Text

2017 Perry Nuclear Power Plant Initial Licensed Operator Examination Administered Admin JPMs
	ML17096A729
Person / Time
Site:	Perry
Issue date:	04/05/2017
From:	David Reeser; NRC/RGN-III/DRS/OLB
To:	; NRC/RGN-III/DRS/OLB, FirstEnergy Nuclear Operating Co
Shared Package
ML16242A242	List: ML17096A729; ML17096A732; ML17096A737; ML17096A738; ML17096A744;
References
	OT-3701-ADM_029_RO
	Download: ML17096A729 (148)
	v • d • e

OT-3701-ADM_029_RO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System: Administrative Time Critical: No Alternate Path: No Applicability: RO Safety Function: Conduct of Operations Validated Time: 32 Minutes

References:

SVI-B33-T1160 Rev 5, PDB-A009 Rev. 19, PDB-A10 Rev. 17, PDB-A12 Rev. 16 Required Material: SVI-B33-T1160, Jet Pump Operability PDB-A009, Expected Jet Pump Normalized dP and Flow Ranges PDB-A10, Recirc Loop Drive Flow vs. FCV Position PDB-A12, Recirc Drive Flow vs. Total Core Flow Pictures of B33 instruments Task: 202-525-01-01 Monitor the Operation of the Reactor Recirc System.

Task Standard: Complete manual surveillance to determine if jet pumps are operable.

K/A: 2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation. Importance: RO 4.4 SRO 4.7

1. Setup: Ensure Required Material available at JPM site.

2. Location / Method: Class Room / Administrative performance.

3. Initial Condition: A control rod sequence exchange was completed last shift. Restoration to 100% power is in progress. Reactor power is currently at 87%. A drive in the SPDS (ICS) computer has failed and ICS is not available.

4. Initiating Cue: As the BOP RO, perform SVI-B33-T1160, Jet Pump Operability for the daily requirement and turn it in to the Unit Supervisor.

Start: Stop:

Candidate:

OT-3701-ADM_029_RO Rev 0 JPM BODY SHEET Standard: Performer obtains or simulates obtaining all materials, procedures, tools, keys, radios, etc before performing task.

Standard: Performer follows management expectations with regards to safety and communication standards.

Step 1 SVI-B33-T1160, Jet Pump Operability 4.0 PREREQUISITES 5.1 Surveillance Test Standard: Candidate reviews the SVI and pictures of B33 instruments to determine that both Recirc Pumps are running and flow is within TS limits.

He/she signs in the surveillance and informs the RO ATC.

Instructor Cue: If informed as RO ATC of starting SVI, repeat back to Candidate.

Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-ADM_029_RO Rev 0 Step 2 5.1.1 Recirculation Loop Drive Flow vs. FCV Position

1. Determine the relationship between each operating recirculation loop drive flow and the corresponding flow control valve position, and indicate the method used.

2. Indicate, for each operating loop, whether the relationship determined in Step 5.1.1.1 is within the appropriate established pattern.

Critical Step: Uses Attachment 1 of SVI to determine the relationship between recirculation loop drive flow and the corresponding flow control valve position. Determines relationship is within established pattern.

Instructor Cue: None Notes: Needs to use PDB-A10, pages 8 & 10.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 3 5.1.2 Recirculation Loop Drive Flow vs. Total Core Flow

1. Determine the relationship between recirculation loop drive flow and total core flow, and indicate the method used.

2. Indicate whether the relationship determined in Step 5.1.2.1 is within the appropriate established pattern.

Critical Step: Uses Attachment 2 of SVI to determine the relationship between recirculation loop drive flow and total core flow. Determines relationship is within established pattern.

Instructor Cue: When Candidate asks for IV, inform him/her that IV is complete.

Notes: Needs to use PDB-A12, page 6.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-ADM_029_RO Rev 0 Step 4 5.1.3 Jet Pump Differential Pressure and Flow

1. Jet Pump Differential Pressure

a. Determine each normalized jet pump diffuser to lower plenum differential pressure for each operating recirculation loop, and indicate the method used.

b. Indicate whether the relationship determined in Step 5.1.3.1.a is within the appropriate established pattern.

2. Jet Pump Differential Flow

a. Determine each normalized jet pump flow for each operating recirculation loop, and indicate the method used.

b. Indicate whether the relationship determined in Step 5.1.3.2.a is within the appropriate established pattern.

Critical Step: Uses Attachment 3 or Attachment 4 of SVI to determine the relationship between recirculation loop drive flow and total core flow. Determines relationship is within established pattern.

Instructor Cue: When Candidate asks for IV, inform him/her that IV is complete.

Notes: It is not necessary to satisfy both Section 5.1.3.1 and Section 5.1.3.2. The preferred method is contained in Section 5.1.3.1. The unnecessary section may be marked N/A.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-ADM_029_RO Rev 0 Step 5 5.3 Acceptance Criteria Critical Step: Complete the Acceptance Criteria and the Data Package Cover Sheet.

Instructor Cue: None Notes: See Answer Key for expected markups.

The checkmark in the NON TECH SPEC/PERIODIC TEST DATA block is not CRITICAL on the Data Package Cover Sheet.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Terminating Cue: SVI-B33-T1160 is complete.

Evaluation Results: SAT_____ UNSAT_____

End Time OT-3701-ADM_029_RO Rev 0 OT-3701-ADM_029_RO Rev 0 OT-3701-ADM_029_RO Rev 0 OT-3701-ADM_029_RO Rev 0 OT-3701-ADM_029_RO Rev 0 OT-3701-ADM_029_RO Rev 0 OT-3701-ADM_029_RO Rev 0 JPM CUE SHEET INITIAL

A control rod sequence exchange was completed last shift.

CONDITIONS:

Restoration to 100% power is in progress.

Reactor power is currently at 87%.

A drive in the SPDS (ICS) computer has failed and ICS is not available.

INITIATING CUE: As the BOP RO, perform SVI-B33-T1160, Jet Pump Operability for the daily requirement and turn it in to the Unit Supervisor.

Functional Location:

TEST COVER SHEET PY- SVI-B33-T1160 (PY: DATA PACKAGE COVER SHEET)

Maintenance Plan #: 52625 NOP-WM-2003-01 Rev. 02 Page 1 of 2 Order #:

Performance Section:

TEST COMPLETION x FULL PARTIAL FAILED TECHNICAL SPECIFICATION DATA x ACCEPTABLE UNACCEPTABLE NA ACCEPTABLE OUTSIDE LAIZ ACCEPTABLE OUTSIDE AV (Allowable Value)

Condition Report #

NON TECHNICAL SPECIFICATION/ x ACCEPTABLE UNACCEPTABLE NA PERIODIC TEST DATA TEST CREDIT x CREDIT NO CREDIT Additional Surveillance Test Crediting: Credit ST/PT: Plan: Order Number: Y N ST/PT: Plan: Order Number: Y N Work Start (Prerequisites) Approval: N/A - Initial /

Print Name Signature Date and Time Test Start Approval: RO Smith - Notified / Date / Time Print Name Signature Date and Time Test Completed (Test Leader): Name / Signature Date / Time Print Name Signature Date and Time Lead Work Group Supervisor Review: /

Print Name Signature Date and Time Comments:

Functional Location:

TEST COVER SHEET PY- SVI-B33-T1160 (PY: DATA PACKAGE COVER SHEET)

Maintenance Plan #: 52625 NOP-WM-2003-01 Rev. 02 Page 2 of 2 Order #:

Signature Validation Section NOTE: Printed name or signature must be legible, this is required by 10 CFR 50 Appendix B, Section XVII; Quality Assurance Records which states in part, Inspection and test records shall, as a minimum, identify the inspector or data recorder... and by ANSI N45.2.9 - 1974, Section 3.2 which states in part, quality assurance records shall be legible, completely filled out and adequately identifiable to the item involved.

Print Name Signature Initials Date SAP ID Number Name Signature Initials Date SAP ID #

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-B33-T1160

Title:

Use Category:

Jet Pump Operability Step-by-Step Revision: Page:

6 1 of 22 JET PUMP OPERABILITY Surveillance Instruction Effective Date: 8-5-16 Preparer: Thomas Naylor / 7-13-16 Date Approver: Ben Huck / 7-19-16 Date

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-B33-T1160

Title:

Use Category:

Jet Pump Operability Step-by-Step Revision: Page:

6 2 of 22

1.0 DESCRIPTION

1.1 Scope This instruction demonstrates the operability of each jet pump in each operating recirculation loop by confirming the existence of two of the following three conditions for each operating recirculation loop:

Recirculation loop drive flow versus flow control valve position differs by less than or equal to 10% from established patterns,

Recirculation loop drive flow versus total core flow differs by less than or equal to 10% from established patterns,

Each jet pump diffuser to lower plenum differential pressure differs by less than or equal to 20% from established patterns, or each jet pump flow differs by less than or equal to 10% from established patterns.

This instruction satisfies the requirements of Technical Specification SURVEILLANCE REQUIREMENT SR 3.4.3.1.

NOTES

Not required to be performed until 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after associated recirculation loop is in operation.

Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after greater than 25% RTP.

1.2 Frequency 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 1.3 Technical Specification Applicable MODES 1 and 2 2.0 PRECAUTIONS AND LIMITATIONS

1. Step numbers marked with a dollar sign ($) immediately to the left are required by Technical Specifications. Such items, if found to exceed their Acceptance Criteria, may be NRC reportable and shall be brought to the immediate attention of the Unit Supervisor.

2. Those steps of this instruction with an initial line are to be initialed as data are entered or as each step is completed.

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-B33-T1160

Title:

Use Category:

Jet Pump Operability Step-by-Step Revision: Page:

6 3 of 22

3. Sections 5.1.1, 5.1.2, and 5.1.3 may be performed in any order. Steps within a section are to be performed in the order specified unless otherwise indicated.

4. Avoid performing this test at less than 10% FCV position, as position indication is not consistent there.

5. Verification of established patterns is conducted in accordance with SVI-F41-T3008, Reactor Recirculation System Flow Data Verification during the initial weeks of operation under circumstances such as:

a. Following refueling activities (fuel assembly replacement or shuffle, as well as any modifications to fuel support orifice size or core plate bypass flow) that can affect the relationship between core flow, jet pump flow and recirculation loop flow, or

b. Initial entry into extended single loop recirculation operation Jet pump operability is considered acceptable prior to startup based on the acceptable results obtained during the previous cycle. During performance of SVI-F41-T3008, the Shift Engineer, Responsible System Engineer, or a Reactor Engineer normally provides an engineering judgment of the daily surveillance results to detect significant abnormalities which could indicate a jet pump failure. This engineering judgment may be based upon the nature of the refueling activities and may consider the self-consistency of the daily surveillance results, but jet pump noise is the most positive indication that the jet pump is operating. If established patterns are to be revised the associated Plant Data Book entries and SDS screens will be placed on hold.

Copies of the SVI-F41-T3008 data should be retained in the Control Room for reference until the revisions have been processed.

6. In order to permit sufficient opportunity for the baselining of new established patterns, the period of time covering the initial weeks of operation following refueling activities normally extends to include five weeks after reaching rated power and flow.

7. When using the established patterns in the Plant Data Book Curves, confirm the two loop curves are used during two loop operations and the single loop curves are used during single loop operations; likewise, for slow or fast speed operation.

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-B33-T1160

Title:

Use Category:

Jet Pump Operability Step-by-Step Revision: Page:

6 4 of 22

8. During single loop operations, only the jet pumps associated with the operating recirculation loop need to be demonstrated operable. However, data may be collected from the idle loop for use in demonstrating the OPERABILITY of the operating loop.

9. The following ICS SDS Displays may be used during the performance of this surveillance instruction, as appropriate for the configuration of the recirculation system:

a. JPFLOW, TWO LOOP NORMALIZED JET PUMP FLOWS

b. JPDP, TWO LOOP NORMALIZED JET PUMP DPS

c. RFPERF, TWO LOOP RCIRC - FAST SPEED PERFORMANCE

d. RSPERF, TWO LOOP RCIRC - SLOW SPEED PERFORMANCE 3.0 MANPOWER AND EQUIPMENT 3.1 Manpower/Location/Communication

1. Control Room operator or other qualified member of the unit technical staff to record data from instruments that are located on UNIT CONTROL CONSOLE 1H13-P680 and/or JET PUMP MONITORING PANEL 1H13-P619.

2. Shift Engineer, Responsible System Engineer, or Reactor Engineer, if needed, to provide engineering judgment of daily surveillance results.

3. The Independent Verifier may be any of the above individuals.

3.2 Required Measuring and Test Equipment (M&TE)

None 3.3 Additional Tools and Equipment

1. PDB-A0009, Expected Jet Pump Normalized dP and Flow Ranges, if needed.

2. PDB-A0010, Recirc Loop Drive Flow vs. FCV Position, if needed.

3. PDB-A0012, Recirc Drive Flow vs. Total Core Flow, if needed.

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-B33-T1160

Title:

Use Category:

Jet Pump Operability Step-by-Step Revision: Page:

6 5 of 22

4. SVI-F41-T3008, Reactor Recirculation System Flow Data Verification, if needed.

5. Plant computer provides data, if used.

4.0 PREREQUISITES Initials

1. MARK the Unit Supervisors Authorization to Start Prerequisites signature N/A on the Data Package Cover Sheet (DPCS) and initial. RO

2. CONFIRM that the plant is operating in MODE 1 with THERMAL POWER greater than 25% RTP. RO

3. CONFIRM that the recirculation flow is steady and INDICATE the configuration of the recirculation loops:

a. Loop A (only) in operation, with recirculation flow control in loop manual.

b. Loop B (only) in operation, with recirculation flow control in loop manual.

c. Both recirculation loops in fast speed operation, with recirculation loop jet pump flow mismatch within the limits of SR 3.4.1.1.

d. Both recirculation loops in slow speed operation, with recirculation loop jet pump flow mismatch within the limits of SR 3.4.1.1. RO

4. IF using plant computer points or ICS SDS screens, THEN VERIFY no other maintenance or testing is in progress which would affect recirculation flow indication, OTHERWISE MARK this step N/A. N/A

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-B33-T1160

Title:

Use Category:

Jet Pump Operability Step-by-Step Revision: Page:

6 6 of 22 4.0 PREREQUISITES Initials Note During performance of SVI-F41-T3008, engineering judgment by the Shift Engineer, Reactor Engineering, or Responsible System Engineer may determine existing patterns of PDB-A0009, PDB-A0010, and PDB-A0012 to be adequate for performance of this surveillance.

5. For at least 2 of the following, CONFIRM 1 or more listed source is available OR SVI-F41-T3008 is in progress.

RFPERF/RSPERF OR PDB-A0010

RFPERF/RSPERF OR PDB-A0012

JPDP OR JPFLOW OR PDB-A0009 RO (INTENTIONALLY BLANK)

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-B33-T1160

Title:

Use Category:

Jet Pump Operability Step-by-Step Revision: Page:

6 7 of 22 5.0 SURVEILLANCE INSTRUCTION Initials 5.1 Surveillance Test

1. NOTIFY the Reactor Operator before starting and write R.O. (operators name) notified in the Authorization to Start Test signature on the DPCS. RECORD the time and date and initial the line. RO Note Steps 5.1.1, 5.1.2, and 5.1.3 may be performed in any order. Steps within a section are to be performed in the order specified unless otherwise noted.

5.1.1 Recirculation Loop Drive Flow vs. FCV Position

1. DETERMINE the relationship between each operating recirculation loop drive flow and the corresponding flow control valve position, AND indicate the method used.

SDS Screen Attachment 1 RO

a. IF using ICS SDS, THEN ATTACH a copy of the screen that is appropriate for the recirculation loop configuration indicated in Step 4.3 (e.g., RFPERF for two loop - fast speed, or RSPERF for two loop - slow speed),

OTHERWISE COMPLETE Attachment 1, Manual Recirculation Loop Drive Flow vs. FCV Position. RO

2. INDICATE, for each operating loop, whether the relationship determined in Step 5.1.1.1 is within the appropriate established pattern.

a. IF using ICS SDS, THEN OBSERVE cursor is within limits for the DRIVE FLOW A VS. FCV A and/or for the DRIVE FLOW B VS. FCV B, OTHERWISE REFER to Step 3 on Attachment 1.

Loop A: YES NO N/A

Loop B: YES NO N/A RO

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-B33-T1160

Title:

Use Category:

Jet Pump Operability Step-by-Step Revision: Page:

6 8 of 22 5.1.2 Recirculation Loop Drive Flow vs. Total Core Flow Initials

1. DETERMINE the relationship between recirculation loop drive flow and total core flow, AND INDICATE the method used.

SDS Screen Attachment 2 RO

a. IF using ICS SDS, THEN ATTACH a copy of the screen that is appropriate for the recirculation loop configuration indicated in Step 4.3 (e.g., RFPERF for two loop - fast speed, or RSPERF for two loop - slow speed),

OTHERWISE COMPLETE Attachment 2, Manual Recirculation Loop Drive Flow vs. Total Core Flow. RO

2. INDICATE whether the relationship determined in Step 5.1.2.1 is within the appropriate established pattern.

a. IF using ICS SDS, THEN OBSERVE cursor is within limits for the DRIVE FLOW VS.

CORE FLOW, OTHERWISE REFER to Step 3 on Attachment 2.

YES NO RO

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-B33-T1160

Title:

Use Category:

Jet Pump Operability Step-by-Step Revision: Page:

6 9 of 22 5.1.3 Jet Pump Differential Pressure and Flow Initials Notes

It is not necessary to satisfy both Section 5.1.3.1 and Section 5.1.3.2. The preferred method is contained in Section 5.1.3.1. The unnecessary section may be marked N/A.

For single loop operation, the spaces in this section may be marked N/A for the idle loop.

1. Jet Pump Differential Pressure

a. DETERMINE each normalized jet pump diffuser to lower plenum differential pressure for each operating recirculation loop, AND INDICATE the method used.

SDS Screen Attachment 3 RO

1) IF using ICS SDS, THEN ATTACH a copy of the JPDP screen, OTHERWISE COMPLETE Attachment 3, Normalized Jet Pump dPs Data Sheet. RO

b. INDICATE whether the relationship determined in Step 5.1.3.1.a is within the appropriate established pattern.

2) IF using ICS SDS, THEN OBSERVE NORMAL indication for the JET PUMP DPS, OTHERWISE REFER to Step 6 on Attachment 3.

YES NO N/A RO

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-B33-T1160

Title:

Use Category:

Jet Pump Operability Step-by-Step Revision: Page:

6 10 of 22 Section 5.1.3 Initials

2. Jet Pump Differential Flow

a. DETERMINE each normalized jet pump flow for each operating recirculation loop, AND INDICATE the method used.

SDS screen Attachment 4

1) IF using ICS SDS, N/A THEN ATTACH a copy of the JPFLOW screen, OTHERWISE COMPLETE Attachment 4, Normalized Jet Pump Flows Data Sheet.

b. INDICATE whether the relationship determined in Step 5.1.3.2.a is within the appropriate established pattern.

1) IF using ICS SDS, THEN OBSERVE NORMAL indication for the JET PUMP FLOWS, OTHERWISE, REFER to Step 7 on Attachment 4.

YES NO N/A 5.2 Plant/System Restoration None

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-B33-T1160

Title:

Use Category:

Jet Pump Operability Step-by-Step Revision: Page:

6 11 of 22 5.3 Acceptance Criteria Initials Notes

Satisfactory completion of this surveillance shall be based only on Technical Specification items (marked with a $ sign).

While baselining new established patterns, copies of SVI-F41-T3008 data should be retained in the Control Room so that the Shift Engineer, the Responsible System Engineer, or a Reactor Engineer may consider the self-consistency of the data in making the engineering judgment on the existence of significant abnormalities which could indicate a jet pump failure. Jet pump noise is the most positive indication that the jet pump is operating.

$ 1. The jet pumps, in each operating recirculation loop, have been demonstrated OPERABLE by one of the following two methods:

a. At least two of the following three criteria have been satisfied:

1) Recirculation loop drive flow versus flow control valve position differs by less than or equal to 10% from established patterns. (YES in Step 5.1.1.2)

2) Recirculation loop drive flow versus total core flow differs by less than or equal to 10% from established patterns.

(YES in Step 5.1.2.2)

3) Each jet pump diffuser to lower plenum differential pressure differs by less than or equal to 20% from established patterns, OR each jet pump flow differs by less than or equal to 10%

from established patterns. (YES in either Step 5.1.3.1.b or Step 5.1.3.2.b)

YES NO, U.S. notified N/A RO

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-B33-T1160

Title:

Use Category:

Jet Pump Operability Step-by-Step Revision: Page:

6 12 of 22 SECTION 5.3 Initials

b. While baselining the new established patterns, the Shift Engineer (SE), or the Responsible System Engineer (RSE), or a Reactor Engineer (RE) has reviewed the surveillance results and has determined, based upon engineering judgment, that no significant abnormality exists that could indicate a jet pump failure.

N/A

___________________________________ /________ RO SE, RSE, or RE Signature / Date

2. All other items checked in this surveillance performed satisfactorily.

YES NO, applicable Supervisor notified RO

3. Check the appropriate block on the Data Package Cover Sheet to indicate acceptable or unacceptable test results. RO Comments: ________________________________________________________

Performed By:

Reactor Operator

______________________________________________/_________/________ RO Date

______________________________________________/_________/________

Name (Print) Initials / Date

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-B33-T1160

Title:

Use Category:

Jet Pump Operability Step-by-Step Revision: Page:

6 13 of 22 6.0 RECORDS 6.1 Records Handling Records handling shall be performed per NOP-SS-3300.

6.2 Records Capture The following documents are completed/generated by this instruction:

Quality Records Data Package Cover Sheet SVI-B33-T1160, pages 5 through 11, and:

Attachment 1, Manual Recirculation Loop Drive Flow vs. FCV Position, if used Attachment 2, Manual Recirculation Loop Drive Flow vs. Total Core Flow, if used Attachment 3, Normalized Jet Pump dPs Data Sheet, if used Attachment 4, Normalized Jet Pump Flows Data Sheet, if used Copy SDS screen JPFLOW, TWO LOOP NORMALIZED JET PUMP FLOWS, if used Copy SDS display JPDP, TWO LOOP NORMALIZED JET PUMP DPS, if used Copy SDS display RFPERF, TWO LOOP RCIRC - FAST SPEED PERFORMANCE, if used Copy SDS display RSPERF, TWO LOOP RCIRC - SLOW SPEED PERFORMANCE, if used Non-Quality Records None

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-B33-T1160

Title:

Use Category:

Jet Pump Operability Step-by-Step Revision: Page:

6 14 of 22

7.0 REFERENCES

7.1 Discretionary B-208-016, Sht. B02, B03, B04 D-302-603 D-302-604 NUREG/CR-3052, Closeout of 1E Bulletin 80-07: BWR Jet Pump Assembly Failure General Electric, Jet Pump Beam Cracks, SIL 330 with supplements NOP-WM-2003, Surveillance Test Control PAP-0500, Perry Technical Procedure Writers Guide PAP-0507, Perry Supplemental Procedure Requirements/Guidance SVI-F41-T3008, Reactor Recirculation System Flow Data Verification Plant Data Book 7.2 Obligations Technical Specification SURVEILLANCE REQUIREMENT SR 3.4.3.1 USAR Section 3.2.3.2.1, Definition of Safety Class 2 USAR Section 3.9.5.1.2, Reactor Internals USAR Figure 3.9-22, Jet Pump USAR Section 3.9.5.3.7, Special Requirements for Jet Pump Holddown Beams USAR Section 4.4.3.3.2, Regions of the Power-Flow Map USAR Section 15F.2.1.1, Core Flow Measurement During Single Loop Operation USAR Section 5.4.1.4, Safety Evaluation USAR Section 6.2.1.1.3.3.1, Recirculation Line Break USAR Section 6.3.3.7.2, Accident Description Commitments addressed in this document:

None

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-B33-T1160

Title:

Use Category:

Jet Pump Operability Step-by-Step Revision: Page:

6 15 of 22 8.0 SCOPE OF REVISION:

Rev. 6 1. Revise Precaution and Limitation 2.5 to clarify when data from SVI-F41-T3008 will be used to complete the surveillance.

2. Add Prerequisite Step 4.5 to confirm which data sources will be used to complete the surveillance.

3. Remove Commitment L01960 from References. L01960 implemented License Amendment 61, related changes would now go through the 10CFR50.59 process. The commitment is now closed.

4. Upgrade procedure to comply within current SVI format in accordance with PAP-0500, rev bars omitted.

5. Update Steps 4.1 and 5.1.1 to match the words on the current revision of the DPCS, rev bars omitted.

9.0 ATTACHMENTS Attachment 1 - Manual Recirculation Loop Drive Flow vs. FCV Position Attachment 2 - Manual Recirculation Loop Drive Flow vs. Total Core Flow Attachment 3 - Normalized Jet Pump dPs Data Sheet Attachment 4 - Normalized Jet Pump Flows Data Sheet

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-B33-T1160

Title:

Use Category:

Jet Pump Operability Step-by-Step Revision: Page:

6 16 of 22 ATTACHMENT 1: Manual Recirculation Loop Drive Flow vs. FCV Position Page 1 of 1 Initials Note For single loop operation, the spaces in this attachment may be marked N/A for the idle loop.

1. RECORD, for each operating loop, the flow control valve position from the instrument on 1H13-P680:

a. RCIRC LOOP A FLOW CONTROL: 36

_________ 1B33-K603A (%)

b. RCIRC LOOP B FLOW CONTROL: 34

_________ 1B33-K603B (%) RO

2. RECORD, for each operating loop, the recirculation loop drive flow from the plant computer or instruments on 1H13-P680, AND indicate the source of the data and the units:

C51-R614-blue (%)

a. 72.81 Flow A: _________ B33EA028 (kGPM)

C51-R614-red (%)

RO

b. 73.14 Flow B: _________ B33EA030 (kGPM)

NOTES The limits on the established recirculation loop drive flows are determined from the:

PDB-A0010 graphs for the recirculation loop configuration of Step 4.3,

Flow control valve positions of Step 1 of this attachment,

Units indicated in Step 2 of this attachment.

3. CONFIRM, for each operating loop, the recirculation loop drive flow recorded in Step 2 is between the corresponding limits determined from the appropriate Flow + 10% and Flow - 10% curves in PDB-A0010.

a. Loop A: YES NO N/A

b. Loop B: YES NO N/A RO

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-B33-T1160

Title:

Use Category:

Jet Pump Operability Step-by-Step Revision: Page:

6 17 of 22 ATTACHMENT 2: Manual Recirculation Loop Drive Flow vs. Total Core Flow Page 1 of 2 Initials

1. DETERMINE the total Recirc Drive Flow by adding the individual Recirc Drive Flows recorded in Step 2 of Attachment 1, AND indicate the corresponding units.

a. IF in single loop operation, THEN use zero for the Recirc Drive Flow of the idle loop.

(%)

Total Recirc Drive Flow: 145.95

_________ (kGPM) RO (72.81 + 73.14 = 145.95)

Independent Verifier:

2. IF 1B33-R613 is being used to determine Total Core Flow, THEN RECORD Total Core Flow from 1B33-R613 below, AND MARK Step 2.a. N/A, OTHERWISE COMPLETE Step 2.a.

a. IF Dual loop operation is indicated in Step 4.3, THEN RECORD the sum of the jet pump loop flows as Total Core Flow, AND MARK the corrected idle loop flow space N/A, OTHERWISE CORRECT the idle loop jet pump flow by multiplying by 0.95, AND RECORD the Total Core Flow as the operating loop jet pump flow minus the corrected idle loop jet pump flow.

Will be marked Jet Pump Loop A Flow: ______ 39 1B33-R612A (Mlb/hr) N/A if used value Jet Pump Loop B Flow:38______ (or 39)1B33-R612B (Mlb/hr) from R613 Corrected Idle Loop Flow: ______N/A (Mlb/hr) Loop: A B RO 1B33-R612A & B Total Core Flow: ______ 1B33-R613 (Mlb/hr) RO Will be 77 or 78 if Independent Verifier:

R612A/B used or 76 if R613 used. Need correct box checked.

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-B33-T1160

Title:

Use Category:

Jet Pump Operability Step-by-Step Revision: Page:

6 18 of 22 ATTACHMENT 2: Manual Recirculation Loop Drive Flow vs. Total Core Flow Page 2 of 2 Initials Note The limits on the established recirculation loop drive flow are determined from the:

PDB-A0012 graph for the recirculation loop configuration of Step 4.3,

Total Core Flow of Step 2 of this attachment,

Units indicated in Step 1 of this attachment.

3. Confirm that the flow recorded in Step 1 of this attachment is within the limits determined from the appropriate Drive Flow +10% and Drive Flow - 10% curves in PDB-A0012.

YES NO RO

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-B33-T1160

Title:

Use Category:

Jet Pump Operability Step-by-Step Revision: Page:

6 19 of 22 ATTACHMENT 3: Normalized Jet Pump dPs Data Sheet Page 1 of 2 Initials

1. Record each Jet Pump diffuser to lower plenum dP (%): RO

2. Sum all Jet Pump dPs for each loop, and record as Loop Total dP: RO

3. Divide each Loop Total dP by 10 and record as Loop Average dP: RO

4. Divide each Jet Pump dP by its Loop Average dP, and record as Normalized Jet Pump dP: RO Loop A 1H13-P619 Jet Pump Normalized Jet Pump Instrument dP (%) Jet Pump dP

1. 1B33-R610A 26

________ 1.03

2. 1B33-R610E 25

________ 0.99

3. 1B33-R610J 24

________ 0.95

4. 1B33-R610N 26

________ 1.03

5. 1B33-R610T 25

________ 0.99

6. 1B33-R610C 26

________ 1.03

7. 1B33-R610G 25

________ 0.99

8. 1B33-R610L 25

________ 0.99 Due to readability of

9. 1B33-R610R 25

________ 0.99 the pictures, some Jet

10. 1B33-R610V 26

________ 1.03 Pump P may deviate +/-1 from what A Loop Total dP 253

________ is listed. However, A Loop Average dP 25.3

________ Loop Total P should only deviate +/-3 Loop B 1H13-P619 Jet Pump Normalized from listed. In all Jet Pump Instrument dP (%) Jet Pump dP cases, Normalized jet

11. 1B33-R610B 24

________ 0.99

________ Pump P values will

12. 1B33-R610F 24

________ 0.99

________ be in bounds.

13. 1B33-R610K 24

________ 0.99

14. 1B33-R610P 23

________ 0.95

15. 1B33-R610U 28

________ 1.16

16. 1B33-R610D 29

________ 1.20

17. 1B33-R610H 23

________ 0.95

18. 1B33-R610M 22

________ 0.91

19. 1B33-R610S 24

________ 0.99

20. 1B33-R610W 21

________ 0.87 B Loop Total dP 242 B Loop Average dP 24.2

5. All calculations independently verified: Independent Verifier:

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-B33-T1160

Title:

Use Category:

Jet Pump Operability Step-by-Step Revision: Page:

6 20 of 22 ATTACHMENT 3: Normalized Jet Pump dPs Data Sheet Page 2 of 2 Initials

6. Confirm that each normalized jet pump diffuser to lower plenum differential pressure as determined in Step 4 of this Attachment is within the corresponding Normalized dP Range of PDB-A0009 for the Recirculation Loop configuration indicated in Step 4.3.

YES NO N/A RO

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-B33-T1160

Title:

Use Category:

Jet Pump Operability Step-by-Step Revision: Page:

6 21 of 22 ATTACHMENT 4: Normalized Jet Pump Flows Data Sheet Page 1 of 2 Initials

1. RECORD each Jet Pump diffuser to lower plenum dP (%):

2. TAKE the square root of each Jet Pump dP, and RECORD as Jet Pump SQRT(dP):

3. SUM all Jet Pump SQRT(dP)s for each loop, and RECORD as Loop Total SQRT(dP):

4. DIVIDE each Loop Total SQRT(dP) by 10 and RECORD as Loop Average SQRT(dP):

5. DIVIDE each Jet Pump SQRT(dP) by its Loop Average SQRT(dP), and RECORD as Normalized Jet Pump Flow:

Loop A 1H13-P619 Jet Pump Jet Pump Normalized Jet Pump Instrument dP (%) SQRT(dP) Jet Pump Flow

1. 1B33-R610A ________ _________ _________

2. 1B33-R610E ________ _________ _________

3. 1B33-R610J ________ _________ _________

4. 1B33-R610N ________ _________ _________

5. 1B33-R610T ________ _________ _________

6. 1B33-R610C ________ _________ _________

7. 1B33-R610G ________ _________ _________

8. 1B33-R610L N/A

9. 1B33-R610R ________ _________ _________

10. 1B33-R610V ________ _________ _________

A Loop Total SQRT(dP) ________

A Loop Average SQRTdP) ________

Loop B 1H13-P619 Jet Pump Jet Pump Normalized Jet Pump Instrument dP (%) SQRT(dP) Jet Pump Flow

11. 1B33-R610B ________ ________ _________

12. 1B33-R610F ________ ________ _________

13. 1B33-R610K ________ ________ _________

14. 1B33-R610P ________ ________ _________

15. 1B33-R610U ________ ________ _________

16. 1B33-R610D ________ ________ _________

17. 1B33-R610H ________ ________ _________

18. 1B33-R610M ________ ________ _________

19. 1B33-R610S ________ ________ _________

20. 1B33-R610W ________ ________ _________

B Loop Total SQRT(dP) ________

B Loop Average SQRT(dP) ________

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-B33-T1160

Title:

Use Category:

Jet Pump Operability Step-by-Step Revision: Page:

6 22 of 22 ATTACHMENT 4: Normalized Jet Pump Flows Data Sheet Page 2 of 2 Initials

6. All calculations independently verified: Independent Verifier:

7. Confirm that each normalized jet pump flow as determined in Step 5 of this attachment is within the corresponding Normalized Flow Range of PDB-A0009 for the Recirculation N/ALoop configuration indicated in Step 4.3.

YES NO N/A

OT-3701-ADM_012_RO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System: Administrative Time Critical: No Applicability: RO Administrative Topic: Conduct of Operations Validated Time: 15 Minutes Setting: Classroom

References:

OAI-1702 Rev 15, SOI-R45 Rev 17, SOI-R45/E22B Rev 17, & Form PNPP-7961 Rev 10/5/10 Required Material: OAI-1702, Operations Section Rounds Sheets, Logs, and Records SOI-R45, Division 1 And 2 Diesel Generator Fuel Oil System SOI-R45/E22B, Division 3 Diesel Generator Fuel Oil System Form PNPP-7961, Diesel Fuel Oil Record Task: 299-770-03-01 Complete Diesel Fuel Oil Record Task Standard: Complete Weekly Diesel Generator Fuel Oil Record, calculating storage tank levels.

K/A Data: 2.1.18 Ability to make accurate, clear, and concise logs, records, status boards, and reports.

Importance: RO 3.6 SRO 3.8

1. Setup Instructions: None

2. Location / Method: Classroom / Administrative Performance

3. Initial Condition: Today is Sunday - Day Shift. The monthly surveillance run was completed on Div. 1 Diesel Generator this past Thursday. A maintenance run was completed on 3 Diesel Generator last shift. Division 2 Diesel Generator received fuel oil this past Wednesday. Attached are the diesel counters reported by the NLO and a picture of the fuel oil storage tank meters from P877 and P601.

4. Initiating Cue: Unit Supervisor directs you, the Reactor Operator to complete the Diesel Fuel Oil Record.

Start: Stop:

Candidate:

1

OT-3701-ADM_012_RO Rev 0 JPM BODY SHEET Standard: Performer obtains or simulates obtaining all materials, procedures, tools, keys, radios, etc before performing task.

Standard: Performer follows management expectations with regards to safety and communication standards.

Step 1 OAI-1702, Operations Section Rounds Sheets, Logs, and Records 4.3.2 The following records are controlled by this procedure:

2. Diesel Fuel Oil Record (PNPP No. 7961) is used to compile data for billing purposes, monitor leakage from the Diesel Fuel Oil Storage Tanks and to provide required Environmental Protection Agency (EPA) data. This record should be maintained in the Control Room and completed as directed by SOI-R45 and SOI-R45/E22B. The completed Fuel Oil Records should be reviewed once per week by the Unit Supervisor. Upon completion, this record should be forwarded to Operations Services.

SOI-R45, Division 1 And 2 Diesel Generator Fuel Oil System (& SOI-R45/E22B, Division 3 Diesel Generator Fuel Oil System) 7.1 Diesel Fuel Oil Record, PNPP No. 7961 7.1.2 COMPLETE the FUEL INVENTORY/ USE THIS WEEK portion of the Diesel Fuel Oil Record each Sunday on dayshift.

Standard: Candidate reviews OAI-1702, SOI-R45, & SOI-R45/E22B.

Instructor Cue: None Notes: Refer to Answer Key for Calculated numbers.

SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

2

OT-3701-ADM_012_RO Rev 0 Step 2 7.1.2.a DETERMINE the approximate gallons consumed by each diesel for the week each Sunday on dayshift.

Critical Step: Candidate enters Div. 1 Runtime Counter in PRESENT COUNTER and determines that Div. 1 DG consumed ~600 gallons of fuel.

Instructor Cue: None Notes: Div. 2 did not consume any fuel oil.

SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

Step 3 SOI-R45/E22B, Division 3 Diesel Generator Fuel Oil System 7.1 Diesel Fuel Oil Record (OAI-1702) 7.2.2.b DETERMINE the approximate gallons consumed by each diesel for the week each Sunday on dayshift.

Critical Step: Candidate enters Div. 3 Runtime Counter in PRESENT COUNTER and determines that Div. 3 DG consumed ~800 gallons of fuel.

Instructor Cue: None Notes: See Answer Key SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

3

OT-3701-ADM_012_RO Rev 0 Step 4 Continue to complete Fuel Inventory/Use This Week for Div. 1 DG Critical Step: Candidate enters 79% in PRESENT LEVEL and determines that corresponds to 76025 gallons, which is below the ADMIN LEVEL and will require a dipstick reading.

Candidate directs NLO to perform Manual Determination of Storage Tank Level for Div. 1 FOST.

Instructor Cue: When directed, Understand perform Manual Determination of Storage Tank Level for Div. 1 fuel oil storage tank.

Report back, Div. 1 fuel oil storage tank is at 132 inches.

Notes: Candidate may inform Unit Supervisor about Div.1 FOST level now or upon completion of all three divisions.

SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

Step 5 Continue to complete Fuel Inventory/Use This Week for Div. 2 DG Critical Step: Candidate enters ~92% in PRESENT LEVEL and determines that corresponds to 84866 gallons, which falls within the acceptable channel check range for adding 7500 gallons of fuel.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

4

OT-3701-ADM_012_RO Rev 0 Step 6 Continue to complete Fuel Inventory/Use This Week for Div. 3 DG Critical Step: Candidate enters 93% in PRESENT LEVEL and determines that corresponds to 37435 gallons, which is below the ADMIN LEVEL and will require a dipstick reading.

Candidate directs NLO to perform Manual Determination of Storage Tank Level for Div. 3 FOST.

Instructor Cue: When directed, Understand perform Manual Determination of Storage Tank Level for Div. 3 fuel oil storage tank.

Report back, Div. 3 fuel oil storage tank is at 131.0 inches by manual determination.

Notes: Candidate may inform Unit Supervisor about Div.3 FOST level now or upon completion of all three divisions.

SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

Step 7 COMPLETE the FUEL INVENTORY/ USE THIS WEEK portion of the Diesel Fuel Oil Record each Sunday on dayshift per SOI-R45 and SOI-R45/E22B Standard: Candidate completes the fuel oil inventory record and reports that Div. 1 and Div. 3 fuel oil storage tanks are below the Admin Limits, but above the Tech Spec Limits.

Instructor Cue: None Notes: Terminate the JPM SAT ___ UNSAT ___

Comment(s):_________________________________________________________________

5

OT-3701-ADM_012_RO Rev 0 Terminating Cue: Candidate calculates/determines fuel oil storage tank levels for Divisional DGs and completes the Diesel Fuel Oil Record (Sunday Requirements) and determines that Div. 1 and Div. 3 fuel oil storage tanks are below the Admin Limits.

Evaluation Results: SAT_____ UNSAT_____

End Time:

6

OT-3701-ADM_012_RO Rev 0 DIESEL FUEL OIL RECORD WEEK OF: February 5, 2017 PNPP No. 7961 Rev. 10/5/10 OAI-1702 FUEL OIL RECEIPTS THIS WEEK DIESEL F.O. DATE TIME LEVEL (% or Inches) GALLONS IN TANK* GALLONS INVOICE END OF MONTH STORAGE TANK PRE-FILL POST-FILL PRE-FILL POST-FILL RECEIVED NUMBER INVENTORY (GAL) **

DIVISION 1 DIV 1 2/8/17 14:50 134.5 150.5 77630 85130 7500 0165823 DIV 2 DIVISION 2 DIV 3 DIVISION 3 DATE:

To be completed on Day Shift Sunday FUEL INVENTORY/USE THIS WEEK PREVIOUS LEVEL (From previous weeks Record) TOTAL GALLONS PRESENT LEVEL GALLONS USED THIS WEEK DIESEL F.O. RECEIVED THIS WEEK

% or Inches GALLONS * (Sum of gallons received above)

% or Inches GALLONS * (Previous Gal + Gal received - Present gal)

STORAGE TANK 79% 76025 DIVISION 1 80% 76800 76800 + 0 - 76301 = 499 132 76301 DIVISION 2 81% 77630 7500 92% 84866 77630 + 7500 - 84866 = 264 93% 37435 DIVISION 3 97% 38242 38242 + 0 - 37435 = 807 131.0% 37435 FOR EACH DIESEL VERIFY THAT THE GALLONS USED THIS WEEK IS WITHIN 900 GAL (FOR DIV 1 OR DIV 2) OR 400 GALS (FOR DIV 3) OF RUNTIME TOTAL HOURS APPROX APPROX GAL THE APPROX GALLONS CONSUMED.

PREVIOUS PRESENT DIESEL RUN GPH USED CONSUMED DIESEL WEEK COUNTER THIS WEEK THIS WEEK VERIFY EACH F. O. STORAGE TANK LEVEL IS GREATER THAN THE TECH SPEC LIMIT IDENTIFIED IN THE SOI OR APPROPRIATE ACTION HAS BEEN INITIATED.

DIV 1 1895.4 1896.9 1.5 400 GPH 600 gal DIV 2 2067.7 2067.7 0 400 GPH 0 gal Initials:

DIV 3 1356.0 1360.0 4.0 200 GPH 800 gal IV Initials:

7

OT-3701-ADM_012_RO Rev 0 Reported Field Data Diesel runtime counters reported by NLO performing Plant Equipment Rounds Div. 1 DG - 1896.9 Div. 2 DG - 2067.7 Div. 3 DG - 1360.0 8

OT-3701-ADM_012_RO Rev 0 JPM CUE SHEET INITIAL

Today is Sunday - Day Shift.

CONDITIONS:

The monthly surveillance run was completed on Div. 1 Diesel Generator this past Thursday.

A maintenance run was completed on 3 Diesel Generator last shift.

Division 2 Diesel Generator received fuel oil this past Wednesday.

Attached are the diesel counters reported by the NLO and a picture of the fuel oil storage tank meters from P877 and P601.

INITIATING CUE: Unit Supervisor directs you, the Reactor Operator to complete the Diesel Fuel Oil Record.

9

DIESEL FUEL OIL RECORD WEEK OF: February 5, 2017 PNPP No. 7961 Rev. 10/5/10 OAI-1702 FUEL OIL RECEIPTS THIS WEEK DIESEL F.O. DATE TIME LEVEL (% or Inches) GALLONS IN TANK* GALLONS INVOICE END OF MONTH STORAGE TANK PRE-FILL POST-FILL PRE-FILL POST-FILL RECEIVED NUMBER INVENTORY (GAL) **

DIVISION 1 DIV 1 2/8/17 14:50 134.5 150.5 77630 85130 7500 0165823 DIV 2 DIVISION 2 DIV 3 DIVISION 3 DATE:

To be completed on Day Shift Sunday FUEL INVENTORY/USE THIS WEEK PREVIOUS LEVEL (From previous weeks Record) TOTAL GALLONS PRESENT LEVEL GALLONS USED THIS WEEK DIESEL F.O. RECEIVED THIS WEEK STORAGE TANK

% or Inches GALLONS * (Sum of gallons received above) % or Inches GALLONS * (Previous Gal + Gal received - Present gal)

DIVISION 1 80% 76800 DIVISION 2 81% 77630 DIVISION 3 97% 38242 FOR EACH DIESEL VERIFY THAT THE GALLONS USED THIS WEEK IS WITHIN 900 GAL (FOR DIV 1 OR DIV 2) OR 400 GALS (FOR DIV 3) OF RUNTIME TOTAL HOURS APPROX APPROX GAL THE APPROX GALLONS CONSUMED.

PREVIOUS PRESENT DIESEL RUN GPH USED CONSUMED DIESEL WEEK COUNTER THIS WEEK THIS WEEK VERIFY EACH F. O. STORAGE TANK LEVEL IS GREATER THAN THE TECH SPEC LIMIT IDENTIFIED IN THE SOI OR APPROPRIATE ACTION HAS BEEN INITIATED.

DIV 1 1895.4 400 GPH DIV 2 2067.7 Initials:

400 GPH DIV 3 1356.0 200 GPH IV Initials:

As determined by the % - inches - gallons cross reference in SOI-R45 or SOI-R45/E22B.

- Record tank volumes (gallons) on the last day of the month.

OT-3701-ADM_022_RO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System: Administrative Time Critical: No Applicability: RO/SRO Administrative Topic: Equipment Control Setting: Simulator Validated: 20 minutes

References:

PRI-TSR Rev 38, SVI-E31-T0374 Rev 7 Tasks: 035-506-01-01 Determine Identified/Unidentified leakage rates Task Standard: Calculate Drywell Sump in-leakage rate per SVI-E31-T0374 and complete Tech Spec Rounds for Drywell Sump in-leakage Required Material: Pictures of DW FDS level of 11.78 with time (T=0130 hrs).

Pictures of DW EDS with a leak rate of 1.5 and DW Cnds Flow with 0 gpm.

Partially completed PRI-TSR page 34 Calculator.

SVI-E31-T0374 with US signature on the Test Cover Sheet and filled out up to but not including step 5.1.3 K / A Data: 2.2.12 Knowledge of surveillance procedures. 3.7 / 4.1

1. Setup Instructions: If to be done in simulator: Set Overrides ZA1E31R0618-BLU to 6.0 for DW FDS Level, ZA1E31R0619-RED to 1.5 for DW EDS Rate and ZA1E31R0609 to 0.0 for Upper DW Cooler Drain Flow. Reset gross fail on 1E31R609. If to be done in classroom: Use 01:00 pictures.

2. Location / Method: Simulator / Perform

3. Initial Condition: The plant is at 100% power. It has been determined that DW Floor Drain Sump 1E31-R618 (red indicator) is inoperable. SVI-E31-T0374, Reactor Cooling System Unidentified Leakage Determination has been started. The DW Floor Drain Sump has NOT been recently pumped down (within the last hour). It is Tuesday, 0100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months and you are the BOP operator.

4. Initiating Cue

Complete SVI-E31-T0374, Reactor Cooling System Unidentified Leakage Determination using the Sump Level Recorder Method.

Perform the Operator Tech Spec Rounds for Drywell Leak Detect, Step 42.

Start Time: End Time:

Candidate:

OT-3701-ADM_022_RO Rev 0 JPM BODY SHEET Standard: Performer obtains or simulates obtaining all materials, procedures, tools, keys, radios, etc before performing task.

Standard: Performer follows management expectations with regards to safety and communication standards.

Step 1 Record DW Floor Drain Sump Level.

Standard: Operator records the 1E31-R618 blue sump level reading of 6.0 in the surveillance.

Instructor Cue: None Notes: Provide Candidate with handouts 1, 2, & 3.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 2 Wait for sump to fill up for second reading.

Standard: Operator waits for sump to fill.

Instructor Cue: After the operator logs the initial 6 sump reading, inform the operator that, using time compression, it is now 01:30 hrs and provide the operator with the 01:30 hour pictures of the sumps/flow (Handouts 4 & 5).

Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-ADM_022_RO Rev 0 Step 3 Calculate floor sump level increase.

Critical Step: Operator determines sump level has increased by 5.78 Instructor Cue: None Notes: 5.7 to 5.8 is acceptable.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 4 Calculate elapsed time.

Critical Step: Operator determines 30 minutes have elapsed.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-ADM_022_RO Rev 0 Step 5 Calculate Unidentified Leakage.

Critical Step: Operator determines 90.3414 gallons of unidentified leakage.

Instructor Cue: None Notes: An answer from 89.0 to 90.7 gallons is acceptable (based upon acceptable answers for step 3)

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 6 Calculate Unidentified Leakage Rate.

Critical Step: Operator determines an Unidentified Leakage Rate of 3.01138 Instructor Cue: None Notes: An answer of 2.9 to 3.1 is acceptable (based upon acceptable answers for step 5).

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-ADM_022_RO Rev 0 Step 7 Independently verify calculations Standard: Operator asks for independent verification.

Instructor Cue: When asked, inform the operator that the calculations have been verified.

Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 8 Record DW FDS rate in PRI-TSR.

Standard: Operator records 3.01 gpm leakage rate on TS Rounds sheet.

Instructor Cue: None Notes: An answer of 2.9 to 3.1 is acceptable (based upon acceptable answers for step 5).

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-ADM_022_RO Rev 0 Step 9 Determine Equipment Drain Sump Rate.

Standard: Operator records 1.5 gpm on TS Rounds Sheet.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 10 Determine total leakage rate.

Standard: Operator records a total leakage rate of 4.51 on TS Rounds Sheet.

Instructor Cue: None Notes: An answer of 4.4 to 4.6 is acceptable. (based upon acceptable answers for step 8).

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-ADM_022_RO Rev 0 Step 11 Determine 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months total leakage average rate Standard: Operator averages the last 3 readings and obtains an average of 3.20.

Instructor Cue: None Notes: An answer of 3.1 to 3.3 is acceptable. (based upon acceptable answers for step 10).

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 12 Record DW CNDS FLOW Standard: Records zero GPM.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-ADM_022_RO Rev 0 Step 13 Verify increase in Unidentified Leakage is < 2 gpm in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

Critical Step: Operator notifies US that increase in unidentified leakage is > 2 gpm in a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period.

Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Terminating Cue: Operator notifies US that increase in Unidentified Leakage is > 2 gpm in a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period.

Evaluation Results: SAT_____ UNSAT_____

End Time:

PRI-TSR Rev 37 Candidate Handout 1 Sheet 18 of 36 Page 37 SHEET 17 MODES 1, 2 & 3 WEEK OF :___________________________

TSR-MODES 1,2&3-17 Rev. Error! Reference TECHNICAL SPECIFICATION ROUNDS source not found.

T R U MONDAY TUESDAY WEDNESDAY THURSDAY FRIDAY SATURDAY SUNDAY I E N PANEL OR PARAMETER/ M D A M D A M D A M D A M D A M D A M D A T Q I ORIGIN INSTRUMENT I A F I A F I A F I A F I A F I A F I A F L M T D Y T D Y T D Y T D Y T D Y T D Y T D Y T E T S RCIC AREA T CC 41 P632 °F 78 80 82 79 (1E31-N700A-A6-1) (143)

LEAK DETECTION RCIC RCIC AREA T CC 1H13-P642 °F 78 81 78 80 (1E31-N700B-A6-1) (143)

RHR AREA 1 T CC 1H13-P632 °F 80 82 78 78 (1E31-N700A-A6-4) (157)

RHR AREA 1 T CC

°F ISOLATION <B00139>

1H13-P642 (1E31-N700B-A6-4) (157) 82 82 80 81 RHR AREA 2 T CC 1H13-P632 °F 81 80 79 78 (1E31-N700A-A6-5) (157)

RHR AREA 2 T CC 1H13-P642 °F 83 81 81 79 (1E31-N700B-A6-5) (157)

Reading for 1E31-R618 (red) is only valid if DW Floor Drains Sump Level 1E31-R618 (blue) is < 12.5. If 1E31-R618 (red) is not operable, perform SVI-E31-T0374 to determine DW Floor Drains Rate.

42 Obtain TOTAL LEAKAGE RATE by summing DW FDS RATE and DW EDS RATE. Obtain 24 Hr TOTAL LEAKAGE AVERAGE by averaging the last 3 TOTAL LEAKAGE RATES. Verify 24 Hr TOTAL LEAKAGE AVERAGE 30 gpm.

<F01291> FDS SUMP LEV

<F01332> 1E31-R618 (blue)

< 12.5 INCH 8.00 7.20 6.30 11.78

DRYWELL LEAK DETECT DW FDS RATE

<L01448> 1E31-R618 (red) 5 GPM .7 .8 .7 3.01 DW EDS RATE 1E31-R619 (red)

GPM 1.8 1.9 1.7 1.5 TOTAL SEE 1H13-P642 LEAKAGE RATES NOTE GPM 2.5 2.7 2.4 4.51 24 Hr TOTAL SEE LEAKAGE AVG GPM 2.4 2.6 2.5 3.20 NOTE DW CNDS FLOW 1H13-P692 1E31-R609 GPM 0 0 0 0 Required in Mode 1. Verify that the increase in Unidentified Leakage within the previous 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period is 2 gpm.

DW FDS RATE SEE 1H13-P642 INCREASE NOTE INIT AJ BN CC XX Initials circled in RED ink.

PRI-TSR Rev 37 Candidate Handout 1 Sheet 18 of 36 Page 37 SHEET 17 MODES 1, 2 & 3 WEEK OF :___________________________

TSR-MODES 1,2&3-17 Rev. Error! Reference TECHNICAL SPECIFICATION ROUNDS source not found.

T R U MONDAY TUESDAY WEDNESDAY THURSDAY FRIDAY SATURDAY SUNDAY I E N PANEL OR PARAMETER/ M D A M D A M D A M D A M D A M D A M D A T Q I ORIGIN INSTRUMENT I A F I A F I A F I A F I A F I A F I A F L M T D Y T D Y T D Y T D Y T D Y T D Y T D Y T E T S RCIC AREA T CC 41 P632 °F 78 80 82 79 (1E31-N700A-A6-1) (143)

LEAK DETECTION RCIC RCIC AREA T CC 1H13-P642 °F 78 81 78 80 (1E31-N700B-A6-1) (143)

RHR AREA 1 T CC 1H13-P632 °F 80 82 78 78 (1E31-N700A-A6-4) (157)

RHR AREA 1 T CC

°F ISOLATION <B00139>

1H13-P642 (1E31-N700B-A6-4) (157) 82 82 80 81 RHR AREA 2 T CC 1H13-P632 °F 81 80 79 78 (1E31-N700A-A6-5) (157)

RHR AREA 2 T CC 1H13-P642 °F 83 81 81 79 (1E31-N700B-A6-5) (157)

Reading for 1E31-R618 (red) is only valid if DW Floor Drains Sump Level 1E31-R618 (blue) is < 12.5. If 1E31-R618 (red) is not operable, perform SVI-E31-T0374 to determine DW Floor Drains Rate.

42 Obtain TOTAL LEAKAGE RATE by summing DW FDS RATE and DW EDS RATE. Obtain 24 Hr TOTAL LEAKAGE AVERAGE by averaging the last 3 TOTAL LEAKAGE RATES. Verify 24 Hr TOTAL LEAKAGE AVERAGE 30 gpm.

<F01291> FDS SUMP LEV

<F01332> 1E31-R618 (blue)

< 12.5 INCH 8.00 7.20 6.30

DRYWELL LEAK DETECT DW FDS RATE

<L01448> 1E31-R618 (red) 5 GPM .7 .8 .7 DW EDS RATE 1E31-R619 (red)

GPM 1.8 1.9 1.7 TOTAL SEE 1H13-P642 LEAKAGE RATES NOTE GPM 2.5 2.7 2.4 24 Hr TOTAL SEE LEAKAGE AVG GPM 2.4 2.6 2.5 NOTE DW CNDS FLOW 1H13-P692 1E31-R609 GPM 0 0 0 Required in Mode 1. Verify that the increase in Unidentified Leakage within the previous 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period is 2 gpm.

DW FDS RATE SEE 1H13-P642 INCREASE NOTE INIT AJ BN CC Candidate Handout 1 OT-3701-ADM_022_RO Rev 0 Time = 01:00 01:00 hrs Upper Drywell Cooler Drain Flow Monitor Candidate Handout 2 OT-3701-ADM_022_RO Rev 0 Time = 01:00 01:00 hrs DWS & EDS Level/Rate Monitors Candidate Handout 3 OT-3701-ADM_022_RO Rev 0 Time = 01:30 01:30 hrs DWS & EDS Level/Rate Monitors Candidate Handout 4 OT-3701-ADM_022_RO Rev 0 Time = 01:30 01:30 hrs Upper Drywell Cooler Drain Flow Monitor Candidate Handout 5 OT-3701-ADM_022_RO Rev 0 JPM CUE SHEET INITIAL

The plant is at 100% power.

CONDITIONS:

It has been determined that DW Floor Drain Sump 1E31-R618 (red indicator) is inoperable.

SVI-E31-T0374, Reactor Cooling System Unidentified Leakage Determination has been started.

The DW Floor Drain Sump has NOT been recently pumped down (within the last hour).

It is Tuesday, 0100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months and you are the BOP operator.

INITIATING CUE:

Complete SVI-E31-T0374, Reactor Cooling System Unidentified Leakage Determination using the Sump Level Recorder Method

Perform the Operator Tech Spec Rounds for Drywell Leak Detect, Step 42.

Functional Location:

TEST COVER SHEET PY-SVI-E31-T0374 (PY: DATA PACKAGE COVER SHEET)

Maintenance Plan #:

NOP-WM-2003-01 Rev. 02 Page 1 of 2 Order #:

Performance Section:

TEST COMPLETION FULL PARTIAL FAILED TECHNICAL SPECIFICATION DATA ACCEPTABLE UNACCEPTABLE NA ACCEPTABLE OUTSIDE LAIZ ACCEPTABLE OUTSIDE AV (Allowable Value)

Condition Report #

NON TECHNICAL SPECIFICATION/ ACCEPTABLE UNACCEPTABLE NA PERIODIC TEST DATA TEST CREDIT CREDIT NO CREDIT Additional Surveillance Test Crediting: Credit ST/PT: Plan: Order Number: Y N ST/PT: Plan: Order Number: Y N Work Start (Prerequisites) Approval: Tom Smith / Tom Smith Today / Now Print Name Signature Date and Time Test Start Approval: Jack Jones / Jack Jones Today / Now Print Name Signature Date and Time Test Completed (Test Leader): /

Print Name Signature Date and Time Lead Work Group Supervisor Review: /

Print Name Signature Date and Time Comments:

Functional Location:

TEST COVER SHEET PY-SVI-E31-T0374 (PY: DATA PACKAGE COVER SHEET)

Maintenance Plan #:

NOP-WM-2003-01 Rev. 02 Page 2 of 2 Order #:

Signature Validation Section NOTE: Printed name or signature must be legible, this is required by 10 CFR 50 Appendix B, Section XVII; Quality Assurance Records which states in part, Inspection and test records shall, as a minimum, identify the inspector or data recorder... and by ANSI N45.2.9 - 1974, Section 3.2 which states in part, quality assurance records shall be legible, completely filled out and adequately identifiable to the item involved.

Print Name Signature Initials Date SAP ID Number Tom Smith Tom Smith TS Today 10110 Jack Jones Jack Jones JJ Today 11100 Roy X. Opter Roy X. Opter RXO Today 10100

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-E31-T0374

Title:

Use Category:

Reactor Cooling System Unidentified Leakage Step-by-Step Revision: Page:

Determination 7 1 of 11 REACTOR COOLING SYSTEM UNIDENTIFIED LEAKAGE DETERMINATION Surveillance Instruction Effective Date: 4-22-15 Preparer: Kurt Jones / 4-15-15 Date Approver: Ed Condo / 4-20-15 Date Working Copy Verified - Today - RXO

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-E31-T0374

Title:

Use Category:

Reactor Cooling System Unidentified Leakage Step-by-Step Revision: Page:

Determination 7 2 of 11

1.0 DESCRIPTION

1.1 Scope A Drywell Floor Drain Sump Monitoring System is required by Technical Specifications 3.4.7. This instruction provides two alternate methods of verifying that unidentified leakage is within the limits of Technical Specifications 3.4.5. These alternate methods are required by the Bases for Technical Specifications 3.4.7.

This instruction records the necessary data and calculates the unidentified leakage rate. The calculated leakage rate will then be recorded in the PRI-TSR. The PRI-TSR is still the procedure that satisfies the surveillance requirement of Technical Specifications SR 3.4.5.1.

1.2 Frequency At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the normal method of the PRI-TSRs can not be used.

1.3 Technical Specification Applicable MODES 1, 2, and 3 2.0 PRECAUTIONS AND LIMITATIONS

1. Those steps of this instruction designated with an initial block/line are to be initialed as data is entered or as each step is completed. These steps may require additional initials or signatures to be entered on other sheets, such as an attachment.

2. This instruction should be read in its entirety before proceeding with the performance of the instructional steps.

3. All steps are to be performed in sequence and the instruction carried through to completion unless otherwise indicated.

4. The Unit Supervisor must be notified immediately if an instruction step cannot be completed as stated or if problems develop during the performance of this instruction.

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-E31-T0374

Title:

Use Category:

Reactor Cooling System Unidentified Leakage Step-by-Step Revision: Page:

Determination 7 3 of 11 3.0 MANPOWER AND EQUIPMENT 3.1 Manpower/Location/Communication

1. One operator is required to perform this instruction.

2. Operation of the drywell floor drain sump pumps will require assistance of the Radwaste Control Room.

3.2 Required Measuring and Test Equipment (M&TE)

N/A 1. A stopwatch (Robotic SC-700 or equivalent) will be required if determining unidentified leakage per 5.1.4, Manual Timing Method.

3.3 Additional Tools and Equipment None (INTENTIONALLY BLANK)

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-E31-T0374

Title:

Use Category:

Reactor Cooling System Unidentified Leakage Step-by-Step Revision: Page:

Determination 7 4 of 11 4.0 PREREQUISITES Initials

1. OBTAIN USs Work Start (Prerequisites) Approval signature on the Test Cover Sheet/Surveillance Order. RXO N/A 2. IF determining unidentified leakage per 5.1.4, Manual Timing Method, THEN VERIFY the calibration due date is current on all M&TE.

Stopwatch RXO Floc ________ Cal Date ________ Due Date ________

3. This surveillance may be performed in any Mode. RXO 5.0 SURVEILLANCE INSTRUCTION 5.1 Surveillance Test 5.1.1 OBTAIN the Reactor Operators Test Start Approval signature on the Test Cover Sheet/Surveillance Order. RXO NOTE If the Sump Level Recorder Method can be used to determine unidentified leakage rate, then the Drywell Floor Drain Sump Monitoring System can be considered operable per T.S. 3.4.7.

5.1.2 PERFORM one of the following alternate methods of determining unidentified leakage: (N/A section not used.)

1. Sump Level Recorder Method per 5.1.3. RXO

2. Manual Timing Method per 5.1.4 N/A

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-E31-T0374

Title:

Use Category:

Reactor Cooling System Unidentified Leakage Step-by-Step Revision: Page:

Determination 7 5 of 11 5.1.3 Sump Level Recorder Method Initials

1. IF drywell floor drain sump level is t 12.5 inches, as indicated on Panel H13-P642 level recorder 1E31-R618, THEN REQUEST Radwaste Control Room to manually pump down the sump per RWI-G61(FDSS) until the sump level is

< 10 inches.

NOTES x If the sump was recently pumped down to the automatic pump trip, it may take greater than an hour for level to increase sufficiently to accurately perform the following step.

x The following readings must cover a period of time when the sump pump has not been in operation and sump level is <12.5 inches.

x The more time allowed between the initial and current readings the more accurate the calculation.

2. Using Panel H13-P642 level recorder, 1E31-R618 blue pen, RECORD the following information:

a. in.

(Initial Sump Level (Time of Taking From 1E31-R618) Initial Reading)

b. in.

(Current Sump Level (Time of Taking From 1E31-R618) Current Reading)

3. CALCULATE the sump level rate of increase by performing the following:

a. in. (Current Level 5.1.3.2.b)

- in. (Initial Level 5.1.3.2.a)

= in. (Sump Level Increase)

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-E31-T0374

Title:

Use Category:

Reactor Cooling System Unidentified Leakage Step-by-Step Revision: Page:

Determination 7 6 of 11 SECTION 5.1.3 Initials

b. min. (Current Time 5.1.3.2.b)

- min. (Initial Time 5.1.3.2.a)

= min. (Elapsed Time)

c. in. (Sump Level Increase 5.1.3.3.a)

15.63 gals/in.

= gal. (Unidentified Leakage)

d. gal. (Unidentified Leakage 5.1.3.3.c) y min. (Elapsed Time 5.1.3.3.b)

= gpm (Unidentified Leakage Rate)

4. INDEPENDENTLY VERIFY all calculations.

5. RECORD the calculated unidentified leakage rate in the Drywell Leak Detect section of the PRI-TSR in place of the 1E31-R618 red pen reading.

5.1.4 Manual Timing Method

1. VERIFY that the last performance of PTI-G61-P0001 is within the previous 24 months.

Date of last performance

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-E31-T0374

Title:

Use Category:

Reactor Cooling System Unidentified Leakage Step-by-Step Revision: Page:

Determination 7 7 of 11 SECTION 5.1.4 Initials

2. ESTABLISH the initial conditions for leakage determination as follows:

a. REQUEST that the Radwaste Control Room manually pump down the drywell floor drain sump and note the time (clock time) that the pump trips on low level.

b. Time pump tripped:

c. REQUEST that the Radwaste Control Room place both drywell floor drain sump pumps in OFF.

NOTE The following steps should not be performed until the sump level has increased sufficiently that a sump pump run time can be accurately determined. The waiting period will be determined by the expected leakage rate into the sump, taking into consideration the required 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months frequency of T.S. SR 3.4.5.1.

3. During the following step RECORD the time the pump trips (clock time) and MEASURE the time from pump start until the pump trips on sump low level. (stopwatch time)

4. COORDINATE with the Radwaste Control Room Operator to manually pumpdown the drywell floor drain sump using one sump pump.

a. Sump pump used (circle one) A or B

b. Sump pump run time in minutes -

(stopwatch time)

c. Time sump pump tripped -

(clock time)

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-E31-T0374

Title:

Use Category:

Reactor Cooling System Unidentified Leakage Step-by-Step Revision: Page:

Determination 7 8 of 11 SECTION 5.1.4 Initials NOTE Capacity of drywell floor drain sump pumps per PTI-G61-P0001 (04-08-2015):

x 1G61-C008A: 36.0 gpm x 1G61-C008B 45.0 gpm

5. To calculate the unidentified leakage rate, PERFORM the following:

a. min. (Time Pump tripped 5.1.4.4.c)

- min. (Time Pump tripped 5.1.4.2.b)

= min. (Fill time)

b. min. (Sump Pump Run time 5.1.4.4.b)

gpm (Pump Capacity)

= gal. (Gallons Pumped Out)

c. gal. (Gallons Pumped Out 5.1.4.5.b) y min. (Fill time 5.1.4.5.a)

= gpm (Unidentified Leakage Rate)

6. INDEPENDENTLY VERIFY all calculations.

7. RECORD the calculated unidentified leakage rate in the Drywell Leak Detect section of the PRI-TSR in place of the 1E31-R618 red pen reading.

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-E31-T0374

Title:

Use Category:

Reactor Cooling System Unidentified Leakage Step-by-Step Revision: Page:

Determination 7 9 of 11 5.2 Plant/System Restoration Initials

1. IF Section 5.1.4 was performed, THEN RESTORE the Drywell Floor Drain Sump Pumps as required by RW Supervisor:

1H51-P031 1G61-C008A 1G61-C008B 5.3 Acceptance Criteria

$ 1. Drywell unidentified leakage rate has been determined and recorded in the PRI-TSR at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

YES NO, U.S. notified Comments:

Performed By: Roy X. Opter / RXO / Today

/ /

Signature Initials Date

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-E31-T0374

Title:

Use Category:

Reactor Cooling System Unidentified Leakage Step-by-Step Revision: Page:

Determination 7 10 of 11 6.0 RECORDS 6.1 Records Handling Records completed/generated by this document shall be handled in accordance with the established records management program.

6.2 Records Capture The following documents are completed/generated by this instruction:

Quality Records Test Cover Sheet/Surveillance Order SVI-E31-T0374, pages 4 through 9 Non-Quality Records None

7.0 REFERENCES

7.1 Discretionary B-208-99-15 B-208-99-16 D-302-740 D-302-964 7.2 Obligations Perry Plant Technical Specifications Commitments addressed in this document:

None

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-E31-T0374

Title:

Use Category:

Reactor Cooling System Unidentified Leakage Step-by-Step Revision: Page:

Determination 7 11 of 11 8.0 SCOPE OF REVISION Rev. 7 1. Note at 5.1.4 Step 5 - corrected the referenced performance date and data for PTI-G61-P0001.

9.0 ATTACHMENTS None

OT-3701-ADM_011_RO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System: Administrative Time Critical: No Alternate Path: No Applicability: RO/SRO Safety Function: Radiation Control Setting: Classroom Validated: 15 minutes

References:

Radiation Worker Training Handout Rev 3 NORM-OP-4000, Radiation Protection Definitions & References Rev 1 Form NOP-OP-4107-4, ALARA Plan Tasks: 299-848-01-01 Comply with the Administrative Requirements for the Perry Plant Radiation Dose Control Program Task Standard: Determine if a radiological entry to perform an assigned evolution would be more ALARA with or without a respirator.

Required Material: Calculator & Computer with access to FileNet K / A Data: 2.3.14 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.

Importance: RO 3.4 SRO 3.8

1. Instructions: None

2. Location / Method: Classroom / Administrative performance.

3. Initial Condition: The Plant is in a Site Area Emergency. You have been assigned to enter Containment to isolate a primary system leak. The general area dose rates for the travel path and the work location are 25 mrem/hr. In addition Containment is posted an Airborne Area with current airborne particulate levels of 20 DAC. You estimate that it will take 45 minutes without a respirator and 75 minutes with a respirator.

4. Initiating Cue: As the assigned worker in order to keep your exposure ALARA would you perform the job with or without a respirator and how much dose would you save?

Start Time End Time Candidate OT-3701-ADM_011_RO Rev 0 JPM BODY SHEET Standard: Performer obtains or simulates obtaining all materials, procedures, tools, keys, radios, etc before performing task.

Standard: Performer follows management expectations with regards to safety and communication standards.

Step 1 Determine dose without respiratory protection.

Critical Step: The Candidate calculates radiation dose:

Area radiation dose 0.75 hr x 25 mr/hr = 18.75 mrem.

Airborne dose 20 DAC x 2.5 mrem/DAC-hr x 0.75 hr = 37.50 mrem.

Total Dose = 56.25 mrem Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-ADM_011_RO Rev 0 Step 2 Determine dose with respiratory protection.

Critical Step: The Candidate calculates radiation dose:

Area radiation dose 1.25 hr x 25 mr/hr = 31.25 mrem.

Airborne dose 0 mrem.

Total Dose = 31.25 mrem Instructor Cue: None Notes: None SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 3 Determine how to maintain Dose ALARA.

Critical Step: The Candidate determines a Respirator should be worn, with a dose savings of 25 mrem.

Instructor Cue: None Notes: Terminate the JPM SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Terminating Cue: The Candidate calculates dose both with and without a respirator and determines a respirator should be worn to maintain dose ALARA with a dose savings of 25 mrem.

Evaluation Results: SAT_____ UNSAT_____

End Time OT-3701-ADM_011_RO Rev 0 JPM CUE SHEET INITIAL

The Plant is in a Site Area Emergency.

CONDITIONS:

You have been assigned to enter Containment to isolate a primary system leak.

The general area dose rates for the travel path and the work location are 25 mrem/hr.

In addition Containment is posted an Airborne Area with current airborne particulate levels of 20 DAC.

You estimate that it will take 45 minutes without a respirator and 75 minutes with a respirator.

INITIATING CUE:

As the assigned worker in order to keep your exposure ALARA would you perform the job with or without a respirator and

How much dose would you save?

OT-3701-ADM_029SRO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System: Administrative Time Critical: No Alternate Path: No Applicability: SRO Safety Function: Conduct of Operations Validated Time: 17 Minutes

References:

SVI-B33-T1160 Rev 6, PDB-A009 Rev. 19, PDB-A10 Rev. 17, PDB-A12 Rev. 16 Required Material: SVI-B33-T1160, Jet Pump Operability PDB-A009, Expected Jet Pump Normalized dP and Flow Ranges PDB-A10, Recirc Loop Drive Flow vs. FCV Position PDB-A12, Recirc Drive Flow vs. Total Core Flow Task: 202-525-01-01 Monitor the Operation of the Reactor Recirc System.

Task Standard: Review manual surveillance to determine if jet pumps are operable.

K/A: 2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation. Importance: RO 4.4 SRO 4.7

1. Setup: Ensure Required Material SVI-B33-T1160, PDB-A009, PDB-A10, PDB-A12 and calculator available at JPM site.

2. Location / Method: Class Room / Administrative performance.

3. Initial Condition: A control rod sequence exchange was completed last shift. Restoration to 100% power is in progress. Reactor power is currently at 87%. A drive in the SPDS (ICS) computer has failed and ICS is not available. SVI-B33-T1160, Jet Pump Operability was just completed for the daily requirement.

4. Initiating Cue: As the Unit Supervisor, perform SRO review of the attached SVI-B33-T1160, Jet Pump Operability. Document the results of your review on the Data Package Cover Sheet. The data collected was recorded accurately.

Start: Stop:

Candidate:

OT-3701-ADM_029SRO Rev 0 JPM BODY SHEET Standard: Performer obtains or simulates obtaining all materials, procedures, tools, keys, radios, etc before performing task.

Standard: Performer follows management expectations with regards to safety and communication standards.

Step 1 Review surveillance.

SVI-B33-T1160, Jet Pump Operability 4.0 PREREQUISITES 3 Confirm that the recirculation flow is steady; and indicate the configuration of the recirculation loops:

c. Both recirculation loops in fast speed operation, with recirculation loop jet pump flow mismatch within the limits of SR 3.4.1.1.

Critical Step: Candidate reviews the SVI and determine that PREREQUISITE Step 4.3.D was inappropriately checked. Step 4.3.C should be checked.

Instructor Cue: If asked, direct candidate to continue review.

Notes: Candidate should be able to ascertain that Recirc Pumps cannot be in SLOW speed with the Rx at 87% power.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-ADM_029SRO Rev 0 Step 2 Review surveillance.

Critical Step: Candidate determines jet pumps 1 and 15 are not within established pattern.

Instructor Cue: None Notes: Step 5.1.3.1.b should be marked NO vs. YES and Attachment 3 Step 6 should be marked NO vs. YES.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 3 Review surveillance.

Standard: Candidate determines All other items checked in this surveillance did not perform satisfactorily.

Instructor Cue: None Notes: Step 5.3.2 should be marked NO vs. YES.

On Data Package Cover Sheet, NON TECHNICAL SPECIFICATION TEST DATA is marked UNACCEPTABLE.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

OT-3701-ADM_029SRO Rev 0 Step 4 Review surveillance.

Standard: Reviews Acceptance Criteria 5.3.1.a and determines 2 of the 3 have been satisfied.

Instructor Cue: None Notes: Need only 2 of the 3 criteria for surveillance to be considered SAT.

SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Step 5 Review surveillance Data Package Cover Sheet.

Critical Step: Reviews Data Package Cover Sheet and determines that TECHNICAL SPECIFICATION DATA block should be checked ACCEPTABLE.

Instructor Cue: None Notes: Jet pumps 1 and 15 NORMALIZED JET PUMP dP was not within the established pattern. Therefore Acceptance Criteria 5.3.2 was not met.

Terminate the JPM SAT ___ UNSAT ___

Comment(s):________________________________________________________________

Terminating Cue: Review of SVI-B33-T1160 is complete and problems have been documented on the Data Package Cover Sheet.

Evaluation Results: SAT_____ UNSAT_____

End Time OT-3701-ADM_019SRO Rev 0 JPM CUE SHEET INITIAL

A control rod sequence exchange was completed last shift. Restoration to CONDITIONS: 100% power is in progress.

Reactor power is currently at 87%.

A drive in the SPDS (ICS) computer has failed and ICS is not available.

SVI-B33-T1160, Jet Pump Operability was just completed for the daily requirement.

INITIATING CUE: As the Unit Supervisor, perform SRO review of the attached SVI-B33-T1160, Jet Pump Operability. Document the results of your review on the Data Package Cover Sheet.

The data collected was recorded accurately.

Functional Location:

TEST COVER SHEET PY- SVI-B33-T1160 (PY: DATA PACKAGE COVER SHEET)

Maintenance Plan #: 52625 NOP-WM-2003-01 Rev. 02 Page 1 of 2 Order #:

Performance Section:

TEST COMPLETION X FULL PARTIAL FAILED TECHNICAL SPECIFICATION DATA ACCEPTABLE UNACCEPTABLE NA ACCEPTABLE OUTSIDE LAIZ ACCEPTABLE OUTSIDE AV (Allowable Value)

Condition Report #

NON TECHNICAL SPECIFICATION/ ACCEPTABLE X UNACCEPTABLE NA PERIODIC TEST DATA TEST CREDIT X CREDIT NO CREDIT Additional Surveillance Test Crediting: Credit ST/PT: Plan: Order Number: Y N ST/PT: Plan: Order Number: Y N Work Start (Prerequisites) Approval: / N/A - RXO Print Name Signature Date and Time Test Start Approval: /RO Smith Notified Today / 30 min.. ago - RXO Print Name Signature Date and Time Test Completed (Test Leader): Rector X Operator Rector X Operator

/ Today / 10 min.. ago Print Name Signature Date and Time Lead Work Group Supervisor Review: /

Print Name Signature Date and Time Comments:

Performed manual SVI due to ICS being out of service.

Functional Location:

TEST COVER SHEET PY- SVI-B33-T1160 (PY: DATA PACKAGE COVER SHEET)

Maintenance Plan #: 52625 NOP-WM-2003-01 Rev. 02 Page 2 of 2 Order #:

Signature Validation Section NOTE: Printed name or signature must be legible, this is required by 10 CFR 50 Appendix B, Section XVII; Quality Assurance Records which states in part, Inspection and test records shall, as a minimum, identify the inspector or data recorder... and by ANSI N45.2.9 - 1974, Section 3.2 which states in part, quality assurance records shall be legible, completely filled out and adequately identifiable to the item involved.

Print Name Signature Initials Date SAP ID Number Rector X Operator Rector X Operator RXO Today 10010 Indy V. Rever Indy V. Rever IVR Today 10110

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-B33-T1160

Title:

Use Category:

Jet Pump Operability Step-by-Step Revision: Page:

6 1 of 22 JET PUMP OPERABILITY Surveillance Instruction Effective Date: 8-5-16 Preparer: Thomas Naylor / 7-13-16 Date Approver: Ben Huck / 7-19-16 Date Working Copy Verified - Today - RXO

Procedure Number:

PERRY NUCLEAR POWER PLANT SVI-B33-T1160

Title:

Use Category:

Jet Pump Operability Step-by-Step Revision: Page:

6 2 of 22

1.0 DESCRIPTION

1.1 Scope This instruction demonstrates the operability of each jet pump in each operating recirculation loop by confirming the existence of two of the following three conditions for each operating recirculation loop:

Recirculation loop drive flow versus flow control valve position differs by less than or equal to 10% from established patterns,

Recirculation loop drive flow versus total core flow differs by less than or equal to 10% from established patterns,

Each jet pump diffuser to lower plenum differential pressure differs by less than or equal to 20% from established patterns, or each jet pump flow differs by less than or equal to 10% from established patterns.

This instruction satisfies the requirements of Technical Specification SURVEILLANCE REQUIREMENT SR 3.4.3.1.

NOTES

Not required to be performed until 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after associated recirculation loop is in operation.

Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after greater than 25% RTP.