ML21144A268

SRO Admin JPM

ML21144A268
Person / Time
Site:	Clinton
Issue date:	04/13/2021
From:	Gregory Roach Operations Branch III
To:	NRC/RGN-III/DRS/OLB
Roach G
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ML20136A302	List: ML21144A234 ML21144A237 ML21144A238 ML21144A240 ML21144A244 ML21144A247 ML21144A250 ML21144A254 ML21144A258 ML21144A264 ML21144A268 ML21144A273
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TQ-AA-150-J020 Revision 01 Page 1 of 14 Job Performance Measure Review a Completed SRV Actuation Report JPM Number: JPM444 Revision Number: 04 Date: 8/19/2020 Developed By: Bill Kiser / 8/19/20 Instructor: Print / Sign Date Reviewed By: /

SME or Instructor: Print / Sign Date Reviewed By: /

Operations Representative: Print / Sign Date Approved By: /

Training Department: Print / Sign Date SRRS: 3D.105 (when utilized for operator initial or continuing training)

TQ-AA-150-J020 Revision 01 Page 2 of 14 JPM444 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation.

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

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

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

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

4. Initial setup conditions are identified.

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

6. Task standards identified and verified by instructor or SME review.

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

8. IAW NUREG 1021 Appendix C, clearly identify the task standard (i.e., the predetermined qualitative or quantitative outcome) against which task performance will be measured.

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

Procedure: CPS 3831.01 Revision: 6d Procedure: CPS 3831.01D002 Revision: 6 Procedure: CPS 9056.02 Revision: 29c Procedure: CPS 9056.02C001 Revision: 28

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

11. Verify performance time is accurate.

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

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

/

SME / Instructor (Print/Sign) Date

/

SME / Instructor (Print/Sign) Date

/

SME / Instructor (Print/Sign) Date SRRS: 3D.100; There are no retention requirements for this section

TQ-AA-150-J020 Revision 01 Page 3 of 14 JPM444 Revision Record (Summary)

Revision # Summary 00 New JPM number (old 3831.0102) 01 2/22/11 - Updated for procedure revisions.

02 8/25/15 - Updated to new JPM template.

03 11/6/17 - Updated to new JPM template. Updated procedure references.

04 8/19/20 - Updated to new JPM template. Updated procedure references.

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

TQ-AA-150-J020 Revision 01 Page 4 of 14 JPM444 SETUP INSTRUCTIONS

1. No setup is required for this JPM.

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

TQ-AA-150-J020 Revision 01 Page 5 of 14 JPM444 INITIAL CONDITIONS CPS 9056.02, Safety/Relief Valve Actuation Test was completed during steady state operations at approximately 80% power.

CPS 3831.01, Safety Relief Valve Report has been completed.

INITIATING CUE As the CRS, you are to review CPS 3831.01, Safety Relief Valve Report. If the report can NOT be approved, then correct or note any deficiencies found.

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

Information For Evaluators Use:

UNSAT requires written comments on respective step.

• Denotes critical steps.

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

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

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

The timeclock starts when the candidate acknowledges the initiating cue.

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

TQ-AA-150-J020 Revision 01 Page 6 of 14 JPM444 JPM Start Time: JPM Sequence #: of Task Standard:

The examinee will review a completed SRV Actuation Report and identify errors on CPS 3831.01D002 Actuation Log blocks 305, 306 and 309.

Comment STEP ELEMENT STANDARD SAT UNSAT Number CUE Provide the examinee with the following marked up procedures and attached diagrams:

• Initiating Cue (last page of JPM)

• JPM Attachments 1-4 (pages 10 - 13) o SRV Tailpipe Temperature Graph o IRM/APRM PPC Screenshot o SPDS Summary Display PPC Screenshot o SPDS RPV, PRI-CNMT and H2 PPC Screenshot

• CPS 9056.02 Safety/Relief Valve Actuation Test

• CPS 9056.02C001 Safety/Relief Valve Manual Actuation Checklist

• CPS 3831.01 Safety Relief Valve Report

• CPS 3831.01D002 Actuation Log NOTE: JPM steps 1 - 5 can be performed in any order.

• 01 Reviews blocks 302 - 305 of Examinee determines that the CPS 3831.01D002 Actuation type of actuation recorded in Log. block 305 is incorrectly entered ___

as A and should be B.

CUE If the examinee reports the error, cue him/her to complete the review of the report.

If the examinee asks for a copy of CPS 4009.01 Inadvertent Opening Safety Relief Valve, inform him/her that the off-normal procedure is being completed by another operator.

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

TQ-AA-150-J020 Revision 01 Page 7 of 14 JPM444 Comment STEP ELEMENT STANDARD SAT UNSAT Number

• 02 Reviews block 306 of CPS Examinee determines that the 3831.01D002 Actuation Log. cause/reason for actuation recorded in block 306 is ___

incorrectly entered as E and should be C.

CUE If the examinee reports the error, cue him/her to complete the review of the report.

• 03 Reviews blocks 307 - 309 of Examinee determines that the CPS 3831.01D002 Actuation time for tailpipe temperature to Log. return to normal recorded in block 309 is incorrectly entered ___

as 95 min (tailpipe temperature has not yet returned to normal).

04 Reviews blocks 310 - 314 of Examinee determines that block CPS 3831.01D002 Actuation 314 is correctly entered as Log. N/A (based on the fact that the SRV passed the acceptance criteria of CPS 9056.02) and could be annotated as A and/or E (based on seat leakage).

05 Reviews blocks 315 - 316 of Examinee determines that block CPS 3831.01D002 Actuation 316 is incorrectly entered as Log. No and should be annotated as Yes Note 1 (or equivalent).

CUE JPM is complete.

JPM Stop Time:

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

TQ-AA-150-J020 Revision 01 Page 8 of 14 JPM444 JPM

SUMMARY

Operators Name: Emp. ID#:

Job

Title:

EO RO SRO FS STA/IA SRO Cert JPM

Title:

Review a Completed SRV Actuation Report JPM Number: JPM444 Revision Number: 04 Task Number and

Title:

383101.01, Complete Control Room actions to document data on failures and actuations of the Safety Relief Valves in the Main Steam System and to generate reports required by the Nuclear Regulatory Commission.

Task Standard: The examinee will review a completed SRV Actuation Report and identify errors on CPS 3831.01D002 Actuation Log blocks 305, 306 and 309.

K/A Number and Importance:

K/A System K/A Number Importance (RO/SRO)

Generic 2.1.18 3.6 3.8 Suggested Testing Environment: Classroom Alternate Path: Yes No SRO Only: Yes No Time Critical: Yes No Reference(s):

Procedure: CPS 3831.01 Revision: 6d CPS 3831.01D002 Revision: 6 CPS 9056.02 Revision: 29c CPS 9056.02C001 Revision: 28 Actual Testing Environment: Simulator Control Room In-Plant Other Testing Method: Simulate Perform Estimated Time to Complete: 20 minutes Actual Time Used: minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily? Yes No The operators performance was evaluated against standards contained within this JPM and has been determined to be: Satisfactory Unsatisfactory SRRS: 3D.105 (when utilized for operator initial or continuing training)

TQ-AA-150-J020 Revision 01 Page 9 of 14 JPM444 NOTE: Enter finalized grading, comments, and notes relevant to this evaluation in the associated TQ-AA-150-F03A/B. (See AR 4282419).

Evaluators Name (Print):

Evaluators Signature: Date:

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

TQ-AA-150-J020 Revision 01 Page 10 of 14 JPM444 Attachment 1: SRV Tailpipe Temperature Graph SRV 47A Tailpipe Temperature (°F) 400 350 SRV 47A Tailpipe Temperature (°F) 300 250 200 150 100 50 0

0:00 0:28 0:57 1:26 1:55 2:24 2:52 3:21 3:50 4:19 4:48 Time (hr:min)

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

TQ-AA-150-J020 Revision 01 Page 11 of 14 JPM444 Attachment 2: IRM/APRM PPC Screenshot SRRS: 3D.100; There are no retention requirements for this section

TQ-AA-150-J020 Revision 01 Page 12 of 14 JPM444 Attachment 3: SPDS Summary Display PPC Screenshot SRRS: 3D.100; There are no retention requirements for this section

TQ-AA-150-J020 Revision 01 Page 13 of 14 JPM444 Attachment 4: SPDS RPV, PRI-CNMT and H2 PPC Screenshot SRRS: 3D.100; There are no retention requirements for this section

TQ-AA-150-J020 Revision 01 Page 14 of 14 JPM444 INITIAL CONDITIONS CPS 9056.02, Safety/Relief Valve Actuation Test was completed during steady state operations at approximately 80% power.

CPS 3831.01, Safety Relief Valve Report has been completed.

INITIATING CUE As the CRS, you are to review CPS 3831.01, Safety Relief Valve Report. If the report can NOT be approved, then correct or note any deficiencies found.

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

CPS 3831.01 SAFETY RELIEF VALVE REPORT SCOPE OF REVISION:

• EDITORIAL: Procedure references and title updates.

Specific Rev. 6a [Baker]: EDITORIAL - IR 554876, updated appendix A failure reports from Nuclear Plant Reliability Data System (NPRDS) to the current Equipment Performance and Information Exchange System (EPIX).

Specific Rev. 6b [Leffel]: EDITORIAL - IR 2390620 corrected a typo in the step referenced in the NOTE prior to step 8.2.

Specific Rev. 6c [J. Delaney]: EDITORIAL - IR 2530316 Removed references to ITS 5.6.4 which has been deleted from Tech. Specs.

Specific Rev. 6d [J. Delaney]: Mngt Request - Removed references to reporting SRV challenges per LS-AA-2003 (superseded by PI-AA-2003) - Safety Eval for License Amendment 165 states that reporting challenges to SRVs to the NRC is FOR TRAINING adequately addressed by reporting requirements in 10 CFR 50.73. Corrected typo -

no rev marks used.

ONLY REFERENCE USE ORIGINATOR: Thomas J. Landin CLASS CODE: NNNN SQR: N/A APPROVAL DATE: 04/02/04 CURRENT CHANGES TO GENERAL REVISION Change # Date List of Affected Pages 6a 09/16/10 1, 5 6b 10/21/14 1, 3 6c 03/14/17 1, 2, 4 6d 01/09/19 1-4 Rev. 6d Page 1 of 5

CPS 3831.01 1.0 PURPOSE Document data on failures and actuations of the Safety Relief Valves (SRV's) in the Main Steam System and to generate reports required by the Nuclear Regulatory Commission (NRC).

2.0 DISCUSSION/DEFINITIONS 2.1 SRV actuations shall be reported to the NRC by the means of 10CFR50.73, Licensee Event Report System.

CPS 3831.01D002, Actuation Log shall be initiated when a SRV lifts, either manually or automatically.

An SRV failing to lift when required shall be considered and reported as an actuation event.

2.2 Each actuation shall be recorded by type according to the following letter codes from Appendix A.

A - Type A shall include all automatic actuation's which result from non-operator initiated energization of the A or B solenoid.

B - Type B shall be remote manual actuation's.

This shall include all personnel initiated actuation's resulting in the energization of the A or B solenoid.

C - Type C shall be an actuation resulting from the pressure within the Reactor Pressure Vessel (RPV) exceeding the spring tension of the SRV.

2.3 Each actuation shall be further classified by the cause or reason for the actuation according to the following letter code from Appendix A.

A - Reason or Cause A shall be an actuation which is the result of pressure within the RPV exceeding the (electrical or spring) setpoint.

B - Reason or Cause B shall be an automatic or manual initiation of Automatic Depressurization System (ADS).

C - Reason or Cause C shall be an actuation which results from the proper performance of an approved and authorized Surveillance or Test procedure.

D - Reason or Cause D shall be an actuation of an SRV outside of the normal controls of actuation instruments, logic circuits, or procedures.

E - Reason or Cause E shall be a manual actuation for relief of pressure within the RPV.

Rev. 6d Page 2 of 5

CPS 3831.01 3.0 RESPONSIBILITY 3.1 Operations Department Head is the responsible for the proper implementation of this procedure.

3.2 Plant Engineering is responsible for review and preparation of Plant Report.

4.0 PRECAUTIONS - None 5.0 PREREQUISITES Notify SMngt prior to logging a new actuation event or failure.

6.0 LIMITATIONS 6.1 SRV actuations shall be reported to the NRC by the means of 10CFR50.73, Licensee Event Report System.

7.0 MATERIALS/TEST EQUIPMENT - None 8.0 PROCEDURE NOTE Up to five actuation events may be recorded on each log sheet. Refer to Appendix A for applicable codes when completing blocks 305, 306, 307 and 314 on activation log.

8.1 (Record) Fill in blocks 302, 303, 304, 305, 306, 307, 308, 309, 310, and 311 of the CPS 3831.01D002, Actuation Log.

NOTE If information for 8.2 becomes available after the report has been submitted, report information with a duplicate log entry and a CPS 3831.01F001, Comment Sheet indicating the availability of this new information.

8.2 (Record) Fill in blocks 312, 313, 314 and 315 of the CPS 3831.01D002 ACTUATION LOG, if available at the time of reporting or enter "not available" when completing the log. Additional data may be entered later for cross reference.

Rev. 6d Page 3 of 5

CPS 3831.01 8.0 PROCEDURE (cont'd)

NOTE Date and time on CPS 3831.01F001, Comment Sheet shall match those of the associated actuation event log entry.

8.3 (Record)

If CPS 3831.01F001, Comment Sheet is completed for this log entry, indicate "YES" in block 316.

If a comment sheet was not completed, indicate "NO" in block 316.

8.4 Operations transmit the original log sheets and associated comment sheets to Records Management Group (RMG) and a copy to Plant Engineering for their plant report preparation.

9.0 ACCEPTANCE CRITERIA - None 10.0 FINAL CONDITIONS - None

11.0 REFERENCES

11.1 10CFR50.73, Licensee Event Reporting System 12.0 APPENDICES A. ACTUATION EVENTS CODES 13.0 DOCUMENTS CPS 3831.01F001, Comment Sheet CPS 3831.01D002, Actuation Log Rev. 6d Page 4 of 5

CPS 3831.01 APPENDIX A ACTUATION EVENTS CODES NOTE For each actuation event, select the appropriate code corresponding to the block number on CPS 3831.01D002, Actuation Log.

BLOCK # DESCRIPTION CODES (Select One) 305 Type of Actuation A. Automatic B. Remote Manual C. Spring 306 Cause/Reason for A. Overpressure Actuation B. ADS C. Test D. Inadvertent (Accidental, Spurious)

E. Manual Relief 307 Reactor Operating C. Routine Startup Condition Prior D. Routine Shutdown to Lift E. Steady State Operation (LER Codes) F. Load Changes During Routine Operation G. Shutdown (Hot or Cold) Except Refueling H. Refueling 314 Failure-Reports (Select as Many as Applicable)

A. Failure of any Part of Valve Assembly -

SRV Report Required B. No Failures Occurred C. LER Submitted -

Give LER Number in Block # 315 D. Equipment Performance and Information Exchange System (EPIX) will Be Submitted E. Failure Rev. 6d Page 5 of 5

CPS No. 3831.01D002 ACTUATION LOG SCOPE OF REVISION:

• Updated format.

FOR TRAINING ONLY ROUTINE USE ORIGINATOR: Brant Chambers CLASS CODE: NNNN1 APPROVAL SEP 28 1998 DATE:

CHANGE NO. DATE PAGES Rev. No. 6 Page No. 1 of 2

CPS No. 3831.01D002 Rev. No. 6 Page No. 2 of 2

CPS No. 3831.01D002 Plant Docket No. 50-461 ACTUATION LOG NOTE Includes all IN-SERVICE tests.

Equipment Identification 302. B21-F047A Number (EIN) 303. Date of Actuation (MM/DD/YY) XX/XX/XX 304. Time of Day (24 Hour Clock) XX:XX Type of Actuation 305. A (Code - Appendix A)

Cause/Reason for Actuation 306. E (Code - Appendix A)

Rx Operating Condition 307. Prior to Lift E (Code - Appendix A)

Rx Power Level Prior to Lift 308. 82

(% Rated Thermal)

Time for Tailpipe Temperature 309. 95 min to Return to Normal Other Instrumentation - Number 310.

Reading and Units N/A 311. Rx Pressure Prior to Actuation 1013 IF AVAILABLE/IF APPLICABLE (See Step 8.1.2 and accompanying NOTE.)

Reseat Pressure at Valve 312.

Closure (PSIG) 1013 Duration of this Actuation 313. ~ 1 min (Minutes: Seconds)

Failure, Reports 314.

(Code - Appendix A)

N/A 315. LER Number (5 Digit Number) N/A Comment Sheet Regarding This No 316. Actuation Attached?(Yes or No)

Completed By Rocky Operator XX/XX/XX Signature Date REVIEW AND APPROVAL Shift Supervision Signature Date Rev. No. 6 Page No. 3 of 2

CPS 9056.02 SAFETY/RELIEF VALVE ACTUATION TEST SCOPE OF REVISION:

• Incorporated PDRs 99-0528 and 99-0987.

Specific Rev. 29a [Landin]: Editorial - 1.0 updated to reflect ITS amendment for Method 1 or Method 2 SRV testing allowances. Supports C1R08.

Specific Rev. 29b [Landin]: EDITORIAL -

C1R10: 24 Month ITS Surveillance Project update.

EDITORIAL Rev. 29c [Helton]: IR 4049579 Frequency statement change for STI-17-018 to staggered.

FOR TRAINING ONLY CONTINUOUS USE ORIGINATOR: A. E. Schultz CLASS CODE: SNNI SQR: N/A APPROVAL DATE: SEP 20, 1999 CURRENT CHANGES TO GENERAL REVISION Change # Date List of Affected Pages 29a 02/20/02 1, 2 29b 08/31/05 1, 2 29c 03/12/18 1, 2, 11 Rev. 29c Page 1 of 11

CPS 9056.02 1.0 PURPOSE Provide instructions for performing ITS Method 1 Safety/Relief Valve (SRV) Actuation Test, including the Automatic Depressurization System (ADS) Valves.

Can use ITS Method 2 instead to satisfy ITS/ISI per CPS 9061.11C022, SRV Open/Close Test Using A And B Solenoids And Slow Closure Rig.

This procedure fully satisfies:

ITS SR 3.4.4.2: SRV Relief Function Actuation ITS SR 3.4.4.3: SRV Manual Actuation ITS SR 3.5.1.6: ADS Automatic Actuation ITS SR 3.5.1.7: ADS Manual Actuation ITS SR 3.6.1.6.1: LLS valve manual actuation This procedure partial satisfies:

ITS SR 3.3.5.1.5 T4.a-h: ECCS LSF ADS 1 (A&E) functions ITS SR 3.3.5.1.5 T5.a-g: ECCS LSF ADS 2 (B&F) functions ITS SR 3.6.1.6.2: LLS System automatic actuation (Overlaps with ITS SR 3.3.6.5.4: Relief and LLS LSF)

This procedure partial satisfies:

ISI SRV Position Indication [2 years]

2.0 DISCUSSION/DEFINITIONS 2.1 Discussion 2.1.1 Frequency <<LBD-1>>

1. Normal Frequency - 24 months staggered.

(STI - CL-17-018)

2. Other Trigger - CPS 3002.01, Heatup & Pressurization.

2.1.2 In this procedure the Safety/Relief valves are operated from the remote keylock switches located in the MCR.

The switches on panel 1H13-P601 operate solenoid A, the switches on panel 1H13-P642 operate solenoid B.

2.1.3 This test is performed with the Reactor critical at less than 90% Reactor power. It may be accomplished with or Rev. 29c Page 2 of 11

CPS 9056.02 without the turbine operating. The preferred method is with Bypass valves and not with Control valves.

Rev. 29c Page 3 of 11

CPS 9056.02 2.0 DISCUSSION/DEFINITIONS (contd) 2.1.4 The order in which the Safety/Relief valves are opened allows for maximum distance between discharge points to reduce the possibility of localized overheating of the Suppression Pool.

2.1.5 Portions of this surveillance may be performed independently for post maintenance testing to facilitate inspections due to repairs, etc.

2.1.6 This surveillance may be performed in MODE 1 or MODE 2.

MODE 1 is preferred. If this test is performed in MODE 2, special consideration shall be given to reducing reactor steam loads as necessary to achieve sufficient bypass valve opening with reactor power 12%.

2.2 Definitions Reactor steam pressure adequate to perform this test -

in the band of 950 to 1045 psig [ITS LCO 3.4.12]. <<CM-1>>

3.0 RESPONSIBILITY Operations Department Head is responsible for proper implementation of this procedure.

4.0 PRECAUTIONS 4.1 Continuously monitor RPV water level, RPV pressure, Drywell Pressure, and Containment Pressure while performing this surveillance.

4.2 Evacuate the Containment Building while testing Safety/Relief valves.

4.3 Monitor Containment Building radiation levels frequently throughout the procedure.

Rev. 29c Page 4 of 11

CPS 9056.02 5.0 PREREQUISITES 5.1 In conjunction with the Shift Manager/Control Room Supervisor (SM/CRS), review the following impact statements to determine required plant status to perform this test:

ITS/ORM Impacted:

ITS LCO 3.3.6.5: Relief and Low-Low Set Instrumentation ITS LCO 3.4.4: Safety/Relief Valves (SRVs)

ITS LCO 3.5.1: ECCS-Operating ITS LCO 3.6.2.1: Suppression Pool Average Temperature ITS LCO 3.6.2.2: Suppression Pool Water Level RPS Trip: N/A CRVICS Isolation:

CCP Exhaust Hi Rad Monitors, 1RIX-PR042A,B,C,D may cause CCP Isolation if monitor alarms are initiated.

Logic Type: N/A, manual cycling of SRVs Minimum Operable Channels:

One relief valve pressure actuation channel and/or one acoustic monitor channel and/or one low-low set channel may be placed in an inoperable status for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for the purpose of performing surveillance testing in accordance with ITS LCO 3.3.6.5 Surveillance NOTE.

Plant/System Conditions Required To Conduct This Test:

Reactor power 90%; MODE 1 or 2 with RPV at rated pressure Other Systems Affected:

Suppression Pool RHR - Suppression Pool Cooling Mode Main Steam RCIC and HPCS suctions may transfer if suppression pool high level signal comes in Other Channels Required Operable To Prevent Inadvertent Actuation: N/A 5.2 (Initial) Obtain SM/CRS permission to perform this surveillance.

Initialing also indicates that the IMPACT MATRIX in 5.1 has been discussed with the SM/CRS.

5.3 (Initial) As required to maintain temperature within applicable limits ITS SR 3.6.2.1.1, initiate Suppression Pool cooling per CPS 3312.01, Residual Heat Removal (RHR).

Rev. 29c Page 5 of 11

CPS 9056.02 5.0 PREREQUISITES (contd) 5.4 Adjust Suppression Pool level (low end of acceptable band) as required. (Observe limitation 6.5) 5.5 (Initial) Initiate CPS 9000.05, Suppression Pool Temperature Log.

5.6 (Initial) Sound Containment evacuation alarm, evacuate Containment, and have Security secure access.

5.7 (Initial) Place CCP in Filter Mode per CPS 3408.01, Containment Building/Drywell HVAC (VR, VQ).

5.8 (Initial) Notify Transmission Electric System Coordinator of anticipated load changes if the turbine is on line.

5.9 (Initial) Initiate SRV Actuation Log per CPS 3831.01, Safety Relief Valve Report.

Annunciator 5066-5B, Automatic Depressurization System Or Safety Relief Valve Leaking is to be expected during the first SRV lift, and will remain in until the SRV lines cool down.

5.10 (Initial) Operators in direct communications as required between Acoustic Monitoring PNL and MCR horseshoe (sound powered headphones recommended).

5.11 (Initial) Reactor Power 90%.

5.12 (Initial)

N/A IF performing this procedure in MODE 2, THEN Remove reactor steam loads as necessary to maximize turbine bypass valve opening with reactor power 12%.

Rev. 29c Page 6 of 11

CPS 9056.02 6.0 LIMITATIONS 6.l Allow adequate time between relief valve blow downs to prevent Suppression Pool temperature from reaching l05°F.

6.2 Monitor the relief valve temperature recorder to ensure the valve has properly seated.

If temperature does not return to within l0°F of the original value within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, or does not return to original value within one shift, then a leaking SRV is indicated.

No specific action other than initiating an AR is required.

Cycling a leaking SRV in order to seat it has resulted in increased leakage at other plants.

6.3 If plant parameters indicate a relief valve has stuck open, then refer to CPS 4009.0l, Inadvertent Opening Of Safety/Relief Valve.

6.4 Per ITS SR 3.6.2.1.1, suppression pool water temperature must be monitored at least once per five minutes during testing which adds heat to the Suppression Pool.

6.5 Maintain the following Suppression Pool conditions:

Temperature < 103.7°F, and Level 18 11 and 19 5.

a) Stop all safety/relief valve testing if suppression pool temperature > 103.7°F.

b) Document suppression pool temperature per CPS 9000.05, Suppression Pool Temperature Log.

6.6 During performance of this test, the SRVs shall not be operated outside the normal use range (950 to 1045 psig).

<<CM-1>>

7.0 MATERIALS AND/OR TEST EQUIPMENT - None Rev. 29c Page 7 of 11

CPS 9056.02 8.0 PROCEDURE NOTE Section 8.1 provides the test sequence for all valves listed on the checklist beginning with 1B21-F047A.

8.l Manually Testing ADS/SRV Valves 8.1.1 (Initial) Adjust Pressure Regulator set point and/or Reactor Power to establish Reactor Pressure 950 to 1045 psig, AND: <<CM-1>>

N/A a) IF test is performed with the turbine off-line, THEN Fully open at least two bypass valves to prevent pressure surge during relief valve operation, OR b) Verify turbine on-line with PRESS AMPL IN CONTROL light ON.

8.l.2 (Record) Log Main Turbine Bypass or Control Valve position as applicable.

8.1.3 (Record) Log Steam line flows for A, B, C, D steam lines from DCS computer points 1C34-DA003, 4, 5, 6 respectively.

8.1.4 Monitor the following parameters during SRV testing:

a) Reactor water level b) Reactor pressure c) Suppression pool temperature (local rise) d) Stabilization of generator loads (when on-line) 8.1.5 (Initial) Turn the key lock switch on 1H13-P601 for the selected SRV valve to the OPEN position.

Rev. 29c Page 8 of 11

CPS 9056.02 8.l Manually Testing ADS/SRV Valves (contd) 8.1.6 (Initial) Verify the following responses: <<LBD-1>>

a) SRV MONITORING SYSTEM TROUBLE annunciator 5067-8L.

b) Bypass Valve or Control Valve actuated in close direction.

c) Steam flow increases in corresponding steam line, as shown on DCS.

d) Verify open indication for solenoid A for selected SRV at 1H13-P601.

8.1.7 (Initial) Turn the keylock switch on 1H13-P642 for the selected SRV valve to the OPEN position.

8.1.8 (Initial) Turn the keylock switch on 1H13-P601 for the selected SRV valve to the AUTO position.

8.1.9 (Initial) Verify the following responses: <<LBD-1>>

a) SRV MONITOR SYSTEM TROUBLE remains in alarm.

b) Bypass Valve or Control Valve did not change from step 8.1.6.b.

c) Steam flow did not change from step 8.1.6.c.

d) Verify open indication for solenoid B for selected SRV at 1H13-P642.

e) Verify closed indication for solenoid A for selected SRV at 1H13-P601.

8.1.10 (Initial) Turn the keylock switch on 1H13-P642 for the selected SRV valve to the AUTO position.

8.1.11 (Initial) Verify the following responses: <<LBD-1>>

a) SRV MONITOR SYSTEM TROUBLE annunciator 5067-8L alarm clears.

b) Bypass valve or Control valve returned to approximately the same position recorded in step 8.1.2.

c) Steam flow returns to approximately same values recorded in step 8.1.3.

d) Verify closed indication for solenoid A & B for selected SRV.

Rev. 29c Page 9 of 11

CPS 9056.02 8.1.12 Manually test the remaining desired Safety/Relief, ADS Valves per steps 8.1.2 through 8.1.11.

Rev. 29c Page 10 of 11

CPS 9056.02 8.2 Test Recovery 8.2.1 (Initial) As applicable, when airborne radioactivity has returned to normal levels, return CCP to Normal Operations per CPS 3408.01, Containment Building/Drywell HVAC (VR, VQ).

8.2.2 (Initial) Adjust pressure regulator set point and/or reactor power to desired value for given plant conditions.

8.2.3 (Initial)

IF Reactor steam loads were removed in N/A step 5.12 of this procedure, THEN Return reactor steam loads per the appropriate system operating procedure.

NOTE Steps 8.2.4-6 may be performed in any order and/or concurrently.

8.2.4 Notify Security to restore CNMT access with RP concurrence.

8.2.5 When desired, secure RHR Suppression Pool Cooling Mode (if running) per CPS 3312.01 (RHR).

8.2.6 Notify Transmission Electric System Coordinator that the test is complete.

Rev. 29c Page 11 of 11

CPS 9056.02 8.3 System Restoration 8.3.1 (Initial) Verify the following SRV/ADS keylock switches are in AUTO on 1H13-P601 and 1H13-P642.

a) 1B21-F047A i) 1B21-F051G b) 1B21-F047B j) 1B21-F051B c) 1B21-F047F k) 1B21-F047D d) 1B21-F047C l) 1B21-F051C e) 1B21-F041A m) 1B21-F041F f) 1B21-F041B n) 1B21-F041L g) 1B21-F041G o) 1B21-F041C h) 1B21-F041D p) 1B21-F051D 8.3.2 (Record) Notify the SM/CRS when the test is completed by initials, time, and date.

9.0 ACCEPTANCE CRITERIA 9.1 Operability Requirements Failure to meet the Acceptance Criteria shall constitute a failure to comply with the applicable LCO. ITS should be immediately reviewed to identify Action Statements needed for implementation. Refer to Supplemental Review Sheet for applicable LCOs.

Each Safety/Relief and ADS Valve actuates open by energizing its solenoids from the MCR, and verifying Bypass Valve or control valve response, or change in corresponding measured steam flows.

9.2 Other Requirement Each Safety/Relief and ADS Valve A&B solenoid indications correspond correctly to Bypass/Control Valve, steam flow, acoustic tail-pipe monitor alarm responses, and applicable annunciator alarms.

Inform SM/CRS if solenoid indications do not correspond correctly.

10.0 FINAL CONDITIONS Rev. 29c Page 12 of 11

CPS 9056.02 All Safety/Relief and ADS valves shut, and the associated key lock switches in AUTO.

Rev. 29c Page 13 of 11

CPS 9056.02

11.0 REFERENCES

11.1 Licensing Bases Documents LBD-1: <<2.1.1, 8.1.6, 8.1.9, 8.1.11>>

11.1.1 ITS SR 3.3.5.1.5 T4.a-h: ECCS LSF ADS 1 (A&E) functions 11.1.2 ITS SR 3.3.5.1.5 T5.a-g: ECCS LSF ADS 2 (B&F) functions 11.1.3 ITS LCO 3.3.6.5: Relief and Low-Low Set Instrumentation 11.1.4 ITS SR 3.4.4.2: SRV Relief Function Actuation 11.1.5 ITS SR 3.4.4.3: SRV Manual Actuation 11.1.6 ITS LCO 3.4.12: Reactor Steam Dome Pressure 11.1.7 ITS SR 3.5.1.6: ADS Automatic Actuation 11.1.8 ITS SR 3.5.1.7: ADS Manual Actuation 11.1.9 ITS SR 3.6.1.6.1: LLS valve manual actuation 11.1.10 ITS SR 3.6.1.6.2: LLS System automatic actuation 11.1.11 USAR 3.1.2.4.8.1, 6.3.4.2.2 11.2 CPS Procedures 11.2.1 CPS 3002.01, Heatup And Pressurization 11.2.2 CPS 3101.01, Main Steam (MS, IS & ADS) 11.2.3 CPS 3l05.04, Steam Bypass And Pressure Regulation (SB) 11.2.4 CPS 3312.01, Residual Heat Removal (RHR) 11.2.5 CPS 3408.01, Containment Building/Drywell HVAC (VR, VQ) 11.2.6 CPS 3831.01, Safety Relief Valve Report 11.2.7 CPS 4009.01, Inadvertent Opening Of Safety/Relief Valve 11.2.8 CPS 9000.05, Suppression Pool Temperature Log 11.3 CALC IP-0-0071 11.4 CM-1: K280l-0088: DIKKERS SRV Manual, part A, Section 5, GE DTF: JK-1396 dated 3-3-87 <<2.2, 6.6, 8.1.1>>

11.5 STI Change Request Number - CL-17-018 12.0 APPENDICES - None 13.0 DOCUMENTS CPS 9056.02C00l, Safety/Relief Valve Manual Actuation Checklist Rev. 29c Page 14 of 11

CPS No. 9056.02C001 SAFETY/RELIEF VALVE MANUAL ACTUATION CHECKLIST SCOPE OF REVISION:

• Enhanced formatting.

• Changes incorporated as a result of CCF#s 98-2260, 98-1673, and 98-455 that were incorporated into parent procedure 9056.02 rev. 28.

ITR:

FOR TRAINING ONLY CONTINUOUS USE ORIGINATOR: A.E. Shultz CLASS CODE: SNNI1 APPROVAL MAR 16 1999 DATE:

CHANGE NO. DATE PAGES Rev. No. 28 Page No. 1 of 5

CPS No. 9056.02C001 Rev. No. 28 Page No. 2 of 5

CPS No. 9056.02C001 SAFETY/RELIEF VALVE MANUAL ACTUATION CHECKLIST INITIALS 5.2 Shift Manager/Control Room Supervisor (SM/CRS) permission and Impact Matrix Assessed.

WD / DK SM/CRS Test Performer Date/Time XX/XX/XX / XX:XX WDK 5.3 Suppression Pool Cooling is in service. _______

WDK 5.5 Suppression Pool Temperature Log initiated. WDK 5.6 Containment Building evacuated of all personnel and Containment Evacuation alarm sounded.

Access secured by Security. _______

WDK 5.7 CCP in filtered mode. _______

WDK 5.8 Notify Transmission Electric System Coordinator of Load changes during test if turbine is on line. _______

WDK 5.9 SRV Actuation Log initiated. _______

WDK 5.10 Operators in direct communications. _______

WDK 5.11 Reactor Power level 90%. _______

WDK 5.12 Remove reactor steam loads as necessary to maximize turbine bypass valve opening with reactor power < 12%. N/A (Required for MODE 2 testing only).

PROCEDURE VERIFICATION 8.1.1 Adjust pressure regulator or reactor power until reactor pressure 950 to 1045 psig AND, _______

WDK a) IF test is performed with the turbine off-line, THEN 2 bypass valves are fully open N/A OR Rev. No. 28 Page No. 3 of 5

CPS No. 9056.02C001 b) Turbine on-line with PRESS AMPL IN CONTROL light ON. WDK Rev. No. 28 Page No. 4 of 5

CPS No. 9056.02C001 8.1.2 8.1.3 8.1.5 8.1.6 8.1.7 8.1.8 8.1.9 8.1.10 8.1.11 Step (record) (record) Remarks Valve** Steam Flow P601 Verify P642 P601 Verify P642 Verify H/S OPEN H/S H/S OPEN H/S CLOSED Position A B C D OPEN Rspns OPEN AUTO Rspns AUTO Rspns B21-F047A* 85 2.9 3.0 3.0 2.9 WDK WDK WDK WDK WDK WDK WDK B21-F047B N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A B21-F047F N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A B21-F047C* N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A B21-F041A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A B21-F041B* N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A B21-F041G N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A B21-F041D* N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A B21-F051G* N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A B21-F051B N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A B21-F047D N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A B21-F051C N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A B21-F041F* N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A B21-F041L N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A B21-F041C* N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A B21-F051D N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A

• Designates ADS valve

• • Bypass or Control Valve position H/S Designates Hand Switch Rev. No. 28 Page No. 5 of 5

CPS No. 9056.02C001 8.2 TEST RECOVERY INITIALS 8.2.1 CCP in Normal Operation WDK 8.2.2 Pressure Regulator Set Point and/or Reactor Power adjusted to desired position. WD DK I /

8.2.3 IF reactor steam loads were removed in step 5.12 of this procedure, THEN Verify reactor steam loads returned per the appropriate system operating procedure. _______

N/A 8.3 SYSTEM RESTORATION

8.3.1 Verify the following SRV/ADS keylock switches are in AUTO on H13-P601 and H13-P642.

P601 P642 a) B21-F047A IWD/DK IWD/DK b) B21-F047B IWD/DK IWD/DK c) B21-F047F IWD/DK IWD/DK d) B21-F047C IWD/DK IWD/DK e) B21-F041A IWD/DK IWD/DK f) B21-F041B IWD/DK IWD/DK g) B21-F041G IWD/DK IWD/DK h) B21-F041D IWD/DK IWD/DK i) B21-F051G IWD/DK IWD/DK j) B21-F051B IWD/DK IWD/DK k) B21-F047D IWD/DK IWD/DK l) B21-F051C IWD/DK IWD/DK m) B21-F041F IWD/DK IWD/DK n) B21-F041L IWD/DK I WD/DK o) B21-F041C IWD/DK IWD/DK p) B21-F051D IWD/DK I WD/DK 8.4 SM/CRS notified test is complete.

Time ________

XX:XX Date ________

XX/XX/XXXX _______

WDK Rev. No. 28 Page No. 6 of 5

CPS No. 9056.02C001 SAFETY/RELIEF VALVE MANUAL ACTUATION CHECKLIST SUPPLEMENTAL REVIEW SHEET CORRECTIVE ACTION TAKEN 9.1 ACCEPTANCE CRITERIA ITS LCOs: 3.3.5.1 3.3.6.5 3.4.4 3.5.1 3.6.1.6 ORM ORs: None ODCM ORs: None As applicable:

Initiated Condition Report __________

(yes/no)

Initiated Action Request (AR) No. __________________

9.2 ACCEPTANCE CRITERIA As applicable:

Initiated Condition Report __________

(yes/no)

Initiated Action Request (AR) No. __________________

COMMENTS/DEFICIENCIES REVIEW AND APPROVAL Cognizant Plant Engineer ____________________________________________

(ISI Pump & Valve) (Signature) (Date)

Surveillance Coordinator ____________________________________________

(Signature) (Date)

Rev. No. 28 Page No. 7 of 5

TQ-AA-150-J020 Revision 01 Page 1 of 11 Job Performance Measure Failed SRM During Refuel JPM Number: JPM434 Revision Number: 00 Date: 8/19/2020 Developed By: Bill Kiser / 8/19/20 Instructor: Print / Sign Date Reviewed By: /

SME or Instructor: Print / Sign Date Reviewed By: /

Operations Representative: Print / Sign Date Approved By: /

Training Department: Print / Sign Date SRRS: 3D.105 (when utilized for operator initial or continuing training)

TQ-AA-150-J020 Revision 01 Page 2 of 11 JPM434 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation.

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

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

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

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

4. Initial setup conditions are identified.

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

6. Task standards identified and verified by instructor or SME review.

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

8. IAW NUREG 1021 Appendix C, clearly identify the task standard (i.e., the predetermined qualitative or quantitative outcome) against which task performance will be measured.

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

Procedure: CPS 9000.01D002 Revision: 39 Procedure: CPS 9000.03 Revision: 27c Procedure: ITS 3.3.1.2 Amend: 188 Procedure: Revision:

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

11. Verify performance time is accurate.

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

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

/

SME / Instructor (Print/Sign) Date

/

SME / Instructor (Print/Sign) Date

/

SME / Instructor (Print/Sign) Date SRRS: 3D.100; There are no retention requirements for this section

TQ-AA-150-J020 Revision 01 Page 3 of 11 JPM434 Revision Record (Summary)

Revision # Summary 00 8/19/20 - New JPM SRRS: 3D.100; There are no retention requirements for this section

TQ-AA-150-J020 Revision 01 Page 4 of 11 JPM434 SETUP INSTRUCTIONS

1. No setup is required for this JPM.

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

TQ-AA-150-J020 Revision 01 Page 5 of 11 JPM434 INITIAL CONDITIONS You are the CRS on the Night shift.

The reactor plant is in Mode 5.

All Control Rods are inserted and core alterations are in progress in the Northwest Quadrant.

Ninety-two new bundles are installed in the core.

The Reactor Operator has just completed CPS 9000.03 Core Alteration Surveillance Log and CPS 9000.01D002 Control Room Surveillance Log - Mode 4, 5 Data Sheet and handed them to you for review.

INITIATING CUE Review and approve CPS 9000.03 and CPS 9000.01D002. Identify all discrepancies and take appropriate actions as necessary.

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

Information For Evaluators Use:

UNSAT requires written comments on respective step.

• Denotes critical steps.

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

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

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

The timeclock starts when the candidate acknowledges the initiating cue.

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

TQ-AA-150-J020 Revision 01 Page 6 of 11 JPM434 JPM Start Time: JPM Sequence #: of Task Standard:

The examinee will review CPS 9000.01D002 & CPS 9000.03 and determine core alterations:

• are being performed in a quadrant without an operable SRM.

• must be immediately suspended IAW ITS LCO 3.3.1.2 SRM Instrumentation.

Comment STEP ELEMENT STANDARD SAT UNSAT Number CUE Provide the examinee with a copy of:

• Initiating Cue (last page of JPM)

• Reactor Core Map (Attachment 1 of the JPM)

• Marked Up procedures:

o CPS 9000.03 Core Alteration Surveillance Log o CPS 9000.01D002 Control Room Surveillance Log - Mode 4, 5 Data Sheet

• CPS Technical Specifications (Books 1 & 2)

• 01 Conducts Shift Management a. Examinee determines that review of CPS 9000.03 and SRM 'A' is downscale (less ___

CPS 9000.01D002. than 3 cps).

b. Examinee determines that SRM 'A' is located in the quadrant where core alterations are occurring.

c. Examinee determines that adjacent quadrants have ___

operable SRMs.

• 02 Reviews CPS 9000.03 Examinee determines Acceptance Criteria. Acceptance Criteria is not ___

met.

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

TQ-AA-150-J020 Revision 01 Page 7 of 11 JPM434 Comment STEP ELEMENT STANDARD SAT UNSAT Number

• 03 Reviews ITS 3.3.1.2 SRM Examinee enters ITS 3.3.1.2 Instrumentation to identify Required Actions E.1 and E.2 Action Statements for and reports that CORE ___

implementation. ALTERATIONS are to be suspended immediately.

CUE If the examinee reports that core alterations should be suspended, acknowledge the report.

JPM is complete.

JPM Stop Time:

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

TQ-AA-150-J020 Revision 01 Page 8 of 11 JPM434 JPM

SUMMARY

Operators Name: Emp. ID#:

Job

Title:

EO RO SRO FS STA/IA SRO Cert JPM

Title:

Failed SRM During Refuel JPM Number: JPM434 Revision Number: 00 Task Number and

Title:

900003.01 / Core Alteration Surveillance Log Task Standard: The examinee will review CPS 9000.01D002 & CPS 9000.03 and determine core alterations:

• are being performed in a quadrant without an operable SRM.

• must be immediately suspended IAW ITS LCO 3.3.1.2 SRM Instrumentation.

K/A Number and Importance:

K/A System K/A Number Importance (RO/SRO)

Generic 2.1.36 3.0 4.1 Suggested Testing Environment: Classroom Alternate Path: Yes No SRO Only: Yes No Time Critical: Yes No Reference(s):

Procedure: CPS 9000.01D002 Revision: 39 CPS 9000.03 Revision: 27c CPS ITS 3.3.1.2 Amend: 188 Actual Testing Environment: Simulator Control Room In-Plant Other Testing Method: Simulate Perform Estimated Time to Complete: 10 minutes Actual Time Used: minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily? Yes No The operators performance was evaluated against standards contained within this JPM and has been determined to be: Satisfactory Unsatisfactory SRRS: 3D.105 (when utilized for operator initial or continuing training)

TQ-AA-150-J020 Revision 01 Page 9 of 11 JPM434 NOTE: Enter finalized grading, comments, and notes relevant to this evaluation in the associated TQ-AA-150-F03A/B. (See AR 4282419).

Evaluators Name (Print):

Evaluators Signature: Date:

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

TQ-AA-150-J020 Revision 01 Page 10 of 11 JPM434 Attachment 1: Reactor Core Map SRRS: 3D.100; There are no retention requirements for this section

TQ-AA-150-J020 Revision 01 Page 11 of 11 JPM434 INITIAL CONDITIONS You are the CRS on the Night shift.

The reactor plant is in Mode 5.

All Control Rods are inserted and core alterations are in progress in the Northwest Quadrant.

Ninety-two new bundles are installed in the core.

The Reactor Operator has just completed CPS 9000.03 Core Alteration Surveillance Log and CPS 9000.01D002 Control Room Surveillance Log - Mode 4, 5 Data Sheet and handed them to you for review.

INITIATING CUE Review and approve CPS 9000.03 and CPS 9000.01D002. Identify all discrepancies and take appropriate actions as necessary.

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

CPS 9000.01D002 CONTROL ROOM SURVEILLANCE LOG - MODE 4, 5 DATA SHEET SCOPE OF REVISION:

• Incorporated Specific Revs 38 - 38e, rev marks not retained.

• General Rev 39. [Palmer]: Revised procedure to facilitate Operations transition from 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shifts. Updated Technical Specification references.

Rev Marks not used For Training Only CONTINUOUS USE ORIGINATOR: Terry Palmer CLASS CODE: SNND1 SQR: Mark Dodds APPROVAL DATE: 10/11/19 CURRENT CHANGES TO GENERAL REVISION Change # Date List of Affected Pages Rev. 39 Page 1 of 18

CPS 9000.01D002 CONTROL ROOM SURVEILLANCE LOG - MODE 4, 5 MON TUE WED THU FRI SAT SUN 5.1 (Record) Inform SMngt of test start Shiftly N XX:XX

_____ N _____ N _____ N _____ N _____ N _____ N _____

and record date/time of notification. Start D _____ D _____ D _____ D _____ D _____ D _____ D _____

Weekly Start Date/TimeXX/XX/XXXX______/______

XX:XX Time NOTES:

- Remaining data sheet steps may be performed in any order.

- Shift logs will be performed between 0800 and 1100 for the day shift. Night Shift performance shall be between 2000 and 2300.

- Daily/Weekly logs will be performed on Night Shift between 2000 and 2300 or as otherwise indicated.

(ITS SR 3.0.2) 8.1 Reactor MODE Switch Position

1. (Initial) Verify Reactor MODE Switch is LOCKED in SHUTDOWN or REFUEL position when:

WDK N _____ N _____ N _____ N _____ N _____ N _____

a) In MODE 4 when:

Suppression pool water level < 12 8 or ITS LCO 3.10.4 is being utilized.

OR D _____ D _____ D _____ D _____ D _____ D _____

b) In MODE 5.

(ORM TR 4.6.7)(Refer to ITS LCO 3.10.2 and 3.10.8 for exceptions.)

2. (Initial) Verify Reactor MODE Switch is LOCKED in REFUEL position when:

N WDK

_____ N _____ N _____ N _____ N _____ N _____ N _____

In MODE 5, AND Any control rod withdrawn.

(ITS SR 3.9.2.1) D _____ D _____ D _____ D _____ D _____ D _____ D _____

OR PC-TCC dummy plug installed into Jack 26 at 1H13-P651 or 1H13-P652 IAW CPS 3509.01C001 or C002 8.2 (Record) Plant Operating MODE. 5 / / / / / / /

Rev. 39 Page 2 of 18

CPS 9000.01D002 CONTROL ROOM SURVEILLANCE LOG - MODE 4, 5 MON TUE WED THU FRI SAT SUN 8.3 SURVEILLANCE PROCEDURE TRACKING VERIFICATIONS

° Normally preformed/maintained current as recommended irrespective of previous triggered performances.

1. Reactivity Control [NIGHTs only]

(MODE 5 with a withdrawn control rod) d XX/XX/XXXX

_____ d _____ d _____ d _____ d _____ d _____ d _____

(Record) Date/time CPS 9011.01, Control Rod/Position Indication Operability t _____

XX:XX t _____ t _____ t _____ t _____ t _____ t _____

required. (ITS SR 3.9.5.1)

2. CPS 9082.01, Offsite Source Power /X Verification completed. (ITS SR 3.8.2.1)

3. CPS 9082.02, Electrical Distribution Verification completed. /X (ITS SR 3.8.8.1, 3.8.10.1)

4. CPS 9094.01D001, Cumulative Data Report Data Sheet updated.

(ITS SR 3.6.4.3.2, 3.7.3.3; /X ITS 5.5.7.c)

Rev. 39 Page 3 of 18

CPS 9000.01D002 CONTROL ROOM SURVEILLANCE LOG - MODE 4, 5 MON TUE WED THU FRI SAT SUN 8.4 INSTRUMENTATION 8.4.1 Source Range Monitors (SRM)

SRM Comparison Guideline:

3 to 500 cps when all rods are inserted. Use DCS indication if available, or SRM Backpanels.

If a channel is > 500 cps, refer to CPS 1401.09 (or equivalent) to evaluate channel operability.

1. MODE 4 [DAYs only]

a) Record/Verify 3.0 cps. SRM Channel Verify SRMs full in. A cps cps cps cps cps cps cps

( 2 channels) B cps cps cps cps cps cps cps (ITS SR 3.3.1.2.4 T1) C cps cps cps cps cps cps cps D cps cps cps cps cps cps cps b) (Initial) Channel Check SRM indications.

• 1H13-P678 X/ X/ X/ X/ X/ X/ X/

• DCS and/or SRM Drawers (flux & period)(ITS SR 3.3.1.2.3 T1)

2. MODE 5 [Shiftly]

a) Record/Verify 3.0 cps. SRM Channel Verify SRMs full in. Nights A 2 cps cps cps cps cps cps cps

( 2 channels) Nights B 10 cps cps cps cps cps cps cps (ITS SR 3.3.1.2.4 T1) Nights C 8 cps cps cps cps cps cps cps Nights D 6 cps cps cps cps cps cps cps b) Record/Verify 3.0 cps. SRM Channel Verify SRMs full in. Days A cps cps cps cps cps cps cps

( 2 channels) Days B cps cps cps cps cps cps cps (ITS SR 3.3.1.2.4 T1) Days C cps cps cps cps cps cps cps Days D cps cps cps cps cps cps cps d) (Initial) Channel Check SRM indications.

• 1H13-P678 WDK/ / / / / / /

• DCS and/or SRM Drawers (flux & period)(ITS SR 3.3.1.2.1 T1)

Rev. 39 Page 4 of 18

CPS 9000.01D002 CONTROL ROOM SURVEILLANCE LOG - MODE 4, 5 MON TUE WED THU FRI SAT SUN 8.4 INSTRUMENTATION (contd) 8.4.2 Intermediate Range Monitors (IRM)

(MODE 5 with any control rod withdrawn from a core cell containing one or more fuel assemblies.)

(Initial) Channel Check IRM indications on 1H13-P678. (ITS SR 3.3.1.1.1 T1.a) WDK/ / / / / / /

8.4.3 Narrow Range (NR) Reactor Vessel Water Level (Initial) Channel Check ATM indications of Reactor Vessel Water Level (NR). WDK/ / / / / / /

RPS/RHR ATM 1B21-N680A, B, C, D (ITS SR 3.3.5.2.1 T4.a) 8.4.4 Wide Range (WR) Reactor Vessel Water Level (Initial) Channel Check Reactor Vessel Water Level (WR) indications. WDK/ / / / / / /

1. NS4 ATM 1B21-N681A, B, C, D (ITS SR 3.3.5.2.1 T5.a, ITS SR 3.3.6.2.1 T1)

2. Div 1, LPCS ATM 1B21-N691A, E (ITS SR 3.3.5.1.1 T1.a)

3. Div 2, RHR ATM 1B21-N691B, F (ITS SR 3.3.5.1.1 T2.a)

4. Div 3, HPCS ATM 1B21-N673C, G (ITS SR 3.3.5.1.1 T3.a)

5. Div 4, HPCS ATM 1B21-N673D, H (ITS SR 3.3.5.1.1 T3.a) 8.4.5 Reactor Vessel Pressure (Initial) Channel Check Reactor Vessel Pressure indications. WDK/ / / / / / /

1. Div 1, LPCS ATM 1B21-N697A, E (ITS SR 3.3.5.2.1 T1.a)

2. Div 2, RHR ATM 1B21-N697B, F (ITS SR 3.3.5.2.1 T2.a)

Rev. 39 Page 5 of 18

CPS 9000.01D002 CONTROL ROOM SURVEILLANCE LOG - MODE 4, 5 MON TUE WED THU FRI SAT SUN 8.4 INSTRUMENTATION (contd) 8.4.6 Scram Discharge Volume (SDV) Level (MODE 5 with any control rod withdrawn from a core cell containing one or more fuel assemblies.)

(Initial) Channel Check SDV Level indications. WDK/ / / / / / /

RPS ATM 1C11-N601A, B, C, D (ITS SR 3.3.1.1.1 T8.a) 8.4.7 Suppression Pool Level

1. (Initial) Channel Check Suppression Pool Level indications. WDK/ / / / / / /

a) ATM 1E22-N655C, G (inst. zero = 731 5) b) 1LR-CM240, -CM241 or 1LY-CM030, -CM031, 1LY-SM006 (1H13-P852), 1LY-SM013 (1H13-P862)

Instrument zero is 7270.

1LR-CM240 & CM241 read in feet and inches.

1LY-SM006, 1LY-SM013 read 0 - 100%,

with full scale equal to +70.

Use following when conducting channel check.

(Also applicable to 1LY-CM030 & CM031.)

0% = 15.0 (150) 67% = 18.9 (1811) 100% = 20.8 (2010) 25% = 16.6 (165.5) 71% = 19.2 (192) 50% = 17.9 (1711) 76% = 19.4 (195)

2. (Record) Record/Verify CM030 Suppression Pool Water Level >20.8/X /X /X /X /X /X /X is 12.8 (129) from recorder ft ft ft ft ft ft ft 1LR-CM030 and 1LR-CM031 on P601. CM031 (ITS SR 3.5.2.2, 3.5.2.3.a) >20.8/X /X /X /X /X /X /X ft ft ft ft ft ft ft If either recorder is inoperable or below range (16.0 [160]),

then refer to recorders 1LR-SM014 and 1LR-SM016 on 1H13-P601.

If recorder sets 1LR-CM030 and 1LR-CM031, or 1LR-SM014 and 1LR-SM016 are not operable, then locally verify Suppression Pool water level is above the top of the upper row of drywell vents ( 13.1 [131]).

Rev. 39 Page 6 of 18

CPS 9000.01D002 CONTROL ROOM SURVEILLANCE LOG - MODE 4, 5 MON TUE WED THU FRI SAT SUN 8.4 INSTRUMENTATION (contd) 8.4.8 RCIC Storage Tank

1. (Initial) Channel Check RCIC Storage Tank Level indications. WDK/ / / / / / /

ATM, 1E22-N654C, G (Instrument zero is 739 10.75 or 2 10.75 from tank bottom)

(ITS SR 3.3.5.2.1 T3.a)

Used for HPCS suction source switching.

2. (Initial) Verify that RCIC storage tank WDK/ / / / / / /

available water volume is 125,000 gal.

This volume is maintained when the trip Light under 1E51-N801 (1H13-P862) indicator is ON. (ITS SR 3.5.2.3.b) 8.4.9 LPCS Pump Discharge Flow (Initial) Channel Check LPCS Pump Discharge Flow indications. WDK/ / / / / / /

LPCS ATM 1E21-N651 (ITS SR 3.3.5.2.1 T1.b) 8.4.10 LPCI Pump A Discharge Flow (Initial) Channel Check LPCI Pump A Discharge Flow indications. WDK/ / / / / / /

RHR ATM 1E12-N652A (ITS SR 3.3.5.2.1 T1.c) 8.4.11 LPCI Pump B Discharge Flow (Initial) Channel Check LPCI Pump B Discharge Flow indications. WDK/ / / / / / /

RHR ATM 1E12-N652B (ITS SR 3.3.5.2.1 T2.b) 8.4.12 LPCI Pump C Discharge Flow (Initial) Channel Check LPCI Pump C Discharge Flow indications. WDK/ / / / / / /

RHR ATM 1E12-N652C (ITS SR 3.3.5.2.1 T2.b)

Rev. 39 Page 7 of 18

CPS 9000.01D002 CONTROL ROOM SURVEILLANCE LOG - MODE 4, 5 MON TUE WED THU FRI SAT SUN 8.4 INSTRUMENTATION (contd) 8.4.13 HPCS Pump Discharge Pressure (Initial) Channel Check HPCS Pump Discharge Pressure indications. WDK/ / / / / / /

HPCS ATM 1E22-N651 (ITS SR 3.3.5.2.1 T3.b) 8.4.14 HPCS Pump Minimum Flow (Initial) Channel Check HPCS Pump Minimum Flow indications. WDK/ / / / / / /

HPCS ATM 1E22-N656 (ITS SR 3.3.5.2.1 T3.c) 8.5 RESIDUAL HEAT REMOVAL (Initial) Verify proper operation of the RHR Shutdown Cooling MODE per applicable MODE:

1. (MODE 4)

Verify one RHR shutdown cooling subsystem or

/ / / / / / /

recirculation pump is operating.

(ITS SR 3.4.10.1)

2. (MODE 5 with irradiated fuel in the RPV and water level 22 ft 8 inches above the top of the RPV flange) WDK/ / / / / / /

Verify one RHR shutdown cooling subsystem is operating. (ITS SR 3.9.8.1)

3. (MODE 5 with irradiated fuel in the RPV and water level < 22 ft 8 inches above the top of the RPV flange) / / / / / / /

Verify one RHR shutdown cooling subsystem is operating. (ITS SR 3.9.9.1)

Rev. 39 Page 8 of 18

CPS 9000.01D002 CONTROL ROOM SURVEILLANCE LOG - MODE 4, 5 MON TUE WED THU FRI SAT SUN 8.6 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION - TANK LEVEL INDICATIONS (during liquid additions to associated tank)

1. (Initial) Channel Check the Cycled Condensate Storage Tank Level on 1H13-P870. WDK/

/ / / / / /

(ODCM SR Table 4.1-1 4.a: CK)

2. (Initial) Channel Check the Reactor Core Isolation Cooling Tank Level on 1H13-P862. WDK/

/ / / / / /

(ODCM SR Table 4.1-1 4.b: CK) 8.7 SECONDARY CONTAINMENT INTEGRITY [NIGHTs only]

(During movement of recently irradiated fuel assemblies in the primary or secondary containment.)

(Record) Record/Verify Secondary Containment to Atmosphere D/P is 0.25 inch of vacuum 0.75 /X /X /X /X /X /X /X water gauge from 0PDI-VG001 or 0PDI-VG101. in. vac in. vac in. vac in. vac in. vac in. vac in. vac (ITS SR 3.6.4.1.1)Refer to 9000.01, Section 2.1.8 WG WG WG WG WG WG WG 8.8 REACTOR COOLANT SYSTEM

1. (Initial) Verify reactor coolant conductivity is being recorded continuously on 1H13-P678. (ORM TR 4.3.1.5) WDK/ / / / / / /

If the continuous conductivity recorder is INOPERABLE, notify Chemistry to perform in-line conductivity measurements at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per CPS 9940.01.

2. (Initial) Verify Reactor Coolant temperature is > 90°F. WDK/ / / / / / /

If temperature decreases to 90°F, then initiate 9000.06D002, Vessel and Head Flange Temperature Log (ITS SR 3.4.11.7) MODE 4, by use of any of the following:

• Read from B33-R604 on 1H13-P614.

• Read from E12-R601, 1E12-N004A (RHR HX 1A Inlet) or 1E12-N004B (RHR HX 1B Inlet) on 1H13-P601.

Ensure point used is associated with S/D cooling loop in operation.

• Bottom Head drain temp from point 4 on B21-R643.

Rev. 39 Page 9 of 18

CPS 9000.01D002 CONTROL ROOM SURVEILLANCE LOG - MODE 4, 5 MON TUE WED THU FRI SAT SUN 8.9 NSS AND BOP ANNUNCIATOR HIDDEN GROUND FAULT TEST [Wednesday NIGHTs only]

NOTE If an annunciator card(s) has a hidden ground fault in the system being tested, it will alarm.

1. (Initial) Perform a NSS Hidden Ground

/X Fault Test.

In 1H13-P630, depress Ground Fault Test push-button and observe the Ground Fault lamp lights and verify annunciator H13-P630 ANNUNCIATOR GRD FAULT (5006-1L) alarms, then release push-button.

2. (Initial) Perform a BOP Hidden Ground

/X Fault Test.

In 1H13-P6850, depress Ground Fault Test push-button and observe the Ground Fault lamp lights and verify annunciator H13-P850 ANNUNCIATOR GRD FAULT (5007-1D) alarms, then release push-button.

8.10 THERMAL OVERLOAD PROTECTION (MOV Test Switches)

(Initial) Verify thermal overload protection is bypassed for motor operated valves (MOV)

WDK/ / / / / / /

required to be operable. Verify MOV Test Prep switches are in NORM position. (ORM TR 4.5.2.2) <<CM-1>>

8.11 SVC PROTECTION SYSTEMS [NIGHTs only]

Verify required E-Area Daily Rounds - SVC local panel checks are complete.

(ITS SR 3.8.11.1)

1. (Initial) RAT SVC Protection System WDK/X /X /X /X /X /X /X

2. (Initial) ERAT SVC Protection System WDK/X /X /X /X /X /X /X Rev. 39 Page 10 of 18

CPS 9000.01D002 CONTROL ROOM SURVEILLANCE LOG - MODE 4, 5 MON TUE WED THU FRI SAT SUN 8.12 AR/PR RADIATION MONITORS CHANNEL CHECKS Code Table for 8.12 items on Page 13.

(Initial) Verify Channel Check of AR/PR Channels on an AR/PR LAN Terminal.

1. 1RIX-PR001A, B, C, D (ITS SR 3.3.6.1.1 T2.h (g) WDK/ / / / / / /

ITS SR 3.3.6.2.1 T4 (g))

2. 1RIX-PR008A, B, C, D (ITS SR 3.3.6.1.1 T2.g (g) WDK/ / / / / / /

ITS SR 3.3.6.2.1 T3 (g))

3. 1RIX-PR042A, B, C, D (ITS SR 3.3.6.1.1 T2.i (g) WDK/ / / / / / /

ITS SR 3.3.6.2.1 T5 (g))

4. 1RIX-AR013 [Sunday DAYs only]

X/

5. 1RIX-AR010 [Sunday DAYs only]

X/

6. 0UIX-PR050 1/2/4/5/7 [ORM TR 4.2.8.1 (a)]

WDK/ / / / / / /

7. 1RIX-PR004 [ODCM SR Table 4.1-1 2.c] (d)

WDK/ / / / / / /

8. 1RIX-PR005 [ODCM SR Table 4.1-1 2.c] (d)

WDK/ / / / / / /

9. 1RIX-PR036 [ODCM SR Table 4.1-1 2.a] (d)

WDK/ / / / / / /

10. 1RIX-PR037 [ODCM SR Table 4.1-1 2.d] (d)

WDK/ / / / / / /

11. 1RIX-PR038 [ODCM SR Table 4.1-1 2.b] (d)

WDK/ / / / / / /

12. 1RIX-PR039 [ODCM SR Table 4.1-1 2.b] (d)

WDK/ / / / / / /

Rev. 39 Page 11 of 18

CPS 9000.01D002 CONTROL ROOM SURVEILLANCE LOG - MODE 4, 5 MON TUE WED THU FRI SAT SUN 8.12 AR/PR RADIATION MONITORS CHANNEL CHECKS (contd)

Code Table for 8.12 items on Page 13.

13. 1RIX-PR023 1/3/5/6 [Sunday DAYs only] X/

14. 1RIX-AR001 [Sunday DAYs only] X/

15. 1RIX-AR003 [Sunday DAYs only] X/

16. 1RIX-AR002 [Sunday DAYs only] X/

17. 1RIX-AR012 [Sunday DAYs only] X/

18. 1RIX-PR019 1/3/5/6 [Sunday DAYs only] X/

19. 1RIX-PR006A, B, C, D WDK/ / / / / / /

[ITS SR 3.3.6.2.1 T6 (h)]

20. 1RIX-AR019 [ORM TR 4.2.6.1 Ta (e)] WDK/ / / / / / /

21. 1RIX-AR052 [ORM TR 4.2.6.1 Ta (e)] WDK/ / / / / / /

22. 1RIX-AR016 [ORM TR 4.2.6.1 Tb (f)] WDK/ / / / / / /

23. 0RIX-PR001 5/7/15 [ODCM SR Table 4.2-2 1/b/a/e] WDK

/ / / / / / /

(note a)(also verify Ch 14 not deleted - supports Ch 15)(Ch 15 is INOP when flow < 45 LPM)

24. 0RIX-PR002 5/7/15 [ODCM SR Table 4.2-2 1/b/a/e] WDK

/ / / / / / /

(note a)(also verify Ch 14 not deleted - supports Ch 15) (Ch 15 is INOP when flow < 45 LPM)

25. 0RIX-PR003 6/9/15 [ODCM SR Table 4.2-2 2/b/a/e WDK/

(note b)(also verify Ch 14 not deleted - supports / / / / / /

Ch 15) (Ch 15 is INOP when flow < 45 LPM)

26. 0RIX-PR004 6/9/15 [ODCM SR Table 4.2-2 2/b/a/e] WDK

/ / / / / / /

(note b)(also verify Ch 14 not deleted - supports Ch 15) (Ch 15 is INOP when flow < 45 LPM)

Rev. 39 Page 12 of 18

CPS 9000.01D002 CONTROL ROOM SURVEILLANCE LOG - MODE 4, 5 MON TUE WED THU FRI SAT SUN 8.12 AR/PR RADIATION MONITORS CHANNEL CHECKS (contd)

27. 0UIX-PR051 1/6 [ODCM SR Table 4.2-2 6/5](b/a) WDK/ / / / / / /

28. 1RIX-PR009A, B, C, D WDK/ / / / / / /

[ITS SR 3.3.7.1.1 T1 (i)]

29. 1RIX-AR035 [ORM TR 4.2.6.1 Tc (a)] WDK/ / / / / / /

0UIX-PR050 should be used as the primary means of satisfying ORM Channel Checks.

Recorder 1UR-EM015 (60 meter wind velocity and direction, 10 meter wind velocity and direction and Pt. 7 Delta Temperature), may be used to satisfy the channel checks when 0UIX-PR050 is inoperable or not communicating (POLL OFF) with the AR/PR LAN.

If 0UIX-PR050 is inoperable or not communicating (POLL OFF) with the AR/PR LAN, contact the Buffer System Manager to notify IDNS that meteorological data will be unavailable.

If channel checks are performed with the recorders, a notation shall be made in the Comments section.

(a) At all times.

(b) When standby gas treatment system is in standby or operation.

(d) Any time system is in service.

(e) With fuel in the new fuel storage vault.

(f) With irradiated fuel in the spent fuel storage pool.

(g) During movement of recently irradiated fuel assemblies in the primary or secondary containment.

(h) During movement of recently irradiated fuel assemblies in the fuel building.

(i) During CORE ALTERATIONS, and during movement of irradiated fuel assemblies in the primary or secondary containment.

Rev. 39 Page 13 of 18

CPS 9000.01D002 CONTROL ROOM SURVEILLANCE LOG - MODE 4, 5 MON TUE WED THU FRI SAT SUN 8.13 SELF TEST SYSTEM (ITS SR {see 2.1.7})(ORM TR 4.2.14.1)

(Initial) Status indications of the STS shall be obtained at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, whenever the STS is operating in the fully or partially automatic MODE.

• N/A the MODE not being credited for ITS/ORM.

• STS Summary print-out per CPS 3513.01 (STS).

1. Fully Automatic MODE, or WDK/X /X /X /X /X /X /X

2. Partially Automatic MODE with all required tests performed once per 90 days. WDK/X /X /X /X /X /X /X (i.e., Fully Auto MODE SAT or CPS 9030.05: PMRQ 159560-01.)

8.14 DELETED Rev. 39 Page 14 of 18

CPS 9000.01D002 CONTROL ROOM SURVEILLANCE LOG - MODE 4, 5 MON TUE WED THU FRI SAT SUN 8.15 ULTIMATE HEAT SINK TEMPERATURE (NIGHTS only)

(Record) UHS temp from computer pt:

a) CW-BA001 or CW-BA002 with CW in service and flow through the associated waterbox A/B.

b) If CW is NOT in service, computer point SX-DA001 can be used with flow through RHR HX A, SX-DA002 with flow 81°F /X /X /X /X /X /X /X through RHR HX B.

Initiate an IR at or approaching 93°F.

95°F is the design inlet temperature of SX.

Ref IR 1525666 (EC 394281).

8.16 SFSC HEAT REMOVAL SYSTEMS [Days only]

Verify required E-Area Daily Rounds - SFSC Heat Removal Systems local checks are complete FOR EACH LOADED CASK (no vents have any observed blockage).

(Technical Specifications for the HI-STORM FW MPC Storage System SR 3.1.2)

<<LBD-5>>

(Initial) X/ X/ X/ X/ X/ X/ X/

Rev. 39 Page 15 of 18

CPS 9000.01D002 CONTROL ROOM SURVEILLANCE LOG - MODE 4, 5 MON TUE WED THU FRI SAT SUN 8.17 REACTOR PRESSURE VESSEL WATER INVENTORY CONTROL

1. (Record) RPV WIC DRAIN TIME per 3006.01P001 N >36 hrs N _____ N _____ N _____ N _____ N _____ N _____

D _____ D _____ D _____ D _____ D _____ D _____ D _____

2. (Initial) Verify DRAIN TIME > 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. N _____

WDK N _____ N _____ N _____ N _____ N _____ N _____

(SR 3.5.2.1)

D _____ D _____ D _____ D _____ D _____ D _____ D _____

8.18 SPENT FUEL POOL TIME TO 200 DEGREES UPDATED Reference 3317.01C001. Includes update of TSC data.

a. Shiftly with the plant shut down for a refueling outage only unless a bounding number is established for the outage per OP-AA-108-117-1001, Spent Fuel Storage Pools WDK/

/ / / / / /

Heat-Up Rate With Loss Of Normal Cooling

b. Weekly on SUNDAY otherwise 8.19 SURVEILLANCE COMPLETION (Record) Record finish time of N _____

XX:XX N _____ N _____ N _____ N _____ N _____ N _____

CPS 9000.01D002.

D _____ D _____ D _____ D _____ D _____ D _____ D _____

Rev. 39 Page 16 of 18

CPS 9000.01D002 SHIFT TEST RESULTS Operability Other Requirements Requirements F P P F P F U A A A A A SMngt L R S I S I COMMENTS REVIEW L T S L S L

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Rev. 39 Page 17 of 18

CPS 9000.01D002 CONTROL ROOM OPERATOR SURVEILLANCE LOG - MODE 4, 5 DATA SHEET SUPPLEMENTAL REVIEW SHEET Corrective Action Taken Operability Requirements:

ITS LCOs: see body of Data Sheet ORM ORs: see body of Data Sheet ODCM TRs: see body of Data Sheet As applicable:

Initiated Issue Report No. ____________________

Comments/Deficiencies REVIEW AND APPROVAL SMgmt Review: _________________________________________________________

(Signature) (Date)

Rev. 39 Page 18 of 18

CPS 9000.03 CORE ALTERATION SURVEILLANCE LOG SCOPE OF REVISION:

• Periodic review and format update.

• Revised required RPV water level for step 8.1.5 from 23 ft. to 22 ft. 8 in. per ITS Amendment 133.

• Revised old step 8.2 (now 8.2 and 8.3) to record time of completion and document Shift Management review shiftly.

Specific Rev. 27a [Landin]: EDITORIAL - Step 8.1.6 structure enhancement/typo fix per JPM feedback (CCF 01-0313: Sympson).

Specific Rev. 27b [Landin]: EDITORIAL - Added ORM TR 4.6.7 link (Shelton).

Specific Rev. 27c [Landin]: C1R09:

Added additional monitoring criteria per EC TCHG 335418 when a PC-TCC for For Training Refuel Bridge MODE Switch Interlock is installed via CPS 3509.01C001/C002.

Only CONTINUOUS USE ORIGINATOR: David W. Reeser CLASS CODE: SNNN SQR: Thomas J. Landin APPROVAL DATE: OCT 13 2000 CURRENT CHANGES TO GENERAL REVISION Change # Date List of Affected Pages 27a 01/22/03 1, 5 27b 01/27/04 1, 4, 6, 7 27c 02/06/04 1, 4, 6 Rev. 27c Page 1 of 7

CPS 9000.03 1.0 PURPOSE 1.1 Ensure the proper operation of certain plant equipment covered by the applicable CPS ITSs as required for CORE ALTERATIONS.

The procedure must be performed when in CORE ALTERATIONS MODE, whether or not CORE ALTERATIONS are in progress.

1.2 Completion of this procedure satisfies the requirements of ITS SR 3.3.1.2.2, SR 3.9.2.1, SR 3.9.3.1, SR 3.9.6.1, SR 3.9.7.1, and ORM TR 4.6.2.

2.0 DISCUSSION/DEFINITIONS 2.1 Discussion 2.1.1 Frequency

1. Normal Frequency - Shiftly

2. Other Triggers - CPS 3007.01, Preparation For And Recovery From Refueling Operations.

2.1.2 This procedure shall be routinely performed as close to the beginning of the shift as possible.

If only two shifts are present during a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period, this surveillance should be performed at 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> intervals.

2.1.3 This log will be maintained by an on-shift RO, and reviewed by SMngt.

2.2 Definitions 2.2.1 CORE ALTERATIONS: the movement of any fuel, sources, or reactivity control components within the reactor vessel with the vessel head removed and fuel in the vessel.

The following exceptions are not considered to be CORE ALTERATIONS:

• Movement of source range monitors, local power range monitors, intermediate range monitors, traversing in-core probes, or special movable detectors (including under-vessel replacement); and

• Control rod movement, provided there are no fuel assemblies in the associated core cell.

2.2.2 CORE ALTERATIONS MODE: inclusive combination of plant conditions which satisfy Technical Specifications for performing Core Alterations.

Rev. 27c Page 2 of 7

CPS 9000.03 3.0 RESPONSIBILITY Operations Department Head is responsible for ensuring the implementation of this procedure.

4.0 PRECAUTIONS 4.1 During prolonged outages, with vessel level lowered and the reactor head removed, the reactor vessel level reference legs are to be periodically refilled due to evaporation losses.

Refer to PMID 150928-03, fill and vent on shutdown range level transmitter 1B21-N027. <<CM-1>>

4.2 If a significant change in reactor vessel level occurs, the MCR shall notify the Refueling SRO and they shall notify Radiation Protection. <<CM-1>>

5.0 PREREQUISITES 5.1 This is a passive test and does not affect plant equipment, therefore, an impact statement is not required.

5.2 Notify Shift Management of the start of this test.

XX/XX/XXXX/XX:XX WDK Date/Time Initial 6.0 LIMITATIONS 6.1 The use of special movable detectors during core alterations in place of normal Source Range Monitor (SRM) detectors is permissible as long as they are connected to the normal SRM circuits.

7.0 MATERIALS/TEST EQUIPMENT - None Rev. 27c Page 3 of 7

CPS 9000.03 MIDS/DAYS/SWINGS 8.0 PROCEDURE Date: XX/XX/XXX Time: XX:XX / /

8.1 Verify the following checks are current:

• Prior to CORE ALTERATIONS; and

• Prior to resuming CORE ALTERATIONS following an exit from the CORE ALTERATIONS MODE.

• Thereafter, perform steps 8.1.1, 8.1.2, 8.1.3 and 8.1.4 shiftly (refer to step 2.1.2), and steps 8.1.5 and 8.1.6 daily.

NOTE Steps 8.1.1 through 8.1.6 may be performed concurrently or in any logical order.

8.1.1 Reactor Mode Selector Switch is locked in the Refuel Position (with the key removed). <<LBD-2>> <<LBD-7>> WDK/ /

1. IF PC-TCC For MODE Switch in Refuel Interlock is installed per CPS 3509.01C001, Division 1 NSPS Bus (1C71-P001A) Outage, <<LBD-8>>

THEN In the back of RC&IS panel 1H13-P651, (upper right corner at back of panel) verify PC-TCC installation by checking that the dummy plug is installed into jack 26. N/A / /

2. IF PC-TCC For MODE Switch in Refuel Interlock is installed per CPS 3509.01C002, Division 2 NSPS Bus (1C71-P001B) Outage, <<LBD-8>>

THEN In the back of RC&IS panel 1H13-P652, (upper right corner at back of panel) verify PC-TCC installation by checking that the dummy plug is installed into jack 26. N/A / /

8.1.2 All Control Rods are fully inserted. <<LBD-3>> WDK/ /

Rev. 27c Page 4 of 7

CPS 9000.03 MIDS/DAYS/SWINGS 8.1.3 Verify operability of the required SRMs. <<LBD-1>>

1. Verify SRM portion of CPS 9000.01D002, Control Room Operator Surveillance Log - Mode 4,5 Data Sheet is current for the SRMs required to satisfy the sub-step 2 below. WDK/ /

2. Verify an OPERABLE SRM detector is located in:

1. The fueled region; and WDK/ /

2. The core quadrant where CORE ALTERATIONS are being performed when the associated SRM is included in the fueled region; WDK and / /

3. A core quadrant, adjacent to where CORE ALTERATIONS are being performed, when the associated SRM is included in the fueled WDK region. / /

8.1.4 During CORE ALTERATIONS, except during movement of control rods with their normal drive system, Verify direct communication between the MCR and the refuel platform personnel. <<LBD-6>> WDK/ /

8.1.5 During movement of irradiated fuel, Verify Reactor Pressure Vessel Level is at least 22 ft. 8 in. over the top of the reactor pressure vessel flange. WDK

<<LBD-4>> / X / X

NOTE RPV water level is ~ 50 feet above the top of irradiated fuel assemblies seated within the RPV when upper CNMT pool water level is at the top of the weir wall separating the Reactor refueling pool and steam dryer storage pool.

8.1.6 During movement of new fuel assemblies or handling of control rods (by other than their normal drive system) within the RPV, Verify Reactor Pressure Vessel Level is 23 above the top of irradiated fuel assemblies seated within the RPV. <<LBD-5>> WDK/ X / X Rev. 27c Page 5 of 7

CPS 9000.03 MIDS/DAYS/SWINGS 8.2 (Record) Finish time of CPS 9000.03. XX:XX/ /

8.3 (Initial) Shift Management Review. (SMngt) / /

Rev. 27c Page 6 of 7

CPS 9000.03 9.0 ACCEPTANCE CRITERIA 9.1 Operability Requirements NOTE Failure to meet the Acceptance Criteria shall constitute a failure to comply with the applicable LCO. ITS should be immediately reviewed to identify Action Statements needed for implementation. Refer to Supplemental Review Sheet for applicable LCOs.

9.1.1 Items in section 8.0 of CPS 9000.03 are satisfactory.

9.2 Other Requirements - None 10.0 FINAL CONDITIONS - None

11.0 REFERENCES

11.1 Licensing Basis Documents 11.1.1 LBD-1: SR 3.3.1.2.2 <<8.1.3>>

11.1.2 LBD-2: SR 3.9.2.1 <<8.1.1>>

11.1.3 LBD-3: SR 3.9.3.1 <<8.1.2>>

11.1.4 LBD-4: SR 3.9.6.1 <<8.1.5>>

11.1.5 LBD-5: SR 3.9.7.1 <<8.1.6>>

11.1.6 LBD-6: ORM TR 4.6.2 <<8.1.4>>

11.1.7 LBD-7: ORM TR 4.6.7 <<8.1.1>>

11.1.8 LBD-8: EC TCHG 335418 <<8.1.1.1, 8.1.1.2>>

11.2 Procedures 11.2.1 CPS 3007.01, Preparation For And Recovery From Refueling Operations 11.3 Design/Vendor/Print/Other -- None 11.4 Commitments 11.4.1 CM-1: SOER 82-01, Radiation Overexposure of Maintenance Personnel <<4.1, 4.2>>

12.0 APPENDICES - None 13.0 DOCUMENTS - None Rev. 27c Page 7 of 7

CPS 9000.03 CORE ALTERATION SURVEILLANCE LOG SUPPLEMENTAL REVIEW SHEET Corrective Action Taken Operability Requirements:

ITS LCOs: 3.9.2 3.9.3 3.9.6 3.3.1.2 ORM ORs: 4.6.2 4.6.7 ODCM ORs: None As applicable:

Initiated Condition Report No. ____________________

Initiated Work Document No. _______________________

Comments/Deficiencies Review and Approval Surveillance Coordinator: ____________________________________________

(Signature) (Date)

Rev. 27c Page 8 of 7

TQ-AA-150-J020 Revision 01 Page 1 of 11 Job Performance Measure Review CPS 9071.01A Diesel Driven Fire Pump A Operability Test JPM Number: JPM556 Revision Number: 01 Date: 8/20/2020 Developed By: Bill Kiser / 8/20/20 Instructor: Print / Sign Date Reviewed By: /

SME or Instructor: Print / Sign Date Reviewed By: /

Operations Representative: Print / Sign Date Approved By: /

Training Department: Print / Sign Date SRRS: 3D.105 (when utilized for operator initial or continuing training)

TQ-AA-150-J020 Revision 01 Page 2 of 11 JPM556 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation.

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

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

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

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

4. Initial setup conditions are identified.

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

6. Task standards identified and verified by instructor or SME review.

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

8. IAW NUREG 1021 Appendix C, clearly identify the task standard (i.e., the predetermined qualitative or quantitative outcome) against which task performance will be measured.

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

Procedure: CPS 9071.01A Revision: 00a Procedure: CPS 1893.01 Revision: 22a Procedure: CPS 1893.06 Revision: 13 Procedure: Revision:

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

11. Verify performance time is accurate.

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

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

/

SME / Instructor (Print/Sign) Date

/

SME / Instructor (Print/Sign) Date

/

SME / Instructor (Print/Sign) Date SRRS: 3D.100; There are no retention requirements for this section

TQ-AA-150-J020 Revision 01 Page 3 of 11 JPM556 Revision Record (Summary)

Revision # Summary 00 3/5/18 - New JPM.

01 8/20/20 - Updated references. Updated JPM template.

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

TQ-AA-150-J020 Revision 01 Page 4 of 11 JPM556 SETUP INSTRUCTIONS

1. No setup is required for this JPM.

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

TQ-AA-150-J020 Revision 01 Page 5 of 11 JPM556 INITIAL CONDITIONS The plant is in Mode 1.

CPS 9071.01A Diesel Driven Fire Pump A Operability Test is field complete for 0FP01PA Diesel Driven Fire Pump A, awaiting supervisory review.

INITIATING CUE Review CPS 9071.01A Diesel Driven Fire Pump A Operability Test.

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

Information For Evaluators Use:

UNSAT requires written comments on respective step.

• Denotes critical steps.

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

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

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

The timeclock starts when the candidate acknowledges the initiating cue.

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

TQ-AA-150-J020 Revision 01 Page 6 of 11 JPM556 JPM Start Time: JPM Sequence #: of Task Standard:

The examinee will review CPS 9071.01A and determine:

• Acceptance Criteria of sections 9.2.1.1 and 9.2.2 were not met, and

• the pump must be restored to FUNCTIONAL status within 7 days or an alternate backup pump must be provided.

Comment STEP ELEMENT STANDARD SAT UNSAT Number CUE Provide the examinee with a copy of the Initiation Cue (last page of JPM) and a marked up copy of CPS 9071.01A Diesel Driven Fire Pump A Operability Test.

Upon request ONLY, provide the examinee with a copy of CPS 1893.06 Fire Protection Maintenance And Testing Program.

NOTE: JPM steps 1 and 2 can be performed in any order.

• 01 Determines 0FP01PA: Reviews the procedure and discovers the following:

• coolant temperature exceeded section 9.2.2

• 8.2.14 - Determines Acceptance Criteria, and that test performer

• was not run for the failed to correctly required time (section determine engine 9.2.1.1 Acceptance coolant temperature Criteria from step 4.2.1. Actual engine coolant ___

temperature exceeded 200°F.

• 8.2.22 - Determines that test performer failed to run 0FP01PA for the required 30 minutes.

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

TQ-AA-150-J020 Revision 01 Page 7 of 11 JPM556 Comment STEP ELEMENT STANDARD SAT UNSAT Number NOTE: Calculations for 8.2.19 are as follows:

• 8.2.2.a.3 start time - 0124

• 8.2.19 time - 0150

• 8.3.5 time - 0152

• Total time operating at full speed - 28 minutes.

CUE If the examinee identifies at least one of the deficiencies in step 1, cue him/her to determine required actions, if any.

Provide examinee with a copy of CPS 1893.01 Fire Protection Impairment Reporting.

• 02 Determines required action for a For high coolant temperature non-functional Fire Pump. (valid non-functional Fire Pump call):

• Reviews CPS 1893.01 Fire Protection Impairment Reporting Appendix A Fire Protection Functionality ___

Requirements, and determines that the non-functional pump must be restored to FUNCTIONAL status within 7 days or provide an alternate backup pump.

For time requirement not met:

• Surveillance is not met and cannot be credited as such.

However, since the ___

surveillance is not late, the functionality of the pump is not affected.

CUE If requested, inform examinee that the surveillance is not past its late date.

CUE JPM is complete.

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

TQ-AA-150-J020 Revision 01 Page 8 of 11 JPM556 JPM Stop Time:

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

TQ-AA-150-J020 Revision 01 Page 9 of 11 JPM556 JPM

SUMMARY

Operators Name: Emp. ID#:

Job

Title:

EO RO SRO FS STA/IA SRO Cert JPM

Title:

Review CPS 9071.01A Diesel Driven Fire Pump A Operability Test JPM Number: JPM556 Revision Number: 01 Task Number and

Title:

101100.01 Apply the administrative requirements of SURVEILLANCE TESTING PROGRAM Task Standard: The examinee will review CPS 9071.01A and determine:

• Acceptance Criteria of sections 9.2.1.1 and 9.2.2 were not met, and

• the pump must be restored to FUNCTIONAL status within 7 days or an alternate backup pump must be provided.

K/A Number and Importance:

K/A System K/A Number Importance (RO/SRO)

Generic 2.2.12 3.7 4.1 Suggested Testing Environment: Classroom Alternate Path: Yes No SRO Only: Yes No Time Critical: Yes No Reference(s):

Procedure: CPS 9071.01A Revision: 00a CPS 1893.01 Revision: 22a CPS 1893.06 Revision: 13 Actual Testing Environment: Simulator Control Room In-Plant Other Testing Method: Simulate Perform Estimated Time to Complete: 15 minutes Actual Time Used: minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily? Yes No The operators performance was evaluated against standards contained within this JPM and has been determined to be: Satisfactory Unsatisfactory SRRS: 3D.105 (when utilized for operator initial or continuing training)

TQ-AA-150-J020 Revision 01 Page 10 of 11 JPM556 NOTE: Enter finalized grading, comments, and notes relevant to this evaluation in the associated TQ-AA-150-F03A/B. (See AR 4282419).

Evaluators Name (Print):

Evaluators Signature: Date:

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

TQ-AA-150-J020 Revision 01 Page 11 of 11 JPM556 INITIAL CONDITIONS The plant is in Mode 1.

CPS 9071.01A Diesel Driven Fire Pump A Operability Test is field complete for 0FP01PA Diesel Driven Fire Pump A, awaiting supervisory review.

INITIATING CUE Review CPS 9071.01A Diesel Driven Fire Pump A Operability Test.

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

CPS 9071.01A DIESEL DRIVEN FIRE PUMP A OPERABILITY TEST SCOPE OF REVISION:

• Created new procedure to ease burden on Operations and mitigate potential configuration control error.

• Incorporated 9071.01 Revs 0 - 40f

• Incorporated changes from: IR 4231067-46, IR 4153297, IR 4246467, IR 4256368 and IR 4266785 Specific Rev. 0a [Helton]: IR 3991761 Deleted Frequencies and added DISCUSSION step to refer to 1893.06 for current frequencies.

For Training Only CONTINUOUS USE ORIGINATOR: Terry M. Palmer CLASS CODE: SNQN SQR: Robert Rush APPROVAL DATE: 08/12/19 CURRENT CHANGES TO GENERAL REVISION Change # Date List of Affected Pages 0a 03/18/20 1, 3 Rev. 0a Page 1 of 22

CPS 9071.01A TABLE OF CONTENTS 1.0 Purpose 2.0 Discussion/Definitions 3.0 Responsibility 4.0 Precautions 5.0 Prerequisites 6.0 Limitations 7.0 Materials/Test Equipment 8.0 Procedure 8.1 Diesel Fire Pump Prestart Checks 8.2 Startup and Operation of the Diesel Fire Pump 8.3 Stopping the Diesel Fire Pump 8.4 System Restoration 9.0 Acceptance Criteria 10.0 Final Conditions 11.0 References 12.0 Appendices 13.0 Documents Rev. 0a Page 2 of 22

CPS 9071.01A 1.0 PURPOSE The purpose of this procedure is to demonstrate operability of the 0FP01PA, Diesel Fire Pump A. This partially satisfies CPS 1893.01, Fire Protection Impairment Reporting and CPS 1893.06, Fire Protection Maintenance and Testing Program.

2.0 DISCUSSION/DEFINITIONS 2.1 Discussion 2.1.1 Frequency - Refer to 1893.06, Fire Protection Maintenance and Testing Program for required frequencies for this procedure.

2.1.2 The Diesel Fire Pumps serve as the supply to the Fire Protection Water System. They shall be started and demonstrated operable to ensure reliable automatic starting in the event of an emergency.

2.1.3 All failures to meet the acceptance criteria shall be reported and actions taken IAW CPS 1893.01.

2.1.4 To satisfy NFPA 20 requirements, the Diesel Fire Pumps shall operate smoothly at rated speed for at least 30 minutes. To prolong engine life, it is suggested that the Diesel Fire Pumps be run for a minimum of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

2.1.5 Portions of this surveillance may be performed independent for PMT to facilitate inspections due to repairs etc.

2.1.6 Completed test package shall be routed IAW CPS 1011.02, Implementation and Control of Surveillance Testing.

2.1.7 Operation of a Stationary Reciprocating Internal Combustion Engine is subject to the regulations set forth in 40CFR63, Subpart ZZZZ, National Emissions Standards for Hazardous Air Pollutants for Stationary Reciprocating Internal Combustion Engines. These regulations require documentation of runtime of these engines as read on the Engine Runtime meter. Other requirements include documentation of visual inspection of the engines, and periodic sampling of the engine lube oil, all of which are covered by other procedures. <<CM-1>>

Rev. 0a Page 3 of 22

CPS 9071.01A 2.2 Definitions 2.2.1 FIRE PUMP UNLOADED: The fire pump is running at its shutoff head (e.g., no fire water flow).

2.2.2 LECT is the Low Estimate of Engine Coolant Temperature.

2.2.3 HECT is the High Estimate of Engine Coolant Temperature.

2.2.4 TCP is the temperature measured using a contact pyrometer.

3.0 RESPONSIBILITY 3.1 Operations is responsible for proper implementation and performance of this procedure.

3.2 CPS Fire Marshal is responsible for review of this procedure.

3.3 System Manager Fire Protection is responsible for reviewing the test frequency if a fire pump operability test failure occurs.

4.0 PRECAUTIONS 4.1 Hearing protection shall be worn at all times while the Diesel Engine is operating.

4.2.1 Normal operating engine coolant temperature is 160° to 200°F. MAXIMUM engine coolant temperature shall not exceed 200°F, continuously.

IF the maximum normal temperature is reached (200oF),

THEN the engine shall be shut down and the cause of the high temperature investigated.

Temperature Monitoring using a Surface Pyrometer Per ECR 377017, a surface pyrometer may be used to monitor coolant temperature. Per ECR407246 correction constants when using a contact pyrometer are such that, LECT = TCP + 20 °F HECT = TCP + 28 °F Where, LECT is the low estimate of the engine coolant temperature.

HECT is the high estimate of the engine coolant temperature.

TCP is as measured temperature using a contact pyrometer.

Rev. 0a Page 4 of 22

CPS 9071.01A 4.0 PRECAUTIONS (Contd)

For Example:

Given that the engine LECT band is 160 °F (using the temperature gauge 1TI-FP289), the lowest acceptable temperature using a contact pyrometer is:

160 °F - 20 °F= 140 °F.

Given that the engine HECT band is 200 °F (using the temperature gauge 1TI-FP289), the highest acceptable temperature using a contact pyrometer is:

200 °F - 28 °F= 172 °F.

4.2.2 Continuous diesel operation with engine coolant temperature < 140 °F can cause damage to the diesel engine. This does not apply during idle operation IF the minimum normal operating temperature of 160° cannot be maintained, THEN the engine shall be shut down and the cause of the continuous low temperature investigated.

4.3 The Diesel Fire Pump Control Switch has to be placed in the OFF position in order to clear and reset all alarms or trips with the exception of a Low Fuel Level alarm.

4.4 IF the engine should trip on an overspeed condition, THEN the overspeed switch has to be reset by depressing the pushbutton on top of the switch before resetting the controller. Failure to do so will erase the overspeed memory circuit and cause an immediate shutdown of the engine the next time it receives a start signal.

4.5 An Operator shall be stationed near the fire pump room whenever the diesel fire pump is idling to ensure the idle control valve can be restored from the IDLE position to RUN in an emergency. Maintenance Rule availability tracking is not required for fire pumps.

4.6 The Exhaust Fan 1VH03CA is started as a precautionary measure to minimize personnel safety consequences in the unlikely event of an exhaust leak in the pump rooms.

Operation of the exhaust fans is not a condition for Fire Pump operability. The Fire Pumps can still be run even if the exhaust fans are out of service.

Rev. 0a Page 5 of 22

CPS 9071.01A 4.0 PRECAUTIONS (contd) 4.7 Personnel should be cognizant of the CO Detector in the Fire Pump rooms. The yellow WARNING light will light at CO levels of 35 ppm. 35 ppm is the eight-hour time weighted average for CO exposure and therefore is not an immediate threat to personnel safety. The red WARNING light will light at a CO level of 50 ppm. An audible horn will sound at 100 ppm. Whenever any warning lights light and/or the meter alarms, all personnel in the room shall secure any work being done (fire pump can continue to run), leave the room and notify SMngt.

A portable gas analyzer capable of detecting CO may be used in place of the installed CO Detector.

4.8 When the fire pump engine is not running, its respective tachometer may not read zero.

The pointer position when de-energized is random.

Rev. 0a Page 6 of 22

CPS 9071.01A INITIAL 5.0 PREREQUISITES 5.1 Fire Pump is available for testing. EO1 NOTE Periodically MM performs an oil sample which is required to be performed within 30 minutes of the engine shutdown. Perform the following step for MM to determine if this oil sample is required.

5.2 Notify MM department that Fire Pump A will be run per the monthly surveillance and provide approx. time that the engine will be shutdown. EO1 NOTE Quarterly Chemistry needs to perform 9981.02, Fire Protection Fuel Oil Analysis. This surveillance requires the associated Fire Pump to be running for at least 1Hr prior to the sampling.

Perform the following step for Chemistry to determine if this sample is required.

5.3 Notify Chemistry department that Fire Pump A will be run per the monthly surveillance and provide approx. time that the engine will be started. EO1 NOTE A portable gas analyzer capable of detecting CO may be used in place of the installed CO Detector 5.4 The MSA Toxgard II Carbon Monoxide Monitor, installed near north wall in fire pump room for 0FP01PA, Diesel Fire Pump A, indicates SYSTEM OK (No Alarms). EO1 Rev. 0a Page 7 of 22

CPS 9071.01A INITIAL 5.0 PREREQUISITES (contd) 5.5 In conjunction with SMngt, review the following impact statements to determine required plant status to perform this test:

OPERABILITY IMPACT: N/A SYSTEMS AFFECTED: Fire Protection Water System.

The Diesel Fire Pump being tested cannot auto start to full speed operation when its IDLE/RUN switch is in IDLE.

AFFECTED ANNUNCIATORS AND COMPUTER POINTS: Device 22-24, ENGINE RUN DIESEL FIRE PUMP A, 1H13-P841 RPS TRIP: N/A CRVICS ISOLATION: N/A REQUIRED OPERABLE CHANNELS: N/A PLANT/SYSTEM CONDITIONS REQUIRED TO CONDUCT TEST:

• No special conditions required. Test may be done at any time.

• Fire pump not being tested should be operable.

IF not operable, THEN ensure compensatory actions per CPS 1893.01 are in effect.

COINCIDENT CHANNELS THAT PREVENT ACTUATION: N/A 5.6 Impact Matrix reviewed

____________________/_____________________

EO1 SRO1 Test Performer SMngt 5.7 Obtain SMngt permission to perform this surveillance.

Date/Time ________/________

Today 0030 SMngt________________

SRO1 5.8 IF crane operations are in progress in the screenhouse, THEN prior to placing 1AP48E4EL MCC breaker to notify crane operator that crane operations will be suspended to start Diesel fire pump room exhaust fans in support of the operatbility test for the diesel driven fire pump. N/A Rev. 0a Page 8 of 22

CPS 9071.01A 6.0 LIMITATIONS 6.1 IF fuel oil tank level drops below 275 gallons, THEN stop the Diesel Fire Pump and declare it inoperable. Refer to CPS 1893.01 for additional required actions.

6.2 IF a fire occurs during performance of this surveillance, THEN stop this procedure and restore the system to normal operation.

6.3 IF abnormal conditions exist (e.g., oil pressure below 40 psig, coolant temperature above 200°F, excessive smoke, unusual noise, or high vibrations),

THEN the diesel engine shall be stopped.

6.4 Both Fire Pumps Shall Not be Idled concurrently. This lineup disables rated speed operation of both pumps.

7.0 MATERIALS/TEST EQUIPMENT 7.1 Oil absorbent rags and container for diesel fuel.

7.2 Ruler or tape measure.

7.3 Hose to drain water from test gage and from fuel oil tank.

7.4 Fuel Oil Flush Bottle.

7.5 Bucket.

7.6 Adjustable wrench for pump discharge relief valve.

Rev. 0a Page 9 of 22

CPS 9071.01A INITIAL 8.1 Diesel Fire Pump Prestart Checks 8.1.1 Perform the following prestart checks in any order.

1. Verify engine water heater is operational and maintaining diesel warm to the touch. EO1

2. Verify engine lubricating oil level is between HI and LOW marks on the dipstick. EO1

3. Verify adequate coolant level for 0FP01PA, Diesel Fire Pump, coolant level is 21/2 inches below the top of the fill neck. EO1

4. Verify gear drive oil level even with bottom threads of fill hole. EO1

5. Record the CO reading. (ppm) 1

_______ EO1 NOTE Placekeeping may be suspended until completion step 8.1.1.6

6. Drain the fuel oil tank to check for water and sediment as follows:

1) Remove associated pipe cap. EO1

2) With flush bottle under drain line, throttle open 0FP610A, Fuel Oil Tank 0DO01TA drain until 1 liter of fuel is obtained EO1___

4) Shut the 0FP610A, Fuel Oil tank 0DO01TA drain EO1

5) Replace pipe cap. EO1

6) IF water or sediment is found, THEN notify Ops Mgnt EO1___

Rev. 0a Page 10 of 22

CPS 9071.01A INITIAL 8.1 Diesel Fire Pump Prestart Checks (contd) 8.1.1 (contd)

7. Record fuel oil tank level from 1LI-FP282.

Fuel oil level ________ 400 EO1 NOTE Run hour meter log entry required per 40CFR63 Include Diesel Fire Pump EIN and procedure number in run hour meter log entry

8. Record the Run Hour meter number in the Operator Logs. <<CM-1>>

Run Hours XXX.X

____________(hrs) EO1 NOTE Contact Security prior to entry into Isolation Zone.

9. Inspect Diesel Fire Pump Combustion Air Supply outside vent piping for obstructions from ground level. EO1 8.2 Startup and Operation of the Diesel Fire Pump 8.2.1 IF Circulating Water System is in operation, THEN contact MCR to determine lake temperature from 1TI-CW009, CW CDSR 1A INLT TEMP, at P800.

Lake temperature ________ 56 EO1 WARNING Potential Shock Hazard. Take appropriate electrical safety measures.

8.2.2 Verify 1AP48E4EL, Overhead Crane HCO5G, Breaker is OFF.

8.2.3 IF 1AP48E4EL is ON, THEN perform the following:

1) Ensure crane operations are secured.

2) Place 1AP48E4EL to OFF.

8.2.4 Start 1VH03CA, N Fire Pump Room Exhaust Fan. EO1 Rev. 0a Page 11 of 22

CPS 9071.01A INITIAL 8.2 Startup and Operation of the Diesel Fire Pump (Contd) 8.2.5 Place bucket under 1FP138B, Test Gauge Drain Valve. EO1 NOTE 8.2.6 may require two persons to perform.

8.2.6 Perform the following simultaneously:

1) While observing Pump Discharge Pressure Switch Test Gauge, 1PI-FP148, slowly open 1FP138B, Test Gauge Drain Valve. EO1

2) Record pressure diesel engine starts.

Start pressure _________ 143 EO1

3) Record time diesel starts.

0124 Start time __________ EO1

4) Confirm diesel engine starts at 137 - 143 psig for 0FP01PA. EO1

5) Observe that the LOW OIL PRESSURE light at local panel 0FP01JA comes on momentarily during cranking. EO1

6) Observe the battery voltmeters on local panel 0FP01JA during engine cranking.

Record the battery which the engine starts on and verify battery voltage remains 18 VDC during cranking.

Starting battery bank __________ A EO1 8.2.7 Shut 1FP138B, Test Gauge Drain Valve. IV___/___

EO1 EO2 8.2.8 Verify cooling water flow by observing temperature difference between cooling water inlet and outlet piping. EO1 Rev. 0a Page 12 of 22

CPS 9071.01A INITIAL 8.2 Startup and Operation of the Diesel Fire Pump (Contd)

NOTE Failure of tach. 1SIFP306 does not make the fire pump inoperable.

8.2.9 Record engine running at rated speed 2347 - 2447 RPM using tach 1SIFP306.

Engine speed __________2390 EO1 8.2.10 Record charging Generator Output of 0-20 amps as Indicated on 1II-FP283.

Generator amps __________ 5 EO1 8.2.11 Verify pump discharge pressure 165-175 psig as indicated by 1PI-FP008.

Discharge pressure __________ 171 EO1 8.2.12 IF Discharge pressure is outside limits, THEN 1) Remove plastic cap from 1FP013 0FP01PA Discharge Relief Valve pressure regulator.

2) Loosen pressure regulator adjustment bolt locking nut.

3) Adjust pressure regulator adjustment N A bolt until pressure is approximately in the middle of the band.

4) Re-tighten pressure regulator adjustment bolt locking nut.

5) Replace pressure regulator plastic cap.

6) Record final discharge pressure.

Discharge pressure __________ _______

8.2.13 Observe oil spray in sightglass on angle gear drive unit. EO1 Rev. 0a Page 13 of 22

CPS 9071.01A INITIAL 8.2 Startup and Operation of the Diesel Fire Pump (Contd)

CAUTION Normal engine coolant temperature range is 160°F-200°F. Continuous diesel operation with engine coolant temperature greater than 200°F, or continuous diesel operation with engine water temperature less than 140°F (120°F if using a surface contact pyrometer - ECR 407246), can damage the diesel. The 140°F limitation does not apply during idle operations.

See limitations 4.2.1 and 4.2.2.

NOTE A surface contact pyrometer may be used to obtain engine coolant temperature if the installed temperature indicator is malfunctioning. When using a surface contact pyrometer, the normal engine coolant range would be 140-172°F.

8.2.14 Record engine coolant temperature as indicated on 1TI-FP289 or contact pyrometer.

Method: Contact Pyrometer_____ X 1TI-FP289_____

Engine coolant temperature: __________ 195 F EO1 NOTE 1 : Pyrometer reading 175 F, LECT= 175+20=195 F NOTE (per 4.2.1)

Oil pressure will read high until engine is at operating temperature. High oil pressure during start up is not cause for concern.

8.2.15 Verify oil pressure is greater than 40 psig as indicated on 1PI-FP288.

Oil pressure __________ 80 psig EO1 8.2.16 IF N 0FP01PA, Diesel Fire Pump Oil pressure is less than 40 psig, A

THEN Shutdown Fire Pump to preclude damage.

8.2.17 Verify that MCR received device 22-24, ENGINE RUN DIESEL FIRE PUMP A, on 1H13-P841. RO1 / EO1 8.2.18 To reduce carbon monoxide levels in the room, Start 1VH03CA, N Fire Pump Room Exhaust Fan. EO1 Rev. 0a Page 14 of 22

CPS 9071.01A INITIAL 8.2 Startup and Operation of the Diesel Fire Pump (Contd)

NOTE Placekeeping may be suspended until completion step 8.2.19 8.2.19 Flush cooling water strainer as follows:

1. Place bucket under DFP4A, Cooling Water Strainer Flush Valve. EO1

2. Open DFP4A, Cooling Wtr Strainer Flush Valve. EO1

3. Ensure no debris flows from the strainer. EO1

3. Shut DFP4A, Cooling Wtr Strainer Flush Valve. IV ___/___

EO1 EO2 8.2.20 Record cooling water pressure FOR 0FP01PA for trending purposes:

Cooling water pressure _________ 14 psig EO1 NOTES

• NFPA codes require diesel engine operation at rated speed for a minimum of 30 minutes.

• Operating diesel engine for 60 minutes at rated speed prolongs engine life.

• Quarterly Chemistry needs to perform 9981.02, Fire Protection Fuel Oil Analysis. This surveillance requires the associated Fire Pump to be running for at least 1Hr(60 minutes) prior to the sampling. Perform the following step for Chemistry to determine if this sample is completed, if it was required.

8.2.21 IF required to be performed, THEN verify Chemistry department has completed 9981.02, Fire Protection Fuel Oil Analysis. EO1 8.2.22 Operate diesel at rated speed for at least 30 minutes. EO1 Rev. 0a Page 15 of 22

CPS 9071.01A INITIAL 8.2 Startup and Operation of the Diesel Fire Pump (Contd)

CAUTION Normal engine coolant temperature range is 160°F-200°F. Diesel operation with engine coolant temperature greater than 200°F, or continuous diesel operation with engine water temperature less than 140°F (120°F if using a surface contact pyrometer - ECR 407246), can damage the diesel. The 140°F limitation does not apply during idle operations. See limitations 4.2.1 and 4.2.2.

NOTE A surface contact pyrometer may be used to obtain engine coolant temperature if the installed temperature indicator is malfunctioning. When using a surface contact pyrometer, the normal engine coolant range would be 140-172°F. ( ECR 407246) 8.2.18 Record engine coolant temperature as indicated on 1TI-FP289 or contact pyrometer.

Method: Contact Pyrometer_______ X 1TI-FP289_______

See NOTE 1 _______

Engine coolant temperature: __________ 195 F EO1 Page 14 8.2.19 Verify diesel engine has run smoothly for at least 30 minutes and record the time.

Time 0150

__________ EO1 8.2.20 IF conducting yearly PMRQ 00158480-01, THEN Record pressure at 0PI-FP516 and verify pressure is greater than 65 psig (Hose Station 0FP607A).

Pressure N/A

__________ psig N/A 8.2.21 IF conducting yearly PMRQ 00158480-01, THEN Record pressure at 0PI-FP511 and verify pressure is greater than 65 psig (Hose Station 0FP605A).

Pressure N/A

__________ psig N/A Rev. 0a Page 16 of 22

CPS 9071.01A INITIAL 8.3 Stopping the Diesel Fire Pump CAUTION Idling both Fire Pumps concurrently disables the low header pressure automatic start signal and rated speed operation for both pumps.

8.3.1 Verify 0FP01PB, Diesel Fire Pump is not idling. EO1 8.3.2 Record engine speed and pump discharge pressure.

(1SIFP306) Engine Speed _________ 2390 rpm (1PI-FP148) Discharge pressure ________ 171 psig EO1 8.3.3 Record the CO reading. (ppm) 1

_______ EO1 8.3.4 Remove padlock and Lockout device from Idle Control Valve. EO1 CAUTION Continuous presence of an Operator near the diesel fire pump room during diesel fire pump idling operations ensures the fire pump can be placed in RUN if required in an emergency.

8.3.5 Place Idle Control Valve in IDLE and record time.

0152 Time _________ EO1 NOTE 0FP01PA, Diesel Fire Pump idle speed range is 586 - 1224 rpm.

8.3.6 Record 0FP01PA, Diesel Fire Pump A idle speed:

1100 rpm Idle speed __________ EO1 Rev. 0a Page 17 of 22

CPS 9071.01A INITIAL 8.3 Stopping the Diesel Fire Pump (Contd)

CAUTION When idling, Low Oil Pressure could alarm (below 10 psig). Diesel engine operation below 8 psig can damage the diesel.

8.3.7 During Idle ensure the following:

1. Oil Pressure is at least 8 psig. EO1

2. Engine coolant temperature is below 200°F, indicated on 1TI-FP289, N/A OR 172°F with contact pyrometer. EO1

3. IF Oil pressure drops below 8 psig, OR Engine coolant temperature rises to greater than or equal to 200°F (172°F with contact pyrometer).

THEN Shutdown the engine and inform SMngt.

(N/A if not used) N/A 8.3.8 After at least 30 minutes of engine running time at idle speed, stop engine by pressing STOP button and record time.

0230 Time __________ EO1 Rev. 0a Page 18 of 22

CPS 9071.01A INITIAL 8.4 System Restoration 8.4.1 Take the Idle Control Valve to RUN. IV EO1 /EO2 8.4.2 Install Lockout Device and Padlock to Idle Control Valve. IV EO1 /EO2 8.4.3 Verify Device 22-24, ENGINE RUN DIESEL FIRE PUMP A, annunciator at 1H13-P841 can be cleared. RO1 / EO1 8.4.4 Ensure 0D001TA, Diesel Fire Pump Day Tank, contains at least 275 gallons of fuel. EO1 8.4.5 Record fuel oil tank level from 1LI-FP282.

375 gal EO1 Fuel oil level __________ _______

8.4.6 IF fuel oil tank level is 350 gallons, N/A THEN inform MCR. (N/A if MCR not notified) _______

EO1 8.4.7 Stop N Fire Pump Room Exhaust Fan 1VH03CA. _______

8.4.8 IF Room temperature is less than 78°F THEN Verify damper LV1-7 is Closed. EO1 8.4.9 Observe that battery ammeter has returned to less than 2 amps charging current within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after engine starting. EO1 8.4.10 Log the Run Hour meter number in the Operator Logs fulfilling a 40CFR63 requirement. <<CM-1>>

Run Hours XXX.X

____________(hrs) EO1 8.4.11 Notify SMngt of test completion. EO1 Date/TIME Today / 0300 Rev. 0a Page 19 of 22

CPS 9071.01A 9.0 ACCEPTANCE CRITERIA 9.1 Operability Requirements None 9.2 Other Requirements 9.2.1 CPS 1893.06 Appendix A Requirements

1. The Diesel Fire Pump started from ambient conditions and operated satisfactorily for at least 30 minutes on recirculation flow.

2. 0D001TA, Diesel Fire Pump Day Tank, contains at least 275 gallons of fuel.

3. IF not acceptable, THEN notify SM and CPS Fire Marshal, AND Take applicable actions IAW CPS 1893.01.

9.2.2 CPS 1893.06 Appendix B Requirements CAUTION Continuous diesel operation with engine water temperature less than 140°F, can damage the diesel. 140°F limitation does not apply during idle operations. See limitations 4.2.1 and 4.2.2.

When using a contact pyrometer, the operating limitation would be 120°F. (ECR 407246)

1. The Diesel Fire Pump operated at normal temperatures of 160-200°F on 1TI-FP289, or 140-172°F with contact pyrometer, and ran smoothly at rated speed for at least 30 minutes.

2. The Fire Protection Pump operates to maintain the fire protection water system pressure greater than or equal to 65 psig at hose station 0FP605A and hose station 0FP607A. (A drop below this value for up to 5-6 seconds during pump starts does not fail this requirement).

3. IF not acceptable, THEN notify SM and CPS Fire Marshal, AND Take applicable actions IAW CPS 1893.01.

Rev. 0a Page 20 of 22

CPS 9071.01A 10.0 FINAL CONDITIONS The Diesel Fire Pump is returned to Automatic Standby.

11.0 REFERENCES

11.1 Licensing Basis Documents 11.1.1 ORM 6.8.1.e 11.1.2 USAR 9.5.1.2.1, 9.5.1.2.2.2 11.1.3 USAR Appendix E, 3.1.2.6, 4.0.E.2.c 11.2 Procedures 11.2.1 CPS 1019.00, Control of Chemicals 11.2.2 CPS 1893.01, Fire Protection Impairment Reporting 11.2.3 CPS 3213.01, Fire Detection and Protection 11.2.4 CPS 9071.02, Diesel Fire Pump Capacity Check/Sequential Starting 11.2.5 CPS 1893.06, Fire Protection Maintenance and Testing Program 11.3 Design/Vendor/Print/Other 11.3.1 K2830.0001 Technical Manual for Diesel Driven Fire Pumps 11.3.2 Engineering Evaluation EE-00-029, Rev. 0 11.3.3 NFPA-20-1976/CCT No. 001896/CCT No. 043084 11.4 Commitments 11.4.1 CM-1: 40CFR63, Subpart ZZZZ, National Emissions Standards for Hazardous Air Pollutants for Stationary Reciprocating Internal Combustion Engines 12.0 APPENDICES - None 13.0 DOCUMENTS - None Rev. 0a Page 21 of 22

CPS 9071.01A SUPPLEMENTAL REVIEW SHEET CORRECTIVE ACTION TAKEN 9.1 Operability Acceptance Criteria - None 9.2 Other Criteria:

As Applicable:

Initiated Issue Report _________ (yes/no)

Initiated Issue Report No. ________

COMMENTS/DEFICIENCIES:___________________________________________________

REVIEW AND APPROVAL Fireme Marshall xx/xx/xxxx CPS Fire Marshal: ________________________________________________

(Signature) (Date)

Shift Management: ________________________________________________

(Signature) (Date)

FP System Manager: ________________________________________________

(Signature) (Date)

Rev. 0a Page 22 of 22

TQ-AA-150-J020 Revision 01 Page 1 of 14 Job Performance Measure Select Volunteers and Authorize an Emergency Exposure for a Life-Saving Operation JPM Number: JPM516 Revision Number: 02 Date: 8/20/2020 Developed By: Bill Kiser / 8/20/20 Instructor: Print / Sign Date Reviewed By: /

SME or Instructor: Print / Sign Date Reviewed By: /

Operations Representative: Print / Sign Date Approved By: /

Training Department: Print / Sign Date SRRS: 3D.105 (when utilized for operator initial or continuing training)

TQ-AA-150-J020 Revision 01 Page 2 of 14 JPM516 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation.

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

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

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

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

4. Initial setup conditions are identified.

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

6. Task standards identified and verified by instructor or SME review.

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

8. IAW NUREG 1021 Appendix C, clearly identify the task standard (i.e., the predetermined qualitative or quantitative outcome) against which task performance will be measured.

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

Procedure: EP-AA-113 Revision: 15 Procedure: EP-AA-113-f-02 Revision: B Procedure: Revision:

Procedure: Revision:

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

11. Verify performance time is accurate.

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

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

/

SME / Instructor (Print/Sign) Date

/

SME / Instructor (Print/Sign) Date

/

SME / Instructor (Print/Sign) Date SRRS: 3D.100; There are no retention requirements for this section

TQ-AA-150-J020 Revision 01 Page 3 of 14 JPM516 Revision Record (Summary)

Revision # Summary 6/14/13 - New JPM developed for the ILT 12-1 NRC Exam. JPM was 00 modeled after a JPM administered during an ILT Exam at LaSalle in 2012.

01 7/11/16 - Updated procedure references.

02 8/20/20 - Updated references. Updated JPM template.

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

TQ-AA-150-J020 Revision 01 Page 4 of 14 JPM516 SETUP INSTRUCTIONS

1. No setup is required for this JPM.

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

TQ-AA-150-J020 Revision 01 Page 5 of 14 JPM516 INITIAL CONDITIONS A General Emergency has been declared.

Fuel failure has occurred together with a large break LOCA.

Containment venting is in progress in order to maintain containment integrity.

The TSC has been activated, but has not been staffed.

The appropriate EAL has been declared.

An emergency lifesaving operation must be performed.

• The operation is estimated to take between 12 and 15 minutes

• There is a 200 R/hr field in the area The operation requires two (2) people to enter the field. Three (3) people have volunteered:

• Bob Black, Employee # B537347 o Has never received an emergency exposure o He is familiar with the procedures for rescuing the victim, and is fully aware of the risks involved.

• Gary Green, Employee # B734753 o Has never received an emergency exposure o He is familiar with the procedures for rescuing the victim, and is fully aware of the risks involved.

• Walter White, Employee # B573472 o Received a 27 R dose at a reactor in South Africa when he volunteered to assist in a similar life-saving operation.

o He is familiar with the procedures for rescuing the victim, and is fully aware of the risks involved.

Per RP-AA-203 Exposure Control and Authorization, a Rad Protection Supervisor has briefed the three volunteers and presented you with the forms to authorize the emergency exposure.

INITIATING CUE As the acting Station Emergency Director, perform the actions necessary to permit the life-saving operation.

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

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

TQ-AA-150-J020 Revision 01 Page 6 of 14 JPM516 Information For Evaluators Use:

UNSAT requires written comments on respective step.

• Denotes critical steps.

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

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

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

The timeclock starts when the candidate acknowledges the initiating cue.

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

TQ-AA-150-J020 Revision 01 Page 7 of 14 JPM516 JPM Start Time: JPM Sequence #: of Task Standard:

The examinee will evaluate three candidates for a lifesaving operation in accordance with EP-AA-113:

• determine one candidate is ineligible, and

• authorize the remaining two candidates to perform the work.

Comment STEP ELEMENT STANDARD SAT UNSAT Number CUE Provide the examinee with copies of:

• Initiating Cue (last page of JPM)

• Marked Up copies of EP-AA-113-F-02 Authorization For Emergency Exposure (pages 11-14 of JPM)

• EP-AA-113 Personnel Protective Actions 01 4.3.1 Examinee determines exposure is:

Makes emergency exposure determination.

• for a bona fide emergency.

• In excess of 5 Rem TEDE ___

o calculated to be in excess of 25 Rem (12 to 15 minutes in a 200 Rem/Hr field is 40 to 50 Rem).

02 4.3.2.1 Examinee verifies applicable forms:

Verifies EP-AA-113-F-02 Authorization for Emergency

• have Name / Date / Time /

Exposure form completed by Employee ID # / Current Emergency Worker. Annual Exposure / Reason ___

For Request blocks filled in.

• have the REQUESTING AUTHORIZATION TO EXCEED box checked for 25 Rem TEDE.

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

TQ-AA-150-J020 Revision 01 Page 8 of 14 JPM516 Comment STEP ELEMENT STANDARD SAT UNSAT Number 03 4.3.2.2 Examinee verifies applicable Verifies that emergency workers forms have the Rad Protection Management signature /Date /

have been briefed on the Time. ___

possible health effects of the anticipated exposure.

04 4.3.2.3 Examinee verifies applicable Verifies that emergency workers forms have signatures for Bob Black, Gary Green, and Walter have volunteered.

White. ___

• 05 4.3.3 NOTE Examinee eliminates Walter White as a potential rescuer Recognizes emergency and the examinee does not exposure in excess of 25 Rem sign this volunteers form EP- ___

TEDE is to be limited to once in a lifetime. AA-113-F-02.

• 06 4.3.3.1 Examinee signs the EP-AA-113-F-02 for Bob Black and Completes Authorization for Gary Green as Station Emergency Exposure for Bob Emergency Director. ___

Black and Gary Green CUE JPM is complete.

JPM Stop Time:

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

TQ-AA-150-J020 Revision 01 Page 9 of 14 JPM516 JPM

SUMMARY

Operators Name: Emp. ID#:

Job

Title:

EO RO SRO FS STA/IA SRO Cert JPM

Title:

Select Volunteers and Authorize an Emergency Exposure for a Life-Saving Operation JPM Number: JPM516 Revision Number: 02 Task Number and

Title:

997777.03 Emergency Plan Activities performed by an SRO Task Standard: The examinee will evaluate three candidates for a lifesaving operation in accordance with EP-AA-113:

• determine one candidate is ineligible, and

• authorize the remaining two candidates to perform the work.

K/A Number and Importance:

K/A System K/A Number Importance (RO/SRO)

Generic 2.3.4 3.2 3.7 Suggested Testing Environment: Classroom Alternate Path: Yes No SRO Only: Yes No Time Critical: Yes No Reference(s):

Procedure: EP-AA-113 Revision: 15 EP-AA-113-F-02 Revision: B Revision:

Actual Testing Environment: Simulator Control Room In-Plant Other Testing Method: Simulate Perform Estimated Time to Complete: 15 minutes Actual Time Used: minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily? Yes No The operators performance was evaluated against standards contained within this JPM and has been determined to be: Satisfactory Unsatisfactory SRRS: 3D.105 (when utilized for operator initial or continuing training)

TQ-AA-150-J020 Revision 01 Page 10 of 14 JPM516 NOTE: Enter finalized grading, comments, and notes relevant to this evaluation in the associated TQ-AA-150-F03A/B. (See AR 4282419).

Evaluators Name (Print):

Evaluators Signature: Date:

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

TQ-AA-150-J020 Revision 01 Page 11 of 14 JPM516 Bob Black XX XX XXXX XX XX B537347 152 Lifesaving operation.

X Bob Black XX/XX/XXXX XX:XX R. P. Manager XX/XX/XXXX XX:XX SRRS: 3D.100; There are no retention requirements for this section

TQ-AA-150-J020 Revision 01 Page 12 of 14 JPM516 Gary Green XX XX XXXX XX XX B734753 57 Lifesaving operation.

X Gary Green XX/XX/XXXX XX:XX R. P. Manager XX/XX/XXXX XX:XX SRRS: 3D.100; There are no retention requirements for this section

TQ-AA-150-J020 Revision 01 Page 13 of 14 JPM516 Walter White XX XX XXXX XX XX B573472 98 Lifesaving operation.

X Walter White XX/XX/XXXX XX:XX R. P. Manager XX/XX/XXXX XX:XX SRRS: 3D.100; There are no retention requirements for this section

TQ-AA-150-J020 Revision 01 Page 14 of 14 JPM516 INITIAL CONDITIONS A General Emergency has been declared.

Fuel failure has occurred together with a large break LOCA.

Containment venting is in progress in order to maintain containment integrity.

The TSC has been activated, but has not been staffed.

The appropriate EAL has been declared.

An emergency lifesaving operation must be performed.

• The operation is estimated to take between 12 and 15 minutes

• There is a 200 R/hr field in the area The operation requires two (2) people to enter the field. Three (3) people have volunteered:

• Bob Black, Employee # B537347 o Has never received an emergency exposure o He is familiar with the procedures for rescuing the victim, and is fully aware of the risks involved.

• Gary Green, Employee # B734753 o Has never received an emergency exposure o He is familiar with the procedures for rescuing the victim, and is fully aware of the risks involved.

• Walter White, Employee # B573472 o Received a 27 R dose at a reactor in South Africa when he volunteered to assist in a similar life-saving operation.

o He is familiar with the procedures for rescuing the victim, and is fully aware of the risks involved.

Per RP-AA-203 Exposure Control and Authorization, a Rad Protection Supervisor has briefed the three volunteers and presented you with the forms to authorize the emergency exposure.

INITIATING CUE As the acting Station Emergency Director, perform the actions necessary to permit the life-saving operation.

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

EP-AA-113 Revision 15 Page 1 of 15 Level 2 - Reference Use PERSONNEL PROTECTIVE ACTIONS

1. PURPOSE 1.1. This procedure provides the necessary guidance used in determining onsite personnel protective actions during an event.

Assembly, Accountability and Evacuation REFER to Section 4.1 Habitability REFER to Section 4.2 Emergency Exposure Limits REFER to Section 4.3 KI Assessment REFER to Section 4.4

2. TERMS AND DEFINITIONS 2.1. Accountability - Accountability is the process of verifying the location of personnel who are inside the Protected Area. That is, any personnel within the Protected Area who have not carded into the card reader are identified as missing (unaccounted for). Accountability is required to be performed within 30 minutes of declaration of a Site Area or General Emergency (the names of any missing persons identified by security and the number of missing provided to the Shift Emergency Director). The accountability process continues until all missing personnel are accounted.

Accountability is conducted at a Site Area or General Emergency, if not previously initiated. Accountability may be conducted at the Alert level following TSC activation, at the discretion of the Station Emergency Director.

2.2. Assembly - Assembly occurs at a Site Area Emergency (or at the discretion of the Station Emergency Director). On-duty and ERO personnel assemble in the emergency response facilities. All other non-essential personnel, contractors and visitors are directed to report to either an onsite or offsite Assembly Area. The Assembly Area is used to coordinate the need for any immediate additional resources and to establish an ERO shift relief roster and schedule.

EP-AA-113 Revision 15 Page 2 of 15 2.3. Evacuation - A site evacuation is required at the Site Area Emergency classification level in conjunction with Accountability actions. Site evacuation may be called for at any lower classification; however, conditions that require a site evacuation are inherently defined as Site Area Emergency events and should be classified as such.

Evacuation can involve the movement of large numbers of personnel outside of the Protected Area by keying out of the turnstiles. Evacuation may warrant station egress control by Security. Security provides specific instructions to personnel leaving the Protected Area. Evacuees may be directed to a Relocation Center (offsite assembly areas) for monitoring and decontamination, or sent home. Other situations that involve the evacuation of personnel from occupied localized onsite areas are controlled on a case-by-case basis.

2.4. OCA - Owner Controlled Area. Company owned property on which a nuclear station is located and may include Exelon Nuclear leased-lands adjacent to that nuclear station.

2.5. Protected Area - Area controlled by Security and surrounded by a double fence. Access is normally gained through the Main Access Facility (or Gatehouse).

2.6. Release - A Release in Progress is defined as any radioactive release that is a result of, or associated with, the emergency event.

2.7. Thyroid Blocking Agent - an agent which when properly administered to an individual will result in sufficient accumulation of stable iodine in the thyroid to prevent significant uptake of radioiodine. Potassium Iodide (KI) is such an agent.

3. RESPONSIBILITIES 3.1. The Shift Manager (Shift Emergency Director) shall perform the responsibilities of the Station Emergency Director until relieved.

3.2. The Station Emergency Director is responsible for the following protective actions:

Authorization of emergency exposure greater than 5 Rem (per EPA-400 lower limits).

Authorization for issuance of KI to Exelon Nuclear emergency workers and/or onsite personnel.

Direction of Assembly, Accountability and Evacuation of personnel.

EP-AA-113 Revision 15 Page 3 of 15 3.3. The respective Radiation Protection Manager (TSC or EOF) is responsible for approval of emergency exposures below 5 Rem (EPA-400 lower limits) for Exelon personnel associated with response actions under their facilitys direction.

3.4. The Security Shift Supervisor (or Security Coordinator when the TSC is activated) is responsible for performing Accountability, controlling site access, and coordinating Site and OCA Evacuations.

3.5. The Security Coordinator in the TSC is responsible for coordinating activities between the TSC and the Security force.

3.6. The Operations Manager and Maintenance Manager are responsible for coordinating Search and Rescue Teams and Assembly Area rosters.

NOTES: Protective Actions for the onsite workers shall be based on preventing or minimizing radiological exposures to the emergency workers onsite.

For NMP and JAF Only - NMP and JAF stations share a site boundary.

Personnel Protective Actions should be considered at the co-located facility when either JAF or NMP classifies at a Site Area Emergency or GE.

4. MAIN BODY 4.1. Assembly, Accountability and Evacuation 4.1.1. Protective Measure Guidelines

1. Accountability is required to be conducted at a Site Area or General Emergency, if not previously initiated and maintained. Accountability may be conducted at the Alert level at the discretion of the Station Emergency Director, or Shift Manager (Shift Emergency Director) prior to TSC activation.

A. Accountability and evacuation of non-essential site personnel should also be considered when a security-related Unusual Event or Alert has been declared.

B. Accountability shall be initiated expeditiously, but only after evaluating the need for offsite assembly and appropriate evacuation route based on radiological release and meteorological conditions.

EP-AA-113 Revision 15 Page 4 of 15 C. Once initiated, accountability is required to be performed (i.e., the names of any missing persons identified by security and the number of missing provided to the Station Emergency Director) within 30 minutes of the declaration of a Site Area Emergency or General Emergency. The accountability process continues until all missing personnel are accounted.

2. A Site Evacuation may be delayed if the health and safety of the plant personnel may be in jeopardy, such as severe weather or due to a security-related Unusual Event or Alert.

3. Non-essential personnel evacuating the site, contractors and visitors, shall report to a Remote (Off-Site) Assembly Area, if designated, for radiological monitoring and decontamination as warranted.

4. Protected Area access is halted during personnel accountability, except for the following:

ERO responders requiring access to staff the Operations Support Center (OSC) and/or Technical Support Center (TSC).

Direct approval from the TSC Security Coordinator or Shift Manager for others.

5. Accountability, once achieved, is maintained by restricting Protected Area access and controlling/tracking the movement of on-shift personnel or ERO personnel on site in or out of their respective emergency response facility.

4.1.2. Determination of Actions NOTE: Site Evacuation of non-essential personnel shall be conducted immediately after a Site Area or General Emergency has been declared. An exception may be made for events that could require the pre-planned evacuation to be rerouted or delayed such as:

Severe weather, radiological or other hazardous conditions threaten safe movement of personnel.

A security threat is occurring which could have an adverse impact on security response or personnel while leaving the site.

1. If a Site Area Emergency has been declared, then immediately PERFORM protective measure steps per EP-AA-113-F-07, Emergency Director Assembly, Accountability and Evacuation Checklist.

EP-AA-113 Revision 15 Page 5 of 15 NOTE: Site Assembly and/or Site Evacuation of non-essential personnel should be considered when a security related Unusual Event or Alert has been declared.

2. If a Site Area Emergency has not been declared, then EVALUATE the need for and ability to conduct a Site Assembly and/or Site Evacuation.

A. CONDUCT a Site Assembly whenever it has been determined that:

1. Excess dose or other dangers exist to the onsite personnel.

2. Positive control of location and movement of all onsite personnel is necessary for support of response efforts.

B. CONDUCT a Site Evacuation whenever it has been determined that:

1. Hazardous conditions exist that necessitate the removal of all non-essential personnel from the site.

2. Positive control of location and movement of essential personnel is necessary for support of response efforts.

4.2. Habitability 4.2.1. DETERMINE if radiological controls are required to protect onsite personnel.

The need for radioactive controls shall be based on monitored radioactive releases, exposure levels, and plant status information. Standard Radiation Protection policies and procedures shall form the basis of the decision-making for the administration of radiological controls.

4.2.2. DOCUMENT the decision to use radiological controls that differ from standard Radiation Protection practices in position logs.

4.2.3. EVALUATE radiological controls for continuously occupied areas for emergency workers using EP-AA-113-F-01, On-Site Habitability Checklist.

4.2.4. USE onsite radiological controls to the extent practical based on the emergency condition. They include but are not limited to the following:

1. Radiological Access Control for Rad/High Rad Areas - Access Control is used to limit the personnel who may be exposed to the radiological condition.

EP-AA-113 Revision 15 Page 6 of 15

2. Use of Radiological Protective Clothing - Protective clothing shall be used to limit the spread of radiological contamination and to protect the emergency worker from becoming radiologically contaminated.

3. Use of Radiological Respiratory Protective Equipment - Respiratory protective equipment shall be used to limit the inhalation and ingestion of radioactive materials during the course of the emergency event. The need for respirators shall be based on air samples, plant monitoring systems, and plant conditions.

4. Use of Contamination Control Techniques - Contamination control techniques such as Step-off Pads, Posting, Contamination surveys, and whole body frisking shall be used to the extent practical based on the emergency condition.

4.3. Emergency Exposure Limits NOTE: This section implements the requirements of RP-AA-203 and should not be revised without first reviewing the requirements of the current revision of the procedure.

Emergency Exposure Determination REFER to Section 4.3.1 Briefing Personnel (greater than 5 Rem TEDE) REFER to Section 4.3.2 Authorization (greater than 5 Rem TEDE) REFER to Section 4.3.3 Tracking and Recording of Exposures REFER to Section 4.3.4 4.3.1. Emergency Exposure Determination NOTE: In certain onsite emergency situations, extremely high dose rates may be encountered (more than 500 Rem/hr).

Before a rescue team is committed to life-saving emergency dose limits, weigh the probability of success against the probable cost of the commitment. Specifically there shall be reasonable assurance that the victim is in the area and that they are alive or likely to survive.

1. ASSURE that the emergency exposure is for a bona fide emergency involving risk of life or limb, or the destruction of valuable property.

A. PLAN emergency operations prior to entry.

B. WEAR respiratory protection and protective clothing to reduce contamination where possible.

EP-AA-113 Revision 15 Page 7 of 15

2. DETERMINE if emergency exposure limits in excess of 5 Rem TEDE (EPA-400 lower limits) are required for Exelon emergency workers.

3. If emergency exposure is less than 5 Rem TEDE (EPA-400 lower limits),

then OBTAIN approval as appropriate:

TSC Radiation Protection Manager for onsite Exelon personnel EOF Radiation Protection Manager for Exelon field team personnel 4.3.2. Briefing Personnel (greater than 5 Rem TEDE)

1. For exposures at or above 5 Rem TEDE (EPA-400 lower limits),

COMPLETE an Authorization for Emergency Exposure (EP-AA-113-F-02).

2. INFORM emergency personnel (volunteers) before the fact of possible health effects at the anticipated exposure level using Attachment 1, Emergency Worker Exposure Limits and Associated Risks.

3. OBTAIN emergency workers acknowledge that they have volunteered and understand the associated risks. Acknowledgement should be in writing on Authorization for Emergency Exposure Form if possible or verbally for teams in the field.

4. FORWARD to the completed form to the Station Emergency Director for approval.

EP-AA-113 Revision 15 Page 8 of 15 4.3.3. Authorization greater than 5 Rem TEDE (EPA-400 lower limits):

CAUTION Emergency exposure limits greater than 5 Rem TEDE may be applicable for stopping a release, life saving actions, and protection of major equipment and large populations.

All emergency exposures in excess of 25 Rem TEDE shall be voluntary and shall be limited to once in a lifetime. Persons who may receive exposures greater than 25 Rem TEDE shall be fully aware of the risks involved.

1. OBTAIN and DOCUMENT Station Emergency Director approval, by signature, for the use of the emergency dose limits above 5 Rem TEDE (EPA-400 lower limits) on the Authorization for Emergency Exposure form.

NOTE: The decision to authorize personnel exposure per EPA-400 limits is the responsibility of the Station Emergency Director and shall not be delegated.

2. NOTIFY Occupational Health (Medical) Services Department promptly if any EPA-400 dose limit is exceeded.

4.3.4. Tracking and Recording

1. ESTIMATE and RECORD personnel dose equivalents resulting from any emergency situation.

2. REPORT final emergency exposures greater than 5 Rem TEDE (EPA-400 lower limits) to the NRC.

EP-AA-113 Revision 15 Page 9 of 15 4.4. KI Assessment Determination REFER to Section 4.4.1 Authorization and Issuing KI REFER to Section 4.4.2 Briefing Personnel REFER to Section 4.4.3 4.4.1. Determination

1. ASSESS the potential of high thyroid exposure to emergency workers in, or projected to be sent into, areas where the possibility exists of exposure to radioactive iodine as follows:

A. For Field Monitoring Teams or other Exelon emergency workers working offsite, DETERMINE if either of the following conditions exist:

Condition 1 There is an Offsite Release in Progress.

And There has been a loss or potential loss of the Reactor Fuel Clad Barrier.

OR Condition 2 Dose Assessments project iodine thyroid exposure for emergency workers will be 50 Rem Committed Dose Equivalent (CDE).

B. For OSC Emergency Teams and other onsite workers, determine if either of the following conditions exist:

Condition 1 Workers will be entering an unknown radiological atmosphere that is suspected to have a high iodine concentration. Loss of the Reactor Fuel Clad barrier is a good indication of possible high iodine concentrations.

OR Condition 2 The calculated iodine thyroid exposure (actual or projected) for emergency workers, base on station Radiation Protection procedures or use of the dose assessment program, will be 50 Rem Committed Dose Equivalent (CDE).

EP-AA-113 Revision 15 Page 10 of 15 NMP/JAF/Ginna Only C. A General Emergency has been declared.

2. If the condition A, B and/or C listed above are met then, RECOMMEND the issuance of one (1) 130 mg KI tablet (or (2) 65 mg KI tablets) to each emergency worker affected per day for 10 consecutive days or until directed that the risk no longer exists.

MA/MW/CCNPP Only

3. If the condition A and/or B listed above are met then, RECOMMEND the issuance of one (1) 130 mg KI tablet to each emergency worker affected per day for 10 consecutive days or until directed that the risk no longer exists.

4.4.2. Authorization NOTE: The Radiation Protection Manager and OSC Director should avoid the use of individuals known to have possible adverse reactions to KI for tasks where exposure to iodine may occur. A list of individuals who indicated possible allergies is available.

1. DOCUMENT the decision to issue KI and OBTAIN the Emergency Directors authorization on EP-AA-113-F-03, Thyroid Blocking Agent Authorization.

2. NOTIFY Occupational Health (Medical) Services Department promptly if KI is to be issued to Exelon Nuclear personnel or contractors.

EP-AA-113 Revision 15 Page 11 of 15 4.4.3. Briefing Personnel and Issuing KI NOTE: The effectiveness of potassium iodide as a thyroid blocking agent decreases as a function of time. The effectiveness of potassium iodide is as follows:

90% effective if taken immediately prior to or concurrent with exposure to radioactive iodine.

50% effective if taken within 3 to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following exposure.

Ineffective if taken more than 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> following exposure.

NOTE: The FDA KI Package insert provided with the KI product identifies the side effects and risks involved with KI usage. It is general use guidance intended for members of the public. It states approval from state and public health authorities is needed prior to use, this applies to members of the public. Exelon has the authority and responsibility to direct use of KI by Exelon Emergency Workers.

NOTE: Persons with a known allergy to iodine should not be considered for work requiring the use of potassium iodide blocking agents.

CAUTION KI dosage in excess of that recommended by this procedure could lead to possible effects including: rash, swelling of salivary glands, soreness in the teeth and gums, upset stomach and diarrhea.

1. REVIEW Thyroid Blocking Agent Authorization Form (EP-AA-113-F-03) to ensure all individuals being issued KI are listed and form is complete.

2. READ, or instruct the Emergency Worker(s) to read, Information on use of Thyroid Blocking Agent on authorization form or the FDA KI package insert prior to taking or administering KI.

EP-AA-113 Revision 15 Page 12 of 15 NOTE: Potassium Iodide (KI) has a limited effective shelf life, which may be extended by the manufacturer. Potassium iodide shall be stored in sealed containers that are protected from light and are in areas that meet all manufacturers limitations on temperature variances.

3. VERIFY the expiration date of the KI to ensure it is within its acceptable shelf life period prior to being used.

4. ISSUE of one (1) 130 mg KI tablet to each emergency worker affected per day for 10 consecutive days or until directed that the risk no longer exists.

5. DOCUMENTATION 5.1. The following forms, when completed during a declared event document implementation of this procedure:

EP-AA-113-F-01, On-Site Habitability Checklist EP-AA-113-F-02, Authorization of Emergency Exposure EP-AA-113-F-03, Thyroid Blocking Agent Authorization Form EP-AA-113-F-05, Vehicle and Evacuee Control Group Leader Checklist EP-AA-113-F-06, Vehicle and Evacuee Control Group Member Checklist EP-AA-113-F-07, Emergency Director - Site Assembly, Accountability and Evacuation Checklist EP-AA-113-F-08, PBAPS Assembly, Accountability and Evacuation Guidelines EP-AA-113-F-09, LGS Assembly, Accountability and Evacuation Guidelines EP-AA-113-F-11, Remote Assembly Area Muster List EP-AA-113-F-12, Vehicle Survey and Decontamination Report EP-AA-113-F-13, Facility Accountability List (Within Protected Area)

EP-AA-113-F-17, Braidwood Assembly, Accountability and Evacuation Guidelines EP-AA-113-F-18, Byron Assembly, Accountability and Evacuation Guidelines EP-AA-113-F-19, Dresden Assembly, Accountability and Evacuation Guidelines EP-AA-113-F-20, LaSalle Assembly, Accountability and Evacuation Guidelines

EP-AA-113 Revision 15 Page 13 of 15 EP-AA-113-F-21, Quad Cities Assembly, Accountability and Evacuation Guidelines EP-AA-113-F-22, Clinton Assembly, Accountability and Evacuation Guidelines EP-AA-113-F-23, Assembly Area Roster EP-AA-113-F-24, Relocation Center Operations Checklist EP-AA-113-F-25, Relocation Center Accountability Log EP-AA-113-F-26, Relocation Center Monitoring Log EP-AA-113-F-30, CCNPP Assembly, Accountability and Evacuation Guidelines EP-AA-113-F-31, Ginna Assembly, Accountability and Evacuation Guidelines EP-AA-113-F-32, NMP Assembly, Accountability and Evacuation Guidelines EP-AA-113-F-33, JAF Assembly, Accountability and Evacuation Guidelines 5.2. The Standard Records Retention ID for the above documents per the Standards Records Retention Schedule is 5B.100.

EP-AA-113 Revision 15 Page 14 of 15

6. REFERENCES 6.1. Development References 6.1.1. Nuclear Operations Directive NOD-RP.14, "ALARA, Exposure Management, Work Controls and Radiological Monitoring," current revision.

6.1.2. EPA 400-R-92-001, "Manual of Protective Action Guides and Protective Actions for Nuclear Incidents," October 1991.

6.1.3. "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion, "Federal Guidance Report No. 11, Office of Radiation Programs, U.S. EPA, EPA-520/1-88-020, September 1988.

6.1.4. "Potassium Iodide as a Thyroid Blocking Agent in Radiation Emergency: Final Recommendations on use," Federal Register, Vol. 47, No. 125, June 29, 1982.

6.1.5. "Protection of Thyroid Gland in the Event of Releases of Radioiodine," NCRP Report No. 55, 1977.

6.1.6. Commonwealth Edison Quality Verification Audit Finding, Audit No. CE 04, CAR# CE-92-029 (Nov. 18, 1992) 6.1.7. Commonwealth Edison Medical Dept. Procedure and Practice Guideline, "Exposure Evaluation: Ionizing Radiation" (10/5/93).

6.1.8. RP-AA-203, Exposure Control and Authorization 6.2. User References None

7. ATTACHMENTS 7.1. Attachment 1 - Emergency Worker Exposure Limits and Associated Risks

EP-AA-113 Revision 15 Page 15 of 15 ATTACHMENT 1 EMERGENCY WORKER EXPOSURE LIMITS AND ASSOCIATED RISKS Page 1 of 1 EMERGENCY WORKER EXPOSURE LIMITS The dose-limiting recommendations for emergency situations are as follows:

Dose Limit Activity Condition (Rem TEDE)*

5 All Personnel should be kept within normal 10CFR20 limits during emergencies, except as authorized for activities as indicated below 10 Protecting Valuable Property When a lower dose is not practical 25 Life Saving or Protection of Large When a lower dose is not practical Populations

>25 Life Saving or Protection of Large Only on a voluntary basis to persons fully aware Population of the risks involved

• Dose Equivalent Limit (TEDE in Rem). Workers performing services during emergencies should limit dose to the lens of the eye (LDE) to three times each listed value and doses to any other organ (including skin and body extremities) to ten times each listed value.

EMERGENCY EXPOSURE RISKS Health effects associated with whole body absorbed doses received within a few hoursa Percent of population affected by prodromalb effects (e.g. reddening of Dose in rad skin, loss of appetite, nausea, Dose in rad Early fatalitiesc

( Rem DDE) fatigue, diarrhea) ( Rem DDE) (percent affected) 50 rad 2% 140 rad 5%

100 rad 15 % 200 rad 15 %

150 rad 50 % 300 rad 50 %

200 rad 85 % 400 rad 85 %

250 rad 98 % 460 rad 95 %

Approximate cancer risk to average individuals from 25 Rem TEDE received promptly Age at exposure Risk of premature death Average years of life lost (years) (deaths per 1000 persons if premature death occurs exposed) (years) 20 to 30 9.1 24 30 to 40 7.2 19 40 to 50 5.3 15 50 to 60 3.5 11 a Risks will be lower for extended exposure periods.

b Forewarning symptoms of more serious health effects associated with large doses of radiation.

c Supportive medical treatment may increase the dose at which these frequencies occur by approximately 50 percent.

TQ-AA-150-J020 Revision 01 Page 1 of 10 Job Performance Measure Determine Reporting And Notification Requirements (RPS Trip)

JPM Number: JPM564 Revision Number: 00 Date: 8/20/2020 Developed By: Bill Kiser / 8/20/20 Instructor: Print / Sign Date Reviewed By: /

SME or Instructor: Print / Sign Date Reviewed By: /

Operations Representative: Print / Sign Date Approved By: /

Training Department: Print / Sign Date SRRS: 3D.105 (when utilized for operator initial or continuing training)

TQ-AA-150-J020 Revision 01 Page 2 of 10 JPM556 JOB PERFORMANCE MEASURE VALIDATION CHECKLIST NOTE: All steps of this checklist should be performed upon initial validation.

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

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

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

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

4. Initial setup conditions are identified.

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

6. Task standards identified and verified by instructor or SME review.

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

8. IAW NUREG 1021 Appendix C, clearly identify the task standard (i.e., the predetermined qualitative or quantitative outcome) against which task performance will be measured.

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

Procedure: LS-AA-1110 Revision: 30 Procedure: OP-AA-106-101 Revision: 22 Procedure: Revision:

Procedure: Revision:

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

11. Verify performance time is accurate.

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

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

/

SME / Instructor (Print/Sign) Date

/

SME / Instructor (Print/Sign) Date

/

SME / Instructor (Print/Sign) Date SRRS: 3D.100; There are no retention requirements for this section

TQ-AA-150-J020 Revision 01 Page 3 of 10 JPM556 Revision Record (Summary)

Revision # Summary 00 8/20/20 - New JPM.

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

TQ-AA-150-J020 Revision 01 Page 4 of 10 JPM556 SETUP INSTRUCTIONS

1. No setup is required for this JPM.

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

TQ-AA-150-J020 Revision 01 Page 5 of 10 JPM556 INITIAL CONDITIONS You are the Shift Manager (SM).

The plant is shutdown. A maintenance outage is in progress with the following conditions:

• RHR Pump B is operating in Shutdown Cooling (SDC) mode.

• Reactor coolant temperature is 110°F.

• RPV level is at the natural circulation level.

THEN, a mechanical failure on the SDC loop occurs, causing RPV level to LOWER:

• At 0800 RPV level reaches its lowest point of +5.0 inches NR.

• At 0803 the failure is isolated and RPV level stabilizes at +11.3 inches NR.

Emergency Action Level has been evaluated per EP-AA-1003 Addendum 3.

INITIATING CUE Determine reportability requirements IAW LS-AA-1110 Safety (SAF) and notification requirements IAW OP-AA-106-101 Significant Event Reporting.

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

Information For Evaluators Use:

UNSAT requires written comments on respective step.

• Denotes critical steps.

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

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

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

The timeclock starts when the candidate acknowledges the initiating cue.

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

TQ-AA-150-J020 Revision 01 Page 6 of 10 JPM556 JPM Start Time: JPM Sequence #: of Task Standard:

The examinee will review LS-AA-1110 & OP-AA-106-101 and determine:

• the NRC Operations Center must be notified via the ENS as soon as practical and in all cases, within eight (8) hours of the occurrence IAW LS-AA-1110 Safety (SAF)

Reportable Event SAF 1.6 RPS Actuation and 1.7 System Actuation Not Including RPS, AND

• additional notifications IAW OP-AA-106-101 Significant Event Reporting Attachment 2 Shift Managers Notification Worksheet.

Comment STEP ELEMENT STANDARD SAT UNSAT Number CUE Provide the examinee with the Cue Sheet and the following:

• LS-AA-1110 Safety (SAF)

• OP-AA-106-101 Significant Event Reporting

• 01

• Determines reporting LS-AA-1110 requirements. Reviews Reportable Event SAF 1.6: RPS Actuation.

Determines event:

• Is reportable per SAF 1.6 and 1.7

• Requires NRC Operations Center notification via ENS within eight (8) hours.

Evaluator Note - LS-AA-1110 is located in the Reportability Manual.

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

TQ-AA-150-J020 Revision 01 Page 7 of 10 JPM556 Comment STEP ELEMENT STANDARD SAT UNSAT Number

• 02 Determines notification OP-AA-106-101 requirements. Reviews Attachment 2: Shift Managers Notification Worksheet.

Determines the following notifications are required:

• SOS / OD

• NRC Operations Center

• Duty Station Manager o Plant Manager (PM)* ___

o Site Vice President (SVP) o Nuclear Duty Officer (NDO)

• o Manager, Reg Assurance*

o Site Communicator (as required)

• o Environmental (as required) *

• NRC Senior Resident Inspector NOTE: Notifications designated by an asterisk (*) are performed by the Duty Station Manager. To meet the intent of this step, the candidate must identify (at a minimum) the bolded notifications.

CUE If the examinee reports results to the Shift Operations Superintendent (SOS),

acknowledge the report.

JPM is complete.

JPM Stop Time:

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

TQ-AA-150-J020 Revision 01 Page 8 of 10 JPM556 JPM

SUMMARY

Operators Name: Emp. ID#:

Job

Title:

EO RO SRO FS STA/IA SRO Cert JPM

Title:

Determine Reporting And Notification Requirements (RPS Trip)

JPM Number: JPM564 Revision Number: 00 Task Number and

Title:

(Exelon-SM-02) Apply non-routine reporting requirements to operational situations.

Task Standard: The examinee will review LS-AA-1110 & OP-AA-106-101 and determine:

• the NRC Operations Center must be notified via the ENS as soon as practical and in all cases, within eight (8) hours of the occurrence IAW LS-AA-1110 Safety (SAF)

Reportable Event SAF 1.6 RPS Actuation, AND

• additional notifications IAW OP-AA-106-101 Significant Event Reporting Attachment 2 Shift Managers Notification Worksheet.

K/A Number and Importance:

K/A System K/A Number Importance (RO/SRO)

Generic 2.4.30 2.7 4.1 Suggested Testing Environment: Classroom Alternate Path: Yes No SRO Only: Yes No Time Critical: Yes No Reference(s):

Procedure: LS-AA-1110 Revision: 30 OP-AA-106-101 Revision: 22 Actual Testing Environment: Simulator Control Room In-Plant Other Testing Method: Simulate Perform Estimated Time to Complete: 15 minutes Actual Time Used: minutes EVALUATION

SUMMARY

Were all the Critical Elements performed satisfactorily? Yes No The operators performance was evaluated against standards contained within this JPM and has been determined to be: Satisfactory Unsatisfactory SRRS: 3D.105 (when utilized for operator initial or continuing training)

TQ-AA-150-J020 Revision 01 Page 9 of 10 JPM556 NOTE: Enter finalized grading, comments, and notes relevant to this evaluation in the associated TQ-AA-150-F03A/B. (See AR 4282419).

Evaluators Name (Print):

Evaluators Signature: Date:

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

TQ-AA-150-J020 Revision 01 Page 10 of 10 JPM556 INITIAL CONDITIONS You are the Shift Manager (SM).

The plant is shutdown. A maintenance outage is in progress with the following conditions:

• RHR Pump B is operating in Shutdown Cooling (SDC) mode.

• Reactor coolant temperature is 110°F.

• RPV level is at the natural circulation level.

THEN, a mechanical failure on the SDC loop occurs, causing RPV level to LOWER:

• At 0800 RPV level reaches its lowest point of +5.0 inches.

• At 0803 the failure is isolated and RPV level stabilizes at +11.3 inches NR.

Emergency Action Level has been evaluated per EP-AA-1003 Addendum 3 NR.

INITIATING CUE Determine reportability requirements IAW LS-AA-1110 Safety (SAF) and notification requirements IAW OP-AA-106-101 Significant Event Reporting.

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