Text

FC-2012-04 Final Operating Test
	ML12156A003
Person / Time
Site:	Fort Calhoun
Issue date:	04/20/2012
From:	Kelly Clayton; Operations Branch IV
To:	;
References
	50-285/12-004
	Download: ML12156A003 (313)
	v • d • e

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Fort Calhoun Station Date of Examination: April 16, 2012 Examination Level: RO Operating Test Number: 2012-01 Administrative Topic Type Describe activity to be performed (see Note) Code*

Calculate the estimated critical boron concentration for a reactor startup (Per TDB-II worksheet and curves)

RA1: Conduct of Operations N, R K/A 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc (CFR: 41.10, 45.12)

RO IR: 3.9 Performa a Quadrant Power Tilt Calculation with Excore detectors operable and ERF inoperable per OI-NI-1 RA2: Conduct of Operations N, R K/A 2.1.20 Ability to interpret and execute procedure steps (CFR: 41.10, 45.12)

RO IR: 4.6 Prepare a manual clearance for maintenance on component cooling water pump AC-3C.

RA3: Equipment Control N, R K/A 2.2.13 Knowledge of tagging and clearance procedures (CFR: 41.10, 45.13)

RO IR: 4.1 Determine whether to install shielding based on given dose rates and work times.

RA4: Radiation Control K/A 2.3.12 Knowledge of radiological safety principles N, R pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc. (CFR: 45.9, 45.10)

RO IR: 3.2 Emergency Procedures/Plan N/A NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)

(N)ew or (M)odified from bank ( 1)

(P)revious 2 exams ( 1; randomly selected)

ES-301 Administrative Topics Outline Form ES-301-1

Facility: Fort Calhoun Station Date of Examination: April 16, 2012 Examination Level: SRO Operating Test Number: 2012-01 Administrative Topic Type Describe activity to be performed (see Note) Code*

Calculate amount of water and boric acid required to raise SIRWT level ten inches and maintain current SIRWT boric acid concentration.

SA1: Conduct of Operations N, R K/A 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.

(CFR: 43.5, 45.12)

SRO IR: 4.2 Perform a Quadrant Power Tilt Calculation with Excore detectors operable and ERF inoperable per OI-NI-1 SA2: Conduct of Operations N, R K/A 2.1.20 Ability to interpret and execute procedure (same as RA2) steps (CFR: 43.5, 45.12)

SRO IR: 4.6 Review manual clearance for maintenance on component cooling water pump AC-3C.

SA3: Equipment Control N, R K/A 2.2.13 Knowledge of tagging and clearance procedures (CFR: 45.13)

SRO IR: 4.3 Determine whether to install shielding based on given dose rates and work times.

SA4: Radiation Control K/A 2.3.12 Knowledge of radiological safety principles N, R pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc. (CFR: 45.9, 45.10)

SRO IR: 3.7 Determine Emergency Action Level for a given emergency.

SA5: Emergency K/A 2.4.38 Ability to take actions called for in the facility N, R emergency plan, including supporting or acting as Procedures/Plan emergency coordinator if required. (CFR: 43.5, 45.11)

SRO IR: 4.4 NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)

(N)ew or (M)odified from bank ( 1)

(P)revious 2 exams ( 1; randomly selected)

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Fort Calhoun Station Date of Examination: April 16, 2012 Exam Level: RO Operating Test No.: 2012-01 Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function S-1: Swap pressurizer pressure mode from manual to automatic, N, A, S 3 followed by spurious actuation of PORV (block valve initially fails to close)

S-2: Engineered Safeguards Actuation Verification (A PPLS relay N, EN, A, S 2 fails to actuate, requiring manual initiation of PPLS, and HPSI injection valves fail to open, requiring control room action to open)

S-3: Place a containment cooling unit in service (VA-8A/VA-7C) D, S 5 S-4: Place shutdown cooling in service per OI-SC-1, Att. 1 N, L, S 4P S-5: Maintain S/G water levels during startup using AFW. (Loss of N, A, L, S 4S AFW, have to start a main feedwater pump to restore flow)

S-6: Valve stroke time testing of containment pressure relief valve N, S 8 HCV-246B S-7: Dilute to achieve desired boron concentration for desired critical N, A, L, S 1 rod height (an unexpected reactivity increase occurs, requiring securing of dilution)

S-8: Transfer non-vital buses 1A1 and 1A2 onto 345kV bus per AOP- N, S 6 32 In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

P-1: Respond to a steam bound AFW pump FW-6 (MDAFW pump) D, E 4S P-2: Rack down a non-remote equipped 4160V circuit breaker N 6 P-3: Waste gas transfer from the vent header to the gas decay tank D, A, R 9

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

Type Codes Criteria for RO / SRO-I / SRO-U

(A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank 9/8/4 (E)mergency or abnormal in-plant 1/1/1 (EN)gineered safety feature - / - / 1 (control room system)

(L)ow-Power / Shutdown 1/1/1 (N)ew or (M)odified from bank including 1(A) 2/2/1 (P)revious 2 exams 3 / 3 / 2 (randomly selected)

(R)CA 1/1/1 (S)imulator

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Fort Calhoun Station Date of Examination: April 16, 2012 Exam Level: SRO-I Operating Test No.: 2012-01 Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function S-1: Swap pressurizer pressure mode from manual to automatic, N, A, S 3 followed by spurious actuation of PORV (block valve initially fails to close)

S-2: Engineered Safeguards Actuation Verification (A PPLS relay N, EN, A, S 2 fails to actuate, requiring manual initiation of PPLS, and HPSI injection valves fail to open, requiring control room action to open)

S-3: Place a containment cooling unit in service (VA-8A/VA-7C) D, S 5 S-5: Maintain S/G water levels during startup using AFW. (Loss of N, A, L, S 4S AFW, have to start a main feedwater pump to restore flow)

S-6: Valve stroke time testing of containment pressure relief valve N, S 8 HCV-246B S-7: Dilute to achieve desired boron concentration for desired critical N, A, L, S 1 rod height (an unexpected reactivity increase occurs, requiring securing of dilution)

S-8: Transfer non-vital buses 1A1 and 1A2 onto 345kV bus per AOP- N, S 6 32 In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

P-1: Respond to a steam bound AFW pump FW-6 (MDAFW pump) D, E 4S P-2: Rack down a non-remote equipped 4160V circuit breaker N 6 P-3: Waste gas transfer from the vent header to the gas decay tank D, A, R 9

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

Type Codes Criteria for RO / SRO-I / SRO-U

(A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank 9/8/4 (E)mergency or abnormal in-plant 1/1/1 (EN)gineered safety feature - / - / 1 (control room system)

(L)ow-Power / Shutdown 1/1/1 (N)ew or (M)odified from bank including 1(A) 2/2/1 (P)revious 2 exams 3 / 3 / 2 (randomly selected)

(R)CA 1/1/1 (S)imulator

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Fort Calhoun Station Date of Examination: April 16, 2012 Exam Level: SRO-U Operating Test No.: 2012-01 Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System / JPM Title Type Code* Safety Function S-1: Swap pressurizer pressure mode from manual to automatic, N, A, S 3 followed by spurious actuation of PORV (block valve initially fails to close)

S-2: Engineered Safeguards Actuation Verification (A PPLS relay N, EN, A, S 2 fails to actuate, requiring manual initiation of PPLS, and HPSI injection valves fail to open, requiring control room action to open)

S-7: Dilute to achieve desired boron concentration for desired critical N, A, L, S 1 rod height (an unexpected reactivity increase occurs, requiring securing of dilution)

In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

P-1: Respond to a steam bound AFW pump FW-6 (MDAFW pump) D, E 4S P-3: Waste gas transfer from the vent header to the gas decay tank D, A, R 9

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank 9/8/4 (E)mergency or abnormal in-plant 1/1/1 (EN)gineered safety feature - / - / 1 (control room system)

(L)ow-Power / Shutdown 1/1/1 (N)ew or (M)odified from bank including 1(A) 2/2/1 (P)revious 2 exams 3 / 3 / 2 (randomly selected)

(R)CA 1/1/1 (S)imulator

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RA1 Rev 3 JPM

Title:

Estimated Critical Condition Calculation Location: Classroom Approximate Time: 30 minutes Start Time:__________________

End Time:___________________

Actual Time: _________________

Reference(s): K/A# 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.

Procedures: TDB-V-1-B, Estimated Critical Conditions Worksheet, Rev 23, TDB-II, Reactivity Curves, Rev 32 Handout(s): TDB-V-1-B Task List#: 1528 Applicable Position(s): RO/SRO Time Critical: No Alternate Path: No JPM Prepared by: Jerry Koske Date: 3/22/12 Page 1 of 7

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RA1 Rev 3 JPM

Title:

Estimated Critical Condition Calculation Operators Name:

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:

Comments:

Page 2 of 7

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RA1 Rev 3 JPM

Title:

Estimated Critical Condition Calculation TASK The Applicant calculated the estimated critical boron STANDARD: concentration for a reactor startup using the given conditions, the Estimated Critical Conditions Worksheet and the Reactivity Curves in TDB-II. The estimated critical boron concentration was determined to be approximately 1000 ppm (950 - 1050 ppm)

INITIAL CONDITIONS:

The plant is shutdown as the result of a reactor trip and a reactor startup is scheduled at 0900 on 4/15/12.

Shutdown from 100% power occurred at 2000 on 4/13/12

The plant was operating with all rods out prior to the trip

Boron concentration prior to the trip was 638 ppm

Average core burnup is 6,000 MWD/MTU

The Reactor Engineer has specified a desired CEA position for criticality, group 4 at 85 inches

Boron concentration was increased to 750 ppm to ensure adequate shutdown margin

DEN-Nuclear states that no correction is needed for boron depletion INITIATING CUE: You are directed to determine the estimated critical boron concentration for this startup.

Another Operator will determine the amount of Water or Acid needed to change the boron concentration.

Page 3 of 7

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RA1 Rev 3 JPM

Title:

Estimated Critical Condition Calculation Critical Steps shown in gray and **

STEP ELEMENT STANDARD 1 Obtains TDB-V.1.B, Estimated Located TDB-V.1.B Critical Conditions Worksheet from the Technical Data Book. [ SAT ] [ UNSAT ]

NOTE: Provide procedure copy after it is located in TDB.

2 (A.1) Records the following: Recorded 4/13/12 @ 2000 Shutdown date and time

[ SAT ] [ UNSAT ]

3 (A.2) Reactor power before Recorded 100%

shutdown

[ SAT ] [ UNSAT ]

4 (A.3) CEA positions before time of Recorded 126 for all groups shutdown

[ SAT ] [ UNSAT ]

5 (A.4) Reactor Coolant System boron Recorded 638 ppm concentration before shutdown.

[ SAT ] [ UNSAT ]

6 (A.5) Core average burnup Recorded 6000 MWD/MTU

[ SAT ] [ UNSAT ]

7 (B.1) Startup date and time Recorded 4/15/12 @ 0900

[ SAT ] [ UNSAT ]

8 (B.2) Time interval between Calculated and recorded 37 shutdown and startup hours

[ SAT ] [ UNSAT ]

Page 4 of 7

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RA1 Rev 3 JPM

Title:

Estimated Critical Condition Calculation STEP ELEMENT STANDARD 9 (B.3) Desired CEA positions at time Recorded 85 for group 4 and of startup. (Manual Sequential 126 for all other groups Mode)

[ SAT ] [ UNSAT ]

10 (B.4) Present Reactor Coolant Recorded 750 ppm System boron concentration

[ SAT ] [ UNSAT ]

11 (C.1) Reactivity change due to Used one of the selected change in power: figures. Recorded Using TDB Figure II.C.2.a or approximately 1.60-1.71 II.C.2.b, the power level from depending on figure used.

A.2, and the Average Core Burnup from A.5, record [ SAT ] [ UNSAT ]

the power defect added due to the shutdown.

12 (C.2) Reactivity change due to Used one of the selected control rod position change: figures. Calculated and recorded approximately -0.17 to -0.19 (C.2.c) depending on figure used.

[ SAT ] [ UNSAT ]

13 (C.3) Reactivity change due to Used the referenced figures.

changes in Xenon Recorded approximately Concentrations. 1.50% delta rho

[ SAT ] [ UNSAT ]

14 (C.4) Reactivity change due to Used the referenced figures.

change in boron concentration. Calculated and recorded approximately -0.94% delta rho

[ SAT ] [ UNSAT ]

Page 5 of 7

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RA1 Rev 3 JPM

Title:

Estimated Critical Condition Calculation STEP ELEMENT STANDARD 15 (C.5) Sum of reactivity changes: Entered values, calculated and entered approximately 2.097 (1.7-2.5) % delta rho (C.5.e)

[ SAT ] [ UNSAT ]

16 (D.1) Find and record inverse boron Used figure to determine worth using TDB Figure II.A.4 inverse boron worth to be at HZP and the approximately 119.5 ppm/%

burnup A.5 above. delta rho

[ SAT ] [ UNSAT ]

17 (D.2) Find the change in boron Calculated and recorded concentration by multiplying approximately 250 ppm (200-C.5.e by D.1. (Be sure to 300 ppm) in space D.2 transcribe the algebraic sign of C.5.e.) [ SAT ] [ UNSAT ]

- 18 (D.3) Find the estimated boron Calculated and recorded concentration. approximately 1000 ppm (950-1050 ppm) in space D.3.d

[ SAT ] [ UNSAT ]

Termination Criteria: Applicant has determined Estimated Critical boron concentration.

Page 6 of 7

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

INITIAL CONDITIONS:

The plant is shutdown as the result of a reactor trip and a reactor startup is scheduled at 0900 on 4/15/12.

Shutdown from 100% power occurred at 2000 on 4/13/12

The plant was operating with all rods out prior to the trip

Boron concentration prior to the trip was 638 ppm

Average core burnup is 6,000 MWD/MTU

The Reactor Engineer has specified a desired CEA position for criticality, group 4 at 85 inches

Boron concentration was increased to 750 ppm to ensure adequate shutdown margin

DEN-Nuclear states that no correction is needed for boron depletion INITIATING CUE: You are directed to determine the estimated critical boron concentration for this startup.

Another Operator will determine the amount of Water or Acid needed to change the boron concentration.

Name: _____________________________________________

Estimated critical boron concentration:______________ ppm Page 7 of 7

KEY KEY KEY KEY KEY KEY KEY KEY KEY KEY KEY KEY KEY KEY Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RA2 and SA2 Rev 3 JPM

Title:

Perform a Quadrant Power Tilt Calculation Location: Classroom Approximate Time: 20 minutes Start Time:__________________

End Time:___________________

Actual Time: _________________

Reference(s): K/A# 2.1.20 Ability to interpret and execute procedure steps.

OI-NI-1, Attachment 4, Quadrant Power Tilt Calculation, Rev 22 Form FC-171, Corrected Excore Azimuthal Power Tilt Limits, Revision 11 Handout(s): Partially completed OI-NI-1, Attachment 4 Filled out Form FC-171 Task List#: 0083 Applicable Position(s): RO/SRO Time Critical: No Alternate Path: No JPM Prepared by: Date:

Page 1 of 6

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RA2 and SA2 Rev 3 JPM

Title:

Perform a Quadrant Power Tilt Calculation Operators Name:

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:

Page 2 of 6

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RA2 and SA2 Rev 3 JPM

Title:

Perform a Quadrant Power Tilt Calculation TASK Applicant performed a quadrant power tilt calculation STANDARD: per OI-NI-1 Attachment 4 Step 2. Applicant calculated QPTR to be 0.53% for the upper and 0.90% for the lower. Applicant determined that the calculated lower tilt exceeds the FC-171 value provided.

INITIAL

ERF and GARDEL are inoperable.

CONDITIONS:

Excore detectors are available.

I&C measured and recorded voltage readings for the excore detectors per OI-NI-1, NUCLEAR INSTRUMENTATION SYSTEM, Attachment 4, Quadrant Power Tilt Calculation, Step 2.a.

FC-171, CORRECTED EXCORE AZIMUTHAL POWER TILT LIMITS, is attached.

INITIATING CUE: You are directed to perform a quadrant power tilt calculation per OI-NI-1, Attachment 4, Step 2, using the information collected by I&C. Based on your calculations, determine if the indicated upper tilt and indicated lower tilt are within the values given in FC-171.

Page 3 of 6

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RA2 and SA2 Rev 3 JPM

Title:

Perform a Quadrant Power Tilt Calculation Critical Steps shown in gray and **

STEP ELEMENT STANDARD

- 1 (OI-NI-1, Calculate Upper Quadrant Candidate determines upper , Power Tilt quadrant power tilt to be Step 2.c) 0.53%:

(5.125 - 5.075) / (5.125 +

5.075) = 4.902 E-3 (5.1 - 5.05) / (5.1 + 5.05) =

4.9261 E-3 (4.902E-3)2 + (4.9261E-3)2 -

(1.48628

4.902E-3 *4.9261E-

3) = 1.2406 E-5 (1.2406E-5*2.2334)

100 =

0.526%

Range of 0.52%-0.535% is acceptable.

[ SAT ] [ UNSAT ]

- 2 (Step 2.d) Calculate Lower Quadrant Candidate determines lower Power Tilt quadrant power tilt to be 0.90%.

(4.925 - 4.85) / (4.925 + 4.85)

7.673 E-3 (4.9 - 4.875) / (4.9 + 4.875)

2.5575 E-3 (7.673E-3)2 + (2.5575E-3)2 -

(1.48628

7.673E-3

2.5575E-3) = 3.6245 E-5 (3.6245E-5

2.2334)

100 =

0.90%

Page 4 of 6

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RA2 and SA2 Rev 3 JPM

Title:

Perform a Quadrant Power Tilt Calculation STEP ELEMENT STANDARD Range of 0.89% - 0.91% is acceptable.

[ SAT ] [ UNSAT ]

- 3 (Step 2.e) Verify calculated tilt values are Candidate reviews FC-171 less than current FC-171 and determines that the lower indicated tilt values. tilt is greater than current FC-171 indicated tilt value.

[ SAT ] [ UNSAT ]

Termination Criteria: Calculated upper and lower quadrant power tilts and determined that the lower quadrant power tilts is not within current values specified in FC-171 Page 5 of 6

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RA2 and SA2 Rev 3 INITIAL

ERF and GARDEL are inoperable.

CONDITIONS:

Excore detectors are available.

I&C measured and recorded voltage readings for the excore detectors per OI-NI-1, NUCLEAR INSTRUMENTATION SYSTEM, Attachment 4, Quadrant Power Tilt Calculation, Step 2.a.

FC-171, CORRECTED EXCORE AZIMUTHAL POWER TILT LIMITS, is attached.

INITIATING CUE: You are directed to perform a quadrant power tilt calculation per OI-NI-1, Attachment 4, Step 2, using the information collected by I&C. Based on your calculations, determine if the indicated upper tilt and indicated lower tilt are within the values given in FC-171.

Applicant Name: _________________________________________

Upper Quadrant Power Tilt: %

Lower Quadrant Power Tilt: %

Values within current FC-171 values? ___________________

If not, which one(s) is (are) outside current FC-171 values? _____________

Page 6 of 6

KEY KEY

Reactor Engineer Today

I&C

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RA3 Rev 3 JPM

Title:

Prepare a Manual Clearance for Maintenance on AC-3C Location: Classroom Approximate Time: 20 minutes Start Time:__________________

End Time:___________________

Actual Time: _________________

Reference(s): K/A# 2.2.13 RO IMP: 4.1 Knowledge of tagging and clearance procedures Procedures: SO-G-20A Other (tech specs, etc): P&IDs Handout(s): Three Blank SOMS forms per Candidate Task List#: 0075 Applicable Position(s): RO/SRO Time Critical: NO Alternate Path: NO JPM Prepared by: Jerry Koske Date: 3/22/2012 Page 1 of 6

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RA3 Rev 3 JPM

Title:

Prepare a Manual Clearance for Maintenance on AC-3C Operators Name:

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:

Safety Considerations:

Comments:

Page 2 of 6

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RA3 Rev 3 JPM

Title:

Prepare a Manual Clearance for Maintenance on AC-3C TASK STANDARD: The candidate prepared a Manual Clearance in accordance with SO-G-20A. All of the criteria for critical steps 2, 4, 5 and 6 were satisfied.

INITIAL CONDITIONS: Maintenance is being planned to replace the impeller on Component Cooling Pump, AC-3C.

SOMS is unavailable.

INITIATING CUE:

You are directed to prepare a manual Clearance for Maintenance on AC-3C in accordance with SO-G-20A using the blank SOMS forms provided. The following information is required:

Tag Type

Equipment

Placement Sequence

Placement Configuration The Shift Manager has directed that AC-3Cs casing vent and drain valves remain closed Please write your name on each SOMS Form.

Page 3 of 6

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RA3 Rev 3 JPM

Title:

Prepare a Manual Clearance for Maintenance on AC-3C Critical Steps shown in gray and **

STEP ELEMENT STANDARD 1 Refer to applicable references: Candidate used reference

SO-G-20A material as required.

Plant Procedures

P&IDs [ SAT ] [ UNSAT ]

- 2 Prepare Clearance per SO-G- The Control Switch for AC-3C 20A using blank SOMS form must be first item in the sequence. It is placed in PTL and CAUTION tagged.

[ SAT ] [ UNSAT ]

3 The breaker 69 switch should be the second item in the sequence. It is placed in PTL with No Tag.

[ SAT ] [ UNSAT ]

- 4 The breaker must be in the sequence before any valves. It is racked out with a DANGER tag.

[ SAT ] [ UNSAT ]

- 5 AC-3Cs discharge valve, AC-108, and AC-3Cs suction valve, AC-106 must be the next 2 items in the sequence.

It is not required that AC-108 be listed before AC-106. Both of these valves must be danger tagged closed.

[ SAT ] [ UNSAT ]

Page 4 of 6

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RA3 Rev 3 JPM

Title:

Prepare a Manual Clearance for Maintenance on AC-3C STEP ELEMENT STANDARD

- 6 AC-3Cs vent and drain valves, At least 2 of the following valves must be listed:

AC-359

AC-360

AC-361 They should be designated as CLOSED (per Initiating Cue) or per Shift Manager Discretion with NO TAG

[ SAT ] [ UNSAT ]

Note: AC-163, AC-1116, AC-838 and AC-837 may also be listed but are not required.

Examiner Note: Ensure Candidate has written name on blank SOMS Forms Termination Criteria: The candidate has completed the clearance form with the information listed in the initiating Cue.

Page 5 of 6

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RA3 INITIAL CONDITIONS: Maintenance is being planned to replace the impeller on Component Cooling Pump, AC-3C.

SOMS is unavailable.

INITIATING CUE: You are directed to prepare a manual Clearance for Maintenance on AC-3C in accordance with SO-G-20A using the blank SOMS forms provided. The following information is required:

Tag Type

Equipment

Placement Sequence

Placement Configuration The Shift Manager has directed that AC-3Cs casing vent and drain valves remain closed Please write your name on each SOMS Form.

Page 6 of 6

Clearance Tag List FORT CALHOUN STATION Clearance: EXAM SOMSFORM Clearance:

Tag Type Equipment Pia Placement Place. 1" Verif Place. 2"" Rest Rest. Config. Rest.. 15 Verif Rest.. 20* Verif

...... - ............... _-- ......... Seq Configuration Verif Seq *As Left (If Diff.)

.. - *Equipment Description ................ __ .... __ ........ DatefTime -_ ............................... - DatefTime DatelTime Serial No. *Equipment Location

Notes DatelTime (qf!1!~~ ..(l~:-:~.f: ..... ...f.I .f:.:,....... -_ .... _-_ .................... -

{OI)1"}t>/ .s luite? I (8-// J.) 3 N~Ifj. j/3

- ........3_--- - 't C-lf( .............

2. . ... f.!..1:: ...... -_ .... __ .. _-----_ .... _-

67 ..5 wife h A-3 KEY D.!l..I}-9t'..~ .t P..~ !-::-. Y:~.:.Cf .3 RI(,ktJ. ..().~T. .... _ ................................

Bre+ fret-

'p'~(J!3~}- ..tl~:-/9.?.... Lf- CloSed Ac- 3C. Dischf~

Vq/ve 0.((}J-t: t- .If.~::(p..( .... S- ..~f~~~~ ...... ------------------

AC. -3£:. svchO?

Vf1/ve lip..T.f1-j ..It.~. t:~-?.t. 6 closed AC.- 3[. C".5/fJ!j V ey/ T

Clearance Tag List FORT CALHOUN STATION Clearance: EXAM SOMSFORM Clearance:

Tag Type Equipment Pia Seq I Configuration Placement Place. 1srVerf'--jPlace. 2""

Verif Rest Seq I Rest. Config.

As Left (If Diff.)

Rest.. 1st Verif Rest.. ~ Verif

- - - - - - - - I *Equipment Description DatelTime DatelTime DatelTime Serial No. *Equipment Location

Notes DatelTime

_~Vf?_~~I-A'<:-:--}-~~-- 6 I _f jq$. f.~ _

Alo

- .*.*.*.*.**. TflQ

...:J I AC- 3 , JJ

.... _ *...*..*....* . 6 ,_.()o.>e.J A-3 KEY

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RA4/SA4 Rev 3 JPM

Title:

Determine if temporary shielding should be requested Location: Classroom Approximate Time: 5 minutes Start Time:__________________

End Time:___________________

Actual Time: _________________

Reference(s): K/A# 2.3.12 Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

K/A# 2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions.

RP-307, Use and Control of Temporary Shielding, Rev 20 Handout(s): None Task List#: None (GET Rad Worker Knowledge)

Applicable Position(s): RO/SRO Time Critical: No Alternate Path: No JPM Prepared by: Date:

Page 1 of 5

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RA4/SA4 Rev 3 JPM

Title:

Determine if temporary shielding should be requested Operators Name:

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:

Page 2 of 5

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RA4/SA4 Rev 3 JPM

Title:

Determine if temporary shielding should be requested TASK Applicant calculated total estimated dose for the work STANDARD: without installing shielding to be 140 mrem. Applicant calculated total estimated dose for the work with shielding (including shielding installation) to be approximately 132 mrem. Applicant recommends requesting temporary shielding be installed.

INITIAL Work is being planned to be performed in Room 13 CONDITIONS: near HS#23 which has a 30 cm dose rate reading of 80 mR/hr. This work is performed by one person and is expected to take 1.75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months . It has been determined that if shielding is installed, the dose rate will decrease to 45 mR/hr. The time for one person to install the shielding is estimated to take 40 minutes.

INITIATING CUE: Determine:

The total expected dose for the work if shielding is not installed.

The total expected dose if the worker installs the shielding and then performs the work.

Recommend whether or not temporary shielding should be requested.

Page 3 of 5

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: RA4/SA4 Rev 3 JPM

Title:

Determine if temporary shielding should be requested Critical Steps shown in gray and **

STEP ELEMENT STANDARD

- 1 Determine expected dose Applicant determines expected without shielding. dose without shielding.

80 mR/hr

1.75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months = 140 mrem

[ SAT ] [ UNSAT ]

- 2 Determine expected dose with Applicant determines total shielding installation. expected dose if shielding is installed.

80 mR/hr

40 min * (1 hr / 60 min) + 45 mR/hr

1.75 hr =

132 mrem

[ SAT ] [ UNSAT ]

- 3 Determine if shielding should Applicant determines that the be requested. total dose with shielding is 8 mrem less than the total expected dose without shielding and therefore, temporary shielding should be requested.

[ SAT ] [ UNSAT ]

Termination Criteria: Applicant has calculated the total expected dose both with and without shielding and has determined that shielding should be requested.

Page 4 of 5

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: SA4 Rev 3 INITIAL CONDITIONS: Work is being planned to be performed in Room 13 near HS#23 which has a 30 cm dose rate reading of 80 mR/hr. This work is performed by one person and is expected to take 1.75 hours8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months . It has been determined that if shielding is installed, the dose rate will decrease to 45 mR/hr. The time for one person to install the shielding is estimated to take 40 minutes.

INITIATING CUE: Determine:

The total expected dose for the work if shielding is not installed.

The total expected dose if the worker installs the shielding and then performs the work.

Recommend whether or not temporary shielding should be requested.

Applicant Name: _______________________________

Total dose if shielding is NOT installed: _____________

Total dose if shielding is installed: ______________

Recommend requesting temporary shielding (YES or NO)? ____________

Page 5 of 5

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: SA1 Rev 3 JPM

Title:

Calculate amount of water and boric acid required to raise SIRWT level 10 inches and maintain SIRWT concentration Location: Classroom Approximate Time: 20 minutes Start Time:__________________

End Time:___________________

Actual Time: _________________

Reference(s): K/A 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.

TDB-V.12, Miscellaneous Formula Sheet, Rev. 13 TDB-VII, Tank Curves, Rev.16 Handout(s): None Task List#: 1192 Applicable Position(s): SRO Time Critical: No Alternate Path: No Page 1 of 6

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: SA1 Rev 3 JPM

Title:

Calculate amount of water and boric acid required to raise SIRWT level 10 inches and maintain SIRWT concentration JPM Prepared by: Date:

Operators Name:

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 Page 2 of 6

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: SA1 Rev 3 JPM

Title:

Calculate amount of water and boric acid required to raise SIRWT level 10 inches and maintain SIRWT concentration Safety Considerations: None Comments:

TASK Applicant calculates the amount of demineralized water STANDARD: and the amount of boric acid to add to the SIRWT to raise level from 185 inches to 195 inches while maintaining current SIRWT concentration. Applicant determines that 6117 gallons of water (6110-6125 gal) and 3883 gallons of boric acid (3875-3890) must be added.

INITIAL

Current SIRWT level is 185 inches.

CONDITIONS:

Current SIRWT boric acid concentration is 2247 ppm.

Both BASTs most recent sample indicate 3.31 %wt boric acid.

INITIATING CUE: You have been asked to determine that total number of gallons required to raise SIRWT level 10 inches to a final level of 195 inches. You have also been asked to determine that amount of demineralized water and the amount of water from the BASTs required to raise the SIRWT 10 inches while maintaining current SIRWT boric acid concentration. Calculations that are normally used for determining additions to the RCS can be used for the SIRWT without change.

Page 3 of 6

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: SA1 Rev 3 JPM

Title:

Calculate amount of water and boric acid required to raise SIRWT level 10 inches and maintain SIRWT concentration Critical Steps shown in gray and **

STEP ELEMENT STANDARD

- 1 TDB-VII Determine total number of Applicant determines from the gallons required to raise graph that approximately SIRWT level from 185 inches 10,000 total gallons are to 195 inches. required to raise SIRWT level 10 inches (330,000 -320,000 =

10,000 gallons).

(9,950 - 10,050 gallons acceptable)

[ SAT ] [ UNSAT ]

- 2 TDB- Determine number of gallons of Gal water / gal acid =

V.12 demineralized water and (1748*3.31%) / 2247 ppm -1 =

number of gallons of water 1.575 from BASTs Gal water = 1.575

gal acid Gal water + gal acid = 10,000 gal 2.575 gal acid = 10,000 gal Gal acid =3883.5 gal (3875-3890 gal)

Gal water = 10,000 - 3883.5 =

6116.5 gal (6110 - 6125 gal)

OR Gal water = 1.575

3883.5 =

6116.5 gal (6110-6125)

[ SAT ] [ UNSAT ]

Page 4 of 6

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: SA1 Rev 3 JPM

Title:

Calculate amount of water and boric acid required to raise SIRWT level 10 inches and maintain SIRWT concentration Termination Criteria: Applicant has calculated that it will require 3884 (3875 - 3890) gallons of boric acid and 6117 (6110 -

6125) gallons of demineralized water for a total of 10,000 (9,950 -10,050) gallons to raise SIRWT level 10 inches while maintaining current SIRWT boric acid concentration.

Page 5 of 6

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: SA1 Rev 3 INITIAL

Current SIRWT level is 185 inches.

CONDITIONS:

Current SIRWT boric acid concentration is 2247 ppm.

Both BASTs most recent sample indicate 3.31 %wt boric acid.

INITIATING CUE: You have been asked to determine that total number of gallons required to raise SIRWT level 10 inches to a final level of 195 inches. You have also been asked to determine that amount of demineralized water and the amount of water from the BASTs required to raise the SIRWT 10 inches while maintaining current SIRWT boric acid concentration. Calculations that are normally used for determining additions to the RCS can be used for the SIRWT without change.

Applicant Name: _______________________________

Total number of gallons to raise SIRWT level from 185 to 195 inches:

Amount of demineralized water: ___________________

Amount of borated water from the BASTs: ___________________

Page 6 of 6

FORT CALHOUN STATION TDB-VII TECHNICAL DATA BOOK PAGE 22 OF 29 Safety Injection and Refueling Water Tank (SIRWT), SI-5 SIRWT TANK SI- 5 VOLUME 360 350 340 330 320 310 300 290 280 270 260 Volume of Water (x1000 gal.)

250 240 230 220 210 200 190 180 170 160 150 140 130 120 110 100 90 80 70 60 50 40 30 20 10 0

0 10 20 30 40 50 60 70 80 90 100 110 120 130 140 150 160 170 180 190 200 210 220 Level (in.)

Minimum of 283,000 gallons of usable water above 16" recirculation level (approx. 28,000 gal) per Tech Spec 2.1.4(5). Hence minimum tank level is 311,000 gal at 180". Reference calculation FC07376.

R16

FORT CALHOUN STATION TDB-V.12 TECHNICAL DATA BOOK PAGE 3 OF 5 BLEND GAL WATER 1748

CA GAL ACID 1

C LOOP OR DEMIN WATER FLOW BA FLOW 1748

CA C LOOP / C LOOP PPM = (% WT) * (1748)

CA = CONCENTRATION IN BORIC ACID TANK (% WT)

CI = INITIAL CONCENTRATION OF RCS (PPM)

CF = FINAL CONCENTRATION OF RCS (PPM)

C LOOP = CONCENTRATION OF RCS LOOP (PPM)

BA = BORIC ACID DEMIN FLOW = GALLONS PER MINUTE (GPM)

BA FLOW = GALLONS PER MINUTE (GPM)

HZP = Hot Zero Power (Tavg = 532°F and Pressurizer Level = 48%)

HFP = Hot Full Power (Tavg = 567.6°F and Pressurizer Level = 60%)

SUBCRITICAL MULTIPLICATION CR1 1 K EFF2 CR INITIAL 1 CR2 1 K EFF1 CR FINAL M R13

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: SA3 Rev 3 JPM

Title:

Review a Manual Clearance for Maintenance on AC-3C Location: Classroom Approximate Time: 20 minutes Start Time:__________________

End Time:___________________

Actual Time: _________________

Reference(s): K/A# 2.2.13 RO IMP: 4.1 Knowledge of tagging and clearance procedures Procedures: SO-G-20A Other (tech specs, etc): P&IDs Handout(s): Filled out SOMS Forms Task List#: 0075 Applicable Position(s): SRO Time Critical: NO Alternate Path: NO JPM Prepared by: Jerry Koske Date: 3/22/2012 Page 1 of 5

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: SA3 Rev 3 JPM

Title:

Review a Manual Clearance for Maintenance on AC-3C Operators Name:

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:

Safety Considerations:

Comments:

Page 2 of 5

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: SA3 Rev 3 JPM

Title:

Review a Manual Clearance for Maintenance on AC-3C TASK STANDARD: The Applicant reviewed the Manual Clearance in accordance with SO-G-20A. The Applicant did not approve the Clearance because items were not listed in the required sequence. The Control Switch in the Control Room should have been the first item in the sequence.

INITIAL CONDITIONS: Maintenance is being planned to replace the impeller on Component Cooling Pump, AC-3C.

SOMS is unavailable. A Manual Clearance has been prepared.

INITIATING CUE:

You are directed to perform a SRO review of the manual Clearance for Maintenance on AC-3C in accordance with SO-G-20A. The following information should be reviewed:

Tag Type

Equipment

Placement Sequence

Placement Configuration The Shift Manager has directed that AC-3Cs casing vent and drain valves remain closed Page 3 of 5

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: SA3 Rev 3 JPM

Title:

Review a Manual Clearance for Maintenance on AC-3C Critical Steps shown in gray and **

STEP ELEMENT STANDARD 1 Reviewed Manual Clearance Applicant reviewed Form form.

[ SAT ] [ UNSAT ]

2 Refer to applicable references: Applicant used reference

SO-G-20A material as required.

Plant Procedures

P&IDs [ SAT ] [ UNSAT ]

3** Approve Clearance The Applicant did not approve the clearance (Circled NO) because the Control Switch for AC-3C must be first item in the sequence.

[ SAT ] [ UNSAT ]

Note: the Applicant may also wish to add AC-163, AC-1116, AC-838 and AC-837 to the Clearance.

Termination Criteria: The Applicant has completed the clearance form with the information listed in the initiating Cue.

Page 4 of 5

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: SA3 Rev 3 INITIAL CONDITIONS: Maintenance is being planned to replace the impeller on Component Cooling Pump, AC-3C.

SOMS is unavailable. A Manual Clearance has been prepared.

INITIATING CUE: You are directed to perform a SRO review of the manual Clearance for Maintenance on AC-3C in accordance with SO-G-20A. The following information should be reviewed:

Tag Type

Equipment

Placement Sequence

Placement Configuration The Shift Manager has directed that AC-3Cs casing vent and drain valves remain closed Name:__________________________________________________

Approve Clearance: (Circle One) YES NO If you did not approve, specify why below:

Page 5 of 5

Clearance Tag List FORT CALHOUN STATION Clearance: EXAM SOMSFORM Clearance: )\ C - 3 C.

Tag Type Equipment Pia Placement Place. 1'" Verif Place.2na Rest Rest. Config. Rest.. 1$ Verif Rest .. 2'N Verif

Seq Configuration Verif Seq *As Left (If Ditt.)

*Equipment Description --------_ ...... _----- DatelTime _ .*. ---------------- DatelTime DatelTime

____ r T.!-::_______

Serial No. *Equipment Location

Notes DatelTime

>>~T9j ) ~_~_~ .: t.;:r;._ ~_ 'f (

6 9 ..5Witc~

QqIJ3C~ IB3C.-lfC-'f Jll{fJ(~__ C?t..: T_ --_ _------

-i3 ~~~}-e-.;- --- ~

11(-3 C (kll~f7-----------------

3 __---f_I_ ?::--__ ------- .. _---------

(0 n1}o/ s. 'l/itc?

C8-// ;).;3 p~(lfjt:;!- __f+.[:-:/9_? ____ Lf- CloSed A (- 3 C. [)i'> C b¥l-,J vet/ve Pt IjJ.s: 't- _ _

1~ .:(~_~ _____ S- __ ~l?~~~ ______ ---- .. _----------- ..

Ac -3(. S~(f;O'J Vq/ve

/'/9.. T..lfj __A-_~_t:?>'-?:_1 __ 6 closed Ac.- 3C. c".5J*n~

V eY/ 7

Clearance Tag List FORT CALHOUN STATION Clearance: EXAM SOMSFORM Clearance: fie - 3 C Tag Type Equipment Pia I Placement Place.1S'-Verif I Place::Z"" Rest I Rest. Config. Rest.. 1S[ Verif Rest.. 2M Verif Seq Configuration Verif Seq *As Left (If Diff.)

- - - - - - - - I *Equipment Description DatelTime DatelTime DatelTime Serial No. *Equipment Location

Notes DatelTime

_~Vf?_7fr~I - It~_:-_}_ ~C?__ b -.( jQ$~~- --- ---

A/~_T.rt:J I_(tf:_-:_~_~) _ 6 cJo.seJ _------

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: SA5 Rev 3 JPM

Title:

Classify Emergency Action Levels and make Protective Action Recommendations Location: Classroom Approximate Time: 12 minutes Start Time:__________________

End Time:___________________

Actual Time: _________________

Reference(s): 1. K/A# 000000 2.4.41 (SRO 4.6): Knowledge of the emergency action level thresholds and classifications.

2. K/A# 000000 2.4.44 (SRO 4.4): Knowledge of emergency plan protective action recommendations.

3. EPIP-OSC-1, EMERGENCY CLASSIFICATION.

4. TBD-EPIP-OSC-1A, Recognition Category A - Hazards and Other Conditions Affecting Plant Safety.

5. EPIP-EOF-7, PROTECTIVE ACTION GUIDELINES.

Task List#: 1453 Applicable Position(s): SRO Time Critical: YES Alternate Path: NO JPM Prepared by: Jerry Koske Date: 3/8/2012 Page 1 of 7

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: SA5 Rev 3 JPM

Title:

Classify Emergency Action Levels and make Protective Action Recommendations Operators Name:

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:

Page 2 of 7

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: SA5 Rev 3 JPM

Title:

Classify Emergency Action Levels and make Protective Action Recommendations TASK The SRO Applicant reviewed the plant conditions, STANDARD: referred to EPIP-OSC-1A and TDB-IV.8 and classified the event as a General Emergency, IC AG1, EAL 1.

Within 15 minutes of classifying the event, the Applicant determined that the Protective Action Recommendation is to evacuate all sectors 0-2 miles and completed page one of form FC-1188 so that offsite notifications can be made.

INITIAL

A loose parts monitoring alarm came in an hour CONDITIONS: ago

20 minutes ago, the reactor tripped on TMLP and Radiation Monitors RM-057 and RM-054A alarmed

EOP-00 Standard Post Trip Actions have been completed and EOP-04 has been entered

The ERO was activated and an Alert was declared based on FA1, EAL 2, Loss of RCS Barrier.

Attempts to isolate Steam Generator RC-2A have been unsuccessful.

RM-064 has been placed in service and its S/G A reading has increased from 975 cpm to 990 cpm over the past 15 minutes.

The wind is from 180° @ 15 mph.

The Met Tower T is -1.3°C/100m

There is no precipitation

Dose Assessment has not yet been performed INITIATING CUE You are the Shift Manager. Determine the appropriate IC and EAL, if any, in accordance with EPIP-OSC-1.

Page 3 of 7

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: SA5 Rev 3 JPM

Title:

Classify Emergency Action Levels and make Protective Action Recommendations CUE #2: ***********TIME CRITICAL JPM***************

Specify any Protective Action Recommendations and Complete Form FC-1188.

Critical Steps shown in gray and **

STEP ELEMENT STANDARD 1 Refer to Emergency Plan. Refer to TBD-EPIP-OSC-1A.

[ SAT ] [ UNSAT ]

2** Classify the event. This Event should be classified as a GENERAL EMERGENCY using IC AG1, EAL 1.

[ SAT ] [ UNSAT ]

3** Determine Protective Action ***** TIME CRITICAL *****

Recommendations and fill out form FC-1188 for notifications. Provide CUE# 2 and Blank FC-1188 to Applicant Start Time: _____________

Form FC-1188 must be filled out within 15 minutes and must contain the following information:

Initial Declaration

General Emergency

IC#: AG1

EAL: 1 (Loss)

PARs: EVACUATE all Page 4 of 7

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: SA5 Rev 3 JPM

Title:

Classify Emergency Action Levels and make Protective Action Recommendations STEP ELEMENT STANDARD Sectors, 0-2 Miles End Time:____________

Elapsed Time:__________

[ SAT ] [ UNSAT ]

Prognosis: Worsening

4. Non-Critical Form FC-1188

Plant Status: Shutdown Information

Wind Direction:180°

Wind Speed:15 MPH

Precipitation: No

Temperature difference:

-1.3 °C/100m

Stability Class: D

There is an airborne release

Approval Signature, date and time Termination Criteria: The Event has been classified and PARs have been made.

Page 5 of 7

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: SA5 Rev 3 INITIAL CONDITIONS:

A loose parts monitoring alarm came in an hour ago

20 minutes ago, the reactor tripped on TMLP and Radiation Monitors RM-057 and RM-054A alarmed

EOP-00 Standard Post Trip Actions have been completed and EOP-04 has been entered

The ERO was activated and an Alert was declared based on FA1, EAL 2, Loss of RCS Barrier.

Attempts to isolate Steam Generator RC-2A have been unsuccessful.

RM-064 has been placed in service and its S/G A reading has increased from 975 cpm to 990 cpm over the past 15 minutes.

The wind is from 180° @ 15 mph.

The Met Tower T is -1.3°C/100m

There is no precipitation

Dose Assessment has not yet been performed INITIATING CUE: You are the Shift Manager. Determine the appropriate IC and EAL, if any, in accordance with EPIP-OSC-1.

Applicant Name: __________________________________

Event Classification (circle one): NONE NOUE ALERT SAE GE IC#__________________ EAL#_______________

Time of Declaration:________________

Page 6 of 7

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: SA5 Rev 3 CUE #2: ***********TIME CRITICAL JPM***************

Specify any Protective Action Recommendations and Complete Form FC-1188.

Page 7 of 7

- - - - KEY *************************

FORT CALHOUN STATION FC-1188 GENERAL FORM R27 PAGE 1 OF 2 FORT CALHOUN STATION - EMERGENCY NOTIFICATION FORM Off-Site Contact Time: Person Making Off-Site Report: Contactor's Call Back #:

lime A14/Y) f:- fholJc II-1.

M Initial Declaration - for Initial declaration of any emergency classification Hourly - When completing Hourly updates, one hour from time of the most recent event notification and on an hourly basis until event termination.

[ 1 PAR Change - Any change in Protective Action Recommendations (PARs) and a new classification is not being declared.

[ 1 Shiftly during ongoing events IF requested by the states AND the status of the event has not changed.

[ 1 Termination - Requirements of EPIP-OSC-2, Attachment 6.6, must be met.

2. Classification: 3. IC#: 4. EAL#: J

[ 1 NOUE I[ 1 Alert I[ 1 Site Area 11><1 General I[ 1 None

,A-r;.J.. (If Fission Product Barrier, complete box #7)

5. Time Event Declared: 6. Time Event Terminated:

7. Complete if Fission Product Barrier Fuel Clad:z£:

T7me. EAL# A~ Loss/ Potential Loss (Circle one)

8. Prognosis: 9. Plant Status:

RCS:

EAL#

AI}1t Loss / Potential Loss (Circle one)

[ 1 Stable [ 1 At Power Containment:

f.XI Worsening (X1'Shutdown EAL# 4YA Loss / Potential Loss (Circle one)

OBTAIN METEOROLOGICAL DATA FROM ERF PAGE 197 (see Note 1 on page 2, if ERFCS is unavailable)

10. Wind From Degrees(10m): 11. Wind Speed MPH (Use Slowest 12. Precipitation: [ 1 Yes P\rNo J goo 10m): / S- ;11f~

13. Temperature Difference - /*3 DC/100m (use most positive 11T)

14. Stability Class -[ lA [ 1B [ 1C t><J'D [ 1E [ 1F [ 1 G+

s -1.9 >-1.9 to > -1.7 to >-1.5to > -0.5 to > 1.5 to > 4.0 s -1.7 ::;-1.5 ::;-0.5 s 1.5 ::;4.0

15. There f41 is was

[

~

1 no an airborne release of radioactive effluent to the environment that is the result of or associated with this event

[ 1 will be [ 1 a liquid REVIEW EPIP-EOF-7 FOR GUIDANCE ON PARS 16 Protective Action Recommendations (PARs)

None Evacuate Sectors Shelter Sectors 0-2 Miles ALL-2-5 Miles 5-10 Miles

17. Remarks Approved: 5/* q /J; f tit c Date: D'11-C Time: Tt-h; e, CONFIRMED TIME (COUNTY USE ONLY) _

- - - - KEY *****************************

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-P1 Rev 3 JPM

Title:

Respond to a steam bound auxiliary feedwater pump Location: Auxiliary Building Approximate Time: 20 minutes Start Time:__________________

End Time:___________________

Actual Time: _________________

Reference(s): K/A#: 000061, K3.01, A2.04 Ability to (a) predict the impacts of the following malfunctions or operations on the AFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: pump failure or improper Operation.

Procedures: AOP-28,Section III, Steam/Air Bound AFW Pumps Revision 16 Handout(s): AOP-28,Section III Task List#: 0107 Applicable Position(s): RO, SRO-I, SRO-U Time Critical: No Alternate Path: No Page 1 of 11

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-P1 Rev 3 JPM

Title:

Respond to a steam bound auxiliary feedwater pump JPM Prepared by: Date:

Operators Name:

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 Page 2 of 11

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-P1 Rev 3 JPM

Title:

Respond to a steam bound auxiliary feedwater pump Safety Considerations: Take precautions in the vicinity of hot piping and steam drains Comments: This JPM will be conducted as a static JPM in the plant.

TASK Respond to a steam bound auxiliary feedwater pump, STANDARD: take the necessary corrective actions, and restart auxiliary feedwater pump FW-6.

INITIAL The plant is in hot shutdown. FW-10 and FW-54 are CONDITIONS: out of service. When attempting to feed the steam generators using auxiliary feedwater pump FW-6, feedwater flow to the steam generators lowered.

FW-6 is suspected to be steam or air bound due to low flow and oscillating amps. S/G pressure is 900 psia.

INITIATING CUE: CRS directs you to restore normal flow from Auxiliary Feedwater Pump, FW-6, to service using AOP-28,Section III.

Page 3 of 11

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-P1 Rev 3 JPM

Title:

Respond to a steam bound auxiliary feedwater pump Critical Steps shown in gray AND **

STEP ELEMENT STANDARD 1 Obtain a copy of AOP-28 Knowledge of where to obtain Section III. a copy of AOP-28

[ SAT ] [ UNSAT ]

CUE: Provide copy of AOP-28,Section III.

2 (AOP-28, Check that discharge pipe Room 19 Section III, temperature is greater than Checks TI-1382 for Step 1) 260°F for at least one of the temperature.

following Aux Feedwater Pumps (Room 19): [ SAT ] [ UNSAT ]

TI-1382 TI-1382 reads approximately FW-6, Electric AFW Pump 275°F.

(FW-6 Discharge Temperature Indicator) CUE: Do not allow candidate to enter FW-10 cage. If checked, TI-1383 reads approximately 85°F.

Page 4 of 11

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-P1 Rev 3 JPM

Title:

Respond to a steam bound auxiliary feedwater pump STEP ELEMENT STANDARD 3 (Step 2) CUE: IF Applicant contacted IF discharge pipe temperature Control Room, Control for FW-6 is greater than 260°F, Room directs you to stop THEN stop FW-6. the pump locally.

Stopped the pump locally by depressing RED local Stop button.

RED light OFF and GREEN light ON

[ SAT ] [ UNSAT ]

4 (Step 3) IF discharge pipe temperature Procedure step 3 N/A.

for FW-10, Steam AFW Pump, is greater than 260°F, 5 CAUTION Read caution.

Opening AFW Pump Drain Valves may cause steam to [ SAT ] [ UNSAT ]

issue.

- 4 (Step 4.a) IF FW-6 is the affected pump, Examiner NOTE: Valve is THEN vent FW-6 by performing hard to move, Applicant may the following (Room 19): use valve wrench.

a. Unlock and close FW-171, Acknowledge Deviation Log "MOTOR DRIVEN AUX FEED Entry PUMP FW-6 DISCHARGE Room 19 VALVE". FW-171 unlocked and close in clockwise direction.

[ SAT ] [ UNSAT ]

CUE: Stem lowers until resistance is felt.

- 5 (Step 4.b) Open FW-688, "MOTOR- Room 19 Page 5 of 11

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-P1 Rev 3 JPM

Title:

Respond to a steam bound auxiliary feedwater pump STEP ELEMENT STANDARD DRIVEN AUX FEED PUMP FW- Opened FW-688 by turning 6 DISCHARGE DRAIN VALVE". counter-clockwise.

[ SAT ] [ UNSAT ]

CUE: Stem rises, steam observed.

- 6 (Step 4.c) WHEN a steady stream of water CUE 1: A steady stream of issues from the drain valve, water is observed.

THEN close the drain valve.

Room 19 Closed FW-688 (clockwise) following cue 1.

[ SAT ] [ UNSAT ]

CUE 2: Stem lowers until resistance is felt.

CUE: If candidate reads TI-1382 again, it reads approximately 170°F 7 (Step 5) IF EFWST level was less than CUE: EFWST level never fell 25%, THEN vent Auxiliary below 25%.

Feedwater suction pipe by performing the following: Step is N/A 8 (Note) NOTE Note reviewed.

The "43/FW" Switch lines up nine pumps for Auto-Start [ SAT ] [ UNSAT ]

operation. Auto start is inhibited for these nine pumps if the "43/FW" Switch is in the "OFF" position.

9 (Step 6.a) IF FW-6 is the affected pump, Contacted control room to Page 6 of 11

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-P1 Rev 3 JPM

Title:

Respond to a steam bound auxiliary feedwater pump STEP ELEMENT STANDARD THEN verify operability of FW- place 43/FW switch in OFF.

6 by performing the following:

a. Place the "43/FW" Switch in [ SAT ] [ UNSAT ]

"OFF".

CUE: 43/FW switch is in OFF.

10 (Step 6.b) Open FW-175, "MOTOR- Room 19 DRIVEN AUX FEED PUMP Opened FW-175 (counter-FW-6 DISCHARGE PRESS clockwise).

INDIC PI-1379 ROOT VALVE" (Room 19). [ SAT ] [ UNSAT ]

CUE: FW-175 stem rises until resistance is felt.

11 (Step 6.c) Start FW-6, Electric AFW Pump. CUE: IF Applicant contacted Control Room, Control Room directs you to start the pump locally.

Started the pump locally by depressing local Start button.

RED light ON and GREEN light OFF

[ SAT ] [ UNSAT ]

CUE: FW-6 red light is ON and you hear pump noise.

12 (Step 6.d) Allow FW-6 to run until pressure Room 19 on PI-1379, "FW-6 DISCH. Checked PI-1379 to determine PRESSURE" (Room 19), is discharge pressure.

greater than S/G(s) pressure.

[ SAT ] [ UNSAT ]

CUE: Indicator reads 1200 psia.

Page 7 of 11

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-P1 Rev 3 JPM

Title:

Respond to a steam bound auxiliary feedwater pump STEP ELEMENT STANDARD 13 (Step 6.e) Stop FW-6, Electric AFW Pump. CUE: IF Applicant contacted Control Room, Control Room directs you to stop the pump locally.

Stopped the pump locally by depressing RED local Stop button.

RED light OFF and GREEN light ON

[ SAT ] [ UNSAT ]

14 (Step 6.f) (Local) Verify that FW-6 stops Room 19 (Room 19). Verify green light is lit.

[ SAT ] [ UNSAT ]

CUE: Green light is lit. No motor noise. Pump shaft is not moving.

- 15 (Step Open and lock FW-171, Room 19 6.g) "MOTOR-DRIVEN AUX FEED FW-171 opened (counter-PUMP FW-6 DISCHARGE clockwise) and locked.

VALVE".

[ SAT ] [ UNSAT ]

CUE: FW-171 stem rises until resistance is felt, Locked with padlock (if applicant completes this action)

Page 8 of 11

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-P1 Rev 3 JPM

Title:

Respond to a steam bound auxiliary feedwater pump STEP ELEMENT STANDARD

- 16 (Step Start FW-6, Electric AFW Pump. CUE: IF Applicant contacted 6.h) Control Room, Control Room directs you to start the pump locally.

Started the pump locally by depressing local Start button.

RED light ON and GREEN light OFF

[ SAT ] [ UNSAT ]

CUE: FW-6 red light is ON, you hear pump noise.

17 (Step 6.i) Monitor pressure on PI-1379, Room 19 "FW-6 DISCH. PRESSURE" Checks PI-1379 for fluctuation.

(Room 19), for any abnormal fluctuation. [ SAT ] [ UNSAT ]

CUE: Indicator for PI-1379 reads 980 psia and is stable.

18 (Step 7) IF the Plant is in Mode 1, THEN This step N/A place the "43/FW" Switch in "AUTO". [ SAT ] [ UNSAT ]

19 (Step 8) Restore AFW to the desired CUE: Another operator will lineup PER OI-AFW-1, Auxiliary perform OI-AFW-1.

Feedwater Actuation System Normal Operation.

20 (Step 9) Ensure BOTH of the following Room 19 valves are closed (Room 19): FW-175 is closed (clockwise).

FW-175, "MOTOR-DRIVEN AUX FEED PUMP FW-6 [ SAT ] [ UNSAT ]

DISCHARGE PRESS INDIC PI-1379 ROOT VALVE" CUE: FW-175 stem position lowers until resistance if felt.

Page 9 of 11

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM-P1 Rev 3 JPM

Title:

Respond to a steam bound auxiliary feedwater pump Termination Criteria: Pump FW-6 is running and supplying AFW flow to the steam generators.

Page 10 of 11

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P1 Rev 3 INITIAL CONDITIONS: The plant is in hot shutdown. FW-10 and FW-54 are out of service. When attempting to feed the steam generators using auxiliary feedwater pump FW-6, feedwater flow to the steam generators lowered.

FW-6 is suspected to be steam or air bound due to low flow and oscillating amps. S/G pressure is 900 psia.

INITIATING CUE: CRS directs you to restore normal flow from Auxiliary Feedwater Pump, FW-6, to service using AOP-28,Section III.

Page 11 of 11

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-2 Rev 3 JPM

Title:

Racking Down a Non-Remote Equipped 4160 V Circuit Breaker Location: Electrical Lab Approximate Time: 20 minutes Start Time:__________________

End Time:___________________

Actual Time: _________________

Reference(s): K/A# 062000 A4.04 Ability to manually operate and/or monitor in the Control Room:

Local operation of breakers Procedures: OI-EE-1A, Attachment 2, Racking Down A Non-Remote Equipped 4160 V Breaker. Rev 25 Handout(s): OI-EE-1A, Attachment 2 Task List#: 0296 Applicable Position(s): AO/RO/SRO Time Critical: No Alternate Path: No JPM Prepared by: Jerry Koske Date: 3/22/12 Page 1 of 9

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-2 Rev 3 JPM

Title:

Racking Down a Non-Remote Equipped 4160 V Circuit Breaker Operators Name:

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:

Safety Considerations:

Comments:

Page 2 of 9

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-2 Rev 3 JPM

Title:

Racking Down a Non-Remote Equipped 4160 V Circuit Breaker TASK STANDARD: The Applicant racked down the 4160 Volt breaker in accordance with OI-EE-1A, Attachment 2. The breaker was left in its cubicle with the wheels blocked and the cubicle door closed.

INITIAL CONDITIONS: The plant is in mode 4.

INITIATING CUE: You are directed to rack down a 4160 Volt breaker per OI-EE-1A Attachment 2 Racking down is associated with an emergency condition. Therefore, arc flash protection clothing and establishment of a flash protection boundary is not required.

Page 3 of 9

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-2 Rev 3 JPM

Title:

Racking Down a Non-Remote Equipped 4160 V Circuit Breaker Critical Steps shown in gray and **

STEP ELEMENT STANDARD 1 CAUTIONS Applicant read cautions As a minimum, the following protective clothing shall be [ SAT ] [ UNSAT ]

worn when raising or lowering 4160 Volt breakers for all persons within the Flash Protection Boundary:

40 calorie arc flash protection clothing Safety glasses Hearing protection

2. A Flash Protection Boundary shall be established at all doors to the Switchgear room of the breaker. If a roll up door is required to be open, the Flash Protection Boundary shall be established at all exterior doors into both Switchgear rooms.

3. A safety monitor shall be established inside the Flash Protection Boundary to:

a. Monitor the Flash Protection Boundary to prevent entry by personnel not wearing minimum required protective clothing during the racking evolution.

b. Provide emergency aid to persons within the Flash Protection Boundary, if needed.

4. All personnel in the area shall stand clear of the breaker cubicle front.

5. When raising or lowering a breaker, your head must be turned or your eyes covered to protect against possible electrical flash.

Page 4 of 9

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-2 Rev 3 JPM

Title:

Racking Down a Non-Remote Equipped 4160 V Circuit Breaker STEP ELEMENT STANDARD

6. Operate the Breaker Elevator Motor with one hand, standing to one side of the cubicle.

7. Do not energize the motor circuit or interrupt raising or lowering a breaker using the Motor Raise/Lower selector switch.

8. The breaker springs will discharge as the breaker is lowered.

2 (1.a) Complete the following to rack CUE: Control Room breaker down a circuit breaker: 1. control switch is in PULL-Ensure breaker control switch, TO-LOCK is in PULL-TO-LOCK (Control Room). [ SAT ] [ UNSAT ]

3 (1.b) Ensure the green indicating Verified the GREEN light was light is on (local switchgear ON.

cabinet).

[ SAT ] [ UNSAT ]

- 4 (1.c) Ensure the breaker 69 Placed the breaker 69 switch permissive switch, on the local in PULL-TO-LOCK switchgear cabinet, is in PULL-TO-LOCK. [ SAT ] [ UNSAT ]

5 NOTE Read Note To prevent disturbing protective relays, breaker cubicle doors [ SAT ] [ UNSAT ]

should be opened and closed carefully.

6 (1.d) Verify the breaker local Verified the local indicator open/closed indicator displays displayed OPEN OPEN.

[ SAT ] [ UNSAT ]

Page 5 of 9

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-2 Rev 3 JPM

Title:

Racking Down a Non-Remote Equipped 4160 V Circuit Breaker STEP ELEMENT STANDARD

- 7 (1.e) Press the manual trip push Pressed the manual TRIP button. pushbutton

[ SAT ] [ UNSAT ]

- 8 (1.f) Install, latch, and plug in the Installed, latched and plugged elevator motor into the cubicle in the elevator motor elevating mechanism.

[ SAT ] [ UNSAT ]

- 9 (1.g) Place the elevator motor control Placed the elevator motor selector switch in the LOWER control selector switch in the position. LOWER position.

[ SAT ] [ UNSAT ]

- 10 (1.h) Pull the clutch handle above the Pulled the clutch handle elevator motor towards the toward the motor until it motor until it engages the engages and lowered the elevator motor lowering the breaker to the lower limit.

breaker until the elevator motor limits out. [ SAT ] [ UNSAT ]

- 11 (1.i) Release the clutch handle. Released the clutch handle

[ SAT ] [ UNSAT ]

- 12 (1.j) Place the elevator motor selector Placed the elevator motor switch in OFF and remove from selector switch in OFF and the cubicle elevating removed the motor from the mechanism. elevating mechanism.

[ SAT ] [ UNSAT ]

CUE: The Reactor is in Mode 4 and the equipment associated with this breaker is required to be available per SO-O-21 Page 6 of 9

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-2 Rev 3 JPM

Title:

Racking Down a Non-Remote Equipped 4160 V Circuit Breaker STEP ELEMENT STANDARD 13 (2) IF the reactor operating Maintained breaker in cubicle.

condition is in Mode 4 or 5 AND Blocked the breaker wheels.

the associated 2.equipment is required to be available per SO-O-21, THEN maintain the [ SAT ] [ UNSAT ]

breaker in its cubicle AND block the breaker wheels.

13 NOTE Read Note.

Use only the breaker handles to pull the breaker from its [ SAT ] [ UNSAT ]

cubicle.

14 (3.a) WHEN the breaker is racked Verified breaker in cubicle with down, 3.THEN complete the wheels blocked.

following:

a. Place the breaker in one of [ SAT ] [ UNSAT ]

the following conditions:

The breaker is removed from the cubicle AND stored per SO-G-107. The breaker is in its cubicle AND the breaker wheels are blocked.

15 NOTE Read Note To prevent disturbing protective relays, breaker cubicle doors should be opened and closed [ SAT ] [ UNSAT ]

carefully.

- 16 (3.b) Raise the upper door hinge Raised the upper door hinge arm AND carefully close the and closed the cubicle door.

cubicle door.

[ SAT ] [ UNSAT ]

Page 7 of 9

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-2 Rev 3 JPM

Title:

Racking Down a Non-Remote Equipped 4160 V Circuit Breaker STEP ELEMENT STANDARD 17 (3.c) If desired, return elevator motor CUE: Leave motor in the Lab and protective clothing to their proper storage place. [ SAT ] [ UNSAT ]

Termination Criteria: Breaker has been racked down, wheels blocked and cubicle door closed.

Page 8 of 9

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

INITIAL CONDITIONS: The plant is in mode 4.

INITIATING CUE: You are directed to rack down a 4160 Volt breaker per OI-EE-1A Attachment 2 Racking down is associated with an emergency condition. Therefore, arc flash protection clothing and establishment of a flash protection boundary is not required.

Page 9 of 9

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-3 Rev 3 JPM

Title:

Waste Gas Transfer from the Vent Header to the Gas Decay Tank Location: RCA Approximate Time: 30 minutes Start Time:__________________

End Time:___________________

Actual Time: _________________

Reference(s): K/A# 071000 A4.05 RO IMP: 2.6 SRO IMP:2.6 Ability to manually operate and/or monitor in the control room:

Gas decay tanks, including valves, indicators, and sample line.

Procedures: OI-WDG-1, Attachment 3, Waste Gas Transfer from the Vent Header to a Waste Gas Decay Tank, Rev 42 Handout(s): OI-WDG-1, Attachment 3 Task List#: 0736 Applicable Position(s): EONA/RO/SRO Time Critical: NO Alternate Path: YES JPM Prepared by: Jerry Koske Date: 3/21/2012 Page 1 of 12

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-3 Rev 3 JPM

Title:

Waste Gas Transfer from the Vent Header to the Gas Decay Tank Operators Name:

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:

Safety Considerations: Requires RCA Entry Comments:

Page 2 of 12

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-3 Rev 3 JPM

Title:

Waste Gas Transfer from the Vent Header to the Gas Decay Tank TASK STANDARD: The Applicant transferred waste gas from the vent header to the in-service Gas Decay Tank in accordance with OI-WDG-1, Attachment 3. Prior to starting WD-28A, the Applicant drained the moisture separator tank.

INITIAL CONDITIONS: Vent header pressure is at 2 psig. CCW cooling water is lined up and providing cooling to WD-28A, A Waste Gas Compressor. The pressure of the in-service Waste Gas Decay Tank, WD-29B, is 45 psig. AI-110 is inoperable. The Shift Chemist is on standby to take samples when notified. PI-686 is out of service.

INITIATING CUE:

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 1.0 psig using OI-WDG-1, Attachment 3. All prerequisites are met.

Page 3 of 12

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-3 Rev 3 JPM

Title:

Waste Gas Transfer from the Vent Header to the Gas Decay Tank Critical Steps shown in gray and **

STEP ELEMENT STANDARD 1 (1) IF it is desired to pump the vent Determined that it was not header below 1.0 psig, THEN desired to pump below 1.0 perform Steps 1 through 4 of psig. Marked step as N/A Attachment 7.

[ SAT ] [ UNSAT ]

2 CAUTION Candidate read Caution To prevent an uncontrolled release of radioactive gas to [ SAT ] [ UNSAT ]

the Auxiliary Building and a possible Ventilation Isolation Actuation Signal (VIAS), the Waste Gas Vent Header shall not be drained while a VCT Gas Sample is being drawn.

3 (2) Ensure the following VCT Gas AI-110 Space Sampling valves are closed (AI-110, Waste Gas Verified WD-242 and WD-analyzer): 1080 are closed.

WD-242 Note: Inform candidate that

WD-1080 visual indication of valve position is all that is required. Valve is closed when handle is perpendicular to piping.

[ SAT ] [ UNSAT ]

Page 4 of 12

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-3 Rev 3 JPM

Title:

Waste Gas Transfer from the Vent Header to the Gas Decay Tank STEP ELEMENT STANDARD 4 (3) Verify the Waste Gas Vent Room 13 Header is void of water by performing the following steps Examiner CUE: Before (Room 13): Applicant enters room 13, tell Applicant that The vent header in room 13 has been drained, Step 3 is complete (ALARA) 5 NOTE Candidate read note and LCV-533B, Moisture Separator A caution Makeup Control Valve, and LCV-534B, Moisture Separator B Makeup Control Valve, will only [ SAT ] [ UNSAT ]

open when there is a low level.

CAUTION To prevent pump rotor failure, a Waste Gas Compressor must not be run dry.

6 (4.a) Ensure the selected Waste Gas Room 16 Compressor is operable and primed by performing the Ensured DW-156 was OPEN following steps (Room 16):

CUE: DW-156 stem is as you

a. Ensure the Seal Water see it.

Isolation Valve to the Waste Gas Compressor Skid is open: [ SAT ] [ UNSAT ]

WD-28A, DW-156

WD-28B, DW-157 7 NOTE Applicant read note Normal Moisture Separator Tank level, relative to the pump [ SAT ] [ UNSAT ]

casing, is above the casing bottom and below the pump rotor centerline (C L )

Page 5 of 12

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-3 Rev 3 JPM

Title:

Waste Gas Transfer from the Vent Header to the Gas Decay Tank STEP ELEMENT STANDARD Alternate Path

- 8 (4.b) IF Moisture Separator Tank is Room 16 above the pump rotor centerline, drain the tank: Checked Moisture Separator Tank Level

WD-28A, WD-216

WD-28B, WD-217 CUE: Water level is at second set of nuts from top on sightglass. (above the pump rotor centerline)

a. Opened WD-216 (counter-clockwise)

b. Stem rises until resistance felt.

b. CUE: Water level is below pump rotor centerline

c. Closed WD-216 (clockwise)

[ SAT ] [ UNSAT ]

CUE: stem lowers until resistance felt NOTE Read note before step 4C Reference drawing file numbers referencing drawing.

41162, 19745 and 19954

[ SAT ] [ UNSAT ]

Page 6 of 12

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-3 Rev 3 JPM

Title:

Waste Gas Transfer from the Vent Header to the Gas Decay Tank STEP ELEMENT STANDARD 9 (4.c) IF Moisture Separator Tank level Room 16 is below the casing bottom, fill by performing the following steps: Checked Moisture Separator Tank Level CUE: Water level is above the casing bottom.

Marked step N/A

[ SAT ] [ UNSAT ]

10 (5) If running one or more Waste Determines the CCW is Gas Compressors without CCW available to the Waste Gas cooling water, station an Compressor (Initial Conditions)

Operator to ensure seal water and marks step N/A temperature does not exceed 150 F. [ SAT ] [ UNSAT ]

TI/WD-28A, Waste Gas Compressor WD-28A Seal Water Temperature Indicator

TI/WD-28B, Waste Gas Compressor WD-28B Seal Water Temperature Indicator 11 (6) IF AI-110 is operable, THEN Determined AI-110 is not perform the following: operable (Initial Condition) and Marked step as N/A.

[ SAT ] [ UNSAT ]

12 CAUTION Applicant read caution H2 and O2 Concentrations in the WGDT must not exceed 3%. [ SAT ] [ UNSAT ]

Page 7 of 12

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-3 Rev 3 JPM

Title:

Waste Gas Transfer from the Vent Header to the Gas Decay Tank STEP ELEMENT STANDARD

- 13 (7.a) Commence Waste Gas AI-100 Transfer by performing the Note: if power is off, then following steps: cue, GREEN light is ON.

a. Start the selected Waste Gas WD-28A control switch to Compressor: HAND

WD-28A RED light ON

WD-28B GREEN light OFF Cue:You hear compressor noise.

[ SAT ] [ UNSAT ]

14 (7.b) Monitor the following: Examiner Note: H2 and O2

H2 and O2 concentrations cannot be

WGDT Pressure (PI- monitored with AI-110 517) inoperable.

Vent Header Pressure AI-100 (PI-589) Monitored WGDT and Vent Header Pressures PI-517 Pressure starts at 50 psig and rising PI-589 pressure 2 psig and slowly decreasing

[ SAT ] [ UNSAT ]

15 NOTE Candidate read note AI-110 HI H2 and O2 CONCENTRATION (AI-100, A- [ SAT ] [ UNSAT ]

50, B-4) will be in alarm (AI-100) when H2 and O2 Concentrations exceed 3%.

Page 8 of 12

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-3 Rev 3 JPM

Title:

Waste Gas Transfer from the Vent Header to the Gas Decay Tank STEP ELEMENT STANDARD 16 (8) IF H2 and O2 Concentrations Examiner Note: H2 and O2 exceed 3%, THEN secure the concentrations cannot be Waste Gas Transfer by monitored with AI-110 performing the following steps: inoperable.

Mark step N/A 17 (9) If running a Waste Gas Determines the CCW is Compressor without CCW available to the Waste Gas cooling water and seal water Compressor (Initial Conditions) temperature reaches 150°F, stop and marks step N/A the Waste Gas Compressor.

[ SAT ] [ UNSAT ]

18 NOTE Candidate read note and Waste Gas Compressors caution automatically shutdown on a Low Suction Pressure of [ SAT ] [ UNSAT ]

approximately 0.5 psig.

CAUTION The Vent Header should not be pumped down beyond atmospheric pressure. Placing a vacuum on the vent header could cause damage to the system and/or system components. This header was not designed to be under a vacuum.

CUE: WGDT (PI-517) = 50 psig Vent Header(PI-526 or PI-589) = 1.0 psig NOTE: PI-526 is in room 16 PI-589 is on AI-100 in AI-100 room Page 9 of 12

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-3 Rev 3 JPM

Title:

Waste Gas Transfer from the Vent Header to the Gas Decay Tank STEP ELEMENT STANDARD

- 19 (10) WHEN the Vent Header AI-100 pressure is approximately 1.0 psig (PI-526), In Service WGDT WD-28A control switch to OFF pressure reaches full capacity and GREEN light ON (95-100 psig), or Degassing Operations are completed, or [ SAT ] [ UNSAT ]

Vent Header is at desired pressure below 1.0 psig (PI- CUE: GREEN light ON, RED 526), THEN stop the selected light OFF. You hear Waste Gas Compressor: compressor stop.

WD-28A

WD-28B 20 (11) IF AI-110 is operable, THEN 5 Determined AI-110 is minutes after the Waste Gas inoperable. Marked step as Transfer is secured. N/A.

[ SAT ] [ UNSAT ]

22 (12) IF AI-110 is inoperable, CUE: Shift Chemist Acknowledges.

THEN notify the following:

Shift Chemist to obtain grab [ SAT ] [ UNSAT ]

samples.

22 (12) Shift Manager to review CUE: Shift Manager Notified Technical Specification 2.9.

[ SAT ] [ UNSAT ]

CUE: JPM Complete Page 10 of 12

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-3 Rev 3 JPM

Title:

Waste Gas Transfer from the Vent Header to the Gas Decay Tank Termination Criteria: Waste gas has been transferred from the Vent Header to the in-service gas decay tank and the Waste Gas Compressor has been secured.

Page 11 of 12

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: P-3 Rev 3 INITIAL CONDITIONS: Vent header pressure is at 2 psig. CCW cooling water is lined up and providing cooling to WD-28A, A Waste Gas Compressor. The pressure of the in-service Waste Gas Decay Tank, WD-29B, is 45 psig. AI-110 is inoperable. The Shift Chemist is on standby to take samples when notified. PI-686 is out of service.

INITIATING CUE: 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 1.0 psig using OI-WDG-1, Attachment 3. All prerequisites are met.

Page 12 of 12

FORT CALHOUN STATION CONTINUOUS USE ARP-CB-1,2,3/A4 ANNUNCIATOR RESPONSE PROCEDURE PAGE 4 OF 52 Panel: CB-1/2/3 Annunciator: A4 Window: A-2 PRESSURIZER POWER OPERATED RELIEF VALVES DISCHARGE TAILPIPE TEMPERATURE HIGH Page 1 of 2 PRESSURIZER SAFETY RELATED PWR OPERATED RELIEF VALVE DISCH TEMP HI Tech Spec

References:

2.1.4, 2.15 Initiating Device TIA-134 Setpoint >130°F Power AI-42A OPERATOR ACTIONS

1. Check the Power Operated Relief Valves Tailpipe Temperature (TIA-134, CB-3).

2. IF Temperature is High, THEN perform the following:

2.1 Check the Containment Temperature (T887, T888, T889, T890, ERF).

2.1.1 IF Containment Temperature is greater than 120°F, THEN provide additional cooling to the Containment.

2.2 Check the VCT Level Recorder for decreasing Level (YR-4100, CB-2).

2.3 Monitor Pressurizer Quench Tank.

2.3.1 IF temperature (TIA-133, CB-3) approaches 120°F, THEN perform OI-RC-6 Attachment 5, Quench Tank Temperature Control Following Safety or Relief Valve Discharge.

(continue)

PROBABLE CAUSES Power Operated Relief Valve seat leakage Containment Temperature high Instrument malfunction REFERENCES 136B3081 Sh 20 06244 161F561 Sh 2 09477 161F561 Sh 14 09496 EM-134 00804 E-23866-210-110 10475 IC-ST-RC-0029 R30

FORT CALHOUN STATION CONTINUOUS USE ARP-CB-1,2,3/A4 ANNUNCIATOR RESPONSE PROCEDURE PAGE 5 OF 52 Panel: CB-1/2/3 Annunciator: A4 Window: A-2 PRESSURIZER POWER OPERATED RELIEF VALVES DISCHARGE TAILPIPE TEMPERATURE HIGH Page 2 of 2 SAFETY RELATED OPERATOR ACTIONS (continued) 2.4 Perform RCS Leak Rate Test OP-ST-RC-3001.

2.4.1 IF RCS Leakage is indicated, THEN close the PORV Block Valves one at a time AND monitor Tailpipe Temperature for decrease.

PCV-102-1 HCV-151 PCV-102-2 HCV-150

3. IF TIA-134 remains high AND no leakage from the RCS is indicated, THEN notify I&C to check the function of the instrument.

R30

FORT CALHOUN STATION CONTINUOUS USE ARP-CB-1,2,3/A6 ANNUNCIATOR RESPONSE PROCEDURE PAGE 57 OF 61 Panel: CB-1/2/3 Annunciator: A6 Window: E-5 LOSS OF POWER TO HCV-151, PZR PORV PCV-102-1 BLOCK VALVE HCV-151 SAFETY RELATED TROUBLE Tech Spec

References:

2.1.6 Initiating Device 74/HCV-151 Setpoint UNDERVOLTAGE Power MCC-4A1 OPERATOR ACTIONS

1. Check the indicating lights HCV-151 (CB-3).

2. IF the valve indicating lights are off, THEN dispatch an Operator to check the valve breaker closed (MCC-4A1, Breaker C05).

2.1 IF breaker is tripped, THEN notify Electrical Maintenance of valve motor fault.

2.2 IF breaker is closed, THEN notify Electrical Maintenance to check the Control Power Fuses.

2.3 Ensure the requirements of Technical Specification 2.1.6 are met.

3. IF the breaker is closed, THEN reset breaker overloads.

3.1 Ensure the Overload Bypass Switch is in the NORMAL position.

3.2 IF the annunciator is still in alarm, THEN notify Electrical Maintenance.

PROBABLE CAUSES Overcurrent or overload on the breaker for HCV-151 REFERENCES 136B3081 Sh 35 06259 11405-E-51 41445 R46

FORT CALHOUN STATION OI-RC-7 OPERATING INSTRUCTION C PAGE 21 OF 26 Continuous Use Attachment 5 - MANUAL to AUTOMATIC Transfer for the Selected Channel PREREQUISITES ~ INITIALS

1. Procedure Revision Verification Revision Number_--'-/-:7 _ Date: 1#1 PROCEDURE

1. Note Output Meter reading and mark with moveable slide marker.

PC-103X, Pressurizer Press Controller

PC-103Y, Pressurizer Press Controller NOTE The following setpoint adjustment is made such that any deviation which may exist between manual and automatic output will drive controller output in the direction of proportional heaters.

2. Adjust SET pushbuttons such that Setpoint Meter (Blue) indication is slightly greater than Process Meter (Red) indication.

PC-103X, Pressurizer Press Controller

PC-103Y, Pressurizer Press Controller R17

FORT CALHOUN STATION OI-RC-7 OPERATING INSTRUCTION C PAGE 22 OF 26 Continuous Use Attachment 5 - MANUAL to AUTOMATIC Transfer for the Selected Channel PROCEDURE (continued)

NOTE Immediately following the transfer from Manual to Auto, the output meter will deflect in the heater direction. This change in output will occur linearly over approximately a 10 second period.

3. Place controller in automatic by pressing the A push-button and monitor the output meter for change.

PC-103X, Pressurizer Press Controller

PC-103Y, Pressurizer Press Controller NOTES

1. Left deflection on the meter will require a lowering of the setpoint, and right deflection on meter will require a raise in the setpoint, for compensation. This adjustment will take approximately 10 seconds.

2. At the final desired setpoint, it is normal for a slight offset to exist between Process Meter and Setpoint Meter indications.

4. Use SET pushbuttons and make small setpoint adjustments as necessary to return Output Meter reading to original position, indicated by the moveable slide marker.

PC-103X, Pressurizer Press Controller

PC-103Y, Pressurizer Press Controller Completed by Date/Time ':.-_

R17

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-1 Rev 3 JPM

Title:

Swap Pressurizer Pressure Mode from Manual to Automatic Location: Simulator Approximate Time: 20 minutes Start Time:__________________

End Time:___________________

Actual Time: _________________

Reference(s): K/A# 010000 A2.03 RO IMP: 4.1 SRO IMP: 4.2 Ability to (a) predict the impacts of the following malfunctions or operations on the PZR PCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: PORV failures.

Procedures: OI-RC-7, Attachment 5, MANUAL to AUTOMATIC Transfer for the Selected Channel, Rev 17 ARP-CB-1,2,3/A4, A-2 ARP-CB-1,2,3/A6, E-5 Other (tech specs, etc)

Handout(s): OI-RC-7, Attachment 5, MANUAL to AUTOMATIC Transfer for the Selected Channel, Rev 17 Task List#: 1314 Applicable Position(s): RO/SRO Time Critical: NO Alternate Path: YES JPM Prepared by: Jerry Koske Date: 3/17/2012 Page 1 of 11

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-1 Rev 3 JPM

Title:

Swap Pressurizer Pressure Mode from Manual to Automatic Operators Name:

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:

Safety Considerations:

Comments: IC# 106 Page 2 of 11

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-1 Rev 3 JPM

Title:

Swap Pressurizer Pressure Mode from Manual to Automatic TASK STANDARD: The Candidate transferred PC-103Y to automatic mode in accordance with OI-RC-7, Attachment 5. The candidate responded to a PORV PCV-102-1 leak by attempting to close block valve HCV-151. When an overload occurred on the breaker for HCV-151, the Candidate directed the Building Operator to reset the overload trip. The Candidate than ensured HCV-151 closed and isolated the leaking PORV.

INITIAL CONDITIONS: The plant is operating at full power. Pressurizer Pressure Controller PC-103 Y is in manual for I&C testing. I&C testing is complete.

INITIATING CUE: You are directed to transfer PC-103Y to Automatic using OI-RC-7, Attachment 5. All prerequisites are met.

Critical Steps shown in gray and **

Page 3 of 11

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-1 Rev 3 JPM

Title:

Swap Pressurizer Pressure Mode from Manual to Automatic STEP ELEMENT PERFORMANCE STANDARD 1 (1) Note Output Meter reading and CB-1,2,3 mark with moveable slide marker. Positioned PC-103Y movable

PC-103X, Pressurizer slide meter to match output Press Controller meter reading

PC-103Y, Pressurizer Press Controller [ SAT ] [ UNSAT ]

2 Note: Read Note The following setpoint adjustment is made such that any deviation which may exist [ SAT ] [ UNSAT ]

between manual and automatic output will drive controller output in the direction of proportional heaters.

3 (2) Adjust SET pushbuttons such CB-1,2,3 that Setpoint Meter (Blue) Used PC-103Y SET indication is slightly greater pushbuttons to adjust Blue than Process Meter (Red) indication slightly greater than Indication. Red indication

PC-103X, Pressurizer Press Controller [ SAT ] [ UNSAT ]

PC-103Y, Pressurizer Press Controller Note: Read Note Immediately following the transfer from Manual to Auto, the output meter will deflect in [ SAT ] [ UNSAT ]

the heater direction. This change in output will occur linearly over approximately a 10 second period.

Page 4 of 11

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-1 Rev 3 JPM

Title:

Swap Pressurizer Pressure Mode from Manual to Automatic STEP ELEMENT PERFORMANCE STANDARD

- 4 (3) Place controller in automatic by CB-1,2,3 pressing the A push-button and Pressed the PC-103Y A monitor the output meter for pushbutton and monitored the change. output meter.

PC-103X, Pressurizer Press Controller [ SAT ] [ UNSAT ]

PC-103Y, Pressurizer Press Controller 5 Notes: Read the Notes

1. Left deflection on the meter will require a lowering of the setpoint, and right deflection on [ SAT ] [ UNSAT ]

meter will require a raise in the setpoint, for compensation.

This adjustment will take approximately 10 seconds.

2. At the final desired setpoint, it is normal for a slight offset to exist between Process Meter and Setpoint Meter indications.

6 (4) Use SET pushbuttons and CB-1,2,3 make small setpoint Adjusted PC-103Y SET adjustments as necessary to pushbuttons as required to return Output Meter reading to return output meter to position original position, indicated by indicated by movable slide the movable slide marker. marker.

PC-103X, Pressurizer Press Controller

PC-103Y, Pressurizer [ SAT ] [ UNSAT ]

Press Controller EXAMINER: Provide cue to simulator operator to insert PCV-102-1 malfunction.

Page 5 of 11

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-1 Rev 3 JPM

Title:

Swap Pressurizer Pressure Mode from Manual to Automatic STEP ELEMENT PERFORMANCE STANDARD Alternate Path Begins 7 PRESSURIZER PWR Entered ARP-CB-1,2,3/A4 and OPERATED RELIEF VALVE turned to Window A-2 DISCH TEMP HI alarm

[ SAT ] [ UNSAT ]

8 (1) Check the Power Operated CB-1,2,3 Relief Valves Tailpipe Determined that temperature Temperature (TIA-134, CB-3) indicated by TIA-134 has risen.

[ SAT ] [ UNSAT ]

9 If Temperature is High, THEN ERF Computer (2, 2.1, 2.1.1) Perform the following: Used ERF Computer and Check the Containment determined that Containment Temperature (T887, T888, temperature was below 120°F T889,T890, ERF)

IF Containment Temperature is greater than 120°F, THEN [ SAT ] [ UNSAT ]

provide additional cooling to the Containment.

10 (2.2) Check the VCT Level Recorder CB-1,2,3 for decreasing Level (YR-4100, Checked VCT level recorder.

CB-2) May have determined that level was decreasing slowly.

[ SAT ] [ UNSAT ]

Page 6 of 11

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-1 Rev 3 JPM

Title:

Swap Pressurizer Pressure Mode from Manual to Automatic STEP ELEMENT PERFORMANCE STANDARD 11 Monitor Pressurizer Quench CB-1,2,3 (2.3, 2.3.1) Tank Monitored Quench Tank IF temperature (TIA-133, CB-3) Temperature and Level. May approaches 120°F, THEN have determined that pressure perform OI-RC-6 Attachment 5, and level were slowly Quench Tank Temperature increasing. Determined that Control Following Safety or temperature was below 120°F.

Relief Valve Discharge.

[ SAT ] [ UNSAT ]

12 (2.4) Perform RCS Leak Rate Test Examiner CUE: RCS leak OP-ST-RC-3001 rate test indicates 4 gpm leakage

- 13 (2.4.1) IF RCS Leakage is indicated, CB-1,2,3 THEN close the PORV Block Attempted to close HCV-151 Valves one at a time AND by placing Control Switch in monitor Tailpipe Temperature the CLOSE Position for decrease.

[ SAT ] [ UNSAT ]

NOTE: HCV-151 Breaker overload tripped when Candidate attempted to close the block valve.

14 HCV-151 TROUBLE Alarm Entered ARP-CB-1,2,3/A6 and turned to Window E-5

[ SAT ] [ UNSAT ]

15 (1) Check the indicating lights CB-1,2,3 HCV-151 Determined that valve indicating lights are off.

[ SAT ] [ UNSAT ]

Page 7 of 11

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-1 Rev 3 JPM

Title:

Swap Pressurizer Pressure Mode from Manual to Automatic STEP ELEMENT PERFORMANCE STANDARD 16 (2) IF the valve indicating lights are Dispatched Building Operator off, THEN dispatch an Operator to MCC-4A1, Breaker C05 to to check the valve breaker check if the valve breaker is closed (MCC-4A1, Breaker closed.

C05)

[ SAT ] [ UNSAT ]

Examiner Cue: Water Plant Operator reports breaker is closed. Overload trip has occurred.

17 (2.1) If breaker is tripped, THEN Determined step N/A because notify Electrical Maintenance of breaker did not trip.

valve motor fault.

[ SAT ] [ UNSAT ]

18 (2.2) If breaker is closed, THEN Notified Electrical Maintenance notify Electrical Maintenance to to check the Control Power check the Control Power Fuses.

Fuses.

[ SAT ] [ UNSAT ]

Examiner Cue: Electrical Maintenance reports Control Power fuses are good.

19 (2.3) Ensure the requirements of Examiner Cue: The CRS is Technical Specification 2.1.6 addressing the Technical are met. Specification.

20 If the breaker is closed, THEN Directed Building Operator to (3., 3.1) reset breaker overloads. reset breaker overloads on Ensure the Overload Bypass MCC-4A1, Breaker C05 and Switch is in the NORMAL ensure the Overload Bypass position. Switch is in the Normal position

[ SAT ] [ UNSAT ]

Page 8 of 11

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-1 Rev 3 JPM

Title:

Swap Pressurizer Pressure Mode from Manual to Automatic STEP ELEMENT PERFORMANCE STANDARD NOTE: The HCV-151 TROUBLE alarm will reset.

Examiner Cue: Building Operator reports breaker overloads are reset and overload bypass switch is in the Normal position.

21 (3.2) IF the annunciator is still in CB-1,2,3 alarm, THEN notify Electrical Determined annunciator was Maintenance. not in alarm.

[ SAT ] [ UNSAT ]

NOTE: HCV-151 will close when overloads are reset unless the HCV-151 switch was returned to the open position.

- 22 (2.4.1) IF RCS Leakage is indicated, This step in NOT critical if THEN close the PORV Block the HCV-151 switch was left Valves one at a time in the Close position.

CB-1,2,3.

Closed HCV-151 by placing Control Switch in the CLOSE Position, Green Light ON

[ SAT ] [ UNSAT ]

23 (2.4.1) AND monitor Tailpipe CB-1,2,3 Temperature for decrease. Monitored TIA-134 and determined that tailpipe temperature was decreasing.

[ SAT ] [ UNSAT ]

Page 9 of 11

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-1 Rev 3 JPM

Title:

Swap Pressurizer Pressure Mode from Manual to Automatic Termination Criteria: PC-103Y is controlling in Automatic and HCV-151 is closed isolating PORV PCV-102-1.

Page 10 of 11

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-1 Rev 3 INITIAL CONDITIONS: The plant is operating at full power. Pressurizer Pressure Controller PC-103 Y is in manual for I&C testing. I&C testing is complete.

INITIATING CUE: You are directed to transfer PC-103Y to Automatic using OI-RC-7, Attachment 5. All prerequisites are met.

Page 11 of 11

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S2 Rev 3 JPM

Title:

Engineered Safeguards Actuation Verification Location: Simulator Approximate Time: 15 minutes Start Time:__________________

End Time:___________________

Actual Time: _________________

Reference(s): K/A# 006000 A3.03 RO IMP: 4.1 SRO IMP:4.1 Ability to monitor automatic operation of the ECCS, including:

ESFAS-operated valves.

Procedures: EOP/AOP Floating Step W, Rev 3 EOP/AOP Attachment 3 Other (tech specs, etc)

Handout(s): EOP/AOP Floating Step W, ENFGINEERED SAFEGUARDS ACTUATION VERIFICATION.

Task List#: 0334 Applicable Position(s): RO/SRO Time Critical: NO Alternate Path: YES JPM Prepared by: Jerry Koske Date: 3/17/2012 Page 1 of 8

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S2 Rev 3 JPM

Title:

Engineered Safeguards Actuation Verification Operators Name:

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:

Safety Considerations:

Comments: IC-105 Event File: Close HPSI, Fail 86/B PPLS Page 2 of 8

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S2 Rev 3 JPM

Title:

Engineered Safeguards Actuation Verification TASK STANDARD: The Candidate verified Engineered Safeguards Actuation in accordance with EOP/AOP Floating Step W. During this verification, the Candidate determined that a PPLS Relay failed to actuate and manually initiated PPLS. The Candidate also determined that SI flow was inadequate per EOP/AOP Attachment 3 and took action to restore adequate flow by opening the HPSI Injection Valves.

INITIAL CONDITIONS: The plant was operating at full power when a reactor trip and safeguards actuation occurred.

INITIATING CUE: The CRS directs you to verify Engineered Safeguards Actuation using EOP/AOP Attachment W.

Page 3 of 8

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S2 Rev 3 JPM

Title:

Engineered Safeguards Actuation Verification Critical Steps shown in gray and **

STEP ELEMENT STANDARD 1 (1) IF PPLS is blocked, THEN GO Verified PPLS was NOT TO Step 4. blocked by:

CB-1,2,3 Verified the following annunciators are NOT in alarm:

PPLS "A" BLOCKED (CB-1/2/3, A4, E-5)

PPLS "B" BLOCKED (CB-1/2/3, A4, E-6)

AND/OR AI-30A/B Verified the following annunciators are NOT in alarm:

PPLS-A BLOCKED (AI-30A, A33-1, C-1)

PPLS-B1 BLOCKED (AI-30A, A33-2, C-1)

PPLS-B BLOCKED (AI-30B, A34-1, C-7)

PPLS-A1 BLOCKED (AI-30B, A34-2, C-4)

[ SAT ] [ UNSAT ]

2 (2) IF ALL of the following exists, Determined that all of the

RCS pressure less than listed conditions are NOT met 1600 psia because pressure in both S/Gs

Containment pressure is greater than 500 psia. Went greater than 5 psig to step 3.

At least one S/G pressure less than or equal to 500 [ SAT ] [ UNSAT ]

psia Page 4 of 8

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S2 Rev 3 JPM

Title:

Engineered Safeguards Actuation Verification STEP ELEMENT STANDARD 3 (3) IF RCS pressure is less than or AI-30A/B equal to 1600 psia, THEN verify Checked the status of each of Engineered Safeguards are the listed relays. Determined actuated by performing the that 86B/PPLS did not actuate following steps:

Verify ALL of the following PPLS [ SAT ] [ UNSAT ]

relays have tripped:

86A/PPLS

86B1/PPLS

86B/PPLS

86A1/PPLS Next Step is Alternate Path

- 4 (3.a.1) IF any of the PPLS relays have AI-30B NOT tripped, THEN manually initiate using the PPLS Test

Removed key from key Switches holder

Inserted it into the B PPLS Test Switch

Turned key clockwise

Verified 86/B PPLS relay actuated.

[ SAT ] [ UNSAT ]

5 (3.b) Ensure CIAS has initiated as AI-30A/B indicated by ALL of the following CIAS relays being tripped: Verified that each of the listed

86A/CIAS relays was in the TRIPPED

86B1/CIAS position with its Amber light

86B/CIAS OFF

86A1/CIAS

[ SAT ] [ UNSAT ]

Page 5 of 8

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S2 Rev 3 JPM

Title:

Engineered Safeguards Actuation Verification STEP ELEMENT STANDARD 6 (3.c) Ensure VIAS has initiated as AI-30A/B indicated by ALL of the following VIAS relays being tripped: Verified that each of the listed

86A/VIAS relays was in the TRIPPED

86B1/VIAS position with its Amber light

86B/VIAS OFF

86A1/VIAS

[ SAT ] [ UNSAT ]

7 (3.d) Ensure Emergency Boration is in Verified Emergency Boration progress. in progress by:

CB-4 Ensured the following valves were open (Red light ON)

HCV-268

HCV-265

HCV-258 Ensured the following pumps are running:

CH-4A

CH-4B CB-1,2,3 Ensured the following pumps are running:

CH-1A

CH-1B

CH-1C Ensured the following valves are closed:

LCV-218-2

LCV-218-3 CB-4 Ensured the following valve are closed:

HCV-257

HCV-264

[ SAT ] [ UNSAT ]

Page 6 of 8

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S2 Rev 3 JPM

Title:

Engineered Safeguards Actuation Verification STEP ELEMENT STANDARD Next step is alternate path

- 8 (3.e) Ensure SI flow is acceptable AI-30A/B or ERF Computer PER Attachment 3, Safety Injection Flow vs. Pressurizer Determined that flow was Pressure. inadequate due to HPSI injection valves being closed.

Opened the HPSI Injection Valves as required by turning switches clockwise until adequate flow was established:

HCV-311

HCV-312

HCV-314

HCV-315

HCV-317

HCV-318

HCV-320

HCV-321

[ SAT ] [ UNSAT ]

Examiner Cue: JPM Complete Termination Criteria: Candidate has completed EOP/AOP Floating Step W through step 3 and restored adequate SI flow.

Page 7 of 8

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S2 Rev 3 INITIAL CONDITIONS: The plant was operating at full power when a reactor trip and safeguards actuation occurred.

INITIATING CUE: The CRS directs you to verify Engineered Safeguards Actuation using EOP/AOP Attachment W.

Page 8 of 8

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM S-3 Rev 3 JPM

Title:

Place a Containment Cooling Unit in Service Location: Simulator Approximate Time: 10 minutes Start Time:__________________

End Time:___________________

Actual Time: _________________

Reference(s): K/A# 022000 A4.01 (RO 3.6 / SRO 3.6):

Ability to manually operate and/or monitor in the control room:

CCS Fans Procedures: OI-VA-1, Attachment 2 Rev 79 Other (tech specs, etc)

Handout(s): OI-VA-1, Attachment 2, Containment Cooling Operation VA-7C

& VA-7D Task List#: 0718 Applicable Position(s): RO/SRO Time Critical: NO Alternate Path: NO JPM Prepared by: Date:

Page 1 of 7

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM S-3 Rev 3 JPM

Title:

Place a Containment Cooling Unit in Service Operators Name:

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:

Safety Considerations:

Comments: Run in parallel to JPM S8, IC# 107 Page 2 of 7

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM S-3 Rev 3 JPM

Title:

Place a Containment Cooling Unit in Service TASK STANDARD: The Applicant initiated CCW flow to Containment Cooling Coil, VA-8A and started Containment Air Cooling Fan, VA-7C.

INITIAL CONDITIONS: The plant is in hot shutdown following a normal plant shutdown using OP-3A.

INITIATING CUE: You are directed to place Containment Air Cooling Fan, VA-7C, and Containment Cooling Coil, VA-8A, in service per OI-VA-1, Attachment 2.

All prerequisites are met.

Page 3 of 7

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM S-3 Rev 3 JPM

Title:

Place a Containment Cooling Unit in Service Critical Steps shown in gray and **

STEP ELEMENT STANDARD 1 CAUTION Applicant read caution During Power Operations, either VA-3A and VA-7C OR VA-38 and VA-7D must be maintained [ SAT ] [ UNSAT ]

operable. (SAO 07-003 and CR 2007-3052)

- 2 (1.a.1) IF VA-7C, Cntmt Vent Fan, is to be started, THEN perform the following:

a. IF Containment Cooling is desired, THEN initiate CCW to VA-8A as follows:

CB-1,2,3

1) Momentarily place HCV- Momentarily place HCV-402B/D, Cntmt Clg Coil VA-8A AC 402B/D in OPEN. Verify RED Vlvs Control SW to OPEN. lights lit for both valves.

[ SAT ] [ UNSAT ]

3 (1.a.2) Ensure HCV-402C, Cntmt Clg Coil CB-1,2,3 VA-8A Outlt Isol Vlv Cntrlr is Ensure controller POT in closed. closed position (100% output),

GREEN light ON

[ SAT ] [ UNSAT ]

- 4 (1.a.3) Momentarily place HCV-402NC, CB-1,2,3 Cntmt Clg Coil VA-8A Isol Momentarily place HCV-Vlvs Control SW to CIRC. 402A/C in CIRC position and release HCV-402A RED light ON

[ SAT ] [ UNSAT ]

Page 4 of 7

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM S-3 Rev 3 JPM

Title:

Place a Containment Cooling Unit in Service STEP ELEMENT STANDARD

- 5 (1.a.4) Throttle open HCV-402C CB-1,2,3 maintaining PI-499, CCW Adjust POT for HCV-402C Discharge Header Pressure, toward OPEN position.

greater than or equal to 70 psig. ENSURE pressure on PI-499 does not go below 70 psig.

[ SAT ] [ UNSAT ]

6 (1.a.5) Monitor the following CB-1,2,3 parameters:

FI-418

VA-8A Flow

TIC-422

VA-8A Temperature

PI-499

CCW Discharge Header

TIC-2800 Press

CCW Discharge Header [ SAT ] [ UNSAT ]

Temp 7 CAUTION Applicant read caution Running a fan for an extended period with the CCW isolated to the cooling coil can cause the [ SAT ] [ UNSAT ]

water to heatup inside the coil and possibly lift or cause the reliefs to weep.

Note: VA-7C low DP alarm expected next step

- 8 (1.b) Start VA-7C AI-30A VA-7C CS to AFTER-START (Red flag), RED light lit

[ SAT ] [ UNSAT ]

Page 5 of 7

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: JPM S-3 Rev 3 JPM

Title:

Place a Containment Cooling Unit in Service STEP ELEMENT STANDARD 9 (1.b) Monitor Parameters: AI-30A

VA-7C amps

VA-7C ammeter AI-44 Monitor:

VA-7C DP

PIC-702

VA-7C cooling coil DP

PI-710

VA-7C Outlet Temp

TI-719

[ SAT ] [ UNSAT ]

Termination Criteria: VA-7C is running and CCW is being supplied to VA-8A Page 6 of 7

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-3 Rev 3 INITIAL CONDITIONS: The plant is in hot shutdown following a normal plant shutdown using OP-3A.

INITIATING CUE: You are directed to place Containment Air Cooling Fan, VA-7C, and Containment Cooling Coil, VA-8A, in service per OI-VA-1, Attachment 2.

All prerequisites are met.

Page 7 of 7

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-4 Rev. 3 JPM

Title:

Initiation of Shutdown Cooling Location: Simulator Approximate Time: 15 minutes Start Time:__________________

End Time:___________________

Actual Time: _________________

Reference(s): K/A#

Procedures: OI-SC-1, Attachment 1, Rev 56 Other (tech specs, etc)

Handout(s): OI-SC-1, Attachment 1, Initiation of Shutdown Cooling.

Task List#: 0320 Applicable Position(s):RO, SRO-I Time Critical: No Alternate Path: No JPM Prepared by: Date:

Page 1 of 9

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-4 Rev. 3 JPM

Title:

Initiation of Shutdown Cooling Operators Name:

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:

Safety Considerations:

Comments: IC 109, Ensure TR-346 is Off.

Page 2 of 9

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-4 Rev. 3 JPM

Title:

Initiation of Shutdown Cooling TASK The Applicant initiated shutdown cooling using LPSI STANDARD: pump, SI-1A in accordance with OI-SC-1, Attachment 1.

Established 1460-1540 gpm SDC flow rate as indicated by FIC-326.

INITIAL The plant is shutdown. Fuel is in the reactor vessel.

CONDITIONS: Current plant status meets requirements for initiating shutdown cooling. OI-SC-1 has been completed through Step 18 of Attachment 1 for shutdown cooling using LPSI pump, SI-1A. RCPs RC-3B and RC-3D are running.

INITIATING CUE: Continue in OI-SC-1, Attachment 1, at Step 19 to initiate shutdown cooling using LPSI pump, SI-1A.

Page 3 of 9

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-4 Rev. 3 JPM

Title:

Initiation of Shutdown Cooling Critical Steps shown in gray and **

STEP ELEMENT STANDARD

- 1 (OI-SC-1, IF initiating SDC with fuel in the CB-1,2,3 Att. 1, Step vessel, Placed HCV-341, Shutdown 19.a) THEN warm up the SDC piping Heat Exchanger Valve Flow by performing the following: Controller Override Switch key switch in MAN position.

a. Place HCV-341, Shtdn HT Exch Valve Flow Cntrlr Ovrd [ SAT ] [ UNSAT ]

SW, Key Switch in MAN.

- 2 (OI-SC-1, Throttle HCV-341 10% open. CB-1,2,3 Att. 1, Step Turned HCV-341 19.b) potentiometer clockwise until meter indicated approximately 10% open.

[ SAT ] [ UNSAT ]

- 3 (OI-SC-1, Place LPSI/Shtdn Clg Flow CB-1,2,3 Att. 1, Step Cntrlr FCV-326 Override Switch Placed FCV-326 19.c) in MAN. LPSI/Shutdown Cooling Flow Controller FCV-326 override switch in MAN.

[ SAT ] [ UNSAT ]

- 4 (OI-SC-1, Throttle FCV-326, SDC Flow CB-1,2,3 Att. 1, Step Control Valve, 20% open Throttled FCV-326 19.d) (Controller output at 80%). approximately 20% open.

NOTE: For FCV-326 to be 20% open, controller output must 80%)

[ SAT ] [ UNSAT ]

Page 4 of 9

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-4 Rev. 3 JPM

Title:

Initiation of Shutdown Cooling STEP ELEMENT STANDARD

- 5 (OI-SC-1, Open HCV-347 CB-1,2,3 Att. 1, Step (Shtdn Clg/Loop 2 Isolation Opened HCV-347. Held HCV-19.e) Valve Outbd) 347 Control Switch in the open position until fully open.

RED light ON, GREEN light OFF NOTE: Stroke time is approximately one minute.

[ SAT ] [ UNSAT ]

6 NOTE Read Note.

After placing HC-348 in the open position, SHUTDOWN [ SAT ] [ UNSAT ]

COOLING FLOW HI-LO (CB-1,2,3, A2, D-2U) will be enabled and will be in alarm until flow is established.

- 7 (OI-SC-1, Open HCV-348 CB-1,2,3 Att. 1, Step (Shtdn Clg/Loop 2 Isolation Opened HCV-348. Placed 19.f) Valve Inbd) HCV-348 Control Switch in open position.

Verified RED light ON and GREEN light OFF.

[ SAT ] [ UNSAT ]

8 SHUTDOWN COOLING FLOW CB-1,2,3 HI-LO (CB-1,2,3, A2, D-2U) Acknowledged Alarm Alarm

[ SAT ] [ UNSAT ]

9 (OI-SC-1, Vent the selected LPSI pump Directed AO to vent SI-1A Att. 1, Step by opening the following 19.g) valve(s) until full water flow is [ SAT ] [ UNSAT ]

observed and then close the valve(s): CUE: SI-1A has been vented.

SI-334, LPSI Pump Casing SI-334 is closed.

Vent Valve (SI-1A)

Page 5 of 9

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-4 Rev. 3 JPM

Title:

Initiation of Shutdown Cooling STEP ELEMENT STANDARD

- 10 (OI-SC- Start selected LPSI pump: CB-30A 1, Att. 1, Step Started SI-1A. Placed CS in 19.h) SI-1A After-Start position.

RED light ON, GREEN light OFF

[ SAT ] [ UNSAT ]

11 CB-30A Verified SI-1A ammeter current increased to starting current and returned to normal current.

[ SAT ] [ UNSAT ]

12 NOTE Read Note.

SDC System Heatup should take at least ten minutes [ SAT ] [ UNSAT ]

13 (OI-SC-1, Place TR-346 in service. CB-10,11 Att. 1, Step Placed TR-346 in service.

19.i) Pulled out recorder drawer and placed switch on left hand side of drawer in OFF. Pushed drawer back in.

[ SAT ] [ UNSAT ]

14 NOTE Read Note.

Reclosing the LPSI Loop Injection Valve may be required to maintain the desired heatup [ SAT ] [ UNSAT ]

rate.

Page 6 of 9

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-4 Rev. 3 JPM

Title:

Initiation of Shutdown Cooling STEP ELEMENT STANDARD 15 (OI-SC-1, Crack open a LPSI Loop AI-30A/B Att. 1, Step Injection Valve to a loop with a Cracked open HCV-329 or 19.j) running RCP to obtain a gradual HCV-333. Verified gradual heatup rate (approximately 20°F heatup rate obtained.

/min) as indicated on TR-346.

[ SAT ] [ UNSAT ]

16 NOTE Read Note.

More than two LPSI Loop Injection Valves may be opened for testing, maintenance or if two [ SAT ] [ UNSAT ]

SDC pumps are running.

Examiner Cue: Temperature has stabilized

- 17 (OI-SC- When TR-346 temperature AI-30A/B 1, Att. 1, Step stabilizes, THEN open any two Opened two of the following 19.k) LPSI loop injection valves LPSI loop injection valves:

HCV-327

HCV-329

HCV-331

HCV-333

[ SAT ] [ UNSAT ]

- 18 (OI-SC- Throttle FCV-326 to obtain Verified 1460-1540 gpm flow 1, Att. 1, Step 1500 gpm on FIC-326 through FIC-326 or throttled as

20) required to obtain 1460-1540 gpm as indicated on FIC-326.

[ SAT ] [ UNSAT ]

- 19 (OI-SC- Place FCV-326 in AUTOMATIC Placed FCV-326 in automatic.

1, Att. 1, Step and verify 1500 gpm flow is Verified 1460-1540 gpm as

21) maintained indicated on FIC-326.

[ SAT ] [ UNSAT ]

Page 7 of 9

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-4 Rev. 3 JPM

Title:

Initiation of Shutdown Cooling Termination Criteria: Shutdown cooling initiated using LPSI pump, SI-1A with FCV-326 in automatic and 1460-1540 gpm flow through FIC-326.

Page 8 of 9

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-4 Rev 3 INITIAL CONDITIONS: The plant is shutdown. Fuel is in the reactor vessel.

Current plant status meets requirements for initiating shutdown cooling. OI-SC-1 has been completed through Step 18 of Attachment 1 for shutdown cooling using LPSI pump, SI-1A. RCPs RC-3B and RC-3D are running.

INITIATING CUE: Continue in OI-SC-1, Attachment 1, at Step 19 to initiate shutdown cooling using LPSI pump, SI-1A.

Page 9 of 9

PAGE 1 OF 54 Fort Calhoun Station Unit No.1 OI-SC-1 OPERATING INSTRUCTION SHUTDOWN COOLING INITIATION Change No. EC 54544, 54733 Reason for Change Add guidance for HC-347 and HC-348 to be in override when Pressurizer manway is removed (EC 54544). Add venting instructions for vent valve SI-472 (EC 54733).

Requestor C. Kuchta, N. Bretey Preparer K. Bessey Issue Date 02-07-12 3:00pm R56

~-- --

FORT CALHOUN STATION OI-SC-1 OPERATING INSTRUCTION PAGE 2 OF 54 SHUTDOWN COOLING INITIATION SAFETY RELATED ATT PURPOSE PAGE - Initiation of Shutdown Cooling 6 - Initiation of Shutdown Cooling with Void in Combined Suction Piping 21 - Venting of Shutdown Cooling .41 PRECAUTIONS

1. Per Technical Specification 2.1.1 (3), at least one RCP or one Shutdown Cooling Loop shall be in operation whenever fuel is in the Reactor, and RCS boron concentration is being changed.

2. Shutdown Cooling flow (nominally 1500 gpm on FIC-326) should be provided through the Reactor Core before stopping the last RCP.

3. The minimum Shutdown Cooling System flow rate shall be maintained greater than 1000 gpm per the most recent Boron Dilution Analysis.

4. The minimum pressure limitation for RCP operation per TDB-1I1.7.aOR TDB-1I1.7.dwhen going into Shutdown Cooling shall be observed.

5. Whenever a LPSI Pump is in operation, then a minimum pump flow of 200 gpm must exist at all times. This flow may be provided by minimum recirculation flow.

6. If while operating in the SDC mode either HCV-347 and/or HCV-348 were to inadvertently close, prompt operator action must be taken to either reopen the valve(s) or secure the operating SDC Pump(s).

7. Whenever RCS level is below the top of the Hot Leg, monitor level using LI-197 and LlS-119 or LI-199 and SDC pump parameters (pressure, flow, amps) to detect a loss of SDC pump suction due to vortexing or air binding of the SDC pump. [AR 9369]

8. Do not exceed a Pressurizer level of 60% actual. This provides a sufficient steam volume in the Pressurizer for insurges.

9. Loss of Shutdown Cooling, AOP-19, shall be entered if Shutdown Cooling is lost.

10. When RCS Level is below 1025.2' (less than 23' above the top of the core), two Shutdown Cooling loops shall be OPERABLE, and one Shutdown Cooling Loop shall be IN OPERATION. (Technical Specification 2.8.1 (4))

R56

FORT CALHOUN STATION OI-SC-1 OPERATING INSTRUCTION PAGE 3 OF 54 PRECAUTIONS (continued)

11. When the RCS level is above 1025.2' (greater than 23' above the top of the core), one Shutdown Cooling Loop shall be IN OPERATION except as noted in Technical Specification 2.8.1 (3).

12. With fuel in the Reactor and the RCS in a reduced inventory condition, (less than 1010' elevation) at least one off-site power source, both Diesel Generators and both vital electrical distribution trains must be available. [AR 9368]

13. Containment Spray Pumps are not available for Shutdown Cooling unless RCS Temperature is less than 120°F and the RCS is vented by an area greater than or equal to 47 in2.

14. Maintain RCS temperature greater than 64°F per TR-346 inlet temperature (black pen), Head Bolt-Up Temperature, until the Reactor Vessel Head is de-tensioned.

15. To ensure the assumptions made in Shutdown Margin Calculations remain valid, maintain Shutdown Cooling Inlet Temperature above 54°F (TR-346) when fuel is in the core.

16. When RCS Level is below 1010' (Reduced Inventory Condition), no more than two LPSI Loop Injection Valves shall be open. This is to minimize SDC pump runout and reduce the likelihood of vortexing in the event FCV-326 fails open.

17. To prevent possible RCS overpressurization when the Reactor Vessel Head is installed and Shutdown Cooling is required to be operable, one of the following conditions shall be maintained:

A Steam Generator shall be available to remove decay heat with:

1) No nozzle dams installed. [AR 9361]

2) A Secondary side minimum water level of 63% narrow range. [AR 9361]

3) U-tubes have not been drained or have been swept after filling.

The Pressurizer Manway is removed. [AR 9361]

PORVs operable per TS 2.1.6(4), and S/G Nozzle Dams not installed, and RCS not in reduced inventory condition (below 1010' elevation)

18. The Isolation Valves HCV-347, SHTDN CLG/Loop 2 Isolation Valve Outbd and HCV-348, SHTDN CLG/Loop 2 Isolation Valve Inbd shall be available when Shutdown Cooling is in operation. [AR 9361]

R56

FORT CALHOUN STATION OI-SC-1 OPERATING INSTRUCTION PAGE 4 OF 54 PRECAUTIONS (continued)

19. When SDC is required to be operable, the following shall be maintained: [AR 9362]

The required number of Shutdown Cooling Loops with backup power sources

One Containment Spray Pump with a backup power source, a flow path and a suction source in order to satisfy the minimum delivery requirements of 575 gpm of borated water to the Reactor Vessel, if needed, to maintain the core cool NOTE For RCS temperatures, Te less than 270°F, one HPSI Pump may be made operable provided the flowrate is throttled to the equivalent of three Charging Pumps (120 gpm) and all three Charging Pumps are disabled.

One HPSI Pump or two Charging Pumps with backup power sources, a flow path and a suction source. (This satisfies the minimum delivery requirements of 55 gpm borated water to the Reactor Vessel, if required, to maintain the core covered)

20. When fuel is in the Reactor, the RCS Level must remain above the Center Line of the Leg (1006.5') to ensure a suction for Shutdown Cooling. [AR 9362]

21. To prevent possible degradation to the motor windings, the following criteria should be observed for SI-1A and SI-1 B:

Allow the motor to come to a complete stop before starting.

If the LPSI pump has been shutdown for at least one hour, two successive starts are allowed.

If the LPSI pump has been at rated speed and has been shutdown less than one hour, only one start is allowed.

These criteria should be disregarded if multiple LPSI pump starts are needed to either maintain plant Technical Specifications, respond to a plant emergency, or as directed by the Shift Manager.

22. For the purposes of fulfilling Shutdown Cooling requirements per Technical Specifications 2.1.1 or 2.8, Component Cooling Water or Raw Water Backup to the Low Pressure Safety Injection Pumps or Containment Spray Pumps is required. This does not apply to Safety Injection requirements in accordance with Technical Specification 2.3 and 2.4.

23. Reactivity should be monitored during and after any evolutions that change SDC or SDC Purification flows or temperatures when fuel is in the Reactor Vessel.

R56

FORT CALHOUN STATION OI-SC-1 OPERATING INSTRUCTION PAGE 5 OF 54 REFERENCES/COMMITMENT DOCUMENTS

1. Technical Specifications:

2.1.1 : Reactor Coolant System Operable Components

2.1.2: Reactor Coolant System Heatup and Cooldown Rate

2.4: Containment Cooling

2.8: Refueling

2.8.1 (3): Shutdown Cooling System - High Water Level

2.8.1 (4): Shutdown Cooling System - Low Water Level

3.2 Table 3-5, Item 23, P-T Limit Curve

2. Drawings File Description E-23866-21 0-130 44353 Safety Injection and Containment Spray D-4768 45997 Simplified Flow Path Diagram

3. USAR:

Section 4.0: Reactor Coolant System

Section 7.4: Regulating Systems

Section 9.3: Shutdown Cooling

Section 14.3: Safety Analysis: Boron Dilution Incident

4. Technical Data Book:

Figure TDB-1I1.7.a, RCS Pressure and Temperature Limits

Figure TDB-1I1.7.d, RCS Pressure and Temperature Limits

5. Ongoing Commitments:

AR 9369, LlC-88-1106

AR 9362, LlC-88-11 06

AR 9361, LlC-88-11 06

AR 9368, LlC-88-11 06 APPENDICES OI-SC-1-CL-A 45 OI-SC-1-CL-B 46 OI-SC-1-CL-C 53 R56

FORT CALHOUN STATION OI-SC-1 OPERATING PROCEDURE C PAGE 6 OF 54 Continuous Use Attachment 1 - Initiation of Shutdown Cooling PREREQUISITES f.{l INITIALS

1. Procedure Revision Verification Revision No. S; b Date: a;/7/;Z I ~

2. RCS Temperature is less than 515°F. j?!r:

3. Pressurizer Pressure is less than 1700 psia and PPLS is blocked. >~/

4. IF Shutdown Cooling has been secured and maintenance has been performed on the Shutdown Cooling System, THEN perform OI-SC-1-CL-B.

5. Shutdown Cooling Checklist OI-SC-1-CL-A has been performed and independently verified. \Y!(

TV Ind Verif

6. IF venting of Shutdown Cooling is desired, THEN perform OI-SC-1 Attachment 3.

R56

FORT CALHOUN STATION OI-SC-1 OPERATING PROCEDURE C PAGE 7 OF 54 Continuous Use Attachment 1 - Initiation of Shutdown Cooling PREREQUISITES (continued) f.{l INITIALS

7. Component Cooling System is in operation and available to provide cooling to the Shutdown Cooling Heat Exchangers and the Low Pressure Safety Injection (LPSI) Pump Seals. 5t

8. Perform applicable step based on Pressurizer Manway position.

a. IF the Pressurizer Manway is installed, THEN the Shutdown Cooling Containment Isolation Valves, HCV-347/348, PZR Press PC-118A Auto Sig Override Sw HC-347/348 is in the NORMAL position with key inserted and ready for operation. V

b. IF the Pressurizer Manway is removed, THEN the Shutdown Cooling Containment Isolation Valves, HCV-34 7/348, PZR Press PC-118A Auto Sig Override Sw HC-34 7/348 is in the OVERRIDE position with key inserted and ready for operation.

-p1;-

\

9. IF the Refueling Cavity is less than refueling level, THEN ensure the following components/flowpaths are available for adequate RCS makeup:

v

One Containment Spray Pump with a backup power source One HPSI Pump or two Charging Pumps with backup power sources (/

Flowpaths to the RCS and suction flow path from the SIRWT and/or BAST t/ >>k:

R56

FORT CALHOUN STATION OI-SC-1 OPERATING PROCEDURE C PAGE 8 OF 54 Continuous Use Attachment 1 - Initiation of Shutdown Cooling PREREQUISITES (continued) f.{l INITIALS

10. IF the Refueling Cavity is less than refueling level, THEN designate each make up flow path by performing the following:

a. Indicate the flowpath on FC-1291; Designated Make Up Flow Paths to the RCS and attach the form to the Control Room Shift Turnover Log.

Flow Path shall include:

Manual Valves

Hand Control Valves

Pumps

b. Highlight the flow path on the Control Room "Simplified Flow Path Diagram" (0-4768 File No. 45997).

c. Place designated placards on equipment manipulated from the Control Room (Hand Control Switches etc.), indicated on FC-1291.

CAUTION When the RCS is unvented (pressurized), operator action will be required to secure charging pumps in the event that purification flow is limited or lost.

This is to prevent loss of Shutdown Cooling due to rapid increase of RCS pressure. With three charging pumps operation, as little as 1.1 minute is available prior to the loss of Shutdown Cooling.

11. A Dedicated Operator has been assigned to monitor the RCS pressure and shutdown the charging pump(s) as required prior to RCS pressure reaching 300 psia until the RCS is vented.

Dedicated operator __ .fJ-D'--_O _

R56

FORT CALHOUN STATION OI-SC-1 OPERATING PROCEDURE C PAGE 9 OF 54 Continuous Use Attachment 1 - Initiation of Shutdown Cooling PROCEDURE f{l INITIALS NOTES

1. Definition of "Available": The status of a system, structure or component that is in service or can be placed in service within a reasonably short period of time (consistent with its intended function) and can be expected to perform the intended functional need.

2. Initially, both LPSI Pumps shall be aligned for SDC and three of the following power sources shall be available: 345KV, 161KV, DG-1, and DG-2.

3. When RCS Temperature is less than 120°F and vented by an area greater than or equal to 47 in2, then a Containment Spray Pump may be used for SOC.

4. Steps 1 through 6 may be performed in any order.

1. Place placards for both LPSI Pumps to indicate they are operable (aligned) for SDC per Technical Specification 2.1.1 or 2.8. 5/(

2. Place placards on any three of the following AC power sources to indicate they are available as backup power sources for SDC Pumps required per Technical Specification 2.1.1. [AR 9368]

345KV

161KV

DG-1 and 4160 KV Bus 1A3

DG-2 and 4160 KV Bus 1A4 R56

FORT CALHOUN STATION OI-SC-1 OPERATING PROCEDURE C PAGE 10 OF 54 Continuous Use Attachment 1 - Initiation of Shutdown Cooling PROCEDURE (continued) f.{} INITIALS NOTE IF CCW Low Flow Switches are inoperable, local Ultrasonic Flow Readings shall be taken and logged every four hours (refer to PMID-2560).

3. Verify SI-1A and SI-1 B CCW flow switches (FC-2817 and 2818), are operable by performing the following:

a. Momentarily close HCV-2808A1B, SI-1A Bearing Cooler CCW Valves, and verify LPSI SI-1A BEARING COOLER NO FLOW (CB-1,2,3, A1, A-3L) is in alarm.

b. Open HCV-2808A1B and verify LPSI 51-1A BEARING COOLER NO FLOW (CB-1,2,3, A1, A-3L) clears.

c. Momentarily close HCV-2809A1B, SI-1 B Bearing Cooler CCW Valves, and verify LP51 51-1B BEARING COOLER NO FLOW (CB-1,2,3, A1, B-4U) is in alarm.

d. Open HCV-2809A1B and verify LP51 51-1B BEARING COOLER NO FLOW (CB-1 ,2,3, A 1, B-4U) clears.

4. Reverse the logic for HCV-347 and HCV-348 Trouble Alarms by completing the following:

NOTE HCV-347 TROUBLE (CB-1, 2, 3, A6, E-7) should be in alarm.

a. Unlock and place MCC-4C2-E01, HCV-347 Shutdown Cooling Loop Isolation Valve Breaker in ON (Breaker Located in Corridor 4). ,12k

b. Pull Annunciator Card HCV-347 TROUBLE (CB-1,2,3, A6, E-7). \p/{

c. Place Annunciator N.O.lN.C. selector switch in the N.O. position. e;n EM

d. Reinstall Annunciator Card HCV-347 TROUBLE (CB-1,2,3, A6, E-7).

4 R56

FORT CALHOUN STATION OI-SC-1 OPERATING PROCEDURE C PAGE 11 OF 54 Continuous Use Attachment 1 - Initiation of Shutdown Cooling PROCEDURE (continued) f.{l INITIALS 4.

.-----------------------~~~----------------------~

NOTE HCV-348 TROUBLE CB-1 ,2,3, A6, E-6 should be in alarm.

e. Unlock and place MCC-3B1-F04, HCV-348 Loop SDC Isolation Valve Breaker in ON. (Room 57 East). y/(

f. Pull Annunciator Card HCV-348 TROUBLE (CB-1 ,2,3, A6, E-6). ylr

g. Place Annunciator N.O.lN.C. selector switch in the N.O. position. FI'1 EM

h. Reinstall Annunciator Card HCV-348 TROUBLE (CB-1 ,2,3, A6, E-6). P(

5. Ensure HCV-344, Containment Spray Valve, and HCV-345, Containment Spray Valve, are closed by performing the following:

a. Place the following controllers in CLOSED:

HIC-344, Cntmt Spray Vlv HCV-344 Controller (AI-30A)

HIC-345, Cntmt Spray Vlv HCV-345 Controller (AI-30B)

b. Place the following control switches in OVERRIDE:

HC-344, Cntmt Spray Vlv HCV-344 Control Switch (AI-30A)

HC-345, Cntmt Spray Vlv HCV-345 Control Switch (AI-30B)

c. Verify the following are in alarm:

SPRAY VALVE HCV-344 HEADER ISOLATED (AI-30A, A33-1, H-6)

SPRAY VALVE HCV-345 HEADER ISOLATED (AI-30B, A34-1, H-2)

d. Ensure the following valves are CLOSED:

HCV-344, Containment Spray Valve (AI-30A)

HCV-345, Containment Spray Valve (AI-30B)

R56

FORT CALHOUN STATION OI-SC-1 OPERATING PROCEDURE C PAGE 12 OF 54 Continuous Use Attachment 1 - Initiation of Shutdown Cooling PROCEDURE (continued) f.{l INITIALS NOTE The following step disables the function of Pressure Switches, PS-484 and PS-485. Disabling these pressure switches prevents Shutdown Cooling Heat Exchanger CCW Outlet Valves HCV-484 and HCV-485 from cycling to a closed position on a loss of Instrument Air pressure.

6. Place the following Control Switches in OVERRIDE: (East end of Corridor 4)

HC-484, CCW Valve Press Switch PS-484 Manual Override Switch (JB-137A)

HC-485, CCW Valve Press Switch PS-485 Manual Override Switch (JB-138A)

7. Ensure Pressurizer Pressure is less than 300 psia.

8. Ensure RCS Temperature is less than 350°F.

NOTES

1. TDB Figure TDB-III.7.d provides more detail to assist in aRCS cooldown.

2. Once the cooldown is started, OP-ST-RC-0008, RCS Heatup/Cooldown Rate, or the e uivalent ma be used to track the RCS cooldown rate.

CAUTIONS

1. If RCS pressure drops below the RCP minimum pressure limitation per TDB Figure TDB-III.7.d, the operating RCP shall be stopped.

2. If Pressurizer level drops to 32% actual (corrected for temperature) while initiating Shutdown Coolin ,HCV-347 and HCV-348 shall be closed.

9. Place HCV-347, SHTDN CLG/LOOP 2 ISOLATION VALVE OUTBD, Key Switch in ON.

R56

FORT CALHOUN STATION OI-SC-1 OPERATING PROCEDURE C PAGE 13 OF 54 Continuous Use Attachment 1 - Initiation of Shutdown Cooling PROCEDURE (continued) f.{l INITIALS

10. A Dedicated Operator has been briefed to close HCV-347 or HCV-348 if any of the following indications exceed 300 psia:

P-105

P-115 Dedicated Operator _-f[).......c..._----'O'""""'-- _

Name

11. Ensure RCS Pressure is below 300 psia as indicated:

P-105 V

P-115 (/ ~

12. Place "PZR Press PC-118A Auto Sig Override Sw HC-347/348" to the OVERRIDE position. -.pIC

13. Open HCV-347 to allow piping between HCV-347 and HCV-348 to fill with borated water.

yJ(

14. Close HCV-347. j3~/

15. Align selected LPSI Pump(s) for Shutdown Cooling as follows:

a. Ensure the selected LPSI Pump is secured:

SI-1A V

SI-18 P!

b. Close both SI Pump Minimum Recirculation Return to SIRWT Valves:

HCV-385 V

HCV-386

--V

£K

c. Close both LPSI Pump Minimum Recirculation Stop Valves:

SI-1A SI-18 SI-132 SI-124 v;, --M R56

FORT CALHOUN STATION OI-SC-1 OPERATING PROCEDURE C PAGE 14 OF 54 Continuous Use Attachment 1 - Initiation of Shutdown Cooling PROCEDURE (continued) f!} INITIALS 15.

d. Close both lPSI Pump Suction Valves:

SI-1A HCV-2947 c-

SI-18 HCV-2937 i/' J?(

TV Ind Verif

e. Handjack closed both lPSI Pump Suction Valves from the SIRWT:

v HCV-2947 SI-1A SI-18 HCV-2937 / yk

]:1/

Ind Verif NOTE The following steps will depressurize the lPSI Header.

16. Remove SI-18, lPSI Header Jockey Pump from service by completing the following:

a. Place HC-301, lPSI Header Jockey Pump SI-18 Control Switch in OFF.

b. Close the following valves:

SI-434, lPSI Header Jockey Pump SI-18 Discharge Valve

SI-425, lPSI Header Jockey Pump SI-18 Suction Valve

17. Open SI-186, Safety Injection Pumps SI-1A, 18 Shutdown Cooling Warm Up Isolation Valve.

R56

FORT CALHOUN STATION OI-SC-1 OPERATING PROCEDURE C PAGE 15 OF 54 Continuous Use Attachment 1 - Initiation of Shutdown Cooling PROCEDURE (continued) L{l INITIALS CAUTION Maximum, flow rate is 650 gpm with no fuel in the Reactor Vessel, and the UGS installed with the ICI plate in the lowered position. With the ICI plate in the raised position, there is no flow restriction.

18. IF initiating SDC without fuel in the vessel, THEN perform the following:

a. Place HCV-341, Shtdn HT Exch Valve Flow Cntrlr Ovrd SW, Key Switch in MAN.

b. Close HCV-341.

c. Place LPSIIShtdn Clg Flow Cntrlr FCV-326 Override Switch in MAN.

d. Throttle FCV-326, SDC Flow Control Valve, 20% open (Controller output at 80%).

e. Open HCV-347.

NOTE After placing HC-348 in the open position, SHUTDOWN COOLING FLOW HI-LO (CB-1 ,2,3, A2, D-2U) will be enabled and will be in alarm until flow is established.

f. Open HCV-348.

g. Vent the selected LPSI pump by opening the following valve(s) until full water flow is observed and then close the valve(s):

SI-334, LPSI Pump Casing Vent Valve (SI-1A)

SI-372, LPSI Pump Casing Vent Valve (SI-1 B)

SI-335, LPSI Pump Casing Vent Valve (SI-1 B)

h. Start selected LPSI pump:

SI-1A

SI-1 B R56

FORT CALHOUN STATION OI-SC-1 OPERATING PROCEDURE C PAGE 16 OF 54 Continuous Use Attachment 1 - Initiation of Shutdown Cooling PROCEDURE (continued) f{l INITIALS 18.

i. Throttle open one or two LPSI Loop Injection Valves to obtain the desired flow rate.

j. Throttle FCV-326 to obtain the desired flow rate on FIC-326.

k. Place FCV-326 in AUTOMATIC and verify flow is maintained.

I. Fully open one or two LPSI Loop Injection Valves.

m. Place TR-346 in service.

n. GO TO Step 22.

\.v NOTE Heatup of the Shutdown Cooling System is necessary to reduce thermal shock to the system when hot Reactor Coolant flow is established.

19. IF initiating SDC with fuel in the vessel, THEN warm up the SDC piping by performing the following:

a. Place HCV-341, Shtdn HT Exch Valve Flow Cntrlr Ovrd SW, Key Switch in MAN.

b. Throttle HCV-341 10% open.

c. Place LPSI/Shtdn Clg Flow Cntrlr FCV-326 Override Switch in MAN.

d. Throttle FCV-326, SDC Flow Control Valve, 20% open (Controller output at 80%).

e. Open HCV-347.

R56

FORT CALHOUN STATION OI-SC-1 OPERATING PROCEDURE C PAGE 17 OF 54 Continuous Use Attachment 1 - Initiation of Shutdown Cooling PROCEDURE (continued) ~ INITIALS NOTE After placing HC-348 in the open position, SHUTDOWN COOLING FLOW HI-LO (CB-1 ,2,3, A2, D-2U) will be enabled and will be in alarm until flow is established.

19.

f. Open HCV-348.

g. Vent the selected LPSI pump by opening the following valve(s) until full water flow is observed and then close the valve(s):

SI-334, LPSI Pump Casing Vent Valve (SI-1A)

SI-372, LPSI Pump Casing Vent Valve (SI-1 B)

SI-335, LPSI Pump Casing Vent Valve (SI-1 B)

h. Start selected LPSI pump:

SI-1A

SI-1 B NOTE SDC S stem Heatu should take at least ten minutes.

i. Place TR-346 in service.

NOTE Reclosing the LPSI Loop Injection Valve may be required to maintain the desired heatup rate.

j. Crack open a LPSI Loop Injection Valve to a loop with a running RCP to obtain a gradual heatup rate (approximately 20°F Imin) as indicated on TR-346.

R56

FORT CALHOUN STATION OI-SC-1 OPERATING PROCEDURE C PAGE 18 OF 54 Continuous Use Attachment 1 - Initiation of Shutdown Cooling PROCEDURE (continued) f.{l INITIALS NOTE More than two LPSI Loop Injection Valves may be opened for testing, maintenance or if two SDC pumps are runnin .

19.

k. WHEN TR-346 temperature stabilizes, THEN open any two LPSI Loop Injection Valves.

20. Throttle FCV-326 to obtain 1500 gpm on FIC-326.

21. Place FCV-326 in AUTOMATIC and verify 1500 gpm flow is maintained.

NOTE When T c is 178°F or greater, then maximum RCS cooldown rate is 100°F/hr.

When Te is less than 178°F, the maximum RCS cooldown rate is 50°F/hr.

22. Establish desired RCS cooldown rate by adjusting the following valves:

HCV-484

HCV-485

HCV-341 NOTE Monitor for expected temperature rise on T339 and/or T340 when flow is initially diverted through SDC Hx when adjusting HCV-341, HCV-484, and HCV-485.

23. The applicable ERF point is being monitored for the in service Shutdown Cooling Heat Exchanger(s).

T339, SDC Htxr A Outlet Temperature

T340, SDC Htxr B Outlet Temperature R56

FORT CALHOUN STATION OI-SC-1 OPERATING PROCEDURE C PAGE 19 OF 54 Continuous Use Attachment 1 - Initiation of Shutdown Cooling PROCEDURE (continued) f.{l INITIALS NOTES

1. The following step may be performed at any time when conditions are met.

2. PC-118A is located behind C8-1, second door under GM2, and is approximately eye level. When both red lights are out, the relays are reset.

24. IF ALL of the following criteria are met:

Pressurizer Manway is installed

PC-118A interlocks are reset

RCS pressure stable below the 300 psia close signal THEN return PZR Press PC-118A Auto Sig Override Sw HC-347/348 to the NORMAL position.

25. Release Dedicated Operator.

26. If desired, start additional CCW Pumps.

27. At the Shift Manager's discretion, place the second LPSI Pump in operation by performing the following steps:

a. Start the second LPSI Pump:

SI-1A

SI-18

b. Adjust FCV-326 Setpoint to 3000 gpm.

c. Establish desired RCS cooldown rate by adjusting the following valves as necessary:

HCV-484

HCV-485

HCV-341 R56

FORT CALHOUN STATION OI-SC-1 OPERATING PROCEDURE C PAGE 20 OF 54 Continuous Use Attachment 1 - Initiation of Shutdown Cooling PROCEDURE (continued) f{l INITIALS

28. WHEN the desired RCS temperature is reached, THEN adjust cooling to match decay heat and maintain the RCS at the desired temperature.

Completed by DaterTime ---..!-/ _

R56

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-5 Rev 3 JPM

Title:

Maintain S/G Water Levels during Startup Using AFW.

Location: Simulator Approximate Time: 25 minutes Start Time:__________________

End Time:___________________

Actual Time: _________________

Reference(s): K/A# 061000 A2.04 RO IMP:3.4 SRO IMP:3.8 Ability to (a) predict the impacts of the following malfunctions or operations on the AFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: pump failure or improper operation.

Procedures: AOP-28, section 1, Rev 15 Other (tech specs, etc)

Handout(s): AOP-28, AUXILLIARY FEEDWATER SYSTEM MALFUNCTIONS, section 1 Task List#: 0025 Applicable Position(s): RO/SRO Time Critical: NO Alternate Path: YES JPM Prepared by: Jerry Koske Date: 3/18/2012 Page 1 of 9

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-5 Rev 3 JPM

Title:

Maintain S/G Water Levels during Startup Using AFW.

Operators Name:

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:

Safety Considerations:

Comments: IC 108 This JPM is run in parallel with JPM S-6 VLV/AFW/SGN_YCV1045/0%,

FW-54 will not start Page 2 of 9

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-5 Rev 3 JPM

Title:

Maintain S/G Water Levels during Startup Using AFW.

TASK STANDARD: The Applicant responded to a loss of feedwater by using AOP-28, Section 1, by attempting to start FW-10 and Tripping RCPs. Applicant established FW flow by Starting the B Main Feedwater Pump and adjusting FW Bypass Valves to restore flow to at least one Steam Generator.

INITIAL CONDITIONS: The plant was being maintained in hot shutdown due to a chemistry hold. FW-54 was being used to feed the Steam Generators. When FW-54 tripped, FW-6 was started and used to feed the steam generators through the nozzles. FW-6 tripped 5 minutes ago.

INITIATING CUE: You are directed to restore flow to the Steam Generators per AOP-28, Section 1.

Page 3 of 9

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-5 Rev 3 JPM

Title:

Maintain S/G Water Levels during Startup Using AFW.

Critical Steps shown in gray and **

STEP ELEMENT STANDARD Examiner Note:

Provide Applicant with a copy of AOP-28, Section 1 1 NOTES Applicant read note.

Technical Specification 2.5, Steam and Feedwater System, [ SAT ] [ UNSAT ]

discusses operating lomits associated with the AFW Examiner Cue: If Applicant System. refers to TS, The CRS will address Tech Spec requirements.

- 2 (1) Start FW-10, Steam AFW Pump. AI-65/66 Applicant attempted to open the following valves by placing the YCV-1045 Control Switch in OPEN position and verify RED light ON:

YCV-1045

YCV-1045A

YCV-1045B

[ SAT ] [ UNSAT ]

3 (1.1) Start FW-54, Diesel AFW Pump Applicant determined FW-54 was not available.

[ SAT ] [ UNSAT ]

4 (2) IF feedwater is restored, THEN Applicant determined that GO TO Section 5.0, Exit feedwater was NOT restored Conditions. and did NOT exit procedure.

[ SAT ] [ UNSAT ]

Page 4 of 9

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-5 Rev 3 JPM

Title:

Maintain S/G Water Levels during Startup Using AFW.

STEP ELEMENT STANDARD 5 (3) IF the Reactor is critical, THEN Applicant determined that the initiate shutdown of the Reactor reactor was NOT critical.

by performing the following:

[ SAT ] [ UNSAT ]

6 (4) Stabilize RCS temperature by DCS adjusting steaming rate. Applicant MAY adjust steam dump and bypass valve position.

[ SAT ] [ UNSAT ]

- 7 (5) Trip all RCPs. CB-1,2,3 Applicant tripped all four RCPs by placing their Control Switches in the AFTER-TRIP position and verified no current on ammeter.

[ SAT ] [ UNSAT ]

8 (6) Ensure ALL of the Blowdown CB-10/11 Isolation Valves are closed: Applicant verified ALL of the listed valves were closed.

HCV-1388A Control Switches in the

HCV-1388B CLOSE position and verified

HCV-1387A Green Lights ON

HCV-1387B

[ SAT ] [ UNSAT ]

9 (7) Monitor the Floating Steps. EXAMINER CUE: Another Operator will monitor the floating steps 10 (8) IMPLEMENT the Emergency EXAMINER CUE: The Shift Plan Manager will implement the Emergency Plan Page 5 of 9

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-5 Rev 3 JPM

Title:

Maintain S/G Water Levels during Startup Using AFW.

STEP ELEMENT STANDARD 11 (9) IF a SGIS has actuated, THEN CB-4 override SGIS by placing ALL of Applicant determined that the following SGIS Override SGIS has not actuated.

Switches in "OVERRIDE

[ SAT ] [ UNSAT ]

12 (10.a) IF Main Feedwater is available, CB-10/11 THEN restore S/G levels to 35- Applicant ensured that the 85% NR (73-94% WR) by 43/FW switch was in the OFF performing the following: Position.

Place the "43/FW" Switch in [ SAT ] [ UNSAT ]

"OFF".

13 (10.b) Ensure at least one Condensate CB-10/11 Pump, FW-2A/B/C, is operating. Applicant ensured at least one Condensate Pump was running by checking:

Control Switch Position

Red Light ON

Ammeter Current

[ SAT ] [ UNSAT ]

Note to Examiner: The procedure does not direct starting the Lube Oil Pump prior to starting the Main Feed Pump. However, an interlock will prevent the start of the Feed pump unless the Lube Oil Pump is running.

Page 6 of 9

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-5 Rev 3 JPM

Title:

Maintain S/G Water Levels during Startup Using AFW.

STEP ELEMENT STANDARD

- 14 (10.c) Start the B Feed Pump, FW- CB-10/11 4B.

Applicant started Lube Oil Pump for B FW Pump by placing Control Switch in AFTER-START (Red flag) and verifying Red Light ON.

Applicant Started B FW Pump by placing Control Switch in AFTER-START(Red flag), Verifying Red Light ON and verifying ammeter Current

[ SAT ] [ UNSAT ]

15 (10.d) Open BOTH Feed Header CB-10/11 Isolation Valves: Verified Control Switches in

HCV-1386 the OPEN Position with Red

HCV-1385 Light ON.

[ SAT ] [ UNSAT ]

- 16 (10.e) Manually control feed flow via DCS BOTH Feed Reg Bypass Valves: Adjusted HCV-1105 and/or

HCV-1105 HCV-1106 to initiate flow to at

HCV-1106 least one Steam Generator.

[ SAT ] [ UNSAT ]

17 (10.f) IF Feedwater flow is established, Determined Feedwater flow THEN GO TO Section 5.0, Exit was established and exited Conditions. procedure.

[ SAT ] [ UNSAT ]

Page 7 of 9

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-5 Rev 3 JPM

Title:

Maintain S/G Water Levels during Startup Using AFW.

Termination Criteria: The Steam Generators are being fed by the B Main Feed Pump.

Page 8 of 9

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-5 Rev 3 INITIAL CONDITIONS: The plant was being maintained in hot shutdown due to a chemistry hold. FW-54 was being used to feed the Steam Generators. When FW-54 tripped, FW-6 was started and used to feed the steam generators through the nozzles. FW-6 tripped 5 minutes ago.

INITIATING CUE: You are directed to restore flow to the Steam Generators per AOP-28, Section 1.

Page 9 of 9

WP12 Fort Calhoun Station Unit No.1 OP-ST-VA-3001A SURVEILLANCE TEST

Title:

VENTILATING AIR SYSTEM QUARTERLY CATEGORY A VALVE EXERCISE TEST FC-68 Number: EC 48010 Reason for Change: Adjusted HCV-881 Close Reference Stroke time for post-maintenance activity.

Requestor: G. Miller Preparer: L. Hautzinger ISSUED: 01-21-10 3:00 pm R10

FORT CALHOUN STATION o P-ST-VA-300 1A SURVEILLANCE TEST CONTINUOUS USE PAGE 1 OF 30 VENTILATING AIR SYSTEM QUARTERLY CATEGORY A VALVE EXERCISE TEST SAFETY RELATED

1. PURPOSE 1.1 To satisfy, in part, the requirements of USAR 4.5.6.5 for:

PCV-742E HCV-882 PCV-742F HCV-820A HCV-746A HCV-820B HCV-746B HCV-883A HCV-881 HCV-883B 1.2 This test will be performed quarterly in accordance with the Fort Calhoun Station Inservice Inspection Program Plan.

2. REFERENCES/COMMITMENT DOCUMENTS 2.1 Technical Specifications:

2.6 Containment System

2.8 Refueling Operations

2.15 Instrument and Control Systems

3.2 Equipment and Sampling Tests

3.3 Reactor Coolant System and Other Components Subject to ASME XI Boiler and Pressure Vessel Code Inspection and Testing Surveillance.

2.2 USAR 4.5.6.5: In-service Inspection of ASME Code Class 1, Class 2, and Class 3 Components 2.3 Fort Calhoun Station Inservice Inspection (ISI) Program Plan 2.4 Fort Calhoun Station Off-Site Dose Calculation Manual (ODCM) 2.5 AOP-12, Loss of Containment Integrity 2.6 SO-G-23, Surveillance Test Program R10

FORT CALHOUN STATION o P-ST-VA-300 1A SURVEILLANCE TEST CONTINUOUS USE PAGE 2 OF 30 2.7 Drawings File Description

11405-M-1, Sh 1 10431 Containment Heating, Cooling and Ventilation Flow Diagram

11405-M-1, Sh 2 48962 Containment Heating, Cooling and Ventilation Flow Diagram

3. DEFINITIONS Proper Valve Operation in both directions: Smooth stem travel with no indication of

Excessive binding,

Unusual hesitation,

Unusual noise (e.g., squealing),

Visible stem damage (e.g., bent, deformed, metal filings caused by rubbing),

Excessive packing leakage,

4. EQUIPMENT LIST 4.1 Test Equipment Required/Used:

EQUIPMENT OPPD NO./ CAL DUE DATE INITIALS/DATE Stopwatch I 4:) / ibrJf 'j

5. PRECAUTIONS AND LIMITATIONS 5.1 If any Containment Isolation Valve is found to be inoperable during any step of this procedure, Loss of Containment Integrity, AOP-12 shall be followed.

5.2 All anomalies and deficiencies shall be reported immediately to the Shift Manager and noted in the Comment Sheet. An immediate check shall be made to verify Limiting Conditions for Operation, per Technical Specifications, have not been exceeded.

5.3 Valve stroke times shall be determined by timing the interval between actuation of the control switch and the end of valve motion as observed by full open/closed remote indicating lights.

5.4 If a valve fails to operate properly (as defined in Section 3), contact the System Engineer for evaluation and to determine appropriate corrective action. Note any abnormality on the Comment Sheet.

R10

FORT CALHOUN STATION OP-ST-VA-3001A SURVEILLANCE TEST CONTINUOUS USE PAGE 3 OF 30 5.5 Mechanical agitation (tapping), multiple stroking of valves, pre-test stroking of valves or any action taken to produce satisfactory test results due to SOV failure/sticking is prohibited. Any SOV failure/sticking shall result in the valve and its associated process valve, if applicable, being immediately declared inoperable, even if subsequent stroking produces acceptable SOV performance.

5.6 The System Engineer shall be notified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of the completion of this test of any marginal, unexpected, or unacceptable results.

6. PREREQUISITES INITIALS/DATE 6.1 Procedure Revision Verification:

Revision No._----<Ii_D::..-- __

6.2 An RWP has been issued, if required.

y:J/ ..L RWP No. _----If~'-....:..../_!7- _ ~ / UJt7ly J

6.3 No other test is in progress which could potentially affect this test, or if this test were performed, could have an effect on that test. J?f: / lo,Jry 6.4 Calibration of test equipment has been verified. IPt / ipjo/

6.5 A prejob briefing has been conducted prior to the start of this test. Yi( / fq~-y 6.6 If remote indication verification is required, then perform OP-ST-VX-3024A concurrently with this test. f/it, 6.7 Shift Manager authorizes the performance of this test.

Shift Manager __ _~M~..!..:.~~~~~

S=---..!:!'-6-"'~~* ....

=-- __ ,DatelTimel~Y / 1)v

7. PROCEDURE NOTE: Step 7.1 can be performed at anytime and repeated as necessary.

NOTE: Independent Verification need not be performed in sequence, but must be completed before starting next attachment(s).

7.1 IF this Surveillance Test is turned over, a prejob briefing must be conducted prior to the continuation of this test. /

R10

FORT CALHOUN STATION o P-ST-VA-300 1A SURVEILLANCE TEST CONTINUOUS USE PAGE 4 OF 30 7.2 Perform the following Attachments in any order at the discretion of the Shift Manager.

Attachments 1 - PCV-742E Valve Stroke Test 6 2 - PCV-742F Valve Stroke Test 10 I 3 - HCV-746A Valve Stroke Test 13 I 4 - HCV-746B Valve Stroke Test 15 /

5 - HCV-881 Valve Stroke Test 16 I 6 - HCV-882 Valve Stroke Test 19 I 7 - HCV-820A Valve Stroke Test 22 /

8 - HCV-820B Valve Stroke Test 23 /

9 - HCV-883A Valve Stroke Test 25 I 10 - HCV-883B Valve Stroke Test 27 "--If-_--'I'--- __

7.3 Completed by Date/Time __ ----!./__

8. RESTORATION 8.1 Shift Manager has been notified this test has been completed.

Shift Manager Date/Time I=----__

9. ACCEPTANCE CRITERIA 9.1 Each valve tested fully stroked in less than the Required Action Range indicated on their respective attachments.

10. TEST RECORD 10.1 This entire procedure.

R10

FORT CALHOUN STATION o P-ST-VA-300 1A SURVEILLANCE TEST CONTINUOUS USE PAGE 15 OF 30 Attachment 4 - HCV-746B Valve Stroke Test PROCEDURE INITIALS NOTE: If Containment Pressure Relief is in progress it may be desirable to delay performance of this test until Containment Pressure Relief is completed.

1. Station an operator at HCV-746B, Containment Pressure Relief Outboard Isolation Valve, in direct coordination with the Control Room to observe for proper valve operation per Section 3 (Rm 60).

2. Record "As Found" position for HCV-746B, Cntmt Press Relief (AI-44).

HCV-746B _

3. IF HCV-746B is Closed, THEN Open HCV-746B and locally observe for proper valve operation.

4. Close HCV-746B and locally observe for proper valve operation. Time valve remotely using control panel lights.

5. Record stroke time on Attachment 11 under Test Stroke Time.

6. Open HCV-746B and locally observe for proper valve operation.

7. IF the initial stroke time was in the Alert Range, THEN perform a verification (second) stroke time by completing the following:

7.1 Close HCV-746B and time valve remotely using control panel lights.

7.2 Record stroke time on Attachment 11 under Verification Stroke Time.

8. Place HCV-746B in the "As Found" position recorded in Step 2 or at the discretion of the Shift Manager. Record "As Left" position.

HCV-746B _

Completed by DatelTime '=--- _

R10

FORT CALHOUN STATION OP-ST-VA-3001A SURVEILLANCE TEST CONTINUOUS USE PAGE 28 OF 30 Attachment 11 - Test Data Evaluation Sheet Instructions Page 1 of 2 STA: Compare Test Stroke Times with the Required Action Range values. If the Test Stroke Time is in Required Action Range the valve shall be immediately declared inoperable. If any stroke time is in the Alert Range, the test results require additional analysis.

TEST VERIF REF ALERT RANGE REQUIRED STROKE STROKE STROKE ACTION VALVE TIME TIME

TIME RANGE (see) (see) (sec) LOW (sec) HIGH (sec)

PCV-742E 1.7 <0.9 or >2.5 >4.2 CLOSE PCV-742F 1.2 <0.6 or >1.8 >3.0 CLOSE HCV-746A 2.4 <1.2 or >3.6 >4.0 (1)

CLOSE HCV-746B 2.5 <1.3 or >3.7 >4.0 (1)

CLOSE HCV-820A 1.0 N/A N/A >2.0 CLOSE HCV-820B 1.0 N/A N/A >2.0 CLOSE HCV-820B 1.0 N/A N/A >2.0 OPEN

Only if required (1) Value is credited in FC 06959, Site Boundary and Control Room Doses following a LOCA Accident using Alternative Source Term.

R10

FORT CALHOUN STATION o P-ST-VA-300 1A SURVEILLANCE TEST CONTINUOUS USE PAGE 29 OF 30 Attachment 11 - Test Data Evaluation Sheet Instructions Page 2 of2 STA: Compare Test Stroke Times with the Required Action Range values. If the Test Stroke Time is in Required Action Range the valve shall be immediately declared inoperable. If any stroke time is in the Alert Range, the test results require additional analysis.

TEST VERIF REF ALERT RANGE REQUIRED STROKE STROKE STROKE ACTION VALVE TIME TIME* TIME RANGE (sec) (sec) (sec) LOW (see) HIGH (see)

HCV-881 13.5 < 10.1 > 16.8 > 33.7 sec.

OPEN HCV-881 14.8 < 11.1 > 18.5 > 37.0 sec.

CLOSE HCV-882 13.4 < 10.0 > 16.7 > 33.5 sec.

OPEN HCV-882 7.7 < 3.8 > 11.5 > 19.2 sec.

CLOSE HCV-883A 1.6 < 0.8 >2.4 > 4.0 sec.

CLOSE HCV-883A 5.0 < 2.5 > 7.5 > 12.5 sec.

OPEN HCV-8838 1.0 N/A N/A > 2.0 sec.

CLOSE

Only if required STA, Date/Time __ ...!...' _

ISI Coordinator Date/Time __ ...!...I _

R10

FORT CALHOUN STATION o P-ST-VA-300 1A SURVEILLANCE TEST CONTINUOUS USE PAGE 30 OF 30 Comment Sheet R10

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-6 Rev 3 JPM

Title:

Valve stroke time testing of HCV-746B Location: Simulator Approximate Time: 10 minutes Start Time:__________________

End Time:___________________

Actual Time: _________________

Reference(s): K/A# 029000 2.2.12, Knowledge of surveillance procedures (RO IMP 3.7 / SRO IMP 4.1)

Procedures: OP-ST-VA-3001A Attachments 4 and 11 Other (tech specs, etc)

Handout(s): OP-ST-VA-3001A, VENTILATING AIR SYSTEM QUARTERLY CATEGORY A VALVE EXERCISE TEST, Attachments 4 and 11 Task List#: 0708 Applicable Position(s): RO / SRO Time Critical: NO Alternate Path: NO JPM Prepared by: Date:

Page 1 of 8

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-6 Rev 3 JPM

Title:

Valve stroke time testing of HCV-746B Operators Name:

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:

Safety Considerations:

Comments: This JPM is performed in parallel with JPM S-5 Page 2 of 8

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-6 Rev 3 JPM

Title:

Valve stroke time testing of HCV-746B TASK STANDARD: The Applicant completed stroke time testing of Containment Pressure Relief valve, HCV-746B. HCV-746B was opened to prepare for the test. The Applicant closed HCV-746B while timing the valve closure time.

The Applicant recorded the closure time and compared it to the acceptance criteria. The Applicant then reopened the valve to verify proper operation and reclosed the valve to restore it to its as found position.

INITIAL CONDITIONS: The reactor is currently in hot shutdown.

INITIATING CUE: You are directed to perform valve stroke time testing of HCV-746B per OP-ST-VA-3001A, Attachment 4 for PMT.

An operator has been stationed locally at the valve.

A pre-job briefing has been conducted.

All prerequisites have been met Page 3 of 8

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-6 Rev 3 JPM

Title:

Valve stroke time testing of HCV-746B Critical Steps shown in gray STEP ELEMENT STANDARD Provide Applicant with a copy of OP-ST-VA-3001A, Attachments 4 and 11 1 NOTE: If Containment Read note. Determined Pressure Relief is in progress it Containment Pressure Relief may be desirable to delay is NOT in progress.

performance of this test until Containment Pressure Relief is [ SAT ] [ UNSAT ]

completed.

2 (1) Station an operator at HCV- Examiner Cue: An Operator 746B, Containment Pressure is stationed at HCV-746B.

Relief Outboard Isolation Valve, in direct coordination with the Control Room to observe for proper valve operation per Section 3 (Rm 60).

3 (2) Record "As Found" position for AI-44 HCV-746B, Cntmt Press Relief Green light indicates the valve (AI-44). HCV-746B________ is closed. Recorded as found position as closed.

[ SAT ] [ UNSAT ]

Page 4 of 8

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-6 Rev 3 JPM

Title:

Valve stroke time testing of HCV-746B STEP ELEMENT STANDARD

- 4 (3) IF HCV-746B is Closed, THEN AI-44 Open HCV-746B and locally Turned control switch to OPEN observe for proper valve and verified RED light ON operation.

[ SAT ] [ UNSAT ]

CUE: Local Operator reports valve opened with no indication of:

Excessive binding

Unusual hesitation

Unusual noise

Visible stem damage

Excessive packing leakage

- 5 (4) Close HCV-746B and locally AI-44 observe for proper valve Turned control switch to operation. Time valve remotely CLOSE and verified GREEN using control panel lights. light ON Used stopwatch to time valve using control panel lights.

[ SAT ] [ UNSAT ]

CUE: Local Operator reports valve closed with no indication of:

Excessive binding

Unusual hesitation

Unusual noise

Visible stem damage

Excessive packing leakage Page 5 of 8

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-6 Rev 3 JPM

Title:

Valve stroke time testing of HCV-746B STEP ELEMENT STANDARD

- 6 (5) Record stroke time on Recorded stroke time on Att.

Attachment 11 under Test 11 Stroke Time.

[ SAT ] [ UNSAT ]

- 7 (6) Open HCV-746B and locally AI-44 observe for proper valve Turned control switch to OPEN operation. and verified RED light ON

[ SAT ] [ UNSAT ]

CUE: Local Operator reports valve opened with no indication of:

Excessive binding

Unusual hesitation

Unusual noise

Visible stem damage

Excessive packing leakage 8 (7) IF the initial stroke time was in Determined that the stroke the Alert Range, THEN perform tome was NOT in the Alert a verification (second) stroke Range time by completing the following:

7.1 Close HCV-746B and time [ SAT ] [ UNSAT ]

valve remotely using control panel lights.

7.2 Record stroke time on Attachment 11 under Verification Stroke Time.

Page 6 of 8

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-6 Rev 3 JPM

Title:

Valve stroke time testing of HCV-746B STEP ELEMENT STANDARD

- 9 (8) Place HCV-746B in the "As CUE: If asked, Shift Found" position recorded in Manager directs HCV-746B Step 2 or at the discretion of be placed in its as found the Shift Manager. position AI-44 Turned control switch to CLOSE and verified GREEN light ON

[ SAT ] [ UNSAT ]

CUE: Local Operator reports valve closed with no indication of:

Excessive binding

Unusual hesitation

Unusual noise

Visible stem damage

Excessive packing leakage 10 Record As Left position. HCV- Recorded as left position as 746B _____ closed

[ SAT ] [ UNSAT ]

CUE: JPM Complete Termination Criteria: Valve stroke time testing for HCV-746B completed Page 7 of 8

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

INITIAL CONDITIONS: The reactor is currently in hot shutdown.

INITIATING CUE: You are directed to perform valve stroke time testing of HCV-746B per OP-ST-VA-3001A, Attachment 4 for PMT.

An operator has been stationed locally at the valve.

A pre-job briefing has been conducted.

All prerequisites have been met Page 8 of 8

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S7 Rev 3 JPM

Title:

Dilute RCS to Estimated Critical Conditions Boron Concentration Location:

Approximate Time: 20 minutes Start Time:__________________

End Time:___________________

Actual Time: _________________

Reference(s): K/A#

Procedures: TDB-V.1.B Estimated Critical Conditions Worksheet, Rev 23 OP-2A, Attachment 2, CEA Withdrawal to Criticality Mode 2.

Rev 107, OI-CH-4, Attachment 4, Normal Dilution of the RCS, Rev 45 Handout(s): TDB-V.1.B OP-2A, Attachment 2 OI-CH-4 Task List#: 0124 Applicable Position(s):

Time Critical: No Alternate Path: Yes Page 1 of 9

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S7 Rev 3 JPM

Title:

Dilute RCS to Estimated Critical Conditions Boron Concentration JPM Prepared by: Date:

Operators Name:

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:

Safety Considerations:

Page 2 of 9

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S7 Rev 3 JPM

Title:

Dilute RCS to Estimated Critical Conditions Boron Concentration Comments:

TASK Applicant began dilution to the ECC boron STANDARD: concentration. During dilution, an unexpected rise in reactivity occurred, and Applicant stopped the dilution in progress.

INITIAL The plant is shutdown in Mode 3. A plant startup is CONDITIONS: in progress per OP-2A, PLANT STARTUP, Attachment 2, CEA Withdrawal to Criticality Mode

2. Actions have been taken through Step 4 of OP-2A, Attachment 2, to withdraw Shutdown Groups A and B to the ARO position. TDB-V.1.B Estimated Critical Conditions Worksheet has been completed to determine final boron concentration.

INITIATING CUE: You are directed to dilute the RCS to the ECC Boron Concentration as calculated in TDB-V.1.B, Estimated Critical Conditions Worksheet per Step 5 of OP-2A, Attachment 2.

Page 3 of 9

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S7 Rev 3 JPM

Title:

Dilute RCS to Estimated Critical Conditions Boron Concentration Critical Steps shown in gray and **

STEP ELEMENT STANDARD 1 CUE: Provide copy of OP-2A, Attachment 2 and ECC Worksheet.

2 (OP-2A, Att. IF required, THEN dilute the Obtained copy of OI-CH-4.

2, Step 5) RCS per OI-CH-4 until ECC Boron Concentration is obtained. [ SAT ] [ UNSAT ]

CUE: Provide copy of OI-CH-4, Attachment 4 3 (OI-CH-4, Review prerequisites. All prerequisites are met.

Att. 4)

[ SAT ] [ UNSAT ]

4 (OI-CH-4, Record the following values: Obtained current boron Att. 4, Step 1)

Current RCS Boron concentration from ECC, RCS Concentration___ppm Tavg from control room

Desired RCS Boron instrumentation/plant computer Concentration____ppm and desired boron

RCS Tavg_____°F concentration from TDB-V-1.B Recorded values.

[ SAT ] [ UNSAT ]

5 NOTE Read Note.

Verifier must independently assess initial parameters as [ SAT ] [ UNSAT ]

part of calculation verification per OI-ERFCS-1 or TDB-V.12.

Page 4 of 9

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S7 Rev 3 JPM

Title:

Dilute RCS to Estimated Critical Conditions Boron Concentration STEP ELEMENT STANDARD 6 (OI-CH-4, Determine the number of Determined number of gallons Att. 4, Step 2) gallons of Makeup Water to be to be added.

added using ERF computer per OI-ERFCS-1 or the Dilution [ SAT ] [ UNSAT ]

Formula in TDB-V.12 CUE: STA has determined that 500 gallons of makeup water must be added.

CUE: Independent verifier has verified calculation and 500 gallons.

7 (OI-CH-4, Record the number of gallons Recorded 500 gallons to be Att. 4, Step 3) of makeup water to be added added.

to the RCS

[ SAT ] [ UNSAT ]

8 (OI-CH-4, Ensure HC-269, Makeup Water CB-4 Att. 4, Step 4) Mode Selector Switch, is in Ensured HC-269 was in the DILUTE. DILUTE position.

[ SAT ] [ UNSAT ]

9 (OI-CH-4, Ensure FCV-269, Makeup CB-4 Att. 4, Step 5) Water Control Valve, is in Ensured FCV-269 was in CLS CLOSE. position. GREEM light ON, RED light OFF

[ SAT ] [ UNSAT ]

10 NOTE Read Note.

Dilution of the RCS may be performed in intermittent [ SAT ] [ UNSAT ]

batches of makeup water to verify proper response.

Page 5 of 9

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S7 Rev 3 JPM

Title:

Dilute RCS to Estimated Critical Conditions Boron Concentration STEP ELEMENT STANDARD

- 11 (OI-CH- Set FQS-269X, Demin Water CB-4 4, Att. 4, Step Flow Batching Switch, to the Set FQS-269X to (500) gallons

6) desired number of gallons of water to be added [ SAT ] [ UNSAT ]

NOTE: Applicant may choose to batch intermittently to verify proper response. This is allowed by procedure so long as the total will be 500 gallons.

12 (OI-CH-4, Record initial Demin Water CB-4 Att. 4, Step 7) Makeup Flow Totalizer reading: Read and recorded value on FQI-269X __________ gal Makeup Flow Totalizer FQI-269X.

[ SAT ] [ UNSAT ]

13 NOTE Read Notes.

1. Makeup Water flow may be stopped at any time by closing [ SAT ] [ UNSAT ]

FCV-269.

2. Steps 8 through 14 may be signed off after these steps are complete.

- 14 (OI-CH- Open FCV-269 CB-4 4, Att. 4, Step Opened FCV-269. Placed

8) FCV-269 Control Switch in OPN position.

Verified RED light ON, GREEN light OFF

[ SAT ] [ UNSAT ]

Page 6 of 9

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S7 Rev 3 JPM

Title:

Dilute RCS to Estimated Critical Conditions Boron Concentration STEP ELEMENT STANDARD 15 CAUTION Read Caution.

All available indications shall be monitored for desired [ SAT ] [ UNSAT ]

effects during any reactivity change.

- 16 (OI-CH- Place FCV-269X, Demin Water CB-4 4, Att. 4, Step Makeup Flow Control Valve, in Placed FCV-269X in AUT

9) AUTO position.

[ SAT ] [ UNSAT ]

17 (OI-CH-4, With FC-269X, Demin Water CB-4 Att. 4, Step Makeup Flow Controller, set Set FC-269X to desired flow

10) Demin Water flow to the rate.

desired flow rate.

[ SAT ] [ UNSAT ]

CUE: Desired flow rate is 80 gallons per minute.

18 (OI-CH-4, Verify VCT level and pressure CB-1,2,3 Att. 4, Step respond as expected. Verified response is as

11) expected. (slow increase in level and pressure)

[ SAT ] [ UNSAT ]

Alternate Path Begins Examiner Note: Source range count rate will begin to increase Page 7 of 9

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S7 Rev 3 JPM

Title:

Dilute RCS to Estimated Critical Conditions Boron Concentration STEP ELEMENT STANDARD

- 19 (OI-CH- If unexpected reactivity effects Recognized indications of 4, Att. 4, Step are observed, then stop the undesired reactivity change

12) makeup flow and evaluate. and terminated dilution.

Unexpected reactivity effects occur after approximately 150 Closed FCV-269X by placing gallons added. FCV-269X Control Switch in CLS position.

Verified GREEN light ON, RED light OFF OR Closed FCV-269 by placing FCV-269 Control Switch in CLS position.

Verified GREEN light ON, RED light OFF

[ SAT ] [ UNSAT ]

CUE: Acknowledge report of unexpected reactivity effects CUE: JPM Complete Termination Criteria: Dilution was secured due to unexpected reactivity effects at approximately 150 gallons added.

Page 8 of 9

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-7 Rev 3 INITIAL CONDITIONS: The plant is shutdown in Mode 3. A plant startup is in progress per OP-2A, PLANT STARTUP, Attachment 2, CEA Withdrawal to Criticality Mode

2. Actions have been taken through Step 4 of OP-2A, Attachment 2, to withdraw Shutdown Groups A and B to the ARO position. TDB-V.1.B Estimated Critical Conditions Worksheet has been completed to determine final boron concentration.

INITIATING CUE: You are directed to dilute the RCS to the ECC Boron Concentration as calculated in TDB-V.1.B, Estimated Critical Conditions Worksheet per Step 5 of OP-2A, Attachment 2.

Page 9 of 9

FORT CALHOUN STATION OP-2A OPERATING PROCEDURE C PAGE 27 OF 58 Continuous Use Attachment 2 - CEA Withdrawal to Criticality Mode 2 PREREQUISITES J.{l INIT/DATE

1. Procedure Revision Verification Revision No._ .....*

L.....,v<-...,<.? _ 5tIJ~?f

2. OP-1 requirements for criticality are completed. :if I ppJ,y

3. A prejob brief, per SO-G-92, has been conducted prior to the start of this evolution. Department Manager or above attendance is required at the prejob brief. [SOER 10-2] fYr IjvJy SO-G-92 Briefing Manager NOTES

1. Do not connect an inoperable Wide Range Logarithmic Channel to a scaler-timer.

2. The scaler-timers should be disconnected from the Wide Range Logarithmic Channel when the scaler-timers are not in use.

3. One operable Wide Range Logarithmic Channel (not connected to a scaler-timer) shall be used to verify the proper response of the channels connected to the scaler-timers unless otherwise directed by the Reactor Engineer.

4. Scaler-timers are connected to operable Wide Range Logarithmic Channels A and C, OR as directed~ the React9:-~ngineer.

Channels (circle as applicable) \.Y B \S/ D

5. STA is available to perform 11M plots during the approach to criticality.

R107

FORT CALHOUN STATION OP-2A OPERATING PROCEDURE C PAGE 28 OF 58 Continuous Use Attachment 2 - CEA Withdrawal to Criticality Mode 2 PREREQUISITES (continued) l{l INITIDATE

6. Margin to Trip meters on CB-4 indicate less than or equal to 20% power. _-PI" 1 ro~,/

7. HC-909, Steam Dump Auto/lnhibit Switch, is in INHIBIT. Yf 17~fl

8. RCS temperature is being maintained between 529-535°F. S//,1o)(/

9. H2 concentration in the VCT gas space is greater than 80%. ff 1 to)l Chemist

10. Condensate Pump Discharge Suspended Solids is less than or equal to 0.100 ppm. ~(y Chemist

11. Maximum Spray Operation shall be performed per OI-RC-7. J§= 1 PJry

12. Pressurizer level is being automatically maintained between 44-52%

(normal 48%). :£l( 1 ptJy

13. Pressurizer pressure control is in AUTO AND maintaining between 2075-2150 psia (normal 2100 psia). .Jk 1 pJ<y

14. Control Element Assembly drive control system is operable. Ylr, to"'!

15. The Reactor is shutdown with all CEAs fully inserted. 3r IpJ,y

16. Estimated Critical Conditions (ECC) Worksheet has been completed. :fir 1 pJy

17. All operable Wide Range Nls indicate greater than one CPS. If less than one CPS, consult the Reactor Engineer. Sir 1 p)cy

18. Audible Count Rate Meter is in service. \f~ IJuly

19. A Specifically Designated RO or SRO Licensed Operator has been assigned to take the Reactor critical.

Designated operator_--+Dr-_Q~ _ ~/ 110Jy c:;...

20. Ensure Containment is evacuated of personnel. vr P)fY

-52/(11

21. Flushing through FW-16A and FW-16B Feedwater Heaters is secured. To)tY R107

FORT CALHOUN STATION OP-2A OPERATING PROCEDURE C PAGE 29 OF 58 Continuous Use Attachment 2 - CEA Withdrawal to Criticality Mode 2 PREREQUISITES (continued) l{l INIT/DATE

22. The following valves are open:

c--:

FW-137, HP Heater FW-16A Outlet Valve

FW-138, HP Heater FW-16B Outlet Valve v Ift(/P~y PROCEDURE

1. Review the Estimated Critical Condition Worksheet for Critical CEA position AND their +/- 1% f::..p values calculated in TDB-V.1 b.

CAUTION Only one method of positive reactivity addition shall be used at anyone time.

2. IF required, THEN borate the RCS per OI-CH-4 until ECC Boron Concentration is obtained.

3. Place each Zero Power Mode Bypass Switch on the RPS cabinets to OFF and verify the following:

Lo Flow light goes out for each channel v

TM/LP Bypass light goes out for each channel r:

The Zero Power Mode Bypassed annunciator clears (CB-4, A20) ~ .it /D)IY

4. Withdraw Shutdown Groups A and B to ARO using the Manual Group (MG) mode per OI-RR-1.

R107

FORT CALHOUN STATION OP-2A OPERATING PROCEDURE C PAGE 30 OF 58 Continuous Use Attachment 2 - CEA Withdrawal to Criticality Mode 2 PROCEDURE (continued) J.{1 INIT/DATE NOTE Sufficient time should be given prior to obtaining a RCS sample to allow proper mixing.

5. IF required, THEN dilute the RCS per OI-CH-4 until ECC Boron Concentration is obtained. /

6. IF not withdrawn, THEN withdraw all Non-Trippable CEAs to ARO using the Manual Group (MG) mode per OI-RR-1. /

7. Commence Reactor Engineer criticality Log (Figure 2). /

RE

8. Verify all individual Shutdown and Non-Trippable CEAs positions indicate fully withdrawn by Individual CEA Position indicators. /

9. RCS Hydrogen concentration is greater than or equal to 15 cc/kg. /

Chemist

10. Withdraw regulating CEA Groups 1, 2, 3, and 4 to four inches using Manual Individual Control. /

11. Commence 1/M Plots per OP-2A Attachment 2A and establish a 100 second Base Count Rate per OP-2A Attachment 2A. /

STA R107

FORT CALHOUN STATION OP-2A OPERATING PROCEDURE C PAGE 31 OF 58 Continuous Use Attachment 2 - CEA Withdrawal to Criticality Mode 2 PROCEDURE (continued) J.{l INIT/DATE NOTE CEA withdrawal may be halted at additional hold points for 1/M plotting at the discretion of the Reactor Engineer.

CAUTION The Reactor shall be considered critical when there is sustained rising flux level (positive Startup Rate) with no CEA movement OR Reactor Power indicates greater than 10-4%.

12. Using the Manual Sequential (MS) mode, take the Reactor critical by withdrawing the Regulating CEA Groups per OI-RR-1 as follows:

a. Withdraw Group 1 to 90 inches. /

b. Wait five minutes while monitoring count rate. /

c. Verify the 1/M plot predicts that the reactor will go critical above the Power Dependent Insertion Limit (POlL). /

d. IF the 1/M plot predicts that the reactor will go critical below POlL OR outside the ECP +/- 1% b..p, THEN consult the Reactor Engineer or their designated alternate for guidance. I

e. Withdraw Group 2 to 90 inches, AND verify Group 1 All Rods Out (ARO). I

f. Wait five minutes while monitoring count rate. I

g. Verify the 11M plot predicts that the reactor will go critical above the Power Dependent Insertion Limit (POlL). I

h. IF the 11M plot predicts that the reactor will go critical below POlL OR outside the ECP +/- 1% b..p, THEN consult the Reactor Engineer or their designated alternate for guidance. I

i. Withdraw Group 3 to 90 inches, AND verify Group 2 All Rods Out (ARO). I R107

FORT CALHOUN STATION OP-2A OPERATING PROCEDURE C PAGE 32 OF 58 Continuous Use Attachment 2 - CEA Withdrawal to Criticality Mode 2 PROCEDURE (continued) ~ INITIDATE 12

j. Verify Group 4 is at approximately 18 inches withdrawn. I

k. Wait five minutes while monitoring count rate. /

I. Verify the 11M plot predicts that the reactor will go critical above the Power Dependent Insertion Limit (POlL). /

m. IF the 11M plot predicts that the reactor will go critical below POlL OR outside the ECP +/- 1% IIp, THEN consult the Reactor Engineer or their designated alternate for guidance. /

n. IF the 11M plot predicts that the reactor will go critical beyond Group 4 ARO, THEN complete the following:

1) Withdraw Group 4 to 60 inches. /

2) Verify Group 3 All Rods Out (ARO). /

3) Wait five minutes while monitoring count rate. /

4) Verify the 11M plot predicts that the reactor will go critical above the Power Dependent Insertion Limit (POlL). /

5) IF the 11M plot predicts that the reactor will go critical below POlL OR outside the ECP +/- 1% IIp, THEN consult the Reactor Engineer or their designated alternate for guidance. /

CAUTION Do not exceed 115 inches on Group 4.

o. Withdraw Group 4 as required to achieve criticality or a maximum height of 115 inches. /

13. IF criticality is not reached by Group 4 at 115 inches, THEN complete the following:

a. Wait five minutes while monitoring count rate. /

R107

FORT CALHOUN STATION OP-2A OPERATING PROCEDURE C PAGE 33 OF 58 Continuous Use Attachment 2 - CEA Withdrawal to Criticality Mode 2 PROCEDURE (continued) J.{1 INIT/DATE 13

b. Perform TDB-V.1.b Step F. /

STA

c. Insert Group 4 using the Manual Sequential (MS) mode per OI-RR-1 to the minimum position determined in TDB-V.1.b Step F.4 or lower. /

d. Dilute the RCS by the amount determined in TDB-V.1.b Step F.5 per OI-CH-4, Attachment 6. /

e. Allow for adequate mixing in the RCS AND obtain a RCS boron sample. /

f. Perform a 100 second Base Count Rate per OP-2A, Attachment 2A. /

g. Withdraw Group 4 using the Manual Sequential (MS) mode per OI-RR-1 as directed by Reactor Engineer. /

h. Wait five minutes while monitoring count rate. /

i. IF the 1/M prediction shows criticality prior to ARO, THEN withdraw Group 4 as required to achieve criticality. /

j. IF the 1/M prediction is beyond ARO, THEN consult with the Reactor Engineer for further actions. /

14. IF the reactor should go critical below the Power Dependent Insertion Limit (POlL),

THEN perform the following:

a. Ensure the reactor is subcritical. /

b. Consult the Reactor Engineer OR their designated alternate for guidance. /

15. At 10-3% Reactor power perform the following:

a. Insert Group 4 using the Manual Sequential (MS) mode per OI-RR-1 to stabilize Reactor power. /

R107

FORT CALHOUN STATION OP-2A OPERATING PROCEDURE C PAGE 34 OF 58 Continuous Use Attachment 2 - CEA Withdrawal to Criticality Mode 2 PROCEDURE (continued) J.{} INIT/DATE 15

b. Verify the High Power Rate of Change Trip is enabled by performing the following:

1) Verify HIGH POWER RATE OF CHANGE TRIP ENABLED (CB-4, A20, E-4) is in alarm

2) Verify the level 1 light is on for operable wide range power drawers. /

c. Record Actual Critical Data on TDB-V.1.B, Estimated Critical Conditions Worksheet, AND Control Room Log. /

d. Discontinue the RE Criticality Log AND attach to this procedure. /

16. Remove the scaler timers connected to the Wide Range Logarithmic Channels. /

I&C

/

Ind Verif

17. IF it is desired to raise power, THEN refer to OP-2A Attachment 4. /

Completed by DatelTime ~/ _

R107

WP12 Fort Calhoun Station Unit No.1 OI-CH-4 OPERATING INSTRUCTION

Title:

CHEMICAL AND VOLUME CONTROL SYSTEM MAKEUP OPERATIONS FC-68 Number: EC 45338 Reason for Change: Added a precaution concerning the risk of operating FC-269Y at a flow rate of greater than or equal to 25 gpm.

Requestor: S. Breault Preparer: L. Hautzinger Editorial Correction (a) EC 45710: Pages 2,3, and 36 (05-14-09)

ISSUED: 02-12-09 3:00 pm R45

FORT CALHOUN STATION OI-CH-4 OPERATING INSTRUCTION PAGE 1 OF 41 CHEMICAL AND VOLUME CONTROL SYSTEM MAKEUP OPERATIONS An PURPOSE PAGE 1 - Neutral Batching to the VCT 4 2 - Blended Makeup to the VCT .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 3 - Normal Boration of the RCS 10 4 - Normal Dilution of the RCS .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 5 - Borating to the Charging Pump Suction Header . . . . . . . . . . . . . . . . . . . . . . . 17 6 - Diluting to the Charging Pump Suction Header 21 7 - Filling the SIRWT 25 8 - Boron Adjustment of the SIRWT 28 9 - Makeup to the RCS When Depressurized Using Boric Acid Pumps 31 10 - Makeup to the RCS Using HPSI Header 35 11 - Batching to the VCT for Power ControlNCT Inventory 38 12 - Normal Dilution of the RCS to Control Reactor Power 40 PRECAUTIONS

1. A minimum of one Reactor Coolant Pump or Low Pressure Safety Injection Pump supplying Shutdown Cooling must be in operation when changing Reactor Coolant System Boron Concentration.

2. Dilution to criticality shall not be initiated or continued when the CEAs are at or below the Power Dependent Insertion Limit.

3. When diluting to obtain the ECC Boron Concentration, Shutdown Groups A and B must be ARO.

4. During Refueling Operations, borated water supplies available for makeup to the Reactor Coolant System must have a Boron Concentration greater than or equal to Refueling Boron Concentration.

5. Do not allow VCT pressure to exceed 65 psig.

R45

FORT CALHOUN STATION OI-CH-4 OPERATING INSTRUCTION PAGE 2 OF 41 PRECAUTIONS (continued)

6. With LCV-218-1 in AUTO letdown will be diverted to waste ifVCT level is allowed to exceed 94.4%.

7. Boric Acid and Demineralized Water Totalizer readings will be logged every 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months on FC-75 to accurately track makeup to the RCS.

8. The effects of Boration or Dilution should be observed in terms of changes in Source Count Rate or RCS Cold Leg Temperature.

9. During Boric Acid addition, when FQS-269Y, Boric Acid Batching Switch, counts down to zero, FCV-269Y will close.

10. During Makeup Water addition, when FQS-269X, Demin Water Batching Switch, counts down to zero, FCV-269X will close.

11. The Demin Water Batching Switch FQS-269X and Flow Totalizer FQI-269X measure Demin Water addition in tens of gallons. Actual number of gallons added, or to be added, is 10 times the indicated value.

12. With the control switches for FCV-269X, Demin Water Makeup Flow Control Valve and FCV-269Y, Boric Acid Makeup Flow Control Valve, in AUTO:

A loss of control power to FCV-269Y will cause both FCV-269Y and FCV-269X to close

A loss of control power to FCV-269X will close FCV-269X only

13. The inherent design of FQI-269X allows internal pulses to accumulate (100 pulses 10 =

gallons). These pulses carry over from one use of the counter to the next. Once these extra pulses add to 100, an extra 10 gallons will be added. Therefore, operators must be continuously alert of all indications and be prepared to secure from an evolution if indications warrant.

14. Setting Flow Controller FC-269Y to greater than or equal to 25 gpm creates the possibility for the totalizer to click off an extra gallon of boric acid. (CR 2008-4382)

15. Minimize any pressure lock condition between the SI loop check valves in Mode 1, 2 or 3. A pressure lock is indicated by greater than or equal to 500 psig on SI Leakage Cooler inlet pressure transmitter(s). If the pressure lock is maintained for greater than 30 minutes in any 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period without SI or CVCS flow, RCS coolant leak by, due to lower differential pressure across SI check valve(s), may result. Production of steam and resultant water hammer is possible. (CR 200505030) I

16. Due to Containment Sump Strainer clogging issues following a LOCA, BAST levels should be kept greater than or equal to 85% and BAST concentrations should be kept greater than or equal to 3% (NRC Bulletin 2003-01).

R45

FORT CALHOUN STATION OI-CH-4 OPERATING INSTRUCTION PAGE 3 OF 41 REFERENCES/COMMITMENT DOCUMENTS

1. Technical Specification

2.2.7: Chemical and Volume Control System Borated Water Source - Shutdown

2.2.8: Chemical and Volume Control System Borated Water Sources - Operating

2. Technical Data Book (TDB) Figures:

TDB-1I1.37A, Boron Addition Rate (HZP) SIRWf @ 1900 ppm

TDB-111.37B,Boron Addition Rate (HZP) SIRWf @ 2000 ppm

TDB-1I1.37C, Boron Addition Rate (HZP) SIRWf @ 2100 ppm

TDB-111.37D,Boron Addition Rate (HZP) SIRWf @ 2200 ppm

TDB-1I1.371,Boron Addition Rate (HZP) SIRWf @ 2300 ppm

TDB-111.37E,Boron Addition Rate (HZP) BASTs @ 3.0% BA

TDB-111.37F,Boron Addition Rate (HZP) BASTs @ 3.5% BA

TDB-1I1.37G, Boron Addition Rate (HZP) BASTs @ 4.0% BA

TDB-1I1.37H, Boron Addition Rate (HZP) BASTs @ 4.5% BA

TDB-111.38A,Boron Addition Rate (HFP) SIRWf @ 1900 ppm

TDB-1I1.38B, Boron Addition Rate (HFP) SIRWf @ 2000 ppm

TDB-111.38C,Boron Addition Rate (HFP) SIRWf @ 2100 ppm

TDB-111.38D,Boron Addition Rate (HFP) SIRWf @ 2200 ppm

TDB-1I1.381,Boron Addition Rate (HFP) SIRWf @ 2300 ppm

TDB-1I1.38E, Boron Addition Rate (HFP) BASTs @ 3.0% BA

TDB-111.38F,Boron Addition Rate (HFP) BASTs @ 3.5% BA

TDB-111.38G,Boron Addition Rate (HFP) BASTs @ 4.0% BA

TDB-111.38H,Boron Addition Rate (HFP) BASTs @ 4.5% BA

TDB-V.12, Miscellaneous Formula Sheet

3. Commitments other than Ongoing:

AR 13140, LER 92-027

4. CR 200505030 I

5. CR 2008-4382

6. Drawing File Description E-23866-210-120, Sh1 10476 Chemical and Volume Control System E-23866-21 0-121 , Sh 1 10478 Chemical and Volume Control System E-23866-21 0-121 , Sh 2 55250 Chemical and Volume Control System E-23866-210-130, Sh 1 10479 Safety Injection and Containment Spray System APPENDICES None R45

FORT CALHOUN STATION OI-CH-4 OPERATING INSTRUCTION PAGE 14 OF 41 C

Continuous Use Attachment 4 - Normal Dilution of the RCS PREREQUISITES ill INITIALS

1. Procedure Revision Verification Revision No. <t.r Date: J rte

2. A Deaerated Water Booster Pump, DW-43A or DW-43B, is in operation OR if cross-connected to Demin Water, a Demineralized Water Booster Pump, DW-41 A or DW-41B, is in operation.

3. Waste Disposal System is available to receive Letdown flow diverted from the VCT.

4. At least one of the following is in operation:

One or more Reactor Coolant Pumps

One LPSI Pump supplying Shutdown Cooling PROCEDURE

1. Record the following values:

Current RCS Boron Concentration ppm

Desired RCS Boron Concentration ppm

RCS Tav9 OF NOTE Verifier must independently assess initial parameters as part of calculation verification per OI-ERFCS-1 or TDB-V.12.

2. Determine the number of gallons of Makeup Water to be added using the ERF Computer per OI-ERFCS-1 or the Dilution Formula in TDB-V.12.

Ind Verif

3. Record the number of gallons of Makeup Water to be added to the RCS.

_____ Gallons

4. Ensure HC-269, Makeup Water Mode Selector Switch, is in DILUTE.

R45

~

FORT CALHOUN STATION OI-CH-4 OPERATING INSTRUCTION PAGE 15 OF 41 C

Continuous Use Attachment 4 - Normal Dilution of the RCS PROCEDURE (continued) ill INITIALS

5. Ensure FCV-269, Makeup Water Control Valve, is in CLOSE.

NOTE Dilution of the RCS may be performed in intermittent batches of makeup water to verify proper response.

6. Set FQS-269X, Demin Water Makeup Flow Batching Switch, to the desired number of gallons of water to be added.

7. Record initial Demin Water Makeup Flow Totalizer reading:

FQI-269X gals NOTE

1. Makeup Water flow may be stopped at any time by closing FCV-269.

2. Steps 8 through 14 may be signed off after these steps are complete.

8. Open FCV-269.

CAUTION All available indications shall be monitored for desired effects during any reactivity change.

9. Place FCV-269X, Demin Water Makeup Flow Control Valve, in AUTO.

10. With FC-269X, Demin Water Makeup Flow Controller, set Demin Water flow to the desired flow rate.

11. Verify VCT level and pressure respond as expected.

12. IF unexpected reactivity effects are observed, THEN stop the makeup flow and evaluate.

13. WHEN Dilution is complete, THEN place FCV-269X in CLOSE.

R45

FORT CALHOUN STATION OI-CH-4 OPERATING INSTRUCTION PAGE 16 OF 41 C

Continuous Use Attachment 4 - Normal Dilution of the RCS PROCEDURE (continued) ill INITIALS

14. Close FCV-269.

15. Record final Demin Water Makeup Flow Totalizer reading:

FQI-269X gals

16. Verify the amount of Demin Water added from the flow totalizer is consistent with the amount of water added.

Completed by DatelTime ......!....i __

R45

FORT CALHOUN STATION TDB-V.1.B TECHNICAL DATA BOOK PAGE 12 OF 16 Part II - Performed after a refueling outage.

1:1- 6/

Criticality No.

~te A. Conditions at Time of Startup A.1. Startup date and time. YD el,Y DA E TIME A.2. Desired CEA Group 4 position at time of startup. (Manual Sequential Mode)

Group 4 __ =8;.....S' inches A.3. Sequential Rod Worth at ARO (TDB Figure II.B.2.a) ------'3'--"._;;{.;......;.1 __ %~p A.4. Sequential Rod Worth, Group 4 at position from A.2 __ 3_._o....;...S" __ %~p (TDB Figure II.B.2.a)

A.S. Critical Boron Concentration for BOC, ARO, HZP No Xenon _.;;...1_S-_6_~~_ppm (TDB Figure II.A.1.a.1)

A.6. Reactor Coolant System Inverse Boron Worth __ 1---,,-;;2.---,,7__ ppm / %~p (TDB Figure II.A.4)

A.7. Current RCS Boron Concentration IS" 6S- ppm Sample DatelTime ~

7?1)~"/"' ..*

I.

B. Estimated Critical Boron Concentration B.1. Change in reactivity due to CEA Group 4

~3~.J~/__ %~p-~3~,~D_~_- __ %~p= _0..::.........;;, I<--b=--_ %~p A.3 A.4 B.1 B.2. Change in boron due to CEA Group 4

=.0---" 1'----=6'---_

B.1

%~p X / ';1 7 A.6 ppm/%~p = _--==:1~o B.2 ppm B.3. Estimated Critical Boron Concentration (ECB)

<../_5---"-6_;;t__ ppm - _......;;.~_O ppm = ----=-/_s_'t..L-..=:....~~_ppm A.S B.2 B.3 R23

FORT CALHOUN STATION TDB-V.1.B TECHNICAL DATA BOOK PAGE 13 OF 16 C. Calculation of Reactor Coolant System Additions Required C.1. Calculate the gallons of water or boric acid required to attain the ECB boron concentration using the plant computer following OI-ERFCS-1A, Attachment 8.

Gallons of water required: see Gallons of boric acid required:

Circle boric acid source: CH-11A 3.3/ % CH-11B 3.3) %

% boron % boron D. Minimum and Maximum Critical Rod Position D.1. The maximum critical CEA position is CEA Group 4 at ARO.

D.2. Find the minimum critical CEA position.

D.2.a. Calculate the critical CEA worth -1 %~p by subtracting 1%~p from the critical CEA worth A.4.

__ 2---,-, _o_5_-__ - 1%~p = __ ~~. O_S- __ %~p A.4 D.2.a D.2.b. Using TDB Figure II.B.2.a, find the CEA position corresponding to estimated critical rod position -1 %~p and enter here.

Group 1 /J 6 inches Group 2 100 inches Group 3 ¢ inches Group 4 rl inches D.2.c. Using TDB Section VI COLR Figure 2, record the zero power dependent insertion limit by obtaining PDIL or transient insertion limit value for 0%

power.

Group 1 / ;;;.c inches Group 2 I;] 6 inches Group 3 'ds inches Group 4 rj)

, inches R23

FORT CALHOUN STATION TDB-V.1.B TECHNICAL DATA BOOK PAGE 14 OF 16 D.2.d. Use the higher of CEA positions from D.2.b and D.2.c as the minimum critical CEA position.

Group 1 _--L-I..;::.,J<--b inches Group 2 _---'-1_~_6 inches Group 3 __ ....;.a_s- inches Group 4 __ --L..¢ inches D.3. Completed by I~ ~ DatelTime P)r / l2ok/

D.4. Results of this calculation have been independently reviewed prior to Reactor Criticality.

Reactor Engineer _+;~ "----'oS:=.J.,--------o:;;;;..;;;;..--=- __ DatelTime 7o~r/M ~

R23

FORT CALHOUN STATION TDB-V.1.B TECHNICAL DATA BOOK PAGE 15 OF 16 E. Perform the Following if the Reactor Is Not Critical with Group 4 at 115" (Otherwise this is N/A)

E.1. Using Figure TDB II.B.3.a, determine the amount of reactivity needed to offset inserting Group 4 to 85".

= ------_%~p CEA worth @ 115" CEA worth @ 85" E.1 E.2. Calculate RCS boron dilution change using Inverse Boron Worth (Step A.6) and the reactivity difference calculated in Step E.1.

______ ppm/%~p X %~p = _______ ppm A.6 E.1 E.2 E.3. Calculate the New desired critical boron concentration.

_______ ppm - ppm = _______ ppm B.3 E.2 E.3 E.4. Performed by _ DatelTime ...:.../ _

E.5. Verify Step E calculations reviewed prior to Reactor Criticality.

Reactor Engineer _ DatelTime L _

R23

FORT CALHOUN STATION TDB-V.1.B TECHNICAL DATA BOOK PAGE 16 OF 16 F. Actual Critical Data F.1. After achieving criticality, complete the following record:

F.1.a. CEA Positions Group 1 inches Group 2 inches Group 3 inches Group 4 inches Group N inches F.1.b. Reactor Coolant System boron concentration: ppm F.1.c. Time at which criticality was attained:

F.1.d. Reactor Coolant System average temperature (TAVG): OF F.2. Completed by DatelTime ,

G. Review G.1. Forward to Reactor Engineer for review.

NOTE: If the reactivity difference between actual and estimated critical conditions is greater than O.5%~p, then the Reactor Engineer will review the results with the Supervisor-Reactor Physics and determine the appropriate actions, if necessary.

G.2. Reviewed by Date/Time ,

Supervisor-Reactor Performance Analysis G.3. Reviewed by _ DatelTime ....:' _

Reactor Engineer R23

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-8 Rev 3 JPM

Title:

Feed Non-Vital Buses 1A1 and 1A2 From 345 KV Location: Simulator Approximate Time: 20 minutes Start Time:__________________

End Time:___________________

Actual Time: _________________

Reference(s): K/A# 062000 A4.01 RO IMP:3.3 SRO IMP: 3.1 Ability to manually operate and/or monitor in the control room: All breakers (including applicable switchyard)

Procedures: OI-EE-1, Attachment 2, Rev 28 Other (tech specs, etc)

Handout(s): OI-EE-1, Attachment 2, Feed Non-Vital Buses 1A1 and 1A2 From 345 KV.

Task List#: 0290 Applicable Position(s): RO/SRO Time Critical: NO Alternate Path: NO JPM Prepared by: Date:

Page 1 of 10

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-8 Rev 3 JPM

Title:

Feed Non-Vital Buses 1A1 and 1A2 From 345 KV Operators Name:

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:

Safety Considerations:

Comments: This JPM is performed in parallel with JPM S-3. IC#

107 Page 2 of 10

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-8 Rev 3 JPM

Title:

Feed Non-Vital Buses 1A1 and 1A2 From 345 KV TASK STANDARD: The Applicant transferred buses 1A1 and 1A2 from 161 KV to 345 KV. Applicant closed breaker 3451-5.

Applicant then closed breaker 1A11 and opened breaker 1A31 transferring bus 1A1 from 161 KV to 345 KV. Applicant then closed breaker 1A22 and opened breaker 1A42 transferring bus 1A2 from 161 KV to 345 KV.

INITIAL CONDITIONS: The plant is in hot shutdown following a normal plant shutdown using OP-3A. 345 KV is in service per OI-EG-

1. Breaker 3451-4 is not available because substation is correcting a low gas pressure.

INITIATING CUE:

You are directed to transfer 4160 V buses 1A1 and 1A2 from 161 KV to 345 KV using OI-EE-1, Attachment 2.

Line Dispatch has ensured all Substation Personnel are clear of the breakers.

All prerequisites are met.

Page 3 of 10

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-8 Rev 3 JPM

Title:

Feed Non-Vital Buses 1A1 and 1A2 From 345 KV Critical Steps shown in gray and **

STEP ELEMENT STANDARD Provide Applicant with a copy of OI-EE-1, Attachment 2

1 NOTE: Read note.

Steps 1 and 2 may be performed in any order. [SAT ] [ UNSAT ]

2 (1.) IF open and available, THEN Determined breaker 3451-4 close 3451-4 as follows: was not available

[SAT ] [ UNSAT ]

- 3 (2.a) IF open and available, THEN CB-20 close 3451-5 as follows:

Placed switch handle in synch

a. Turn on Synchroscope for switch 3451-5 and turned 3451-5. clockwise.

[SAT ] [ UNSAT ]

4 (2.b) Verify Synchroscope is CB-20 approximately at a 12 o'clock position. Verified Synchroscope dial at 12 oclock.

[SAT ] [ UNSAT ]

Page 4 of 10

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-8 Rev 3 JPM

Title:

Feed Non-Vital Buses 1A1 and 1A2 From 345 KV STEP ELEMENT STANDARD

- 5 (2.c) Close 3451-5. CB-20

Placed Control switch for breaker 3451-5 in the AFTER-CLOSE (Red flag) position

Verified RED light ON

[SAT ] [ UNSAT ]

6 (2.d) Turn off Synchroscope. CB-20 Turned switch handle in synch switch 3451-5 counter-clockwise.

[SAT ] [ UNSAT ]

7 (3.a) Transfer 1A1, Non-Vital Bus, to CB-20 22 KV as follows:

Verified 43/1A1-1A3 in

a. Ensure 43/1A1-1A3, Fast MANUAL position Transfer Switch, is in MANUAL.

[SAT ] [ UNSAT ]

8 (3.b) Turn on Synchroscope for CB-20 1A11. Placed switch handle in synch switch 1A11 and turned clockwise.

[SAT ] [ UNSAT ]

9 (3.c) Verify Incoming and Running CB-20 voltages are approximately Verified voltages on Incoming matched. and Running voltmeters are approximately equal

[SAT ] [ UNSAT ]

Page 5 of 10

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-8 Rev 3 JPM

Title:

Feed Non-Vital Buses 1A1 and 1A2 From 345 KV STEP ELEMENT STANDARD 10 (3.d) Verify Synchroscope is CB-20 approximately at a 12 o'clock position. Verified Synchroscope dial at 12 oclock.

[SAT ] [ UNSAT ]

- 11 (3.e) Close 1A11. CB-20

Placed Control switch for breaker 1A11 in the AFTER-CLOSE (Red flag) position

Verified RED light ON

[SAT ] [ UNSAT ]

- 12 (3.f) Open 1A31. CB-20

Placed Control switch for breaker 1A31 in the AFTER-TRIP (Green flag) position

Verified GREEN light ON

[SAT ] [ UNSAT ]

13 (3.g) Turn off Synchroscope. CB-20 Turned switch handle in synch switch counter-clockwise.

[SAT ] [ UNSAT ]

Page 6 of 10

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-8 Rev 3 JPM

Title:

Feed Non-Vital Buses 1A1 and 1A2 From 345 KV STEP ELEMENT STANDARD 14 (3.h) IF the following condition for CB-20 Fast Transfer are met, Placed 43/1A1-1A3 in AUTO

All lock-outs on CB-20 position have amber light on

Appropriate 4160 volt [SAT ] [ UNSAT ]

breakers are not in pull-to-lock

Power is available to transfer to THEN place 43/1A1-1A3, Fast Transfer Switch, in AUTO.

15 (4.a) Transfer 1A2, Vital Bus, to 22 CB-20 KV as follows:

Verified 43/1A2-1A4 in

a. Ensure 43/1A2-1A4, Fast MANUAL position Transfer Switch, is in MANUAL.

[SAT ] [ UNSAT ]

16 (4.b) Turn on Synchroscope for CB-20 1A22. Placed switch handle in synch switch 1A22 and turned clockwise.

[SAT ] [ UNSAT ]

17 (4.c) Verify Incoming and Running CB-20 voltages are approximately Verified voltages on Incoming matched. and Running voltmeters are approximately equal

[SAT ] [ UNSAT ]

Page 7 of 10

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-8 Rev 3 JPM

Title:

Feed Non-Vital Buses 1A1 and 1A2 From 345 KV STEP ELEMENT STANDARD 18 (4.d) Verify Synchroscope is CB-20 approximately at a 12 o'clock position. Verified Synchroscope dial at 12 oclock.

[SAT ] [ UNSAT ]

- 19 (4.e) Close 1A22. CB-20

Placed Control switch for breaker 1A22 in the AFTER-CLOSE (Red flag) position

Verified RED light ON

[SAT ] [ UNSAT ]

- 20 (4.f) Open 1A42. CB-20

Placed Control switch for breaker 1A42 in the AFTER-TRIP (Green flag) position

Verified GREEN light ON

[SAT ] [ UNSAT ]

21 (4.g) Turn off Synchroscope. CB-20 Turned switch handle in synch switch counter-clockwise.

[SAT ] [ UNSAT ]

Page 8 of 10

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-8 Rev 3 JPM

Title:

Feed Non-Vital Buses 1A1 and 1A2 From 345 KV STEP ELEMENT STANDARD 22 (4.h) IF the following condition for CB-20 Fast Transfer are met, Placed 43/1A2-1A4 in AUTO All lock-outs on CB-20 have position amber light on Appropriate 4160 volt breakers are not in pull-to-lock [SAT ] [ UNSAT ]

Power is available to transfer to THEN place 43/1A2-1A4, Fast Transfer Switch, in AUTO.

23 NOTE Read note.

Under certain plant conditions, while supplying all 4160 volt buses, overheat of T1A1 or [SAT ] [ UNSAT ]

T1A2 could occur. To minimize this potential, loads between the 2 transformers should be balanced as much as practicable.

24 (5) Balance loads between T1A1 EXAMINER CUE: Another and T1A2 as plant conditions Operator will balance loads allow.

Termination Criteria: Buses 1A1 and 1A2 are powered from 345 KV.

Page 9 of 10

Fort Calhoun Station - Operations Training JOB PERFORMANCE MEASURE JPM No: S-8 Rev 3 INITIAL CONDITIONS: The plant is in hot shutdown following a normal plant shutdown using OP-3A. 345 KV is in service per OI-EG-

1. Breaker 3451-4 is not available because substation is correcting a low gas pressure.

INITIATING CUE: You are directed to transfer 4160 V buses 1A1 and 1A2 from 161 KV to 345 KV using OI-EE-1, Attachment 2.

Line Dispatch has ensured all Substation Personnel are clear of the breakers.

All prerequisites are met.

Page 10 of 10

FORT CALHOUN STATION OI-EE-1 OPERATING INSTRUCTION C PAGE 9 OF 39 Continuous Use Attachment 2 - Feed Non-Vital Buses 1A1 and 1A2 From 345 KV PREREQUISITES ({l INITIALS

1. Procedure Revision Verification Revision No. d8 Date: 16),)!

2. 345 KV is in service per OI-EG-1.

3. IF Gen G1 is shutdown, THEN ensure DS-T1, T1 Disconnect Switch, is open per Attachment 4.

4. IF 3451-4 and 3451-5 Breakers are to be operated, THEN notify Line Dispatch to ensure all Substation Personnel are clear of breakers.

5. The following Turbine Trip Lockout Relays are RESET:

86-1/SVG1

86-2/SVG1 PROCEDURE NOTE Steps 1 and 2 may be performed in an order.

1. IF open and available, THEN close 3451-4 as follows:

a. Turn on Synchroscope for 3451-4.

b. Verify Synchroscope is approximately at a 12 o'clock position.

c. Close 3451-4.

d. Turn off Synchroscope.

2. IF open and available, THEN close 3451-5 as follows:

a. Turn on Synchroscope for 3451-5.

R28

FORT CALHOUN STATION OI-EE-1 OPERATING INSTRUCTION C PAGE 10 OF 39 Continuous Use Attachment 2 - Feed Non-Vital Buses 1A1 and 1A2 From 345 KV PROCEDURE (continued) ((l INITIALS 2

b. Verify Synchroscope is approximately at a 12 o'clock position.

c. Close 3451-5.

d. Turn off Synchroscope.

NOTE

1. Steps 3 through 4 may be performed in any order.

2. If 43/1A1-1A3 is in manual and 1A13 is closed, 1A3 is inoperable.

3. Transfer 1A1, Non-Vital Bus, to 22 KV as follows:

a. Ensure 43/1A1-1A3, Fast Transfer Switch, is in MANUAL.

b. Turn on Synchroscope for 1A11.

c. Verify Incoming and Running voltages are approximately matched.

d. Verify Synchroscope is approximately at a 12 o'clock position.

e. Close 1A11.

f. Open 1A31.

g. Turn off Synchroscope.

h. IF the following condition for Fast Transfer are met,

All lock-outs on CB-20 have amber light on

Appropriate 4160 volt breakers are not in pull-to-lock

Power is available to transfer to THEN place 43/1A1-1A3, Fast Transfer Switch, in AUTO.

R28

FORT CALHOUN STATION OI-EE-1 OPERATING INSTRUCTION C PAGE 11 OF 39 Continuous Use Attachment 2 - Feed Non-Vital Buses 1A1 and 1A2 From 345 KV PROCEDURE (continued) ((l INITIALS NOTE If 43/1A2-1A4 is in manual and 1A24 is closed, 1A4 is ino erable.

4. Transfer 1A2, Vital Bus, to 22 KV as follows:

a. Ensure 43/1A2-1A4, Fast Transfer Switch, is in MANUAL.

b. Turn on Synchroscope for 1A22.

c. Verify Incoming and Running voltages are approximately matched.

d. Verify Synchroscope is approximately at a 12 o'clock position.

e. Close 1A22.

f. Open 1A42.

g. Turn off Synchroscope.

h. IF the following condition for Fast Transfer are met,

All lock-outs on CB-20 have amber light on

Appropriate 4160 volt breakers are not in pull-to-Iock

Power is available to transfer to THEN place 43/1A2-1A4, Fast Transfer Switch, in AUTO.

NOTE Under certain plant conditions, while supplying all 4160 volt buses, overheat of T1A 1 or T1A2 could occur. To minimize this potential, loads between the 2 transformers should be balanced as much as practicable.

5. Balance loads between T1A1 and T1A2 as plant conditions allow.

Completed by DatelTime __ ---=-I__

R28

Appendix D Scenario Outline Form ES-D-1 Facility: _Fort Calhoun Station__ Scenario No.: __1_(Spare)___ Revision __1__ Op-Test No.:

Examiners: ____________________________ Operators: _____________________________

Initial Conditions: _100% power, diesel generator #1 is tagged out for maintenance.________________

Turnover: __Reduce power to <95% per grid operator.___________________

Event Malf. No. Event Event No. Type* Description 1

R-ATCO Reduce power to <95% per OP-4, Attachment 2.

N-BOPO N-CRS 2 I-ATCO PIC-244 fails, causing HCV-204 (Letdown heat exchanger isolation valve ) to close. Alarms are for VCT level low and Pressurizer level TS-CRS high (CB-1,2,3/A2 Window B-2 and CB-1,2,3/A4 Window A-8). If pressurizer level goes >69.2%, TS 2.1.7 applies.

3 C-ATCO HCV-153 opens, causing quench tank level to decrease. Alarm is C-BOPO CB-1,2,3/A4 Window C-3. Action will be to restore level and close HCV-153 4 C-BOPO Inadvertent VIAS. AOP-23 Section IV. TS 2.15(3) applies.

TS-CRS (CT) Critical task is to reset relays that tripped and reset the inadvertent VIAS actuation.

5 C-BOPO Loss of 161 kV line. Alarm is CB-20/A15, Window A-1, 4160V TS-CRS Supply Breaker from 161KV Tripped, also Windows A-2 and A-3.

Since a fast transfer will occur, the ARP states to go to AOP-31.

TS 2.7(2)c and TS 2.01 BOTH apply.

6 M-All Loss of 345kV line (LOOP) Reactor trips, SRO enters EOP-00 and after SPTAs, transfers to EOP-07, due to below failure. Upon operator manually closing breaker, power will be restored to one vital bus.

7 C-BOPO AFW valve HCV-1108A remains closed. It can be opened from the control panel. EOP-07 Step 6.1.

(CT)

Critical task is to restore AFW flow using either FW-54 or FW-10 to steam generator RC-2B prior to reaching 27% wide range level.

8 C-BOPO Diesel Generator #2 breaker fails to close automatically due to diesel not reaching rated speed. When operators increase (CT) governor, the output breaker will close once breaker synch conditions are met. See Step 12 of EOP-07.

Critical task is to perform this action before exiting EOP-07.

Page 1 of 17

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 1 of 17

Scenario Event Description NRC Scenario #1 SCENARIO

SUMMARY

NRC #1 The crew will assume the watch at 100% power, with diesel generator #1 out of service for maintenance, and instructions to downpower to less than 95% per OP-4, LOAD CHANGE AND NORMAL POWER OPERATION, Attachment 2, "Load Reduction".

The first event is the power reduction which will continue until an observable effect on the reactor is seen (approximately 1-2% load reduction).

The next event is a failure of PIC-244 which senses pressure downstream of letdown backpressure control valve. This causes letdown to isolate. Operator actions are per ARP-CB-1,2,3/A2 and require securing charging flow. Operators will use OI-CH-1, CHEMICAL AND VOLUME CONTROL SYSTEM NORMAL OPERATION, to restore letdown and charging after manually overriding the HCV-204 Interlock Override Switch in DEFEAT. SRO will refer to Technical Specifications. T.S. 2.1.7 might apply if pressurizer level goes above 69.2%.

The next event is a spurious opening of HCV-153, quench tank drain valve, causing quench tank level to decrease. Operator actions are per ARP-CB-1,2,3/A4 and include closing HCV-153 and taking action to restore quench tank level using deaerated water.

The next event is an inadvertent ventilation isolation actuation signal. Operator actions are per ARP-AI-30B/A34-1 and AOP-23 and include verifying that the VIAS was inadvertent and taking actions to reset the relays and reset the actuation (these two steps are critical tasks). The SRO will refer to Technical Specifications. T.S. 2.15(3) applies.

The next event is a loss of the 161 KV line. Operator actions are per ARP-CB-20/A15 and AOP-31, 161 KV GRID MALFUNCTIONS and include establishing balanced 4160 V bus loading by ensuring that condensate pump FW-2A, feed pump FW-4A and heater drain pump FW-5A are operating. SRO will refer to Technical Specifications. T.S. 2.7.2(c) and TS 2.01 both apply.

Once actions for the loss of the 161 KV line are complete, there will be a loss of the 345 KV line, resulting in a LOOP. Diesel generator #2 does not reach rated speed and breaker does not automatically close, causing a station blackout. Crew will enter EOP-00 and perform standard post trip actions. Following diagnosis of event, SRO will transition to EOP-07, STATION BLACKOUT.

While performing the actions for a station blackout, the crew should recognize that HCV-1108A failed to open and will must restore AFW flow to the RC-2A steam generator (critical task).

The crew will also take actions to raise the governor speed for diesel generator #2, which will result in the breaker closing automatically (critical task). Once this occurs and diesel generator

2 is feeding its respective bus, the scenario will be terminated.

Page 2 of 17

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: _1__ Event No.: __1__ Page _4__ of __17_

Event

Description:

__Reduce power to less than 95%._____________________________________

Time Position Applicants Actions or Behavior CRS Enter OP-4, LOAD CHANGE AND NORMAL POWER OPERATION, Attachment 2, Power Reduction CRS Ensure prerequisites are met and read notes on page 21.

CRS Maximize pressurizer spray. CRS may or may not choose to do this. This step is required if a change in boron concentration of greater than 50 ppm will occur.

ATCO Maximize pressurizer spray per OI-RC-7, REACTOR COOLANT SYSTEM PRESSURE CONTROL NORMAL OPERATION, Attachment 4, Maximum Pressurizer Spray for Mixing) (OP-4, Att. 2, Step 1)

ATCO Verify PC-103X pressurizer press controller in automatic (OI-RC-7, Att. 4, Step 1.a)

ATCO Ensure proportional heaters bank P1 group 6 and P2 group 7 are in AUTO (OI-RC-7, Att. 4, Step 1.b)

ATCO Ensure PCV-103-1, PZR spray valve from loop 2A, and PCV-103-2, PZR spray valve from loop 1B, are in AUTO (OI-RC-7, Att. 4, Step 1.c)

ATCO Energize backup heaters by placing each of four control switches

{ HC-103-3/4/5/6} in ON (OI-RC-7, Att. 4, Step 1.d)

ATCO Ensure two spray valves {PCV-103-1 and PCV-103-2} open automatically to terminate pressure rise ((OI-RC-7, Att. 4, Step 1.e)

ATCO Adjust PC-103X setpoint pushbuttons to maintain 2100 psia ((OI-RC-7, Att. 4, Step 1.f). Crew may not need to adjust if at current SP.

CRS Read Cautions on page 24 CRS Direct ATCO and BOPO to lower reactor and turbine load to 95% per step 5.a-g.

ATCO Add boric acid per the reactivity plan, PAPeRS guidance, and visual aids on CRS desk as directed by CRS. The CRS may also use OI-CH-4, CHEMICAL AND VOLUME CONTROL SYSTEM MAKEUP OPERATIONS, Attachment 3, Normal Boration of the RCS (OP-4, Att. 2, Step 5.g)

Note: validation crew used 90 gallons Event description continues on next page.

Op-Test No.: _____ Scenario No.: _1__ Event No.: __1__ Page _5__ of _17__

Event

Description:

__Reduce power to less than 95%._____________________________________

Time Position Applicants Actions or Behavior ATCO Reviews prerequisites.

ATCO Record information required in Step 1. (OI-CH-4, Att. 3, Step 1)

ATCO Determine amount of boric acid to be added and record. (OI-CH-4, Att. 3, Steps 2-3)

Note: validation crew used 90 gallons ATCO Ensure FCV-269, Makeup Water Control Valve, is in CLOSE. (OI-CH-4, Att. 3, Step 4)

ATCO Set FQS-269Y, Boric Acid Makeup Flow Batching Switch to desired amount of boric acid (approx. 90 gal). Record initial totalizer reading. (OI-CH-4, Att. 3, Steps 5-6)

ATCO Ensure Boric Acid Pump Recirculation Valves, HCV-264, HCV-257 are closed. (OI-CH-4, Att. 3, Step 7)

ATCO Place HC-269, Makeup Water Mode Select Switch, in BORATE.

(OI-CH-4, Att. 3, Step 8)

ATCO Open FCV-269. (OI-CH-4, Att. 3, Step 9)

ATCO Place FCV-269Y, Boric Acid Makeup Flow Control Valve, in AUTO. (OI-CH-4, Att. 3, Step 10)

ATCO Use FC-269Y, Boric Acid Makeup Flow Controller, to set boric acid flow to desired flow rate. (OI-CH-4, Att. 3, Step 11)

ATCO Verify VCT level and pressure respond as expected. (OI-CH-4, Att.

3, Step 12)

ATCO When boration is complete, place FCV-269Y in CLOSE. Close FCV-269. Place HC-269 in DILUTE. (OI-CH-4, Att. 3, Steps 14-15)

BOPO Lower Turbine Generator Load to maintain RCS TAVE program per TDB Figure III.1. (OP-4, Att. 2, Step 5.a)

Examiner note: Double arrows on digital turbine screen are 0.5 degrees of change while single arrows are 0.2 degrees of change.

Event description continues on next page.

Op-Test No.: _____ Scenario No.: _1__ Event No.: __1__ Page _6__ of _17__

Event

Description:

__Reduce power to less than 95%._____________________________________

Time Position Applicants Actions or Behavior ATCO Maintain pressurizer level within 4% of programmed level per OI-RC-8.

Level control in automatic. No operator action required. (OP-4, Att. 2, Step 5.c)

ATCO Maintain pressurizer pressure 2075-2150 PSIA per OI-RC-7. Pressure control in automatic. No operator action required (OP-4, Att. 2, Step 5.d)

BOPO Maintain steam generator levels at 55-75% NR per OI-FW-3. Level control in automatic. No operator action required (OP-4, Att. 2, Step 5.e)

ATCO Maintain ASI per OI-RR-1, REACTOR REGULATING SYSTEM NORMAL OPERATION, Attachment 4, ASI Control (OP-4, Step 5.f) or the crew may use Attachment 3. Also may use PAPeRS guidance.

ATCO Review prerequisites.

ATCO Use group 4 CEAs to control ASI. Insert CEAs to make ASI more positive. Withdraw CEAs to move ASI negative. When inserting rods, take mode select switch to MS, drive Group 4 rods in the desired amount (approx 4 inches), mode select switch to OFF.

(OI-RR-1, Att. 4, Step 1)

ATCO Maintain ASI per TDB Figure III.23.a. (-0.01 to + 0.01) (OI-RR-1, Att. 4, Step 2)

If crew uses OI-RR-1, Attachment 3:

ATCO Review Notes.

ATCO Ensure an out-of-scan CEA is not selected as the target rod on CB-4. (OI-RR-1, Attachment 3, Step 1)

ATCO Verify REGULATING GROUP WITHDRAWAL PROHIBIT is clear. (Step 2)

ATCO Place Rod Control Mode Selector Switch in Manual Sequential position.

(Step 3)

ATCO Review Note.

Event description continues on next page.

Op-Test No.: _____ Scenario No.: _1__ Event No.: __1__ Page _7__ of __17_

Event

Description:

__Reduce power to less than 95%._____________________________________

Time Position Applicants Actions or Behavior ATCO Place Manual Rod Control Switch to LOWER, then verify the following (Step 4):

Primary CEAPIS indicates motion in the proper direction

Secondary CEAPIS indicates motion in the proper direction

ERF (Page 302 or LPP) indicates motion in the proper direction ATCO Verify the following group motion overlap (Step 5.b):

Group 3 starts when Group 4 is at 53 inches Note: This will not be reached during this downpower.

ATCO When the group is at the desired position, release Manual Rod Control Switch (Step 7).

ATCO Verify all CEA motion stops as indicated by the following (Step 9):

Primary CEAPIS

Secondary CEAPIS

ERF (Page 302 or LPP)

ATCO Place Rod Control Mode Selector Switch in OFF. (Step 11)

Next event is cued at Lead Examiner's discretion once a reactivity effect is seen.

Op-Test No.: _____ Scenario No.: _1__ Event No.: __2__ Page _8__ of _17__

Event

Description:

PIC-244 fails high, causing HCV-204 to close, isolating letdown.

Time Position Applicants Actions or Behavior ATCO Respond to alarms CB-1,2,3/A2 Window B1L, INTERMEDIATE LETDOWN PRESSURE HI-LO, and CB-1,2,3/A2, A1L, RELIEF VALVE CH-223 DISCHARGE TEMPERATURE HI ATCO Enter ARP-CB-1,2,3/A2 Window A1L ATCO Check TIA-205 Letdown Relief Line Temperature (Step 1)

ATCO Ensure TCV-202 and HCV-204 are closed. (Step 2)

ATCO Monitor TIA-205 to verify CH-223 and verify temperature is trending down.

(Step 2.1)

Booth Cue when called as field operator such as Water Control Operator: The linkage is broken and will need EM to repair.

ATCO Place HC-204-1, Letdown Flow HCV-204 Interlock Override SW-1, in DEFEAT. (Step 2.2)

Lead Examiner note: If the crew chooses not to put HC-204-1 SW-1 in DEFEAT, then have the booth call as SM to direct them to do it. Not performing this step correctly is a failure to follow the procedure as written.

ATCO Restore letdown to service per OI-CH-1. (Step 2.3)

Examiner note: Once the crew reaches this point do not allow them to continue to restore letdown-this takes too long for this scenario.

CRS TS 2.1.7 might apply if pressurizer level gets above 69.2%.

Next event is initiated at Lead Examiner direction.

Op-Test No.: _____ Scenario No.: _1__ Event No.: __3__ Page _9__ of _17__

Event

Description:

HCV-153 opens, causing quench tank level to decrease.

Time Position Applicants Actions or Behavior ATCO Respond to alarm CB-1,2,3/A4 Window C-3, QUENCH TANK LEVEL HI-LO ATCO Enter ARP-CB-1,2,3/A4 Window C-3 ATCO Check pressurizer quench tank level on LIA-132 or L132, ERF. (Step 1)

Booth note: CRS may call work week manager for help.

ATCO Restore PQT Level per OI-RC-6, PRESSURIZER QUENCH TANK NORMAL OPERATION. (Step 2)

BOPO/ATCO Open dearated water header isolation valves HCV-1560A and 1560B.

(OI-RC-6, Attachment 1, Step 1)

ATCO Monitor PIA-131, Pressurizer Quench Tank pressure. (Step 2)

ATCO Open quench tank vent valve, HCV-155, as necessary to maintain pressure less than 10 psig. (Step 3)

BOPO/ATCO When filled to desired level (typ. 73%), close HCV-1560A, HCV-1560B. (Step 4)

ATCO Check for leakage from PQT to RCDT and/or containment sump. (ARP-CB-1,2,3/A4, Window C-3, Step 2.1)

ATCO Determine that the quench tank drain valve, HCV-153 is open.

ATCO Close HCV-153. (OI-RC-6, Attachment 2, Step 5)

Next event is cued at Lead Examiner direction

Op-Test No.: _____ Scenario No.: _1__ Event No.: __4__ Page _10__ of _17__

Event

Description:

Inadvertent Ventilation Isolation Actuation Signal.

Time Position Applicants Actions or Behavior BOPO Respond to alarm AI-30B/A34-1 Window C-2, VENTILATION ISOLATION COMMAND.

BOPO Enter ARP- AI-30B/A34-1 Window C-2.

BOPO Verify 86B/VIAS is tripped. Verify valves isolated by VIAS are closed.

(Step 1)

BOPO Verify that none of the following relays are tripped: 86B/CRHS, 86B/SIAS, 86B/CSAS. (Step 2)

CRS Direct entry into AOP-23, RESET OF ENGINEERED SAFEGUARDS,Section IV, Reset of Containment Isolation Actuation Signal (CIAS) and Ventilation Isolation Actuation Signal (VIAS)

BOPO Verify VIAS is inadvertent: No PPLS, CPHS, SIAS, or CSAS. RM-051, RM-052, RM-062 not in alarm. (AOP-23,Section IV, Step 1)

BOPO Ensure BOTH emergency operate THINK switches, SE-A and SE-B, are in NORM. (AOP-23,Section IV, Step 2)

BOPO Ensure all RCP Coolers CCW valves are open. (AOP-23,Section IV, Step 3)

BOPO Ensure hand controller thumbwheel is set fully counter-clockwise for any of the following valves that are open: HCV-400C, HCV-401C, HCV-402C, HCV-403C. (AOP-23,Section IV, Step 4)

Examiner note: 400C and 401C are currently throttled open for containment cooling and the crew may choose to leave them in this position.

BOPO Ensure relays are reset: 86A/CIAS, 86B1/CIAS, 86B/CIAS, 86A1/CIAS. (AOP-23,Section IV, Step 5)

BOPO Ensure 86/AI-43A, 86/AI-43B are reset. (AOP-23,Section IV, Step 6)

BOPO Ensure detector well cooling by opening HCV-467A, B, C, D, and starting any detector well cooling fan. (AOP-23,Section IV, Step 7)

BOPO Ensure 86A/CRHS, 86B/CRHS, 86B1/CRHS, and 86A1/CRHS reset. (AOP-23,Section IV, Steps 8-9)

Event description continues on next page.

Op-Test No.: _____ Scenario No.: _1__ Event No.: __4__ Page _11__ of _17__

Event

Description:

Inadvertent Ventilation Isolation Actuation Signal.

Time Position Applicants Actions or Behavior BOPO Ensure 86A/VIAS, 86B1/VIAS, 86B/VIAS, and 86A1/VIAS reset.

(CT) (AOP-23,Section IV, Step 10)

Examiner note: The 86B/VIAS must be reset, the others are in the correct position BOPO (CT) Depress both 94A/VIAS-RESET and 94B/VIAS-RESET pushbuttons. (AOP-23,Section IV, Step 11)

BOPO Complete Attachment D, Equipment Operated by VIAS. (AOP-23,Section IV, Step 13)

TS-CRS Enter TS 2.15(3) for loss of isolation logic subsystem : Restore to operable status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or placed in hot shutdown within the following 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ; operation can continue without containment ventilation isolation signals available if ventilation isolation valves are closed.

Next event is cued at Lead Examiner's direction.

Op-Test No.: _____ Scenario No.: _1__ Event No.: __5__ Page _12__ of _17__

Event

Description:

Loss of 161 kV line.

Time Position Applicants Actions or Behavior BOPO Respond to alarms: CB-20/A15 Windows A-1, BREAKER 111 TRIPPED, Window A-2, 161 KV SUPPLY BKR LOCKOUT RELAY OPERATED 86/161, Window A-3, BREAKER 110 TRIPPED BOPO Enter ARP-CB-20/A15, Windows A-1, A-2, A-3 (all have the same actions)

BOPO Notify Energy Marketing and Shift Manager. (ARP-CB-20/A15 A-3, Step 2)

Booth Cue when called as Energy Marketing: The 161 kV line has been lost and there is no estimate for its return.

BOPO Verify Fast Transfer has occurred and go to AOP-31. (Step 3.1)

CRS Enter AOP-31, 161 KV GRID MALFUNCTIONS,Section II, All 4160 V Buses Fed from 22 KV CRS Ensure 2 condensate pumps, 2 feed pumps, and 2 heater drain pumps are operating. (AOP-31, Step 1)

BOPO Adjust main generator terminal voltage less than 22,000 volts per the following: N/A. (Step 2)

BOPO Establish balanced 4160 V bus loading on T1A1 and T1A2 by ensuring all the following are operating: condensate pump FW-2A, feed pump FW-4A, and heater drain pump FW-5A. (Step 3)

BOPO Start Heater Drain Pump, FW-5A (Step 3)

BOPO Verify voltage is greater than 430 volts on all the following buses: 1B3A, 1B3B, 1B3C, 1B4A, 1B4B, 1B4C. If not, refer to attachment A to determine loads to realign. (Step 4)

CRS Notify NRC of loss of 161 KV within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . (Step 5)

BOPO Match flags on following breakers: 110, 111, 1A31, 1A33, 1A42, 1A44.

(Step 6)

CRS Enter TS 2.7.2(c) for loss of 161 kV line inop-ing both house service transformers.

May be inoperable for up to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , after which it must be placed in a hot shutdown condition within following 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . Notify NRC Operations Center by phone within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of inoperability of transformers.

Enter TS 2.01 because a loss of 161kV and one EDG OOS (#1) concurrently, therefore this TS is required.

Next event is cued at Lead Examiner's direction. Events 7 and 8 are preprogrammed and need not be cued.

Op-Test No.: _____ Scenario No.: _1__ Event No.: __6,7,8__ Page _13__ of _17_

Event

Description:

Loss of 345 kV line. Failure of diesel generator #2 to reach rated speed, so breaker does not automatically close, causing a station blackout. AFW valve HCV-1108A remains closed but can be opened from the control panel.

Time Position Applicants Actions or Behavior CRS Enter EOP-00, STANDARD POST TRIP ACTIONS ATCO BOPO Respond to reactor trip. Perform SPTAs, EOP-00, STANDARD POST TRIP ACTIONS ATCO Verify reactivity control established: reactor power is lowering, startup rate is negative, no more than 1 regulating or shutdown CEA not inserted, and monitor for uncontrolled RCS cooldown (EOP-00 Step 1)

BOPO Verify turbine tripped as indicated by stop and intercept valves indicating closed. (EOP-00, Step 2)

BOPO Ensure all of the following generator breakers tripped: output breakers 3451-4, 3451-5, and field breaker 41E/G1F. (EOP-00 Step 3)

BOPO Verify buses 1A3 and 1A4 energized (EOP-00 Step 4). Transition to contingency column.

BOPO Minimize DC loads per attachment 6. Ensure diesel generator is started for affected bus (EOP-00 Step 4.1).

BOPO Direct an auxiliary operator to perform the following:

BOPO Place DC Bus 2 breakers EE-8G-CB12, 400 Cycle Inverter EE-21 and EE-8G-CB8, Emergency Lighting Pnl ELP-2 Transfer Switch in OFF (EOP Attachment 6, Step 1.a)

BOPO Place DC Bus 1 breaker EE-8F-CB11, Aux Bldg Emgy Lighting Panel ELP-1 in OFF (EOP Attachment 6, Step 1.b)

BOPO Place 125 VDC Panel DC-PNL-1, Breaker 15, ELP-5 Emergency Lighting Panel in OFF (EOP Attachment 6, Step 1.c)

BOPO Vent hydrogen from generator using G-03, Generator ST-2 Vent Header Isolation Valve behind AI-134 (EOP Attachment 6, Step 2)

BOPO Check that Buses 1A1 and 1A2 are energized (EOP-00 Step 6). No contingency actions.

BOPO Check that 125 VDC buses 1 and 2 are energized. (EOP-00, Step 7)

BOPO Verify instrument air is available by both of the following: IA pressure greater than or equal to 90 psig and at least one air compressor running (EOP-00, Step 8) Contingency action is to restore instrument air, but no power at this time to run the pump or compressor.

Events description continued on next page.

Op-Test No.: _____ Scenario No.: _1__ Event No.: __6,7,8__ Page __14_ of _17_

Event

Description:

Loss of 345 kV line. Failure of diesel generator #2 to reach rated speed, so breaker does not automatically close, causing a station blackout.

Time Position Applicants Actions or Behavior ATCO Determine normal CCW system operation: At least one CCW pump operating, CCW pump discharge pressure is greater than or equal to 60 psig, at least one RW pump is operating, and RCP coolers CCW valves HCV-438A/B/C/D are open if CCW pump discharge pressure is greater than 40 psig (EOP-00 Step 9). Transition to contingency action.

ATCO Contingency action is to stop RCPs which has already occurred. (EOP-00 Step 9.1)

ATCO Verify all of the following: PZR level 30-70%, trending to 45-60%, RCS subcooling greater than or equal to 20°F. (EOP-00, Step 10)

ATCO Verify all of the following: RCS pressure 1800-2300 psia, trending to 2050-2150 psia, and PORVs are closed. (EOP-00, Step 11)

Note: Because level and pressure are slowly lowering due to RCP seal leakoff, crew may enter contingency actions for this step, which check for a PORV open, verify ESF if pressure <1600 psia, trip 1 RCP in each loop if pressure <1350 psia, and manually control sprays and heaters to maintain pressure.

ATCO Verify forced circulation with at least one RCP operating, transition to contingency column (EOP-00, Step 12)

BOPO Place TCV-909 temperature controller in manual (DCS, Secondary/MS/SD&B Control. (EOP-00, Step 12.2.a)

BOPO Ensure TCV-909 temperature controller output is zero. (EOP-00, Step 12.2.b)

ATCO Verify development of natural circulation flow in at least one loop by all of the following: Core T less than or equal to 50°F, difference between CETs and RCS TH is less than or equal to 10°F, RCS subcooling greater than or equal to 20°F, and TH and TC are stable or lowering. (EOP-00, Step 12.2.b)

BOPO Verify Main Feedwater is restoring level in at least one steam generator (EOP-00, Step 13). Transition to contingency step 13.1.b, c, d, or e.

BOPO Critical Task is to perform one of the next four steps to restore AFW flow using either FW-54 or FW-10 to steam generator RC-(CT) 2A prior to reaching 27% wide range level.

Event description continues on next page.

Op-Test No.: _____ Scenario No.: _1__ Event No.: __6,7,8__ Page __15_ of _17_

Event

Description:

Loss of 345 kV line. Failure of diesel generator #2 to reach rated speed, so breaker does not automatically close, causing a station blackout.

Time Position Applicants Actions or Behavior BOPO Initiate AFW using diesel driven AFW pump to Feed Ring (EOP-00, Step 13.1.b)

1) Start FW-54.

2) Restore level in at least one S/G to 35-85% NR.

OR BOPO Initiate AFW using FW-10, AFW pump to AFW nozzle (EOP-00 Step 13.1.c)

1) Start FW-10

2) Restore level in at least one S/G to 35-85% NR.

OR BOPO Initiate AFW using FW-10 AFW pump to Feed Ring by starting FW-10 and opening HCV-1383, Aux FW/FW Header Cross Connect Valve (EOP-00, Step 13.1.d)

OR BOPO Initiate AFW using FW-54, diesel AFW pump, to AFW nozzles by starting FW-54, directing an auxiliary operator to unlock and close FW-170, Aux Feedwtr X-Tie Vlv HCV-1384 Outlet Valve, and opening HCV-1384, Aux FW/FW Header Cross Connect Valve (EOP-00, Step 13.1.e)

Note: Crew may decide to use an override on the Main FW regulating bypass valves, which allows the use of an accumulator to hold these valves completely open (cannot throttle). This action would allow FW-54 to continue to feed directly into the steam generators through the MFW line (Step 13.1.b), since a SBO causes a loss of instrument air, resulting in these valves drifting closed. This would keep the operators from having to realign FW-54 to go through the AFW nozzles (and needing to reopen HCV-1108A). However, the override of the feed reg bypass valves is NOTproceduralized in the EOP.

BOPO Verify Steam Dump and Bypass valves are controlling RCS TC 525-535°F and steam generator pressure 850-925 psia (EOP-00 Step 14). Transition to contingency action 14.c.

BOPO Operate at least one of the air assisted main steam safety valves MS-291 and/or MS 292 (EOP-00, Step 14.c)

Event description continues on next page.

Op-Test No.: _____ Scenario No.: _1__ Event No.: __6,7,8__ Page __16_ of _17_

Event

Description:

Loss of 345 kV line. Failure of diesel generator #2 to reach rated speed, so breaker does not automatically close, causing a station blackout.

Time Position Applicants Actions or Behavior ATCO Verify normal containment conditions: no unexpected rise in sump level; no containment area radiation monitor alarms; RM-051, RM-052, and RM-062 not in alarm; no steam generator blowdown or condenser off gas radiation monitors in alarm or trending upward; containment pressure less than 3 psig; and containment temperature less than 120°F. (EOP-00, Step 15)

CRS Determine that EOP-07 should be implemented per EOP-00 Section 6.0 (EOP-00, Step 16)

CRS Enter EOP-07, STATION BLACKOUT CRS Confirm SPTAs performed (EOP-07, Step 1)

CRS Confirm SBO diagnosis by verifying safety function status check (EOP-07, Step 2)

CRS Implement the Emergency Plan (EOP-07, Step 3)

ATCO/BOPO Monitor the Floating Steps (EOP-07, Step 4)

BOPO If condenser vacuum less than 19 inches Hg, ensure steam dump and bypass valves and turbine stop valves are closed. (EOP-07, Step 5)

BOPO If feeding through Feed Rings, verify S/G levels 35-85% NR (EOP-07, Step 6) OR BOPO (CT) restore AFW flow using either FW-54 or FW-10 to SG RC-2A prior to reaching 27% wide range level.

(CT)

If feeding through AFW nozzles, maintain S/G level 35-85% NR by ensuring FW-10 operating, both AFW isolation valves, HCV-1107A and HCV-1108A are open, and locally throttle both AFW isolation valves HCV-1107B and HCV-1108B. (EOP-07, Step 6.1)

Note: These actions and the action to open HCV-1108A may already have been completed in EOP-00.

BOPO Maintain S/G pressure 850-1000 psia by performing EOP-07, Step 7.a, or c (Step B has local operator actions)

BOPO Steam S/Gs by ensuring MS-164 Main Steam Line A Steam Dump to Atmosphere Isolation Valve is open (local action), ensure MS-407, nd Atmospheric Dump Valve HCV-1040 2 Isolation is open (local action), and control HCV-1040, Atmospheric Dump Valve. (EOP-07, Step 7.a) OR BOPO Operate FW-10, Steam AFW pump (EOP-07, Step 7.c)

Event description continues on next page.

Op-Test No.: _____ Scenario No.: _1__ Event No.: __6,7,8__ Page __18_ of _17_

Event

Description:

Loss of 345 kV line. Failure of diesel generator #2 to reach rated speed, so breaker does not automatically close, causing a station blackout.

Time Position Applicants Actions or Behavior BOPO Trip all of the following normal and standby supply feeder breakers to the vital 4160V buses: 1A13, 1A33, 1A24, 1A44. (EOP-07, Step 8)

BOPO Ensure all the following breakers tripped: CW-1C (circ water pump), FW-5C (heater drain pump), FW-2C (condensate pump), FW-6 (electric AFW pump), FW-4C (feed pump), RC-3C (RCP), RC-3D (RCP), AC-10A/B/C/D (raw water pumps), SI-1A/B (LPSI pumps) (EOP-07, Step 9)

BOPO Verify both diesels started. (Maintenance on DG#1 will preclude emergency start) (EOP-07, Step 10)

BOPO If D-2 is operating and none of the following lockout relays are tripped: 86/1A24, 86/1A44, 86/1A4-TFB, then synchronize and close (CT) breaker 1AD2 (EOP-07, Step 12)

CRS Direct exit from EOP-07 and entry into EOP-02, LOSS OF OFF-SITE POWER/LOSS OF FORCED CIRCULATION (EOP-07, Step 13)

Scenario is terminated after successful transition from EOP-07 is made.

Page 17 of 17 Procedure Number Procedure Title Revision OP-4 LOAD CHANGE AND NORMAL POWER OPERATION 48 OI-RC-7 REACTOR COOLANT SYSTEM PRESSURE CONTROL 17 NORMAL OPERATION OI-CH-4 CHEMICAL AND VOLUME CONTROL SYSTEM MAKEUP 45 OPERATIONS OI-RR-1 REACTOR REGULATING SYSTEM NORMAL OPERATION 29 ARP-CB-1,2,3/A2 38 OI-CH-1 CHEMICAL AND VOLUME CONTROL SYSTEM NORMAL 88 OPERATION ARP-CB-1,2,3/A4 30 OI-RC-6 PRESSURIZER QUENCH TANK NORMAL OPERATION 12 ARP-AI-30B/A34-1 25 AOP-23 RESET OF ENGINEERED SAFEGUARDS 9 ARP-CB-20/A15 40 AOP-31 161 KV GRID MALFUNCTIONS 11 EOP-00 STANDARD POST TRIP ACTIONS 29 EOP/AOP ATTACHMENTS 32 EOP-07 STATION BLACKOUT 14

Scenario # 1 Malfunction List - Rev1 Event # Description Type System Command Severity Ramp 1 Power Reduction normal 2 PIC 244 Fails BIST CVC CVC_PIC244_C TRUE 3 Quench tank drain Op WDL Operator Mode down action open HCV-153 4 Inadvertent VIAS MALF ESF ESF18 TRIP 5 Loss of 161 KV MALF SWD SWD02 TRUE 6 Loss of 345 KV MALF SWD SWD01 TRUE 7 HCV-1108A failed VLV AFW FWC_HCV1108A 0%

closed (Preset) 8 DG-2 breaker does Run governor down until 500 RPM light.

not close (Preset) Replace bulb with burned out bulb

Appendix D Scenario Outline Form ES-D-1 Facility: _ Fort Calhoun Station__ Scenario No.: __2____ Revision __1__ Op-Test No.: _______

Examiners: ____________________________ Operators: _____________________________

Initial Conditions: 100% power. Condensate pump FW-2B is currently in service ____________

Turnover: ____. Rotate condensate pumps FW-2B and FW-2C._____________________________

Event Malf. Event Event No. No. Type* Description 1 N/A N-BOPO Rotate condensate pumps FW-2B and FW-2C per OI-FW-1 Attachment 4.

2 C-ATCO Charging pump CH1B trips. Alarm CB-1,2,3/A2, Window A-6L.

TS-CRS This isolates letdown. Another charging pump should be started per OI-CH-1. T.S. 2.15(5) applies because it requires CH-1B and other instruments for AI-179 (Alt shutdown panel)

I-BOPO 3 LT-903Y (Steam generator RC-1 level transmitter) degrades over a 10 minute period until it fails. This will shift FWCS to manual at the last good signal, requiring operator action to restore level. Alarm is ARP-DCS-FW, L0903E_AL5.

4 I-ATCO TS-CRS Pressurizer pressure instrument fails high. Possible TS 2.10.4(5) if pressure falls below 2075 psia. Uses ARP-CB-1,2,3/A4 Window B-4 Pressurizer Pressure Deviation C-ATCO 5 C-BOPO Dropped CEA 4-01. Alarm CB-4/A8 Window A-5L. This will send TS-CRS the operators to AOP-02, which has actions to stabilize the plant.

TS 2.10.2(4)(e)Section III applies because the rod is dropped, this will require a rapid down-power per AOP-05.

R-ATCO 6 N/A N-BOPO Rapid down-power per AOP-05.

M-All 7 RCP Seal Cooler Leak of CVC16. Due to high RCP temperatures, AOP-35 will be entered. AOP-35 will direct the operators to trip the reactor and enter EOP-00. This is an intersystem LOCA. EOP-03 will be entered after SPTAs are performed.

TS 2.1.4(3) applies but is not counted because it is part of the major event and per the NUREG may be over-shadowed by it.

8 C-BOPO Turbine fails to trip. Critical task is for BOP to immediately trip the (CT) turbine before performing other SPTAs 9 C-ATCO HCV-438C fails to close on demand. This LOCA cannot be C-BOPO isolated. It will require a cooldown and depressurization to stop the LOCA. Critical task is to lower RCS pressure before attempting to (CT) locally close HCV-438C.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 1 of 16

Scenario Event Description NRC Scenario #2 SCENARIO

SUMMARY

NRC #2 The crew will assume the watch at 100% power with no equipment out of service and instructions to swap condensate pumps FW-2B and FW-2C.

The first event is swapping out the two condensate pumps per OI-FW-1, CONDENSATE SYSTEM NORMAL OPERATION, Attachment 4.

The next event is a trip of charging pump CH-1B, which secures charging flow. Operator actions are per ARP-CB-1,2,3/A2 and include securing letdown. Operator action is then to restore charging and letdown per OI-CH-1, CHEMICAL AND VOLUME CONTROL SYSTEM NORMAL OPERATION. SRO will refer to the Technical Specification. T.S. 2.15(5) applies for the loss of CH-1B.

The next event is a degradation of LT-903Y to 40% over a 10 minute period before failing low, resulting in an incorrect setting on the feedwater digital control system. Operator actions are per ARP-DCS-FW, L0903E_AL5 and include the operator taking manual control of the main feed regulating valve to restore steam generator levels to program.

The next event is the controlling pressurizer pressure instrument, PT-103X failing high.

Operator actions are per ARP-CB-1,2,3/A4 and include taking the controller to manual to maintain pressurizer pressure, and shifting pressure control to PC-103Y. SRO will refer to Technical Specifications. T.S. 2.10.4(5)(a)(ii) applies if pressure falls below 2075 psia.

The next event is a CEA drop of CEA 4-01. Operator actions are per ARP-CB-4/A8 and AOP-02, CEA AND CONTROL SYSTEM MALFUNCTIONS and include stabilizing the plant and taking action to lower reactor power to less than or equal to 70% T within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per AOP-5, EMERGENCY SHUTDOWN. SRO will refer to Technical Specifications. T.S. 2.10.2(4)(e) applies.

Once actions have been taken to start lowering reactor power to less than 70%, a 100%

severity RCP seal cooler leak on CVC 16 will be cued. Operator actions are from ARP-CB-1,2,3/A1 and AOP-35, REACTOR COOLANT PUMP MALFUNCTIONS. At this time one of the bearing temperatures will exceed the trip criteria for the RCP. Operators will manually trip the reactor and enter EOP-00. They will also trip the RCP whose trip criteria was exceeded (RCP 3A).

When the operators manually trip the reactor, the turbine will fail to trip and the operators will take action to manually trip the turbine (critical task). After actions of EOP-00 are complete, the SRO will direct entry into EOP-03 for a loss of coolant accident.

When operators attempt to isolate the leak by closing HCV-438C, it fails to close. Operators must commence a cooldown and depressurization prior to sending a local operator to close this valve (critical task). TS 2.1.4(3) applies but is not counted because it is part of the major event and per the NUREG may be over-shadowed by it.

The scenario can be terminated once actions have begun to cooldown and depressurize the RCS to allow local operator action to close HCV-438C.

Page 2 of 16

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __2___ Event No.: __1___ Page _3__ of _16__

Event

Description:

___Rotate condensate pumps FW-2B and FW-2C.________________

Time Position Applicants Actions or Behavior BOPO Review OI-FW-1, CONDENSATE SYSTEM NORMAL OPERATION, Attachment 4, Rotating Condensate Pumps prerequisites.

BOPO Select condensate pump to be started (in this case, FW-2C). (OI-FW-1, Att. 4, Step 1)

BOPO Suspend GARDEL data feed IAW OI-ERFCS-2, CORE MONITORING SYSTEMS, Att. 6, Suspending GARDEL Data Feed (Step 2) NOTE:

GARDEL is NOT modeled in the simulator, so these steps will not be performed.

If asked, the booth/lead examiner reports back to the crew as STA that Gardel is suspended.

BOPO Review CAUTIONS.

BOPO Perform the following: ensure 43/FW switch in off and verify 43/FW Transfer Switch Off-Auto (CB-10,11/A10, B-6L) is in alarm. (Step 3)

BOPO Review NOTE.

BOPO Start condensate pump FW-2C. (Step 4)

BOPO Verify ammeter returns to less than 250 amps in less than 15 seconds and stabilizes (Step 5)

BOPO Ensure condensate pump minimum flow maintained by verifying discharge pressure 490-600 psig. If recirculation valve FCV-1172 is not operating properly, then establish minimum flow by opening FCV-1172 bypass valve, FW-273 (Step 6) Note: These are local valves.

BOPO Monitor FW-2C for any the following: unusual noise or vibration, lube oil level, seal water inlet pressure (70-90 psig on PI-1214), FW-2C discharge pressure (490-600 psig on PI-1232C at pump), FW-2C discharge pressure (490-600 psig on PI-1181C in CR), check ERF computer points.

ERF points are F1172, T1179A, T1179B, T1184C, T1185C. (Step 7)

Note: Bold values are local operator cued values (local parameters).

BOPO Stop FW-2B (Step 8)

BOPO Review NOTE.

BOPO Place FW-2B in AFTER-STOP or PULL-STOP (Step 9) (optional)

BOPO Verify FW-2B ammeter drops to zero (Step 10)

Event description continues on next page.

Op-Test No.: _____ Scenario No.: __2___ Event No.: __1___ Page _4__ of __16_

Event

Description:

___Rotate condensate pumps FW-2B and FW-2C.________________

Time Position Applicants Actions or Behavior BOPO Observe check valve closure by verifying FW-2B not rotating in reverse direction (Step 11) - a local operator action.

BOPO Ensure Post-SIAS/CSAS running condensate pump switch 43-SIAS/FW2 is positioned to FW-2C. (Step 12)

BOPO Place 43/FW Switch in AUTO and verify alarm clears (Step 13)

BOPO Restore GARDEL data feed IAW OI-ERFCS-2, Attachment 7, Restoring the GARDEL Data Feed (Step 14) NOTE: GARDEL not modeled in simulator, so these steps will not be performed.

If asked, the booth/lead examiner reports back to the crew as STA that Gardel is restored.

Lead examiner cues the next malfunction at his/her discretion.

Booth should also enter the Event 3 malfunction at this time (LT-903Y degrades to 40% over 10 minute period before failing low)

Op-Test No.: _____ Scenario No.: __2___ Event No.: __2___ Page __5_ of _16__

Event

Description:

Charging pump CH-1B trips.

Time Position Applicants Actions or Behavior ATCO Respond to alarm CB-1,2,3/A2 Window A-6L, CHARGING FLOW LO, and Window C-6U, CHARGING PUMPS TRIP ATCO Enter ARP CB-1,2,3/A2, Window A-6L ATCO Check charging header flow on FIA-236 (ARP-CB-1,2,3/A2, A-6L, Step 1)

ATCO If charging flow lost, then isolate letdown by closing TCV-202 and HCV-204 (Step 2)

ATCO If charging flow is less than 30 gpm, then check charging pump operation, valve alignment, pipe break, and charging pump discharge or suction relief valve. (Step 3)

Note: If called, booth role-plays that the CH-1B breaker has an overcurrent trip.

ATCO Rotate charging pumps per OI-CH-1, CHEMICAL AND VOLUME CONTROL SYSTEM NORMAL OPERATION, Att. 1, Startup of Charging and Letdown (Step 4)

ATCO Crew may decide to put CH-1B in Pull-to-lock.

ATCO Review prerequisites for restoring charging at letdown (OI-CH-1, Att. 1)

CRS Enter TS 2.15(5) for loss of CH-1B and controls for AI-185 Restore in 7 days or be in hot shutdown within next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

CRS Ensure compliance with SO-O-23, SYSTEMS AND EQUIPMENT USAGE DATA. (ARP-CB-1,2,3/A2, A6L, Step 7)

Lead examiner cues the next malfunction at his/her discretion.

Op-Test No.: _____ Scenario No.: __2___ Event No.: __3___ Page _6__ of _16__

Event

Description:

___LT-903Y degrades to 40% over 10 minute period before failing low. This malfunction should be entered with the charging pump trip.

Time Position Applicants Actions or Behavior BOPO Respond to alarm DCS-FW, L0903E_AL5 and H1105_AL1 BOPO Enter ARP-DCS-FW, L0903E_AL5 or FWR-CTL-XX-BD, LY903_BD.

BOPO Ensure FWCS IN MANUAL is displayed for bad channel on feedwater regulating system display (Step 2)

BOPO Control steam generator level by either selecting OUT (ie bypassing) on level controller LC0903_1E and adjusting as necessary to control feed reg or bypass valves to maintain levels, OR take manual control of feed reg or bypass valves and adjust as necessary to maintain steam generator levels (Step 4).

BOPO Dispatch operator to verify level indication at AI-179. Level indication at AI-179 is not affected by this failure. (Step 6)

CRS Reference TDB-VIII, EQUIPMENT OPERABILITY GUIDANCE. (Step 7)

BOPO Notify system engineer and I&C of alarm condition. (Step 8)

Lead examiner cues the next malfunction at his/her discretion.

Op-Test No.: _____ Scenario No.: _2__ Event No.: __4__ Page _7__ of __16_

Event

Description:

Controlling pressurizer pressure instrument, PT 103X fails high.

Time Position Applicants Actions or Behavior ATCO Respond to alarm CB-1,2,3/A4 Window A-4 PRESSURIZER PRESSURE OFF NORMAL HI-LO CHANNEL X.

ATCO Enter ARP-CB-1,2,3/A4 Window A-4.

CRS Apply T.S. 2.10.4(5)(a)(ii) if pressure is less than or equal to 2075 psia.

(Step 2.1)

ATCO Check pressurizer heaters are energized. (Step 2.2)

ATCO Ensure pressurizer spray valves are closed. (Step 2.3)

ATCO Ensure pressurizer heater control switches are in AUTO (Step 2.4)

ATCO Check pressurizer level for decreasing trend (Step 2.5)

ATCO Check VCT level for level trend (Step 2.6)

ATCO Monitor pressurizer pressure and the operation of PC-103X. (Step 4)

ATCO If PC-103X is not controlling pressure, shift pressure control to PC-103Y (Step 4.1)

ATCO If necessary, take manual control of pressurizer pressure. (Step 4.2)

TS-CRS Possible technical specification call depending on how low pressurizer pressure falls before ATCO takes action. TS 2.10.4(5)(a)(ii) if pressure falls below 2075 psia.

CRS Notify Work Week manager of failure.

Lead examiner cues the next malfunction at his/her discretion.

Op-Test No.: _____ Scenario No.: _2__ Event No.: __5, 6__ Page _8__ of _16__

Event

Description:

CEA 4-01 drop, requiring a rapid downpower using AOP-05.

Time Position Applicants Actions or Behavior ATCO Respond to alarm CB-4/A8, Window A-5L, DROPPED ROD, Window B-1U, ROD POSITION DEVIATION LOW LIMIT, Window B-1L, ROD POSITION DEVIATION LOW-LOW LIMIT, and CB-4/A20, Window B-6, ROD DROP NUCLEAR INSTRUMENTATION CHANNEL ATCO Enter ARP-CB-4/A8, Window A-5L.

ATCO Verify at least one CEA is at Lower Mechanical Stop with green rod position indicator light on. (ARP-CB-4/A8, Window A-5L, Step 1)

TS-CRS Possible momentary entry into TS 2.10.4(5)(a)(ii) for pressurizer pressure less than 2075 psia.

CRS Enter AOP-02, CEA AND CONTROL SYSTEM MALFUNCTIONS,Section III, Misaligned Group 4 CEA (ARP-CB-4/A8, Window A-5L, Step 2)

CRS Review cautions, prerequisites and notes of AOP-02.

BOPO Adjust turbine load to match reactor power (AOP-02,Section III, Step 3)

ATCO Establish steady reactor power (AOP-02,Section III, Step 4)

ATCO Ensure RCS pressure is 2075 to 2150 psia (AOP-02,Section III, Step 5)

ATCO Ensure PZR level is within 2% of program level (AOP-02,Section III, Step 6)

ATCO Reset rod drop detection circuit bistables on all RPS linear power channels and power range control channels drawers (AOP-02,Section III, Step 7)

ATCO Verify ROD DROP NUCLEAR INSTRUMENTATION CHANNEL alarm resets on CB-4, A20 (AOP-02,Section III, Step 8)

CRS Notify system operations of power reduction (AOP-02,Section III, Step 9)

CRS Notify reactor engineer of CEA misalignment (AOP-02,Section III, Step 10)

CRS If CEA misaligned greater than 18 inches, go to Step 20 (AOP-02, Step 11)

ATCO Lower reactor power to less than or equal to 70% T power within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of misalignment using boration from the SIRWT per AOP-05, EMERGENCY SHUTDOWN (AOP-02,Section III, Step 20)

CRS Enters AOP-05 ATCO Ensure one charging pump is running (AOP-05, Step 1.a)

Event description continued on next page

Op-Test No.: _____ Scenario No.: _2__ Event No.: __5, 6__ Page _9__ of __16_

Event

Description:

CEA 4-01 drop, requiring a rapid downpower using AOP-05.

Time Position Applicants Actions or Behavior ATCO Open LCV-218-3, Charging Pump Suction SIRWT Isolation Valve (AOP-05, Step 1.b)

ATCO Close LCV-218-2, VCT Outlet Valve (AOP-05, Step 1.c)

BOPO Maintain RCS TC by adjusting turbine load as necessary. (AOP-05 Step 3)

ATCO/BOPO Maintain both of the following primary plant parameters during the power reduction: TC 527-545°F and PZR 45-60%. (AOP-05, Step 4)

ATCO Maximize pressurizer heaters and spray (AOP-05, Step 5)

CRS Direct shift chemist to sample the RCS to satisfy TS 3.2, Equipment and Sampling Tests (AOP-02,Section III, Step 21)

CRS Enter TS 2.10.2(4)(e) for a full length CEA misaligned greater than 18 inches.

Must reduce power less than 70% within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , then within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after that, realign CEA or declare CEA inoperable.

Once applicants have commenced the rapid down-power and reactor effects have been noted, the lead examiner cues the next malfunction at his/her discretion.

Op-Test No.: _____ Scenario No.: _2__ Event No.: _7, 8__ Page _10__ of _16_

Event

Description:

100% severity RCP Seal Cooler Leak on CVC 16.

Time Position Applicants Actions or Behavior ATCO Respond to alarm CB-1,2,3/A1 Window A5U, CC WATER FROM RC-3A SEAL COOLER TEMP HI ATCO Enter ARP-CB-1,2,3/A1 Window A5U.

ATCO If alarm is not due to operation of selector switches, then check TI-458/465, CCW temperature from RC-3A seal cooler greater than 120 degrees (Step 1)

ATCO If CCW temperature is high, then raise flow through RC-3A seal cooler with HCV-442, RC-3A pump seal cir AC outlet. (Step 2)

ATCO Monitor CCW flow from RC-3A seal cooler (Step 2.1)

ATCO Monitor RC-3A parameters on ERF display 440. (Step 2.2)

ATCO ARP-CB-1,2,3/A1 Window A5U CAUTION: RCP operation must be terminated if CCW flow is not re-established within 5 minutes OR high temperature alarms are received on RCP lube oil coolers, RCP seal bleed-off or CEDM seals.

CRS Direct entry into AOP-35 for RCP malfunctions.

CRS Enter Section I if lower seal temperature exceeds 200 degrees. Enter Section II if motor radial or thrust bearing temperatures exceed 203 degrees (actions are the same).

CRS Direct ATCO to manually trip the reactor and enter EOP-00, STANDARD POST TRIP ACTIONS ATCO Trip the reactor (Step 1.1.a)

ATCO Perform SPTAs per EOP-00. (Step 1.1.b)

BOPO ATCO Stop RCP-3A. (AOP-35 Step 1.1.c)

Event description continues on next page.

Op-Test No.: _____ Scenario No.: _2__ Event No.: __7,8__ Page _11__ of _16_

Event

Description:

__100% severity RCP Seal Cooler Leak on CVC 16. Turbine fails to trip on reactor trip. The malfunction is preprogrammed and will occur when the ATCO manually trips the reactor.

Time Position Applicants Actions or Behavior ATCO Verify reactivity control is established by verifying reactor power lowering, startup rate is negative, no more than one regulating or shutdown CEA not inserted, and monitor for an uncontrolled RCS cooldown (EOP-00, Step 1)

Note: the crew may emergency borate because they think that they have an uncontrolled cooldown but it is really because of the crews delay in tripping the turbine in the next step below this one.

BOPO Verify turbine tripped as indicated by stop and intercept valves indicating closed. (EOP-00, Step 2)

BOPO Trip the turbine on CB-10,11. (Step 2.1.a) OR Stop EHC pumps by placing both EHC-3A and EHC-3B in pull-to-lock.

(CT)

Critical task is to perform these actions before performing any other actions.

BOPO Ensure generator output breaker 3451-4, generator output break 3451-5, and generator field breaker 41E/G1F are tripped (EOP-00, Step 3)

BOPO Verify buses 1A3 and 1A4 are energized (EOP-00, Step 4)

BOPO If SIAS has occurred, then ensure both diesel generators have started (EOP-00, Step 5)

BOPO Check that buses 1A1 and 1A2 are energized (EOP-00, Step 6)

BOPO Check that 125 VDC buses 1 and 2 are energized (EOP-00, Step 7)

BOPO Verify instrument air available: instrument air pressure greater than or equal to 90 psig and at least one air compressor operating (EOP-00, Step 8)

ATCO Determine normal CCW system operation: ensure at least one CCW pump operating, CCW pump discharge pressure greater than or equal to 60 psig, at least one RW pump operating, and if CCW pump discharge pressur greater than or equal to 50 psig, ensure RCP coolers CCW valves HCV-438A/B/C/D are open (EOP-00, Step 9)

ATCO Verify RCS inventory control: PZR level 30-70%, PZR level trending to 45-60%, and RCS subcooling greater than or equal to 20°F (EOP-00, Step 10). Transition to contingency action.

ATCO Restore inventory control, manually control charging and letdown to restore pressurizer level (EOP-00, Step 10.1.a)

Event description continued on next page

Op-Test No.: _____ Scenario No.: _2__ Event No.: __7, 8__ Page _12__ of _16_

Event

Description:

100% severity RCP Seal Cooler Leak on CVC 16 (contd)

Time Position Applicants Actions or Behavior ATCO If HPSI stop and throttle criteria (RCS subcooling greater than or equal to 20°F, PZR level greater than or equal to 10% and not lowering, at least one steam generator available for heat removal, and RVLMS indicates level is at or above top of the hot leg), then throttle and stop any or all HPSI pumps (EOP-00, Step 10.1.b)

ATCO Verify RCS Pressure Control: RCS pressure 1800-2300 psia, trending to 2050-2150 psia, and PORVs are closed (EOP-00, Step 11). Transition to contingency.

ATCO If RCS pressure less than 1350 psia, trip one RCP in each loop (EOP-00, Step 11.2)

ATCO If RCS pressure less than or equal to 1600 psia, verify engineered safeguards actuated: emergency boration in progress, SI flow acceptable per Attachment 3, VIAS has actuated (86A/VIAS, 86B1/VIAS, 86B/VIAS, 86A1/VIAS are all tripped), and CIAS has actuated (86A/CIAS, 86B1/CIAS, 86B/CIAS, 86A1/CIAS) (EOP-00, Step 11.3)

ATCO If RCS pressure control not established, manually control PZR heaters and spray to restore pressure (EOP-00, Step 11.4)

ATCO Verify core heat removal via forced circulation by all of the following:

(EOP-00, Step 12)

RCP NPSH requirements are satisfied per Att. 2 At least one RCP is operating Core T is less than or equal to 10°F Note: Due to the seal cooler leak, eventually all 4 RCP's will require stopping and at that point, the ATCO should verify development of natural circulation.

BOPO Verify Main Feedwater is restoring level in at least one steam generator to 35-85% NR by performing the following: (EOP-00, Step 13)

BOPO Ensure both feed reg valves, FCV-1101 and FCV-1102, have ramped closed (EOP-00, Step 13.a)

BOPO Ensure both feed reg bypass valves, HCV-1105 and HCV-1106, have ramped to 40-45% (EOP-00, Step 13.b)

BOPO Place the 43/FW switch in OFF (EOP-00, Step 13.c)

BOPO Ensure no more than one feed pump operating (EOP-00, Step 13.d)

BOPO Ensure no more than one condensate pump is operating (EOP-00, Step 13.e)

Event description continues on next page

Op-Test No.: _____ Scenario No.: _2__ Event No.: __7, 8__ Page _13__ of _16_

Event

Description:

100% severity RCP Seal Cooler Leak on CVC 16 (contd).

Time Position Applicants Actions or Behavior BOPO Stop all operating heater drain pumps, FW-5A/B/C (EOP-00, Step 13.f)

BOPO Ensure both sets of steam generator blowdown isolation valves, HCV-1387A/B and HCV-1388A/B, are closed (EOP-00, Step 13.g)

BOPO Verify steam dump and bypass valves are controlling both RCS TC 525-535°F and S/G pressure 850-925 psia (EOP-00, Step 14)

Note: The validation crew thought they had a problem with PCV-910 being stuck open when actually the big cooldown was caused by their delay in tripping the turbine approx 10 seconds.

ATCO Verify normal containment conditions: no unexpected rise in sump level, no containment area alarms, RM-051, 052, and 062 not in alarm, RM-054A/B and RM-057 not in alarm or trending upward, containment pressure less than 3.0 psig and containment temperature less than 120°F(EOP-00, Step 15)

CRS Determine appropriate procedure to implement per Section 6, Diagnostic Actions(EOP-00, Step 16)

CRS Direct entry into EOP-03, LOSS OF COOLANT ACCIDENT CRS Confirm SPTAs performed (EOP-03, Step 1)

CRS Confirm diagnosis of LOCA by: verify safety function status check acceptance criteria satisfied and direct shift chemist to perform rapid activity analysis of both steam generators (EOP-03, Step 2)

Note: Eventually, all four reactor coolant pumps will have to be tripped due to temp issues. RC-3B should be the last one tripped due to its different design from the others.

CRS Implement the emergency plan (EOP-03, Step 3)

ATCO/BOPO Monitor the floating steps (EOP-03, Step 4)

ATCO If RCS pressure is less than or equal to 1600 psia, verify engineered safeguards actuated: emergency boration in progress, SI flow acceptable per Attachment 3 (EOP-03, Step 6)

ATCO If SIAS has actuated, then maximize SI and charging flow to RCS by operating all of the following pumps: HPSI pumps, SI-2A/B or SI-2B/C, LPSI pumps, SI-1A/B, and charging pumps CH-1A/C (EOP-03, Step 8)

Event description continues on next page.

Op-Test No.: _____ Scenario No.: _2__ Event No.: __7,9__ Page _14__ of _16 Event

Description:

100% severity RCP Seal Cooler Leak on CVC 16. RCP seal cooler CCW isolation valve HCV-438C fails to close on demand.

Time Position Applicants Actions or Behavior ATCO Verify RCP operating parameters: if TC less than 500°F, ensure at least one RCP stopped; if RCS pressure less than 1350 psia following SIAS actuation, ensure no more than 1 RCP running in each loop (EOP-03, Step 9)

CRS Record time of SIAS initiation (EOP-03, Step 10)

ATCO Verify normal CCW/RW system operation by performing the following:

(EOP-03, Step 11).

Note the validation crew deviated from the procedure on this step.

ATCO Ensure at least two CCW pumps operating (EOP-03, Step 11.a)

Note: Only 1 pump is operating.

ATCO Verify CCW pump discharge pressure greater than or equal to 60 psig (EOP-03, Step 11.b)

ATCO Ensure at least two raw water pumps operating (EOP-03, Step 11.c)

Note: Only 1 pump is operating ATCO Ensure at least three CCW heat exchangers in service (EOP-03, Step 11.d)

Note: Only one HX is in service.

ATCO Ensure all RCP Coolers CCW valves, HCV-438A/B/C/D are open (EOP-03, Step 11.e)

ATCO Verify PORVs and PZR code safety valves are closed by performing the following: (EOP-03, Step 12)

ATCO Check that all PZR quench tank alarms are clear (QUENCH TANK TEMP HI, QUENCH TANK PRESS HI, AND QUENCH TANK LEVEL HI-LO) (EOP-03, Step 12.a)

ATCO Check all relief header temperature alarms are clear (PRESSURIZER PWR OPERATED RELIEF VALVE DISCH TEMP HI, PRESSURIZER SAFETY VALVE RC-141 DISCH TEMP HI, PRESSURIZER SAFETY VALVE RC-142 DISCH TEMP HI) (EOP-03, Step 12.b)

ATCO Check both relief header acoustic flow alarms are clear (RC-142/PCV-102-1 VALVE FLOW and RC-141/PCV-102-2 VALVE FLOW) (EOP-03, Step 12.c)

Event description continues on next page.

Op-Test No.: _____ Scenario No.: _2__ Event No.: __7,9__ Page _15__ of _16_

Event

Description:

100% severity RCP Seal Cooler Leak on CVC 16. RCP seal cooler CCW isolation valve HCV-438C fails to close on demand.

Time Position Applicants Actions or Behavior ATCO If an RCS to CCW leak is evident, then minimize RCS leakage by performing the following: (EOP-03, Step 13)

ATCO Trip all RCPs (EOP-03, Step 13.a)

ATCO Close all RCP coolers CCW valves, HCV-438A/B/C/D (EOP-03, Step 13.b)

Note: HCV-438C fails to close on demand from control room.

CRS Transition to contingency action (EOP-03, Step 13.b.1)

ATCO/BOPO Lower RCS pressure less than 380 psia (EOP-03, Step 13.b.1). Critical task is to lower RCS pressure before attempting to locally manually close (CT) HCV-438C.

Note: TS 2.1.4(3) applies for RCS leakage limits but is not counted in this scenario because it is part of the major event and per the NUREG may be over-shadowed by it.

Lead examiner can end scenario after the cooldown/depressurization is in progress at his/her discretion.

Page 16 of 16 Procedure Number Procedure Title Revision OI-FW-1 CONDENSATE SYSTEM NORMAL OPERATION 60 ARP-CB-1,2,3/A2 38 OI-CH-1 CHEMICAL AND VOLUME CONTROL SYSTEM NORMAL 88 OPERATION SO-O-23 SYSTEMS AND EQUIPMENT USAGE DATA 21 ARP-DCS-FW 3 ARP-CB-1,2,3/A4 30 ARP-CB-4/A8 24 AOP-02 CEA AND CONTROL SYSTEM MALFUNCTIONS 8 AOP-05 EMERGENCY SHUTDOWN 11 ARP-CB-1,2,3/A1 34 AOP-35 REACTOR COOLANT PUMP MALFUNCTIONS 5 EOP-00 STANDARD POST TRIP ACTIONS 29 EOP-03 LOSS OF COOLANT ACCIDENT 36

Scenario # 2 Malfunction List Event # Description Type System Command Severity Ramp 1 Rotate Normal Condensate Pumps 2 CH-1B Trips MALF CVC BUS_1B4C_6_BKR_TRIP TRUE 3 LT-903Y Fails TRAN FWC SGN_LT903Y 40% 10 min 4 Pressure TRANS RRS RCS_PT103X 100% 2 min Transmitter fails high 5 Dropped rod MALF CRD ROD_PWR_401_1 DEENERGIZED 6 AOP-05 Power Normal Reduction 7 RCP Seal Cooler MALF RCP CVC28 25%

Leak 8 Turbine Fails to Preset Engineering Mode Trip (preset) Freeze Flags 9 HCV-438C fails VLV CCW CCW_HCV438C 100%

open (preset)

Appendix D Scenario Outline Form ES-D-1 Facility: _Fort Calhoun Station__ Scenario No.: ___3____ Revision __1__ Op-Test No.: _______

Examiners: ____________________________ Operators: _____________________________

Initial Conditions: _Reactor is currently at approximately 90% power. I&C is currently troubleshooting the power range NI power supply. Technical Specification 2.15(1) was entered at 0428 today. Trip units 1, 2, 9, 10, and 12 are currently in BYPASS for channel A.

Turnover: ___The plant entered TS 2.0.1 due to a condition affecting both diesel generators. A plant shutdown was initiated. After power had been reduced to 90%, the condition was resolved and TS 2.0.1 was exited. You have been directed to maintain power at 90% until the Reactor Engineer prepares PAPeRS guidance for power ascension back to 100% power.____________________

Event Malf. Event Event No. No. Type* Description R-ATCO 1 N-BOPO Maintain power at 90%.

C-BOPO 2 Instrument Air Compressor CA-1C fails. Standby compressor CA-1B running but not loaded. Alarm is ARP-CB-10,11/A11 Window B-3L. No entry into AOP-17.

TS-CRS 3 I-ATCO Channel B power range NI summing amplifier fails low. T.S.

2.15(1) was already entered due to bypassed trip units 1, 2, 9, 10, 12 and these must be placed in trip per T.S. 2.15(2). Also, per T.S.

Table 2-2 note C, power must be reduced to less than 70%. AOP-15.

C-BOPO 4 Heater Drain Pump FW-5B trips, standby fails to autostart. Alarm is ARP-CB-10,11/A12 Window A-4L. Actions are required to start the standby pump.

TS-CRS 5 RCS oxygen levels are greater than 0.20 ppm, causing entry into T.S. 2.1.5(1).

C-ATCO 6 Raw water pump AC-10D trips, standby fails to autostart. Alarm is ARP-CB-1,2,3/A1 Window D1U. Also, alarms CB-1,2,3/A1 C1U and C1L will come in shortly after pump trip.

C-BOPO 7 Loss of MCC 3C2 due to a ground fault. This causes a loss of boric acid pump CH-4A, boric acid gravity feed line valve HCV-265, and boric acid pumps discharge valve HCV-268. Alarm: CB-4/A7 Boric Acid Valves Trouble. AOP-32 M-ALL 8 (CT) ATWS - RPS pressurizer pressure channel D/PIA-102Y fails low, causing 2 out of 3 for TM/LP but no RPS trip. Critical task is for ATCO to manually trip the reactor before performing any other actions.

Page 1 of 18

C-ATCO 9 (CT) Following manual trip, 5 control rods fail to insert. This will require emergency boration. However, HCV-258 is mechanically bound when the operators attempt to open it. This results in the inability to emergency borate using the BASTs and requires use of the SIRWT to emergency borate. EOP-20. Critical task is to open LCV-218-3, Charging pump suction SIRWT isol. Valve, close LCV-218-2, VCT Outlet valve, and starting all charging pumps prior to exiting that safety function success path.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 2 of 18

Scenario Event Description NRC Scenario #3 SCENARIO

SUMMARY

NRC #3 The crew assumes the watch with the reactor at 90% power. Trip units 1, 2, 9, 10, and 12 for channel A are in BYPASS due to troubleshooting efforts. The crew instructions are to maintain power at 90%.

The first event is a trip of instrument air compressor CA-1C. The standby is running but unloaded. Operator actions are per ARP-CB-10,11/A7 and include starting the CS air compressor.

The next event is a failure of the B channel power range NI summing amplifier. Operator action is to place the channel in the tripped position within one hour and downpower to less than 70%

per T.S. 2.15(2) and Table 2-2 Note C. SRO will refer to Technical Specifications. T.S. 2.15(2) applies as does Note C of Table 2-2.

The next event is a trip of heater drain pump FW-5B. Backup heater drain pump will not start automatically. Operator will need to start the backup pump.

The next event is a high oxygen concentration in the RCS of 0.20 ppm, which is called in by chemistry. No operator action. SRO will refer to Technical Specifications. T.S. 2.1.5(1) applies.

The next event is a trip of raw water pump AC-10D. Backup raw water pump will not start automatically. Operator will need to start backup pump.

The next event is a loss of MCC 3C2 due to a ground fault. Operator action is per ARP-CB-4/A7 and AOP-32, LOSS OF 4160 VOLT OR 480 VOLT BUS POWER and includes operating the primary water booster pump and steam generator blowdown transfer pump as necessary.

SRO will refer to Technical Specifications (T.S. 2.7.2(g) for loss of MCC-3C2 is under review by NRR TS branch and was not included as part of the exam grading criteria).

The D channel for RPS pressurizer pressure then fails low, resulting in a 2 out of 3 trip logic for TM/LP, but no reactor trip has occurred. The crew is expected to recognize that an RPS actuation was required, and take action to manually trip the reactor (critical task).

When the operator manually trips the reactor, five CEA's fail to insert requiring emergency boration, which is unsuccessful due to HCV-258 failure to open. Following completion of standard post trip actions, SRO directs entry into EOP-20, FUNCTIONAL RECOVERY, Success Path RC-2. The crew will initiate boration using the SIRWT (critical task).

Once the crew has initiated boration using the SIRWT, the scenario can be terminated.

Page 3 of 18

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: __3__ Event No.: __1__ Page _4_ of _18__

Event

Description:

____Maintain power at 90% using OP-4, Attachment 2, Step 5 and Attachment 3, Step 1.

Time Position Applicants Actions or Behavior CRS Reviews OP-4, LOAD CHANGE AND NORMAL POWER OPERATION, Attachment 2, "Power Reduction" and Attachment 3, "Steady State" BOPO Lower Turbine Generator Load to maintain RCS Tave program per TDB Figure III.1. (OP-4, Att. 2, Step 5.a). CRS should give BOPO a band to maintain Tcold, 532°F +0°F -1°F. This will maintain Tave on program.

ATCO For fuel burnup or xenon changes, borate or dilute as necessary per OI-CH-4 to maintain the following (OP-4, Att. 3, Step 1):

Desired reactor power

Desired regulating CEA group position

RCS Tave Program per TDB Figure III.1 In this case, the ATCO will be diluting per OI-CH-4, CHEMICAL AND VOLUME CONTROL SYSTEM MAKEUP OPERATIONS, Attachment 12, "Normal Dilution of the RCS to Control Reactor Power".

ATCO Verify a deaerated water booster pump, DW-43A or DW-43B, is in operation, or if cross-connected to demin water, a demineralized water booster pump, DW-41A or DW-41B, is in operation. (OI-CH-4, Att. 12, Prereq. 2)

ATCO Verify waste disposal system is available to receive letdown flow diverted from the VCT. (OI-CH-4, Att. 12, Prereq. 3)

ATCO Determine required gallons of demineralized water by using FC-1250A, Power/Inventory Maintenance Log. (OI-CH-4, Att. 12, Step 1) ATCO should determine approximately 300 gallons of water should be added.

ATCO Record number of gallons of makeup water to be added to the RCS. (OI-CH-4, Att. 12, Step 2)

ATCO Ensure HC-269, Makeup Water Mode Selector Switch, is in DILUTE. (OI-CH-4, Att. 12, Step 3). Note: Switch should already be in DILUTE.

ATCO Ensure FCV-269, Makeup Water Control Valve, is in CLOSE. (OI-CH-4, Att. 12, Step 4). Note: Valve should already be in CLOSE.

ATCO Review note. Dilution of the RCS may be performed in intermittent batches of makeup water to verify proper response.

Event description continues on next page

Op-Test No.: _____ Scenario No.: __3__ Event No.: __1__ Page _5__ of _18_

Event

Description:

____ Maintain power at 90% using OP-4, Attachment 2, Step 5 and Attachment 3, Step 1._______

Time Position Applicants Actions or Behavior ATCO Set FQS-269X, Demin Water Makeup Flow Batching Switch, to the desired number of gallons of water to be added. (OI-CH-4, Att. 12, Step 5)

Note: ATCO may add any amount of water provided it is less than the calculated and recorded value in Step 2. They may choose to add the water in batches, as allowed by the note.

ATCO Record the initial Demin Water Makeup Flow Totalizer reading, FQI-269X.

(OI-CH-4, Att. 12, Step 6)

ATCO Review notes: 1. Makeup water flow may be stopped at any time by closing FCV-269, 2. Steps 7 through 12 may be signed off after these steps are complete.

ATCO Open FCV-269, Makeup Water Control Valve. (OI-CH-4, Att. 12, Step 7)

ATCO Review Caution: All available indications shall be monitored for desired effects during any reactivity change.

ATCO Place FCV-269X, Demin Water Makeup Flow Control Valve, in AUTO. (OI-CH-4, Att. 12, Step 8)

ATCO With FC-269X, Demin Water Makeup Flow Controller, set Demin Water flow to the desired flow rate. (OI-CH-4, Att. 12, Step 9). Note: Expected desired flow rate to be between 80 - 90 gallons per minute.

ATCO If unexpected reactivity effects are observed, then stop the makeup flow and evaluate. (OI-CH-4, Att. 12, Step 10).

ATCO When dilution is complete, then place FCV-269X, Demin Water Makeup Flow Control Valve, in CLOSE. (OI-CH-4, Att. 12, Step 11)

ATCO Close FCV-269, Makeup Water Control Valve. (OI-CH-4, Att. 12, Step 12)

ATCO Verify VCT level and pressure respond as expected. (OI-CH-4, Att. 12, Step 13)

ATCO Record final Demin Water Makeup Flow Totalizer reading, FQI-269X. (OI-CH-4, Att. 12, Step 14)

ATCO Verify the amount of Demin Water added from the flow totalizer is consistent with the amount of water added. (OI-CH-4, Att. 12, Step 15)

Event is terminated once reactor reactivity effects are seen. Lead examiner cue next event.

Op-Test No.: _____ Scenario No.: __3__ Event No.: __2__ Page _6__ of _18 Event

Description:

____Instrument air compressor CA-1C fails. Standby compressor CA-1B is running but unloaded. Event is initiated at lead examiners cue.

Time Position Applicants Actions or Behavior BOPO Respond to alarm CB-10,11/A11 Window B-3L, AIR COMPRESSORS BKR TRIP BOPO Enter ARP-CB-10,11/A11, Window B-3L.

BOPO Dispatch an operator to the air compressors. (Step 1.1)

BOPO Ensure AC-9A or 9B, TPCW pump, is running. (Step 1.2)

BOPO Start the CS air compressor, CA-1A. (Step 1.3)

BOPO Check 1B3C power supply for undervoltage, and dispatch an operator to check the air compressor breaker for overcurrent trip. (Step 2.1)

CRS If breaker tripped, notify electrical maintenance.

BOPO Check running air compressor for proper operation. (Step 3)

Note: the crew may decide to put air compressor CA-1C in pull-to-lock.

Event is terminated once the CS air compressor is started and verified to be operating. Lead examiner will cue next event.

Op-Test No.: _____ Scenario No.: __3__ Event No.: __3__ Page _7__ of _18__

Event

Description:

____ Channel B power range NI summing amplifier fails low. ____________

Time Position Applicants Actions or Behavior ATCO Respond to alarm CB-4/A20 Window B-6, ROD DROP NUCLEAR INSTRUMENTATION CHANNEL, Window D-5, LOSS OF LOAD CHANNEL TRIP BYPASSED, and Window E-6, NUCLEAR T POWER CHANNEL DEVIATION ATCO Enter ARP-CB-4/A20 Window B-6.

ATCO If more than one rod dropped, then trip the reactor and go to EOP-00.

(Step 1). No rod dropped, so this step is N/A.

ATCO Check for indication of Dropped Rod (Step 2):

Core mimic for green rod bottom light

Decrease in reactor power

Decrease in reactor coolant loop Tavg

DROPPED ROD (CB-4, A8, A-5L)

4" and 8" Rod Deviation Annunciators (CB-4, A8, B-1U and B1L)

SCEAPIS indicates rod deviation

SCEAPIS indicates dropped rod

PPDIL and PDIL alarms

Rod drop light on RPS Note: No dropped rod.

ATCO Reset the six rod drop detection circuit bistables on the four RPS Linear Power Channel and two Power Range Control Channel drawers. (Step 2.1)

ATCO If a dropped rod is indicated, go to AOP-02. (Step 2.2) No dropped rod.

ATCO If there is no indication of a dropped rod, check the following (Step 3):

1. Check all nuclear instrumentation channels high voltage energized.

2. Verify both NI Subchannel Trip Test Switches in OFF.

3. Verify the NI Subchannel Calibrate Switch in the Operate position.

ATCO If NI channel high voltage is lost, then notify I&C of malfunction. (Step 4)

Step is N/A.

ATCO If switch is found out of position and testing is not in progress, then return the affected switch to the proper position. (Step 5). Step is N/A.

ATCO If an NI channel is declared inoperable, then bypass the affected channel per T.S. 2.15 and make notifications per SO-O-28. (Step 6) ATCO should realize that the affected trip units on channel A are already in bypass, and this step cannot be performed.

CRS Determine that entry conditions for AOP-15 are met and direct entry into AOP-15, LOSS OF FLUX INDICATION OR FLOW STREAMING,Section I, Loss of Power Range Safety Channels.

Event description continues on next page.

Op-Test No.: _____ Scenario No.: __3__ Event No.: __3__ Page _8__ of _18__

Event

Description:

____ Channel B power range NI summing amplifier fails low. ____________

Time Position Applicants Actions or Behavior CRS If one power range safety channel has failed or operates erratically, then disable the affected RPS Trip Units within one hour. (AOP-15,Section I, Step 1). Two power range safety channels are inoperable, therefore, transition to contingency.

CRS If more than one power range safety channel fails, go to Step 6. (Step 1.1)

CRS Review Note: If two power range safety channels remain failed for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , then the plant must be placed in hot shutdown within the following 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

ATCO If two power range safety channels fail or operate erratically, then disable the affected RPS trip units within one hour of failure of the second channel by performing the following: (Step 6)

CRS Place all of the following RPS trip units on one of the inoperable channels in bypass within one hour: TU-1, TU-2, TU-9, TU-10, TU-12. (Step 6.a)

Note: This has already been done as part of the initial conditions.

ATCO Place affected RPS trip units on the other inoperable channel in trip within one hour by performing the following: (Step 6.b) This should be performed on Channel B.

ATCO Place the Power Range Monitor drawer "TEST ENABLE" switch in "ENABLE" on the inoperable channel. (Step 6.b.1) Channel B ATCO Place the Power Range Monitor drawer "TEST SELECT" switch in "CAL MID" on the inoperable channel. (Step 6.b.2) Channel B ATCO Verify the red trip indicator light is lit on TU-1, TU-9 and TU-12. (Step 6.b.3) Channel B CRS Remove all the following trip units from the inoperable channel (Step 6.b.4). CRS will direct I&C to remove these units.

CRS With two power range safety channels inoperable, reduce reactor power to less than or equal to 70% per OP-4, LOAD CHANGE AND NORMAL POWER OPERATION. (Step 7)

CRS Enter T.S. 2.15(2) for two inoperable channels for TU-1, TU-2, TU-9, TU-10, and TU-12. This requires placing one channel for these trip units in trip. Also, Note C on Table 2-2 requires that power be reduced to less than 70%.

Event is terminated once T.S. call is made. Lead examiner will cue the next event.

Op-Test No.: _____ Scenario No.: __3__ Event No.: __4__ Page _9__ of _18 Event

Description:

____Heater drain pump FW-5B trips, standby pump fails to autostart Time Position Applicants Actions or Behavior BOPO Respond to alarm CB-10,11/A12, Window A-4L, HEATER DRAIN PUMP B OVERLOAD/TRIP ATCO or Enter ARP-CB-10,11/A12 Window A-4L.

BOPO BOPO If no heater drain pumps are operating, then consider starting an additional condensate pump. (Step 1). BOPO determines one heater drain pump is operating.

BOPO Dispatch an operator to check the status of FW-5B, heater drain pump.

(Step 2)

BOPO If FW-5B is tripped, then ensure that standby heater drain pump FW-5A or C has automatically started. (Step 3) Note: standby pump failed to autostart.

BOPO If two pumps are required, then start standby heater drain pump FW-5A.

(Step 3.1) Note: Two heater drain pumps are required.

BOPO Check the following for the cause of the FW-5B trip:

Heater Drain Tank low level

49/FW-5B, Overcurrent Relay, tripped at 1A2 (1A2-9)

Motor stopped from the local stop pushbutton

Motor stopped from the 69 permissive switch (1A2-9)

Low voltage on 4160V Bus 1A2 (Step 3.2)

CRS Notify Electrical Maintenance of pump trip. (Step 3.3)

Note: Crew may decide to place the tripped pump in pull-to-lock.

Event is terminated once the standby pump has been started. Lead examiner will cue the next event.

Op-Test No.: _____ Scenario No.: __3__ Event No.: _5__ Page _10__ of _18__

Event

Description:

____High oxygen concentration (0.20 ppm) in the RCS. Report is called in by chemistry at the lead examiners cue.__________________________________________________

Time Position Applicants Actions or Behavior CRS Take report from chemistry about 0.20 ppm dissolved oxygen in RCS.

This is in Action Level 2 per CH-AD-0003.

CRS Direct entry into AOP-41,Section II RCS Chemistry CRS Direct shift manager to notify Operations Manager, Reactor Engineer, Supervisor-Reactor Performance Analysis, and Manager-Chemistry (Section II, Step 5.a)

CRS Refer to Technical Specification 2.1.5(1). T.S. 2.1.5(1) states that if the oxygen concentration exceeds 0.1 ppm during power operation, initiate corrective action within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months to return oxygen levels to <0.1 ppm. If not restored within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , place in hot shutdown within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after that.

If not restored within an additional 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period, put in cold shutdown 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after that (2.1.5(5)). (Step 5.b)

CRS Restore chemistry to below action level 2 within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Event is terminated once technical specification call is made.

Op-Test No.: _____ Scenario No.: __3__ Event No.: _6__ Page _11__ of __18_

Event

Description:

_________ Raw water pump AC-10D trips, standby fails to autostart.______

Time Position Applicants Actions or Behavior ATCO Respond to alarms CB-1,2,3/A1 Window D1U, RAW WATER PUMPS BREAKER OVERLOAD OR TRIP, Window C1U, RAW WATER SUPPLY HEADER FLOW LO, and Window C1L, RAW WATER SUPPLY HEADER PRESS LO. Note: Alarm D1U comes in first, and the other two come in a few moments later.

ATCO Enter ARP-CB-1,2,3/A1 Window D1U.

ATCO Ensure a raw water pump is running and supplying raw water system.

(Step 1) ATCO take action to start raw water pump determined by CRS (AC-10A).

ATCO Verify RW system flow by the following indications:

FIC-2890, East Header

FIC-2891, West Header (Step 2)

ATCO If both RW header flows are low (less than 1000 gpm), then go to AOP-18.

(Step 2.1) Note: Since a raw water pump was able to be started, flows should recover and alarms C1U and C1L should clear. AOP-18 should not be entered.

ATCO Verify the white light for the tripped pump is on. (Step 3)

CRS Notify Electrical Maintenance to determine the cause of the pump trip.

(Step 4)

Event is terminated once a raw water pump has been started. Lead examiner will cue the next event.

Op-Test No.: _____ Scenario No.: __3__ Event No.: _7__ Page _12__ of __18_

Event

Description:

____Loss of MCC 3C2 due to a ground fault. This event is initiated at lead examiners cue.__________________________________________________

Time Position Applicants Actions or Behavior ATCO Respond to alarm CB-4/A7 Window B5U, BORIC ACID VALVES TROUBLE and Window B1U, BORIC ACID PUMP CH-4A OVERLOAD Note: backpanel alarm is AI-44/A39, A3, 480V Motor Overload Trip ATCO Enter ARP-CB-4/A7 Window B5U ATCO Check indicating lights for valves HCV-258, HCV-265, and HCV-268. (Step 1). Determine that valves HCV-265 and HCV-268 lights are off.

ATCO Dispatch equipment operator to check affected valve breakers. (Step 2)

Determine that MCC-3C2 is deenergized.

CRS Direct entry into AOP-32, LOSS OF 4160 VOLT OR 480 VOLT BUS POWER, for loss of 480V bus MCC-3C2.

CRS Enter AOP-32 Section I, Plant Stabilization and Diagnostics BOPO Ensure 43-1/D1 and 43-1/D2 DG mode selector switches are in EMERGENCY STANDBY. (Step 2)

CRS Go to Step 9 because plant is not on shutdown cooling. (Step 3)

BOPO Verify at least one vital 4160 V bus is energized. (Step 9)

ATCO Verify at least one CCW pump is running with discharge pressure greater than 60 psig (Step 10)

ATCO Ensure at least one raw water pump running. (Step 11)

BOPO Ensure one bearing water pump is running (Step 12)

BOPO Verify IA operation by ensuring any air compressor is running and instrument air pressure is greater than 90 psig. (Step 13)

ATCO Ensure any or all charging pumps are running (Step 14)

ATCO Maintain RCS pressure per pressure-temperature limits. (Step 15)

ATCO Terminate all radiaoactive releases. (Step 16)

ATCO Verify at least one RCP is operating (Step 18)

BOPO Maintain S/G levels 35-85% NR. (Step 19)

ATCO If condenser vacuum greater than 19 inches, verify RCS temperature being controlled by normal turbine generator operation. (Step 20)

CRS N/A step 21 because lighting is not lost.

CRS Determine that MCC-3C2 has been lost and transition to Section XXVII (Step 22)

Event description continues on next page.

Op-Test No.: _____ Scenario No.: __3__ Event No.: _7__ Page _13__ of __18_

Event

Description:

____Loss of MCC 3C2 due to a ground fault. This event is initiated at lead examiners cue.__________________________________________________

Time Position Applicants Actions or Behavior ATCO Verify alarm CB-4/A7 BORIC ACID VALVES TROUBLE in alarm, Boric Acid pump CH-4A status lights out, and VA-40A and VA-40C, Aux. Bldg.

exhaust fan status lights out. (Step 1)

CRS Direct chemistry to obtain dew point readings as necessary to maintain radiation monitor operability. (Step 2)

BOPO Operate DW-41B, demineralized water booster pump as necessary (Step 3)

CRS Ensure all radioactive gaseous releases are terminated. (Step 4)

BOPO Operate FW-34B, steam generator blowdown transfer pump B, as necessary. (Step 5)

ATCO/BOPO Refer to Att. B for a complete list of components powered from MCC-3C2.

(Step 6)

CRS Determine the cause of the loss of power to MCC-3C2. (Step 7)

CRS Enter T.S. 2.7.2(g) for loss of MCC-3C2 8-hour shut-down action statement. (Step 8)

Either group of MCCs (3A1, 3A2, 3B1, 3C1, 3C2) or (4A1, 4A2, 4B1, 4C1, 4C2) may be inoperable for up to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , then placed in a hot shutdown within the following 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , and cold shutdown 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after that.

CRS Refer to ODCM. (Step 8)

Event may be terminated once technical specification call is made.

Op-Test No.: _____ Scenario No.: __3__ Event No.: _8__ Page _14__ of _18__

Event

Description:

____ATWS. Channel D for RPS pressurizer pressure fails low. This results in a 2 of 3 logic, requiring a reactor trip. RPS fails, and no automatic RPS actuation occurs. This event is initiated at lead examiners cue._________

Time Position Applicants Actions or Behavior ATCO Respond to alarm CB-1,2,3/A4 Window D-5, PRESSURIZER SAFETY INJ SIGNAL LO-LO PRESSURE D/P102Y ATCO/CRS Determine that TM/LP meets the 2 out of 3 logic criteria, requiring a reactor trip which has not occurred.

CRS Direct ATCO to manually trip the reactor and enter EOP-00, SPTAs.

ATCO Manually trip the reactor. Critical task is to manually trip the reactor before entry into ARP-CB-1,2,3/A4.

(CT)

Op-Test No.: _____ Scenario No.: __3__ Event No.: _9__ Page _15__ of _18__

Event

Description:

____5 control rods fail to insert, requiring emergency boration. When ATCO attempts to emergency borate, HCV-258 mechanically bounds and cannot be opened. These events are preprogrammed into the scenario and will occur automatically once the reactor is manually tripped.__________________________________________________

Time Position Applicants Actions or Behavior ATCO Verify reactor power is lowering, startup rate is negative and no more than one regulating or shutdown CEA not inserted. (Step 1). Transition to contingency action.

ATCO Manually trip reactor at CB-4 and/or AI-31, place DSS manual trip switches to TRIP, manually open the CEDM clutch power supply breakers at AI-57.

(Step 1.1)

ATCO If more than one CEA not fully inserted, emergency borate by ensuring both FCV-269X and FCV-269Y are closed and attempt to open HCV-258, which fails to open. (Step 1.2a&b). Note: may direct a local operator to attempt to open boric acid gravity feed valves HCV-265 and HCV-258.

If so, these actions will not be completed successfully prior to procedural direction to borate using the SIRWT.

ATCO Notify CRS of failure of emergency boration.

Note: A possible parallel path will be to emergency borate using the SIRWT using guidance from AOP-03. This operates the same valves as for the EOP-20 guidance.

BOPO Verify turbine is tripped as indicated by stop and intercept valves indicating closed. (Step 2)

BOPO Ensure generator output breakers 3451-4 and 3451-5 and generator field breaker 41E/G1F are tripped. (Step 3)

BOPO Verify buses 1A3 and 1A4 are energized. (Step 4)

BOPO Check buses 1A1 and 1A2 are energized. (Step 6)

BOPO Check that 125 VDC buses 1 and 2 are energized. (Step 7)

BOPO Verify instrument air is available by both the following conditions: IA pressure greater than or equal to 90 psig and at least one air compressor is operating. (Step 8)

ATCO Ensure at least one CCW pump is operating with discharge pressure greater than or equal to 60 psig and at least one raw water pump is operating. Ensure RCP Coolers CCW valves HCV-438A/B/C/D are open(Step 9)

ATCO Verify RCS inventory control: pressurizer level 30-70%, trending to 45-60%, and RCS subcooling is greater than or equal to 20 degrees F. (Step 10)

ATCO Verify RCS pressure control: RCS pressure is 1800-2300 psia, trending to 2050-2150 psia and PORVs are closed. (Step 11)

Event description continues on next page.

Op-Test No.: _____ Scenario No.: __3__ Event No.: _9__ Page _16__ of _18__

Event

Description:

____5 control rods fail to insert, requiring emergency boration. When ATCO attempts to emergency borate, HCV-258 mechanically bounds and cannot be opened. These events are preprogrammed into the scenario and will occur automatically once the reactor is manually tripped._

Time Position Applicants Actions or Behavior ATCO Verify core heat removal via forced circulation: RCP NPSH requirements satisfied, at least one RCP is operating, and core T is less than or equal to 10 degrees F. (Step 12)

BOPO Verify main feedwater is restoring level in at least one S/G to 35-85% NR (73-94% WR) by performing the following (Step 13):

Ensure FCV-1101 and FCV-1102 feed reg valves have ramped closed.

Ensure both feed reg bypass valves have ramped to 40-45%

Place 43/FW switch in OFF

Ensure no more than one feed pump operating

Ensure no more than one condensate pump operating

Stop all operating heater drain pumps

Ensure both sets of S/G blowdown isolation valves are closed (HCV-1387A/B and HCV-1388A/B)

BOPO Verify steam dump and bypass valves are controlling RCS Tcold 525-535 degrees F and S/G pressure 850-925 psia. (Step 14)

ATCO Verify normal containment conditions: no unexpected rise in the containment sump level, no containment area radiation alarms, no alarms on RM-051, RM-052, and RM-062, and no S/G blowdown or condenser off-gas radiation monitors are in alarm or trending upward. (RM-054A, RM-054B, and RM-057). (Step 15a-e)

ATCO Verify containment pressure less than 3.0 psig and temperature less than 120 degrees F. (Step 15.f)

CRS Determine appropriate procedure per Section 6.0, Diagnostic Actions.

(Step 16). CRS should determine that EOP-20, Functional Recovery, must be entered due to the 5 CEA's that failed to insert and failure of emergency boration.

CRS Determine need to and enter RC-2 success path.

BOPO Maintain RCS temperature constant by controlled steaming using steam dump and bypass valves. (RC-2, Step 1)

ATCO Verify BAST is available for boration. (Step 2) Transition to contingency action.

CRS If both BASTs are unavailable, go to Step 4. (Step 2.1)

ATCO (CT) Commence boration using the SIRWT (Step 4)

ATCO Open LCV-218-3, charging pump suction SIRWT isolation valve (Step 4.a)

Event description continues on next page.

Op-Test No.: _____ Scenario No.: __3__ Event No.: _9__ Page _17__ of _18__

Event

Description:

____5 control rods fail to insert, requiring emergency boration. When ATCO attempts to emergency borate, HCV-258 mechanically bounds and cannot be opened. These events are preprogrammed into the scenario and will occur automatically once the reactor is manually tripped._

Time Position Applicants Actions or Behavior ATCO Stop both boric acid pumps (Step 4.b)

ATCO Ensure HCV-268, HCV-265, HCV-258, and LCV-218-2 (VCT outlet valve) are closed (Step 4.c)

ATCO Ensure charging isolation valves HCV-247, HCV-238, HCV-248, and HCV-239 are open. (Step 4.d)

ATCO Start all charging pumps (Step 4.e)

ATCO Insert CEAs into the core using MANUAL SEQUENTIAL or MANUAL GROUP Scenario can be terminated once emergency boration has been started.

Page 18 of 18 Procedure Number Procedure Title Revision OP-4 LOAD CHANGE AND NORMAL POWER OPERATION 48 OI-CH-4 CHEMICAL AND VOLUME CONTROL SYSTEM 45 MAKEUP OPERATIONS ARP-CB-10,11/A11 23 ARP-CB-4/A20 44 AOP-15 LOSS OF FLUX INDICATION OR FLOW STREAMING 12 ARP-CB-10,11/A12 12 CH-AD-0003 PLANT SYSTEMS CHEMICAL LIMITS AND 84 CORRECTIVE ACTIONS AOP-41 CHEMISTRY OUT OF SPECIFICATION 0 ARP-CB-1,2,3/A1 34 ARP-CB-4/A7 17 AOP-32 LOSS OF 4160 VOLT OR 480 VOLT BUS POWER 17 EOP-00 STANDARD POST TRIP ACTIONS 29 EOP-20 FUNCTIONAL RECOVERY PROCEDURE 25

Scenario # 3 Malfunction List Event # Description Type System Command Severity Ramp IC Power Range MAL NIS NIS09 TRUE Channel A HV Power supply Bypass trip units failure 1,2,9,10,12 1 Maintain Power at 90%

2 Air compressor MALF CAS BUS_1B3A_4A_2_BKR_TRIP TRUE Fails C C AC 3 Power Range B MAL NIS NIS30 0%

summing amp fails 4 FW-5B Trips MALF CON BUS_1A2_9_BKR_TRIP TRUE 5 RCS O2 high Report O2 at 0.20 ppm 6 AC-10D Trips MALF RWS BUS_1A4_12_BKR_TRIP TRUE 7 MCC 3C2 fault REM EDA REM:BUS_1B3C_2 OPEN 8 ATWS TRAN RRS RCS_PT102D 1500 ATWS (preset) MALF RPS RPS01 E ATWS (preset) MALF RPS RPS02 E ATWS (preset) MALF RPS RPS03 E ATWS (preset) MALF RPS RPS04 E 9 CEA Stuck MALF CRD ROD_PWR_A30_2 TRUE (preset)

CEA Stuck MALF CRD ROD_PWR_A33_2 TRUE (preset)

CEA Stuck MALF CRD ROD_PWR_B15_2 TRUE (preset)

CEA Stuck MALF CRD ROD_PWR_B16_2 TRUE (preset)

CEA Stuck MALF CRD ROD_PWR_112_2 TRUE (preset) 10 HCV-258 stuck VLV CVC HCV-258 0%

closed (preset)

Appendix D Scenario Outline Form ES-D-1 Facility: _Fort Calhoun Station__ Scenario No.: ____4___ Revision __1__ Op-Test No.: _______

Examiners: ____________________________ Operators: _____________________________

Initial Conditions: __Mode 2 <1% power. Next step in OP-2A is to start 1 MFW pump. Desired MFW pump is FW-4B.___________

Turnover: _____Continue in OP-2A to raise power and load turbine. All requirements to transition to Mode 1 in OP-4 have been met.__________________________________________________

Event Malf. Event Event No. No. Type* Description N-BOPO 1 Start MFW pump FW-4B per OP-2A, Attachment 3. Attachment 2 contains local operator actions and the instructions for starting the lube oil pump.

R-ATCO 2 Raise reactor power to 10% per OP-2A.

C-ATCO Wide range log NI-002 fails high. This failure should occur when 3 TS-CRS the ATC has raised power sufficient to see reactor response and when directed by lead examiner. ARP-CB-4/A20, Windows B-7 and C-1. This will send the operators to AOP-15, where they are directed to secure from raising power and stabilize reactor.

T.S. 2.15(1) applies for failure of NI.

4 C-BOPO MFW pump FW-4B trips, no auto start of standby pump. Alarm is ARP-CB-10,11/A12.

5 C-ATCO Controlling pressurizer level instrument 101X fails low. Alarm is ARP-CB-1,k2,3/A4 Windows A-8 and C-8 C-ATCO 6 TS-CRS CCW pump AC-3A trips, no autostart of standby pump. Alarm is ARP-CB-1,2,3/A2 Window D-3U. T.S. 2.4(1)b applies.

7 C-BOPO Inadvertent AFAS. AOP-28 for inadvertent AFAS. T.S.2.5.(1)D TS-CRS and TS 2.15(3) apply. Critical task is to recognize the AFAS is (CT) inadvertent and take action to mitigate (stop feeding the steam generators with AFW) 8 M-ALL Steam line break inside containment on RC-2A. EOP-00 to EOP-05.

9 C-BOPO SGIS fails. Critical task will be for BOPO to isolate steam generator before exiting procedure step.

(CT) 10 C-ATCO Containment spray pump 3B fails to autostart but can be started from control panel. Containment spray pump 3A shaft shears.

(CT) Critical task is to restore containment spray flow by either starting containment spray pump 3C or 3B.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Page 1 of 18

Scenario Event Description NRC Scenario #4 SCENARIO

SUMMARY

NRC #4 The crew assumes the watch with the reactor is Mode 2 at less than 1% reactor power. The crew instructions are to start main feedwater pump FW-4B and continue with power ascension.

The first event is to start a main feedwater pump per OP-2A, PLANT STARTUP, Attachment 3.

The next event is to raise reactor power to 10% per OP-2A. Once a reactivity effect is seen on the reactor, the next event will be cued.

The next event is a failure of wide range logarithmic NI-002 high. Operator action is per CB-4/A20 and AOP-15, and includes securing from the power ascension and stabilizing the reactor.

SRO will refer to Technical Specifications. T.S. 2.15(1) applies.

The next event is a trip of main feedwater pump FW-4B with no autostart of the standby pump.

Operator actions are per ARP-CB-10,11/A12 and include starting the standby pump, setting the post SIAS feedwater pump to FW-4C, and selecting a new standby pump.

The next event is a failure of controlling pressurizer level instrument 101X low. Operator actions are per ARP-CB-1,2,3/A4 and include placing the pressurizer level control switch to channel Y and placing the pressurizer heater cutout channel select switch to channel Y.

The next event is a trip of CCW pump AC-3A with no autostart of the standby pump. Operator actions are per ARP-CB-1,2,3/A2 and include starting the standby CCW pump. SRO will review Technical Specifications. T.S. 2.4(1)b applies.

The next event is an inadvertent auxiliary feedwater actuation signal. Operator actions are per AOP-28, AUXILIARY FEEDWATER SYSTEM MALFUNCTIONS and include actions to stop the aux feed and bypass the affected AFAS signal (critical task). SRO will refer to Technical Specifications. T.S.'s 2.5(1)D and 2.15(3) apply.

After this event a steam line break occurs inside containment on RC-2A. The crew will enter EOP-00 and perform standard post trip actions. Automatic SGIS fails and the crew should recognize this and take action to manually isolate the steam generators (critical task).

Once the containment spray is actuated, containment spray pump 3A shaft shears and pump 3B fails to automatically start. The crew should recognize that they do not have any containment spray and take actions to start containment spray pump 3B, or containment spray pump 3C (critical task)., and they might close one of the containment spray head valves.

Once the crew has successfully isolated the steam generator and restored containment spray, the scenario may be terminated.

Page 2 of 18

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: _____ Scenario No.: _4___ Event No.: __1__ Page _3__ of _18__

Event

Description:

__Start MFW pump FW-4B per OP-2A Att. 4 Step 5.a.__

Time Position Applicants Actions or Behavior BOPO Start MFW pump using OI-FW-2. (OP-2A, Att. 4, Step 5.a)

BOPO Direct local operator to perform actions per OI-FW-2, Attachment 2.

(Attachment 3, Step 1). Note: Actions have already been completed prior to turnover, including actions to start the auxiliary lube oil pump.

BOPO Ensure lockout relay is reset and amber indicating light is on for 86/FW-4B. (Attachment 3, Step 2)

BOPO Ensure 43/FW switch is in off and the 43/FW TRANSFER SWITCH OFF-AUTO alarm is in alarm (Step 3)

BOPO Ensure 43-SIAS/FW4 is in the FW-4B position. (Step 4)

BOPO Start FW pump FW-4B by placing control switch in AFTER-START. (Step 6)

BOPO Verify ammeter returns to less than 460 amps in less than 15 seconds and stabilizes for FW-4B. (Step 7.a)

BOPO Verify discharge isolation valve HCV-1150B opens and operates properly.

(Step 7.b)

BOPO Verify auxiliary lube oil pump FW-30B stops. (Step 7.c)

BOPO Direct local operator to ensure HCV-1150B stem indicator goes to open position. (Step 8)

BOPO At discretion of shift manager, place 43/FW switch in AUTO and verify alarm clears. (Step 9). Note: cue this if asked.

Event is terminated once the main feedwater pump is started.

Op-Test No.: _____ Scenario No.: _4___ Event No.: __2__ Page _4__ of _18__

Event

Description:

__Raise reactor power to 10% per OP-2A, Attachment 4, Step 5.__

Time Position Applicants Actions or Behavior BOPO Direct local operator to secure FW-54 by performing OI-AFW-4, Attachment 5, Steps 13-15. (OP-2A, Att. 4, Step 5.b)

ATCO Raise reactor power by dilution using OI-CH-4 Attachment 12 ATCO Record current boron concentration, desired boron concentration, and RCS Tavg. (Step 1) Note: may use reactivity sheets to determine approximate number of gallons of water to be added instead of Steps 1-2 ATCO Determine number of gallons of makeup water to be added using ERF computer per OI-ERFCS-1 or the dilution formula in TDB-V.12. (Step 2)

ATCO Record the number of gallons of makeup water to be added to the RCS.

(Step 3) Note: During validation, crew added 10 gallons of water to the VCT.

ATCO Ensure HC-269, makeup water mode selector switch, is in DILUTE. (Step 4)

ATCO Ensure FCV-269, makeup water control valve, is in CLOSE. (Step 5)

ATCO Set FQS-269X, demin water makeup flow batching switch, to the desired number of gallons of water to be added. (Step 6) Note: will likely choose to added water in smaller batches, as allowed by note in procedure.

ATCO Record initial demineralized water makeup flow totalizer reading. (Step 7)

ATCO Open FCV-269. (Step 8)

ATCO Place FCV-269X in AUTO. (Step 9)

ATCO Set demineralized water flow to desired flow rate with FC-269X controller.

(Step 10)

ATCO Verify VCT level and pressure respond as expected. (Step 11)

ATCO Place FCV-269X in CLOSE when dilution complete. (Step 13)

ATCO Close FCV-269 and record final demineralized water makeup flow totalizer reading. (Steps 14-15)

ATCO Verify amount of demineralized water added from flow totalizer is consistent with amount of water added. (Step 16)

BOPO Maintain RCS temperature 527-535 degrees F using steam dump and bypass valves. (OP-2A, Attachment 4, Step 5.c)

Event can be terminated once reactivity effects are seen. Lead examiner will cue the next event.

Op-Test No.: _____ Scenario No.: _4___ Event No.: __3__ Page _5__ of __18_

Event

Description:

__Wide range log power NI-002 fails high.

Time Position Applicants Actions or Behavior ATCO Respond to alarms CB-4/A20 Window B-7, NUCLEAR INSTRUMENTATION CHANNEL INOPERATIVE, Window C-1, HIGH POWER RATE OF CHANGE CHANNEL TRIP, Window D-1, HIGH POWER RATE OF CHANGE CHANNEL PRETRIP, and Window E-4, HIGH POWER RATE OF CHANGE TRIP ENABLED.

ATCO Enter ARP-CB-4/A20, Window B-7 ATCO Verify nuclear instrumentation testing in progress. (Step 1) Testing is not in progress.

ATCO Check that the non-op light is on for one of the WRNI drawers. (Step 2).

Determine that NI-002 has failed high.

ATCO Check the following on the WRNI drawer (Step 3):

Level test and rate test switches in OPR for WR NI drawers

NI drawer power-on lights are on for WR NI drawers

-4 ATCO If a wide range channel is failed AND power is greater than 10 but less than 15%, go to AOP-15. (Step 6)

CRS Transition to AOP-15,Section II.

ATCO Stabilize the reactor. (Step 1). Note: ATCO will drive rods in slightly to counteract the positive reactivity from the dilution, using OI-RR-1, REACTOR REGULATING SYSTEM NORMAL OPERATION, Attachment 3, "Manual Sequential Mode Operation" ATCO Review Notes.

ATCO Ensure an out-of-scan CEA is not selected as the target rod on CB-4. (OI-RR-1, Attachment 3, Step 1)

ATCO Verify REGULATING GROUP WITHDRAWAL PROHIBIT is clear. (Step 2)

ATCO Place Rod Control Mode Selector Switch in Manual Sequential position.

(Step 3)

ATCO Review Note.

ATCO Place Manual Rod Control Switch to LOWER as required by the situation, then verify the following (Step 4):

Primary CEAPIS indicates motion in the proper direction

Secondary CEAPIS indicates motion in the proper direction

ERF (Page 302 or LPP) indicates motion in the proper direction Event description continues on next page.

Op-Test No.: _____ Scenario No.: _4___ Event No.: __3__ Page _6__ of _18__

Event

Description:

__Wide range log power NI-002 fails high.

Time Position Applicants Actions or Behavior ATCO Verify the following group motion overlap (Step 5.b):

Group 3 starts when Group 4 is at 53 inches Note: Shouldn't reach this point during reactor stabilization ATCO When the group is at the desired position, release Manual Rod Control Switch (Step 7).

ATCO Verify all CEA motion stops as indicated by the following (Step 9):

Primary CEAPIS

Secondary CEAPIS

ERF (Page 302 or LPP)

ATCO Place Rod Control Mode Selector Switch in OFF. (Step 11)

ATCO Verify at least two wide range channels are operable. (AOP-15,Section II, Step 2)

CRS Notify operations manager or work week manager of WR NI failure. (Step 3)

ATCO Place RPS TU-2 in either bypass or trip within one hour. (Step 4)

CRS Direct I&C to restore WR NI to service. (Step 5)

CRS Enter T.S. 2.15(1). Place inoperable channel in either bypass or tripped condition within one hour. Channel may be bypassed up to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months . The specification applies to the wide range NI channel when reactor power is

-4 between 10 and 15% power Event is terminated once T.S. call is made or at lead examiner discretion. Lead examiner will cue the next event.

Op-Test No.: _____ Scenario No.: _4___ Event No.: __4__ Page _7__ of __18_

Event

Description:

__MFW pump FW-4B trips, no autostart of backup pump.

Time Position Applicants Actions or Behavior BOPO Respond to alarm CB-10,11/A12 Window A-6L, STEAM GEN FEED PUMP B OVERLOAD/TRIP BOPO Enter ARP-CB-10,11/A12 Window A-6L BOPO Dispatch an operator to check status of FW-4B. (Step 1)

Booth role plays at water plant operator when called to investigate FW-4B pump trip. Report back after a few minutes that it tripped on overcurrent.

BOPO Start standby feedwater pump. (Step 2). Note: The ARP does not contain instructions about starting the auxiliary lube oil pump prior to starting MFW pump, however the nature of this failure has the lube oil pump start automatically. BOPO will start FW-4C.

BOPO Ensure 43-SIAS/FW4 Post SIAS Running Feedwater Pump is selected to FW-4C. (Step 2.2)

BOPO Check the following for the cause of the FW-4B trip (Step 2.4):

49/FW-4B overcurrent relay tripped at 1A2

Motor stopped from local stop pushbutton

Motor stopped from the 69 permissive switch

Low voltage on 4160V Bus 1A2

Low oil pressure on feedwater pump

86/FW-4B Feedwater Pump Motor Differential Overcurrent BOPO Notify electrical maintenance of feedwater pump trip. (Step 2.5)

BOPO Place running pump in AFTER-START. (Step 2.6)

BOPO If desired, align another pump to standby by placing control switch for FW-4B in AFTER-STOP and the control switch for the pump in PULL-OUT to AFTER-STOP. (Step 3)

Event is terminated once feedwater pump is operating. Lead examiner will cue the next event.

Op-Test No.: _____ Scenario No.: _4___ Event No.: __5__ Page __8_ of _18__

Event

Description:

__Controlling pressurizer level instrument 101X fails low. ________________

Time Position Applicants Actions or Behavior ATCO Respond to alarm ARP-CB-1,2,3/A4 Window A-8, PRESSURIZER LEVEL HI-LO CHANNEL X and Window C-8, PRESSURIZER LEVEL LO-LO CHANNEL X.

ATCO Enter ARP-CB-1,2,3/A4 Window C-8.

ATCO Check pressurizer level on LIC-101Y. (Step 1)

ATCO Check RCS pressure. (A,B,C,D/PIA-102Y) (Step 2)

ATCO Ensure all pressurizer heaters are deenergized. (Step 3)

ATCO Check RCS cold leg temperature for decrease (Step 4)

ATCO Check VCT level for indication of decreasing level (Step 4.1)

ATCO If VCT level is decreasing, perform RCS leak rate test. (Step 4.2)

ATCO Check letdown flow at a minimum and all available charging pumps are running and supplying flow to the RCS. (Step 5)

ATCO Place pressurizer level control to channel Y (Step 6.1)

ATCO Place PZR heater cutout channel select switch to Y (Step 6.2)

ATCO Notify I&C. (Step 7)

Note: If crew takes too long to swap from "bad" channel (Channel 101X) to "good" channel (Channel 101Y), the change in the setpoint error (Channel 101X reads 0% level, Channel 101Y reads >60% level) can cause a pressure "spike" in the letdown system, causing HCV-204, RC to Letdown Heat Exchanger, to close, isolating letdown. Alarm CB-1,2,3/A2 Window B1L, Intermediate Letdown Pressure HI/LO will alarm if this occurs.

Event is terminated once level is controlled within band either manually or using channel Y. Lead examiner will cue the next event.

Op-Test No.: _____ Scenario No.: _4___ Event No.: __6__ Page __9_ of __18_

Event

Description:

__CCW pump AC-3A trips, no autostart of standby pump. ________________

Time Position Applicants Actions or Behavior ATCO Respond to alarm CB-1,2,3/A2 Window D-3U, CCW PUMPS TRIP ATCO Enter ARP-CB-1,2,3/A2 Window D-3U.

ATCO Verify standby CCW pumps have started. (Step 1)

ATCO If standby pump has not started, start a standby CCW pump. (Step 2)

ATCO will start pump AC-3B.

ATCO Monitor CCW component temperatures and flows. (Step 3)

BOPO Direct local operator to check CCW pump breaker. (Step 5)

ATCO Notify maintenance of CCW pump trip. (Step 6)

CRS Enter T.S. 2.4(1)(b). Restore CCW pump to operability within 7 days or place in hot shutdown within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after that. If not restored within an additional 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , enter cold shutdown within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Note: Some other alarms may come in depending on how quickly the crew restores component cooling water flow. During validation, Alarm CB-1,2,3/A1 B5U came in for high seal cooler temperature on RC-3B.

Event is terminated once CCW flow is restored and at lead examiner discretion. Lead examiner will cue the next event.

Op-Test No.: _____ Scenario No.: _4___ Event No.: __7__ Page _10__ of _18__

Event

Description:

__Inadvertent AFAS (Aux. FW actuation signal).

Time Position Applicants Actions or Behavior BOPO Respond to alarms AI-66A/A66A Window 44, AFWS STEAM GEN RC-2A CHANNEL A ACTUATED and Window 45, AFWS STEAM GEN RC-2B CHANNEL A ACTUATED CRS Determine that AFAS actuated NOT required.

CRS Direct entry into AOP-28,Section II, Inadvertent AFW actuation BOPO Verify AFAS is inadvertent. (Section II, Step 1)

CRS Refer to both T.S.s 2.5 and 2.15. (Step 2)

BOPO Ensure both FCV-1368, FW-6 recirculation valve, and FCV-1369, FW-10 recirculation valve, are in AUTO. (Step 3)

BOPO Place control switches for AFW isolation valves HCV-1107A, HCV-1107B, HCV-1108A, and HCV-1108B in CLOSE. (Step 4)

(CT)

BOPO Bypass affected channel or logic subsystem per OI-AFW-2 CRS Determine if an instrument channel or logic subsystem channel is to be bypassed. (OI-AFW-2, Attachment 1, Step 1). CRS determines that logic subsystem channel A is to be bypassed, and proceeds to Step 3.

CRS Log entry into T.S. 2.15(3) (OI-AFW-2, Attachment 1, Step 3.a)

BOPO Bypass selected Logic Subsystem using Table 2, Auxiliary Feedwater Actuation System Logic Subsystem Bypass Switch Alignment and record the As-Left information in the appropriate slots. (Step 3.b)

BOPO Stop all AFW pumps by: (AOP-28,Section II, Step 6)

BOPO Close YCV-1045, FW-10 steam inlet valve (Step 6.a)

BOPO Place isolation valve YCV-1045A override switch and isolation valve YCV-1045B override switch in OVERRIDE. (Step 6.b)

BOPO Close YCV-1045A and YCV-1045B, FW-10 steam supply valves. (Step 6.c)

BOPO Ensure FW-10 recirc flow drops to zero. (Step 6.d)

BOPO Stop FW-6, electric AFW pump, by placing HC-1367, FW-6 control switch, in PULL-TO-LOCK. (Step 6.e)

BOPO Ensure FW-6 recirc flow drops to zero.

BOPO Once affected channel is bypassed return AFW system to automatic: (Step 7)

Event description is continued on the next page.

Op-Test No.: _____ Scenario No.: _4___ Event No.: __7__ Page _11 __ of _18__

Event

Description:

__Inadvertent AFAS (Aux. FW actuation signal). Event is initiated at lead examiners cue.

Time Position Applicants Actions or Behavior BOPO Place control switches for HCV-1107A, HCV-1107B, HCV-1108A, and HCV-1108B in RESET. (Step 7.a)

Place control switches for HCV-1107A, HCV-1107B, HCV-1108A, and HCV-1108B in AUTO. (Step 7.b)

BOPO Place YCV-1045 control switch in RESET. (Step 7.c)

BOPO Place YCV-1045 control switch in AUTO. (Step 7.d)

BOPO Place isolation valve YCV-1045A override switch and isolation valve YCV-1045B override switch in NORMAL. (Step 7.e)

BOPO Place HC-1367, FW-6 control switch, in AFTER-STOP. (Step 7.f)

BOPO Ensure FW-64-RL, Aux Feed Pump FW-10 Manual Trip Latch Reset Lever, is latched. (Step 8)

CRS Enter T.S.s:

TS 2.5(1)D for two trains of AFW inoperable due to overriding and stopping AFW. This is then exited once AFW is restored to automatic.

Actions are to initiate immediate actions to restore AFW and suspend T.S.s requiring a mode change TS 2.15(3) for logic subsystem. 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months shutdown LCO.

Note: Due to time constraints, examiners might secure from this event following performance of the critical task (to isolate the inadvertent AFW flow to the steam generators). This will result in AFW flow being overridden for the next event, and should be watched by the examiners to ensure that the candidates are aware of need to restore AFW flow before intact steam generator (RC-2B) level drops below 27% WR level.

Event is terminated once AFW has been restored to automatic

Op-Test No.: _____ Scenario No.: _4___ Event No.: __8__ Page _12__ of _18__

Event

Description:

__Steam line break inside containment on RC-2A. Event is initiated at lead examiners cue.

Time Position Applicants Actions or Behavior CRS Direct entry into EOP-00 and performance of SPTAs.

ATCO Verify reactor power lowering, startup rate negative, and no more than one regulating/shutdown CEA not inserted. (Step 1.a)

ATCO Monitor for an uncontrolled RCS cooldown. (Step 1.b). Transition to contingency action.

BOPO CRS may direct BOPO to close all MSIV's due to the uncontrolled cooldown.

ATCO Emergency borate. (Step 1.2) Note: emergency boration should automatically initiate due to SIAS ATCO Ensure both FCV-269X and FCV-269Y are closed. (Step 1.2.a)

ATCO Open HCV-268, HCV-265, and HCV-258. (Step 1.2.b)

ATCO Start all boric acid and charging pumps. (Step 1.2.c)

ATCO Close LCV-218-2, VCT outlet valve. (Step 1.2.d)

ATCO Ensure LCV-218-3, HCV-257, and HCV-264 are closed. (Step 1.2.e)

ATCO Borate until adequate shutdown established. (Step 1.2.f)

BOPO Verify turbine tripped by stop and intercept valves indicating closed. (Step 2)

BOPO Ensure generator output breakers 3451-4 and 3451-5 and generator field breaker 41E/G1F are tripped. (Step 3)

BOPO Verify buses 1A3 and 1A4 are energized. (Step 4)

BOPO If SIAS has occurred, ensure both diesel generators have started. (Step 5)

BOPO Check buses 1A1 and 1A2 are energized. (Step 6)

BOPO Check 125 VDC buses 1 and 2 are energized. (Step 7)

BOPO Verify instrument air available with IA pressure greater than or equal to 90 psig and at least one air compressor operating. (Step 8)

ATCO Ensure at least one CCW pump operating with discharge pressure greater than or equal to 60 psig and at least one raw water pump operating. (Step 9.a-c)

ATCO Ensure RCP coolers CCW valves are open. (Step 9.d)

Event description is continued on next page.

Op-Test No.: _____ Scenario No.: _4___ Event No.: __8, 9__ Page _13__ of _18__

Event

Description:

__Steam line break inside containment on RC-2A. Event is initiated at lead examiners cue. SGIS fails, and manual action must be taken to isolate steam generator RC-2A.

Time Position Applicants Actions or Behavior ATCO Verify pressurizer level is 30-70%, trending to 45-60% with an RCS subcooling greater than or equal to 20 degrees. Transition to contingency.

(Step 10)

ATCO Manually control charging and letdown to restore pressurizer level. (Step 10.1.a)

ATCO Verify RCS pressure 1800-2300 psia, trending to 2050-2150 psia, and PORVs are closed. (Step 11). Transition to contingency actions.

ATCO If RCS pressure less than or equal to 1350 psia, trip one RCP in each loop. (step 11.2)

ATCO If RCS pressure less than or equal to 1600 psia, ensure emergency boration in progress and SI flow acceptable per Attachment 3. (Step 11.3.a-b)

ATCO If RCS pressure less than or equal to 1600 psia, ensure VIAS has initiated (86A/VIAS, 86B1/VIAS, 86B/VIAS, 86A1/VIAS) and CIAS has initiated (86A/CIAS, 86B1/CIAS, 86B/CIAS, 86A1/CIAS)

ATCO Manually control pressurizer heaters and spray to restore RCS pressure.

(Step 11.4)

ATCO Verify RCP NPSH requirements are satisfied, at least one RCP is operating, and core T less than or equal to 10 degrees F. (Step 12)

BOPO Verify MFW is restoring level in at least one S/G to 35-85%. (Step 13)

BOPO Ensure both feed reg valves have ramped closed. (Step 13.a)

BOPO Ensure both feed reg bypass valves have ramped to 40-45%. (Step 13.b)

BOPO Place 43/FW switch in OFF and ensure no more than one feed pump running. (Step 13.c&d)

BOPO Ensure no more than one condensate pump running and stop all heater drain pumps. (Step 13.e&f)

BOPO Ensure both sets of S/G blowdown isolation valves are closed. (Step 13.g)

Note: Due to the uncontrolled heat extraction event, the operators may have already isolated feed to RC-2A.

BOPO Verify steam dump and bypass valves are controlling both RCS Tcold 525-535 degrees F and S/G pressure 850-925 psia. (Step 14). Transition to contingency action.

Event description is continued on next page.

Op-Test No.: _____ Scenario No.: _4___ Event No.: __8, 9__ Page _14__ of _18__

Event

Description:

__Steam line break inside containment on RC-2A. Event is initiated at lead examiners cue. SGIS fails, and manual action must be taken to isolate steam generator RC-2A.

Time Position Applicants Actions or Behavior BOPO Stop cooldown by closing steam dump and bypass valves, atmospheric dump valve, and directing a local operator to check both air assisted main steam safety valves closed. (Step 14.2.a-c)

BOPO If S/G pressure less than 700 psia, isolate main steam header by closing both MSIVs and both MSIV bypass valves. (Step 14.2.d)

BOPO If S/G pressure less than or equal to 500 psia, ensure SGIS closes all of the following valves: HCV-1041A, HCV-1041C, HCV-1042A, HCV-1042C, (CT) HCV-1105, HCV-1106, HCV-1386, HCV-1385, HCV-1103, HCV-1104.

(Step 14.2.e).

Note: Critical task will be for the BOPO to take actions required by SGIS due to a failure of SGIS prior to exiting EOP-00 Step 14.2.e. The AFW-10 steam supply valve YCV-1045A is not part of SGIS and is closed later in EOP-5 step 16.

BOPO Steam S/G RC-2B prior to an uncontrolled Tcold rise of 5 degrees F or 27%WR level on RC-2A by operating air assisted main steam safety valve MS-292. (Step 14.2.f)

ATCO If Tcold is less than 500 degrees F, ensure at least one RCP is stopped.

(Step 14.3)

ATCO Verify normal containment conditions. (Step 15)

ATCO No unexpected rise in containment sump level. (Step 15.a)

ATCO Check no containment area radiation monitor alarms. (Step 15.b)

ATCO Verify RM-051, RM-052, and RM-062 not in alarm. (Step 15.c)

ATCO Verify RM-054A, RM-054B, and RM-057 are not in alarm or trending upward. (Step 15.d&e)

ATCO Verify containment pressure less than 3.0 psig and temperature less than 120 degrees F. (Step 15.f). Transition to contingency action.

ATCO Start VA-3A, VA-7C, VA-3B, VA-7D. (Step 15.f.1.1)

ATCO Ensure CCW supplied to coils of operating containment vent fans.

(Step 15.f.1.2)

ATCO If containment pressure greater than or equal to 5 psig, verify engineered safeguards are actuated. (Step 15.f.2)

ATCO Ensure emergency boration in progress. (Step 15.f.2.1)

ATCO Ensure SI flow acceptable. (Step 15.f.2.2)

Event description is continued on next page.

Op-Test No.: _____ Scenario No.: _4___ Event No.: __8, 9, 10__ Page _15__ of _18__

Event

Description:

__Steam line break inside containment on RC-2A. Event is initiated at lead examiners cue. SGIS fails, and manual action must be taken to isolate steam generator RC-2A.

When CSAS occurs, containment spray pump 3A shaft shears and pump 3B fails to automatically start, but can be started from the control room.

Time Position Applicants Actions or Behavior ATCO Ensure VIAS has initiated. (Step 15.f.2.3)

ATCO Ensure CIAS has initiated. (Step 15.f.2.4)

BOPO Ensure SGIS has closed HCV-1041A, HCV-1041C, HCV-1042A, HCV-1042C, HCV-1105, HCV-1106, HCV-1386, HCV-1385, HCV-1103, and HCV-1104. (Step 15.f.2.5)

ATCO If containment pressure is greater than or equal to 5 psig, RCS pressure is less than or equal to 1600 psia, and at least one S/G pressure is less than (CT) or equal to 500 psia, ensure containment spray is greater than or equal to 2300 gpm with only one spray pump per header. (Step 15.f.3).

Critical task is to start either containment spray pump 3B or 3C and obtain 2300 gpm flow prior to exiting this procedure step.

CRS Use Section 6.0 to determine appropriate procedure to implement. (Step 16)

CRS Determine need to transition to EOP-05, Uncontrolled Heat Extraction Event CRS Confirm SPTAs have been performed. (EOP-05, Step 1)

CRS Confirm diagnosis of UHE by verifying safety function status check acceptance criteria are being maintained. (Step 2)

CRS Implement the Emergency Plan. (Step 3)

ATCO/BOPO Monitor the floating steps. (Step 4)

ATCO If RCS pressure less than 1600 psia, containment pressure greater than 5 psig, and at least one steam generator pressure less than or equal to 500 psia, verify containment spray flow is greater than or equal to 2300 gpm with only one spray pump per header. (Step 5.a). If not performed in EOP-00, transition to contingency action.

ATCO Restore containment spray by starting the idle containment spray pumps.

(Step 5.a.1.2)

ATCO If only one CS pump is operating, ensure either HCV-344 or HCV-345 is closed. (Step 5.b). If ATCO started 3B, HCV-345 must be closed. If ATCO started 3C, either HCV-344 or HCV-345 must be closed.

ATCO Initiate containment cooling by starting all available containment vent fans and ensuring CCW is supplied to the coils of the operating vent fans. (Step 5.c)

Event description is continued on next page.

Op-Test No.: _____ Scenario No.: _4___ Event No.: __8, 9, 10__ Page _16__ of _18__

Event

Description:

__Steam line break inside containment on RC-2A. Event is initiated at lead examiners cue. SGIS fails, and manual action must be taken to isolate steam generator RC-2A.

When CSAS occurs, containment spray pump 3A shaft shears and pump 3B fails to automatically start, but can be started from the control room.

Time Position Applicants Actions or Behavior BOPO Ensure SGIS has closed valves (see above sections for list of valves).

(Step 5.d)

ATCO If RCS pressure less than or equal to 1600 psia, verify emergency boration and SI flow. (Step 6)

ATCO If containment pressure greater than or equal to 5 psig, verify CPHS, CIAS, VIAS have initiated, emergency boration in progress, and SI flow is acceptable. (Step 7.a-e)

BOPO Ensure SGIS has closed valves (see above sections for list of valves).

(Step 7.f)

ATCO Optimize SI and charging flow to RCS by operating either HPSI pumps SI-2A/B or SI-2B/C, LPSI pumps SI-1A/B, and charging pumps CH-1A/B/C.

(Step 8).

ATCO If Tcold is less than 500 degrees F, ensure at least one RCP is stopped.

(Step 9.a)

ATCO If RCS pressure is less than or equal to 1350 psia, ensure no more than 1 RCP running in each loop. (Step 9.b)

ATCO Verify normal CCW/RW system operation with at least two CCW pumps running with discharge pressure greater than or equal to 60 psig, at least 2 raw water pumps running, 3 CCW heat exchangers in service, and all RCP cooler CCW valves are open. (Step 10)

CRS N/A step 11 since affected steam generator should be identified by this time.

CRS Transition to Step 12.1 since UHE is not isolated.

ATCO Emergency borate. (Step 12.1)

BOPO Ensure SGIS has closed required valves (see earlier portion for list). (Step 13)

BOPO Identify most affected S/G by downward trends in steam pressure, level, or RCS Tcold (Step 14)

CRS Transition to Step 16.

BOPO Isolate RC-2A (Step 16)

BOPO Close the following valves: HCV-1041A, HCV-1041C, MS-291, FCV-1101, HCV-1105, HCV-1386, HCV-1103, HCV-1388A, HCV-1388B, HCV-1107A, HCV-1107B, MS-298. (Step 16.a)

Event description continues on next page.

Op-Test No.: _____ Scenario No.: _4___ Event No.: __8, 9, 10__ Page _17__ of __18_

Event

Description:

__Steam line break inside containment on RC-2A. Event is initiated at lead examiners cue. SGIS fails, and manual action must be taken to isolate steam generator RC-2A.

When CSAS occurs, containment spray pump 3A shaft shears and pump 3B fails to automatically start, but can be started from the control room.

BOPO Override and close YCV-1045A. (Step 16.b)

BOPO If sampling not in progress, close both HCV-2506A and HCV-2506B (Step 16.c)

BOPO Verify most affected steam generator is isolated. (Step 17)

BOPO Direct local operator to open breaker MCC-4C1-F03, HCV-1042C main steam bypass valve and locally open HCV-1042C. (Step 18.1.b.1-2)

BOPO Steam S/G RC-2B using steam dump and bypass valves. (Step 19)

Note: AFAS might still be overridden near the end of the scenario depending on how far they get in event 7 to restore from the inadvertent actuation of AFAS, in which case the examiners need to be sure the operators are aware of the need to align feed to RC-2B before it reaches 27% WR level.

Event can be terminated once RC-2A is isolated and decay heat is being removed by RC-2B.

Page 18 of 18 Procedure Number Procedure Title Revision OP-2A PLANT STARTUP 107 OI-FW-2 FEEDWATER SYSTEM NORMAL OPERATION 40 OI-AFW-4 AUXILIARY FEEDWATER STARTUP AND SYSTEM 84 OPERATION OI-CH-4 CHEMICAL AND VOLUME CONTROL SYSTEM MAKEUP 45 OPERATIONS ARP-CB-4/A20 44 AOP-15 LOSS OF FLUX INDICATION OR FLOW STREAMING 12 OI-RR-1 REACTOR REGULATING SYSTEM NORMAL OPERATION 29 ARP-CB-10,11/A12 12 ARP-CB-1,2,3/A4 30 ARP-CB-1,2,3/A2 38 AI-66A/A66A 13 AOP-28 AUXILIARY FEEDWATER SYSTEM MALFUNCTIONS 16 OI-AFW-2 AUXILIARY FEEDWATER SYSTEM BYPASS 9 EOP-00 STANDARD POST TRIP ACTIONS 29 EOP-05 UNCONTROLLED HEAT EXTRACTION 25

Scenario # 4 Malfunction List Event # Description Type System Command Severity Ramp 1 Start FW-4B Normal 2 Raise power to Normal 10%

3 NI-002 Fails High MALF NIS NIS36 200%

MALF NIS NIS03 FAIL 1 sec delay 4 FW-4B Trips MALF FWC BUS_1A2_8_BKR_TRIP TRUE 5 Pressurizer Level TRAN RRS RCS_LT101X 0%

fails Low 6 AC-3A trips MALF CCW BUS_1B3B_4_BKR_TRIP TRUE 7 Inadvertent AFAS MALF AFW A_RC_2A_AFAS Deenergize 8 SLB inside MALF SGN SGN01A 10%

Containment 9 SGIS Fails MALF ESF ESF27 BLOCK (preset) ESF28 BLOCK 10 SI-3B fails to start OVR ECC Sequencer switches OFF (preset)

SI-3A Shaft Shear Engineering mode drawing malfunction (preset) Ecc_SI3A_M Shaft Shear Status TRUE

ML12156A003

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