Text

Draft Operating Test (Section a, Section B, Section C) (Folder 2)
	ML21237A478
Person / Time
Site:	Peach Bottom
Issue date:	03/26/2021
From:	Todd Fish; Operations Branch I
To:	; Exelon Generation Co
Shared Package
ML20259A377	List: ML21237A478; ML21237A518;
References
	EPID L-2021-OLL-0002
	Download: ML21237A478 (172)
	v • d • e

EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET

~

JPM QUALIFICATION MANUAL OJT MODULE Licensed Operator Training PLOR-348C 2021 IL T NRC JPM RO C001 003 D. W.Adams dwa Evaluation of High CRD Temperature on Control Rod Scram Time APPROVALS:

I Signature/ Title Date Signature/ Title Date Signature/ Title Date Signature / Title Date PPROVED FOR USE:

Signature I Title Date EFFECTIVE DATE:

NAME:

ISSUE DATE:

Last First M.I.

EMPLOYEE ID NO.

COMPLETION DATE:

COMMENTS:

Training Review for Completeness:

LMS CODE:

LMS ENTRY:

Signature/Date PLOR348C Rev0033 Page 1 of 5 I I I

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EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE

I

i POSITION TITLE:

Unit Reactor Operator TASK-JPM DESIGNATOR:

2011050401 / PLOR-348C KIA: 1 G2.1.32 RO: 3.8 TASK DESCRIPTION:

Evaluation of High CRD Temperature on Control Rod Scram Time A.

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NOTES TO EVALUATOR:

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1.

2.

3.

4.

5.

An asterisk(*) before the step number denotes a CRITIC1L STEP. CRITICAL STEP.1 are those steps which when not performed correctly will prevent the system from 1

functioning properly or prevent successful task completion.

1 System cues included in the performance checklist are to be provided to the examinee when no system response is available.

I JPM Performance

[

a. -

"Control Room" JPMs are designed to be performed in the simulator. If a I

"Control Room" JPM is to be performed in the Control Room all perform steps W) shall be simulated (S).

j

b.

When performing "In-Plant" JPMs, no equipment will be operated without Shift 1

Management approval.

Satisfactory performance of this JPM is accomplished if:

a.

The task standard is met.

b.

JPM completion time requirement is met.

I

1)

For non-time critical JPMs, completion within double the estimated time I (listed in paragraph D.2) is acceptable provided the evaluator determin~s that the progress to completion is acceptable.

2)

For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

The estimated time to complete this JPM, though listed in the task standard, is not to 1lbe given to the examinee.

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PLOR348C Rev0033 Page 2 of 5

B.

TOOLS AND EQUIPMENT

1.

BLANK Copy of AO 3.8 "Evaluation of High CRD Temperature on Control Rod Scram Time"

2.

Calculator C.

REFERENCES

1.

AO 3.8, Rev. 2 "Evaluation of High CRD Temperature on Control Rod Scram Time"

2.

Unit 3 Tech Spec 3.1.4 D.

TASK STANDARD

1.

Satisfactory task completion is indicated when steps 4.1-4.5 are complete and the out of spec scram times are identified.

2.

Estimated time to complete: 20 minutes Non-Time Critical E.

DIRECTIONS TO EXAMINEE When given the initiating cue, complete steps 4.1 through 4.5 of AO 3.8, "Evaluation of High CRD Temperature on Control Rod Scram Time". I will describe initial plant conditions and provide you the materials required to complete this task. I will provide a copy of the required Tech Spec table.

F.

TASK CONDITIONS/PREREQUISITES

1.

Unit 3 is at 100% power.

2.

Control Rod 18-55 temperature is 405 °F and cannot be lowered.

3.

System Manager has provided the latest Scram Time data for CR 18-55 from the current operating cycle, as recorded in ST-R-003-475-3:

Position 46 - 0.343 Sec Position 36 - 0.844 Sec Position 26 - 1.396 Sec Position 06 - 2.599 Sec G.

INITIATING CUE The Control Room Supervisor directs you to: (1) complete steps 4.1 through 4.5 AND 4.8 of !

AO 3.8, "Evaluation of High CRD Temperature on Control Rod Scram Time" for Unit 3 Contr0I Rod 18-55, and (2) if applicable, identify any out-of-specification conditions by circling all unsatisfactory data points on the AO datasheets.

PLOR348C Rev0033 Page 3 of 5

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H.

PERFORMANCE CHECKLIST i

TEP STEP ACT STANDARD

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NO

- - NOTE ***

1 is a copy of AO 3.8 formatted as an answer key. Copy of AO 3.8 provided tO Candidate should NOT CONTAIN ANY DATA.

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Obtain a BLANK copy of AO 3.8.

p AO 3.8, "Evaluation of High CRD I

(CUE: Provide candidate with a BLANK Temperature on Control Rod Scram I

copy of AO 3.8 - ENSURE YOU DO NOT Time" is obtained.

HAND OUT ANSWER KEY -Also provide candidate with Tech Spec Table I

3.1.4-1) 2 Record Unit, Control Rod number, and p

Unit 3, Control Rod 18-55, and 405°F :

CRD Temperature on AO 3.8, Pages 7-recorded ora AO 3.8, Pages 7-10.

10.

- - NOTE***

Data obtained for AO 3.8 Step 4.2 is given in lnit!ating Cue.

3 Record the Position 46 (36, 26, 06) scram p

Scram Time recorded - Position 46 (36!

time in appropriate location in AO 3.8 26, 06) Scr~m Time (0.343, 0.844, 1.396, 2.599 sec, respectively) and record in* 1 appropriate location in AO 3.8.

4 Determine the Position 46 (36, 26, 06) p Correctly determine the Position 46 (36, Penalty and record in AO 3.8 26, 06) Penalty (0.35, 0.60, 0.70, 0.70:

sec, respectively) and record in appropriate location in AO 3.8.

I

5 Add the Position 46 (36, 26, 06) Scram p

Scram Tim~ and Penalty summed Time to the associated Penalty and correctly - Position 46 (36, 26, 06) -

I record in AO 3.8 (0.693, 1.444, 2.096, 3.299 sec, I

respectively) and record in AO 3.8.

6 Record the Maximum Notch Scram Time p

Correctly determine the Maximum Notch allowed by Tech Spec Table 3.1.4-1 for Scram Timia allowed by Tech Spec T a,le Position 46 (36, 26, 06) and record in 3.1.4 Refer to Key provided as AO3.8 PLOR348G Rev000 at 3

7 Review data for out of specification p

IDENTIFY Scram Time to positions 46, conditions, annotate datasheets by 36, 26 OUT OF SPECIFICATION.

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circling out-of-spec points.

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8 Inform Control Room Supervisor of p

Control room Supervisor is notified of t~sk completion of AO 3.8 Steps 4.1-4.5 and completion: Ca~didate turns o~er

I 4.8.

datasheets, and informs supervisor th~t II (Cue: acknowledge communication.)

there are o~t-of-spec points.

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PLOR348C Rev0033 Page 4 of 5 I

I STEP NO 9

STEP As an evaluator, ensure that you have positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND procedures.

Under "ACT" P - must perform S - must simulate I.

TERMINATING CUE ACT STANDARD p

Positive control established.

When steps 4.1 through 4.5 AND 4.8 of the AO are complete, the Control Room Supervisor should be informed, the evaluator will terminate the exercise.

PLOR348C Rev0033 Page 5 of 5 I

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EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET QUALIFICATION MANUAL OJT MODULE LICENSED OPERATOR TRAINING PLOR-391C

-2021 IL T NRC JPM RO C002 001 N. Patrou ntp APPLICATION OF WORK HOUR RULES APPROVALS:

Signature I Title Date Signature/ Title Date Signature/ Title Date Signature / Title Date

/\\ PP ROVED FOR USE:

Signature I Title Date EFFECTIVE DATE: _____

NAME:

ISSUE DATE:

Last First M.I.

EMPLOYEE ID NO.

COMPLETION DATE:

COMMENTS:

Training Review for Completeness:

LMS CODE:

LMS ENTRY:

Signature/Date PLOR391 C Rev001 Page 1 of 6 I

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I

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:

Reactor Operator TASK-JPM DESIGNATOR:

2990990101 / PLOR-391C KIA:

G2.1.5 RO: 2.9 TASK DESCRIPTION:

Application of Work Hour Rules A.

NOTES TO EVALUATOR:

1.

An asterisk(*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion~

2.

System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3.

JPM Performance

a.

"Control Room" JPMs are designed to be performeg in the simulator. If a "Control Room" JPM is to be performed in the Control Room all perform steps ( )

shall be simulated (S).

b.

When performing "In-Plant" JPMs, no equipment will be operated without Shift Management approval.

4.

Satisfactory performance of this JPM is accomplished if:*

5.

a.

The task standard is met.

b.

JPM completion time requirement is met.

1)

For non-time critical JPMs, completion within. double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determine that the progress to completion is acceptable.

2)

For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

c.

Applicable JPM Work Practice Standards, TQ-JA-150-04 graded satisfactorily.

The estimated time to complete this JPM, though listed in the task standard, is not to _l:le given to the examinee.

I PLOR391 C Rev001 Page 2 of 6

8.

TOOLS AND EQUIPMENT None C.

REFERENCES

1.

LS-AA-119, Rev 14, "Fatigue Management and Work Hour Rules" D.

TASK STANDARD

1.

Satisfactory task completion is indicated when the candid~te states that the proposed work schedule cannot be worked due to: 1) greater than 26 hours3.009259e-4 days 0.00722 hours 4.298942e-5 weeks 9.893e-6 months in a 48-hour period; and, 2) greater than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in a 7 day period.

2.

Estimated time to complete: 10 minutes Non-Time CriticJ1 E.

DIRECTIONS TO EXAMINEE C'

When given the initiating cue, perform necessary steps to determ;ine post maintenance testing requirements and the associated surveillance test performance steps which are required to be performed using appropriate procedures. I will describe initial pl~nt conditions and provide yJu access to the materials required to complete this task.

i TASK CONDITIONS/PREREQUISITES

1. The plant is at rated power.

2. Today is Monday, June 9th, at 2000. You have worked the day-shift with the following I

schedule for the past 8 days:

1 I

i Sunday Monday Tuesday Wednesday Thursday 1.

Friday Saturday

, 6/1 6/2 6/3 6/4 6/5 I

6/6 6/7

1 0700-1900 OFF

OFF OFF 0700-1800 *i 0700-2000 0700-1906

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Saturda~

Sunday Monday Tuesday Wednesday Thursday 1 Friday 6/8 6/9 6/10 6/11 6/12 6/13 6/14

1 I I 0700-1700 TODAY Scheduled Scheduled I

OFF OFF I

I 0700-1800 i

I

.j PLOR391C Rev001 I

Page 3 of 6 I

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G.

INITIATING CUE I

At 2000 tonight, Monday, you were called at home to cover shift the following day, Tuesday,

~

from 0500 until 2100, as a covered worker.

i State whether you are allowed or not allowed to report for the scheduled work. If not allowedj, state any and all reasons why. No waivers will be approved.

PLOR391C Rev001 Page 4 of6

H.

PERFORMANCE CHECKLIST TEP NO STEP ACT STANDARD 1

Review LS-AA-119.

p Reviews LS-AA-119.

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Note: The following steps may be performed in any order.

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2 Determine the number of hours worked in p

Determines, the number of hours worker a 24-hour period (from 0500 to 2100 in a 24-hour period (from 0500 to 2100 Tuesday) is 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months .

Tuesday) is 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months .

3 Determine that 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months worked in a 24-p Determines that 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months worked in a ~4-hour period is within the limit of 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months hour period 1 is within the limit of 16 ho~~s in a 24-hour period.

in a 24-hour period.

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4 Determine the number of hours worked in p

Determines the number of hours workecJ a 48-hour period (from 0700 Monday to in a 48-hour period (from 0700 Monday! to 0700 Wednesday) is 11 + 16 = 27 hours3.125e-4 days 0.0075 hours 4.464286e-5 weeks 1.02735e-5 months .

0700 Wednesday) is 11 + 16 = 27 hours3.125e-4 days 0.0075 hours 4.464286e-5 weeks 1.02735e-5 months .

/

I

5 Determine that 27 hours3.125e-4 days 0.0075 hours 4.464286e-5 weeks 1.02735e-5 months worked in a 48-p Determines that 27 hours3.125e-4 days 0.0075 hours 4.464286e-5 weeks 1.02735e-5 months worked in a 48-hour period exceeds the limit of 26 hours3.009259e-4 days 0.00722 hours 4.298942e-5 weeks 9.893e-6 months hour period exceeds the limit of 26 hours3.009259e-4 days 0.00722 hours 4.298942e-5 weeks 9.893e-6 months in a 48-hour period.

in a 48-hour period, and thus cannot

I report to work.

I 6

Determine that the number of hours p

Determine that the number of hours

\\

worked in a 7 day period (from 0700 worked in a 7 day period (from 0700 Wednesday to 0700 Wednesday) is Wednesday to 0700 Wednesday) is 11+13+12+10+11+16=73 hours.

11+13+12+10+11+16=73 hours.

i

7 Determine that 73 hours8.449074e-4 days 0.0203 hours 1.207011e-4 weeks 2.77765e-5 months worked in a 7 p

Determine that 73 hours8.449074e-4 days 0.0203 hours 1.207011e-4 weeks 2.77765e-5 months worked in a 71 I

day period exceeds the limit of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months day period exceeds the limit of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in a 7 day period.

in a 7 day period.

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8 As an evaluator, ensure that you have p

Positive co~trol established.

i positive control of all exam material provided to the examinee (Task Conditions/Prerequisite~) AND procedures.

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'I PLOR391C Rev001 Page 5 of 6 I

Under "ACT" P - must perform S - must simulate I.

TERMINATING CUE I

When the candidate states that the proposed work schedule cannot be worked due to: 1)

I greater than 26 hours3.009259e-4 days 0.00722 hours 4.298942e-5 weeks 9.893e-6 months in a 48-hour period; and, 2) greater than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in a 7 day period, the evaluator will terminate the exercise.

PLOR391 C Rev001 Page 6 of6 1

EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET

~

JPM QUALIFICATION MANUAL OJT MODULE LICENSED OPERATOR TRAINING PLOR-245C 2021 IL T NRC JPM RO EC 000 M. J. KELLY mjk INITIATING A TEMPORARY PROCEDURE CHANGE APPROVALS:

Signature I Title Date Signature / Title Date Signature / Title Date Signature / Title Date PPROVED FOR USE:

Signature I Title Date EFFECTIVE DATE:

/

NAME:

ISSUE DATE:

Last First M.I.

SOC. SEC. NO.

COMPLETION DATE:

COMMENTS:

Training Review for Completeness:

PIMS CODE:

PIMS ENTRY:

Signature/Date PLOR245C Rev000 Page 1 of 6 i

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JSITION TITLE:

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE Unit Reactor Operator TASK-JPM DESIGNATOR:

3421130302 / PLOR-245C KIA:

G2.2.6 URO: 3.0 TASK DESCRIPTION:

Temporary Changes to Approved Documents and Procedures A.

NOTES TO EVALUATOR:

1.

An asterisk(*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion':

2.

System cues included in the performance checklist are to be provided to the examine when no system response is available.

3.

JPM Performance

a.

"Control Room" JPMs are designed to be performed in the simulator. If a "Control Room" JPM is to be performed in the Control Room all perform steps ( )

shall be simulated (S).

b.

When performing "In-Plant" JPMs, no equipment will be operated without Shift Management approval.

4.

Satisfactory performance of this JPM is accomplished if:

a.

The task standard is met.

b.

JPM completion time requirement is met.

1)

For non-time critical JPMs, completion withiq double the estimated time*

(listed in paragraph D.2) is acceptable provided the evaluator determine that the progress to completion is acceptable.

2)

For time critical JPMs, completion within the 'estimated time (listed in paragraph D.2) is required.

5.

The estimated time to complete this JPM, though listed in the task standard, is not to e given to the examinee.

PLOR245C Rev000 Page 2 of6 I

(

B.

TOOLS AND EQUIPMENT D.

1.

None REFERENCES

1.

AD-PB-101-1003, Rev. 15, Temporary Changes to Approved Documents and Partial Procedure Use.

2.

SO 52A.1.B, Rev. 66, Diesel Generator Operations, Section 4.1, Slow Start.

TASK STANDARD I

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1.

Satisfactory task completion is indicated when Temporary Change has been submitted to the SRO using Attachment 1, Temporary Change Control Form, Originator Section, 1is completed in accordance with the approved procedure.

2.

Estimated time to complete: 20 minutes Non-Time Critical E.

DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to initiate :a "single use" temporary change to SO 52A.1.B, "Diesel Generator Operations, Slow Start!', step 4.1.2.4, using I

AD-PB-101-1003, "Temporary Changes to Approved Documents.and Partial Procedure Use":.

I will describe initial plant conditions and provide you access to the materials required to complete this task.

TASK CONDITIONS/PREREQUISITES

1.

2.

3.

4.

5.

6.

The Plant is operating at full power.

A "slow start" of the E-1 Diesel Generator using SO 52A.1,B "Diesel Generator Operations", is required today for performance monitoring,by Predictive Maintenance.

SO 52A.1.B "Diesel Generator Operations" has no existing Temporary Changes.

The E-1 Diesel Generator Coolant Expansion Tank level indicating sightglass, LG-061 0A, has a crack in it. The sightglass is isolated with an Equipment Status Tag (EST), but t~e tank is still available for use.

i Maintenance reports that the sightglass will be repaired tomorrow on dayshift under Work Order 01234567.

I The Control Room Supervisor has directed that the System Manager will determine a~d verify Coolant Expansion Tank level, then report it to the Control Room as part of the*

1 pre-start check of the E-1 Diesel Generator.

PLOR245C Rev000 Page 3 of 6

G.

INITIATING CUE The Control Room Supervisor directs you as the Originator to initiate a "single use" temporary change to SO 52A.1.B, "Diesel Generator Operations", step 4.1.2.4, using AD-PB-101-1003, "Temporary Changes to Approved Documents and Partial Procedure Use" beginning with step 4.2.7.

PLOR245C Rev000 Page 4 of6

I I H.

PERFORMANCE CHECKLIST I

I II STEP STEP ACT STANDARD NO 1

Obtain a copy of the reference p

A copy of AD-PB-101-1003, "Temporary procedures and review/utilize the Changes to Apprdved Documents and Partial correct section of the procedure.

Procedure Usage',l and SO 52A.1.B, "Diesel Generator Operat/ons" is obtained.

(Cue: Provide the Student with a I

copy of SO 52A.1.B and AD-PB-Initiator responsibllity is reviewed in AD-PB-,

101-1003.)

101-1003.

,I 2

Determine the temporary change p

Uses the information provided from the classification.

Tasks/Prerequisit$s Condition Sheet and determines that thiis temporary change is a SINGLE USE cha',,ge in accordance with I I Step 4.2.7.

i 3

Verify that the recommended p

Check the list of if~ms in Step 2.1 of AD-PB-change does not change the intent 101-1003 and verify that none of them of the procedure.

matches this temporary change (which would indicate a change'iof intent.

I I

,I I

4 Verify that there are no other TCs to p

Uses the informat\\on provided from the this procedure.

Tasks/Prerequisites Condition Sheet and recognizes that th13re are no previously (Cue: If the candidate asks a existing TCs on t~

1e Diesel Procedure. This question, refer them back to the will be documentJd later on Attachment 1 of,

Task Conditions sheet.)

AD-PB-101-1003.'.

I

5 Complete Temporary Change p

Completes AD-Pa-101-1003-F-01 Approval Control Form, Attachment 1, Form.

I Originator Section.

I Note: Attachmenti2 of this JPM.

I I

NOTE:

This Diesel Generator I

procedure is common to both Units.

I I

NOTE:

The exact wording by the Student may vary from that of this

' i JPM step. As long as the intent is clear the exact wording is not I

I important.

II i

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PLOR245C Rev000 Page 5 of 6 I I

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STEP NO

6 7

8 STEP Complete the required mark-up of SO 52A.1.B, "Diesel Generator Operations, Slow Start".

NOTE: The exact wording by the Student may vary from that of this JPM step. As long as the intent is clear the exact wording is not important.

Present the temporary change for review and approval.

(Cue: Accept AD-PB-101-1003-F-01 Approval Form and SO 52A.1.B, Diesel Generator Operations, Slow Start" from the Student as the SQR and SRO.)

As an evaluator ensure that you have positive control of all exam material provided to the examinee (Task Conditions/Prerequisites)

AND procedures.

ACT p

p p

~TANDARD ii Completes the mark-up of SO 52A.1.B, "Diesel Generator1[Operations, Slow Start" by performing the follbwing:

Draws a singl~ line through each sentence of st~p 4.1.2.4 of SO 52A.1.B, "Diesel Generator Operations, Slow Start".

Inserts the folfowing text as close to the affected step a~ possible:

o "The Syst~m Manager will verify and report Co~lant Expansion tank level to the Control Room and will have coolant ad:~ed as necessary."

Rev Bar, lnitial11 and Date changes.

Presents AD-PB-1. 01-1003-F-O 1 Approval Form and the entire Diesel Generator Operation procedl!lre SO 52A.1.B, "Diesel Generator Operations, Slow Start" with the marked up step 4}1.2.4 to the SQR and SRO:

for review and approval.

Positive control established.

Under "ACT" P - must perform S - must simulate I.

TERMINATING CUE:

When the originator section of AD-PB-101-1003-F-01 Approval Form, and the entire Diesel :

Generator Operation procedure SO 52A.1.B, "Diesel Generator ©perations, Slow Start" with the marked up step 4.1.2.4 have been presented to the SQR and SRO for review and approval, the evaluator will terminate the exercise.

PLOR245C Rev000 Page 6 of 6

EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET

~

JPM QUALIFICATION MANUAL OJT MODULE LICENSED OPERATOR TRAINING PLOR-418C 2021 ILT NRC RO EP 000 D.W. Adams dwa PERFORM STATE/LOCAL NOTIFICATIONS FOR A DECLARED EMERGENCY APPROVALS:

Signature / Title Date Signature / Title Date Signature/ Title Date Signature/ Title Date PPROVED FOR USE:

Signature/ Title Date EFFECTIVE DATE: ____

NAME: ---------------

ISSUE DATE: _________ _

Last First M.I.

EMPLOYEE ID NO.

COMPLETION DATE:

COMMENTS:

Training Review for Completeness:

LMS CODE:

LMS ENTRY:

Signature/Date PLOR418C Rev000 Page 1 of 6 1

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE I

I POSITION TITLE:

Unit Reactor Operator TASK-JPM DESIGNATOR:

2950110501 / PLOR-246C KIA: I G2.4.39 i URO: 3.9 TASK DESCRIPTION:

Perform State/Local Notifications for a Declared Event A.

NOTES TO EVALUATOR:

I

1.

An asterisk(*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will pnevent the system from

! I functioning properly or prevent successful task completion.

2.

System cues included in the performance checklist are to be provided to the examinek when no system response is available.

I

3.

JPM Performance I

a.

"Control Room" JPMs are designed to be performed in the simulator. If a

'I "Control Room" JPM is to be performed in the Control Room all perform steps*

(P) shall be simulated (S).

b.

When performing "In-Plant" JPMs, no equipment will be operated without Shift Management approval.

4.

Satisfactory performance of this JPM is accomplished if:

a.

The task standard is met.

b.

JPM completion time requirement is met.

1)

For non-time critical JPMs, completion within double the estimated time.

(listed in paragraph 0.2) is acceptable provided the evaluator determine~

that the progress to completion is acceptable.

I I

2)

For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

1 I

c.

Applicable JPM Work Practice Standards, TQ-JA-150-04 graded satisfactorily.:

I Ii PLOR418C Rev000 Page 2 of 6 * [

I

5.

The estimated time to complete this JPM, though listed in *the task standard, is not to.be given to the examinee.

I TOOLS AND EQUIPMENT I

I None I

C.

REFERENCES D.

1.

EP-MA-114-100 Rev 27, "Mid-Atlantic State/Local Notifications".

2.

EP-MA-114-100-F-01 Rev. T, "State/Local Event Notification Form" TASK STANDARD I

I

1.

Satisfactory completion of this task is indicated when the ~tate/Local Event Notifications have been properly completed.

2.

Estimated time to complete: 13 minutes (Time-critical).

I ':

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E.

DIRECTIONS TO EXAMINEE When given the initiating cue, make State/Local Notifications in ~ccordance with EP-MA-1141 100, Mid-Atlantic State/Local Notifications. I will describe the initjal conditions and provide you access to the materials required to complete this task. This is a ti'me critical JPM.

[

F.

TASK CONDITIONS/PREREQUISITES

1.

A transient has occurred on Peach Bottom Unit 2.

2.

The Shift Manager, acting as the Station Emergency Director, has completed the initi~I classification of the event via EONS and provided you with the State/Local Notificatiol' Form, EP-MA-114-1 00-F-01.

3.

The event is classified as a RS1 (Site Area Emergency).

I

4.

Another operator has been assigned to fax the State/Loca'I Notification Form to the T$C and the EOF.

5.

EONS is not available.

G.

INITIATING CUE As the communicator, transmit the required State and Local 15-rninute Notifications in accordance with Attachment 2 of EP-MA-114-100, Mid-Atlantic S,tate/Local Notifications usii:,g the provided STATE/LOCAL NOTIFICATION FORM.

[

PLOR418C Rev000 Page 3 of 6::

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H.

PERFORMANCE CHECKLIST TEP STEP ACT STANDARD I

I NO I

I I

- - NOTE TO EVALUATOR***

I I

1. When the cue is provided to the candidate, WRITE the "DECLARED AT TIME and DATE" (21 minutes previous to actual time, and today's date) on the State/Local Event Notification form 1in Block 5 and provide the Event Notification Form to the candidate.

I

2. Verify that the NARs phone in the simulator is set to Simulator Mode prior to performance of~

this JPM to ensure no calls are made to outside agencies. When the NARs phone is activat~d from the simulator floor, the companion NARs phone will ring in the simulator booth.

I I

1 Obtain a copy of EP-MA-114-100, "Mid-p Candidate obtains a copy of EP-MA-11!4-Atlantic State/Local Notifications", and 100, Mid-Atlantic State/Local I

EP-MA-114-1 00-F-01, "State/Local Event Notifications, and the filled out EP-MA-Notification Form".

114-100-F-O 1, State/Local Event Notification Form.

(Cue: Provide the examinee with a copy of Attachment 2 of this JPM).

2 Ensure that "Utility Message No." has p

Verifies that no. 1 is entered in the Utilr~y been assigned using a sequential Message Number.

i number.

I 3

Verify "Emergency Director Approval" p

Verifies the Emergency Director has I

signed the Emergency Director Approval section.

I I

4 Review form for completeness.

p Verifies the state/local notification formi is completely filled out.

I

5 Initiates the all-call notification by p

Picks up receiver from the EMnet phon 1e pressing the "Notify" button for the and depresses the "Notify" button.

applicable station.

I I

I

6 Confirm that you would like to initiate the p

Depresses the "Yes" button on the EMilet call by pressing "Yes" when prompted.

I phone screen.

7 State the following:

p States the phrase while holding down t,he "This is the Exelon Nuclear Peach Bottom EMnet "Push to Talk" button.

Unit 2. Please standby for notification I

I message".

I

8 Conduct an initial roll call for the agencies p

Conducts a roll call and verifies the listed on Page 3 of the State/Local following agencies acknowledge:

Notification form.

Pennsylvania EMA

Maryland EMA

York County

Hartford County I

I

Cecil County I

I

Lancaster County I

I

Chester County I

PLOR418C Rev000 Page 4 of 6

I I

STEP STEP ACT I

STANDARD I

NO I

I,,

9 Record the time (in 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months clock) as p

Writes the ~ime each party responds to I each required party responds to the roll the roll call 1and the time of completion of call and the time the initial roll call is*

the initial r9II call on the State/Local

I completed.

Notification \\form.

10 Read blocks one at a tme from the p

Reads the ~ollowing to the agencies on approved notification form.

the phone:;

Call Status - Drill

Affectbd Station - Peach Bottom:

'I

Affected Unit-Unit 2 i

Classification - Site Area

'i Emergency I

Declar:ed at - as annotated

This r~presents a - Initial Declaration I

Emergency Action Level - RS 1

Non-technical Description -

Abn~rmal Rad Levels/Radiologieal I

Effluent I

Radiological Release Status -

Airb0rne release in progress

Wind ~irection - 120 degrees

Wind speed - 5 mph I

Proteqtive Action Recommendatiln

-Nqne

11 Record message delivery completion p

Records message delivery completion date and time in Block 12:

date and time in Block 12:

I CONCLUSION CONCLUSION*

I I

NOTE: This time is required to be less than 15 minutes from time of emergency I

declaration. Record Time:

I I.

12 Ask if there are any questions about the p

Asks if there are any questions about the information provided and clarify as informationi provided and clarify as

\\

needed. Record any unanswered needed. Records any unanswered 1

questions or inquiries on an Information questions dr inquiries on an Information Request/ Message Form Request/ N/lessage Form I

I I

I

' I (Cue: State that there are no questions.)

'i I

13 To end the call, READ the following:

p To end the 1call, reads the following:

"This concludes the notification "This conclµdes the notification message."

message."i II (Cue: acknowledge statement.)

I I

PLOR418C Rev000 Page 5 of 6:

STEP NO 14 STEP As an evaluator, ensure that you have positive control of all exam material provided to examinees (Task Conditions/Prerequisites AND procedures).

Under "ACT" P - must perform S - must simulate ACT

,1 STANDARD I

I i

p Positive Control Established.

. I I

I I

I I I I

I I

I I.

TERMINATING CUE:

'i I

When the candidate reports that the State/Local Event Notifications are complete, the Shift Manager will be notified. The evaluator will then terminate the exercise.

PLOR418C Rev000

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I Page 6 of 6: I I

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EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET

~

JPM QUALIFICATION MANUAL OJT MODULE LICENSED OPERATOR TRAINING PLOR-393C 2021 IL T NRC JPM SRO C001 000 N. Patrou ntp PERFORM SRO REVIEW OF COMPLETED SURVEILLANCE TEST APPROVALS:

Signature / Title Date Signature / Title Date Signature/ Title Date Signature/ Title Date PPROVED FOR USE:

Signature / Title Date EFFECTIVE DATE: -----

NAME:

ISSUE DATE:

Last First M.I.

EMPLOYEE ID NO.

COMPLETION DATE:

COMMENTS:

Training Review for Completeness:

LMS CODE:

LMS ENTRY:

Signature/Date PLOR393C Rev000 Page 1 of 5 I

I I

i

. I I

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:

Senior Reactor Operator TASK-JPM DESIGNATOR:

2991070302/ PLOR-393C KIA:

G2.1.25 SRO: 4.2 TASK DESCRIPTION:

Perform SRO Review of Completed Surveillance Test A.

NOTES TO EVALUATOR:

1.

An asterisk(*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will p!ievent the system from

I functioning properly or prevent successful task completion.

2.

System cues included in the performance checklist are to.:be provided to the examinee when no system response is available.

I

3.

- JPM Performance I

a.

When performing "In-Plant" JPMs, no equipment will be operated without Shift Management approval.

4.

Satisfactory performance of this JPM is accomplished if:

a.

The task standard is met.

b.

JPM completion time requirement is met.

1)

For non-time critical JPMs, completion within double the estimated time :

(listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

! I

2)

For time critical JPMs, completion within the :estimated time (listed in paragraph D.2) is required.

5. The estimated time to complete this JPM, though listed in the task standard, is not to be, given to the examinee.

6. This JPM can be performed in the classroom/simulator.

PLOR393C Rev000 Page 2 of 5 I I

I I

B.

C.

TOOLS AND EQUIPMENT I

A completed copy of ST-O-014-301-2, Rev. 41, "Core Spray Loop A Pump, Valve, Flow, andl Cooler Functional and In-service Test". [Note: a) Complete sections for Core Spray Pump A only; b) Mark Step 6.2.12 as UNSAT; c) Record vibration X1 to be in the Alert Range; d) all*

other procedure steps are satisfactory.]

REFERENCES

1.

ST-O-014-301-2, Rev. 42, "Core Spray Loop A Pump, Valye, Flow, and Cooler Functional and In-service Test".

2.

TS LCOs 3.3.5.4, 3.5.1, 3.5.4, and TRM 3.11 (and Bases).

D.

TASK STANDARD I

1.

Satisfactory task completion is indicated when the student determines the Core Spray, Pump vibration is in the Alert Range, which requires the pump be placed on an increased test frequency. Also, recognize that the Core Spray Room Cooler is not I

operating, and the TRM will require declaring the associated Core Spray Pump inoperable.

2.

Estimated time to complete: 20 minutes Non-Time Critical DIRECTIONS TO EXAMINEE When given a completed surveillance test, determine if the test is acceptable or not acceptable. State all required actions, if any.

F.

TASK CONDITIONS/PREREQUISITES Unit 2 is at 100% power.

I

, I I

1.

2.

ST-O-014-301-2, "Core Spray Loop A Pump, Valve, Flow,.and Cooler Functional and~

In-service Test" has just been completed in the field. The test was performed for Core 1

Spray Pump "A" only.

I G.

INITIATING CUE The Control Room Supervisor directs you to perform an SRO review of the completed surveillance test. State if the surveillance test is satisfactory, or n~t satisfactory. If not

/

satisfactory, state why the surveillance is not satisfactory, and what actions are required due to the unsatisfactory surveillance test. (Do not include management notifications.)

PLOR393C Rev000 Page 3 of 5

H.

PERFORMANCE CHECKLIST STEP STEP ACT NO 1

Obtain a copy of ST- 0-014-301-2, p

"Core Spray Loop A Pump, Valve, Flow, and Cooler Functional and lnservice Test".

(Cue: Provide the Operator a marked up copy of ST-O-014-301-2, as described) 2 Review ST- 0-014-301-2, "Core Spray p

Loop A Pump, Valve, Flow, and Cooler Functional and lnservice Test".

NOTE I STANDARD

' I Obtains a copy of ST- 0-014-301-2, "Core Spray Eoop A Pump, Valve, Flow, and Cooler Functional and lnservice Test".

i i

I

'I I

Reviews ST- 0-014-301-2, "Core Spray, Loop A Pump., Valve, Flow, and Cooler Functional and lnservice Test".

I I

I The steps below are not required to be performed/documented in the otder provided.

3 Recognize that Core Spray Pump "A" p

Recognizes tryat Core Spray Pump "A" X 1 vibration is in the "Alert Range" X1 vibration is in the "Alert Range"

4 Recognize "Alert Range" vibration p

Recognizes "f lert Range" vibration reading requires initiation of an Issue reading requines initiation of an Issue to to place Core Spray Pump "A" on I

place Core Spray Pump "A" on increased test frequency.

increased test frequency.

5 Recognize 2BV024, "A Core Spray Pp p

Recognizes 2BV024, "A Core Spray Pp Rm Unit Cooler Fan is not operating.

Rm Unit Cooler Fan is not operating.

I

6 Recognize entry into TRM 3.11.B:

p Recognizes ehtry into TRM 3.11.B:

Required Core Spray or RHR Required Core Spray or RHR cooler/fans unit(s) inoperable.

cooler/fans uriit(s) inoperable.

Required Compensatory Measure:

I Comply with the appropriate Technical Specification requirements associated the inoperability of the required core spray or RHRcooler/fan unit(s) immediately.

7 Declare Core Spray Pump "A" p

Declares Core Spray Pump "A" inoperable.

inoperable.

PLOR393C Rev000 Page 4 of 5 I

STEP STEP NO

8 9

Recognize entry into TS 3.5.1.A: One low pressure ECCS injection/spray subsystem inoperable.

As an evaluator, ensure that you have positive control of all exam material provided to the examinees (Task Conditions/Prerequisites AND procedures.)

Under "ACT" P - must perform S - must simulate I.

TERMINATING CUE ACT STANDARD p

Recognizes entry into TS 3.5.1.A: One low pressure ECCS injection/spray subsystem inoperable.

Required action to restore low pressure ECCS injection/spray subsystem(s) to operable status within 7 days.

p Positive Control Established.

When the operator states an increased surveillance test frequency for Core Spray Pump A is required and declares Core Spray Pump A inoperable IAW TRM 3.11.B and TS 3.5.1.A, the 1

evaluator will terminate the exercise.

PLOR393C Rev000 Page 5 of 5

EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET

~

JPM QUALIFICATION MANUAL OJT MODULE LICENSED OPERATOR TRAINING PLOR-218C 2021 IL T NRC JPM SRO C002 009 R. J. Artus rja RESOLUTION OF THERMAL LIMIT VIOLATION APPROVALS:

Signature I Title Date Signature/ Title Date Signature / Title Date Signature/ Title Date

\\PPROVED FOR USE:

Signature / Title Date EFFECTIVE DATE: -----

NAME:

ISSUE DATE:

Last First M.I.

I EMPLOYEE ID NO.

COMPLETION DATE:

COMMENTS:

Training Review for Completeness:

LMS CODE:

I LMS ENTRY:

Signature/Date PLOR218C Rev0099 Page 1 of 5 '

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:

Senior Reactor Operator TASK-JPM DESIGNATOR:

2830150401 / PLOR-218C KIA:

2.1.7 SRO: 4.7 TASK DESCRIPTION:

Resolution of Thermal Limit Violation A.

NOTES TO EVALUATOR:

1.

2.

3.

4.

An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

I I

I System cues included in the performance checklist are to be provided to the examine~

when no system response is available.

JPM Performance

a.

"Control Room" JPMs are designed to be performed in the simulator. If a "Control Room" JPM is to be performed in the Control Room all perform steps W)

b.

shall be simulated (S).

i I

I When performing "In-Plant" JPMs, no equipment will be operated without Shift 1

Management approval.

i I

Satisfactory performance of this JPM is accomplished if:

I

a.

The task standard is met.

b.

JPM completion time requirement is met.

1)

For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2)

For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

I

5.

The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

PLOR218C Rev0099 Page 2 of 5

B.

TOOLS AND EQUIPMENT

1.

JPM Attachment 2, Prepared Official 3D P1 Edit on greeri colored paper REFERENCES

1.

GP-13 Rev. 25, "Resolution of Thermal Limit Violations"

2.

GP-5-3 Rev. 015, "Power Operations"

3.

Technical Specification 3.2.1, "Average Planer Linear Heat Generation Rate (APLHGR)"

D.

TASK STANDARD

1.

Satisfactory task completion is indicated when the examir:iee has determined that MFLCPR is above 0.980 and MAPRAT is above 1.000, a;reactor power reduction usirg GP-5, "Power Operations" and entry into Technical Specification 3.2.1, "Average Pia. er Linear Heat Generation Rate (APLHGR)" are required.

2.

Estimated time to complete: 10 minutes Non-Time Critical E.

DIRECTIONS TO EXAMINEE When given the initiating cue, review the initial 3D Monitor Case! (P1) edit run following a recent Unit 3 power ascension. Identify any unsatisfactory data :ipoints and document any actions that are required. I will describe initial plant conditions and provide you access to the materials required to complete this task.

~

F.

TASK CONDITIONS/PREREQUISITES

1. Unit 3 Reactor power was recently raised from 90% to 100%

1following a rod pattern adjustment in accordance with GP-5-3, "Power Operations.":

I

2. Unit 3 reactor power is currently stable at 100%.

3. A valid OFFICIAL 3D Monitor Case (P1) edit has just been run to assess the reactor power I

ascension.

4. The Plant Monitoring System (PMS) and 3D MONICORE were operable at the time the:

OFFICIAL 3D Monitor Case (P1) edit was run. The OFFICIAL 3D Monitor Case [P1] has no unexplained changes to its input parameters.

1 G.

INITIATING CUE As the CRS, review the official Unit 3 3D Monitor Case (P1) editlprovided for errors.

If any errors are found, list them and document all actions/notifiqations that are required by 1

applicable procedures or Technical Specifications / Technical R~quirements Manual, and record what document I step number requires the action/notification on the Cue Sheet.

PLOR218C Rev0099 Page 3 of 5

II STEP NO H.

PERFORMANCE CHECKLIST STEP ACT STANDARD

- - NOTE ***

j Provide examinee with the official Unit 3 3D Monitor Case (P1) Edit (Attachment 2 of this J I

M).

Ensure it is printed on green paper.

1 2

3 4

5 Review the official 3D P1 edit.

P Reviews 3D P1 edit to ensure Core Thermai Limits are within specified limits. Focuses o:

MFLCPR, MFLPD, MAPRAT and FLLP valu s Determine MFLCPR is above 0.980 in one location (19-20).

(Cue: As the Shift Manager, request the examinee to determine what actions, if any, need to be performed to resolve the thermal limit violation.)

Determine MAP RAT is above 1.000 in one location (27-52-5).

(Cue: As the Shift Manager, request the examinee to determine what actions, if any, need to be performed to resolve the thermal limit violation.)

Notify Shift Management and Reactor Engineers that MFLCPR is above 0.989 (and MAPRAT is above 1.000.

(Cue: Acknowledge notifications.)

References GP-5, Power Operations, (MFLCPR) and GP-13, Resolution of Thermal Limit Violations (MAP RAT).

toward the top of 11the page.

_. I p

States and / or records on the cue sheet that a MFLCPR value of 0.989 is listed at core 1

location 19-20.

P States and / or records on the cue sheet that a MAPRAT value of 1.001 is listed at core location 27-52-5.

'1 I

P States and / or re:cords on the cue sheet that Shift Management and Reactor Engineering require notification of core thermal limit violat on as required by GIP-13, step 3.1.

P Obtains and references GP-5, Power I

Operations, and GP-13, "Resolution of Thermal Limit Violations."

1 I

PLOR218C Rev0099 Page 4 of 5

STEP NO

6 7

8 8

9 STEP Determine that Reactor power must be reduced with the assistance of Reactor Engineering in accordance with GP-5, "Power Operations" to restore MAPRAT to below 1.000.

(GP-13, step 3.2)

Examine the OFFICIAL 30 Monitor Case (P1) for unexplained changes to its input parameters.

(GP-13, step 3.5)

Determine that TS LCO 3.2.1 "Average Planer Linear Heat Generation Rate (APLHGR)" is not met and state the associated action requirements a and b.

Determine that a Condition Report should be written to address the thermal limit violation.

(GP-13, *step 3.11)

As the evaluator, ensure that you have positive control of all exam material provided to the examinee (Task Conditions/Prerequisites AND procedures).

Under "ACT" P - must perform S - must simulate I.

TERMINATING CUE:

ACT p

p I

. STANDARD States and I or records on the cue sheet thatl a GP-5 power reduction is required to restore,

1 MFLCPR to below 1.000 as required by GP-;I3, I

step 3.2.

I As stated in the cue, the OFFICIAL 30 Monitol r

. Case [P1] has no unexplained changes to its input parameters~ This action is required by pP-13, step 3.5.

I

. I P

Identifies TS LCO 3.2.1 is not met and APLH:GR must be restored:to below 1.000 within j

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or thermcill power must be reduced t9 below 22.6% RTP within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

MAPRAT ~ 1.ooq means that APLHGR is restored to within limits of the Core Operating Limits Report (C~LR)

. I I

P States and I or records on the cue sheet that 1a Condition Report should be written to address the thermal limit violation.

I P

Positive control 1established.

When the examinee has reviewed the 30 Monitor Case (P1) edit and determined actions associated with the thermal limit violation, the evaluator may ter!ilinate the exercise.

. i PLOR218C Rev0099 Page 5 of 5

I

EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET

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JPM QUALIFICATION MANUAL OJT MODULE LICENSED OPERATOR TRAINING PLOR-416C 2021 ILT NRC JPM SRO EC 000 D.W.Adams dwa APPROVE A PARTIAL PROCEDURE APPROVALS:

Signature I Title Date Signature I Title Date Signature I Title Date Signature I Title Date APPROVED FOR USE:

Signature I Title Date EFFECTIVE DATE: ----

I NAME:

ISSUE DATE:

Last First M.I.

SOC. SEC. NO.

COMPLETION DATE:

i I

COMMENTS:

i Training Review for Completeness:

PIMS CODE:

PIMS ENTRY:

Signature/Date PLOR416C Rev0002 Page 1 of 5

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:

Senior Reactor Operator TASK-JPM DESIGNATOR:

3421130302 / PLOR-416C KIA:

2.2.6 SRO: 3.6 TASK DESCRIPTION:

Approve a Partial Procedure A.

NOTES TO EVALUATOR:

1.

An asterisk(*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2.

System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3.

JPM Performance

a.

"Control Room" JPMs are designed to be performed in the simulator. If a "Control Room" JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b.

When performing "In-Plant" JPMs, no equipment will be operated without Shift Management approval.

4.

Satisfactory performance of this JPM is accomplished if:

a.

b.

The task standard is met.

JPM completion time requirement is met.

I

1)

For non-time critical JPMs, completion within double the estimated time 1 (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2)

For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

5.

The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

PLOR416C Rev0002 Page 2 of 5,

B.

TOOLS AND EQUIPMENT

1.

A marked up copy of ST-0-010-501-2, Rev. 7, "RHR Loop A Valves Remote Position I

Indication Verification" C.

REFERENCES D.

E.

1.

HU-AA-104-101, Rev. 7, "Procedure Use and Adherence" I

2.

AD-PB-101-1003, Rev. 15 "Temporary Changes to Approved Documents and Partial Procedure Use"

'I I

. I

3.

ST-O-010-501-2, Rev. 7, "RHR Loop A Valves Remote Position Indication Verificatio11" TASK STANDARD

1.

2.

Satisfactory task completion is indicated when the candid 1ate has correctly reviewed ~nd approved the partial procedure for ST-O-010-501-2, Rev:. 7, "RHR Loop A Valves, I Remote Position Indication Verification" as a partial for the completion of Post Maintenance Testing on the "A" RHR Loop Isolation Valve.

Estimated time to complete: 15 minutes Non-Time Critical DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to appro,ye a partial procedure for P9st Maintenance Testing of the MO-2-10-015A, RHR Pump 2A Shutdown Cooling Suction Valve using appropriate procedures. I will describe initial plant conditions and provide you access ito the materials required to complete this task.

F.

TASK CONDITIONS/PREREQUISITES

1.

2.

3.

An outage is in progress on Unit 2.

The plant is in Mode 4.

, I

I Work has been performed on MO-2-10-015A, RHR Pump 2A Shutdown Cooling Suction Valve.

1

4.

Maintenance has completed repairs on the valve, and it is ready for Post Maintenance Testing.

I

5.

A partial procedure for ST-O-010-501-2, Rev. 7, "RHR Loop A Valves Remote Position Indication Verification" has been developed and is ready for review and approval.

I G.

INITIATING CUE I

The Control Room Supervisor directs you to review and approve the Partial Procedure for ST-O-010-501-2, Rev. 7, "RHR Loop A Valves Remote Position Indication Verification" to 1

complete Post Maintenance Testing of the MO-2-10-015A.

PLOR416C Rev0002 Page 3 of 5 ;

H.

PERFORMANCE CHECKLIST STEP NO 1

2 3

4

5

6 7

STEP

. Obtain a copy of the procedure.

Note: Partial Procedures are completed in accordance with HU-AA-104-101, "Procedure Use and Adherence" and AD-PB-101-1003, "Temporary Changes to Approved Documents and Partial Procedure Use". The candidate may refer to these procedures during the JPM.

Verify the word "PARTIAL" is on the front page.

Verifies the procedure is valid as it is intended to be performed AND accomplishes its objectives including proper restoration of affected equipment.

Verifies the appropriate steps were marked out and annotated with an N/A.

Verifies marked out steps have been initialed and dated.

Approves the partial procedure by entering his/her name, initials, AND date at the top of the cover page.

As an evaluator ensure that you have positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND procedures.

I I

I ACT STANDARD i

P A copy of pT-O-010-501-2 is obtainef.

I I

p p

I

'*i Observes ~hat the word "PARTIAL" is entered o~ the front page.

I I

Concludes that the procedure is valid: and accomplishes its objectives as intend~d.

i l I I

Identifies that the incorrect section was marked N~A.

! I Identifies that steps were missing initi.als and date.

. I I

I Determine'.s the partial procedure can'.r' ot be approv~d until corrected.

Positive central established.

I I

- - NOTE***

I Terminate the exercise when the activities listed above are performed. i Under "ACT" P - must perform S - must simulate.

TERMINATING CUE PLOR416C Rev0002 Page 4 of 5 1

When the candidate determines approval status of the Partial Procedure, the evaluator will i then terminate the exercise.

PLOR416C Rev0002 Page 5 of 51 I

0 JPM EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET QUALIFICATION MANUAL LICENSED OPERATOR TRAINING 2021 IL T NRC JPM SRO RC D.W. Adams I

OJT MODULE!

PLOR-417C 000 dwa REVIEW AND AUTHORIZE ISSUANCE OF THYROID BLOCKING AGENT (Kl)

APPROVALS:

Signature / Title Date Signature/ Title Date Signature / Title Date Signature / Title Date

\\PPROVED FOR USE:

Signature/ Title Date EFFECTIVE DATE:

NAME:

ISSUE DATE:

Last First M.I.

EMPLOYEE ID NO.

COMPLETION DATE:

COMMENTS:

Training Review for Completeness:

LMS CODE:

LMS ENTRY:

Signature/Date PLOR417C Rev0000 Page 1 of 6 I

I I

l I

i I

I I

I

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATllON JOB PERFORMANCE MEASURE POSITION TITLE:

Senior Reactor Operator TASK-JPM DESIGNATOR:

2007560502 / PLOR-417C KIA:

G2.3.14 I

SRO: 3.8 TASK DESCRIPTION:

REVIEW AND AUTHORIZE ISSUANCE:OF THYROID BLOCKING A.

AGENT (Kl)

,1 NOTES TO EVALUATOR:

1.

2.

3.

4.

I I

An asterisk (*) before the step number denotes a CRITIC~L STEP. CRITICAL STERS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completior,.

I I 'I I

I System cues included in the performance checklist are to be provided to the examinee when no system response is available.

\\

JPM Performance I

. I I

a.

b.

i "Control Room" JPMs are designed to be performed in the simulator. If a

1 "Control Room" JPM is to be performed in the Coritrol Room all perform steps l(P) shall be simulated (S).

1 I

I I

When performing "In-Plant" JPMs, no equipment "'{ill be operated without Shift!

Management approval.

i

. I Satisfactory perfmmance of this JPM is accomplished if: :

I

. I I

I

a.

The task standard is met.

i I

b.

JPM completion time requirement is met.

1)

2)

For non-time critical JPMs, completion withih double the estimated time (listed in paragraph 0.2) is acceptable provi~ed the evaluator determines I

I that the progress to completion is acceptable.

For time critical JPMs, completion within th~ estimated time (listed in paragraph 0.2) is required.

c.

Applicable JPM Work Practice Standards, TQ-AA-150-J040 graded satisfactOr,ily.

I I I

5.

The estimated time to complete this JPM, though listed iri: the task standard, is not to.be given to the examinee.

I

.1 PLOR417C Rev0000 Page 2 of6 I

I I

B.

TOOLS AND EQUIPMENT

1.

2.

3.

4.

5.

EP-AA-113, Personnel Protective Actions EP-AA-113-F-03, Thyroid Blocking Agent Authorization Fbrm completed with the exception of the Station Emergency Director authorizatio~.

I I

EP-AA-1007, Radiological Emergency Plan Annex for Pe*ch Bottom Atomic Power Station I

EP-AA-114-F-02, BWR Release in Progress Determinatidn Guidance Procedure index for EP procedures.

6.

Worker history descriptions.

I

. I I

C.

REFERENCES D.

E.

1.

2.

3.

4.

5.

I EP-AA-112-1 00-F-01, Rev. AC, "Shift Emergency Director Checklist" I

EP-AA-113, Rev. 15, "Personnel Protective Actions" I

EP-AA-113-F-03, Rev. G, "Thyroid Blocking Agent Authojization" EP-AA-1007, Rev 035, Radiological Emergency Plan Annex for Peach Bottom Atomib Power Station i

I I

EP-AA-114-F-02, Rev A, "BWR Release in Progress Determination Guidance" I

I TASK STANDARD

1.

2.

I I

Satisfactory completion of this task is indicated when the Emergency Director has reviewed and approves the issuance of Thyroid Blocking ~gent.

I I

Estimated time to complete: 20 minutes Non-Time CriticJ1 I

DIRECTIONS TO EXAMINEE

' I (Reviewing this section with the Examinee is optional)

When given the initiating cue, review the information provided inpluding the Thyroid Blocking Agent Authorization and make the decision as to whether to aut?orize the issuance of Thyrdid Blocking Agent. I will describe the initial conditions and provide you access to the material~

required to complete this task.

1 PLOR417C Rev0000 Page 3 of 6

I

, I I

'I F.

TASK CONDITIONS/PREREQUISITES G.

1.

2.

3.

4.

5.

6.

7.

8.

9.

I Unit 2 experienced a LOCA transient that resulted in a Si~e Area Emergency declaration.

I A small steam leak continues to exist in the Turbine Building due to failure of both Inboard and Outboard MSIVs in the B line to close.

I I

Reactor power is 2.34 E-5% and dropping.

I T-116 has been entered and indications of the RPV being flooded have not been observed.

I RPV pressure is 800 psig and dropping slowly.

Primary Containment pressure on PR-2508 is 8 psig and, lowering slowly due to Dryvvell sprays in service. Highest observed Primary Containmerlt pressure was 13 psig.

i I

I

. I P~imary Containment radiation on Rl-8103A-D is 5.0 Renr/hour, the highest observe9 to this point.

i 1

Field Monitoring Teams have been mobilized by the Shi~ Dose Assessor.

1 I

Iodine air samples have been completed and a Committ~d Dose Equivalent (COE) 1 Thyroid Dose has been calculated and verified. Total COE Thyroid Dose is expected to be 30 Rem.

j

. [

10.

Due to concerns for the exposure the Field Monitoring T, ams may receive, EP-AA-1 ~ 3-F-03, Thyroid Blocking Agent Authorization Forms, have [been completed and reviewed/approved by the Radiation Protection Manager.

I I

i I

I I

I As the Shift Emergency Director, authorize the attached Thyroid Blocking Agent Authorizatipn Form (EP-AA-113-F-03), in accordance with EP-AA-113. Document the basis for your decision on the que sheet.

I i

INITIATING CUE PLOR417C Rev0000 Page 4 of 6

TEP NO 1

2 H.

PERFORMANCE CHECKLIST STEP Obtain a copy of EP-AA-113, "Personnel Protective Actions".

Use Section 4.4 of the procedure for Kl assessment.

ACT p

p STANDARD The examihee obtains the current revision of 1EP-AA-113, "Personnel Protective Actions".

I

, I

. I The examihee references section 4.4 ~f EP-AA-113.

- - - NOTE: ****

IF the Operator requests to review the Kl calculation, inform the Qperator that the EP-MA-1'[10-1 00-F-02 form is not currently available, but it has been verified a'nd is accurate.

,3

4 5

6

7 8

Analyze given conditions and determine that a release IS in progress Recognize that the conditions for issuing Kl are currently met.

Determine that Thyroid Blocking Agent (Kl) should be issued.

(Cue: Acknowledge report.)

Reviews EP-AA-113-F-03 for completion.

Approves issuance of Thyroid Blocking Agent (Kl).

As an evaluator, ensure that you have positive control of all exam material provided to the examinees (Task Conditions/Prerequisites AND procedures.

PLOR417C Rev0000 P

Examinee determines that a release IS in I

progress 1

' I P

Examinee determines and documents:

that the conditions for Step 4.4.1.1.A a 1re met due to:

1 Condition 1: there is a potential loss of the Fuel Clad Barrier.

I p

Recognize: and report that Kl should b~

issued.

1 I

I

'I P

Verifies EP-AA-113-F-03 has been filled out appropriately.

. j P

The examinee signs and dates EP-AAi 113-F-03, "Thyroid Blocking Agent Authorizatibn Form."

'I i

.1, I p

Positive Control Established.

I Page 5 of 6

Under "ACT" P - must perform S - must simulate TERMINATING CUE:

When the examinee has determined the conditions for issuing Kl are met, documented and EP-AA-113-F-03 "Thyroid Blocking Agent Authorization Form" is returned authorized, the evaluator may terminate the exercise.

PLOR417C Rev0000 Page 6 of 6

~

JPM EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET QUALIFICATION MANUAL LICENSED OPERATOR TRAINING 2021 ILT NRG JPM SRO EP D. W.Adams I

OJT MODULE!

PLOR-180C 005 dwa I

EAL CLASSIFICATION AND STATE/LOCAL NOTIFICATIONS FOR SAE - CONTRPL ROOM EVACUATION APPROVALS:

Signature/ Title Date Signature / Title Date Signature/ Title Date Signature / Title Date

.~PPROVED FOR USE:

Signature I Title Date EFFECTIVE DATE:

/

I I

NAME:

ISSUE DATE:

I Last First M.I.

SOC. SEC. NO.

COMPLETION DATE:

COMMENTS:

I Training Review for Completeness:

PIMS CODE:

PIMS ENTRY:

Signature/Date PLOR180C Rev005 Page 1 of 6

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:

Senior Reactor Operator TASK-JPM DESIGNATOR:

2007540502 / PLOR-180C KIA:

2.4.41 SRO: 4.6 TASK DESCRIPTION:

EAL Classification and State / Local Notifications for SAE - Control Room Evacuation A.

NOTES TO EVALUATOR:

I

1.

An asterisk(*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS I

are those steps which when not performed correctly will prevent the system from 1

functioning properly or prevent successful task completion.

I I

2.

System cues included in the performance checklist are to be provided to the examineb when no system response is available.

1

3.

JPM Performance

a.

"Control Room" JPMs are designed to be performed in the simulator. If a

1 "Control Room" JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b.

When performing "In-Plant" JPMs, no equipment will be operated without Shift Management approval.

4.

Satisfactory performance of this JPM is accomplished if:

5.

a.

The task standard is met.

b.

JPM completion time requirement is met.

1)

For non-time critical JPMs, completion within double the estimated timel (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

2)

For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

I The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

PLOR180C Rev005 Page 2 of 6 I I

I I

B.

TOOLS AND EQUIPMENT None C.

REFERENCES

1.

EP-AA-112-100, Rev. 19, "Control Room Operations" (R):

2.

EP-AA-111, Rev. 23, "Emergency Classification and Protective Action Recommendations" (R)

3.

EP-MA-114-100, Rev. 27, "Mid-Atlantic State/Local Notifi9ations" (R)

4.

EP-AA-1007, Addendum 3, Rev. 9 Emergency Action Levels for Peach Bottom Atomi6 Power Station

I

5.

EP-AA-112-1 00-F-01, Rev. AC, "Shift Emergency Directo( Checklist".

D.

TASK STANDARD

1.

Satisfactory task completion is indicated when plant conditions have been classified as an Alert using EP-AA-1007 and when EP-MA-114-100-F-91, "State/Local Event Notification Form", has been completed accurately.

, I (NOTE: The criteria for accurate Event Notification form completion is derived from EP-AA-125-1002, Rev. 3, "ERO Performance-Performance Indicators Guidance").

I

, I

2.

Estimated time to complete: Event Classification - 15 minutes: Time Critical State/Local Notification - 13 minutes: Time Critical E.

DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to classify the event and perform Shi-ft Emergency Director initial actions using appropriate procedures.: I will describe initial plant : I conditions and provide your access to the materials required to complete this task.

F.

TASK CONDITIONS/PREREQUISITES

1.

A fire occurred in the Control Room and was extinguished within 9 minutes.

2.

Plant control was established from the Alternative Shutdown Panels in 16 minutes on Unit 2 and 13 minutes on Unit 3 of the SE.:.10, "Plant Shuttjown from the Alternative 1

Shutdown Panels" procedure entry.

3.

Both Units are being controlled from the Alternative Shutdown Panels.

I

4.

Both reactors are shutdown at 5X10E-4% power.

I

5.

Indicated RPV level is -155 inches and rising due to HPCI, operation on Unit 2.

PLOR180C Rev005 Page 3 of6 I

I

6.

Indicated RPV level is +35 inches and steady due to HPCI operation on Unit 3.

7.

RPV pressure is 1000 psig and steady on both Units.

8.

EONS is unavailable.

G.

INITIATING CUE As the Emergency Director, classify the event per Emergency Pl~m guidance and perform the initial actions required by EP-AA-112-100-F-01, "Shift Emergency Director Checklist".

PLOR180C Rev005 Page 4 of 6

H.

PERFORMANCE CHECKLIST 1

TEP STEP ACT STANDARD

I NO I

- - NOTE***

Record the time using the clock above the Full Core Display. Time=

"1 1

Obtain a copy of procedure EP-AA-1007.

p A copy of procedure EP-AA-1007 is I I obtained.

I

2 Determine the appropriate EAL IC.

p EP-AA-1007, Table PBAPS 3-1, EAL:

HS2 is referenced. The event is (Cue: Classification is acknowledged.)

classified as a Site Area Emergency. *

- - NOTE***

. I I

I

I WHEN the examinee completes the classification determination, THEN record the time using the clock above the Full Core Display.: Time =

I Determine if the elapsed time since the initiating cue exceeds 15 111inutes.

I This recorded time will also be used as the starting time for the state/local notification procebs.

3 Obtain a copy of procedure EP-AA-112-p A copy of procedure EP-AA-112-100 is 100.

obtained. :

I 4

Obtain a copy of procedure EP-AA-112-p A copy of procedure EP-AA-112-100-~-

100-F-01.

01 obtained.

I I

5 Announce the event classification to the p

Announces classification to control roo'm facility staff.

crew.

(Cue: Acknowledge announcement to I

the control room staff.)

. I 6

Direct the Alert Station Public Address p

The Statioiil PA is used to make the Announcement.

announcement IAW EP-AA-112-F-09.,

(Cue: State that the Shift Communicator is making the PA announcement.)

7 Direct the "ERO Response Required" p

Properly cci>mpetes EP-AA-112-100-F'-07, I

steps of ERO Notification or Mid-AtlantiG ERO Notification or

. i Augmentation Form.

Augmentation.

I (Cue: State that the Shift Communicator is making the PA announcement.)

- - NOTE***

I The following steps are associated with completion of EP-MA-114-1 00-F-01, "State/Local Event Notification Form".

8 Check the call status.

p "This is a drill" line is checked in Blockl#1.

9 Check the affected station.

p "Peach Bottom" is checked in Block #~.

10 Check the affected unit.

p Unit "Two":: is checked in Block #3.

'i I

11 Check the event classification.

p "Site Area Emergency" classification is checked in Block #4.

I

, I PLOR180C Rev005 Page 5 of 6.'

STEP STEP ACT STANDARD

I NO

12 Enter the time and date of the p

Declaration time (in 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months clock declaration.

nomenclature) and today's date are entered in Block #5. The declaration time should match the time the examiner entered in the note before JPM step 1:

13 Check the applicable change in p

"Initial Declaration" is checked in Block classification status.

6.

14 Enter the EAL number declared.

p EAL# "HS2" is annotated in Block #7

1 15 Enter a brief non-technical description of p

Annotates that the event is "D - Hazan: s the event.

and Other Conditions Affecting Plant Safety" in block #8.

16 Check the non-routine radiological p

"NO" radiolbgical release in progress ii; release status.

checked in:'Block #9.

, I 17 Enter the wind direction "Degrees from".

p Wind direction is obtained form either: I PMS Meteorologic data or control room (Cue: Wind direction is from 180 panel OOC767 and is entered as the :

degrees.)

"wind direction degrees from" in Block.

10.

18 Enter the wind speed.

p Wind spee~ is obtained from either PM;s Meteorologic data or control room panel (Cue: Wind speed is 15 mph.)

OOC767 apd is entered in Block #10.

1

19 Check the utility Protective Action p

The "None" box.is checked in Block #1 j1.

recommendation.

20 Check the appropriate conclusion.

p "This is a drill" line is checked in Bloc~ I

13.

20 Approve the event notification form.

p The event notification form is signed inl the form's header area by the Emergency Director.

- - NOTE***

WHEN the examinee completes the Event Notification form, THEN record the time using the clock above the Full Core Display. Time=

Determine if the elapsed time since the classification exceeds 13 minutes.

21 As an evaluator, ensure that you have p

Positive control established.

positive control of all exam material provided to the examinee (Task condition/Prerequisites) AND procedures.

Under "ACT" P - must perform S - must simulate i

I.

TERMINATING CUE When the event has been class1f1ed and the State/Local not1f1cat1on form has been completetl, the evaluator will terminate the exercise.

PLOR180C Rev005 Page 6 of 6

EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET

~

JPM QUALIFICATION MANUAL OJT MODULE,

LICENSED OPERATOR TRAINING PLOR-412CA 2021 IL T NRG JPM A 000 D.W.Adams dwa INSERT CONTROL RODS USING INDIVIDUAL SCRAM TEST SWITCHES (T-213-~)

(ALTERNATE PATH -SCRAM SWITCH FAILS)

APPROVALS:

Signature I Title Date Signature I Title Date Signature / Title Date Signature I Title Date APPROVED FOR USE:

Signature I Title Date EFFECTIVE DATE:

/

I NAME:

ISSUE DATE:

Last First M.I.

I EMPLOYEE 1.0. NO.

COMPLETION DATE:

COMMENTS:

I Training Review for Completeness:

LMS CODE:

LMS ENTRY:

Signature/Date EXELON NUCLEAR PLOR412CA Rev0000 Page 1 of 5

POSITION TITLE:

PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR:

2004020501 / PLOR-412CA KIA:

295037EA 1.01 URO: 4.6 SRO: 4.6

TASK DESCRIPTION:

Insert Control Rods using Individual Scram Test Switches (T-213-2)

(Alternate Path - Scram Switch Fails)

A NOTES TO EVALUATOR:

I

1.

An asterisk(*) before the step number denotes a CRITIC~L STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2.

System cues included in the performance checklist are to be provided to the examine when no system response is available.

3.

JPM Performance

a.

"Control Room" JPMs are designed to be performed in the simulator. If a "Control Room" JPM is to be performed in the Control Room all perform steps, 1P) shall be simulated (S).

b.

When performing "In-Plant" JPMs, no equipment will be operated without Shift Management approval.

4.

Satisfactory performance of this JPM is accomplished if:

a.

The task standard is met.

b.

JPM completion time requirement is met.

1)

For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptabl7.

2)

For time critical JPMs, completion within the. estimated time (listed in 1

paragraph D.2) is required.

5.

The estimated time to complete this JPM, though listed in the task standard, is not to* e given to the examinee.

PLOR412CA Rev0000 Page 2 of 5

B.

TOOLS AND EQUIPMENT

1.

None C.

REFERENCES

1.

T-213-2, Rev.10, "Scram Solenoid Deenergization" D.

TASK STANDARD

1.

Performance Location: Simulator

2.

Satisfactory task completion is indicated when all Group Scram Solenoid fuses have been removed.

3.

Estimated time to complete: 10 Minutes Non-Time Critical E.

DIRECTIONS TO EXAMINEE r

When given the initiating cue, perform necessary steps to insert rod 34-27 with the use of its individual scram test switch and remove the Group Scram Solenoid fuses using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.

TASK CONDITIONS/PREREQUISITES

1.

T-117, ATWS RPV Control, is being performed.

2.

All control rods are withdrawn with blue lights NOT lit.

3.

Control Rod Drive Scram Solenoid Group 1, 2, 3, 4 white lights are lit.

4.

All field operators are busy with other tasks.

G.

INITIATING CUE The Control Room Supervisor directs you, the Unit Reactor Operator, to perform T-213-2, "Scram Solenoid Deenergization" to insert control rods using the individual scram test switches, beginning with control rod 34-27.

PLOR412CA Rev0000 Page 3 of 5 j I

I

I H.

PERFORMANCE CHECKLIST

,TEP NO STEP ACT STANDARD 1

Obtain a copy of procedure T-213-2.

p A copy of procedure T-213-2 is obtainek Determine the appropriate section of T-I 2

p Determines that Section 4.2 is to be 213-2 to perform.

performed.

3 Access the Individual Scram Test p

Opens the door to the Individual Scram Switches Test Switch panel.

- - - NOTE****

The Alternate Path portion of this JPM begins with the next step.

4 Place the individual scram test switch for p

Pushes the test switch down into the I

control rod 34-27 in the down (SCRAM)

SCRAM position and waits 10 seconds.

1 position for 10 seconds.

5 Verify the blue scram lights are lit on the p

Observes b'lue scram lights are NOT lit !for Full Core Display.

rod 34-27.

(Cue: Acknowledge report that the scram switches failed.)

6 Places the individual scram test switch for p

Pushes the test switch up into the control rod 34-27 in the up (NORMAL)

NORMAL position.

position.

7 Proceeds to step 4.3, Group Scram p

Determines that section 4.3 is required to Solenoids.

complete the task.

8 Obtains fuse pulling tool from the EOP p

Retrieves fuse pullers from Control Rodm Toolbox.

EOP Toolbox.

(Note: This step can be simulated)

Locates the Group Scram Solenoid fuses.

I 9

p Accesses panels 20C015 and 20C0171to (Cue: When the candidate correctly locate the Group Scram Solenoid Fuses.

locates the 20C015 and 20C017 panels, hold up Attachment 2 of this JPM to illustrate the Group Scram fuses in the panel. They are not modeled in the Simulator.)

PLOR412CA Rev0000 Page 4 of 5

STEP NO STEP

10 Pull all Group Scram Solenoid Fuses.

11 (Cue: Group Scram Solenoid Fuses have been removed.)

Verify all blue scram lights lit on the full core display and all control rods fully inserted.

(Cue: All blue lights are lit, and all control rods are fully inserted.)

12 Inform Control Room Supervisor of task completion.

(Cue: Control Room Supervisor acknowledges report.)

13 As an evaluator ensure that you have positive control of all exam material provided to the* examinee (Task Conditions/Prerequisites) AND procedures.

Under "ACT" P - must perform S - must simulate I.

TERMINATING CUE ACT STANDARD

. I S

Removes the following fuses from 20C015 and 20C017:

F6 (5~-F18A) and (5A-F188)

F7 (5A-F1 BE) and (5A-F18F)

F8 (5A-F18C) and (5A-F18D)

F9 (5A-F18G) and (5A-F18H) p I

Observes tne full core display and verifies all blue scram lights lit and all control rdds fully inserted.

P Task completion reported.

P Positive control established.

When Group Scram Solenoid fuses have been removed, the Control Room Supervisor shou d be informed. The evaluator will then terminate the exercise.

PLOR412CA Rev0000 Page 5 of 5:

EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET

~

JPM QUALIFICATION MANUAL Licensed Operator Training 2021 IL T NRC JPM B M. J. Kelly OJT MODULE I I

PLOR-012C I

I I

006 I

I NTP I

I START THE "C" REACTOR FEEDPUMP WITH VESSEL LEVEL CONTROL THROUGH AO-8091 APPROVALS:

Signature/ Title Date Signature / Title Date Signature/ Title Date Signature/ Title Date

,PPROVED FOR USE:

Signature/ Title Date EFFECTIVE DATE:

/

NAME:

ISSUE DATE:

Last First M.I.

EMPLOYEE NO.

COMPLETION DATE:

COMMENTS:

Training Review for Completeness:

PIMS CODE:

PIMS ENTRY:

Signature/Date PLOR012C Rev006 Page 1 of 6 I

I I

I

JOB PERFORMANCE MEASURE 1OSITION TITLE:

Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR:

2590030101 / PLOR-012C KIA:

259001 A4.02 URO: 3.9 SRO: 3.7' TASK DESCRIPTION:

Start the "C" Reactor Feedpump with Vessel Level Control Through AO-8091 A.

NOTES TO EVALUATOR:

1.

An asterisk(*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will p'revent the system from functioning properly or prevent successful task completioo.

2.

System cues included in the performance checklist are to'be provided to the examinee when no system response is available.

3.

JPM Performance

a.

"Control Room" JPMs are designed to be performed in the simulator. If a "Control Room" JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b.

When performing "In-Plant" JPMs, no equipment w.ill be operated without Shift Management approval.

4.

Satisfactory performance of this JPM is accomplished if:

a.

The task standard is met.

b.

JPM completion time requirement is met.

1)

For non-time critical JPMs, completion withim double the estimated time (listed in paragraph D.2) is acceptable provi9ed the evaluator determines that the progress to completion is acceptable.

2)

For time critical JPMs, completion within the1 estimated time (listed in 1

paragraph D.2) is required.

5.

The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

PLOR012C Rev006 Page 2 of 6'

B.

TOOLS AND EQUIPMENT None

I I

C.

REFERENCES i

I I

1.

SO 6C.1.A-2 Rev.31, "C" Reactor Feedwater Pump Stark1p with Vessel Level Cantre;>\\

Established Through AO-8091

2.

6C.1.A-2 COL Rev. 6, Feedwater System Lineup for Reactor Feedwater Pump Start; I D.

TASK STANDARD

1.

Satisfactory task completion is indicated when "C" RFP in: service with vessel level control established through AO-8091.

I

2.

Estimated time to complete: 18 minutes Non-Time Critical E.

DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to place the "C" RFP in service with vessel level control established through AO-8091, using appropriate procedures. I will describe initial plant conditions and provide you access to the m~terials required to complete this task.

I I

i TASK CONDITIONS/PREREQUISITES

I

1.

A Unit 2 startup is in progress in accordance with GP-2-2,1 "Normal Plant Startup".

I

2.

Preparations are being made to place the first feedwater pump in service.

I

'I I

. I

3.

All prerequisites of SO 6C.1.A-2, "C Reactor Feedwater P1ump Startup with Vessel Level Control Established through AO-8091," are complete.

4.

SO 6C.1.A-2 has been completed up to Step 4.3.8.

'I G.

INITIATING CUE The Control Room Supervisor directs you perform steps 4.3.9 through 4.4.10 to place the "2C" RFP in service with vessel level control established through AO-8091 in accordance with S~

6C.1.A-2, "C Reactor Feedwater Pump Startup with Vessel Level Control Established through AO-8091".

PLOR012C Rev006 Page 3 of 61 I

, I

H.

PERFORMANCE CHECKLIST TEP NO STEP 1

Obtain a copy of SO 6C.1.A-2.

2 3

4

5 6

7 Place A0-2147C, "Feed Pump C Check" in "AUTO".

Open or verify open M0-2140C, "Feed Pump C Suet" valve, at Panel 20C006A.

Verify the following at Panel 2CC162:

"PS-2137C-1 TRIPPED" light is NOT lit

"PS-2137C-2 TRIPPED" light is NOT lit (CUE: When requested as the EO, report that PS-2137C-1 TRIPPED and PS-2137C-2 TRIPPED lights are not lit.)

Verify A0-2139C, "Feed Pump C Recirc" control switch in "OPEN" at Panel 20C006A AND verify the valve is open.

Verify the turning gear disengages by observing the green turning gear DISENGAGED light is lit AND the Turning Gear Motor green light is lit at Panel 20C005A.

Momentarily place the turning gear control switch to "STOP" AND allow switch to spring return to "AUTO".

ACT STANDARD P

Obtains a eopy of SO 6C.1.A-2.

p p

Places A0-2147C, "Feed Pump C Ch9ck" in "AUTO".

I Open or verifies open M0-2140C, "Fe~d Pump C Si;ict" valve, at Panel 20C006~

1 by placing its ?antral switch to OPEN.

Contacts an Equipment Operator and.

verifies the1following at Panel 2CC162:

"PS-2137C-1 TRIPPED" light is NOT lit I

"PS-2137C-2 TRIPPED" light is NOT lit I

Verifies AQ-2139C, "Feed Pump C Ref ire" control switch in "OPEN" at Panel 20C006A AND verify the valve is ope~ I Verifies the turning gear disengages b}('l 1

observing t,r,e green turning gear DISENGAGED light is lit AND the Turn*ng Gear Motm green light is lit at Panel

20C005A.

Momentaril1/ places the turning gear I.

control switch to "STOP" AND allow switch to spring return to "AUTO".

- - Note***

The next step involves opening the back panel of 20C005 in the Control Room that is modeled, b~1 not connected. Use the provided cue to complete step.

~

B Verify RMS~2-06D-~0685, "RF_P ~ow Suet p

Verifies RMS-2-06D-80~85, "RFP L_o~I Press Rx HI Lev Trip Bypass" ms1de Panel Suet Press Rx Hi Lev Trip Bypass" ms1ae 20C005A is NOT in position "C".

Panel 20C005A is NOT in position "C".

(CUE: Report that "RFP Low Suet Press Rx Hi Lev Trip Bypass" is in Position B.)

I PLOR012C Rev006 Page 4 of 6:

STEP NO STEP g

Verify "C" RFP M/A Station is in MANUAL.

1 o Reset "C" RFPT at Panel 20C005A AND verify the following:

Green trip light goes out

Red reset light comes on

HO-2-06D-2166C, "2C Rx Feed Pump Turbine High Pressure Stop Valve" is open

HO-2-06D-2165C, "2C Rx Feed Pump Turbine Low Pressure Stop Valve" is open (Note: Candidate should hold the switch in RESET until the red light is on.),

11 Raise "C" RFP speed demand to approximately 200 rpm higher than its current "windmill" speed.

12 Check reactor water level is stable.

13 Slowly raise "C" RFP speed until AO-8091 is between 40 to 60% open.

PLOR012C Rev006 ACT STANDARD P

Verifies "C'.' RFP M/A Station is in MANUAL..

p Reset "C" !R,FPT by taking "C" Feed

I Turbine switch to and holding it in RESET at Panel 20C005A AND verifying the '

following:

Green trip light goes out

Red reset light comes on

HO-2-0'6D-2166C, "2C Rx Feed Pump Turbine High Pressure Stop Valve\\' is open

HO-2-06D-2165C, "2C Rx Feed Pu 1mp Turbine Low Pressure Stop Valve"! is open P

Raises "C" RFP speed demand to approximately 200 rpm higher than its

-'current "wimdmill" speed by pressing the RAISE/LO\\?\\fER pushbutton OR the RFP M/A Station Output Raise/Lower pushbuttons until RFP speed is approximately 200 rpm higher than original. (180-220 rpm)

P Verifies reactor water level is stable.

I p

I Verifies AO-8091 is between 40 to 60%

open by pressing the RAISE/LOWER: I pushbutton or the RFP M/A Station Output Raise/Lower pushbuttons as necessa~.

I Page 5 of 6, I

II STEP NO STEP 14 While raising Reactor power, perform the following:

Maintain RFP discharge pressure at least 60 psi greater than Reactor pressure by adjusting RFPT speed.

Maintain AO-8091 position between 30 AND 70% open by adjusting RFPT speed.

(CUE: Report that reactor power is stable.)

15 Inform Shift Supervisor of task completion.

(Cue: Shift Supervisor acknowledges report.)

16 As an evaluator ensure that you have positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND procedures.

Under "ACT" P - must perform S - must simulate I.

TERMINATING CUE ACT p

STANDARD While raisi~g Reactor power, perform tre following:

t

Maintain RFP discharge pressure at least 6ij psi greater than Reactor * !

pressu~e by adjusting RFPT speed

Maintai,h AO-8091 position betwee~ 30 AND 7()% open by adjusting RFPT speed.,;

P Task comp.letion reported.

'i I

p Positive control maintained.

I I

I When "C" RFT is in service with vessel level control established through AO-8091, the Cont~ol Room Supervisor should be informed. The evaluator will then te 1rminate the exercise.

I PLOR012C Rev006 Page 6 of 6.1 I

EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET 0

JPM QUALIFICATION MANUAL OJT MODULE LICENSED OPERATOR TRAINING PLOR-413C 2021 IL T NRG JPM C 000 D. W.Adams dwa PERFORM A SLOW CLOSURE AND RESTORATION OF A MAIN STEAM ISOLATION VALVE APPROVALS:

Signature / Title Date Signature/ Title Date Signature / Title Date Signature/ Title Date APPROVED FOR USE:

Signature / Title Date EFFECTIVE DATE: ___

/ ___

/ __

NAME:

ISSUE DATE:

Last First M.I.

EMPLOYEE ID NO.

COMPLETION DATE:

COMMENTS:

Training Review for Completeness:

LMS CODE:

LMS ENTRY:

Signature/Date I

I I

I PLOR413C Rev000 Page 1 of 41 I

POSITION TITLE:

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION

. JOB PERFORMANCE MEASURE Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR:

2390300101/PLOR-413C K/A:i 239001 A4.01 RO: 4.2 SRO: 4.0.

TASK DESCRIPTION:

Perform a Slow Closure and Restoration bf a Main Steam Isolation,

Valve

'I A.

NOTES TO EVALUATOR:

I I

1.

An asterisk(*) before the step number denotes a CRITIC~L STEP. CRITICAL STEPS are those steps which when not performed correctly will p:revent the system from

. functioning properly or prevent successful task completior:i.

2.

System cues included in the performance checklist are toi be provided to the examinee when no system response is available.

3.

JPM Performance

a.

"Control Room" JPMs are designed to be perform~d in the simulator. If a "Control Room" JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b.

When performing "In-Plant" JPMs, no equipment will be operated without Shift Management approval.

4.

Satisfactory performance of. this JPM is accomplished if: :

a.

The task standard is met.

b.

JPM completion time requirement is met.

1)

For non-time critical JPMs, completion within double the estimated tim~

1 (listed in paragraph D.2) is acceptable provi;ded the evaluator determin, s that the progress to completion is acceptabl,e.

2)

For time critical JPMs, completion within thJ estimated time (listed in paragraph D.2) is required.

c.

Applicable JPM Work Practice Standards, TQ-AA-:150-J040 graded satisfactq ily.

5.

The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

PLOR413C Rev000 Page 2 of 4

B.

TOOLS AND EQUIPMENT 1.

Stopwatch C.

REFERENCES

1.

SO 1A.7.D-2 Rev 10, Isolation of One Main Steam Line at Power D.

TASK STANDARD I

1.

Satisfactory task completion is indicated when the B Outboard MSIV has been closed.

2.

Estimated time to complete: 15 minutes Non-Time Critical E.

DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to perform a slow closure of the B outboard MSIV using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F.

TASK CONDITIONS/PREREQUISITES

1.

Reactor Power is 50%

2.

Scram Margin is 35%

3.

No RPS testing is in progress or scheduled

4.

Reactor Pressure is 944psig

5.

ST-M-01A-471-2, Main Steam Isolation Valve Timing, Springs Only Closure and Position Switch Adjustment will not be performed.

G.

INITIATING CUE The Control Room Supervisor directs you to perform a slow closure and reopening of the B,

Inboard MSIV in accordance with SO 1A.7.D-2, Isolation of One Main Steam Line at Power.I I

i PLOR413C Rev000 Page 3 of 4

i H.

PERFORMANCE CHECKLIST I

,TEP STEP ACT STANDARD

I i

NO l

1 Obtain a copy of SO 1A.7.D-2 and reviews p

Obtains a ~opy of the procedure and : I the precautions.

reviews the precautions.

2

Determine the appropriate step to p

Determine~ step 4.2 will be performed]

perform.

3 Determine if ST-M-01A-471-2, Main p

Reviews initial conditions and determines Steam Isolation Valve Timing, Springs that ST-M~01A-471-2 will not be Only Closure and Position Switch performed; Adjustment is to be performed.

4 Depress AND hold the associated MSIV P*

Depresse~ and holds 16AS3B, MSIV1est Test Pushbutton.

Pushbutto~ for the B Inboard MSIV.. I

5 When the MSIV indicates closed, then p

Verifies the B Inboard MSIV green ligh~ is

'I I

place the associated MSIV control switch lit and plaqes its control switch in CLOSE, to CLOSE then release the pushbutton.

then releai;,es the pushbutton.

I 6

Verify the associated RPS relays for the p

Verifies relays 5A-K3E and 5A-K3D orl selected MSIV is de-energized.

panels 208015 and 20C017 are open.I 7

Verify the B MSIV has not been closed for p

Verifies the B MSIV has not been closed greater than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

for greaten than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

(Cue: The B MSIV has been closed for 10 minutes.)

I

8 Open the B MSIV.

p Places th~ control switch for the B Inboard M$1V to the AUTO/OPEN I

position.

9 Verify the associated RPS relays for the p

Verifies reiays 5A-K3E and 5A-K3D on selected MSIV is energized.

I panels 20C015 and 20C017 are close¢!.

10 Inform the Control Room Supervisor of p

Task completion reported.

task completion.

(Cue: Acknowledge report.)

11 As an evaluator, ensure that you have p

Positive c0ntrol established.

positive control of all exam material I

provided to the examinee. (Task I

Conditions/Prerequisites) AND procedures.

Under "ACT" P - must perform i

S - must simulate i

I i

I.

TERMINATING CUE I

When B Inboard MSIV is open, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.

PLOR413C RevOOO I

Page 4 of 4

'I

0 JPM EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET QUALIFICATION MANUAL OJT MODULE LICENSED OPERATOR TRAINING PLOR-414CA i 2021 IL T NRC JPM D 000 D. W.Adams dwa RESET RECIRC PUMP SPEED HOLD (ALTERNATE PATH - RECIRC SPEED OSCILLATES)

APPROVALS:

Signature I Title Date Signature I Title Date Signature I Title Date Signature I Title Date APPROVED FOR USE:

Signature I Title Date EFFECTIVE DATE:

/

NAME:

ISSUE DATE:

Last First M.I.

EMPLOYEE ID NO.

COMPLETION DATE:

COMMENTS:

Training Review for Completeness:

LMS CODE:

LMS ENTRY:

Signature/Date PLOR414CA Rev 000 Page 1 of 5 I

I i

i i

I I

I

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATIION JOB PERFORMANCE MEASURE

,i POSITION TITLE:

Unit Reactor Operator/Senior Reactor ORerator I

TASK-JPM DESIGNATOR:

2021110201/PLOR-414CA KIA:*

202001 A2.05 RO: 3.8 SRO: 4.0

TASK DESCRIPTION:

Reset Recirc Pump Speed Hold (Alternafe Path - Recirc Speed Oscillates)

A.

NOTES TO EVALUATOR:

1.

An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STEPS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2.

System cues included in the performance checklist are toi be provided to the examin: e when no system response is available.

3.

JPM Performance

a.

"Control Room" JPMs are designed to be perform~d in the simulator. If a "Control Room" JPM is to be performed in the Con~rol Room all perform step~ (P) shall be simulated (S). *

b.

When performing "In-Plant" JPMs, no equipment will be operated without Shift Management approval.

4.

Satisfactory performance of this JPM is accomplished if: *

a.

The task standard is met.

b.

JPM completion time requirement is met.

1)

2)

I For non-time critical JPMs, completion withip double the estimated tim~

(listed in paragraph D.2) is acceptable provi,ded the evaluator determin s that the progress to completion is acceptable.

l For time critical JPMs, completion within th~ estimated time (listed in paragraph D.2) is required.

c.

Applicable JPM Work Practice Standards, TQ-AA.:~150-J040 graded satisfacto ily.

5.

The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

PLOR414CA Rev 000 Page 2 of 51

B.

TOOLS AND EQUIPMENT

1.

None C.

REFERENCES

1.

SO 2H.7.B-2, Reactor Recirculation Adjustable Speed Drive Manual Hold and Reset D.

TASK STANDARD

1.

Satisfactory task completion is indicated when the A Recirc Pump Speed Hold has bEien re-established.

2.

Estimated time to complete: 5 minutes Non-Time Critical E.

DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to remove the speed hold on the 2A 1

Recirc Pump using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F.

TASK CONDITIONS/PREREQUISITES

1.

A speed hold was placed on the A Recirc Pump due to pump oscillations.

2.

Repairs have been made to the A Recirc Pump ASD control system.

G.

INITIATING CUE The Control Room Supervisor directs you to reset the speed hold on the A Recirc Pump in accordance with SO 2H.7.B-2, Reactor Recirculation Adjustable Speed Drive Manual Hold and I

Reset.

PLOR414CA Rev 000 Page 3 of 5; I I

I H.

PERFORMANCE CHECKLIST.

I STEP STEP ACT STANDARD

I NO 1

Obtain a copy of SO 2H.7.B-2.

p Obtains a copy of the procedure and I reviews the precautions.

2 Verifies that repairs have been completed p

Reviews initial conditions and determi,,es on the A Recirc Pump.

repairs have been completed.

3 Verifies 2A ASD is in REMOTE control.

p Observes,annunciator 214 D-4, A Redirc ASD Speed Demand Local, alarm is ~ OT in.

4 Verify 2A ASD Motor Speed and Speed p

Observes motor speed and speed i

Demand match.

demand on XR-2-02H-21012A, "ASD:A Recorder"; and verifies the values match.

5 Reset speed hold on the A Recirc Pump.

p Places SS-2-02H-21 QA, "Speed Rese1:-

Hold" switch in the RESET position an 1d returns to normal.

I 6

Verify alarm panels 214 D-5, "A Recirc p

Observes alarm windows for 214 D-fr 1:md ASD Speed Hold", and 214 C-2, "A C-2 clear.

Recirc ASD Minor Trouble" reset.

- - - NOTE ****

The Alternate Path portion of this JPM begins with': the next step.

7 Verifies Recirc Pump speeds are within p

Observes.:A Recirc Pump speed

I limits.

oscillating.

8 Places a speed hold on the A Recirc p

Places SS-2-02H-210A, "Speed Reset-Pump.

Hold" switch in the HOLD position andl returns to normal.

9 Verify alarm panels 214 D-5, "A Recirc p

Observes,alarm windows for 214 D-5, and ASD Speed Hold", and 214 C-2, "A C-2 alarm.

Recirc ASD Minor Trouble" alarm.

10 Inform the Control Room Supervisor of A p

CRS informed.

I Recirc pump hold due to uncontrolled rising speed.

(Cue: Acknowledge report.)

11 As an evaluator, ensure that you have p

Positive c0ntrol established.

positive control of all exam material i

provided to the examinee. (Task Conditions/Prerequisites) AND i.

procedures.

I Under "ACT" P - must perform i

I S - must simulate L

TERMINATING CUE When the s eed hold is laced on the 2A Recirc Pum p

p p, the Control Room Su p ervisor shoul,I be informed. The evaluator will then terminate the exercise.

PLOR414CA Rev 000 Page4 of 51

PLOR414CA Rev 000 Page 5 of 5

EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET

~

JPM QUALIFICATION MANUAL OJT MODULE LICENSED OPERATOR TRAINING PLOR-079C 2021 IL T NRC JPM E 013 D. W. Adams dwa SPRAY THE CONTAINMENT USING HPSW PER T-205 APPROVALS:

Signature/ Title Date Signature/ Title Date Signature / Title Date Signature / Title Date APPROVED FOR USE:

Signature / Title Date EFFECTIVE DATE: -----

NAME:

ISSUE DATE:

I Last First M.I.

I EMPLOYEE ID NO.

COMPLETION DATE:

I COMMENTS:

I Training Review for Completeness:

LMS CODE:

I LMS ENTRY:

Signature/Date PLOR079C Rev013 Page 1 of 91 I

. I

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:

Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR:

2003300501 / PLOR-079C KIA:

295024EA 1.11 URO: 4.2 SRO: 4.2 TASK DESCRIPTION:

Spray the Containment Using HPSW per T-205 A.

NOTES TO EVALUATOR:

1.

An asterisk(*) before the step number denotes a CRITICAL STEP. CRITICAL STE:' S are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2.

System cues included in the performance checklist are t6 be provided to the examin e when no system response is available.

3.

JPM Performance

a.

"Control Room" JPMs are designed to be performed in the simulator. If a

"Control Room" JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b.

When performing "In-Plant" JPMs, no equipment "'.Ifill be operated without Shi Management approval.

4.

Satisfactory performance of this JPM is accomplished if:

5.

a.

The task standard is met.

b.

JPM completion time requirement is met.

1) For non-time critical JPMs, completion within double the estimated time,

(listed in paragraph 0.2) is acceptable provided the evaluator determines; 1hat the progress to completion is acceptable.

1

2) For time critical JPMs, completion within the estimated time (listed in paragraph 0.2) is required.

i

c.

Applicable JPM Work Practice Standards, TQ-JA-150-04 graded satisfactoril' 1

The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

PLOR079C Rev013 Page 2 of~

B.

TOOLS AND EQUIPMENT Keys for MO-2-10-174, MO-2-10-176, and MO-2-10-186 C.

REFERENCES T-205-2, Rev. 9, Initiation of Containment Sprays Using HPSW D.

TASK STANDARD Satisfactory task completion is indicated when the "2B" HPSW pump is in service supplyingi Drywell Sprays below 5300 gpm.

Allotted time to complete: 15 minutes (A.5) Non-Time Critical E.

DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to initiate Drywell Spray using the "W HPSW pump, using appropriate procedures. I will describe initial plant conditions and provi;de you access to the materials required to complete this task.

F.

TASK CONDITIONS/PREREQUISITES

1.

Unit 2 is experiencing a LOCA.

2.

Reactor level is -20 inches and steady.

3.

Reactor pressure is 400 psig and dropping slowly.

4.

Drywell pressure is 15 psig and rising slowly.

5.

A LPCI initiation (LOCA) signal has been present for 6 minutes.

6.

RHR pumps are NOT available for Drywell Spray.

7.

HPSW injection into the RPV is NOT in progress.

8.

All 4 KV Buses are receiving power from their respective startup feeds.

9.

Prerequisites for T-205-2, "Initiation of Containment Sprays Using HPSW" are complete.

10.

No nitrogen injection operations are in progress.

11.

Use of T-205-2 has been directed by TRIPs.

12_.

Outside air temperature is 60 degrees F.

PLOR079C Rev013 Page 3 of 9 1

G.

INITIATING CUE I

I The Control Room Supervisor directs you, the Plant Reactor Operator, to perform T-205-2,:

"Initiation of Containment Sprays Using HPSW" to spray only the Drywell using the 28 HPSW I

pump.

PLOR079C Rev013 Page 4 of 9

II H.

PERFORMANCE CHECKLIST STEP NO START TIME:

STEP 1

Obtain a copy of procedure T-205-2.

2 Verify the following valves are closed:

3 MO-2-10-0268 MO-2-10-0318 MO-2-10-348 MO-2-10-388 (Cue: Green lights on, red lights off.)

Direct an Operator to close E324-R-8 (3863), "Emergency lntertie Valve MO 10-176 (Cue: Role Play as Equipment Operator and perform 3-part of direction.)

(Note: Operator is expected to continue in procedure. You will need to insert

(

RHR Remote function RHR25 to "Closed" Then follow up with JPM step

15.

4 Close the MO-2-10-1548, Outboard Discharge valve.

5 6

(Cue: MO-2-10-1548 green light is on, red light is off.)

Verify MO-2-10-1548, Outboard Discharge valve is closed.

Verify outside air temperature and align HPSW Ventilation appropriately PLOR079C Rev013 ACT STANDARD P

A copy of T-205-2 is obtained and

1 prepares to perform steps 4.2, 4.3, 4.4 and 4.6.

j P

The four valves are verified closed, grJen P*

lights on, red lights off.

Directs Eqµipment Operator to perforrm[

1 appropriate procedure step or specific action usirig 8reakerNalve nomenclat re.

P The Operator should continue in

I procedure :step 4.6 since a LOCA signial has occurred with RPV pressure below 450 psig and MO-2-10-1548 CAN be closed.

MO-2-10-1548 green light verified 0~ and red light verified OFF at panel 20C003-02.

P MO-2-10-1548 green light verified ONland red light verified OFF at panel 20C00l02.

P Verify using Task Conditions/Prereq~i~ites that Air temp 60 degrees F and does not have EO adjust HPSW ventilation.

j Page 5 of 9

II STEP I NO STEP II 7

Verify the 2B and 2D HPSW pumps are shut down.

8 (Cue: 2B and 2D HPSW pump green lights are on red lights are off.)

Verify the following valves are closed:

MO-2-10-89B and D, HPSW Hx Outlet valves.

(Cue: MO-2-10-89B and D green lights are on, red lights are off.)

9 Verify closed the HPSW loop cross tie valve, MO-2-32-2344 (10-186).

(Cue: MO-2-32-2344 green light is on; red light is off.)

10 Place "HPSW MODE" 10A-S19B in "MANUAL OVERRD."

(Cue: Annunciator 225 B-4 is alarming, "SYSTEM II HIGH PRESS SERVICE WATER PUMP IN MANUAL OVER-RIDE".)

11 Open the "HPSW/RHR Em Inner Cross Tie," MO-2-10-174.

(Cue: Acknowledge keylock switch operation.)

14 Verify MO-2-10-174,"HPSW/RHR Em Inner Cross Tie" is open.

15 (Cue: MO-2-10-174 red light is on; green light is off.)

Verify power available to MO-2-10-176 (Cue: Call as Equipment Operator and report (as directed in JPM step #3) that the breaker for MO-2-10-176 is closed and the RO should have indication)

PLOR079C Rev013 ACT p

p STANDARD I

Observes ~B and 2D HPSW pump green lights are ON at panel 20C003-02.

M0-2-10-~9B and D green lights veritibd ON and re~ lights verified OFF at pan~I 20C003-02.

I P

MO-2-32-4344 green light verified ON and red light vJrified OFF at panel P

Key is obtcjlined from SSV key box,

I inserted in~o 1 0A-S 19A keylock switch and placed in the "MANUAL OVERRD" position ati panel 20C003-02.

I P

Key is obtained from SSV key box, inserted into MO-2-10-17 4 keylock sw tch and placed in the OPEN position at panel 20C003-03.

I P

MO-2-10-1.74 red light verified ON anc p

green ligh~ verified OFF at panel 1

i 20C003-03.

i I

RO ackno~ledges report and verifies!~hat MO-2-10-1. 76 has a green light lit and red light out.

(Cue: Green light is lit, and red light is out)

Page 6 of~

II STEP II NO STEP

16 Open the "HPSW/RHR Em Outer Cross Tie", MO-2-10-176.

(Cue: Acknowledge keylock switch operation.)

17 Verify MO-2-10-176, "HPSW/RHR Em Outer Cross Tie" is open.

(Cue: MO-2-10-176 red light is on, green light is off.)

ACT STANDARD P

Key is obt~ined from SSV key box,

I inserted into MO-2-10-176 keylock switch and placeq in the OPEN position at p~

1nel 20C003-03.

P MO-2-10-176 red light verified ON and green light, verified OFF at panel 20C003-03.

- NOTE TO EVALUATOR **

I If the examinee asks whether containment sprays are required !regardless of ACC, say N©.

This will be the cue not to perform steps 4.7.7.t:'and 4.7.7.2.

i I 18 Verify the "SYSTEM II DRYWELL P

"SYSTEM :11 DRYWELL PRESSURE ; I PRESSURE PERMITS CONTAINMENT PERMITS,iCONTAINMENT SPRAY" alarm SPRAY" alarm is lit.

is verified l,it on alarm panel 225 8-3. :

(Cue: Alarm 225 8-3 is lit.)

I

19 Momentarily place "CTMT Spray Viv Cont" P

10A-S17B!control switch is momentarily switch 10A-S178 in "MAN".

placed in the "MAN" position at panel 20C003-02.

(Cue: Acknowledge control switch operation.)

20 Start the "B" HPSW pump.

(Cue: "B" HPSW pump red light is on, green light is off.)

21 Verify proper start of the "B" HPSW pump.

(Cue: 1 0A-A28 indicates ~62 amps, Pl-23308 indicates ~430 psig and DPl-2-10-1308 indicates ~100 psid.)

22 Verify both Recirc Pumps are tripped.

(Drive Motor breaker green lights lit, red lights OFF).

(Cue: Both Recirc Pumps OFF)

PLOR079C Rev013 p

p "B" HPS~ pump control switch is

I momentari,ly placed in the START position at panel 2QC003-02.

1 I

Pump amps, discharge pressure and I ~X DP are verified stable after starting c~ rent decays.

i I I P/S Both Recirc Pumps are tripped.

I Page7of91

II STEP NO STEP I.

21 Verify all OW Cooling fan switches are in "OFF" (Cue: All OW Cooling Fan Switches "OFF").

23 Open MO-2-10-031 B, Drywell Spray Inboard valve. (Green light OFF, red light ON).

(Cue: Flow is observed.)

24 Open MO-2-10-26B, Drywell Spray Outboard valve. (Green light OFF, red light ON. Both ON if valve is throttled).

(Cue: Flow is observed.)

25 Throttle MO-2-10-026B to limit flow to 5,300 gpm on Fl-2-10-136B.

(Cue: Flow indication rises to >O gpm and 5,300 ~1Pm or less on Fl-2-10-136B.)

26 Monitor drywell pressure.

(Cue: Drywell pressure is 12 psig and lowering.)

27 Inform Control Room Supervisor of task completion.

(Cue: Control Room Supervisor acknowledges report.)

28 As an evaluator ensure that you have positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND procedures.

COMPLETION TIME: --------

Under "ACT" P - must perform S - must simulate TERMINATING CUE PLOR079C Rev013 ACT STANDARD I

P/S All OW co01ing switches are taken p

p p

p (verified) ttj> "OFF".

MO-2-10-031B control switch is

I momentarily placed in the OPEN position.

The red light is ON and the green light is I

OFF.

M0-2-10-26B control switch is

[

momentarily placed in the OPEN position.

The red light is ON and the green ligh~ is OFF (if va(ve was taken to full open 1

position). :

II

, I Flow indicates less than or equal to 5:,soo gpm on FH-2-10-136B.

Drywell pressure is monitored using,

I available control room indications.

P Task completion reported.

P Positive control established.

I i I Page 8 of 9

I When the "A" HPSW pump is supplying Drywell Sprays, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.

. I PLOR079C Rev013 Page 9 of 9~

EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET

~

JPM QUALIFICATION MANUAL OJT MODULE LICENSED OPERATOR TRAINING PLOR-039C 2021 IL T NRG JPM F 011 R. W. Long mda TRANSFER HOUSE LOADS TO THE UNIT AUXILIARY TRANSFORMER APPROVALS:

Signature/ Title Date Signature / Title Date Signature / Title Date Signature/ Title Date PPROVED FOR USE:

Signature / Title Date EFFECTIVE DATE:

/

NAME:

ISSUE DATE:

Last First M.I.

SOC. SEC. NO.

COMPLETION DATE:

COMMENTS:

Training Review for Completeness:

PIMS CODE:

PIMS ENTRY:

Signature/Date I

I i

I PLOR039C Rev011 Page 1 of 7

POSITION TITLE:

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE Unit Reactor Operator TASK-JPM DESIGNATOR:

2620160101/ PLOR-039C KIA:

262001A4.04 URO: 3.6 TASK DESCRIPTION:

Transfer House Loads to the Unit Auxilia:rv Transformer A.

NOTES TO EVALUATOR:

1.

An asterisk(*) before the step number denotes a CRITIC.AL STEP. CRITICAL STE,* S are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completio*n.

2.

System cues included in the performance checklist are to be provided to the examin

e when no system response is available.

i

3.

JPM Performance

a.

"Control Room" JPMs are designed to be performed in the simulator. If a "Control Room" JPM is to be performed in the Control Room all perform step~

(P) shall be simulated (S).

b.

When performing "In-Plant" JPMs, no equipment will be operated without Shi Management approval.

4.

Satisfactory performance of this JPM is accomplished if:

a.

The task standard is met.

b.

JPM completion time requirement is met.

1)

2)

For non-time critical JPMs, completion within double the estimated tim'e (listed in paragraph D.2) is acceptable provjded the evaluator determi~

1 s that the progress to completion is acceptable.

For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

5.

The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

.PLOR039C Rev011 Page 2 of 71

B.

TOOLS AND EQUIPMENT Synchronizing switch removable handle C.

REFERENCES Procedure SO 53.1.B-2 Rev. 11, "Electrical System Operations,During Generator Start-up nd Loading"

'~

D.

TASK STANDARD

1.

Satisfactory task completion is indicated when Unit Auxilii:iry loads have been transferred to the Unit Auxiliary Transformer in accordancbe with Procedure SO 53.1.B-2.

2.

Estimated time to complete: 12 minutes Non-Time Critical

'\\

E.

DIRECTIONS TO EXAMINEE

\\ :

When given the initiating cue, perform necessary steps to transfer house loads to the Unit Auxiliary Transformer using appropriate procedures. I will desc~ibe initial plant conditions and provide you access to the materials required to complete this ta~k.

I F.

TASK CONDITIONS/PREREQUISITES

1.

The electrical system is lined up in accordance with SO $0.1.A-2, "Main Generator Synchronizing and Loading".

2.

The generator is connected to the grid and ready to pick up house loads.

G.

INITIATING CUE The Control Room Supervisor directs you to transfer house loads to the Unit Auxiliary Transformer and set up 13 KV for "NORMAL" fast transfer lineup using procedure SO 53. t. B-2, "Electrical System Operations During Generator Startup and Loading".

PLOR039C Rev011 Page 3 of 7

H.

PERFORMANCE CHECKLIST STEP I

NO STEP ACT STANDARD I

1 Obtain a copy of procedure SO 53.1.B-2.

p A copy of procedure SO 53.1.B-2 is obtained.

I I

I

2 Insert handle and place "1 BKR Sync p

Sync switch handle is obtained from panel 225-0101" switch in "ON".

2OC009, inserted into sync switch for :

breaker 225-0101 and placed in the "ON" I

(Cue: Synchroscope is at approximately position at panel 2OC009.

I 12 o'clock, Sync Lights are deenergized at Top Dead Center, and Incoming and Running Voltmeters indicate approximately 120 VAC.)

3 Adjust #1 Startup Feed Bus Voltage or p

Incoming and Running Voltmeters are Generator Output Voltage to match verified to be within 5 volts of each oth,er.

incoming and running voltages while If required, place the connected L TC i~

maintaining Unit Auxiliary voltage > 13.0 "MANUAL" and adjust #1 S/U Feed 8(1s KV.

Voltage using the L TC control switch, PR Generator output Voltage via the "Auto I

(Cue: Incoming and Running Voltmeters Voltage Reg Rheostat" to match lncorrring both read 120 VAC.)

and Running voltage at panel 2OC009,.

4 Verify phase angle difference less than 16 p

Phase angle difference is verified to be degrees.

less than 16 degrees on Xl-80601 Ph~se Angle Display at panel 20C009.

I I

(Cue: Phase Angle Display reading is I

001, and Synchroscope reading is i

approximately 12 o'clock.)

I I

5. Close 1 BKR 252-0101.

p 1 BKR control switch is momentarily placed in the "CLOSE" position while :

(Cue: Acknowledge control switch observing Unit #2 Aux. Transformer a'111p operation.)

and MW meters at panel 20C009.

I I

6 Verify 1 BKR 252-0101 is closed.

p 1 BKR red light is verified ON at panel!

20C009.

. I (Cue: 252-0101 red light is on, green light I

. I is off, annunciator B-3 on alarm panel 219 I

is alarming.)

. I I

PLOR039C Rev011 Page 4 of 7 I

, I STEP NO STEP ACT STANDARD I

I 7

Verify 11 BKR 252-0105 and 21 BKR p

11 BKR and 21 BKR green lights are I

I 252-0113 are tripped.

verified ON at panel 20C009.

I (Cue: 252-0105 and 252-0113 green I

I lights are on, red lights are off, I

annunciator 219 B-3 is flashing.)

i I

I 8

Acknowledge the "11 OR 21 BKR TRIP" p

The annunciator "ACKNOWLEDGE" I

annunciator.

pushbutton is depressed at panel I

20C009.

(Cue: Annunciator 219 B-3 is lit solid.)

I I

i I

9 Place 1 BKR Sync 225-0105 switch in p

225-0105 is placed in the "OFF" positiqn "OFF" and remove handle.

and Sync Switch Handle is removed at:

panel 20C009.

I (Cue: Incoming and Running Voltmeters indicate© VAC.)

I 10 Green flag 11 BKR 252-0105 and 21 BKR p

11 BKR control switch is momentarily 252-0113 control switches.

placed in the "TRIP" position at panel i 20C009.

i (Cue: Acknowledge control switch operation. Annunciator 219 B-3 is not lit.)

I I

I 11 Check 11 BKR 252-0105 control switch is p

11 BKR control switch is verified to be :in green flagged.

the "NORMAL AFTER TRIP" position at panel 20C009.

i (Cue: 252-0105 control switch is in I

normal, with a green flag showing.)

I i

I

12 Place 21 BKR 252-0113 control switch in p

21 BKR control switch is placed in the "PULL TO LOCK".

"PULL TO LOCK" position at panel I

20C009.

(Cue: 252-0113 control switch shows a I

I black flag. Annunciator 219 C-3 is not lit.)

13 Insert handle and place "2 BKR Sync p

Sync switch handle is obtained from panel 225-0214" switch in "ON".

20C009, ioserted into sync switch for I I

breaker 225-0214 and placed in the "GN" I

(Cue: Synchroscope is at approximately position at panel 20C009.

12 o'clock, Sync Lights are deenergized and Incoming and Running Voltmeters I

indicate approximately 120 VAC.)

I PLOR039C Rev011 Page 5 of 1:

I

//sTEP

. NO STEP 14 Adjust #2 Startup Feed Bus Voltage or Generator Output Voltage to match incoming and running voltages while main-taining Unit Auxiliary voltage > 13.0 KV.

(Cue: Incoming and Running Voltmeters both read 120 VAC.)

15 Verify phase angle difference less than 16 degrees.

(Cue: Phase Angle Display reading is 001, and Synchroscope reading is approximately 12 o'clock.)

16 Close 2 BKR 252-0214.

(Cue: Acknowledge control switch operation.)

17 Verify 2 BKR 252-0214 is closed.

(Cue: 252-0214 red light is on, green light is off, annunciator B-4 on alarm panel 219 is alarming.)

18 Verify 12 BKR 252-0210 and 22 BKR 252-0202 are tripped.

(Cue: 252-021 O and 252-0202 green lights are on, red lights are off.)

19 Acknowledge the "12 or 22 BKR TRIP" annunciator.

(Cue: Annunciator 219 8-4 is lit solid.)

20 Place 2 BKR Sync 225-0214 switch in "OFF" and remove handle.

(Cue: Incoming and Running Voltmeters indicate© VAC.)

ACT p

p p

i STANDARD Incoming ahd Running Voltmeters are; I verified to be within 5 volts of each othbr.

If required,iplace the connected L TC (M "MANUALl(j and adjust #2 S/U feed bu~

voltage usirg the L TC control switch, OR Generator Output Voltpge via the "Au~o Voltage R~:g Rheostat" to match lncorriing and Runni~g voltage at panel 20C009]

I

I Phase angle difference is verified to bJ less than 1~ degrees on Xl-80601 Phake Angle Disp,lay at panel 20C009.

I i

I I

I

'I I

2 BKR control switch is momentarily,

placed in tte "CLOSE" position while i observing ~nit #2 Aux. Transformer ar,p and MW 1eters at panel 20C009.

! I I

2 BKR red ight is verified ON at panel 20C009.

i I

12 BKR arid 22 BKR green lights are '

verified O~ at panel 20C009.

I I

i The annun!ciator "ACKNOWLEDGE" I pushbutto~ is depressed at panel 2OC009. :

i 225-0214 \\S placed in the "OFF" positipn and Sync $witch Handle is removed ~t panel20C009.

I

,=================================I=========,;=;======!!

i t

PLOR039C Rev011 Page 6 of~

STEP NO 21 22

23 24 STEP Green flag 12 BKR 252-0210 and 22 BKR 252-0202 control switch.

(Cue: Acknowledge control switch operation. Annunciator is not lit.)

Check 22 BKR 252-0202 control switch is green flagged.

(Cue: 252-0202 control switch is in Normal, with a green flag showing.)

Place 12 BKR 252-0210 control switch in "PULL TO LOCK".

(Cue: 252-0210 control switch shows a black flag. Annunciator 219 C-4 is not lit.)

Inform Control Room Supervisor of task completion.

(Cue: Control Room Supervisor acknow-ledges report.)

Under "ACT" P - must perform S - must simulate I

ACT STANDARD i

p 22 BKR control switch is momentarily!

placed in the "TRIP" position at panel i 20C009.

i I

I p

22 BKR control switch is verified to beI in the "NORMAL AFTER TRIP" position !at panel 20C009.

I I

I p

12 BKR control switch is placed in thel "PULL TO LOCK" position at panel I

20C009.

I i

p Task completion reported.

I I

I I.

TERMINATING CUE When house loads have been transferred to the Unit Auxiliary Transformer and the 13KV busses are setup for "NORMAL" fast transfer, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.

PLOR039C Rev011 Page 7 of 7:

I

EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET 0

JPM QUALIFICATION MANUAL OJT MODULE.

LICENSED OPERATOR TRAINING PLOR-415CA*

2021 IL T NRG JPM G 000 D. W.Adams dwa PLACING THE STANDBY TBCCW PUMP IN-SERVICE (ALTERNATE PATH -

STANDBY PUMP TRIPS)

APPROVALS:

Signature I Title Date Signature I Title Date Signature I Title Date Signature I Tille Date APPROVED FOR USE:

Signature I Title Date EFFECTIVE DATE: __

_...;/ ___

/ __

I NAME:

ISSUE DATE:

Last First M.I.

I EMPLOYEE ID NO.

COMPLETION DATE:

I I

COMMENTS:

I I

Training Review for Completeness:

LMS CODE:

i LMS ENTRY:

Signature/Date PLOR415CA Rev 000 Page 1 of 5:

POSITION TITLE:

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR:

2740100101/PLOR-415CA KIA:

400000 A2.01 TASK DESCRIPTION:

RO: 3.3 SRO: 3.4 Placing the Standby TBCCW Pump in Service (Alternate Path -

Standby Pump Trips)

A.

NOTES TO EVALUATOR:

1.

An asterisk(*) before the step number denotes a CRITICAL STEP. CRITICAL STEF11S are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2.

System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3.

JPM Performance

a.

"Control Room" JPMs are designed to be performed in the simulator. If a i

"Control Room" JPM is to be performed in the Control Room all perform stepsI (P) shall be simulated (S).

I

b.

When performing "In-Plant" JPMs, no equipment will be operated without Shift Management approval.

4.

Satisfactory performance of this JPM is accomplished if:

a.

b.

The task standard is met.

JPM completion time requirement is met.

j

1)

For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determin~s that the progress to completion is acceptable.

I

2)

For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

c.

Applicable JPM Work Practice Standards, TQ-AA-150-J040 graded satisfactorily.

5.

The estimated time to complete this JPM, though listed in the task standard, is not to be given to the examinee.

PLOR415CA Rev 000 Page 2 of 5

8.

TOOLS AND EQUIPMENT

1.

None

'I C.

REFERENCES

1.

SO 34.6.A-2, Placing Standby Turbine Building Closed Cooling Water System Pump in

~~~

D.

TASKSTANDARD I

, I

1.

Satisfactory task completion is indicated when the 28 TB;CCW pump failure has be~~

recognized and the 2A TBCCW has been restarted.

i

2.

Estimated time to complete: 10 minutes Non-Time Critical E.

DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to perfotm a swap of the TBCCW pumps using appropriate procedures. I will describe initial plant conditions and provide you I

access to the materials required to complete this task.

F.

TASK CONDITIONS/PREREQUISITES G.

1.

The TBCCW system is in operation in accordance with ~O 34.1.A-2, Turbine Building Closed Cooling Water System Startup and Normal Oper~tions, with the 2A TBCCW Pump in service.

i

2.

The 28 TBCCW pu,mp casing has been vented.

I INITIATING CUE

I The Control Room Supervisor directs you to place the 28 TBC(rW Pump in service and place the 2A TBCCW Pump in Standby in accordance with SO 34.6.A-2, Placing Standby Turbin:J Building Closed Cooling Water System Pump in Service.

PLOR415CA Rev 000 Page 3 of 5 1

H.

PERFORMANCE CHECKLIST STEP STEP ACT STANDARD I

I NO i

1 Obtain a copy of SO 34.6.A-2.

p Obtains a copy of the procedure and I

reviews the precautions.

I

2 Start the 28 T8CCW Pump.

p Places the control switch for the 28 I

TBCCW Pump in RUN. Verifies red light is on and green light is off.

I 3

Verify discharge pressure of standby p

Directs EO to verify discharge pressure pump is greater than 70 psig.

on Pl-2220B is greater than 70 psig.

(Cue: Discharge pressure is 85 psig.)

4 Stop the 2A TBCCW Pump.

p Places the control switch for the 2A TBCCW Pump in AUTO. Verifies red light is off and green light is on.

- - - NOTE****

The Alternate Path portion of this JPM begins with the next step.

5 6

7 8

9 10 Recognize annunciators 217 A-5, "B" Turb Bid Cooling Water Pump Ovid, and 217 C-5, Turb Bldg Cooling Water Supply Lo Press, in.

Recognizes trip of the 28 T8CCW Pump and failure of the 2A T8CCW Pump to start.

Starts the 2A T8CCW Pump.

Verify discharge pressure of the 2A TBCCW pump is greater than 70 psig and less than 87 psig.

(Cue: Discharge pressure is 80 psig.)

Inform the Control Room Supervisor of the trip of the 2B T8CCW pump and that the 2A TBCCW pump is running.

(Cue: Acknowledge report.)

As an evaluator, ensure that you have positive control of all exam material provided to the examinee. (Task Conditions/Prerequisites) AND procedures.

Under "ACT" P - must perform S - must simulate I.

TERMINATING CUE PLOR415CA Rev 000 p

p p

p Observes flashing alarm light and depresses alarm acknowledge pushbutton.

Observes 2B TBCCW amps and I

discharge pressure are low. Both green lights are lit, and the red lights are off.I Places the control switch for the 2A I

TBCCW Pump in RUN. Verifies red light is on and green light is off.

I Directs EO to verify discharge pressu1e on Pl-2220A is greater than 70 psig and less than 87 psig.

I CRS informed.

Positive control established.

I Page 4 of sl I

I

When the 2A TBCCW Pump is placed back in service, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.

PLOR415CA Rev 000 Page 5 of~

.EXELON NUCLEAR Nuclear Generation Group OJT/TPE,MATERIAL COVERSHEET:

~

JPM I

QUALIFICATION MANUAL LICENSED OPERATOR TRAINING 2021 IL T NRC JPM H D.Adams OJT MODULEf I PLOR-265C~ I 000 dwa MANUALLY PLACE SBGT ON THE EQUIPMENT CELL EXHAUST (ALTERNATE:

PATH - 1sT FAN FAILS TO ALIGN)

APPROVALS:

Signature/ Title Date Signature/ Title Date Signature/ Title Date Signature/ Title Date APPROVED FOR USE:

Signature/ Title Date EFFECTIVE DATE:

I NAME:

ISSUE DATE:

I Last First M.I.

i EMPLOYEE I.D. NO.

COMPLETION DATE:

I

'I COMMENTS:

I I

Training Review for Completeness:

LMS CODE:

i I I

LMS ENTRY:

I I Signature/Date I

I I

I PLOR265CA Rev000

,1 Page 1 of 7 I

I

POSITION TITLE:

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR:

2610070101 / PLOR-265CA KIA:

261000 A2.05 RO: 3.0 SRO: 3.1 TASK DESCRIPTION:

Manually Place SBGT on the Equipment Cell Exhaust (Alternate Path -

1st Fan Fails to Align)

A.

NOTES TO EVALUATOR:

1.

An asterisk(*) before the step number denotes a CRITICAL STEP. CRITICAL STERS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2.

System cues included in the performance checklist are to be provided to the examinee when no system response is available.

3.

JPM Performance

a.

"Control Room" JPMs are designed to be perform~d in the simulator. If a "Control Room" JPM is to be performed in the Control Room all perform steps:(P) shall be simulated (S).

1

b.

When performing "In-Plant" JPMs, no equipment will be operated without Shift Management approval.

4.

Satisfactory performance of this JPM is accomplished if:

a.

The task standard is met.

b.

JPM completion time requirement is met.

1)

For non-time critical JPMs, completion within double the estimated tim~

(listed in paragraph D.2) is acceptable provided the evaluator determines that the progress to completion is acceptable.

I

. I

2)

For time critical JPMs, completion within the estimated time (listed in * :

paragraph D.2) is required.

5.

The estimated time to complete this JPM, though listed in the task standard, is not toi be given to the examinee.

PLOR265CA Rev000 Page2 of7i

B.

TOOLS AND EQUIPMENT None C.

REFERENCES I

I

1.

Procedure SO 9A.7.G Rev. 13, "SBGT Manual Startup on Equipment Cell Exhaust" (R)

2.

ST-O-09A-500-2 Rev. 7, "SBGT Filter Train Operation Log" (A)

D.

TASK STANDARD

t.

Satisfactory task completion is indicated when the A outlet damper failure is found and the B SBGT system is operating on Equipment Cell Exhaust.

2.

Estimated time to complete: 9 minutes (A.5) Non-Time Critical E.

DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to place'SBGT on Equipment Cell Exhaust using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.

F.

TASK CONDITIONS/PREREQUISITES

1.

Standby Gas Treatment System lined up for automatic operation per SO 9A.1.A, "Standby Gas Treatment System Lineup for Automatic Operation"

2.

Operator stationed at Reactor Building Vent Panel 20C132.

3.

Standby Gas Treatment Filter Train "A" has the least amount of run-hours.

G.

INITIATING CUE The Control Room Supervisor directs you to place SBGT on Equipment Cell Exhaust using,the A SBGT Fan IAW SO 9A.7.G, "Standby Gas Treatment System Manual Startup on Equipment Cell Exhaust".

I PLOR265CA Rev000 Page 3 of 7i

II H.

STEP NO 1

2

3

4

5

6

7 8

PERFORMANCE CHECKLIST STEP Obtain a copy of procedure SO 9A.7.G.

Notify Health Physics that SBGT is to be started on Unit 2 Equipment Cell Exhaust.

(Cue: Health Physics acknowledges notification.)

Open PO-20465, Exh To SBGT Equip Cell Damper.

Open AO-20469-1, SBGT DW Rx Bldg Exh Damper.

(Cue: Acknowledge control switch operation.)

(Evaluator Note: This step is critical IF AO-20469-2 is NOT opened.)

Open AO-20469-2, SBGT DW Rx Bldg Exh Damper.

(Cue: Acknowledge control switch operation.)

(Evaluator Note: This step is critical IF AO-20469-1 is NOT opened.)

Open AO-00475-1, SBGT "A" Filter Inlet Damper.

Open AO-00475-2, SBGT "A" Filter Outlet Damper.

ACT p

STANDARD A copy of procedure SO 9A.7.G is obtained. :

P Health Physics notified that SBGT is to be started on:: Unit 2 Equipment Cell ExhJust.

P PO-20465; control switch placed in the OPEN po~ition at panel 20C012. Verifies red light is! on, green light is off.

I

,I P

AO-20469 1-1 control switch placed in the OPEN position at panel 20C012. Verifies red light iS on, green light is off.

p p

p AO-20469-2 control switch is placed irnl' the OPE Ni, position at panel 20C012.,

Verifies re;d light is on, green light is of.

AO-00475-1 control switch is placed ir' the OPENi position at panel 20C012. :

Verifies re 1d light is on, green light is off.

l I AO-0047~-2 control switch is placed \\n the OPENi position at panel 20C012. i

~

- - - NOTE ****

The Alternate Path portion of this JPM begins with the next step.

Identifies failure of AO-00475-2, SBGT P

Identifies green light on, red light off..

"A" Filter Outlet Damper to open.

PLOR265CA Rev000 Page 4 of 7,

STEP NO 9

10 11

12

13

14 15 16

17

18 STEP Determines the "B" SBGT Train should be placed in service.

(Cue: Acknowledges report of starting the "B" SBGT Fan.)

Closes AO-00475-1, SBGT "A" Filter Inlet Damper.

Closes AO-00475-2, SBGT "A" Filter Outlet Damper.

Open AO-00476-1, SBGT "B" Filter Inlet Damper.

Open AO-00476-2, SBGT "B" Filter Outlet Damper.

Start "A" SBGT Fan.

Verify the "A" SBGT Fan Start.

Wait 3 to 5 seconds after "A" SBGT fan starts to close AO-20467.

Close AO-20467, Ventilation Exhaust Equip Cell Damper.

(Cue: Acknowledge control switch operation.)

Close AO-20468, Ventilation Exhaust Equip Cell Damper.

(Cue: Acknowledge control switch operation.)

PLOR265CA Rev000 ACT STANDARD p

p p

I I

Informs the CRS that the "B" SBGT Train I

will be placed in service.

AO-00475-1 control switch is placed i~1 the CLOSE position at panel 20C012.. 1 Verifies red light is off, green light is 0/1.

I AO-00475-2 control switch is placed i~I'1 the CLOSE position at panel 20C012.

Verifies red light is off, green light is on.

I I

AO-00476-1 control switch is placed im the OPEN position at panel 20C012. I Verifies red light is on, green light is off.

I I I AO-00476-2 control switch is placed ij' the OPEN position at panel 20C012.

Verifies red light is on, green light is o1f.

I I

I "A" SBGT Fan control switch is placed in the RUN position at panel 20C012.

I Identifies the "A" SBGT Fan failed to start.

Verifies flow rises to 6000scfm, filter d~p rises to 1" water pressure, red light is on, green light is off.

I AO-20467 is closed more than 3 secohds after "A" SBGT fan is started.

I I

AO-20467 control switch is placed in the CLOSE position at panel 20C012.

I Verifies green light is on, red light is off.

AO-20468 control switch is placed in the CLOSE position at panel 20C012.

Verifies green light on, red light off.

I Page 5 of7!

I

STEP STEP ACT STANDARD I

NO I

I 19 Direct Equipment Operator to verify p

Equipment Operator directed to verify ;the Equipment Cell Exhaust Fans 2AV18 and Equipment Cell Exhaust Fans not run~ing 2BV18 are not running and verify the and Fan control switches in "OFF".

i control switches for both of the I

Equipment Cell Exhaust Fans are in I

I "OFF".

I I

I (Cue: Equipment Operator reports 2AV18 and 2BV18 are not running and both of the Equipment Cell Exhaust Fan control switches are in OFF".)

I i

20 Verify proper operation of the SBGT p

The "A" SBGT Filter DP is verified to ~e system.

in Expected Performance Region of I

Figure 1 of SO 9A.7.G and SBGT Sys:tem (Cue: SBGT Filter DP is in the Expected flow is verified to be between 2000 and Performance Region of SO 9A.7.G, 9000 SCFM on FR-20008.

I I

Figure 1.)

i I

i 21 Verify Unit 2 Reactor Building differential p

Reactor Building DPl-20003-01 indicaJes pressure between -.1 and -.4" H2O as between -.1 and -.4" H2O. Equipment!

indicated on DPl-20003-01.

Operator is directed to adjust differential (Cue: Reactor Building DP is between -

pressure between -.1 to -.4 inches of [

water as necessary.

I 0.1 and -0.4" H2O.)

I I

22 Verify Unit 2 Refuel Floor differential p

Equipment Operator is directed to vedfy pressure between -.1 and -.4" H2O as Refuel Floor DPl-20003-02 indicates i indicated on DPl-20003-02.

between -.1 and -.4" H2O.. Equipmeht Operator is directed to adjust differential (Cue: Refuel Floor DP is between -0.1 pressure between -.1 to -.4 inches of water as necessary.

and -0.4" H2O.)

23 Log start time in the SBGT Filter Train p

Logs start time in ST-O-09A-500-2, Data Run Log in accordance with ST-O-09A-Sheet 1.

1 500-2.

(Cue: Start time is logged in ST-O-09A-500-2.)

PLOR265CA Rev000 Page 6 of 7

'.I

,1 I

STEP STEP ACT i

STANDARD

I I

I NO I

24 Inform Control Room Supervisor of task p

Task completion reported.

'I completion.

i (Cue: Control Room Supervisor i

acknowledges report.)

25 As an evaluator ensure you have positive p

Positive c0ntrol established.

'I control of all exam material provided to the examinee (Task Conditions/

Prerequisites) AND procedures.

Under "ACT" P - must perform S - must simulate I.

TERMINATING CUE

i.

I When Equipment Cell Exhaust is placed on Standby Gas Treatment, the Control Room Supervisor should be informed. The evaluator will then termina~e the exercise.

I i

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I I

' I I

I I

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I PLOR265CA Rev000 Page 7 of 71

EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET:

-~ JPM Licensed Operator Training 2021 IL T NRC JPM I N. Patrou QUALIFICATION MANUAL I

I OJT MODUL~I PLOR-409P

I 000

I ntp LOWERING TORUS LEVEL USING THE TORUS WA llER FILTER PUMP

'I APPROVALS:

Signature / Title Date Signature / Title Date Signature I Title Date

Signature / Title Date PPROVED FOR USE:

Signature I Title Date EFFECTIVE DATE: ___

I NAME: ---------------

ISSUE DATE:

I Last First M.I.

EMPLOYEE NO.

COMPLETION qATE:

COMMENTS:

Training Review for Completeness:

PIMS CODE:

I PIMS ENTRY:

Signature/Date PLOR409P Rev000 Page 1 of q

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:

Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR:

2008660501 / PLOR-409P KIA:

295029 EA2.01 RO: 3.9 SRO: 3.9 TASK DESCRIPTION:

LOWERING TORUS LEVEL USING THE TORUS WATER FILTER PUMP A.

NOTES TO EVALUATOR:

1.

An asterisk(*) before the step number denotes a CRITICAL STEP. CRITICAL STE~S are those steps which when not performed correctly will prevent the system from I

functioning properly or prevent successful task completion.

i I

2.

System cues included in the performance checklist are to be provided to the examinke when no system response is available.

3.

JPM Performance

a.

b.

"Control Room" JPMs are designed to be performed in the simulator. If a I

"Control Room" JPM is to be performed in the Control Room all perform steps, (P) shall be simulated (S).

I When performing "In-Plant" JPMs, no equipment will be operated without Shift Management approval.

4.

Satisfactory performance of this JPM is accomplished if:

5.

a.

The task standard is met.

b.

JPM completion time requirement is met.

1)

2)

For non-time critical JPMs, completion within double the estimated time (listed in paragraph D.2) is acceptable provided the evaluator determin~s that the progress to completion is acceptable.

For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

The estimated time to complete this JPM, though listed in the task standard, is not tol 1 be given to the examinee.

PLOR409P Rev000 Page 2 of 5

B.

TOOLS AND EQUIPMENT None C.

REFERENCES Procedure T-234-2, Rev. 0, LOWERING TORUS LEVEL USING THE TORUS WATER FILTER PUMP D.

TASK STANDARD

1.

Satisfactory task completion is indicated when Torus water is being pumped to Radwaste IAW T-234-2.

2.

Estimated time to complete: 15 minutes Non-Time Critical E.

DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to recoyple Control Rod 26-03 using appropriate procedures. I will describe initial plant conditions amd provide you access to the materials required to complete this task.

F.

TASK CONDITIONS/PREREQUISITES

1.

Unit 2 is at 100% power, when an event occurred.

2.

T-102, "Primary Containment Control", has been entered:.

'I

3.

Torus water level is approaching 17 feet and torus water*:can be retained in radwaste.

I

4.

Torus Water Filter Pump isolation valves will be operatetj locally.

5.

The Torus Water Filter Pump is energized from 1 RB-4-B;

6.

Offsite power sources are supplying electrical power to the plant.

G.

INITIATING CUE I

I The Control Room Supervisor directs you to lower Torus water I.evel in accordance with T-234-2, "Lowering Torus Level Using The Torus Water Filter Pump". :

PLOR409P Rev000 Page 3 of~

H.

,STEP NO 1

PERFORMANCE CHECKLIST STEP Obtain a copy of procedure T-234-2.

ACT STANDARD p

Obtains a copy of procedure T-234-~-I

- - Note***

I It is not required to actually remove the Tool Package from the EOP Tool Locker for the Step belpw.

2 Obtain the T-234 Tool Package from the S

Obtains the T-234 Tool Package frorr 1 the

3

4 5

6 Emergency Operating Procedure Tool EOP Tool, Locker.

Locker located in Radwaste Bldg 165'(near the Unit 2 Remote Shutdown Panel) OR the Auxiliary EOP Tool Locker on the South End Hallway of the Warehouse Complex Supply Office Area.

(Cue: You have the T-234-2 Tool Package.)

Open the following breakers:

Valve MO-2-14-070

Breaker 52-3623

MCC E124-R-C

Valve MO-2-14-070

Breaker 29-1112

MCC 2DB-R-B (Cue: The breakers indicate open.)

s Opens the following breakers by rotafng the breaker operators to OPEN/TRIP:

Valve MO-2-14-070

Breaker 52-3623

MCC E124-R-C

Valve MO-2-14-070

Breaker 29-1112

MCC 2DB-R-B

- - Note***

It is not required to open the front of Panel 20C041 in the Step below.

Install the following jumper in Panel S

Installs the following jumper in Panel 20C041 :

20C041 :

Panel 20C041 (front); Terminal 88-19 to 88-20 (Cue: The jumper has been placed in the location you have stated.)

Notify Radwaste Operator of intent to transfer Torus Water to Radwaste.

(Cue: Acknowledge the report.)

Verify closed HV-2-14A-73, "Torus Wtr Filter Pp 20P142 Discharge Block Valve".

(Cue: The valve does not turn.)

Panel 20C041 (front); Terminal 88-19 to 88-20 S

Notifies Radwaste Operator of intenti 'o transfer Torus Water to Radwaste.

1 i

S Verifies clpsed HV-2-14A-73, "Torusi~tr Filter Pp 20P142 Discharge Block Val 1ve" by attempting to rotate the valve operator in the closed direction (CW) and with ho motion obtained.

, I PLOR409P Rev000 Page 4 of 5

STEP NO

7

8

9

10 11 12 I.

STEP Open HV-2-14A-29038, "Torus Wtr Cleanup Block Vv to Radwaste Collection Tank".

(Cue: Handwheel is turning until it stopped.)

Open MO-2-14-070, "lnbd Suet".

(Cue: Handwheel is turning until it stopped.)

Open MO-2-14-071, "Outbd Suet".

(Cue: Handwheel is turning until it stopped.)

Start the Torus Water Filter Pump 20P142, by placing its control switch to "START" on Panel 20C003.

(Cue: Red liQht is ON.)

Inform Control Room Supervisor that Torus water is being pumped to Radwaste IAW T-234-2.

(Cue: Control Room Supervisor acknow-ledQes report.)

As an evaluator ensure that you have positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND p raced u res.

Under"ACT" P - must perform S - must simulate TERMINATING CUE ACT s

s s

p STANDARD Opens H\\?-2-14A-29038, "Torus Wtr1 i Cleanup Block Vv to Radwaste Collection Tank" by totating the valve operator if the open direction (CCW) until the motion stops.

I Ope~s M<p-2-14-070, "lnbd_ Suet" by I rotating t~e valve operator in the op~~

direction (CCW) until the motion stops.

I Opens MO-2-14-071, "Outbd Suet". :

I By rotating the valve operator in the open direction (CCW) until the motion stops.

Starts the:Torus_W~ter Filter Pun:,p

I 20P142, qy placing its control sw1tch,to "START" bn Panel 20C003.

Operator informs CRS that Torus water is I

I being pu1111ped to Radwaste IAW T-2B4-

2.

I I

Positive control maintained.

i When Torus water 1s being pumped to Radwaste IAW T-234-2,:the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.

I I

I PLOR409P Rev000 Pages of 5

EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET

~

JPM QUALIFICATION MANUAL OJT MODULE Licensed Operator Training PLOR-191P 2021 IL T NRC JPM J 005 D.W. Adams dwa REMOVE FUSES PER OT-114 FOR STUCK OPEN SRV - UNIT 3 APPROVALS:

Signature I Title Date Signature / Title Date Signature / Title Date Signature I Title Date PPROVED FOR USE:

Signature I Title Date EFFECTIVE DATE: -----

NAME:

ISSUE DATE:

Last First M.I.

Employee ID NO.

COMPLETION DATE:

COMMENTS:

Training Review for Completeness:

LMS CODE:

I LMS ENTRY:

Signature/Date PLOR191P Rev005 Page 1 of 51 I

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION JOB PERFORMANCE MEASURE POSITION TITLE:

Unit Reactor Operator/Senior Reactor Operator TASK-JPM DESIGNATOR:

2007400501 / PLOR-191P KIAi 239002A2.03 I.

I I

'I SRO: 4.2

TASK DESCRIPTION:

RO: 4.1 Remove Fuses per OT-114 for Stuck Open SRV A.

'I I NOTES TO EVALUATOR:

.1 I

1.

2.

3.

4.

5.

I An asterisk (*) before the step number denotes a CRITICAL STEP. CRITICAL STERS are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

i System cues included in the performance checklist are to be provided to the exami~le I

when no system response is available.

I JPM Performance

I

a.

"Control Room" JPMs are designed to be performed in the simulator. If a I

"Control Room" JPM is to be performed in the Control Room all perform steps 1 (P) shall be simulated (S).

I

b.

When performing "In-Plant" JPMs, no equipment will be operated without Shift Management approval.

Satisfactory performance of this JPM is accomplished if:

a.

The task standard is met.

b.

JPM completion time requirement is met.

1)

For non-time critical JPMs, completion wit~in double the estimated timi (listed in paragraph D.2) is acceptable provided the evaluator determi~es that the progress to completion is acceptable.

! I

2)

For time critical JPMs, completion within the estimated time (listed in,

paragraph D.2) is required.

The estimated time to complete this JPM, though listed i_n the task standard, is not ta be given to the examinee.

I PLOR191P Rev005 Page 2 of5 I

B.

TOOLS AND EQUIPMENT

1.

None REFERENCES

1.

2.

OT-114, Rev 23, "Inadvertent Opening of a Relief Valve" 1

IR 175886, "Dual Unit Scram - 30 SRV Failed to Close l.Jntil 400 PSIG"

I D.

TASK STANDARD E.

F.

1.

Satisfactory task completion is indicated when fuses for stuck open SRV are remove?

and reported to Shift Management.

2.

Estimated time to complete: 5 minutes Non-Time Critical DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to remove fuses for stuck open SR~

using appropriate procedures. I will describe initial plant conditions and provide you access: to the materials required to complete this task.

/

TASK CONDITIONS/PREREQUISITES

1.

2.

3.

Reactor power is being reduced per GP-9-3, "Fast Reactor Power Reduction."

RV-3-02-071J has opened unexpectedly and has not re-plosed.

I RV-3-02-071J control switch was cycled open and closed on panel 30C003.

ii I I I

G.

INITIATING CUE The Control Room Supervisor directs you to remove fuses for RV-3-02-071 J by performing I step 3.5.2 of OT-114.

PLOR191P Rev005 I

I I

'I Page 3 of 5

H.

PERFORMANCE CHECKLIST II STEP STEP ACT NO 1

Obtain a copy of procedure OT-114 p

2 Request Concurrent Verification (CV).

p (Cue: Acknowledge request, inform examinee that for purposes of evaluation CV will NOT be conducted) 3 Open panel 30C32 rear doors.

p (Cue: Panel 30C32 rear doors are open.)

4 In rear of panel 30C32, locate terminal p

strip EE, fuse F9.

5 Remove fuse F9.

s (Cue: F9 [2E-F11J] fuse is removed.)

6 In rear of panel 30C32, locate terminal p

strip EE, fuse F20.

7 Remove fuse F20.

s (Cue: F20 [2E-F12J] fuse is removed.)

8 In rear of panel 30C32, locate terminal p

strip GG, fuse F11.

9 Remove fuse F11.

s (Cue: F11 [2E-F3J] fuse is removed.)

10 In rear of panel 30C32, locate terminal p

strip GG, fuse F24.

11 Remove fuse F24.

s (Cue: F24 [2E-F4J] fuse is removed.)

PLOR191P Rev005 STANDARD I

I I

A copy of procedure OT-114 obtained!

Table 1, S 1RV Fuse Removal, referentjed.

Concurreht Verification (CV) requeste~.

I I

I The center panel door handle turned; j doors pulled outward to gain access tcp terminal strips in rear of panel 30C32 in the Cable:spreading Room.

, I I

I Terminal strip EE, fuse F9 located in 'the I

left rear of Cable Spreading Room panel 30C32.

I I

Examinee, correctly identifies Fuse F~I on terminal strip EE and describes process for removal.

I Terminal strip EE, fuse F20 located inl the right rear bf Cable Spreading Room p 1anel 30C32.

I Examined correctly identifies Fuse F~O on terminal strip EE and describes

. i process f~r removal.

! I I

Terminal strip GG, fuse F11 located i~ the rear of Cable Spreading Room pane!

30C32.

i Examinee correctly identifies Fuse F11 on terminal strip GG and describes

1 process for removal.

Terminal strip GG, fuse F24 located :ih the rear of Cable Spreading Room pane:I 30C32.

i I

Examinee correctly identifies Fuse F~4 on terminal strip GG and describes I

I process for removal.

I I

Page 4 of 5

-I

12 13 14 I.

Close panel 30C32 rear doors.

(Cue: Panel 30C32 rear doors are closed and latched.)

Inform Control Room Supervisor that step 3.5.2 of OT-114 is complete.

(Cue: Control Room Supervisor acknowledges report.)

As an evaluator ensure that you have positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND procedures.

Under "ACT" P - must perform S - must simulate TERMINATING CUE p

s p

I I

I Panel 30C;32 rear doors are closed a~a latched using the handle.

I I

Task com~letion reported using telephone /or GAI-TRONICS page system.

1 I

,1 I

'I I

NOTE: Handheld radio is NOT to be, used in th~ Cable Spreading Room. :

Positive c6ntrol established.

I I

When all four fuses for 3J SRV are removed and the Control Ro;om Supervisor informed, the evaluator will then terminate the exercise.

PLOR191P Rev005 Page 5 of?

I

EXELON NUCLEAR Nuclear Generation Group OJT/TPE MATERIAL COVERSHEET

~

JPM QUALIFICATION MANUAL OJT MODULE LICENSED OPERATOR TRAINING PLOR-073P 2021 IL T NRC JPM K 014 J. R. Felice crf LOSS OF CRD REGULATING FUNCTION (OUTSIDE OF CONTROL ROOM ACTIONS)

APPROVALS:

Signature/ Title Date Signature / Title Date Signature / Title Date Signature/ Title Date APPROVED FOR USE:

Signature / Title Date EFFECTIVE DATE: ----

NAME:

ISSUE DATE:

Last First M.I.

SOC. SEC. NO.

COMPLETION DATE:

COMMENTS:

Training Review for Completeness:

PIMS CODE:

PIMS ENTRY:

Signature/Date PLOR073P Rev014 Page 1 of 5 I

I I

I I I

EXELON NUCLEAR PEACH BOTTOM ATOMIC POWER STATION

'I JOB PERFORMANCE MEASURE POSITION TITLE:

Unit Reactor Operator/Senior Reactor O,;?erator TASK-JPM DESIGNATOR:

2010100404 / PLOR-073P KIA:

201001A2.06 RO: 2.9 SRO: 2.9 TASK DESCRIPTION:

Loss of CRD Re Outsi~e of Control Room Actions,

A.

NOTES TO EVALUATOR:

1.

An asterisk(*) before the step number denotes a CRITICAL STEP. CRITICAL STE S I

are those steps which when not performed correctly will prevent the system from functioning properly or prevent successful task completion.

2.

System cues included in the performance checklist are to be provided to the examin,ee when no system response is available.

3.

JPM Performance

a.

"Control Room" JPMs are designed to be performed in the simulator. If a "Control Room" JPM is to be performed in the Control Room all perform steps (P) shall be simulated (S).

b.

When performing "In-Plant" JPMs, no equipment will be operated without Shi Management approval.

4.

Satisfactory performance of this JPM is accomplished if:

a.

The task standard is met.

b.

JPM completion time requirement is met.

1)

F?r no~-time critical JPM~, completion withi_n double the estimated ti~~

(listed m paragraph D.2) Is acceptable provided the evaluator determines that the progress to completion is acceptable.

2)

For time critical JPMs, completion within the estimated time (listed in paragraph D.2) is required.

5.

The estimated time to complete this JPM, though listed in the task standard, is not k> be given to the examinee.

PLOR073P Rev014 Page 2 of 5

B.

TOOLS AND EQUIPMENT None C.

REFERENCES

1.

Procedure ON-107, Rev. 25, "Loss of CRD Regulating Function"

2.

Procedure SO 3.7.H-2(3), "CRD Hydraulic System Pump Suction Filter Replacement1'

3.

P&ID M-356 Sheet 1 (2), "Control Rod Drive Hydraulic System" D.

TASK STANDARD

1.

Satisfactory task completion is indicated when the CRD pump suction filter is bypass~d and isolated.

2.

Estimated time to complete: 10 minutes Non-Time Critical E.

DIRECTIONS TO EXAMINEE When given the initiating cue, perform necessary steps to bypass and isolate the CRD pump suction filter using appropriate procedures. I will describe initial plant conditions and provide you access to the materials required to complete this task.

TASK CONDITIONS/PREREQUISITES

1.

Unit 2(3) is operating at full power steady state conditions.

2.

Both CRD pumps have tripped on low suction pressure.

3.

ON-107 "Loss of CRD Regulating Function" procedure has been entered.

G.

INITIATING CUE I

The Control Room Supervisor directs you, the Equipment Operator, to bypass and isolate t~e Unit 2(3) CRD pump suction filter in accordance with ON-107, "Loss of CRD Regulating Function".

PLOR073P Rev014 Page 3 of 5;

H.

PERFORMANCE CHECKLIST

iTEP NO 1

2

3

4 5

STEP Obtain a copy of procedure ON-107.

Slowly open HV-2(3)-3-129, GROHS Bypass Valve for Pump Suction Filter 2(3)0F101.

(Cue: Valve handwheel is turned

[COUNTERCLOCKWISE] until stem length above valve yoke rises 4 inches, then will not turn.).

Slowly close HV-2(3)-3-130, CRDHS Outlet Block Valve from Pump Suction Filter 2(3)0F101.

(Cue: Valve handwheel is turned

[CLOCKWISE] until stem length above valve yoke lowers 4 inches, then handwheel will not turn.)

Close HV-2(3)-3-127, CRD Water Pump Suet Fltr 2(3)0F101 Inlet Block Valve.

(Cue: Valve handwheel is turned

[CLOCKWISE] until stem length above valve yoke lowers 4 inches, theri handwheel will not turn.)/

Inform Control Room Supervisor of task completion.

(Cue: Control Room Supervisor acknowledges report.)

6 As an evaluator ensure that you have positive control of all exam material provided to the examinee (Task Conditions/Prerequisites) AND procedures.

Under "ACT" P - must perform S - must simulate PLOR073P Rev014 ACT p

s s

I I

I

(

1 i

I I

i STANDARD I

A copy of ~rocedure ON-107 is obtaintd.

I HV-2(3)-3-,129, handwheel is slowly tl,lfned COUNTERCLOCKWISE until resistance of valve backseat is felt.

I HV-2(3)-3-:130 handwheel is slowly tu'rhed CLOCKWl'SE until resistance of valve 1seat is felt.

1 1

HV-2(3)-3-127 handwheel is turned

CLOCKWl(SE until resistance of valv~ seat is felt.

Task completion reported using telepHone handheld radio, or GAI-TRONICS pag 1e system.

I P

Positive control established.

I

' I I !

I I 1

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Page 4 of 5 i

I.

TERMINATING CUE When the Unit 2(3) CRD pump suction filter is bypassed and isolated, the Control Room Supervisor should be informed. The evaluator will then terminate the exercise.

I I PLOR073P Rev014 Page 5 of 5;

SIMULATOR OPERATOR INSTRUCTIONS FOR 2021 NRC SCENARIO #1 GENERAL REQUIREMENTS Recorders will be rolled prior to the scenario and paper from selected recorders will be retained for the examination team as requested.

All procedures, flow charts, curves, graphs, etc. will be in their normal storage places.

All markable procedures, boards, etc. will be erased.

All paper used by the Crew will be retained for the examination team as requested.

The simulator operators will keep a log of all communications during the scenario as requested by the examination team.

SCENARIO SOURCE HISTORY This scenario is a modified scenario written for the 2021 NRC exam.

INITIAL SETUP Initial Conditions Reset to IC-9, 10% power Insert Control Rods to lower Reactor power to 5%.

Set Remote MCS08 (MO2205A-C MVP Suction) to OPEN Start the Mechanical Vacuum Pump Ensure recorder power is on; roll recorders as required Ensure annunciator horns are active Blocking Tags None Event Triggers ET6, (Mode Switch or Scram PB)

ET7, ZGl13A1S101A==1 (HPCI Manual Initiation Pushbutton) 1

, I I

i

. I

Malfunctions INSERTED HPC01, Failure of HPCI to Auto-start PCI01TO, PCIS Group I Isolation - Override TRG 1 CRM043447, "Control Rod (34-47) Drift In" TRG2 PCS04A, OW Pressure Transmitter PT-5-12A Failure - SV 100%

TRG 6 RRS20, Recirculation Loop Rupture - SV 3%, 10 Min Ramp Time MCS0SA, Condensate Pump A Trip MCS0SB, Condensate Pump B Trip MCS0SC, Condensate Pump C Trip TRG7 HPC0J, HPCI Turbine Trip - 1 Min Delay Time Overrides TRG2 ANO205LD4, RPS/PC15 Trip Unit in Calibration -ALARM_ON TRG 3 ZGl12A1S07, 2A Core Spray Pump (STOP,STRT) - START, 5 Sec Delete Time TRGS PT2184, Main Steam Line Press A - 930, 30 Min Ramp Time PT2185, Main Steam Line Press B - 930, 30 Min Ramp Time Trip Overrides None Remote Functions TRG 8 RHR02A, LPCI Line A Stay Full Valve HV-70A - CLOSE RHR028, LPCI Line A Stay Full Valve HV-708 - CLOSE TRG9 MCS0B, MO2205A-C MVP Suction - CLOSE Turnover Procedures GP-2-2, "Normal Plant Startup" completed up to step 6.2.61 SO 8.1.A-2, "Off-Gas System Startup for Normal Operations",, starting at step 4.7.

2

EVENT 1 EVENT 2 EVENT 3 EVENT 4 SIMULATOR OPERATOR DIRECTIONS Secure the Mechanical Vacuum Pump Support the Crew as necessary to allow the PRO to secure the Mechanical Vacuum Pump per step 4.7 of SO 8.1.A-2, "Off-gas System Startup for Normal Operations".

When called to close HS-2-08E-2205A(B)(C), "Condenser 2A(B)(C) Off-gas to Mechanical Vacuum Pp 20P009, insert TRG 9 and verify the following:

MCS08, MO2205A-C MVP Suction - CLOSE Wait 1 minute and report HS-2-08E-2205A(B)(C), "Condenser 2A(B)(C)

Off-gas to Mechanical Vacuum Pp 20P009" closed.

Control Rod Withdraw Support the Crew as necessary during Control Rod withdrawal till 2 main turbine bypass valves are open.

Control Rod Drift When directed by the Lead Examiner, insert TRG 1 and verify the following malfunction activates:

CRM043447, "Control Rod (34-47) Drift In" If directed to inspect HCU 34-47, wait 3 minutes and report the Exhaust header is hot to the touch and you hear flow noise.

When Control Rod 34-47 position indicates fully inserted, delete malfunction CRM043447.

Drywall Pressure Instrument Failure I

When directed by the Lead Examiner, initiate pending events on TRG 2 and verify !

that the following events activate:

PCS04A, OW Pressure Transmitter PT-5-12A Failure - SV 100%

ANO205LD4, RPS/PC15 Trip Unit in Calibration -ALARM_ON If directed to investigate failure of the A Drywell Pressure Transmitter, wait 2 minutes and report a gross failure of the A instrument.

3

EVENT 5 EVENT 6 Core Spray Spurious Start At the direction of the Lead Examiner, initiate pending events on TRG 3 and:

verify the following Overrides activate:

ZGl12A1S07, 2A Core Spray Pump (STOP,STRT) - START, 5 Sec Delete Time If directed to investigate the Core Spray pump starts, wait approximately 3,

minutes and report that you don't know why the Core Spray pumps started. :

Pressure Regulator Fails High Verify the following malfunctions are inserted:

HPC01, Failure of HPCI to Autostart PCI01TO, PCIS Group I Isolation - Override At the direction of the Lead Examiner, initiate pending events on TRG 5 and:

verify the. following Override activates:

PT2184, Main Steam Line Press A - 930, 30 Min Ramp Time PT2185, Main Steam Line Press B - 930, 30 Min Ramp Time\\

4

EVENT 7 EVENT 8 TERMINATION Recirc Water Leak in Containment When the Mode Switch is taken to Shutdown, verify TRG 6 and the following malfunction activates:

RRS20, Recirculation Loop Rupture_; SV 3%, 10 Min Ramp Tim~~

MCS0SA, Condensate Pump A Trip MCS0SB, Condensate Pump B Trip MCS0SC, Condensate Pump C Trip When the crew attempts a manual start of HPCI; verify TRG 7 and the following malfunction activates:

HPC03, HPCI Turbine Trip - 1 Min Delay Time If directed to investigate trip of HPCI, wait 3 minutes and report HPCI Aux Oil Pump is damaged.

If directed to close HV-2-10-70A and B, wait 3 minutes and insert TRG 8 an~

verify the following remotes activate:

RHR02A, LPCI Line A Stay Full Valve HV-70A - CLOSE RHR028, LPCI Line A Stay Full Valv~ HV-70B - CLOSE Repot completion to the Control Room.

HPCI Fails to Autostart Verify the following malfunction is inserted:

HPC01, Failure of HPCI to Autostart If directed to investigate failure of HPCI to start, wait 3 minutes and report that there is damage to the Aux Oil Pump.

1 The scenario may be terminated when reactpr pressure and level are under control following the Slowdown.

5

SHIFT TURNOVER PLANT CONDITIONS:

A Unit 2 startup is in progress at approximately 4% Reactor power.

INOPERABLE EQUIPMENT/LCOs:

None SCHEDULED EVOLUTIONS:

Continue the Reactor startup in accordance with GP-2-2.

Secure the Mechanical Vacuum Pump per GP-2-2, Step 6.2.q1.

SURVEILLANCES DUE THIS SHIFT:

None ACTIVE CLEARANCES:

None GENERAL INFORMATION:

When the Crew assumes the shift, secure the Mechanical Vacuum Pump. Continue GP-2-2 at step 6.2.62 with Control Rod withdrawal until 2 Byp 1ass Valves are open.

Control Rod withdrawal begins at Sequence Step 12 Rod Array 7, control rod 18-19, to achieve 2 bypass valves open. A Reactivity Briefing was a:lready completed and you are ready to begin withdrawing rods.

6

CRITICAL TASK LIST

1.

Close the MSIVs prior to exceeding 450psig Reactor Pressure.

a. Given the plant experiencing lowering reactor pressure due to an EHC failure, the crew will manually isolate MSIVs before pressure exceeds 450 psig in accordance with T-101, RPV Control. Failure to do so will result in the plant exceeding the tech spec cooldown rate limit and potentially damaging the RPV.

2.

Inhibit ADS before an automatic depressurization occurs.

a. Given the plant experiencing a lowering RPV water level with a failure of high pressure injection, the crew will inhibit ADS prior to ADS initiation in accordance with T-101, RPV Control. Failure to do so will result in an uncontrolled depressurization and potential damage to the RPV and Primary Containment.

3.

Perform an Emergency Slowdown when RPV water level cannot be restored and maintained above -172".

a. Given the pant experiencing a loss of adequate core cooling, the crew will perform an Emergency Slowdown when RPV water level cannot be restored and maintained above -172" in accordance with T-101, RPV Control and T-112, RPV Slowdown. Failure to do so will result in damage to fuel cladding.

7

Operator Actions Op Test No.:

1 Event

Description:

Cause:

N/A Effects:

N/A I

.1 ES-D-2 Scenario 1 No.:

Event No.: 1 Secure the Mechanical Vacuum Pump per SO 8.1.A-2, Off-Gas System Startup for Normal Operations.

Time Position Applicant's Actions or Behavior i

CRS Direct the PRO to secure the Mechanical Vacuum Pump per GP-2, Reactor Startup, and SO 8.1.A-2, Off-Gas System Startup for Normal Operations.

PRO Verifies the Off-Gas Recombiner and SJAEs are in service.

Places the control switch for the Mechanical Vacuum pump in STOP.

Directs EO to close HS-2-08E-2205A(B)(C), Condenser 2A(B)(C)

Off-Gas to Mechanical Vacuum Pump Pp 20P009.

Reports to CRS that the Mechanical Vacuum Pump has been secured.

8

Operator Actions Op Test No.:

1 Event

Description:

Cause:

N/A Effects:

NIA Time Position CRS Scenario 1 No.:

Event No.: 2 1

Power ascension with control rods Applicant's Actions or Behavior

'I Direct the URO to commence rod withdrawal in accordance with the Startup REMA and the Startup Se~uence beginning with Rod*

I Sequence step 12 Rod Array 7, Contrd>I Rod 18-19 to achieve 2 I

bypass valves open.

URO Commence rod withdrawal beginning '(Vith Rod group 8, Rod 10-t~.

PRO Withdraw control rods by selecting the: rod on the matrix and then I using the Single Notch Withdrawal switch to withdraw control rods.

Monitor nuclear instrumentation and reactor power during control' rod withdrawal.

I Monitor balance of plant conditions during rod withdrawal.

I Peer check Control rod movement as directed by the CRS.

I NOTE: the scenario will continue whe~ the Lead Examiner is satisfied with the reactivity manipulatio:n.

I 9

Op Test No.:

1 Operator Actions Scenario No.:

1 Event No.:

3 Event

Description:

Control Rod 34-47 Drift Cause:

Effects:

TS Failed Exhaust Line Solenoid Valve Control Rod will drift into the core Position URO Applicant's Actions or Behavior Identify rod 34-47 drifting into the core.

Recognize by reporting the "Rod Drift" Alarm (211 D-4)

Enter and execute ON-121, Control Rod Drift Notify the CRS Fully insert Control Rod 34-47 using the Emergency Rod In switch.

Hold the Emergency Rod In Switch in the IN position for 30 seconds Recognize the control rod settled at position 00.

Resets the Control Rod Drift alarm CRS Enter and execute ON-121, Control Rod Drift Directs RO to fully insert Control Rod 34-47 Notify the Reactor Engineering PRO Determines T.S. 3.1.3, condition C applies and the HCU must be disarmed within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Dispatches EO to investigate HCU 34-47.

Provide Peer checks as directed by the CRS ES-D,-2

Op Test No.:

1 Operator Actions Scenario No.:

1 ES-D.:2 Event No.:

4 Event

Description:

Failed Drywell Pressure Instrument Cause:

Effects:

Time Gross failure of the A Drywell Pressure Transmitter

1. Half Scram/Half Group II and Ill isolations Position URO Applicant's Actions or Behavior 1

Recognize by reporting the "High Drywell Pressure" scram alarm and A 1*

RPS half scram.

Identifies and reports drywell pressure is normal.

Reports annunciator 210 D-4, RPIS/PCIS Trip Units in Calibration or Gross Failure alarm is in.

Performs ARC 210 D-4.

PRO Performs ARC 210 D-4.

TS CRS Dispatches EO to investigate drywell pressure transmitters.

Identifies that T.S. 3.3.1.1 Condition A applies and the channel must be placed in TRIP within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

11

Operator Actions Op Test No.:

1 Scenario 1 No.:

Event No.: 5 Event

Description:

Spurious start of A Core spray Cause:

Effects:

Short in the control circuit for the A Core Spray pump breaker Start of the A Core Spray pump.

Time Position Applicant's Actions or Behavior PRO Recognize and Report alarms TS CRS PRO 223 A-5, "SYSTEM I CORE SPRAY TEST/ ARMED".

223 A-1, "A CORE SPRAY PUMP AUTO START".

Enter and execute ARCs 223 A-5, "SYSTEM I CORE SPRAY TEST/ ARMED".

223 A-1, "A CORE SPRAY PUMP AUTO START".

Direct the PRO to secure the A Core Spray pump Evaluate Tech Specs 3.5.1, "ECCS Operating" 3.5.1.A, determine, that the "A" Core Spray loop must be returned to operable within i days.

When directed, secure the A Core Spray pump by placing pump switch to off and letting spring return to normal.

12

Operator Actions Op Test No.:

1 Scenario No.:

1 Event No.: 6 Event

Description:

Pressure Regulator Failure Cause:

Effects:

Time Main Steam Line pressure transmitter fails high Control Valves begin to open Reactor pressure lowers Position URO Applicant's Actions or Behavior Recognize by reporting lowering reactor pressure Enter and execute OT-111, Reactor Low Pressure.

Reports reactor pressure is approaching 880psig.

CRS Direct crew to manually scram the reactor using GP-4 Enter and execute T-101, RPV Control per OP-PB-101-111-1001 "Strategies for Successful Transient Mitigation".

URO Perform URO scram actions per RRC 94.1-2, "Reactor Operator Scram Actions" Depresses the Scram Pushbuttons Place the mode switch to SHUTDOWN.

Verify control rods are inserting.

Verify APRMs are downscale.

Establish and maintain RPV level control with feedwater.

Verify all control rods are inserted.

Verify scram discharge volume vents and drains are closed.

Verify RPV pressure, trend, and status of EHC.

Notify health physics of changing plant conditions.

13 I

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Operator Actions ES-D-'2 Op Test No.:

Event

==

Description:==

1 Scenario No.: 1 Event No. 6 Pressure Regulator Failure Cont.

PRO Per RRC 94.2-2, PRO Scram Actions:.

Verify Group II and Ill isolations and SGTS initiation (if RPV level < 1 inch)

Verify hydrogen water chemistry is isolated.

Verify both recirc pumps speed are at minimum Monitor instrument air header pressure and drywell pressure.:

When the CRS is ready, report scram actions.

CRS Direct RPV level restored and maintained between +5 and +35 inches.

Direct restoration of drywell instrument nitrogen IAW GP-8.E "Primary Containment Isolation Bypass" (if RPV level < 1 inch).

Acknowledges report of HPCI failing to start.

Directs maintaining RPV water level with HPCI and RCIC.

URO Recognizes and reports loss of condensate and feedwater.

Recognizes HPCI failure to start on low water level. (Event 8)

Manually initiates HPCI to restore RPV water level.

PRO Bypass and restore drywell instrument nitrogen IAW RRC 94.2-2 (if RPV level < 1 inch).

URO/PRO Reports RPV pressure continuing to lower CRS Directs closure of the MS IVs and transferring pressure control to the SRVs.

CT URO/PRO Closes the MSIVs and controls reactor pressure with SRVs CRS Directs RPV level control be transferred to RCIC.

URO Manually initiates RCIC and injects to maintain RPV water level.

14

I Operator Actions Op Test 1

Scenario 1 No.:

Event No.: 7 i No.:

Event

Description:

Recirc Water Leak Cause:

Effects:

Unisolable rupture in the A Recirc line Lowering RPV water level and rising Drywell pressure Time Position t.pplicant's Actions or Behavior URO/PRO CRS PRO Crew URO CRS CT PRO CRS I

I Recognize and report rising drywell prrssure.

l Enters and executes OT-101, High Drywe~I Pressure, ~nd T-102, Prima Containment Control

' I

! i Directs maximizing Drywell Cooling Starts all Drywell Chill Water Pumps and cthillers.

I Contacts EO to determine DWCW Retum 1Header pressure.

I I

Recognizes and updates drywell pressure: exceeding 2 psig I

Recognizes that HPCI has failed to start and reports to the CRS. (Event

8)

~

Recognizes lowering RPV water level and! reports to the CRS.

Directs bypassing ADS Places the ADS Keylock switches in Bypass i

Determines that RPV water level cannot b~ maintained above -172?

Directs starting Core Spray and RHR pum;ps i

URO/PRO Starts RHR and Core Spray pumps as dir~cted.

CRS Enters T-112, RPV Slowdown Verifies Torus Level is above 7 feet Directs opening all ADS valves 15 I

I

. I Operator Actions ES-D-2 Op Test No.:

1 Scenario 1 No.:

Event No.: 7 Event

Description:

Recirc Water Leak Cont.

Time Position Applicant's Actions or Behavior URO/PRO Opens all ADS valves CRS Direct RPV water level be restored and maintained at +5 to +35" with RHR and/or Core Spray I

URO When pressure lowers below the shutoff head of the ECCS pump$,

injects to restore and maintain RPV water level in the normal band.

16

Operator Actions Op Test No.:

1 Scenario 1 No.:

Event

Description:

Failure of HPCI to Start Cause:

Effects:

Failure of HPCI Aux Oil Pump HPCI will not start Event No.: 8 Time Position Applicant's Actions or Behavior ES-D~2 I

URO/PRO Recognizes HPCI failure to start on low RPV water level and high drywell pressure.

Attempts a manual start of HPCI.

Recognizes that manual start of HPCI failed.

Reports failure of HPCI to CRS.

CRS Acknowledges failure of HPCI to start.

TERMINATION CRITERIA:

The scenario may be terminated when the RPV is depressurizing and RPV water level is being restored to the normal band.

17

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SIMULATOR OPERATOR INSTRUCTIONS FOR 2021 NRC SCENARIO #2 GENERAL REQUIREMENTS Recorders will be rolled prior to the scenario and paper from selected recorders will be retained for the examination team as requested.

All procedures, flow charts, curves, graphs, etc. will be in their normal storage places.

All markable procedures, boards, etc. will be erased.

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I All paper used by the crew will be retained for the examination team as requested.

I The simulator operators will keep a log of all communications during 1 the scenario as requested by*

the examination team.

SCENARIO SOURCE HISTORY This scenario is modified scenario written for the 2021 NRC exam.

INITIAL SETUP Initial Conditions IC-14 100% Power Ensure recorder power is on; roll recorders as required Ensure annunciator horns are active Blocking Tags 2B EHC Pump Event Triggers ET6, ZGI02A4S1==1 (Mode Switch in Shutdown) 1

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Malfunctions INSERTED PCI01V, RWCU INBD ISO Valve M0-12-15 Failure PCI01W, RWCU OTBD ISO Valve M0-12-18 Failure TRG 1 CRH03A, CRD Hydraulic Pump Trip TRG2 MTA02B, Main Turbine Bearing B High Vibration - Initial SV 10%, Final SV50%, 20 Min Ramp TRG3 MSS0BC, Reactor Pressure Relief Valve C Failure-SV 100%

TRG5 TBW01 A, TBCCW Pump A Trip TBW01 B, TBCCW Pump B Trip TRG 6 RWC06, RWCU.Inlet Piping Rupture - SV 30%, 20 Min Ramp Remote Functions None Overrides INSERTED ZGI03A2S52, RWCU Bottom HD ORN Viv M0-12 OPEN ZGI03A2S54, CU INBD Inlet lsol Viv M0-12 OPEN ZGI03A2S47, CU OTBD Inlet lsol Viv M0-12 OPEN TRG 1 ANO205RF3, A CRD Pump Suction Lo Pressure-ALARM_ON TRG4 ZGI04A8S04, (E-4 DG QUICK START pushbutton) - ON, 5 Sec Delete Time Trip Overrides None Expert Command None Turnover Procedures SO 28B.1.A, Cooling Tower Startup for Normal Operation 2

EVENT 1 EVENT 2 EVENT 3 I -

SIMULATOR OPERATOR DIRECTIONS Placing a Cooling Tower in Service Support the crew as necessary to place a cooling tower:in service.

2A CRD Pump Suction Pressure Trip Wnen directed by the Lead Examiner, activate TRG 1 arid verify the following activates:

CRH03A, CRD Hydraulic Pump Trip ANO205RF3, A CRD Pump Suction Lo Pressure-ALARM_ON If directed to investigate trip of the A CRD pump, wait 2 minutes and report no apparent signs of why the pump tripped.

If directed by bypass the suction filter per ON-107, Loss! of CRD Regulating Function, wait 3 minutes and report completion.

I When directed to perform pre-start checks for the B CRD pump, wait 2 minutes and report pre-start checks completed satisfactory.

When directed to open the B CRD Pump discharge valve, modify the following remote:

I CRH02, CRD Pump B Discharge Check Valve HV OPEN

' I High Vibrations on Main Turbine When directed by the Lead Examiner initiate pending events on TRG 2 and verify the following malfunction activates:

1 MTA02B, Main Turbine Bearing B High Vibration - Initial SV 10%, Final SV50%, 20 Min Ramp If directed to walk down the Lube Oil system for possible issues, wait 15 minutes I

and report no indications of failure.

When reactor power has been reduced by 10%, modify :malfunction MTS02B to hold the current severity level.

3

EVENT 4 Spurious opening of 'C' ADS valve At the direction of the Lead examiner initiate pending events on TRG 3 and verify the following malfunction activates:

MSS08C, Reactor Pressure Relief Valve C Failure - SV 100%

Support crew as necessary to place torus cooling in service. When contacted as the EO to close HV-2-10-?0A and B. Wait 3 minutes and enter the following remote functions RHR02A CLOSE RHR028 CLOSE Report that HV-2-10-?0A and Bare closed.

If directed to remove or re-install the control power fuse for the C SRV, wait 3 minutes and modify the following malfunction and report (by phone call) completion to the Control Room:

ADS02C, C SRV Cntl Pwr Fuse-REMOVE/INTALL When Pam Pressure is reduced by use of the 885psig button, delete malfunction MSS08C.

4

EVENT 5 EVENT 6 EVENT 7 SIMULATOR OPERATOR DIRECTIONS E4 Diesel Generator Spurious Start

After the Tech Spec determination has been made and when directed by the Lead Examiner, initiate pending events on TRG 4 and verify the following Override activates:

ZGI04A8S04, (E-4 DG QUICK START pushbutton)- ON, 5 Sec Delete Time i

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1 I

If asked to perform a running inspection on the E4 Dies.~! Generator, wait

I approximately 5 minutes and report that the E4 diesel is running but that there is a large fuel oil leak spraying onto the exhaust manifold.

If after 3 minutes the crew has not secured the diesel, call again and report that the,

exhaust manifold is starting to smoke.

If directed to trip the fuel racks for the E-4 Diesel Generator, wait approximately 1 minute, insert the following Remote and Override and report that the fuel racks are tripped:

DGA01 D, Diesel Local Trip Reset Switch - TRIP ANO226DD5, E4 Diesel Gen Not Reset - ALARM_ON Loss of TBCCW After the Tech Spec determination has been made and :when directed by the Lead Examiner, insert TRG 5 and verify the following malfunctions activate:

TBW01A, TBCCW Pump A Trip TBW01 B, TBCCW Pump B Trip If directed to investigate trip of the TBCCW pumps, wait 3 minutes and report the A TBCCW pump tripped on overcurrent and there is no apparent reason the B TBCCW pump failed to start.

If directed to investigate alarms on the lsophase bus, wait 1 minute and report alarms are due to loss of cooling.

If directed to verify the RB-TB Swap-over has occurred, 1 wait 3 minutes and report the swapover is verified complete.

Loss of the #2 Bus When directed by the Lead Evaluator, load the following Batch File:

2_BUS_FAULT 5

EVENT 8 Cleanup Area Steam Leak When the Mode Switch is taken to Shutdown, verify TRG 6 activates and the following malfunction activates:

RWC06, RWCU Inlet Piping Rupture - SV 30%, 20 Min Ramp If directed as the Fire Brigade to investigate fire alarm, acknowledge as the fire brigade, then wait 1 minute and report that there is steam in the Reactor Building.

TERMINATION The scenario may be terminated when an RPV Slowdown is in progress and plant parameters are being controlled.

6

PLANT CONDITIONS:

Unit 2 is at 97% power INOPERABLE EQUIPMENT/LCOs:

SHIFT TURNOVER 28 EHC pump is blocked OOS for micron filter replacement SCHEDULED EVOLUTIONS:

Perform SO 288.1.A, Cooling Tower Startup for Normal Operation~ for the A Cooling Tower, in :

preparation for summer operations; starting at step 4.11.

SURVEILLANCES DUE THIS SHIFT:

None ACTIVE CLEARANCES:

28 EHC pump GENERAL INFORMATION:

I I

24 Hour soak on the cooling tower was completed during its initial 'run.

Pump tripped and has been repaired.

7 A Cooling Tower Lift

CRITICAL TASK LIST

1. Scram the reactor or restore charging header pressure above 940psig within 20 minutes of charging header pressure lowering below 940 psig and 2 or mor~ accumulator alarms come in.

a. Given the plant at power with a loss of charging header pressure, the crew will either restart a Control Rod Drive pump or scram the reactor with'in 20 minutes of charging header pressure lowering below 940psig with 2 or more accumulator alarms in accordance with ON-107, Loss of CRD Regulating Functio*h. Failure to do so will result !

in inadequate pressure to fully insert all control rods in the event of a scram and lead to :

fuel damage due to uneven power distribution.

2. Perform an RPV Slowdown when the second Reactor Building area temperature exceeds an Action Level.

a. Given the plant shutdown with an unisolable steam leak into the Secondary Containment and 2 areas above the Maximum Safe Value,, the crew will perform an RPV Slowdown in accordance with T-103, Secondary Containment Control. Failure to do so will result in increased heat load and loss of the Secondary Containment.

8

I Operator Actions ES-D-2 1

I I Op Test No.:

1 Event

Description:

Cause:

N/A Effects:

N/A Position CRS Scenario No.:

2 Starting the A Cooling Tower Event No.:

Applicant's Actions or Behavior 1

Direct PRO to start the A Cooling Tower Lift Pump and Fans per SO 288.1.A.

PRO Performs SO 288.1.A, Cooling Tower Startup for Normal Operations Places the A Cooling Tower Lift Pump control switch to START Call EO to perform inspections of the A Cooling Tower Places the A Cooling Tower Fans control switch to START.

Verifies all 11 Cooling Tower fans have started.

URO Monitor plant parameters/assist as directed.

9 i i' i I I'

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Op Test No.:

1 Operator Actions Scenario No.:

2 ES-D-2 Event No.:

2 Event

Description:

2A CRD Pump Trip Cause:

Effects:

Time Clogged suction strainer 2A CRD pump trips Position URO Applicant's Actions or Behavior Reports annunciators for a trip of the 2A CRD pump and low suction pressure.

CRS Updates and enters ON-107, Loss of CRD Regulating Function Directs URO to bypass the suction filter to the CRD pumps Directs URO to start the B CRD pump per SO 3.1.B, Control Rod Drive Hydraulic System Startup with the System Filled and Vented.

URO Directs EO to bypass the CRD Suction Filter.

Performs SO 3.1.B, Control Rod Drive Hydraulic System Startup with the System Filled and Vented URO Reports annunciators for a trip of the 2A CRD pump and low suction pressure.

CRS Updates and enters ON-107, Loss of CRD Regulating Function Directs URO to bypass the suction filter to the CRD pumps Directs URO to start the B CRD pump per SO 3.1.B, Control Rod Drive Hydraulic System Startup with the System Filled and Vented.

URO Directs EO to bypass the CRD Suction Filter.

CT CRS Performs SO 3.1.B, Control Rod Drive Hydraulic System Startup with the System Filled and Vented Direct URO to place 2B CRD pump in service in accordance with SO 3.1.B-2, "Control Rod Drive Hydraulic System Startup with the System Filled and Vented"

Op Test No.:

1 Event

Description:

URO URO Operator Actions ES-D-2*

Scenario No.:

2 2A CRD Pump Trip Cont.

Event No.:

Perform SO 3.1.B-2(3), "Control Rod Drive Hydraulic System Startup with the System Filled and Vented"

_ i

ReviewSO Contact EO to perform starting checks (step 4.1) for the 2B CRD pump Verify CRD flow valve controller in "MAN.UAL" AND AO-2-3-19A(B),

"GROHS Flow Control Valve" is closed I Verify MO-2-3-20, "Drive Water Pressure" is fully open Verify the Reactor recirc pump seal purg$ is isolated by verifying closed MO-2-2A-8029A AND MO-2-2A-8029B, "Seal Purge"

~tart the 2B CRD Pump Direct the EO to slowly open HV-2-3-368 for the 2B CRD Pump With the CRD flow valve controller in mahual, adjust AO-2-3-19A(B)

to obtain 55 to 65 gpm CRD System flow: OR as required when maintaining Reactor water level WHEN the flow is stabilized, THEN adju~t the CRD flow controller to a null deviation AND transfer to "AUTO" ;

Throttle MO-2-3-20, "Drive Water Pressure" to obtain 260 to 280 psid as read on DPl-303 Check that cooling water header dp is 25 1 to 30 psid as read on DPl-304 Check the CRD flow control valve AO-2-3-19A(B) holds system flow at the setpoint without permitting the chafging water pressure to exceed 1500 psig on Pl-302 Check that drive water flow is zero gpm as read on Fl-305 Check that cooling water flow is 55 to 65 1gpm on Fl-306 I

Restore Reactor recirc pumps seal purg~ in accordance with SO 2A.1.C-2, "Operation of the Recirculation: Pump Seal Purge System o

Direct EO to perform steps 4.1.1 through 4.1. 7 of SO 2A.1.C-2, "Operation of the Recirculation Pump Seal I

Purge System o

Open MO-2-8029A "Seal Pur~e Supply Valve" o

Direct EO to finish section 4.1 i and then continue on step 4.2.1 through 4.2. 7 o

Open MO-2-8029B "Seal Purge Supply Valve" Notify CRS that the 2B CRD pump has been:placed in service.

I 11

Op Test No.:

1 Operator Actions Scenario No.:

2 ES-D-2 '

Event No.:

3 Event

Description:

High Main Turbine Vibrations Cause:

Effects:

Failure of the #2 main turbine bearing Alarm 205 A-2 "Turbine Vibration!Thrust High" Position PRO/URO Applicant's Actions or Behavior Recognize by reporting the "Turbine Vibration!Thrust High" alarm.

Enter and execute ARC 205 A-2.

Report vibration of the Main Turbine B bearing is rising CRS Enter and execute ARC 205 A-2.

Direct the URO to begin lowering Reactor Power in accordance with GP-1 9 "Fast Reactor Power Reduction" URO Begin power reduction in accordance with GP'-9 "Fast Reactor Power Reduction" Lower Recirc Flow to power directed by CRS or to the Recirc Flow limit Use 'A' and B ASD 30 RPM lower buttons in order to continue lowering power with the 'A' recirc pump CRS Assign PRO critical parameter of Main Turbine Vibrations of the B bearing PRO Report out Main Turbine Vibrations as necessary.

Dispatches EO to walk down the Lube Oil system for indications of failure.

12

Op Test No.:

1 Scenario 2 No.:

Event No.:

4 Event

Description:

Spurious ADS safety relief valve opening Cause:

Effects:

Time Faulty wiring ADS valve 'C' spuriously opens causing Torus temperatu~e to rise.

Position Applicant's Actions or Behavior URO/PRO Recognize by reporting alarm 210 D-2 "Safety Relief Valve Open" Recognize the Stuck open SRV as a symptom for entry into OT-114 "Inadvertent opening of a relief valve".

Confirm valve is open by SRV position indication Bypass Valve closure Steam flow - Feed flow mismatch Alarm 227 8-4 "Slowdown Relief valves Hi Temp Rising Torus temperature CRS Enter and execute OT-114 "Inadvertent ope~ing of a relief valve" Direct PRO to place both loops of Torus Co~ling in service Direct PRO to OPEN and CLOSE SRV using the SRV control switch PRO Place both loops of Torus Cooling in service.:

Place 'C' SRV control switch to OPEN and t~en to CLOSE Directs EO to remove the control power fuse for the C SRV.

Recognizes the C SRV is still open.

Directs EO to re-install the control power fuse for the C SRV.

URO Performs GP-9 to lower Recirc flow to the Flow Limit Lowers Pam Pressure using the 885 PSIG button.

Report that the 'C' SRV has closed TS CRS Acknowledge the closure of the 'C' SRV Reference Technical Specifications 3.4.3 and 3.5.1 Declare '.C' SRV inoperable as an ADS valve and enter Tech Spec 3.5.1 condition E 1

Restore ADS valve to operable in 14 ~ays 13

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Op Test No.:

1 Operator Actions Scenario No.:

2 Event No.:

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ES-D-2::

Event

Description:

E4 diesel generator spurious start Cause:

Effects:

Spurious automatic start signal

1. Alarm 005 F-4 "E4 Diesel Running".

2. The diesel will continue to run until manually shutdown... it should not be left running due to accumulation of fuel oil on the exhaust manifold.

Position PRO Applicant's Actions or Behavior Acknowledge and report alarm 005 F-4 "E4 DIESEL RUNNING" and enter corresponding Alarm Response Card.

Recognize the E4 diesel is running unloade~.

Red flag the breaker for the E4 diesel.

Verify diesel automatic response using SO 52B.1.B "Diesel Generator Automatic Start".

Verify an ESW pump started.

Red-flag the ESW pump to remain in service.

Shutdown the remaining ESW pump.

Direct an Equipment Operator to perform a running inspection of the E-4 diesel generator.

I I

I I CRS Per SO 52B.1. B ( step 4. 7), direct a shutdown of the E-4 diesel generator.

IAW the applicable steps of section 4.5 of SO 52A.1.B "Diesel Generator ;

Operations".

PRO (May) direct placing the E4 diesel in Pull-to-Lock.

Shutdown the E4 diesel IAW SO 52A.1.B:

Place the E4 diesel generator control switch to "STOP".

Shutdown the running ESW pump in acc~rdance with SO 33.2.A.

Direct the Equipment Operator to continue with the E4 diesel shutdown in accordance with SO 52A.1.B, section 4.5.

Place the E4 diesel in Pull-to-Lock, as directed.

CRS Declare the E-4 diesel inoperable.

Review Tech Spec 3.8.1 and determine Condition B applies:

Verify alignmenUavailability of the Conowingo tie line immediately.

Verify breaker alignment for operable offsite circuits within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Restore the E-4 diesel generator to operable status within 14 days.

14

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Op Test No.:

1 Operator Actions Scenario No.:

2 ES-D-2 Event No.:

6 Event

Description:

Loss of TBCCW Cause:

Effects:

Time Overcurrent condition on the running pump and control switch failure on the standby pump.

Loss of cooling to cooled plant components.

Position Applicant's Actions or Behavior PRO Identifies and reports annunciators for TBCCW Pump trip Recognizes failure of the B TBCCW Pump to start Places the B TBCCW Pump control switch to START Recognizes that the B TBCCW pump failed to start Dispatches EO to investigate failure of the TBCCW pumps.

Places both TBCCW pump switches in OFF CRS Updates and enters ON-118, Loss of TBCCW Determines that Main Generator current is above 20,000 Amps Directs URO to lower generator loading using GP-9, Fast Power Reduction Directs PRO to place both TBCCW Pump switches in OFF URO Reduces recirc flow to the flow limit Inserts GP-9 rods Monitors generator -current

/

PRO Dispatches EO to investigate the lsophase bus alarms.

Dispatches EO to verify TB-RB Swap-over has occurred.

15

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Operator Actions Op Test No.:

1 Scenario 2

Event No.:

iES-D-2 I

No.:

Event

Description:

Loss of the #2 Bus Cause:

Effects:

Time Electrical Fault on the bus Loss of multiple plant components Position CREW Applicant's Actions or Behavior Recognize by reporting the loss of the #2 bus URO/PRO Recognize and report loss of 2 Condensate Pumps CRS Directs a GP-4 Shutdown CRS Direct crew to manually scram the reactor using GP-4 Enter and execute T-101, RPV Control per OP-PB-101-111-1001 "Strategi~s for Successful Transient Mitigation".

URO Perform URO scram actions per RRC 94.1-2, "Reactor Operator Scram Actions" Depresses the Scram Pushbuttons.

Place the mode switch to SHUTDOWN.

Verify control rods are inserting.

Verify APRMs are downscale.

Establish and maintain RPV level control with feedwater.

Verify all control rods are inserted.

Verify scram discharge volume vents and drains are closed.

Verify RPV pressure, trend, and status of EHC.

Notify health physics of changing plant conditions.

URO Place the mode switch to "SHUTDOWN".

Verify control rods are inserting.

I Report APRMs are NOT downscale and that an ATWS is in progress wth reactor power> 4% (T-101 entry conditio'n).

16

I I

I I I'

Op Test No.:

1 Scenario 2 No.:

Event No.:

7 i

'i Event

Description:

Loss of the 2 Bus Cont.

'I I

Time Position CRS URO Applicant's Actions or Behavior Enter and execute T-101, "RPV Control" per OP-PB-101-111-1001 "StrateQies for Successful Transient Mitigation":

I Enter and execute T-117, Level Power Control" per OP-PB-101-111-1001 1

"Strategies for Successful Transient Mitigatic;m".

i Direct the Reactor Operators to perform the A TWS RRCs.

i Perform RRC 94.3-2, "URO Actions During an A TWS with Power Above 41 I

Percent or Unknown":

Depress both Scram pushbuttons Emergency Stop RFPTs as necessary Initiate ARI Inform the CRS of Reactor power and that you are ready to inject SLC.

Inject SLC when directed

! I Verify RWCU isolates I I Verify that SLC is injecting Verify closed the SDV vent and drain valves When the CRS is ready, Report A TWS actions i

'I PRO Per RRC ~-li~.Slel~Mfl(attmrmm Actions:

[

Verify i3roht1mdlfyiGtdilliislilatidrlti mm;ffiffiISanttialaliS initiation (if RPV leve Recog111ize\\laiifveiyxll~~lJMm:EiscaiebJnistry is isolated.

[

Verify lllyd!V)@efywatarrebm01puryps ~dire at minimum Verify llotH\\.iecitorpast~irahea!latipieastlre and drywell presbure.

Manito, inM'berettteateR&mere~~seJl!Darat~tjmtassure.

I When the CRS is ready, report scram actions.

I Direct RPV level restored and maintained between +5 and +35 inches.

Direct RP\\DIEIKtl ~

~lriastlMt\\eeenitrOgem I~ m~ "P~imary C CRS Direct rest~n of drywell instrument nitrqgen IAW GP-8.E "Primary Containment Isolation Bypass" (if RPV level < 1 inch).

URO Performs £Glfil.r11>6~P>>'ide~mb1:~d159tbi:ldt6§'.' with feedwater/Condeqsate.

Control RPV level between +5" to +35" with feedwater/Condensate.

Bypass and restore drywell instrument nitrogen IAW RRC 94.2-2 (if RPV level < 1 inch) 17 I I!

1,

Op Test No.:

1 Operator Actions Scenario No.:

2 ES-D-2' Event No.:

8 Event

Description:

RWCU Area Leak Cause:

Rupture in the Inlet piping of RWCU Effects:

Rising area temperatures in the Secondary Containment Time Position Applicant's Actions or Behavior URO/PRO Recognize annunciator for high area temperatures and fire alarm

/CRS Dispatches Fire Brigade to investigate Identify RWCU area temperatures are rising CRS Updates and enters T-103, Secondary Containment Control Directs RO to attempt to isolate RWCU URO/PRO Attempts to isolate RWCU CRS URO Reports failure of RWCU to isolate Verifies the reactor has been scrammed Directs URO to depressurize the reactor to 500-600 psig Lowers EHC control pressure to 550 psig Monitors lowering pressure CRS Identifies the second area temperature is approaching the Action level Directs URO to open all bypass valves per T~101, RC/P-3.

Identifies the second area temperature has exceeded the Action level Updates and enters T-112, RPV Slowdown Verifies Torus water level is above 7' Directs RO to open all ADS valves CT URO/PRO Opens all bypass valves 18 i

I I

I

, I

'i ' I

' I

TERMINATION CRITERIA:

The scenario may be terminated when an RPV Slowdown is in progress and plant parameters are being controlled.

19

SIMULATOR OPERATOR INSTRUCTIONS FOR 2021 NRC SCENARIO #4 GENERAL REQUIREMENTS Recorders will be rolled prior to the scenario and paper from selected recorders will be retained for the examination team as requested.

All procedures, flow charts, curves, graphs, etc. will be in their normal storage places.

All markable procedures, boards, etc. will be erased.

All paper used by the Crew will be retained for the examination team as requested.

The simulator operators will keep a log of all communications during the scenario as requested by the examination team.

Establish the monitored parameters list with the Lead Examiner.

SCENARIO SOURCE HISTORY This scenario is modified for the 2021 NRC Exam.

INITIAL SETUP Initial Conditions IC-14, 100% power Lower Reactor Power to 97%

Ensure recorder power is on; roll recorders as required Ensure annunciator horns are active Print a P-1 prior to turnover Blocking Tags None Event Triggers ET8: ZGI02A6S33==1 (SBLC Control Switch in Start A)

DMF SLC01B ET9: ZGI02A6S33==3 (SBLC Control Switch in Start B)

DMF SLC01A Malfunctions INSERTED CRM034203, Control Rod (42-03) Uncoupled SLC01 A, Standby Liquid Pump A Trip SLC01 B, Standby Liquid Pump B Trip TRG2 RBW01 A, RBCCW Pump A Trip RBW01 B, RBCCW Pump B Trip 1

TRG3 RRS29A, A 3401 RPT Breaker Trip RRS29C, 8 3401 RPT Breaker Trip TRG4 CRH03A, CRD Hydraulic Pump A Trip Overrides TRG 1 ANO236RE2, RPS "8" M-G Set Trouble or in Test - ALARM_ON Remotes.

TRG5 T221_1, Remove Low PRV Level GP-1 Isolation - DEFEAT TRG6 CRH02, CRD Pump 8 Discharge Check Valve HV OPEN 1

TRG7 T214, Venting Scram Air Header - VENT Batch Files Load ATWS_JAV Batch File Expert Commands None Turnover Procedures SO 35.6.A-2, Placing Standby Reactor Building Closed Cooling Water Pump in Service ST-O-003-470-2, CRD Coupling Integrity Test 2

I i I

EVENT 1 EVENT 2 EVENT3 SIMULATOR OPERATOR DIRECTIONS Uncoupled Control Rod I

When Control Rod 42-03 is withdrawn for a cou~ling check, the Control Ro9 will fail and will be required to be recoupled.

When the control rod is being fully inserted, del~te malfunction CRM034203.:

Raise Reactor Power with Recirc When control rod 42-03 is recoupled, the URO will raise power to 100% with Recirc Support the crew as necessary.

Swap of RBCCW Pumps When directed to verify open HV-2-35-24200A, RBCCW Pump 2AP010 Suction i I

Block Valve, and HV-2-35-24203A, RBCCW Pump 2A010 Discharge Block Valve, wait 2 minutes and report both valves are open.

When directed to perform prestart checks on the 2A RBCCW pump, wait 2 minutes and report completion.

3

EVENT4 I

SIMULATOR OPERATOR DIRECTIONS Loss of trip logic to "B" RPS output breaker 1

i When directed by the Lead Evaluator, initiate pending events on TRG 1 and verify the following activates to simulate a loss of DC power to the 'B' RPS :

MG set output breaker:

AN0236RE2, RPS "B" M-G Set Trouble or in Test - ALARM_ON If directed as the Equipment Operator to report on the status of the "B" RPS output breaker, wait approximately 3 minutes an'.d report that:

I The BC757 breaker is NOT tripped in thei E-22 Room (TRIP light is ;

NOT lit).

i Any attempts to reset the alarm logic by depressing the red "RESET' pushbutton have no effect.

I DC control power from 2BD25 circuit 17 switch is ON.

DC control power from 2DD25 circuit 19 ~as a blown fuse.

(This will inop 1 of the 2 output breakers for the 'B' RPS MG set.)

NOTE: Once the CRS has determined the correct Tech Spec action, the,

Lead Examiner will inform the CRS that EngineJring has determined the 1

other (in-series) 'B' RPS MG set output breaker ~o be inoperable and to take the appropriate action (transfer the 'B' RPS bus 'to the alternate power supply).

Support the crew as the Equipment Operator foli transferring 2B RPS bus to the alternate power supply.

1 When directed to perform step 4.1.6 through 4.11.8 of SO 60F.6.A-2, report*

back that voltage on transformer 20X040 is 120 IV. No voltage adjustments were necessary.

When directed to Place all Reactor Building andi Refuel Floor Supply Fans to OFF, initiate Batch File; RB_VENT_FANS_OFF When directed to Restart Reactor Building and !Refuel Floor Supply Ventilation Fans per step 4.8 of GP-8.D, wait ap'proximately 1 minute and initiate Batch File; RB_VENT_RESTORE.

4

EVENT 5 EVENT 6 EVENT 7 I

Loss of RBCCW When directed by the Lead Evaluator, insert TRG 2 and verify the following malfunctions activate:

RBW01A, RBCCW Pump A Trip RBW01 B, RBCCW Pump B Trip I

I I

If directed to investigate trip of the 2A RBCCW Pump and failure of the 28 RBCCV\\/j pump to start, wait 3 minutes and report the 2A RBCCW Pump tripped due to overcurrent..

Trip of Both Recirculation Pumps When directed by the Lead Examiner, initiate pending events on TRG 3 and verify 1

the following malfunction activates:

RRS29A, A 3401 RPT Breaker Trip RRS29C, B 3401 RPT Breaker Trip If directed to investigate trip of both Recirc Pumps, wait 3 minutes and report trip of both 3401 ASD Breakers.

Electric A TWS Do not permit the operators to utilize the individual scram test switches on the RPS panels when performing T-213 "Scram Splenoid Deenergization."

When the applicant opens the panel, inform him/her that the individual scram switches are all in the down position.

When directed to perform T-221, Main Steam Isolation Valve Bypass, wait 5 minutes and insert TRG 5 and verify the following remote activates:

T221_1, Remove Low PRV Level GP-1 Isolation - DEFEAT When directed to perform T-214, Venting the Scram Air Header, wait for the direction from the Lead Evaluator and enter TRG 7 and verify the following remote; activates:

T214, Venting Scram Air Header-VENT If directed to perform T-213, Scram Solenoid Deenergization, acknowledge the direction and take no action.

5 I

I I I

EVENT 8 EVENT9 TERMINATION SLC Pump Trip When the first SLC pump is started, verify the malfunction on the opposite SLC pump deletes.

I If directed to investigate trip of the first SLC pump, wait 2 minutes and report pump:

breaker has tripped on overcurrent.

CRD Pump Trip When directed by the Lead Examiner, insert TRG 4 and verify the following malfunction activates:

CRH03A, CRD Hydraulic Pump A Trip When directed to open the B CRD Pump discharge valve, wait 1 minute and insert TRG 6 and verify the following remote activates:

CRH02, CRD Pump B Discharge Check Valve HV OPEN If directed to investigate trip of the 2A CRD pump, report an acrid odor coming from.

the pump.

The scenario may be terminated when the RPV is being restored to the normal band.

6

SHIFT TURNOVER PLANT CONDITIONS:

Reactor Power is approximately 97%.

Control Rod Coupling Checks are in progress. Next rods to be checked are 42-03, 18-55, 34-47, and 14-35.

RBCCW Pump B is showing signs of bearing failure INOPERABLE EQUIPMENT/LCOs:

None SCHEDULED EVOLUTIONS:

Control Rod Coupling Checks Swap of RBCCW Pumps per SO 35.6.A-2, Placing Standby Reactqr Building Closed Cooling Water Pump in Service SURVEILLANCES DUE THIS SHIFT:

ST-O-003-470-2, CRD Coupling Integrity Test ACTIVE CLEARANCES:

None GENERAL INFORMATION:

Adjust Reactor power to 100% after coupling checks are complete.

7

. I CRITICAL TASK LIST

1. Attempt to shutdown the reactor by performing one or more of the following:

a. T-213, Scram Solenoid Deenergization

b. T-214, Isolating and Venting the Scram Air Header

c. T-220, Driving Control Rods during a Failure to Scram

d. Injecting Standby Liquid before Torus Temperature exceeds 110°F

i. Given the reactor experiencing a failure to scranJ, the crew will perform auxiliary procedures to insert control rods and r~duce reactor power in

\\

accordance with T-117, ATWS RPV Control. Failure to do so will result in thermal hydraulic instabilities and damage to fuel cladding.

I I

2. Perform T-240, Termination and Prevention of Injection intQ the RPV, to minimize thermal/hydraulic instabilities (THI) until RPV water level is, below -60".

a. Given the reactor experiencing a failure to scram, the crew will lower RPV water level to below -60" in accordance with T-117, ATWS RPV Control. Failure to do so will result in thermal hydraulic instabilities and damage to fuel cladding.

8 r I I

Operator Actions ES-D 2 Op Test No.:

1 Scenario 4 No.:

Event No.:

1 Event

Description:

Uncoupled Control Rod (ON-105, "Control Rod Uncoupled")

Cause:

Effects:

Time TS Rod uncoupled during previous rod withdrawal Control rod 42-03 will withdraw past the full out position.

Position Applicant's Actions or Behavior I

' I I

URO Recognize by reporting alarm 211 E-4, Rod Overtravel, and 211 D-4, Rod Drift.

Identify that control rod 42-03 is uncoupled.

Halt all control rod motion and power changes not directed by ON 105.

Notify Shift Management.

Notify the Reactor Engineers of the uncoupled Control Rod.

CRS Enter and execute ON-105, "Control Rod Uncoupled".

Notify the Reactor Engineers of the uncoupled Control Rod.

Directs URO to perform ON-105 to recouple control rod 42-03.

URO Inserts control rod 42-03 to position 46 and withdraws to position 48 CRS Re-performs coupling check and recognizes that rod is still uncoupled. (First 2 steps are repeated 3 times)

Fully inserts control rod 42-03 and holds the control switch in "Emerg In" for 10 seconds Withdraws control rod 42-03 to position 48.

Re-performs coupling check and recognizes that control rod 42-03 is not coupled.

Fully inserts control rod 42-03.

Acknowledge that control rod 42-03 failed coupling attempts Declares rod inoperable per T.S. 3.1.3.

PRO Peer Check rod movement as directed by the CRS.

9

Op Test No.:

1 Event

Description:

Cause:

N/A Effects:

N/A.

Time Position CRS URO Operator Actions Scenario No.:

4 Event No.:

'2 I

Raise Reactor Power to 100% using Recirc Fiow.

Applicant's Actions or Behavior Direct the URO to raise Reactor Power to:100% using Recirc flow

, I ES-D-2

. I Raise Recirc Pump speed by depressing ~ither raise 10, 5, or 1 rpm on, the A(B) ASD and monitor for the followin@

Verify pushbutton backlight is lit and e'xtinguishes when button released Verify Recirc Pump speed changes Following speed change verify Recirc response Monitor Reactor Level Monitor Reactor Power Notify CRS when 100% power is reached i PRO Support power changes as necessary

Op Test No.:

1 Event

Description:

Cause:

N/A Effects:

N/A.

Time Position CRS Operator Actions ES-D 2 Scenario No.:

4 Event No.:

13 RBCCW Pump Swap Applicant's Actions or Behavior Direct PRO place the A RBCCW Pump in !service and secure the B RBCCW pump per SO 35.6.A-2.

PRO Performs SO 35.6.A-2 Directs EO to verify suction and discharge valves open for the A RBCCWpump Directs EO to perform pre-startup che9ks on the A RBCCW pump.,

Starts the A RBCCW Pump i

Places the control switch for the B RBGCW pump to OFF Directs EO to perform SO 35.8.A-2, Reactor Building Closed Coolin Water System Routine Inspection.

I

.1

. I 11

Op Test No.:

1 Operator Actions ES-D 1

2 Scena~o No.:

4 Event No.:

4 Event

Description:

Loss of DC power to the 'B' RPS MG set output breaker/ transfer RPS bus 'B' to the alternate supply Cause:

Effects:

Loss of DC power from 2DD25, circuit 19, to breaker BC757

1. Alarm: 208 E-2 "RPS 'B' M-G Set Trouble or in Test"

2. Loss of trip capability for one of the two 'B' RPS ;MG set output breakers Position URO Applicant's Actions or Behavior I

I Recognize and report alarm 208 E-2 "RPS 'B' M-G Set Trouble or in Test" and enter corresponding alarm response card.

Recognize that RPS 'B' is NOT tripped.

CRS Enter and execute ARC 208 E-2:

PRO URO TS CRS Recognize that BC757 breaker is not tripped since RPS did not trip.

I Direct an Equipment Operator dispatched to verify the status o DC control power at 2BD25, circuit: 17, and 2DD25, circuit 19..

Use the alarm response card to assisf in troubleshooting the annunciator, as directed.

Monitor plant parameters/assist as dir~cted or requested.

Reference Tech Spec 3.3.8.2 Conditio:n A to make the following determination:

With DC power and therefore trip capability lost for one of the.

two 'B' RPS MG set output breakers, the 'B' RPS MG set must be removed from service within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

NOTE: Once the CRS has determined the correct Tech Spec action, the Lead Examiner will inform the CRS that Engineering h: s determined the other (in-series) 'B' RPS MG set output breaker to be inoperable, and to take the appropriiate action (transfer the 'B' 1 RPS bus to the alternate power supply).

12

Operator Actions Op Test No.:

1 Scenario No.:

4 Event No.:

4 Event

Description:

I I

Loss of DC power to the 'B' RPS MG set output breaker/ transfer RP$

bus 'B' to the alternate supply (continued)

Time Position Applicant's Actions or Behavior CRS Direct 2B RPS power supply transferred to alternate using SO 60F.6.A-2, "Transferring Reactor Protection System Power Supplies".

PRO At the 20C017 panel verify:

"Alt. Source Available" light is on, Control Rod Drive Scram Solenoid Group 1,2,3,4 indicating lights are lit on the 20C015 panel, Place B RPS M/G Set Alt. Feed Transfer Switch to ALTERNATE position.

URO Reset the half scram using GP-11.E "Reset Reactor Protection System-Scram Reset:

CRS Place the Scram Reset switch in the Group 1 & 4 position, then in the Group 2 & 3 position.

Verify the four scram group white lights are lit on the 20C015 and 20C017 panels.

Verify the A and B Reactor Auto Scram annunciators are clear.:

(May) place SDV Inboard Valve switch 5A-S14A to OPEN position and verify the inboard SDV vents and drains are open (condition met).

Place SDV Outboard Valve switch 5A-S14B to OPEN position and verify the outboard SDV vents and drains are open.

Verify SDV not drained annunciators 210(C-1) and 210 (B-2) fqr are clear.

Recognize by reporting the High Ar;ea Temperature alarm (21 di J-3)

Enter and execute T-103, "Secondary Containment Control".

13

Operator Actions Op Test No.:

1 Scenario No.:

4 Event No.:

4 Event

Description:

Loss of DC power to the 'B' RPS MG set output breaker/ transfer RPS bus 'B' to the alternate supply (continued)

Time Position PRO Applicant's Actions or Behavior Reset the Group 1 and 3 half isolations using GP-8.D "Group 1,2,3 Outboard Half Isolation:

Verify the isolation has occurred IAW COL GP-8.D "Required '

Position" column.

o Recognize by reporting that the 'B' SBGT Fan did not start as expected (see Event 5) o Place 'B' SBGT Fan control switch to start and verify fan starts Direct an Equipment Operator to verify all Reactor Building anc;I Refuel Floor fans are tripped and to place all fan control switches to OFF.

Place control switches in COL GP-8.D to the position listed in '

the "PLACE SWITCH TO" column.

Reset Exhaust Radiation Monitors RIS-2-17-452B & D, AND RIS-2-17-458B & Don the 20C010 panel.

Place Outboard Isolation Logic Reset Switch 16A-S33 on the 20C05A panel to the "GRP 2/3" position AND verify "Group 2/3 Outboard Isolation Relays Not Reset" annunciator is clear.

Shutdown SBGT System using SO 9A.2.A "SBGT System Shutdown Following an Automatic Start."

Restore RB and Refuel Floor ventilation using SO 40B.1.A-2 "RB Ventilation System Startup and Normal Operation" PRO Direct an Equipment Operator to measure voltage at the 20X040 '

transformer per step 4.1.6 of SO 60F.6.A-2.

14

Operator Actions I

ES-D-*2 Op Test No.:

1 Scenario No.:

4 Event No.:

5 Event

Description:

Loss of RBCCW Cause:

Effects:

Time Trip of the A RBCCW Pump Rising temperatures on RBCCW cooled components Applicant's Actions or Behavior I

I I

Position PRO Recognize by reporting that the 'A' RBCCW pump has tripped.

I Attempts to start the B RBCCW Pump and recognizes pump has failed tb start.

CRS Dispatches EO to investigate trip of the A RBCCW pump Updates and enters ON-113, Loss of RBCCW Directs PRO to shut down and isolate RWCU.

Directs URO to lower power per GP-9 to control component temperatures.

PRO Secures the running RWCU Pump Closes MO-2-12-068, RWCU Outlet URO Lowers recirc flow to the flow limit Inserts control rods per the GP-9 sequence 15

. I

Operator Actions Op Test No.:

1 Scenario No.:

4 Event No.:

6 Event

Description:

Trip of Both Recirculation Pumps Cause:

Effects:

Time Bearing failure due to loss of RBCCW Loss of core circulation Position URO Applicant's Actions or Behavior Recognize by reporting loss of both Recirc Pumps Depresses Scram Pushbuttons Places Mode Switch in SHUTDOWN Reports control rods are not inserting and an electrical A TWS 16 ES-D--2

Operator Actions Op Test No.:

1 Event

Description:

Scenario No.:

4 A TWS - Electric (PRA)

ES-D-2 Event No.:

7 Cause:

Effects:

Time Scram signal is not generated Requires the crew to take actions to terminate the A TWS, as well as control RPV

, level/power Position Applicant's Actions or Behavior URO Place the mode switch to "SHUTDOWN".

PRO CRS

I Verify control rods are inserting.

I 1 Report APRMs are NOT downscale and that an ATWS is in progres~

with reactor power> 4% (T-101 entry condition).

Perform GP-4 "Manual Reactor Scram":

Transfer 13 KV house loads using RRC 53.1-2.

Enter and execute T-101, "RPV Control" per OP-PB-101-111-1001 "Strategies for Successful Transient Mitigation":

I Enter and execute T-117, Level Power Control" per OP-PB-101-111-1001 "Strategies for Successful Transient Mitigation".

Direct the Reactor Operators to perform the A TWS RR Cs.

I URO Perform RRC 94.3-2, "URO Actions During an ATWS with Power Above

4 Percent or Unknown":

Depress both Scram pushbuttons Emergency Stop RFPTs as necessary to keep RPV level beloVI(

1

+35 inches

1 Initiate ARI

. j Inform the CRS of Reactor power:and that you are ready to injelt S~.

Inject SLC when directed

[

Identifies the first SLC pump failed to start and starts the secon.

Verify that SLC is injecting Verify closed the SDV vent and drain valves When the CRS is ready, Report A TWS actions 17

I

Operator Actions Op Test No.:

1 Event

Description:

Time Position PRO CT CT CRS CT CT ES-D-2 I

Scenario No.: 4 Event No.:

7' I

I ATWS - Electric (continued) (PRA)

Applicant's Actions or Behavior

. 1 Perform RRC 94.4-2, "PRO Actions Duri~g an A TWS with Power Abovjl 4 Percent or Unknown":

Inhibit ADS Inform the CRS that ADS is inhibited and that you are ready to perform T-240-2 When directed, bypass and restore instrument nitrogen When directed, perform T-240-2, Termination and Prevention of lnjecti1 1 n into the RPV" I

I Direct the URO to inject SLC Direct the PRO to perform T-240-2, "Termination and Prevention of I

Injection into the RPV" to lower RPV level to below -60 inches.

I Direct the PRO to establish a RPV level band of -70 to -130 inches.

Direct the PRO to bypass and restore instrument nitrogen.

Direct the URO to stabilize RPV pressure below 1050 using bypass valves.

Direct the URO to insert control rods usin'.g:

T-213, "De-energize scram solenoids".

T-214 "Vent Scram Air Header

T-220, "Driving Control Rods during Failure to Scram".

Direct the Third RO or an Equipment Operator to perform T-221, "Main' Steam Isolation Valve Bypass".

18

I I

I Operator Actions Op Test No.:

1 Scenario 4 No.:

Event No.: 7, I

ES-D~2 I

Event

Description:

ATWS - Electric (continued) (PRA)

Time Position URO I I Applicant's Actions or Behavior

! I Direct an Equipment Operator to perform T-214 "Vent Scram Air Heade(.

Drive Control Rods using T-220 "Driving Control Rods During Failure T~

Scram".

[

Raise CRD drive water pressure by either placing the flow controller in manual and opening AO-2-3-19A, "Control Rod Driye Hydraulic Flow Control" or directing an Equipment Operator to ' J close HV-2-3-56, "Charging Wtr Hor Blk Vv to Hydraulic Control 1 Units" 1

Bypass the Rod Worth Minimizer ~

Fully insert control rods I

Ii I

i URO/PRO Recognize and report entry into T-102 "Primary Containment Control" due to high Torus temperature of 95 degr 1ees F and/or Torus level high; 14.9 feet (depending on whether or not SRVs are lifting).

CRS Enter and execute T-102:

Ensure Torus cooling has been maximized.

19

Operator Actions Op Test No.:

1 Event

Description:

Time Position CT PRO ES-D 2 Scenario 4 No.:

Event No.:

7 ATWS (Electric) (continued) (PRA)

Applicant's Actions or Behavior Perform T-240, "Termination and Prevention of Injection into the RPV";I control RPV level below -60 inches and within the specific RPV level I band directed by the CRS.

o Place HPCI Aux Oil Pump in the Pull-to-Lock" position.

0 0

0 Press "Emergency Stop" for all reactor feed pumps.

Close reactor feed pump discharge valves MO-2149A, B, C.

Verify closed MO-8090 "C RFP Discharge Bypass".

I i

When RPV level is below -60 inches, restore injection and maintain RR level between -60 and -195 inches as follows:

1 Using Feedwater:

o Place LIC-8091 in "MAN" and close the valve.

o Open MO-8090 "C RFP Bypass".

o Raise RFP speed until discharge pressure is75-100 psig above RPV pressure.

I o

Control RPV injection by adjusting RFPT speed, OR LIC8091.

setting, OR MO-2149C "RFP C Discharge" valve position.

Verify PCIS Group II and Ill isolations and SBGT initiation.

When directed bypass and restore Drywell Instrument Nitrogen.

Place AO-2969A control switch to "CLOSE".

Place AO-2969B control switch to "CLOSE".

Place Drywell Instrument Nitrogen BY:pass Swi,tch 16A-S100 in thej "BYPASS" position.

I Place Drywell Instrument Nitrogen Bypass Switch 16A-S99 in the j

"BYPASS" position.

20

Operator Actions Op Test No.:

1 Event

Description:

Time CT CT Position CRS Scenario 4 No.:

Event No.: 7 Reactor scram/ ATWS (continued) (PRA)

Applicant's Actjons or Behavior ES-1

, 1

'i NOTE: Torus temperature is NOT expected to reach 110 degrees F during this scenario.

IF Torus temperature reach~s 11 O degrees F, direct the crew to perform T-240 using Attachment 1, Figure 1, if no SRVs are open; 1

OR Attachment 1, Figure 2, if any SRY is open.

If not already done, direct initiation of SBLC at or before Torus temperature reaches 110 degrees F I

CT URO/PRO Perform T-240 again, if directed.

i I

, I Terminate and prevent injection using T-240, Attachment 1, Figure 2 Restore RPV injection when a_ny of the following are reached:

o RPV level reaches -17,2 inches, or o

Reactor power drops below 4%, or o

All SRVs remain closed.

Control level as directed by the CRS to prevent level from lowering below

-226 inches (2/3 core coverage).

21

Operator Actions Op Test No.:

1 Scenario No.:

4 Event No.:

8 Event

Description:

Standby Liquid Pump Trip Cause:

Effects:

Overcurrent condition on the pump breaker SLC Pump trip.

Position Applicant's Actions or Behavior URO Recognize failure of the SLC pump to start.

Starts the opposite SLC pump and verifies injection.

Dispatches EO to investigate trip of the first SLC pump.

Reports to CRS failure of the first SLC Pump.

CRS Acknowledge report 22 ES-D-2

Operator Actions ES-D 2 Op Test No.:

1 Scenario No.:

4 Event No.:

9 Event

Description:

CRD Pump Trip Time Position Applicant's Actions or Behavior URO Recognizes and reports loss of drive water flow and trip of the A CRD :

Pump CRS Updates and enters ON-107, Loss of CRD Regulating Function.

Directs URO to start the B CRD Pump URO Performs ON-107 to start the B CRD Pump Directs EO to investigate trip of the A CRD Pump Starts the B CRD Pump Directs EO to open the B CRD Pump discharge valve Resumes control rod insertion.

TERMINATION CRITERIA:

The scenario may be terminated when the RPV water level is being restored to the normal band.

23

v t e Letter Sequence Draft Other
EPID:L-2021-OLL-0002, (Open)
Initiation Acceptance... Administration Questions Answers Results Approval... Other: ML21237A514, ML21237A518, ML21237A524, ML21348A054, ML21348A065
MONTHYEAR2021-05-18 [Table View]

ML21237A478

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