ML20054A158

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Proposed RO Admin JPMs
ML20054A158
Person / Time
Site: Byron  Constellation icon.png
Issue date: 12/16/2019
From: Joseph Demarshall
Exelon Generation Co
To:
NRC/RGN-III/DRS/OLB
Demarshall J
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Download: ML20054A158 (77)
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RA-1-03-0 Revision 11 Page 1 of 19 SRRS: 3D.105 (when utilized for operator initial or continuing training)

Job Performance Measure Perform Shutdown Margin Calculation JPM Number: RA-1-03-0 Revision Number: 11 Date: 08 / 16 / 2019 Developed By:

Benjamin Reyes 08/16/2019 Instructor Date Validated By:

Timothy McDougal /s/

08/22/2019 SME or Instructor Date Reviewed By:

Mace Davis /s/

08/22/2019 Operations Representative Date Approved By:

Training Department Date

RA-1-03-0 Revision 11 Page 2 of 19 SRRS: 3D.100; There are no retention requirements for this section JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation.

Prior to JPM usage, revalidate JPM using steps 9 and 13 below.

TLM____

1.

Task description and number, JPM description and number are identified.

TLM____

2.

Knowledge and Abilities (K/A) references are included.

TLM____

3.

Performance location specified. (in-plant, control room, simulator, or other)

TLM____

4.

Initial setup conditions are identified.

TLM____

5.

Initiating cue (and terminating cue if required) are properly identified.

TLM____

6.

Task standards identified and verified by SME review.

TLM____

7.

Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

N/A_____

8.

If an alternate path is used, the task standard contains criteria for successful completion.

TLM____

9.

Verify the procedure(s) referenced by this JPM reflects the current revision:

Procedure 1BOSR 1.1.1-1 Rev: 15 Procedure COLR U1 Cycle 23 Rev: 14 Procedure BCB-1 Table 1-1 Rev: 72 Procedure BCB-1 Table 1-1a Rev: 13 Procedure BCB-1 Table 1-2 Rev: 37 Procedure BCB-1 Table 1-5 Rev: 33 Procedure BCB-1 Table 1-6 Rev: 25 Procedure BCB-1 Figure 8B Rev: 32 TLM____

10. Verify cues both verbal and visual are free of conflict.

TLM____

11. Verify performance time is accurate N/A_____
12. If the JPM cannot be performed as written with proper responses, then revise the JPM.

TLM____

13. When JPM is initially validated, sign and date JPM cover page. Subsequent validations, sign and date below:

SME / Instructor Date SME / Instructor Date SME / Instructor Date

RA-1-03-0 Revision 11 Page 3 of 19 SRRS: 3D.100; There are no retention requirements for this section Revision Record (Summary)

Revision 8 Applied new template TQ-JA-150-02 Rev.1 Verified/ updated KAs and TPOs to current revision Validated 03/03/13 by Bill Hochstetter and Rob Lawlor, revised calculational errors Updated procedure ref.

Changed Tave in initial conditions from 580 to 587 Revision 9 Revised to new cycle data Revision 10 This JPM previously used as SAa on 2014 Certification exam. Applied new template TQ-AA-150-J020. Revised procedures referenced to current revision, and revised standards to current cycle data. Revised Task Number (typo).

Revision 11 Modified to remove dropped rod, lowered reactor power to 50% from 100%, and mode 3 instead of mode 1.

Revised procedure references to current revision Updated calculations to align with current tables and graphs This JPM was previously utilized on 2010 NRC Exam as JPM RA-1. Updated the JPM to new template TQ-JA-150-J020. JPM number format has been revised to better track JPMs as opposed to changing letter designations based on where placed sequentially on ES-301 forms.

Added a Task Performance Standard. Verified/ updated KAs and TPOs to current revision Updated the referenced procedures to the current revisions. Revised the set-up instructions to reflect the changes.

RA-1-03-0 Revision 11 Page 4 of 19 SRRS: 3D.100; There are no retention requirements for this section JPM SETUP INSTRUCTIONS

1. This is an administrative JPM that may be performed in any setting where the necessary procedures and support information can be provided.
2. Verify current revisions of the following information is available for the JPM performance:
  • 1BOSR 1.1.1-1 Rev: 15
  • BCB-1 Table 1-1 Rev: 72
  • BCB-1 Table 1-1a Rev: 13
  • BCB-1 Table 1-2 Rev: 37
  • BCB-1 Table 1-5 Rev: 33
  • BCB-1 Table 1-6 Rev: 25
  • BCB-1 Figure 8B Rev: 32
3. ENSURE the following is available during performance of the JPM:
  • 1BOSR 1.1.1-1 Rev: 15
  • BCB-1 Table 1-1 Rev: 72
  • BCB-1 Table 1-1a Rev: 13
  • BCB-1 Table 1-2 Rev: 37
  • BCB-1 Table 1-5 Rev: 33
  • BCB-1 Table 1-6 Rev: 25
  • BCB-1 Figure 8B Rev: 32
  • 1BGP 100-7T1 Reference
  • Calculator
4. ENSURE the following between performances of the JPM:
  • New clean procedure copies for examinee to work from during performance
5. This completes the setup for this JPM.

RA-1-03-0 Revision 11 Page 5 of 19 SRRS: 3D.100; There are no retention requirements for this section INITIAL CONDITIONS You are the Unit 1 Assist NSO.

  • Unit 1 tripped 25 minutes ago from 50% power.
  • The unit had been at 50% for 1 week.
  • Before the trip, Control Bank D was at 150 steps with all rods in proper alignment, bank overlap and sequence.
  • All RCPs are running
  • All Rod At Bottom lights are lit.
  • Boron concentration is 700 ppm per sample 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> ago.
  • No changes to boron concentration have been made.
  • Tave is 557°F, maintained on the steam dumps.
  • Reactor average burn-up is 6500 EFPH, MOL.
  • QNE is not available.
  • The plant is to be cooled to 500°F.

INITIATING CUE The Unit Supervisor directs you to perform 1BOSR 1.1.1-1, Unit One Shutdown Margin Surveillance to determine if Shutdown Margin is met for:

  • POST SHUTDOWN ASSESSMENT AND
  • SHUTDOWN MARGIN REQUIREMENTS SUPPORTING RAPID COOLDOWN Fill in the JPM Start Time when the student acknowledges the Initiating Cue.

RA-1-03-0 Revision 11 Page 6 of 19 SRRS: 3D.100; There are no retention requirements for this section Information For Evaluators Use:

Task Performance Standard: Applicant correctly completes 1BOSR 1.1.1-1 to show that Unit 1 meets the current Shutdown Margin and that added boration was sufficient to allow the Unit to cooldown to 500°F.

UNSAT requires written comments on respective step.

  • Denotes critical steps: 2 - 5, 7 - 12 and 15 - 18 Number any comments in the Comment Number column on the following pages. Then annotate that comment in the Comments section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.

Comments relating to procedural or equipment issues should be entered and tracked using the sites appropriate tracking system.

Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.

The timeclock starts when the candidate acknowledges the initiating cue.

RA-1-03-0 Revision 11 Page 7 of 19 SRRS: 3D.105 (when utilized for operator initial or continuing training)

JPM Start Time:

STEP ELEMENT STANDARD SAT UNSAT Comment Number NOTE:

JPM task conditions and initiating cues provide the values for core average burnup (6500), RCS Tave (557), and RCS boron concentration (700).

NOTE:

Minor calculational differences may exist between the examinees calculation and the provided surveillance for values that are correctly calculated. All calculated values should be between the ranges stated in JPM by the bounding values.

NOTE:

Provide the examinee with copy of 1BOSR 1.1.1-1, Unit One Shutdown Margin Surveillance.

CUE The reactor tripped at ___________. (Fill in the time as 25 minutes before the JPM start time).

1 Refer to 1BOSR 1.1.1-1, Shutdown Margin Surveillance.

o OPEN 1BOSR 1.1.1-1 o Go to step F.1

  • F.1.a: Yes
  • F.1.b: Yes
  • F.1.c: Yes
  • F.1.d: Yes
  • F.1.e: No
  • Goes to step F.2 (from F.1.e).

CUE Provide the examinee with a copy of the Byron Curve Book or applicable tables and figures and 1BGP 100-7T1 upon request.

RA-1-03-0 Revision 11 Page 8 of 19 SRRS: 3D.105 (when utilized for operator initial or continuing training)

STEP ELEMENT STANDARD SAT UNSAT Comment Number

  • 3 Post Shutdown Assessment (4 Hours)
  • F.2.a: Yes
  • F.2.b: Record time and date of the Mode 3 Entry
  • F.2.c: Add 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and record time and date
  • F.2.d: Determine Shutdown Margin is acceptable for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> o Examinee initials and dates section NOTE:

If candidate suggests waiting until the SRO signs and verifies the surveillance to this point, cue the NSO as the US to complete all sections as required and the verifications will be performed after they are complete.

CUE Acknowledge the request for the SRO approval / verification. Complete all sections as required and verifications will be performed after you are complete.

  • 4 Shutdown Margin Requirements Supporting Rapid Cooldown Candidate determines and records the following:
  • F.3.a: 700 ppm
  • F.3.b: 500°F
  • F.3.c: 847 ppm
  • Determine that a boration is required to meet Cooldown Shutdown Margin NOTE:

If candidate correctly determines that a boration is required, provide the subsequent cues to allow the candidate to continue and complete the surveillance.

CUE Another NSO has completed a boration of the RCS.

CUE Chemistry reports RCS boron concentration of 1090 ppm after the last boration at time - 2 minutes. (Record time given: __________.)

RA-1-03-0 Revision 11 Page 9 of 19 SRRS: 3D.105 (when utilized for operator initial or continuing training)

STEP ELEMENT STANDARD SAT UNSAT Comment Number NOTE:

Candidate may request 1BGP 100-7T1 at this time.

CUE Here is the most recent completed copy of 1BGP 100-7T1.

  • 5 Shutdown Margin Requirements Supporting Rapid Cooldown determination Candidate determines and records the following:
  • Determine that Shutdown Margin is acceptable for Cooldown temperature o Examinee initials and dates section 6

Present Conditions Candidate determines and records the following:

o F.4.a: Record time and date o F.4.b: Core average burnup (6500 EFPH from turnover) o F.4.c: RCS average temperature (557°F from turnover) o F.4.d: Record RCS boron concentration (1090 ppm from last Chemistry report) o F.4.e: Total inoperable control rods (0) o F.4.f: Required SDM from COLR (1.3% K/K = 1300 pcm)

RA-1-03-0 Revision 11 Page 10 of 19 SRRS: 3D.105 (when utilized for operator initial or continuing training)

STEP ELEMENT STANDARD SAT UNSAT Comment Number

  • 7 Bounding Assumptions Candidate determines:
  • F.5.a: Record bounding core average temperature (500°F

- 557°F)

  • F.5.b: Record most limiting core average temperature (F.5.b) (500°F)
  • F.5.c: Determine bounding time and date (Time determined plus 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />)
  • 8 Minimum Required Boron Concentration Candidate determines:
  • F.6.a: Obtain Minimum Required Boron Concentration from BCB-1 Table 1-1
  • 1065 ppm from Table 1-1.
  • Add 120 ppm for Bias.
  • Total = 1185 ppm
  • F.6.b: Determine that present RCS Boron Concentration is NOT >

Minimum Required Boron Concentration

  • Goes to Step F.7 NOTE:

Two values are given for the subsequent steps; both for a bounding value from the tables (used to complete the presented 1BOSR 1.1.1-1) or for an interpolated value. Candidates may/will perform calculations to verify accuracy of the completed 1BOSR 1.1.1-1. Values obtained by candidate should be within this range.

RA-1-03-0 Revision 11 Page 11 of 19 SRRS: 3D.105 (when utilized for operator initial or continuing training)

STEP ELEMENT STANDARD SAT UNSAT Comment Number

  • 9 Reactivity Worth of Boron Candidate determines:
  • F.7a.1: Integral Boron Worth from 1BCB-Table 1-5 at limiting core avg temperature and current boron concentration (7.a.1) (Bounding) o -9174 pcm (675 ppm bounds actual value of 1090 ppm at 500°F)

(7.a.1) (Interpolated) o Calculates as follows:

o From 1050ppm= -9174pcm o From 1125ppm = -9792pcm o 40/75 of -618 (difference between -9174pcm and

-9792pcm) = -330pcm o -9174pcm + -330pcm =

-9504 pcm

RA-1-03-0 Revision 11 Page 12 of 19 SRRS: 3D.105 (when utilized for operator initial or continuing training)

STEP ELEMENT STANDARD SAT UNSAT Comment Number

  • 10 Reactivity Worth of Boron Candidate determines:
  • F.7.a.2: Integral Boron Worth from 1BCB-Table 1-5 at limiting core avg temperature and minimum required boron concentration (7.a.2) (Bounding) o -10404 pcm (1200 ppm bounds calculated value of 1185 ppm)

(7.a.2) (Interpolated) o Calculates as follows:

o From 1125ppm= -9792pcm o From 1200ppm = -10404pcm plus 60/75 of - 612 (difference between -

9792pcm and -10404pcm) = -

490pcm o -9792pcm + -490pcm =

-10282pcm

RA-1-03-0 Revision 11 Page 13 of 19 SRRS: 3D.105 (when utilized for operator initial or continuing training)

STEP ELEMENT STANDARD SAT UNSAT Comment Number

  • 11 Reactivity Worth of Boron Candidate determines:
  • F.7.a.3: Determines the difference of Reactivity Worth of Boron (7.a.3) (Bounding) o -9174pcm - (-)10404pcm =

+1230pcm (7.a.3) (Interpolated) o -9404pcm - (-)9792pcm =

+778pcm

  • 12 Reactivity Worth of Boron Candidate determines:
  • F.7.b: Calculate net Boron Reactivity Worth o (7.b) (Bounding)

+1230pcm + (-)1300pcm =

-70pcm o (7.b) (Interpolated)

+778pcm + (-)1300pcm =

-522pcm 13 Reactivity Worth of Untrippable Rods Candidate determines:

o F.8.a: Number of inoperable control rods (0) o Predicted Most-reactive rod worth from 1BCB-Table 1-6 (2400 pcm) o F.8.b: Calculate Reactivity Worth of Untrippable Rods (0 pcm)

RA-1-03-0 Revision 11 Page 14 of 19 SRRS: 3D.105 (when utilized for operator initial or continuing training)

STEP ELEMENT STANDARD SAT UNSAT Comment Number 14 Reactivity Change Due to Xenon Candidate determines:

o F.9.a: Determine Xenon Equivalent power from RRD o F.9.b: Determine SD Time and date o F.9.c: Determines the value for Xenon Worth using RRD and BCB-1 Table 1-2 (-2581 pcm)

  • 15 Reactivity Worth of Samarium Candidate determines:
  • Credit not taken for Samarium (calculation, if performed, equates to 0 at time of shutdown)

RA-1-03-0 Revision 11 Page 15 of 19 SRRS: 3D.105 (when utilized for operator initial or continuing training)

STEP ELEMENT STANDARD SAT UNSAT Comment Number

(F.11) (Interpolated)

Candidate determines:

(F.11) (Bounding) o F.11.a: Determines integral worth of boron (-9174 pcm) o F.11.b: Review correction factor (0.889)

  • F.11.c: Determines Xenon Worth is utilized Xe and Sm worth (-2581 pcm)
  • Determines a net value of fission product is obtained (step F.11.d) (-2295 pcm)

(F.11) (Interpolated) o F.11.a: Reviews integral worth of boron (-9504 pcm) o F.11.b: Review correction factor (0.884)

  • F.11.c: Determines Xenon Worth is utilized Xe and Sm worth (-2581 pcm)
  • F.11.d: Determines the net value of fission product

(-2282 pcm)

RA-1-03-0 Revision 11 Page 16 of 19 SRRS: 3D.105 (when utilized for operator initial or continuing training)

STEP ELEMENT STANDARD SAT UNSAT Comment Number

(F.12) (Interpolated)

Candidate reviews:

(F.12) (Bounding)

  • Determines Untrippable Rod Worth utilized (0 pcm)
  • Determines Fission Product Worth utilized (-2295 pcm)
  • Present Operating Mode (3)

(F.12) (Interpolated)

  • Determines Untrippable Rod Worth utilized (0 pcm)
  • Determines Fission Product Worth (-2282 pcm)
  • Present Operating Mode (3)
  • 18 Determine Acceptance Criteria IS MET
  • Answers YES to acceptance criteria o Initials/dates calculation CUE This JPM is complete.

RA-1-03-0 Revision 11 Page 17 of 19 SRRS: 3D.105 (when utilized for operator initial or continuing training)

STEP ELEMENT STANDARD SAT UNSAT Comment Number NOTE:

40 Minutes is allowed for completion of this JPM.

JPM Stop Time:

RA-1-03-0 Revision 11 Page 18 of 19 SRRS: 3D.105 (when utilized for operator initial or continuing training)

JPM

SUMMARY

Operators Name:

Emp. ID#: ____________

Job

Title:

EO RO SRO FS STA/IA SRO Cert JPM

Title:

Perform Shutdown Margin Calculation JPM Number: RA-1-03-0 Revision Number: 11 Task Number and

Title:

4C.GP-03 Perform Shutdown Margin Calculations K/A Number and Importance: 2.1.37 Importance: 4.6 Suggested Testing Environment: Simulator or Classroom Alternate Path:

Yes No SRO Only:

Yes No Time Critical:

Yes No Reference(s):

Procedure 1BOSR 1.1.1-1 Rev: 15 Procedure COLR U1 Cycle 23 Rev: 14 Procedure BCB-1 Table 1-1 Rev: 72 Procedure BCB-1 Table 1-1a Rev: 13 Procedure BCB-1 Table 1-2 Rev: 37 Procedure BCB-1 Table 1-5 Rev: 33 Procedure BCB-1 Table 1-6 Rev: 25 Procedure BCB-1 Figure 8B Rev: 32 Actual Testing Environment:

Simulator Control Room In-Plant Other Testing Method:

Simulate Perform Estimated Time to Complete: 40 minutes Actual Time Used:

minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily?

Yes No The operators performance was evaluated against standards contained within this JPM and has been determined to be:

Satisfactory Unsatisfactory Comments:

Evaluators Name (Print):

Evaluators Signature:

Date:

RA-1-03-0 Revision 11 Page 19 of 19 SRRS: 3D.100; There are no retention requirements for this section INITIAL CONDITIONS You are the Unit 1 Assist NSO.

  • Unit 1 tripped 25 minutes ago from 50% power.
  • The unit had been at 50% for 1 week.
  • Before the trip, Control Bank D was at 150 steps with all rods in proper alignment, bank overlap and sequence.
  • All RCPs are running
  • All Rod At Bottom lights are lit.
  • Boron concentration is 700 ppm per sample 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> ago.
  • No changes to boron concentration have been made.
  • Tave is 557°F, maintained on the steam dumps.
  • Reactor average burn-up is 6500 EFPH, MOL.
  • QNE is not available.
  • The plant is to be cooled to 500°F.

INITIATING CUE The Unit Supervisor directs you to perform 1BOSR 1.1.1-1, Unit One Shutdown Margin Surveillance to determine if Shutdown Margin is met for:

  • POST SHUTDOWN ASSESSMENT AND

BYRON STATION PROCEDURE NO.

1BOSR 1.1.1-1 UNIT NO.

1 REVISION NO.

15 PROCEDURE TITLE:

UNIT ONE SHUTDOWN MARGIN SURVEILLANCE Rev Summary IR/AT#

EC#

Procedure Database Tracking #

15 Add model bias term to step F.13 4095955 26330 14 Add notes to make the procedure more user friendly 25704 13 Editorial enhancement due to lessons learned 2677310 24929 12 Clarify SDM calculations.

22276 11 Clarify SDM calculations.

2489685-02 21280 10 Editorial to clarify language due to confusion.

9 Add new step F.3, Shutdown Margin Supporting Rapid Cooldown.

1BOSR 1.1.1-1 Revision 15 Page 1 of 19 Continuous Use UNIT ONE SHUTDOWN MARGIN SURVEILLANCE STATEMENT OF APPLICABILITY:

This procedure applies to the verification of Shutdown Margin in Mode 2 with Keff

< 1.0 and Modes 3, 4, and 5.

a.

Daily when the Present RCS Boron Concentration is greater than the Minimum Required Boron Concentration.

b.

Shiftly when the Present RCS Boron Concentration is less than or equal to the Minimum Required Boron Concentration.

c.

More frequently, as appropriate, when the bounding assumptions are due to expire or be exceeded.

2.

The procedure applies to the verification of shutdown margin during the following infrequent conditions:

a.

Within one hour after detection of one or more inoperable shutdown or control rod(s) in Modes 1 and 2. (LCO 3.1.4)

b.

Within one hour after detection of one shutdown or control rod not within alignment limits and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter while the rod is not within alignment limits. (LCO 3.1.4)

c.

Within one hour after detection of more than one shutdown or control rod not within alignment limits. (LCO 3.1.4)

d.

Within one hour after detection of one or more shutdown banks not within the insertion limits specified in the COLR in Mode 1 and 2 with any control bank not fully inserted. (LCO 3.1.5)

e.

Within one hour after detection of one or more control banks not within the insertion, sequence or overlap limits specified in the COLR in Modes 1 and 2 with keff > 1.0. (LCO 3.1.6)

f.

Within one hour after detection of two Boron Dilution Alert channels being inoperable in Modes 3, 4, and 5. (LCO 3.3.9)

g.

Within one hour after last RCP Shutdown in Modes 3, 4, and 5.

(LCO 3.3.9)

h.

Within one hour after first RCS Loop Isolation Valve not open in Modes 3, 4, and 5. (LCO 3.3.9)

A.

1.

1BOSR 1.1.1-1 Revision 15 Page 2 of 19 Continuous Use B.

REFERENCES:

1.

Tech Spec Surveillance Requirements:

a.

LCO 3.1.1

b.

LCO 3.1.4

c.

LCO 3.1.5

d.

LCO 3.1.6

e.

LCO 3.1.8

f.

LCO 3.3.9

g.

SR 3.1.1.1

h.

SR 3.1.8.4

2.

TRM:

a.

LCO 3.1.h

3.

UFSAR:

a.

Section 4.3.1.5, Shutdown Margin.

b.

Section 15.1, Increase in Heat Removal by the Secondary System.

c.

Section 15.4, Reactivity and Power Distribution Anomalies.

4.

Station Procedures:

a.

BCB-1, Byron Curve Book - Unit One.

b.

1BGP 100-5, Plant Shutdown and Cooldown.

c.

1BGP 100-7T1, Reference Reactivity Data Worksheet.

d.

1BOL 1.1, Shutdown Margin (SDM).

e.

1BOL 1.h, Shutdown Margin (SDM) Mode 1 and Mode 2 with Keff > 1.0.

f.

BOP CV-6, Operation of the Reactor Makeup System in the Borate Mode.

1BOSR 1.1.1-1 Revision 15 Page 3 of 19 Continuous Use B.4. continued

g.

BOP CV-7, Operation of the Reactor Makeup System in the Auto Makeup or Manual Mode.

h.

1BOSR NR-1, Unit One Power History Hourly Surveillance.

5.

Core Operating Limits Report (COLR).

6.

NDIT No. NFM9800254, Byron and Braidwood Shutdown Margin within four (4) hours after Reactor Trip (or Shutdown).

7.

Station Commitments:

a.

CM-1 454-402-90-01702-01

b.

CM-2 454-251-88-15100

8.

Design Analysis No. PNDCN: 01-002, Generic 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SDM Calculation.

9.

Westinghouse Technical Bulletin 13-5: Calculation of Shutdown Margin for N-2 Configurations PREREQUISITES:

Receive permission from the Shift Manager or designated SRO licensed assistant prior to performing the surveillance by having the Data Package Cover Sheet signed and dated.

1BGP 100-7T1 is available prior to completing Step F.3 of this surveillance. If the unit is in Mode 1 or 2, the RRD shall be completed assuming the reactor trips from its present condition.

PRECAUTIONS:

None.

LIMITATIONS AND ACTIONS:

As stated in Technical Specification LCO 3.1.1 and TRM LCO 3.1.h.

In the event the Acceptance Criteria is not met during the performance of this surveillance, IMMEDIATELY NOTIFY the Shift Manager or designated SRO licensed assistant to initiate procedure 1BOL 1.1 or 1BOL 1.h, as applicable.

C.

1.
2.

D.

1.

E.

1.
2.

1BOSR 1.1.1-1 Revision 15 Page 4 of 19 Continuous Use E. continued The RCS Average Temperature shall be determined using the following:

N/A a.

If in Mode 1 or 2, use 557°F.

If any RCP's are running:

At > 530°F, loop average temperature on unisolated loops with RCP(s) running.

N/A 2).

At < 530°F, WR Thot and Tcold temperature on unisolated loops with RCP(s) running.

N/A c.

If on Natural Circulation:

N/A1).

WR Thot and Tcold temperature on unisolated loops.

N/A d.

If RH is providing Shutdown Cooling, and if no RCP's are running:

N/A1). RH pump discharge temperature (to represent hot leg) and RH HX return temperature (to represent cold leg) of the RH train providing shutdown cooling for core average temperature.

N/A 4.

If RH is providing Shutdown Cooling, and if no RCP's are running, temporarily stabilize RCS temperature during heatup or cooldown to obtain a more accurate core average temperature.

3.
b.

1).

1BOSR 1.1.1-1 Revision 15 Page 5 of 19 Continuous Use MAIN BODY:

POST REACTOR TRIP ASSESSMENT (12 HOURS)

Is the performance of this surveillance for Mode 3 conditions with the reactor trip breakers open?

Are all control rods operable? (LCO 3.1.4)

Were all control rods within their alignment (LCO 3.1.4), insertion (LCOs 3.1.5 and 3.1.6), sequence (LCO 3.1.6), and overlap (LCO 3.1.6) limits?

Has the RCS boron concentration NOT been diluted subsequent to Mode 3 entry?

Yes ------>

Continue with step F.1.e.

No ------->

Go to step F.4.

Yes ------>

Continue with step F.1.d.

No ------->

Go to step F.4.

Yes ------>

Continue with step F.1.c.

No ------->

Go to step F.4.

Yes ------>

Continue with step F.1.b.

No ------->

Go to step F.4.

NOTE Step F.1 verifies adequate SDM when certain conditions are met. IF it is desired to cooldown, THEN perform this step and proceed to step F.3.

NOTE IF this surveillance is being executed in Modes 3, 4, or 5, using COLR values, THEN proceed to step F.4.

NOTE IF the Unit is in Mode 1 or 2, this surveillance should be performed assuming the reactor has tripped and is in Mode 3 with RCS Tave at 557°F.

F.

1.
a.
b.
c.
d.

1BOSR 1.1.1-1 Revision 15 Page 6 of 19 Continuous Use F.1. continued Was Control Bank D greater than 200 steps withdrawn immediately prior to the reactor trip?

N/A

f.

Was reactor power greater than 60% RTP for the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> period prior to the Mode 3 entry?

Yes ------>

Continue with step F.1.g.

No ------->

Go to step F.2.

g.

Was the RCS boron concentration greater than 100 ppm prior to the reactor trip?

Yes ------>

Continue with step F.1.h.

No ------->

Go to step F.2.

h.

Is the Core Average Temperature greater than or equal to 550°F?

Yes ------>

Continue with step F.1.i.

No ------->

Go to step F.4.

i.

RECORD the time and date at which the Mode 3 entry was made.

/

Time Date

j.

Add 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to the time and date recorded in step F.1.i.

/

Time Date

k.

Shutdown Margin is acceptable until the time recorded in step F.1.j as long as the conditions listed in step F.1 are maintained. The balance of this procedure shall be performed prior to the time and date recorded in step F.1.j or prior to initiating a plant cooldown or RCS dilution.

(¢)

NSO or QNE Date SRO Date

l.

MARK step F.2 N/A and CONTINUE with step F.3.

Yes ------>

Continue with step F.1.f.

No ------->

Go to step F.2.

e.

1BOSR 1.1.1-1 Revision 15 Page 7 of 19 Continuous Use F. continued POST SHUTDOWN ASSESSMENT (4 HOURS)

Is the Core Average Temperature at nominal 557°F?

RECORD the time and date of the Mode 3 entry.

25 minutes ago /

Today Time Date ADD 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to the time and date recorded in step F.2.b.

3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> and 35 minutes from now /

Today Time Date Shutdown Margin is acceptable until the time recorded in step F.2.c as long as the applicable conditions listed in steps F.1 and F.2 are maintained. The balance of this procedure shall be performed prior to the time and date recorded in step F.2.c or prior to initiating a plant cooldown or RCS dilution.

Candidate signature / initial Today

(¢)

NSO or QNE Date SRO Date Yes ------>

Continue with step F.2.b.

No ------->

Go to step F.4.

NOTE IF certain conditions in step F.1 are not met, this step may be performed to verify adequate SDM for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. IF it is desired to cooldown, THEN perform this step and proceed to step F.3.

2.
a.
b.
c.
d.

1BOSR 1.1.1-1 Revision 15 Page 8 of 19 Continuous Use F. continued SHUTDOWN MARGIN REQUIREMENTS SUPPORTING RAPID COOLDOWN RECORD the Existing (pre-shutdown) RCS Boron Concentration (from most recent sample prior to the reactor shutdown). INCLUDE sample time and date:

700 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> ago Today ppm

/

Time Date RECORD the Core Average Temperature for the proposed plant cooldown:

500

°F RECORD the minimum required RCS Boron Concentration for the proposed Core Average Temperature in step F.3.b (top row) using the Existing RCS Boron Concentration in step F.3.a (left column) from BCB-1, Table 1-1a.

847 ppm BORATE the RCS to the minimum required RCS Boron Concentration in step F.3.c for the proposed Core Average Temperature using 1BGP 100-5, BOP CV-6, or BOP CV-7.

VERIFY, through RCS Boron chemistry sampling, that the minimum RCS Boron Concentration recorded in step F.3.c is obtained or exceeded.

RECORD the current boron concentration below.

1090 ppm NOTE Before a plant cooldown to the desired lower RCS Temperature, steps F.3.d through F.3.g shall be completed.

NOTE IF steps F.1 or F.2 were performed and a plant cooldown is desired, THEN perform step F.3 to determine the required RCS boron concentration for adequate SDM.

3.
a.
b.
c.
d.
e.

1BOSR 1.1.1-1 Revision 15 Page 9 of 19 Continuous Use F.3. continued RECORD the current RCS 557°F based Shutdown Margin expiration time from step F.1.j or F.2.c as previously determined:

3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> and 35 minutes from now / Today Time Date SHUTDOWN MARGIN is acceptable until the time recorded in step F.3.f down to the temperature recorded in step F.3.b. If it is desirable to dilute the RCS or cool down the RCS below that which is recorded in step F.3.b, either step F.3 shall be re-performed or the balance of this procedure shall be performed for that lower RCS temperature. Either way, the balance of this procedure shall be performed prior to the time and date recorded in step F.3.f.

Candidate signature / initial Today

(¢)

NSO or QNE Date SRO Date NOTE This procedure calculates the available shutdown margin by comparing core conditions to a reference condition based on BCB-1, Table 1-1. This table lists the boron concentration required to provide the shutdown margin specified in the COLR at various core burnups and RCS temperatures. The table was derived by using the following assumptions:

a.

No Xenon.

b.

Equilibrium Samarium (i.e. Time = 0).

c.

All rods at bottom with the exception of the highest worth rod, which is assumed to be stuck out.

d.

Boron concentrations listed in BCB-1, Table 1-1, include 100 ppm factor of safety.

Deviations from each of the base assumptions and from the reference boron value given in the table are calculated in the procedure, and the sum of these effects is added to the required SDM to arrive at the actual shutdown margin available.

f.
g.

1BOSR 1.1.1-1 Revision 15 Page 10 of 19 Continuous Use F. continued NOTE In the event that a control rod is known to be untrippable, this is adjusted for in addition to the rod assumed to be stuck in the table.

NOTE Use 1BGP 100-7T1 for reactivity information prior to the shutdown.

PRESENT CONDITIONS RECORD Time and Date.

Current time / Today Time Date RECORD the Core Average Burnup in EFPH (RRD, step F.2.b prior to core reload).

6500 EFPH NOTE The minimum temperature that can be used when performing a shutdown margin calculation is 60°F. Notify the Shift Manager and a Qualified Nuclear Engineer if the RCS temperature is less than 60°F.

(CM-1)

RECORD the RCS Average Temperature (if in Mode 1 or 2, use 557°F).

557

°F NOTE IF a trend of the RCS Boron Concentration indicates an unexpected decrease, THEN determine the cause of the trend and either increase the RCS boron or request additional boron samples.

If boration/dilution processes have occurred since the most recent sample, request a new boron concentration sample to determine present boron concentration.

RECORD the Present RCS Boron Concentration (from most recent sample of the RCS or RH Train if it is providing shutdown cooling).

Include the sample time and date.

Time sample reported / Today 1090 Time Date ppm

4.
a.
b.
c.
d.

1BOSR 1.1.1-1 Revision 15 Page 11 of 19 Continuous Use F.4. continued

e.

RECORD the Total Number of Inoperable Control Rods.

NOTE IF one or more control rod(s) is (are) inoperable or not within alignment limits, THEN perform this surveillance within one hour and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter.

If the inoperable control rod(s) is (are) untrippable, then this surveillance must be performed in its entirety.

NOTE 1% k/k = 1000 pcm = 0.01 k/k 0

RECORD the required SDM from the COLR.

(-)

1300 pcm DETERMINE and RECORD the bounding Core Average Temperature for this verification.

500

°F to 557

°F BOUNDING ASSUMPTIONS NOTE The Shutdown Margin verification is dependent upon the bounding assumptions recorded in step F.5. These assumptions should be broad enough to not challenge expected plant conditions, but specific enough to avoid unnecessary RCS boron adjustments. A Qualified Nuclear Engineer may be requested to provide guidance in making these assumptions.

The actual conditions recorded in step F.4 shall lie within the bounding values recorded in step F.5. This procedure shall be re-performed if these bounding assumptions are due to expire or will be exceeded.

5.

NOTE IF this surveillance is being executed in Modes 3, 4, or 5, using COLR values, THEN proceed to step F.13.

NOTE A control rod is considered to be inoperable if it is untrippable or fails to fully insert upon a reactor trip.

f.
a.

1BOSR 1.1.1-1 Revision 15 Page 12 of 19 Continuous Use F.5. continued RECORD the most Limiting Core Average Temperature within the above temperature range. This is the temperature from BCB-1, Table 1-1, with the largest minimum required boron concentration at the current core burnup.

500 °F DETERMINE the bounding Time and Date for this verification.

OBTAIN the Minimum Required Boron Concentration from either BCB-1, Table 1-1 (bounding value would be the largest number), a QNE, or a QNE supplied document, as appropriate.

BCB-1, Table 1-1, using the burnup from step F.4.b and the RCS Tave from step F.5.b:

Add cycle Model Bias Term from BCB-1 Table 1-1:

+

=

1065 120 1185 ppm ppm ppm o

N/A N/A ppm Qualified Nuclear Engineer MINIMUM REQUIRED BORON CONCENTRATION NOTE The minimum required boron concentration may be obtained from either BCB-1, Table 1-1, directly from a QNE, or from a QNE signed document written for this specific application. Independent verification is required for determining the minimum required boron concentration from the QNE supplied document to ensure the value is bounded by the assumptions recorded in step F.5.

6.

Time now / Today to +12 hours / Today NOTE When obtaining values from the Byron Curve Book, interpolation or a bounding value may be used. Each individual step will include guidance on what constitutes a bounding value.

b.
c.
a.

o

1BOSR 1.1.1-1 Revision 15 Page 13 of 19 Continuous Use F.6.a. continued o

QNE supplied document N/A ppm Candidate signature / initial Today NSO Date NSO or SRO Date Is the Present RCS Boron Concentration (F.4.d) > Minimum Required Boron Concentration (F.6.a)?

Yes ------>

Continue with step F.6.c.

No ------->

Go to step F.7.

N/A c.

Are all control rods operable? (LCO 3.1.4)

Yes ------>

Continue with step F.6.d.

No ------->

Go to step F.7.

d.

The SDM requirement is satisfied and this surveillance may be performed on a daily basis, provided the bounding assumption is step F.5 remain satisfied. Mark the remainder of this procedure N/A.

NSO or QNE Date SRO Date

(¢)

REACTIVITY WORTH OF BORON CALCULATE the reactivity difference between the current boron concentration and the concentration specified in Table 1-1.

RECORD the Integral Boron Worth from BCB-1, Table 1-5 at the limiting core average temperature (F.5.b) for the time period specified in F.5.c and current boron concentration (F.4.d). (A bounding value would be the least negative number.)

500

°F 1090 ppm

(-) 9174 pcm Core Tavg (F.5.b)

Cb from (F.4.d) or bounding Cb used in Table 1-5

b.
7.
a.

1).

1BOSR 1.1.1-1 Revision 15 Page 14 of 19 Continuous Use F.7.a. continued RECORD the Integral Boron Worth from BCB-1, Table 1-5 at the limiting core average temperature (F.5.b) and minimum required boron concentration from Table 1-1 (F.6.a). (A bounding value would be the most negative number.)

500

°F 1185 ppm

(-)10404 pcm Core Tavg (F.5.b)

Cb from (F.6.a) or bounding Cb used in Table 1-5 SUBTRACT the result of step F.7.a.2) from step F.7.a.1).

(-)

9174 pcm

(-) 10404 pcm = (+) 1230 pcm F.7.a.1 F.7.a.2 CALCULATE the net worth of boron by ADDING the result of step F.7.a.3) to the required SDM (F.4.f).

(+) 1230 pcm

+

(-) 1300 pcm =

-70 pcm (F.7.a.3))

(F.4.f)

REACTIVITY WORTH OF UNTRIPPABLE RODS RECORD the Total Number of Untrippable Control Rods from step F.4.e.

CORRECT for untrippable control rods by MULTIPLYING the Total Number of Stuck Rods (F.8.a) by the Most Reactive Stuck Rod Worth from BCB-1, Table 1-6 for Modes 2 (keff < 1.0), 3, 4, and 5.

0 Total Rods x 2400 pcm/rod = (+) 0 pcm (F.8.a)

Predicted Worth 0

Total Rods NOTE IF the number of untrippable rods in step F.8.a is greater than 2, proceed to step F.13.

2).

3).

b.
8.
a.
b.

1BOSR 1.1.1-1 Revision 15 Page 15 of 19 Continuous Use F. continued REACTIVITY CHANGE DUE TO XENON RECORD the Xenon Equivalent Power from RRD, step F.2.d.

46.7

% Xe Pwr RECORD the Shutdown Time and Date from RRD, step F.2.a.

S/D Time Same as F.2.b S/D Date Today DETERMINE the Xenon Worth using the Xe Equivalent Power (F.9.a) and "Time After Shutdown". From BCB-1, Figure 8C or Table 1-2, select the time within the "bounding time" from step F.5.c that corresponds to the least negative (most positive) amount of reactivity. RECORD the respective Xe Worth and RECORD the associated "Time after Shutdown".

Choosing the least negative (most positive) Xe Worth over the shift will yield a bounding SDM calculation.

Number of Hours Shutdown 12 hrs

(-) 2581 pcm Xe Worth RECORD the Samarium equivalent power from the RRD step F.2.c.

50

% Sm Pwr CALCULATE the worth of Samarium from BCB-1, Table 1-4 by determining the Sm at the equivalent power from step F.10.a, with the number of hours shutdown based on the present time and SUBTRACTING the Sm worth at time of shutdown (t=0). (A bounding value would be 0 pcm for Sm Worth. If zero is entered, mark other blanks N/A.)

N/A pcm -

N/A

=

(-)

0 pcm Sm Worth at Sm Worth at Sm Worth present time S/D (time = 0) for % Sm Pwr for % Sm Pwr (F.10.a)

REACTIVITY WORTH OF SAMARIUM NOTE For accumulated burnup less than 600 EFPH, make no adjustments for Samarium. Mark steps F.10.a and F.10.b N/A.

10.
9.
a.
b.
c.
a.
b.

1BOSR 1.1.1-1 Revision 15 Page 16 of 19 Continuous Use F. continued CORRECTION FOR BORON EFFECTS ON XENON AND SAMARIUM WORTHS From step F.7.a.1) RECORD the integral worth of boron.

(-) 9174 pcm From BCB-1, Figure 8B DETERMINE the correction factor at the integral boron worth recorded in F.11.a.

0.889 ADD the Xenon worth from step F.9.c and the Samarium worth from step F.10.b.

(-) 2581 pcm +

(-) 0 pcm=

(-) 2581 pcm (F.9.c)

(F.10.b)

MULTIPLY the sum of the fission product poison worths (step F.11.c) by the correction factor (F.11.b). This is the net value of fission product adjusted for competition effects of boron.

(-) 2581 pcm x 0.889

=

(-) 2295 pcm (F.11.c)

(F.11.b)

TOTAL SHUTDOWN MARGIN CALCULATE the Total Shutdown Margin, in "pcm", by adding:

BORON WORTH (step F.7.b)

- 70 pcm

+

UNTRIPPABLE CONTROL ROD WORTH (step F.8.b)

(+) 0 pcm

+

FISSION PRODUCT WORTH (step F.11.d)

(-) 2295 pcm

=

TOTAL SHUTDOWN MARGIN

-2365 pcm RECORD the present Operating Mode (1-5).

Mode 3

11.
a.
b.
c.
d.
12.
a.
b.

1BOSR 1.1.1-1 Revision 15 Page 17 of 19 Continuous Use N/A F.12. continued NOTE For Modes 1-5, the Total Shutdown Margin (F.12.a) must be equal to or more Negative than the Shutdown Margin specified in the COLR (F.4.f).

ANSWER whether the Acceptance Criteria is satisfied or not and INITIAL.

(YES or NO)

YES

(¢)

Candidate signature / initial Today NSO or QNE Date SRO Date If the Acceptance Criteria is not satisfied, IMMEDIATELY notify the Shift Manager and INITIATE 1BOL 1.1 or 1BOL 1.h.

If the Acceptance Criteria is satisfied, this surveillance should be performed each shift provided the bounding assumptions in step F.5 remain satisfied. Mark the remainder of this procedure N/A.

13.

COLR BORON CONCENTRATION NOTE The minimum required boron concentration shall be obtained from the current operating cycle COLR, Section 2.13.2. plus the cycle Model Bias Term from BCB-1 Table 1-1. This SDM maintains keff 0.987 with all shutdown and control rods fully withdrawn in MODES 3, 4, or 5.

a.

CALCULATE the Minimum Required Boron Concentration as follows:

RECORD COLR Section 2.13.2 boron concentration:

ppm ADD cycle Model Bias Term from BCB-1 Table 1-1:

+

ppm

=

ppm

c.

1BOSR 1.1.1-1 Revision 15 Page 18 of 19 Continuous Use F.13. continued N/A NOTE For Modes 3, 4, or 5, the Present RCS Boron Concentration (F.4.d) must be greater than or equal to the Minimum Required Boron Concentration (F.13.a)

b.

ANSWER whether the Acceptance Criteria is satisfied or not and INITIAL.

(YES or NO)

(¢)

NSO or QNE Date SRO Date If the Acceptance Criteria is not satisfied, IMMEDIATELY notify the Shift Manager and INITIATE 1BOL 1.1 or 1BOL 1.h.

If the Acceptance Criteria is satisfied, this surveillance should be performed each shift provided the bounding assumptions in step F.5 remain satisfied.

G.

ACCEPTANCE CRITERIA:

1.

For Modes 1-5, SDM shall be within the limits of the COLR (SR 3.1.1.1). This is verified by one of the following methods:

a.

For the first 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> following a reactor trip by having the following conditions met (F.1.k):

1).

All RCCAs operable.

2).

All RCCAs within alignment, insertion, sequence, and overlap limits prior to trip.

3).

No RCS dilutions since reactor trip.

4).

Control Bank D greater than 200 steps withdrawn prior to the trip.

5).

Reactor power was greater than 60% RTP for the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> period prior to the reactor trip.

6).

RCS boron concentration greater than 100 ppm.

7).

RCS Tave greater than 550°F or a lower temperature evaluated in section F.3.

1BOSR 1.1.1-1 Revision 15 Page 19 of 19 Continuous Use G.1. continued OR

b.

For the first 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following a shutdown by having the following conditions met (F.2.d):

1).

All RCCAs operable.

2).

All RCCAs within alignment, insertion, sequence, and overlap limits prior to trip.

3).

No RCS dilutions since reactor trip.

4).

RCS Tave at nominal 557°F or at a lower evaluated temperature from section F.3.

OR

c.

At any time when the Present RCS Boron Concentration is greater than or equal to the Minimum Required Boron Concentration with no untrippable control rods (F.6.d).

OR

d.

At any time when the Total Shutdown Margin (F.12.a) is equal to or more negative than the SDM specified in the COLR (F.4.f).

OR

e.

At any time when the Present RCS Boron Concentration is greater than or equal to the Minimum Required Boron Concentration found in the COLR Section 2.13.2 (F.13.b)

RA-2-02-0 Revision 00 Page 1 of 12 SRRS: 3D.105 (when utilized for operator initial or continuing training)

Job Performance Measure Establish Clearance Boundary for 0A FP Pump JPM Number: RA-2-02-0 Revision Number: 00 Date: 08 / 20 / 2019 Developed By:

Benjamin Reyes 8/20/2019 Instructor Date Validated By:

Timothy McDougal /s/

08/22/2019 SME or Instructor Date Reviewed By:

Mace Davis /s/

08/22/2019 Operations Representative Date Approved By:

Training Department Date

RA-2-02-0 Revision 00 Page 2 of 12 SRRS: 3D.100; There are no retention requirements for this section JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation.

Prior to JPM usage, revalidate JPM using steps 9 and 13 below.

TLM____

1.

Task description and number, JPM description and number are identified.

TLM____

2.

Knowledge and Abilities (K/A) references are included.

TLM____

3.

Performance location specified. (in-plant, control room, simulator, or other)

TLM____

4.

Initial setup conditions are identified.

TLM____

5.

Initiating cue (and terminating cue if required) are properly identified.

TLM____

6.

Task standards identified and verified by SME review.

TLM____

7.

Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

N/A_____

8.

If an alternate path is used, the task standard contains criteria for successful completion.

TLM____

9.

Verify the procedure(s) referenced by this JPM reflects the current revision:

Procedure OP-AA-109-101 Rev: 14 Procedure OP-BY-101-0001 Rev: 45 Drawing M-52 Sheet 5 Rev: AL Drawing 6E-0-4030FP01 Rev: M Procedure BOP FP-32 Rev: 0 Procedure BOP FP-2 Rev: 08 TLM____

10. Verify cues both verbal and visual are free of conflict.

TLM____

11. Verify performance time is accurate N/A_____
12. If the JPM cannot be performed as written with proper responses, then revise the JPM.

TLM____

13. When JPM is initially validated, sign and date JPM cover page. Subsequent validations, sign and date below:

SME / Instructor Date SME / Instructor Date SME / Instructor Date

RA-2-02-0 Revision 00 Page 3 of 12 SRRS: 3D.100; There are no retention requirements for this section Revision Record (Summary)

Revision 00, New JPM developed for 2019-2 NRC Exam.

RA-2-02-0 Revision 00 Page 4 of 12 SRRS: 3D.100; There are no retention requirements for this section JPM SETUP INSTRUCTIONS

1. This is an administrative JPM that may be performed in any setting where the necessary procedures and support information can be provided.
2. Verify current revisions of the following information is available for the JPM performance:
  • OP-BY-101-0001
3. ENSURE the following are available during performance of the JPM:
  • OP-BY-101-0001
  • M-52 Sheet 5
  • color highlighters: yellow, blue, green, and orange
4. ENSURE the following between performances of the JPM:
  • New clean procedure copies for examinee to work from during performance
5. This completes the setup for this JPM.

RA-2-02-0 Revision 00 Page 5 of 12 SRRS: 3D.100; There are no retention requirements for this section INITIAL CONDITIONS You are the extra NSO.

  • 0FP03PA, 0A Fire Protection Pump, Seal Package is leaking.
  • A Clearance Order must be prepared to allow repairs to the pump.

INITIATING CUE The Shift Manager directs you to identify the Minimum Required clearance boundaries and generate Manual Tag Out 19-032, using OP-AA-109-101 Att. 12 to allow MMD to repack, clean, and inspect the shaft on pump 0FP03PA, 0A Fire Protection Pump, in accordance with work order #0651137-01. Inform the Shift Manager when complete.

Fill in the JPM Start Time when the student acknowledges the Initiating Cue.

Information For Evaluators Use:

Task Performance Standard: Applicant identifies the required isolation points for component to isolated by a Clearance Order per OP-AA-109-103 and OP-BY-101-0001 such that all critical steps are completed in accordance with the specified standards.

UNSAT requires written comments on respective step.

  • Denotes critical steps: 3 & 5 Number any comments in the Comment Number column on the following pages. Then annotate that comment in the Comments section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.

Comments relating to procedural or equipment issues should be entered and tracked using the sites appropriate tracking system.

Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.

The timeclock starts when the candidate acknowledges the initiating cue.

RA-2-02-0 Revision 00 Page 6 of 12 SRRS: 3D.105 (when utilized for operator initial or continuing training)

JPM Start Time:

STEP ELEMENT STANDARD SAT UNSAT Comment Number CUE Provide the applicant with a of OP-AA-109-101, PERSONNEL AND EQUIPMENT TAGOUT PROCESS, including ATTACHMENT 1, Manual Tagout Form Template, along with color highlighters: yellow, blue, green, and orange.

CUE (If requested), Provide a copy of OP-BY-101-0001, BYRON OPERATIONS STANDARDS PHILOSOPHY HANDBOOK, BOP FP-32, and BOP FP-2.

NOTE:

Examinee is not required to locate and print drawings to meet step 1.

Satisfactory answers for questions on how to obtain documents are sufficient to provide examinee with required drawings (ANS: hard copy prints, EDMS).

1 Obtain required drawings.

o Obtain M-52, Sheet 5 o Obtain 6E-0-4030FP01 NOTE:

The information on pages 1 -2 of Attachment 12 are included for reference only.

The applicants may arrive at different conclusions dependent on site experience. The applicant is only responsible for the required isolation points on pages 3 and 4.

2 Record information on OP-AA-109-101, Attachment 12, Manual Tagout Form Template RECORD the following:

o Tagout number o EIN/EID o Equipment Description o Equipment Location o Work Description o Working Department o W/O Number CUE (If asked) Provide the examinee with the following information:

o Tagout number: 19-032 o Work

Description:

Repack, clean, and inspect shaft on pump 0FP03PA o Working Dept: MMD o Equipment IN: 0FP03PA o Equipment Description 0A FP Pp

RA-2-02-0 Revision 00 Page 7 of 12 SRRS: 3D.105 (when utilized for operator initial or continuing training)

STEP ELEMENT STANDARD SAT UNSAT Comment Number NOTE:

Tagout sequence:

o C/S prior to power supply o Power supply prior to component NOTE:

Tagout sequence:

o Discharge valves prior to suction valves o Vents prior to drains.

NOTE:

Applicant may specify a DANGER tag in place of an INFORMATION/CAUTION tag for the specified fuses.

  • 3 Determine the electrical boundaries, card type and sequence for tagout to be used to isolate the pump.

Determine the tagout boundaries:

  • 0A FP Pump C/S (0HS-FP009) PTL, INFORMATION/CAUTION tagged, and sequence 1.
  • 0A FP Pump Control Power Fuses (1AP08E-R-FU-1) OFF or REMOVED, INFORMATION/CAUTION or DANGER tagged and sequence 2.
  • 0A FP Pump Breaker (1AP08E-R) R/O, DANGER tagged, and sequence 3.

RA-2-02-0 Revision 00 Page 8 of 12 SRRS: 3D.105 (when utilized for operator initial or continuing training)

STEP ELEMENT STANDARD SAT UNSAT Comment Number NOTE:

Drawing will be marked in accordance with OP-BY-101-0001 step 4.1.2.7.3 and step 4.1.2.7.4 (reference key).

4 Mark the electrical boundaries on the required drawing for determined boundary points.

Mark up 6E-0-4030FP01 with the identified boundary points.

o 0A FP Pump MCB C/S (0HS-FP009) o Yellow, PTL, R.I.

o 0A FP Pump Control Power Fuses (1AP08E-R-FU-1) o Yellow, OFF or REMOVED, R.I. or R.D.

(as determined in performance step 3) o 0A FP Pump Breaker (1AP08E-R) o Yellow, R/O, R.I.

RA-2-02-0 Revision 00 Page 9 of 12 SRRS: 3D.105 (when utilized for operator initial or continuing training)

STEP ELEMENT STANDARD SAT UNSAT Comment Number NOTE:

It is possible that the examinee may add the principle equipment 0FP03PA as an item on the checklist NOTE:

It is possible that the examinee may add additional cards for several other valves identified inside the Clearance Order boundary. Any of these valves are NOT significant to the Clearance Order boundary and should be indicated by INFO cards only.

  • 5 Determine the mechanical boundaries, card type and sequence for tagout to be used to isolate the pump.

Determine the tagout boundaries:

  • 0A FP Pump Discharge valve (0FP018A) CLOSED, DANGER tagged, and sequence 4.

o No suction for 0A FP Pump.

o 0A FP Pump Recirc valve (0FP607) not required. If chosen, INFO tagged and sequence 5.

o 0A FP Pump Vent Valve (0FP761A) not required. If chosen, INFO tagged and sequence 5 or 6.

NOTE:

Drawing will be marked in accordance with OP-BY-101-0001 step 4.1.2.7.3 and step 4.1.2.7.4 (reference key).

RA-2-02-0 Revision 00 Page 10 of 12 SRRS: 3D.105 (when utilized for operator initial or continuing training)

STEP ELEMENT STANDARD SAT UNSAT Comment Number 6

Mark the mechanical boundaries on the required drawing for determined boundary points.

Mark up Obtain M-52, Sheet 5 with the identified boundary points.

o 0A FP Pump Discharge valve (0FP018A) o Yellow, CLOSED, RD.

o 0A FP Pump Recirc valve (0FP607) o Yellow, RI.

o 0A FP Pump Vent Valve (0FP761A) o Yellow, RI. (as determined in performance step 4) 7 Inform the Shift Manager of task completion.

Informs the Shift Manager that the clearance boundaries have been identified.

CUE This JPM is complete.

JPM Stop Time:

RA-2-02-0 Revision 00 Page 11 of 12 SRRS: 3D.105 (when utilized for operator initial or continuing training)

JPM

SUMMARY

Operators Name:

Emp. ID#: ____________

Job

Title:

EO RO SRO FS STA/IA SRO Cert JPM

Title:

Establish Clearance Boundary for 0A FP Pump JPM Number: RA-2-02-0 Revision Number: 01 Task Number and

Title:

4E.AM-06 Implement the Equipment Clearance Process K/A Number and Importance: 2.2.13 Importance: 4.1 Suggested Testing Environment: Simulator or Classroom Alternate Path:

Yes No SRO Only:

Yes No Time Critical:

Yes No Reference(s):

Procedure OP-AA-109-101 Rev: 14 Procedure OP-BY-101-0001 Rev: 45 Drawing M-52 Sheet 5 Rev: AL Drawing 6E-0-4030FP01 Rev: M Procedure BOP FP-32 Rev: 0 Procedure BOP FP-2 Rev: 08 Actual Testing Environment:

Simulator Control Room In-Plant Other Testing Method:

Simulate Perform Estimated Time to Complete: 30 minutes Actual Time Used:

minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily?

Yes No The operators performance was evaluated against standards contained within this JPM and has been determined to be:

Satisfactory Unsatisfactory Comments:

Evaluators Name (Print):

Evaluators Signature:

Date:

RA-2-02-0 Revision 00 Page 12 of 12 SRRS: 3D.100; There are no retention requirements for this section INITIAL CONDITIONS You are the extra NSO.

  • 0FP03PA, 0A Fire Protection Pump, Seal Package is leaking.
  • A Clearance Order must be prepared to allow repairs to the pump.

INITIATING CUE The Shift Manager directs you to identify the Minimum Required clearance boundaries and generate Manual Tag Out 19-032, using OP-AA-109-101 Att. 12 to allow MMD to repack, clean, and inspect the shaft on pump 0FP03PA, 0A Fire Protection Pump, in accordance with work order #0651137-01. Inform the Shift Manager when complete.

OP-AA-109-101 Revision 14 Page 97 of 99 ATTACHMENT 12 Manual Tagout Form Template Page 1 of 3 Tagout:

Date:

Time:

Equipment to be Worked EIN/EID:

Equipment

Description:

Equipment Location:

Work Description Hazards Completion Attributes (Station Dependent):

Attribute Description Attribute Value Attribute Description Attribute Value Exceptional Tagout?

Yes No 2nd SRO Application Approval Condition Dependent Tagout?

Yes No 2nd SRO Removal Approval Equipment Draining Required?

Yes No Dose Estimate - Application Equipment Purge Required?

Yes No Dose Estimate - Removal Leads Lifted?

Yes No Dose Actual - Application Jumper Installed?

Yes No Dose Actual - Removal Lock Valve Change Required?

Yes No Threat to Generation?

Yes No Contains Energy Injection Activit ies?

Yes No Elevated Risk?

Yes No Rotational Checks?

Yes No Work Orders Number/Equipment ID Description 19-032 today now 0FP03PA 0A FP Pp 881' CWPH Repack, clean, and inspect shaft on pump 0FP03PA X

X X

X X

X X

X X

X X

0651137-01 Repack, clean, and inspect shaft on pump 0FP03PA KEY

OP-AA-109-101 Revision 14 Page 98 of 99 ATTACHMENT 12 Manual Tagout Form Template Page 2 of 3 Tagout:

Date:

Time:

Verification Status Verified By Verification Date Prepared By Reviewed By SRO Approval By SRO Application Authorization By Reserved for future use N/A Active Removal Sequence Prepared By SRO Removal Authorization By Reserved for future use N/A Tags Removed & Verified Grounds List Number Description Ground Location Attachments Number Description 19-032 today now applicant's name today KEY 6E-0-4030FP01 M-52 Sheet 5 Electrical Schematic Diagram Fire Pump 0A 0FP03A Diagram of Fire Protection at Circulating Water Pumphouse

OP-AA-109-101 Revision 14 Page 99 of 99 ATTACHMENT 12 Manual Tagout Form Template Page 3 of 3 Tagout:

Date:

Time:

Tag Serial Number Tag Type Equipment ID Ver.

Req.

Place Seq Placement Configuration Place.

1st Verif Date/Time Place.

2nd Verif Date/Time Ver.

Req. Rem. Seq.

Removal Configuration As-Left Config Rest.

1st Verif Date/Time Rest.

2nd Verif Date/Time EQ. Description Placement Notes Removal Notes Page of 0HS-FP009 0A FP Pump MCB C/S today now 1AP08E-R-FU-1 1

2 0A FP Control Power Fuses 1AP08E-R 0A FP Pump Breaker 0FP018A 0A FP Pump Discharge valve 0FP607 0A FP Pump Recirc valve 1

2 3

4 5

19-032 INFO PTL OFF or Removed R/O or Racked Out CLOSED CLOSED INFO IV IV IV RD RD N

N 1

2 3

4 5

KEY INFO

OP-AA-109-101 Revision 14 Page 99 of 99 ATTACHMENT 12 Manual Tagout Form Template Page 3 of 3 Tagout:

Date:

Time:

Tag Serial Number Tag Type Equipment ID Ver.

Req.

Place Seq Placement Configuration Place.

1st Verif Date/Time Place.

2nd Verif Date/Time Ver.

Req. Rem. Seq.

Removal Configuration As-Left Config Rest.

1st Verif Date/Time Rest.

2nd Verif Date/Time EQ. Description Placement Notes Removal Notes Page of 6

0FP761A 0A FP Pump Vent Valve INFO N

6 As Required N

19-032 today now 2

2 KEY

RA-3-01-0 Revision 01 Page 1 of 10 SRRS: 3D.105 (when utilized for operator initial or continuing training)

Job Performance Measure Change RMS Setpoints in Preparation for a Unit 1 Containment Release JPM Number: RA-3-01-0 Revision Number: 01 Date: 05 / 21 / 2019 Developed By:

Mark Kultgen /s/

08/21/2019 Instructor Date Validated By:

Timothy McDougal /s/

08/21/2019 SME or Instructor Date Reviewed By:

Mace Davis /s/

08/21/2019 Operations Representative Date Approved By:

Training Department Date

RA-3-01-0 Revision 01 Page 2 of 10 SRRS: 3D.100; There are no retention requirements for this section JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation.

Prior to JPM usage, revalidate JPM using steps 9 and 13 below.

TLM____

1.

Task description and number, JPM description and number are identified.

TLM____

2.

Knowledge and Abilities (K/A) references are included.

TLM____

3.

Performance location specified. (in-plant, control room, simulator, or other)

TLM____

4.

Initial setup conditions are identified.

TLM____

5.

Initiating cue (and terminating cue if required) are properly identified.

TLM____

6.

Task standards identified and verified by SME review.

TLM____

7.

Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

N/A_____

8.

If an alternate path is used, the task standard contains criteria for successful completion.

TLM____

9.

Verify the procedure(s) referenced by this JPM reflects the current revision:

Procedure BCP 400-TCNMT/ROUTINE Rev: 28 Procedure Rev:

Procedure Rev:

TLM____

10. Verify cues both verbal and visual are free of conflict.

TLM____

11. Verify performance time is accurate N/A_____
12. If the JPM cannot be performed as written with proper responses, then revise the JPM.

TLM____

13. When JPM is initially validated, sign and date JPM cover page. Subsequent validations, sign and date below:

SME / Instructor Date SME / Instructor Date SME / Instructor Date

RA-3-01-0 Revision 01 Page 3 of 10 SRRS: 3D.100; There are no retention requirements for this section Revision Record (Summary)

Revision 01 This JPM was previously utilized on 2016 NRC Exam as JPM RA-c. Updated the JPM to new template TQ-JA-150-J020. JPM number format has been revised to better track JPMs as opposed to changing letter designations based on where placed sequentially on ES-301 forms. Added a Task Performance Standard. Verified/ updated KAs and TPOs to current revision.

Updated the referenced procedures to the current revisions. Revised the set-up instructions to reflect the changes. Revised procedures referenced to current revision, and revised standards to current cycle data.

RA-3-01-0 Revision 01 Page 4 of 10 SRRS: 3D.100; There are no retention requirements for this section SIMULATOR SETUP INSTRUCTIONS

1. Reset to IC-22 NOTE:

It is okay to use a similar IC to the IC listed above, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.

2. Ensure that either the 0A or 0B Aux Building Exhaust Fan is in operation.
3. Verify that the RMS values for the appropriate channels agree with the surveillance paperwork.
4. Enter indication for Noble gas trend for 1PR11J (1PB111) on RMS as 4.684 E-06 by entering in Ph.D expert mode: ramp rmr1pr11b.00000468.00000468 7200
5. When the above steps are completed for this and other JPMs to be run concurrently then validate, if not previously validated, the concurrently run JPMs using the JPM Validation Checklist.
6. This completes the setup for this JPM.

RA-3-01-0 Revision 01 Page 5 of 10 SRRS: 3D.100; There are no retention requirements for this section INITIAL CONDITIONS You are the Unit 1 Assist NSO.

  • A Unit 1 Containment release is pending.
  • 1RE-PR011 was In Service prior to beginning BCP preparations and has remained In Service.
  • Daily Channel Checks of 1RE-PR001 have been performed Satisfactorily per 0BOSR 0.1-
0.
  • 1BOSR 11.b.6-1, RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURV. CNMT PURGE EFFLUENT (1(2)PR01J SOURCE/CHANNEL CHECK) has been completed and has been reviewed as Satisfactory.

INITIATING CUE You have been instructed to perform Section 4 of BCP 400-TCNMT/ROUTINE in preparation for this release.

Fill in the JPM Start Time when the student acknowledges the Initiating Cue.

Information For Evaluators Use:

Task Performance Standard: Applicant completes Section 4 of BCP 400-TCNMT/ROUTINE such that all critical steps are completed in accordance with the specified standards.

UNSAT requires written comments on respective step.

  • Denotes critical steps: 7 - 13 Number any comments in the Comment Number column on the following pages. Then annotate that comment in the Comments section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.

Comments relating to procedural or equipment issues should be entered and tracked using the sites appropriate tracking system.

Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.

The timeclock starts when the candidate acknowledges the initiating cue.

RA-3-01-0 Revision 01 Page 6 of 10 SRRS: 3D.105 (when utilized for operator initial or continuing training)

JPM Start Time:

STEP ELEMENT STANDARD SAT UNSAT Comment Number CUE To initiate this JPM, hand the partially completed BCP 400-TCNMT/ROUTINE and Pre-Release Permit Report to the examinee.

1 (4.1) Refer to the partially completed BCP 400-TCNMT/ROUTINE

  • REVIEW BCP 400-TCNMT/ROUTINE for completeness up to Section 4

NOTE:

Performance steps 2 through 4 were met per the Initial Conditions.

2 (4.2) Verify status of 1RE-PR011 has not changed by comparing status denoted on page 1.

(4.2.1.1) Complete daily channel checks

  • VERIFY/COMPLETE the daily channel check on 1RE-PR001 CUE (If asked) The daily channel check of 1RE-PR001 has been performed satisfactorily.

4 (4.2.1.2) Perform Source/Channel check

  • Determine the 1PR01J source/channel check PERFORMED CUE (If asked) 1BOSR 11.b.6-1 has been completed and reviewed satisfactorily.

5 (4.2.1.3) Evaluate Noble gas trend for 1PR11J (1PB111)

  • VERIFY noble gas trend from 1PB111 has not increased by >10% from current reading on Gaseous Pre-release Permit Report

RA-3-01-0 Revision 01 Page 7 of 10 SRRS: 3D.105 (when utilized for operator initial or continuing training)

STEP ELEMENT STANDARD SAT UNSAT Comment Number 6

(4.2.1.4) Record As Found setpoints of 1RE-PR001 RECORD the As Found Setpoints of 1RE-PR001 Gas Channel 1PB101 (Grid 2)

  • 1PB101 - HIGH Alarm Setpoint
  • 1PB101 - ALERT Alarm Setpoint
  • 7 (4.2.1.5) RMS supervisory mode
  • PLACE the RMS console in SUPERVISOR MODE
  • 8 (4.2.1.6) SELECT the required Rad Monitor using the appropriate grid display
  • SELECT Grid 2
  • SELECT 1PB101
  • 9 (4.2.1.7) Select high alarm setpoint channel
  • SELECT CHANNEL ITEMS
  • SELECT 9
  • 10 (4.2.1.8-11) High alarm setpoint
  • ENTER the High Alarm setpoint documented in Section 2.5 on 1PB101 5.855 E-04 or.0005855
  • SELECT SAVE to submit the change.
  • SELECT YES to confirm the change and submit to the RM-80.

o RECORD New 1PB101 HIGH Alarm Setpoint o Request verification CUE (If asked) Your request for verification is acknowledged, please continue.

  • 11 SELECT the required Rad Monitor using the appropriate grid display
  • SELECT Grid 2
  • SELECT 1PB101

RA-3-01-0 Revision 01 Page 8 of 10 SRRS: 3D.105 (when utilized for operator initial or continuing training)

STEP ELEMENT STANDARD SAT UNSAT Comment Number

  • 12 Select alert alarm setpoint channel
  • SELECT CHANNEL ITEMS
  • SELECT 10
  • 13 Alert alarm setpoint
  • ENTER the Alert Alarm setpoint documented in Section 2.5 on 1PB101 3.140 E-04 or.0003140
  • SELECT SAVE to submit the change.
  • SELECT YES to confirm the change and submit to the RM-80.

o RECORD New 1PB101 ALERT Alarm Setpoint o Request verification CUE (If asked) Your request for verification is acknowledged, please continue.

14 (4.2.1.13) Place the RMS in Normal Mode

  • PLACE the RMS console in NORMAL MODE 15 (4.3) Aux building exhaust fan status At 0PM02J:
  • ENSURE the 0A OR 0B Aux Building Exhaust Fan is in operation 16 Turn in Package for approval Hand in Release package to Unit Supervisor for approval.

CUE The US will continue at Step 5.

CUE This JPM is complete.

JPM Stop Time:

RA-3-01-0 Revision 01 Page 9 of 10 SRRS: 3D.105 (when utilized for operator initial or continuing training)

JPM

SUMMARY

Operators Name:

Emp. ID#: ____________

Job

Title:

EO RO SRO FS STA/IA SRO Cert JPM

Title:

Change RMS Setpoints in Preparation for a Unit 1 Containment Release JPM Number: RA-3-01-0 Revision Number: 01 Task Number and

Title:

4C.GW-01PERFORM a Gaseous Release K/A Number and Importance: G2.3.5; 2.9 Suggested Testing Environment: Simulator Alternate Path:

Yes No SRO Only:

Yes No Time Critical:

Yes No Reference(s): Procedure BCP 400-TCNMT/ROUTINE Rev: 28 Actual Testing Environment:

Simulator Control Room In-Plant Other Testing Method:

Simulate Perform Estimated Time to Complete: 15 minutes Actual Time Used:

minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily?

Yes No The operators performance was evaluated against standards contained within this JPM and has been determined to be:

Satisfactory Unsatisfactory Comments:

Evaluators Name (Print):

Evaluators Signature:

Date:

RA-3-01-0 Revision 01 Page 10 of 10 SRRS: 3D.100; There are no retention requirements for this section INITIAL CONDITIONS You are the Unit 1 Assist NSO.

  • A Unit 1 Containment release is pending.
  • 1RE-PR011 was In Service prior to beginning BCP preparations and has remained In Service.
  • Daily Channel Checks of 1RE-PR001 have been performed Satisfactorily per 0BOSR 0.1-
0.
  • 1BOSR 11.b.6-1, RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURV. CNMT PURGE EFFLUENT (1(2)PR01J SOURCE/CHANNEL CHECK) has been completed and has been reviewed as Satisfactory.

INITIATING CUE You have been instructed to perform Section 4 of BCP 400-TCNMT/ROUTINE in preparation for this release.

RA-4-02-0 Revision 00 Page 1 of 10 SRRS: 3D.105 (when utilized for operator initial or continuing training)

Job Performance Measure Respond to a Diesel Generator FOST Room Fire Alarm JPM Number: RA-4-02-0 Revision Number: 00 Date: 06 / 18 / 2019 Developed By:

Mark Kultgen /s/

08/20/2019 Instructor Date Validated By:

Timothy McDougal /s/

08/21/2019 SME or Instructor Date Reviewed By:

Mace Davis /s/

08/21/2019 Operations Representative Date Approved By:

Training Department Date

RA-4-02-0 Revision 00 Page 2 of 10 SRRS: 3D.100; There are no retention requirements for this section JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation.

Prior to JPM usage, revalidate JPM using steps 9 and 13 below.

TLM____

1.

Task description and number, JPM description and number are identified.

TLM____

2.

Knowledge and Abilities (K/A) references are included.

TLM____

3.

Performance location specified. (in-plant, control room, simulator, or other)

TLM____

4.

Initial setup conditions are identified.

TLM____

5.

Initiating cue (and terminating cue if required) are properly identified.

TLM____

6.

Task standards identified and verified by SME review.

TLM____

7.

Critical steps meet the criteria for critical steps and are identified with an asterisk (*).

N/A_____

8.

If an alternate path is used, the task standard contains criteria for successful completion.

TLM____

9.

Verify the procedure(s) referenced by this JPM reflects the current revision:

Procedure BAR 0-37-A4 Rev: 12 Procedure BAR 1PM09J-C6 Rev: 3 Procedure BAP 1100-10 Rev: 18 Procedure BOP FR-1 Rev: 23 Procedure BOP FR-1T5 Rev: 3 Procedure PFP AB1 383-0 FZ 10.2-1 Rev: 2 TLM____

10. Verify cues both verbal and visual are free of conflict.

TLM____

11. Verify performance time is accurate N/A_____
12. If the JPM cannot be performed as written with proper responses, then revise the JPM.

TLM____

13. When JPM is initially validated, sign and date JPM cover page. Subsequent validations, sign and date below:

SME / Instructor Date SME / Instructor Date SME / Instructor Date

RA-4-02-0 Revision 00 Page 3 of 10 SRRS: 3D.100; There are no retention requirements for this section Revision Record (Summary)

Revision 00, JPM developed for 2019-2 NRC exam.

RA-4-02-0 Revision 00 Page 4 of 10 SRRS: 3D.100; There are no retention requirements for this section SIMULATOR SETUP INSTRUCTIONS

1. 1.Reset the simulator to IC 22; 100% power MOL NOTE:

It is okay to use a similar IC to the IC listed above, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.

2. Initiate Smart Scenario:
  • Place Simulator in RUN
  • Open SMART SCENARIO (Extreme Ace icon)
  • Open file Scenario 2019-2 NRC JPM RA-4-02-0.ssf
  • Click on the MODE button (near top of screen) and pick EXECUTE
  • Click on the PLAY button (bottom left of screen)
3. Verify the following are included in the Smart Scenario:
4. Silence/Acknowledge Alarms
5. Place Simulator in FREEZE
6. Ensure clean copies of the following Procedures are available for performance:
  • BAR 0-37-A4, Unit 1 Area Fire
  • BAP 1100-10, Response Procedure for Fire/Fire Alarm
  • BOP FR-1, Fire Response Guidelines
  • PFP AB1 383-0 FZ 10.2-1, Aux. Bldg. 383-0 Elev. 1a Diesel Fuel Oil Storage Tank Room
7. When the above steps are completed for this and other JPMs to be run concurrently then validate, if not previously validated, the concurrently run JPMs using the JPM Validation Checklist.
8. This completes the setup for this JPM.

RA-4-02-0 Revision 00 Page 5 of 10 SRRS: 3D.100; There are no retention requirements for this section INITIAL CONDITIONS You are the Unit 1 Assist NSO.

  • Unit 1 is currently operating at 100% power with all systems in automatic control.
  • 0-37-A4, UNIT 1 AREA FIRE, is alarming
  • DO (1D-10) is alarming on 1PM09J INITIATING CUE The Unit Supervisor directs you to address the alarms per the applicable Annunciator Response procedures.

Fill in the JPM Start Time when the student acknowledges the Initiating Cue.

Information For Evaluators Use:

Task Performance Standard: Applicant will complete notifications/communications of the Diesel Fuel Oil Storage Room 1A&1B, 383'-0" L/P-6/8 (1D-10) per BAP 1100-10, RESPONSE PROCEDURE FOR FIRE / FIRE ALARM and in accordance with the specified standards.

UNSAT requires written comments on respective step.

  • Denotes critical steps: 4 - 6, & 8 Number any comments in the Comment Number column on the following pages. Then annotate that comment in the Comments section. The comment section should be used to document: the reason that a step is marked as unsatisfactory, marginal performance relating to management expectations, or problems the examinee had while performing the JPM.

Comments relating to procedural or equipment issues should be entered and tracked using the sites appropriate tracking system.

Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.

The timeclock starts when the candidate acknowledges the initiating cue.

RA-4-02-0 Revision 00 Page 6 of 10 SRRS: 3D.105 (when utilized for operator initial or continuing training)

JPM Start Time:

STEP ELEMENT STANDARD SAT UNSAT Comment Number 1

Refer to Byron Annunciator Responses:

Locates and implements:

  • BAR 0-37-A4, UNIT 1 AREA FIRE
  • BAR 1PM09J-C6, Diesel Fuel Oil Storage Room 1A&1B, 383'-0" L/P-6/8 (1D-
10) 2 U1 Assist NSO dispatches an EO to investigate at the location of the alarm.
  • DISPATCH an operator to locally investigate Diesel Fuel Oil Storage Room 1A&1B, 383'-0" L/P-6/8 CUE The Equipment Operator reports 1A Diesel Tank To TB1 has a high temp alarm on 1FP05J. Door 0DSD649, 1A Diesel Tank To TB1 is hot to the touch. Door 0DSD648, 1B Diesel Tank Room to TB1 is about ambient temperature.

3 NSO notifies Unit Supervisor of the fire.

  • NOTIFY Unit Supervisor of fire in the Diesel Fuel Oil Storage Tank Room 1A.

CUE The Unit Supervisor acknowledges notification of a fire in the Diesel Fuel Oil Storage Tank Room 1A.

CUE If contacted as the Equipment Operator or subsequently as the Brigade Leader to manually initiate protein foam extinguishing system (1S-27 and 1S-28) Using BOP FP-10, Manual Initiation of Foam to the Diesel Generator Fuel Oil Storage Tank Room 1A, from 401' K7 TB1 to the affected room; Acknowledge request for foam initiation to Diesel Generator Fuel Oil Storage Tank Room 1A.

NOTE:

Steps 4, 5 and 6 may be performed in any order.

NOTE:

Applicant may utilize Byron Station Operating Report Sheet, Attachment 2; Fire/Smoke to perform notifications.

RA-4-02-0 Revision 00 Page 7 of 10 SRRS: 3D.105 (when utilized for operator initial or continuing training)

STEP ELEMENT STANDARD SAT UNSAT Comment Number

  • 4 NSO announces the fire over the public address system.
  • ANNOUNCE the fire over the public address system:
  • "Attention all personnel, Attention all personnel, A fire has been detected in Diesel Fuel Oil Storage Tank Room 1A. All Fire Brigade members please respond. I repeat, a fire has been detected in Diesel Fuel Oil Storage Tank Room 1A. All Fire Brigade members please respond.
  • 5 NSO announces the fire over the radio.
  • ANNOUNCES the fire location over the radio
  • REQUESTS fire brigade members to respond.
  • 6 NSO actuates the fire alarm
  • ACTUATES the fire alarm for approximately 2 minutes.

NOTE:

CO2 or Halon systems will not actuate as a result of this fire.

7 NSO makes follow-up calls

  • MAKE follow-up calls to:
  • Radiation Protection
  • Security
  • REQUEST that each report to the Fire Brigade Leader at the scene CUE Fire Brigade Chief notifies the control room of fire status and requests Offsite Fire Department assistance.

RA-4-02-0 Revision 00 Page 8 of 10 SRRS: 3D.105 (when utilized for operator initial or continuing training)

STEP ELEMENT STANDARD SAT UNSAT Comment Number

  • 8 NSO Notifies Offsite Fire Dept.

and Emergency Medical Service

  • NOTIFY Fire Dept by calling 911 CUE Fire Department will be dispatched to Byron Station.

9 NSO Notifies Security

  • NOTIFY Security that offsite assistance has been requested, and may require entry to protected area.

CUE Security will prepare for Fire Department arrival.

10 NSO notifies Fire Brigade Leader

  • NOTIFY the Fire Brigade Leader that off site assistance is responding.

CUE The Fire Brigade Leader acknowledges that off site assistance is responding.

CUE This JPM is complete.

JPM Stop Time:

RA-4-02-0 Revision 00 Page 9 of 10 SRRS: 3D.105 (when utilized for operator initial or continuing training)

JPM

SUMMARY

Operators Name:

Emp. ID#: ____________

Job

Title:

EO RO SRO FS STA/IA SRO Cert JPM

Title:

Respond to Turbine Building Fire Alarm JPM Number: RA-4 Revision Number: 01 Task Number and

Title:

4D.AM-01 Respond to a plant fire K/A Number and Importance: 2.4.27, importance 3.4 Suggested Testing Environment: Simulator Alternate Path:

Yes No SRO Only:

Yes No Time Critical:

Yes No Reference(s): Procedure BAR 0-37-A4 Rev: 12 Procedure BAR 1PM09J-C6 Rev: 3 Procedure BAP 1100-10 Rev: 18 Procedure BOP FR-1 Rev: 23 Procedure BOP FR-1T5 Rev: 3 Procedure PFP AB1 383-0 FZ 10.2-1 Rev: 2 Actual Testing Environment:

Simulator Control Room In-Plant Other Testing Method:

Simulate Perform Estimated Time to Complete: 10 minutes Actual Time Used:

minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily?

Yes No The operators performance was evaluated against standards contained within this JPM and has been determined to be:

Satisfactory Unsatisfactory Comments:

Evaluators Name (Print):

Evaluators Signature:

Date:

RA-4-02-0 Revision 00 Page 10 of 10 SRRS: 3D.100; There are no retention requirements for this section INITIAL CONDITIONS You are the Unit 1 Assist NSO.

  • Unit 1 is currently operating at 100% power with all systems in automatic control.
  • 0-37-A4, UNIT 1 AREA FIRE, is alarming
  • DO (1D-10) is alarming on 1PM09J INITIATING CUE The Unit Supervisor directs you to address the alarms per the applicable Annunciator Response procedures.
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