Text

Administered SRO Admin JPMs
	ML20054C077
Person / Time
Site:	Byron
Issue date:	12/16/2019
From:	Joseph Demarshall; Exelon Generation Co LLC
To:	; NRC/RGN-III/DRS/OLB
	Demarshall J
Shared Package
ML17214A837	List: ML20054C056; ML20054C077; ML20054C119; ML20054C143; ML20054C170;
References
	Download: ML20054C077 (107)
	v • d • e

SA-1-03-0 Revision 04 Page 1 of 11 Job Performance Measure 0B0BEvaluate License Holders Status 1B1BJPM Number: SA-1-03-0 2B2BRevision Number: 04 3B3BDate: 08 / 21 / 2019 4B4BDeveloped By:

Benjamin Reyes /s/

08/21/2019 5B5BInstructor Date 6B6BValidated By:

Timothy McDougal /s/

08/22/2019 7B7BSME or Instructor Date 8B8BReviewed By:

Mace Davis /s/

08/22/2019 9B9BOperations Representative Date 10B10BApproved By:

J.E. Smith /s/

10/10/2019 1B1BTraining Department Date SRRS: 3D.105 (when utilized for operator initial or continuing training)

SA-1-03-0 Revision 04 Page 2 of 11 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-105-101 Rev: 22 Procedure OP-AA-105-102 Rev: 14 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 SRRS: 3D.100; There are no retention requirements for this section

SA-1-03-0 Revision 04 Page 3 of 11 Revision Record (Summary)

Revision 00, Initial revision of JPM Comment Resolution OTPS: Need more than 1 critical step Added criteria to determine reason each is not qualified and made each a critical step individually Rev. 01-Updated Procedure revisions Updated dates used Validated on 3/3/13 by Rob Lawlor and Bill Hochstetter Revision 02 Applied new template TQ-AA-150-J020.

This JPM is modified from the 2013 NRC Exam JPM RA-1a.

Added an additional NSO who had performed a license reactivation.

Listed specific dates and times for watches stood, changed dates to more current, and rearranged listed NSO order.

NSO now listed as #4 changed from NOT qualified to stand the watch to qualified to stand the watch based on revision to OP-AA-105-101 since last delivered which revised the definition/requirements of Annual: once per calendar year.

Changed the task number to agree with VISION.

Revision 03 Revised to incorporate changes due to OP-AA-105-102 Revision 14 and OP-AA-105-101 Revision 22.

Changed dates to current year.

Per Facility Representatives request, NSO #2 changed from licensed issued previous quarter; along with four qualifying watches stood and one non-qualifying watch stood; to having license issued during the current quarter.

No change as a result to Critical Step 3.

SRRS: 3D.100; There are no retention requirements for this section

SA-1-03-0 Revision 04 Page 4 of 11 Revision 04 This JPM has been modified from administration as 2018 Certification Exam JPM RA-1 and 2017 NRC JPM RA-1. This JPM has been modified by making the following changes:

NSO #3 revised to be qualified by changing date of last medical exam from greater than 730 days to within 730 days plus the current month.

NSO #2 remains qualified, but license issuance changed from the current quarter to license issuance the immediately previous quarter.

NSO #4 revised to be NOT qualified by changing date of last medical exam to greater than 730 days plus the current month.

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 to include date changes to data sheet to make current.

SRRS: 3D.100; There are no retention requirements for this section

SA-1-03-0 Revision 04 Page 5 of 11 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-AA-105-101

OP-AA-105-102

3. ENSURE the following is available during performance of the JPM:

NSO License Maintenance Record (page 11 of JPM)

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.

SRRS: 3D.100; There are no retention requirements for this section

SA-1-03-0 Revision 04 Page 6 of 11 INITIAL CONDITIONS The current date is October 30, 2019.

All NSOs are eligible per ESOMS work hour rules.

All hours from the previous quarter are contained in the attached NSO License Maintenance Record.

INITIATING CUE The Shift Manager has directed you to evaluate five NSOs License Status to determine whether they are qualified to take duty as the Unit 1 NSO.

Inform the Shift Manager of who is eligible

Inform the Shift Manager of who is NOT eligible and why Fill in the JPM Start Time when the student acknowledges the Initiating Cue.

Information For Evaluators Use:

Task Performance Standard: Applicant properly determines the eligibility of the NSOs based on the information provided on the NSO License Maintenance Record in accordance with OP-AA-105-101 and OP-AA-105-102.

UNSAT requires written comments on respective step.

Denotes critical steps: 2 - 6 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.

SRRS: 3D.100; There are no retention requirements for this section

SA-1-03-0 Revision 04 Page 7 of 11 JPM Start Time:

STEP ELEMENT STANDARD SAT UNSAT Comment Number NOTE:

These steps may be performed in any order.

1 Refer to:

o OP-AA-105-102, Rev 14, NRC Active License Maintenance o OP-AA-105-101, Rev 22, Administrative Process for NRC License and Medical Requirements Evaluate NSO status IAW:

o OP-AA-105-102, Rev 14, NRC Active License Maintenance o OP-AA-105-101, Rev 22, Administrative Process for NRC License and Medical Requirements CUE Provide candidate with OP-AA-105-101 and OP-AA-105-102.

2 Evaluate NSO #1

Determines that NSO #1 is NOT qualified because he has not met the 56-hour quarterly shift watch requirement in a qualifying watchstation during the previous quarter and informs the SM.

NOTE:

For NSO #2, though the license was active previous quarter, due to initial license issuance, the minimum watchstanding requirements were not required to be met to maintain an active license in the subsequent quarter.

3 Evaluate NSO #2

Determines that NSO #2 is qualified to perform watchstanding duties and informs the SM.

4 Evaluate NSO #3

Determines that NSO #3 is qualified to perform watchstanding duties and informs the SM.

SRRS: 3D.105 (when utilized for operator initial or continuing training)

SA-1-03-0 Revision 04 Page 8 of 11 STEP ELEMENT STANDARD SAT UNSAT Comment Number

5 Evaluate NSO #4

Determines that NSO #4 is NOT qualified because they have exceeded the required frequency for the Biennial Medical Examination and informs the SM.

6 Evaluate NSO #5

Determine that NSO #5 is qualified to perform watchstanding duties and informs the SM.

7 Inform Shift Manager of the status of the NSOs evaluated.

o Inform Shift Manager of the status of the NSOs evaluated CUE This JPM is complete.

JPM Stop Time:

SRRS: 3D.105 (when utilized for operator initial or continuing training)

SA-1-03-0 Revision 04 Page 9 of 11 JPM

SUMMARY

Operators Name:

Emp. ID#: ____________

Job

Title:

EO RO SRO FS STA/IA SRO Cert JPM

Title:

Evaluate License Holders Status JPM Number: SA-1-03-0 Revision Number: 04 Task Number and

Title:

8E.AM-029 Ensure minimum shift staffing and authorize additional shift staffing as necessary K/A Number and Importance: G 2.1.4 : 3.8 Suggested Testing Environment: Classroom Alternate Path:

Yes No SRO Only:

Yes No Time Critical:

Yes No Reference(s): Procedure OP-AA-105-101 Rev: 22 Procedure OP-AA-105-102 Rev: 14 Actual Testing Environment:

Simulator Control Room In-Plant Other Testing Method:

Simulate Perform Estimated Time to Complete: 25 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:

SRRS: 3D.105 (when utilized for operator initial or continuing training)

SA-1-03-0 Revision 04 Page 10 of 11 INITIAL CONDITIONS The current date is October 30, 2019.

All NSOs are eligible per ESOMS work hour rules.

All hours from the previous quarter are contained in the attached NSO License Maintenance Record.

INITIATING CUE The Shift Manager has directed you to evaluate five NSOs License Status to determine whether they are qualified to take duty as the Unit 1 NSO.

Inform the Shift Manager of who is eligible

Inform the Shift Manager of who is NOT eligible and why SRRS: 3D.100; There are no retention requirements for this section

SA-1-03-0 Revision 04 Page 11 of 11 Operator Date Description Date of last NRC comprehensive requalification written exam Date of last NRC operating exam Date of last NRC medical exam NSO #1 License was active during the last quarter.

11/02/2018 11/01/2018 5/22/2018 8/01/2019 0700-1900 shift as Unit 1 NSO 8/02/2019 0700-1900 shift as Unit 1 NSO 8/03/2019 0700-1900 shift as Unit 1 Admin 8/05/2019 0700-1900 shift as WEC NSO 8/25/2019 0700-1900 shift as Unit 2 NSO NSO #2 License issued July 19, 2019.

N/A N/A 1/10/2019 8/01/2019 0700-1900 shift as Unit 2 NSO 8/02/2019 0700-1900 shift as Unit 2 NSO 8/03/2019 0700-1900 shift as Unit 2 Admin 8/04/2019 0700-1900 shift as Unit 1 Admin 8/25/2019 0700-1900 shift as WEC NSO NSO #3 License was active during the last quarter.

10/26/2018 10/24/2018 10/04/2017 7/09/2019 1900-0700 shift as Unit 2 NSO 7/10/2019 1900-0700 shift as Unit 2 Admin 7/11/2019 1900-0700 shift as Unit 2 NSO 7/12/2019 1900-0700 shift as Unit 2 Admin 8/21/2019 0700-1900 shift as Unit 1 NSO NSO #4 License was active during the last quarter.

9/21/2018 9/19/2018 9/29/2017 7/09/2019 1900-0700 shift as Unit 1 Admin 7/10/2019 1900-0700 shift as Unit 1 NSO 7/11/2019 1900-0700 shift as Unit 1 Admin 7/12/2019 1900-0700 shift as Unit 1 NSO 8/21/2019 0700-1900 shift as Unit 2 NSO NSO #5 Hours below were completed under the direction of the applicable Unit NSO to reactivate an RO license and included the completion of an activation guide, a review of turnover procedures and the completion of a plant tour under direction of a licensed RO.

11/16/2018 11/14/2018 8/30/19 9/05/2019 0700-1900 on Unit 1 9/06/2019 0700-1900 on Unit 1 9/07/2019 0700-1900 on Unit 2 9/22/2019 0700-1300 on Unit 2 SRRS: 3D.100; There are no retention requirements for this section

SA-1-04-0 Revision 11 Page 1 of 19 Job Performance Measure 0BReview/Approve Shutdown Margin Calculation 1BJPM Number: SA-1-04-0 2BRevision Number: 11 3BDate: 08 / 19 / 2019 4BDeveloped By:

Benjamin Reyes /s/

10/10/2019 5BInstructor Date 6BValidated By:

Timothy McDougal /s/

10/10/2019 7BSME or Instructor Date 8BReviewed By:

Mace Davis /s/

10/10/2019 9BOperations Representative Date 10BApproved By:

J.E. Smith /s/

10/10/2019 1BTraining Department Date SRRS: 3D.105 (when utilized for operator initial or continuing training)

SA-1-04-0 Revision 11 Page 2 of 19 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: 13 Procedure COLR U1 Cycle 22 Rev: 12 Procedure BCB-1 Table 1-1 Rev: 67 Procedure BCB-1 Table 1-1a Rev: 13 Procedure BCB-1 Table 1-2 Rev: 36 Procedure BCB-1 Table 1-4 Rev: 28 Procedure BCB-1 Table 1-5 Rev: 32 Procedure BCB-1 Figure 8B Rev: 31 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 SRRS: 3D.100; There are no retention requirements for this section

SA-1-04-0 Revision 11 Page 3 of 19 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 This JPM was previously utilized on 2017 Certification Exam JPM SA-1. This JPM is modified by making the following changes:

Removed dropped rod from the initial conditions

Lowered reactor power to 50% from 100%

Changed evaluation to mode 3 post trip instead of mode 1.

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 calculations to align with current tables and graphs.

SRRS: 3D.100; There are no retention requirements for this section

SA-1-04-0 Revision 11 Page 4 of 19 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

COLR U1 Cycle 22

BCB-1 Table 1-1

BCB-1 Table 1-1a

BCB-1 Table 1-2

BCB-1 Table 1-4

BCB-1 Table 1-5

BCB-1 Figure 8B

3. ENSURE the following is available during performance of the JPM:

A clean copy of partial performed 1BOSR 1.1.1-1 for review.

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.

SRRS: 3D.100; There are no retention requirements for this section

SA-1-04-0 Revision 11 Page 5 of 19 INITIAL CONDITIONS You are the Unit 1 Unit Supervisor.

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 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months ago.

Boration completed 15 minutes ago.

Chemistry reports subsequent RCS boron sample as 1090 ppm.

Tave is 557°F, maintained on the steam dumps.

Reactor average burn-up is 6500 EFPH, MOL.

The plant is to be cooled to 500°F.

The Reactor Operator just completed 1BOSR 1.1.1-1, Shutdown Margin Surveillance and determined that Shutdown Margin was met at time of trip.

INITIATING CUE You are directed by the Shift Manager to review the SDM calculation for accuracy to determine if the SDM is:

Sufficient for current conditions Sufficient to support the cooldown to 500°F Fill in the JPM Start Time when the student acknowledges the Initiating Cue.

SRRS: 3D.100; There are no retention requirements for this section

SA-1-04-0 Revision 11 Page 6 of 19 Information For Evaluators Use:

Task Performance Standard: Applicant reviews the Shutdown Margin to be sufficient for both as found conditions and to support cooldown to 500°F. This SDM is flawed. The applicant is required to identify incorrect calculations and determine that the SDM will be adequate for cooldown. This will be performed by reviewing a partial completed copy and evaluating it in accordance with 1BOSR 1.1.1-1.

UNSAT requires written comments on respective step.

Denotes critical steps: 3, 8, 10, 11, 13, 15, 16, and 17 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.

SRRS: 3D.100; There are no retention requirements for this section

SA-1-04-0 Revision 11 Page 7 of 19 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 sufficient to prove accuracy of the completed sections. The Bounding values indicated are values found in the appropriate tables.

NOTE:

Note: Step 1 may be performed at any time 1

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

o Candidate reviews completed 1BOSR 1.1.1-1 CUE Hand the candidate the completed copy of 1BOSR 1.1.1-1.

2 Post Reactor Trip Assessment (12 Hours) o Goes to step F.2 (from F.1.e).

NOTE:

Required SDM from COLR is 1.3% K/K = 1300 pcm CUE Provide the examinee with a copy of the Byron Curve Book or applicable tables and figures upon request.

3 Post Reactor Trip Assessment (4 Hours)

Determines Shutdown Margin is acceptable for 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months

Examinee initials and dates section SRRS: 3D.105 (when utilized for operator initial or continuing training)

SA-1-04-0 Revision 11 Page 8 of 19 STEP ELEMENT STANDARD SAT UNSAT Comment Number 4

Shutdown Margin Requirements Supporting Rapid Cooldown Candidate reviews:

o Existing RCS Boron concentration (700 ppm from turnover) (F.3.a) o Correct Core average Temperature for cooldown (F.3.b) (500°F) o Correct RCS average temperature (F.3.c) (847 ppm) o Boration of RCS to meet minimum required performed (F.3.d) o Verify new RCCS boron sample indicates more than the minimum required (F.3.e) (1090 ppm from recorded sample) o Shutdown Margin is acceptable until time recorded in F.3.f) o Examinee initials and dates section SRRS: 3D.105 (when utilized for operator initial or continuing training)

SA-1-04-0 Revision 11 Page 9 of 19 STEP ELEMENT STANDARD SAT UNSAT Comment Number 5

Present Conditions Candidate reviews:

o Time and date (F.4.a) o Core average burnup (F.4.b)

(6500 EFPH from turnover) o RCS average temperature (F.4.c) (557°F from note) o RCS boron concentration (F.4.d) (1090 ppm from sample report) o Total inoperable control rods (F.4.e) (0) o Required SDM from COLR (F.4.f) (1.3% K/K = 1300 pcm) 6 Bounding Assumptions Candidate reviews:

o REVIEW bounding core average temperature (F.5.a) o REVIEW most limiting core average temperature (F.5.b)

(500°F) o REVIEW bounding time and date (F.5.c) (12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months from turnover)

SRRS: 3D.105 (when utilized for operator initial or continuing training)

SA-1-04-0 Revision 11 Page 10 of 19 STEP ELEMENT STANDARD SAT UNSAT Comment Number 7

Minimum Required Boron Concentration Candidate reviews:

o REVIEW Minimum Required Boron Concentration from BCB-1 Table 1-1 (F.6.a) o 1065 ppm from Table 1-1.

o Add 120 ppm for Bias.

o Total = 1185 ppm o REVIEW and initial and date for minimum boron concentration (F.6.a) o Present RCS Boron Concentration is NOT >

Minimum Required Boron Concentration (F.6.b)

NOTE:

Two values are given for the subsequent steps; One indicating the reference value and the second is the bounding value from the tables (used to complete the presented 1BOSR 1.1.1-1) Candidates may/will perform calculations to verify accuracy of the completed 1BOSR 1.1.1-1. The candidates values should be sufficient to prove values correct or incorrect.

CUE If candidate determines incorrect value is used and contacts NSO to recalculate, inform him that the Shift Manager directs him to continue his review of the SDM calculation, document any discrepancies, and determine unit requirements.

SRRS: 3D.105 (when utilized for operator initial or continuing training)

SA-1-04-0 Revision 11 Page 11 of 19 STEP ELEMENT STANDARD SAT UNSAT Comment Number

8 Reactivity Worth of Boron (F.7.a.1)

Candidate reviews:

o Integral Boron Worth from 1BCB-Table 1-5 at limiting core avg temperature and current boron concentration (F.7.a.1)

(7.a.1) (Indicated)

Identifies an incorrect value of -6010 pcm (Incorrect value based on 1BCB Table 1-5 6357 burnup for 675 ppm at 500°F)

(7.a.1) (Correct)

Determines correct value of

-9174 pcm bounding value from 1BCB Table 1-5 6357 burnup for 1050 ppm at 500°F SRRS: 3D.105 (when utilized for operator initial or continuing training)

SA-1-04-0 Revision 11 Page 12 of 19 STEP ELEMENT STANDARD SAT UNSAT Comment Number 9

Reactivity Worth of Boron (F.7.a.2)

Candidate reviews:

o Integral Boron Worth from 1BCB-Table 1-5 at limiting core avg temperature and minimum required boron concentration (F.7.a.2)

(7.a.2) (Indicated) o -10404 pcm (Correct value based on 1BCB Table 1-5 6357 burnup 1200 ppm at 500°F)

(7.a.2) (Correct) o -10404 pcm

10 Reactivity Worth of Boron (F.7.a.3)

Candidate reviews:

o Subtract the result of above 2 steps (F.7.a.3)

(7.a.3) (Indicated)

Identifies an incorrect value of +4394 pcm (Incorrect.

Error carried forward.)

(7.a.3) (Correct)

Determines correct value of

+1230 pcm SRRS: 3D.105 (when utilized for operator initial or continuing training)

SA-1-04-0 Revision 11 Page 13 of 19 STEP ELEMENT STANDARD SAT UNSAT Comment Number

11 Reactivity Worth of Boron (F.7.B)

Candidate reviews:

Calculate net Boron Reactivity Worth. (F.7.b)

(7.b) (Indicated)

Identifies an incorrect value of +3094 pcm (Incorrect.

Error carried forward.)

(7.b) (Correct)

Determines correct value of

-70 pcm 12 Reactivity Worth of Untrippable Rods Candidate reviews:

o (F.8.a) Number of inoperable control rods (0) o (F.8.b) Calculate Reactivity Worth of Untrippable Rods (0 pcm)

SRRS: 3D.105 (when utilized for operator initial or continuing training)

SA-1-04-0 Revision 11 Page 14 of 19 STEP ELEMENT STANDARD SAT UNSAT Comment Number

13 Reactivity Change Due to Xenon Candidate reviews:

o (F.9.a) Review Xenon Equivalent power from RRD o (F.9.b) Review SD Time and date

(F.9.c) Identifies an incorrect value utilized for Xenon Worth using RRD and BCB-1 Table 1-2

Determines the value on SDM is incorrect:

-3019 pcm (used for at 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months from SD instead of the more conservative value of NOW). Actual value should be -2581 pcm.

CUE If candidate determines incorrect value is used and contacts NSO to recalculate, inform him that the Shift Manager directs him to continue his review of the SDM calculation, document any discrepancies, and determine unit requirements.

14 Reactivity Worth of Samarium Candidate reviews:

o Credit not taken for Samarium (calculation, if performed, equates to 0 at time of shutdown)

SRRS: 3D.105 (when utilized for operator initial or continuing training)

SA-1-04-0 Revision 11 Page 15 of 19 STEP ELEMENT STANDARD SAT UNSAT Comment Number

15 Correction for Boron Effects on Xenon and Samarium Worths (F.11) (Bounding)

Candidate reviews:

(F.11) (Indicated)

(F.11.a) Identifies an incorrect integral worth of boron (-6010 pcm error carried forward) o (F.11.b) Correction factor (0.926)

(F.11.c) Identifies an incorrect Xenon Worth is utilized Xe and Sm worth

(-3019 pcm error carried forward)

(F.11.d) Identifies an incorrect net value of fission product is obtained (-2798 pcm error carried forward)

(F.11) (Correct)

(F.11.a) Determines the correct value of (-9174 pcm)

(F.11.b) Determines the correct value of (0.89)

(F.11.c) Determines the correct value of (-2581 pcm)

(F.11.d) Determines the correct value of (-2297 pcm)

CUE If candidate determines incorrect value is used and contacts NSO to recalculate, inform him that the Shift Manager directs him to continue his review of the SDM calculation, document any discrepancies, and determine unit requirements.

SRRS: 3D.105 (when utilized for operator initial or continuing training)

SA-1-04-0 Revision 11 Page 16 of 19 STEP ELEMENT STANDARD SAT UNSAT Comment Number

16 Total Shutdown Margin (F.12) (Bounding)

Candidate reviews:

(F.12) (Indicated)

Identifies an incorrect Boron Worth utilized (3094 pcm)

Identifies a correct Untrippable Rod Worth utilized (0 pcm)

Identifies an incorrect Fission Product Worth utilized (-2798 pcm)

Identifies an incorrect Total Shutdown Margin obtained

(+296 pcm)

Present Operating Mode (3)

(F.12) (Correct)

Determines correct value of Boron Worth (-70 pcm)

Determines correct value of Untrippable Rod Worth (0 pcm)

Determines correct value of Fission Product Worth utilized (-2297 pcm)

Determines correct value of Total Shutdown Margin

(-2367 pcm)

Present Operating Mode (3)

SRRS: 3D.105 (when utilized for operator initial or continuing training)

SA-1-04-0 Revision 11 Page 17 of 19 STEP ELEMENT STANDARD SAT UNSAT Comment Number

17 Determine Acceptance Criteria (F.12.c) Determines acceptance criteria for Shutdown Margin is actually MET and calculated is more negative than -1300 pcm

(-2367 pcm)

Determines that acceptance criteria is MET Does NOT provide Initials/dates for incorrect calculation o

Returns to NSO for new performance o

Notifies SM of incorrect performance and actual status CUE This JPM is complete.

JPM Stop Time:

SRRS: 3D.105 (when utilized for operator initial or continuing training)

SA-1-04-0 Revision 11 Page 18 of 19 JPM

SUMMARY

Operators Name:

Emp. ID#: ____________

Job

Title:

EO RO SRO FS STA/IA SRO Cert JPM

Title:

Review/Approve Shutdown Margin Calculation JPM Number: SA-1-04-0 Revision Number: 11 Task Number and

Title:

8E.AM-123 REVIEW surveillances to ensure compliance with Tech Specs and Non-Tech Spec requirements 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: 13 Procedure COLR U1 Cycle 22 Rev: 12 Procedure BCB-1 Table 1-1 Rev: 67 Procedure BCB-1 Table 1-1a Rev: 13 Procedure BCB-1 Table 1-2 Rev: 36 Procedure BCB-1 Table 1-4 Rev: 28 Procedure BCB-1 Table 1-5 Rev: 32 Procedure BCB-1 Figure 8B Rev: 31 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:

SRRS: 3D.105 (when utilized for operator initial or continuing training)

SA-1-04-0 Revision 11 Page 19 of 19 INITIAL CONDITIONS You are the Unit 1 Unit Supervisor.

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 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months ago.

Boration completed 15 minutes ago.

Chemistry reports subsequent RCS boron sample as 1090 ppm.

Tave is 557°F, maintained on the steam dumps.

Reactor average burn-up is 6500 EFPH, MOL.

The plant is to be cooled to 500°F.

The Reactor Operator just completed 1BOSR 1.1.1-1, Shutdown Margin Surveillance and determined that Shutdown Margin was met at time of trip.

INITIATING CUE You are directed by the Shift Manager to review the SDM calculation for accuracy to determine if the SDM is:

Sufficient for current conditions Sufficient to support the cooldown to 500°F SRRS: 3D.100; There are no retention requirements for this section

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.

KEY

1BOSR 1.1.1-1 Revision 15 Page 1 of 19 Continuous Use UNIT ONE SHUTDOWN MARGIN SURVEILLANCE A.

STATEMENT OF APPLICABILITY:

1.

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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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)

KEY

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.

KEY

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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SDM Calculation.

9.

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

PREREQUISITES:

1.

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.

2.

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.

D.

PRECAUTIONS:

1.

None.

E.

LIMITATIONS AND ACTIONS:

1.

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

2.

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.

KEY

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

The RCS Average Temperature shall be determined using the following:

a.

If in Mode 1 or 2, use 557F.

b.

If any RCP's are running:

1).

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

2).

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

c.

If on Natural Circulation:

1).

WR Thot and Tcold temperature on unisolated loops.

d.

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

1).

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.

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.

KEY N/A N/A N/A N/A N/A N/A N/A

1BOSR 1.1.1-1 Revision 15 Page 5 of 19 Continuous Use F.

MAIN BODY:

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 557F.

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

1.

POST REACTOR TRIP ASSESSMENT (12 HOURS) a.

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

Yes ------>

Continue with step F.1.b.

No ------->

Go to step F.4.

b.

Are all control rods operable? (LCO 3.1.4)

Yes ------>

Continue with step F.1.c.

No ------->

Go to step F.4.

c.

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?

Yes ------>

Continue with step F.1.d.

No ------->

Go to step F.4.

d.

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.

KEY

1BOSR 1.1.1-1 Revision 15 Page 6 of 19 Continuous Use F.1. continued e.

Was Control Bank D greater than 200 steps withdrawn immediately prior to the reactor trip?

Yes ------>

Continue with step F.1.f.

No ------->

Go to step F.2.

f.

Was reactor power greater than 60% RTP for the 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 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 550F?

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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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.

KEY N/A

1BOSR 1.1.1-1 Revision 15 Page 7 of 19 Continuous Use F. continued 2.

POST SHUTDOWN ASSESSMENT (4 HOURS)

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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . IF it is desired to cooldown, THEN perform this step and proceed to step F.3.

a.

Is the Core Average Temperature at nominal 557F?

Yes ------>

Continue with step F.2.b.

No ------->

Go to step F.4.

b.

RECORD the time and date of the Mode 3 entry.

/

Time Date c.

ADD 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months to the time and date recorded in step F.2.b.

/

Time Date d.

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.

(¢)

NSO or QNE Date SRO Date KEY 25 minutes ago Today Today 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months and 35 minutes from now BJC Today

1BOSR 1.1.1-1 Revision 15 Page 8 of 19 Continuous Use F. continued 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.

SHUTDOWN MARGIN REQUIREMENTS SUPPORTING RAPID COOLDOWN a.

RECORD the Existing (pre-shutdown) RCS Boron Concentration (from most recent sample prior to the reactor shutdown). INCLUDE sample time and date:

ppm

/

Time Date b.

RECORD the Core Average Temperature for the proposed plant cooldown:

F c.

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.

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

d.

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.

e.

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.

ppm KEY 700 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months ago Today 500 847 1090

1BOSR 1.1.1-1 Revision 15 Page 9 of 19 Continuous Use F.3. continued f.

RECORD the current RCS 557F based Shutdown Margin expiration time from step F.1.j or F.2.c as previously determined:

/

Time Date g.

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.

(¢)

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.

KEY 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months and 35 minutes from now Today BJC Today

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.

4.

PRESENT CONDITIONS a.

RECORD Time and Date.

/

Time Date b.

RECORD the Core Average Burnup in EFPH (RRD, step F.2.b prior to core reload).

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

(CM-1) c.

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

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.

d.

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.

/

ppm Time Date KEY 25 minutes ago Today 6500 557 10 minutes ago Today 1090

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

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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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 f.

RECORD the required SDM from the COLR.

(-) pcm 5.

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.

a.

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

F to F

KEY 0

1300 500 557

1BOSR 1.1.1-1 Revision 15 Page 12 of 19 Continuous Use F.5. continued b.

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.

F c.

DETERMINE the bounding Time and Date for this verification.

/ to /

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.

6.

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.

a.

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.

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

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

+

ppm

=

ppm o

ppm Qualified Nuclear Engineer KEY 500 Now up to +12 hours /

Today Today 1065 120 1185 N/A N/A

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

QNE supplied document ppm NSO Date NSO or SRO Date b.

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.

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 7.

REACTIVITY WORTH OF BORON a.

CALCULATE the reactivity difference between the current boron concentration and the concentration specified in Table 1-1.

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.)

F ppm

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

Cb from (F.4.d) or bounding Cb used in Table 1-5 KEY Bounding - 1050

-9174 Incorrect values. Correct values noted below.

N/A BJC DLR Today Today N/A 500 700 6010

1BOSR 1.1.1-1 Revision 15 Page 14 of 19 Continuous Use F.7.a. continued 2).

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.)

F ppm

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

Cb from (F.6.a) or bounding Cb used in Table 1-5 3).

SUBTRACT the result of step F.7.a.2) from step F.7.a.1).

(-)

pcm

(-)

pcm = (+) pcm F.7.a.1 F.7.a.2 b.

CALCULATE the net worth of boron by ADDING the result of step F.7.a.3) to the required SDM (F.4.f).

(+) pcm

+

(-) pcm =

pcm (F.7.a.3))

(F.4.f) 8.

REACTIVITY WORTH OF UNTRIPPABLE RODS a.

RECORD the Total Number of Untrippable Control Rods from step F.4.e.

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

b.

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.

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

Predicted Worth KEY Incorrect values. Correct values noted.

9174 1230 1230 70 500 1185 10404 10404 6010 4394 4394 1300 3094 2400 0

0 0

1BOSR 1.1.1-1 Revision 15 Page 15 of 19 Continuous Use F. continued 9.

REACTIVITY CHANGE DUE TO XENON a.

RECORD the Xenon Equivalent Power from RRD, step F.2.d.

% Xe Pwr b.

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

S/D Time S/D Date c.

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 hrs

(-) pcm Xe Worth 10.

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.

a.

RECORD the Samarium equivalent power from the RRD step F.2.c.

% Sm Pwr b.

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.)

pcm -

=

(-)

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

KEY Incorrect values.

Correct values noted.

(-) 2581 Today Now 50 0

3019 50 0

N/A N/A

1BOSR 1.1.1-1 Revision 15 Page 16 of 19 Continuous Use F. continued 11.

CORRECTION FOR BORON EFFECTS ON XENON AND SAMARIUM WORTHS a.

From step F.7.a.1) RECORD the integral worth of boron.

(-) pcm b.

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

c.

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

(-) pcm +

(-) pcm=

(-) pcm (F.9.c)

(F.10.b) d.

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.

(-)

pcm x

=

(-) pcm (F.11.c)

(F.11.b) 12.

TOTAL SHUTDOWN MARGIN a.

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

BORON WORTH (step F.7.b) pcm

+

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

(+) pcm

+

FISSION PRODUCT WORTH (step F.11.d)

(-) pcm

=

TOTAL SHUTDOWN MARGIN pcm b.

RECORD the present Operating Mode (1-5).

Mode KEY Incorrect values.

Correct values noted.

Incorrect values.

Correct values noted.

9174 0.89 2581 2581 2581 0.89

(-) 2297

-70

(-) 2297

-2367 6010 0.926 3019 0

3019 0.9268 2798 3019 3

3094 0

2798 296

1BOSR 1.1.1-1 Revision 15 Page 17 of 19 Continuous Use 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).

c.

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. 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 KEY Incorrect value.

Correct value noted.

YES Today BJC NO N/A

1BOSR 1.1.1-1 Revision 15 Page 18 of 19 Continuous Use F.13. continued 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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 0.02 hours 1.190476e-4 weeks 2.7396e-5 months period prior to the reactor trip.

6).

RCS boron concentration greater than 100 ppm.

7).

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

KEY N/A

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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 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 557F 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)

KEY

SA-2-02-0 Revision 00 Page 1 of 21 Job Performance Measure 0BComplete a Plant Barrier Impairment for 0DSD351 1BJPM Number: SA-2-02-0 2BRevision Number: 00 3BDate: 08 / 21 / 2019 4BDeveloped By:

Benjamin Reyes /s/

10/10/2019 5BInstructor Date 6BValidated By:

Timothy McDougal /s/

10/10/2019 7BSME or Instructor Date 8BReviewed By:

Mace Davis /s/

10/10/2019 9BOperations Representative Date 10BApproved By:

J.E. Smith /s/

10/11/2019 1BTraining Department Date SRRS: 3D.105 (when utilized for operator initial or continuing training)

SA-2-02-0 Revision 00 Page 2 of 21 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 CC-AA-201 Rev: 12 Procedure BAP 1100-3 Rev: 024 Procedure BAP 1100-3A3 Rev: 042 Procedure 0BOL 10.g Rev: 009 Procedure Pre-Fire Plan #43 - PFP FZ 5.2-1 Rev: 004 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 SRRS: 3D.105 (when utilized for operator initial or continuing training)

SA-2-02-0 Revision 00 Page 3 of 21 Revision Record (Summary)

Revision 00, JPM created for 19-2 NRC ILT Exam 2019.

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.

SRRS: 3D.105 (when utilized for operator initial or continuing training)

SA-2-02-0 Revision 00 Page 4 of 21 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:

CC-AA-201

BAP 1100-3

BAP 1100-3A3

0BOL 10.g

Pre-Fire Plan #43 - FZ 5.2-1

3. ENSURE the following is available during performance of the JPM:

None

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.

SRRS: 3D.105 (when utilized for operator initial or continuing training)

SA-2-02-0 Revision 00 Page 5 of 21 INITIAL CONDITIONS You are the WEC Supervisor.

You have just received a call that door 0DSD351 (Door Fire / Security TB1 to ESF-11 RM A252) will not latch.

IR# 01234567 has been submitted.

WO# 11121314 has been generated.

MMD estimates 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to complete repairs.

INITIATING CUE The Shift Manager has directed you to determine if a Plant Barrier Impairment (PBI) is required, and if so, complete the PBI.

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

SRRS: 3D.105 (when utilized for operator initial or continuing training)

SA-2-02-0 Revision 00 Page 6 of 21 Information For Evaluators Use:

Per BAP 1100-3 Step D.5.c, A fire door is considered inoperable if it will not latch (manipulation of the door handle to help latch the door is not allowed.

Task Performance Standard: Applicant determines all required compensatory actions for the inoperability of door 0DSD351 in accordance with BAP 1100-3 and completes PBI Form CC-AA-201 Attachment 1.

UNSAT requires written comments on respective step.

Denotes critical steps. 2 - 4, 7 & 11 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.

SRRS: 3D.105 (when utilized for operator initial or continuing training)

SA-2-02-0 Revision 00 Page 7 of 21 JPM Start Time:

STEP ELEMENT STANDARD SAT UNSAT Comment Number NOTE:

When Plant Barrier Impairment (PBI) procedure requested, provide candidate a copy of CC-AA-201, Plant Barrier Control Program.

NOTE:

The following additional resources may be solicited during the performance of this JPM:

BAP 1100-3, PLANT BARRIER IMPAIRMENT (PBI) PROGRAM

BAP 1100-3A3, PRE-EVALUATED PLANT BARRIER MATRIX

0BOL 10.g LCOAR FIRE ASSEMBLIES TRM LCO # 3.10.g

PFP FZ 5.2-1 Division 11 ESF Switchgear Room Additional Evaluator Notes are contained within JPM where they are likely to be requested and subsequently provided to the candidate.

1 Refer to CC-AA-201.

Determine that Attachment 1, Plant Barrier Impairment Permit needs to be filled out.

CUE When site specific procedures are requested; provide candidate a copy of BAP 1100-3, Plant Barrier Impairment Program for guidance and BAP 1100-3A3, Pre-Evaluated Plant Barrier Matrix.

SRRS: 3D.105 (when utilized for operator initial or continuing training)

SA-2-02-0 Revision 00 Page 8 of 21 STEP ELEMENT STANDARD SAT UNSAT Comment Number NOTE:

Wording equivalent to that provided in the standard is acceptable for completion of the Barrier Impairment Permit.

2 Complete Section I. of PBI Permit Complete Section I. of PBI Permit o Component: Door Fire/Security TB1 to ESF-11 RM o WO: 11121314

EPN / ID: 0DSD351 o Unit: 1

Col/Row/Elevation: 8/L/426 o Applicable Dwgs: A-252

Description of Barrier Impairment: Door will not latch properly

Reason for Barrier Impairment: Broken latch o Support of Maint Activity:

Yes o Planned Duration: 1 day

Initiator signature:

(candidate) and date (current)

CUE The next sequential PBI log number is19-859.

NOTE:

If applicant asks for Pre-Fire plan drawing for the affected zone, provide PFP FZ 5.2-1 AUX. BLDG. 426-0 ELEV. DIVISION 11 ESF SWITCHGEAR ROOM.

NOTE:

When Fire Protection LCOAR procedure requested, provide candidate a copy of 0BOL 10.g LCOAR Fire Assemblies TRM LCO # 3.10.g.

SRRS: 3D.105 (when utilized for operator initial or continuing training)

SA-2-02-0 Revision 00 Page 9 of 21 STEP ELEMENT STANDARD SAT UNSAT Comment Number

3 Complete Fire Barrier,Section II. of PBI Permit Complete Section II. of PBI Permit

Fire Barrier Applicable: Yes o Per: BAP 1100-3A3

Compensatory Action Required: Yes

Type of Fire Watch Required: Hourly or Continuous

Fire Detection OP Check Required: Yes (for Hourly watches) or NO (for Continuous watch)

Detection Zones: 1D-78

Fire Zones: 5.2-1 o Testing required: No o CO2/Halon area affected:

No

Fill in written compensatory action block: Per BAP 1100-3A3, compensatory action F7 required for Fire.

Enter 0BOL 10.g.

RECORD name (candidate) and date (current) as reviewer SRRS: 3D.105 (when utilized for operator initial or continuing training)

SA-2-02-0 Revision 00 Page 10 of 21 STEP ELEMENT STANDARD SAT UNSAT Comment Number

4 Complete Security Barrier,Section II. Of PBI Permit

Security Barrier: Yes o Per: BAP 1100-3A3

Compensatory Action Required: Yes

Fill in written compensatory action block: Security has been contacted and is providing compensatory actions per the Security Plan.

AND PBI Permit is required for other design-basis disciplines

RECORD name (candidate) and date (current) as reviewer CUE If applicant notifies security provide the following cue: A Security Guard will be posted.

SRRS: 3D.105 (when utilized for operator initial or continuing training)

SA-2-02-0 Revision 00 Page 11 of 21 STEP ELEMENT STANDARD SAT UNSAT Comment Number NOTE:

Per BAP 1100-3A3, the ventilation column is marked with an X. This states that these are doors, penetrations and floor plugs in the ventilation boundary for the VA, VC, VD, VI, VL, VS, VT, VV, and WW systems. They are either interior doors which do not impact the ventilation boundary, OR have been determined to not negatively impact the ventilation design basis of the plant if impaired.

Therefore control under the PBI program is not necessary.* This means that no compensatory actions are required. This may lead some examinees to mark the Ventilation Barrier as NO. This also acceptable as long as the applicant references the above definition as reason for the decision.

5 Complete Ventilation Barrier,Section II. Of PBI Permit

Ventilation Barrier: Yes/No o Per: BAP 1100-3A3 o Compensatory Action Required: No o Mode restrictions: No o Fill in written compensatory action block: None o 90-day clock applicable: No o Is a 50.59 review required?:

No

RECORD name (candidate) and date (current) as reviewer IF Ventilation Barrier type is checked No, THEN the only other item required to be completed is the Reviewer signature and date. IF Yes is checked, THEN section should be completed as indicated.

SRRS: 3D.105 (when utilized for operator initial or continuing training)

SA-2-02-0 Revision 00 Page 12 of 21 STEP ELEMENT STANDARD SAT UNSAT Comment Number 6

Complete Flood Barrier,Section II. Of PBI Permit

Flood Barrier: No o Per: BAP 1100-3A3 o Compensatory Action Required: No o Mode restrictions: No o Fill in written compensatory action block: None o 90-day clock applicable: No o Is a 50.59 review required?:

No

RECORD name (candidate) and date (current) as reviewer

7 Complete HELB Barrier,Section II. Of PBI Permit

HELB Barrier: Yes o Per: BAP 1100-3A3 Compensatory Action Required: Yes Mode restrictions: No

Fill in written compensatory action block: Temporary HELB Barrier required

90-day clock applicable:

Yes

Is a 50.59 review required?:

No

RECORD name (candidate) and date (current) as reviewer IF barrier type is checked No, THEN the only other item required to be completed is the Reviewer signature and date.

SRRS: 3D.105 (when utilized for operator initial or continuing training)

SA-2-02-0 Revision 00 Page 13 of 21 STEP ELEMENT STANDARD SAT UNSAT Comment Number 8

Complete Missile Barrier,Section II. Of PBI Permit

Missile Barrier: No o Per: BAP 1100-3A3 o Compensatory Action Required: No o Mode restrictions: No o Fill in written compensatory action block: None o 90-day clock applicable: No o Is a 50.59 review required?:

No

RECORD name (candidate) and date (current) as reviewer 9

Complete Occupational Rad Protection,Section II. Of PBI Permit

Occupational Rad Protection: No o Per: BAP 1100-3A3 o Compensatory Action Required: No o Mode restrictions: No o Fill in written compensatory action block: None o 90-day clock applicable: No o Is a 50.59 review required?:

No

RECORD name (candidate) and date (current) as reviewer IF barrier type is checked No, THEN the only other item required to be completed is the Reviewer signature and date.

IF barrier type is checked No, THEN the only other item required to be completed is the Reviewer signature and date.

SRRS: 3D.105 (when utilized for operator initial or continuing training)

SA-2-02-0 Revision 00 Page 14 of 21 STEP ELEMENT STANDARD SAT UNSAT Comment Number 10 Complete Post LOCA Radiation EQ,Section II. Of PBI Permit

Post LOCA Radiation EQ:

No o Per: BAP 1100-3A3 o Compensatory Action Required: No o Mode restrictions: No o Fill in written compensatory action block: None o 90-day clock applicable: No o Is a 50.59 review required?:

No

RECORD name (candidate) and date (current) as reviewer CUE If candidate asks, reply that PBI tags are prepared.

11 Complete Section III. of PBI Permit Sign and Date

Sign (candidate) / date (current)Section III.

Approval of Plant Barrier Impairment CUE If examinee asks, reply the FIN supervisor reports expected repair time is 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

IF barrier type is checked No, THEN the only other item required to be completed is the Reviewer signature and date.

SRRS: 3D.105 (when utilized for operator initial or continuing training)

SA-2-02-0 Revision 00 Page 15 of 21 STEP ELEMENT STANDARD SAT UNSAT Comment Number 12 Complete Section IV. of PBI Permit Sign and Date

Est. Barrier Degradation Period: 1 day

Is 90-day time clock applicable: Yes

Expiration Date: Todays Date + 90 days

Time: JPM Start Time

Sign (candidate) / date (current)Section IV.

Permission to Impair Barrier as WEC Supvr.

CUE This JPM is complete.

JPM Stop Time:

SRRS: 3D.105 (when utilized for operator initial or continuing training)

SA-2-02-0 Revision 00 Page 16 of 21 JPM

SUMMARY

Operators Name:

Emp. ID#: ____________

Job

Title:

EO RO SRO FS STA/IA SRO Cert JPM

Title:

Complete a Plant Barrier Impairment for 0DSD351 JPM Number: SA-2-02-0 Revision Number: 00 Task Number and

Title:

8E-AM-089 PROCESS a Fire Protection / Plant Impairment Permit K/A Number and Importance: G 2.2.21 : 4.1 Suggested Testing Environment: Classroom Alternate Path:

Yes No SRO Only:

Yes No Time Critical:

Yes No Reference(s):

Procedure CC-AA-201 Rev: 12 Procedure BAP 1100-3 Rev: 024 Procedure BAP 1100-3A3 Rev: 042 Procedure 0BOL 10.g Rev: 009 Procedure Pre-Fire Plan #43 - FZ 5.2-1 Rev: 004 Actual Testing Environment:

Simulator Control Room In-Plant Other Testing Method:

Simulate Perform Estimated Time to Complete: 20 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:

SRRS: 3D.105 (when utilized for operator initial or continuing training)

SA-2-02-0 Revision 00 Page 17 of 21 SRRS: 3D.100; There are no retention requirements for this section

SA-2-02-0 Revision 00 Page 18 of 21 SRRS: 3D.100; There are no retention requirements for this section

SA-2-02-0 Revision 00 Page 19 of 21 SRRS: 3D.100; There are no retention requirements for this section

SA-2-02-0 Revision 00 Page 20 of 21 SRRS: 3D.100; There are no retention requirements for this section

SA-2-02-0 Revision 00 Page 21 of 21 INITIAL CONDITIONS You are the WEC Supervisor.

You have just received a call that door 0DSD351 (Door Fire / Security TB1 to ESF-11 RM A252) will not latch.

IR# 01234567 has been submitted.

WO# 11121314 has been generated.

MMD estimates 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to complete repairs.

INITIATING CUE The Shift Manager has directed you to determine if a Plant Barrier Impairment (PBI) is required, and if so, complete the PBI.

SRRS: 3D.100; There are no retention requirements for this section

SA-3-02-0 Revision 07 Page 1 of 11 Job Performance Measure 0BAccessing Containment at Power 1BJPM Number: SA-3-02-0 2BRevision Number: 07 3BDate: 08 / 20 / 2019 4BDeveloped By:

Benjamin Reyes /s/

10/10/2019 5BInstructor Date 6BValidated By:

Timothy McDougal /s/

10/10/2019 7BSME or Instructor Date 8BReviewed By:

Mace Davis /s/

10/10/2019 9BOperations Representative Date 10BApproved By:

J.E. Smith /s/

10/11/2019 1BTraining Department Date SRRS: 3D.105 (when utilized for operator initial or continuing training)

SA-3-02-0 Revision 07 Page 2 of 11 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 BAP 1450-1 Rev: 44 Procedure BAP 1450-T2 Rev: 38 Procedure 1BOL PC-1 Rev: 06 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 SRRS: 3D.100; There are no retention requirements for this section

SA-3-02-0 Revision 07 Page 3 of 11 Revision Record (Summary)

Revision 00, Initial Revision of JPM 04- - Changed to current format 05- - Updated to current procedure revision

- Changed RWP # to match current RW

- Added step for SRO to determine which entry condition to enter in 1BOL PC-1

- Validated on 3/3/13 by Bill Hochstetter and Rob Lawlor

- Made time critical for unidentified RCS leakage. Note: LCO is 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months made JPM at 50% of that time 06-Applied new template TQ-AA-150-J020 Updated referenced procedures to current revisions Corrected Task Number Removed time critical element based on feedback 07-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 to include date changes to data sheet to make current.

SRRS: 3D.100; There are no retention requirements for this section

SA-3-02-0 Revision 07 Page 4 of 11 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:

BAP 1450-1

BAP 1450-T2

1BOL PC-1

3. ENSURE the following is available during performance of the JPM:

BAP 1450-1

BAP 1450-T2 Reference

1BOL PC-1

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.

SRRS: 3D.100; There are no retention requirements for this section

SA-3-02-0 Revision 07 Page 5 of 11 INITIAL CONDITIONS You are the WEC Supervisor.

Unit 1 has just failed 1BOSR 4.13.1-1, Reactor Coolant System Water Inventory Balance 72 Hour Surveillance, due to unidentified leakage of 2.2 gpm.

Reactor power is 100% steady state.

Two EOs (Collin Pope, Daniel Welch) and one RP Technician (Mark Mueller) will be entering Unit 1 Containment to search for an RCS leak outside the missile barrier.

Collin Pope, ext 2473, is originating the Containment Entry Checklist, BAP 1450-T2.

The access control guard will be Tim Stevens, a security guard.

They expect to spend up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months searching for the leak.

RP directs entry through the emergency hatch.

INITIATING CUE Complete the required form for the containment entry for the WEC Supervisor responsibilities.

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

Information For Evaluators Use:

Task Performance Standard: Candidate will complete the WEC Supervisor section of BAP 1450-T2 and correctly identify the Condition and Required Actions per 1BOL PC-1.

UNSAT requires written comments on respective step.

Denotes critical steps. 2, 4, 6, and 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.

SRRS: 3D.100; There are no retention requirements for this section

SA-3-02-0 Revision 07 Page 6 of 11 JPM Start Time:

STEP ELEMENT STANDARD SAT UNSAT Comment Number NOTE:

The order of the steps is slightly different in the procedure and checklist.

NOTE:

The examinee may elect to notify Radiation Protection of the intent to enter containment first in order to expedite the verification of sampling requirements.

1 REFER to BAP 1450-1, Access to Containment, and BAP 1450-T2, Containment Entry Checklist LOCATE and OPEN:

o BAP 1450-1 o BAP 1450-T2 NOTE:

Provide the examinee with a copies of BAP 1450-1 and 1450-T2

2 Ensure MCR Turbine and Rx Panel placards are in place

Contacts MCR to PLACE Do Not Change Power placards

Turbine panel

Reactor panel CUE The Do Not Change Power placards are in place.

3 Ensure NSO is notified of Access Control Guards name o NSO is notified of name of Access Control Guard o Tim Stevens CUE NSO acknowledges security guards name.

4 MIDs are tagged out

VERIFY the MIDs are De-energized in accordance with OP-AA-109-101 MIDs shall be in storage or at the bottom of the reactor vessel Checklist marked YES CUE The MIDs are parked at the bottom the vessel and are Tagged Out SRRS: 3D.105 (when utilized for operator initial or continuing training)

SA-3-02-0 Revision 07 Page 7 of 11 STEP ELEMENT STANDARD SAT UNSAT Comment Number 5

For emergency hatch entry, initiate 1BOL PC-1 Determines 1BOL PC-1 initiation is required CUE When applicant identifies that 1BOL PC-1, LCOAR CONTAINMENT AIRLOCK DOOR SEALS, initiation is required or asks for a copy of 1BOL PC-1. Provide a blank a copy of 1BOL PC-1 NOTE:

A key has been provided for 1BOL PC-1.

CUE (If asked, which C.2 condition to apply), reply as follows: C.2.1

6 Determines BOL entry condition

Candidate reviews 1BOL PC-1

Condition C: Containment entry made through Emergency Hatch Airlock.

Immediately Document Containment Entry on Attachment A, Containment Entry Log AND Perform 1BOSR 6.2.1-2, Unit 1 Primary Containment Type B Local Leakage Rate Tests of the Emergency Personnel Airlock Door Gasket Interspaces within 7 days ( OR 30 Days AND containment entry is more frequent than once every 7 days)

CUE (WHEN candidate determines, which BOL entry condition and actions would be entered for this LCO) Return to BAP 1450-1 completion.

NOTE:

(from cue sheet) There will be no entry inside missile barrier.

SRRS: 3D.105 (when utilized for operator initial or continuing training)

SA-3-02-0 Revision 07 Page 8 of 11 STEP ELEMENT STANDARD SAT UNSAT Comment Number 7

Turn on lights inside missile barrier if entering inside the missile barrier o Determines No Entry Inside the Missile Barrier (No Lights required)

8 Sign WEC Supervisor Approval Examinee signs WEC approval CUE The JPM is complete.

JPM Stop Time:

SRRS: 3D.105 (when utilized for operator initial or continuing training)

SA-3-02-0 Revision 07 Page 9 of 11 JPM

SUMMARY

Operators Name:

Emp. ID#: ____________

Job

Title:

EO RO SRO FS STA/IA SRO Cert JPM

Title:

Assessing Containment At Power JPM Number: SA-3-02-0 Revision Number: 07 Task Number and

Title:

8E.AM-128 AUTHORIZE Containment Entry K/A Number and Importance: G 2.3.13: 3.8 Suggested Testing Environment: Classroom Alternate Path:

Yes No SRO Only:

Yes No Time Critical:

Yes No Reference(s): Procedure BAP 1450-1 Rev: 44 Procedure BAP 1450-T2 Rev: 38 Procedure 1BOL PC-1 Rev: 06 Actual Testing Environment:

Simulator Control Room In-Plant Other Testing Method:

Simulate Perform Estimated Time to Complete: 20 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:

SRRS: 3D.105 (when utilized for operator initial or continuing training)

SA-3-02-0 Revision 07 Page 10 of 11 SRRS: 3D.100; There are no retention requirements for this section

SA-3-02-0 Revision 07 Page 11 of 11 INITIAL CONDITIONS You are the WEC Supervisor.

Unit 1 has just failed 1BOSR 4.13.1-1, Reactor Coolant System Water Inventory Balance 72 Hour Surveillance, due to unidentified leakage of 2.2 gpm.

Reactor power is 100% steady state.

Two EOs (Collin Pope, Daniel Welch) and one RP Technician (Mark Mueller) will be entering Unit 1 Containment to search for an RCS leak outside the missile barrier.

Collin Pope, ext 2473, is originating the Containment Entry Checklist, BAP 1450-T2.

The access control guard will be Tim Stevens, a security guard.

They expect to spend up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months searching for the leak.

RP directs entry through the emergency hatch.

INITIATING CUE Complete the required form for the containment entry for the WEC Supervisor responsibilities.

SRRS: 3D.100; There are no retention requirements for this section

KEY BAP 1450-T2 Revision 38 Page 1 of 1 Level 1 - Continuous Use CONTAINMENT ENTRY CHECKLIST Unit to be Entered (X)

___Unit ONE

___Unit TWO ORIGINATOR Name:

Ext:

Date:

Estimated Duration:

Reason for Entry:

ENTRY CONDITIONS Radiation Protection 1.

Rad / Non-Rad Air Samples Satisfactory 2.

ALARA / RP/ Pre-job Brief Complete Radiation Protection Approval:

_______________________________ ______ / ______

RP Manager Approval (IMB Only)

(Modes 1 & 2 Only):

_______________________________ ______ / ______

WEC Supervisor 1.

Turbine / Reactor Placards in Place / NSO notified of Access Control Guard name.

2.

MIDS: Tagged Out (In Storage or at Vessel Bottom) Yes ____ No* ____

(*if NO, control in accordance with Sec: 4.3.3. of BAP 1450-1, RPM _____/_____)

3.

Entry Point:

Equipment Hatch - Verify Door Seal Alarm Operable or Initiate 1/2BOL PC-1, Containment Airlock Door Seals.

Emergency Hatch - Initiate 1/2BOL PC-1, Containment Airlock Door Seals.

4.

Contact Operating to turn on inside missile barrier lights if entry inside missile barrier required.

WEC Supervisor Approval: _______________________________ ______ / ______

Work Group Lead 1.

Access Control Guard Assigned. __________________

2.

Security notified to support Cnmt entry as required. __________________

3.

BAP 1450-8 reviewed during pre-job brief.

4.

Cnmt Evac monitor assigned. __________________

5.

Hatch Emergency Tool Kit Available.

6.

Emergency toolkit tamper seal unbroken.

7.

Each work group initiate _BOSR Z.5.b.1-1T2, Containment Loose Debris Log. N/A if not in MODE 1-4.

8.

Communication for Cnmt Evac established.

____ YES

____ N/A 9.

Successful test of Cnmt Evac Alarm.

____ SAT

____ UNSAT

_____ N/A Work Group Lead:

_______________________________ ______ / ______

CONTAINMENT EXIT / CHECKLIST CLOSEOUT Work Group Lead 1.

Containment Loose Debris Surveillance Complete. All material and equipment taken into containment has been removed or evaluation to remain in place has been approved by Engineering.

2.

Attach completed _BOSR Z.5.b.1-1T2, Containment Loose Debris Log, to this form.

3.

WEC Informed of Containment Entry Completion.

4.

Contact Operating to turn off inside missile barrier lights if no other entries planned.

Work Group Lead:

_______________________________ ______ / ______

WEC Supervisor 1.

Turbine / Reactor placards removed, if all personnel have exited containment.

2.

Verify Blue Tamper Seal installed on Emergency Hatch ONLY if Emergency Hatch remained closed. (inner hatch door and outer security door) 3.

Initiate 1/2BOSR 6.2.1-1/2, Airlock Door Gasket Interspace Test, as applicable.

WEC Supervisor:

_______________________________ ______ / ______

Collin Pope 2473 Today 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Search for a RCS leak outside the Missile Barrier Oliver Kents 20 minutes ago Today N/A X

X Applicant's name/signature Now Today N/A N/A

KEY 1BOL PC-1 Revision 6 Page 1 of 7 Reference Use FILE LOCATION: 2.05.0500 LCOAR CONTAINMENT AIRLOCK DOOR SEALS IMMEDIATE A.

NOTIFICATION TIME/DATE:

BY:

TITLE:

PRESENT MODE:

APPLICABLE MODE(s): 1, 2, 3, 4 INITIATING EVENT(s):

CONDITION(S)

Pg(s)

NAME OF SM NOTIFIED:

PLANNED TIME/DATE:

UNPLANNED WAS AN IR RELATED WO/WR(s):

RELATED CLEARANCE ORDER(s):

WRITTEN?

YES NO If NO, Reason:

LCO 3.0.3: N/A MODE Change Allowed Per LCO 3.0.4: N/A Separate Condition entry allowed: YES B.

ACTIONS 1.

COMPLETE, as required, the LCOAR Table per BAP 1400-6, checking all conditions to verify all applicable conditions are entered and followed.

/

One U1 Containment Entry for leak inspection C

5 X

X XXXXXX-XX U1 MIDS CO

KEY 1BOL PC-1 Revision 6 Page 2 of 7 Reference Use LCOAR TABLE CONTAINMENT AIRLOCK DOOR SEALS TECH SPEC SR 3.0.3 LCO compliance with a missed Surveillance.

CONDITION REQUIRED ACTION COMPLETION TIME Z.

Discovery of a surveillance not performed within its specified frequency.

______/______

TIME DATE Z.1.1 PERFORM the surveillance within EITHER 24 hrs OR the surveillance frequency, whichever is greater.

AND SR number: ____________________

CIRCLE completion time limit:

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Max Allowance SR Frequency

______/______ ________________

TIME DATE SRO SRO Z.1.2

NOTE------------------

Only applicable for surveillance to be delayed

> 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

VERIFY COMPLETE a risk evaluation which indicates a risk impact that is manageable.

OR 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Max Allowance

______/______ ________________

TIME DATE SRO Z.2 DECLARE the applicable function inoperable, complete Section A of this and/or any applicable BOL, and enter the appropriate conditions.

(Note 1)

______/______ ________________

TIME DATE SRO Notes:

1.

This time and date should also be entered in Section A (NOTIFICATION).

N/A

KEY 1BOL PC-1 Revision 6 Page 3 of 7 Reference Use LCOAR TABLE CONTAINMENT AIRLOCK DOOR SEALS TECH SPEC Pg COND Any Of The Following CONDITIONS:

CIRCLE applicable CONDITION(S) 3 A.

Alarm 1-1-B2, Cnmt Hatch Door Seal Trouble, is lit and alarm is inoperable as indicated by one of the following conditions.

1.

Airlock doors are closed and leak detection system parameters indicate out of spec:

Low Pressure < 3.1 PSIG High Pressure > 4.6 PSIG High Flow > 1.0 SCFH 2.

Airlock doors are closed and leak detection system parameters are normal.

(eg. annunciator failure) 4 B.

Cnmt Entry made through Personnel Airlock with door seal trouble alarm inoperable.

5 C.

Containment entry made through Emergency Airlock.

5 D.

Required Action not met for Condition B.2 or C.2.

CONDITION REQUIRED ACTION COMPLETION TIME A.

Alarm 1-1-B2, Cnmt Hatch Door Seal Trouble, alarm is lit, and alarm is inoperable.

______/______

TIME DATE SRO A.1 Notify WEC that 1BOL PC-1, Attachment A, Unit One Containment Entry Log, will be required for entries using the personnel airlock until alarm is returned to operable.

AND Immediately

______/______ ________________

TIME DATE SRO A.2 Perform 1BOSR 6.2.1-1, Unit 1 Primary Containment Type B Local Leakage Rate Tests of the Equipment Hatch Airlock Door Gasket Interspaces, to verify integrity of door seals.

24 Hours

______/______ ________________

TIME DATE SRO

KEY 1BOL PC-1 Revision 6 Page 4 of 7 Reference Use LCOAR TABLE CONTAINMENT AIRLOCK DOOR SEALS CONDITION REQUIRED ACTION COMPLETION TIME B.

Containment entry made through Personnel Airlock with door seal trouble alarm inoperable.

B.1 Document Cnmt Entry on Attachment A, Containment Entry Log. (Note 1)

AND Immediately

______/______ ________________

TIME DATE SRO

______/______

TIME DATE SRO B.2.1 Perform 1BOSR 6.2.1-1, Unit 1 Primary Containment Type B Local Leakage Rate Tests of the Equipment Hatch Airlock Door Gasket Interspaces.

OR 7 days

______/______ ________________

TIME DATE SRO B.2.2 Perform 1BOSR 6.2.1-1, Unit 1 Primary Containment Type B Local Leakage Rate Tests of the Equipment Hatch Airlock Door Gasket Interspaces.

30 Days AND containment entry is more frequent than once every 7 days. (Note 2)

______/______ ________________

TIME DATE SRO Notes:

1.

Multiple Containment entries may be documented on Attachment A. LLRT must be performed within applicable time limit of the initial entry.

2.

Track entry into Containment occurs every rolling 7 days or surveillance must be performed prior to exceeding 7 days. For periods of multiple containment entries where the airlock doors are routinely used for access more frequently than once every 7 days (e.g., shift or daily inspection tours of the containment), door seals may be tested once per 30 days during this time period. (Ref. NEI-94-01)

KEY 1BOL PC-1 Revision 6 Page 5 of 7 Reference Use LCOAR TABLE CONTAINMENT AIRLOCK DOOR SEALS CONDITION REQUIRED ACTION COMPLETION TIME C.

Containment entry made through Emergency Hatch Airlock.

C.1 Document Containment Entry on Attachment A, Containment Entry Log. (Note 1)

AND Immediately

____/______________________

TIME DATE SRO

______/______

TIME DATE SRO C.2.1 Perform 1BOSR 6.2.1-2, Unit 1 Primary Containment Type B Local Leakage Rate Tests of the Emergency Personnel Airlock Door Gasket Interspaces.

OR 7 days

______/______ ________________

TIME DATE SRO C.2.2 Perform 1BOSR 6.2.1-2, Unit 1 Primary Containment Type B Local Leakage Rate Tests of the Emergency Personnel Airlock Door Gasket Interspaces.

30 Days AND containment entry is more frequent than once every 7 days. (Note 2)

______/______ ________________

TIME DATE SRO D.

Required Action and associated completion time of Condition B.2 or C.2 not met.

D.1 Enter 1BOL 6.2, Containment Airlocks.

Immediately

______/______ ________________

TIME DATE SRO Notes:

1.

Multiple Containment entries may be documented on Attachment A. LLRT must be performed within applicable time limit of the initial entry.

2.

Track entry into Containment occurs every rolling 7 days or surveillance must be performed prior to exceeding 7 days. For periods of multiple containment entries where the airlock doors are routinely used for access more frequently than once every 7 days (e.g., shift or daily inspection tours of the containment), door seals may be tested once per 30 days during this time period. (Ref. NEI-94-01)

KEY 1BOL PC-1 Revision 6 Page 6 of 7 Reference Use C.

RESTORATION 1.

An SRO shall determine the applicable surveillances and/or other actions required to demonstrate LCO restoration and LIST and/or MARK those that apply:

a.

For the Initiating Event(s) in Section A (NOTIFICATION) of this LCOAR 1BOSR 6.2.1-1 1BOSR 6.2.1-2 1BOSR 6.2.1-5 TIME/DATE when these requirements are met /

SRO b.

For the Initiating Event(s)

List the component, etc. from in Section A (NOTIFICATION) line B.2 of the related of a related 1BOL 0.0.

1BOL 0.0.

FOR FOR FOR If more than 1 associated 1BOL 0.0 exists, use comments section to identify when the requirements are met for each.

TIME/DATE when these requirements are met /

SRO 2.

Comments:

3.

Once all of the above requirements have been satisfactorily completed (with SM concurrence if appropriate), RECORD the Time and Date the LCO is met. TERMINATE the Action Requirements excluding any SPECIAL REPORT or SPECIAL ACTIONS and RETURN the affected Equipment/Unit to desired status.

SRO (NOT Duty S.M.):

TIME/DATE:

/

Remarks and/or additional requirements:

DUTY SHIFT MANAGER:

TIME/DATE:

/

KEY 1BOL PC-1 Revision 6 Page 7 of 7 Reference Use ATTACHMENT A UNIT ONE CONTAINMENT ENTRY LOG NOTE The containment entry log sheet is only required if the Cnmt Hatch Door Seal Trouble Alarm is not operable or if access to Containment is gained through the Containment Emergency Hatch. 1BOSR 6.2.1-1, Unit 1 Primary Containment Type B Local Leakage Rate Tests of the Equipment Hatch Airlock Door Gasket Interspaces, or 1BOSR 6.2.1-2, Unit 1 Primary Containment Type B Local Leakage Rate Tests of the Emergency Personnel Airlock Door Gasket Interspaces, are required within 7/30 days as applicable after the first containment entry on this log sheet. Exit LCOAR following successful completion of LLRT.

By:

Name / Date / Time ENTRY TIME/DATE EQUIP AIRLOCK EMERG AIRLOCK REASON FOR ENTRY 1

2 3

4 5

6 7

8 9

10 11 12 Applicant's name Date and time from Condition C Expected time and date or Condtion C time and date N/A X

Unit 1 Rcs leakage inspection (or equivalent)

SA-4-02-1 Revision 00 Page 1 of 17 Job Performance Measure 0BPerform Follow-up PARS for a General Emergency 1BJPM Number: SA-4-02-1 2BRevision Number: 00 3BDate: 08 / 19 / 2019 4BDeveloped By:

Benjamin Reyes /s/

10/17/2019 5BInstructor Date 6BValidated By:

Mark Kultgen /s/

10/17/2019 7BSME or Instructor Date 8BReviewed By:

Mace Davis /s/

10/17/2019 9BOperations Representative Date 10BApproved By:

J.E. Smith /s/

10/17/2019 1BTraining Department Date SRRS: 3D.105 (when utilized for operator initial or continuing training)

SA-4-02-1 Revision 00 Page 2 of 17 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.

MGK___

1.

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

MGK___

2.

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

MGK___

3.

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

MGK___

4.

Initial setup conditions are identified.

MGK___

5.

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

MGK___

6.

Task standards identified and verified by SME review.

MGK___

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.

MGK___

9.

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

Procedure EP-MW-114-100-F01 Rev: 01 Procedure EP-AA-111 Rev: 22 Procedure EP-AA-111-F-03 Rev: 01 Procedure EP-AA-1002 Addendum 3 Rev: 02 Procedure EP-AA-1002 Rev: 35 Procedure EP-MW-114-100 Rev: 18 MGK___

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

MGK___

11. Verify performance time is accurate N/A____

12. If the JPM cannot be performed as written with proper responses, then revise the JPM.

MGK___

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 SRRS: 3D.100; There are no retention requirements for this section

SA-4-02-1 Revision 00 Page 3 of 17 Revision Record (Summary)

Revision 00, JPM creation for NRC Exam 19-2 SRO only.

SRRS: 3D.100; There are no retention requirements for this section

SA-4-02-1 Revision 00 Page 4 of 17 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:

NOTE: Site Emergency Director binder may be accessed to obtain the required procedures if JPM is administered in the Simulator

EP-AA-1002, RADIOLOGICAL EMERGENCY PLAN ANNEX FOR BYRON STATION

EP-AA-1002 Addendum 3, EMERGENCY ACTION LEVELS FOR BYRON STATION

EP-MW-114-100, MIDWEST REGION OFF-SITE NOTIFICATIONS

EP-AA-111-F-03 Rev I, BYRON PAR FLOWCHART

EP-MW-114-100-F-01 Rev J NARS Form Reference

3. ENSURE the following is available during performance of the JPM:

EP-AA-1002, RADIOLOGICAL EMERGENCY PLAN ANNEX FOR BYRON STATION

EP-AA-1002 Addendum 3, EMERGENCY ACTION LEVELS FOR BYRON STATION

EP-MW-114-100, MIDWEST REGION OFF-SITE NOTIFICATIONS

EP-AA-111-F-03 Rev I, BYRON PAR FLOWCHART

EP-MW-114-100-F-01 Rev J NARS Form Reference

Data sheet

4. ENSURE the following between performances of the JPM:

New clean procedure copies and references for examinee to work from during performance

5. This completes the setup for this JPM.

SRRS: 3D.100; There are no retention requirements for this section

SA-4-02-1 Revision 00 Page 5 of 17 INITIAL CONDITIONS FG1 General Area Emergency was declared 30 minutes ago due to the SG rupture / faulted outside of containment with a Safety Injection and RCS Activity. All initial notifications have been completed.

The meteorological data has just changed since the initial EAL declaration

The TSC has NOT been activated

A Rapidly Progressing Severe Accident is NOT in progress INITIATING CUE As Shift Emergency Director, perform any required actions due to the changes in meteorological data.

Note: The STA is unavailable to perform a Peer Check.

This is a Time Critical JPM.

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

SRRS: 3D.100; There are no retention requirements for this section

SA-4-02-1 Revision 00 Page 6 of 17 Information For Evaluators Use:

Task Performance Standard: Applicant determines the correct Protective Action Recommendations, PARs, in accordance with Byron Station EP procedures and completes EP-MW-114-100-F-01, Nuclear Accident Reporting System (NARS) Form per EP-MW-114-100.

UNSAT requires written comments on respective step.

Denotes critical steps: 3, 13 - 15 & 17 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.

SRRS: 3D.100; There are no retention requirements for this section

SA-4-02-1 Revision 00 Page 7 of 17 JPM Start Time:

STEP ELEMENT STANDARD SAT UNSAT Comment Number CUE Complete NARS Form EP-MW-114-100-F-01 for Utility Message #2 filling in the current date and the current time (JPM Start) minus thirty minutes in Block 4, Accident Classified. Provide the completed NARS Form to the applicant.

Provide the applicant with the completed Nuclear Accident Reporting System NARS Forms, EP-MW-114-100-F-01, for Utility Messages #2 along with the meteorological PPCS printout with the new data.

CUE Provide the applicant EP-MW-114-100, EP-MW-114-100-F-01, EP-AA-111, and EP-AA-111-F-03.

1 Refer to Station Emergency Procedures.

Locate and Open the following:

o EP-MW-114-100 o EP-MW-114-100-F-01 o EP-AA-111 o EP-AA-111-F-03 2

Evaluate meteorological data.

Compare the following:

Provided meteorological PPCS printout.

Provided NARS Form EP-MW-114-100-F-01 for Utility Message #2 NOTE:

Due to the wind direction shift, a change in PAR recommendations is required.

While identifying the affected Sub Areas in attachment B, Sub Areas 17, 19, and 23 must be identified. The applicant may also identify Sub Areas 20 and 25 at this time. Sub Areas 20 and 25 are not required to be identified at this time, however, they are required in performance step 15 as they are carried over from the previous PARS Recommendation

3 Evaluate and determine a PAR change is required.

Evaluate for PAR recommendation.

o Refer to EP-AA-11-F-03, Byron PAR Flowchart SRRS: 3D.105 (when utilized for operator initial or continuing training)

SA-4-02-1 Revision 00 Page 8 of 17 STEP ELEMENT STANDARD SAT UNSAT Comment Number o Determine; Classification is a General Emergency:

Yes o Determine; Is this the initial PAR: No o Determine; Hostile Action Events or Rapidly Progressing Severe Accident in progress: No o Go to: Page 2 for all other General Emergency Declarations.

o Determine; Changes in wind direction affecting new downwind areas per Table B: Yes o Determine; Do conditions exist which would require the classification of a General Emergency per the EALs? Yes o Determine; Is this PAR being made from the Control Room? Yes

Determine; Evacuate areas per Table B:

Wind Direction from 125o to 237 o

Sub Areas 17, 19, 23

Recommended PARS change determined to be required time = <15 minutes.

SRRS: 3D.105 (when utilized for operator initial or continuing training)

SA-4-02-1 Revision 00 Page 9 of 17 STEP ELEMENT STANDARD SAT UNSAT Comment Number NOTE:

Record time that a change to recommended PARS is determined to be required.

Change to recommended PARS is determined to be required - JPM Start time =

______:______:______ (<15 minutes)

CUE When the applicant determines that a change to recommended PARS is required; provide the applicant with a blank Nuclear Accident Reporting System NARS Forms, EP-MW-114-100-F-01.

4 Obtain NARS form.

o Locate and Open EP-MW-114-100-F-01, NUCLEAR ACCIDENT REPORTING SYSTEM (NARS) FORM NOTE:

Step 4 is optional and may be performed at any time.

5 Refer to EP-MW-114-100, MWROG Offsite Notifications, to complete NARS form.

o Locate and Open, EP-MW-114-100, MWROG Offsite Notifications, Section 4.2, to complete NARS form.

NOTE:

Key for completed NARS Form, EP-MW-114-100-F-01, attached as pages 14 and 15 of this document.

6 Complete NARS Form, Message No.

UTILITY MESSAGE NO.

Enter: 3 o STATE MESSAGE NO.

o Enter: N/A 7

Complete NARS Form, block 1.

1. STATUS:

Mark: [B]

DRILL/EXERCISE 8

Complete NARS Form, block 2.

2. STATION:

Mark: [B] BYRON SRRS: 3D.105 (when utilized for operator initial or continuing training)

SA-4-02-1 Revision 00 Page 10 of 17 STEP ELEMENT STANDARD SAT UNSAT Comment Number 9

Complete NARS Form, block 3.

3. ONSITE CONDITION:

Mark: [D] GENERAL EMERGENCY NOTE:

Change in wind direction will require new PAGs to be designated. Event does NOT meet the requirements for a Rapidly Progressing Severe Accident.

10 Complete NARS Form, block 4.

4. ACCIDENT CLASSIFIED:

TIME:

Enter: 30 minutes prior to the JPM start time

DATE:

Enter: todays date

EAL#:

Enter: FG1 o ACCIDENT TERMINATED:

o TIME:

o Enter: N/A o DATE:

o Enter: N/A 11 Complete NARS Form, block 5.

5. RELEASE STATUS:

Mark: [B] OCCURRING 12 Complete NARS Form, block 6.

6. TYPE OF RELEASE:

Mark: [B] GASEOUS

13 Complete NARS Form, block 7.

7. WIND DIR:

Enter: 193 SRRS: 3D.105 (when utilized for operator initial or continuing training)

SA-4-02-1 Revision 00 Page 11 of 17 STEP ELEMENT STANDARD SAT UNSAT Comment Number

14 Complete NARS Form, block 8.

8. WIND SPEED:

Mark: [B] MILES/HR:

Enter: 8.6

15 Complete NARS Form, block 9.

9. RECOMMENDED ACTIONS:

UTILITY RECOMMENDATION:

Mark: [D] EVACUATE Illinois Sub-areas:

17, 19, 20, 23, and 25 (as determined from EP-AA-111-F-03 Table B and as carried over from previous PARS Recommendation).

16 Complete NARS Form, block

10.

10. ADDITIONAL INFORMATION:

Enter: None

17 Complete NARS Form, approval block.

o Verified With:

o Enter: N/A

Approved By:

Enter: applicants signature

NARs Form completed = <

12 minutes.

NOTE:

Record time NARS Form completed: ______:______:______

NARS Form completed - Change to recommended PARS is determined to be required time = ______:______:______ (<12 minutes to allow for Initial Roll Call completion of NARS Form transmittal.)

CUE This JPM is complete.

SRRS: 3D.105 (when utilized for operator initial or continuing training)

SA-4-02-1 Revision 00 Page 12 of 17 JPM Stop Time:

SRRS: 3D.105 (when utilized for operator initial or continuing training)

SA-4-02-1 Revision 00 Page 13 of 17 JPM

SUMMARY

Operators Name:

Emp. ID#: ____________

Job

Title:

EO RO SRO FS STA/IA SRO Cert JPM

Title:

Perform Follow-up PARS for a General Emergency JPM Number: SA-4-02-1 Revision Number: 00 Task Number and

Title:

8F.ZP-012 RESPOND to Station Emergency as Station Director K/A Number and Importance: G 2.4.44 4.4 Suggested Testing Environment: Classroom Alternate Path:

Yes No SRO Only:

Yes No Time Critical:

Yes No

14. Reference(s):

Procedure EP-MW-114-100-F01 Rev: 01 Procedure EP-AA-111 Rev: 22 Procedure EP-AA-111-F-03 Rev: 01 Procedure EP-AA-1002 Addendum 3 Rev: 02 Procedure EP-AA-1002 Rev: 35 Procedure EP-MW-114-100 Rev: 18 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:

SRRS: 3D.105 (when utilized for operator initial or continuing training)

SA-4-02-1 Revision 00 Page 14 of 17 SRRS: 3D.105 (when utilized for operator initial or continuing training)

SA-4-02-1 Revision 00 Page 15 of 17 SRRS: 3D.105 (when utilized for operator initial or continuing training)

SA-4-02-1 Revision 00 Page 16 of 17 INITIAL CONDITIONS FG1 General Area Emergency was declared 30 minutes ago due to the SG rupture / faulted outside of containment with a Safety Injection and RCS Activity. All initial notifications have been completed.

The meteorological data has just changed since the initial EAL declaration

The TSC has NOT been activated

A Rapidly Progressing Severe Accident is NOT in progress INITIATING CUE As Shift Emergency Director, perform any required actions due to the changes in meteorological data.

Note: The STA is unavailable to perform a Peer Check.

This is a Time Critical JPM.

SRRS: 3D.100; There are no retention requirements for this section

SA-4-02-1 Revision 00 Page 17 of 17 0

0 9

0 2

7 0

180 SRRS: 3D.100; There are no retention requirements for this section

ML20054C077

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