ML012060416

ST - Init Exam - 09-2001 - Draft Operating Test

ML012060416
Person / Time
Site:	South Texas
Issue date:	01/18/2001
From:	NRC Region 4
To:
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Download: ML012060416 (443)

Text

SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION D0527 H:\WP\APPROVED\PSP\10\0NI0002.05M Page 1 of 11 Effective Date: 07/03/96 Print Time / Date: 3:43 PM 07/03/01 0PSP10-NI-0002 Rev. 5 Excore QPTR Determination Quality Non Safety-Related Usage: Referenced Effective Date: 07/03/96 KEY David Barnstable Jay Eichenlaub Charlie Ayala Nuclear Fuel & Analysis PREPARER TECHNICAL USER COGNIZANT ORGANIZATION Table of Contents Page

1. 0 Purpose and Scope...................................................................................................................................2

2. 0 Notes & Precautions ................................................................................................................................2

3. 0 Prerequisites ............................................................................................................................................2

4. 0 Procedure.................................................................................................................................................3

5. 0 Acceptance Criteria.................................................................................................................................6

6. 0 References ...............................................................................................................................................7 KEY

7. 0 Support Documents ..................................................................................................................................7 Form 1, Data Package Cover Sheet.....................................................................................................8 Form 2, Excore QPTR Data Sheet....................................................................................................11 KEY

0PSP10-NI-0002 Rev. 5 Page 2 of 10 Excore QPTR Determination

1.0 Purpose and Scope

1.1 The purpose of this procedure is to determine the Quadrant Power Tilt Ratio (QPTR) and KEY verify it satisfies the requirements of Technical Specification 3.2.4.

1.2 This procedure is written to be performed sequentially and in its entirety to determine the QPTR.

1.3 This procedure meets the Surveillance Requirements of Technical Specifications 4.2.4.1.a and 4.2.4.1.b.

2.0 Notes & Precautions 2.1 When above 75% RTP with one power range NI channel inoperable, at least once per 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br />, an incore QPTR shall be determined per 0PSP10-II-0004 (Determination of Quadrant Power Tilt Ratio Using Incore Instrumentation) concurrently with this procedure.

3.0 Prerequisites 3.1 At least three power range NI channels are operable.

3.2 3.3 3.4 The plant is in Mode 1.

KEY Reactor power has not changed greater than +/- 0.5% RTP in the last 5 minutes.

Notify the Shift Supervisor to review the limiting conditions for operation associated with Technical Specification 3.2.4, Quadrant Power Tilt Ratio.

3.5 Have the Shift Supervisor sign Form 1 giving permission to start the test.

KEY

0PSP10-NI-0002 Rev. 5 Page 3 of 10 Excore QPTR Determination 4.0 Procedure NOTE

• KEY An approved computer code may be used to perform the calculations on Form 2.

Computer generated forms may also be used for Form 2.

4.1 Verify the prerequisites have been met and sign Form 1.

• 4.2 Record the following information on Excore QPTR Form 2.

4.2.1 Unit number, cycle number, date and time. initials 4.2.2 The current Reactor Power indication being used and its value. initials CAUTION KEY Always use the 100% power detector currents from the latest Figure 5.1 in the Plant Curve Book for ALL the NI channels, even if the new values have not yet been set in all of the NI channels.

4.2.3 Latest 100% power detector current, in microamps, for each operable upper and lower power range NI detector from Figure 5.1 in the Plant Curve Book. initials CAUTION The reading of the upper and lower detector currents for all of the operable power range NI detectors should be done as near the same time as possible to minimize any errors from NI channel oscillations.

4.3 Read the indicated detector currents for each operable upper and lower power range NI detector from CP-011 to the nearest microamp, e.g. 612 microamps, and KEY record the values on Excore QPTR Form 2. initials

0PSP10-NI-0002 Rev. 5 Page 4 of 10 Excore QPTR Determination NOTE

• When one power range NI channel is inoperable, the three operable channels shall be used to determine QPTR.

KEY

• Comments pertaining to the inoperable channel should be recorded in the REMARKS section of Excore QPTR Form 1.

4.4 Calculate the Upper Tilt Ratio (UTR) as follows:

CAUTION The following calculations in steps 4.4.1 through 4.4.4 shall be carried out to at least three decimal places.

4.4.1 Determine the upper normalized current (IU) for each channel by dividing the indicated detector current by the 100% power detector current. Record the upper normalized current (IU) on Excore QPTR Form 2. initials 4.4.2 4.4.3 KEY Determine the sum of the upper normalized detector currents (Sum IU) and record this value on Excore QPTR Form 2.

Determine the average upper normalized current (Average IU) by dividing the sum of the upper normalized currents (Sum IU) by the number of operable detectors. Record the average upper normalized current (Average IU) on Excore QPTR Form 2.

initials initials 4.4.4 Calculate the UTR by dividing the maximum upper normalized current (Maximum IU) by the average upper normalized current (Average IU).

Record the UTR on Excore QPTR Form 2. initials KEY

0PSP10-NI-0002 Rev. 5 Page 5 of 10 Excore QPTR Determination 4.5 Calculate the Lower Tilt Ratio (LTR) as follows:

CAUTION KEY The following calculations in steps 4.5.1 through 4.5.4 shall be carried out to at least three decimal places.

4.5.1 Determine the lower normalized current (IL) for each channel by dividing the indicated detector current by the 100% power detector current. Record the lower normalized current (IL) on Excore QPTR Form 2. initials 4.5.2 Determine the sum of the lower normalized current (Sum IL) and record this value on Excore QPTR Form 2. initials 4.5.3 Determine the average lower normalized current (Average IL) by dividing the sum of the lower normalized currents (Sum IL) by the number of operable detectors. Record the average lower normalized current (Average IL) on Excore QPTR Form 2. initials 4.5.4 KEY Calculate the LTR by dividing the maximum lower normalized current (Maximum IL) by the average lower normalized current (Average IL).

Record the LTR on Excore QPTR Form 2.

NOTE QPTR is defined in Technical Specifications as the value of the UTR or the value of the LTR, whichever is greater.

4.6 Record the larger numerical value (UTR or LTR) as the QPTR on Form 2. initials 4.7 The Test Coordinator SHALL sign Form 2 when calculations are complete.

• 4.8 Obtain independent verification of all calculations, including verification that all of the recorded 100% detector currents on Form 2 are from the latest approved KEY Figure 5.1 of the Plant Curve Book. Sign for independent verification on Form 2. IV 4.9 Verify the QPTR meets the Acceptance Criteria. initials

0PSP10-NI-0002 Rev. 5 Page 6 of 10 Excore QPTR Determination NOTE If the QPTR > 1.02 and Reactor Power is < 50%, then reactor power may be increased above KEY 50% in accordance with the action requirements of Technical Specification 3.2.4.

4.10 If the test results did not satisfy the Acceptance Criteria then immediately notify the Shift Supervisor. initials 4.11 If QPTR > 1.02 and Reactor Power > 50%, then notify the Reactor Engineering Supervisor to prepare to take action per Technical Specification 3.2.4 action b.

4.12 The Test Coordinator SHALL ensure all procedure performers and verifiers print their names, sign and initial Form 1.

• 4.13 Indicate the reason for performing this test on Form 1.

4.14 Indicate the test results and sign Form 1.

• 4.15 Mark sections of Form 1 and Form 2 which were not completed with N/A or similar notation.

4.16 4.17 4.18 Forward the data package to the Shift Supervisor.

KEY The Shift Supervisor SHALL indicate the results of the second review on Form 1.

If the Shift Supervisor determines test results did not satisfy the acceptance criteria, then he SHALL immediately complete the applicable portion of Form 1.

4.19 Forward the Data Package for review in accordance with 0PGP03-ZE-0004 (Plant Surveillance Program).

5.0 Acceptance Criteria 5.1 The Quadrant Power Tilt Ratio shall not exceed 1.02.

KEY

0PSP10-NI-0002 Rev. 5 Page 7 of 10 Excore QPTR Determination 6.0 References 6.1 STPEGS Technical Specification 3/4.2.4 7.0 KEY 6.2 6.3 0PGP03-ZE-0004, Plant Surveillance Program 0PSP10-II-0004, Determination of Quadrant Power Tilt Ratio Using Incore Instrumentation Support Documents 7.1 Form 1 (Data Package Cover Sheet) 7.2 Form 2 (Excore QPTR Data Sheet)

KEY KEY

0PSP10-NI-0002 Rev. 5 Page 8 of 11 KEY Excore QPTR Determination Form 1 Data Package Cover Sheet (SAMPLE) Page 1 of 3 Work Activity -ST Unit 1 Cycle 10 -ST Tech Spec

Reference:

Test Interval: Modes Required: Test Performance Mode 4.2.4.1.a 3.2.4 7 days (alm. op.)

12 hrs (alm. 1 1 4.2.4.1.b inop.)

3.5 Permission to start: Henry Ford Date Shift Supervisor Date 4.13 Reason for Test:

For Surveillance Credit Not for Surveillance Credit Periodic Surveillance Test To Satisfy 4.2.4.1.a. Conditional Surveillance to satisfy 4.2.4.1.b.

Other ____ANNUNCIATOR 05M03-A-4 NOT CLEARED__________________________

4.14 Test Results:

Acceptable (All Acceptance Criteria met)

Unacceptable (any Acceptance Criteria NOT met)

KEY Test Completed By: Signature Date Time Test Coordinator Date Time 4.17 Second Review of Test Results:

Acceptable (All Acceptance Criteria met)

Unacceptable (Any Acceptance Criteria NOT met)

Test Reviewed By:

Shift Supervisor Date Time 4.18 Plant Operations Review of Test Results (if required):

IF test results are unacceptable, IMMEDIATELY inform the Shift Supervisor who SHALL complete the following:

Potential Reportable Occurrence Yes No LCO Action Statement Entered Yes No KEY Corrective Action Taken :

Reviewed By:

Shift Supervisor Date Time All pages of Form 1 and Form 2, SHALL be included in the data package.

This form, when completed, SHALL be retained for the life of the plant.

0PSP10-NI-0002 Rev. 5 Page 10 of 11 Excore QPTR Determination Form 1 Data Package Cover Sheet (SAMPLE) Page 2 of 3 Name KEY Performers and Verifiers:

Name (Printed) Signature Signature Initials Initials Sections Performed Sec. 4.0 Signature Date 4.1 Prerequisites met:

Test Coordinator Date Remarks:

KEY KEY This form, when completed, SHALL be retained for the life of the plant.

0PSP10-NI-0002 Rev. 5 Page 11 of 11 KEY Excore QPTR Determination Form 2 Excore QPTR Data Sheet (SAMPLE) Page 1 of 1 4.2.1 Unit 1 Cycle 10 Date date Time time 4.2.2 Reactor Power 99.9% Indicator U1118 UPPER DETECTORS N41U N42U N43U N44U 4.3 Indicated Detector 4.4.2 4.4.3 537 554 536 579 Current (A) Sum IU Average IU 4.2.3 100% Power Detector 535.0 554.0 534.7 576.1 Current (A) 4.4.1 Normalized (IU)

Currents 1.004 1.000 1.002 1.005 4.011 1.003 M a x i m u m IU 4.4.4 UPPER TILT RATIO (UTR) = = 1.002 Average I U KEY LOWER DETECTORS N41L N42L N43L N44L 4.3 Indicated Detector 4.5.2 4.5.3 561 561 589 571 Current (A) Sum IL Average IL 4.2.3 100% Power Detector 557.4 555.1 584.6 547.1 Current (A) 4.5.1 Normalized (IL)

Currents 1.006 1.011 1.008 1.044 4.069 1.017 M a x i m u m IL 4.5.4 LOWER TILT RATIO (LTR) = = 1.027 A v e r a g e IL 4.6 QPTR = Larger of the UTR or LTR = 1.027 (Numerical value)

KEY 4.7 4.8 Performed by:

Verified (IV) by:

Signature Date:

Date:

Date This form, when completed, SHALL be retained for the life of the plant.

JPM NO: A1 PAGE 1 OF 13 NUCLEAR TRAINING DEPARTMENT JOB PERFORMANCE MEASURE TITLE: PERFORM A QPTR CALCULATION JPM NO.: A1 REVISION: 1 LOCATION: N/A

JPM NO: A1 PAGE 2 OF 13 JOB PERFORMANCE MEASURE WORKSHEET JPM

Title:

PERFORM A QPTR CALCULATION JPM No.: A1 Rev. No.: 1 Task No.: 37750, Perform a Quadrant Power Tilt Ratio calculation STP Objective: Perform a Quadrant Power Tilt Ratio calculation in accordance with 0PSP10-NI-0002.

Related K/A

Reference:

2.1.20 (4.3) Ability to execute Procedure Steps

References:

T.S. 3/4.2.4 Quadrant Power Tilt Ratio 0POP09-AN-05M3(05M3-A-4) PR Lower Det Flux Dev Hi/Auto Def 0PSP10-NI-0002, Rev 5, Excore QPTR Determination Task Normally Completed By: RO Method of Testing: Performance Location of Testing: N/A Time Critical Task: NO Alternate Path JPM: NO Validation Time: 20 minutes Required Materials (Tools/Equipment):

Calculator

JPM NO: A1 PAGE 3 OF 13 JOB PERFORMANCE MEASURE INFORMATION SHEET READ TO PERFORMER:

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

YOU ARE TO INFORM THE EXAMINER WHEN YOU HAVE COMPLETED THE TASK CAUTION: Do not operate or alter equipment configuration in the plant without proper authorization.

INITIAL CONDITIONS:

Unit 1 has been at approximately 100% steady state power (currently at 99.9%) for 5 days.

Control Room Annunciator 05M03-A-4, PR LOWER DET FLUX DEV HI/AUTO DEF, alarms.

Initial action of 0POP09-AN-05M3-A-4 to verify all Control Rods are properly aligned, is complete. All Excore Nuclear Instrumentation Channels are operable and the detector currents (in microamps) are:

N41U = 537 N41L = 561 N42U = 554 N42L = 561 N43U = 536 N43L = 589 N44U = 579 N44L = 571 INITIATING CUE:

The Shift Supervisor instructs you to manually calculate QPTR per 0PSP10-NI-0002, Excore QPTR Determination.

- DO NOT DISCLOSE INFORMATION BELOW THIS LINE -

COMPLETION CRITERIA:

Applicant determines Upper Tilt Ratio = 1.002 (+/-0.003), Lower Tilt Ratio = 1.027 (+/-0.003), and QPTR = 1.027 (+/-0.003) and identifies the Acceptance Criteria is NOT met.

JPM NO:

PAGE 4 OF 7 JOB PERFORMANCE MEASURE INFORMATION SHEET (Cont.)

HANDOUTS:

• Unit 1 Plant Curve Book, Figure 5.1, Incore-Excore Cross-Calibration Constants

• 0PSP10-NI-0002, Excore QPTR Determination

• 0PSP10-NI-0002, Form 1,Data Package Cover Sheet

• 0PSP10-NI-0002, Form 2, Excore QPTR Data Sheet NOTES:

• Examiner has a KEY of Form 1 and Form 2 of 0PSP10-NI-0002 and Figure 5.1 of Unit 1, Plant Curve Book.

• The JPM copy of Figure 5.1 data may not be the current data in the Unit 1, Plant Curve Book.

When the JPM copy of Figure 5.1 is supplied to the applicant, inform the applicant that this is the Figure 5.1 applicable to the plant conditions for this JPM.

• The calculated QPTR is equal to approximately 1.027 (+/-0.003) and does not meet the procedure acceptance criteria and T.S. LCO actions 3.2.4.a and 3.2.4.b are entered.

JPM NO: A1 PAGE 5 OF 13 JOB PERFORMANCE MEASURE CHECK SHEET NOTE:

• Critical steps are identified by (C).

• Sequenced steps are identified by (S1, S2, . . .).

JPM START TIME SAT/UNSAT Performance Step: 1 Obtain the procedure.

Standard:

Applicant obtains current revision of 0PSP10-NI-0002, Excore QPTR Determination.

Comment:

Cue:

Provide the Handout Copy of 0PSP10-NI-0002, Excore QPTR Determination Notes:

The Handout Copy also includes partially completed Forms 1 and 2

JPM NO: A1 PAGE 6 OF 13 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 2 Review 0PSP10-NI-0002 for applicability and prerequisites.

Standard:

Applicant reviews procedure and verifies prerequisites are met and signs Form 1.

Comment:

Cue:

Notes:

SAT/UNSAT Performance Step: 3 Obtain latest Figure 5.1 in the Unit 1 Plant Curve Book.

Standard:

Obtains Figure 5.1 of the Unit 1 Plant Curve Book.

Comment:

Cue:

Provide the Exam Use Only copy of the Unit 1 Plant Curve Book, or the Handout Copy of Figure 5.1, Incore-Excore Cross Calibration Constants.

Notes:

The JPM copy of Figure 5.1 data may not be the current data in the Unit 1, Plant Curve Book, but contains the data applicable to this JPM.

JPM NO: A1 PAGE 7 OF 13 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 4 100% Power Detector Currents from Figure 5.1 and the current Indicated Detector Currents for the Upper and Lower Detectors are entered into Form 2.

Standard:

Enters the 100% and Indicated Power Currents onto Form 2.

Comment:

Cue:

Notes:

SAT/UNSAT Performance Step: 5 For each channel of Upper Detectors, calculate Normalized Current, then the sum of normalized currents, and average of normalized current.

Standard:

Calculates the Average Normalized Upper Current to be 1.003 (+/-0.003)

Comment:

Cue:

Notes:

JPM NO: A1 PAGE 8 OF 13 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 6(C)

Calculate Upper Tilt Ratio.

Standard:

Calculates the Upper Tilt Ratio to be 1.002 (+/-0.003)

Comment:

Cue:

Notes:

SAT/UNSAT Performance Step: 7 For each channel of Lower Detectors, calculate Normalized Current, then the sum of normalized currents, and average of normalized currents.

Standard:

Calculates the Average Normalized Lower Current to be 1.017 (+/-0.003)

Comment:

Cue:

Notes:

JPM NO: A1 PAGE 9 OF 13 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 8(C)

Calculate Lower Tilt Ratio.

Standard:

Calculates the Lower Tilt Ratio to be 1.027 (+/-0.003)

Comment:

Cue:

Notes:

SAT/UNSAT Performance Step: 9(C)

Determine QPTR.

Standard:

Determines the QPTR to be 1.027 (+/-0.003)

Comment:

Cue:

Notes:

JPM NO: A1 PAGE 10 OF 13 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 10 Obtain independent verification of calculations.

Standard:

Applicant informs examiner that independent verification is needed.

Comment:

Cue:

Inform applicant that the independent verification is complete with no changes.

Notes:

JPM NO: A1 PAGE 11 OF 13 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 11(C)

Verify the calculated QPTR meets acceptance criteria.

Standard:

Determines QPTR does NOT meet acceptance criteria and immediately notifies Shift Supervisor.

Comment:

Cue:

As Shift Supervisor, acknowledge applicants determination of results.

Notes:

- TERMINATE THE JPM -

JPM STOP TIME

JPM NO: A1 PAGE 12 OF 13 VERIFICATION OF COMPLETION Job Performance Measure: A1, PERFORM A QPTR CALCULATION Applicant's Name:

SSN:

Date Performed:

Time to Complete:

JPM Results: Sat / Unsat Evaluator: Signature __________________________

Date ____________________

JPM NO: A1 PAGE 13 OF 13 JPM - HANDOUT READ TO PERFORMER:

The evaluator will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

YOU ARE TO INFORM THE EXAMINER WHEN YOU HAVE COMPLETED THE TASK CAUTION: Do not operate or alter equipment configuration in the plant without proper authorization.

INITIAL CONDITIONS:

Unit 1 has been at approximately 100% steady state power (currently at 99.9%) for 5 days.

Control Room Annunciator 05M03-A-4, PR LOWER DET FLUX DEV HI/AUTO DEF, alarms.

Initial action of 0POP09-AN-05M3-A-4 to verify all Control Rods are properly aligned, is complete. All Excore Nuclear Instrumentation Channels are operable and the detector currents (in microamps) are:

N41U = 537 N41L = 561 N42U = 554 N42L = 561 N43U = 536 N43L = 589 N44U = 579 N44L = 571 INITIATING CUE:

The Shift Supervisor instructs you to manually calculate QPTR per 0PSP10-NI-0002, Excore QPTR Determination.

13admina2 - boration addition calculation formula (from Figure 3.1) 8.4298 ) ln( 7500 414 ) =

( 624461 KEY 7500 153 VB = 2679 gals OR 8.4298 ) ln( 7500 423 ) =

( 624461 7500 153 VB = 2774 gals KEY KEY

SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION D0527 KEY h:\wp\approved\psp\10\0zg0003.07w Effective Date: 02/05/97 Print Date: 1547 7/3/1 Quality Jay Eichenlaub PREPARER 0PSP10-ZG-0003 Shutdown Margin Verification - Modes 3, 4 and 5 Safety-Related Ernie Kee TECHNICAL Usage: REFERENCED Roland Dunn USER Rev. 7 General Effective Date: 02/05/97 Page 1 of 19 Nuclear Fuel & Analysis COGNIZANT ORGANIZATION Table of Contents Page

1.0 Purpose and Scope

. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 2.0 Responsibilities . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 3.0 Precautions and Notes . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 4.0 5.0 6.0 7.0 KEY Prerequisites . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 Procedure . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 Acceptance Criteria . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 References . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 8.0 Support Documents . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 Addendum 1 - Xenon Boron Correction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 Addendum 2 - SDM Validity Time . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 12 Form 1 - Data Package Cover Sheet . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 13 KEY Form 2 - Short Form SDM Limit Curve Method . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15 Form 3 - Long Form SDM Limit Curve Method . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 Form 4 - 0.95 Keff Method . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17 Form 5 - RCS Boron Concentration Inoperable Rod Correction . . . . . . . . . . . . . . . . . . . . . . . . . . 18 Form 6 - RCS Boron Concentration Xenon Correction and SDM Validity Time . . . . . . . . . . . . . 19

0PSP10-ZG-0003 Rev. 7 Page 2 of 19 KEY Shutdown Margin Verification - Modes 3, 4 and 5

1.0 Purpose and Scope

1.1 To verify that the SHUTDOWN MARGIN satisfies the requirements of Technical Specifications 4.1.1.1.1.a and 4.1.1.1.1.d when in Mode 3 or 4, and Technical Specifications 4.1.1.2.a and 4.1.1.2.b when in Mode 5.

1.2 This procedure is to be performed by Plant Operations or Reactor Engineering personnel.

2.0 Responsibilities 2.1 The Test Coordinator is responsible for identifying the portions of this procedure that are to be performed to satisfy the test purpose.

2.2 The Test Coordinator SHALL ensure that all requirements of this procedure are completed 2.3 2.4 data package. KEY and determine acceptability of the test results.

The procedure performer SHALL obtain data as specified in the procedure and prepare the The verifier SHALL verify all entries and calculations in the data package as specified in the procedure.

2.5 Shift Supervisor or designee SHALL complete the Second Review of Test Results on Form 1.

2.6 Shift Supervisor SHALL complete the Plant Operations Review of Test Results on Form 1 if acceptance criteria are not met.

3.0 Precautions and Notes KEY 3.1 Asterisk (*) on the checkoff denotes a step within the procedure that SHALL be signed off in the data package.

3.2 IF test results did NOT satisfy the acceptance criteria, THEN immediately notify the Shift Supervisor who SHALL complete the applicable portion of Form 1.

3.3 IF Xenon credit is used to verify SDM, THEN action SHALL be taken to prevent loss of SDM as Xenon concentration decreases due to decay.

3.4 The SDM limit typically increases as RCS temperature decreases; ensure adequate SDM exists to accommodate anticipated changes in plant conditions.

4.0 Prerequisites

0PSP10-ZG-0003 Rev. 7 Page 3 of 19 KEY Shutdown Margin Verification - Modes 3, 4 and 5 NOTE

! Data transferred from the Nuclear Design Report (NDR), Plant Curve Book, or alternate source SHALL be independently verified per Step 5.13.

! IF the NDR in step 4.1 is not available, THEN an alternate source may be used if it is approved and the source is recorded in the remarks section of Form 1.

4.1 An approved Nuclear Design Report (NDR) for the applicable unit and cycle is available.

4.2 The applicable unit and cycle Plant Curve Book Figure 5.5 Shutdown Margin KEY Limit Curve is available.

4.3 The plant is in Modes 3, 4, 5 or 6.

4.4 Notify the Shift Supervisor to review the Limiting Conditions for Operation Action Statements associated with TS 3.1.1.1 and 3.1.1.2, and Surveillance Requirements 4.1.1.1.1 and 4.1.1.2.

4.5 Obtain verbal permission from the Shift Supervisor to determine SDM and sign Form 1.

• KEY

0PSP10-ZG-0003 Rev. 7 Page 4 of 19 KEY Shutdown Margin Verification - Modes 3, 4 and 5 5.0 Procedure NOTE

! This procedure provides three methods of verifying SDM. Use the following guidelines to choose the best method to verify SDM based on plant conditions.

The "0.95 Keff" method is the most conservative. This method will verify actual RCS boron conditions greater than the Refueling, All Rods Out (ARO), K # 0.95 boron concentration. This method will provide the easiest way to verify SDM if multiple control and shutdown rods are inoperable (i.e. Rapid Refueling). This method SHALL only be used in Mode 5 or 6.

KEY The "Short Form SDM Limit Curve" method will verify RCS boron concentration greater than the Shutdown Margin Limit Curve in the Plant Curve Book. This method will account for inoperable control and shutdown rods, however, this method may be too conservative with multiple rods inoperable. This method will NOT account for Xenon or Samarium which adds conservatism. This method may be used in Modes 3, 4, or 5.

The "Long Form SDM Limit Curve" method provides less conservatism than the other two methods. This method will adjust the Shutdown Margin Limit Curve in the Plant Curve Book for Xenon. Samarium is not accounted for which adds conservatism. This method will also account for inoperable control and shutdown rods. This method may be used in Modes 3, 4, or 5.

! Throughout this procedure, Form 2 SHALL be used if verifying SDM by the "Short Form SDM Limit Curve" method, Form 3 SHALL be used if verifying SDM by the "Long Form SDM Limit Curve" method, and Form 4 SHALL be used if verifying SDM by the "0.95 Keff" method.

KEY 5.1 5.2 5.3 Verify applicable Prerequisites have been met AND Precautions and Notes have been read AND sign Form 1.

Enter the Unit and Cycle number on Form 1, Form 2, Form 3, Form 4, Form 5 and Form 6 as applicable.

Record the following information on Form 1:

5.3.1 Cycle burnup in MWD/MTU.

5.3.2 Minimum Loop RCS average temperature (Tavg) from QDPS, CP-005 or CP-018. Tavg may be obtained by averaging Thot and Tcold.

0PSP10-ZG-0003 Rev. 7 Page 5 of 19 KEY Shutdown Margin Verification - Modes 3, 4 and 5 NOTE

! Inoperable rods are those which are not fully inserted and are immovable as a result of excess friction or mechanical interference or known to be untrippable.

! Because of the Incomplete Rod Insertion issue at STP, safety evaluations may be applicable which allow stuck rods to be considered operable under certain RCS conditions. Refer to Plant Curve Book Figure 1.2 for a summary of any applicable safety evaluations for Incomplete Rod Insertion.

5.3.3 Inoperable rods.

KEY 5.3.3.1 Record the Number of inoperable rods with incomplete insertion at greater than 18 steps as indicated by DRPI.

5.3.3.2 Record the Number of inoperable rods with incomplete insertion at less than or equal to 18 steps as indicated by DRPI.

NOTE

! An RCS boron concentration greater than 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> old SHALL not be used to verify SDM at current conditions.

5.3.4 RCS boron concentration (CB RCS), sample date and sample time.

A boron sample up to 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br /> old may be used provided the RCS was not diluted since the sample time. Initiate RCS boron sampling KEY if required.

5.4 IF SDM is to be verified using the "Short Form SDM Limit Curve" method THEN proceed to Step 5.5 IF SDM is to be verified using the "Long Form SDM Limit Curve" method THEN proceed to Step 5.6. IF SDM is to be verified using the "0.95 Keff" method THEN proceed to Step 5.7.

0PSP10-ZG-0003 Rev. 7 Page 6 of 19 KEY Shutdown Margin Verification - Modes 3, 4 and 5 5.5 "Short Form SDM Limit Curve" method.

5.5.1 Verify the plant is in Mode 3, 4 or 5 and initial Form 2.

• 5.5.2 IF the number of inoperable rods recorded per Step 5.3 is NOT zero (0), THEN determine the RCS boron concentration inoperable rod correction (CB Rod) by completing Form 5. Record the value of CB Rod on Form 2.

5.5.3 IF the number of inoperable rods recorded per Step 5.3 is zero (0),

THEN record a value of zero (0) on Form 2 for the RCS boron concentration inoperable rod correction (CB Rod).

5.5.4 Determine the effective boron concentration (CB Effective) by the KEY following expression. Record CB Effective on Form 2.

CB Effective = CB RCS - CB Rod NOTE Do NOT interpolate Figure 5.5 for RCS average temperature. IF the RCS average temperature is between two of the supplied curves, THEN use the curve which provides the greater required boron concentration.

! A more conservative (more positive value) SHUTDOWN MARGIN Limit boron concentration (CB SDM Limit) may be recorded on Form 2. Ensure the RCS average temperature and cycle burnup used to determine the conservative value of SHUTDOWN MARGIN Limit boron concentration (CB SDM Limit) are recorded on Form 2, if applicable.

KEY 5.5.5 Obtain the SHUTDOWN MARGIN Limit boron concentration (CB SDM Limit) from Plant Curve Book Figure 5.5 at the RCS average temperature and cycle burnup recorded in Step 5.3.

5.5.5.1 5.5.5.2 Record the SHUTDOWN MARGIN Limit boron concentration (CB SDM Limit) on Form 2.

Record the RCS average temperature and cycle burnup used to determine the SHUTDOWN MARGIN Limit boron concentration (CB SDM Limit) on Form 2.

5.5.6 Continue with Step 5.8.

5.6 "Long Form SDM Limit Curve" method.

0PSP10-ZG-0003 Rev. 7 Page 7 of 19 KEY Shutdown Margin Verification - Modes 3, 4 and 5 5.6.1 Verify the plant is in Mode 3, 4 or 5 and initial Form 3.

• 5.6.2 IF the number of inoperable rods recorded per Step 5.3 is NOT zero (0), THEN determine the RCS boron concentration inoperable rod correction (CB Rod) by completing Form 5. Record the value of CB Rod on Form 3.

5.6.3 IF the number of inoperable rods recorded per Step 5.3 is zero (0),

THEN record a value of zero (0) on Form 3 for the RCS boron concentration inoperable rod correction (CB Rod).

5.6.4 Determine the RCS boron concentration Xenon correction (CB Xenon) per Addendum 1 and record the value on Form 3.

5.6.5 KEY Determine the effective boron concentration (CB Effective) by the following expression. Record CB Effective on Form 3.

CB Effective = CB RCS - CB Rod + CB Xenon NOTE

! Do NOT interpolate Figure 5.5 for RCS average temperature. IF the RCS average temperature is between two of the supplied curves, THEN use the curve which provides the greater required boron concentration.

! A more conservative (more positive value) SHUTDOWN MARGIN Limit boron concentration (CB SDM Limit) may be recorded on Form 3. Ensure the RCS average temperature and cycle burnup used to determine the conservative value of SHUTDOWN MARGIN Limit boron concentration (CB SDM Limit) are recorded on Form 3, if applicable.

KEY 5.6.6 Obtain the SHUTDOWN MARGIN Limit boron concentration (CB SDM Limit) from Plant Curve Book Figure 5.5 at the RCS average temperature and cycle burnup recorded in Step 5.3.

5.6.6.1 Record the SHUTDOWN MARGIN Limit boron concentration (CB SDM Limit) on Form 3.

0PSP10-ZG-0003 Rev. 7 Page 8 of 19 KEY Shutdown Margin Verification - Modes 3, 4 and 5 5.6.6.2 Record the RCS average temperature and cycle burnup used to determine the SHUTDOWN MARGIN Limit boron concentration (CB SDM Limit) on Form 3.

5.6.7 Continue with Step 5.8.

5.7 "0.95 Keff" method.

5.7.1 Verify the plant is in Mode 5 or 6 and initial Form 4.

• 5.7.2 The effective boron concentration (CB Effective) is equal to the RCS boron concentration (recorded on Form 1, Step 5.3.4). Record CB Effective on Form 4.

5.8 5.7.3 CB Effective = CB RCS KEY Obtain the Refueling CB, ARO, K # 0.95 from the applicable unit and cycle Plant Curve Book Figure 5.5. Record the value on Form 4 as the SHUTDOWN MARGIN Limit boron concentration (CB SDM Limit).

Compare the Effective boron concentration (CB Effective) with the SHUTDOWN MARGIN Limit boron concentration (CB SDM Limit). Record the results of the comparison on Form 2, Form 3 or Form 4.

5.9 Evaluate the test results against the acceptance criteria.

5.9.1 IF CB Effective is greater than or equal to CB SDM Limit, THEN adequate SHUTDOWN MARGIN is present.

KEY 5.9.2 IF CB Effective is less than CB SDM Limit, THEN adequate SHUTDOWN MARGIN is NOT present.

5.10 IF SDM was verified using the "Long Form SDM Limit Curve" method, complete Addendum 2 to determine the length of time that the SDM verification remains valid. Record the SDM Validity Time on Form 3.

5.11 The test coordinator SHALL sign completed Form 2, Form 3, Form 4, Form 5, or Form 6.

• 5.12 Forward the test package to a verifier.

0PSP10-ZG-0003 Rev. 7 Page 9 of 19 KEY Shutdown Margin Verification - Modes 3, 4 and 5 5.13 The verifier SHALL perform the following:

5.13.1 Independently verify all entries on completed Form 2, Form 3, Form 4, Form 5 and Form 6.

5.13.2 Verify any assumed conservative values on Form 2 or Form 3 are truly conservative.

5.13.3 Sign completed Form 2, Form 3, Form 4, Form 5 and Form 6 when the verification is complete.

• 5.13.4 Forward the test package to the Test Coordinator.

5.14 The Test Coordinator SHALL ensure the names of all data takers and 5.15 5.16 5.17 KEY procedure performers are entered on Form 1.

Indicate the reason for performing this test on Form 1.

Evaluate the test results against the acceptance criteria.

Indicate the test results, sign, AND enter the date and time on Form 1.

• 5.18 IF the test results did not satisfy the acceptance criteria, THEN perform the following:

5.18.1 Immediately notify the Shift Supervisor who SHALL complete the applicable portion of Form 1.

5.18.2 Notify the Reactor Engineering Supervisor.

KEY 5.18.3 Initiate a Condition Report.

5.19 IF xenon credit was used to verify SDM, THEN ensure the Shift Supervisor is notified of the SDM Validity Time and a Control Room log entry is made to document the SDM Validity Time.

5.20 Notify the Shift Supervisor that testing has been completed, then sign Form 1.

• 5.21 Ensure this surveillance is logged as complete in the Control Room Log Book.

5.22 Forward the Data Package to the Shift Supervisor or designee for a second review.

0PSP10-ZG-0003 Rev. 7 Page 10 of 19 KEY Shutdown Margin Verification - Modes 3, 4 and 5 5.23 The Shift Supervisor or designee SHALL indicate the acceptability of the test results AND sign Form 1.

• 5.24 IF the second review, or any subsequent review reveals that the test results have not satisfied the Acceptance Criteria, THEN notify the Shift Supervisor who SHALL complete applicable portion of Form 1.

5.25 Forward the test package for review in accordance with 0PGP03-ZE-0004 (Plant Surveillance Program).

6.0 Acceptance Criteria The Effective boron concentration (CB Effective) is greater than or equal to the SHUTDOWN MARGIN Limit boron concentration (CB SDM Limit).

7.0 References 7.1 7.2 7.3 KEY Technical Specification 3.1.1.1 and 3.1.1.2.

0PEP02-ZG-0001 (Xenon Worth Calculation), Rev. 1 SER 92-015 (Loss of Shutdown Reactivity Margin) 7.4 5Z010Z51003 STP Setpoint Document - Section Q.1 8.0 Support Documents 8.1 Addendum 1 Xenon Boron Correction 8.2 Addendum 2 SDM Validity Time KEY 8.3 8.4 8.5 8.6 Form 1 Data Package Cover Sheet Form 2 Short Form SDM Limit Curve Method Form 3 Long Form SDM Limit Curve Method Form 4 0.95 Keff Method 8.7 Form 5 RCS Boron Concentration Inoperable Rod Correction 8.8 Form 6 RCS Boron Concentration Xenon Correction and SDM Validity Time

0PSP10-ZG-0003 Rev. 7 Page 11 of 19 KEY Shutdown Margin Verification - Modes 3, 4 and 5 Addendum 1 Xenon Boron Correction Page 1 of 1 1.0 Determine the present Xenon Worth (XW) per 0PEP02-ZG-0001 (Xenon Worth Calculation) or from an approved computer code. Record the Xenon Worth (XW), date and time on Form 6 as a negative value.

2.0 Obtain the Differential Boron Worth (DBW) from the applicable unit and cycle Nuclear Design Report (NDR) for the RCS conditions recorded on Form 3. The DBW should be obtained by interpolating on boron concentration, RCS average temperature and burnup. DBW values should be located in NDR Appendix A. Record the DBW on Form 6 as a negative value.

3.0 Calculate the RCS boron concentration poison correction (CB Xenon) by dividing the Xenon Worth (XW) by the Differential Boron Worth (DBW). Record CB Xenon on Form 6.

KEY CB Xenon = XW / DBW KEY

0PSP10-ZG-0003 Rev. 7 Page 12 of 19 KEY Shutdown Margin Verification - Modes 3, 4 and 5 Addendum 2 SDM Validity Time Page 1 of 1 This Addendum SHALL be performed if Xenon credit was used to verify adequate SDM. This Addendum is necessary since poison decay may cause a loss of adequate SDM unless appropriate operator action is taken to account for the decay. This Addendum assumes that RCS boron concentration does not decrease and the SDM Limit remains unchanged through the SDM Validity Time.

1.0 Using the data recorded on Form 3, calculate the amount of Effective boron concentration in excess of the SHUTDOWN MARGIN limit boron concentration (CB Excess). Record CB Excess on Form 6.

CB Excess = CB Effective - CB SDM Limit KEY 2.0 Calculate the Excess Boron Worth (EBW) by multiplying CB Excess by the Differential Boron Worth (DBW). Obtain the DBW from Addendum 1, Step 2, Form 6. Record EBW on Form 6 as a negative value.

EBW = CB Excess x DBW 3.0 Calculate the Minimum Xenon Worth (MXW) required to ensure adequate SDM by subtracting the Excess Boron Worth (EBW) from the Xenon Worth (XW). Obtain XW from Addendum 1, Step 1, Form 6. Record the MXW on Form 6.

MXW = XW - EBW NOTE SDM Validity Time is that time at which SDM is lost due to xenon concentration decrease from radioactive decay.

4.0 5.0 KEYIF the Minimum Xenon Worth (MXW) is greater than or equal to zero (0), THEN adequate SDM exists assuming no credit for Xenon. IF the MXW is greater than or equal to zero (0), THEN the SDM Validity Time is indefinite. Record the SDM Validity Time on Form 6.

IF the MXW is less than zero (0), THEN use 0PEP02-ZG-0001 (Xenon Worth Calculation) or an approved computer code to determine the time (SDM Validity Time) when the Xenon worth will be less negative than the Minimum Xenon Worth (MXW). Record the SDM Validity Time on Form 6.

0PSP10-ZG-0003 Rev. 7 Page 13 of 19 KEY Shutdown Margin Verification - Modes 3, 4 and 5 Form 1 Data Package Cover Sheet (Sample) Page 1 of 2 Unit 1 Cycle 10 Tech Spec

Reference:

Test Interval: Modes Required: Test Performance Mode:

4.1.1.1.1.d or 4.1.1.2.b 24 Hour (Periodic) 4.1.1.1.1.a or 4.1.1.2.a 12 Hour (Conditional) Mode 3, 4 or 5 3, 4, 5, or 6 Reason for Test:

X For Surveillance Credit (T.S.4.1.1.1.1.a) G Periodic Surveillance Test G Not for Surveillance Credit G Other Test Results:

G X

Test Completed By:

Second Review of Test Results:

Signature Test Coordinator KEY Acceptable (All Acceptance Criteria met)

Unacceptable (Any Acceptance Criteria NOT met)

Date Date Time Time G Acceptable (All Acceptance Criteria met)

G Unacceptable (Any Acceptance Criteria NOT met)

Test Reviewed By:

Shift or Unit Supervisor Date Time Plant Operations Review of Test Results(if required):

IF test results are unacceptable, IMMEDIATELY inform the Shift Supervisor who SHALL KEY complete the following:

Potential Reportable Occurrence G Yes G No LCO Action Statement Entered G Yes G No Corrective Action Taken:

Reviewed By:

Shift Supervisor Date Time All pages of this form and Form 2, Form 3, or Form 4 SHALL be included in the data package. The data package SHALL also include Form 5 or Form 6 if completed.

This Form, when complete, SHALL be retained for the life of the plant.

0PSP10-ZG-0003 Rev. 7 Page 14 of 19 KEY Shutdown Margin Verification - Modes 3, 4 and 5 Form 1 Data Package Cover Sheet (Sample) Page 2 of 2 Performers and Verifiers Name (Printed) Signature Initials Sections Performed 4.0, 5.0-5.5, 5.8, 5.9, 5.11, Name Signature Initials 5.12, 5.14-5.18 4.5 Verbal permission from the Shift Supervisor Signature obtained to commence testing: Test Coordinator 5.1 5.3 Applicable prerequisites have been met and Precautions and Notes have been read:

Cycle Burnup:

Minimum Loop RCS Tavg:

16,100 567 KEY MWD/MTU EF Signature Test Coordinator

1. of Inoperable Rods 0 Rods with incomplete insertion at > 18 Steps on DRPI 0 Rods with incomplete insertion at # 18 Steps on DRPI CB RCS 153 ppm (20 minutes ago)

Sample Date Sample Time 5.20 Shift Supervisor notified of test completion: Signature Test Coordinator KEY Remarks:

This Form, when complete, SHALL be retained for the life of the plant.

0PSP10-ZG-0003 Rev. 7 Page 15 of 19 KEY Shutdown Margin Verification - Modes 3, 4 and 5 Form 2 Short Form SDM Limit Curve Method (Sample) Page 1 of 1 Unit __1__ Cycle __10__

5.5.1 Plant is in Mode 3, 4 or 5: Initial Initial 5.5.2 CB Rod = (+) 0 ppm 5.5.3 5.5.4 CB Effective = 153 - 0 CB RCS CB Rod This value may be 414 ppm or 423 ppm KEY CB Effective = 153 ppm depending on the method used to extract the SDM limit from figure 5.5 5.5.5.1 CB SDM Limit = ppm 5.5.5.2 RCS Average Temperature 567 °F Cycle Burnup 16100 MWD/MTU 5.8 Is CB Effective $ CB SDM Limit? Yes X No KEY Completed By: Signature Date: Date Verified By: Date:

This Form, when complete, SHALL be retained for the life of the plant.

0PSP10-ZG-0003 Rev. 7 Page 16 of 19 KEY Shutdown Margin Verification - Modes 3, 4 and 5 Form 3 Long Form SDM Limit Curve Method (Sample) Page 1 of 1 Unit _____ Cycle _____

5.6.1 Plant is in Mode 3, 4 or 5:

Initial 5.6.2 CB Rod = (+) ppm 5.6.3 5.6.4 CB Xenon = (+) ppm KEY 5.6.5 CB Effective = - +

CB RCS CB Rod CB Xenon CB Effective = ppm 5.6.6.1 CB SDM Limit = ppm 5.6.6.2 RCS Average Temperature °F Cycle Burnup MWD/MTU 5.8 Is CB Effective $ CB SDM Limit? Yes No 5.10 KEY SDM Validity Time (until):

Date Time Completed By: Date:

Verified By: Date:

This Form, when complete, SHALL be retained for the life of the plant.

0PSP10-ZG-0003 Rev. 7 Page 17 of 19 KEY Shutdown Margin Verification - Modes 3, 4 and 5 Form 4 0.95 Keff Method (Sample) Page 1 of 1 Unit _____ Cycle _____

5.7.1 Plant is in Mode 5 or 6:

Initial 5.7.2 CB Effective = ppm 5.7.3 CB SDM Limit = ppm 5.8 Is CB Effective > CB SDM Limit? Yes KEY No KEY Completed By: Date:

Verified By: Date:

This Form, when complete, SHALL be retained for the life of the plant.

0PSP10-ZG-0003 Rev. 7 Page 18 of 19 KEY Shutdown Margin Verification - Modes 3, 4 and 5 RCS Boron Concentration Inoperable Rod Correction Form 5 Page 1 of 1 (Sample)

Unit ___1_ Cycle __10___

Number of Equivalent Boron Equivalent Inoperable Rods per Rod (ppm/rod) Boron (ppm)

(1) (2) (3)

Inoperable rods with incomplete insertion at > 18 Steps on DRPI Inoperable rods with incomplete insertion at # 18 Steps on DRPI (1)

(2)

1. of inoperable rods from Form 1 Values are from Reference 7.4 KEY RCS Boron Concentration Inoperable Rod Correction (ppm) CB Rod (4)

(3) Equivalent Boron is equal the Number of Inoperable Rods times the Equivalent Boron per Rod.

(3) = (1) x (2)

(4) RCS Boron Concentration Inoperable Rod Correction (CB Rod) is the sum of the Equivalent Boron for Inoperable rods with incomplete insertion at > 18 Steps on DRPI and Equivalent Boron for Inoperable rods with incomplete insertion at # 18 Steps on DRPI.

[Sum of column (3)]

KEY Remarks:

Completed By: Date:

Verified By: Date:

This Form, when complete, SHALL be retained for the life of the plant.

0PSP10-ZG-0003 Rev. 7 Page 19 of 19 KEY Shutdown Margin Verification - Modes 3, 4 and 5 RCS Boron Concentration Xenon Correction Form 6 Page 1 of 1 and SDM Validity Time (Sample)

Unit _____ Cycle _____

Addendum 1 1.0 XW = (-) pcm Date Time 2.0 DBW = (-) pcm/ppm 3.0 CB Xenon = /

XW DBW KEY CB Xenon = (+) ppm Addendum 2 1.0 CB Excess = -

CB Effective CB SDM Limit CB Excess = (+) ppm 2.0 EBW = x CB Excess DBW EBW = (-) pcm 3.0 MXW = -

XW EBW 4.0 5.0 KEY MXW = ( ) pcm SDM Validity Time (until):

Date Time Completed By: Date:

Verified By: Date:

This Form, when complete, SHALL be retained for the life of the plant.

JPM NO: A2 PAGE 1 OF 11 NUCLEAR TRAINING DEPARTMENT JOB PERFORMANCE MEASURE TITLE: DETERMINE BORATION REQUIRED TO ACHIEVE DESIRED SHUTDOWN MARGIN JPM NO.: A2 REVISION: 1 LOCATION: N/A

JPM NO: A2 PAGE 2 OF 11 JOB PERFORMANCE MEASURE WORKSHEET JPM

Title:

DETERMINE BORATION REQUIRED TO ACHIEVE DESIRED SHUTDOWN MARGIN JPM No.: A2 Rev. No.: 1 Task No.: 76950, Perform a Shutdown Margin verification 70100, Perform a boration of the Reactor Coolant System STP Objective: Determine Shutdown Margin Using Procedures Perform Boration of RCS Related K/A

Reference:

2.1.25 [2.8] Ability to Obtain and Interpret References

References:

0PSP10-ZG-0003, Shutdown Margin Verification Modes 3, 4, and 5 Figure 3.1, Unit 1 Plant Curve Book, Boration / Dilution Figure 5.5, Unit 1 Plant Curve Book, Shutdown Margin Limit Curve Task Normally Completed By: RO Method of Testing: Actual Performance Location of Testing: N/A Time Critical Task: NO Alternate Path JPM: NO Validation Time: 20 minutes Required Materials (Tools/Equipment):

Calculator

JPM NO: A2 PAGE 3 OF11 JOB PERFORMANCE MEASURE INFORMATION SHEET READ TO PERFORMER:

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

YOU ARE TO INFORM THE EXAMINER WHEN YOU HAVE COMPLETED THE TASK CAUTION: Do not operate or alter equipment configuration in the plant without proper authorization.

INITIAL CONDITIONS:

Unit 1 was manually tripped from 100% power due to Main Turbine governor valve problems.

The Unit will remain in Mode 3, NOP/NOT, while troubleshooting governor valves.

Additional plant conditions are:

• Unit 1 Cycle 10

• Mode 3, Tavg = 567°F (all loops)

• 439 EFPD (16,100MWD/MTU)

• RCS Boron Concentration 153 ppm (20 minutes ago)

• BAT A & B at 7500 ppm

• All control rods have inserted fully into the core INITIATING CUE:

You are the extra Reactor Operator and the Unit Supervisor directs you to determine the Xenon Free shutdown margin for Mode 3, 567°F using the Short Form in accordance with 0PSP10-ZG-0003 and then, if necessary, determine how many gallons of boron addition are needed to attain the required shutdown margin.

JPM NO: A2 PAGE 4 OF 11 JOB PERFORMANCE MEASURE INFORMATION SHEET (Cont.)

- DO NOT DISCLOSE INFORMATION BELOW THIS LINE -

COMPLETION CRITERIA:

Completes Form 2 of 0PSP10-ZG-0003, Short Form SDM Limit Curve Method to obtain a target boron concentration. Calculates the boron addition needed to maintain proper shutdown margin is a minimum of 2679 gals. (Based on Interpolation of Figure 5.5 table at 16,100 MWD/MTU - yielding 414 ppm .)

OR The applicant may choose to use a more conservative value of 423 ppm at 16,000 MWD/MTU and not do this interpolation. This would yield a calculated value for boron addition of a minimum of 2,774 gals (423ppm).

HANDOUTS:

• 0PSP10-ZG-0003, Shutdown Margin Verification Modes 3, 4, and 5 NOTES:

• Interpolation of Figure 5.5 table yields 414 ppm @ 16,100 MWD/MTU.

• The applicant may choose to use the more conservative value of 423ppm @

16,000 MWD/MTU and not do this interpolation.

• The calculated values for boron addition from Figure 3.1 formula are a minimum of 2,679 gals (414ppm) or 2,774 gals (423ppm)

• A copy of a Unit 1 Plant Curve Book will be available in the examination area.

• A copy of the Nuclear Design Report (NDR) will be available in the examination area.

• The examiner is provided a KEY for the procedure and one for the calculation.

JPM NO: A2 PAGE 5 OF 11 JOB PERFORMANCE MEASURE CHECK SHEET NOTE:

• Critical steps are identified by (C).

• Sequenced steps are identified by (S1, S2, . . .).

JPM START TIME SAT/UNSAT Performance Step: 1 Obtain the procedure.

Standard:

Obtains controlled or working copy of 0PSP10-ZG-0003, Shutdown Margin Verification -

Modes 3, 4, and 5.

Comment:

Cue:

Provide the Handout Copy of 0PSP10-ZG-0003.

Notes:

JPM NO: A2 PAGE 6 OF 11 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 2 Verifies the prerequisites are complete.

Standard:

____ Verifies copies of the NDR and Unit 1 Plant Curve Book are available.

____ Verifies the plant is in Modes 3, 4, 5 or 6

____ Notifies the Shift Supervisor to review Tech Specs 3.1.1.1 and 3.1.1.2

____ Obtains verbal permission from the shift Supervisor to determine shutdown margin Comment:

Cue:

• As Shift Supervisor, acknowledge the request to review Tech Specs 3.1.1 and 3.1.2

• As Shift Supervisor, give applicant verbal permission to determine shutdown margin.

Notes:

Applicant will enter cycle data on form 1, then transition to procedure step 5.5 to perform the Short Form SDM Limit Curve Method on Form 2.

JPM NO: A2 PAGE 7 OF 11 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 3(C)

Determine CB Effective.

Standard:

Calculates CB Effective to be 153 ppm.

Comment:

Cue:

Notes:

JPM NO: A2 PAGE 8 OF 11 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 4(C)

Determine CB SDM Limit.

Standard:

Interpolates Figure 5.5 table for burnup of 16,100 MWD/MTU and 567°F and determines CB SDM Limit = 414 ppm OR the applicant may choose to use the more conservative value at 16,000 MWD/MTU and not do this interpolation which yields a CB SDM Limit of 423 ppm.

Comment:

The applicant may determine that the acceptance criteria of the test are not met, but since the Shutdown Margin was calculated for a xenon free condition (which does not exist now), a Tech Spec violation has NOT occurred.

Cue:

• If asked, inform applicant that a verification of data has been completed.

• When applicant informs SS that RCS boron is NOT adequate, direct the applicant to determine how many gallons of boron addition is needed to achieve the Xenon Free Shutdown Margin.

Notes:

JPM NO: A2 PAGE 9 OF 11 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 5(C)

Calculate volume of Boric Acid needed to maintain Xenon Free Shutdown Margin at 567°F.

Standard:

Calculates $ 2,679 gals (414 ppm) or $ 2,774 gals (423 ppm).

Comment:

It is expected that the applicant use the boration formula located on Figure 3.1 of the Plant Curve Book to perform this calculation.

Cue:

Notes:

The applicant may opt to calculate the boron addition for a few ppm higher than what the shutdown margin calculation calls for or add several gallons of acid to the final answer for conservatism as it is common practice to do this at STP.

- TERMINATE THE JPM -

JPM STOP TIME

JPM NO: A2 PAGE 10 OF 11 VERIFICATION OF COMPLETION Job Performance Measure: A2, DETERMINE BORATION REQUIRED TO ACHIEVE DESIRED SHUTDOWN MARGIN Applicant's Name:

SSN:

Date Performed:

Time to Complete:

JPM Results: Sat / Unsat Evaluator: Signature __________________________

Date ____________________

JPM NO: A2 PAGE 11 OF 11 JPM - HANDOUT READ TO PERFORMER:

The evaluator will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

YOU ARE TO INFORM THE EXAMINER WHEN YOU HAVE COMPLETED THE TASK CAUTION: Do not operate or alter equipment configuration in the plant without proper authorization.

INITIAL CONDITIONS:

Unit 1 was manually tripped from 100% power due to Main Turbine governor valve problems.

The Unit will remain in Mode 3, NOP/NOT, while troubleshooting governor valves.

Additional plant conditions are:

• Unit 1 Cycle 10

• Mode 3, Tavg = 567°F (all loops)

• 439 EFPD (16,100MWD/MTU)

• RCS Boron Concentration 153 ppm (20 minutes ago)

• BAT A & B at 7500 ppm

• All control rods have inserted fully into the core INITIATING CUE:

You are the extra Reactor Operator and the Unit Supervisor directs you to determine the Xenon Free shutdown margin for Mode 3, 567°F using the Short Form in accordance with 0PSP10-ZG-0003 and then, if necessary, determine how many gallons of boron addition are needed to attain the required shutdown margin.

SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION D0527 Rev. 21 Page 1 of 64 STI 31200449 0PSP03-EW-0018 KEY Quality C. Gellner PREPARER Table of Contents Essential Cooling Water System Train B Testing Safety-Related K. D. Regis TECHNICAL Usage: IN HAND Effective Date: 11/15/2000 Crew 2B USER Operations COGNIZANT DEPT.

Page Procedure Performance Data Sheet................................................................................................................ 2

1. 0 Purpose and Scope............................................................................................................................. 5

2. 0 Responsibilities ................................................................................................................................. 6

3. 0 Precautions and Notes........................................................................................................................ 7

4. 0 Prerequisites .................................................................................................................................... 10

5. 0 Procedure......................................................................................................................................... 13 5.1 Preparations........................................................................................................................... 13 5.2 Essential Cooling Water Pump 1B(2B) Startup ..................................................................... 14 5.3 Testing Emergency Backflush Valves 1(2)-EW-0278 and 1(2)-EW-0404 ............................ 18 5.4 Testing Essential Cooling Water Pump 1B(2B)..................................................................... 19 5.5 Testing ECW Pump 1B(2B) Discharge Check Valve 1(2)-EW-0042 .................................... 35 5.6 Restoration of Essential Cooling Water System Flow ........................................................... 39 5.7 Testing ECW Screen Wash Booster Pump 1B(2B)................................................................ 42 5.8 Testing ECW Screen Wash Booster Pump Discharge Check Valve 1(2)-EW-0254 .............. 47 5.9 Restoration of ECW Screen Wash System............................................................................. 48 5.10 Testing ECW Blowdown Isolation Valve 1(2)-EW-FV-6936 ............................................... 50 5.11 Testing Essential Cooling Water Valves................................................................................ 52 5.12 Restoration & Documentation................................................................................................ 54

6. 0 Acceptance Criteria ......................................................................................................................... 55

7. 0 References ....................................................................................................................................... 56

8. 0 Support Documents .......................................................................................................................... 59 Addendum 1, Essential Cooling Water Pump Bay Level Correction Factor.................................... 60 Addendum 3, ECW Screen Wash Booster Pump Vibration Test Point Locations and Instructions ................................................................................................................ 62 Addendum 4, ECW Screen Wash Booster Pump 1B(2B) Flow ....................................................... 63 KEY Data Sheet 1, Essential Cooling Water Flow from CCW Heat Exchanger....................................... 64

KEY Unit Number:

1 0PSP03-EW-0018 Essential Cooling Water System Train B Testing Procedure Performance Data Sheet Work Activity Number: 191260 Rev. 21

-ST: 86000720 Page 2 of 64 Technical Specification

Reference:

3.7.4 [ITS 3.7.8]

4.0.5 [ITS 5.5.8]

4.3.2.1.1.c.7 [ITS SR 3.3.2.7.1c]

Test Interval: Test Performance Allowed in Plant Modes: Train

Reference:

Quarterly 1, 2, 3, 4, 5, 6 and Core Offloaded to the Spent Fuel Pool B Reason for Test:

Periodic Surveillance Test For Surveillance Credit Maintenance Work Package # 178605 ¨ Not for Surveillance Credit

¨ Other ¨ Increased Frequency Testing Radiation Work Permit No.: Fire Hazard Evaluation No.: Equipment Clearance No.:

N/A N/A N/A Administrative Approval to Perform Test:

Shift Supervisor Shift Supervisor Date Time Test Results Review:

Pump Test Results:

¨ Acceptable - All data within Acceptance Criteria

¨ Acceptable - Data within Alert Range (explain in Remarks Section)

Unacceptable - Any data NOT within Acceptance Criteria (explain in Remarks Section)

Valve Test Results:

¨ Acceptable - All data within Acceptance Criteria

¨ Unacceptable - Any data NOT within Acceptance Criteria (explain in Remarks Section)

Reviewed by: Test Coordinator Test Coordinator Date Time Plant Operations Review:

All data within Acceptance Criteria? ¨ Yes ¨ No Any pump data within Alert Range? ¨ Yes ¨ No ECW Train B in Service? ¨ Yes ¨ No Potential Reportable Occurrence? ¨ Yes ¨ No LCO Action Statement Entered? ¨ Yes ¨ No Reviewed by:

Shift Supervisor Date Time KEY This procedure, when complete, shall be retained for the life of the plant.

KEY 0PSP03-EW-0018 Essential Cooling Water System Train B Testing Procedure Performance Data Sheet Division Surveillance Coordinator Review:

Rev. 21 Page 3 of 64 Reviewed by:

Division Surveillance Coordinator Date Time Section XI Coordinator:

Pump Test Results:

¨ Acceptable - All data within Acceptance Criteria

¨ Acceptable - Data within Alert Range (explain in Remarks Section)

¨ Unacceptable - Any data NOT within Acceptance Criteria (explain in Remarks Section)

Valve Test Results:

¨ Acceptable - (All data within Acceptance Criteria)

¨ Unacceptable - (Any data NOT within Acceptance Criteria)(explain in Remarks Section)

Corrective Action Taken:

Reviewed by:

Section XI Coordinator Date Time M&TE Used:

Description STPEGS No. Cal. Due Date 0-100 psig Test gage 100-9-27 11-11-01 Stopwatch 100-12 12-10-01 Vibration Instrument 100-01352-001 03-21-02 Vibration Instrument probe 100-01352-001 03-21-02 Vibration Instrument 100-01121-001 01-14-02 Vibration Instrument Probe KEY This procedure, when complete, shall be retained for the life of the plant.

KEY Performers and Verifiers:

Name (Print) 0PSP03-EW-0018 Essential Cooling Water System Train B Testing Procedure Performance Data Sheet Signature Rev. 21 Initials Page 4 of 64 Sections Performed Remarks:

KEY This procedure, when complete, shall be retained for the life of the plant.

KEY

1.0 Purpose and Scope

1.1 0PSP03-EW-0018 Essential Cooling Water System Train B Testing Rev. 21 Page 5 of 64 This procedure provides instructions to demonstrate components in the Essential Cooling Water System, required to perform a specific function in shutting down the Reactor to a Cold Shutdown Condition or mitigating the consequences of an accident, are Operable per Technical Specification 4.0.5 [ITS 5.5.8] and the Unit 1/Unit 2 Pump and Valve Inservice Test Plan.

1.2 Satisfactory performance of Section 5.4 will partially satisfy the quarterly testing requirements of a Slave Relay Test for ECW Pump 1B(2B) per Technical Specification 4.3.2.1.1.c.7 [ITS SR 3.3.2.7.1c].

1.3 This procedure provides instructions to verify the following pumps are operating properly by observing that pump performance is within the allowable range of Acceptance Criteria:

• Essential Cooling Water Pump 1B(2B)

• Essential Cooling Water Screen Wash Booster Pump 1B(2B) 1.4 This procedure provides instructions for verifying the following Essential Cooling Water System valves are Operable by cycling open and closed and verifying valve stroke time is within Acceptance Criteria:

• 1(2)-EW-FV-6936, ECW Blowdown Valve

• 1(2)-EW-FV-6924, ECW Screen Wash Booster Pump 1B(2B) Discharge Valve

• 1(2)-EW-MOV-0137, ECW Pump 1B(2B) Discharge Valve 1.5 This procedure provides instructions for verifying the following valves move to the fail-safe position upon loss of actuator power:

• 1(2)-EW-FV-6936, ECW Blowdown Valve

• 1(2)-EW-FV-6924, ECW Screen Wash Booster Pump 1B(2B) Discharge Valve 1.6 This procedure provides instructions for verifying the following check valves will pass full design accident flow:

• 1(2)-EW-0042, ECW Pump 1B(2B) Discharge Check Valve

• 1(2)-EW-0404, Emergency Backflush Check Valve

• 1(2)-EW-0254, ECW Screen Wash Booster Pump 1B(2B) Discharge Check Valve KEY This procedure, when complete, shall be retained for the life of the plant.

KEY 1.7 0PSP03-EW-0018 Essential Cooling Water System Train B Testing Rev. 21 Page 6 of 64 This procedure provides instructions for manual operation of Self Cleaning Strainer Emergency Backflush Valve 1(2)-EW-0278 and ECW Pump 1B(2B) Discharge Strainer Backflush Throttle Valve 1(2)-EW-0189 through at least one cycle of operation.

1.8 This procedure verifies that ECW Pump 1B(2B) Room Fans and dampers operate during ECW Pump 1B(2B) operation.

1.9 This procedure verifies the ECW Self Cleaning Strainer starts on ECW Pump Start.

2.0 Responsibilities 2.1 Test Coordinator shall ensure that the procedure revision is correct and that all applicable Field Changes are incorporated.

2.2 Shift Supervisor shall grant permission for performance of this test.

2.3 This procedure shall be performed by Plant Operations.

2.4 WHEN "_____" (blank) follows a step, THEN the performer shall enter initials to verify step completion.

2.5 Plant Performance personnel may perform the vibration monitoring portion of this procedure on the ECW Pump.

2.6 Plant Performance personnel may perform the vibration-monitoring portion of this procedure for the ECW Screen Wash Booster Pump (ECWSWBP).

2.7 I&C Maintenance shall perform venting of the ECW System flow instruments.

NOTE After completion, procedure routing is per 0PGP03-ZE-0004, Plant Surveillance Program, and 0PGP03-ZA-0055, Plant Surveillance Scheduling.

2.8 The following shall review the test results:

• Test Coordinator

• Shift Supervisor

• Division Surveillance Coordinator

• Section XI Coordinator KEY This procedure, when complete, shall be retained for the life of the plant.

KEY 3.0 Precautions and Notes 3.1 0PSP03-EW-0018 Essential Cooling Water System Train B Testing Rev. 21 Page 7 of 64 IF one of the following occurs during performance of this test, THEN suspend the test AND restore Essential Cooling Water System to normal.

• Safety Injection Signal

• Loss of Offsite Power 3.2 IF either of the following conditions occur during testing of the ECW Pump, THEN suspend performance of the test until the condition is restored to the pre-test condition and the Essential Cooling System is stabilized prior to continuing:

• Automatic start of the ECW Screen Wash Booster Pump

• Increasing temperatures from components supplied with ECW which may be an indication of inadequate ECW flow 3.3 IF during performance of this test, the ECW Self Cleaning Strainer differential pressure exceeds 5 psid as indicated by a Plant Computer alarm OR local indication on 1(2)-EW-PDI-6869, THEN the following shall be performed:

• Suspend testing

• Open 1(2)-EW-0189

• Start ECW Self Cleaning Strainer 3.3.1 WHEN strainer differential pressure is <5 psid, THEN perform the following:

• Stop the ECW Self Cleaning Strainer

• Close 1(2)-EW-0189

• Resume testing 3.4 This procedure should be reviewed in its entirety prior to performing the test.

KEY This procedure, when complete, shall be retained for the life of the plant.

KEY 3.5 0PSP03-EW-0018 Essential Cooling Water System Train B Testing Rev. 21 Page 8 of 64 Specific Reference Values incorporated in this procedure were obtained for the respective equipment on the following dates:

Component Description Reference Value Date Essential Cooling Water Pump 1B 10-14-00 ECW Screen Wash Booster Pump 1B 05-31-94 Essential Cooling Water Pump 2B 05-09-97 ECW Screen Wash Booster Pump 2B 08-03-94 3.6 Essential Cooling Water System flows from QDPS are indicated on QDPS Detail Data Menu Page 9.

3.7 Communications between the Control Room, ECW Intake Structure, and CCW Heat Exchanger Room shall be maintained during testing in which valves or control switches are NOT in normal alignment.

3.8 Valves subject to testing shall be closed/opened by normal operation and without preliminary or subsequent exercising or adjustments. Tightening of a valve by manual means after operation of a valve operator, cycling a valve to improve leakage or stroke time performance, and mechanical agitation (tapping) of valves are examples of activities NOT allowed. (Ref. 7.4.4) 3.9 In order to ensure an air operated valve has sufficient time to reach normal air pressure prior to stroke timing the valve, approximately 2 minutes should have elapsed since the valve was last stroked.

3.10 IF the Essential Chillers are in Cold Weather alignment, THEN it will be necessary to use 0POP02-CH-0005, Essential Chiller Operation, to ensure 1(2)-EW-3016 and 1(2)-EW-3019 are properly restored to their AS FOUND position in Section 5.6.

3.11 The Valve Database, as referred to in this procedure, is the currently approved database used by Plant Operations to determine required valve positions. As of the Effective Date of this procedure, the ECO Database is the currently approved database. Future plans are a database within the Station MED system.

3.12 IF a discrepancy is found between AS FOUND position and REQUIRED POSITION as directed by a Step in this procedure, THEN the Shift Supervisor SHALL be notified to determine system/component operability or reportability status.

KEY This procedure, when complete, shall be retained for the life of the plant.

KEY 3.13 0PSP03-EW-0018 Essential Cooling Water System Train B Testing Rev. 21 This procedure verifies the fail-safe position of valves 1(2)-EW-FV-6924 and 1(2)-EW-FV-6936.

Page 9 of 64 3.13.1 Special timing of valves is NOT required since full stroke valve exercising in this procedure will de-energize the valves that have fail-safe positions.

3.13.2 The Solenoid valves tested in this procedure are spring loaded to vent air from air operated valve when the solenoid is de-energized.

3.14 IF the Essential Cooling Water System is shutdown, THEN testing of valves in Section 5.11 may be performed prior to starting the ECW Pump.

3.15 Acceptance Criteria steps are annotated with the letters AC in the left margin preceding the step.

3.16 IF this procedure CAN NOT be performed as written, THEN the procedure performer shall stop and immediately notify the Shift Supervisor.

3.17 IF any ECW Pump or ECW Screen Wash Booster Pump parameter falls in the Alert Range, THEN calibration of the affected instruments may be performed and the pump may be retested.

3.18 IF a valve with measured stroke times DOES NOT meet Acceptance Criteria AND DOES NOT exceed limiting values per Reference 7.8.3, THEN the valve SHALL be immediately retested OR declared inoperable per 0PGP03-ZE-0021, Inservice Testing Program for Valves. An Engineering evaluation SHALL be performed for each retested valve.

3.19 IF this procedure is terminated for any reason, THEN immediately notify the Shift Supervisor.

3.20 IF any Acceptance Criteria are NOT met, THEN immediately notify the Shift Supervisor AND document failure per 0PGP03-ZE-0004, Plant Surveillance Program.

KEY This procedure, when complete, shall be retained for the life of the plant.

KEY 4.0 Prerequisites 0PSP03-EW-0018 Essential Cooling Water System Train B Testing Rev. 21 Page 10 of 64 Initials 4.1 Ensure procedure revision is correct and all applicable Field Changes are incorporated. AC 4.2 This procedure may be performed in any Mode. Record the current plant Mode:

Mode 1 4.3 Review Operability Assessment System (OAS) to ensure no equipment is out of service that could conflict with test completion or cause unexpected multiple trains to be inoperable while performing this test. AC 4.4 Essential Cooling Water System Train B is in operation or available for operation per 0POP02-EW-0001, Essential Cooling Water Operation. AC 4.5 Verify I&C Maintenance personnel are available for performance of instrument venting. AC 4.6 Verify qualified personnel are available for performance of ECW Pump vibration measurement. AC 4.7 For ECW pump testing, obtain the following test instrumentation:

• Test Gage with a range of 0 to 100 psig with an accuracy of +/- 0.1% of full scale to measure ECW Pump 1B(2B) discharge pressure.

(Ref. 7.4.2) AC

• A vibration instrument with an accuracy +/- 5% of full scale to measure vibration velocity in in/sec. AC 4.8 For ECW Screen Wash Booster Pump testing, obtain the following test instrumentation:

• A vibration instrument with an accuracy +/- 5% of full scale to measure vibration velocity in in/sec. AC 4.9 For any valve timing, obtain a calibrated stopwatch accurate to +/- 1%. AC KEY This procedure, when complete, shall be retained for the life of the plant.

KEY 4.10 0PSP03-EW-0018 Essential Cooling Water System Train B Testing Rev. 21 Ensure ECW System pumps to be operated are inspected and acceptable for operation per the criteria established in 0POP01-ZQ-0022, Plant Operations Page 11 of 64 Initials Shift Routines.

• Essential Cooling Water Pump 1B(2B) AC

• ECW Screen Wash Booster Pump 1B(2B) AC 4.11 IF this procedure is being performed to demonstrate post-maintenance operability OR increased frequency testing of an Essential Cooling Water System component, THEN N/A the applicable subsection(s) for the component(s) NOT being tested, OTHERWISE N/A this step. N/A 4.12 Evaluate current plant conditions and note in the Remarks Section of the PPDS any changes in Work Risk Assessment due to special plant conditions. AC Work Risk Assessment by Plant Mode Reactor Trip Potential:

Mode 1 Mode 2 Mode 3 Mode 4 Mode 5 Mode 6 No Mode NONE NONE NONE NONE NONE NONE NONE Turbine Trip Potential:

Mode 1 Mode 2 Mode 3 Mode 4 Mode 5 Mode 6 No Mode NONE NONE NONE NONE NONE NONE NONE ESF Actuation Potential:

Mode 1 Mode 2 Mode 3 Mode 4 Mode 5 Mode 6 No Mode LOW LOW LOW LOW LOW LOW LOW KEY This procedure, when complete, shall be retained for the life of the plant.

KEY 4.13 0PSP03-EW-0018 Essential Cooling Water System Train B Testing Record the following or "N/A", as applicable, on the PPDS:

Rev. 21 Page 12 of 64 Initials

• Unit Number

• Work Activity Number

• Surveillance Test (ST) Number(s)

• Reason for Test

• M&TE Data for vibration instrument

• M&TE Data for 0-100 psig test gage

• M&TE Data for stopwatch AC 4.14 Notify the Shift Supervisor to review Technical Specifications LCO 3.7.4

[ITS 3.7.8] and LCOs for systems affected by ECW for action requirements prior to performing this surveillance. AC 4.15 Obtain Shift Supervisor signature on PPDS for administrative approval to perform test. AC KEY This procedure, when complete, shall be retained for the life of the plant.

KEY 5.0 Procedure 5.1 Preparations 0PSP03-EW-0018 Essential Cooling Water System Train B Testing Rev. 21 Page 13 of 64 Initials 5.1.1 Ensure Prerequisites Section has been completed and Precautions and Notes Section has been read. AC 5.1.2 Conduct a prejob briefing, including any changes in Work Risk Assessment as noted in the Remarks Section of the PPDS. AC 5.1.3 Ensure Control Room Logbook entry documents the commencement of this surveillance test. AC 5.1.4 Ensure personnel performing sections of this test have locked valve keys. Keys are required for testing the following:

• Sections 5.3, 5.4, and 5.5 for testing 1(2)-EW-0404, -0278,

-0042 and ECW Pump testing requires key for 1(2)-EW-0189.

AC

• Sections 5.4 and 5.5 for testing ECW Pump and 1(2)-EW-0042 requires key for "1(2)-EW-0064 CCW HEAT EXCHANGER 1B(2B) ECW RETURN THROTTLE VALVE" AC 5.1.5 IF ECW Pump inservice testing is to be performed, THEN install Test Gage for ECW Pump 1B(2B) discharge pressure as follows, OTHERWISE mark this step as N/A: {ECWIS, Room 105(102)} (Ref.

7.4.1, 7.4.2) 5.1.5.1 Install 0-100 psig Test Gage at test connection for "1(2)-EW-PI-6885 ECW PUMP 1B(2B) DISCHARGE PRESSURE INDICATOR". AC 5.1.5.2 Verify Test Gage is installed at the same elevation as "1(2)-EW-PI-6885 ECW PUMP 1B(2B) DISCHARGE PRESSURE INDICATOR". AC KEY This procedure, when complete, shall be retained for the life of the plant.

KEY 5.2 0PSP03-EW-0018 Essential Cooling Water System Train B Testing Essential Cooling Water Pump 1B(2B) Startup Rev. 21 Page 14 of 64 Initials 5.2.1 IF ECW Pump 1B(2B) is shutdown, THEN perform the following, OTHERWISE GO TO Step 5.2.2:

NOTE IF ECW Pump room temperature is high, THEN the ECW Pump room fan will restart after being shutdown with handswitch in AUTO AND Step 5.2.1.1 will be marked N/A.

5.2.1.1 IF ECW Pump 1B(2B) room fan(s) running, THEN stop running fan(s) AND ensure handswitches in AUTO:

{CP022}

• "RM 105 FAN 11B HZ-VFN003 (RM 102 FAN 21B HZ-VFN003)" N/A

• "RM 105 FAN 12B HZ-VFN004 (RM 102 FAN 22B HZ-VFN004)" N/A NOTE ECW Screen Wash Booster Pump and Traveling Screens may start on high differential pressure when the ECW Pump is started.

5.2.1.2 Start ECW Pump 1B(2B) per 0POP02-EW-0001, Essential Cooling Water Operation. N/A 5.2.1.3 IF ECW Screen Wash Booster Pump and Traveling Screen 1B(2B) start, THEN perform the following, OTHERWISE mark the following N/A: {CP002}

a. Approximately 4 minutes after ECW Pump start, ensure the "TRAV SCRN 1B(2B)" stops. N/A

b. Stop "SCRN WASH PUMP 1B(2B)". N/A 5.2.2 Verify "ECW SELF CLEANING STRAINER 1B(2B)" is running.

{ECWIS, MCC E1B3(E2B3)/C1} AC KEY This procedure, when complete, shall be retained for the life of the plant.

KEY 0PSP03-EW-0018 Essential Cooling Water System Train B Testing NOTE Rev. 21 IF ECWIS fans fail to operate OR ventilation dampers fail to open, THEN the Shift Page 15 of 64 Initials Supervisor shall be notified and an entry made in the Remarks Section of the PPDS.

5.2.3 Verify ECWIS ventilation operation as follows: {CP022}

5.2.3.1 ECWIS fans started on ECW Pump start OR are operating with ECW Pump running:

• "RM 105 FAN 11B HZ-VFN003 (RM 102 FAN 21B HZ-VFN003)" AC

• "RM 105 FAN 12B HZ-VFN004 (RM 102 FAN 22B HZ-VFN004)" AC 5.2.3.2 ECWIS intake and exhaust dampers are OPEN:

• "INTAKE FV-9895" AC

• "EXHAUST FV-9895A" AC KEY This procedure, when complete, shall be retained for the life of the plant.

KEY 0PSP03-EW-0018 Essential Cooling Water System Train B Testing NOTE Rev. 21 Page 16 of 64 Initials Steps 5.2.4 and 5.2.5 may be performed concurrently. IF ECW Screen Wash Booster Pump is to be tested, THEN Steps 5.2.4, 5.2.5, 5.7.6, and 5.7.7 may be performed concurrently.

5.2.4 Request I&C Maintenance vent the following instruments:

• "1(2)-EW-FT-6863 CCW HEAT EXCHANGER 1B(2B) ECW RETURN FLOW TRANSMITTER"

{26' MAB, Room 106} IC

• "1(2)-EW-FT-6866 CCW PUMP SUPPLEMENTAL COOLER 11B(21B) ECW RETURN FLOW TRANSMITTER" {10' MAB Room 067E} IC

• "1(2)-EW-FT-6905 ESSENTIAL CHILLER 12B(22B) ECW RETURN FLOW TRANSMITTER" {10' MAB Room 067E} IC

• "1(2)-EW-FT-6864 ESSENTIAL CHILLER 11B(21B) ECW RETURN FLOW TRANSMITTER" {10' MAB Room 067E} IC

• "1(2)-EW-FT-6865 DIESEL GENERATOR #12(#22) ECW RETURN FLOW TRANSMITTER" {29' DGB, Room 002} IC

• "1(2)-EW-FI-6948 ECW PUMP 1B(2B) LUBE WATER FLOW INDICATOR" {ECWIS Room 105(102)} IC

• Test gage installed at "1(2)-EW-PI-6885 ECW PUMP 1B(2B)

DISCHARGE PRESSURE INDICATOR".

{ECWIS Room 105(102)} IC KEY This procedure, when complete, shall be retained for the life of the plant.

KEY 5.2.5 0PSP03-EW-0018 Essential Cooling Water System Train B Testing Rev. 21 IF ECW from Essential Chillers is in Cold Weather alignment, THEN request I&C Maintenance vent the bypass flow indicator(s) for the Page 17 of 64 Initials OPERABLE chiller(s) AND mark the inoperable chiller bypass flow indicator as N/A, OTHERWISE N/A this step.

• 1(2)-EW-FI-6864C ESSENTIAL CHILLER 11B(21B)

ECW OUTLET BYPASS FLOW INDICATOR

{10 MAB, Room 067E} N/A

• 1(2)-EW-FI-6905C ESSENTIAL CHILLER 12B(22B)

ECW OUTLET BYPASS FLOW INDICATOR

{10 MAB, Room 067E} N/A 5.2.6 Station operators and establish communications between the following locations:

• Control Room

• ECW Pump 1B(2B) Room 105(102) at the ECWIS

• CCW Heat Exchanger Room 26' MAB, Room 106 (if needed) AC KEY This procedure, when complete, shall be retained for the life of the plant.

KEY5.3 0PSP03-EW-0018 Essential Cooling Water System Train B Testing Rev. 21 Testing Emergency Backflush Valves 1(2)-EW-0278 and 1(2)-EW-0404 (Ref.

7.4.5)

Page 18 of 64 Initials 5.3.1 Verify flow through the discharge strainer emergency backflush line is less than or equal to 1/2 of pipe diameter. (On ECW Pond side of ECWIS) AC 5.3.2 Record AS FOUND position of "1(2)-EW-0278 ECW PUMP 1B(2B)

DISCHARGE STRAINER EMERGENCY BACKFLUSH VALVE" in Step 5.6.3. {ECWIS, Room 105(102)} AC AC 5.3.3 Open "1(2)-EW-0278 ECW PUMP 1B(2B) DISCHARGE STRAINER EMERGENCY BACKFLUSH VALVE".

{ECWIS Room 105(102)} AC 5.3.4 Record REQUIRED POSITION, including the throttled position and lock status, of "1(2)-EW-0189 ECW PUMP 1B(2B) DISCHARGE STRAINER BACKFLUSH THROTTLE VALVE" from Valve Database here AND in Step 5.6.3. {ECWIS, Room 105(102)}

REQUIRED POSITION LIP 41/4 TURNS OPEN AC 5.3.5 WHEN Step 5.3.7 is performed, THEN RECORD the AS FOUND position of "1(2)-EW-0189 ECW PUMP 1B(2B) DISCHARGE STRAINER BACKFLUSH THROTTLE VALVE".

{ECWIS, Room 105(102)}

AS FOUND LIP 41/4 TURNS OPEN AC 5.3.6 IF the REQUIRED POSITION recorded in Step 5.3.4 AND the AS FOUND position recorded in Step 5.3.5 are different, THEN NOTIFY the Shift Supervisor, OTHERWISE N/A this Step. N/A AC 5.3.7 Unlock and close "1(2)-EW-0189 ECW PUMP 1B(2B) DISCHARGE STRAINER BACKFLUSH THROTTLE VALVE". AC AC 5.3.8 Verify flow through the discharge strainer emergency backflush line increases to full pipe diameter. (On ECW Pond side of ECWIS) AC AC 5.3.9 Close "1(2)-EW-0278 ECW PUMP 1B(2B) DISCHARGE STRAINER EMERGENCY BACKFLUSH VALVE".

{ECWIS, Room 105(102)} AC 5.3.10 Verify flow through the discharge strainer emergency backflush line KEY returned to less than or equal to 1/2 of pipe diameter.

(On ECW Pond side of ECWIS) AC This procedure, when complete, shall be retained for the life of the plant.

KEY 5.4 0PSP03-EW-0018 Essential Cooling Water System Train B Testing Testing Essential Cooling Water Pump 1B(2B)

Rev. 21 Page 19 of 64 Initials NOTE Placing ECW Self Cleaning Strainer handswitch in STOP will cause ESF Status Monitoring Lampbox 2M22 BYP/INOP ECW STRN 1B(2B) to alarm.

5.4.1 Remove ECW Self Cleaning Strainer 1B(2B) from service by placing "ECW SELF CLEANING STRAINER 1B(2B)" handswitch in STOP. {ECWIS, MCC E1B3(E2B3)/C1} AC 5.4.2 IF ECW Self Cleaning Strainer 1B(2B) Normal Backflush is in service, THEN perform the following, OTHERWISE mark the following as N/A:

5.4.2.1 Record REQUIRED POSITION, including the throttled position and lock status, of "1(2)-EW-0189 ECW PUMP 1B(2B) DISCHARGE STRAINER BACKFLUSH THROTTLE VALVE" from Valve Database here AND in Step 5.6.3.

{ECWIS, Room 105(102)}

REQUIRED POSITION N/A 5.4.2.2 WHEN Step 5.4.2.4 is performed, THEN RECORD the AS FOUND position, including the throttled position and lock status, of "1(2)-EW-0189 ECW PUMP 1B(2B)

DISCHARGE STRAINER BACKFLUSH THROTTLE VALVE". {ECWIS, Room 105(102)}

AS FOUND N/A 5.4.2.3 IF the REQUIRED POSITION recorded in Step 5.4.2.1 AND the AS FOUND position recorded in Step 5.4.2.2 are different, THEN NOTIFY the Shift Supervisor, OTHERWISE N/A this Step. N/A AC 5.4.2.4 Close "1(2)-EW-0189 ECW PUMP 1B(2B)

DISCHARGE STRAINER BACKFLUSH THROTTLE VALVE". {ECWIS, Room 105(102)} N/A KEY This procedure, when complete, shall be retained for the life of the plant.

KEY 5.4.3 0PSP03-EW-0018 Essential Cooling Water System Train B Testing Rev. 21 WHEN Step 5.4.2 is complete, THEN record the start time of the 5 minute system stabilization period.

Page 20 of 64 Initials 0145 AC 5.4.4 WHEN at least 5 minutes have passed, THEN record the end time of the 5 minute system stabilization period.

0152 AC NOTE

• Actual indicated ECW Pump Bay Level should be recorded and NOT corrected for elevation.

• Normal ECW Pump Bay Level is 15.5 to 16.0 feet.

5.4.5 Record ECW Pump Bay Level "BAY LVL LI-6921": {CP002}

ECW Pump Bay Level 15.9 feet (LI-6921) AC 5.4.6 Using ECW Pump Bay Level recorded in Step 5.4.5 and Addendum 1, Essential Cooling Water Pump Bay Level Correction Factor, record the Bay Level Correction Factor for ECW Pump 1B(2B):

Non-Critical Error; Bay Level Correction Factor 4.4 psig Correct Value is AC 4.3 5.4.7 Record ECW Pump 1B(2B) discharge pressure from 0-100 psig Test Gage at test connection for "1(2)-EW-PI-6885 ECW PUMP 1B(2B)

DISCHARGE PRESSURE INDICATOR".

ECW Pump Discharge Pressure 50.4 psig AC KEY This procedure, when complete, shall be retained for the life of the plant.

KEY 0PSP03-EW-0018 Essential Cooling Water System Train B Testing NOTE Rev. 21 Page 21 of 64 Initials The Bay Level Correction Factor value is ADDED to the ECW pump discharge pressure to compensate for the difference in the discharge pressure reading (as measured at centerline of the ECW pump horizontal discharge piping) and actual discharge pressure at the outlet of the ECW pump impeller (minus the suction pressure that is derived from bay level). (

Reference:

Addendum 1, Essential Cooling Water Pump Bay Level Correction Factor) 5.4.8 Calculate ECW Pump 1B(2B) Delta P using the following formula:

50.4 psig + 4.4 psig = 54.8 psig AC Disch Press Bay Level Corr Delta P (Step 5.4.7) Factor (Step 5.4.6) Errors carried forward 5.4.9 Record ECW flow from the following components in Table 1 (ECW System Flow):

• ECW Pump Lube Water flow from 1(2)-EW-FI-6948,

{ECWIS} AC

• Flow to CCW Pump Supplementary Cooler "TRN B FT 6866" (QDPS) AC

• ECW Flow to "ESF DG 12(22) FT 6865" (QDPS) AC 5.4.10 Record ECW flow from Essential Chillers in Table 1 (ECW System Flow) AND mark step NOT performed as N/A:

5.4.10.1 IF ECW from Essential Chillers is in normal Warm Weather alignment, THEN record the following in Table 1:

• "TRN B CHLR 11B(21B) FT 6864" (QDPS) AC

• "TRN B CHLR 12B(22B) FT 6905" (QDPS) AC KEY This procedure, when complete, shall be retained for the life of the plant.

KEY 0PSP03-EW-0018 Essential Cooling Water System Train B Testing NOTE Rev. 21 Page 22 of 64 Initials IF both Essential Chillers are OPERABLE, THEN Steps 5.4.10.2a, 5.4.10.2b and 5.6.4 will be marked as N/A.

5.4.10.2 IF ECW from Essential Chillers is in Cold Weather alignment, THEN perform the following:

(MAB 10', Room 067E)

a. Record AS FOUND position of ECW return bypass valve from INOPERABLE Essential Chiller in Step 5.6.4 AND mark OPERABLE chiller valve as N/A:

• "1(2)-EW-3016 ESSENTIAL CHILLER 11B(21B) ECW RETURN BYPASS ISOLATION VALVE" N/A

• "1(2)-EW-3019 ESSENTIAL CHILLER 12B(22B) ECW RETURN BYPASS ISOLATION VALVE" N/A

b. Close ECW return bypass valve from INOPERABLE Essential Chiller AND mark OPERABLE chiller valve as N/A:

• "1(2)-EW-3016 ESSENTIAL CHILLER 11B(21B) ECW RETURN BYPASS ISOLATION VALVE" N/A

• "1(2)-EW-3019 ESSENTIAL CHILLER 12B(22B) ECW RETURN BYPASS ISOLATION VALVE" N/A KEY This procedure, when complete, shall be retained for the life of the plant.

KEY 0PSP03-EW-0018 Essential Cooling Water System Train B Testing c.

Rev. 21 Record ECW flow from OPERABLE Essential Chiller(s) in Table 1: ECW System Flow AND Page 23 of 64 Initials mark INOPERABLE chiller flow as N/A:

• "1(2)-EW-FI-6864C ESSENTIAL CHILLER 11B(21B) ECW RETURN BYPASS FLOW INDICATOR" N/A

• "1(2)-EW-FI-6905C ESSENTIAL CHILLER 12B(22B) ECW RETURN BYPASS FLOW INDICATOR" N/A 5.4.11 Determine ECW flow from CCW Heat Exchanger 1B(2B) as follows:

5.4.11.1 Record ECW flow from CCW Heat Exchanger 1B(2B) using QDPS "TRN B FT6863" on Data Sheet 1 (Essential Cooling Water Flow from CCW Heat Exchanger) at approximately 30 second intervals until 21 flows have been recorded. AC 5.4.11.2 After 21 flows have been recorded, then add the individual flows and record total on Data Sheet 1. AC 5.4.11.3 Calculate and record the average ECW Flow from CCW Heat Exchanger in AVERAGE block of Data Sheet 1. AC 5.4.11.4 Sign and Date Performance of Data Sheet 1. AC KEY This procedure, when complete, shall be retained for the life of the plant.

KEY 5.4.12 0PSP03-EW-0018 Essential Cooling Water System Train B Testing Rev. 21 Record the AVERAGE ECW Flow from CCW Heat Exchanger from Data Sheet 1 in Table 1, ECW System Flow.

Page 24 of 64 Initials AC 5.4.13 Calculate and record Total ECW System Flow in Table 1, ECW System Flow. AC Table 1: ECW System Flow Component ECW Flow Units ECW Pump 1B(2B) Lube Water 11.7 gpm ECW Flow to Essen Chlr 11B(21B) 639 gpm ECW Flow to Essen Chlr 12B(22B) 1236 gpm Error Carried ECW Flow to CCW Pump Cooler 45 gpm Forward Correct value:

ECW Flow to ESF DG 12(22) 1694 gpm 13302.1 gpm ECW Flow to CCW HX 13802.1 gpm (AVERAGE from Data Sheet 1)

TOTAL ECW SYSTEM FLOW = 17427.8 gpm Error Carried Forward Correct value:

5.4.14 IF performing this test in Unit 1, THEN perform the following, 16927.8 gpm OTHERWISE N/A Steps 5.4.14.1 through 5.4.14.7:

5.4.14.1 Determine ECW Total Flow Range of Table 2: ECW Error Carried Pump 1B Reference Values, for the Total ECW SystemForward Flow recorded in Table 1: ECW System Flow. Correct range:

16900 - 16949 ECW Total Flow Range 17400 - 17449 gpm AC 5.4.14.2 Record ECW Pump 1B Delta P from Step 5.4.8 in Table 2: ECW Pump 1B Reference Values, at the corresponding ECW Total Flow Range determined in Step 5.4.14.1. AC KEY This procedure, when complete, shall be retained for the life of the plant.

KEY Ref.

ECW Total Flow Delta Test Delta P 0PSP03-EW-0018 Essential Cooling Water System Train B Testing Table 2: ECW Pump 1B Reference Values Required Action Alert Range Low Rev. 21 Acceptable Range Page 25 of 64 Required Range P Low Action High 15,700-15,749 63.0 dP< 58.6 58.6 <=dP< 59.8 59.8 <=dP<= 69.3 dP> 69.3 15,750-15,799 62.8 dP< 58.4 58.4 <=dP< 59.7 59.7 <=dP<= 69.1 dP> 69.1 15,800-15,849 62.6 dP< 58.3 58.3 <=dP< 59.5 59.5 <=dP<= 68.9 dP> 68.9 15,850-15,899 62.5 dP< 58.1 58.1 <=dP< 59.3 59.3 <=dP<= 68.7 dP> 68.7 15,900-15,949 62.3 dP< 57.9 57.9 <=dP< 59.2 59.2 <=dP<= 68.5 dP> 68.5 15,950-15,999 62.1 dP< 57.8 57.8 <=dP< 59.0 59.0 <=dP<= 68.4 dP> 68.4 16,000-16,049 62.0 dP< 57.6 57.6 <=dP< 58.9 58.9 <=dP<= 68.2 dP> 68.2 16,050-16,099 61.8 dP< 57.5 57.5 <=dP< 58.7 58.7 <=dP<= 68.0 dP> 68.0 16,100-16,149 61.6 dP< 57.3 57.3 <=dP< 58.6 58.6 <=dP<= 67.8 dP> 67.8 16,150-16,199 61.5 dP< 57.2 57.2 <=dP< 58.4 58.4 <=dP<= 67.6 dP> 67.6 16,200-16,249 61.3 dP< 57.0 57.0 <=dP< 58.2 58.2 <=dP<= 67.4 dP> 67.4 16,250-16,299 61.1 dP< 56.9 56.9 <=dP< 58.1 58.1 <=dP<= 67.3 dP> 67.3 N/A 16,300-16,349 61.0 dP< 56.7 56.7 <=dP< 57.9 57.9 <=dP<= 67.1 dP> 67.1 16,350-16,399 60.8 dP< 56.6 56.6 <=dP< 57.8 57.8 <=dP<= 66.9 dP> 66.9 16,400-16,449 60.6 dP< 56.4 56.4 <=dP< 57.6 57.6 <=dP<= 66.7 dP> 66.7 16,450-16,499 60.5 dP< 56.2 56.2 <=dP< 57.5 57.5 <=dP<= 66.5 dP> 66.5 16,500-16,549 60.3 dP< 56.1 56.1 <=dP< 57.3 57.3 <=dP<= 66.3 dP> 66.3 16,550-16,599 60.2 dP< 55.9 55.9 <=dP< 57.1 57.1 <=dP<= 66.2 dP> 66.2 16,600-16,649 60.0 dP< 55.8 55.8 Correct range for <=dP<

Delta P: 57.0 57.0 <=dP<= 66.0 dP> 66.0 16,650-16,699 59.8 dP<

Test55.6 Delta P is 55.6 <=dP<

within the 56.8 56.8 <=dP<= 65.8 dP> 65.8 16,700-16,749 59.7 dP< 55.5 Action Required 55.5 Low<=dP< 56.7 56.7 <=dP<= 65.6 dP> 65.6 16,750-16,799 59.5 dP< 55.3 55.3 <=dP< 56.5 56.5 <=dP<= 65.4 dP> 65.4 16,800-16,849 59.3 dP< 55.2 55.2 <=dP< 56.4 56.4 <=dP<= 65.3 dP> 65.3 16,850-16,899 59.2 dP< 55.0 55.0 <=dP< 56.2 56.2 <=dP<= 65.1 dP> 65.1 16,900-16,949 59.0 54.7 dP< 54.9 54.9 <=dP< 56.0 56.0 <=dP<= 64.9 dP> 64.9 16,950-16,999 58.8 dP< 54.7 54.7 <=dP< 55.9 55.9 <=dP<= 64.7 dP> 64.7 17,000-17,049 58.7 dP< 54.6 54.6 <=dP< 55.7 55.7 <=dP<= 64.5 dP> 64.5 17,050-17,099 58.5 N/A dP< 54.4 54.4 <=dP< 55.6 55.6 <=dP<= 64.4 dP> 64.4 17,100-17,149 58.4 dP< 54.3 54.3 <=dP< 55.4 55.4 <=dP<= 64.2 dP> 64.2 17,150-17,199 58.2 dP< 54.1 54.1 <=dP< 55.3 55.3 <=dP<= 64.0 dP> 64.0 KEY This procedure, when complete, shall be retained for the life of the plant.

KEY Ref.

0PSP03-EW-0018 Essential Cooling Water System Train B Testing Table 2: ECW Pump 1B Reference Values (continued from previous page)

Required Rev. 21 Page 26 of 64 ECW Total Flow Delta Test Delta P Action Alert Range Low Acceptable Range Required Range P Low Action High 17,200-17,249 58.0 dP< 54.0 54.0 <=dP< 55.1 55.1 <=dP<= 63.9 dP> 63.9 17,250-17,299 57.9 dP< 53.8 53.8 <=dP< 55.0 55.0 <=dP<= 63.7 dP> 63.7 N/A 17,300-17,349 57.7 dP< 53.7 53.7 <=dP< 54.8 54.8 <=dP<= 63.5 dP> 63.5 17,350-17,399 57.6 dP< 53.5 53.5 <=dP< 54.7 54.7 <=dP<= 63.3 dP> 63.3 17,400-17,449 57.4 54.8 dP< 53.4 53.4 <=dP< 54.6 54.6 <=dP<= 63.2 dP> 63.2 17,450-17,499 57.3 dP< 53.3 53.3 <=dP< 54.4 54.4 <=dP<= 63.0 dP> 63.0 17,500-17,549 57.1 dP< 53.1 Error Carried 53.1 <=dP< 54.3 Forward 54.3 <=dP<= 62.8 dP> 62.8 17,550-17,599 57.0 dP< 53.0 53.0 <=dP< 54.1 54.1 <=dP<= 62.6 dP> 62.6 Places test incorrectly in 17,600-17,649 56.8 dP< 52.8 52.8 <=dP< 54.0 54.0 <=dP<= 62.5 dP> 62.5 Acceptable Range 17,650-17,699 56.6 dP< 52.7 52.7 <=dP< 53.8 53.8 <=dP<= 62.3 dP> 62.3 17,700-17,749 56.5 dP< 52.5 52.5 <=dP< 53.7 53.7 <=dP<= 62.1 dP> 62.1 17,750-17,799 56.3 dP< 52.4 52.4 <=dP< 53.5 53.5 <=dP<= 62.0 dP> 62.0 17,800-17,849 56.2 dP< 52.2 52.2 <=dP< 53.4 53.4 <=dP<= 61.8 dP> 61.8 17,850-17,899 56.0 dP< 52.1 52.1 <=dP< 53.2 53.2 <=dP<= 61.6 dP> 61.6 17,900-17,949 55.9 dP< 51.9 51.9 <=dP< 53.1 53.1 <=dP<= 61.4 dP> 61.4 17,950-17,999 55.7 dP< 51.8 51.8 <=dP< 52.9 52.9 <=dP<= 61.3 dP> 61.3 18,000-18,049 55.5 dP< 51.7 51.7 <=dP< 52.8 52.8 <=dP<= 61.1 dP> 61.1 18,050-18,099 55.4 N/A dP< 51.5 51.5 <=dP< 52.6 52.6 <=dP<= 60.9 dP> 60.9 18,100-18,149 55.2 dP< 51.4 51.4 <=dP< 52.5 52.5 <=dP<= 60.8 dP> 60.8 18,150-18,199 55.1 dP< 51.2 51.2 <=dP< 52.3 52.3 <=dP<= 60.6 dP> 60.6 18,200-18,249 54.9 dP< 51.1 51.1 <=dP< 52.2 52.2 <=dP<= 60.4 dP> 60.4 18,250-18,299 54.8 dP< 50.9 50.9 <=dP< 52.0 52.0 <=dP<= 60.2 dP> 60.2 18,300-18,349 54.6 dP< 50.8 50.8 <=dP< 51.9 51.9 <=dP<= 60.1 dP> 60.1 18,350-18,399 54.4 dP< 50.6 50.6 <=dP< 51.7 51.7 <=dP<= 59.9 dP> 59.9 18,400-18,449 54.3 dP< 50.5 50.5 <=dP< 51.6 51.6 <=dP<= 59.7 dP> 59.7 18,450-18,499 54.1 dP< 50.3 50.3 <=dP< 51.4 51.4 <=dP<= 59.5 dP> 59.5 18,500-18,549 54.0 dP< 50.2 50.2 <=dP< 51.3 51.3 <=dP<= 59.4 dP> 59.4 18,550-18,599 53.8 dP< 50.1 50.1 <=dP< 51.1 51.1 <=dP<= 59.2 dP> 59.2 18,600-18,649 53.7 dP< 49.9 49.9 <=dP< 51.0 51.0 <=dP<= 59.0 dP> 59.0 18,650-18,699 53.5 dP< 49.8 49.8 <=dP< 50.8 50.8 <=dP<= 58.9 dP> 58.9 KEY This procedure, when complete, shall be retained for the life of the plant.

KEY Ref.

0PSP03-EW-0018 Essential Cooling Water System Train B Testing Table 2: ECW Pump 1B Reference Values (continued from previous page)

Required Rev. 21 Page 27 of 64 ECW Total Flow Delta Test Delta P Action Alert Range Low Acceptable Range Required Range P Low Action High 18,700-18,749 53.4 dP< 49.6 49.6 <=dP< 50.7 50.7 <=dP<= 58.7 dP> 58.7 18,750-18,799 53.2 dP< 49.5 49.5 <=dP< 50.5 50.5 <=dP<= 58.5 dP> 58.5 18,800-18,849 53.0 dP< 49.3 49.3 <=dP< 50.4 50.4 <=dP<= 58.3 dP> 58.3 18,850-18,899 52.9 dP< 49.2 49.2 <=dP< 50.2 50.2 <=dP<= 58.2 dP> 58.2 18,900-18,949 52.7 dP< 49.0 49.0 <=dP< 50.1 50.1 <=dP<= 58.0 dP> 58.0 18,950-18,999 52.6 dP< 48.9 48.9 <=dP< 49.9 49.9 <=dP<= 57.8 dP> 57.8 19,000-19,049 52.4 dP< 48.7 48.7 <=dP< 49.8 49.8 <=dP<= 57.7 dP> 57.7 19,050-19,099 52.3 dP< 48.6 48.6 <=dP< 49.6 49.6 <=dP<= 57.5 dP> 57.5 19,100-19,149 52.1 dP< 48.5 48.5 <=dP< 49.5 49.5 <=dP<= 57.3 dP> 57.3 19,150-19,199 51.9 dP< 48.3 48.3 <=dP< 49.3 49.3 <=dP<= 57.1 dP> 57.1 19,200-19,249 51.8 dP< 48.2 48.2 <=dP< 49.2 49.2 <=dP<= 57.0 dP> 57.0 19,250-19,299 51.6 dP< 48.0 48.0 <=dP< 49.0 49.0 <=dP<= 56.8 dP> 56.8 19,300-19,349 51.4 dP< 47.8 47.8 <=dP< 48.8 48.8 <=dP<= 56.5 dP> 56.5 19,350-19,399 51.2 dP< 47.6 47.6 <=dP< 48.6 48.6 <=dP<= 56.3 dP> 56.3 19,400-19,449 50.9 dP< 47.4 47.4 <=dP< 48.4 48.4 <=dP<= 56.0 dP> 56.0 N/A 19,450-19,499 50.7 dP< 47.2 47.2 <=dP< 48.2 48.2 <=dP<= 55.8 dP> 55.8 19,500-19,549 50.5 dP< 47.0 47.0 <=dP< 48.0 48.0 <=dP<= 55.5 dP> 55.5 19,550-19,599 50.3 dP< 46.8 46.8 <=dP< 47.8 47.8 <=dP<= 55.3 dP> 55.3 19,600-19,649 50.0 dP< 46.5 46.5 <=dP< 47.5 47.5 <=dP<= 55.1 dP> 55.1 19,650-19,699 49.8 dP< 46.3 46.3 <=dP< 47.3 47.3 <=dP<= 54.8 dP> 54.8 19,700-19,749 49.6 dP< 46.1 46.1 <=dP< 47.1 47.1 <=dP<= 54.6 dP> 54.6 19,750-19,799 49.4 dP< 45.9 45.9 <=dP< 46.9 46.9 <=dP<= 54.3 dP> 54.3 19,800-19,849 49.2 dP< 45.7 45.7 <=dP< 46.7 46.7 <=dP<= 54.1 dP> 54.1 19,850-19,899 48.9 dP< 45.5 45.5 <=dP< 46.5 46.5 <=dP<= 53.8 dP> 53.8 19,900-19,949 48.7 dP< 45.3 45.3 <=dP< 46.3 46.3 <=dP<= 53.6 dP> 53.6 19,950-19,999 48.5 dP< 45.1 45.1 <=dP< 46.1 46.1 <=dP<= 53.3 dP> 53.3 20,000-20,049 48.3 dP< 44.9 44.9 <=dP< 45.9 45.9 <=dP<= 53.1 dP> 53.1 20,050-20,099 48.1 dP< 44.7 44.7 <=dP< 45.7 45.7 <=dP<= 52.9 dP> 52.9 20,100-20,149 47.8 dP< 44.5 44.5 <=dP< 45.4 45.4 <=dP<= 52.6 dP> 52.6 20,150-20,199 47.6 dP< 44.3 44.3 <=dP< 45.2 45.2 <=dP<= 52.4 dP> 52.4 KEY This procedure, when complete, shall be retained for the life of the plant.

KEY 0PSP03-EW-0018 Essential Cooling Water System Train B Testing Table 2: ECW Pump 1B Reference Values (continued from previous page)

Rev. 21 Page 28 of 64 Initials ECW Total Flow Ref. Test Required Alert Range Low Acceptable Range Required Range Delta Delta P Action Action High P Low 20,200-20,249 47.4 dP< 44.1 44.1 <=dP< 45.0 45.0 <=dP<= 52.1 dP> 52.1 20,250-20,299 47.2 dP< 43.9 43.9 <=dP< 44.8 44.8 <=dP<= 51.9 dP> 51.9 20,300-20,349 46.9 dP< 43.7 43.7 <=dP< 44.6 44.6 <=dP<= 51.6 dP> 51.6 N/A 20,350-20,399 46.7 dP< 43.5 43.5 <=dP< 44.4 44.4 <=dP<= 51.4 dP> 51.4 20,400-20,449 46.5 dP< 43.2 43.2 <=dP< 44.2 44.2 <=dP<= 51.2 dP> 51.2 20,450-20,500 46.3 dP< 43.0 43.0 <=dP< 44.0 44.0 <=dP<= 50.9 dP> 50.9 AC 5.4.14.3 Complete the following and mark steps that DO NOT apply N/A:

Critical Error:

(Acceptance Criteria a. ECW Pump 1B Delta P is within Acceptable Range. AC NOT met)

b. ECW Pump 1B Delta P is within Required Should be N/A Action High. N/A

c. ECW Pump 1B Delta P is within Alert Range Low. N/A Should be Initialed d. ECW Pump 1B Delta P is within Required Action Low. N/A 5.4.14.4 IF Total ECW System Delta P is within a Required Action Range, THEN immediately notify Shift Supervisor, OTHERWISE mark this step N/A. N/A 5.4.14.5 Measure the unfiltered vibration velocity (V) at indicated test points (Addendum 2, Vibration Test Point Locations and Instructions) and record vibration in Table 3: Unit 1 ECW Pump 1B Vibration Data. AC KEY This procedure, when complete, shall be retained for the life of the plant.

KEY Vibration 0PSP03-EW-0018 Essential Cooling Water System Train B Testing Table 3: Unit 1 ECW Pump 1B Vibration Data Ref Test Data Accept Range Rev. 21 Alert Range High Page 29 of 64 Reqd Action Units Initials Data Points Value High 1H1 0.126 0.120 V 0.315 0.315 < V 0.700 >0.700 in/sec 1H2 0.088 0.088 V 0.220 0.220 < V 0.528 >0.528 in/sec 1A 0.046 0.049 V 0.115 0.115 < V 0.276 >0.276 in/sec 2H1* 0.027 in/sec 2H2* 0.017 in/sec 3H1* 0.155 in/sec 3H2* 0.059 in/sec

• - Data point is reference only for system health monitoring, NOT a code requirement and NO acceptance criteria applicable.

AC 5.4.14.6 Complete the following and mark steps that DO NOT apply N/A:

a. ECW Pump vibration is within Acceptable Range. AC

b. ECW Pump vibration is within the Alert Range. N/A

c. ECW Pump vibration is within the Required Action Range. N/A 5.4.14.7 IF ECW Pump 1B vibration is within Required Action Range, THEN immediately notify Shift Supervisor, OTHERWISE mark this step N/A. N/A 5.4.15 IF performing this test in Unit 2, THEN perform the following, OTHERWISE N/A Steps 5.4.15.1 through 5.4.15.7:

5.4.15.1 Determine ECW Total Flow Range of Table 4: ECW Pump 2B Reference Values, for the Total ECW System Flow recorded in Table 1: ECW System Flow.

ECW Total Flow Range _______________ gpm N/A 5.4.15.2 Record ECW Pump 2B Delta P from Step 5.4.8 in Table 4: ECW Pump 2B Reference Values, at the corresponding ECW Total Flow Range determined in KEY Step 5.4.15.1. N/A This procedure, when complete, shall be retained for the life of the plant.

KEY Ref.

ECW Total Flow Delta Test Delta P 0PSP03-EW-0018 Essential Cooling Water System Train B Testing Table 4: ECW Pump 2B Reference Values Required Action Alert Range Low Rev. 21 Acceptable Range Page 30 of 64 Required Range P Low Action High 15,700-15,749 61.9 dP< 57.6 57.6 dP< 58.8 58.8 dP 68.1 dP> 68.1 15,750-15,799 61.8 dP< 57.5 57.5 dP< 58.7 58.7 dP 68.0 dP> 68.0 15,800-15,849 61.6 dP< 57.3 57.3 dP< 58.5 58.5 dP 67.8 dP> 67.8 15,850-15,899 61.5 dP< 57.2 57.2 dP< 58.4 58.4 dP 67.7 dP> 67.7 15,900-15,949 61.4 dP< 57.1 57.1 dP< 58.3 58.3 dP 67.5 dP> 67.5 15,950-15,999 61.3 dP< 57.0 57.0 dP< 58.2 58.2 dP 67.4 dP> 67.4 16,000-16,049 61.2 dP< 56.9 56.9 dP< 58.1 58.1 dP 67.3 dP> 67.3 16,050-16,099 61.1 dP< 56.8 56.8 dP< 58.0 58.0 dP 67.2 dP> 67.2 16,100-16,149 61.0 dP< 56.7 56.7 dP< 58.0 58.0 dP 67.1 dP> 67.1 16,150-16,199 60.8 dP< 56.5 56.5 dP< 57.8 57.8 dP 66.9 dP> 66.9 16,200-16,249 60.7 dP< 56.5 56.5 dP< 57.7 57.7 dP 66.8 dP> 66.8 16,250-16,299 60.6 dP< 56.4 56.4 dP< 57.6 57.6 dP 66.7 dP> 66.7 16,300-16,349 60.5 dP< 56.3 56.3 dP< 57.5 57.5 dP 66.6 dP> 66.6 16,350-16,399 60.4 dP< 56.2 56.2 dP< 57.4 57.4 dP 66.4 dP> 66.4 16,400-16,449 60.3 dP< 56.1 56.1 dP< 57.3 57.3 dP 66.3 dP> 66.3 N/A 16,450-16,499 60.1 dP< 55.9 55.9 dP< 57.1 57.1 dP 66.1 dP> 66.1 16,500-16,549 60.0 dP< 55.8 55.8 dP< 57.0 57.0 dP 66.0 dP> 66.0 16,550-16,599 59.9 dP< 55.7 55.7 dP< 56.9 56.9 dP 65.9 dP> 65.9 16,600-16,649 59.8 dP< 55.6 55.6 dP< 56.8 56.8 dP 65.8 dP> 65.8 16,650-16699 59.7 dP< 55.5 55.5 dP< 56.7 56.7 dP 65.7 dP> 65.7 16,700-16,749 59.6 dP< 55.4 55.4 dP< 56.6 56.6 dP 65.6 dP> 65.6 16,750-16,799 59.4 dP< 55.2 55.2 dP< 56.4 56.4 dP 65.3 dP> 65.3 16,800-16,849 59.3 dP< 55.1 55.1 dP< 56.3 56.3 dP 65.2 dP> 65.2 16,850-16,899 59.2 dP< 55.1 55.1 dP< 56.2 56.2 dP 65.1 dP> 65.1 16,900-16,949 59.1 dP< 55.0 55.0 dP< 56.1 56.1 dP 65.0 dP> 65.0 16,950-16,999 59.0 dP< 54.9 54.9 dP< 56.1 56.1 dP 64.9 dP> 64.9 17,000-17,049 58.8 dP< 54.7 54.7 dP< 55.9 55.9 dP 64.7 dP> 64.7 17,050-17,099 58.7 dP< 54.6 54.6 dP< 55.8 55.8 dP 64.6 dP> 64.6 17,100-17,149 58.5 dP< 54.4 54.4 dP< 55.6 55.6 dP 64.4 dP> 64.4 17,150-17,199 58.4 dP< 54.3 54.3 dP< 55.5 55.5 dP 64.2 dP> 64.2 KEY This procedure, when complete, shall be retained for the life of the plant.

KEY Ref.

0PSP03-EW-0018 Essential Cooling Water System Train B Testing Table 4: ECW Pump 2B Reference Values (continued from previous page)

Required Rev. 21 Page 31 of 64 ECW Total Flow Delta Test Delta P Action Alert Range Low Acceptable Range Required Range P Low Action High 17,200-17,249 58.2 dP< 54.1 54.1 dP< 55.3 55.3 dP 64.0 dP> 64.0 17,250-17,299 58.0 dP< 53.9 53.9 dP< 55.1 55.1 dP 63.8 dP> 63.8 17,300-17,349 57.9 dP< 53.8 53.8 dP< 55.0 55.0 dP 63.7 dP> 63.7 17,350-17,399 57.7 dP< 53.7 53.7 dP< 54.8 54.8 dP 63.5 dP> 63.5 17,400-17,449 57.6 dP< 53.6 53.6 dP< 54.7 54.7 dP 63.4 dP> 63.4 17,450-17,499 57.4 dP< 53.4 53.4 dP< 54.5 54.5 dP 63.1 dP> 63.1 17,500-17,549 57.3 dP< 53.3 53.3 dP< 54.4 54.4 dP 63.0 dP> 63.0 17,550-17,599 57.1 dP< 53.1 53.1 dP< 54.2 54.2 dP 62.8 dP> 62.8 17,600-17,649 56.9 dP< 52.9 52.9 dP< 54.1 54.1 dP 62.6 dP> 62.6 17,650-17,699 56.8 dP< 52.8 52.8 dP< 54.0 54.0 dP 62.5 dP> 62.5 17,700-17,749 56.6 dP< 52.6 52.6 dP< 53.8 53.8 dP 62.3 dP> 62.3 17,750-17,799 56.5 dP< 52.5 52.5 dP< 53.7 53.7 dP 62.2 dP> 62.2 17,800-17,849 56.3 dP< 52.4 52.4 dP< 53.5 53.5 dP 61.9 dP> 61.9 17,850-17,899 56.2 dP< 52.3 52.3 dP< 53.4 53.4 dP 61.8 dP> 61.8 17,900-17,949 56.0 dP< 52.1 52.1 dP< 53.2 53.2 dP 61.6 dP> 61.6 N/A 17,950-17,999 55.8 dP< 51.9 51.9 dP< 53.0 53.0 dP 61.4 dP> 61.4 18,000-18,049 55.7 dP< 51.8 51.8 dP< 52.9 52.9 dP 61.3 dP> 61.3 18,050-18,099 55.5 dP< 51.6 51.6 dP< 52.7 52.7 dP 61.1 dP> 61.1 18,100-18,149 55.4 dP< 51.5 51.5 dP< 52.6 52.6 dP 60.9 dP> 60.9 18,150-18,199 55.2 dP< 51.3 51.3 dP< 52.4 52.4 dP 60.7 dP> 60.7 18,200-18,249 55.1 dP< 51.2 51.2 dP< 52.3 52.3 dP 60.6 dP> 60.6 18,250-18,299 54.9 dP< 51.1 51.1 dP< 52.2 52.2 dP 60.4 dP> 60.4 18,300-18,349 54.8 dP< 51.0 51.0 dP< 52.1 52.1 dP 60.3 dP> 60.3 18,350-18,399 54.6 dP< 50.8 50.8 dP< 51.9 51.9 dP 60.1 dP> 60.1 18,400-18,449 54.5 dP< 50.7 50.7 dP< 51.8 51.8 dP 60.0 dP> 60.0 18,450-18,499 54.4 dP< 50.6 50.6 dP< 51.7 51.7 dP 59.8 dP> 59.8 18,500-18,549 54.2 dP< 50.4 50.4 dP< 51.5 51.5 dP 59.6 dP> 59.6 18,550-18,599 54.1 dP< 50.3 50.3 dP< 51.4 51.4 dP 59.5 dP> 59.5 18,600-18,649 53.9 dP< 50.1 50.1 dP< 51.2 51.2 dP 59.3 dP> 59.3 18,650-18,699 53.8 dP< 50.0 50.0 dP< 51.1 51.1 dP 59.2 dP> 59.2 KEY This procedure, when complete, shall be retained for the life of the plant.

KEY Ref.

0PSP03-EW-0018 Essential Cooling Water System Train B Testing Table 4: ECW Pump 2B Reference Values (continued from previous page)

Required Rev. 21 Page 32 of 64 ECW Total Flow Delta Test Delta P Action Alert Range Low Acceptable Range Required Range P Low Action High 18,700-18,749 53.6 dP< 49.8 49.8 dP< 50.9 50.9 dP 59.0 dP> 59.0 18,750-18,799 53.5 dP< 49.8 49.8 dP< 50.8 50.8 dP 58.9 dP> 58.9 18,800-18,849 53.3 dP< 49.6 49.6 dP< 50.6 50.6 dP 58.6 dP> 58.6 18,850-18,899 53.2 dP< 49.5 49.5 dP< 50.5 50.5 dP 58.5 dP> 58.5 18,900-18,949 53.0 dP< 49.3 49.3 dP< 50.4 50.4 dP 58.3 dP> 58.3 18,950-18,999 52.9 dP< 49.2 49.2 dP< 50.3 50.3 dP 58.2 dP> 58.2 19,000-19,049 52.7 dP< 49.0 49.0 dP< 50.1 50.1 dP 58.0 dP> 58.0 19,050-19,099 52.6 dP< 48.9 48.9 dP< 50.0 50.0 dP 57.9 dP> 57.9 19,100-19,149 52.5 dP< 48.8 48.8 dP< 49.9 49.9 dP 57.8 dP> 57.8 19,150-19,199 52.3 dP< 48.6 48.6 dP< 49.7 49.7 dP 57.5 dP> 57.5 19,200-19,249 52.1 dP< 48.5 48.5 dP< 49.5 49.5 dP 57.3 dP> 57.3 19,250-19,299 51.9 dP< 48.3 48.3 dP< 49.3 49.3 dP 57.1 dP> 57.1 19,300-19,349 51.8 dP< 48.2 48.2 dP< 49.2 49.2 dP 57.0 dP> 57.0 19,350-19,399 51.6 dP< 48.0 48.0 dP< 49.0 49.0 dP 56.8 dP> 56.8 19,400-19,449 51.4 dP< 47.8 47.8 dP< 48.8 48.8 dP 56.5 dP> 56.5 N/A 19,450-19,499 51.2 dP< 47.6 47.6 dP< 48.6 48.6 dP 56.3 dP> 56.3 19,500-19,549 51.0 dP< 47.4 47.4 dP< 48.5 48.5 dP 56.1 dP> 56.1 19,550-19,599 50.8 dP< 47.2 47.2 dP< 48.3 48.3 dP 55.9 dP> 55.9 19,600-19,649 50.7 dP< 47.2 47.2 dP< 48.2 48.2 dP 55.8 dP> 55.8 19,650-19,699 50.5 dP< 47.0 47.0 dP< 48.0 48.0 dP 55.6 dP> 55.6 19,700-19,749 50.3 dP< 46.8 46.8 dP< 47.8 47.8 dP 55.3 dP> 55.3 19,750-19,799 50.1 dP< 46.6 46.6 dP< 47.6 47.6 dP 55.1 dP> 55.1 19,800-19,849 49.9 dP< 46.4 46.4 dP< 47.4 47.4 dP 54.9 dP> 54.9 19,850-19,899 49.7 dP< 46.2 46.2 dP< 47.2 47.2 dP 54.7 dP> 54.7 19,900-19,949 49.6 dP< 46.1 46.1 dP< 47.1 47.1 dP 54.6 dP> 54.6 19,950-19,999 49.4 dP< 45.9 45.9 dP< 46.9 46.9 dP 54.3 dP> 54.3 20,000-20,049 49.2 dP< 45.8 45.8 dP< 46.7 46.7 dP 54.1 dP> 54.1 20,050-20,099 49.0 dP< 45.6 45.6 dP< 46.6 46.6 dP 53.9 dP> 53.9 20,100-20,149 48.8 dP< 45.4 45.4 dP< 46.4 46.4 dP 53.7 dP> 53.7 20,150-20,199 48.6 dP< 45.2 45.2 dP< 46.2 46.2 dP 53.5 dP> 53.5 KEY This procedure, when complete, shall be retained for the life of the plant.

KEY 0PSP03-EW-0018 Essential Cooling Water System Train B Testing Table 4: ECW Pump 2B Reference Values (continued from previous page)

Rev. 21 Page 33 of 64 Initials ECW Total Flow Ref. Test Delta P Required Alert Range Low Acceptable Range Required Range Delta Action Action High P Low 20,200-20,249 48.4 dP< 45.0 45.0 dP< 46.0 46.0 dP 53.2 dP> 53.2 20,250-20,299 48.3 dP< 44.9 44.9 dP< 45.9 45.9 dP 53.1 dP> 53.1 20,300-20,349 48.1 dP< 44.7 44.7 dP< 45.7 45.7 dP 52.9 dP> 52.9 N/A 20,350-20,399 47.9 dP< 44.5 44.5 dP< 45.5 45.5 dP 52.7 dP> 52.7 20,400-20,449 47.7 dP< 44.4 44.4 dP< 45.3 45.3 dP 52.5 dP> 52.5 20,450-20,500 47.5 dP< 44.2 44.2 dP< 45.1 45.1 dP 52.3 dP> 52.3 AC 5.4.15.3 Complete the following and mark steps that DO NOT apply N/A:

a. ECW Pump 2B Delta P is within Acceptable Range. N/A

b. ECW Pump 2B Delta P is within Required Action High. N/A

c. ECW Pump 2B Delta P is within Alert Range Low. N/A

d. ECW Pump 2B Delta P is within Required Action Low. N/A 5.4.15.4 IF Total ECW System Delta P is within a Required Action Range, THEN immediately notify Shift Supervisor, OTHERWISE mark this step N/A. N/A KEY This procedure, when complete, shall be retained for the life of the plant.

KEY 0PSP03-EW-0018 Essential Cooling Water System Train B Testing 5.4.15.5 Rev. 21 Page 34 of 64 Measure the unfiltered vibration velocity (V) at indicated test points (Addendum 2, Vibration Test Point Locations Initials and Instructions) and record vibration in Table 5: Unit 2 ECW Pump 2B Vibration Data. N/A Table 5: Unit 2 ECW Pump 2B Vibration Data Vibration Ref Test Data Accept Range Alert Range High Reqd Action Units Data Points Value High 1H1 0.053 V 0.132 0.132 < V 0.318 > 0.318 in/sec 1H2 0.039 V 0.097 0.097 < V 0.234 > 0.234 in/sec 1A 0.026 V 0.065 0.065 < V 0.156 > 0.156 in/sec 2H1* in/sec N/A 2H2* in/sec 3H1* in/sec 3H2* in/sec

• - Data point is reference only for system health monitoring, NOT a code requirement and NO acceptance criteria applicable.

AC 5.4.15.6 Complete the following and mark steps that DO NOT apply N/A:

a. ECW Pump vibration is within Acceptable Range. N/A

b. ECW Pump vibration is within the Alert Range. N/A

c. ECW Pump vibration is within the Required Action Range. N/A 5.4.15.7 IF ECW Pump 2B vibration is within Required Action Range, THEN immediately notify Shift Supervisor, OTHERWISE mark this step N/A. N/A KEY This procedure, when complete, shall be retained for the life of the plant.

KEY 5.5 0PSP03-EW-0018 Essential Cooling Water System Train B Testing Testing ECW Pump 1B(2B) Discharge Check Valve 1(2)-EW-0042 Rev. 21 Page 35 of 64 Initials 5.5.1 IF ECW Total System Flow recorded in Step 5.4.13 is equal to or greater than 18290 gpm, THEN perform the following, OTHERWISE mark the following as N/A:

AC 5.5.1.1 Record the Total ECW System Flow from Step 5.4.13:

Total ECW System Flow ___________ gpm N/A Acceptance Criteria 18290 gpm 5.5.1.2 Mark Steps 5.5.2 through 5.5.7 as N/A. N/A NOTE Parts of Step 5.5.2 may have been performed in previous sections. Steps performed prior to this may be marked as N/A.

5.5.2 Perform the following for testing of 1(2)-EW-0042:

5.5.2.1 Ensure ECW Pump 1B(2B) is in operation per 0POP02-EW-0001, Essential Cooling Water Operation. AC 5.5.2.2 IF ECW Self Cleaning Strainer 1B(2B) Normal Backflush is in service, THEN perform the following, OTHERWISE mark the following as N/A:

a. Record REQUIRED POSITION, including the throttled position and lock status, of "1(2)-EW-0189 ECW PUMP 1B(2B)

DISCHARGE STRAINER BACKFLUSH THROTTLE VALVE" from Valve Database here AND in Step 5.6.3.

{ECWIS, Room 105(102)}

REQUIRED POSITION N/A KEY This procedure, when complete, shall be retained for the life of the plant.

KEY 0PSP03-EW-0018 Essential Cooling Water System Train B Testing b.

Rev. 21 WHEN Step 5.5.2.2.d is performed, THEN RECORD the AS FOUND position, including the Page 36 of 64 Initials throttled position and lock status, of "1(2)-EW-0189 ECW PUMP 1B(2B)

DISCHARGE STRAINER BACKFLUSH THROTTLE VALVE".

{ECWIS, Room 105(102)}

AS FOUND N/A

c. IF the REQUIRED POSITION recorded in Step 5.5.2.2.a AND the AS FOUND position recorded in Step 5.5.2.2.b are different, THEN NOTIFY the Shift Supervisor, OTHERWISE N/A this step. N/A AC d. Close "1(2)-EW-0189 ECW PUMP 1B(2B)

DISCHARGE STRAINER BACKFLUSH THROTTLE VALVE".

{ECWIS, Room 105(102)} N/A NOTE Placing ECW Self Cleaning Strainer handswitch in STOP will cause ESF Status Monitoring Lampbox 2M22 BYP/INOP ECW STRN 1B(2B) to alarm.

5.5.2.3 Ensure ECW Self Cleaning Strainer 1B(2B) is NOT in service by placing "ECW SELF CLEANING STRAINER 1B(2B)" handswitch in STOP.

{ECWIS, MCC E1B3(E2B3)/C1} AC CAUTION IF one of the following occurs, THEN opening of 1(2)-EW-0064 shall be stopped:

• Increasing temperatures from components cooled by ECW

• Exceeding ECW Pump capacity of 20610 gpm 5.5.3 Slowly open "1(2)-EW-0064 CCW HEAT EXCHANGER 1B(2B)

ECW RETURN THROTTLE VALVE" to obtain Total ECW System Flow greater than 18290 gpm. (QDPS ECW TRN FLOW "TRN B") AC KEY This procedure, when complete, shall be retained for the life of the plant.

KEY 5.5.4 0PSP03-EW-0018 Essential Cooling Water System Train B Testing Rev. 21 Record ECW flow from the following components in Table 6 (ECW System Flow for 1(2)-EW-0042):

Page 37 of 64 Initials

• ECW Pump 1B(2B) Lube Water flow from 1(2)-EW-FI-6948,

{ECWIS} AC

• Flow to CCW Pump Supplementary Cooler "TRN B FT 6866" (QDPS) AC

• ECW Flow to "ESF DG 12(22) FT 6865" (QDPS) AC 5.5.5 Record ECW flow from Essential Chillers in Table 6 (ECW System Flow for 1(2)-EW-0042) and mark step NOT performed as N/A:

5.5.5.1 IF ECW from Essential Chillers is in normal Warm Weather alignment, THEN record the following in Table 6:

• "TRN B CHLR 11B(21B) FT 6864" (QDPS) AC

• "TRN B CHLR 11B(22B) FT 6905" (QDPS) AC 5.5.5.2 IF ECW from Essential Chillers is in Cold Weather alignment, THEN record Essential Chiller flows from OPERABLE Essential Chiller(s) in Table 6 and mark data for any INOPERABLE chiller as N/A:

• "1(2)-EW-FI-6864C ESSENTIAL CHILLER 11B(21B) ECW RETURN BYPASS FLOW INDICATOR" N/A

• "1(2)-EW-FI-6905C ESSENTIAL CHILLER 12B(22B) ECW RETURN BYPASS FLOW INDICATOR" N/A KEY This procedure, when complete, shall be retained for the life of the plant.

KEY 5.5.6 0PSP03-EW-0018 Essential Cooling Water System Train B Testing Rev. 21 Determine ECW flow from CCW Heat Exchanger 1B(2B) as follows:

Page 38 of 64 Initials 5.5.6.1 Record ECW flow from CCW Heat Exchanger 1B(2B) using QDPS "TRN B FT6863" on Data Sheet 1 (Essential Cooling Water Flow from CCW Heat Exchanger) at approximately 30 second intervals until 21 flows have been recorded. AC 5.5.6.2 After 21 flows have been recorded, then add the individual flows and record total on Data Sheet 1. AC 5.5.6.3 Calculate and record the average ECW Flow from CCW Heat Exchanger in AVERAGE block of Data Sheet 1. AC 5.5.6.4 Sign and Date Performance of Data Sheet 1. AC 5.5.7 Record AVERAGE ECW Flow from CCW Heat Exchanger from Data Sheet 1 in Table 6 (ECW System Flow for 1(2)-EW-0042) and calculate Total ECW System Flow through 1(2)-EW-0042: AC Table 6: ECW System Flow for 1(2)-EW-0042 Component ECW Flow Units ECW Pump 1B(2B) Lube Water 10.7 gpm ECW Flow to Essen Chlr 11B(21B) 620 gpm ECW Flow to Essen Chlr 12B(22B) 1154 gpm ECW Flow to CCW Pump Cooler 46 gpm ECW Flow to ESF DG 12(22) 1746 gpm ECW Flow to CCW HX 15650.5 gpm (AVERAGE from Data Sheet 1)

TOTAL ECW SYSTEM FLOW = 19227.2 gpm AC 5.5.8 Verify Total ECW System Flow through 1(2)-EW-0042 is equal to or greater than 18290 gpm from one of the following and mark criteria NOT used as N/A:

• ECW Pump Flow (Step 5.5.1.1) N/A KEY TOTAL ECW SYSTEM FLOW from Table 6 (Step 5.5.7) AC This procedure, when complete, shall be retained for the life of the plant.

KEY5.6 0PSP03-EW-0018 Essential Cooling Water System Train B Testing Restoration of Essential Cooling Water System Flow Rev. 21 Page 39 of 64 Initials 5.6.1 IF adjustments to "1(2)-EW-0064 CCW HEAT EXCHANGER 1B(2B) ECW RETURN THROTTLE VALVE" have been performed in Step 5.5.3, THEN restore ECW flow from CCW Heat Exchanger 1B(2B) to normal operating range of 14040 gpm to 17400 gpm. AC Perform YZ Ind. Verif 5.6.2 IF adjustments to "1(2)-EW-0064 CCW HEAT EXCHANGER 1B(2B) ECW RETURN THROTTLE VALVE" have been performed in Step 5.5.3, THEN Ensure "1(2)-EW-0064 CCW HEAT EXCHANGER 1B(2B) ECW RETURN THROTTLE VALVE" is locked in the throttled position. AC Perform YZ Ind. Verif AC 5.6.3 DV Restore the following valves to the AS FOUND or REQUIRED POSITION position, or as directed by the Shift Supervisor, and record AS LEFT position:

• 1(2)-EW-0189 REQUIRED POSITION LIP 41/4 TURNS OPEN

• 1(2)-EW-0189 AS LEFT LIP 41/4 TURNS OPEN AC Perform YZ Dual Verif

• 1(2)-EW-0278 AS FOUND CLOSED

• 1(2)-EW-0278 AS LEFT CLOSED AC Perform YZ Ind. Verif KEY This procedure, when complete, shall be retained for the life of the plant.

KEY 0PSP03-EW-0018 Essential Cooling Water System Train B Testing NOTE Rev. 21 Page 40 of 64 Initials IF the Essential Chillers are in Cold Weather alignment, THEN it will be necessary to use 0POP02-CH-0005, Essential Chiller Operation, to ensure 1(2)-EW-3016 AND 1(2)-EW-3019 are properly restored to their AS FOUND position.

5.6.4 IF ECW from Essential Chillers is in Cold Weather alignment, THEN restore the following valves to the AS FOUND position or as directed by the Shift Supervisor and record AS LEFT position, OTHERWISE mark this step as N/A:

• 1(2)-EW-3016 AS FOUND ___________

• 1(2)-EW-3016 AS LEFT ___________ N/A Perform N/A Ind. Verif

• 1(2)-EW-3019 AS FOUND ___________

• 1(2)-EW-3019 AS LEFT ___________ N/A Perform N/A Ind. Verif 5.6.5 Return ECW Self Cleaning Strainer 1B(2B) to service by placing "ECW SELF CLEANING STRAINER 1B(2B)" handswitch in AUTO. {ECWIS, MCC E1B3(E2B3)/C1} AC Perform YZ Ind. Verif KEY This procedure, when complete, shall be retained for the life of the plant.

KEY 0PSP03-EW-0018 Essential Cooling Water System Train B Testing NOTE Rev. 21 Page 41 of 64 Initials

• IF Essential Chillers are in Cold Weather alignment, THEN ECW flow to Essential Chillers is in accordance with 0POP02-CH-0005, Essential Chiller Operation.

• IF Standby Diesel Generator 12(22) flow is NOT within the required range, THEN SED Performance Technicians should be notified to perform individual heat exchanger flow measurements prior to any valve adjustments. (Reference 7.4.6)

• IF Emergency Diesel Generator ECW flow is adjusted, THEN System Engineering should be notified that the individual cooler flows on the diesel engine may have been affected.

5.6.6 Ensure ECW System flows are restored to normal flow range and record flow in Table 7 (As Left ECW System Flow): AC Table 7: As Left ECW System Flow COMPONENT ECW FLOW NORMAL FLOW RANGE ECW Pump 1B(2B) Lube Water 10.5 gpm >3.0 gpm 1(2)-EW-FI-6948 ECW Flow to CCW HX QDPS FT-6863 15450 gpm 14040 to 17400 gpm TRN B FT 6863 ECW Flow to Essen Chlr 11B(21B) 600 to 693 gpm Normal Warm Weather Alignment QDPS FT-6864 610 gpm 110 to 130 gpm Cold Weather 150 T Chiller OP 1(2)-EW-FI-6864C ECW throttled Cold Weather 150 T Chiller INOP ECW Flow to Essen Chlr 12B(22B) 1100 to 1272 gpm Normal Warm Weather Alignment QDPS FT-6905 1140 gpm 230 to 250 gpm Cold Weather 150 T Chiller OP 1(2)-EW-FI-6905C ECW throttled Cold Weather 150 T Chiller INOP ECW Flow to CCW Pump Cooler 43 gpm 40 to 50 gpm QDPS TRN B FT 6866 ECW Flow to ESF DG 1723 gpm 1486 to 1743 gpm QDPS DG 12(22) FT 6865 5.6.7 Remove the 0-100 psig Test Gage installed at ECW Pump discharge test connection for "1(2)-EW-PI-6885 ECW PUMP 1B(2B)

DISCHARGE PRESSURE INDICATOR" and install cap. AC Perform KEY YZ Ind. Verif This procedure, when complete, shall be retained for the life of the plant.

KEY 5.7 0PSP03-EW-0018 Essential Cooling Water System Train B Testing Testing ECW Screen Wash Booster Pump 1B(2B)

Rev. 21 Page 42 of 64 Initials 5.7.1 Ensure ECW Pump 1B(2B) is in operation per 0POP02-EW-0001, Essential Cooling Water Operation. AC 5.7.2 Ensure the following are shutdown: {CP002}

• "TRAV SCRN 1B(2B)" AC

• "SCRN WASH PUMP 1B(2B)" AC NOTE Steps 5.7.3 through 5.9.4 are performed at the ECW Intake Structure, unless otherwise noted.

5.7.3 Verify "1(2)-EW-0172 ECW SCREEN WASH BOOSTER PUMP 1B(2B) SUCTION VALVE" is open. AC 5.7.4 Open the following instrument isolation valves:

• "1(2)-EW-0373B ECW SCREEN WASH BOOSTER PUMP 1B(2B) FE-6958 HIGH SIDE TEST VALVE" AC

• "1(2)-EW-0374B ECW SCREEN WASH BOOSTER PUMP 1B(2B) FE-6958 LOW SIDE TEST VALVE" AC

• "1(2)-EW-0375B ECW SCREEN WASH BOOSTER PUMP 1B(2B) SUCTION TEST VALVE" AC NOTE Normal lubricating oil level is at the approximate midpoint of the sight glass. IF level is low, THEN lubricant shall be added prior to continuing with this test.

5.7.5 Check ECW Screen Wash Booster Pump 1B(2B) lubricant level at approximately one-half (1/2) of sight glass. AC 5.7.6 Notify I&C Maintenance to place the following instruments in service at the instrument manifold:

• "N1(2)EW-PDI-6941" AC KEY

• "N1(2)EW-FI-6958" AC This procedure, when complete, shall be retained for the life of the plant.

KEY 5.7.7 0PSP03-EW-0018 Essential Cooling Water System Train B Testing Rev. 21 Ensure the following instruments are properly vented:

Page 43 of 64 Initials

• "N1(2)EW-PDI-6941" AC

• "N1(2)EW-FI-6958" AC

• "1(2)-EW-PI-6941 ECW SCREEN WASH PUMP 1B(2B)

DISCHARGE PRESSURE INDICATOR" AC 5.7.8 Start ECW Screen Wash Booster Pump by momentarily placing "SCRN WASH PUMP 1B(2B)" to START. {CP002} AC 5.7.9 Record AS FOUND position, including the throttled position and lock status, of "1(2)-EW-0003 ECW TRAVELING SCREEN 1B(2B)

SPRAY WASH VALVE". {Room 108(111)}

AS FOUND LIP 31/2 TURNS OPEN AC 5.7.10 RECORD the REQUIRED POSITION, including the throttled position and lock status, of "1(2)-EW-0003 ECW TRAVELING SCREEN 1B(2B) SPRAY WASH VALVE" from Valve Database here AND in Step 5.9.1. {Room 108(111)}

REQUIRED POSITION LIP 31/2 TURNS OPEN AC 5.7.11 IF the AS FOUND position recorded in Step 5.7.9 and the REQUIRED POSITION recorded in Step 5.7.10 are different, THEN NOTIFY the Shift Supervisor, OTHERWISE N/A this Step. N/A KEY This procedure, when complete, shall be retained for the life of the plant.

KEY 5.7.12 0PSP03-EW-0018 Essential Cooling Water System Train B Testing Rev. 21 Establish ECW Screen Wash Booster Pump flow as follows:

Page 44 of 64 Initials 5.7.12.1 Unlock and throttle "1(2)-EW-0003 ECW TRAVELING SCREEN 1B(2B) SPRAY WASH VALVE" until P indicated on "N1(2)EW-FI-6958" is equal to 188 inches H2O and record time:

Start time 0305 Time AC 5.7.12.2 IF P is NOT equal to 188 inches H2O, THEN adjust "1(2)-EW-0003 ECW TRAVELING SCREEN 1B(2B)

SPRAY WASH VALVE" until pump flow is stable for 5 minutes with a differential pressure equal to 188 inches H2O, OTHERWISE mark this step N/A. N/A 5.7.12.3 After 5 minutes, verify indicated P on "N1(2)EW-FI-6958" is equal to 188 inches H2O and record time:

End time 0311 Time AC 5.7.13 Record differential pressure from "N1(2)EW-FI-6958":

P from "N1(2)EW-FI-6958" 188 inches H2O AC 5.7.14 Record the following for ECW Screen Wash Booster Pump 1B(2B):

5.7.14.1 Discharge pressure from "1(2)-EW-PI-6941 ECW SCREEN WASH PUMP 1B(2B) DISCHARGE PRESSURE INDICATOR" ECWSWBP Disch Press 78 psig (PI-6941) AC 5.7.14.2 Pump differential pressure (DP) from "N1(2)EW-PDI-6941":

ECWSWBP Diff Press 47 psid (PDI-6941) AC KEY This procedure, when complete, shall be retained for the life of the plant.

KEY 0PSP03-EW-0018 Essential Cooling Water System Train B Testing Table 8: ECW Screen Wash Booster Pump 1B(2B) Reference Values Rev. 21 Page 45 of 64 Initials Ref Value Reqd Action Low Acceptable Range Reqd Action High Units Unit 1 46.5 <41.9 41.9 DP 51.1 > 51.1 psid Unit 2 47.5 <42.8 42.8 DP 52.2 > 52.2 psid AC 5.7.14.3 Using ECW Screen Wash Booster Pump differential pressure recorded in Step 5.7.14.2, evaluate the pump differential pressure for acceptable operation on Table 8 (ECW Screen Wash Booster Pump 1B(2B) Reference Values). AC 5.7.14.4 IF ECW Screen Wash Booster Pump 1B(2B) differential pressure is within Required Action Range, THEN immediately notify Shift Supervisor, OTHERWISE mark this step N/A. N/A 5.7.15 IF performing this test in Unit 1, THEN measure unfiltered vibration velocity (V) at indicated test points (Addendum 3, Vibration Test Point Locations and Instructions) AND record vibration in Table 9 (Unit 1 ECW Screen Wash Booster Pump 1B Vibration Data), OTHERWISE mark this step and the Test Data blocks in Table 9 N/A. AC Table 9: Unit 1 ECW Screen Wash Booster Pump 1B Vibration Data Vibration Ref Test Data Accept Range Alert Range High Reqd Action Units Data Points Value High 3H 0.058 0.072 V 0.145 0.145 < V 0.348 > 0.348 in/sec 3V 0.072 0.084 V 0.180 0.180 < V 0.432 > 0.432 in/sec 3A 0.032 0.044 V 0.080 0.080 < V 0.192 > 0.192 in/sec KEY This procedure, when complete, shall be retained for the life of the plant.

KEY 5.7.16 0PSP03-EW-0018 Essential Cooling Water System Train B Testing Rev. 21 IF performing this test in Unit 2, THEN measure unfiltered vibration Page 46 of 64 velocity (V) at indicated test points (Addendum 3, Vibration Test Point Initials Locations and Instructions) AND record vibration in Table 10 (Unit 2 ECW Screen Wash Booster Pump 2B Vibration Data), OTHERWISE mark this step and the Test Data blocks in Table 10 N/A. N/A Table 10: Unit 2 ECW Screen Wash Booster Pump 2B Vibration Data Vibration Ref Test Data Accept Range Alert Range High Reqd Action Units Data Points Value High 3H 0.056 V 0.140 0.140 < V 0.336 > 0.336 in/sec 3V 0.045 V 0.112 0.112 < V 0.270 > 0.270 in/sec 3A 0.024 V 0.060 0.060 < V 0.144 > 0.144 in/sec 5.7.17 Using Table 9 or 10, as applicable, perform the following:

AC 5.7.17.1 Evaluate ECWSWB Pump vibration test data. AC 5.7.17.2 Complete the following and mark steps that DO NOT apply N/A:

a. ECWSWB Pump vibration is within Acceptable Range. AC

b. ECWSWB Pump vibration is within the Alert Range. N/A

c. ECWSWB Pump vibration is within the Required Action Range. N/A 5.7.18 IF any ECW Screen Wash Booster Pump 1B(2B) vibration is within Required Action Range, THEN immediately notify Shift Supervisor, OTHERWISE mark this step N/A. N/A KEY This procedure, when complete, shall be retained for the life of the plant.

KEY 5.8 0PSP03-EW-0018 Essential Cooling Water System Train B Testing Testing ECW Screen Wash Booster Pump Discharge Check Valve 1(2)-EW-0254 Rev. 21 Page 47 of 64 Initials 5.8.1 Ensure ECW Screen Wash Booster Pump 1B(2B) is in operation per 0POP02-EW-0001, Essential Cooling Water Operation. AC 5.8.2 IF the REQUIRED POSITION of "1(2)-EW-0003 ECW TRAVELING SCREEN 1B(2B) SPRAY WASH VALVE" is NOT recorded in Step 5.9.1, THEN PERFORM the following, OTHERWISE mark the following steps as N/A:

5.8.2.1 RECORD the AS FOUND position, including the throttled position and lock status, of "1(2)-EW-0003 ECW TRAVELING SCREEN 1B(2B) SPRAY WASH VALVE". {ECWIS, Room 108(111)}

AS FOUND N/A 5.8.2.2 RECORD the REQUIRED POSITION, including the throttled position and lock status, of "1(2)-EW-0003 ECW TRAVELING SCREEN 1B(2B) SPRAY WASH VALVE" from Valve Database here AND in Step 5.9.1.

{Room 108(111)}

REQUIRED POSITION N/A 5.8.2.3 IF the AS FOUND position recorded in Step 5.8.2.1 AND the REQUIRED POSITION recorded in Step 5.8.2.2 are different, THEN NOTIFY the Shift Supervisor, OTHERWISE N/A this Step. N/A 5.8.3 Open "1(2)-EW-0003 ECW TRAVELING SCREEN 1B(2B) SPRAY WASH VALVE". {ECWIS, Room 108(111)} AC 5.8.4 Record P from "N1(2)EW-FI-6958":

ECWSWBP Diff Press 188 in H2O (FI-6958) AC AC 5.8.5 Determine ECW Screen Wash Booster Pump 1B(2B) flow rate using P recorded in Step 5.8.4 from Addendum 4 (ECW Screen Wash Booster Pump 1B(2B) Flow) and record:

ECWSWBP Flow 158.4 gpm AC Acceptance Criteria > 158 gpm KEY This procedure, when complete, shall be retained for the life of the plant.

KEY 5.9 0PSP03-EW-0018 Essential Cooling Water System Train B Testing Restoration of ECW Screen Wash System Rev. 21 DV Restore "1(2)-EW-0003 ECW TRAVELING SCREEN 1B(2B)

Page 48 of 64 Initials 5.9.1 SPRAY WASH VALVE" to the REQUIRED POSITION or as directed by the Shift Supervisor and record AS LEFT position:

• 1(2)-EW-0003 REQUIRED POSITION LIP 31/2 TURNS OPEN

• 1(2)-EW-0003 AS LEFT LIP 31/2 TURNS OPEN AC Perform YZ Dual Verif 5.9.2 Stop "SCRN WASH PUMP 1B(2B)". {CP002} AC 5.9.3 Equalize and isolate the following at the respective instrument manifold:

• "N1(2)EW-PDI-6941" IC Perform MN Ind. Verif

• "N1(2)EW-FI-6958" IC Perform MN Ind. Verif KEY This procedure, when complete, shall be retained for the life of the plant.

KEY 5.9.4 0PSP03-EW-0018 Essential Cooling Water System Train B Testing Close the following valves:

Rev. 21 Page 49 of 64 Initials

• "1(2)-EW-0373B ECW SCREEN WASH BOOSTER PUMP 1B(2B) FE-6958 HIGH SIDE TEST VALVE" AC Perform YZ Ind. Verif

• "1(2)-EW-0374B ECW SCREEN WASH BOOSTER PUMP 1B(2B) FE-6958 LOW SIDE TEST VALVE" AC Perform YZ Ind. Verif

• "1(2)-EW-0375B ECW SCREEN WASH BOOSTER PUMP 1B(2B) SUCTION TEST VALVE" AC Perform YZ Ind. Verif KEY This procedure, when complete, shall be retained for the life of the plant.

KEY5.10 0PSP03-EW-0018 Essential Cooling Water System Train B Testing Testing ECW Blowdown Isolation Valve 1(2)-EW-FV-6936 Rev. 21 Page 50 of 64 Initials 5.10.1 ECW Pump 1B(2B) is in operation per 0POP02-EW-0001, Essential Cooling Water Operation. AC 5.10.2 Record the AS FOUND position of handswitch "ECW TRAIN B BLWDN ISOL FV-6936" in Step 5.10.5. AC NOTE Steps 5.10.3 and 5.10.4 may be performed in any order.

5.10.3 Perform "ECW TRAIN B BLWDN ISOL FV-6936" close exercise and stroke timing as follows:

5.10.3.1 Ensure approximately 2 minutes have elapsed since "ECW TRAIN B BLWDN ISOL FV-6936" was opened to allow time for the valve control/operator to reach normal air pressure prior to stroke-timing. AC 5.10.3.2 Simultaneously start stopwatch and close FV-6936 by placing handswitch "ECW TRAIN B BLWDN ISOL FV-6936" to CLOSE. AC AC 5.10.3.3 WHEN "ECW TRAIN B BLWDN ISOL FV-6936" is fully closed (Red lamp OFF, Green lamp ON), THEN stop stopwatch and record valve closing time:

Time 8.72 seconds AC Acceptance Criteria: Unit 1: 3.35 t 10.05 seconds Unit 2: 1.91 t 5.73 seconds KEY This procedure, when complete, shall be retained for the life of the plant.

KEY 5.10.4 0PSP03-EW-0018 Essential Cooling Water System Train B Testing Rev. 21 Perform "ECW TRAIN B BLWDN ISOL FV-6936" open exercise as follows:

Page 51 of 64 Initials 5.10.4.1 Place handswitch "ECW TRAIN B BLWDN ISOL FV-6936" to AUTO. AC AC 5.10.4.2 Verify "ECW TRAIN B BLWDN ISOL FV-6936" is full open (Red light ON, Green light OFF). AC 5.10.5 Restore handswitch "ECW TRAIN B BLWDN ISOL FV-6936" to the AS FOUND position or as directed by the Shift Supervisor and record AS LEFT position:

• 1(2)-EW-FV-6936 AS FOUND CLOSED

• 1(2)-EW-FV-6936 AS LEFT CLOSED AC Perform YZ Ind. Verif KEY This procedure, when complete, shall be retained for the life of the plant.

KEY 5.11 0PSP03-EW-0018 Essential Cooling Water System Train B Testing Testing Essential Cooling Water Valves Rev. 21 Page 52 of 64 Initials NOTE Steps 5.11.1 and 5.11.2 may be performed in any order.

5.11.1 Testing of ECW Pump 1B(2B) Discharge Valve 1(2)-EW-MOV-0137 5.11.1.1 ECW Pump 1B(2B) is shutdown per 0POP02-EW-0001, Essential Cooling Water Operation. AC 5.11.1.2 Ensure "DISCH ISOL MOV-0137" is CLOSED.

{CP002} AC 5.11.1.3 Perform ECW Pump Discharge Valve open exercise and stroke timing as follows:

a. Simultaneously start stopwatch and open ECW Pump Discharge Valve by momentarily placing handswitch "DISCH ISOL MOV-0137" to OPEN. AC AC b. WHEN "DISCH ISOL MOV-0137" is fully open (Red lamp ON, green lamp OFF), THEN stop stopwatch and record valve opening time:

Time 8.89 seconds AC Acceptance Criteria: Unit 1: 6.38 t 10.64 seconds Unit 2: 6.18 t 10.29 seconds 5.11.1.4 Perform "DISCH ISOL MOV-0137" close exercise by performing the following:

a. Close ECW Pump Discharge Valve by momentarily placing handswitch "DISCH ISOL MOV-0137" to CLOSE. AC AC b. Verify "DISCH ISOL MOV-0137" is full closed (Red light OFF, Green light ON). AC KEY This procedure, when complete, shall be retained for the life of the plant.

KEY 5.11.2 0PSP03-EW-0018 Essential Cooling Water System Train B Testing Rev. 21 Testing of ECW Screen Wash Booster Pump Discharge Valve 1(2)-EW-FV-6924 Page 53 of 64 Initials 5.11.2.1 ECW Screen Wash Booster Pump 1B(2B) is shutdown per 0POP02-EW-0001, Essential Cooling Water Operation. AC 5.11.2.2 Verify "TRAV SCRN 1B(2B) WASH FV-6924" is CLOSED. {CP002} AC 5.11.2.3 Record the AS FOUND position of handswitch "TRAV SCRN 1B(2B) WASH FV-6924" in Step 5.11.2.6.

{CP002}V 5.11.2.4 Perform ECW Screen Wash Booster Pump Discharge Valve open exercise and stroke timing as follows:

a. Simultaneously start stopwatch and open ECW Screen Wash Booster Pump Discharge Valve by placing handswitch "TRAV SCRN 1B(2B)

WASH FV-6924" to OPEN. AC AC b. WHEN "TRAV SCRN 1B(2B) WASH FV-6924" is fully open (Red lamp ON, green lamp OFF),

THEN stop stopwatch and record valve opening time:

Time 3.66 seconds AC Acceptance Criteria: Unit 1: 1.45 t 4.35 seconds Unit 2: 1.31 t 3.93 seconds 5.11.2.5 Perform "TRAV SCRN 1B(2B) WASH FV-6924" close exercise test as follows:

a. Close ECW Screen Wash Booster Pump Discharge Valve by placing handswitch "TRAV SCRN 1B(2B) WASH FV-6924" to CLOSE. AC AC b. Verify "TRAV SCRN 1B(2B) WASH FV-6924" is closed (Red light OFF, Green light ON). AC KEY This procedure, when complete, shall be retained for the life of the plant.

KEY 0PSP03-EW-0018 Essential Cooling Water System Train B Testing 5.11.2.6 Rev. 21 Return handswitch for "TRAV SCRN 1B(2B) WASH FV-6924" to the AS FOUND position and record Page 54 of 64 Initials AS LEFT position:

• FV-6924 handswitch AS FOUND AUTO

• FV-6924 handswitch AS LEFT AUTO AC Perform YZ Ind. Verif 5.12 Restoration & Documentation 5.12.1 Notify Shift Supervisor that testing is complete. AC 5.12.2 Restore ECW System as directed by the Shift Supervisor per 0POP02-EW-0001, Essential Cooling Water Operation. _____

5.12.3 Ensure Performers and Verifiers Section of PPDS is complete. _____

5.12.4 Ensure M&TE Used Section of PPDS is complete. _____

5.12.5 Ensure required information has been recorded on the M&TE Usage form (WOFWOME) in STP IMPACT for each piece of M&TE used.

(Ref. 7.4.3) _____

5.12.6 IF any problems occurred, THEN initiate Condition Report(s) and log Condition Report number(s) in Remarks Section of PPDS, OTHERWISE mark this step N/A. _____

5.12.7 Complete Test Results Section of the PPDS. _____

5.12.8 Forward test package to Shift Supervisor for review. _____

KEY This procedure, when complete, shall be retained for the life of the plant.

KEY 6.0 Acceptance Criteria 6.1 0PSP03-EW-0018 Essential Cooling Water System Train B Testing Rev. 21 Page 55 of 64 Essential Cooling Water Emergency Backflush Manual Valve 1(2)-EW-0278 shall manually operate full open and full closed. (Steps 5.3.3 and 5.3.9) 6.2 Essential Cooling Water Emergency Backflush Check Valve 1(2)-EW-0404 full opened by indication of flow from emergency backflush piping. (Step 5.3.8) 6.3 Essential Cooling Water Discharge Strainer Backflush Throttle Valve 1(2)-EW-0189 shall manually operate full closed and open to its required safety position (throttled).

(Steps 5.3.7, 5.4.2.4, 5.5.2.2d, 5.6.3) 6.4 ECW Pump 1B(2B) flow shall be within the Acceptable Range or the Alert Range.

(Step 5.4.14.3 or 5.4.15.3) 6.5 ECW Pump 1B(2B) Vibration Test Data shall be within the Acceptable Range or the Alert Range. (Step 5.4.14.6 or 5.4.15.6) 6.6 ECW Pump 1B(2B) Discharge Check Valve 1(2)-EW-0042 exercised to the full open position by verification of flow greater than the Acceptance Criteria. (Step 5.5.1.1 or 5.5.8) 6.7 ECW Screen Wash Booster Pump 1B(2B) Differential Pressure (DP) shall be within the Acceptable Range. (Step 5.7.14.3) 6.8 ECW Screen Wash Booster Pump 1B(2B) Vibration Test Data shall be within the Acceptable Range or the Alert Range. (Step 5.7.17) 6.9 Flow through 1(2)-EW-0254 ECW Screen Wash Booster Pump Discharge Check Valve shall be greater than 158 gpm. (Step 5.8.5) 6.10 1(2)-EW-FV-6936 ECW Blowdown Valve shall close (fail-safe position) with a stroke time within the allowed time listed in Step 5.10.3.3, and operate through one complete cycle open and closed. (Steps 5.10.3.3 and 5.10.4.2) 6.11 1(2)-EW-MOV-0137 ECW Pump Discharge Valve shall open with a stroke time within the allowed time listed in Step 5.11.1.3b, and operate through one complete cycle open and closed. (Steps 5.11.1.3b and 5.11.1.4b) 6.12 1(2)-EW-FV-6924 ECW Screen Wash Booster Pump Discharge Valve shall open (fail-safe position) with a stroke time within the allowed time listed in Step 5.11.2.4b, and operate through one complete cycle open and closed. (Steps 5.11.2.4b and 5.11.2.5b)

KEY This procedure, when complete, shall be retained for the life of the plant.

KEY 7.0 References 7.1 0PSP03-EW-0018 Essential Cooling Water System Train B Testing Technical Specifications Rev. 21 Page 56 of 64 7.1.1 Technical Specification 3.7.4 [ITS 3.7.8]

7.1.2 Technical Specification 4.0.5 [ITS 5.5.8]

7.1.3 Technical Specification 4.3.2.1.1.c.7 [ITS SR 3.3.2.7.1c]

7.2 Regulatory Guides and Standards 7.2.1 ASME OMa-1988, Addenda to ASME OM-1987, Operation and Maintenance of Nuclear Power Plants, Part 6, Inservice Testing of Pumps in Light-Water Reactor Power Plants.

7.2.2 ASME OMa-1988, Addenda to ASME OM-1987, Operation and Maintenance of Nuclear Power Plants, Part 10, Inservice Testing of Valves in Light-Water Reactor Power Plants.

7.3 UFSAR 7.3.1 Section 3.9.6, Inservice Testing of Pumps and Valves 7.3.2 Section 9.2.1.2, Essential Cooling Water System 7.4 Commitments 7.4.1 SPR 870394, ECW Pump Test Failure Due To Instrumentation Problems 7.4.2 SPR 940802, Installed Plant Pump Gages Exceed ASME Section XI Range Requirements 7.4.3 SPR 941413, M&TE Issue Sheets not Completed for each use of Instrument 7.4.4 Generic Letter 91-15, Operating Feedback Report, Solenoid-Operated Valve Problems at U.S. Reactors 7.4.5 ST-HL-AE-7393, Reply to Notice of Violation 9236-05 Regarding Failure to Include Valves in the Inservice Testing (IST) Program 7.4.6 MATS Item 9201148-936 (NRC IR 92-201), July 1992 ECW Inspection 7.4.7 CR 97-12395, Containment Spray Pump Slave Relay Testing KEY This procedure, when complete, shall be retained for the life of the plant.

KEY 7.5 0PSP03-EW-0018 Essential Cooling Water System Train B Testing Technical Standards and Manuals 7.5.1 Rev. 21 Page 57 of 64 14269-4122(8122)-01001-HX, Instruction Manual for ECW Screen Wash Pump, Reactor Makeup Water Pump, and EAB Chilled Water Pump 7.5.2 4Z479Z44810 Sh 23, Instrument Data Sheet, Head-Type Primary Flow Elements 7.5.3 5R289MB1006, Essential Cooling Water System Design Basis Document 7.5.4 Unit 1/Unit 2 Pump and Valve Inservice Test Plan 7.6 Drawings 7.6.1 Piping and Instrument Drawings 7.6.1.1 5R289F05038 #1 and #2 Sheet 2, Essential Cooling Water System Train 1B(2B) 7.6.1.2 5R289F05039 #1 and #2, Essential Cooling Water System 7.6.2 Elementary Wiring Diagrams 7.6.2.1 9-E-EW01-01 #1 and #2, Essential Cooling Water Pumps 1A, 1B & 1C (2A, 2B & 2C) 7.6.2.2 9-E-EW02-02 #1 and #2, Essential Cooling Water Screen Wash Booster Pump 1A, 1B & 1C 7.6.2.3 9-E-EW05-02 #1, Essential Cooling Water Traveling Screens 1A, 1B & 1C 7.6.2.4 9-E-EW05-02 #2, Essential Cooling Water Traveling Screens Train "A", "B" & "C" KEY This procedure, when complete, shall be retained for the life of the plant.

KEY 7.7 0PSP03-EW-0018 Essential Cooling Water System Train B Testing STPEGS Procedures and Policies 7.7.1 0POP02-EW-0001, Essential Cooling Water Operation Rev. 21 Page 58 of 64 7.7.2 0POP02-CH-0005, Essential Chiller Operation 7.7.3 0PSP03-EW-0011, Essential Cooling Water Pump 1B(2B) Reference Values Measurement 7.7.4 0PSP03-EW-0014, ECW Screen Wash Booster Pump 1B(2B) Reference Values Measurement 7.7.5 0POP01-ZQ-0022, Plant Operations Shift Routines 7.7.6 0PGP03-ZE-0004, Plant Surveillance Program 7.7.7 0PGP03-ZE-0005, Plant Surveillance Procedure Preparation 7.7.8 0PGP03-ZA-0055, Plant Surveillance Scheduling 7.7.9 0PGP03-ZC-0004, Measuring and Test Equipment Control Program 7.7.10 0PGP03-ZM-0016, Installed Plant Instrumentation Calibration Verification Program 7.7.11 0PGP03-ZE-0021, Inservice Testing Program for Valves 7.7.12 0PGP03-ZE-0022, Inservice Testing Program for Pumps 7.8 Calculations 7.8.1 MC-6118, Calculation for Screen Wash Pump Minimum Flow 7.8.2 Calculation No. 88-EW-002, ECW Pump Discharge and Suction Pressures 7.8.3 CR 98-12276-35, O&M Code Calculation of Stroke Time Acceptance Criteria KEY This procedure, when complete, shall be retained for the life of the plant.

KEY 8.0 Support Documents 8.1 0PSP03-EW-0018 Essential Cooling Water System Train B Testing Rev. 21 Addendum 1, Essential Cooling Water Pump Bay Level Correction Factor Page 59 of 64 8.2 Addendum 2, ECW Pump Vibration Test Point Locations and Instructions 8.3 Addendum 3, ECW Screen Wash Booster Pump Vibration Test Point Locations and Instructions 8.4 Addendum 4, ECW Screen Wash Booster Pump 1B(2B) Flow 8.5 Data Sheet 1, Essential Cooling Water Flow from CCW Heat Exchanger KEY This procedure, when complete, shall be retained for the life of the plant.

KEYAddendum 1 0PSP03-EW-0018 Rev. 21 Essential Cooling Water System Train B Testing Essential Cooling Water Pump Bay Level Correction Factor Bay Level Bay Level Page 60 of 64 Page 1 of 1 LI-6921 feet Correction Factor 15.0 4.7 15.1 4.7 15.2 4.6 15.3 4.6 15.4 4.6 15.5 4.5 15.6 4.5 15.7 4.4 15.8 4.4 15.9 4.3 16.0 4.3 16.1 4.3 16.2 4.2 16.3 4.2 16.4 4.1 16.5 4.1 NOTE: Values in the above table were calculated using the following:

ECW Bay Level Correction Factor KEY Bay Level Correction Factor = 0.43psi/ft x (26ft - ECW Bay Level)

This procedure, when complete, shall be retained for the life of the plant.

KEY Addendum 2 0PSP03-EW-0018 Essential Cooling Water System Train B Testing Rev. 21 ECW Pump Vibration Test Point Locations and Instructions Page 61 of 64 Page 1 of 1 1A 1 H1, H2 H2 MOTOR 2 H1, H2 H1 3 H1, H2 PUMP D116B D116B.WPG H1-H2-A-

KEY Denotes a horizontal vibration point. Probe shall be held perpendicular to the machine axis and parallel to both the floor and the pump discharge piping.

Denotes a horizontal vibration point. Probe shall be held parallel to the floor and perpendicular to both the machine axis and the pump discharge piping.

Denotes an axial vibration point. Probe shall be held perpendicular to the floor and parallel to the machine axis.

This procedure, when complete, shall be retained for the life of the plant.

KEY Addendum 3 0PSP03-EW-0018 Essential Cooling Water System Train B Testing Rev. 21 ECW Screen Wash Booster Pump Vibration Test Point Locations and Instructions Page 62 of 64 Page 1 of 1 3V 3A 3H MOTOR END PUMP END NOTE: Figure is NOT a specific drawing for the ECW Screen Wash Booster Pump. The Figure is for illustration of the location of vibration measuring points.

H- Denotes a horizontal vibration point. Probe shall be held perpendicular to the machine axis and parallel to the floor.

V- Denotes a vertical vibration point. Probe shall be held perpendicular to the floor and the machine axis.

A- Denotes an axial vibration point. Probe shall be held parallel to the floor and the machine axis.

KEY This procedure, when complete, shall be retained for the life of the plant.

KEY Addendum 4 in H2O gpm in H2O 0PSP03-EW-0018 Essential Cooling Water System Train B Testing ECW Screen Wash Booster Pump 1B(2B) Flow gpm in H2O gpm in H2O Rev. 21 gpm Page 63 of 64 Page 1 of 1 in H2O gpm 170 150.6 190 159.2 210 167.4 230 175.2 250 182.6 171 151.0 191 159.6 211 167.8 231 175.5 251 183.0 172 151.5 192 160.0 212 168.2 232 175.9 252 183.4 173 151.9 193 160.5 213 168.6 233 176.3 253 183.7 174 152.4 194 160.9 214 169.0 234 176.7 254 184.1 175 152.8 195 161.3 215 169.4 235 177.1 255 184.4 176 153.2 196 161.7 216 169.7 236 177.4 256 184.8 177 153.7 197 162.1 217 170.1 237 177.8 257 185.2 178 154.1 198 162.5 218 170.5 238 178.2 258 185.5 179 154.5 199 162.9 219 170.9 239 178.6 259 185.9 180 155.0 200 163.3 220 171.3 240 178.9 260 186.2 181 155.4 201 163.7 221 171.7 241 179.3 261 186.6 182 155.8 202 164.2 222 172.1 242 179.7 262 187.0 183 156.2 203 164.6 223 172.5 243 180.0 263 187.3 184 156.7 204 165.0 224 172.9 244 180.4 264 187.7 185 157.1 205 165.4 225 173.3 245 180.8 265 188.0 186 157.5 206 165.8 226 173.6 246 181.2 266 188.4 187 157.9 207 166.2 227 174.0 247 181.5 267 188.7 187.1 158.0 = MINIMUM ACCEPTABLE FLOW RATE THROUGH 1(2)-EW-0254 188 158.4 208 166.6 228 174.4 248 181.9 268 189.1 189 158.8 209 167.0 229 174.8 249 182.3 269 189.4 Flowrate = 11.55 gpm inch H2O KEY NOTE: Values in the above Table were calculated using the following:

Calculation of ECW Screen Wash Booster Pump 1A(2A) Flow Rate from Differential Pressure 1/2 x DP inch H 2 O This procedure, when complete, shall be retained for the life of the plant.

KEY Data Sheet 1 0PSP03-EW-0018 Essential Cooling Water System Train B Testing Rev. 21 Essential Cooling Water Flow from CCW Heat Exchanger Step 5.4.11 Page 64 of 64 Page 1 of 1 Step 5.5.6 1 13453 15669 2 13397 15797 3 13213 15597 4 13233 15774 5 13265 15723 6 13197 15665 7 13157 15696 8 13385 15681 9 13309 15787 10 13441 15566 11 13249 15703 12 13120 15703 13 13237 15743 14 13461 15488 15 13405 15665 16 13169 15625 17 13249 15573 18 13333 15754 CRITICAL 19 13305 ERROR 15450 20 13361 Correct value: 15549 279344 21 13405 15453 TOTAL = 289844 328661 AVERAGE 13802.1 15650.5 NOTE: IF Column is NOT used, THEN it may be markedError as N/A.

Carried Forward Step 5.4.11 Performed by Correct value:

Date 13302.1 gpm Step 5.5.6 Performed by Date KEY This procedure, when complete, shall be retained for the life of the plant.

JPM NO: A3 PAGE 1 OF 8 NUCLEAR TRAINING DEPARTMENT JOB PERFORMANCE MEASURE TITLE: REVIEW COMPLETED SURVEILLANCE JPM NO.: A3 REVISION: 1 LOCATION: N/A

JPM NO: A3 PAGE 2 OF 8 JOB PERFORMANCE MEASURE WORKSHEET JPM

Title:

REVIEW COMPLETED SURVEILLANCE JPM No.: A3 Rev. No.: 1 Task No.: 41600, Perform Essential Cooling Water Inservice Test STP Objective: 41600, Perform an Essential Cooling Water Pump Inservice Test in accordance with 0PSP03-EW-0017, 0018, or 0019 Related K/A

Reference:

2.2.12 [3.0], Knowledge of Surveillance procedures

References:

0PSP03-EW-0018, Essential Cooling Water System Train B Testing Task Normally Completed By: RO Method of Testing: Actual Performance Location of Testing: N/A Time Critical Task: NO Alternate Path JPM: NO Validation Time: 20 minutes Required Materials (Tools/Equipment):

Calculator

JPM NO: A3 PAGE 3 OF 8 JOB PERFORMANCE MEASURE INFORMATION SHEET READ TO PERFORMER:

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

YOU ARE TO INFORM THE EXAMINER WHEN YOU HAVE COMPLETED THE TASK CAUTION: Do not operate or alter equipment configuration in the plant without proper authorization.

INITIAL CONDITIONS:

Unit 1 is at 100% power during a Train B work week. Essential Cooling Water System Train B testing per 0PSP03-EW-0018 is in progress. Essential Cooling Water Pump 1B was tested per Step 5.4 of 0PSP03-EW-0018.

INITIATING CUE:

Perform a Peer Check of the data collected per Step 5.4, 0PSP03-EW-0018, and determine if acceptance criteria are met.

THREE errors have been inserted into the surveillance, two (2) Critical and one (1) Non-Critical.

As a MINIMUM, you are to IDENTIFY both Critical errors. Editorial errors such as spelling, grammar, or punctuation are unintentional and DO NOT count.

You are to take the following into account during your review:

1) Carryover errors count as only one error (i.e., a single error that carries over from calculation to calculation or multiple line items with the same incorrect information)

- DO NOT DISCLOSE INFORMATION BELOW THIS LINE -

COMPLETION CRITERIA:

Both critical errors have been identified AND it is determined that the acceptance criteria for the test are NOT met.

JPM NO: A3 PAGE 4 OF 8 JOB PERFORMANCE MEASURE INFORMATION SHEET HANDOUTS:

• 0PSP03-EW-0018, Essential Cooling Water System Train B Testing NOTES:

• The examiner is provided a KEY of 0PSP03-EW-0018. Critical errors are identified on pages 64 and 28; non-critical error is identified on page 20.

JPM NO: A3 PAGE 5 OF 8 JOB PERFORMANCE MEASURE CHECK SHEET NOTE:

• Critical steps are identified by (C).

• Sequenced steps are identified by (S1, S2, . . .).

JPM START TIME SAT/UNSAT Performance Step: 1(C)*

Review the surveillance.

Standard:

Identifies the following ERRORS:

1) Incorrect Bay Level Correction Factor was taken from Addendum 1 in Step 5.4.6.

2)* Flows are incorrectly totaled on Data Sheet 1 3)* Step 5.4.14.3 is incorrectly marked as ECW Pump 1B Delta P is within Acceptable Range.

Comment:

• Denotes Critical Error. Error #2 causes the incorrect flow range to be used in Table 2.

Error #3 indicates that the pump is operable when it is in actuality inoperable and an LCO should be entered.

• Error #1 is not critical because it does not affect the outcome of the surveillance, only makes the pump closer to the limit (but still inoperable).

• Error #2 results in incorrect calculations for average flow on Table 1, TOTAL ECW SYSTEM FLOW (step 5.4.13), and use of the incorrect flow range (step 5.4.14.1). If the applicant considers this 2 or more errors, remind him/her of Initiating Cue Assumption #2 - this is considered only 1 error.

Cue:

• After applicant finds flow calculation error, tell him/her to continue on using the new number.

STEP CONTINUED ON NEXT PAGE

JPM NO: A3 PAGE 6 OF 8 JOB PERFORMANCE MEASURE CHECK SHEET Notes:

SAT/UNSAT Performance Step: 2 Report the error to the Unit/Shift Supervisor Standard:

Informs the Unit/Shift Supervisor of the errors found and that the acceptance criteria of the procedure are NOT met.

Comment:

Cue:

The Shift Supervisor acknowledges the report.

Notes:

- TERMINATE THE JPM -

JPM STOP TIME

JPM NO: A3 PAGE 7 OF 8 VERIFICATION OF COMPLETION Job Performance Measure: A3, REVIEW COMPLETED SURVEILLANCE Applicant's Name:

SSN:

Date Performed:

Time to Complete:

JPM Results: Sat / Unsat Evaluator: Signature __________________________

Date ____________________

JPM NO: A3 PAGE 8 OF 8 JPM - HANDOUT READ TO PERFORMER:

The evaluator will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

YOU ARE TO INFORM THE EXAMINER WHEN YOU HAVE COMPLETED THE TASK CAUTION: Do not operate or alter equipment configuration in the plant without proper authorization.

INITIAL CONDITIONS:

Unit 1 is at 100% power during a Train B work week. Essential Cooling Water System Train B testing per 0PSP03-EW-0018 is in progress. Essential Cooling Water Pump 1B was tested per Step 5.4 of 0PSP03-EW-0018.

INITIATING CUE:

Perform a Peer Check of the data collected per Step 5.4, 0PSP03-EW-0018, and determine if acceptance criteria are met.

THREE errors have been inserted into the surveillance, two (2) Critical and one (1) Non-Critical.

As a MINIMUM, you are to IDENTIFY both Critical errors. Editorial errors such as spelling, grammar, or punctuation are unintentional and DO NOT count.

You are to take the following into account during your review:

1) Carryover errors count as only one error (i.e., a single error that carries over from calculation to calculation or multiple line items with the same incorrect information)

JPM NO:A4 PAGE 1 OF 10 NUCLEAR TRAINING DEPARTMENT JOB PERFORMANCE MEASURE TITLE: DETERMINE RADIOLOGICAL REQUIREMENTS TO ENTER A HIGH RAD AREA JPM NO.: A4 REVISION: 1 LOCATION: UNIT 1 OR 2

JPM NO: A4 PAGE 2 OF 10 JOB PERFORMANCE MEASURE WORKSHEET JPM

Title:

DETERMINE RADIOLOGICAL REQUIREMENTS TO ENTER A HIGH RAD AREA JPM No.: A4 Rev. No: 1 STP Task: T49250, Place in or remove a mixed bed or cation bed demineralizer.

STP Objective: NLO49250, When directed by designated Control Room personnel, remove/place in service a CVCS mixed bed demineralizer in accordance with 0POP02-CV-0004.

Related K/ A

Reference:

G 2.3.10 [2.9/3.3] Ability to perform procedures to reduce excessive levels of radiation and guard against personnel exposure.

References:

Technical Specification 6.12.2 0POP02-CV-0005, Rev. 15, CVCS Pre-Start System Alignment 0PGP03-ZR-0051, Rev. 13, Radiological Access and Work Controls Conduct of Operations Manual, Rev. 15, Chapter 2 - step 3.5.12 Task Normally Completed By: PO Method of Testing: Simulated Location of Testing: Unit 1 or 2 RCA Time Critical Task: NO Alternate Path JPM: NO Validation Time: 15 minutes Required Materials (Tools/Equipment):

None

JPM NO: A4 PAGE 3 OF 10 JOB PERFORMANCE MEASURE INFORMATION SHEET READ TO PERFORMER:

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

YOU ARE TO INFORM THE EVALUATOR WHEN YOU HAVE COMPLETED THE TASK.

CAUTION: Do not operate or alter equipment configuration in the plant without proper authorization.

INITIAL CONDITIONS:

The unit is initially increasing power from a refueling outage. Mixed Bed Demineralizer 1(2) B was recently placed in service and subsequently removed when an increase in RCS leakage was observed. 1(2) CV-0430, the demineralizer B inlet vent valve is suspected of causing the leakage because it was recently replaced during the outage.

INITIATING CUE:

The Unit Supervisor directs you to locate the valve to assess its condition. You are to determine the valves location and all radiological requirements necessary to access the valve itself.

You are to discuss all requirements with the evaluator.

- DO NOT DISCLOSE INFORMATION BELOW THIS LINE -

COMPLETION CRITERIA:

Determines valve is in Room 244T, and discusses the radiological requirements for entering a Locked High Rad Area.

JPM NO: A4 PAGE 4 OF 10 JOB PERFORMANCE MEASURE INFORMATION SHEET HANDOUTS:

The Evaluator is provided with a the Radiological Area map handout for the MAB 60' elevation.

The same map is displayed on the wall at the entrance to the mens RCA access point. The applicant may access the wall map to determine that Room 244T is in a Locked High Rad Area. In the unlikely event that radiological conditions have changed and Room 244T is no longer indicated as a Locked High Rad Area, provide the handout (You may also provide the handout as soon as the applicant locates the correct map, if desired).

NOTES:

1) This JPM should be given as the first JPM prior to entering the RCA. It should be performed in conjunction with, and just prior to, JPM P1, Perform Channel check of RT-8038" and JPM P3, Secure Alternate Boration.

2) The JPM may be performed in its entirety outside of the RCA. The applicant most likely will enter the RCA to locate the valve access area; however, it is not required.

3) The NRC Evaluator will use RWP- and use as the WAN.

4) The applicant is expected to access all references on his/her own.

5) There is no answer KEY associated with this JPM.

6) Applicant may discuss entry requirements with Health Physics personnel, however; entry requirements should be confirmed using plant references.

JPM NO: A4 PAGE 5 OF 10 JOB PERFORMANCE MEASURE CHECK SHEET NOTE:

• Critical steps are identified by (C).

• Sequenced steps are identified by (S1, S2, . . .).

JPM START TIME SAT/UNSAT Performance Step: 1 Access references to determine valve location.

Standard:

Accesses ORACLE or the Chemical and Volume Control Procedure (0POP02-CV-0005), to determine location of valve.

Comment:

Applicant may know location from memory or may determine location using a computer either inside or outside of the RCA or 0POP02-CV-0005, Lineup 2, Page 35 of 38.

Cue:

Notes:

JPM NO: A4 PAGE 6 OF 10 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 2 (C)

Determine valve location.

Standard:

Determines 1(2) CV-0430 is in the MAB Room 244T Valve Pit.

Comment:

1) Room 244T is accessed from Room 329, Demineralizer access area on the MAB 60' elevation.

2) Room 244T is a valve pit, with a shielding plug as its access point.

Cue:

Notes:

JPM NO: A4 PAGE 7 OF 10 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 3(C)

Determine Room Radiological Conditions for Room 244T .

Standard:

Determines that Room 244T is in a Locked High Rad Area .

Comment:

1) Radiation area maps are displayed on the wall at entrance to mens RCA entry point.

2) If map on the wall indicates Room 244T is in a Locked High Rad area, then the handout will not be necessary.

Cue:

IF the map on the wall indicates Room 244T is NOT in a Locked High Rad area, then provide the Handout Copy of the map.

Notes:

JPM NO: A4 PAGE 8 OF 10 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 4 (C)*

Determine radiological entry requirements for a Locked High Rad Area (LHRA).

Standard:

Discusses the following radiological requirements for entering a LHRA (in general terms) .

1)* Personnel entering a LHRA SHALL be assigned an active RWP which permits such entry.

(Specific RWP)

2) Personnel entering a LHRA SHALL be assigned an individual monitoring device. (TLD) 3)* Personnel entering a LHRA SHALL be provided with or accompanied by one or more of the following:

• A radiation monitoring device that continuously indicates the dose rate in the area (dose rate meter), OR

• A radiation monitoring device that continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received (alarming dosimeter) ,

OR

• An individual qualified in radiation protection procedures with a radiation dose rate monitoring device, and positive control over the activities within the area. (Health Physics Technician)

Comment:

1) * - denotes critical portion of step.

2) The acceptable general term or phrase may be as short as the underlined portions above.

3) The above information may be accessed in either Technical Specification 6.12.2 or 0PGP03-ZR-0051, Radiological Acess and Work Controls or may ask Health Physics.

4) IF Health Physics is consulted, applicant should still confirm the requirements for entry into a Locked High Radiation Area using plant references.

Cue:

Notes:

- TERMINATE THE JPM -

JPM STOP TIME

JPM NO: A4 PAGE 9 OF 10 VERIFICATION OF COMPLETION Job Performance Measure: A4, DETERMINE RADIOLOGICAL REQUIREMENTS TO ENTER A HIGH RAD AREA Applicant's Name:

SSN:

Date Performed:

Time to Complete:

JPM Results:

Sat / Unsat Evaluator: Signature __________________________

Date ____________________

JPM NO: A4 PAGE 10 OF 10 JPM - STUDENT HANDOUT READ TO PERFORMER:

The evaluator will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

YOU ARE TO INFORM THE EVALUATOR WHEN YOUVE COMPLETED THE TASK.

CAUTION: Do not operate or alter equipment configuration in the plant without proper authorization.

INITIAL CONDITIONS:

The unit is initially increasing power from a refueling outage. Mixed Bed Demineralizer 1(2) B was recently placed in service and subsequently removed when an increase in RCS leakage was observed. 1(2) CV-0430, the demineralizer B inlet vent valve is suspected of causing the leakage because it was recently replaced during the outage.

INITIATING CUE:

The Unit Supervisor directs you to locate the valve to assess its condition. You are to determine the valves location and all radiological requirements necessary to access the valve itself.

You are to discuss all requirements with the evaluator.

JPM NO: A5 PAGE 1 OF 12 NUCLEAR TRAINING DEPARTMENT JOB PERFORMANCE MEASURE TITLE: PERFORM INITIAL EMERGENCY PLAN NOTIFICATIONS TO OFFSITE AGENCIES JPM NO.: A5 REVISION: 1 LOCATION: N/A

JPM NO: A5 PAGE 2 OF 12 JOB PERFORMANCE MEASURE WORKSHEET JPM

Title:

PERFORM INITIAL EMERGENCY PLAN NOTIFICATIONS TO OFFSITE AGENCIES JPM No.: A5 Rev. No.: 1 Task No.: T501000, Respond to plant transients and to actual or potential core damaging events STP Objective: EPT003.01, EO05c, d: State the primary responsibility of the following on-shift personnel for response to emergencies at STPEGS: Reactor Plant Operator and Administrative Reactor Operator.

EPT003.01, EO06: Explain the purpose of emergency use communication circuits.

Related K/A

Reference:

G 2.4.39 [3.3/3.1], Knowledge of the ROs responsibilities in emergency plan implementation.

References:

0ERP01-ZV-IN02, Rev. 10, Notifications to Offsite Agencies Task Normally Completed By: RO Method of Testing: Simulated Location of Testing: N/A Time Critical Task: YES* (portions pertaining to notification of State/County and NRC)

Alternate Path JPM: YES Validation Time: 20 mins.

Required Materials (Tools/Equipment): None

JPM NO: A5 PAGE 3 OF 12 JOB PERFORMANCE MEASURE INFORMATION SHEET READ TO PERFORMER:

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

YOU ARE TO INFORM THE EXAMINER WHEN YOU HAVE COMPLETED THE TASK CAUTION: Do not operate or alter equipment configuration in the plant without proper authorization.

INITIAL CONDITIONS:

An ALERT has just been declared in Unit 1. The Offsite Notification Message Form (Data Sheet-

1) and the NRC Event Notification Worksheet (Data Sheet -4) have been filled out and approved by the Shift Supervisor. No offsite agencies have been notified of the event at this time.

INITIATING CUE:

You are directed to perform ALL OFFSITE notifications associated with the ALERT using the data sheets provided in accordance with 0ERP01-ZV-IN02. Portions of this JPM are time critical.

- DO NOT DISCLOSE INFORMATION BELOW THIS LINE -

COMPLETION CRITERIA:

The Applicant notifies State/County officials within 15 minutes, then notifies the NRC within 60 minutes of the event declaration using applicable forms.

JPM NO: A5 PAGE 4 OF 12 JOB PERFORMANCE MEASURE INFORMATION SHEET (Cont.)

HANDOUTS:

• Working copy of 0ERP01-ZV-IN02, Notifications to Offsite Agencies.

• Marked Up Copy of Data Sheet 1, Offsite Agency Notification Message Form and Data Sheet 4, NRC Event Notification Worksheet .

NOTES:

1) The State/County must be notified within 15 minutes and the NRC within 60 minutes of the EVENT declaration. The time critical portions of this JPM begin when the first event sheet (Data Sheet -1) is handed to the applicant.

2) The Event time and date have intentionally been left blank on the filled out copies of Data Sheet -1 and Data Sheet -4. This is due to the fact that the Event time is directly tied to the 15 and 60 minute notification clocks, which do not start until the Data Sheets are handed to the applicant.

3) The intent of this JPM is for the applicant to make the correct and timely notifications in accordance with 0ERP01-ZV-IN02, Notifications to Offsite Agencies. The intent is NOT to have the applicant read the same forms over and over again. For time considerations acknowledge the notification promptly and do not allow applicant to read the entire content of each message after the initial notification to the respective agency.

JPM NO: A5 PAGE 5 OF 12 JOB PERFORMANCE MEASURE CHECK SHEET NOTE:

• Critical steps are identified by (C).

• Sequenced steps are identified by (S1, S2, . . .).

JPM START TIME SAT/UNSAT Performance Step: 1 Obtain the procedure.

Standard:

Obtains copy of 0ERP01-ZV-IN02 Comment:

1) In accordance with 0ERP01-ZV-IN01, the State/County must be notified within 15 minutes of the initial Classification.

2) Start the 15 minute and 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> clocks when the data sheet is provided and cue below is given.

Cue:

1) Provide the applicant with the Handout Copy of 0ERP01-ZV-IN02, and marked up copies of Offsite Notification Message Form (Data Sheet -1), and NRC Event Notification Worksheet (Data Sheet -4).

2) When the data sheets are handed to the applicant, inform him/her that the time requirement for notification has commenced.

Notes:

SAT/UNSAT Performance Step: 2(C)

JPM NO: A5 PAGE 6 OF 12 JOB PERFORMANCE MEASURE CHECK SHEET Notify state and county officials within 15 minutes.

Standard:

Reviews Data Sheet -1 and notifies the Matagorda County Sheriff and DPS-Pierce within 15 minutes by console ringdown lines or by calling the applicable telephone numbers and reads the Notification Sheet.

Comment:

1) Data Sheet -3 , Offsite Agencies Log, provides telephone numbers of all in state notifications, and should be used by the applicant.

2) The applicant should transition to section 5.2 for NRC notification.

Cue:

• When the call is made, inform the applicant that BOTH parties have answered the phone.

• If asked, inform the applicant that BOTH parties are ready to receive the message (they have their notification forms ready).

• (When contacted by applicant) listen to the message, acknowledge it, and direct the applicant to keep the agency updated as required.

• When applicant mentions faxing Data Sheet -1 to the agencies, as Unit Supervisor inform him/her that the Secondary RO will take care of all faxes.

Notes:

When the ringdown line is used, BOTH the Sheriffs office and DPS-Pierce will answer the phone.

• Completion of this step within 15 minutes of JPM Start Time satisfies the Time Critical requirement for notification of State/County officials.

JPM NO: A5 PAGE 7 OF 12 JOB PERFORMANCE MEASURE CHECK SHEET (cont'd)

SAT/UNSAT Performance Step: 3 Review Data Sheet -4 for NRC notification.

Standard:

Reviews Data Sheet -4 for completeness and accuracy.

Comment:

Since this event does not involve a radiological event, page 2 of Data Sheet-4 is not filled out.

Cue:

Notes:

JPM NO: A5 PAGE 8 OF 12 JOB PERFORMANCE MEASURE CHECK SHEET (cont'd)

SAT/UNSAT Performance Step: 4(C)

Notify NRC Operations Center.

Standard:

Attempts use of ENS phone to notify NRC Operations Center within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of event declaration.

ENS phone does not work and applicant uses appropriate outside phone line to contact NRC.

Comment:

1) If conducting this JPM in the Control Room, DO NOT allow applicant to pick up the ENS phone.

2) The NRC Resident Inspector may be notified before the NRC Operations Center by the applicant.

Cue:

• NRC ENS phone line number is not working.

• When applicant uses appropriate outside phone line, NRC representative acknowledges the Event Notification. The NRC requests another update in ten minutes to establish a continuous communication line.

• When the applicant mentions activating ERDS, as Unit Supervisor, inform him/her that the STA will activate ERDS.

Notes:

• Completion of this step within 60 minutes of JPM Start Time satisfies the Time Critical requirement for notification of NRC.

JPM NO: A5 PAGE 9 OF 12 JOB PERFORMANCE MEASURE CHECK SHEET (cont'd)

SAT/UNSAT Performance Step: 5 Inform NRC Resident Inspector.

Standard:

Informs NRC Resident Inspector of events in progress.

Comment:

1) Informing the NRC Resident Inspector is not an off-site notification, but is commonly done at this time.

2) The NRC Resident Inspector may be notified before the NRC Operations Center by the applicant.

3) The applicant should transition back to procedure step 5.1.2.4 for remaining notifications.

Cue:

The NRC Resident inspector acknowledges the events in progress, if notified.

Notes:

JPM NO: A5 PAGE 10 OF 12 JOB PERFORMANCE MEASURE CHECK SHEET (cont'd)

SAT/UNSAT Performance Step: 6 Make remaining notifications.

Standard:

Notifies, or mentions having to notify the following of events in progress:

• Bureau of Radiation Control (BRC)

• Unaffected Control Room (not off-site)

• H.L & P System Operations Comment:

During this particular event, there will not be an unaffected Control Room. (both Units will lose power and have a reactor trip.)

Cue:

All notified agencies/groups acknowledge.

Notes:

- TERMINATE THE JPM -

JPM STOP TIME

JPM NO: A5 PAGE 11 OF 12 VERIFICATION OF COMPLETION Job Performance Measure: A5, PERFORM INITIAL EMERGENCY PLAN NOTIFICATIONS TO OFFSITE AGENCIES Applicant's Name:

SSN:

Date Performed:

Time to Complete:

JPM Results: Sat / Unsat Evaluator: Signature:

Date:

JPM NO: A5 PAGE 12 OF 12 JPM - HANDOUT READ TO PERFORMER:

The evaluator will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

YOU ARE TO INFORM THE EXAMINER WHEN YOU HAVE COMPLETED THE TASK CAUTION: Do not operate or alter equipment configuration in the plant without proper authorization.

INITIAL CONDITIONS:

An ALERT has just been declared in Unit 1. The Offsite Notification Message Form (Data Sheet-

1) and the NRC Event Notification Worksheet (Data Sheet -4) have been filled out and approved by the Shift Supervisor. No offsite agencies have been notified of the event at this time.

INITIATING CUE:

You are directed to perform ALL OFFSITE notifications associated with the ALERT using the data sheets provided in accordance with 0ERP01-ZV-IN02. Portions of this JPM are time critical.

SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION D0527 O:\PROC\OFFICE97\PSP03\0RC0006.07x Rev. 7 Page 1 of 16 Effective Date: 02/19/98 Print Time / Date: 4:01 PM 07/03/01 0PSP03-RC-0006 Reactor Coolant Inventory Quality Safety-Related Usage: REFERENCED Effective Date: 02/19/98 K. P. Mulligan J. C. Heil Crew 2D Operations PREPARER TECHNICAL USER COGNIZANT DEPT.

Table of Contents Page

1.0 Purpose and Scope

........................................................................................................................... 2 2.0 Responsibilities ............................................................................................................................... 2 3.0 Precautions and Notes...................................................................................................................... 2 KEY 4.0 Prerequisites .................................................................................................................................... 3 5.0 Procedure......................................................................................................................................... 4 6.0 Acceptance Criteria....................................................................................................................... 11 7.0 References ..................................................................................................................................... 11 8.0 Support Documents ........................................................................................................................ 12 Addendum 1, Temperature Change Conversion Factors For Tavg/Tcold 500 - 600°F....................... 13 Data Sheet 1, Leakage Rate (Sample)............................................................................................ 14

0PSP03-RC-0006 Rev. 7 Page 2 of 16 Reactor Coolant Inventory

1.0 Purpose and Scope

1.1 Provide instructions for performing a Reactor Coolant System Water Inventory Balance to determine RCS leakage and satisfy the surveillance requirements of Technical Specification Section 4.4.6.2.1.c [ITS SR 3.4.14.1].

1.2 The calculations in this procedure assume the plant is in Modes 1, 2, 3, or 4 and plant conditions are stable. Performance of an inventory balance at conditions other than previously stated may yield unreliable results.

1.3 Provide a means for updating the Plant Computer Sump Level Monitoring System identified leakage value.

2.0 Responsibilities 2.1 2.2 2.3 KEY This procedure is performed by Plant Operations.

The following personnel shall review this test:

• Test Coordinator Shift Supervisor Division Surveillance Coordinator After completion of test, routing is per 0PGP03-ZE-0004 (Plant Surveillance Program), and 0PGP03-ZA-0055 (Plant Surveillance Scheduling).

3.0 Precautions and Notes 3.1 IF the computer program is used for data calculation, THEN the following applies:

3.1.1 The computer generated form may be substituted for Data Sheet 1, Leakage Rate, Page 2 of 2.

3.1.2 A second qualified individual SHALL sign on the PPDS cover sheet where indicated, to verify the correct transcription of data.

3.2 IF a manual calculation is performed, THEN a second qualified individual SHALL sign on the PPDS cover sheet where indicated, to verify the calculation is correct.

3.3 In Modes 1 or 2, Reactor Power SHALL be maintained in a 1% band.

0PSP03-RC-0006 Rev. 7 Page 3 of 16 Reactor Coolant Inventory Initials 3.4 In Modes 1, 2, or 3, a minimum of one RCP in operation is required.

3.5 IF performing to obtain an Identified OR Unidentified Leakage Rate, THEN VERIFY RCDT level is being maintained between 20 and 70%.

3.6 Diversion of letdown to Recycle Holdup Tanks will invalidate the test.

3.7 IF determining an Identified OR Unidentified Leak Rate, THEN the following will invalidate this test:

3.7.1 Draining of the RCDT or PRT 3.7.2 Venting, draining, or sampling any portion of the RCS, CVCS, or KEY interconnected piping 3.7.3 RCS sampling may be allowed to recirculate to the VCT, however, RCS Coolant SHALL NOT be removed from the RCS during this test.

3.7.4 Opening RC-FV-3650 (PRT SPRAY ISOL) or the opening of RC-FV-3651 (RMW to PRT/RCP standpipe) with known leakage across RC-FV-3650 (Reference 7.4.2).

3.8 Failure to meet the acceptance criteria of the test may require entry into LCO Action Statement 3.4.6.2 [ITS 3.4.14 Condition A].

3.9 Any changes to this procedure requires a review of the computer program for adherence to Software Quality Assurance Standards.

3.10 Operation of the HHSI or LHSI pumps may invalidate the test due to potential relief valve leakage into the PRT (Reference 7.4.2).

4.0 Prerequisites 4.1 Pressurizer/Reactor Coolant System pressure is approximately 400 psig OR 2235 psig. JD 4.2 Record the following on PPDS:

• Unit Number JD

• Reason for Test JD

0PSP03-RC-0006 Rev. 7 Page 4 of 16 Reactor Coolant Inventory Initials 5.0 Procedure 5.1 VERIFY the prerequisites are complete. JD 5.2 RECORD START data and instrumentation on Data Sheet 1, Leakage Rate. JD NOTE This test should be performed over a two hour period unless steady conditions cannot be maintained. A test period of one hour is sufficient to satisfy the surveillance test. The test period may be specified at the discretion of the Shift Supervisor.

KEY 5.3 WHEN the determined test period has elapsed, THEN perform the following:

5.3.1 VERIFY Stop time Reactor Power is within 1% of Start time Reactor Power. JD 5.3.2 VERIFY Stop time PRZR pressure is within 10 psig of Start time PRZR pressure. JD 5.3.3 IF Reactor Power and Pressure data are within limits above, THEN record STOP data on Data Sheet 1, Leakage Rate. JD 5.3.4 IF Reactor Power and Pressure data were NOT within limits above, THEN do NOT record stop data. N/A 5.3.5 WHEN Reactor Power and Pressure stabilize within limits, THEN return to Step 5.2 and obtain new data. N/A 5.4 DETERMINE PRT level in gallons from percent using the Plant Curve Book, Figure 10.8, Pzr Relief Tank. JD 5.5 DETERMINE RCDT level in gallons from percent using the Plant Curve Book, Figure 10.9, RC Drain Tank. JD 5.6 Pressurizer level correction factor calculation:

68.3 + 0.023 (2235 - 2246 psig) = 68.047 gal/% JD Stop Press

0PSP03-RC-0006 Rev. 7 Page 5 of 16 Reactor Coolant Inventory Initials 5.7 Temperature correction factor calculation:

5.7.1 IF pressure is approximately 400 psig AND Stop Temperature is between 240 and 4000F, THEN PERFORM the following:

32 + 0.147 ( N/A °F - 240) = N/A gal/°F Stop Temp N/A Error carried forward Calculation error carried forward -

5.7.2 IF pressure is approximately 2235 psig AND Stop Temperature is from Data Sheet 1 - Value Value should be 184.54 between 500 and 600°F, THEN use Addendum 1. JD should be -41.7 5.8 GROSS Leakage Rate calculation:

KEY 5.8.1 Sum changes in VCT, PRZR, TEMP and Makeup.

41.7 gal + 144.94 gal + 18.34 gal + 63 gal = 267.98 gal VCT PRZR TEMP Makeup Total 5.8.2 Divide the sum by the elapsed time:

267.98 gal ÷ 137 min = 1.96 gpm Total Time GROSS Leakage Rate Calculation error carried forward -

Value should be 1.35

0PSP03-RC-0006 Rev. 7 Page 6 of 16 Reactor Coolant Inventory Initials NOTE Steps 5.9, 5.10, and 5.11 should be performed unless instrumentation problems exist or as directed by the Shift Supervisor.

5.9 Identified Leakage Rate calculation:

5.9.1 Sum data from the PRT and RCDT:

0 gal + 99.7 gal = 99.7 gal PRT RCDT Total KEY 5.9.2 Divide the sum by the elapsed time:

99.7 gal ÷ 137 min = 0.73 gpm Total Time Contained Leak Rate 5.9.3 OBTAIN latest calculated Primary - to - Secondary Leakage from Chemical Analysis per 0PCP09-ZR-0005. JD 5.9.4 Divide results by 1440 to determine leak rate in gallons per minute.

13 gpd ÷ (1440 min/day) = 0.01 gpm JD Primary - to - Secondary Leakage Rate 5.9.5 ENTER other Identified Leakage that is not directed to the PRT or RCDT or is not Primary - to - Secondary Leakage. N/A SOURCES LEAKAGE N/A N/A gpm Other Identified Leakage Other Leakage Rate

0PSP03-RC-0006 Rev. 7 Page 7 of 16 Reactor Coolant Inventory Initials NOTE IDENTIFIED LEAKAGE Rate Acceptance Criteria is less than or equal to 10 gpm.

AC 5.10 DETERMINE IDENTIFIED LEAKAGE Rate by summing Contained, Primary - to - Secondary and Other Leakage Rates.

0.73 gpm + 0.01 gpm + 0 gpm = 0.74 gpm (5.9.2) (5.9.4) (5.9.5) IDENTIFIED LEAKAGE RATE AC 5.11 KEY 1.96 gpm - 0.74 gpm =

(5.8.2) (5.10)

Error carried forward from Step 5.8.2 -

NOTE UNIDENTIFIED LEAKAGE Rate Acceptance Criteria is less than or equal to 1 gpm.

DETERMINE UNIDENTIFIED LEAKAGE Rate by subtracting IDENTIFIED LEAKAGE Rate from GROSS Leakage Rate.

1.22 gpm UNIDENTIFIED LEAKAGE Rate Calculation error carried forward -

Value should be 1.35 Value should be 0.61

0PSP03-RC-0006 Rev. 7 Page 8 of 16 Reactor Coolant Inventory Initials NOTE Mark Section 5.12 "N/A" IF Sump Level Monitoring is NOT available on the Proteus Plant Computer.

5.12 IF this test is being performed due to a high leakage indicated on the Proteus Sump Level Monitoring System (SLM) AND the RCS leak rate is normal, THEN perform the following:

5.12.1 Obtain Reactor Coolant Pressure Boundary (RCPB) sump monitor accessible constants display as follows:

KEY 5.12.1.1 SELECT "MISC FUNCT" N/A 5.12.1.2 ENTER "16" on display and PRESS "EXECUTE" N/A 5.12.2 ENTER the value of ZERO (0.0) in the normal and secondary sump IDENTIFIED INFLOW and PRESS "EXECUTE" N/A 5.12.3 WHEN one hour has elapsed, THEN obtain the RCPB LEAK DETECTION STATUS display as follows:

5.12.3.1 SELECT "SYSTEM MENU" N/A 5.12.3.2 ENTER "RC" on display and PRESS "EXECUTE" N/A 5.12.3.3 SELECT "DISPLAY LIST" N/A 5.12.3.4 ENTER "66"("65" Unit 2) on display and PRESS "EXECUTE" N/A 5.12.4 Obtain the normal and secondary CALCULATED INFLOW from the RCPB LEAK DETECTION STATUS display by:

5.12.4.1 Using the "NEXT FIELD" Button to place the cursor on each inflow value and PRESS "PICK" N/A 5.12.4.2 Document the normal and secondary CALCULATED INFLOW values

• Normal Sump Calculated Inflow N/A gpm N/A

• Secondary Sump Calculated Inflow N/A gpm N/A 5.12.5 Obtain the RCPB sump monitor accessible constants display as follows:

0PSP03-RC-0006 Rev. 7 Page 9 of 16 Reactor Coolant Inventory 5.12.5.1 SELECT "MISC FUNCT" N/A 5.12.5.2 ENTER "16" on display and PRESS "EXECUTE" N/A 5.12.6 ENTER the CALCULATED INFLOW values from Step 5.12.4.2 for the normal and secondary IDENTIFIED INFLOW and press "EXECUTE" N/A 5.12.7 IF the Proteus RCPB Sump Monitoring System IDENTIFIED INFLOWS were changed per this procedure, THEN ENTER the new values.

• Normal Identified Inflow N/A gpm N/A KEY

• Secondary Identified Inflow N/A gpm N/A 5.12.8 ENTER the IDENTIFIED INFLOW values in the Proteus Accessible Constants Log located in the Plant Computer Room. N/A NOTE Mark Section 5.13 "N/A" IF Sump Level Monitoring is NOT available on the ICS Plant Computer.

5.13 IF this test is being performed due to a high leakage indicated on the ICS Plant Computer Sump Level monitoring program AND the RCS leak rate is normal, THEN perform the following on the computer:

5.13.1 Access the Point Information display.

5.13.2 Remove the desired point from Scan and enter the value of ZERO (0.0) for the following constants:

• K7801 Cntmnt Nrm Sump Ident Inflow N/A

• K7802 Cntmnt SCD Sump Ident Inflow N/A

0PSP03-RC-0006 Rev. 7 Page 10 of 16 Reactor Coolant Inventory 5.13.3 WHEN one hour has elapsed, THEN obtain the calculated inflow values from RC-012 RCPB LEAK DETECTION STATUS display and record the values below:

• NORMAL SUMP CALCULATED INFLOW N/A gpm

• SECONDARY SUMP CALCULATED INFLOW N/A gpm 5.13.4 Enter the value for NORMAL SUMP CALCULATED INFLOW from Step 5.13.3 into K7801 Cntmnt Nrm Sump Ident Inflow and return the point to Scan. N/A 5.13.5 Enter the value from SECONDARY SUMP CALCULATED INFLOW from Step 5.13.3 into K7802 Cntmnt SCD Sump Ident Inflow and KEY return the point to Scan. N/A 5.13.6 Enter the new identified inflow values for K7801 and K7802 into the Plant Computer Accessible Constants Log. N/A 5.14 ENSURE all performers and verifiers sign/initial on Data Sheet 1. JD 5.15 DETERMINE test results by using Acceptance Criteria, Section 6.0 AND sign Test Performed by. JD 5.16 NOTIFY Shift Supervisor of test results and completion. JD

0PSP03-RC-0006 Rev. 7 Page 11 of 16 Reactor Coolant Inventory 6.0 Acceptance Criteria NOTE WHEN actual UNIDENTIFIED LEAKAGE is less than 0.2 gpm, THEN calculated values between -0.2 and +0.2 gpm may be expected due to instrument drift and are acceptable for surveillance credit.

6.1 Leakage rates as follows:

• GROSS Leakage Rate less than 1.0 gpm. (Step 5.8.2)

OR KEY

• IDENTIFIED LEAKAGE does not exceed 10.0 gpm. (Step 5.10)

AND

• UNIDENTIFIED LEAKAGE does not exceed 1.0 gpm. (Step 5.11) 7.0 References 7.1 Technical Specifications 7.1.1 3.4.6.2 [ITS 3.4.14]

7.1.2 4.4.6.2.1.c [ITS SR 3.4.14.1]

7.2 Regulatory Guides and Standards None 7.3 UFSAR None 7.4 Commitments 7.4.1 ST-AE-HL-91335, Inspection Report 87-37, Item 3f 7.4.2 CR# 95-239 (IEN 94-46) 7.5 Technical Standards and Manuals None

0PSP03-RC-0006 Rev. 7 Page 12 of 16 Reactor Coolant Inventory 7.6 Drawings None 7.7 STPEGS Procedures and Policies 7.7.1 0PCP09-ZR-0005, Determination of Primary to Secondary Leak Rate 7.7.2 Plant Curve Book 8.0 Support Documents 8.1 Addendum 1, Temperature Change Conversion Factors For Tavg/Tcold 500 - 600°F KEY 8.2 Data Sheet 1, Leakage Rate

0PSP03-RC-0006 Rev. 7 Page 13 of 16 Reactor Coolant Inventory Addendum 1 Temperature Change Conversion Factors For Tavg/Tcold 500 Page 1 of 1

- 600°F TEMP CONVERSION TEMP CONVERSION TEMP CONVERSION TEMP CONVERSION FACTOR FACTOR FACTOR FACTOR 500 46.3 526 52.4 552 60.8 578 72.5 501 46.5 527 52.7 553 60.9 579 73.0 502 46.7 528 52.9 554 61.6 580 73.7 503 46.8 529 53.4 555 61.8 581 74.3 504 47.0 530 53.4 556 62.3 582 74.8 KEY 505 47.4 531 53.9 557 62.6 583 75.4 506 47.6 532 54.1 558 63.1 584 76.1 507 47.7 533 54.4 559 63.4 585 76.4 508 47.9 534 54.8 560 63.9 586 77.3 509 48.3 535 54.9 561 64.2 587 78.0 510 48.4 536 55.5 562 64.7 588 78.6 511 48.6 537 55.6 563 65.3 589 79.2 512 48.9 538 55.9 564 65.6 590 79.8 513 49.1 539 56.3 565 66.1 591 80.6 514 49.5 540 56.4 566 66.6 592 81.3 515 49.6 541 57.0 567 66.8 593 81.9 516 49.8 542 57.3 568 67.5 594 82.9 517 50.2 543 57.4 569 67.8 595 83.5 518 50.3 544 58.0 570 68.3 596 84.2 519 50.5 545 58.1 571 69.0 597 85.0 520 50.8 546 58.6 572 69.3 598 85.8 521 51.2 547 59.0 573 69.8 599 86.8 522 51.3 548 59.3 574 70.4 600 87.5 523 51.7 549 59.4 575 70.9 524 51.9 550 60.2 576 71.4 525 52.2 551 60.3 577 72.1 This procedure, when complete, SHALL be retained for five years.

0PSP03-RC-0006 Rev. 7 Page 14 of 16 Reactor Coolant Inventory Data Sheet 1 Leakage Rate (Sample) Page 1 of 2 Procedure Performance Data Sheet Unit Number: Test Interval: Technical Specifications Plant MODE:

Reference:

ONE 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 4.4.6.2.1.c [ITS SR 3.4.14.1] 1,2,3, or 4 Reason for Test:

¨ Periodic Surveillance Test x For Surveillance Credit Test Results:

Technical Specifications Allowable Value Exceeded: ¨ NO x YES (explain in Remarks)

¨ Acceptable (All AS LEFT data within tolerance) x Unacceptable (Any AS LEFT data NOT within tolerance) (explain in Remarks)

KEY Test Performed by: John Doe 5/21/01 0730 Reactor Operator Date Time Data Transcription or N/A Calculations Verified By: Reactor Operator Date Time Critical Error: The Plant Ops Review: calculations should have been Potential Reportable Occurrence: ¨ Yes ¨ No LCO Action Statement Entered? ¨ Yes ¨ No verified and a signature, time and date entered Reviewed By:

Shift Supervisor Date Time Operations Surveillance Coordinator Review:

Reviewed By:

Operations Surveillance Coordinator Date Time Performers and Verifiers:

Name (Print) Signature Initials John Doe John Doe JD Remarks: Gross leakage is greater than 1.0 gpm. Unidentified leakage has exceeded the Tech Spec limit of 1.0 gpm.

0PSP03-RC-0006 Rev. 7 Page 16 of 16 Reactor Coolant Inventory Critical Error: (STOP - START)CF was used Data Sheet 1 Leakage Rate to calculate (Sample)VCT level change in gallons Page 2instead of 2 of (START - STOP)CF.

NOTECorrect calculation is (48.55-49.78)33.9 = -41.7 Computer generated data should be used whenever possible. However, in all cases the same instrument must be used for STOP data that was used for START data.

Step 5.2 Step 5.3 Correction Instrument Start Stop Factor (CF) Calculation Result 0500 0717 137 KEY Time N/A N/A STOP - START min.

Reactor Power 0.85 < 1.0%

NE0041 100.91  % 100.06  % N/A STOP - START SAT/UNSAT PRZR/RCS QDPS Pressure PT0456 2248 psig 2246 psig N/A STOP - START 2 < 10 psig SAT/UNSAT VCT L0112 or 48.55  % 49.78  % 33.9 (START - STOP)CF 41.7 gal Level _______

PRZR Level LE0465 55.34  % 53.21  % 68.047 (START - STOP)CF 144.94 gal (1)

RCS TA0412A 589.7 °F 589.93 °F 79.76 (STOP - START)CF 18.34 gal Tavg/Tcold (2 or 3)

Makeup FQI-0111B 43602 gal 43665 gal N/A STOP - START 63 gal Totalizer PRT L0485 or 71.1  % 71.1  %

N/A STOP - START 0 gal Level _______

11544.4 gal 11544.4 gal RCDT 40  % 66  %

LI-4901 N/A STOP - START 99.7 gal Level 148.7 gal 248.4 gal GROSS ___________ gpm - IDENTIFIED ___________ gpm = UNIDENTIFIED ___________ gpm (4) (5)

IDENTIFIED includes (Primary - to - Secondary) ___________ gpm and (Other) ___________ gpm (6) (7)

(1) Step 5.6 (2) Step 5.7.1 (3) Step 5.7.2 (4) Step 5.8.2 (5) Step 5.10 (6) Step 5.9.4 (7) Step 5.9.5 NON-Critical Error: Data in these blanks is expected to be filled in This DATA SHEET, when completed, shall be retained for 5 years.

JPM NO: A6 PAGE 1 OF 9 NUCLEAR TRAINING DEPARTMENT JOB PERFORMANCE MEASURE TITLE: REVIEW RCS INVENTORY AND DETERMINE TECH SPEC APPLICABILITY JPM NO.: A6 REVISION: 1 LOCATION: N/A

JPM NO: A6 PAGE 2 OF 9 JOB PERFORMANCE MEASURE WORKSHEET JPM

Title:

REVIEW RCS INVENTORY AND DETERMINE TECH SPEC APPLICABILITY JPM No.: A6 Rev. No.: 1 Task No.: 10300, Interpret Technical Specifications.

STP Objective: 10300, Given that a condition exists requiring entry into a Technical Specification action statement, interpret Technical Specifications accurately, such that plant activities occur safely and smoothly, and that contacting superiors for advice is unnecessary.

Related K/A

Reference:

2.1.7 [4.4] Ability to evaluate plant performance and make operational judgements based on operating characteristics, reactor behavior, and instrument response.

References:

0PSP03-RC-0006, Rev. 7, Reactor Coolant Inventory South Texas Project Technical Specifications Task Normally Completed By: SRO Method of Testing: Actual Performance Location of Testing: N/A Time Critical Task: NO Alternate Path JPM: NO Validation Time: 25 minutes Required Materials (Tools/Equipment):

Calculator Technical Specifications

JPM NO: A6 PAGE 3 OF 9 JOB PERFORMANCE MEASURE INFORMATION SHEET READ TO PERFORMER:

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

YOU ARE TO INFORM THE EXAMINER WHEN YOU HAVE COMPLETED THE TASK CAUTION: Do not operate or alter equipment configuration in the plant without proper authorization.

INITIAL CONDITIONS:

Unit 1 is at 100% steady state power with indications of increased RCS leakage.

0PSP03-RC-0006, Reactor Coolant Inventory, has just been completed using a manual calculation and indicates a Technical Specification Allowable Value has been exceeded.

INITIATING CUE:

You are the Unit Supervisor and are to complete the Plant Operations Review of the completed surveillance, including Technical Specification applicability.

THREE errors have been inserted into the surveillance, two (2) Critical and one (1) Non-Critical.

As a MINIMUM, you are to IDENTIFY both Critical errors. Editorial errors such as spelling, grammar, or punctuation are unintentional and DO NOT count.

You are to take the following into account during your review:

1) There are NO intended errors in the Instrument, Start or Stop columns of Data Sheet 1.

2) Carryover errors count as only one error (i.e., a single error that carries over from calculation to calculation or multiple line items with the same incorrect information)

- DO NOT DISCLOSE INFORMATION BELOW THIS LINE -

COMPLETION CRITERIA:

BOTH critical errors have been identified AND it is determined that Technical Specification LCO entry is NOT required.

JPM NO: A6 PAGE 4 OF 9 JOB PERFORMANCE MEASURE INFORMATION SHEET CONT HANDOUTS:

Handout Copy of the completed surveillance.

NOTES:

1) A completed Answer KEY is provided for the Evaluator. The Key contains the same errors as the handout. The location of the errors will be highlighted and described on the evaluator copy. Do Not Hand to the Applicant

JPM NO: A6 PAGE 5 OF 9 JOB PERFORMANCE MEASURE CHECK SHEET NOTE:

• Critical steps are identified by (C).

• Sequenced steps are identified by (S1, S2, . . .).

JPM START TIME SAT/UNSAT Performance Step: 1 (C)*

Review the completed surveillance.

Standard:

Identifies the following ERRORS:

1)* VCT level change calculation is reversed (STOP-START was used instead of START-STOP) 2)* Data Transcription or Calculations Verified By signature block is N/Ad instead of being signed.

3) Data entry points at the bottom of page 2 of Data Sheet 1 are blank instead of being filled in.

Comment:

1)

• Denotes Critical Error. Error #1 potentially causes an LCO entry and possible plant shutdown. Error #2 is a requirement of procedure step 3.2 (if a manual calculation is performed) designed to prevent this situation from occurring.

2) Error #3 is not considered critical because it does not affect the outcome of the surveillance, only makes the surveillance easier to reconstruct once vaulted.

3) Error #1 results in incorrect calculations for GROSS Leakage rate (steps 5.8.1 and 5.8.2) and UNIDENTIFIED LEAKAGE Rate (step 5.11). If the applicant considers this 2 or more errors, remind him/her of Initiating Cue assumption #2 - this is considered only 1 error.

STEP CONTINUED ON NEXT PAGE

JPM NO: A6 PAGE 6 OF 9 JOB PERFORMANCE MEASURE CHECK SHEET Cue:

Notes:

JPM NO: A6 PAGE 7 OF 9 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 2 (C)

Determine Technical Specification applicability.

Standard:

Determines that the Acceptance Criteria of the surveillance are NOT met (GROSS Leakage Rate is >1 gpm), however Technical Specification limits have NOT been exceeded and LCO entry is NOT required.

Comment:

This surveillance is unique in that the Acceptance Criteria may not be met, yet an entry into a Technical Specification LCO may not be required.

Cue:

Notes:

Technical Specification limits are as follows:

• No Pressure Boundary leakage

• 1 gpm Unidentified Leakage

• 150 gpd primary-to-secondary leakage through any one steam generator

• 10 gpm Identified Leakage

- TERMINATE THE JPM -

JPM STOP TIME

JPM NO: A6 PAGE 8 OF 9 VERIFICATION OF COMPLETION Job Performance Measure: A6, REVIEW RCS INVENTORY AND DETERMINE TECH SPEC APPLICABILITY Applicant's Name:

SSN:

Date Performed:

Time to Complete:

JPM Results: Sat / Unsat Evaluator: Signature __________________________

Date ____________________

JPM NO: A6 PAGE 9 OF 9 JPM - HANDOUT READ TO PERFORMER:

The evaluator will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

YOU ARE TO INFORM THE EXAMINER WHEN YOU HAVE COMPLETED THE TASK CAUTION: Do not operate or alter equipment configuration in the plant without proper authorization.

INITIAL CONDITIONS:

Unit 1 is at 100% steady state power with indications of increased RCS leakage.

0PSP03-RC-0006, Reactor Coolant Inventory, has just been completed using a manual calculation and indicates a Technical Specification Allowable Value has been exceeded.

INITIATING CUE:

You are the Unit Supervisor and are to complete the Plant Operations Review of the completed surveillance, including Technical Specification applicability.

THREE errors have been inserted into the surveillance, two (2) Critical and one (1) Non-Critical.

As a MINIMUM, you are to IDENTIFY both Critical errors. Editorial errors such as spelling, grammar, or punctuation are unintentional and DO NOT count.

You are to take the following into account during your review:

5) There are NO intended errors in the Instrument, Start or Stop columns of Data Sheet 1.

6) Carryover errors count as only one error (i.e., a single error that carries over from calculation to calculation or multiple line items with the same incorrect information)

Logsheet 1 Modes 1, 2, 3 and 4 Control Room Logsheet Page 1 of 35 CR UNIT: 1 KEY DATE: 9/17/01 0000-0200 SHIFT KEY 1200-1400 SHIFT Start Time: 0010 Mode: 1 Finish Time: 0140 Start Time: Mode: Finish Time:

1) Currently batching acid to Boric acid tank 1A.

Additionally, this remark should include comments to the effect of "Due to the batching lineup the tank is isolated and is unavailable as a reactivity source ."

Shaded areas on pages 10, 12, and 13 of 35 represent the errors inserted and are indicative of parameters which have exceeded their associated limits.

A note/remark should appear on the cover page which includes the out of specification reading/parameter, the associated limit exceeded, and corrective actions taken or in progress. In addition, the parameter would normally be circled in red with a number corresponding to the note on the cover page.

Temporary Logs: YES___ NO X Temporary Logs: YES___ NO___

IF Yes, Number of Temporary Logsheets: N/A IF Yes, Number of Temporary Logsheets:______

START N/A hrs. STOP N/A hrs. (Ref. 6.8.18 START hrs. STOP hrs. (Ref. 6.8.18)

Note change to temporary log status in Remarks Section. Note change to temporary log status in Remarks Section.

OPERATOR: Eli Whitney OPERATOR:__________________________________

SUPERVISOR: __________ SUPERVISOR:________________________________

KEY PLANT OPS SURVEILLANCE COORDINATOR:

KEY

Logsheet 1 Modes 1, 2, 3 and 4 Control Room Logsheet Page 10 of 35 UNIT: 1 KEY PARAMETER DATE:

PRT LEVEL 9/17/01 LOCATION CP-004 INSTR LI-0670 00-02 73 12-14 LIMIT (UNIT 1) 65-75%

(UNIT 2) 70-79%

TECH SPEC N/A MODE ALL KEY NOTE PRT PRESS PI-0669 4 < 6 PSIG RCDT LEVEL LI-4901 52 8-92%

RCDT PRESS PI-4900 3 < 6 PSIG RCDT TEMP TI-4902 85 < 187EF RCB SEC SUMP CP-004 LI-7811 64 N/A 3.3.3.6 1,2,3 LEVEL  %

RCB NORM. LI-7812 30 3.4.6.2 1,2,3,4 SUMP LEVEL NORM SUMP FQI- 428323 N/A DISCHARGE 7823 GAL BAT A LVL LI-0103 15,000 1 N/A TRM 1,2,3,4 (1) ONLY APPLICABLE IF BAT(S) IS GAL 3.1.2.6 DESIGNATED BORON SOURCE.

BAT A TEMP. TI-0104 112 1 $ 65EF (2) SUM OF OPERABLE BAT TANKS.

(1)

BAT B TEMP. TI-0107 95 $ 65EF (1)

BAT B LVL LI-0105 28,000 N/A GAL BAT VOLUME N/A CALC 43,000 $ 27,000 GAL (2) (1)

KEY Non-Critical Error:

KEY

Logsheet 1 Modes 1, 2, 3 and 4 Control Room Logsheet Page 11 of 35 UNIT: 1 KEY PARAMETER DATE:

PRZR VAPOR 9/17/01 LOCATION CP-004 INSTR TI-0607 00-02 650 12-14 LIMIT N/A TECH SPEC 3.4.9.2 KEY MODE ALL NOTE (1) TI-0607 MINUS TI-0126.

(2) ONLY IF AUX SPRAY IN USE.

REGEN HX TI-0126 545 N/A TEMP AUX SPRAY CALC. N/A # 621EF DELTA-T (1) (2)

PORV 655A MOV- N/A OPEN 3.4.9.3 4 (1) IF PORVs USED FOR COLD BLOCK VLV 0001A (1) (2) ONLY OVERPRESSURE PROTECTION.

(2) IF ALT VENT PATH ESTABLISHED, PORV 656A MOV- THEN LOG VENT VERIF SAT PER BLOCK VLV 0001B N/A T.S.4.4.9.3.2.

CHARGING CP-004 PI-0204 2550 CHNL CHECK 3.3.2 Table 1,2,3,4 1) TRANSCRIBE READING OF ONE PUMP # 200 PSIG 3.3-3, RUNNING PUMP FROM PRESSURE BETWEEN Item 3d-2, LOGSHEET 13, MEAB MODES 1, 2, 3, PI-0204 AND Action 16 AND 4 TECH SPECS LOGSHEET.

PI-0288B 2660 PI-0288B/287B/

PI-0287B 286B PI-0286B KEY KEY

Logsheet 1 Modes 1, 2, 3 and 4 Control Room Logsheet Page 12 of 35 UNIT: 1 KEY PARAMETER RCS TAVG DATE: 9/17/01 LOCATION CP-005 INSTR TI-0412A 00-02 590 12-14 LIMIT TECH SPEC 3.3.2, Table 3.3-3, Item 5f, MODEKEY 1,2,3 1)

NOTE IF < 571EF WITH TAVG-TREF DEV ALARM NOT RESET IN MODE 1 OR IN

$ 571EF Action 20 MODE 2 WITH KEFF $ 1, THEN TI-0422A 589 (1) 3.1.1.4 COMPLETE LOGSHEET 7.

TI-0432A CHNL (2) MAX DIFFERENCE BETWEEN OPERABLE 588 CHECK 5EF CHANNELS.

(2)

TI-0442A 589 RCS TAVE DNB CP-005 CALC 589 # 595EF 3.2.5 1) AVERAGE OF ALL OPERABLE RCS TAVE PARAMETER (1) CHANNELS (3 MINIMUM).

LOOP CP-005 OR TI-0411 99 $ 5% N/A 1,2 (1) IF PLANT COMPUTER USED, THEN DELTA-T PLANT BELOW (3) COMPARE TO PLANT COMPUTER COMPUTER TI-0421 100 SETPOINT SETPOINT.

(1) (2)

TI-0431 98 Non-Critical Error - Should be (2) LOG ACTUAL VALUE. IF LESS THAN 5%

BELOW OTDT OR OPDT SETPOINTS, identified as having exceeded the THEN RESTORE MARGIN TO GREATER TI-0441 THAN 5%.

99 administrative limit (3) N/A IN MODES 3 AND 4.

OPDT TI-0412B 107 CHNL 3.3.1, 1,2 SETPOINT CHECK 6% Items 8,9 (3) (4) MAX DIFFERENCE BETWEEN OPERABLE (4) Action 6 CHANNELS DUE TO INSTRUMENT TI-0422B 104 ERROR. LIMIT MAY BE EXCEEDED DUE TO DIFFERENT LOOP OPERATING TI-0432B 108 TEMPERATURES.

TI-0442B 108 OTDT TI-0412C 117 CHNL SETPOINT CHECK 10%

TI-0422C 117 (4)

TI-0432C 115 KEY KEY TI-0442C 118 VESSEL TI-0600 89 N/A 3.4.6.2 1,2,3,4 FLANGE L/O EF TEMP

Logsheet 1 Modes 1, 2, 3 and 4 Control Room Logsheet Page 13 of 35 UNIT:

KEY 1

PARAMETER FOP DATE: 9/17/01 INSTRUMENT N/A (1) 00-02 249 12-14 LIMIT N/A TECH SPEC 3.1.3.1 3.1.3.2 MODE 1,2 (4)

KEY NOTE (1) FULL OUT POSITION (FOP) FROM PLANT CURVE BOOK TABLE 1.1.

3.1.3.6 CONTROL ROD GP. 1 DEMAND POS. +/- 12 STEPS (2) RECORD BANK INSERTION LIMIT FOR 249 PRESENT PWR LEVEL FROM CORE BANK A BETWEEN POSITION DRPI & OPERATING LIMITS REPORT.

GP. 2 DEMAND POS. 249 INDICATION DEMAND (3) FULLY WITHDRAWN AS SPECIFIED IN DRPI HIGHEST ROD 252 ALL RODS CORE OPERATING LIMITS REPORT.

IN BANK DRPI LOWEST ROD 252 ABOVE (4) MODE 2 WITH KEFF $ 1. N/A IN MODES 3 INSERT AND 4.

ROD INS LIMIT (2) (3) (3) LIMIT CONTROL ROD GP. 1 DEMAND POS. 249 BANK B POSITION GP. 2 DEMAND POS. 249 INDICATION DRPI HIGHEST ROD 252 DRPI LOWEST ROD 246 ROD INS LIMIT (2) 249 CONTROL ROD GP. 1 DEMAND POS. 249 BANK C POSITION GP. 2 DEMAND POS.

INDICATION 249 DRPI HIGHEST ROD 252 DRPI LOWEST ROD 252 ROD INS LIMIT (2) 249 CONTROL ROD GP. 1 DEMAND POS. 228 Critical Error - Difference between demand BANK D position and DRPI is >12 steps (and hasnt KEY KEY POSITION GP. 2 DEMAND POS.

INDICATION 228 DRPI HIGHEST ROD 246 DRPI LOWEST ROD 246 ROD INS LIMIT (2) 174

KEY KEY KEY KEY

Logsheet 1 Modes 1, 2, 3 and 4 Control Room Logsheet Page 14 of 35 UNIT: 1 KEY PARAMETER SHUTDOWN ROD POS IND.

DATE: 9/17/01 LOCATION ALL BANKS INSTR HIGHEST DEMAND 00-02 249 12-14 LIMIT

+/-12 STEPS BETWEEN DRPI TECH SPEC 3.1.3.1 3.1.3.2 KEY MODE 1,2 NOTE (1) FULLY WITHDRAWN AS SPECIFIED IN CORE OPERATING LIMITS POSITION POS. & DEMAND 3.1.3.5 REPORT.

POS.

LOWEST 249 DEMAND VERIFY POSITION EACH ROD FULLY WITHDRAWN HIGHEST 252 WHEN CRITICAL DRPI USING DRPI.

LOWEST DRPI 252 (1)

EXTENDED CP-005 NY-0046 N/A CHNL CHECK 3.3.1, 3,4 ONLY (1) IF HIGHEST READING $ 1000 CPS, RANGE CPS Table 4.3-1, THEN THE MAX DEV IS BY A NEUTRON NY-0045 (1) Item 7, FACTOR OF 10. IF NOT, MAX DEV.

FLUX N/A Action 12,17 IS BY A FACTOR OF 15.

(S/D MONITOR) NY-0046 TEST N/A (2) (2) VERIFY NO ERROR MESSAGES P.B. WHEN PUSHBUTTON IS DEPRESSED. (Ref. 6.8.5)

NY-0045 TEST N/A P.B.

QPTR 5M3-A3 SAT ALARM CLEAR 4.2.4.1.a 1 > 50% (1) IF ALARM NOT CLEAR, THEN ANNUNC (1) PWR PERFORM 0PSP10-NI-0002 EVERY 12 WINDOW 5M3-B3 SAT HRS.

KEY KEY

JPM NO: A7 PAGE 1 OF 9 NUCLEAR TRAINING DEPARTMENT JOB PERFORMANCE MEASURE TITLE: REVIEW CONTROL ROOM LOGS JPM NO.: A7 REVISION: 1 LOCATION: N/A

JPM NO: A7 PAGE 2 OF 9 JOB PERFORMANCE MEASURE WORKSHEET JPM

Title:

REVIEW CONTROL ROOM LOGS JPM No.: A7 Rev. No.: 1 Task No.: 30200, Review Operations Logs STP Objective: 30200, Review Operations Logs IAW 0POP01-ZQ-0022, Plant Operations Shift Routines, to verify that all forms have been completed and any Corrective Action initiated.

Related K/A

Reference:

2.1.3 [3.4], Knowledge of Shift Turnover Practices

References:

0POP01-ZQ-0022, Plant Operations Shift Routines 0POP02-CV-0003, Mixing of Boric Acid Technical Specifications SPR-940598, Low Boron Concentration, BAT 1A Task Normally Completed By: SRO Method of Testing: Simulated Location of Testing: N/A Time Critical Task: NO Alternate Path JPM: NO Validation Time: 15 minutes Required Materials (Tools/Equipment):

None

JPM NO: A7 PAGE 3 OF 9 JOB PERFORMANCE MEASURE INFORMATION SHEET READ TO PERFORMER:

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

YOU ARE TO INFORM THE EXAMINER WHEN YOU HAVE COMPLETED THE TASK CAUTION: Do not operate or alter equipment configuration in the plant without proper authorization.

INITIAL CONDITIONS:

The plant is in MODE 1, 100% steady state conditions.

INITIATING CUE:

You are directed to review the enclosed log package for accuracy and locate technical and/or procedural errors which have been inserted.

THREE errors have been inserted into the log package, one Critical and two Non-Critical. As a MINIMUM, you are to IDENTIFY the Critical error. Editorial errors such as spelling, grammar, or punctuation are unintentional and DO NOT count.

You are to take the following into account during your review:

1) Carryover errors count as only one error (i.e., a single error that carries over from calculation to calculation or multiple line items with the same incorrect information)

- DO NOT DISCLOSE INFORMATION BELOW THIS LINE -

COMPLETION CRITERIA:

Correctly locates the critical error which has been inserted into the Control Room Log Package.

JPM NO: A7 PAGE 4 OF 9 JOB PERFORMANCE MEASURE INFORMATION SHEET HANDOUTS:

Copy of faulted Control Room Log Package.

NOTES:

1) The Control Room log package will consist of a cover page plus 5 of the 34 logsheets.

Three errors have been inserted into the Log Package, two of which are noncritical and one of which is critical. The critical error relates to a missed Technical Specification violation, and the non critical errors relate to STP administrative or procedural limit violations. As a minimum, the examinee must locate the Critical error for successful completion of the task.

2) The Evaluator is provided with an ANSWER KEY which is appropriately marked

("KEY"). The location of inserted errors is also mentioned in the body of this JPM. The evaluator shall not hand out any page(s) marked as "KEY" to the examinee.

JPM NO: A7 PAGE 5 OF 9 JOB PERFORMANCE MEASURE CHECK SHEET NOTE:

• Critical steps are identified by (C).

• Sequenced steps are identified by (S1, S2, . . .).

JPM START TIME SAT/UNSAT Performance Step: 1 Review faulted log package.

Standard:

The applicant reviews faulted log package for errors and/or omissions.

Comment:

While there is no time limit associated with this JPM, the examinee is expected to make reasonable progress during the review process.

Cue:

Notes:

JPM NO: A7 PAGE 6 OF 9 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 2(C)

• Discuss errors and/or omissions located within the logsheets.

Standard:

• As a minimum, the examinee correctly locates the critical error inserted in the log package:

1) Log page 10 of 35 - The logtaker has incorrectly taken credit for the level in BAT Tank 1A, which is being batched (filled) to a normal level. Because it is in a batching lineup (the tank would only be available as a gravity feed source), and it's boric acid concentration is unknown, the tank is technically inoperable. Therefore the total BAT Volume recorded on the logs should be the amount present in BAT tank 1B ONLY (this figure should be 28K and not 43K gal.) Because the amount of boric acid present in BAT 1B is greater than the minimum required in the TRM (27K), this is not a violation of the TRM.

2) Log page 12 of 35- The margin between LOOP DELTA-T TI-0421 and OPDT SET POINT TI-0422B is less than the STP administrative limit required 5%, and is not red circled or noted on the cover page. There are no TS or TRM limits associated with the Loop Delta-T indicators.

3) Log page 13 0f 35- There is greater than a 12 step difference between DRPI and the STEP DEMAND POSITION INDICATION for CONTROL ROD BANK "D".

This is a violation of TS 3.1.3.2, requiring DRPI and Step Demand to indicate within 12 steps of each other. This should be red circled and noted on the cover page. *(Critical Error)*

STEP CONTINUED ON NEXT PAGE

JPM NO: A7 PAGE 7 OF 9 JOB PERFORMANCE MEASURE CHECK SHEET Comment:

1) A summary of Technical Specification 3.1.3.2 is as follows:

a) With a maximum of 1 DRPI per bank inoperable, either (1) Determine position of the non-indicating rod(s) indirectly by the movable incore detectors every 8 hours0.333 days <br />0.0476 weeks <br />0.011 months <br />... or (2) Reduce thermal power to < 50% of rated thermal power within 8 hours0.333 days <br />0.0476 weeks <br />0.011 months <br />.

b) With a maximum of one demand position indicator per bank inoperable either (1)

Verify all DRPI for the affected bank are operable and that the most withdrawn rod and the least withdrawn rod of the bank are within 12 steps of each other at least once per 8 hours0.333 days <br />0.0476 weeks <br />0.011 months <br />, or (2) Reduce thermal power to < 50% of rated thermal power within 8 hours0.333 days <br />0.0476 weeks <br />0.011 months <br />.

2) For All Control Room Log readings, Step 4.3.9 of 0POP01-ZQ-0022, Shift Routines applies:

"IF any log reading is outside its specified limits, THEN:

a) Circle the reading in RED.

b) IF the reading is related to Technical Specification equipment OR satisfies a Technical Specifications Surveillance, THEN immediately notify the Unit/Shift Supervisor.

c) Record corrective action(s) taken or in progress in the remarks section of the applicable log.

Cue:

Notes:

- TERMINATE THE JPM -

JPM STOP TIME

JPM NO: A7 PAGE 8 OF 9 VERIFICATION OF COMPLETION Job Performance Measure: A7, REVIEW CONTROL ROOM LOGS Applicant's Name:

SSN:

Date Performed:

Time to Complete:

JPM Results: Sat / Unsat Evaluator: Signature __________________________

Date ____________________

JPM NO: A7 PAGE 9 OF 9 JPM - HANDOUT READ TO PERFORMER:

The evaluator will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

YOU ARE TO INFORM THE EXAMINER WHEN YOU HAVE COMPLETED THE TASK CAUTION: Do not operate or alter equipment configuration in the plant without proper authorization.

INITIAL CONDITIONS:

The plant is in MODE 1, 100% steady state conditions.

INITIATING CUE:

You are directed to review the enclosed log package for accuracy and locate technical and/or procedural errors which have been inserted.

THREE errors have been inserted into the log package, one Critical and two Non-Critical. As a MINIMUM, you are to IDENTIFY the Critical error. Editorial errors such as spelling, grammar, or punctuation are unintentional and DO NOT count.

You are to take the following into account during your review:

1) Carryover errors count as only one error (i.e., a single error that carries over from calculation to calculation or multiple line items with the same incorrect information)

SOUTH TEXAS PROJECT ELECTRIC GENERATING STATION D0527

\\DATANW01\DATA1\PROCEDURES\APP Rev. 4 Page 1 of 24 ROVED\PSP\03\0SI0004.04x Effective Date: 01/26/00 Print Time / Date: 4:08 PM 07/03/01 0PSP03-SI-0004 High Head Safety Injection Pump 1A(2A) Inservice Test Quality Safety-Related Usage: IN HAND Effective Date: 01/26/00 R. Hamilton R.L. McAnnally Crew 1C Operations PREPARER TECHNICAL USER COGNIZANT DEPT.

Table of Contents Page Procedure Performance Data Sheet............................................................................................................. 2

1.0 Purpose and Scope

.......................................................................................................................... 5 2.0 Responsibilities .............................................................................................................................. 5 3.0 Precautions and Notes..................................................................................................................... 6 KEY 4.0 Prerequisites ................................................................................................................................... 8 5.0 Procedure...................................................................................................................................... 10 5.1 Preparation ........................................................................................................................... 10 5.2 HHSI Pump 1A(2A) Inservice Test...................................................................................... 11 5.3 SI-0005A Partial Stroke Test................................................................................................ 17 5.4 Restoration and Documentation ............................................................................................ 18 6.0 Acceptance Criteria...................................................................................................................... 20 7.0 References .................................................................................................................................... 20 8.0 Support Documents ....................................................................................................................... 23 Addendum 1, Vibration Test Point Locations and Instructions...................................................... 24

0PSP03-SI-0004 Rev. 4 Page 2 of 24 High Head Safety Injection Pump 1A(2A) Inservice Test Procedure Performance Data Sheet Unit Number: Work Activity Number: 14763 -ST: 860001374 ONE Technical Specification

Reference:

4.0.5, 4.3.2.1.1.c.7, 4.5.2.f.1 [ITS 5.5.8, SR 3.3.2.7-1c, SR 3.5.2.4]

Test Interval: Test Performance Allowed in Plant Modes: Train

Reference:

Quarterly 1, 2, 3, 4, 5, 6, or Core Off-Loaded to Spent Fuel Pool A Reason for Test:

x Periodic Surveillance Test x For Surveillance Credit

¨ Maintenance per Work Package # ¨ Not for Surveillance Credit

¨ Other KEY Radiation Work Permit No.: Fire Hazard Evaluation No.: Equipment Clearance No.:

N/A N/A N/A Administrative Approval to Perform Test:

John Wayne 5/17/01 0400 Shift Supervisor Date Time Test Results Review:

Pump Test Results:

¨ Acceptable - All data within Acceptance Criteria

¨ Acceptable - Data within Alert Range (explain in Remarks)

¨ Unacceptable - Any data NOT within Acceptance Criteria (explain in Remarks)

Critical Error - The test Valve Test Results:

results are unacceptable

¨ Acceptable - All data within Acceptance Criteria

¨ Unacceptable - Any data NOT within Acceptance Criteria (explain in Remarks)

Reviewed By: John Doe 5/17/01 0630 Test indefinitely suspended at Step 5.3.4 Test Coordinator Date Time This procedure, when complete, shall be retained for the life of the plant.

0PSP03-SI-0004 Rev. 4 Page 3 of 24 High Head Safety Injection Pump 1A(2A) Inservice Test Procedure Performance Data Sheet Plant Operations Review:

All data within Acceptance Criteria? ¨ Yes ¨ No Any data within Alert Range? ¨ Yes ¨ No Train in Service? ¨ Yes ¨ No Potential Reportable Occurrence? ¨ Yes ¨ No LCO Action Statement Entered? ¨ Yes ¨ No Reviewed By:

Shift Supervisor Date Time KEY Division Surveillance Coordinator Review:

Reviewed By:

Division Surveillance Coordinator Date Time Section XI Coordinator:

Pump Test Results:

¨ Acceptable - All data within Acceptance Criteria

¨ Acceptable - Data within Alert Range (explain in Remarks)

¨ Unacceptable - Any data NOT within Acceptance Criteria (explain in Remarks)

Valve Test Results:

¨ Acceptable - All data within Acceptance Criteria

¨ Unacceptable - Any data NOT within Acceptance Criteria (explain in Remarks)

Corrective Action Taken:

Reviewed By:

Section XI Coordinator Date Time M&TE Used:

Description STPEGS No. Cal. Due Date Vibration Instrument 800-017463 10/20/01 This procedure, when complete, shall be retained for the life of the plant.

0PSP03-SI-0004 Rev. 4 Page 4 of 24 High Head Safety Injection Pump 1A(2A) Inservice Test Procedure Performance Data Sheet M&TE Used:

Description STPEGS No. Cal. Due Date Performers and Verifiers:

Name (Print) Signature Initials Sections Performed John Doe John Doe JD 4.0 (all), 5.1-5.3.4 KEY Remarks: Test indefinitely suspended at Step 5.3.4, Shift Supervisor notified.

CR# 01-8732 written to calibrate pump suction and discharge pressure gauges.

Critical Error - The as left status of the system is not recorded in the remarks This procedure, when complete, shall be retained for the life of the plant.

0PSP03-SI-0004 Rev. 4 Page 5 of 24 High Head Safety Injection Pump 1A(2A) Inservice Test

1.0 Purpose and Scope

1.1 This procedure will satisfy the following Technical Specifications:

• 4.0.5 [ITS 5.5.8] For inservice testing of HHSI Pump 1A(2A) per Ref 7.3.1 and Ref 7.3.2 for partial stroke test of valves SI-0002A and SI-0005A.

• 4.3.2.1.1.c.7 [ITS SR 3.3.2.7-1c] Satisfactory performance of this Surveillance Procedure will partially satisfy the quarterly Slave Relay Test requirements for HHSI Pump 1A(2A) breaker continuity.

• 4.5.2.f.1 [ITS SR 3.5.2.4] Verifying HHSI Pump 1A(2A) developed head at the test flow point is greater than or equal to the required developed head.

1.2 This procedure provides instructions to verify High Head Safety Injection Pump (HHSI)

KEY 1A(2A) is Operable by pump performance during operation on recirculation flow.

1.3 This procedure provides instructions for partial stroke test of SI-0002A, Safety Injection Train 1A(2A) Suction Header Check Valve.

1.4 This procedure provides instructions for partial stroke test of SI-0005A, HHSI Pump 1A(2A) Discharge Check Valve, when Reactor Coolant System pressure is greater than HHSI Pump shutoff head at 1750 psig.

1.5 This procedure provides instructions to verify LHSI/HHSI/CSS pump cubicle cooler fan will automatically start when HHSI Pump 1A(2A) is placed in service.

1.6 This procedure provides instructions to verify containment sump isolation valve cubicle cooler fan will automatically start when HHSI Pump 1A(2A) is placed in service.

2.0 Responsibilities 2.1 Test Coordinator shall ensure that the procedure revision is correct and that all applicable Field Changes are incorporated.

2.2 Shift Supervisor shall grant permission for performance of this test.

2.3 This procedure shall be performed by Plant Operations.

This procedure, when complete, shall be retained for the life of the plant.

0PSP03-SI-0004 Rev. 4 Page 6 of 24 High Head Safety Injection Pump 1A(2A) Inservice Test 2.4 WHEN "_____" (blank) follows a step, THEN performer shall enter initials to verify step completion.

2.5 The Plant Performance Section may perform the vibration monitoring portion of this procedure.

2.6 After completion, procedure routing is per 0PGP03-ZE-0004 (Plant Surveillance Program) and 0PGP03-ZA-0055 (Plant Surveillance Scheduling).

2.7 The following shall review the test results:

• Test Coordinator

• Shift Supervisor KEY

• Department Surveillance Coordinator

• Section XI Coordinator 3.0 Precautions and Notes 3.1 IF Safety Injection Signal occurs, THEN ensure the following valves in proper position:

• "PUMP 1A(2A) DISCH ISOL MOV-0004A" is open

• "HHSI Tc UP STREAM FV-3952" is closed 3.2 This procedure should be reviewed in its entirety prior to performing the test.

3.3 Acceptance Criteria steps are annotated with the letters AC in the left margin preceding the step.

3.4 IF this procedure cannot be performed as written, THEN the procedure performer shall stop and immediately notify Shift Supervisor.

3.5 IF this procedure is terminated for any reason, THEN immediately notify Shift Supervisor.

3.6 IF any Acceptance Criteria are NOT met, THEN immediately notify Shift Supervisor and document failure per 0PGP03-ZE-0004 (Plant Surveillance Program).

This procedure, when complete, shall be retained for the life of the plant.

0PSP03-SI-0004 Rev. 4 Page 7 of 24 High Head Safety Injection Pump 1A(2A) Inservice Test 3.7 Specific Reference Values incorporated in this procedure were obtained for the respective equipment on the following dates:

Component Description Reference Value Date High Head Safety Injection Pump 1A differential 01/23/2000 pressure, recirculation flow, and vibration High Head Safety Injection Pump 2A differential 01/23/2000 pressure, recirculation flow, and vibration 3.8 The instructions for obtaining new Reference Values for HHSI Pump 1A(2A) are contained in 0PSP03-SI-0010 (High Head Safety Injection Pump 1A(2A)

Reference Values Measurement).

3.9 3.10 3.11 3.12 KEY HHSI Pump operation on recirculation should be limited to less than 2 hours0.0833 days <br />0.0119 weeks <br />0.00274 months <br /> to prevent pump overheating.

IF Reactor Coolant System (RCS) pressure is less than 1750 psig AND "PUMP 1A(2A) DISCH ISOL MOV-0004A" is closed, THEN Train A HHSI Pump 1A(2A) may be inoperable per Technical Specification 3.5.2 [ITS 3.5.2].

(SPR 940428)

IF RCS pressure is less than 1750 psig, THEN partial stroke test of SI-0005A, HHSI Pump 1A(2A) Discharge Check Valve, shall NOT be required.

IF any HHSI Pump parameter falls in the Alert Range, THEN recalibration of the affected instruments and retest of the pump may be performed.

This procedure, when complete, shall be retained for the life of the plant.

0PSP03-SI-0004 Rev. 4 Page 8 of 24 High Head Safety Injection Pump 1A(2A) Inservice Test Initials 4.0 Prerequisites 4.1 Ensure procedure revision is correct and all applicable Field Changes are incorporated. JD 4.2 This procedure may be performed in any plant Mode. Record current plant Mode:

Mode 3 JD 4.3 Review Operability Assessment System (OAS) to ensure no equipment is out of service that could conflict with test completion or cause unexpected multiple trains to be inoperable while performing this test. JD 4.4 Verify plant condition for current operating Mode and mark the steps that do not KEY apply N/A:

4.4.1 IF the plant is in Modes 1, 2, or 3, THEN HHSI Trains B and C are Operable per Technical Specification 3.5.2 [ITS 3.5.2]. JD 4.4.2 IF the plant is in Mode 4, THEN HHSI Pumps B and C are Operable per Technical Specification 3.5.3.1 [ITS 3.4.12 and 3.5.3]. N/A 4.4.3 IF the plant is in Mode 5 or Mode 6 when the reactor vessel head is on, THEN all HHSI Pumps are inoperable per Technical Specification 3.5.3.2 [ITS 3.4.13]. N/A 4.5 Verify Safety Injection System Train A is aligned per 0POP02-SI-0002 (Safety Injection System Initial Lineup). JD 4.6 Ensure HHSI Pump 1A(2A) inspected and acceptable per criteria established in 0POP01-ZQ-0022 (Plant Operations Shift Routines). JD 4.7 Verify Train A Low Head Safety Injection Pump is shutdown. (CP001) JD 4.8 Verify Train A Containment Spray Pump is shutdown. (CP002) JD 4.9 Verify the following cubicle cooler fans are aligned per 0POP02-SI-0002 (Safety Injection System Initial Lineup):

• LHSI/HHSI/CSS pump room JD

• Containment sump isolation valve room JD This procedure, when complete, shall be retained for the life of the plant.

0PSP03-SI-0004 Rev. 4 Page 9 of 24 High Head Safety Injection Pump 1A(2A) Inservice Test Initials 4.10 Verify Refueling Water Storage Tank (RWST) contained volume is greater than or equal to 33,000 gallons. ("LVL LI-0931" or "LVL LI-0932", CP001)

(Technical Requirements Manual 3.1.2.5) JD 4.11 Obtain the following test instrumentation:

• Obtain a vibration instrument with an accuracy + 5% of full scale to measure vibration amplitude in in/sec. JD 4.12 Establish communications between the Control Room and the HHSI Pump in Train A Pump Room 006. (FHB -29') JD NOTE Performance of Steps 4.13 and 4.14 apply only to partial stroke test of SI-0005A, HHSI Pump KEY 1A(2A) Discharge Check Valve, in Section 5.4 of this test. Performance of Section 5.4 is done only with RCS pressure greater than 1750 psig. IF RCS pressure is less than 1750 psig, THEN Steps 4.13, 4.14 AND Section 5.4 shall be marked N/A.

4.13 Verify RCS pressure is equal to or greater than 1750 psig.

("PRESS PI-0455 PI-0456 PI-0457 PI-0458", CP004) JD 4.14 Verify no other Safety Injection or Containment Spray Pump inservice testing is in progress. JD 4.15 Record the following, or "N/A", as applicable, on the Procedure Performance Data Sheet (PPDS):

• Unit Number

• Work Activity Number

• Surveillance Test (ST) Number(s)

• Reason for Test

• RWP Number

• M&TE Data for vibration instrument JD 4.16 Notify the Shift Supervisor to review Technical Specifications LCOs 3.5.2, 3.5.3.1, and 3.5.3.2 [ITS 3.4.12, 3.4.13, 3.5.2 and 3.5.3] for action requirements prior to performing this surveillance. JD This procedure, when complete, shall be retained for the life of the plant.

0PSP03-SI-0004 Rev. 4 Page 10 of 24 High Head Safety Injection Pump 1A(2A) Inservice Test Initials 4.17 IF this procedure is being performed to demonstrate post-maintenance operability, THEN N/A the applicable subsection(s) for the component(s) NOT being tested, OTHERWISE N/A this step. N/A 4.18 Obtain Shift Supervisor signature on PPDS for administrative approval to perform test. JD 5.0 Procedure 5.1 Preparation 5.1.1 Ensure Prerequisites Section has been completed and Precautions and Notes Section has been read. JD 5.1.2 Conduct a prejob briefing. JD KEY 5.1.3 Ensure Control Room Logbook entry documents the commencement of this surveillance test. JD This procedure, when complete, shall be retained for the life of the plant.

0PSP03-SI-0004 Rev. 4 Page 11 of 24 High Head Safety Injection Pump 1A(2A) Inservice Test Initials 5.2 HHSI Pump 1A(2A) Inservice Test CAUTION IF RCS pressure is less than 1750 psig AND PUMP 1A(2A) DISCH ISOL MOV-0004A is closed, THEN Train A HHSI Pump 1A(2A) may be inoperable per Technical Specification 3.5.2 [ITS 3.5.2]. (SPR 940428) 5.2.1 IF RCS pressure is less than 1750 psig, THEN ensure "PUMP 1A(2A)

DISCH ISOL MOV-0004A" is closed, OTHERWISE N/A this step.

("PRESS PI-0455 PI-0456 PI-0457 PI-0458", CP001) N/A Perform N/A KEY Ind. Verif NOTE IF SI Pump or isolation valve room temperature is high, THEN the LHSI/HHSI/CSS pump cubicle or containment sump isolation valve cubicle cooler fan will restart after being shutdown with handswitch in AUTO.

5.2.2 IF any of the following fans are running, THEN stop the fan AND place in AUTO: (CP022)

• LHSI/HHSI/CSS pump cubicle fan "TRN A/RM 006 SUPP CLR 11A(21A) HF-VAH004" JD

• Containment sump isolation valve cubicle fan "TRN A/RM 007 SUPP CLR 11A(21A) HF-VAH012" JD This procedure, when complete, shall be retained for the life of the plant.

0PSP03-SI-0004 Rev. 4 Page 12 of 24 High Head Safety Injection Pump 1A(2A) Inservice Test Initials CAUTION Operation of High Head Safety Injection Pump on recirculation should be limited to less than 2 hours0.0833 days <br />0.0119 weeks <br />0.00274 months <br /> to prevent pump overheating.

NOTE LHSI/HHSI/CSS pump cubicle cooler fan and containment sump isolation valve cubicle cooler fan will automatically start when the HHSI Pump is started.

AC 5.2.3 Start "HHSI PUMP 1A(2A)" with handswitch at CP001 and record time:

KEY 0417 Time JD 5.2.4 Verify the following fans are running: (CP022)

AC 5.2.4.1 LHSI/HHSI/CSS pump cubicle fan "TRN A/RM 006 SUPP CLR 11A(21A) HF-VAH004" JD AC 5.2.4.2 Containment sump isolation valve cubicle fan "TRN A/RM 007 SUPP CLR 11A(21A) HF-VAH012" JD 5.2.5 WHEN at least 5 minutes has elapsed since HHSI pump start, THEN record time and HHSI Pump 1A(2A) discharge pressure from "1(2)-SI-PI-0957 HI HEAD SAFETY INJECTION PUMP 1A(2A)

DISCHARGE PRESSURE INDICATOR": (FHB -29', Train A Pump Room 006, SPR 931954) 0426 Time 1765 psig (PI-0957) JD 5.3 Record HHSI Pump 1A(2A) dynamic suction pressure from HHSI Pump 1A(2A)

Suction Pressure gage PI-0911.:

(FHB -29', Train A Pump Room 006) 32.5 psig JD This procedure, when complete, shall be retained for the life of the plant.

0PSP03-SI-0004 Rev. 4 Page 13 of 24 High Head Safety Injection Pump 1A(2A) Inservice Test Initials NOTE IF High Head Safety Injection Pump 1A(2A) differential pressure is less than 1480 psid, THEN the Shift Supervisor shall be notified immediately.

5.3.1 Calculate HHSI Pump 1A(2A) differential pressure (DP) using the following formula:

DP = Discharge Pressure - Dynamic Suction Pressure DP = 1765 - 32.5 Step 5.2.5 Step 5.3 DP = 1732.5 psid KEY JD 5.3.2 Record HHSI Pump 1A(2A) recirculation flow rate from "1-SI-FI-0907 HI HEAD SAFETY INJECTION PUMP 1A MINIFLOW FLOW INDICATOR (N2SI-FI-0907)":

(FHB, -13', Train A Valve Room 007) 107 gpm (FI-0907) JD This procedure, when complete, shall be retained for the life of the plant.

0PSP03-SI-0004 Rev. 4 Page 14 of 24 High Head Safety Injection Pump 1A(2A) Inservice Test Initials AC 5.3.3 Using Table 1 (HHSI Pump 1A(2A) Reference Values), perform the following:

5.3.3.1 Evaluate pump DP obtained in Step 5.3.1. JD 5.3.3.2 Complete the following and mark steps that DO NOT apply N/A:

a. Pump DP is within Acceptable Range. N/A

b. Pump DP is within the Required Action Range. JD

c. Pump Flow is within the Acceptable Range. JD

d. Pump Flow is within the Required Action Range.

N/A Pump DP Unit 1 Pump KEY Ref Value P r/Qr 1573 105 Table 1. HHSI Pump 1A(2A) Reference Values Test Value 1732.5 Req'd Action Low P t < 0.90P r Qt < 0.90Qr P t < 1480*

DP < 1480 Flow < 94.5 Accept Range 0.90Pr < P t < 1.10Pr 0.90Qr < Qt < 1.10Qr 1480* < P t 1480 < DP < 1730.3 94.5 < Flow < 115.5 Req'd Action High P t > 1.10P r Qt > 1.10Qr DP > 1730.3 Flow > 115.5 Units psid gpm Recirc 107 Unit 1 Pump DP 1541.5 DP < 1480 1480 < DP < 1695 DP > 1695 psid N/A Unit 2 Pump 105 Flow < 94.5 94.5 < Flow < 115.5 Flow > 115.5 gpm Recirc N/A Unit 2

• Technical Specification 4.5.2.f.1 5.3.4 IF HHSI Pump 1A(2A) DP or Flow is within Required Action Range, THEN immediately notify Shift Supervisor, OTHERWISE N/A this step. JD This procedure, when complete, shall be retained for the life of the plant.

0PSP03-SI-0004 Rev. 4 Page 15 of 24 High Head Safety Injection Pump 1A(2A) Inservice Test Initials 5.3.5 IF performing this test in Unit 1, THEN determine unfiltered vibration Velocity (Vt) at indicated test points (Addendum 1, Vibration Test Non-Critical Error - The Point Locations and Instructions) AND record vibration Velocity (Vt) remainder of the test in Table 2 (Unit 1 Vibration Data), OTHERWISE N/A this step and was left blank the Test Data block in Table 2. _____

Table 2. Unit 1 Vibration Data Reqd Action Vibration Data Ref Test Acceptable Alert Range High Units Point Value Data Range High Vt > 6Vr 2.5Vr < Vt <6Vr OR Vr Vt Vt < 2.5Vr OR 0.325 < Vt < 0.7 Vt > 0.7 1H1* in/sec KEY 1H2* in/sec 2H1* in/sec 2H2* in/sec 3H1 0.155 V 0.325 0.325< V 0.700 V > 0.700 in/sec 3H2 0.126 V 0.315 0.315< V 0.700 V > 0.700 in/sec 1A* in/sec

• Data point reference only for system health monitoring, NOT a Code requirement and NO Acceptance Criteria Applicable.

This procedure, when complete, shall be retained for the life of the plant.

0PSP03-SI-0004 Rev. 4 Page 16 of 24 High Head Safety Injection Pump 1A(2A) Inservice Test Initials 5.3.6 IF performing this test in Unit 2, THEN determine unfiltered vibration Velocity (Vt) at indicated test points (Addendum 1, Vibration Test Point Locations and Instructions) AND record vibration Velocity (Vt) in Table 3 (Unit 2 Vibration Data), OTHERWISE N/A this step and the Test Data block in Table 3. _____

Table 3. Unit 2 Vibration Data Reqd Action Vibration Data Ref Test Acceptable Alert Range High Units Point Value Data Range High Vt > 6Vr 2.5Vr < Vt <6Vr OR Vr Vt Vt < 2.5Vr OR 0.325 < Vt < 0.7 Vt > 0.7 1H1* in/sec 1H2* in/sec KEY 2H1* in/sec 2H2* in/sec 3H1 0.068 V 0.170 0.170 < V 0.408 V > 0.408 in/sec 3H2 0.064 V 0.160 0.160 < V 0.384 V > 0.384 in/sec 1A* in/sec

• Data point reference only for system health monitoring, NOT a Code requirement and NO Acceptance Criteria Applicable.

AC 5.3.7 Using the applicable Table (2 or 3), perform the following:

5.3.7.1 Evaluate pump vibration test data. _____

5.3.7.2 Complete the following and mark steps that DO NOT apply N/A:

a. Pump vibration is within Acceptable Range. _____

b. Pump vibration is within the Alert Range. _____

c. Pump vibration is within the Required Action Range. _____

5.3.8 IF HHSI Pump 1A(2A) vibration is within Required Action Range, THEN immediately notify Shift Supervisor, OTHERWISE N/A this step. _____

This procedure, when complete, shall be retained for the life of the plant.

0PSP03-SI-0004 Rev. 4 Page 17 of 24 High Head Safety Injection Pump 1A(2A) Inservice Test Initials NOTE Performance of Section 5.4 is required when RCS pressure is greater than 1750 psig, and shall be marked N/A when RCS pressure is less than 1750 psig.

5.4 SI-0005A Partial Stroke Test 5.4.1 Ensure Section 5.2 is complete. _____

5.4.2 Establish communications between the Control Room and MAB 10' Non Radioactive Pipe Chase Room 064. _____

5.4.3 Open SI System Test Line valves: (CP001)

KEY

• "TEST LN ICIV FV-3970" _____

• "TEST LN OCIV FV-3971" _____

5.4.4 Verify "1(2)-SI-FI-0920A SIS CHECK VALVE TEST FLOW INDICATOR" indicates no flow. (MAB 10', Room 064) _____

5.4.5 Open "HHSI Tc UP STREAM FV-3952". (CP001) _____

AC 5.4.6 Verify flow increases through "1(2)-SI-FI-0920A SIS CHECK VALVE TEST FLOW INDICATOR". (MAB 10', Room 064) _____

5.4.7 Close "HHSI Tc UP STREAM FV-3952". (CP001) _____

Perform Ind. Verif 5.4.8 Verify "1(2)-SI-FI-0920A SIS CHECK VALVE TEST FLOW INDICATOR" indicates no flow. (MAB 10', Room 064) _____

This procedure, when complete, shall be retained for the life of the plant.

0PSP03-SI-0004 Rev. 4 Page 18 of 24 High Head Safety Injection Pump 1A(2A) Inservice Test Initials 5.4.9 Close SI System Test Line valves: (CP001)

• "TEST LN ICIV FV-3970" _____

Perform Ind. Verif

• "TEST LN OCIV FV-3971" _____

Perform Ind. Verif 5.5 Restoration and Documentation 5.5.1 Stop "HHSI PUMP 1A(2A)" with handswitch at CP001. _____

marked N/A.

5.5.2 KEY NOTE Steps 5.5.2 through 5.5.4 align HHSI Pump, LHSI/HHSI/CSS pump and containment sump isolation valve cubicle cooler fans to normal. IF any component(s) is NOT returned to normal, THEN reason(s) should be stated in the Remarks Section AND affected step(s)

IF required by plant conditions, THEN place "HHSI PUMP 1A(2A)"

in AUTO. (CP001) _____

Perform Ind. Verif 5.5.3 Ensure "PUMP 1A(2A) DISCH ISOL MOV-0004A" is open. (CP001) _____

Perform Ind. Verif This procedure, when complete, shall be retained for the life of the plant.

0PSP03-SI-0004 Rev. 4 Page 19 of 24 High Head Safety Injection Pump 1A(2A) Inservice Test Initials 5.5.4 Stop the following fans and place in AUTO: (CP022)

• LHSI/HHSI/CSS pump cubicle fan "TRN A/RM 006 SUPP CLR 11A(21A) HF-VAH004" _____

Perform Ind. Verif

• Containment sump isolation valve cubicle fan "TRN A/RM 007 SUPP CLR 11A(21A) HF-VAH012" _____

Perform Ind. Verif 5.5.5 Notify the Shift Supervisor that testing is complete. _____

5.5.6 Complete Test Results Section of the PPDS. _____

5.5.7 5.5.8 5.5.9 5.5.10 KEY Ensure required information has been recorded on the M&TE Usage form (WOFWOME) in STP IMPACT for each piece of M&TE used.

(SPR 941413)

Ensure M&TE Used Section of PPDS is complete.

Ensure Performers and Verifiers Section of the PPDS is complete.

IF any problems occurred, THEN initiate Condition Report(s) and log Condition Report number(s) in the Remarks section of PPDS, OTHERWISE N/A this step.

5.5.11 Forward procedure to Shift Supervisor for review. _____

This procedure, when complete, shall be retained for the life of the plant.

0PSP03-SI-0004 Rev. 4 Page 20 of 24 High Head Safety Injection Pump 1A(2A) Inservice Test 6.0 Acceptance Criteria 6.1 HHSI Pump 1A(2A) breaker continuity is verified by HHSI Pump 1A(2A) start.

(Step 5.2.3) 6.2 LHSI/HHSI/CSS pump cubicle cooler fan automatically starts when HHSI Pump 1A(2A) is placed in service or running during pump operation. (Step 5.2.4.1) 6.3 Containment sump isolation valve cubicle cooler fan automatically starts when HHSI Pump 1A(2A) is placed in service or running during pump operation. (Step 5.2.4.2 )

6.4 HHSI Pump 1A(2A) differential pressure (DP) shall be within the Acceptable Range.

(Step 5.3.3) 6.5 HHSI Pump 1A(2A) Flow shall be within the Acceptable Range. (Step 5.3.3) 6.6 HHSI Pump 1A(2A) Vibration Test Data shall be within the Acceptable Range or the Alert KEY Range. (Step 5.3.7) 6.7 Partial stroke test of SI-0005A, HHSI Pump 1A(2A) Discharge Check Valve, if performed, shall be acceptable if a flow increase is indicated on "1(2)-SI-FI-0920A SIS CHECK VALVE TEST FLOW INDICATOR" when test line valves are opened. (Step 5.4.6) 6.8 Partial stroke test of SI-0002A, Safety Injection Train 1A(2A) Suction Header Check Valve, shall be acceptable if HHSI Pump 1A(2A) meets or exceeds the requirements of Acceptance Criteria Step 6.4.

7.0 References 7.1 Technical Specifications 7.1.1 Technical Specification 3.5.2 [ITS 3.5.2]

7.1.2 Technical Specification 3.5.3.1 [ITS 3.4.12 and 3.5.3]

7.1.3 Technical Specification 3.5.3.2 [ITS 3.4.13]

7.1.4 Technical Specification 4.0.5 [ITS 5.5.8]

7.1.5 Technical Specification 4.3.2.1.1.c.7 [ITS SR 3.3.2.7-1c]

This procedure, when complete, shall be retained for the life of the plant.

0PSP03-SI-0004 Rev. 4 Page 21 of 24 High Head Safety Injection Pump 1A(2A) Inservice Test 7.2 Technical Requirements Manual 7.2.1 Technical Requirements Manual 3.7.13 7.2.2 Technical Requirements Manual 3.1.2.5 7.3 Regulatory Guides and Standards 7.3.1 ASME OMa-1988, Addenda to ASME OM-1987, Operation and Maintenance of Nuclear Power Plants, Part 6, Inservice Testing of Pumps in Light-Water Reactor Power Plants.

7.3.2 ASME OMa-1988, Addenda to ASME OM-1987, Operation and Maintenance of Nuclear Power Plants, Part 10, Inservice Testing of Valves in Light-Water Reactor Power Plants.

7.4 UFSAR KEY 7.4.1 Section 3.9.6 (Inservice Testing of Pumps and Valves) 7.4.2 Section 6.3 (Emergency Core Cooling System) 7.4.3 Section 9.4.2 (Fuel Handling Building Heating, Ventilation, and Air Conditioning) 7.5 Commitments 7.5.1 SPR 920849 (Changing Temp Switch Setting to Actuate Cubicle Cooler) 7.5.2 SPR 931954 (Stabilization Period Required in AF Inservice Tests) 7.5.3 SPR 940428 (Declaration of LHSI Trains Inoperable During Surveillance Testing) 7.5.4 SPR 940802 (Installed Plant Pump Gages Exceed ASME Section XI Range Requirements) 7.5.5 SPR 941413 (M&TE Issue Sheets not Completed for each use of Instrument) 7.5.6 CR 97-12395 (Containment Spray Pump Slave Relay Testing)

This procedure, when complete, shall be retained for the life of the plant.

0PSP03-SI-0004 Rev. 4 Page 22 of 24 High Head Safety Injection Pump 1A(2A) Inservice Test 7.6 Technical Standards and Manuals 7.6.1 VTD-P025-0004 (High Head Safety Injection Pump Operating & Maintenance Manual) 7.6.2 5N129MB1045 (Safety Injection System Design Basis Document) 7.6.3 Unit 1/Unit 2 Pump and Valve Inservice Test Plan.

7.7 Drawings 7.7.1 Piping and Instrumentation Diagrams 7.7.1.1 5N129F05013 #1 and #2 (Safety Injection System) 7.7.1.2 5N129F05016 #1 and #2 (Safety Injection System) 7.7.2 Elementary Wiring Diagrams KEY 7.7.2.1 7.7.2.2 7.7.2.3 7.7.2.4 9-E-SI05-01 #1 and #2 (High Head Safety Injection Pumps PA101A, PA101B, PA101C {PA201A, PA201B, PA201C})

9-E-SI13-01 #1 and #2 (HHSI Pumps 1A, 1B, 1C Discharge MOV's 0004A, 0004B, 0004C) 9-E-HF03-01 #1 and #2 (FHB HVAC LHSI Pump Supply Clr Unit Fans (AH004, AH005, AH006))

9-E-HF12-01 #1 and #2 (FHB HVAC CS IV Cubicle Supplementary Coolers AH012, 013 & 014)

This procedure, when complete, shall be retained for the life of the plant.

0PSP03-SI-0004 Rev. 4 Page 23 of 24 High Head Safety Injection Pump 1A(2A) Inservice Test 7.8 STPEGS Procedures and Policies 7.8.1 0POP01-ZQ-0022 (Plant Operations Shift Routines) 7.8.2 0POP02-SI-0002 (Safety Injection System Initial Lineup) 7.8.3 0PSP03-SI-0010 (High Head Safety Injection Pump 1A(2A) Reference Values Measurement) 7.8.4 0PGP03-ZC-0004 (Measuring and Test Equipment Control Program )

7.8.5 0PGP03-ZM-0016 (Installed Plant Instrumentation Calibration Verification Program) 7.8.6 0PGP03-ZE-0021 (Inservice Testing Program for Valves) 7.8.7 0PGP03-ZE-0022 (Inservice Testing Program for Pumps)

KEY 7.8.8 0PGP01-ZE-0005 (Plant Surveillance Procedure Preparation) 7.8.9 0PGP03-ZE-0004 (Plant Surveillance Program) 7.8.10 0PGP03-ZA-0055 (Plant Surveillance Scheduling) 8.0 Support Documents 8.1 Addendum 1, Vibration Test Point Locations and Instructions This procedure, when complete, shall be retained for the life of the plant.

0PSP03-SI-0004 Rev. 4 Page 24 of 24 High Head Safety Injection Pump 1A(2A) Inservice Test Addendum 1 Vibration Test Point Locations and Instructions Page 1 of 1 1A 1 H1, H2 H2 MOTOR KEY 2 H1, H2 H1 3 H1, H2 PUMP D116B D116B.WPG H1 - Denotes a horizontal vibration point. Probe shall be held perpendicular to the machine axis and parallel to both the floor and the pump discharge piping.

H2- Denotes a horizontal vibration point. Probe shall be held parallel to the floor and perpendicular to both the machine axis and the pump discharge piping.

NOTE: 3H vibration readings are taken on the pump seal assembly inside of pump frame.

A- Denotes an axial vibration point. Probe shall be held perpendicular to the floor and parallel to the machine axis.

This procedure, when complete, shall be retained for the life of the plant.

JPM NO: A8 PAGE 1 OF 8 NUCLEAR TRAINING DEPARTMENT JOB PERFORMANCE MEASURE TITLE: REVIEW COMPLETED SURVEILLANCE JPM NO.: A8 REVISION: 1 LOCATION: N/A

JPM NO: A8 PAGE 2 OF 8 JOB PERFORMANCE MEASURE WORKSHEET JPM

Title:

REVIEW COMPLETED SURVEILLANCE JPM No.: A8 Rev. No.: 1 Task No.: 12000, Authorize the start of and review surveillance tests.

STP Objective: 12000, Authorize the start of surveillance tests, and review completion in accordance with PGP03-ZE-0004.

Related K/A

Reference:

2.2.12 [3.4], Knowledge of surveillance procedures.

References:

0PGP03-ZE-0004, Rev. 20, Plant Surveillance Program Task Normally Completed By: SRO Method of Testing: Actual Performance Location of Testing: N/A Time Critical Task: NO Alternate Path JPM: NO Validation Time: 25 minutes Required Materials (Tools/Equipment):

None

JPM NO: A8 PAGE 3 OF 8 JOB PERFORMANCE MEASURE INFORMATION SHEET READ TO PERFORMER:

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

YOU ARE TO INFORM THE EXAMINER WHEN YOU HAVE COMPLETED THE TASK CAUTION: Do not operate or alter equipment configuration in the plant without proper authorization.

INITIAL CONDITIONS:

Unit 1 is in Mode 3 preparing for reactor startup. 0PSP03-SI-0004, High Head Safety Injection Pump 1A(2A) Inservice Test is in progress. The pump ? P is determined to be just in the Required Action High range. The test was indefinitely suspended and a condition report initiated to calibrate the pump suction and discharge pressure gauges used in the surveillance.

INITIATING CUE:

As the on-shift SRO, you are directed to review the indefinitely suspended surveillance in accordance with 0PGP03-ZE-0004, Plant Surveillance Program.

THREE errors have been inserted into the surveillance, two (2) Critical and one (1) Non-Critical.

As a MINIMUM, you are to IDENTIFY both Critical errors. Editorial errors such as spelling, grammar, or punctuation are unintentional and DO NOT count.

You are to take the following into account during your review:

1) The suction and discharge pressure gauges and recirc flowmeter were indicating stable readings during the test.

2) It is planned to re-run the test from the beginning following calibration of the gauges.

3) Carryover errors count as only one error (i.e., a single error that carries over from calculation to calculation or multiple line items with the same incorrect information)

JPM NO: A8 PAGE 4 OF 8 JOB PERFORMANCE MEASURE INFORMATION SHEET CONT

- DO NOT DISCLOSE INFORMATION BELOW THIS LINE -

COMPLETION CRITERIA:

The 1A HHSI Pump has been declared inoperable and the pump lineup restored to normal.

HANDOUTS:

• Handout Copy of the completed surveillance, 0PSP03-SI-0004.

• Handout Copy of 0PGP03-ZE-0004, Plant Surveillance Program (if requested).

NOTES:

1) A completed Answer KEY is provided for the Evaluator. The Key contains the same errors as the handout. The location of the errors will be highlighted and described on the evaluator copy. Do Not Hand to the Applicant

JPM NO: A8 PAGE 5 OF 8 JOB PERFORMANCE MEASURE CHECK SHEET NOTE:

• Critical steps are identified by (C).

• Sequenced steps are identified by (S1, S2, . . .).

JPM START TIME SAT/UNSAT Performance Step: 1 (C)*

Review the completed procedure in accordance with 0PGP03-ZE-0004.

Standard:

Identifies the following ERRORS:

1)* Test results should be marked as Unacceptable and the pump declared inoperable.

2)* The as left status of the system should be identified in the remarks section and actions taken to secure the pump (completing the remainder of the test would also satisfy this).

3) The remainder of the procedure past Step 5.3.4 should be N/Ad (or the remainder of the test could be completed), such that there are no blanks in the completed data package.

Comment:

1)

• Denotes Critical Error.

2) Error #1 results in a piece of equipment that should be inoperable to continue to be considered operable. Addendum 2 , step 1.b to 0PGP03-ZE-0004 states that in this instance where there is no obvious indication of instrument failure, the test should be considered unacceptable and not suspended.

3) Error #2 is a requirement of step 4.4.5.2.d of 0PGP03-ZE-0004. As indicated by the surveillance, the HHSI pump was left running on recirc which needs to be included in the remarks section of the procedure especially since there is a caution which limits pump runtime on recirc to 2 hours0.0833 days <br />0.0119 weeks <br />0.00274 months <br /> (to prevent pump damage due to overheating). And due to the time limit, action should be taken to secure the pump.

STEP CONTINUED ON NEXT PAGE

JPM NO: A8 PAGE 6 OF 8 JOB PERFORMANCE MEASURE CHECK SHEET

4) Error #3 is a Non-Critical error which violates the requirement of Addendum 1, step 2.B of 0PGP03-ZE-0004. The overall results of the test are not affected by this error.

Cue:

1) If asked, the surveillance will be run again from the beginning with a new surveillance package.

2) If asked, there were NO other indications consistent with an instrument malfunction of the pump suction pressure, discharge pressure, and recirc flowmeter.

3) If asked, no procedure steps were completed beyond step 5.3.4 (the pump is still running)

4) If asked, the pump has been running on recirc for 1.5 hours0.208 days <br />0.0298 weeks <br />0.00685 months <br />.

Notes:

If requested, supply the Handout Copy of 0PGP03-ZE-0004, Plant Surveillance Program.

- TERMINATE THE JPM -

JPM STOP TIME

JPM NO: A8 PAGE 7 OF 8 VERIFICATION OF COMPLETION Job Performance Measure: A8, REVIEW COMPLETED SURVEILLANCE Applicant's Name:

SSN:

Date Performed:

Time to Complete:

JPM Results: Sat / Unsat Evaluator: Signature __________________________

Date ____________________

JPM NO: A8 PAGE 8 OF 8 JPM - HANDOUT READ TO PERFORMER:

The evaluator will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

YOU ARE TO INFORM THE EXAMINER WHEN YOU HAVE COMPLETED THE TASK CAUTION: Do not operate or alter equipment configuration in the plant without proper authorization.

INITIAL CONDITIONS:

Unit 1 is in Mode 3 preparing for reactor startup. 0PSP03-SI-0004, High Head Safety Injection Pump 1A(2A) Inservice Test is in progress. The pump ? P is determined to be just in the Required Action High range. The test was indefinitely suspended and a condition report initiated to calibrate the pump suction and discharge pressure gauges used in the surveillance.

INITIATING CUE:

As the on-shift SRO, you are directed to review the indefinitely suspended surveillance in accordance with 0PGP03-ZE-0004, Plant Surveillance Program.

THREE errors have been inserted into the surveillance, two (2) Critical and one (1) Non-Critical.

As a MINIMUM, you are to IDENTIFY both Critical errors. Editorial errors such as spelling, grammar, or punctuation are unintentional and DO NOT count.

You are to take the following into account during your review:

1) The suction and discharge pressure gauges and recirc flowmeter were indicating stable readings during the test.

2) It is planned to re-run the test from the beginning following calibration of the gauges.

3) Carryover errors count as only one error (i.e., a single error that carries over from calculation to calculation or multiple line items with the same incorrect information)

0ERP01-ZV-IN01 Rev. 4 Page 16 of 106 Emergency Classification Addendum 1 Emergency Classification Tables Page 7 of 25 KEY

0ERP01-ZV-SH01 Rev. 15 Page 16 of 35 Shift Supervisor Data Sheet 2 Alert Checklist Page 1 of 7 (Name) (Date) (Unit)

Action A. INITIAL ACTIONS KEY

1. Announce to Control Room personnel the declaration of an Alert and the continuation (or assumption) of Emergency Director responsibilities by the Shift Supervisor.

Time

2. Ensure the following announcement (or a similar announcement) is made over the public address system using the Unit Override button:

(READ SLOWLY) ATTENTION ALL PERSONNEL; ATTENTION ALL PERSONNEL. AN ALERT HAS BEEN DECLARED IN UNIT(S) ___. ALL DESIGNATED MEMBERS OF THE EMERGENCY RESPONSE ORGANIZATION REPORT TO YOUR FACILITY. ALL OTHER PERSONNEL ARE TO CONTINUE WITH THEIR NORMAL DUTIES UNLESS FURTHER INSTRUCTIONS ARE GIVEN. (Optional: Give brief description of the event.)

JPM NO: A9 PAGE 1 OF 10 NUCLEAR TRAINING DEPARTMENT JOB PERFORMANCE MEASURE TITLE: DECLARE EMERGENCY ACTION LEVELS JPM NO.: A9 REVISION: 1 LOCATION: N/A

JPM NO: A9 PAGE 2 OF 10 JOB PERFORMANCE MEASURE WORKSHEET JPM

Title:

DECLARE EMERGENCY ACTION LEVELS JPM No.: A9 Rev. No.: 1 Task No.: 74026 (SRO), Classify emergency conditions.

STP Objective: Given an emergency condition and a copy of the emergency classification tables from 0ERP01-ZV-IN01, Emergency Classification, classify the emergency condition.

Related K/A

Reference:

2.4.41 [4.0], Knowledge of the emergency action level thresholds and classifications.

References:

0ERP01-ZV-IN01, Rev. 4, Emergency Classification 0ERP01-ZV-SH01, Rev. 15, Shift Supervisor Task Normally Completed By: SRO Method of Testing: Actual Performance Location of Testing: N/A Time Critical Task: YES (15 minutes based on E-Plan Evaluation criteria)

Alternate Path JPM: NO Validation Time: 20 minutes Required Materials (Tools/Equipment):

NONE

JPM NO: A9 PAGE 3 OF 10 JOB PERFORMANCE MEASURE INFORMATION SHEET READ TO PERFORMER:

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

YOU ARE TO INFORM THE EXAMINER WHEN YOU HAVE COMPLETED THE TASK CAUTION: Do not operate or alter equipment configuration in the plant without proper authorization.

INITIAL CONDITIONS:

You are the Unit 1 Shift Supervisor and the following series of events has just occurred:

1. Complete loss of Main Feedwater while the unit was at 100% power.

2. Unit trip occurred (Main Turbine and Reactor)

3. Main Steam Line Monitor RT-8048 is indicating 1.5E-1 µci/cc and increasing.

4. All of the Annunciator Panels in the Control Room failed 15 minutes ago.

5. No steam release to the environment is present at this time.

INITIATING CUE:

Classify the event at its MINIMUM Emergency Action Level and initiate the STPEGS Emergency Plan. Portions of this JPM are time critical.

- DO NOT DISCLOSE INFORMATION BELOW THIS LINE -

COMPLETION CRITERIA:

An ALERT is declared and the first step of Emergency Plan is implemented.

JPM NO: A9 PAGE 4 OF 10 JOB PERFORMANCE MEASURE INFORMATION SHEET HANDOUTS:

NONE NOTES:

• No handouts are provided for the performer.(The procedure is very large)

• A Key is provided for the evaluator with the applicable page of 0ERP01-ZV-IN01, EMERGENCY CLASSIFICATION, and ERP01-ZV-SH01, SHIFT SUPERVISOR.

• A copy of 0ERP01-ZR-IN01 will be available in the examination area.

JPM NO: A9 PAGE 5 OF 10 JOB PERFORMANCE MEASURE CHECK SHEET NOTE:

• Critical steps are identified by (C).

• Sequenced steps are identified by (S1, S2, . . .).

JPM START TIME SAT/UNSAT Performance Step: 1 Obtain a copy of 0ERP01-ZV-IN01, Emergency Classification.

Standard:

Obtains a copy of 0ERP01-ZV-IN01, Emergency Classification.

Comment:

A procedural handout will not be provided. The appropriate procedure manuals will be available in the examination area.

Cue:

Notes:

The 15 minute time limit for declaring the Emergency Action Level starts when the applicant understands the initial conditions and initiating cue.

JPM NO: A9 PAGE 6 OF 10 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 2 (C)

Classify the event in accordance with Addendum 1 and 2 in 0ERP01-ZV-IN01.

Standard:

Classifies the event as an ALERT.

Comment:

• The ALERT classification is based on a loss of most (>50%) of Control Room Safety System annunciators for greater than 15 minutes with a significant plant transient in progress (COMMUNICATIONS/ALARMS/ASSESSMENT Section, SA4 EAL-1).

• Compare with Answer KEY Cue:

If requested: QDPS and ICS are available.

Notes:

This step must be completed within 15 minutes of the time when the applicant understands the initial conditions and initiating cue.

JPM NO: A9 PAGE 7 OF 10 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 3 Implement 0ERP01-ZV-SH01, Shift Supervisor.

Standard:

Implements 0ERP01-ZV-SH01, Shift Supervisor.

Comment:

A procedural handout will not be provided. The appropriate procedure manuals will be available in the examination area.

Cue:

Notes:

JPM NO: A9 PAGE 8 OF 10 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 4 (C)

Initiate Data Sheet 2, Alert Checklist, starting at Step A.1.

Standard:

Implements Data Sheet 2 of 0ERP01-ZV-SH01 and begins by announcing to Control Room personnel the declaration of an Alert.

Comment:

Cue:

Notes:

- TERMINATE THE JPM -

JPM STOP TIME

JPM NO: A9 PAGE 9 OF 10 VERIFICATION OF COMPLETION Job Performance Measure: A9, DECLARE EMERGENCY ACTION LEVELS Applicant's Name:

SSN:

Date Performed:

Time to Complete:

JPM Results: Sat / Unsat Evaluator: Signature __________________________

Date ____________________

JPM NO: A9 PAGE 10 OF 10 JPM - HANDOUT READ TO PERFORMER:

The evaluator will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

YOU ARE TO INFORM THE EXAMINER WHEN YOU HAVE COMPLETED THE TASK CAUTION: Do not operate or alter equipment configuration in the plant without proper authorization.

INITIAL CONDITIONS:

You are the Unit 1 Shift Supervisor and the following series of events has just occurred:

1. Complete loss of Main Feedwater while the unit was at 100% power.

2. Unit trip occurred (Main Turbine and Reactor)

3. Main Steam Line Monitor RT-8048 is indicating 1.5E-1 µci/cc and increasing.

4. All of the Annunciator Panels in the Control Room failed 15 minutes ago.

5. No steam release to the environment is present at this time.

INITIATING CUE:

Classify the event at its MINIMUM Emergency Action Level and initiate the STPEGS Emergency Plan. Portions of this JPM are time critical.

JPM NO: C1 PAGE 1 OF 18 NUCLEAR TRAINING DEPARTMENT OPERATING JOB PERFORMANCE MEASURE TITLE: DETERMINE AND ESTABLISH CONTAINMENT SPRAY PUMP REQUIREMENTS JPM NO.: C1 REVISION: 2 LOCATION: Unit 1 or 2 Control Room or Simulator

JPM NO: C1 PAGE 2 OF 18 JOB PERFORMANCE MEASURE WORKSHEET JPM

Title:

DETERMINE AND ESTABLISH CONTAINMENT SPRAY PUMP REQUIREMENTS JPM No: C1 Rev. No: 2 STP Task: 82495 Respond to a Loss of Emergency Coolant Recirculation STP Objective: 82495 Respond to a Loss of Emergency Coolant Recirculation Condition in accordance with POP05-EO-EC11 Related K/A

Reference:

013A1.06 [3.6/3.9], Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ESFAS controls including: RWST level.

026A4.01 [4.5/4.3], Ability to manually operate and/or monitor in the control room: CSS controls.

References:

0POP05-EO-EC11, Rev. 8, Loss of Emergency Coolant Recirculation Task Normally Completed By: RO or SRO Method of Testing: Simulated Location of Testing: Control Room / Simulator Time Critical Task: NO Alternate Path JPM: NO Validation Time: 20 minutes Required Materials (Tools/Equipment):

None

JPM NO: C1 PAGE 3 OF 18 JOB PERFORMANCE MEASURE INFORMATION SHEET READ TO PERFORMER (a copy of this information is included at the end of the JPM as a tear-away sheet to be given to the student):

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

YOU ARE TO INFORM THE EVALUATOR WHEN YOUVE COMPLETED THE TASK.

CAUTION: Do not operate or alter equipment configuration in the plant without proper authorization.

INITIAL CONDITIONS:

A Large Break LOCA has occurred on the primary system. Load Center E1(2)C2 lost power 10 minutes after the LOCA occurred. Control room operators have completed all steps of 0POP05-EO-EO00 and were partially through 0POP05-EO-EO10 when the RWST LO-LO Level alarm came in. The crew transitioned to and were proceeding through 0POP05-EO-ES13, TRANSFER TO COLD LEG RECIRCULATION, until they were unable to open any of the Containment Sump to SI Suction Header Valves (SI-MOV-0016A, B, & C). RCFC 11(21)B is tagged out for motor replacement and RCFC 12(22)B has tripped.

The Unit Supervisor has now transitioned to 0POP05-EO-EC11, LOSS OF EMERGENCY COOLANT RECIRCULATION, and has commenced cooldown per Step 5.

INITIATING CUE:

The Unit Supervisor directs you to continue with Step 6 and take appropriate actions per 0POP05-EO-EC11, LOSS OF EMERGENCY COOLANT RECIRCULATION.

- DO NOT DISCLOSE INFORMATION BELOW THIS LINE -

COMPLETION CRITERIA:

Containment Spray Pumps are operated in accordance with 0POP05-EO-EC11 requirements.

JPM NO: C1 PAGE 4 OF 18 JOB PERFORMANCE MEASURE INFORMATION SHEET HANDOUTS:

Working copy of 0POP05-EO-EC11, Loss of Emergency Coolant Recirculation NOTES:

This JPM will be performed statically in either the Unit 1 or Unit 2 Control Room or on a static simulator.

SIMULATOR SETUP:

1. Ensure the PA buttons on the communications consoles are taped to help eliminate usage.

2) Check and Clean the following procedures:

• 0POP05-EO-EC11, Loss of Emergency Coolant Recirculation

3. Reset to IC #1 and verify:

• Step Counter positions

• ICS restored

• Control Switch FLAGS reset

4. Leave the simulator in run. No other actions are necessary for this JPM since it is being performed statically on the simulator.

JPM NO: C1 PAGE 5 OF 18 JOB PERFORMANCE MEASURE CHECK SHEET NOTE:

• Critical steps are identified by (C).

• Sequenced steps are identified by (S1, S2, . . .).

JPM START TIME SAT/UNSAT Performance Step: 1 Obtain the procedure.

Standard:

Obtains a copy of 0POP05-EO-EC11.

Comment:

Provide the operator with a copy of 0POP05-EO-EC11.

If performed in the Simulator, applicant may use the controlled copy of the procedure in the simulator.

Cue:

Notes:

JPM NO: C1 PAGE 6 OF 18 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 2 Verify RCFCs Running. (procedure step 6a )

Standard:

Identifies three (3) RCFCs are running:

RCFC 11(21)A RCFC 12(22)A RCFC 11(21)C Comment:

1) The table below is laid out in the same order as the Control board indicating lights

2) RCFC: 11(21)B tagged out for motor replacement.

12(22)B tripped 12(22)C no power (E1(2)C2 deenergized)

Cue:

• When the applicant asks for RCFC status, provide Student Handout Attachment 1 which contains the following information.

RCFC Run 11(21)B 12(22)B 12(22)C 11(21)A 12(22)A 11(21)C Status (tagged out) (tripped) (no power)

Green Off Off Off On Off On Red On On Off Off On Off

• IF applicant asks for RCFC air temperature, report inlet temperature is 95°F on the three operating RCFCs.

Notes:

JPM NO: C1 PAGE 7 OF 18 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 3 Verify RCFC cooling water transferred to CCW. (procedure step 6b)

Standard:

Verifies RCFC cooling water transferred to CCW (for operable RCFCs):

RCB Chilled Water valves - CLOSED: CCW valves - OPEN:

MOV-0059 MOV-0057 MOV-0070 MOV-0069 MOV-0068 MOV-0137 MOV-0136 MOV-0149 MOV-0148 MOV-0147 MOV-0208 Comment:

No light indication to Train C valves due to loss of LC E1(2)C2.

MOV-0199 MOV-0209 MOV-0197 MOV-0210 Cues:

! When the applicant asks for RCFC cooling water valve status, provide Student Handout Attachment 2 which contains the following information.

(continued next page)

STEP CONTINUED NEXT PAGE

JPM NO: C1 PAGE 8 OF 18 JOB PERFORMANCE MEASURE CHECK SHEET STEP 3 (continued)

CUES:

CHWS CCW RCFC RCFC CHWS CCW SPLY RETURN RETURN 11A/12A RET 11A/12A SPLY OCIV OCIV OCIV OCIV ICIV (21A/22A) MOV-0059 MOV-0057 MOV-0070 MOV-0069 MOV-0068 Green On On Off Off Off Red Off Off On On On CHWS CCW RCFC RCFC CHWS CCW SPLY RETURN RETURN 11B/12B RET 11B/12B SPLY OCIV OCIV MOV-OCIV MOV- OCIV MOV- ICIV (21B/22B) MOV-0137 0136 0149 0148 MOV-0147 Green On On Off Off Off Red Off Off On On On CHWS CCW RCFC RCFC CHWS CCW SPLY RETURN RETURN 11C/12C RET 11C/12C SPLY OCIV OCIV MOV-OCIV MOV- OCIV MOV- ICIV (21C/22C) MOV-0199 0197 0209 0210 MOV-0208 Green Off Off Off Off Off Red Off Off Off Off On

! IF applicant checks CCW Flow to RCFCs, handout Student Handout Attachment 3 which contains the following information.

RCFC 11A(21A) 12A(22A) 11B(21B) 12B(22B) 11C(21C) 12C(22C)

Flow Indicator FI-4536 FI-4538 FI-4553 FI-4555 FI-4570 FI-4572 CCW Flow 2,000 2,000 2,000 2,000 2,000 2,000 (gpm)

Notes:

JPM NO: C1 PAGE 9 OF 18 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 4 Check RWST Level greater than 32,500 gallons (6%). (procedure step 7)

Standard:

Checks RWST level using any MCB Meter/Recorder or ICS/QDPS.

Comment:

Cue:

1) RWST level channels (LI-931, LI-932) or level recorder (LR-931) = 73,000 gallons.

2) ICS or QDPS indication = 73,000 gallons Notes:

ICS is the Integrated Computer System (plant computer) with CRT displays.

QDPS is the computer system with plasma displays.

JPM NO: C1 PAGE 10 OF 18 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 5 Verify containment spray pump suction - ALIGNED TO RWST. (procedure step 8a )

Standard:

Determines Containment Spray Pump suction is aligned to the RWST.

Comment:

Cue:

CNTMT SUMP TO SI SUCT HDR RWST TO SI SUCT HDR ISOL, Train A ISOL, SI-MOV-0016A SI-MOV-0001A Green On Off Red Off On CNTMT SUMP TO SI SUCT HDR RWST TO SI SUCT HDR ISOL, Train B ISOL, SI-MOV-0016B SI-MOV-0001B Green On Off Red Off On CNTMT SUMP TO SI SUCT HDR RWST TO SI SUCT HDR ISOL, Train C ISOL, SI-MOV-0016C SI-MOV-0001C (No power) (No power)

Green Off Off Red Off Off Notes:

JPM NO: C1 PAGE 11 OF 18 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 6 (C)

Determine the Containment Spray Pump Operating Requirements. (procedure step 8b)

Standard:

Determines TWO (2) Containment Spray Pumps should be running.

Comment:

The operator should use RWST Level, CNTMT Pressure and RCFC status to determine that two (2) Containment Spray Pumps should be running.

Cue:

• RWST level channels (LI-931, LI-932), or recorder (LR-931) = 61,000 gallons.

• ICS/QDPS = 61,000 gallons.

• Containment pressure (PR-935/934, PR-9759, or ICS/QDPS) = 9.0 psig.

Notes:

JPM NO: C1 PAGE 12 OF 18 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 7 Verify Containment Spray Pumps running - EQUAL TO NUMBER REQUIRED.

(procedure step 8c)

Standard:

Identifies THREE (3) Containment Spray Pumps are running and only TWO (2) required.

Comment:

Cue:

Run CSS PUMP 1(2)A CSS PUMP 1(2)B CSS PUMP 1(2)C Status Green Off Off Off Red On On On Discharge CSS PUMP 1(2)A CSS PUMP 1(2)B CSS PUMP 1(2)C Flow Indicator FI-0813A FI-0823A FI-0833 Flow 2,200 2,300 2,250 (gpm)

Discharge CSS PUMP 1(2)A CSS PUMP 1(2)B CSS PUMP 1(2)C Valve Number MOV-0001A MOV-0001B MOV-0001C Red - ON Red - ON Red - OFF Status Green - OFF Green - OFF Green - OFF

! Unit Supervisor directs that a CS Pump be secured after need to secure 1 pump is identified.

Notes:

JPM NO: C1 PAGE 13 OF 18 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 8(C)

Manually Operate Containment Spray Pumps. (procedure step RNO 8c)

Standard:

Secures a Containment Spray Pump:

Comment:

The Containment Spray actuation signal has NOT been reset. If the operator places CSS pump control switch to stop and returns to auto, the pump will remain running. The operator must take control switch to PTL or reset containment spray actuation signal to stop the pump.

(Logic Diagram: 9-Z-42130 #2)

Cue:

! IF selected CS Pump handswitch is turned to OFF and applicant asks:

The selected pump lights are: Red - On; Green - Off AND If applicant informs Unit Supervisor or requests direction THEN direct applicant to place the selected CS Pump handswitch in Pull-To-Lock (PTL)

! IF CS Pump handswitch turned to PTL:

The pump lights are: Green - On; Red - Off Notes:

- TERMINATE THE JPM -

JPM STOP TIME

JPM NO: C1 PAGE 14 OF 18 VERIFICATION OF COMPLETION Job Performance Measure: C1, DETERMINE AND ESTABLISH CONTAINMENT SPRAY PUMP REQUIREMENTS Applicant's Name:

SSN:

Date Performed:

Time to Complete:

JPM Results:

Sat / Unsat Evaluator: Signature __________________________

Date ____________________

JPM NO: C1 PAGE 15 OF 18 JPM - STUDENT HANDOUT READ TO PERFORMER:

The evaluator will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

YOU ARE TO INFORM THE EVALUATOR WHEN YOUVE COMPLETED THE TASK.

CAUTION: Do not operate or alter equipment configuration in the plant without proper authorization.

INITIAL CONDITIONS:

A Large Break LOCA has occurred on the primary system. Load Center E1(2)C2 lost power 10 minutes after the LOCA occurred. Control room operators have completed all steps of 0POP05-EO-EO00 and were partially through 0POP05-EO-EO10 when the RWST LO-LO Level alarm came in. The crew transitioned to and were proceeding through 0POP05-EO-ES13, TRANSFER TO COLD LEG RECIRCULATION, until they were unable to open any of the Containment Sump to SI Suction Header Valves (SI-MOV-0016A, B, & C). RCFC 11(21)B is tagged out for motor replacement and RCFC 12(22)B has tripped.

The Unit Supervisor has now transitioned to 0POP05-EO-EC11, LOSS OF EMERGENCY COOLANT RECIRCULATION, and has commenced cooldown per Step 5.

INITIATING CUE:

The Unit Supervisor directs you to continue with Step 6 and take appropriate actions per 0POP05-EO-EC11, LOSS OF EMERGENCY COOLANT RECIRCULATION.

JPM NO: C1 PAGE 16 OF 18 JPM - STUDENT HANDOUT ATTACHMENT 1 RCFC Run 11(21)B 12(22)B 12(22)C 11(21)A 12(22)A 11(21)C Status (tagged out) (tripped) (no power)

Green Off Off Off On Off On Red On On Off Off On Off

JPM NO: C1 PAGE 17 OF 18 JPM - STUDENT HANDOUT ATTACHMENT 2 CHWS CCW RCFC RCFC CHWS CCW SPLY RETURN RETURN 11A/12A RET 11A/12A SPLY OCIV OCIV OCIV OCIV ICIV (21A/22A) MOV-0059 MOV-0057 MOV-0070 MOV-0069 MOV-0068 Green On On Off Off Off Red Off Off On On On CHWS CCW RCFC RCFC CHWS CCW SPLY RETURN RETURN 11B/12B RET 11B/12B SPLY OCIV OCIV MOV-OCIV MOV- OCIV MOV- ICIV (21B/22B) MOV-0137 0136 0149 0148 MOV-0147 Green On On Off Off Off Red Off Off On On On CHWS CCW RCFC RCFC CHWS CCW SPLY RETURN RETURN 11C/12C RET 11C/12C SPLY OCIV OCIV MOV-OCIV MOV- OCIV MOV- ICIV (21C/22C) MOV-0199 0197 0209 0210 MOV-0208 Green Off Off Off Off Off Red Off Off Off Off On

JPM NO: C1 PAGE 18 OF 18 JPM - STUDENT HANDOUT ATTACHMENT 3 RCFC 11A(21A) 12A(22A) 11B(21B) 12B(22B) 11C(21C) 12C(22C)

Flow Indicator FI-4536 FI-4538 FI-4553 FI-4555 FI-4570 FI-4572 CCW Flow 2,000 2,000 2,000 2,000 2,000 2,000 (gpm)

JPM NO: P1 PAGE 1 OF 16 NUCLEAR TRAINING DEPARTMENT OPERATING JOB PERFORMANCE MEASURE TITLE: PERFORM LOCAL CHANNEL CHECK OF RT-8038 (WITH PLUGGED IN-SERVICE FLOW STRAINER)

JPM NO.: P1 REVISION: 2 LOCATION: UNIT 1 or 2

JPM NO: P1 PAGE 2 OF 16 JOB PERFORMANCE MEASURE WORKSHEET JPM

Title:

PERFORM LOCAL CHANNEL CHECK OF RT-8038 (WITH PLUGGED IN-SERVICE FLOW STRAINER)

JPM No.: P1 Rev. No: 2 STP Task: 30100, Operate the Liquid Waste Processing Subsystem.

STP Objective: NLO 30100, Given the specified procedure(s), logs/forms, tools, and equipment, Operate the Liquid Waste Processing Subsystem (LWPS) IAW the specified procedures, with no assistance allowed in operating the system.

Related K/A

Reference:

072 A4.01 [3.0/3.3] Ability to manually operate and/or monitor alarm and interlock setpoint checks and adjustments.

References:

OPOP02-WL-0100, Rev. 5, Liquid Waste Release Task Normally Completed By: PO Method of Testing: Simulated Location of Testing: Plant Time Critical Task: NO Alternate Path JPM: YES Validation Time: 15 minutes Required Materials (Tools/Equipment):

None

JPM NO: P1 PAGE 3 OF 16 JOB PERFORMANCE MEASURE INFORMATION SHEET READ TO PERFORMER (a copy of this information is included at the end of the JPM as a tear-away sheet to be given to the applicant):

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

YOU ARE TO INFORM THE EVALUATOR WHEN YOUVE COMPLETED THE TASK.

CAUTION: Do not operate or alter equipment configuration in the plant without proper authorization.

INITIAL CONDITIONS:

You are the MAB Operator. Preliminary steps 5.1 through 5.15 of 0POP02-WL-0100 have been completed in preparation for release of Waste Monitor Tank 1C(2C). Chemistry has returned the Release Package, proper dilution flowrate has been verified, and Waste Monitor Tank 1C(2C) has been on recirc for 60 minutes. RT-8038, Liquid Waste Effluent Radiation Monitor, is OPERABLE.

INITIATING CUE:

The Unit Supervisor directs you to locally perform a channel check on RT-8038, Liquid Waste Effluent Radiation Monitor in accordance with 0POP02-WL-0100, step 5.16.

- DO NOT DISCLOSE INFORMATION BELOW THIS LINE -

COMPLETION CRITERIA:

A satisfactory channel check of RT-8038, using the Standby LWPS RT-8038 Flow Strainer, has been performed locally in accordance with 0POP02-WL-0100.

JPM NO: P1 PAGE 4 OF 16 JOB PERFORMANCE MEASURE INFORMATION SHEET HANDOUTS:

Working copy 0POP02-WL-0100, Liquid Waste Release NOTES:

1) This is an Alternate Path JPM due to the fact that the first attempt to perform a channel check on RT-8038 fails (on low flow) because the in service flow strainer is plugged.

The operator must place the standby strainer in service and re-attempt the channel check.

2) The Handout copy of the procedure has been signed off up to step 5.16.

3) This JPM should be performed in conjunction with P3, and after, JPM A-4, Determine Radiological Requirements to Enter a High Rad Area. This to help ensure a smooth flow of the exam schedule.

4) The NRC Evaluator will use RWP- and use as the WAN.

JPM NO: P1 PAGE 5 OF 16 JOB PERFORMANCE MEASURE CHECK SHEET NOTE:

• Critical steps are identified by (C).

• Sequenced steps are identified by (S1, S2, . . .).

JPM START TIME SAT/UNSAT Performance Step: 1 Obtain the procedure and review the Prerequisites and the Notes and Precautions.

Standard:

1) Obtains a copy of 0POP02-WL-0100, Liquid Waste Release

2) Reviews the Prerequisites and the Notes and Precautions.

Comment:

Provide the Handout copy of the applicable section of the procedure.

Cue:

Notes:

JPM NO: P1 PAGE 6 OF 16 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 2 Notify the control room that a channel check and source check of RT-8038 will be performed and that an alarm may actuate and be locked in until the setpoints are reset.

(procedure steps 5.16.1 and 5.16.2)

Standard:

Notifies the Control Room that the following will occur on RT-8038 :

• Channel Check

• Source Check

• Alarm may actuate and lock in until reset Comment:

The applicant should proceed to the MAB 10' elevation, Room 72 - Floor Drain Tank Pump 1B (2B) Room Cue:

The Control Room acknowledges the report.

Notes:

JPM NO: P1 PAGE 7 OF 16 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 3 (C)

Open RT-8038 Inlet and Outlet Sample Isolation Valves. (procedure steps 5.16.3 and 5.16.4)

Standard:

1) Opens 1(2)-SRA-3267, WMT PUMPS 1A, B & C DISCHARGE RT-8038 SAMPLE INLET VALVE

2) Opens 1(2)-SRA-3268, WMT PUMPS 1A, B & C DISCHARGE RT-8038 SAMPLE OUTLET VALVE Comment:

1) All RT-8038 local components are located on the 10' elevation of the MAB in Room 072, Floor Drain Tank Pump 1B (2B) Room

2) Inlet and Outlet valves are located at top-center of the RT-8038 Skid.

Cue:

SRA-3267 and SRA-3268: Initially - CLOSED Finally - OPEN Notes:

JPM NO: P1 PAGE 8 OF 16 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 4 (C)

Place local Sample Pump handswitch to AUTO. (procedure steps 5.16.5)

Standard:

Places the Sample PUMP handswitch to AUTO on Panel N1(2)RAPCC8038.

Comment:

1) The panel is on the left side of the RT-8038 skid when facing it.

2) The RT-8038 skid is in the same room and area in both Units, however, the skid faces South in Unit 1 and North in Unit 2.

Cue:

PUMP HANDSWITCH: Initially - OFF Finally - AUTO Notes:

JPM NO: P1 PAGE 9 OF 16 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 5 Depress the PUMP ON/OFF pushbutton on the local panel. (procedure step 5.16.6)

Standard:

Depresses the PUMP ON/OFF pushbutton inside the control panel 1(2)-RA-RT-8038.

Comment:

Pushbutton located inside the control panel.

Cue:

• PUMP ON/OFF pushbutton: Initially - OFF Finally - BACKLIT

• If applicant asks about the pump RED light: Initially - OFF Finally - ON Notes:

JPM NO: P1 PAGE 10 OF 16 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 6 Observe channel check is satisfactory as indicated by illumination of green light on front of monitor. (procedure step 5.16.7)

Standard:

Attempts to verify Green OPERATE Light illuminated on front of control panel 1(2)-RA-RT-8038".

Comment:

Large Green Light located outside right control panel.

Cue:

• Green OPERATE Light: Initially - OFF Finally - OFF

• If applicant desires to replace light bulb, tell applicant the Green OPERATE light is OFF.

• If applicant asks about the pump RED light: RED LIGHT - ON (The pump will start and then automatically turn off with no flow for 60 seconds)

Notes:

ALTERNATE PATH - Applicant will expect the Green OPERATE Light to be LIT, however, the light will not illuminate at this time (due to a plugged in-service flow strainer). Contingency actions must be taken to place the standby flow strainer in service and restart the sample pump.

JPM NO: P1 PAGE 11 OF 16 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 7 Ensure the sample pump has stopped. (procedure step 5.16.9.1 )

Standard:

Depresses the PUMP ON/OFF pushbutton inside the control panel 1(2)-RA-RT-8038.

Comment:

Pushbutton located inside the control panel.

Cue:

• PUMP ON/OFF pushbutton: Initially - BACKLIT Finally - OFF

• If applicant asks about the pump RED light: Initially - ON Finally - OFF Notes:

JPM NO: P1 PAGE 12 OF 16 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 8 (C)

Place the standby LWPS Monitor RT-8038 Flow Strainer in service. (procedure step 5.16.9.2)

Standard:

Selects the standby LWPS MONITOR RT-8038 FLOW STRAINER using yellow T-handle.

Comment:

The selector must first be unlocked using the silver T-handle on top of the strainer; then the yellow T-handle rotated to the position of the opposite strainer. The silver T-handle is then turned to lock the yellow T-handle in place.

Cue:

Yellow T-handle selector is positioned to the desired strainer.

Notes:

JPM NO: P1 PAGE 13 OF 16 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 9 (C)

Depress the PUMP ON/OFF pushbutton on the local panel. (procedure step 5.16.9.3 )

Standard:

Depresses the PUMP ON/OFF pushbutton inside the control panel 1(2)-RA-RT-8038.

Comment:

Pushbutton located inside the control panel.

Cue:

• PUMP ON/OFF pushbutton: Initially - OFF Finally - BACKLIT

• If applicant asks about the pump RED light: Initially - OFF Finally - ON Notes:

JPM NO: P1 PAGE 14 OF 16 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 10 Observe channel check is satisfactory as indicated by illumination of green operate light on front of monitor. (procedure step 5.16.9.4 )

Standard:

Verifies Green OPERATE light illuminated on front of control panel 1(2)-RA-RT-8038.

Comment:

Large Green Light located outside right control panel.

Cue:

Green OPERATE light: Initially - OFF Finally - ON Notes:

- TERMINATE THE JPM -

JPM STOP TIME

JPM NO: P1 PAGE 15 OF 16 VERIFICATION OF COMPLETION Job Performance Measure: P1, PERFORM LOCAL CHANNEL CHECK OF RT-8038 (WITH PLUGGED IN SERVICE FLOW STRAINER)

Applicant's Name:

SSN:

Date Performed:

Time to Complete:

JPM Results: Sat / Unsat Evaluator: Signature __________________________

Date ____________________

JPM NO: P1 PAGE 16 OF 16 JPM - STUDENT HANDOUT READ TO PERFORMER:

The evaluator will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

YOU ARE TO INFORM THE EVALUATOR WHEN YOUVE COMPLETED THE TASK.

CAUTION: Do not operate or alter equipment configuration in the plant without proper authorization.

INITIAL CONDITIONS:

You are the MAB Operator. Preliminary steps 5.1 through 5.15 of 0POP02-WL-0100 have been completed in preparation for release of Waste Monitor Tank 1C(2C). Chemistry has returned the Release Package, proper dilution flowrate has been verified, and Waste Monitor Tank 1C(2C) has been on recirc for 60 minutes. RT-8038, Liquid Waste Effluent Radiation Monitor, is OPERABLE.

INITIATING CUE:

The Unit Supervisor directs you to locally perform a channel check on RT-8038, Liquid Waste Effluent Radiation Monitor in accordance with 0POP02-WL-0100, step 5.16.

JPM NO: P2 PAGE 1 OF 10 NUCLEAR TRAINING DEPARTMENT OPERATING JOB PERFORMANCE MEASURE TITLE: LOCALLY OPEN REACTOR TRIP AND BYPASS BREAKERS JPM NO.: P2 REVISION: 2 LOCATION: Unit 1 or 2

JPM NO: P2 PAGE 2 OF 10 JOB PERFORMANCE MEASURE WORKSHEET JPM

Title:

LOCALLY OPEN REACTOR TRIP AND BYPASS BREAKERS JPM No.: P2 Rev. No.: 2 STP Task: 2600, Manually trip the reactor.

STP Objective: 2600, When required, manually trip the reactor.

Related K/A

Reference:

EPE 029 EA1.11 [3.9/4.1] Ability to operate and monitor the following as they apply to a ATWS: Manual opening of the CRDS breakers.

References:

0POP05-EO-FRS1, Rev. 9, RESPONSE TO NUCLEAR POWER GENERATION - ATWS Task Normally Completed By: PO/RO Method of Testing: Simulated Location of Testing: Plant Time Critical Task: NO Alternate Path JPM: YES Validation Time: 15 minutes Required Materials (Tools/Equipment):

None

JPM NO: P2 PAGE 3 OF 10 JOB PERFORMANCE MEASURE INFORMATION SHEET READ TO PERFORMER (a copy of this information is included at the end of the JPM as a tear-away sheet to be given to the student):

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

YOU ARE TO INFORM THE EVALUATOR WHEN YOUVE COMPLETED THE TASK.

CAUTION: Do not operate or alter equipment configuration in the plant without proper authorization.

INITIAL CONDITIONS:

An ATWS occurred; the Reactor Trip Breakers can not be opened using either of the reactor trip switches. The Primary Operator is inserting control rods per Step 1, 0POP05-EO-FRS1, Response to Nuclear Power Generation - ATWS.

INITIATING CUE:

The Unit Supervisor directs you to perform the remainder of the Immediate Action steps of 0POP05-EO-FRS1, Response to Nuclear Power Generation - ATWS.

- DO NOT DISCLOSE INFORMATION BELOW THIS LINE -

COMPLETION CRITERIA:

The operator has SIMULATED opening the Reactor Trip and Bypass Breakers.

JPM NO: P2 PAGE 4 OF 10 JOB PERFORMANCE MEASURE INFORMATION SHEET HANDOUTS:

None NOTES:

1) This JPM STARTS in the Control Room where the applicant attempts to trip the reactor.

2) This is an Alternate Path JPM due to the fact that the first attempt to trip the reactor by opening the motor generator set feeder breakers does not work as expected. The applicant must then take measures to trip the reactor by locally opening the reactor trip breakers.

3) The actions contained in this JPM are Immediate Actions of 0POP05-EO-FRS1, Response to Nuclear Power Generation - ATWS, and are to be completed without the aid of an in-hand procedure.

JPM NO: P2 PAGE 5 OF 10 JOB PERFORMANCE MEASURE CHECK SHEET NOTE:

• Critical steps are identified by (C).

• Sequenced steps are identified by (S1, S2, . . .).

SAT/UNSAT Performance Step: 1(C)

Open 480V LC 1K1 and 1L1 feeder breakers.

Standard:

The applicant simulates opening 480V LC 1K1 and 1L1 feeder breakers.

Comment:

Cue:

• LC 1K1 feeder breaker failed to open (red light ON, green light OFF)

• LC 1L1 feeder breaker opens as expected (green light ON, red light OFF)

• If asked by applicant if Reactor is tripped after attempting to open breakers, inform applicant the Reactor is NOT tripped.

• If questioned by the applicant, or if the applicant attempts to contact a Plant Operator, as the Unit Supervisor, direct the applicant to continue the immediate actions of 0POP05-EO-FRS1 by performing the necessary actions outside of the Control Room.

Notes:

JPM NO: P2 PAGE 6 OF 10 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 2 (C)

Go to the Rod Control Equipment Room (60 ft EAB RM 323).

Standard:

The applicant proceeds to the Rod Control Equipment Room on the 60 ft. elevation of the EAB.

Comment:

Cue:

Notes:

JPM NO: P2 PAGE 7 OF 10 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 3 (C)

Open the reactor trip breakers.

Standard:

The applicant SIMULATES pushing the trip button for the reactor trip breakers.

Reactor Trip Breaker R Reactor Trip Breaker S Comment:

DO NOT OPEN REACTOR TRIP BREAKER DOORS. Simply inform the applicant that if he were to open the door, that the RED SHUT flag would be dropped, and the GREEN OPEN flag displayed.

Cue:

• The RED flag that says "SHUT" drops. The GREEN flag that says "OPEN" is displayed.

• The control room reports that they have open indication.

Notes:

JPM NO: P2 PAGE 8 OF 10 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 4 Verify that the reactor trip bypass breakers are open.

Standard:

The applicant verifies that the Reactor Trip Bypass Breakers are open.

Bypass Breaker R Bypass Breaker S Comment:

DO NOT OPEN REACTOR TRIP BYPASS BREAKER DOORS. Simply inform the applicant that if he were to open the door, that the GREEN OPEN flag would be displayed.

Under normal conditions the Bypass Breakers are open and racked out.

Cue:

The GREEN flag that says "OPEN" is displayed.

Notes:

- TERMINATE THE JPM -

JPM STOP TIME ________

JPM NO: P2 PAGE 9 OF 10 VERIFICATION OF COMPLETION Job Performance Measure: P2, LOCALLY OPEN REACTOR TRIP AND BYPASS BREAKERS Applicants Name:

SSN:

Date Performed:

Time to Complete:

JPM Results: Sat / Unsat Evaluator: Signature Date

JPM NO: P2 PAGE 10 OF 10 JPM - STUDENT HANDOUT READ TO PERFORMER:

The evaluator will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

YOU ARE TO INFORM THE EVALUATOR WHEN YOUVE COMPLETED THE TASK.

CAUTION: Do not operate or alter equipment configuration in the plant without proper authorization.

INITIAL CONDITIONS:

An ATWS occurred; the Reactor Trip Breakers can not be opened using either of the reactor trip switches. The Primary Operator is inserting control rods per Step 1, 0POP05-EO-FRS1, Response to Nuclear Power Generation - ATWS.

INITIATING CUE:

The Unit Supervisor directs you to perform the remainder of the Immediate Action steps of 0POP05-EO-FRS1, Response to Nuclear Power Generation - ATWS.

JPM NO: P3 PAGE 1 OF 11 NUCLEAR TRAINING DEPARTMENT OPERATING JOB PERFORMANCE MEASURE TITLE: SECURE ALTERNATE BORATION JPM NO.: P3 REVISION: 2 LOCATION: UNIT 1 OR 2

JPM NO: P3 PAGE 2 OF 11 JOB PERFORMANCE MEASURE WORKSHEET JPM

Title:

SECURE ALTERNATE BORATION JPM No.: P3 Rev. No: 2 STP Task: NLO 81000, Perform MAB/EAB watchstation actions for Control Room Evacuation.

STP Objective: 81000, With the Control Room evacuated, respond as MAB/EAB watch to the Control Room Evacuation, by performing the watchstation actions IAW POP04-ZO-0001.

Related K/A

Reference:

APE 068 AA1.08 [4.2/4.2] Ability to operate and/or monitor the following as they apply to the Control Room Evacuation: Local boric acid flow.

References:

0POP04-ZO-0001, Rev. 13, Control Room Evacuation Task Normally Completed By: PO/RO/SRO Method of Testing: Simulated Location of Testing: Plant Time Critical Task: NO Alternate Path JPM: NO Validation Time: 15 minutes Required Materials (Tools/Equipment):

None

JPM NO: P3 PAGE 3 OF 11 JOB PERFORMANCE MEASURE INFORMATION SHEET READ TO PERFORMER (a copy of this information is included at the end of the JPM as a tear-away sheet to be given to the student):

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

YOU ARE TO INFORM THE EVALUATOR WHEN YOUVE COMPLETED THE TASK.

CAUTION: Do not operate or alter equipment configuration in the plant without proper authorization.

INITIAL CONDITIONS:

The Control Room has been evacuated and the operating crew is performing the actions of 0POP04-ZO-0001, Control Room Evacuation, with all watchstations manned in the EAB.

The RCS is being borated using gravity drain to the charging pump (Alternate Boration).

INITIATING CUE:

The Shift Supervisor directs you as the extra RO to secure Alternate Boration in accordance with Addendum 10, Step 1.g. of 0POP04-ZO-0001, Control Room Evacuation.

- DO NOT DISCLOSE INFORMATION BELOW THIS LINE -

COMPLETION CRITERIA:

Charging pump suction has been re-aligned to the RWST and boric acid gravity drain to the charging pump is isolated.

JPM NO: P3 PAGE 4 OF 11 JOB PERFORMANCE MEASURE INFORMATION SHEET HANDOUTS:

Working copy of 0POP04-ZO-0001, Addendum 10 NOTES:

This JPM should be performed in conjunction with P1, and after, JPM A-4, Determine Radiological Requirements to Enter a High Rad Area. This to help ensure a smooth flow of the exam schedule.

1) The NRC Evaluator will use RWP- and use as the WAN.

JPM NO: P3 PAGE 5 OF 11 JOB PERFORMANCE MEASURE CHECK SHEET NOTE:

• Critical steps are identified by (C).

• Sequenced steps are identified by (S1, S2, . . .).

JPM START TIME SAT/UNSAT Performance Step: 1 Obtain a copy of the procedure.

Standard:

Obtains a copy of Addendum 10 to 0POP04-ZO-0001.

Comment:

Provide the Handout Copy of 0POP04-ZO-0001, Addendum 10.

Cue:

Notes:

JPM NO: P3 PAGE 6 OF 11 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 2 (C) (S1)

Direct ESF Switchgear Operators to open and de-energize the following valves:

• CV-MOV-112C, RWST TO CHG PUMP SUCTION ISOL

• CV-MOV-0113B, RWST TO CHG PUMP SUCTION ISOL (Addendum 10, step 1.g.1)

Standard:

Directs the ESF Switchgear Operators to perform step 1.g.1 of Addendum 10 which opens and de-energizes CV-MOV-0112C and CV-MOV-0113B by:

• Contacting the operator at the Aux Shutdown Panel to relay the message to the ESF Switchgear Operators using a radio, OR

• Going to the 35 ft and 60 ft ESF Switchgear Rooms to give the direction to the Switchgear Operators.

Comment:

This step must be performed first to prevent a loss of suction to the running charging pump.

Cue:

Respond as Auxiliary Shutdown Panel Operator or ESF Switchgear Operator(s):

CV-MOV-0112C and CV-MOV-0113B have been opened AND de-energized.

Notes:

JPM NO: P3 PAGE 7 OF 11 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 3 (*C) (S2)

Close and lock 1(2)-CV-0226, MANUAL BORATION. (Addendum 10, step 1.g.2.a)

Standard:

Closes AND locks 1(2)-CV-0226, MANUAL BORATION.

Comment:

• Either this step or JPM step #5 must be completed to satisfy the critical step requirement.

Cue:

• Valve is initially unlocked and open

• Final condition is closed AND locked Notes:

Valve is located on the 19 ft elevation of the MAB, Room 079.

JPM NO: P3 PAGE 8 OF 11 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 4 (S2)

Close the following valves: (Addendum 10, steps 1.g.2.b and 1.g.2.c)

• 1(2)-CV-0335A, BA BATCHING TANK 1A(2A) TO BA TRANSFER PUMP

• 1(2)-CV-0335B, BA BATCHING TANK 1B(2B) TO BA TRANSFER PUMP Standard:

Closes the following valves:

___ 1(2)-CV-0335A, BA BATCHING TANK 1A(2A) TO BA TRANSFER PUMP

___ 1(2)-CV-0335B, BA BATCHING TANK 1B(2B) TO BA TRANSFER PUMP Comment:

Cue:

• Initial condition for each valve - OPEN

• Final condition for each valve - CLOSED Notes:

Valves are located on the 10 ft MAB, in rooms 018A and 018 respectively.

JPM NO: P3 PAGE 9 OF 11 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 5 (*C) (S2)

Close 1(2)-CV-0333, BA TANK 1A(2A) TO CHARGING PUMPS SUCTION ISOL (Addendum 10, step 1.g.2.d)

Standard:

Closes 1(2)-CV-0333, BA TANK 1A(2A) TO CHARGING PUMPS SUCTION ISOL Comment:

• Either this step or JPM step #3 must be completed to satisfy the critical step requirement.

Cue:

• Valve is initially open

• Final condition of the valve is closed Notes:

Valve is located on 19 ft MAB, Room 076

- TERMINATE THE JPM -

JPM STOP TIME

JPM NO: P3 PAGE 10 OF 11 VERIFICATION OF COMPLETION Job Performance Measure: P3, SECURE ALTERNATE BORATION Applicant's Name:

SSN:

Date Performed:

Time to Complete:

JPM Results: Sat / Unsat Evaluator: Signature Date

JPM NO: P3 PAGE 11 OF 11 JPM - STUDENT HANDOUT READ TO PERFORMER:

The evaluator will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

YOU ARE TO INFORM THE EVALUATOR WHEN YOUVE COMPLETED THE TASK.

CAUTION: Do not operate or alter equipment configuration in the plant without proper authorization.

INITIAL CONDITIONS:

The Control Room has been evacuated and the operating crew is performing the actions of 0POP04-ZO-0001, Control Room Evacuation, with all watchstations manned in the EAB.

The RCS is being borated using gravity drain to the charging pump (Alternate Boration).

INITIATING CUE:

The Shift Supervisor directs you as the extra RO to secure Alternate Boration in accordance with Addendum 10, Step 1.g. of 0POP04-ZO-0001, Control Room Evacuation.

JPM NO: S1 PAGE 1 OF 18 NUCLEAR TRAINING DEPARTMENT OPERATING JOB PERFORMANCE MEASURE TITLE: RESTORE OFFSITE POWER TO ESF BUSES JPM NO.: S1 REVISION: 1 LOCATION: Simulator

JPM NO: S1 PAGE 2 OF 18 JOB PERFORMANCE MEASURE WORKSHEET JPM

Title:

RESTORE OFFSITE POWER TO ESF BUSES JPM No.: S1 Rev. No.: 1 STP Task: 44650 Transfer an Emergency Bus from the Emergency Diesel Generator to offsite power.

STP Objective: 44650 Transfer an ESF BUS from the Emergency Diesel Generator to offsite power IAW 0POP02-DG-0001/2/3 until the diesel is back in normal standby lineup.

Related K/A

Reference:

062 A4.07 [3.1/3.1], Ability to manually operate and/or monitor in the control room: Synchronizing and paralleling of different AC supplies.

064 A3.06 [3.3/3.4], Ability to monitor automatic operation of the ED/G system, including: Start and stop.

064 A4.01 [4.0/4.3], Ability to manually operate and/or monitor in the control room: Local and remote operation of the ED/G.

References:

0POP02-DG-0003, Rev. 28, Emergency Diesel Generator 13(23)

Task Normally Completed By: RO/SRO Method of Testing: Actual Performance Location of Testing: Simulator Time Critical Task: NO Alternate Path JPM: NO Validation Time: 20 minutes Required Materials (Tools/Equipment):

None

JPM NO: S1 PAGE 3 OF 18 JOB PERFORMANCE MEASURE INFORMATION SHEET READ TO PERFORMER (a copy of this information is included at the end of the JPM as a tear-away sheet to be given to the student):

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

YOU ARE TO INFORM THE EVALUATOR WHEN YOUVE COMPLETED THE TASK.

CAUTION: Do not operate or alter equipment configuration in the plant without proper authorization.

INITIAL CONDITIONS:

A Large Break LOCA has occurred 5.5 hours0.208 days <br />0.0298 weeks <br />0.00685 months <br /> ago. Additionally, a fault occurred on 4.16KV ESF BUS E1C supply breaker E1C/1. Emergency Diesel Generator 13 started and loaded normally.

The C ESF BUS supply breaker E1C/1 has been repaired and re-installed.

INITIATING CUE:

The Unit Supervisor directs you to restore normal off-site power to 4.16KV ESF Bus C and place ESF Diesel Generator 13 in a cooldown cycle in accordance with 0POP02-DG-0003, Emergency Diesel Generator 13(23). The requirement for having a second operator and the Unit /Shift Supervisor available during the synchronization task has been waived by the Shift Supervisor.

- DO NOT DISCLOSE INFORMATION BELOW THIS LINE -

COMPLETION CRITERIA:

4.16KV ESF bus E1C is being supplied from its associated standby bus. ESF Diesel Generator 13 is in a cooldown cycle.

HANDOUTS:

Working copy of 0POP02-DG-0003, Emergency Diesel Generator 13(23) will be available in the simulator.

JPM NO: S2 PAGE 4 OF 18 JOB PERFORMANCE MEASURE INFORMATION SHEET NOTES:

1. This JPM is formatted for dynamic simulator performance only. The cues provided are related to communications and other general information needed for dynamic performance.

(NO Indication type Cues are provided).

2. The JPM will flow more smoothly if the evaluator provides the cues for the local operator.

3. Use the Simulator Setup section below to prepare the simulator.

SIMULATOR SETUP:

1. JPMs S1 and S2 are to run together. The following steps will set up the simulator for BOTH JPMs.

2. Ensure Radio volume for both stations are set to a reasonable level.

3. Ensure the PA buttons on the communications consoles are taped to help eliminate usage.

4. Check and Clean the following procedures:

• 0POP05-EO-ES14, Transfer to Hot Leg Recirculation

• 0POP02-DG-0003, Emergency Diesel Generator 13(23)

5. Reset to IC #69 and verify:

• Step counter positions

• ICS restored

• Control Switch FLAGS reset

JPM NO: S1 PAGE 5 OF 18 JOB PERFORMANCE MEASURE CHECK SHEET NOTE:

• Critical steps are identified by (C).

• Sequenced steps are identified by (S1, S2, . . .).

JPM START TIME SAT/UNSAT Performance Step: 1 Obtain a copy of the applicable Emergency Diesel Generator procedure.

Standard:

The operator obtains a copy of 0POP02-DG-0003, Emergency Diesel Generator 13(23).

Comment:

Provide the Handout copy of 0POP02-DG-0003, or the operator may use the simulator copy of the procedure.

Cue:

Notes:

JPM NO: S1 PAGE 6 OF 18 JOB PERFORMANCE MEASURE CHECK SHEET (cont'd)

SAT/UNSAT Performance Step: 2 The operator reviews the Notes and Precautions section of 0POP02-DG-0003, Emergency Diesel Generator 13(23).

Standard:

The operator reviews the Notes and Precautions section of the procedure and goes to "Section 9.0, Transferring 4.16 KV Bus E1C(E2C) from Diesel Generator 13(23) to Offsite Supply."

Comment:

Cue:

Throughout this JPM, IF applicant asks the local operator to investigate the cause of a DG13 TROUBLE alarm, report alarm is due to Standpipe level off-normal.

Notes:

SAT/UNSAT Performance Step: 3 VERIFY Diesel Generator 13 is the only source of power to ESF Bus E1C. (Procedure step 9.1)

Standard:

The operator checks to ensure that Diesel Generator 13 is the only source of power to ESF Bus E1C.

Comment:

Cue:

Notes:

JPM NO: S1 PAGE 7 OF 18 JOB PERFORMANCE MEASURE CHECK SHEET (cont'd)

SAT/UNSAT Performance Step: 4 Verify breaker alignment for transfer of power supply from Diesel Generator 13 to Standby Bus 1H. (Procedure step 9.2)

Standard:

The Operator ENSURES each of the following is in the proper position on CP-010:

"EMER BUS 1L TO XFMR E1C BKR SW-EMER" is OPEN "EMER BUS 1L TO XFMR E1C DISC SW-EMER" is OPEN "STBY BUS 1H TO XFMR E1C DISC SW-NORM" is CLOSED "STBY BUS 1H TO XFMR E1C BKR SW-NORM" is CLOSED Comment:

If the operator asks for clarification, tell him that the Unit Supervisor has directed that the bus be energized from STBY Bus 1H (which is energized from UNIT 1 STBY XFMR).

Procedure step 9.3, Tranferring ESF DG to Emergency Bus 1L, is N/A .

Cue:

Notes:

JPM NO: S1 PAGE 8 OF 18 JOB PERFORMANCE MEASURE CHECK SHEET (cont'd)

SAT/UNSAT Performance Step: 5 ENSURE any activated protective relays reset. {ZLP105} (Procedure step 9.4)

Standard:

The operator directs a Plant Operator to locally reset any protective relay that may have tripped.

Comment:

Cue:

As Plant Operator, report no protective relays have tripped.

Notes:

SAT/UNSAT Performance Step: 6 (C)

ENSURE the Train C Load Sequencer reset. (Procedure step 9.5)

Standard:

The operator depresses the white sequencer RESET pushbutton on CP-003 for ESF Diesel Generator 13.

Comment:

• LOOPWR status lights will clear

• Computer Indication of sequencer reset is on ICS display 9713 Cue:

Notes:

JPM NO: S1 PAGE 9 OF 18 JOB PERFORMANCE MEASURE CHECK SHEET (cont'd)

SAT/UNSAT Performance Step: 7 Momentarily DEPRESS the Diesel Generator 13 "RESET" pushbutton to ensure the non-emergency trip logic reset. (Procedure step 9.6)

Standard:

The operator depresses the white RESET pushbutton on CP-003 for Diesel Generator 13.

Comment:

Cue:

If asked, the Unit Supervisor reports that No non-emergency trip signal was received while the diesel was running in the Emergency Mode.

If asked, the Unit Supervisor reports that Non-Class 1E 125 VDC control power was not lost while the diesel was operating in the Emergency Mode.

Notes:

JPM NO: S1 PAGE 10 OF 18 JOB PERFORMANCE MEASURE CHECK SHEET (cont'd)

SAT/UNSAT Performance Step: 8 Verify the MASTER TRIP CIRCUIT "RESET" light illuminated. {ZLP106} (Procedure step 9.7)

Standard:

The operator directs a Plant Operator to verify the MASTER TRIP CIRCUIT RESET light on ZLP-106 is illuminated.

Comment:

Cue:

As Plant Operator, report the Master Trip Circuit Reset light is on.

Notes:

SAT/UNSAT Performance Step: 9 (C)

DEPRESS the "RELEASE" from Emergency Mode Operation pushbutton. {CP003}

(Procedure step 9.8)

Standard:

The Operator depresses the white "RELEASE" (from Emergency Mode) pushbutton on CP-003 for ESF Diesel Generator 13.

Comment:

Cue:

Notes:

JPM NO: S1 PAGE 11 OF 18 JOB PERFORMANCE MEASURE CHECK SHEET (cont'd)

SAT/UNSAT Performance Step: 10 Verify the Emergency Mode white light is extinguished {ZLP 106}. (Procedure step 9.9)

Standard:

The operator directs a Plant Operator to verify the white Emergency Mode light on ZLP-106 is extinguished.

Comment:

Cue:

As Plant Operator, report the white Emergency Mode light on ZLP-106 is extinguished Notes:

SAT/UNSAT Performance Step: 11 Ensure the ENGINE START MODE switch is in the IDLE position {ZLP 106} (Procedure step 9.10)

Standard:

The operator directs a Plant Operator to verify the ENGINE START MODE switch on ZLP-106 is in the IDLE position.

Comment:

Cue:

As Plant Operator, report the ENGINE START MODE switch is in the IDLE position.

Notes:

JPM NO: S1 PAGE 12 OF 18 JOB PERFORMANCE MEASURE CHECK SHEET (cont'd)

SAT/UNSAT Performance Step: 12 ENSURE the GOV MODE SEL switch in the PARALLEL position. {CP003}

(Procedure step 9.11)

Standard:

The operator verifies the GOV MODE SEL switch in the PARALLEL position.

Comment:

The switch should not have been repositioned from the PARALLEL position.

Cue:

Notes:

JPM NO: S1 PAGE 13 OF 18 JOB PERFORMANCE MEASURE CHECK SHEET (cont'd)

SAT/UNSAT Performance Step: 13 (C)*

Parallel the diesel with off-site power. (Procedure steps 9.12 - 9.16)

Standard:

The operator performs ALL of the following for the diesel being shutdown:

• A. PLACEs the SYNCHROSCOPE for Diesel Generator 13 in the ON position. {CP003}

1 B. ENSUREs the US/SS is present when synchronizing Diesel Generator 13.

• C. ADJUSTs engine speed to cause the synchroscope to move slowly in the SLOW direction using the GOV switch. {CP003}

• D. ADJUSTS DG 13 Output voltage using DG 13 VOLT ADJ until DG 13 output voltage is equal to XFRMR E1C VOLTS E. MONITORS the DG 13 Voltage Meter for all three phases of voltage.

• F. CLOSEs ESF Bus E1C Normal SPLY BKR E1C/1 when the synchroscope is approximately in the 12:05 position. {CP003}

G. PLACEs the SYNCHROSCOPE switch in the OFF position. (CP003)

Comment:

• * - Denotes critical portion of the step

• A second operator is NOT AVAILABLE to read the required steps per the procedure. THE EVALUATOR WILL NOT BE THE READER.

Cue:

1 The requirement for having a second operator and the Unit /Shift Supervisor available during the synchronization task has been waived by the Shift Supervisor.

Notes:

SAT/UNSAT Performance Step: 14 (C)

Unload the diesel. (Procedure steps 9.17 - 9.19)

JPM NO: S1 PAGE 14 OF 18 JOB PERFORMANCE MEASURE CHECK SHEET (cont'd)

Standard:

The operator performs ALL of the following for the diesel to be shutdown:

A. Using the Diesel Generator 13 GOV switch, DECREASEs diesel generator load to approximately 100 KW .

B. Using the Diesel Generator VOLT ADJ switch, DECREASEs diesel generator Reactive Power to approximately +50 KVAR .

C. Opens the Diesel Generator 13 DG OUTP BKR. {CP003}

Comment:

Actions 'A' and 'B' above may be simultaneously performed while unloading DG 13.

For time compression considerations in the simulator, the recommended Diesel Generator unloading rates of step 4.45 will not be followed.

Cue:

As US/SS, inform the candidate that the diesel is to be unloaded within 5 minutes.

Notes:

JPM NO: S1 PAGE 15 OF 18 JOB PERFORMANCE MEASURE CHECK SHEET (cont'd)

SAT/UNSAT Performance Step: 15 ENSURE ENGINE START MODE switch is in the RATED position {ZLP106}

(Procedure step 9.20)

Standard:

The operator directs a Plant Operator to ensure the ESF Diesel Generator 13 ENGINE START MODE switch in the RATED position.

Comment:

Cue:

• As Plant Operator, if asked the as found position of the switch, report that the ENGINE START MODE switch is in the IDLE position.

• As Plant Operator, report the ESF Diesel Generator 13 ENGINE START MODE switch is now in the RATED position Notes:

JPM NO: S1 PAGE 16 OF 18 JOB PERFORMANCE MEASURE CHECK SHEET (cont'd)

SAT/UNSAT Performance Step: 16 (C)

STOP Diesel Generator 13. (Procedure step 9.21)

Standard:

The operator TURNs Diesel Generator 13 NORMAL control switch to the STOP position. {CP003}

WHEN Diesel Generator 13 has entered the cooldown cycle, THEN the operator verifies that generator voltage decays indicating proper operation of the Generator Exciter Shunt Relay (K-1) by observing generator voltage decay.

Comment:

An ICS alarm comes in when securing ESF Diesel Generators associated with DG scaled (low) voltage and frequency.

Cue:

Notes:

- TERMINATE THE JPM -

JPM STOP TIME

JPM NO: S1 PAGE 17 OF 16 VERIFICATION OF COMPLETION Job Performance Measure: S1, RESTORE OFFSITE POWER TO ESF BUSES Applicants Name:

SSN:

Date Performed:

Time to Complete:

JPM Results: Sat / Unsat Evaluator: Signature Date

JPM NO: S1 PAGE 18 OF 18 JPM - HANDOUT READ TO PERFORMER:

The evaluator will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

YOU ARE TO INFORM THE EVALUATOR WHEN YOUVE COMPLETED THE TASK.

CAUTION: Do not operate or alter equipment configuration in the plant without proper authorization.

INITIAL CONDITIONS:

A Large Break LOCA has occurred 5.5 hours0.208 days <br />0.0298 weeks <br />0.00685 months <br /> ago. Additionally, a fault occurred on 4.16KV ESF BUS E1C supply breaker E1C/1. Emergency Diesel Generator 13 started and loaded normally.

The C ESF BUS supply breaker E1C/1 has been repaired and re-installed.

INITIATING CUE:

The Unit Supervisor directs you to restore normal off-site power to 4.16KV ESF Bus C and place ESF Diesel Generator 13 in a cooldown cycle in accordance with 0POP02-DG-0003, Emergency Diesel Generator 13(23). The requirement for having a second operator and the Unit /Shift Supervisor available during the synchronization task has been waived by the Shift Supervisor.

JPM NO: S2 PAGE 1 OF 13 NUCLEAR TRAINING DEPARTMENT OPERATING JOB PERFORMANCE MEASURE TITLE: TRANSFER TO HOT LEG RECIRCULATION JPM NO.: S2 REVISION: 0 LOCATION: Simulator

JPM NO: S2 PAGE 2 OF 13 JOB PERFORMANCE MEASURE WORKSHEET JPM

Title:

TRANSFER TO HOT LEG RECIRCULATION JPM No.: S2 Rev. No.: 0 STP Task: 81637 - Transfer to Hot Leg Recirculation STP Objective: 81637 - Transfer to Hot Leg Recirculation IAW 0POP05-E0-ES14 Related K/A

Reference:

EPE 011 EA1.11 [4.2/4.2] - Ability to operate and monitor the following as they apply to a Large Break LOCA: Long-term cooling of the core.

References:

0POP05-E0-ES14, Rev. 4, Transfer to Hot Leg Recirculation Task Normally Completed By: RO Method of Testing: Actual Performance Location of Testing: Simulator Time Critical Task: NO Alternate Path JPM: NO Validation Time: 15 Mins.

Required Materials (Tools/Equipment):

None

JPM NO: S2 PAGE 3 OF 13 JOB PERFORMANCE MEASURE INFORMATION SHEET READ TO PERFORMER (a copy of this information is included at the end of the JPM as a tear-away sheet to be given to the student):

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

YOU ARE TO INFORM THE EVALUATOR WHEN YOUVE COMPLETED THE TASK.

CAUTION: Do not operate or alter equipment configuration in the plant without proper authorization.

INITIAL CONDITIONS:

A large break LOCA occurred 5.5 hours0.208 days <br />0.0298 weeks <br />0.00685 months <br /> ago. The control room operators have completed 0POP05-E0-E010 and are evaluating long term plant status.

INITIATING CUE:

The Unit Supervisor directs you to transfer to hot leg recirculation on SI trains A and B in accordance with 0POP05-E0-ES14, Transfer to Hot Leg Recirculation.

- DO NOT DISCLOSE INFORMATION BELOW THIS LINE -

COMPLETION CRITERIA:

The Performer Transfers SI Recirculation Flow from Cold Leg to Hot Leg for Trains A and B Per 0POP05-EO-ES14.

JPM NO: S2 PAGE 4 OF 13 JOB PERFORMANCE MEASURE INFORMATION SHEET HANDOUTS:

Working copy of: 0POP05-E0-ES14, Transfer to Hot Leg Recirculation NOTES:

1. This JPM is formatted for dynamic simulator performance only. The cues provided are related to communications and other general information needed for dynamic performance. (NO Indication type Cues are provided).

2. Use the Simulator Setup section below to prepare the simulator.

SIMULATOR SETUP:

1. JPMs S1 and S2 are to run together. The following steps will set up the simulator for BOTH JPMs.

2. Ensure Radio volume for both stations are set to a reasonable level.

3. Ensure the PA buttons on the communications consoles are taped to help eliminate usage.

4. Check and Clean the following procedures:

• 0POP05-EO-ES14, Transfer to Hot Leg Recirculation

• 0POP02-DG-0003, Emergency Diesel Generator 13(23)

5. Reset to IC #69 and verify:

• Step counter positions

• ICS restored

• Control Switch FLAGS reset

JPM NO: S2 PAGE 5 OF 13 JOB PERFORMANCE MEASURE CHECK SHEET NOTE:

• Critical steps are identified by (C).

• Sequenced steps are identified by (S1, S2, . . .).

JPM START TIME SAT/UNSAT Performance Step: 1 Obtain the procedure, 0POP05-E0-ES14, Transfer to Hot Leg Recirculation Standard:

Copy of 0POP05-E0-ES14, Transfer to Hot Leg Recirculation obtained.

Comment:

The applicant may use the simulator copy of the procedure or a working copy provided by the evaluator.

Cue:

Notes:

JPM NO: S2 PAGE 6 OF 13 JOB PERFORMANCE MEASURE CHECK SHEET (cont'd)

SAT/UNSAT Performance Step: 2 Check three SI trains operable (Procedure step 1)

Standard:

Three SI trains checked operable.

Comment:

Cue:

Notes:

JPM NO: S2 PAGE 7 OF 13 JOB PERFORMANCE MEASURE CHECK SHEET (cont'd)

SAT/UNSAT Performance Step: 3(C)

Align the first HHSI pump for Hot Leg Recirculation. (Procedure step 2.a)

Standard:

• Energizes selected SI train HHSI hot leg injection valve.

• Opens HHSI hot leg injection valve.

• Closes HHSI cold leg injection valve.

Verifies hot leg injection flow.

Deenergizes selected SI train HHSI hot leg injection valve.

Comment:

1. Applicant may start with either A or B train.

2. Items marked with an

• are the critical steps.

Cue:

Notes:

JPM NO: S2 PAGE 8 OF 13 JOB PERFORMANCE MEASURE CHECK SHEET (cont'd)

SAT/UNSAT Performance Step: 4(C)

Align the first LHSI pump for Hot Leg Recirculation. (Procedure step 2.b)

Standard:

• Energizes selected SI train LHSI hot leg injection valve.

• Opens LHSI hot leg injection valve.

• Closes LHSI cold leg injection valve.

Verifies hot leg injection flow.

Deenergizes selected SI train LHSI hot leg injection valve.

Comment:

1. Applicant may start with either A or B train.

2. Items marked with an

• are the critical steps.

Cue:

Notes:

This step should be performed in a rapid sequence to prevent pump runout.

JPM NO: S2 PAGE 9 OF 13 JOB PERFORMANCE MEASURE CHECK SHEET (cont'd)

SAT/UNSAT Performance Step: 5(C)

Align the second HHSI pump for Hot Leg Recirculation. (Procedure step 3.a)

Standard:

• Energizes selected SI train HHSI hot leg injection valve.

• Opens HHSI hot leg injection valve.

• Closes HHSI cold leg injection valve.

Verifies hot leg injection flow.

Deenergizes selected SI train HHSI hot leg injection valve.

Comment:

1. This step will be performed on either A or B trains, depending on which train was transferred first.

2. Items marked with an

• are the critical steps.

Cue:

Notes:

JPM NO: S2 PAGE 10 OF 13 JOB PERFORMANCE MEASURE CHECK SHEET (cont'd)

SAT/UNSAT Performance Step: 6(C)

Align the second LHSI pump for Hot Leg Recirculation. (Procedure step 3.b)

Standard:

• Energizes selected SI train LHSI hot leg injection valve.

• Opens LHSI hot leg injection valve.

• Closes LHSI cold leg injection valve.

Verifies hot leg injection flow.

Deenergizes selected SI train LHSI hot leg injection valve.

Comment:

1. This step will be performed on either A or B trains, depending on which train was transferred first.

2. Items marked with an

• are the critical steps.

Cue:

Notes:

This step should be performed in a rapid sequence to prevent pump runout.

JPM NO: S2 PAGE 11 OF 13 JOB PERFORMANCE MEASURE CHECK SHEET (cont'd)

SAT/UNSAT Performance Step: 7 Dispatch an Operator to open and lock the breakers for the following valves: (Procedure step 4)

1. LHSI Pump 1A Disch to Loop 1 Cold Leg 1-SI-MOV-0031A

2. LHSI Pump 1B Disch to Loop 2 Cold Leg 1-SI-MOV-0031B

3. LHSI Pump 1C Disch to Loop 3 Cold Leg 1-SI-MOV-0031C Standard:

A Plant Operator is dispatched to open and lock the breakers for the following valves:

• LHSI Pump 1A Disch to Loop 1 Cold Leg 1-SI-MOV-0031A

• LHSI Pump 1B Disch to Loop 2 Cold Leg 1-SI-MOV-0031B

• LHSI Pump 1C Disch to Loop 3 Cold Leg 1-SI-MOV-0031C Comment:

Cue:

As Plant Operator, acknowledge the request to open and lock the above breakers.

Notes:

- TERMINATE THE JPM -

JPM STOP TIME _________

JPM NO: S2 PAGE 12 OF 13 VERIFICATION OF COMPLETION Job Performance Measure: S2, TRANSFER TO HOT LEG RECIRCULATION Applicant's Name:

SSN:

Date Performed:

Time to Complete:

JPM Results: Sat/Unsat Evaluator: Signature Date

JPM NO: S2 PAGE 13 OF 13 JPM - STUDENT HANDOUT READ TO PERFORMER:

The evaluator will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

YOU ARE TO INFORM THE EVALUATOR WHEN YOUVE COMPLETED THE TASK.

CAUTION: Do not operate or alter equipment configuration in the plant without proper authorization.

INITIAL CONDITIONS:

A large break LOCA occurred 5.5 hours0.208 days <br />0.0298 weeks <br />0.00685 months <br /> ago. The control room operators have completed 0POP05-E0-E010 and are evaluating long term plant status.

INITIATING CUE:

The Unit Supervisor directs you to transfer to hot leg recirculation on SI trains A and B in accordance with 0POP05-E0-ES14, Transfer to Hot Leg Recirculation.

JPM NO: S3 PAGE 1 OF 16 NUCLEAR TRAINING DEPARTMENT OPERATING JOB PERFORMANCE MEASURE TITLE: RESPOND TO A FAILED SOURCE RANGE NUCLEAR INSTRUMENT JPM NO.: S3 REVISION: 1 LOCATION: Simulator

JPM NO: S3 PAGE 2 OF 16 JOB PERFORMANCE MEASURE WORKSHEET JPM

Title:

RESPOND TO A FAILED SOURCE RANGE NUCLEAR INSTRUMENT JPM No.: S3 Rev. No.: 1 STP Task: 86050, Respond to a Loss of Source Range Instrumentation STP Objective: 86050, Respond to a Loss of Source Range Instrumentation per 0POP04-NI-0001 Related K/A

Reference:

APE 032 AA2.05 [2.9/3.2], Ability to determine and interpret the following as they apply to the Loss of Source Range Nuclear Instrumentation: Nature of abnormality, from rapid survey of control room data.

References:

0POP04-NI-0001, Rev. 6, Nuclear Instrument Malfunction 0POP09-AN-05M3, Rev. 15, Annunciator Lampbox Instructions Task Normally Completed By: RO Method of Testing: Actual Performance Location of Testing: Simulator Time Critical Task: NO Alternate Path JPM: NO Validation Time: 20 minutes Required Materials (Tools/Equipment):

None

JPM NO: S3 PAGE 3 OF 16 JOB PERFORMANCE MEASURE INFORMATION SHEET READ TO PERFORMER (a copy of this information is included at the end of the JPM as a tear-away sheet to be given to the student):

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

YOU ARE TO INFORM THE EVALUATOR WHEN YOUVE COMPLETED THE TASK.

CAUTION: Do not operate or alter equipment configuration in the plant without proper authorization.

INITIAL CONDITIONS:

The Unit is shutdown in MODE 4. Annunciator 5M03 /E-1, "SR HI VOLT TRBL" has just actuated.

INITIATING CUE:

The Unit Supervisor directs you to take the appropriate actions.

- DO NOT DISCLOSE INFORMATION BELOW THIS LINE -

COMPLETION CRITERIA:

Source Range channel NI-31 is determined to be de-energized and the actions associated with 0POP04-NI-0001, Nuclear Instrument Malfunction, are complete.

HANDOUTS:

Working copy of 0POP04-NI-0001, Nuclear Instrumentation Malfunction

JPM NO: S3 PAGE 4 OF 16 JOB PERFORMANCE MEASURE INFORMATION SHEET (cont'd)

NOTES:

1. This JPM is formatted for dynamic simulator performance only. The cues provided are related to communications and other general information needed for dynamic performance. (NO Indication type Cues are provided).

2. Use the Simulator Setup section below to prepare the simulator.

SIMULATOR SETUP:

1. JPMs S3 and S4 are to run together. The following steps will set up the simulator for BOTH JPMs.

2. Ensure Radio volume for both stations are set to a reasonable level.

3. Ensure the PA buttons on the communications consoles are taped to help eliminate usage.

4. Check and Clean the following procedures:

• 0POP04-NI-0001, Nuclear Instrument Malfunction

• 0POP04-RA-0001, Radiation Monitoring System Alarm Response

5. Reset to IC #70 and verify:

• Step counter positions

• ICS restored

• Control Switch FLAGS reset

6. Tag the following handswitches:

• HHSI Pp 1B - PTL - Danger Tag

• CCP 1B - PTL - Danger Tag

• Positive Displacement Charging Pump - PTL - Danger Tag

• HHSI Pp 1C - PTL Caution Tag

7. Place the simulator in run and perform the following:

A. Ensure the RM-11 display is selected to Grid-3 B. Execute step #1 of lesson #5 in Lesson Group lot13nrc

• Silence the RM-11 alarm by depressing the SYSTEM ACK button, but leave RT-8012 and RT-8013 blinking (DO NOT acknowledge)

8. Ensure the Audio Multiplier is selected to 10" and audio count rate is audible (may need to momentarily select N32 to adjust volume)

9. Ensure N31 is selected for the Audio Count Rate Channel

JPM NO: S3 PAGE 5 OF 16 JOB PERFORMANCE MEASURE CHECK SHEET NOTE:

• Critical steps are identified by (C).

• Sequenced steps are identified by (S1, S2, . . .).

JPM START TIME _______

SAT/UNSAT Performance Step: 1 Obtain appropriate annunciator response procedure.

Standard:

Obtains copy of 0POP09-AN-05M3, Annunciator Lampbox 5M03 Response Instructions, for annunciator window E-1.

Comment:

Cue:

Notes:

Applicant should use the simulator copy of the Annunciator Response Procedure.

JPM NO: S3 PAGE 6 OF 16 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 2 Check status of P-6 permissive. (Ann. Response, step 1)

Standard:

Determines P-6 permissive is not satisfied. {CP-005}

Comment:

Cue:

Notes:

SAT/UNSAT Performance Step: 3 (C)

Evaluate status of Source Range Channels N31 and N32. (Ann Response, step 3)

Standard:

Determines Source Range Channel N31 is de-energized. {CP-005}

Comment:

Cue:

Notes:

Step 2 of the annunciator response does not apply since P-6 is not satisfied.

JPM NO: S3 PAGE 7 OF 16 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 4 Manually RESET the Source Range blocks at CP005 (Ann. Response, step 3.a)

Standard:

Manually resets (unblocks) the Source Range High Level Reactor Trip using the trains R and S manual block switches at CP-005.

Comment:

No change in control board indications will be seen when this step is performed.

Cue:

Notes:

SAT/UNSAT Performance Step: 5 (C)

Evaluate Status of Source Range Channel N31. (Ann. Response, step 3.b)

Standard:

Determines Source Range Channel N31 did not re-energize.

Comment:

Cue:

As Unit Supervisor, direct applicant to go to 0POP04-NI-0001, Nuclear Instrumentation Malfunction.

Notes:

JPM NO: S3 PAGE 8 OF 16 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 6(C)

Transition to 0POP04-NI-0001, Nuclear Instrument Malfunction.

Standard:

Transitions to 0POP04-NI-0001 as directed by annunciator response procedure.

Comment:

The applicant may use the simulator copy of the procedure or a working copy provided by the evaluator.

Cue:

Notes:

JPM NO: S3 PAGE 9 OF 16 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 7 Check Power Range Nuclear Instruments - NORMAL. (Procedure step 1.0)

Standard:

Determines that Power Range Nuclear Instruments are normal.

Comment:

Step 1 is an Immediate Action step.

Cue:

Notes:

SAT/UNSAT Performance Step: 8(C)

Check Source Range Nuclear Instruments - NORMAL. (Procedure step 2.0)

Standard:

Determines that Source Range Nuclear Instrument N31 is de-energized.

Comment:

A transition to Addendum 1 should be made.

Cue:

Notes:

JPM NO: S3 PAGE 10 OF 16 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 9(C)

Determine:

1. If the Plant is in Mode 2 (Addendum 1, step 1.0)

2. If the Plant is in Mode 6 (Addendum 1, step 4.0)

3. If the Plant is in Mode 3, 4, or 5 (Addendum 1, step 7.0)

Standard:

Determines that the Plant is in Mode 4.

Comment:

Mode 4 plant status is part of the initial conditions.

Cue:

Notes:

JPM NO: S3 PAGE 11 OF 16 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 10 (C)

Ensure Audible Countrate in service. (Procedure step 8.0)

Standard:

• Selects N32 for the Audible Countrate channel.

OR

• Initiates visual monitoring of either Source Range Nuclear Instruments or Extended Range Nuclear Instruments OR

• Borates the RCS to the COLD, ARO 0.95 Keff value and notifies Chemistry to sample the RCS Boron Concentration at least once per 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br />.

Comment:

The Audio Countrate channel is selected to N31 Cue:

Notes:

JPM NO: S3 PAGE 12 OF 16 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 11 Verify Reactor Trip Breakers open. (Procedure step 9.0)

Standard:

Determines the Reactor Trip Breakers are already open.

Comment:

Cue:

Notes:

JPM NO: S3 PAGE 13 OF 16 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 12 Check High Flux at Shutdown Alarm in alarm. (Procedure step 10.0)

Standard:

Determines the High Flux at Shutdown Alarm is not in alarm.

Comment:

Cue:

Notes:

SAT/UNSAT Performance Step: 13 Check at least two Source Range or Extended Range (N31, N32, H45, or N46) Nuclear Instrumentation Channels operable. (Procedure step 14.0)

Standard:

Determines N32, N45 and N46 are operable.

Comment:

Cue:

If asked as the Unit Supervisor, no OAS entries exist for N32, N45 or N46.

Notes:

JPM NO: S3 PAGE 14 OF 16 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 14 Check at least One Source Range or Extended Range (N31, N32, N45, or N46) Nuclear Instrumentation Channel functional. (Procedure step 15.0)

Standard:

Determines N32, N45 and N46 are functional.

Comment:

Cue:

Notes:

SAT/UNSAT Performance Step: 15 Select an Operable Source Range Channel on Nuclear Recorder NR-0045. (Procedure step 16.0)

Standard:

Selects N32 on recorder NR-0045.

Comment:

Cue:

Notes:

- TERMINATE THE JPM -

JPM STOP TIME ________

JPM NO: S3 PAGE 15 OF 16 VERIFICATION OF COMPLETION Job Performance Measure: S3, RESPOND TO A FAILED SOURCE RANGE NUCLEAR INSTRUMENT Performer's Name:

SSN:

Date Performed:

Time to Complete:

JPM Results: Sat / Unsat Evaluator: Signature Date

JPM NO: S3 PAGE 16 OF 16 JPM - STUDENT HANDOUT READ TO PERFORMER:

The evaluator will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

YOU ARE TO INFORM THE EVALUATOR WHEN YOUVE COMPLETED THE TASK.

CAUTION: Do not operate or alter equipment configuration in the plant without proper authorization.

INITIAL CONDITIONS:

The Unit is shutdown in MODE 4. Annunciator 5M03 /E-1, "SR HI VOLT TRBL" has just actuated.

INITIATING CUE:

The Unit Supervisor directs you to take the appropriate actions.

JPM NO: S4 PAGE 1 OF 15 NUCLEAR TRAINING DEPARTMENT OPERATING JOB PERFORMANCE MEASURE TITLE: RESPOND TO A RADIATION MONITOR ALARM JPM NO.: S4 REVISION: 2 LOCATION: Simulator

JPM NO: S4 PAGE 2 OF 15 JOB PERFORMANCE MEASURE WORKSHEET JPM

Title:

RESPOND TO A RADIATION MONITOR ALARM JPM No.: S4 Rev. No.: 2 STP Task: 11700, Respond to Radiation Monitoring System alarms STP Objective: 11700, Respond to Radiation Monitoring System alarms per 0POP04-RA-0001 Related K/A

Reference:

APE 061 AA1.01 [3.6/3.6], Ability to operate and/or monitor the following as they apply to the Area Radiation Monitoring System Alarms:

Automatic actuation.

APE 061 AA2.01 [3.5/3.7], Ability to determine and interpret the following as they apply to the Area Radiation Monitoring System Alarms:

ARM panel displays.

References:

0POP04-RA-0001, Rev. 7, RADIATION MONITORING SYSTEM ALARM RESPONSE Task Normally Completed By: RO/SRO Method of Testing: Actual Performance Location of Testing: Simulator Time Critical Task: NO Alternate Path JPM: YES Validation Time: 20 minutes Required Materials (Tools/Equipment):

None

JPM NO: S4 PAGE 3 OF 15 JOB PERFORMANCE MEASURE INFORMATION SHEET READ TO PERFORMER (a copy of this information is included at the end of the JPM as a tear-away sheet to be given to the student):

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

YOU ARE TO INFORM THE EVALUATOR WHEN YOUVE COMPLETED THE TASK.

CAUTION: Do not operate or alter equipment configuration in the plant without proper authorization.

INITIAL CONDITIONS:

The Unit is in Mode 4. RCB Supplementary Purge is in progress.

INITIATING CUE:

You have just received a radiation monitor alarm on the RM-11. The Unit Supervisor directs you to investigate the alarm and take any action necessary.

- DO NOT DISCLOSE INFORMATION BELOW THIS LINE -

COMPLETION CRITERIA:

The Operator determines that RT-8012 indicates above the high alarm setpoint and isolates the Containment Ventilation system.

JPM NO: S4 PAGE 4 OF 15 JOB PERFORMANCE MEASURE INFORMATION SHEET HANDOUTS:

Working copy of 0POP04-RA-0001, Radiation Monitoring System Alarm Response.

NOTES:

1. This JPM is formatted for dynamic simulator performance only. The cues provided are related to communications and other general information needed for dynamic performance. (NO Indication type Cues are provided).

2. Use the Simulator Setup section below to prepare the simulator.

SIMULATOR SETUP:

1. JPMs S3 and S4 are to run together. The following steps will set up the simulator for BOTH JPMs.

2. Ensure Radio volume for both stations are set to a reasonable level.

3. Ensure the PA buttons on the communications consoles are taped to help eliminate usage.

4. Check and Clean the following procedures:

• 0POP04-NI-0001, Nuclear Instrument Malfunction

• 0POP04-RA-0001, Radiation Monitoring System Alarm Response

5. Reset to IC #70 and verify:

• Step counter positions

• ICS restored

• Control Switch FLAGS reset

6. Tag the following handswitches:

• HHSI Pp 1B - PTL - Danger Tag

• CCP 1B - PTL - Danger Tag

• Positive Displacement Charging Pump - PTL - Danger Tag

• HHSI Pp 1C - PTL Caution Tag

7. Place the simulator in run and perform the following:

A. Ensure the RM-11 display is selected to Grid-3 B. Execute step #1 of lesson #5 in Lesson Group lot13nrc

• Silence the RM-11 alarm by depressing the SYSTEM ACK button, but leave RT-8012 and RT-8013 blinking (DO NOT acknowledge)

JPM NO: S4 PAGE 5 OF 15 JOB PERFORMANCE MEASURE CHECK SHEET NOTE:

• Critical steps are identified by (C).

• Sequenced steps are identified by (S1, S2, . . .).

JPM START TIME _______

SAT/UNSAT Performance Step: 1 (C)

Proceed to the RM-11 Panel and call up RT-8012 OR Proceed to the RM-23 and identify RT-8012 high alarm lit.

Standard:

The Operator determines that RT-8012 indicates above the high alarm setpoint.

Comment:

• Alert setpoint is 5.0 E-5 µci/cc.

• High setpoint is 5.0 E-4 µci/cc.

Cue:

Notes:

RT-8013 is above the alert alarm setpoint, but the applicant should focus on the monitor above the high alarm setpoint (RT-8012)

JPM NO: S4 PAGE 6 OF 15 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 2 Obtain a copy of 0POP04-RA-0001, Radiation Monitoring System Alarm Response.

Standard:

The Operator obtains a copy of 0POP04-RA-0001.

Comment:

• The applicant may use the simulator copy of the procedure or a working copy provided by the evaluator.

• The JPM actions taken in Step 1 to determine the alarm condition(s) is considered skill-of-the-craft and Steps 1 - 4 of 0POP04-RA-0001 may be used by the applicant if desired.

• Applicant should transition to Addendum 3.

Cue:

Notes:

JPM NO: S4 PAGE 7 OF 15 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 3 (C)

Ensure Containment Ventilation Isolation (CVI) valves are closed. (Addendum 3, Step 2a, b, & c))

Standard:

The operator determines Containment Ventilation Isolation Actuation did NOT occur, and manually closes the following valves:

____ SUPPL CNTMT PURGE "SPLY OCIV FV-9776

____ SUPPL CNTMT PURGE "SPLY ICIV MOV-0003

____ SUPPL CNTMT PURGE "EXH ICIV MOV-0005

____ SUPPL CNTMT PURGE "EXH OCIV FV-9777

____ CNTMT ATM SAMPLE ICIV RA-MOV-0001

____ CNTMT ATM SAMPLE OCIV RA-MOV-0004

____ CNTMT ATM RETURN ICIV RA-MOV-0003

____ CNTMT ATM RETURN OCIV RA-MOV-0006 Comment:

• Step 2a: Normal Containment Purge Valves are closed and de-energized, therefore no operator action is required.

Cue:

Notes:

JPM NO: S4 PAGE 8 OF 15 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 4 Normal and Supplementary Containment Purge Fans stopped. (Addendum 3, Step 2d &e)

Standard:

The Operator Places the Supplementary Containment Purge Fans in STOP:

____ Supply Fan 11A(21A)

____ Supply Fan 11B(21B)

____ Exhaust Fan 11A(21A)

____ Exhaust Fan 11B(21B)

Comment:

• Step 2d: Normal Containment Purge Fans are already stopped and no operator action is required.

Cue:

Notes:

JPM NO: S4 PAGE 9 OF 15 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 5 Ensure RT-8011 RCB Atmosphere Radiation Monitor Sample Pump has stopped.

(Addendum 3, Step 3.0)

Standard:

The operator stops RT-8011 Sample Pump by performing either of the following:

depress the "PUMP ON/OFF" button for RT-8011 on ZCP-023 OR select RT-8011 on the RM-11 and depress the "FLOW" pushbutton AFTER selecting RT-8011.

Comment:

Cue:

Notes:

JPM NO: S4 PAGE 10 OF 15 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 6 Refer to Technical Specifications 3.3.3.1 and 3.4.6.1 for further actions. (Addendum 3, Step 4.0)

Standard:

The applicant determines that Containment atmosphere grab samples are required and that an RCS Inventory calculation is required once per 24 hours1 days <br />0.143 weeks <br />0.0329 months <br />.

Comment:

Cue:

• If applicant does not refer to Technical Specifications, as Unit Supervisor direct applicant to refer to Technical Specifications.

Notes:

JPM NO: S4 PAGE 11 OF 15 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 7 Notify Health Physics of the alarm condition. (Addendum 3, Step 5.0)

Standard:

The operator notifies Health Physics of the alarm condition.

Comment:

The applicant may notify Health Physics using a simulator phone.

Cue:

• Health Physics has been notified, and are taking appropriate actions.

• If asked, the Health Physics office RM-11 has the same alarm conditions present as the RM-11 in the Control Room.

Notes:

JPM NO: S4 PAGE 12 OF 15 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 8(C)

Notify Chemistry to obtain grab samples using the Post Accident Sampling System.

(Addendum 3, Step 6.0)

Standard:

The operator notifies Chemistry to obtain grab samples.

Comment:

The applicant may notify Chemistry using a simulator phone.

Cue:

Chemistry has been notified.

Notes:

JPM NO: S4 PAGE 13 OF 15 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 9 Check for increased readings on RT-8010A, RT-8010B. (Addendum 3, Step 7.0)

Standard:

The operator checks the following Rad Monitors for increased readings:

RT-8010A RT-8010B Comment:

The operator should see NO increase in these readings.

Cue:

Notes:

- TERMINATE THE JPM -

JPM STOP TIME _______

JPM NO: S4 PAGE 14 OF 15 VERIFICATION OF COMPLETION Job Performance Measure: S4, RESPOND TO A RADIATION MONITOR ALARM Applicants Name:

SSN:

Date Performed:

Time to Complete:

JPM Results: Sat / Unsat Evaluator: Signature Date

JPM NO: S4 PAGE 15 OF 15 JPM - STUDENT HANDOUT READ TO PERFORMER:

The evaluator will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

YOU ARE TO INFORM THE EVALUATOR WHEN YOUVE COMPLETED THE TASK.

CAUTION: Do not operate or alter equipment configuration in the plant without proper authorization.

INITIAL CONDITIONS:

The Unit is in Mode 4. RCB Supplementary Purge is in progress.

INITIATING CUE:

You have just received a radiation monitor alarm on the RM-11. The Unit Supervisor directs you to investigate the alarm and take any action necessary.

JPM NO: S5 PAGE 1 OF 18 NUCLEAR TRAINING DEPARTMENT OPERATING JOB PERFORMANCE MEASURE TITLE: MAXIMIZE LETDOWN DUE TO HIGH RCS ACTIVITY JPM NO.: S5 REVISION: 1 LOCATION: Simulator

JPM NO: S5 PAGE 2 OF 18 JOB PERFORMANCE MEASURE WORKSHEET JPM

Title:

MAXIMIZE LETDOWN DUE TO HIGH RCS ACTIVITY JPM No.: S5 Rev. No: 1 STP Task: 86300, Respond to a high RCS activity greater than TS limits.

STP Objective: CRO 86300, Respond to a high RCS activity greater than TS limits per 0POP04-RC-0001.

Related K/A

Reference:

004 A1.11 [3.0/3.0] Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CVCS controls including letdown and charging flows.

References:

0POP04-RC-0001, Rev. 5, High Reactor Coolant System Activity 0POP02-CV-0004, Rev. 22, Chemical and Volume Control System Task Normally Completed By: RO Method of Testing: Actual Performance Location of Testing: Simulator Time Critical Task: NO Alternate Path JPM: NO Validation Time: 20 mins Required Materials (Tools/Equipment):

None

JPM NO: S5 PAGE 3 OF 18 JOB PERFORMANCE MEASURE INFORMATION SHEET READ TO PERFORMER (a copy of this information is included at the end of the JPM as a tear-away sheet to be given to the student):

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

YOU ARE TO INFORM THE EVALUATOR WHEN YOU HAVE COMPLETED THE TASK CAUTION: Do not operate or alter equipment configuration in the plant without proper authorization.

INITIAL CONDITIONS:

The unit is in Mode 3 following a reactor trip with Centrifugal Charging Pump 1A and the 125 gpm letdown orifice in service. RCS samples indicate an increasing activity, and chemistry has determined that the in-service mixed bed demineralizer decontamination factor is adequate.

In accordance with 0POP04-RC-0001, step 4.a, Chemistry has requested that Operations maximize letdown flow.

INITIATING CUE:

The Unit Supervisor directs you to place Centrifugal Charging Pump 1B in service, then maximize letdown by placing additional letdown orifices in service as necessary to establish 220-250 gpm letdown flow in accordance with 0POP02-CV-0004, Chemical and Volume Control System. You are not to exceed a steady state letdown flow rate of 250 gpm.

- DO NOT DISCLOSE INFORMATION BELOW THIS LINE -

COMPLETION CRITERIA:

Charging pump 1B is placed in service and letdown is maximized with a steady state flow of 220-250 gpm.

JPM NO: S5 PAGE 4 OF 18 JOB PERFORMANCE MEASURE INFORMATION SHEET HANDOUTS:

Working copy 0POP02-CV-0004, Chemical and Volume Control System.

NOTES:

1) This JPM is formatted for dynamic simulator performance only. The cues provided are related to communications and other general information needed for dynamic performance. (NO Indication type Cues are provided).

2) Use the Simulator Setup section below.

SIMULATOR SETUP

1) JPMs S5 and S6 are to run together. The following steps will set up the simulator for BOTH JPMs.

2) Ensure Radio volume for both stations are set to a reasonable level.

3) Ensure the PA buttons on the communications consoles are taped to help eliminate usage.

3) Reset to IC #71 and verify:

C Step counter positions C ICS restored C Control switch FLAGS reset

4) Check and clean the following procedures:

C 0POP02-CV-0004. Chemical and Volume Control System Subsystem C 0POP05-EO-ES01, Reactor Trip Response

5) Place simulator in run.

6) Start lesson #6, (JPMs S5 and S6), but do not execute any steps.

A) If asked to isolate the Main Feedwater Reg Valve for SG B (JPM S6), trigger STEP 1 (FW-0042)

B) If asked to isolate the Main Feedwater Reg Valve for SG C (JPM S6), trigger STEP 2 (FW-0093)

JPM NO: S5 PAGE 5 OF 18 JOB PERFORMANCE MEASURE CHECK SHEET NOTE:

• Critical steps are identified by (C).

• Sequenced steps are identified by (S1, S2, . . .).

JPM START TIME SAT/UNSAT Performance Step: 1 Obtain a copy of procedure.

Standard:

Obtains a copy of 0POP02-CV-0004 and reviews notes and precautions.

Comment:

1) Provide the Handout copy of 0POP02-CV-0004, or the operator may use the simulator copy of the procedure.

2) The operator is expected to transition to procedure section 5.1 for starting a centrifugal charging pump with charging flow already established.

Cue:

A Plant Operator is standing by for start of Centrifugal Charging pump 1B.

Notes:

JPM NO: S5 PAGE 6 OF 18 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 2 Ensure applicable charging pump discharge valve is Open. (procedure step 5.1.1)

Standard:

Verifies CCP 1B DISCH ISOL MOV-8377B is open on CP-004.

Comment:

Cue:

Notes:

SAT/UNSAT Performance Step: 3 Place CHG FLOW CONT FK-0205"in MAN while maintaining charging flow constant.

(procedure step 5.1.2)

Standard:

Places CHG FLOW CONT FK-0205" in MAN and verifies charging flow remains constant on CP-004.

Comment:

Cue:

Notes:

JPM NO: S5 PAGE 7 OF 18 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 4 Verify Centrifugal Charging Pump Aux Lube Oil Pump Running. (procedure step 5.1.3)

Standard:

Verifies Aux lube oil pump is running for CCP 1B by observing the white L.O. AVAILABLE light is illuminated on CP-004.

Comment:

Cue:

Notes:

JPM NO: S5 PAGE 8 OF 18 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 5(C)

Start CCP 1B. (procedure step 5.1.4)

Standard:

Starts CCP 1B by momentarily turning its handswitch to the STARTposition on CP-004.

Comment:

1) The operator is expected to verify the pump is ready to be started with the Plant Operator and make a plant page prior to pump start.

2) After performance of this step the operator is expected to transition to procedure step 5.1.10 since plant conditions will require two CCPs to remain in operation.

Cue:

Notes:

JPM NO: S5 PAGE 9 OF 18 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 6 Close miniflow valve for CCP 1B. (procedure step 5.1.10)

Standard:

Closes CCP 1B miniflow valve RECIRC FCV-202" by taking handswitch on CP-004 to CLOSE.

Comment:

Cue:

Notes:

JPM NO: S5 PAGE 10 OF 18 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 7 Perform post start charging pump checks and alignments. (procedure steps 5.1.11 through 5.1.14)

Standard:

Performs the following to ensure proper control of charging and seal injection after pump start:

____ Places charging flow control valve CHG FLOW CONT FK-0205" in AUTO .

____ Ensures charging flow and pressurizer level stabilize on CP-004.

____ Adjusts RCP seal injection as required to maintain 6-13 gpm to each RCP using FLOW CONT HCV-0218" on CP-004.

____ Ensures cooling fan starts for CCP 1B by verifying status lights for PUMP 1B SUPP CLR 11Bon CP-0022.

Comment:

After verifying cooling fan started for CCP 1B, the operator should transition to procedure section 9.0 for placing a second or third letdown orifice in service with the RCS pressurized.

(step 5.1.15 is N/A - a charging pump was not stopped)

Cue:

Notes:

JPM NO: S5 PAGE 11 OF 18 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 8 Ensure demineralizers bypassed per Section 7.0. (procedure step 9.1)

Standard:

Places DIVERT TCV-0143" in VCT position on CP-004.

Comment:

Cue:

Notes:

SAT/UNSAT Performance Step: 9(C)

Place CVCS header pressure controller in MANUAL. (procedure step 9.2)

Standard:

Places PRESS CONT PCV-0135" in MAN on CP-004.

Comment:

Cue:

Notes:

JPM NO: S5 PAGE 12 OF 18 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 10 Adjust letdown pressure to approximately 200 psig . (procedure step 9.3)

Standard:

Adjusts letdown header pressure to approximately 200 psig by opening PCV-0135 on CP-004.

Comment:

1) PCV-0135 is a back-pressure control valve, therefore the operator must open the valve to reduce pressure from 380 psig to 200 psig.

2) A procedure NOTE states that the Letdown Relief to the PRT valve PSV-3100 shall be monitored during and after opening of PCV-0135 to ensure the relief does not lift. (600 psig)

Cue:

The Unit Supervisor directs the applicant to place the 85 gpm letdown orifice in service first (after letdown pressure has been adjusted to ~200 psig).

Notes:

JPM NO: S5 PAGE 13 OF 18 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 11(C)*

Open the appropriate letdown orifice isolation valve and stabilize conditions.

(procedure steps 9.4 and 9.5)

Standard:

• Opens isolation valve for the 85 gpm letdown orifice by taking handswitch for GPM FV-0013 ORIF ISOL VLV to OPEN.

Adjusts PRESS CONT PCV-0135" to maintain 350-380 psig after opening FV-0013 and places on AUTO.

Comment:

2) * - denotes critical portion of step.

3) It is expected to that the operator will allow conditions to stabilize prior to placing the third letdown orifice in service.

4) The following annunciators may momentarily actuate until charging flow is sufficiently increased to match letdown flow:

1) 4M08/C3 LETDN HX OUTL TEMP HI

2) 4M08/D7 PRZR PRESS DEV LO B/U HTRS ON Cue:

Notes:

The Applicant may increase charging flow to match the increased letdown flow using charging flow controller CHG FLOW CONT FK-0205" OR pressurizer master level controller LEVEL CONT LK-0665.

JPM NO: S5 PAGE 14 OF 18 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 12(C)*

Evaluate CVCS letdown flow and place final CVCS letdown orifice in service.

(repeat of procedure steps 9.3 through 9.5)

Standard:

Determines third letdown orifice is needed to reach required flow.

Adjusts letdown header pressure to approximately 200 psig by opening PCV-0135 on CP-004.

• Opens isolation valve for the 25 gpm letdown orifice by taking handswitch for GPM MOV-0014 ORIF ISOL VLV to OPEN.

Adjusts PRESS CONT PCV-0135" to maintain 350-380 psig after opening FV-0014 and places in AUTO.

• Ensures a steady state flow of 220 - 250 gpm is achieved.

Comment:

• - denote critical portions of step.

Cue:

(If applicant asks for guidance)- Inform him/her (as Unit Supervisor) that the third letdown orifice is to be placed in service if letdown flow is currently less than 220 gpm and immediately removed from service if steady state letdown flow is greater than 250 gpm with it is placed in service.

Notes:

The Applicant may increase charging flow to match the increased letdown flow using charging flow controller CHG FLOW CONT FK-0205" OR pressurizer master level controller LEVEL CONT LK-0665.

JPM NO: S5 PAGE 15 OF 18 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 13 Place Letdown Pressure Controller in AUTO. (procedure step 9.6)

Standard:

Places Letdown pressure controller PK-0135 in Automatic control on CP-004.

Comment:

Cue:

Notes:

JPM NO: S5 PAGE 16 OF 18 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step 14 Ensure demineralizers in service per Section 7.0, as desired. (procedure step 9.7)

Standard:

Transitions to Section 7.0 of the procedure.

Places the DIVERT TCV-0143 in the DEMIN position.

Comment:

Cue:

If asked, as the Unit Supervisor, direct the applicant to place the demineralizers in service.

Notes:

- TERMINATE THE JPM -

JPM STOP TIME

JPM NO: S5 PAGE 17 OF 18 VERIFICATION OF COMPLETION Job Performance Measure: S5, MAXIMIZE LETDOWN DUE TO HIGH RCS ACTIVITY Applicant's Name:

SSN:

Date Performed:

Time to Complete:

JPM Results: Sat / Unsat Evaluator: Signature __________________________

Date ____________________

JPM NO: S5 PAGE 18 OF 18 JPM - STUDENT HANDOUT READ TO PERFORMER:

The evaluator will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

YOU ARE TO INFORM THE EVALUATOR WHEN YOU HAVE COMPLETED THE TASK.

CAUTION: Do not operate or alter equipment configuration in the plant without proper authorization.

INITIAL CONDITIONS:

The unit is in Mode 3 following a reactor trip with Centrifugal Charging Pump 1A and the 125 gpm letdown orifice in service. RCS samples indicate an increasing activity, and chemistry has determined that the in-service mixed bed demineralizer decontamination factor is adequate.

In accordance with 0POP04-RC-0001, step 4.a, Chemistry has requested that Operations maximize letdown flow.

INITIATING CUE:

The Unit Supervisor directs you to place Centrifugal Charging Pump 1B in service, then maximize letdown by placing additional letdown orifices in service as necessary to establish 220-250 gpm letdown flow in accordance with 0POP02-CV-0004, Chemical and Volume Control System Subsystem. You are not to exceed a steady state letdown flow rate of 250 gpm.

JPM NO: S6 PAGE 1 OF 16 NUCLEAR TRAINING DEPARTMENT OPERATING JOB PERFORMANCE MEASURE TITLE: RESTORE MAIN FEEDWATER FOLLOWING REACTOR TRIP JPM NO.: S6 REVISION: 0 LOCATION: Simulator

JPM NO: S6 PAGE 2 OF 16 JOB PERFORMANCE MEASURE WORKSHEET JPM

Title:

RESTORE MAIN FEEDWATER FOLLOWING REACTOR TRIP JPM No.: S6 Rev. No: 0 STP Task: 81658, Respond to a reactor trip.

STP Objective: 81658, Respond to a reactor trip per POP05-EO-ES01.

Related K/A

Reference:

059 A4.11 [3.1/3.3] Ability to manually operate and monitor in the control room: Recovery from automatic feedwater isolation.

References:

0POP05-EO-ES01, Rev. 16, Reactor Trip Response Task Normally Completed By: RO/SRO Method of Testing: Actual Performance Location of Testing: Simulator Time Critical Task: NO Alternate Path JPM: YES Validation Time: 20 minutes Required Materials (Tools/Equipment):

None

JPM NO: S6 PAGE 3 OF 16 JOB PERFORMANCE MEASURE INFORMATION SHEET READ TO PERFORMER (a copy of this information is included at the end of the JPM as a tear-away sheet to be given to the student):

I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

YOU ARE TO INFORM THE EVALUATOR WHEN YOUVE COMPLETED THE TASK.

CAUTION: Do not operate or alter equipment configuration in the plant without proper authorization.

INITIAL CONDITIONS:

A reactor trip has just occurred. The control room operators have completed the immediate actions of 0POP05-EO-EO00 and transition to 0POP05-EO-ES01 has been made.

INITIATING CUE:

The Unit Supervisor directs you to establish Main Feedwater flow to the steam generators in accordance with Addendum 6 of 0POP05-EO-ES01, Reactor Trip Response and stabilize levels between 22% and 50%.

- DO NOT DISCLOSE INFORMATION BELOW THIS LINE -

COMPLETION CRITERIA:

Main Feedwater is supplying all steam generators with the leaking main feedwater regulating valves isolated and Auxiliary Feedwater is secured.

JPM NO: S6 PAGE 4 OF 16 JOB PERFORMANCE MEASURE INFORMATION SHEET HANDOUTS:

Working copy of 0POP05-EO-ES01, Reactor Trip Response NOTES:

1) This JPM is formatted for dynamic simulator performance only. The cues provided are related to communications and other general information needed for dynamic performance. (NO Indication type Cues are provided).

2) Use the Simulator Setup section below to prepare the simulator.

SIMULATOR SETUP:

1) JPMs S5 and S6 are to run together. The following steps will set up the simulator for BOTH JPMs.

2) Ensure Radio volume for both stations are set to a reasonable level.

3) Ensure the PA buttons on the communications consoles are taped to help eliminate usage.

4) Reset to IC #71 and verify:

C Step counter positions C ICS restored C Control switch FLAGS reset

5) Check and clean the following procedures:

C 0POP02-CV-0004. Chemical and Volume Control System Subsystem C 0POP05-EO-ES01, Reactor Trip Response

6) Place simulator in run.

7) Start lesson #6, (JPMs S5 and S6), but do not execute any steps.

A) If asked to isolate the Main Feedwater Reg Valve for SG B (JPM S6), trigger STEP 1 (FW-0042)

B) If asked to isolate the Main Feedwater Reg Valve for SG C (JPM S6), trigger STEP 2 (FW-0093)

JPM NO: S6 PAGE 5 OF 16 JOB PERFORMANCE MEASURE CHECK SHEET NOTE:

• Critical steps are identified by (C).

• Sequenced steps are identified by (S1, S2, . . .).

JPM START TIME SAT/UNSAT Performance Step: 1 Obtain a copy of the procedure.

Standard:

Obtains a copy of 0POP05-EO-ES01 and goes to Addendum 6.

Comment:

Provide the Handout copy of 0POP05-EO-ES01, or the operator may use the simulator copy of the procedure.

Cue:

Notes:

JPM NO: S6 PAGE 6 OF 16 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 2 Verify the availability of the startup steam generator feedpump. (Addendum 6, steps 1 and 2)

Standard:

____ Verifies the S/U SGFP running

____ Verifies the S/U SGFP discharge valve is open Comment:

The pump will be running with discharge valve open.

Cue:

Notes:

JPM NO: S6 PAGE 7 OF 16 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 3 Place feedwater regulating and low power feedwater regulating valves in manual and minimum demand. (Addendum 6, step 3)

Standard:

Verifies the feedwater regulating and low power feedwater regulating valves in manual and minimum demand.

Comment:

The valves will already be in manual and at minimum demand.

Cue:

Notes:

JPM NO: S6 PAGE 8 OF 16 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 4 Place the handswitches for the following valves in the closed position: (Addendum 6, step 4)

• Feedwater Isolation Valves

• Feedwater Isolation Bypass Valves

• Preheater Bypass Valves Standard:

Places/ensures the handswitches for the following valves in the closed position:

____ Feedwater Isolation Valves (4)

____ Feedwater Isolation Bypass Valves (4)

____ Preheater Bypass Valves (4)

Comment:

Handswitches for the Feedwater Isolation Bypass and Preheater Bypass Valves will already be in the closed position.

Cue:

Notes:

JPM NO: S6 PAGE 9 OF 16 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 5 (C)

Reset the feedwater isolation signal. (Addendum 6, steps 5 - 8)

Standard:

Resets the Feedwater Isolation Signal by performing the following:

• Depresses BOTH white LOW Tavg reset pushbuttons

• Depresses BOTH white FW CONT / BYP VLVS reset pushbuttons Depresses BOTH white SI/SG HI-HI LEVEL reset pushbuttons

• Momentarily places ALL (8) feedwater isolation safety-grade solenoid handswitches in the OPEN position. (This must be performed last)

Comment:

Items marked with an

• are the critical steps.

Cue:

If asked, as the Unit Supervisor, report that a S/G HI-HI Level actuation has NOT occurred previously.

Notes:

JPM NO: S6 PAGE 10 OF 16 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 6 (C)

Open the preheater bypass valves. (Addendum 6, step 9)

Standard:

Opens the preheater bypass valves (4)

Comment:

1) A caution in the procedure prior to this step warns the operator that the main feedwater regulating valve may need to be isolated if steam generator level increases uncontrollably after opening the respective preheater bypass valve.

2) The main feedwater regulating valves for steam generators B and C will begin leaking when their respective preheater bypass valves are opened.

Cue:

If the applicant reports, to the Unit Supervisor, the need to isolate feedwater to the steam generator, direct the applicant to isolate feedwater to the steam generator.

Notes:

JPM NO: S6 PAGE 11 OF 16 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 7 (C)

Direct a Plant Operator to isolate the leaking main feedwater regulating valves.

Standard:

Directs a Plant Operator to isolate the following valves:

___ Steam generator B main feedwater regulating valve

___ Steam generator C main feedwater regulating valve Comment:

This step may be performed out of sequence depending on when the applicant recognizes the uncontrolled increase in steam generator levels.

Cue:

If questioned, direct the applicant to contact the Plant Operator using the radio.

Notes:

JPM NO: S6 PAGE 12 OF 16 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 8 (C)

Establish steam generator main feedwater flow with the low power feedwater regulating valves.

(Addendum 6, step 10)

Standard:

Opens each (4) of the low power feedwater regulating valves to establish main feedwater flow to all steam generators.

Comment:

Cue:

Notes:

SAT/UNSAT Performance Step: 9 Verify steam generator narrow range level in at least one steam generator - greater than 14%.

(Addendum 6, step 11)

Standard:

Verifies narrow range level in at least one steam generator is greater than 14%.

Comment:

All narrow range steam generator levels are greater than 14%.

Cue:

Notes:

JPM NO: S6 PAGE 13 OF 16 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 10 Check Auxiliary Feedwater in service to any steam generator. (Addendum 6, step 12)

Standard:

Determines Auxiliary Feedwater is in service to ALL steam generators.

Comment:

All four Auxiliary Feedwater Pumps are running.

Cue:

Notes:

JPM NO: S6 PAGE 14 OF 16 JOB PERFORMANCE MEASURE CHECK SHEET SAT/UNSAT Performance Step: 11 Secure Auxiliary Feedwater to steam generators being supplied by main feedwater.

(Addendum 6, step 13)

Standard:

Secures all four Auxiliary Feedwater Pumps by performing the following:

___ Depresses ALL (3) white SG LO-LO LVL RESET (BLOCK) pushbuttons

___ Closes ALL (4) Auxiliary Feedwater OCIVs

___ Secures ALL (4) Auxiliary Feedwater Pumps by:

• Turning the handswitches for the motor driven pumps to STOP, then to AUTO

• Tripping the steam driven pump and closing the TRIP/THROTTLE VALVE

___ Opening ALL (4) Auxiliary Feedwater flow control valves Comment:

Cue:

Notes:

- TERMINATE THE JPM -

JPM STOP TIME

JPM NO:

PAGE 15 OF 16 VERIFICATION OF COMPLETION Job Performance Measure: S6, RESTORE MAIN FEEDWATER FOLLOWING REACTOR TRIP Applicant's Name:

SSN:

Date Performed:

Time to Complete:

JPM Results: Sat / Unsat Evaluator: Signature Date

JPM NO: S6 PAGE 16 OF 16 JPM - STUDENT HANDOUT READ TO PERFORMER:

The evaluator will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.

YOU ARE TO INFORM THE EVALUATOR WHEN YOUVE COMPLETED THE TASK.

CAUTION: Do not operate or alter equipment configuration in the plant without proper authorization.

INITIAL CONDITIONS:

A reactor trip has just occurred. The control room operators have completed the immediate actions of 0POP05-EO-EO00 and transition to 0POP05-EO-ES01 has been made.

INITIATING CUE:

The Unit Supervisor directs you to establish Main Feedwater flow to the steam generators in accordance with Addendum 6 of 0POP05-EO-ES01, Reactor Trip Response and stabilize levels between 22% and 50%.

OP-TEST #1 SCENARIO #1 PAGE 1 OF 15 INITIAL LICENSE EXAM OPERATING TEST #1 SCENARIO #1 September 17, 2001 Revision 1

OP-TEST #1 SCENARIO #1 PAGE 2 OF 15 SCENARIO OUTLINE Facility: South Texas Project Scenario No.: 1 Op-Test No.: 1 Source:

New X Bank - Significantly Modified _____ Bank - Initial Condition Change _____

(See Page 3 - Scenario Crew Assignments to determine Examiner/Operator assignments)

Initial Conditions: 48% power, on hold for feedpump repair.

Steam Generator Feedpump #11 is OOS for maintenance.

Turnover: Shift Feedwater Booster Pumps for pump vibration inspection and maintain current power.

Event Malf. No. Event Event Description and Timing (Time) & (Value) Type*

1 N/A BOP (N) Shift Feedwater Booster Pumps (0 min) SRO (N) 2 05-12-03 BOP (I) Steam Generator level transmitter LT-0539 fails low - after the discharge valve (15 min) (0.0) SRO (I) for FWBP #11 is opened or after 15 minutes 3 02-26-02 RO (I) Loop 1B T-Cold RTD TT-420B fails high - after Tech Specs are addressed for (25 min) (1.0) SRO (I) LT-0539 or after 10 minutes 4 07-04-03 RO (R) Steam Generator Feedpump #13 trips, Startup Feedpump does not/will not start (45 min) (true) BOP (C) requiring a manual load reduction - after Tech Specs are addressed for TT-420B SRO (C) or after 20 minutes.

5 02-12-01 ALL (M) Pressurizer steam space break.

(57 min) (0.3) ATWS - Reactor fails to trip from the control room.

01-12-02 - after the plant stabilizes following the power reduction or after 12 minutes.

(true) 6 08-02-01 BOP (C) Turbine driven auxiliary feedwater pump overspeeds upon start.

(n/a) (true) SRO (C) 7 04-13-02 RO (C) High head safety injection pump 1B trips - after the HHSI pumps are verified (72 min) (true) SRO (C) running in FRS1 or after 15 minutes following the LOCA.

The scenario is terminated after RCPs are secured in E-0

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor.

OP-TEST #1 SCENARIO #1 PAGE 3 OF 15 Scenario #1 Crew Assignments SESSION 1 - CREW A Examiners: E2 Operators: SRO - U1 E1 RO - R1 E3 BOP - R3 SESSION 2 - CREW B Examiners: E3 Operators: SRO - U2 E2 RO - R2 E4 BOP - R4 SESSION 3 - CREW C Examiners: E4 Operators: SRO - U3 E3 RO - I1 E1 BOP - R5 SESSION 4 - CREW D Examiners: E4 Operators: SRO - I2 E1 RO - I3 E2 BOP - R6

OP-TEST #1 SCENARIO #1 PAGE 4 OF 15 SCENARIO MISCELLANEOUS INFORMATION SIMULATOR BOOTH NOTES:

SIMULATOR SETUP

1. Reset to IC #65 and go to run.

2. Execute lesson plan #1 under lesson plan group LOT13NRC

3. Position and tag control switches as follows:

• #11 SGFP discharge MOV (MOV-0119) - closed - Danger Tag

• #11 SGFP reset pushbutton - not reset - Danger Tag EXPECTED BOOTH OPERATIONS

1. Autograph file "/cae/rose/work/lot13nrcscenario1.agb.3" should load with lesson plan. At the conclusion of the scenario ensure the labels for the parameters on the autograph file are changed to include the verbal description by selecting "options",

"label', then "description" before printing out the critical parameter trends from the autograph file.

2. When directed as Plant Operator to locally open the Reactor Trip Breakers, wait 2 minutes then trigger step 7 of the Lesson Plan.

3. If directed to reset the overspeed trip of the TDAFP, trigger step 8 of the Lesson Plan.

EXPECTED BOOTH COMMUNICATIONS

1. As TGB Operator, when asked to verify lube oil and seal oil systems in service for FWBP #13, report that the systems are operating normally and the pump is ready for a start. If asked, lube oil reservoir temperature is 85EF.

2. As TGB Operator (or CP Operator), when asked following the start of FWBP #13:

• Lube oil pressure - 33 psig

• Lube oil temperature - 110EF

• Recirc valve position - report the recirc valve is closed

3. When called as I&C to trip bistables for LT-539, report that I&C Technicians will report to the control room in 30 minutes to trip bistables. (It will NOT be necessary to trip bistables in this scenario.)

OP-TEST #1 SCENARIO #1 PAGE 5 OF 15 SCENARIO MISCELLANEOUS INFORMATION EXPECTED BOOTH COMMUNICATIONS (cont)

4. When called as I&C to trip bistables for TT-420B, report that I&C Technicians will report to the control room in 30 minutes to trip bistables. (It will NOT be necessary to trip bistables in this scenario.)

5. As Plant Operator, if asked to check SGFP #13 following its trip, after five minutes report:

• All systems appear normal locally at the pump

• The DCS printer shows Unit #13 Cards 3 & 14 Failed trip

6. As Plant Operator, if asked to check the SUFP following its failure to start, after 5 minutes report that all appears normal locally at the pump and at the breaker.

7. As Plant Operator, if asked to check the TDAFP following its overspeed trip, after 5 minutes report that the pump appears normal locally.

8. As Plant Operator, if asked to check HHSI pump 1B following its trip, after 3 minutes report that the 50/51 relay is tripped.

CRITICAL PARAMETERS:

The following parameters may be of value in evaluating crew performance and should be placed in an Autograph file for recall when the scenario is completed:

• Reactor Power

• SG C Narrow Range Level

• Total AFW Flow

• RCS Wide Range Pressure OPERATOR ACTIONS TABLE NOTES:

1. Critical Tasks are indicated by "C" in the position column and indicated in bold type.

2. Actions required throughout the event are indicated as "(continuous)" in the position column.

3. Shaded cells indicate procedural entry points.

OP-TEST #1 SCENARIO #1 PAGE 6 OF 15 OPERATOR ACTIONS Op-Test No.: #1 Scenario No.: #1 Event No.: 1 Event

Description:

Swap Feedwater Booster Pumps Time Position Applicant's Actions or Behavior Notes SRO Direct the BOP to start Feedwater (continuous) Booster Pump (FWBP) # 13 and secure Feedwater Booster Pump #11 per 0POP02-FW-0001, Main Feedwater.

BOP Contact the TGB operator to verify Lube Oil and Seal Water Systems are in service for FWBP #13.

BOP Verify adequate lube oil available for FWBP #13 by verifying the "L.O. AUX PMP TRBL" alarm is clear.

BOP Verify the Deaerator Storage Tank is

>30%

BOP Verify FWBP #13 is properly warmed up by checking pump discharge temperature is within 50 degrees of Deaerator temperature on the Plant Computer.

BOP Announce over the start of FWBP #13 over the plant paging system.

BOP Ensure the handswitch for FWBP #13 discharge valve is in the closed position.

BOP Start FWBP #13.

BOP Contact the TGB operator to verify the following conditions after the start of FWBP #13:

- Proper lube oil pressure

- Proper recirc valve operation

- Proper lube oil temperature BOP Take the FWBP #11 discharge valve to the closed position and Stop the FWBP when the discharge valve is closed.

BOP Perform the following to place FWBP

1. 11 in standby:

- Discharge Valve open

- Control Room handswitch in AUTO

OP-TEST #1 SCENARIO #1 PAGE 7 OF 15 OPERATOR ACTIONS (Cont')

Op-Test No.: #1 Scenario No.: #1 Event No.: 2 Event

Description:

Steam Generator level transmitter LT-539 fails low Time Position Applicant's Actions or Behavior Notes BOP Acknowledges and reports annunciators on Control Panel CP006:

• SG 1C LVL DEV HI/LO

• SG 1C LVL LO

• SG 1C LVL LO-LO ALERT SRO/BOP Performs immediate actions of 0POP04-FW-001:

• Places SG 1C Feedwater Regulating Valve controller in MANUAL

• Adjusts controller output to match feed/steam flow and restore SG 1C level to program SRO Directs/ensures actions of (continuous) 0POP04-FW-0001, Loss of Steam Generator Level Control.

BOP Identifies that SG 1C level channel LT-539 has failed low.

BOP Selects channel LT-573 for SG 1C level control.

SRO/RO Initiates action to trip affected channel within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> BOP Performs the following:

• Verifies SG 1C level between 68%

and 74%

• Places SG 1C Feed Regulating Valve in AUTO SRO Refers to Tech Specs 3.3.1 (6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> action) and 3.3.2 (1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> action).

OP-TEST #1 SCENARIO #1 PAGE 8 OF 15 OPERATOR ACTIONS (Cont')

Op-Test No.: #1 Scenario No.: #1 Event No.: 3 Event

Description:

Loop 1B T-Cold TT-420B fails high Time Position Applicant's Actions or Behavior Notes RO Acknowledges and reports annunciators on Control Panel CP005 which are indicative of a RTD failure.

SRO Directs/ensures actions of (continuous) 0POP04-RP-0004, Failure of RCS Loop RTD Protection Channel.

RO Verifies rod control is in manual.

RO Identifies/reports the failed channel as TI-420B.

RO Selects Loop 2 Defeat on the following switches:

• BYP SEL ? T

• BYP SEL T AVG RO Ensures Tavg is maintained within 1.5EF of Tref.

RO/BOP Takes manual control of FCV-0205, CHG FLOW CONT, if necessary, to maintain pressurizer level at program.

RO/BOP Ensures ? T and ? T Setpoints Recorder selected to an operable channel.

SRO Initiates actions per Tech Spec 3.3.2, Action 20 to trip bistables within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

OP-TEST #1 SCENARIO #1 PAGE 9 OF 15 OPERATOR ACTIONS (Cont')

Op-Test No.: #1 Scenario No.: #1 Event No.: 4 Event

Description:

Steam Generator Feedpump #13 trips, Startup Feedpump does not/will not start requiring a manual load reduction.

Time Position Applicant's Actions or Behavior Notes BOP Acknowledges and reports annunciator SGFPT 13 TRIP on Control Panel CP-006.

SRO/BOP Performs Immediate Actions of 0POP04-FW-0002:

• Attempts start of the Startup Steam Generator Feedpump

• Starts a standby FW Booster Pump SRO Directs/ensures actions of 0POP04-FW-0002, Addendum 1 to reduce turbine load.

SRO/RO Determine 5 gals of boric acid per 10%

power reduction required RO Ensures Rod Control is in automatic.

BOP Reduces turbine load at <5%/min to match steam/feed flow using one of the following methods:

• Operator Auto

• Turbine Manual

• Governor Valve Limiter RO Energizes pressurizer heaters as necessary.

BOP Verifies/maintains VARS within the guidelines of the Plant Curve Book.

RO Commences boration of the RCS (Reactivity)

RO Checks/restores Tavg to within 3oF of (Reactivity) Tref.

RO Checks/restores Pressurizer level and pressure to within limits BOP Checks/restores Steam Generator levels to within 68-74%

OP-TEST #1 SCENARIO #1 PAGE 10 OF 15 OPERATOR ACTIONS (Cont')

Op-Test No.: #1 Scenario No.: #1 Event No.: 5 Event

Description:

Pressurizer steam space break. ATWS - Reactor fails to trip from the control room Time Position Applicant's Actions or Behavior Notes ALL Identify/report an excessive RCS leak as indicated by the following:

• Lowering RCS pressure

• Increasing containment pressure

• Increasing containment sump level SRO Directs a manual reactor trip and safety injection based on low RCS pressure.

RO/BOP Performs the immediate actions of EO00, Reactor Trip or Safety Injection RO/BOP When attempts fail to trip the reactor in Step 1 of EO00, performs the immediate actions of FRS1, Response to Nuclear Power Generation - ATWS:

• Inserts control rods

• Attempts to open breakers to LC 1K1 and 1L1 ALL Dispatches a plant operator to open the reactor trip breakers locally.

SRO Directs/ensures immediate actions of (continuous) FRS1, Response to Nuclear Power Generation - ATWS are completed and direct subsequent actions.

RO/BOP Recloses breakers to LC 1K1 and 1L1 after reactor trip breakers are opened.

ALL Ensures safety injection occurs automatically on low RCS pressure.

RO INITIATE EMERGENCY (continuous) BORATION OF THE RCS.

C BOP Perform FRS1, Addendum 2, (continuous) Verification of SI Equipment Operation, following safety injection.

BOP Maintains total AFW flow $1080 gpm when narrow range level in all SGs are

< 14% (34%) after step 9 of FRS1.

OP-TEST #1 SCENARIO #1 PAGE 11 OF 15 RO Verifies dilution paths isolated:

• Boric Acid flow controller set > 8.0

• Letdown demineralizer bypassed

• Reactor Makeup Water (RMW)

Pumps in PTL

• RMW Non-Essential header isol.

valves closed SRO/RO Verifies Reactor is Subcritical:

• < 5% on Extended Range NIs

• Zero or Negative SUR on Extended Range NIs SRO Verifies Adequate Shutdown Margin:

• Requests RCS boron sample

• Continues emergency boration until RCS boron is greater than SDM limit SRO Transitions back to EO00, Reactor Trip or Safety Injection.

ALL TRIP ALL RCPs IF RCS PRESSURE Terminate the scenario C IS < 1460 PSIG AND AT LEAST 1 HHSI PUMP IS IN OPERATION

OP-TEST #1 SCENARIO #1 PAGE 12 OF 15 OPERATOR ACTIONS (Cont')

Op-Test No.: #1 Scenario No.: #1 Event No.: 6 Event

Description:

Turbine driven auxiliary feedwater pump overspeeds upon start.

Time Position Applicant's Actions or Behavior Notes BOP Acknowledges AFWP 14 T & T MECH OVERSP TRIP alarm and reports that AFWP #14 (TDAFP) has tripped.

BOP Dispatches a Plant Operator to locally Crew may opt to crosstie AFW start/reset the TDAFP. to feed SG D.

SRO/BOP Ensures that total AFW flow is > 1080 Actions continue under event 5 gpm (or > 576 gpm in E0) when narrow range levels in all SGs are < 14%

(34%).

OP-TEST #1 SCENARIO #1 PAGE 13 OF 15 OPERATOR ACTIONS (Cont')

Op-Test No.: #1 Scenario No.: #1 Event No.: 7 Event

Description:

High head safety injection pump 1B trips.

Time Position Applicant's Actions or Behavior Notes RO Acknowledges HHSI PUMP 1B TRIP annunciator and reports that HHSI Pump 1C has tripped.

SRO Directs RO to place HHSI Pump 1B handswitch in the PTL position per 0POP09-AN-01M2-D5.

RO Places HHSI Pump 1B handswitch in the PTL, as directed.

SRO/RO Ensures personnel are dispatched to Actions continue under Event 5 investigate cause of HHSI Pump 1B trip.

OP-TEST #1 SCENARIO #1 PAGE 14 OF 15 CRITICAL TASK

SUMMARY

POSITION EXPECTED RESPONSE ACCEPTANCE CRITERIA SAT/

UNSAT ALL TRIP ALL RCPs IF RCS Trip all RCPs so that an Orange C PRESSURE IS < 1460 PSIG AND Path on Core Cooling does not AT LEAST 1 HHSI PUMP IS IN occur when forced circulation OPERATION is lost (prior to entering E-10)

RO INITIATE EMERGENCY Initiate emergency boration (continuous) BORATION OF THE RCS. prior to exiting FRS1.

C

OP-TEST #1 SCENARIO #1 PAGE 15 OF 15 TURNOVER INFORMATION

• Reactor power is 48%, on hold for feedpump repair, at step 7.36 of 0POP03-ZG-0005.

• Cycle burnup is 150 MWD/MTU

• SGFP #11 is out of service for maintenance. Estimated return to service - 8 hours0.333 days <br />0.0476 weeks <br />0.011 months <br />.

• Start FWBP #13 for a vibration analysis, and secure FWBP #11 as soon as possible following turnover. Engineering and the Turbine Building Plant Operator are standing by the pump and the CP watch is standing by the recirc valve.

• Maintain current power level until SGFP #11 is repaired.

• Xenon is burning out due to the power increase.

• Borating 3 gallons every half hour.

• Boric Acid Tanks A and B are at 7300 ppm.

OP-TEST 1 SCENARIO 2 PAGE 1 OF 16 INITIAL LICENSE EXAM OPERATING TEST 1 SCENARIO 2 September 17, 2001 Revision 1

OP-TEST 1 SCENARIO 2 PAGE 2 OF 16 SCENARIO OUTLINE Facility: South Texas Project Scenario No.: 2 Op-Test No.: 1 Source:

New Bank - Significantly Modified Bank - Initial Condition Change X (See Page 3 - Scenario Crew Assignments to determine Examiner/Operator assignments)

Initial Conditions: 75% power, with a power increase in progress.

Train A Control Room HVAC and Feedwater Booster Pump #13 are OOS for maintenance.

Turnover: Load Steam Generator Feedpump #13 and continue power increase to 100%.

Event Malf. No. Event Event Description (Time) & (Value) Type* & Timing 1 N/A BOP (N) Load Steam Generator Feedpump #13.

(0 min) SRO (N) 2 N/A RO (R) Increase power to 100%.

(0 min) 3 05-17-03 BOP (I) Steam generator 1C PORV pressure transmitter fails high - after both a reactivity (20 min) (1.0) SRO (I) change occurs AND SGFP #13 loaded or after 20 minutes.

4 50-R3-02 RO (I) Power range channel N42 control power failure - after Tech Specs are addressed (30 min) (True) SRO (I) for SG 1C PORV or after 10 minutes.

5 08-23-01 BOP (C) Condensate Pump #11 trips - after Tech Specs are addressed for N42 or after 15 (45 min) (True) SRO (C) minutes.

6 02-01-03 ALL (M) Large Break LOCA on Loop C Cold Leg - after secondary conditions stabilize (52 min) (0.7) following the Condensate Pump trip or after 7 minutes.

7 01-12-4B RO (C) Containment Isolation, Phase A, Train B automatic failure (n/a) (T) SRO (C) CV-MOV-0023, Letdown ICIV, Train A fails to close bmp005 - upon an automatic Phase A Isolation signal.

(1.0) The scenario is terminated after the crew aligns cold leg recirculation per ES13.

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor.

OP-TEST 1 SCENARIO 2 PAGE 3 OF 16 Scenario 2 Crew Assignments SESSION 1 - CREW A Examiners: E2 Operators: SRO - U1 E3 RO - R3 E1 BOP - R1 SESSION 2 - CREW B Examiners: E3 Operators: SRO - U2 E4 RO - R4 E2 BOP - R2 SESSION 3 - CREW C Examiners: E3 Operators: SRO - I1 E1 RO - R5 E4 BOP - U3 SESSION 4 - CREW D Examiners: E1 Operators: SRO - I3 E4 RO - I2 E2 BOP - R6

OP-TEST 1 SCENARIO 2 PAGE 4 OF 16 SCENARIO MISCELLANEOUS INFORMATION SIMULATOR BOOTH NOTES:

SIMULATOR SETUP

1. Reset to IC #66 and go to run.

2. Execute Lesson Plan # under Lesson Plan Group LOT13NRC.

3. Position and Tag control switches as follows:

- CR HVAC SPLY AHU 11A - PTL - Danger Tag

- CR HVAC RET FAN 11A - PTL - Danger Tag

- CR HVAC C/U FAN 11A - PTL - Danger Tag

- FWBP #13 - PTL - Danger Tag

- FWBP #13 discharge valve - Danger Tag EXPECTED BOOTH OPERATIONS

1. Autograph file "/cae/rose/work/lot13nrcscenario2.agb.3" should load with lesson plan. At the conclusion of the scenario ensure the labels for the parameters on the autograph file are changed to include the verbal description by selecting "options",

"label', then "description" before printing out the critical parameter trends from the autograph file.

EXPECTED BOOTH COMMUNICATIONS

1. If asked, report that Aux. Steam header is warmed up.

2. As Plant Operator, if asked to monitor SGFP #13 as it is placed in service, report that no problems can be found locally.

3. As Plant Operator, if asked to check SGFP #13 oil temperature after loading, report oil cooler discharge temperature of 114 EF.

4. If contacted as Reactor Engineering, inform the Control Room that flux maps can/will be performed every 12 hours0.5 days <br />0.0714 weeks <br />0.0164 months <br />.

5. When called as I&C to trip bistables for N42, report that I&C Technicians will report to the control room in 30 minutes to trip bistables. (It will not be necessary to trip bistables in this scenario.)

6. As Plant Operator, if asked to investigate the cause for the Condensate Pump #11 trip, after 5 minutes report that the 50/51 relay is tripped locally.

OP-TEST 1 SCENARIO 2 PAGE 5 OF 16 SCENARIO MISCELLANEOUS INFORMATION EXPECTED BOOTH COMMUNICATIONS CONT

7. As Plant Operator, if asked to check Condensate Pump #13 prior to/after the start, report that the pump is ready for a start/running satisfactorily.

CRITICAL PARAMETERS:

The following parameters may be of value in evaluating crew performance and should be placed in an Autograph file for recall when the scenario is completed:

Reactor Power SG C Steam Flow SG C Narrow Range Level RCS Wide Range Pressure RWST Level OPERATOR ACTIONS TABLE NOTES:

1. Critical Tasks are indicated by "C" in the position column and indicated in bold type.

2. Actions required throughout the event are indicated as "(continuous)" in the position column.

3. Shaded cells indicate procedural entry points.

OP-TEST 1 SCENARIO 2 PAGE 6 OF 16 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 2 Event No.: 1 Event

Description:

Load Steam Generator Feedpump (SGFP) #13.

Time Position Applicant's Actions or Behavior Notes SRO Directs BOP to load SGFP 13 per 0POP02-FW-0002, S.G.F.P. Turbine.

BOP Loads SGFP 13 as follows:

• Checks SG LVL CONTROL light lit

• Opens discharge valve MOV-0061

• Ensures the SGFP SPEED controller is in manual at minimum output

• Raises SGFP speed to match required SGFP differential pressure

• Places SPEED controller in AUTO when SGFP speed matches the SGFP MASTER SPEED controller OR any other operating SGFP speed BOP Monitors SGFP speed controller for proper operation.

OP-TEST 1 SCENARIO 2 PAGE 7 OF 16 OPERATOR ACTIONS (Cont')

Op-Test No.: 1 Scenario No.: 2 Event No.: 2 Event

Description:

Increase power to 100%

Time Position Applicant's Actions or Behavior Notes SRO Enters 0POP03-ZG-0008, Power Operations, at Step 7.2 and directs the RO to commence the power increase.

RO Dilutes RCS as necessary while raising (Reactivity) turbine load to reach desired power level.

RO Maintains Tave within 1.5 EF of Tref and maintains AFD within Tech Spec limits.

OP-TEST 1 SCENARIO 2 PAGE 8 OF 16 OPERATOR ACTIONS (Cont')

Op-Test No.: 1 Scenario No.: 2 Event No.: 3 Event

Description:

Steam Generator 1C PORV Pressure Transmitter Fails High Time Position Applicant's Actions or Behavior Notes BOP Acknowledges and reports annunciator SG PORV NOT CLOSE on Control Panel CP006.

BOP Performs the following actions of 0POP09-AN-06M3-A1:

< Identifies that SG 1C PORV has lifted

< Verifies SG 1C pressure is <1225 psig

< Manually closes SG 1C PORV SRO Ensures SG 1C PORV has been closed manually BOP Identifies SG 1C Pressure Transmitter PT-7431 has failed high.

SRO Initiates actions per Tech Spec 3.7.1.6 and 3.3.5.1 (action 2) to restore SG PORV 1C to operable status within 7 days.

OP-TEST 1 SCENARIO 2 PAGE 9 OF 16 OPERATOR ACTIONS (Cont')

Op-Test No.: 1 Scenario No.: 2 Event No.: 4 Event

Description:

Power Range Channel N42 Control Power Failure Time Position Applicant's Actions or Behavior Notes RO Acknowledges and reports annunciators on Control Panel CP005 which are indicative of a Power Range NI failure and references 0POP09-AN-05M3.

RO/BOP Reports that control power has failed to Power Range Channel N42.

RO Performs immediate actions of 0POP04-NI-0001, Nuclear Instrument Malfunction:

< Ensures rod control is selected to MANUAL

< Verifies Low Power Feedwater Regulating Valves are not in service SRO Enters 0POP04-NI-0001 and ensures that the immediate actions have been completed.

SRO Directs the actions of Addendum 3, (continuous) Power Range NI Malfunction.

SRO/RO Stop Main Turbine load changes or BOP SRO/RO Directs/performs actions to bypass Power Range Channel N42 input to:

< COMPARATOR CHANNEL DEFEAT

< POWER MISMATCH BYPASS

< ROD STOP BYPASS

< DET CURRENT COMPARATOR -

UPPER SECTION

< DET CURRENT COMPARATOR -

LOWER SECTION RO Verifies the following Permissives in their correct state:

< P-7 permissive light - Extinguished

< P-8 permissive light - Extinguished

< P-9 permissive light - Extinguished

< P-10 permissive light - Illuminated

OP-TEST 1 SCENARIO 2 PAGE 10 OF 16 RO/BOP Performs the following:

< Select operable PR channel on NI recorder.

< Contact Rx Engineering to perform flux maps.

SRO Initiates actions per Tech Spec 3.3.1, Table 3.3-1, Action 2 - Bistables tripped within 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br />.

OP-TEST 1 SCENARIO 2 PAGE 11 OF 16 OPERATOR ACTIONS (Cont')

Op-Test No.: 1 Scenario No.: 2 Event No.: 5 Event

Description:

Condensate Pump #11 Trips Time Position Applicant's Actions or Behavior Notes BOP Acknowledges and reports annunciator COND PMP TRIP on Control Panel CP009.

SRO Ensures actions of annunciator response (continuous) are carried out to start a standby pump.

BOP Performs the following actions of 0POP09-AN-09M1-A1:

• Starts standby Condensate Pump

• Opens respective Condensate Pump discharge valve

• Dispatches Plant Operator to determine cause of the trip.

OP-TEST 1 SCENARIO 2 PAGE 12 OF 16 OPERATOR ACTIONS (Cont')

Op-Test No.: 1 Scenario No.: 2 Event No.: 6 Event

Description:

Large Break LOCA on Loop C Cold Leg Time Position Applicant's Actions or Behavior Notes RO/BOP Completes the immediate actions of EO00, Reactor Trip or Safety Injection.

SRO Directs/ensures immediate actions of EO00, Reactor Trip or Safety Injection are completed.

ALL Trips RCPs due to containment isolation Phase B actuation OR RCS pressure

<1460 psig with at least 1 HHSI pump running.

RO/BOP Maintains total AFW flow $576 gpm when narrow range level in all SGs are

< 14% (34% adverse)

ALL Monitor/apply adverse containment (continuous) values when containment pressure is $ 5 psig.

RO/BOP Identifies and reports Containment Actions for failure of Isolation Phase A, Train B has failed to Containment Isolation are automatically actuate and CV-MOV-0023 described under Event #7.

has failed to close automatically.

ALL Complete all actions of EO00 up to Step 14 and transition to EO10, Loss of Reactor or Secondary Coolant.

ALL Monitor Critical Safety Functions upon (continuous) exiting EO00.

SRO Transitions to FRP1, Response to Imminent Pressurized Thermal Shock Condition, due to rapid RCS temperature decrease.

SRO/RO Exits FRP1 at Step 1 (RNO) based on LHSI flow being > 500 gpm.

SRO Transitions to FRZ1, Response to Containment High Pressure and directs operator actions.

OP-TEST 1 SCENARIO 2 PAGE 13 OF 16 SRO Transitions to EO10, Loss of Reactor or Note: Depending on the rate Secondary Coolant and directs operator of procedure progress, the actions as time and conditions permit. crew may or may not perform steps of EO10.

RO Resets the following:

• Safety Injection

• ESF Load Sequencers

• Phase A and B Containment Isolation RO Places containment hydrogen monitoring system in service.

SRO Transitions to ES13, Transfer to Cold Leg (continuous) Recirculation, when RWST level decreases to less than 75,000 gallons.

RO Aligns charging pump suction to the VCT:

• Opens VCT outlet valves

• Closes charging pump RWST suction valves

• Sets boric acid flow controller to >8

• Opens RMW pump discharge isolation valves SRO/RO ALIGNS INJECTION FLOWPATHS Terminate Scenario C FOR COLD LEG RECIRCULATION

• Closes RWST to SI suction header valves

• Resets SI Auto Recirc

OP-TEST 1 SCENARIO 2 PAGE 14 OF 16 OPERATOR ACTIONS (Cont')

Op-Test No.: 1 Scenario No.: 2 Event No.: 7 Event

Description:

Containment Isolation Phase A, Train B Automatic Failure and CV-MOV-0023, Letdown ICIV, Train A Fails to Close from Control Room (Results in Letdown Header CNTMT Penetration being Unisolated)

Time Position Applicant's Actions or Behavior Notes RO/BOP Identifies/Reports Containment Isolation Phase A, Train B has failed to actuate and CV-MOV-0023 has failed to close.

SRO Directs RO to manually actuate Containment Isolation Phase A and close CV-MOV-0023.

RO ENSURES CONTAINMENT C ISOLATION PHASE A BY EITHER:

• MANUALLY INITIATING CONTAINMENT ISOLATION PHASE A OR

• MANUALLY CLOSING CV-MOV-0024, LETDOWN OCIV RO Attempts to manually close Actions continue under Event CV-MOV-0023, Letdown ICIV from the #6.

Control Room panel CP004.

OP-TEST 1 SCENARIO 2 PAGE 15 OF 16 CRITICAL TASK

SUMMARY

POSITION EXPECTED RESPONSE ACCEPTANCE CRITERIA SAT/

UNSAT ALL ENSURES CONTAINMENT Containment isolated such that C ISOLATION PHASE A BY at least one valve in the EITHER: letdown header penetration is

• MANUALLY INITIATING closed before the scenario is CONTAINMENT ISOLATION terminated.

PHASE A OR

• MANUALLY CLOSING CV-MOV-0024, LETDOWN OCIV SRO/RO ALIGNS INJECTION Transfer to cold leg C FLOWPATHS FOR COLD LEG recirculation and establish RECIRCULATION. ECCS recirculation flow prior to RWST level decreasing to 48,000 gallons (6%) RWST EMPTY alarm receipt.

OP-TEST 1 SCENARIO 2 PAGE 16 OF 16 TURNOVER INFORMATION

• 75% power on hold to start up SGFP #13

• Cycle burnup is 150 MWD/MTU, fuel is conditioned to 100% power.

• Hourly dilutions to maintain this power level are approximately 10 gallons.

• Increase power to 100% using 0POP03-ZG-0008, Step 7.0

• While increasing power, load Steam Generator Feedpump #13.

< Pre-Startup testing has been waived by the Shift Supervisor

• Feedwater Booster Pump #13 is OOS for motor bearing inspection.

< Removed from service 4 hours0.167 days <br />0.0238 weeks <br />0.00548 months <br /> ago. Expected to be returned to service tomorrow.

• Train A Control Room HVAC is OOS for preventative maintenance.

< Removed from service 2 hours0.0833 days <br />0.0119 weeks <br />0.00274 months <br /> ago. Expected to be returned to service in 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br />

< TS 3.7.7 - Return to service in 7 days.

• Boric Acid Tanks A and B are at 7300 ppm.

OP-TEST 1 SCENARIO 3 PAGE 1 OF 14 INITIAL LICENSE EXAM OPERATING TEST #1 SCENARIO #3 September 18, 2001 Revision 1

OP-TEST 1 SCENARIO 3 PAGE 2 OF 14 SCENARIO OUTLINE Facility: South Texas Project Scenario No.: 3 Op-Test No.: 1 Source:

New Bank - Significantly Modified Bank - Initial Condition Change X Examiners: E4 Operators: SRO - I2 E2 RO - R6 E1 BOP - I3 Initial Conditions: 27% power with a plant startup in progress.

ESF Diesel Generator #13 is OOS for maintenance.

Turnover: Continue with plant startup towards 100% power.

Event Malf. No. Event Event Description and Timing (Time) & (Value) Type*

1 N/A RO (R) Load increase towards 100% power.

(0 min) 2 02-19-03 RO (I) Pressurizer pressure controlling channel (PT-457) fails low - after an observable (15 min) (V=0) SRO (I) reactivity change or after 15 minutes.

3 05-11-04 BOP (C) SG D steam flow channel fails low - after Tech Specs have been addressed for (30 min) (V=0) SRO (C) the PZR pressure channel or after 15 minutes.

03-23-05 RCP 1C #1 seal failure (ramped in) - after all feedwater regulation valves are RO (C) returned to AUTO or after 10 minutes.

4 (V=1)

SRO (C)

(40 min) 06-02-01 BOP (C)

(V=True) Main Turbine fails to automatically trip 5 05-02-01 Steam break in containment on SG 1A after manual reactor trip from RCP seal ALL (M)

(45 min) (V=1) leakoff trip set point exceeded or after 5 minutes.

6 04-16-01 RO (C) 1A Containment Spray Pump trips following verification or 14 minutes after the (59 min) (V=1) SRO (C) steam break.

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor.

OP-TEST 1 SCENARIO 3 PAGE 3 OF 14 Scenario 3 Crew Assignments SESSION 1 - CREW D Examiners: E4 Operators: SRO - I2 E2 RO - R6 E1 BOP - I3

OP-TEST 1 SCENARIO 3 PAGE 4 OF 14 SCENARIO MISCELLANEOUS INFORMATION SIMULATOR BOOTH NOTES:

SIMULATOR SETUP

1. Reset to IC #67 and go to run

2. Trigger Lesson Plan #3 from Lesson Plan Group LOT13NRC

3. Position and tag control switches as follows:

• ESF DG #13 Output Bkr - PTL - Danger Tag

• ESF DG #13 Emergency Stop - Pulled - Danger Tag EXPECTED BOOTH OPERATIONS

1. Autograph file "cae/rose/work/lot13nrcscenario3.agb.1" should load with lesson plan. At the conclusion of the scenario ensure the labels for the parameters on the autograph file are changed to include the verbal description by selecting "options",

"label', then "description" before printing out the critical parameter trends from the autograph file.

EXPECTED BOOTH COMMUNICATIONS

1. If asked as I&C to trip Channel 3 bistables for PT-457, tell the Control Room a crew will be there in about 30 minutes. Note, it is not necessary to trip bistables for this scenario.

2. If asked as PO to check status of 1A Containment Spray Pump, wait 3 minutes and report that 1A CSP has no local indications for reason of trip.

3. If asked as PO to check status of 1A Containment Spray Pump breaker, wait 3 minutes and report that the breaker has a 50/51 relay tripped.

OP-TEST 1 SCENARIO 3 PAGE 5 OF 14 SCENARIO MISCELLANEOUS INFORMATION CRITICAL PARAMETERS:

The following parameters may be of value in evaluating crew performance and should be placed in an Autograph file for recall when the scenario is completed:

• RCP 1C Seal Leakoff Flow

• RCB Pressure

• SG 1D Narrow Range Level

• RCS Wide Range Pressure OPERATOR ACTIONS TABLE NOTES:

1. Critical Tasks are indicated by "C" in the position column and indicated in bold type.

2. Actions required throughout the event are indicated as "(continuous)" in the position column.

3. Shaded cells indicate procedural entry points.

OP-TEST 1 SCENARIO 3 PAGE 6 OF 14 OPERATOR ACTIONS Op-Test No.: 1 Scenario No.: 3 Event No.: 1 Event

Description:

Load increase towards 100% power Time Position Applicant's Actions or Behavior Notes SRO Directs RO increase reactor power and (continuous) turbine load per 0POP03-ZG-0005, Plant Startup to 100%, Step 7.28 RO Performs dilution of RCS to raise Tave (reactivity) and raises turbine load.

RO Controls Tave to within 1.5°F of Tref and maintains AFD within Tech Spec limits.

OP-TEST 1 SCENARIO 3 PAGE 7 OF 14 OPERATOR ACTIONS (Cont')

Op-Test No.: 1 Scenario No.: 3 Event No.: 2 Event

Description:

Pressurizer pressure controlling channel (PT-457) fails low.

Time Position Applicant's Actions or Behavior Notes ALL Identify and respond to annunciators on CP004 indicative of a failed Pressurizer pressure channel.

RO Identifies the failed pressure channel as failed low.

SRO Enters 0POP04-RP-0001, Loss of (continuous) Automatic Pressurizer Pressure Control.

Places Pressurizer Master Pressure RO Controller in MANUAL.

Removes failed channel RC-PI-0457 RO from control.

ENSURES Pressurizer pressure between RO 2220 and 2250 and controller output signal between 15 and 35%.

RO Places pressure controller in Auto and VERIFY Pressurizer pressure controlling between 2220 and 2250 psig.

SRO NOTIFIES I&C to trip Channel 3 bistables for P0457 per 0POP04-RP-0001, Addendum 2 and INITIATES corrective action.

SRO Refers to Technical Specifications and determines that 3.3.2, Action 20 is the most limiting (requires the channel to be placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />). 3.3.1 also applies (6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> action)

OP-TEST 1 SCENARIO 3 PAGE 8 OF 14 OPERATOR ACTIONS (Cont')

Op-Test No.: 1 Scenario No.: 3 Event No.: 3 Event

Description:

SG D steam flow channel fails low.

Time Position Applicant's Actions or Behavior Notes ALL Identify and respond to annunciators on CP006 indicative of a failed steam flow channel.

BOP Identifies SG D level below set point and takes FCV-0554 to manual to restore SG NR level to 69 to 74%.

BOP Verifies SGFP speed controllers responding in Automatic.

SRO Enters 0POP04-FW-0001, Loss of (continuous) Steam Generator Level Control, and directs BOP to restore SG D NR level to 68 to 74%.

BOP Identifies Steam Flow channel FT-0542 failed low and selects FT-0543 for control.

BOP Places FCV-0554 in Auto and monitors for proper operation.

SRO Initiates corrective action for FT-0542 and determines no Tech Spec actions are required for the failure.

OP-TEST 1 SCENARIO 3 PAGE 9 OF 14 OPERATOR ACTIONS (Cont')

Op-Test No.: 1 Scenario No.: 3 Event No.: 4 Event

Description:

RCP 1C #1 seal failure (ramp over 5 minutes)

Main Turbine fails to automatically trip Time Position Applicant's Actions or Behavior Notes ALL Identify and respond to annunciators on CP004 indicative of a RCP 1C #1 seal failure.

SRO Enters 0POP04-RC-0002, Reactor (continuous) Coolant Pump Off Normal, for indications of abnormal RCP #1 seal indication.

RO Identifies RCP 1C trip criteria on high

1. 1 seal leak off flow (>6gpm) and trips the Reactor and RCP 1C.

BOP MANUALLY TRIPS MAIN C TURBINE RO CLOSES RCP 1C #1 seal leakoff isolation (FV-3156) between 3 to 5 minutes after stopping RCP 1C.

SRO Enters 0POP05-EO-0000, Reactor Trip (continuous) or Safety Injection.

OP-TEST 1 SCENARIO 3 PAGE 10 OF 14 OPERATOR ACTIONS (Cont')

Op-Test No.: 1 Scenario No.: 3 Event No.: 5 Event

Description:

Steam break in containment on SG 1A after manual reactor trip from RCP seal leakoff trip set point exceeded.

Time Position Applicant's Actions or Behavior Notes ALL Responds to the following annunciators, 5M03-F7, CNTMT PRESS HI-1 SI ALERT; 5M04-E2, CNTMT PRESS HI-1 SI, FIRST-OUT ALARM; SI-ESF STATUS MONITORING; PHASE A ISOL, ESF STATUS MONITORING.

SRO Directs RO/BOP to manually initiate SI and/or ensures that SI actuates when required.

RO/BOP Manually initiates SI when directed by the US.

ALL Complete immediate actions of EO00 .

ALL Trips remaining RCPs when RCS pressure is <1460 psig or following Phase B isolation.

RO Verifies Containment Spray initiated and Containment Isolation Phase B actuated.

SRO Transitions to EO20, Faulted SG (continuous) Isolation ALL Commence Critical Safety Function Status Tree usage.

ALL Evaluate plant conditions and alert the crew of an orange path on containment CSF and that entry into FRZ1 is required.

SRO Transitions to FRZ1 on an orange path (continuous) on containment CSF.

SRO Directs/ensures isolation of FAULTED SG A

OP-TEST 1 SCENARIO 3 PAGE 11 OF 14 ALL ISOLATES FAULTED SG A: Once the faulted S/G is C

• Reset SI identified, the AFW pump may

• Reset S/G Lo-Lo level actuation be placed in Pull-To-Lock (this could occur earlier)

• Close A S/G AFW OCIV SRO Returns to EO20, after completing the actions of FRZ1.

SRO Transitions to ES11, SI Termination. Depending on how the crew (continuous) progresses through the procedures, a short transition to EO10 could occur first.

RO Resets Containment Isolation Phase A and B RO/BOP Restores instrument air to containment RO Restores cooling to the Spent Fuel Pool Heat Exchanger RO Secures all LHSI and HHSI pumps as Terminate scenario.

directed.

OP-TEST 1 SCENARIO 3 PAGE 12 OF 14 OPERATOR ACTIONS (Cont')

Op-Test No.: 1 Scenario No.: 3 Event No.: 6 Event

Description:

1A Containment Spray Pump trips (following verification).

Time Position Applicant's Actions or Behavior Notes RO Identifies that Containment Spray Pump 1A tripped and references 0POP09-AN-02M2 \ C4.

SRO/RO Places Containment Spray Pump 1A in PTL per 0POP09-AN-02M2.

RO Dispatches a Plant Operator to Scenario continues with Event investigate trip of the pump. #5

OP-TEST 1 SCENARIO 3 PAGE 13 OF 14 CRITICAL TASK

SUMMARY

POSITION EXPECTED RESPONSE ACCEPTANCE CRITERIA SAT/

UNSAT ALL MANUALLY TRIPS MAIN MAIN TURBINE TRIPPED C TURBINE PRIOR TO ORANGE PATH CONDITION FOR SUBCRITICALITY OR INTEGRITY IS REACHED, OR TRANSITION TO EC21.

SRO/BOP ISOLATES FAULTED SG A SG A ISOLATED PRIOR C TO TRANSITION OUT OF EO20

OP-TEST 1 SCENARIO 3 PAGE 14 OF 14 TURNOVER INFORMATION

• Plant is holding at 27% power following a reactor startup.

• Cycle burnup is 150 MWD/MTU

• Hourly dilutions to maintain this power level are approximately 25 gallons. Xenon is building in slowly.

• Boric Acid Tanks A and B are at 7,300 ppm boron.

• ESF DG #13 is OOS for planned maintenance.

% Removed from service 5 hours0.208 days <br />0.0298 weeks <br />0.00685 months <br /> ago; estimated time for return to service is 35 hours1.458 days <br />0.208 weeks <br />0.0479 months <br />.

% TS 3.8.1.1, action b - Perform 0PSP03-EA-0002 every 8 hours0.333 days <br />0.0476 weeks <br />0.011 months <br /> (last completed 4.5 hours0.208 days <br />0.0298 weeks <br />0.00685 months <br /> ago)

% TS 3.8.1.1, action b - Return to service within 14 days (EAOT will apply after 72 hours3 days <br />0.429 weeks <br />0.0986 months <br />)

• Continue power increase at Step 7.28 of 0POP03-ZG-0005, Plant Startup to 100%.

OP-TEST #1 BACKUP SCENARIO PAGE 1 OF 15 INITIAL LICENSE EXAM OPERATING TEST #1 BACKUP SCENARIO September 17, 2001 Revision 1

OP-TEST #1 BACKUP SCENARIO PAGE 2 OF 15 SCENARIO OUTLINE Facility: South Texas Project Scenario No.: Backup (spare) Op-Test No.: 1 Source:

New Bank - Significantly Modified Bank - Initial Condition Change X (Examiner/Operator position assignments will be determined by the Chief Examiner if and when it is necessary to administer this backup scenario in whole or in part)

Initial Conditions: 100% power Circulating Water Pump #14 is OOS for maintenance Turnover: Shift Centrifugal charging Pumps for upcoming maintenance.

Reduce power to 90% to remove a Steam Generator Feedpump from service Event Malf. No. Event Event Description and Timing (Time) & (Value) Type*

1 RO (N)

N/A Shift Centrifugal Charging Pumps.

(0 min) SRO (N) 2 N/A RO (R) Reduce power to 90%.

(0 min) 3 03-09-02 RO (C) 1B Centrifugal Charging Pump trips - after both a reactivity change occurs AND (18 min) (true) SRO (C) charging pumps are swapped or after 18 minutes.

4 08-15-01 BOP (I) 1A Steam Generator controlling feedwater flow channel fails low - after Tech (23 min) (true) SRO (I) Specs are addressed for Charging Pump 1B or after 5 minutes.

5 50-BM-01 RO (I) VCT level transmitter LT-113 fails high - after feedwater regulating valves are in (33 min) (1.0) SRO (I) AUTO or after 10 minutes.

6 05-03-02 1B Steam Generator Tube Rupture (~700 gpm ramped over 10 minutes) - after ALL (M)

(40 min) (0.16) letdown divert valve is closed or after 7 minutes.

7 05-04-02 BOP (C) Steam Generator 1B Main Steam Safety Valve fails open - after the MSIV is (65 min) (1.0) SRO (C) closed in E30 or after 25 minutes.

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor.

OP-TEST #1 BACKUP SCENARIO PAGE 3 OF 15 SCENARIO MISCELLANEOUS INFORMATION SIMULATOR BOOTH NOTES:

SIMULATOR SETUP

1. Reset to IC #68 and go to run.

2. Execute Lesson Plan #4 under Lesson Plan Group LOT13NRC

3. Position and tag control switches as follows:

• Circulating Water Pump #14 - PTL - Danger Tag EXPECTED BOOTH OPERATIONS

1. Autograph file "cae/rose/work/lot13nrcscenario4.agb.2" should load with lesson plan. At the conclusion of the scenario ensure the labels for the parameters on the autograph file are changed to include the verbal description by selecting "options",

"label', then "description" before printing out the critical parameter trends from the autograph file.

EXPECTED BOOTH COMMUNICATIONS

1. As Plant Operator, if asked to check Charging Pump 1B for a start, report that the pump is ready for a start (you are already in place per the turnover). After pump is started, report the pump running satisfactorily.

2. As Plant Operator, if asked to investigate CCP 1B trip, after 5 minutes report that the 50/51 relay is tripped locally.

3. As Plant Operator, if asked to check CCP 1A following its start, after 3 minutes report that the pump is running satisfactorily.

4. As I&C, if asked to investigate failed feedflow channel, report that a crew will be sent to the Control Room to troubleshoot. Further action is not required.

5. As I&C, if asked to investigate failed VCT level channel, report that a crew will be sent to the control room to troubleshoot. Further action is not required.

OP-TEST #1 BACKUP SCENARIO PAGE 4 OF 15 SCENARIO MISCELLANEOUS INFORMATION CRITICAL PARAMETERS:

The following parameters may be of value in evaluating crew performance and should be placed in an Autograph file for recall when the scenario is completed:

• SG B Wide Range Level

• SG B Pressure

• SG B AFW Flow

• SG A Narrow Range Level

• RCS Wide Range Pressure OPERATOR ACTIONS TABLE NOTES:

1. Critical Tasks are indicated by "C" in the position column and indicated in bold type.

2. Actions required throughout the event are indicated as "(continuous)" in the position column.

3. Shaded cells indicate procedural entry points.

OP-TEST #1 BACKUP SCENARIO PAGE 5 OF 15 OPERATOR ACTIONS Op-Test No.: #1 Scenario No.: Backup (spare) Event No.: 1 Event

Description:

Shift Centrifugal Charging Pumps Time Position Applicant's Actions or Behavior Notes SRO Directs the RO to Start Centrifugal Charging Pump 1B and Secure Centrifugal Charging Pump 1A per POP02-CV-0004, Chemical and Volume Control System Subsystem.

RO Ensures CVCS System is prepared for Centrifugal Charging Pump 1B start.

• Ensures discharge valve open

• Charging flow control valve in manual

• CCP Aux lube oil pump running RO/BOP Announces intention to start CCP 1B over the plant page and dispatches operator to check locally.

RO Starts CCP 1B and monitors the following:

• Charging flow

• RCP Seal injection flows RO Performs valve alignments and shuts down CCP 1A.

RO Places charging flow control valve in auto and monitors the following while adjusting seal injection flow control valve as necessary:

• Charging flow

• RCP Seal injection flows

• Pressurizer level RO Ensure cooling fan starts for CCP 1B and secures cooling fan for CCP 1A RO Reports to the SRO that CCPs have been shifted.

OP-TEST #1 BACKUP SCENARIO PAGE 6 OF 15 OPERATOR ACTIONS (Cont')

Op-Test No.: #1 Scenario No.: Backup (spare) Event No.: 2 Event

Description:

Reduce power to 90%

Time Position Applicant's Actions or Behavior Notes SRO Enters 0POP03-ZG-0008, Power Operations, at step 6.1 and directs the RO to commence power reduction to 90%

RO Borates as necessary while reducing (reactivity) turbine load to reach desired power level.

RO Maintains Tave within 1.5 EF of Tref and maintains AFD within Tech Spec Limits.

OP-TEST #1 BACKUP SCENARIO PAGE 7 OF 15 OPERATOR ACTIONS (Cont')

Op-Test No.: #1 Scenario No.: Backup (spare) Event No.: 3 Event

Description:

1B Centrifugal Charging Pump trips Time Position Applicant's Actions or Behavior Notes RO Acknowledges and reports all (4) RCP SEAL WATER INJ FLOW LO annunciators and CHG FLOW HI/LO annunciator on Control Panel CP004.

SRO/RO Recognizes and reports that CCP 1B has tripped.

SRO Directs/ensures 0POP09-AN-04M8-F3 annunciator response actions to manually start CCP 1A.

RO Ensures the following:

• FCV-0205, CHG FLOW CONT VLV is closed

• MOV-8377A, CCP 1A DISCH ISOL is open

• FCV-0201, CCP 1A RECIRC is open

• CCP 1A white L.O. AVAILABLE light is lit RO Start Centrifugal Charging Pump 1A.

RO Adjusts charging flow and seal injection flow as necessary.

RO Performs the following:

• Closes FCV-0201, CCP 1A RECIRC

• Returns FCV-0205, CHG FLOW CONT to AUTO.

SRO Declares CCP 1B inoperable and refers to Technical Requirement Manual 3.1.2.4, Charging Pumps Operating, and enters Action statement to restore CCP 1B to operable status within 7 days.

OP-TEST #1 BACKUP SCENARIO PAGE 8 OF 15 OPERATOR ACTIONS (Cont')

Op-Test No.: #1 Scenario No.: Backup (spare) Event No.: 4 Event

Description:

1A Steam Generator controlling feedwater flow channel fails low.

Time Position Applicant's Actions or Behavior Notes BOP Acknowledges and reports annunciators on Control Panel CP006:

• SG 1A LVL DEV HI/LO

• SG 1A STM/FW FLOW MSMTCH SRO/BOP Performs immediate actions of 0POP04-FW-0001:

• Places SG 1A feedwater reg. valve controller in MANUAL

• Adjusts controller output to match feed/steam flow and restore SG 1A level to program SRO Directs/ensures actions of (continuous) 0POP04-FW-0001, Loss of Steam Generator Level Control.

BOP Identifies that feedwater flow channel FI-0510 for SG 1A has failed low.

BOP Selects FT-511 for SG 1A level control.

BOP Performs the following:

• Places LK-7406 DA Storage Tank Level Controller in Manual

• Maintains DA Storage Tank level between 65% and 80%

BOP Performs the following:

• Verifies SG 1A level between 68%

and 74%

• Places SG 1A Feed Regulating Valve in AUTO SRO Checks Tech Specs 3.3.1, 3.3.2, 3.3.3.6 and determines that a Tech Spec LCO is not entered.

OP-TEST #1 BACKUP SCENARIO PAGE 9 OF 15 OPERATOR ACTIONS (Cont')

Op-Test No.: #1 Scenario No.: Backup (spare) Event No.: 5 Event

Description:

VCT level transmitter LT-113 fails high.

Time Position Applicant's Actions or Behavior Notes RO Acknowledges and reports annunciator VCT LEVEL HI/LO on Control Panel CP004 RO Performs the following actions of 0POP09-AN-04M8-E2:

• Determines LT-113 is failed using ICS computer

• Monitors computer points to control VCT level SRO Directs LCV-0112A, Divert Valve, be placed in the VCT position.

RO Places LCV-0112A handswitch to the VCT position and ensures valve position changes SRO/RO/ Contacts I&C to investigate failure BOP

OP-TEST #1 BACKUP SCENARIO PAGE 10 OF 15 OPERATOR ACTIONS (Cont')

Op-Test No.: #1 Scenario No.: Backup (spare) Event No.: 6 Event

Description:

1B Steam Generator Tube Rupture (~700 gpm ramped over 10 minutes).

Time Position Applicant's Actions or Behavior Notes RO/BOP Acknowledges and announces radiation monitoring alarms and begins an investigation into possible tube leak.

SRO Begins investigation of SG tube leakage by directing RO/BOP to monitor RCS leakage and identify the affected SG.

RO/BOP Identifies the affected SG.

SRO Directs/ensures operator actions of Actions of 0POP04-RC-0004 (continuous) 0POP04-RC-0004, Steam Generator may not be performed Tube Leakage. depending on how quickly the leak is diagnosed and leak rate estimated.

SRO/BOP Ensures blowdown is isolated from SG B RO Control and monitor CVCS charging and letdown to maintain VCT level greater than 15% and pressurizer level greater than 17%

SRO Ensures that BOP/RO monitor and report status of pressurizer level, VCT level and SG B feed flow steam flow mismatch.

SRO Direct performance of POP03-ZG-0006, Plant Shutdown From 100% to Hot Standby such that the plant is in Mode 3 in < 6 hours0.25 days <br />0.0357 weeks <br />0.00822 months <br />.

ALL Manually initiates SI when directed or prior to pressurizer level decreasing to

< 17%.

SRO Ensures that the crew enters 0POP05-EO-EO00, Reactor Trip or Safety Injection.

RO/BOP Completes immediate actions of EO00, Reactor Trip/SI.

OP-TEST #1 BACKUP SCENARIO PAGE 11 OF 15 SRO Directs/ensures the immediate actions of EO00, Reactor Trip/SI have been completed.

ALL Ensures RCPs are tripped if RCS (continuous) pressure drops to less than 1460 psig.

SRO/BOP Ensures that AFW flow is isolated to (continuous) SG B when level is >14% narrow range.

ALL Completes the actions of EO00 up to the EO30, Ruptured Steam Generator, transition point.

SRO Transitions to EO30, SGTR based on SG radiation abnormal.

ALL Monitors the status of Critical Safety (continuous) Functions when the crew transitions to 0POP05-EO-EO30.

BOP Identifies Ruptured SG as SG B.

SRO/BOP ISOLATES FEEDWATER FLOW Event #7 occurs at this point C INTO AND STEAM FLOW FROM SG B BY:

• ADJUSTING SG B PORV SETPOINT TO BETWEEN 1260 AND 1265 PSIG

• CLOSING SG B MSIV

• ISOLATING AFW TO SG B BOP Recognizes SG B is depressurizing and determines a safety valve is stuck open.

SRO Transitions to E20 based on CIP entry See Event #7 for actions on (any SG depressurizing in an failed open SG safety.

uncontrolled manner).

SRO Transitions back from E20 to E30 step 1 Actions continues from based on high main steam line radiation Event #7 readings SRO/BOP Determine SG B pressure is < 426 psig SRO Transitions to 0POP05-EO-EC31, SGTR With Loss Of Reactor Coolant -

Subcooled Recovery Desired, and directs RO/BOP actions.

RO/BOP Restores IA to containment when directed by resetting Containment Isolation Phase A and opening the IA OCIV.

RO Restores CCW cooling to the Spent Fuel Pool Heat Exchanger

OP-TEST #1 BACKUP SCENARIO PAGE 12 OF 15 SRO/RO Secures LHSI pumps when RCS pressure is determined to be > 415 psig RO Establishes charging flow if not already completed.

SRO/BOP ESTABLISH RCS COOLDOWN Terminate the scenario C RATE AT < 100 EF/HR

OP-TEST #1 BACKUP SCENARIO PAGE 13 OF 15 OPERATOR ACTIONS (Cont')

Op-Test No.: #1 Scenario No.: Backup (spare) Event No.: 7 Event

Description:

Steam Generator 1B Main Steam Safety Valve fails open when actions are taken to isolate the steam generator during the tube rupture.

Time Position Applicant's Actions or Behavior Notes BOP Determines SG B is faulted based on the following:

• SG B pressure decreasing

• Computer indication of Safety open SRO Transitions to EO20, Faulted SG Isolation, and directs RO/BOP actions.

SRO/BOP Closes all MSIVs AND MSIBs.

SRO/BOP Ensures that AFW is isolated on SG B.

BOP/RO When directed, resets SI, SG LO-LO level AFW actuation, SG blowdown and sample isolation.

SRO Notifies Chemical Analysis to sample all Operator actions continue at SGs for activity. event #6

OP-TEST #1 BACKUP SCENARIO PAGE 14 OF 15 CRITICAL TASK

SUMMARY

POSITION EXPECTED RESPONSE ACCEPTANCE CRITERIA SAT/

UNSAT SRO/BOP ISOLATES FEEDWATER FLOW Isolates SG B feedwater and INTO AND STEAM FLOW steam flow before a transition FROM SG B. to EC31 occurs SRO/BOP ESTABLISH RCS COOLDOWN Cooldown the RCS to cold RATE AT < 100 EF/HR shutdown at the highest rate allowed by procedure

(< 100 EF/hr), but such that a severe (Orange path) challenge to the Integrity CSF is not encountered.

OP-TEST #1 BACKUP SCENARIO PAGE 15 OF 15 TURNOVER INFORMATION

• Reactor power is 100%

• Cycle burnup is 150 MWD/MTU

• Circulating Water Pump #14 is out of service for maintenance. Estimated return to service - 4 days.

• Hourly dilutions to maintain current power are approximately 10 gallons. Xenon is at equilibrium conditions.

• Boric Acid Tanks A and B are at 7300 ppm.

• Start Charging Pump 1B and secure Charging Pump 1A for upcoming maintenance. The MAB watch is standing by for the pump start.

• Reduce reactor power to 90% to facilitate removal of SGFP #11 from service to repair an oil leak.

• No liquid waste discharges are in progress or planned.