Text

9-Columbia-2017-02 Final Operating Test
	ML17081A534
Person / Time
Site:	Columbia
Issue date:	03/09/2017
From:	Vincent Gaddy; Operations Branch IV
To:	; Energy Northwest
References
	Download: ML17081A534 (352)
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ES-301 Administrative Topics Outline (Rev 2 - 01/23/17) Form ES-301-1 Facility: Columbia Generating Station Date of Examination: 2/27/17 Examination Level: RO SRO Operating Test Number: 1 Administrative Topic (see Note) Type Describe activity to be performed Code*

PERFORM ALTERNATE POWER CALCULATION WORKSHEET A-1 Conduct of Operations (N)(R)

Description:

Determines that the Core Thermal Power Validation is satisfactory by performing K/A: 2.1.20 (4.6 / 4.6) PPM 9.3.1 Attachment 7.4 (Alternate Power Calculation Worksheet).

MAIN TURBINE CHANGE OF LOAD RATE A-2 DETERMINATION Conduct of Operations (M)(P)(R)

Description:

Determine the Main Turbine Load K/A: 2.1.25 (3.9 / 4.2) Change Recommendation when raising Main Turbine load from 12% to 70%.

A-3 VALIDATE FUSE INSTALLATION PER PPM 1.3.47 (RO)

Equipment Control (N)(R)

K/A: 2.2.41 (3.5 / 3.9)

Description:

For the RO Candidate, given circumstance requiring fuse replacement and OPEX AR 00314141 an electrical print, determine correct replacement fuse and provide justification.

DETERMINE RWP/ALARA TASK TO USE A-4 FOR CLEARANCE TASK Radiation Control (N)(R)

Description:

When hanging a Clearance Order K/A: 2.3.7 (3.5 / 3.6) tag, determination the proper RWP and ALARA Task to sign on to to accomplish the task.

NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs) (0)

(N)ew or (M)odified from bank ( 1) (4)

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

Page 1 of 1

ES-301 Administrative Topics Outline (Rev 2 - 02/13/17) Form ES-301-1 Facility: Columbia Generating Station Date of Examination: 2/27/17 Examination Level: RO SRO Operating Test Number: 1 Administrative Topic (see Note) Type Describe activity to be performed Code*

DETERMINE ACTION BASED ON PLANT A-5 CONDITIONS AND PROCEDURAL GUIDANCE Conduct of Operations (D)(R)

Description:

Given equipment status and an K/A: 2.1.7 (4.4 / 4.7) electrical bus lockout, determine required operator action based on existing plant conditions.

DETERMINE THE OPERABILITY OF THE SLC SYSTEM A-6 Conduct of Operations (M)(R)

Description:

Given OSP-INST-H101 (Shift and Daily Instrument Checks for Modes 1, 2 & 3),

K/A: 2.1.25 (3.9 / 4.2) and CSP-SLC-M101 (Chemistry SLC Surveillance), determine the operability status of the Standby Liquid Control (SLC) System.

VALIDATE FUSE INSTALLATION PER PPM A-7 1.3.47 (SRO)

Equipment Control (N)(R)

Description:

For the SRO Candidate, given K/A: 2.2.41 (3.5 / 3.9) circumstance requiring fuse replacement and an electrical print, validate that the correct OPEX AR 00314141 replacement fuse was chosen and provide justification.

ESTIMATE MAIN CONDENSER AIR EJECTOR GROSS GAMMA ACTIVITY RATE A-8 AND DETERMINE ACTIONS Radiation Control (D)(P)(R)

Description:

Estimate Main Condenser air ejector Gross gamma activity rate and K/A: 2.3.11 (3.8 / 4.3) determine that a reactor power reduction is required to maintain Main Condenser Gross activity LT the LCO 3.7.5 limit.

A-9 COMPLETE CLASSIFICATION NOTIFICATION FORM (CNF) FOR SAE Emergency Plan (M)(R)

Description:

Given a dose projection printout, K/A: 2.4.41 (2.9 / 4.6) classify the event and complete Classification Notification Form. (Time Critical)

Page 1 of 2

ES-301 Administrative Topics Outline (Rev 2 - 02/13/17) Form ES-301-1 NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 4 for SROs) (2)

(N)ew or (M)odified from bank ( 1) (3)

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

Page 2 of 2

JPM A-1 INSTRUCTIONAL COVER SHEET PROGRAM TITLE LICENSED OPERATOR INITIAL TRAINING COURSE TITLE ADMIN JOB PERFORMANCE MEASURE LESSON TITLE PERFORM ALTERNATE POWER CALCULATION WORKSHEET (Admin)

LESSON LENGTH .5 HRS MAXIMUM STUDENTS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code A-1 Rev. No. 2 Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Dave E. Crawford DATE 01/31/17 REVISED BY Dave E. Crawford DATE 02/09/17 TECHNICAL REVIEW BY: DATE INSTRUCTIONAL REVIEW BY: DATE APPROVED BY: DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.

MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

N/A Setup Instructions:

Print a copy of Attachment 7.4, Alternate Power Calculation Worksheet, from PPM 9.3.1, Manual Core Heat Balance.

Have a calculator available.

JPM Instructions:

Verify current procedure against JPM. Revise JPM if any steps have changed.

Tools/Equipment: Calculator Safety Items: None Task Number: Validation Time: 15 minutes Alternate Path: No Time Critical: No PPM

Reference:

PPM 9.3.1 Rev 15 Location: Any NUREG 1123 Ref: 2.1.20 4.6 / 4.6 Performance Method: Perform Task Standard:

Determine that the Core Thermal Power Validation is satisfactory by properly calculating CTPTFSP to be between 87.6% and 87.7% ( 87.6% and 87.7%) and determining that CTPCALC - CTPTFSP is 2%.

A-1 Rev. 2 Page 2 of 8

JPM CHECKLIST INITIAL A Manual Core Heat Balance was performed in accordance with PPM 9.3.1, Manual Core Heat Balance.

CONDITIONS:

The following parameters are provided to you from PPM 9.3.1, Attachment 7.1, DATA Collection Form, and PPM 9.3.1, Attachment 7.2, Calculation of Reactor Core Power.

CTPCALC = 87.6%

MS-PI-20B (Turbine First Stage Pressure)(line 13c of attachment 7.1) = 559.2 psig

B041 (Total Steam Flow)(line 14b of attachment 7.1) = 12.9 Mlb/hr INITIATING You have been directed to perform PPM 9.3.1 Attachment 7.4, Alternate Power Calculation Worksheet, in order to validate the CUE: calculation. Select answer below and return sheet to examiner when task is complete.

A-1 Rev. 2 Page 3 of 8

Items are Critical Steps JPM Start Time: _____________

Time JPM Task Element Evaluators Cue Performance Standard Results Step Step 1 1 Record the Percent Core Thermal Records CTPCALC (87.6%) S/U Power calculated on Attachment 7.2 line 27.

Step 2 If the calculated percent CTP is GT 96% then plot the calculated percent CTP on the following figure as a Recognizes that CTP is less than 2 function of the Turbine First Stage S/U 96% and N/As the step.

Pressure computer point X365, T017 or panel indication from MS-PI-20B recorded on attachment 7.1 line 13a, 13b or 13c.

Step 3 If the calculated percent CTP is GT Recognizes that CTP is less than 3 96% and is within the acceptable area S/U 96% and N/As the step.

then the CTP validation is satisfactory.

Items are Critical Steps A-1 Rev. 2 Page 4 of 8

JPM Time Step Task Element Performance Standard Evaluators Cue Results Step 4 Substitutes turbine first stage Accept value within the range of pressure provided in the initial 87.6% to 87.7% for CTPTFSP.

If the calculated CTP is LE 96% then conditions into the formula (MS-PI-complete the following calculation to ( 87.6% and 87.7%)

20B):

calculate the expected percent CTP based on the Turbine First Stage CTPTFSP = 11.7 + (0.1358

559.2)

Pressure computer point X365, T017 4 Determines that: S / U*

or panel indication from MS-PI-20B recorded on attachment 7.1 line 13a, CTPTFSP = 87.64%

13b or 13c. Determines that:

CTPCALC (87.6%) - CTPTFSP (87.64%) = -0.04%.

Step 5 If the calculated percent CTP is GT 20% and LT 30% then verify the difference between the calculated Recognizes that power is higher than 5 percent CTP and the Turbine First S/U 30% and N/As the step.

Stage Pressure percent CTP is LE to 7%. If the difference is within 7%

then the CTP validation is satisfactory.

Items are Critical Steps A-1 Rev. 2 Page 5 of 8

JPM Time Step Task Element Performance Standard Evaluators Cue Results Step 6 Identifies that the calculated value is within the required band as follows:

If the calculated percent CTP is GE 30% and LE 96% then verify the difference between the calculated CTPCALC (87.6%) - CTPTFSP 6 percent CTP and the Turbine First (87.64%) = -0.04%. S / U*

Stage Pressure percent CTP is LE to 2%. If the difference is within 2% Determines that -0.04% is within the then the CTP validation is required 2% difference.

satisfactory.

Termination Criteria: Student hands completed Student JPM Answer Sheet to the examiner.

JPM Stop Time: _____________

Transfer the following to the Results of JPM page: Any Unsat step - indicate if step was a Critical Step; JPM completion time.

A-1 Rev. 2 Page 6 of 8

RESULTS OF JPM:

Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard:

Determine that the Core Thermal Power Validation is satisfactory by properly calculating CTPTFSP to be between 87.6% and 87.7% ( 87.6% and 87.7%) and determining that CTPCALC - CTPTFSP is 2%.

Overall Evaluation JPM Completion Time SAT / UNSAT (Circle One) Minutes COMMENTS:

Evaluator's Signature: Date:

A-1 Rev. 2 Page 7 of 8

STUDENT JPM INFORMATION CARD Initial Conditions:

A Manual Core Heat Balance was performed in accordance with PPM 9.3.1, Manual Core Heat Balance.

The following parameters are provided to you from PPM 9.3.1, Attachment 7.1, DATA Collection Form, and PPM 9.3.1, Attachment 7.2, Calculation of Reactor Core Power.

CTPCALC = 87.6%

MS-PI-20B (Turbine First Stage Pressure)(line 13c of attachment 7.1) = 559.2 psig

B041 (Total Steam Flow)(line 14b of attachment 7.1) = 12.9 Mlb/hr Initiating Cue:

You have been directed to perform PPM 9.3.1 Attachment 7.4, Alternate Power Calculation Worksheet, in order to validate the calculation.

Select answer below and return sheet to examiner when task is complete.

CTP validation was / was not (circle one) satisfactory.

A-1 Rev. 2 Page 8 of 8

Number: 9.3.1 Use Category: CONTINUOUS Major Rev: 015 Minor Rev: N/A

Title:

Manual Core Heat Balance Page: 36 of 42 ALTERNATE POWER CALCULATION WORKSHEET

1. Record the Percent Core Thermal Power calculated on Attachment 7.2 line 27. Initial 87.6%

CTPCALC = Calculated Percent Core Thermal Power = ____________

2. If the calculated percent CTP is GT 96% then plot the calculated percent CTP on the following figure as a function of the Turbine First Stage Pressure computer point X365, T017 or panel indication from MS-PI-20B recorded on attachment 7.1 line 13a, 13b or N/A 13c.

COLUMBIA ALTERNATE CTP EXPECTED 100.5 HEAT BALANCE VALIDATION FAILED 100.0

. 99.5 99.0 P E R C E N T C T P F R O M H E A T B A L A N C E (% )

98.5 H E A T B A L A N C E V A L ID A T IO N F A IL E D 98.0 97.5 ACCEPTABLE 97.0 96.5 96.0 95.5 95.0 94.5 94.0 93.5 93.0 600 605 610 615 620 625 630 635 640 645 650 655 660 665 670 TURBINE FIRST STAGE PRESSURE (PSIG) .

Attachment 7.4, Alternate Power Calculation Worksheet

Number: 9.3.1 Use Category: CONTINUOUS Major Rev: 015 Minor Rev: N/A

Title:

Manual Core Heat Balance Page: 37 of 42

3. If the calculated percent CTP is GT 96% and is within the acceptable area then the CTP N/A validation is satisfactory.

4. If the calculated CTP is LE 96% then complete the following calculation to calculate the expected percent CTP based on the Turbine First Stage Pressure computer point X365, T017 or panel indication from MS-PI-20B recorded on attachment 7.1 line 13a, 13b or Initial 13c.

CTPTFSP = 11.7 + ( 0.1358 * (Turbine First Stage Pressure) ) = % CTP 559.2 psig ) = _________

CTPTFSP = 11.7 + ( 0.1358 * (____________) 87.64 % CTP CTPCALC-TFSP = CTPCALC - CTPTFSP = _____87.6% 87.64%

__ ___ __ = _____-0.04%

5. If the calculated percent CTP is GT 20% and LT 30% then verify the difference between the calculated percent CTP and the Turbine First Stage Pressure percent CTP is LE to N/A 7%. If the difference is within 7% then the CTP validation is satisfactory.

6. If the calculated percent CTP is GE 30% and LE 96% then verify the difference between the calculated percent CTP and the Turbine First Stage Pressure percent CTP is LE to Initial 2%. If the difference is within 2% then the CTP validation is satisfactory.

7. If the CTP validation based on the Turbine First Stage Pressure was satisfactory in the Initial previous steps then the following steps are not required and may be marked N/A.

Candidate does not have to continue 8. If the Steam Flow computer point X132 was recorded on attachment 7.1 line 14a then N/A past step convert the value to MLB/HR with the following equation.

7, but may elect to do so.

Total Steam Flow = X132 / 1x106 = ______________ / 1x106 = _____________ Mlb/hr

9. If the Steam Flow computer point B041 or panel indication from RFW-FR-607 was Initial recorded on attachment 7.1 line 14b or 14c then record the value in MLB/HR below.

Total Steam Flow = B041 or RFW-FR-607 = _____________ 12.9 Mlb/hr

10. If the calculated percent CTP is GT 96% then plot the calculated percent CTP on the following figure as a function of the Total Steam Flow recorded above. N/A Attachment 7.4, Alternate Power Calculation Worksheet

Number: 9.3.1 Use Category: CONTINUOUS Major Rev: 015 Minor Rev: N/A

Title:

Manual Core Heat Balance Page: 38 of 42 COLUMBIA ALTERNATE CTP EXPECTED 100.5 HEAT BALANCE VALIDATION FAILED 100.0

. 99.5 99.0 P E R C E N T C T P F R O M H E A T B A L A N C E (% )

98.5 H E A T B A L A N C E V A L ID A T IO N F A IL E D 98.0 97.5 ACCEPTABLE 97.0 96.5 96.0 95.5 95.0 94.5 94.0 93.5 93.0 13.25 13.50 13.75 14.00 14.25 14.50 14.75 TOTAL STEAM FLOW (MLB/HR) .

11. If the calculated percent CTP is GT 96% and is within the acceptable area then the CTP N/A validation is satisfactory.

Attachment 7.4, Alternate Power Calculation Worksheet

Number: 9.3.1 Use Category: CONTINUOUS Major Rev: 015 Minor Rev: N/A

Title:

Manual Core Heat Balance Page: 39 of 42

12. If the calculated CTP is LE 96% then complete the following calculation to calculate the expected percent CTP based on the Total Steam Flow from lines 2 or 3. Initial CTPws = -4.6 + ( 8.7 * (Total Steam Flow) ) - ( 0.1 * (Total Steam Flow)2 ) = % CTP 12.9 CTPws = -4.6 + ( 8.7 * (__________) 12.9

) - ( 0.1 * (__________) 2 90.99

) = _________ % CTP 87.6%

CTPCALC-WS = CTPCALC - CTPws = __________ 90.99% = __________

- __________ -3.39%

13. If the calculated percent CTP is GT 20% and LT 30% then verify the difference between the calculated percent CTP and the Steam Flow expected percent CTP is LE to 5%. If the N/A difference is within 5% then the CTP validation is satisfactory.

14. If the calculated percent CTP is GE 30% and LE 96% then verify the difference between the calculated percent CTP and the Steam Flow expected percent CTP is LE to 4%. If the Initial difference is within 4% then the CTP validation is satisfactory.

NOTE: The Alternate Power Calculations can both fail due to operation with the Feed Water Temperature reduced below the normal value. This is a normal and expected condition during FFTR operation or with a #5 or #6 Feed Water Heater out of service.

15. If the CTP validation based on the Turbine First Stage Pressure and Total Steam Flow are both NOT satisfactory then the discrepancy should be investigated to determine the cause.

a. Review the calculations on Attachment 7.2 for potential math errors.

b. Review the input data on Attachment 7.1 for potential input data errors.

c. If the feed water temperature is more than 10 °F below the normal Feed Water Temperature displayed on the chart on the following page then no additional action is required. The Alternate Power Calculations are failed due to the Feed Water Temperature.

16. If the CTP validation based on the Turbine First Stage Pressure and Total Steam Flow are both NOT satisfactory and the cause cannot be determined then plant operation should be conservatively restricted until the discrepancies are justified. {P-123752}

Attachment 7.4, Alternate Power Calculation Worksheet

JPM A-2 INSTRUCTIONAL COVER SHEET PROGRAM TITLE OPERATIONS TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE MAIN TURBINE CHANGE OF LOAD RATE DETERMINATION (Admin)

LESSON LENGTH .5 HRS MAXIMUM STUDENTS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code A-2 Rev. No. 4 Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 10/21/14 REVISED BY Dave E. Crawford DATE 02/08/17 TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE SAT Coordinator APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use

MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

N/A Special Setup Instructions:

Ensure student has access to a calculator, ruler, and a copy of SOP-MT-START.

JPM Instructions:

Verify current procedure against JPM. Revise JPM if any steps have changed.

Tools/Equipment: Calculator; Clear Ruler Safety Items: None Task Number: RO-0325 Validation Time: 10 Minutes Alternate Path: No Time Critical: No PPM

Reference:

SOP-MT-START Rev. 26 Location: Any NUREG 1123 Ref: 2.1.25 (3.9 / 4.2) Performance Method: Perform Task Standard:

The time needed to change main turbine load has been calculated and written in the space provided on the Student JPM Information Card and is within the range allowed. Specifically, the following must be satisfied:

Correlated 12% to a First Stage Steam Temperature of 100°F (accept 95°F to 105°F)

Correlated 70% load to a First Stage Steam Temperature of 250°F (accept 245°F to 255°F)

Calculated the temperature difference (250°F - 100°F) to be 150°F (accept 140°F to 160°F)

Plotted First Stage Steam Temperature Change to Time to Change Load-Hours using the 20,000 cycles curve and determined that the time to change load is 1.1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months (accept a range of 1.05 to 1.20 hour2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months s/63 to 72 minutes).

A-2 Rev. 4 Page 2 of 6

JPM CHECKLIST INITIAL CONDITIONS: Columbia is in the process of starting up. The Main Turbine is on the line and is currently 12% loaded.

INITIATING CUE:

You have been directed to determine the time required to change load from 12% to a load of 70%. Assume a fatigue index of 20,000 cycles. Inform the CRS of your determination when complete by writing it in the space provided below and handing this sheet back to the examiner.

Items are Critical Steps Time Step Task Element Performance Standard Evaluators Cue Results JPM Start Time: ______________

1 Refers to Attachment 6.1 of SOP-MT-START.

S/U 2 SOP-MT-START Referred to example at bottom of Attachment 6.1 to determine Attachment 6.1 S/U use of graphs:

Percent Rated Load vs. First Stage Temp Change

Time to change Load vs. First Stage Temp Change 3 Correlated 12% load to a First Stage Steam Temperature of Accept a range of 95° to S/U*

100°F (accept 95°F to 105°F). 105° 4 Correlated 70% load to a First Stage Steam Temperature of Accept a range of 245° to S/U*

250°F (accept 245°F to 255°F). 255° 5 Calculated the temperature difference (250°F - 100°F) to be Accept a range of 140° to S/U*

150°F (accept 140°F to 160°F). 160° 6 Plotted First Stage Steam Temperature Change to Time to Accept a range of 1.05 S/U*

Change Load-Hours using the 20,000 cycles curve and hours to 1.2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months determined that the time to change load is 1.1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . (63 to 72 minutes)

Termination Criteria: Student hands completed JPM Information Card to the examiner.

JPM Stop Time:______________

A-2 Rev. 4 Page 3 of 6

Time Step Task Element Performance Standard Evaluators Cue Results Transfer the following to the Results of JPM page: Any Unsat step - indicate if step was a Critical Step; JPM completion time.

A-2 Rev. 4 Page 4 of 6

RESULTS OF JPM:

Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard:

The time needed to change main turbine load has been calculated and written in the space provided on the Student JPM Information Card and is within the range allowed. Specifically, the following must be satisfied:

Correlated 12% to a First Stage Steam Temperature of 100°F (accept 95°F to 105°F)

Correlated 70% load to a First Stage Steam Temperature of 250°F (accept 245°F to 255°F)

Calculated the temperature difference (250°F - 100°F) to be 150°F (accept 140°F to 160°F)

Plotted First Stage Steam Temperature Change to Time to Change Load-Hours using the 20,000 cycles curve and determined that the time to change load is 1.1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months (accept a range of 1.05 to 1.20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months ).

Overall Evaluation JPM Completion Time SAT / UNSAT (Circle One) Minutes COMMENTS:

Evaluator's Signature: Date:

A-2 Rev. 4 Page 5 of 6

STUDENT JPM INFORMATION CARD Initial Conditions:

Columbia is in the process of starting up. The Main Turbine is on the line and is currently 12% loaded.

Initiating Cue:

You have been directed to determine the time required to change load from 12% to a load of 70%.

Assume a fatigue index of 20,000 cycles.

Inform the CRS of your determination when complete by writing it in the space provided below and handing this sheet back to the examiner.

The time required to change load from 12% to 70% is:

A-2 Rev. 4 Page 6 of 6

Number: SOP-MT-START Use Category: CONTINUOUS Major Rev: 026 Minor Rev: 002

Title:

Main Turbine Start Page: 64 of 73 LOAD CHANGING RECOMMENDATIONS (HPT FIRST STAGE TEMP CHANGE) 250 12 70 150 1.1 CT-23813-A EXAMPLE (Shown on Charts)

Determine the time required and load change rate to raise load from 25% to 100%. Use a 10,000 cycle fatigue index for this example.

PROCEDURE Enter Figure 1 at 25% load and 100% load and determine from curve the first stage temperature change from 0 to 25% load to be 155° F and from 0 to 100% load to be 295° F. By subtracting the 0-25% temperature change from the 0-100% change, the first stage temperature change that occurs in raising load from 25% to 100% is 295° - 155° =140° F.

Enter Figure 2 with the 140° F first stage steam temperature change and project to the selected 10,000 cycle fatigue index curve. It is determined that load should be raised from 25% to 100% load at a uniform rate over 0.2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months (12 minutes). The load change rate is 75%/12 min.= 6%/min.

END Attachment 6.1, Load Changing Recommendations (HPT First Stage Temp Change)

2017 NRC Exam - JPM A-2 JPM KEY Page 1 of 1

JPM A-3 INSTRUCTIONAL COVER SHEET PROGRAM TITLE OPERATIONS TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE VALIDATE FUSE INSTALLATION PER PPM 1.3.47 (RO) (Admin)

LENGTH OF LESSON 0.5 Hour INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code A-3 Rev. No. 2 Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Steve Bruce DATE 12/05/16 REVISED BY Dave E. Crawford DATE 1/30/17 TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE SAT Coordinator APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use

MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

N/A Special Setup Instructions:

Obtain a cleared fuse (BUSS F10A/250V/1A) and a choice of 3 replacement fuses (BUSS F10A/250V/1A, BUSS F10A/250V/10, and BUSS F10A/250V/20A for the student to select from. Ensure the fuses look similar (same labels).

Provide a copy of EWD-15E-042 and PPM 1.3.47 (Fuse Replacement Control).

It is recommended to provide a magnifying glass to assist in reading the fuse ratings as well as containers marked with Cleared Fuse and Replacement Fuse to help them from getting mixed up for the candidate.

JPM Instructions:

Verify current procedure against JPM. Revise JPM if any steps have changed.

Tools/Equipment: Fuses (as specified above) Safety Items: None Task Number: RO-0570 Validation Time: 10 Minutes Alternate Path: No Time Critical: No PPM

Reference:

PPM 1.3.47 Rev. 11 Location: Any NUREG 1123 Ref: 2.2.41 (3.5 / 3.9) Performance Method: Perform Task Standard: Student determines that the replacement fuse should be a 10A fuse and hands the correct fuse to the CRS (evaluator). The correct fuse is marked with 250V 10A on one end and BUSS F10A on the other end.

A-3 Rev. 2 Page 2 of 7

JPM CHECKLIST SETUP: Provide the student with EWD-15E-042, PPM 1.3.47, the cleared fuse, and three choices of replacement fuses.

INITIAL CRD-LIS-601B, MS-LIS-200B, and MS-LIS-300B have lost power. Plant conditions are now stable.

CONDITIONS:

EFIN troubleshooting has identified that fuse GG-F02 in H13-P611 has cleared.

INITIATING The CRS directs you to determine the correct replacement fuse. All potential replacement fuses have come from the warehouse CUE: and have been validated for use in the plant.

Inform the CRS of your decision by completing the Student JPM Information Card provided with justification of your answer and by handing the CRS (evaluator) the card with the correct replacement fuse.

Items are Critical Steps Time JPM Task Element Performance Standard Evaluators Cue Results Step JPM Start Time: ___________

1 Evaluates EWD-15E-042. Determines that the rating for fuse S/U*

GG-F02 is 10A.

2 Evaluates the cleared fuse. Determines that the cleared fuse May not refer to cleared (blown fuse) rating is 1A. in determining the correct fuse.

Candidate must properly read 250V S/U 1A portion of fuse rating and should not read BUSS F10A portion of rating as documented in Attachment 9.1 of PPM 1.3.47.

A-3 Rev. 2 Page 3 of 7

3 Evaluates available replacement fuses Determines that the fuse marked as a May refer to PPM 1.3.47 to help by looking at the rating printed on 10A fuse is the correct fuse. identify correct fuse.

the fuse.

Candidate must properly read 250V S/U*

10A portion of fuse rating and should not read BUSS F10A portion of rating as documented in Attachment 9.1 of PPM 1.3.47.

4 Informs the CRS. Informs the CRS that the Evaluator may need to prompt the replacement for fuse GG-F02 should candidate to provide the correct be a 10A fuse and provides the replacement fuse.

correct replacement fuse to the CRS.

S/U*

Candidate should provide fuse with rating of 250V 10A to the examiner. The BUSS F10A defines the type of fuse, not the rating.

Termination Criteria: The student turns in the completed answer sheet and selected fuse for replacement to the evaluator.

JPM Stop Time: _____________

Transfer the following to the Results of JPM page: Any Unsat step - indicate if step was a Critical Step; JPM completion time.

A-3 Rev. 2 Page 4 of 7

RESULTS OF JPM:

Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: Student determines that the replacement fuse should be a 10A fuse and hands the correct fuse to the CRS (evaluator). The correct fuse is marked with 250V 10A on one end and BUSS F10A on the other end.

Overall Evaluation JPM Completion Time SAT / UNSAT (Circle One) Minutes COMMENTS:

Evaluator's Signature: Date:

A-3 Rev. 2 Page 5 of 7

STUDENT JPM INFORMATION CARD Initial Conditions:

CRD-LIS-601B, MS-LIS-200B, and MS-LIS-300B have lost power. Plant conditions are now stable.

EFIN troubleshooting has identified that fuse GG-F02 in H13-P611 has cleared.

Initiating Cue:

The CRS directs you to determine the correct replacement fuse.

All potential replacement fuses have come from the warehouse and have been validated for use in the plant.

Inform the CRS of your decision by completing the Student JPM Answer Sheet provided with justification of your answer and by handing the CRS (evaluator) the card along with the correct replacement fuse.

A-3 Rev. 2 Page 6 of 7

STUDENT JPM ANSWER SHEET The correct replacement fuse is: ________________

Provide your justification below:

A-3 Rev. 2 Page 7 of 7

Initials Verify Revision Information Prior To Use Date Number: 1.3.47 Use Category: INFORMATION Major Rev: 011 Minor Rev: 001

Title:

Fuse Replacement Control Page: 1 of 17 PCN#:

PLANT PROCEDURES MANUAL N/A Effective Date:

1.3.47*

1.3.47 12/12/14

Number: 1.3.47 Use Category: INFORMATION Major Rev: 011 Minor Rev: 001

Title:

Fuse Replacement Control Page: 2 of 17 DESCRIPTION OF CHANGES Justification (required for major revision)

Page(s) Description (including summary, reason, initiating document, if applicable)

1. Added reference to MI-1.8 Conduct of Maintenance

2. Added reference to PPM 1.3.1 OPERATING POLICIES, PROGRAMS AND PRACTICES

3. Added reference to ARCR 231072, LPCS-FCV-11 lose position indication when opening

4. Changed Plant Technical to Plant Technical Engineering at step 6.1.2.

5. Clarified search requirements in step 6.4.1d

6. Added instruction to retain and forward a blown fuse to the Fuse Program Engineer for evaluation, step 7.1.

7. Deleted step 7.3 For fuses that have labels, install fuses such that the labels are visible. This step has been iincorporated in MI-1.8 Conduct of Maintenance.

Changed reference to PPM 1.6.2 which has been superseded by SWP-DOC-01 and clarified exceptions for the exact fuse replacement, step 7.6 Minor Rev 001 - Added attachment for fuse type identification; minor reformatting.

Number: 1.3.47 Use Category: INFORMATION Major Rev: 011 Minor Rev: 001

Title:

Fuse Replacement Control Page: 3 of 17 TABLE OF CONTENTS Page 1.0 PURPOSE ................................................................................................................................ 4 2.0 DISCUSSION ........................................................................................................................... 4

3.0 REFERENCES

......................................................................................................................... 4 4.0 DEFINITIONS ........................................................................................................................... 6 4.1 Fuse Control Log Sheet ............................................................................................................ 6 4.2 Fuse Control Station ................................................................................................................. 6 4.3 Fuse Files................................................................................................................................. 6 4.4 Limitations on Use .................................................................................................................... 6 4.5 Replacement ............................................................................................................................ 6 5.0 PRECAUTIONS AND LIMITATIONS ......................................................................................... 7 6.0 RESPONSIBILITIES ................................................................................................................. 7 6.1 Maintenance Manager .............................................................................................................. 7 6.2 Fuse User/Installer ................................................................................................................... 7 6.3 Fuse Control Station Attendant/Supervisor ............................................................................... 7 6.4 Technical Services/System Engineering (Fuse Program Engineer) ........................................... 8 7.0 PROCEDURE........................................................................................................................... 9 8.0 DOCUMENTATION ................................................................................................................ 11 9.0 ATTACHMENTS..................................................................................................................... 11 9.1 Fuse Type Identification .......................................................................................................... 12 9.2 Fuse Control Log .................................................................................................................... 17

Number: 1.3.47 Use Category: INFORMATION Major Rev: 011 Minor Rev: 001

Title:

Fuse Replacement Control Page: 4 of 17 1.0 PURPOSE This procedure provides instructions and administrative controls necessary to assure control of Plant fuses and establish a record of fuse replacements.

2.0 DISCUSSION 2.1 This procedure governs replacement of all Plant fuses unless specifically exempted by procedure.

2.2 This procedure does not apply to removal and subsequent installation of the same fuse, per PPM 1.3.64.

2.3 Fuse replacement internal to discrete non-safety related end devices, such as CCTV cameras and CRTs, are not required to be entered on the Fuse Control Log Sheet.

2.4 Fuses may be drawn from the warehouse or Fuse Control Station. The Fuse Control Log Sheet, Attachment 9.2, is to be filled out regardless of where replacement fuses are obtained.

{3.3}

2.5 Fuse replacement is allowed "one time only" per event. Subsequent events will be documented via WR, WO or CR.

3.0 REFERENCES

3.1 OER 81007A (SOER 81015) Partial Loss of DC Power {3.1}

3.2 PER 294-0526, Fuse Replacement Results in Potential Damage to Valve and Motor {3.2}

3.3 PER 297-0263, Replacement Fuses Not Documented in Fuse Control Log {3.3}

3.4 PER 297-0934, INPO OE 8637, Bussmann Fuse Failure (Type KT Fuse) {P-145869}

3.5 PER 201-0155, Fuse Replacement Without Updating EW {P-175476}

3.6 RECA AU 297-058-A, Quality Audit Report {P-144582}

3.7 PER 299-0856, Inadequate Corrective Actions - Min 20 and 30 AMP Fuses 3.8 PER 205-0502, Wrong Fuse Installed 3.9 SWP-CAP-01, Corrective Action Program 3.10 SWP-MAI-01, Work Management Process Overview 3.11 MI-1.8 Conduct of Maintenance 3.12 PPM 1.3.1 OPERATING POLICIES, PROGRAMS AND PRACTICES

Number: 1.3.47 Use Category: INFORMATION Major Rev: 011 Minor Rev: 001

Title:

Fuse Replacement Control Page: 5 of 17 3.13 CR 2-05-08774, Improper Records Retention {P-235291}

3.14 PPM 1.3.42, Troubleshooting Plant Systems and Equipment 3.15 PPM 1.3.64, Plant Clearance Orders 3.16 AR-CR 231072 LPCS-FCV-11 lost position indication when opening 3.17 AR-CR 314141 CRD-LIS-601B fuse non-conforming condition

Number: 1.3.47 Use Category: INFORMATION Major Rev: 011 Minor Rev: 001

Title:

Fuse Replacement Control Page: 6 of 17 4.0 DEFINITIONS 4.1 Fuse Control Log Sheet Located at Fuse Control Station and Electric Shop for providing inventory control of installed fuses except as exempted from this procedure. Information on the Fuse Control Log Sheet is completed by the User/Installer of the fuse with review for completeness by the Fuse Control Station Attendant or Supervisor.

4.2 Fuse Control Station A location designated by the Maintenance organization where fuses are stored and issued in a controlled manner. A Fuse Control Log is maintained at the Fuse Control Station and Electric Shop.

4.3 Fuse Files Fuse Files contain the Limitations on Use and the Acceptance Tag for each fuse. The Fuse Files are located in the Fuse Control Station.

4.4 Limitations on Use Information containing special instructions or restrictions associated with use of an item.

4.5 Replacement In the context of this procedure, replacement is defined as removal of an existing fuse and installation of a new fuse.

Number: 1.3.47 Use Category: INFORMATION Major Rev: 011 Minor Rev: 001

Title:

Fuse Replacement Control Page: 7 of 17 5.0 PRECAUTIONS AND LIMITATIONS 5.1 Coordinate fuse replacement activity with Operations to assure that acceptable Plant status is maintained.

5.2 The steps in this procedure can be performed in any order.

5.3 Take special precautions when replacing a blown fuse. If the fuse cleared due to a fault, replacing the fuse could cause a high fault current.

5.4 Do not replace a fuse in a MOV circuit without first consulting Electrical Maintenance Supervision. {3.2}

5.5 Deenergize power circuits prior to fuse removal or installation with the following exceptions:

Fuses may be removed or installed under load for circuits less-than 150 volts and less-than-or-equal-to 15 amps with Shift Manager's permission

Fuses may be removed or installed under load if directed by an approved procedure or Work Request 6.0 RESPONSIBILITIES 6.1 Maintenance Manager 6.1.1 Establish the Fuse Control Station and assure completion of Fuse Control Log entries.

6.1.2 Coordinate with Plant Technical Services Engineering to facilitate quarterly technical reviews.

6.2 Fuse User/Installer 6.2.1 Perform fuse replacement under proper Plant procedures.

6.2.2 Document fuse replacement as directed by this procedure. Include information sufficient to identify the specific fuse installed.

6.3 Fuse Control Station Attendant/Supervisor 6.3.1 Review Fuse Control Log Sheets to ensure that all applicable fields are complete and maintain the fuse inventory at the fuse control station.

6.3.2 Fax or email a copy of Fuse Log to Fuse Program Engineer weekly.

6.3.3 Submit completed Fuse Log sheets to Records Control.

6.3.4 Maintain Fuse Files.

Number: 1.3.47 Use Category: INFORMATION Major Rev: 011 Minor Rev: 001

Title:

Fuse Replacement Control Page: 8 of 17 6.4 Technical Services/System Engineering (Fuse Program Engineer) 6.4.1 Retrieve and review the completed Fuse Control Log Sheets weekly to verify that Plant configuration is being maintained as designed. Perform weekly review in the following manner:

a. Collect log sheets from the Fuse Control Station.

b. Enter data from the Fuse Control Log into the master database.

c. For every fuse replacement, verify the proper fuse was installed.

d. Perform an AR search and Ops log search to ensure that there is an entry in the Fuse Log for all reported fuse replacements.

e. Search the master database of the Fuse Log for reoccurring or repeat failures.

6.4.2 Resolve recurring failures of specific fuses or other design discrepancies per applicable Plant procedures.

Number: 1.3.47 Use Category: INFORMATION Major Rev: 011 Minor Rev: 001

Title:

Fuse Replacement Control Page: 9 of 17 7.0 PROCEDURE CAUTION Fuse replacement must be coordinated with Operations to assure that acceptable Plant status is maintained.

CAUTION Do not replace fuses in an MOV circuit without first consulting Electrical Maintenance Supervision. {3.2}

7.1 Replace fuses per applicable procedures. Troubleshoot per PPM 1.3.42. Rework per SWP-MAI-01 and SWP-CAP-01, if appropriate. If conditions warrant, investigate the reason for a blown fuse prior to installing a new fuse. If the reason is known (e.g., overload, short circuit, ground, bad relay coil, etc.), document it in the Additional Information section of the Fuse Control Log. If there is no apparent reason for a blown fuse, note it in the Fuse Control Log and forward the blown fuses to the Fuse Program Engineer for evaluation IAW with MI-1.8 and PPM 1.3.1. The results of the evaluation will be entered into the comments section of the fuse log.

{AR-231072}

7.2 If no PMT is to be performed after fuse replacement, then check fuse continuity. It is preferred to check fuse continuity after installation, if practical. {P-144582}

7.3 If a fuse is found in a spared circuit, notify Maintenance Supervisor. Remove fuse after an engineering review has confirmed it is in a spared circuit.

7.4 Do not mix approved fuse types (for example FRS and TRS) in the same three-phase circuits or DC circuits.

7.5 Use the following to determine which fuses to replace:

Three phase power fuses - replace all three fuses

DC power fuses - replace both fuses

Circuits with secondary fuses (Double Fused) - replace primary and secondary fuses

Number: 1.3.47 Use Category: INFORMATION Major Rev: 011 Minor Rev: 001

Title:

Fuse Replacement Control Page: 10 of 17 7.6 Obtain replacement fuse(s) from the Fuse Control Station, use attachment 9.1 as necessary to verify fuse type and rating. Replace fuse(s) with the exact type and rating as the one being replaced. If required fuse is not available from Fuse Control Station, Warehouse 75, or the main warehouse then contact Maintenance Supervisor or Technical Services/Systems Engineering for direction. Fill out Fuse Control Log Sheet, Attachment 9.2, regardless of where replacement fuse(s) is obtained. {3.1} {3.3}

7.6.1 Two exceptions to the "replace with exact type" requirement are:

a. When an As Found fuse is known to be the wrong type and/or rating, install the correct fuse based on a review of verified design documents by the Maintenance Supervisor or Technical Services/Systems Engineering. Enter drawing reference(s) on the Fuse Control Log Sheet under "Additional Information". {3.1}

b. When an Aas found@ fuse has been shown to be the wrong size based on the results of trouble shooting, operating experience, or review of vendor documents. In this case a fuse can be used that is different than the Aas found@

fuse after obtaining Engineering approval per an approved plant process.

{P-175476}

In either of the above cases, replacement fuses shall be sized based on the fuse sizing criteria in design Engineering procedure EES-5. If the fuse sizing change impacts information on plant drawings the applicable drawings must be redlined in accordance with SWP-DOC-01 and an action request initiated to make the changes to the associated drawings.

{P-175476}, {AR-231072}

7.7 Review and comply with the Limitations on Use for the fuse. The Limitations on Use are located in the Fuse File.

7.8 Fill out Fuse Control Log Sheet, Attachment 9.2. Complete all applicable fields.

Fuse Control Log Reviewer or Supervisor Initials

Load EPN

Fuse Location

Fuse Number, Compartment Number or Circuit Number

Type and Rating of fuse removed (As Found)

Type and Rating of fuse drawn from the Fuse Control Station for installation. If installed fuse was not replaced with the exact type and rated fuse per Section 7.6, record name of person who authorized substitution in Additional Information column.

Quantity of fuses drawn for the given EPN

WR/WO number, N/A if not applicable

Number: 1.3.47 Use Category: INFORMATION Major Rev: 011 Minor Rev: 001

Title:

Fuse Replacement Control Page: 11 of 17

Name and Initials of Installer, Date of installation

Additional Information, if applicable 7.9 Return the Fuse Control Log Sheet to the Fuse Control Station Attendant or Supervisor to verify all applicable fields are completed.

8.0 DOCUMENTATION Completed Fuse Control Log Sheets satisfy all documentation requirements. Retain completed sheets in accordance with the Plant Administrative Procedures.

9.0 ATTACHMENTS 9.1 Fuse Type Identification 9.1 Fuse Log

Number: 1.3.47 Use Category: INFORMATION Major Rev: 011 Minor Rev: 001

Title:

Fuse Replacement Control Page: 12 of 17 FUSE TYPE IDENTIFICATION IDENTIFICATION OF FUSES Fuses have identifications printed on them. The printing on the fuse will identify the physical size, the type of fuse, and the fuse ratings.

There are four different systems used to identify fuses. The systems are the old military designation, the new military designation, the old commercial designation, and the new commercial designation. All four systems are presented here, so you will be able to identify a fuse no matter which designation is printed on the fuse.

You may have to replace an open fuse that is identified by one system with a good fuse that is identified by another system. The designation systems are fairly simple to understand and cross-reference once you are familiar with them.

OLD MILITARY DESIGNATION Figure 2-8 shows a fuse with the old military designation. The tables in the lower part of the figure show the voltage and current codes used in this system. The upper portion of the figure is the explanation of the old military designation. The numbers and letters in parentheses are the coding for the fuse shown in figure 2-8.

Attachment 9.1, Fuse Type Identification

Number: 1.3.47 Use Category: INFORMATION Major Rev: 011 Minor Rev: 001

Title:

Fuse Replacement Control Page: 13 of 17 Figure 2-8. - Old type military fuse designation.

The old military designation always starts with "F," which stands for fuse. Next, the set of numbers (02) indicates the style.

Style means the construction and dimensions (size) of the fuse. Following the style is a letter that represents the voltage rating of the fuse (G).

The voltage code table in figure 2-8 shows each voltage rating letter and its meaning in volts. In the example shown, the voltage ratings is G, which means the fuse should be used in a circuit where the voltage is 250 volts or less. After this is a set of three numbers and the letter "R," which represent the current rating of the fuse. The "R" indicates the decimal point. In the example shown, the current rating is 1R00 or 1.00 ampere. Some other examples of the current rating are shown in the current code table of figure 2-8. The final letter in the old military designation (A) indicates the time delay rating of the fuse.

While the old military designation is still found on some fuses, the voltage and current ratings must be "translated," since they use letters to represent numerical values. The military developed the new military designations to make fuse identification easier.

Attachment 9.1, Fuse Type Identification

Number: 1.3.47 Use Category: INFORMATION Major Rev: 011 Minor Rev: 001

Title:

Fuse Replacement Control Page: 14 of 17 NEW MILITARY DESIGNATION Figure 2-9 is an example of a fuse coded in the new military designation. The fuse identified in the example in figure 2-9 is the same type as the fuse used as an example in figure 2-8.

Figure 2-9. - New type military fuse designation.

The new military designation always starts with the letter "F," which stands for fuse. The set of numbers (02) next to this indicates the style. The style numbers are identical to the ones used in the old military designation and indicate the construction and dimensions of the fuse. Following the style designation is a single letter (A) that indicates the time delay rating of the fuse. This is the same time delay rating code as indicated in the old military designation, but the position of this letter in the coding is changed to avoid confusing the "A" for standard time delay with the "A" for ampere. Following the time delay rating is the voltage rating of the fuse (250) V. In the old military designation, a letter was used to indicate the voltage rating. In the new military designation, the voltage is indicated by numbers followed by a "V," which stands for volts or less. After the voltage rating, the current rating is given by numbers followed by the letter "A." The current rating may be a whole number (1A), a fraction (1/500 A), a whole number and a fraction (1 1/2A), a decimal (0.250A), or a whole number and a decimal (1.50A). If the ferrules of the fuse are silver-plated, the current rating will be followed by the letter "S." If any other plating is used, the current rating will be the last part of the fuse identification.

As you can see, the new military designation is much easier to understand than the old military designation.

You may find a fuse coded in one of the commercial designations.

Attachment 9.1, Fuse Type Identification

Number: 1.3.47 Use Category: INFORMATION Major Rev: 011 Minor Rev: 001

Title:

Fuse Replacement Control Page: 15 of 17 The commercial designations are fairly easy to understand and figure 2-10 shows the old and new commercial designations for the same type of fuse that was used in figures 2-8 and 2-9.

Figure 2-10. - Commercial designations for fuses:

OLD COMMERCIAL DESIGNATION Figure 2-10, view A, shows the old commercial designation for a fuse. The first part of the designation is a combination of letters and numbers (three in all) that indicates the style and time delay characteristics. This part of the designation (3AG) is the information contained in the style and time delay rating portions of military designations.

In the example shown, the code 3AG represents the same information as the underlined portions of F02 G 1R00 A from figure 2-8 (Old Military Designation) and F02A 250VIAS from figure 2-9 (New Military Designation). The only way to know the time delay rating of this fuse is to look it up in the manufacturer's catalog or in a cross-reference listing to find the military designation. The catalog will tell you the physical size, the material from which the fuse is constructed, and the time delay rating of the fuse. A 3AG fuse is a glass-bodied fuse, 1/4 inch X 1 1/4 inches (6.35 millimeters X 31.8 millimeters) and has a standard time delay rating.

Attachment 9.1, Fuse Type Identification

Number: 1.3.47 Use Category: INFORMATION Major Rev: 011 Minor Rev: 001

Title:

Fuse Replacement Control Page: 16 of 17 Following the style designation is a number that is the current rating of the fuse (1). This could be a whole number, a fraction, a whole number and a fraction, a decimal, or a whole number and a decimal.

Following the current rating is the voltage rating; which, in turn, is followed by the letter "V," which stands for volts or less (250V).

NEW COMMERCIAL DESIGNATION Figure 2-10, view B, shows the new commercial designation for fuses. It is the same as the old commercial designation except for the style portion of the coding. In the old commercial system, the style was a combination of letters and numbers. In the new commercial system, only letters are used.

In the example shown, 3AG in the old system becomes AGC in the new system. Since "C" is the third letter of the alphabet, it is used instead of the "3" used in the old system. Once again, the only way to find out the time delay rating is to look up this coding in the manufacturer's catalog or to use a cross-reference listing. The remainder of the new commercial designation is exactly the same as the old commercial designation.

END Attachment 9.1, Fuse Type Identification

Number: 1.3.47 Use Category: INFORMATION Major Rev: 011 Minor Rev: 001

Title:

Fuse Replacement Control Page: 17 of 17 Fuse Control Log (3) (2)

Installer Additional Information Fuse No, As Found Replacement New Fuse (e.g., If Fuse Is Not Comp No, or Type/Rating Type/rating WR/WO No. If Conti-nuity Used Then Give the Reviewer Load EPN Fuse Location Ckt No. (e.g., TRS (e.g., TRS (1) Applicable Check Name Reason) or N/A if not Initials (e.g., LPCS-P-2) (e.g., MC-7B) (e.g., TBL-F14) 25) 25) Qty (N/A If Not) () (Print) Init. Date applicable (1) Replace all three fuses for three phase circuits, both for DC power circuits and secondary fuses where used. Do not mix fuse types.

(2) Provide additional information as necessary to enable others to locate the specific fuse replaced and review the installation for conformance to design requirements.

(3) Fuse(s) replaced with exact type and rating as the installed fuse per Section 7.0. If installed fuse was not replaced with exact type and rated fuse, identify in the Additional Information column the name of the person who authorized the substitution per Section 7.6.

END Attachment 9.2, Fuse Control Log

JPM A-4 INSTRUCTIONAL COVER SHEET PROGRAM TITLE LICENSED OPERATOR INITIAL TRAINING COURSE TITLE ADMIN JOB PERFORMANCE MEASURE LESSON TITLE DETERMINE RWP/ALARA TASK TO USE FOR CLEARANCE TASK (Admin)

MAXIMUM STUDENTS LESSON LENGTH .5 HRS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code A-4 Rev. No. 1 Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Dave E. Crawford DATE 01/20/17 REVISED BY Dave E. Crawford DATE 02/05/17 TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.

MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

N/A Setup Instructions:

Print out copy of ATTACHMENT 1 for student use.

JPM Instructions:

Verify current procedure against JPM. If any steps have changed, the JPM should be revised.

Tools/Equipment: N/A Safety Items: N/A Task Number: Validation Time: 8 minutes Prerequisite Training: N/A Time Critical: No

Reference:

GEN-RPP-01 R8; GEN-RPP-02 R34 Location: Any NUREG 1123 Ref: 2.3.7 (3.5 / 3.6) Performance Method: Perform Task Standard: Candidate fills out the Student JPM Answer Sheet to indicate that the Ops High Rad Area (HRA) RWP 30003963 is required to be signed on to under ALARA Task # 011458161008.

SURVEY MAP REDACTED A-4 Rev. 1 Page 2 of 10

JPM CHECKLIST INITIAL Columbia Generating Station is shutdown for a refueling outage.

CONDITIONS:

INITIATING You have been directed by the Control Room Supervisor to hang Danger tag serial number 41020 as part of tagout D-HPCS-V-CUE: 102R18-001. Health Physics has been contacted. A separate Clearance Tag Hang List was previously used to hang tag serial numbers 41014 through 41019.

Review the task and from the information provided and fill out the Student JPM Answer Sheet to indicate which RWP and ALARA Task is required to be used to hang tag serial number 41020.

Give the Student JPM Answer Sheet to the evaluator when complete.

Items are Critical Steps Time JPM Task Element Performance Standard Evaluators Cue Results Step JPM Start Time: _________

Reviews the Recognizes that tag SN 41020 is to be Clearance Tag Hang hung on the HPCS-V-4 handwheel. S/U 1 List to determine component to hang tag on.

Reviews the Survey Recognizes that HPCS-V-4 is located Map for the Reactor in a High Radiation Area (HRA) and S/U Building 522 areas that a HRA Entry RWP is required.

2 to determine radiological conditions affecting HPCS-V-4.

Refers to available Determines that HRA Entry RWP #

3 choice of RWPs on 30003963 is needed to perform task. S/U*

provided card.

A-4 Rev. 1 Page 3 of 10

Refers to available Determines that ALARA Task #

choice of ALARA 011458161008 is the one to be used. S/U*

4 Tasks under HRA Entry RWP 30003963.

Records RWP and Records RWP # 30003963 and ALARA Task ALARA Task # 011458161008 on S/U*

5 numbers to Student answer sheet.

JPM Answer Sheet Termination Criteria: Student hands completed Student JPM Answer Sheet to the examiner.

JPM Stop Time: _____________

Transfer the following to the Results of JPM page: Any Unsat step - indicate if step was a Critical Step; JPM completion time.

A-4 Rev. 1 Page 4 of 10

RESULTS OF JPM:

Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: Candidate fills out the Student JPM Answer Sheet to indicate that the Ops High Rad Area (HRA) RWP 30003963 is required to be signed on to under ALARA Task # 011458161008.

Overall Evaluation JPM Completion Time SAT / UNSAT (Circle One) Minutes COMMENTS:

Evaluator's Signature: Date:

A-4 Rev. 1 Page 5 of 10

STUDENT JPM INFORMATION CARD Initial Conditions:

Columbia Generating Station is shutdown for a refueling outage.

Cue:

You have been directed by the CRS to hang Danger tag serial number 41020 as part of tagout D-HPCS-V-102R18-001.

Health Physics has been contacted.

A separate Clearance Tag Hang List was previously used to hang tag serial numbers 41014 through 41019.

Review the task and from the information provided, fill out the Student JPM Answer Sheet to indicate which RWP and ALARA Task is required to be used to hang tag serial number 41020. Provide Justification.

Give the Student JPM Answer Sheet to the evaluator when complete.

A-4 Rev. 1 Page 6 of 10

STUDENT JPM ANSWER SHEET RWP # ________________ must be signed onto to perform task.

ALARA Task # ________________ is the one to be used.

Justification:

A-4 Rev. 1 Page 7 of 10

A-4 Rev. 1 Attachment 1 Page 8 of 10

RWP Card (Front and Back)

A-4 Rev. 1 Attachment 1 Page 10 of 10

JPM A-5 INSTRUCTIONAL COVER SHEET PROGRAM TITLE LICENSED OPERATOR TRAINING COURSE TITLE JOB PERFORMANCE MEASURE DETERMINE ACTION BASED ON PLANT CONDITIONS AND LESSON TITLE PROCEDURAL GUIDANCE (SRO)(Admin)

LESSON LENGTH .5 HRS INSTRUCTIONAL MATERIALS INCLUDED LESSON PLAN PQD CODE Rev. No.

SIMULATOR GUIDE PQD CODE Rev. No.

JPM PQD CODE A-5 Rev. No. 4 EXAM PQD CODE Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 02/15/15 REVISED BY Dave E. Crawford DATE 02/07/17 TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use

MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

N/A Special Setup Instructions:

Have copies of ABN-CORE and ABN-RRC-LOSS available for student reference.

JPM Instructions:

Verify current procedure against JPM. Revise JPM if any steps have changed.

Tools/Equipment: None Safety Items: None Task Number: SRO-0659 Validation Time: 15 minutes Alternate Path: No Time Critical: No PPM

Reference:

ABN-CORE Rev. 16; Location: Any ABN-RRC-LOSS Rev. 13 NUREG 1123 Ref: 2.1.7 (4.4 / 4.7) Performance Method: Perform Task Standard:

Determine that a reactor SCRAM is required due to operating in Region A of the Power to Flow map with the OPRM inoperable, per ABN-CORE step 3.2.

JPM A-5 Rev. 4 Page 2 of 6

JPM CHECKLIST INITIAL With Columbia operating at full power, a common cause failure of the OPRMs required the CRS to direct placing both OPRM CONDITIONS Manual Enable/Bypass switches in the BYPASS position. Three hours later a lockout on SH-5 occurs.

The following plant conditions are reported by CRO1: Reactor power 50%. Active loop drive flow is 27500 gpm. Rod line is 85%.

INITIATING From the information given, determine the procedural action required. On the Student JPM Answer Sheet provided, indicate what that action is and provide the procedural reference (including step) for that action. When completed hand the Student JPM Answer CUE: Sheet back to the examiner.

Items are Critical Steps Time Step Element Standard Evaluators Cue Sat/Unsat JPM Start Time: _____________

1 Plots operating points given. Determines operation is now in Region A of the Single Loop Power to Flow map (using S/U*

Attachment 6.1 of ABN-RRC-LOSS).

2 Determines required procedural Refers to ABN-CORE (Step 3.2) and determines action based on conditions given. that a manual reactor scram is required due to operating in Region A of the Power to Flow map S/U*

with the OPRMs inoperable.

3 Fills out answer sheet. Indicates that a Manual Scram is required per ABN-CORE (Step 3.2). S/U*

4 Fills out answer sheet (reason). Indicates that a scram is required because of operation in Region A of the Power to Flow map S/U*

with the OPRMs inoperable.

Termination Criteria: Student hands completed Student JPM Answer Sheet to the examiner.

JPM Stop Time: _____________

Transfer the following to the Results of JPM page: Any Unsat step(s) and JPM completion time.

JPM A-5 Rev. 4 Page 3 of 6

JPM RESULTS:

Examinee (Print): _________________________________________________________________

Evaluator (Print): _________________________________________________________________

Task Standard: Determine that a reactor SCRAM is required due to operating in Region A of the Power to Flow map with the OPRM inoperable, per ABN-CORE step 3.2.

Overall Evaluation JPM Completion Time SAT / UNSAT (Circle One) Minutes COMMENTS:

Evaluator's Signature: Date:

JPM A-5 Rev. 4 Page 4 of 6

STUDENT JPM INFORMATION CARD Initial Conditions:

With Columbia operating at full power, a common cause failure of the OPRMs required the CRS to direct placing the OPRM Manual Enable/Bypass switches in the BYPASS position.

Three hours later a lockout on SH-5 occurs.

The following plant conditions are reported by CRO1:

Reactor power is 50%.

Active loop drive flow is 27500 gpm

Rod line is 85%

Initiating Cue:

From the information given, determine the procedural action required.

On the Student JPM Answer Sheet provided, indicate what that action is and provide the procedural reference (including step) for that action. Also include the reason for that action.

When completed hand the Student JPM Answer Sheet back to the examiner.

JPM A-5 Rev. 4 Page 5 of 6

STUDENT JPM ANSWER SHEET The action required is:

The reason for the action is:

The action is per procedure/step: _____________/_______

JPM A-5 Rev. 4 Page 6 of 6

Number: ABN-RRC-LOSS Use Category: CONTINUOUS Major Rev: 013 Minor Rev: N/A

Title:

Loss of Reactor Recirculation Flow Page: 30 of 32 SINGLE LOOP POWER/FLOW MAP END Attachment 6.1, Single Loop Power/Flow Map

JPM A-6 INSTRUCTIONAL COVER SHEET PROGRAM TITLE LICENSED OPERATOR/STA REQUALIFICATION TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE DETERMINE THE OPERABILITY OF THE SLC SYSTEM (SRO)(Admin)

MAXIMUM STUDENTS LESSON LENGTH .5 HRS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code A-6 Rev. No. 3 Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Dave E. Crawford DATE 02/03/17 REVISED BY DATE TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.

MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

N/A Special Setup Instructions:

Print out a filled out copy of OSP-INST-H101. The only remaining steps of the procedure should be steps 53, 54, and 55. Print out a fully completed copy of CSP-SLC-M101 that indicates Boron Concentration of 14.3

% weight. Have both available for student reference.

JPM Instructions:

Verify current procedure against JPM. Revise JPM if any steps have changed.

The evaluator and student will use current procedure. The evaluator should mark off steps as they are completed, note comments, and transfer the comments to the Results of JPM page.

Tools/Equipment: N/A Safety Items: N/A Task Number: SRO-0163 Validation Time: 10 Minutes Prerequisite Training: N/A Time Critical: No PPM

Reference:

OSP-INST-H101 Rev. 86 Location: Any CSP-SLC-M101 Rev. 14 NUREG 1123 Ref: 2.1.25 (3.9 / 4.2) Performance Method: Perform Task Standard:

Determine that SLC is NOT operable per step #53 of OSP-INST-H101 by graphing SLC Temperature (64°F) vs. SLC Tank Concentration (14.3 % weight) in the Unacceptable Operation region on Attachment 9.6.

A-6 Rev. 3 Page 2 of 6

JPM CHECKLIST INITIAL The plant is operating at 100% power.

CONDITIONS:

Chemistry added water to the SLC tank 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ago and have just completed surveillance CSP-SLC-M101, Standby Liquid Control Boron Concentration Test.

SLC-TIC-2 indicates 64°F SLC-LI-601, SLC-LI-1 and TDAS X077 all indicate 4900 gallons.

INITIATING CUE: Determine SLC Operability and provide justification for your answer on this information card.

Return this sheet to evaluator when complete.

Items are Critical Steps Time Step Element Standard Sat/Unsat JPM Start Time: _____________

1 Reviews copy of CSP-SLC-M101. Determines from Attachment 9.1 of CSP-SLC-M101, that SLC concentration is 14.3 weight S/U*

% Boron 2 Reviews OSP-INST-H101 step #53. Determines the need to use ATT. 9.6 for comparison. S/U 3 Reviews ATT. 9.6 of OSP-INST-H101 Determines SLC concentration/temperature is outside of the acceptable region. Refers to S/U*

NOTE 4.

4 Reviews OPS-INST-H101 step #55. Determines the need to use Att. 9.7 for S/U comparison.

5 Reviews ATT. 9.7 of OPS-INST-H101. Determines SLC Tank volume is acceptable.

S/U A-6 Rev. 3 Page 3 of 6

Items are Critical Steps Time Step Element Standard Sat/Unsat 6 Fills in answer sheet. Fills in answer sheet that SLC is NOT S/U*

operable.

Termination Criteria: Student hands completed Student JPM Answer Sheet to the examiner.

JPM Stop Time: _____________

Transfer the following to the Results of JPM page: Any Unsat step - indicate if step was a Critical Step; JPM completion time.

A-6 Rev. 3 Page 4 of 6

RESULTS OF JPM:

Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: Determine that SLC is NOT operable per step #53 of OSP-INST-H101 by graphing SLC Temperature (64°F) vs. SLC Tank Concentration (14.3 % weight) in the Unacceptable Operation region on Attachment 9.6.

Overall Evaluation JPM Completion Time SAT / UNSAT (Circle One) Minutes COMMENTS:

Evaluator's Signature: Date:

A-6 Rev. 3 Page 5 of 6

STUDENT JPM INFORMATION CARD Initial Conditions:

The plant is operating at 100% power.

Chemistry added water to the SLC tank 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ago and have just completed surveillance CSP-SLC-M101, Standby Liquid Control Boron Concentration Test.

SLC-TIC-2 indicates 64 °F SLC-LI-601, SLC-LI-1 and TDAS X077 all indicate 4900 gallons.

Cue:

Determine SLC Operability and provide justification for your answer on this information card.

Return this sheet to evaluator when complete.

ANSWER The SLC System is:

OPERABLE NOT OPERABLE Justification for answer:

A-6 Rev. 3 Page 6 of 6

JPM A-7 INSTRUCTIONAL COVER SHEET PROGRAM TITLE OPERATIONS TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE VALIDATE FUSE INSTALLATION PER PPM 1.3.47 (SRO) (Admin)

LENGTH OF LESSON 0.5 Hour INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code A-7 Rev. No. 2 Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Steve Bruce DATE 12/05/16 REVISED BY Dave E. Crawford DATE 1/30/17 TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE SAT Coordinator APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use

MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

N/A Special Setup Instructions:

Obtain a cleared fuse (BUSS F10A/250V/1A) and a choice of 3 replacement fuses (BUSS F10A/250V/1A, BUSS F10A/250V/10, and BUSS F10A/250V/20A for the student to select from. Ensure the fuses look similar (same labels).

Provide a copy of EWD-15E-042 and PPM 1.3.47 (Fuse Replacement Control).

It is recommended to provide a magnifying glass to assist in reading the fuse ratings as well as containers marked with Cleared Fuse and Replacement Fuse to help them from getting mixed up for the candidate.

JPM Instructions:

Verify current procedure against JPM. Revise JPM if any steps have changed.

Tools/Equipment: Fuses (as specified above) Safety Items: None Task Number: SRO-0212 Validation Time: 10 Minutes Alternate Path: No Time Critical: No PPM

Reference:

PPM 1.3.47 Rev. 11 Location: Any NUREG 1123 Ref: 2.2.41 (3.5 / 3.9) Performance Method: Perform Task Standard: Student determines that the replacement fuse should be a 10A fuse and hands the correct fuse to the SM (evaluator). The correct fuse is marked with 250V 10A on one end and BUSS F10A on the other end.

A-7 Rev. 2 Page 2 of 7

JPM CHECKLIST SETUP: Provide the student with EWD-15E-042 (see Attachment 1), PPM 1.3.47, the cleared fuse, and three choices of replacement fuses.

INITIAL CRD-LIS-601B, MS-LIS-200B, and MS-LIS-300B have lost power. Plant conditions are now stable.

CONDITIONS:

EFIN troubleshooting has identified that fuse GG-F02 in H13-P611 has cleared.

INITIATING The SM directs you as the FIN Team SRO to independently validate the correct replacement fuse. All potential replacement fuses CUE: have come from the warehouse and have been validated for use in the plant.

Inform the SM of your decision by completing the JPM Answer Sheet provided with justification of your answer and by handing the SM (evaluator) the correct replacement fuse.

Items are Critical Steps Time JPM Task Element Performance Standard Evaluators Cue Results Step Start Time: ____________

1 Evaluates EWD-15E-042 Determines that the rating for fuse S/U*

(Attachment 1). GG-F02 is 10A.

2 Evaluates the cleared fuse. Determines that the cleared fuse May not refer to cleared (blown fuse) rating is 1A. in determining the correct fuse.

Candidate must properly read 250V S/U 1A portion of fuse rating and should not read BUSS F10A portion of rating as documented in Attachment 9.1 of PPM 1.3.47.

A-7 Rev. 2 Page 3 of 7

3 Evaluates available replacement fuses Determines that the fuse marked as a May refer to PPM 1.3.47 to help by looking at the rating printed on 10A fuse is the correct fuse. identify correct fuse.

the fuse.

Candidate must properly read 250V S/U*

10A portion of fuse rating and should not read BUSS F10A portion of rating as documented in Attachment 9.1 of PPM 1.3.47.

4 Informs the SM. Informs the SM that the replacement Evaluator may need to prompt the for fuse GG-F02 should be a 10A candidate to provide the correct fuse and provides the correct replacement fuse.

replacement fuse to the SM.

S/U*

Candidate should provide fuse with rating of 250V 10A to the examiner. The BUSS F10A defines the type of fuse, not the rating.

Termination Criteria: The student turns in the completed answer sheet and selected fuse for replacement.

JPM Stop Time: ____________

Transfer the following to the Results of JPM page: Any Unsat step - indicate if step was a Critical Step; JPM completion time.

A-7 Rev. 2 Page 4 of 7

RESULTS OF JPM:

Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: Student determines that the replacement fuse should be a 10A fuse and hands the correct fuse to the SM (evaluator). The correct fuse is marked with 250V 10A on one end and BUSS F10A on the other end.

Overall Evaluation JPM Completion Time SAT / UNSAT (Circle One) Minutes COMMENTS:

Evaluator's Signature: Date:

A-7 Rev. 2 Page 5 of 7

STUDENT JPM INFORMATION CARD Initial Conditions:

CRD-LIS-601B, MS-LIS-200B, and MS-LIS-300B have lost power.

Plant conditions are now stable.

EFIN troubleshooting has identified that fuse GG-F02 in H13-P611 has cleared.

Initiating Cue:

The SM directs you as the FIN Team SRO to independently validate the correct replacement fuse.

All potential replacement fuses have come from the warehouse and have been validated for use in the plant.

Inform the SM of your decision by completing the Student JPM Answer Sheet provided with justification of your answer and by handing the SM (evaluator) the card along with the correct replacement fuse.

A-7 Rev. 2 Page 6 of 7

STUDENT JPM ANSWER SHEET The correct replacement fuse is: ________________

Provide your justification below:

A-7 Rev. 2 Page 7 of 7

JPM A-8 INSTRUCTIONAL COVER SHEET INITIAL LICENSED OPERATOR TRAINING PROGRAM TITLE ADMIN JOB PERFORMANCE MEASURE COURSE TITLE ESTIMATE MAIN CONDENSER AIR EJECTOR GROSS GAMMA LESSON TITLE ACTIVITY RATE AND DETERMINE ACTIONS (SRO)(Admin)

LESSON LENGTH .5 HRS MAXIMUM STUDENTS 1 INSTRUCTIONAL MATERIALS INCLUDED Lesson Plan PQD Code Rev. No.

Simulator Guide PQD Code Rev. No.

JPM PQD Code A-8 Rev. No. 8 Exam PQD Code Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 10/21/06 REVISED BY Dave E. Crawford DATE 02/10/17 TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use.

A-8 Rev. 8 Page 1 of 8

MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

N/A Setup Instructions:

Provide student a calculator and access to ABN-OG.

JPM Instructions:

Verify current procedure against JPM. If any steps have changed, the JPM should be revised.

Tools/Equipment: Calculator Safety Items: N/A Task Number: SRO-0658 Validation Time: 10 minutes Alternate Path: No Time Critical: No PPM

Reference:

ABN-OG Rev. 4 Location: Any NUREG 1123 Ref: 2.3.11 (3.8 / 4.3) Performance Method: Perform Task Standard: Main Condenser air ejector gross gamma activity rate has been properly calculated per ABN-OG, step 4.1.4 and used to justify reactor power reduction as directed by ABN-OG, step 4.1.5.

A-8 Rev. 8 Page 2 of 8

JPM CHECKLIST INITIAL Columbia is operating at full power. Various alarms are locked in due to suspected fuel pin damage.

CONDITIONS:

OFFGAS POST TREATMENT RADIATION MONITOR, OG-RIS-601A, is in alarm.

Refer to the parameters indicated on the attached handout.

INITIATING Based on the above information, determine what action, if any, should be taken. Fill in the result of your conclusion on the CUE: attachment provided.

Items are Critical Steps Time JPM Task Element Performance Standard Evaluators Cue Results Step Start Time: ___________

1 Determines procedure. Recognizes entry condition into ABN-OG and refers to procedure. S/U 2 Reviews radiation readings on Determines that radiation readings are normal and WEA-RIS-14, RW Building Vent entry into section 4.2 of ABN-OG is not required.

Exhaust Rad Monitor, and TEA- Determines that section 4.1 should be used.

RIS-13, Turbine Building Vent S/U Exhaust Rad Monitor, as indicated on handout.

A-8 Rev. 8 Page 3 of 8

3 ABN-OG Step 4.1.4 Estimate Main Condenser air Determines OG-RR-604 indication on handout reads ejector gross gamma activity rate 7.8E+03 (7800) mr/Hr.

using the following formula:

[OG Pretreatment (mRem/hr) S/U*

(OG-RR-604)] X [OG System flow (scfm) (OG-FR-620)] divided by 1000 = Main Condenser Gross gamma activity (mCi/sec).

4 ABN-OG Step 4.1.4 Estimate Main Condenser air Determines OG-FR-620 indication on handout reads ejector gross gamma activity rate 43.0 SCFM.

using the following formula:

[OG Pretreatment (mRem/hr) (OG- S/U*

RR-604)] X [OG System flow (scfm) (OG-FR-620)] divided by 1000 = Main Condenser Gross gamma activity (mCi/sec).

5 ABN-OG Step 4.1.4 Estimate Main Condenser air Multiplies 7800 x 43.0 = 335,400.

ejector gross gamma activity rate using the following formula:

[OG Pretreatment (mRem/hr) (OG- S/U*

RR-604)] X [OG System flow (scfm) (OG-FR-620)] divided by 1000 = Main Condenser Gross gamma activity (mCi/sec).

A-8 Rev. 8 Page 4 of 8

6 ABN-OG Step 4.1.4 Estimate Main Condenser air Divides 355,400 by 1000 = 335.4 (mCi/sec) ejector gross gamma activity rate using the following formula:

[OG Pretreatment (mRem/hr) (OG- S/U*

RR-604)] X [OG System flow (scfm) (OG-FR-620)] divided by 1000 = Main Condenser Gross gamma activity (mCi/sec).

7 ABN-OG Step 4.1.5 Based on a Main Condenser Gross gamma activity reading of 335.4 mCi/sec, candidate determines that a Determines required action. power reduction per PPM 3.2.4 to maintain Main S/U*

Condenser Gross gamma activity LT 332 mCi/sec is required.

Termination Criteria: Hands the JPM Answer Sheet to the examiner.

JPM Stop Time:______________

Transfer the following to the Results of JPM page: Any Unsat step - indicate if step was a Critical Step; JPM completion time.

A-8 Rev. 8 Page 5 of 8

RESULTS OF JPM:

Examinee (Please Print): ______________________________________________

Evaluator (Please Print): ______________________________________________

Task Standard: Main Condenser air ejector gross gamma activity rate has been properly calculated per ABN-OG, step 4.1.4 and used to justify reactor power reduction as directed by ABN-OG, step 4.1.5.

Overall Evaluation JPM Completion Time SAT / UNSAT (Circle One) Minutes COMMENTS:

Evaluator's Signature: Date:

A-8 Rev. 8 Page 6 of 8

STUDENT JPM INFORMATION CARD Initial Conditions:

Columbia is operating at full power. Various alarms are locked in due to suspected fuel pin damage.

OFFGAS POST TREATMENT RADIATION MONITOR, OG-RIS-601A, is in alarm.

Refer to the parameters indicated on the attached handout.

Cue:

Based on the above, determine what action, if any, should be taken.

Fill in the result of your conclusion on the JPM Answer Sheet. Hand the JPM Answer Sheet to your examiner when complete.

A-8 Rev. 8 Page 7 of 8

JPM ANSWER SHEET INITIAL HERE IF NO ACTIONS ARE REQUIRED:

REASON NO ACTIONS ARE REQUIRED:

INITIAL HERE IF ACTIONS ARE REQUIRED:

ACTION(S) IF REQUIRED AND REASON FOR ACTION:

A-8 Rev. 8 Page 8 of 8

A-8 (rev 8) Attachment 1 Page 1 of 3

WEA-RIS-14 A-8 (rev 8) Attachment 1 Page 2 of 3

TEA-RIS-14 A-8 (rev 8) Attachment 1 Page 3 of 3

JPM A-9 INSTRUCTIONAL COVER SHEET PROGRAM TITLE LICENSED OPERATOR TRAINING COURSE TITLE JOB PERFORMANCE MEASURE LESSON TITLE COMPLETE CLASSIFICATION NOTIFICATION FORM (SAE) (SRO)(TC)(Admin)

LESSON LENGTH .5 HRS INSTRUCTIONAL MATERIALS INCLUDED LESSON PLAN PQD CODE Rev. No.

SIMULATOR GUIDE PQD CODE Rev. No.

JPM PQD CODE A-9 Rev. No. 9 EXAM PQD CODE Rev. No.

DIVISION TITLE Nuclear Training DEPARTMENT Operations Training PREPARED BY Ron Hayden DATE 05/10/01 REVISED BY Dave E. Crawford DATE 2/10/17 TECHNICAL REVIEW BY DATE INSTRUCTIONAL REVIEW BY DATE SAT Coordinator APPROVED BY DATE Operations Training Manager Verify materials current IAW SWP-TQS-01 prior to use A-9 Rev. 9 Page 1 of 6

MINOR REVISION RECORD Minor Description Affected Entered Effective Manager Rev Number of Revision Pages By Date Approval JPM SETUP Simulator ICs; Malfunctions; Triggers; Overrides:

N/A Special Setup Instructions:

Provide for student a completed URI Dose Assessment (with emergency classification hidden) that supports the administration of this JPM and a blank copy of the paper Classification Notification Form (Form 24075 R24).

JPM Instructions:

Verify Current Procedure against JPM. If any steps have changed, the JPM should be revised.

Tools/Equipment: None Safety Items: None Task Number: SRO- 0315, 0529, 0638 Validation Time: 12 Minutes Alternate Path: No Time Critical: Yes 30 Minutes PPM

Reference:

PPM 13.8.1 Rev. 36 Location: Simulator NUREG 1123 Ref: 2.4.41 (2.9/4.6) Performance Method: Perform Task Standard: Applicant classifies event as a SAE (5.1.S.2) within 15 minutes due to Thyroid CDE dose at 1.2 miles of GT 500 mrem. Applicant correctly completes and submits Classification Notification Form within 15 minutes of classification.

A-9 Rev. 9 Page 2 of 6

JPM CHECKLIST INITIAL The plant has experienced an event that has resulted in the following conditions: The plant scrammed an hour ago. A release has CONDITIONS: been ongoing for 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months and 44 minutes. Release rate is stable. A URI Does Assessment has been performed.

INITIATING The Shift Manager has directed you to complete the Classification Notification Form based only upon the results of the completed CUE: Dose Assessment. This is the initial classification of this event. Present the completed CNF to the Shift Manager for signature. This is a Time Critical JPM and your time starts now.

Items are Critical Steps Time Step Element Standard Evaluators Cue Sat/Unsat JPM (Classification) Start Time: _______________________

1 Classifies event Classifies event as a SAE within 15 minutes based upon Thyroid CDE S/U*

dose at 1.2 miles of GT 500 mrem.

NOTE: THIS STOPS THE FIRST 15 MINUTE CLOCK AND STARTS THE NEXT 15 MINUTE NOTIFICATION CLOCK Classification Stop Time / Notification Start Time: _______________________

2 Completes Classification Notification Fills in following information on the S/U Form. CNF:

3 Block 1 Checks b. (Drill) S/U 4 Block 2 Enters a 1 S/U*

5 Block 3 Enters a name S/U*

6 Block 4 Checks a. (Initial Classification) and enters a date and time S/U*

7 Block 5 Checks c. (Site Area Emergency)

S/U*

8 Block 6 Determines that this block is N/A due to classification not being a General S/U*

Emergency A-9 Rev. 9 Page 3 of 6

Items are Critical Steps Time Step Element Standard Evaluators Cue Sat/Unsat 9 Block 7 Checks No S/U*

10 Block 8 Enters 7 for Wind Speed S/U*

11 Block 8 Enters 300 for degrees S/U*

12 Block 8 Checks No for Precipitation S/U*

13 Block 8 Enters A as Stability Classification S/U*

14 Block 9 Checks Release S/U*

15 Block 10 Checks Airborne S/U*

16 Block 11 Enters a date and time for Estimated Start of Release (3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months 44 minutes S/U*

ago) 17 Block 12 Checks Yes.

Checks 250mr/hr Thyroid -OR-S/U*

Checks Unfiltered or Unmonitored Release 18 Block 13 Enters 5.1.S.2 for EAL#

S/U*

19 Block 14 Checks b.

S/U JPM (Notification) Stop Time:____________________

Termination Criteria: Student hands the examiner the completed CNF.

Transfer the following to the Results of JPM page: Any Unsat step - indicate if step was a Critical Step; JPM completion time.

A-9 Rev. 9 Page 4 of 6

RESULTS OF JPM Examinee (Print): _________________________________________________________________

Evaluator (Print): _________________________________________________________________

Task Standard: Applicant classifies event as a SAE (5.1.S.2) within 15 minutes due to Thyroid CDE dose at 1.2 miles of GT 500 mrem. Applicant correctly completes and submits Classification Notification Form within 15 minutes of classification.

Overall Evaluation JPM Completion Time SAT / UNSAT (Circle One) Minutes COMMENTS:

Evaluator's Signature: Date:

A-9 Rev. 9 Page 5 of 6

STUDENT JPM INFORMATION CARD Initial Conditions:

The plant has experienced an event that has resulted in the following conditions:

The plant scrammed an hour ago

A release has been ongoing for 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months and 44 minutes

Release rate is stable.

A URI Dose Assessment has been performed.

Initiating Cue:

The Shift Manager has directed you to complete a Classification Notification Form based only on the results of the completed Dose Assessment.

This is the initial classification of this event.

Present the completed CNF to the Shift Manager for signature.

THIS IS A TIME CRITICAL JPM and your time starts now A-9 Rev. 9 Page 6 of 6

From: Gaddy, Vincent To: Farina, Thomas

Subject:

RE: CGS Request for Modification of JPM A-9 Critical Step Date: Monday, March 13, 2017 9:01:33 AM TJ, I agree with your assessment and recommendation.

Vince From: Farina, Thomas Sent: Wednesday, March 08, 2017 11:00 AM To: Gaddy, Vincent <Vincent.Gaddy@nrc.gov>

Subject:

CGS Request for Modification of JPM A-9 Critical Step

Vince, Following administration of JPM A-9 onsite last week, CGS requested a change to one of the approved critical steps. Specifically, JPM stem 17 is a critical step which requires that an applicant identify that requirements for distribution of KI tablets are met, and check off the reason that the requirements are met on the offsite notification form. KI requirements are met for 2 separate reasons: 1) estimated dose rate to thyroid exceeds 250 mr/hr at site boundary, and 2) unfiltered or unmonitored release in progress. The approved JPM step requires that the applicant check both reasons in order to pass the step and JPM. The licensee requests that this step be modified to an or statement, meaning that if the applicant checks either reason, the JPM step is satisfied. Ive attached their request, the proposed modification to the JPM, and the JPM key.

I support this request from the licensee. Whether an applicant identifies only one reason or both, the same PAR recommendation is submitted to offsite authorities. Ill use your response to this email as justification to modify the JPM step or leave as-is.

Thanks, Please call me if you have questions, TJ

TIMES RECORDED ON FORM ARE BASED ON START TIME OF JPM.

1 Type of Event: 2 COLUMBIA GENERATING STATION

a. Emergency 1

b. X Drill CLASSIFICATION NOTIFICATION FORM (CNF) No:

3 4 Classification/Status Time: Date:

Notification Provided By: Phone:

(Emergency Director) a. X Initial Classification Time Date Name (Print): (509) b. Reclassification Print Name c. Termination

d. PAR Changes/Additions

e. Information Section Map 5 a. UNUSUAL EVENT No Offsite Protective Actions Recommended

b. ALERT No Offsite Protective Actions Recommended

c. X SITE AREA EMERGENCY Automatic Protective Action Recommendation EVACUATE:

Columbia River Ringold Fishing Area Wahluke Hunting Area Schools in EPZ Horn Rapids Recreation Area/ORV Park

d. GENERAL EMERGENCY Automatic Protective Action Recommendation EVACUATE:

Columbia River Ringold Fishing Area Wahluke Hunting Area Schools in EPZ Horn Rapids Recreation Area/ORV Park 8 Meteorological Data: 6 PROTECTIVE ACTION RECOMMENDATIONS Wind Speed: 7 mph from 300 degrees IF a General Emergency is declared, Precipitation: Yes X No THEN Refer to PPM 13.2.2 Determining PARs.

Stability Classification A IF A GE is NOT declared, This section is Not Applicable 9 No Release(Block 10,11&12 are N/A) X Release Basis for PARs: X Not Applicable Radiological Plant Type of release: 11 Estimated Start of Release: 0-2 miles 2-10 miles 10 N/A N/A Start Time - 3 hr 44min All Sections Section 1 Section 2 Section 3 Section 4 X Airborne Time/Date: Time/Date Monitor & Monitor & Monitor & Monitor &

Prepare Prepare Prepare Prepare Water Release Terminated: Shelter In Shelter In Shelter In Shelter In Shelter In Time/Date: Place Place Place Place Place Evacuate Evacuate Evacuate Evacuate Evacuate 12 State Criteria met for administering KI(Information only) 7 Security Event: Yes X No N/A Responding personnel are to report to:

No On-Site Facilities X Yes X 250 mrem/hr thyroid Alternate Facilities, Energy Northwest Office Complex, 1.4 x 10-7 ci/cc I-131 3000 George Washington Way X Unfiltered or unmonitored release 13 EAL# Description; Offsite Release 5.1.S.2 Additional Information; 14 Prognosis of Situation: a. Unknown b. X Stable c. Escalating d. Improving 15 Emergency Director Approval Signature:

24075 R24

Completion of Classification Notification Form (CNF)

Completing the form Block 1. Type of event: For actual emergencies, the block Emergency should be checked.

For drills or exercises, the block Drill should be checked.

Block 2. Classification Form Number: This is a sequential number indicating the order of offsite notifications.

The first CNF is #1 followed by #2, etc.

Block 3. Notification provided by. This is the name of the Emergency Director providing the information for the Crash call. Phone number is the number at which the notifier can be contacted.

Block 4. Classification/Statues: a-e.

Item a or b: The time listed is the time at which the ED declares the emergency classification or upgrade.

This time starts the 15-minute notification requirement.

Item c.: Termination, no Classification Level should exist or be marked.

A CNF and Crash must be initiated at the termination of a drill or actual event.

Item d.: If additional PARs are required after the CNF for the GE has been transmitted, complete this block.

The need for additional PARs requires notifications be completed within 15 minutes of the time in the block.

Item e.: Periodic information updates such as release information, KI, prognosis, and changes in Met conditions should be provided at least once an hour.

Block 5. Check block for appropriate emergency classification.

(UNUSUAL EVENT, ALERT, SITE AREA EMERGENCY, GENERAL EMERGENCY)

Block 6. When a General Emergency is declared, Refer to PPM 13.2.2 Determining Protective Action Recommendations, Check applicable sections/actions and communicated during the Crash call for the GE.

If a GE is NOT declared, this section is N/A and does NOT need to be filled in.

Block 7. Identify whether the event is security based (Auto Dialer Scenario 191) and reporting location for Offsite Response Organization (ie. County and State Personnel) responding to CGS.

Block 8. Enter Meteorological data. Following a release, if meteorological data changes ensure additional PARs are considered and provide offsite notification. To convert Delta T to stability class, refer to PPM 13.8.1.

Block 9. If there is a No RELEASE, then blocks 10, 11 & 12 are N/A.

If there is a RELEASE then enter information in blocks 10, 11 & 12.

If RELEASE starts after CNF and CRASH notification has been completed, then provide new CNF and Crash notifications to offsite agencies as soon as RELEASE Criteria has been met.

Block 10. If there is a RELEASE, mark it as airborne or water.

Block 11. If there is a RELEASE, enter the start time. Enter stop time following release termination.

Block 12. The block with information on the States criteria for KI is an information notification not a PAR.

Block 13. Enter the EAL number. Provide a short description of the event. Do not use jargon and avoid acronyms.

Block 14. Enter Prognosis of Situation. This is a judgment call primarily relating to the condition of the reactor.

Block 15. Ensure the Emergency Director has signed the form prior to transmittal to the offsite agencies.

Additional information to consider when completing the CNF CNF must be filled out in entirely prior to transmittal to offsite agencies. Transmittal of the CNF should occur prior to initiation of each Crash Call. The requirement to complete 15-minute notifications to the offsite agencies should not be delayed if the time needed to complete the form would impact the notification requirement. In cases where the Crash Call is initiated prior to transmittal, the form should be filled out and transmitted as soon as possible.

When the Control Room is providing emergency classifications, they will ensure the SCC has received the CNF at which time the SCC will follow up with the offsite agencies to ensure they have received the information. If the SCC is not available, the Control Room Notifier must provide the information block by block to the offsite agencies.

If the CNF information is being communicated from the EOF or TSC, all information on the form must be verbally communicated. When communicating the CNF information, it must be communicated block by block for each of the blocks.

If an error on the CNF is recognized during the Crash Call, the correction should be noted on the CNF, initialed, and communicated during the Crash Call.

If an error is recognized in block 4, 5, 6, 8, 9, 10, 11, 12 or 13 after the Crash Call has concluded, a new corrected CNF with the next sequential number should be completed, transmitted, and followed up with a Crash Call.

24075 R24

1 Type of Event: 2 COLUMBIA GENERATING STATION

a. Emergency

b. Drill CLASSIFICATION NOTIFICATION FORM (CNF) No:

3 4 Classification/Status Time: Date:

Notification Provided By: Phone:

(Emergency Director) a. Initial Classification Name (Print): (509) b. Reclassification

c. Termination

d. PAR Changes/Additions

e. Information Section Map 5 a. UNUSUAL EVENT No Offsite Protective Actions Recommended

b. ALERT No Offsite Protective Actions Recommended

c. SITE AREA EMERGENCY Automatic Protective Action Recommendation EVACUATE:

Columbia River

Ringold Fishing Area

Wahluke Hunting Area

Schools in EPZ

Horn Rapids Recreation Area/ORV Park

d. GENERAL EMERGENCY Automatic Protective Action Recommendation EVACUATE:

Columbia River

Ringold Fishing Area

Wahluke Hunting Area

Schools in EPZ

Horn Rapids Recreation Area/ORV Park 8 Meteorological Data: 6 PROTECTIVE ACTION RECOMMENDATIONS Wind Speed: mph from degrees IF a General Emergency is declared, Precipitation: Yes No THEN Refer to PPM 13.2.2 Determining PARs.

Stability Classification IF A GE is NOT declared, This section is Not Applicable 9 No Release(Block 10,11&12 are N/A) Release Basis for PARs: Not Applicable Radiological Plant Type of release: 11 Estimated Start of Release: 0-2 miles 2-10 miles 10 N/A N/A All Sections Section 1 Section 2 Section 3 Section 4 Airborne Time/Date: Monitor & Monitor & Monitor & Monitor &

Prepare Prepare Prepare Prepare Water Release Terminated: Shelter In Shelter In Shelter In Shelter In Shelter In Time/Date: Place Place Place Place Place Evacuate Evacuate Evacuate Evacuate Evacuate 12 State Criteria met for administering KI(Information only) 7 Security Event: Yes No N/A Responding personnel are to report to:

No On-Site Facilities Yes 250 mrem/hr thyroid Alternate Facilities, Energy Northwest Office Complex, 1.4 x 10 µci/cc I-131

-7 3000 George Washington Way Unfiltered or unmonitored release 13 EAL# Description; Additional Information; 14 Prognosis of Situation: a. Unknown b. Stable c. Escalating d. Improving 15 Emergency Director Approval Signature: