS TEST OR BYPASS SW B1/TS-DSS in test AI-66B Insert key in switch and place in TEST position 14 Verify alarms:

• TEST SWITCH B1/TS-DSS OFF NORMAL

• DSS MATRIX B BLOCKED AI-66B Listed Alarm Windows LIT Verify DSS Lockout relay 86B/DSS is reset AI-66B Relay in RESET position 15 Turn DSS Manual Trip Switch B/TS-DSS to trip position AI-66B Turn B/TS-DSS to TRIP position and release

[SIM OP File#3]

16 Verify Clutch power Supply breakers are closed:

• CB-AB

• CB-CD AI-57 Breakers CLOSED (Full Up)

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: B.1.f JPM

Title:

Perform DSS Matrix Channel Trip Manual Actuation Relay Test Page 6 of 8 STEP ELEMENT STANDARD 17 Verify the following parameters:

a. DSS 86B/DSS ACTUATED alarm

b. DSS Trip relay 94-B1-DSS white light is on

c. DSS Trip relay 94-B2-DSS white light is on

d. DSS lockout relay 86B/DSS amber light is off

e. All four DSS Matrix supervisory amber lights are off

f. Lockout relay 86B/DSS is tripped AI-66A

a. Alarm Window LIT

b. WHITE light is ON

c. WHITE light is ON

d. AMBER light is OFF

e. AMBER lights are OFF

f. Lockout Relay is TRIPPED 18 Reset DSS Lockout Relay 86B/DSS AI-66B Lockout relay RESET

[SIM OP File#1]

19 Verify the following:

a. All four DSS Matrix supervisory amber lights are on

b. DSS lockout relay 86B/DSS amber light is on

c. DSS Trip relay 94-B2-DSS white light is off

d. DSS Trip relay 94-B1-DSS white light is off

e. DSS 86B/DSS ACTUATED alarm is clear AI-66B

a. AMBER lights ON

b. AMBER light ON

c. WHITE light OFF

d. WHITE light OFF

e. Alarm window CLEAR 20 Place CHAN B DSS TEST OR BYPASS SW switch in normal AI-66B Switch to NORMAL

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: B.1.f JPM

Title:

Perform DSS Matrix Channel Trip Manual Actuation Relay Test Page 7 of 8 STEP ELEMENT STANDARD 21 Verify the following:

• DSS MATRIX B BLOCKED alarm window is clear

• TEST SWITCH B1/TS-DSS OFF NORMAL alarm window is clear AI-66B Both alarm windows CLEAR Termination Criteria:

Section 7.6 and 7.7 of IC-FT-DSS-0002 are complete

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: B.1.f Page 8 of 8 INITIATING CUE:

I&C is testing the DSS system using IC-FT-DSS-0002.

Sections 7.6 and 7.7 of this procedure are conducted by licensed operators.

You have been directed to perform section 7.6 and 7.7 of IC-FT-DSS-0002.

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: B.1.g JPM

Title:

Operate AFW system from AI-179 following Control Room evacuation Page 1 of 7 Location:

Simulator Approximate Time:

20 minutes Actual Time: _________________

Reference(s):

AOP-07 K/A 000061 K1.01 ( RO 4.1 / SRO 4.2)

K/A 000061 A1.01 (RO 3.9 / SRO 4.2)

JPM Prepared by:

Jerry Koske Date:

JPM Reviewed by:

Date:

JPM Approved by:

Date:

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: B.1.g JPM

Title:

Operate AFW system from AI-179 following Control Room evacuation Page 2 of 7 Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment:

None Safety Considerations:

None Comments:

This is a dynamic JPM on the simulator. It uses both the control room and ASP portions of the simulator.

Note: The ASP portion of this procedure is normally performed by the CRS. However, operating AFW from AI-179 is expected RO knowledge.

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: B.1.g JPM

Title:

Operate AFW system from AI-179 following Control Room evacuation Page 3 of 7 INITIATING CUE:

The Shift Manager has directed an evacuation of the Control Room. You are directed to perform the control room portions of AOP-07 and then establish control at the Alternate Shutdown Panels. (You have a radio and the AOP-06 keys)

Critical Steps shown in gray STEP ELEMENT STANDARD 1

Manually TRIP the reactor CB-4 Press reactor Trip pushbutton Verify Reactor has tripped 2

Verify the Turbine has tripped as indicated by stop and intercept valves closed CB-10,11 (vertical)

Verify stop and intercept valve indicators on bottom 3

Place 43/FW Switch in OFF CB-10,11 43/FW switch placed in OFF 4

Ensure no more than one condensate pump, FW-2A/2B/2C, running.

CB-10,11 Trips one (and only one) condensate pump. (Control switch green flagged, GREEN light lit) 5 Stop all running Heater Drain pumps, FW-5A/5B/5C.

CB-10,11 Trips both running Heater Drain pumps. (Control switches green flagged, GREEN lights lit)

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: B.1.g JPM

Title:

Operate AFW system from AI-179 following Control Room evacuation Page 4 of 7 STEP ELEMENT STANDARD 6

Ensure no more than one Feed pump, FW-4A/4B/4C, running.

CB-10,11 Trips one (and only one) Feed pump. (Control switch green flagged, GREEN light lit) 7 Ensure the following Turbine Lube Oil equipment is running:

• LO-3, Turning Gear Oil Pump

• LO-8, Motor Suction Oil Pump

• LO-4, DC-Oil Pump

• Turbine Lift Pumps, LO-14A/B/C CB-10,11 Starts each of the listed pumps by placing its control switch in after start (red flag) RED light lit.

CUE: The remaining actions in step one have been taken. You are directed to AI-185 to continue with step two. (Direct examinee to simulator Aux Shutdown panel) 8 Place REMOTE-LOCAL Transfer Switch 43 in Local AI-185 REMOTE LOCAL TRANSFER SWITCH 43 in LOCAL Lockout relays actuate, AMBER lights OFF 9

Verify control transferred by observing indicating lights lit

• HCV-239

• CH-1B AI-185 Indicating Lights LIT 10 Place YCV-1045 control switch in PULL-TO-LOCK AI-179 Control Switch in PULL-TO LOCK

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: B.1.g JPM

Title:

Operate AFW system from AI-179 following Control Room evacuation Page 5 of 7 STEP ELEMENT STANDARD 11 Place both AFW Controls Transfer Switches 43/RC-2A/B in LOCAL AI-179 Both Switches in LOCAL 12 Verify both AFW Controls Transfer Relays are in TRIP.

AI-179 86 relays are TRIPPED AMBER lights OFF 13 Verify Following valves are OPEN:

• HCV-1107A

• HCV-1107B

• HCV-1108A

• HCV-1108B

• YCV-1045A

• YCV-1045B AI-179 RED lights ON 14 Start Wide range Channel D Recorder.

AI-212 Two toggle switches inside cover to ON.

15 Maintain pressurizer level 45-60%

AI-185 Verify pressurizer level. Operate CH-1B as required 16 Maintain RCS pressure 2050-2150 psia AI-185 Verify pressurizer pressure.

Operate backup heaters as required 17 Maintain S/G levels AI-179 Verify S/G levels Note: levels will be below control band.

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: B.1.g JPM

Title:

Operate AFW system from AI-179 following Control Room evacuation Page 6 of 7 STEP ELEMENT STANDARD 18 Verify HCV-1384 is CLOSED CUE: EONT reports HCV-1384 is CLOSED 19 Place YCV-1045 in AFTER-START AI-179 YCV-1045 control switch in AFTER-START. FW-10 running light is ON 20 Place both of the following switches in THROTTLE:

• HCV-1107B

• HCV-1108B AI-179 HCV-1107B and HCV-1108B switches in THROTTLE 21 Throttle HCV-1107B and HCV-1108B using controllers AI-179 Regulate Air Loaders for desired flow 22 Verify S/G pressures greater than 850 psia AI-179 Verify S/G pressures 23 Establish contact with STA CUE: STA reports All Safety Functions are being met 24 Direct EONT to maintain EFWST level CUE: EONT is maintaining EFWST level CUE: Plant Cooldown is not required Termination Criteria:

Control of AFW has been established at the alternate Shutdown panels

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: B.1.g Page 7 of 7 INITIATING CUE:

The Shift Manager has directed an evacuation of the Control Room. You are directed to perform the control room portions of AOP-07 and then establish control at the Alternate Shutdown Panels. (You have a radio and the AOP-06 keys)

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: B.2.a JPM

Title:

Line up Condenser Evacuation to AB stack Page 1 of 5 Location:

Plant - Aux Building and Turbine Building Approximate Time:

15 minutes Actual Time: _________________

Reference(s):

OI-CE-1 K/A 000037 AA2.07 (RO 3.1 / SRO 3.6)

JPM Prepared by:

Jerry Koske Date:

JPM Reviewed by:

Date:

JPM Approved by:

Date:

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: B.2.a JPM

Title:

Line up Condenser Evacuation to AB stack Page 2 of 5 Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment:

None Safety Considerations:

Requires RCA entry Comments:

This JPM begins in the RCA and finishes in the Turbine Building

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: B.2.a JPM

Title:

Line up Condenser Evacuation to AB stack Page 3 of 5 INITIATING CUE:

Due to High Activity in the RCS, the Shift Manager has directed you to line up Condenser Evacuation to the AUX Building Stack. You are to perform both the EONA and EONT portion of this procedure.

All Prerequisites given in OI-CE-1, attachment 2 are met.

Critical Steps shown in gray STEP ELEMENT STANDARD 1

Slowly Open VA-412 AB Corr. 26 Slowly Turn valve to OPEN position 2

Monitor VD-29, Condenser Evacuation Liquid Drain Trap, for water flow to drain hub Room 59 Monitor Trap for Flow CUE: Trickle flow (Do Not enter contaminated area) 3 Close the following valves:

• VD-359

• VD-360

• VD-361 Turbine Building EL 1011 Valves turned to CLOSE position 4

Notify Control Room prior to closing VD-423 CUE: Control room has been notified 5

Close VD-423 Turbine Building EL 1036 Turn Valve to CLOSED position CUE: Control Room reports condenser vacuum is steady

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: B.2.a JPM

Title:

Line up Condenser Evacuation to AB stack Page 4 of 5 STEP ELEMENT STANDARD Termination Criteria:

Condenser Evacuation is discharging through the AB Stack

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: B.2.A Page 5 of 5 INITIATING CUE:

Due to High Activity in the RCS, the Shift Manager has directed you to line up Condenser Evacuation to the AUX Building Stack. You are to perform both the EONA and EONT portion of this procedure.

All Prerequisites given in OI-CE-1, attachment 2 are met.

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RO B.2.b JPM

Title:

Startup Hydrogen Purge System Page 1 of 5 Location:

Aux Building Approximate Time:

10 minutes Actual Time: _________________

Reference(s):

OI-VA-1 Attachment 5A K/A 028000 A2.02 (RO 3.5 / SRO 3.9)

JPM Prepared by:

Jerry Koske Date:

JPM Reviewed by:

Date:

JPM Approved by:

Date:

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RO B.2.b JPM

Title:

Startup Hydrogen Purge System Page 2 of 5 Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment:

None Safety Considerations:

Performed in RCA Comments:

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RO B.2.b JPM

Title:

Startup Hydrogen Purge System Page 3 of 5 INITIATING CUE:

The plant is in accident recovery following a LOCA.

CIAS and VIAS have initiated. Containment hydrogen is

>3%. A containment hydrogen purge is required. You have been directed to perform the Aux building steps of OI-VA-1, attachment 5A to start a hydrogen purge using VA-80A.

The procedure is complete through step 6.

Critical Steps shown in gray STEP ELEMENT STANDARD 1

Ensure VA-411, VA-82 bypass is closed Corr. 26 IA-VA-411-B1 in FILTERED 2

Ensure VA-291/VA-279 combined remote operator is closed.

Corr 26 VA-291/VA-279 CLOSED 3

Ensure VA-282/VA-284 combined remote operator is closed.

Corr 26 VA-282/VA-284 CLOSED 4

Open hydrogen purge valves for VA-80A:

• VA-290

• VA-292

• VA-289:

Corr 26 Unlock and OPEN valves 5

Contact Control Room CUE: Control room reports procedure steps 8,9 and 10 have been completed 6

Start hydrogen purge fan AI-100 Place VA-80A control switch in PULL TO OVERRIDE Red Light ON Green Light OFF

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RO B.2.b JPM

Title:

Startup Hydrogen Purge System Page 4 of 5 STEP ELEMENT STANDARD 7

Monitor DPI-899D Corr 26 CUE: DPI-899D indicates 10w.g.

Termination Criteria:

Hydrogen purge has been started

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RO B.2.b Page 5 of 5 INITIATING CUE:

The plant is in accident recovery following a LOCA.

CIAS and VIAS have initiated. Containment hydrogen is

>3%. A containment hydrogen purge is required. You have been directed to perform the Aux building steps of OI-VA-1, attachment 5A to start a hydrogen purge using VA-80A.

The procedure is complete through step 6.

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: SRO B.2.b JPM

Title:

Waste Gas transfer from the vent header to the gas decay tank Page 1 of 5 Location:

Auxiliary Building Controlled Area Approximate Time:

10 minutes Actual Time: _________________

Reference(s):

OI-WDG-1, attachment 3 K/A 071000 A4.05 (RO 2.6 / SRO 2.6)

JPM Prepared by:

Jerry Koske Date:

JPM Reviewed by:

Date:

JPM Approved by:

Date:

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: SRO B.2.b JPM

Title:

Waste Gas transfer from the vent header to the gas decay tank Page 2 of 5 Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment:

None Safety Considerations:

This JPM is performed in the RCA Comments:

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: SRO B.2.b JPM

Title:

Waste Gas transfer from the vent header to the gas decay tank Page 3 of 5 INITIATING CUE:

Vent header pressure is at 2 psig and you are directed to pump the vent header to the in service gas decay tank using WD-28A until vent header pressure has been reduced to 1 psig AI-110 is inoperable. The Shift Chemist is on standby to take samples when notified.

All prerequisites are met.

Critical Steps shown in gray STEP ELEMENT STANDARD 1

Verify VCT gas sample is secured.

AI-110 WD-242 and WD-1080 indicate closed.

Note: If examinee contacts HP, CUE that valves have been surveyed and are not contaminated.

2 Verify that the gas vent header is drained Room 13 CUE: Before examinee enters room 13, tell him that The vent header in room 13 has been drained 3

Ensure that gas compressor is primed:

a. DW-156 is open

b. WD-28A moisture separator tank level visible below centerline Room 16

a. DW-156 is OPEN

b. CUE: Water level is above the pump rotor centerline 4

Drain moisture separator tank

a. OPEN WD-216

b. Drain

c. CLOSE WD-216 Room 16

a. WD-216 OPEN

b. CUE: Water level is below pump rotor centerline.

c. WD-216 CLOSED

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: SRO B.2.b JPM

Title:

Waste Gas transfer from the vent header to the gas decay tank Page 4 of 5 STEP ELEMENT STANDARD

5.

Start WD-28A to pump the Vent Header AI-100 WD-28A control switch to hand RED light ON 6

Monitor the following:

• WGDT Pressure

• Vent Header Pressure AI-100 CUE: WGDT = 65 psig Vent Header = 1.0 psig 7

Secure gas transfer AI-100 WD-28A control switch to OFF and GREEN light lit 8

Notify Shift Chemist to obtain grab samples.

CUE: Shift Chemist Acknowledges 9

Notify Shift manager to review Tech Spec 2.9 CUE: Shift Manager Notified 10 Check WGDT pressure CUE: Pressure is 70 psig.

Termination Criteria:

Waste gas has been transferred from the Vent Header to the in-service gas decay tank

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: SRO B.2.b Page 5 of 5 INITIATING CUE:

Vent header pressure is at 2 psig and you are directed to pump the vent header to the in service gas decay tank using WD-28A until vent header pressure has been reduced to 1 psig AI-110 is inoperable. The Shift Chemist is on standby to take samples when notified.

All prerequisites are met.

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: B.2.C JPM

Title:

Switch Inverter Power Supply from bypass to normal Page 1 of 6 Location:

Switchgear Room Approximate Time:

10 minutes Actual Time: _________________

Reference(s):

OI-EE-4, attachment 1 K/A 000057 AA1.01 (RO 3.7 / SRO 3.7)

JPM Prepared by:

Jerry Koske Date:

JPM Reviewed by:

Date:

JPM Approved by:

Date:

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: B.2.C JPM

Title:

Switch Inverter Power Supply from bypass to normal Page 2 of 6 Operators Name: _____________________ Employee # ______________

All Critical Steps (shaded) must be performed or simulated in accordance with the standards contained in this JPM The Operators performance was evaluated as (circle one):

SATISFACTORY UNSATISFACTORY Evaluators Signature: _____________________________ Date: __________

Reason, if unsatisfactory:

Tools & Equipment:

None Safety Considerations:

None Comments:

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: B.2.C JPM

Title:

Switch Inverter Power Supply from bypass to normal Page 3 of 6 INITIATING CUE:

Instrument Inverter A is out of service. AI-40A is being supplied by the bypass transformer. The electricians have cleared their tags and you have been directed to start up inverter A and place it in service.

All prerequisites are complete Critical Steps shown in gray STEP ELEMENT STANDARD 1

Ensure the input breaker, EE-8H-CB1 is open Inverter A (EE-8H)

Breaker in OPEN position 2

Ensure the DC source breaker at the DC panel is closed EE-8F DC Bus #1 EE-8F-CB24 breaker in CLOSED position 3

Ensure the manual (bypass) transfer switch S1 at the inverter is in bypass Inverter A (EE-8H)

S1 in BYPASS position 4

Precharge the inverter Inverter A (EE-8H)

Push precharge button on inverter and wait 10 seconds 5

Close input breaker EE-8H-CB1 Inverter A (EE-8H)

Place breaker in CLOSED position 6

Verify Sync loss light is on Inverter A (EE-8H)

CUE:Sync loss light is ON 7

Verify Reverse Transfer light is ON Inverter A (EE-8H)

CUE: Reverse transfer light is ON

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: B.2.C JPM

Title:

Switch Inverter Power Supply from bypass to normal Page 4 of 6 STEP ELEMENT STANDARD 8

Place S1 EE-8H manual transfer switch in the inverter position Inverter A (EE-8H)

EE-8H-S1 in INVERTER position 9

Ensure sync loss light is off Inverter A (EE-8H)

CUE: Sync Loss Light is ON 10 Terminate procedure and contact Shift Manager DOES NOT push Forward Transfer Button CUE: Electrical Maintenance has repaired inverter and Sync Loss light is now OFF. You are directed to continue with procedure.

11 Push the forward transfer button Inverter A (EE-8H)

PUSH forward transfer button 12 Verify Reverse Transfer light is off Inverter A (EE-8H)

CUE: Reverse Transfer light is OFF 13 Verify Forward Transfer light is on Inverter A (EE-8H)

CUE: Forward Transfer light is ON 14 Ensure EE-8H-CB3 vent fan breaker is closed Inverter A (EE-8H)

Breaker EE-8H-CB3 is in CLOSED position 15 Verify Inverter A output frequency and voltage Inverter A (EE-8H)

CUE: Frequency = 60.0 Hz Voltage = 120.1 volts

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: B.2.C JPM

Title:

Switch Inverter Power Supply from bypass to normal Page 5 of 6 Termination Criteria:

Instrument Bus AI-40A is being supplied by Inverter A

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: B.2.c Page 6 of 6 INITIATING CUE:

Instrument Inverter A is out of service. AI-40A is being supplied by the bypass transformer. The electricians have cleared their tags and you have been directed to start up inverter A and place it in service.

All prerequisites are complete

Appendix D Scenario Outline Form ES-D-2 Facility: Fort Calhoun Scenario No: 2002-1 Op-Test No. ___________

Examiners:

Operators:

Initial Conditions: [IC#124] 50% Reactor Power. 940 ppm boron D/G-1 is tagged out of service for generator brush replacement. Waste Monitor Tank, WD-22A, release is in progress.

[Take off CH-1B, Take RM-052 out of service]

[MFP ESF05A] [MFP ESF05B]

Turnover: Return RM-052 to service on the stack. It was taken out of service to install a new tape drive motor for RM-051. The maintenance is now complete. OI-RM-1-CL-B has been completed.

The local ratemeter keyswitch is on.

Event No.

Malf No.

Event Type*

Event Description 1

N Return RM-052 to service 2 [+10]

NIS02D I

WR NI channel D power supply failure

[MFP NIS02D]

3 [+20]

NBWPAC 9A C

Running Bearing water pump trips (must start backup)

[RFP BCW10A OPEN]

4 [+25]

RCP09B RCP10B C

Lower and middle seals on RCP, RC-3B fails

[MFP RCP09B 100%] [MFP RCP10B 100%]

5 R, N Plant shutdown due to two failed RCS seals 6 [+40]

T:L903X I

Steam Generator level channel fails low

[COP T:L903X 0%]

7 [+45]

GEN01A I

Main Generator voltage regulator fails

[MFP GEN01A full 120 sec ramp]

8 [+50]

RCS01E M

300 gpm LOCA caused by third seal failure on RC-3B

[MFP RCS01E 0.5%]

9 Preset:

ESF05A ESF05B C

PPLS fails to actuate

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 1 Event No.: 1 Page 2 of 10 Event

Description:

Return RM-052 to service Time Position Applicants Actions or Behavior SRO Direct RO to place RM-052 in service RO Ensure RM-052 Keyswitch is in Keypad RO Verify CNTMT amber light off, VENT red light on, Purge amber light off and control room green light is on RO Ensure pump control switch in stop and verify: pump off green light is on, sample flow high/low amber light is on, pump on red light is off, control room green light is on RO Verify RM-052 aligned to stack RO <C>

Place pump control switch to start and verify:

• Pump off green light is off

• Sample flow high/low amber light is off

• Pump on red light is on

• Sample flow between 0.8 and 5.00 SCFM in auto flow control mode

• Sample flow between 1.25 and 2.75 SCFM in manual flow control mode RO Verify RM-052 alert setpoint per TDB-IV.7 RO <C>

Verify RM-052 high setpoint per TDB-IV.7 RO Verify RM-052 alert setpoint on the ERF per TDB-IV.7 RO Verify RM-052 high setpoint on the ERF per TDB-IV.7 RO Ensure RM-052 ratemeter high alarm is reset RO <C>

Place RM-052 Control Room ratemeter keyswitch to ON RO Perform RM-052 check source test RO Ensure RM-052 returns to normal following check source test

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 1 Event No.: 2 Page 3 of 10 Event

Description:

WR NI Channel D power supply failure Time Position Applicants Actions or Behavior PRI Respond to Nuclear Instrument Channel Inoperative Alarm PRI or SEC Refer to ARP-CB4-A20 SRO Direct PRI to check operation of NIS channels PRI <C>

Report failure of WR channel D (NON-OP light lit)

SRO Optional : may refer to AOP-15 (not required at this power level)

SRO Optional: May direct PRI to bypass channel D SUR trip PRI If directed, bypass channel D SUR trip SRO

<C>

Enter Technical Specification 2.15 and enter 7 day LCO because WR channel D feed AI-212 on ASD panels

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 1 Event No.:3 Page 4 of 10 Event

Description:

Running Bearing water pump trips Time Position Applicants Actions or Behavior SEC Respond to Cooling Water Pressure Low alarm SEC Report that AC-9A tripped SRO

<C>

Direct SEC to start AC-9B SEC

<C>

Start AC-9B SRO Direct SEC to verify operation of air compressor SEC Verify operation of air compressors (CA-1C stops and restarts)

PRI Continue to monitor parameters associated with reactor startup SRO May enter AOP-20

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 1 Event No.: 4 Page 5 of 10 Event

Description:

Lower and Middle seals fail on RCP, RC-3B Time Position Applicants Actions or Behavior PRI Identify and communicate high seal leakage from alarms SRO Enter alarm response procedure PRI <C> Monitor RCP seal pressures and determine that the lower and middle sealsl on RCP B have failed SRO

<C>

Direct Emergency Shutdown and enter AOP-05 (Emergency Shutdown)

SEC Monitor secondary parameters

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 1 Event No.: 5 Page 6 of 10 Event

Description:

Plant Shutdown due to two failed RCP seals Time Position Applicants Actions or Behavior SRO May enter AOP-35. Direct PRI and SEC to commence Emergency Shutdown using AOP-05 SRO Notify System Operations of power decrease SRO Direct PRI to begin boration using SIRWT PRI <C> Switch charging pump suction from VCT to SIRWT SRO Direct SEC to control RCS T-cold by reducing turbine load SEC

<C>

Reduce turbine load to control T-cold SRO Direct PRI to operate control rods as required to control ASI PRI Operate control rods to control ASI PRI Monitor and control primary parameters SEC Monitor and control RCS T-cold and secondary parameters

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 1 Event No.: 6 Page 7 of 10 Event

Description:

Steam Generator level channel 903X fails low Time Position Applicants Actions or Behavior SEC Respond to FEEDWATER CONTROL STEAM GENERATOR RC-2A LEVEL LOW alarm PRI or SEC Obtain ARP-CB-4/A8 and determine actions SEC Identify and report failure of steam generator level channel LT-903X SRO Direct SEC to take manual control of Steam Generator, RC-2A level.

SEC<C> Take manual control of FCV-1101, restore and maintain level SRO Notify OCC of failure PRI Monitors primary parameters

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 1 Event No.:7 Page 8 of 10 Event

Description:

Main Generator Voltage Regulator Fails Time Position Applicants Actions or Behavior SEC Respond to GENERATOR VOLTS-PER-CYCLE HI alarm PRI or SEC Refer to ARP-CB-20/A14 SRO Direct SEC to transfer generator voltage regulator control to Manual and lower voltage to less than 23.8 kv SEC

<C>

transfer generator voltage regulator control to Manual and lower voltage to less than 23.8 kv SRO Notify OCC

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 1 Event No.:8 Page 9 of 10 Event

Description:

300 gpm LOCA caused by third seal failure on RC-3B Time Position Applicants Actions or Behavior PRI Identify and communicate lowering pressurizer pressure and level SRO May direct PRI to manually trip the reactor PRI Manually trip the reactor if directed SRO Direct Standard Post-Trip Actions PRI SEC Perform Standard Post Trip Actions:

• Verify control rod insertion, power lowering, negative startup rate

• Verify turbine trip and generator trip

• Verify electrical status - 4160, D/G, instrument power, 125V DC

• Verify instrument air status

• Verify CCW and raw water status

• Verify RCS inventory control

• Verify RCS pressure control

• Verify core heat removal

• Verify S/G feed

• Verify S/G pressure and T-cold

• Verify containment conditions PRI <C> Secure one RCP in each loop at 1350 psia PRI Secure remaining RCPs on loss of NPSH SRO Transition to EOP-03 (LOCA)

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 1 Event No.: 9 Page 10 of 10 Event

Description:

PPLS fails to actuate Time Position Applicants Actions or Behavior PRI Monitor for automatic PPLS actuation PRI Determine and report that PPLS failed to actuate SRO

<C>

Direct PRI to manually initiate PPLS PRI <C>

Manually initiate PPLS PRI Verify and report PPLS actuation and adequate SI flow SRO Direct PRI and SEC to begin RCS cooldown SEC Begin RCS cooldown PRI Monitor primary parameters Scenario ends when all safety functions are met and cooldown is in progress

Appendix D Scenario Outline Form ES-D-1 Facility: Fort Calhoun Scenario No: 2002-2 Op-Test No. ___________

Examiners:

Operators:

Initial Conditions: [IC# 122] 100% Reactor Power. 517 ppm boron D/G-1 is tagged out of service for generator brush replacement.

[Make AC-3A running CCW pump] [MFP ESF06A OFF] [MFP ESF06B OFF]

[COP RSGH042A 100%] [ovr A9 B1U turb diff exp alarm off]

Turnover: Place CCW Pump, AC-3C in service and remove AC-3A from service.

Event No.

Malf No.

Event Type*

Event Description 1

N Rotate CCW pumps

[ will need RFP CCW12A ]

2 [+8] T:P910 I

PIC-910 fails high causing turbine bypass valve to open

[ COP T:P910 1000 psi]

3

[+13]

T:T2897 I

Letdown HX CCW outlet temperature transmitter, T-2897, fails low. (results in high letdown temperature)

[COP T:T2897 50 ]

4

[+20]

CRD06 C

Dropped Control rod

[MFP CRD06 rod 1 grp 4 deenergized]

5 R, N Reduce power to 70% due to dropped rod 6

[+35]

T:P103Y I

Controlling pressurizer pressure channel fails high

[COP T:P103Y]

7

[+40]

MSS03B M

Main steam line break in turbine building

[MFP MSS03B 20% 60 sec ramp]

8 Preset RSGH042A C

SGIS fails to actuate 9

Preset ESF06A,B C

S/G B MSIV will not close

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 2 Event No.: 1 Page 2 of 11 Event

Description:

Rotate CCW pumps Time Position Applicants Actions or Behavior SRO Directs PRI to switch operating CCW pump from Pump AC-3A to Pump AC-3C.

PRI Obtains and reviews Procedure OI-CC-1, Attachment 2.

PRI Directs local operator to Room 69.

PRI <C> Starts pump AC-3C and directs closure of Valve AC-102 (Pump AC-3A discharge valve).

PRI <C> Stops pump AC-3A and takes hand switch to pull-to-Lock.

PRI Ensures proper operation of pump AC-3C. Directs local operator to reopen Valve AC-102.

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 2 Event No.: 2 Page 3 of 11 Event

Description:

PIC-910 fails high causing turbine bypass valve to open Time Position Applicants Actions or Behavior SEC Identify rapid decrease in RCS T cold (VOPT ANN will alarm if uncorrected)

SEC Determine cause as turbine bypass valve being open (red light on CB-10,11)

SRO

<C>

Direct SEC to take manual control of PCV-910 and close valve SEC

<C>

Take manual control of PCV-910 and close it SEC Monitor RCS Tc PRI Monitor and control RCS parameters SRO Notify I & C of failure

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 2 Event No.: 3 Page 4 of 11 Event

Description:

Letdown HX CCW outlet temperature transmitter, T-2897, fails low Time Position Applicants Actions or Behavior PRI Respond to Letdown Heat Exchanger Tube Outlet Temp HI Alarm PRI Determine that TCV-211-2 has repositioned to bypass demineralizers PRI Determine high temperature due to reduced CCW flow to letdown heat exchanger following closure of TCV-2897 SRO

<C>

Direct PRI to manually control CCW flow to letdown HX using TCV-2897 PRI <C>

Manually control TCV-2897to restore letdown temperature SRO May direct PRI to reposition TCV-211-2 and maintain 100°F - 120°F PRI Reposition TCV-211-2 if directed PRI Monitor primary parameters SEC Monitor secondary parameters

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 2 Event No.: 4 Page 5 of 11 Event

Description:

Dropped Control Rod Time Position Applicants Actions or Behavior PRI Identify event from Dropped Rod and other alarms PRI <C> Determine only one rod has dropped (rod #1, grp 4)

SRO Enter AOP-02 (CEDM Malfunction)

SRO

<C>

Direct SEC to adjust turbine load to match reactor power SEC

<C>

Adjust turbine load to match reactor power SRO Direct RO to control pressurizer pressure and level PRI Monitor Pressurizer pressure and level SRO Direct PRI to reset Rod Drop Bistables PRI Reset Rod Drop Bistables SRO Notify Reactor Engineer SRO Consult Tech Sec 2.10.2. (Note: Requirements of this Tech Spec are covered in the actions required by AOP-02 SRO

<C>

Inform RO and SEC that Tech Specs require a power reduction to less than 70% within one hour SRO Notify system Operations of impending power reduction SEC Continue manual control of S/G level

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 2 Event No.: 5 Page 6 of 11 Event

Description:

Reduce Power to 70% due to dropped rod Time Position Applicants Actions or Behavior SRO Direct RO and BOP to commence power reduction SRO Direct RO on method of boration to use. (Options are normal boration, shifting charging pump suction to the SIRWT, or entering AOP-05 (Emergency Shutdown)

PRI<C>

Begin boration SEC<C>

Reduce turbine load to control RCS Tc.

PRI Monitor and control primary parameters during power reduction SEC Monitor and control secondary parameters during power reduction SRO Contact chemistry to sample RCS due to downpower RO May contact Aux Building operator about waste tank level for power reduction

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 2 Event No.: 6 Page 7 of 11 Event

Description:

Controlling pressurizer pressure channel fails high Time Position Applicants Actions or Behavior PRI Respond to Pressurizer Pressure Off Normal HI/LO Channel Y Alarm PRI Identify and report high indication on controlling channel and lowering pressure on other channel PRI/SE C

Obtain ARP and verify actions SRO

<C>

Direct PRI to transfer control to X channel or take manual control of pressurizer pressure PRI <C>

Transfer control channel or take manual control as directed to maintain pressure as directed by SRO (2075 - 2175 psia)

PRI Monitor and Maintain proper pressurizer pressure SEC Monitor and control secondary parameters

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 2 Event No.: 7 Page 8 of 11 Event

Description:

Main Steam line break in turbine building Time Position Applicants Actions or Behavior PRI Report lowering trends in T-cold, pressurizer pressure and level SEC Report lowering Steam generator pressure SRO May direct manual reactor trip PRI Manually trip the reactor if directed SRO<C>

Direct Standard Post-Trip Actions PRI<C>

SEC<C>

Perform Standard Post Trip Actions:

• Verify control rod insertion, power lowering, negative startup rate

• Verify turbine trip and generator trip

• Verify electrical status - 4160, D/G, instrument power, 125V DC

• Verify instrument air status

• Verify CCW and raw water status

• Verify RCS inventory control

• Verify RCS pressure control

• Verify core heat removal

• Verify S/G feed

• Verify S/G pressure and T-cold

• Verify containment conditions

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 2 Event No.: 8 Page 9 of 11 Event

Description:

SGIS fails to actuate Time Position Applicants Actions or Behavior SEC Identify and report that SGIS did not actuate SRO Direct SEC to manually perform SGIS actions SEC<C> Manually perform SGIS actions by closing MSIVs and FW isolation valves

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.: 2 Event No.: 9 Page 10 of 11 Event

Description:

S/G B MSIV will not close Time Position Applicants Actions or Behavior SEC<C>

Report that MSIV on B S/G did not close SRO Perform diagnostic actions and transition to EOP-05 (note: some of the following actions may be performed prior to EOP-05 entry)

SRO<C>

Direct SEC to begin steaming from A S/G before B S/G dries out SEC<C>

Begin steaming from A S/G using MS-291 before B S/G dries out SRO Direct PRI to ensure proper actuation of ESF PRI Ensure SI flow is maximized PRI Trip 1 RCP in each loop if RCS pressure reaches 1350 psia SRO Direct PRI to ensure Emergency Boration PRI Ensure Emergency Boration SRO Direct SEC to establish AFW flow to good S/G SEC Establish AFW flow to good S/G SEC Identify affected S/G (perform 16A,B,C of EOP-05)

SRO<C>

Direct SEC to isolate AFW flow to affected S/G SEC<C>

Isolate affected S/G PRI Report when HPSI stop and throttle criteria is met SRO Direct PRI to perform HPSI stop and throttle PRI <C>

Perform HPSI stop and throttle SRO/PRI Ensure Stop and Throttle criteria continues to be met

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.:2 Event No.:9 cont Page 11 of 11 Event

Description:

S/G B MSIV will not close Time Position Applicants Actions or Behavior SRO Direct PRI to control charging flow and reestablish letdown if needed to control RCS temperature and pressure PRI Control charging/ reestablish letdown if required END Scenario ends with HPSI stop and throttle and RCS pressure and temperature under control

Appendix D Scenario Outline Form ES-D-1 Facility: Fort Calhoun Scenario No: 2002-3 (spare)

Op-Test No. ___________

Examiners:

Operators:

Initial Conditions: [IC#2] 100% Power. FW-54 tagged out to replace fuel pump. Power Range NI channel A is out of service due to failed power supply. A Trip units 1,9 and 12 have been bypassed. FIA-236 is failed. In T.S.2.14

[RFP RCP12B close] [File ATWAS PLUS] [RFP AFW25A STOP] [RFP AFW26A local]

[COP T:F236 0%] [MFP NIS07A] [MFP AFW01] [ bypass keys in A TUs 1,9,12]

[A RPS to delta T power]

Turnover: Place CH-1A in service remove CH-1C from service CH-1A packing cooling pump has been operating for 45 minutes.

Event No.

Malf No.

Event Type*

Event Description 1

N Place CH-1A in service remove CH-1C from service 2 [+5] JLB218LL I

VCT level fails low causing charging pump suction to realign to SIRWT. [COP JLB218LL fail set]

3

[+12]

NIS07D I

Power Range NI Channel D Fails

[MFP NIS07D]

4 R, N Power reduction to 70% power.

5

[+40]

SWD02A,B M

Loss of offsite power (both 161KV and 345 KV)

[MFP SWD02A] [MFP SWD 02B]

6 preset C, M Auto Reactor trip fails (ATWS) 7 preset C

Turbine driven AFW pump, FW-10 fails to start.

8 preset C

RC-3C breaker does not open. (D/G-1 output breaker does not close)

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.:3 Event No.:1 Page 2 of 8 Event

Description:

Place CH-1A in service remove CH-1B from service Time Position Applicants Actions or Behavior SRO Direct PRI to place CH-1A in service and remove CH-1C from service PRI Obtain OI-CH-1, Attachment 5 PRI<C>

Start CH-1A PRI Verify operation of CH-1A by observing pump amps or VCT level (Normal means, FIA-236, is not available)

PRI<C>

Stop CH-1C PRI<C>

Place Charging Pumps Mode Select Stby switch to CH-1B,1C position PRI Report completion of pump rotation.

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.:3 Event No.:2 Page 3 of 8 Event

Description:

VCT level fails low causing charging pump to realign to SIRWT Time Position Applicants Actions or Behavior PRI Respond to Volume Control Tank Level LO-LO alarm PRI or SEC Obtain ARP-CB-1,2,3/A2 SRO Direct PRI to check VCT level PRI Report level on channel LIC-219 is normal PRI Report charging pump suction swapped to SIRWT SRO/PRI Determine that level switch failed SRO

<C>

Direct PRI to manually open LCV-218-2 and close LCV-218-3 PRI <C>

Open LCV-218-2 and close LCV-218-3 PRI Monitor and control primary parameters SEC Monitor and control secondary parameters PRI Optional: may place off-normal placard on LCV-218-2 switch SRO Notify OCC of failure

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.:3 Event No.:3 Page 4 of 8 Event

Description:

Power range NI Channel D Fails Time Position Applicants Actions or Behavior PRI Identify the failure from reflash of alarms SRO Reference AOP-15 SRO Determine the need to place D channel trip units 1,9 & 12 in the tripped condition (may simulate pulling trip unit cards, may use power trip test interlock or may call I&C)

SRO

<C>

Determine the need to lower power to 70% per OP-4 IAW AOP-15 SEC Enter channel failure in control room log

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.:3 Event No.: 4 Page 5 of 8 Event

Description:

Power reduction to 70% power.

Time Position Applicants Actions or Behavior SRO Direct PRI and SEC to commence power reduction using OP-4 SRO Direct PRI on method of boration to use.

SRO Request ASI guidance and provide to RO PRI <C> Begin boration (approximately 138 gallons boric acid)

SEC

<C>

Reduce turbine load to control Tc PRI Monitor and control primary parameters during power reduction SEC Monitor and control secondary parameters during power reduction

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.:3 Event No.:5 and 6 Page 6 of 8 Event

Description:

Loss of offsite power (both 161 KV and 345 KV) with ATWS Time Position Applicants Actions or Behavior PRI Determine and communicate that the reactor failed to trip.

SRO Direct PRI to manually trip the reactor PRI<C>

Push CB-4 manual Reactor Trip Pushbutton.

SEC Determine and communicate that Trip did not actuate.

SRO Direct the PRI and SEC to initiate RPS panel (AI-31) trip and DSS trip.

SEC<C>

Operate DSS Trip.

PRI Determine and communicate that the rods have inserted.

SRO Direct PRI and SEC to take Standard Post Trip Actions (SPTAs).

PRI SEC Perform Standard Post Trip Actions:

• Verify control rod insertion, power lowering, negative startup rate

• Verify turbine trip and generator trip

• Verify electrical status - 4160, D/G, instrument power, 125V DC Report 4160 bus 1A3 is deenergized

• Verify instrument air status

• Verify CCW and raw water status

• Verify RCS inventory control

• Verify RCS pressure control

• Verify core heat removal

• Verify S/G Feed Report loss of feedwater

• Verify S/G pressure and T-cold

• Verify containment conditions SRO Direct PRI or SEC to have EONT minimize DC loads PRI or SEC <C>

Direct EONT to minimize DC loads SRO Verify completion of SPTAs

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.:3 Event No.:7 Page 7 of 8 Event

Description:

Turbine Driven AFW pump, FW-10 fails to start Time Position Applicants Actions or Behavior SEC<C> Attempt to start FW-10 SEC Report loss of FW-10 SRO Direct BOP to monitor S/G level SEC Monitor and report S/G level SRO Enter EOP-06 or EOP-20 due to a loss of all feedwater SRO Determine that heat removal safety function is not being met.

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.:3 Event No.:8 Page 8 of 8 Event

Description:

RC-3C breaker does not open (D/G-1 output breaker does not close)

Time Position Applicants Actions or Behavior PRI Identify failure of RC-3C breaker to open PRI Report failure of breaker to open SRO Direct PRI to direct EONT to manually trip breaker PRI<C>

Direct EONT to manually trip RC-3C breaker SRO Direct SEC to verify restoration of power to bus 1A3 SEC Verify power to bus 1A3 SRO Direct SEC to start FW-6 SEC<C> Starts FW-6 SEC Ensure flowpath to Steam Generators Termination Criteria: FW being supplied to at least one steam generator or Once through cooling in progress

Appendix D Scenario Outline Form ES-D-1 Facility: Fort Calhoun Scenario No: 2002-4 (spare)

Op-Test No. ___________

Examiners:

Operators:

Initial Conditions: [IC#2]100% Power. FW-54 tagged out to replace fuel pump. Safety Injection Tank SI-6B has a low level alarm.

[Lower level in SI-6B] [Disable autostart of CCW pumps]

Turnover: Raise level in Safety Injection Tank SI-6B Event No.

Malf No.

Event Type*

Event Description 1

N Raise level in Safety Injection tank SI-6B 2

NCCPAC3B C

CCW pump trips

[COP NCCPAC3B]

3 SGN01B C

Tube leak on steam generator RC-2B

[MFP SGN01B 1%]

4 R, N AOP-5 plant shutdown 5

T:P907 I

Steam generator pressure transmitter on RC-2A fails low

[COP T:P907 45.1 psi]

6 CND01 M

Loss of condenser vacuum - Reactor Trip

[MFP CND01 100% 300 sec ramp]

7 SGN01A M

Steam Generator Tube Rupture - RC-2A

[MFP SGN01A 40%]

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.:4 Event No.: 1 Page 2 of 8 Event

Description:

raise level in safety Injection tank SI-6B Time Position Applicants Actions or Behavior SRO Directs BOP to raise SIT SI-6B level to 72% using HPSI Pump SI-2A and HCV-311 or HCV-312 IAW OI-SI-1, Attachment 4.

PRI Ensures that recirculation valves HCV-385 and HCV-386 are open and HCV-2983 is closed.

PRI Start SI-2A. Recirc for 15 minutes. CUE: ASSUME 15 MINUTES HAVE ELAPSED.

PRI Stop HPSI Pump SI-2A.

PRI Open loop injection valve HCV-312 or HCV-311.

PRI Open leakage control valve PCV-2909 by placing in MANUAL and controller in OPEN.

PRI Open HCV-2909, fill and drain valve, for desired tank to be filled.

PRI Restart HPCI Pump SI-2A.

PRI Stop HPCI Pump SI-2A when 72% level is reached and level alarm ASAFETY INJECTION TANK SI-6B LO LEVEL@ on Panel A7 has cleared.

PRI Close HCV-2916.

PRI Close HCV-312 or HCV-311.

PRI Place PCV-2909 in CLOSE and valve control in AUTO.

LSO Verify that HPSI loop injection valve is operable by lit amber light on valve used to fill tank.

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.:4 Event No.: 2 Page 3 of 8 Event

Description:

Running CCW pump trips Time Position Applicants Actions or Behavior PRI Respond to CCW Pumps Trip alarm PRI Identify and report CCW pump trip PRI Determine and report autostart failure of backup CCW pumps SRO Direct PRI to manually start a CCW pump PRI<C>

Start a CCW pump SRO Direct PRI to monitor CCW pump discharge pressure and flow PRI Verify CCW operating parameters SRO Report CCW pump trip and autostart failures to OCC

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.:4 Event No.: 3 Page 4 of 8 Event

Description:

Tube leak on Steam generator RC-2B (30 gpm)

Time Position Applicants Actions or Behavior PRI Respond to condenser off-gas radiation alarm (RM-057) and rising trend on RM-054B PRI Identify and report charging/letdown mismatch SRO Enter AOP-22 (May also enter SO G-105)

SRO Direct PRI to control pressurizer level PRI Control pressurizer level SEC Ensure that RCV-978 is closed SRO Initiate Emergency Shutdown (AOP-5)

SRO Identify affected steam generator. (RC-2B)

SRO Direct PRI or SEC to place steamline radiation monitor in service PRI or SEC Place steamline radiation monitor in service (RM-064)

SRO Direct PRI or SEC to have EONA swap blowdown sample flow to waste PRI or SEC Direct EONA to swap blowdown sample flow to waste SRO May direct SEC to place YCV-1045B in override and close

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.:4 Event No.: 4 Page 5 of 8 Event

Description:

AOP-05 Plant Shutdown Time Position Applicants Actions or Behavior SRO Enter AOP-05 (Emergency Shutdown) - Direct Emergency Shutdown SRO Notify System Operations of Power Decrease SRO Direct PRI to begin boration using SIRWT PRI Switch charging pump suction from the VCT to the SIRWT PRI Direct SEC to control RCS cold leg temperature by reducing turbine load SEC Reduce turbine load to control cold leg temperature SRO Direct PRI to operate control rods to control ASI PRI Operate Control Rods to control ASI PRI Monitor and control primary parameters SEC Monitor and control RCS cold leg temperature and secondary parameters SRO Continue to coordinate PRI and SEC actions during power reduction

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.:4 Event No.:5 Page 6 of 8 Event

Description:

Steam Generator pressure transmitter on RC-2A fails low Time Position Applicants Actions or Behavior SEC Identify and communicate lowering FW flow and level in S/G, RC-2A SRO Direct SEC to take manual control of Feedwater SEC<C> Take manual control of feedwater and restore level in RC-2A SEC Identify PT-907 as the failed instrument SRO Inform OCC of the failure of PT-907 SEC Continue to monitor and control S/G level PRI Monitor primary parameters

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.:4 Event No.: 6 Page 7 of 8 Event

Description:

Loss of Condenser Vacuum - Reactor Trip Time Position Applicants Actions or Behavior SRO/PRI/

SEC Recognizes ERF computer alarm for ACONDENSER A/B PRESSURE LOW@ and possibly a ATURBINE HOOD PRESSURE HI@ alarm.

LSO Directs SEC to monitor condenser vacuum trend.

SEC/PRI Reviews Procedure ARP-CB-10, 11/A9 (Window B-6L) and takes appropriate actions:

Dispatches equipment operator to check vacuum pump operation.

Monitors vacuum trend.

SEC Determines that vacuum continues to decrease. Starts FW-8B backup vacuum pump.

SRO Directs entry into AOP-26,Section I.

SEC Reviews AOP-26 and determines that condenser vacuum has slowly decreased to <25".

SRO (C)

Directs plant shutdown (at <10%/min) in accordance with AOP-05 in an attempt to reduce vacuum loss. Note: AOP also allows use of OP-4 SRO Directs operators to perform standard post-trip actions PRI/SEC Perform standard post-trip actions

Appendix D Operator Actions Form ES-D-2 Op-Test No.:

Scenario No.:4 Event No.: 7 Page 8 of 8 Event

Description:

Steam generator Tube Rupture - RC-2A Time Position Applicants Actions or Behavior PRI Identify and report RCS inventory loss SRO May direct reactor trip SRO Following manual or auto reactor trip, direct standard post trip actions PRI SEC Perform Standard Post Trip Actions:

• Verify control rod insertion, power lowering, negative startup rate

• Verify turbine trip and generator trip

• Verify electrical status - 4160, D/G, instrument power, 125V DC

• Verify instrument air status

• Verify CCW and raw water status

• Verify RCS inventory control

• Verify RCS pressure control

• Verify core heat removal

• Verify S/G feed

• Verify S/G pressure and T-cold

• Verify containment conditions SRO Diagnose tube rupture - enter EOP-04 or EOP-20 SRO Direct RCS cooldown - Thot less than 510°F SEC Cooldown RCS Thot to less than 510°F PRI Identify and verify PPLS SRO SEC Identify most affected steam generator (A)

SRO Direct SEC to isolate steam generator A SEC Isolate steam generator A SRO Direct RO to depressurize RCS to less than 1000 psia PRI Depressurize the RCS PRI Maintain subcooling SEC Monitor and control secondary parameters Block SGLS during cooldown.

PRI Monitor and control primary parameters