ML13247A234

CW-2013-08 Final Op Test

ML13247A234
Person / Time
Site:	Callaway
Issue date:	08/27/2013
From:	Kelly Clayton Operations Branch IV
To:	Union Electric Co
laura hurley
References
50-483/13-008
Download: ML13247A234 (203)

Text

ES-301 Administrative Topics Outline Form ES-301-1 Facility: __Callaway_______________________

Date of Examination: _8/27/13______ Examination Level: RO SRO Operating Test Number: 2013 Re-Exam Administrative Topic (see Note) Type Code* Describe activity to be performed RSA-1 Conduct of Operations R N Review ECP Calculation 2.1.37 Knowledge of procedures, guidelines, or limitations associated with reactivity management. (4.6

) RSA-2 Conduct of Operations R D Determine the volume and RMCS control settings for raising RWST level 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc. (4.2)

RSA-3 Equipment Control R N Review CCP Surveillance for Operability 2.2.12 Knowledge of surveillance procedures. (4.1)

RSA-4 Radiation Control R M Determine Maximum Allowable Stay Time 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions. (3.7)

RSA-5 Emergency Procedures/Plan R D Classify Emergency Events Requiring Emergency Plan Implementation 2.4.41 Knowledge of the emergency action level thresholds and classifications. (4.6)

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

• Type Codes & Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from RO retakes)

(N)ew or (M)odified from

Administrative Topic Outline Task Summary RSA-1: Review ECP Calculation The Applicant will review a n ECP calculation performed in accordance with OSP-SF-00005 "Estimated Critical Position Calculation". The critical steps include identifying the errors of using the wrong temperature used

, wrong boron worth, and identifying wrong maximum rod height.

This is a new JPM.

RSA-2: Determine the volume and RMCS control settings for raising RWST level The Applicant will determine the potentiometer settings for Boric Acid and Blended flow using RWST level/volume curves and OTN

-BG-002, "Reactor Makeup Control and Boron Thermal Regeneration System". The critical steps include determining the volume to be added to the RWST, interpolating curves to determine Boric Acid and Makeup Water flows, and determining the potentiometer settings for Boric Acid and Blended flow

. This JPM is from the bank and was used on the 2005 ILT SRO Exam.

RSA-3: Review CCP Surveillance for Operability The Applicant will review Attachment 2 of OSP

-BG-P005B "Centrifugal Charging Pump B Inservice Test

- Group and identify the pump D/P was calculated incorrectly. The critical steps include identifying the calculation error, declaring the pump inoperable and entering the correct Technical Specification.

This is a new JPM

. RSA-4: Determine Maximum Allowable Stay Time The Applicant will determine the allowable stay time using a RWP and Survey Map. The

critical steps include determining the correct RWP, dosimeter setting, dose rate from survey map, and calculate stay time

. This JPM is modified from a bank JPM that was used on the 2005 ILT SRO Exam

RSA-5: Classify Emergency Events Requiring Emergency Plan Implementation The Applicant will be given a set of plant conditions and will implement the Radiological Emergency Response Plan (RERP) to classify the event within 15 minutes (Time Critical)

This JPM is from the bank and has not been used on an ILT exam since 2004.

CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE JPM No: RSA-1 rev2 KSA No: GEN 2.1.37 Revision:

August 2013 KSA Rating:

4.6 Job Title:

SRO Task Title:

Review ECP Calculation

. Validation Time: 20 minutes Learning Objective: T61.003A 6, LP A

-12, Obj D, Given the procedure and actual plant data, Calculate an Estimated Critical Position.

The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY

[ ] UNSATISFACTORY

Reason, if UNSATISFACTORY:

Evaluators Signature:

Date:

Task Performer:

Location of Performance:

Control Room Simulator/Lab Plant Classroom X

Method of Performance:

Simulated Performed X

Alternate Path:

___ ___ Time Critical:

___ ___

Student Handouts

OSP-SF-00005 "Estimated Critical Position Calculation" Curve Book Table 1

-8 WINPCNDR Handouts Calculator

References:

OSP-SF-00005 "Estimated Critical Position Calculation" Plant Curve Book

JPM NO: RSA-1, Rev 1 PAGE 1 of 2 Initial Conditions:

The plant was shutdown for R19 on 4/8/13 at 0322. The refueling outage is complete. The Start

-up is scheduled for 5/26/13 at 1200.

Reactor Engineering department has reported that the ECP program is not available and that the ECP will be calculated using Attachment 1 of OSP

-SF-00005. XEPRED EFPD=0

DATA from various computer programs XEPRED EFPD 0 PCNDR, section 7 BOL critical boron concentration to control at HZP, ARO, (k=1.0) 1421 ppm Anticipated RCS Tavg at startup 557°F The Nuclear engineers have determined that the amount of negative reactivity to

be -242.2 pcm for Step 6.9.3.

It is desired to calculate boron concentration for the ECP.

Initiating Cues:

The Shift Manager has directed you to review and approve the completed Attachment 1 of OSP

-SF-00005 "Estimated Critical Position Calculation" using the printouts and information provided by the Reactor engineer

. Inform the Shift Manager of any issues with the calculation.

Task Standard:

Upon completion of this JPM, th e Applicant will have identified the errors Attachment 1 of OSP

-SF-00005 "Estimated Critical Position Calculation".

START TIME:

STOP TIME:

JPM NO: RSA1, Rev 1 JPM TASK STEP ELEMENT PERFORMANCE STANDARD SCORE PAGE 2 of 2 Provide the candidate with a copy of OSP

-SF-00005 "Estimated Critical Position Calculation" and the print outs from WinPCNDR *1. Candidate reviews Attachment 1 of OSP-SF-00005 "Estimated Critical Position Calculation" Applicant identifies the errors and informs the Shift Manager. See KEY for correct data.

Critical steps of the Attachment are marked on the KEY. Error 1 wrong temperature in step 6.8.1 Wrong differential boron worth in step 6.12.2 Wrong Max rod height in step 6.14.4 S U Comments:

2. The JPM is complete Record stop time on Page 1 S U Comments:

Denotes Critical Step

Initial Conditions:

The plant was shutdown for R19 on 4/8/13 at 0322. The refueling outage is complete. The Start

-up is scheduled for 5/26/13 at 1200.

Reactor Engineering department has reported that the ECP program is not available and that the ECP will be calculated using Attachment 1 of OSP

-SF-00005. XEPRED EFPD=0

DATA from various computer programs XEPRED EFPD 0 PCNDR, section 7 BOL critical boron concentration to control at HZP, ARO, (k=1.0) 1421 ppm Anticipated RCS Tavg at startup 557°F The Nuclear engineers have determined that the amount of negative reactivity to be -242.2 pcm for Step 6.9.3.

It is desired to calculate boron concentration for the ECP.

Initiating Cues:

The Shift Manager has directed you to review and approve the completed of OSP

-SF-00005 "Estimated Critical Position Calculation" using the printouts and information provided by the Reactor engineer

. Inform the Shift Manager of any issues with the calculation.

Page 1 of 22 CONTINUOUS USE

OSP-SF-00005 ESTIMATED CRITICAL POSITION CALCULATION MINOR Revision 019

OSP-SF-00005 Rev. 019 ESTIMATED CRITICAL POSITION CALCULATION TABLE OF CONTENTS Section Page Number Page 2 of 22 CONTINUOUS USE 1.0PURPOSE ...................................................................................................................................... 32.0SCOPE ........................................................................................................................................... 33.0ACCEPTANCE/FUNCTIONAL CRITERIA .............................................................................. 34.0PRECAUTIONS AND LIMITATIONS ....................................................................................... 35.0PREREQUISITES ......................................................................................................................... 56.0PROCEDURE INSTRUCTIONS ................................................................................................. 66.1.Critical Condition Prior To Last Shutdown .......................................................................... 66.2.Pre-Shutdown Reactivity From Rods ................................................................................... 76.3.Critical Boron Concentrations .............................................................................................. 76.4.Power Defect ....................................................................................................................... 86.5.Fission Products At Shutdown ............................................................................................. 96.6.Total Reactivity At Time Of Shutdown ................................................................................ 96.7.Fission Products At Startup ................................................................................................ 106.8.Temperature At Startup ...................................................................................................... 106.9.Desired Critical Rod Height ............................................................................................... 116.10.Desired Critical Boron Concentration................................................................................. 126.11.Total Reactivity ................................................................................................................. 126.12.Critical Boron Concentration ............................................................................................. 136.13.Critical Rod Height ............................................................................................................ 146.14.Rod Limits ......................................................................................................................... 157.0RESTORATION ......................................................................................................................... 1

78.0REFERENCES

............................................................................................................................ 178.1.Implementing ..................................................................................................................... 178.2.Developmental ................................................................................................................... 179.0RECORDS ................................................................................................................................... 1710.0SUMMARY OF CHANGES ....................................................................................................... 18ATTACHMENT 1, Estimated Critical Position Calculation .................................................................... 19ATTACHMENT 2, Input Guidelines For Estimated Critical Position Calculation ................................... 22 OSP-SF-00005 Rev. 019 Page 3 of 22 CONTINUOUS USE ESTIMATED CRITICAL POSITION CALCULATION 1.0 PURPOSE 1.1. To determine critical rod height. 1.2. To determine critical boron concentration. 2.0 SCOPE Used for reactor startup calculations. 3.0 ACCEPTANCE/FUNCTIONAL CRITERIA Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to achieving reactor criticality; verify that the predicted critical control bank position is within the limits of T/S LCO 3.1.6 per the requirements of T/S SR 3.1.6.1. 4.0 PRECAUTIONS AND LIMITATIONS 4.1. The average moderator temperature for criticality shall be greater than or equal to 551°F. 4.2. When the reactor has been shutdown for less than 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />, the Estimated Critical Position/Boron Concentration shall be recalculated whenever the estimated number of hours from actual criticality to predicted criticality differ by more than one hour. 4.3. Curve Book Figures referenced in this procedure are controlled per ETP-ZZ-00015, Preparation, Review, Approval and Control of the Curve Book. 4.4. Data may be obtained as applicable from the following approved software programs for the current cycle:

• ECP

• PC Nuclear Design Report (PCNDR)

• WinPCNDR

• XENON_PREDICTION

• XEPRED

• Applicable Plant Computer Points 4.5. Design end of life may be obtained from plant computer point REK1531, or Curve Book Table 12-1CC.

OSP-SF-00005 Rev. 019 Page 4 of 22 CONTINUOUS USE 4.6. In some cases, the pre-shutdown reference reactivity data may be more accurate if the data is obtained at equilibrium conditions rather than at conditions just prior to the shutdown. For example, if a rapid downpower is commenced prior to the reactor shutdown, then more accurate reference reactivity data may be obtained from equilibrium conditions just prior to the downpower rather than from transient conditions just prior to the reactor shutdown. 4.6.1. Based on the discussion in Step 4.6, the pre-shutdown reference reactivity data may be obtained from equilibrium conditions at some time prior to the shutdown rather than from conditions immediately prior to the time of shutdown. Guidance for selecting reference reactivity data may be found in Attachment 2. 4.6.2. Caution should be taken to ensure that all pre-shutdown reference reactivity data is selected for a consistent reference time (i.e., data for bank height, boron concentration, power level, xenon reactivity, and samarium reactivity should be selected for the same reference time.) -END OF SECTION-

OSP-SF-00005 Rev. 019 Page 5 of 22 CONTINUOUS USE 5.0 PREREQUISITES 5.1. CHECK the plant is in MODE 3 or 4. 5.2. DETERMINE the desired time for criticality. -END OF SECTION-

OSP-SF-00005 Rev. 019 Page 6 of 22 CONTINUOUS USE 6.0 PROCEDURE INSTRUCTIONS NOTE The ECP software should be used to determine the ECP and ECB. Section 6.0 should be used for guidance in obtaining the necessary input for the ECP software. The computer printout should be filed as a record of the ECP. The approved program should be located in folder I:\NUCENG\SYSTEMS\REACTOR\SOFTWARE\APPROVED\ECP. If the ECP program in this folder is not available, Reactor Engineering should be contacted for the approved software. If the software program is NOT being used, data in the following steps will be recorded on Attachment 1. 6.1. Critical Condition Prior To Last Shutdown 6.1.1. RECORD the shutdown date and time, referring to Attachment 2 for additional guidance. 6.1.2. RECORD the predicted startup date and time. 6.1.3. RECORD the burnup in EFPD using one of the following:

• REU1523, BURN UP

• XEPRED -END OF SECTION-OSP-SF-00005 Rev. 019 Page 7 of 22 CONTINUOUS USE 6.2. Pre-Shutdown Reactivity From Rods 6.2.1. OBTAIN the pre-shutdown controlling bank information as follows: a. IF at the beginning of a cycle AND power has not yet exceeded 5%, RECORD the following information for pre-shutdown conditions:

• Bank D

• 228 steps b. IF power in the current cycle has exceeded 5%, RECORD the following information from pre-shutdown conditions, referring to Attachment 2 for additional guidance:

• The controlling control rod bank.

• The step counters readings for the controlling control rod bank height. NOTE Other sources of rod worth data may be used during physics testing as determined by Reactor Engineering. 6.2.2. Using the rod information from Step 6.2.1, DETERMINE and RECORD the amount of pre-shutdown negative reactivity using one of the following:

• WinPCNDR

• PCNDR, Section 5 -END OF SECTION- 6.3. Critical Boron Concentrations 6.3.1. OBTAIN the critical boron concentration as follows:

a. IF at the beginning of a cycle AND power has not yet exceeded 5%, RECORD the critical boron concentration from the BOL critical boron concentration to control at HZP, ARO, (k=1.0) from PCNDR, Section 7. b. IF power in the current cycle has exceeded 5%, RECORD the most recent sample under stable RCS conditions, referring to Attachment 2 for additional guidance. 6.3.2. CHECK which source was used to obtain critical boron. -END OF SECTION-OSP-SF-00005 Rev. 019 Page 8 of 22 CONTINUOUS USE 6.4. Power Defect 6.4.1. OBTAIN the power level before shutdown as follows:

a. IF at the beginning of a cycle AND power has not yet exceeded 5%, RECORD zero for power level before shutdown. b. IF power in the current cycle has exceeded 5%, RECORD the highest indicated power level the last time Keff was equal to one using one of the following and referring to Attachment 2 for additional guidance:

• Power range meters N41A, N42A, N43A, or N44A

• SE NR-45 Recorder after a Rx trip

• REU1150, 1 MIN AVG NIS POWER

• REU1117, RX THERMAL POWER

• REU0485M, 1 MIN AVG OF RCL AVG DT 6.4.2. OBTAIN the total power defect as follows:

a. IF power level was less than 0% the last time Keff was equal to one, RECORD zero for the total power defect. b. RECORD the total power defect for the power level recorded in Step 6.4.1 using one of the following:

• WinPCNDR

• PCNDR, Section 5 -END OF SECTION-OSP-SF-00005 Rev. 019 Page 9 of 22 CONTINUOUS USE 6.5. Fission Products At Shutdown 6.5.1. OBTAIN the negative reactivity from xenon at shutdown as follows: a. IF at the beginning of a cycle AND power has not yet exceeded 5%, RECORD zero. b. IF power in the current cycle has exceeded 5%, RECORD xenon reactivity prior to the time of shutdown using one of the following and referring to Attachment 2 for additional guidance:

• REU1504, XE WORTH (PCM)

• XENON_PREDICTION

• XEPRED 6.5.2. OBTAIN the negative reactivity from samarium at shutdown as follows: a. IF at the beginning of a cycle AND power has not yet exceeded 5%, RECORD zero. b. IF power in the current cycle has exceeded 5%, RECORD samarium reactivity prior to the time of shutdown using one of the following and referring to Attachment 2 for additional guidance:

• REU1505, SM WORTH (PCM)

• XENON_PREDICTION

• XEPRED -END OF SECTION- 6.6. Total Reactivity At Time Of Shutdown NOTE This is the total negative reactivity due to rods, power defect, xenon, and samarium at the time of the last shutdown. 6.6.1. RECORD the algebraic sum the reactivities from Steps 6.2.2, 6.4.2, 6.5.1, and 6.5.2. -END OF SECTION-OSP-SF-00005 Rev. 019 Page 10 of 22 CONTINUOUS USE 6.7. Fission Products At Startup 6.7.1. OBTAIN the negative reactivity from xenon at startup using one of the following: a. IF at the beginning of a cycle AND power has not yet exceeded 5%, RECORD zero. b. IF power in the current cycle has exceeded 5%, RECORD xenon reactivity at time of startup using one of the following:

• XENON_PREDICTION

• XEPRED 6.7.2. OBTAIN the negative reactivity from samarium at startup using one of the following:

a. IF at the beginning of a cycle AND power has not yet exceeded 5%, RECORD zero. b. IF power in the current cycle has exceeded 5%, RECORD samarium reactivity at time of startup using one of the following:

• XENON_PREDICTION

• XEPRED -END OF SECTION- 6.8. Temperature At Startup NOTE The lowest loop RCS Tavg shall be greater than 551°F. [Ref: 8.1.4] 6.8.1. RECORD the anticipated average RCS Tavg at startup. 6.8.2. RECORD the temperature difference between the anticipated temperature at startup and the no-load programmed average temperature of 557 °F. 6.8.3. CALCULATE the isothermal temperature coefficient for the anticipated average temperature and boron concentration at startup using one of the following:

• WinPCNDR

• PCNDR, Section 5 OSP-SF-00005 Rev. 019 Page 11 of 22 CONTINUOUS USE 6.8.4. CALCULATE the reactivity associated with a temperature other than that of the no-load value by multiplying the temperature difference in Step 6.8.2 by the isothermal temperature coefficient Step 6.8.3. -END OF SECTION- 6.9. Desired Critical Rod Height CAUTION The Rod Insertion Limits of Curve Book Figure 13-1 and the Rod Withdrawal Limits of Curve Book Figure 2-13 shall be observed at all times. 6.9.1. IF it is desired to specify critical boron concentration and calculate rod height, PERFORM Section 6.10 and MARK Section 6.9 N/A. 6.9.2. DETERMINE Integral Rod Worth with D Control Bank at 170 steps using one of the following: [Ref: 8.2.7]

• WinPCNDR

• PCNDR, Section 5 6.9.3. ADD 200 pcm or more of negative reactivity to IRW at 170 steps to determine the IRW for a desired rod height at least 200 pcm below Control Bank D at 170 steps. 6.9.4. Using one of the following, DETERMINE the desired critical rod height for the IRW determined in step 6.9.3: [Ref: 8.2.7, 8.2.8]

• WinPCNDR

• PCNDR, Section 5 -END OF SECTION-OSP-SF-00005 Rev. 019 Page 12 of 22 CONTINUOUS USE 6.10. Desired Critical Boron Concentration NOTE After RCS boron adjustments and sampling are complete, it may be necessary to recalculate the ECP by entering the actual RCS boron concentration in Step 6.10.2. 6.10.1. IF it is desired to specify rod height and calculate critical boron concentration, PERFORM Section 6.9 and MARK Section 6.10 N/A. 6.10.2. RECORD the desired boron concentration for the startup. 6.10.3. CALCULATE the change in boron concentration by subtracting the last critical boron concentration in Step 6.3.1 from the desired boron concentration in Step 6.10.2. 6.10.4. RECORD the differential boron worth using one of the following:

• WinPCNDR

• PCNCR, Section 6 6.10.5. CALCULATE the change in reactivity due to boron by multiplying the change in boron concentration in Step 6.10.3 by the differential boron worth in Step 6.10.4. -END OF SECTION- 6.11. Total Reactivity NOTE The correction factor accounts for a bias observed in other startups. 6.11.1. RECORD the ECP Correction Factor from the Curve Book: Table 1-8.

OSP-SF-00005 Rev. 019 Page 13 of 22 CONTINUOUS USE 6.11.2. ALGEBRAICALLY SUM the reactivities for the following to obtain the reactivity that will be present in the core at startup relative to the last time Keff was equal to one:

• Xenon from Step 6.7.1

• Samarium from Step 6.7.2

• Temperature from Step 6.8.4

• ECP correction factor from Step 6.11.1

• One of the following:

• Rods from Step 6.9.3

• Boron from Step 6.10.5 6.11.3. ALGEBRAICALLY SUBTRACT Step 6.11.2 from Step 6.6.1 on the ECP calculation. -END OF SECTION- 6.12. Critical Boron Concentration 6.12.1. IF rod height is being calculated, MARK Section 6.12 N/A and PERFORM Section 6.13. 6.12.2. RECORD the differential boron worth for the estimated boron concentration at the predicted temperature at startup using one of the following:

• WinPCNDR

• PCNDR, Section 6 6.12.3. CALCULATE the required boron change by dividing the reactivity difference in Step 6.11.3 by the differential boron worth in Step 6.12.2.

6.12.4. CALCULATE the required boron concentration for startup by algebraically adding the required boron concentration change in Step 6.12.3 to the last critical boron concentration in Section 6.3. -END OF SECTION-OSP-SF-00005 Rev. 019 Page 14 of 22 CONTINUOUS USE 6.13. Critical Rod Height 6.13.1. IF critical boron concentration is being calculated, MARK Section 6.13 N/A and PERFORM Section 6.12. CAUTION The Rod Insertion Limits of Curve Book Figure 13-1 and the Rod Limits of Curve Book Figure 2-13 shall be observed at all times. 6.13.2. Using the reactivity difference in Step 6.11.3, DETERMINE the rod height from one of the following:

• WinPCNDR

• PCNDR, Section 5 -END OF SECTION-OSP-SF-00005 Rev. 019 Page 15 of 22 CONTINUOUS USE 6.14. Rod Limits 6.14.1. RECORD the remaining control bank reactivity worth from Step 6.9.3 IF calculating critical boron worth or 6.11.3 IF calculating critical rod height. NOTE If the calculated Minimum Rod Height is lower than the RIL, the RIL will be used as the Minimum Rod Height. [Ref: 8.2.7]

6.14.2. DETERMINE Minimum Rod Height for ECP as follows:

a. Subtract 500 pcm from the value in Step 6.14.1. b. Using one of the following, DETERMINE the rod position of the IRW calculated in Step 6.14.2.a:

• WinPCNDR

• PCNDR, Section 5 c. IF the position calculated in Step 6.14.2.b is higher than the RIL, ENTER the position. NOTE Establishing the minimum rod height as the RIL satisfies the Acceptance Criteria of Section 3.0. d. IF the position calculated in Step 6.14.2.b is lower than the RIL, ENTER the RIL.

OSP-SF-00005 Rev. 019 Page 16 of 22 CONTINUOUS USE NOTE If the maximum position reactivity is zero or positive, or the calculated Maximum Rod Height is higher than Control Bank D at 170 steps, Control Bank D at 170 steps will be used as the Maximum Rod Height. If the calculated Maximum Rod Height is higher than the control rod withdrawal limit at 0% power from Curve Book Figure 2-13, the withdrawal limit will be used as the Maximum Rod Height.

6.14.3. DETERMINE Maximum Rod Height for ECP as follows:

a. ADD 500 pcm to the value in Step 6.14.1. b. IF the result of Step 6.14.3.a is zero or positive, ENTER 170 steps on Bank D. c. IF the result of Step 6.14.3.a is negative, PERFORM the following: 1. Using one of the following, DETERMINE the rod position for the IRW calculated in Step 6.14.3.a:

• WinPCNDR

• PCNDR, Section 5 2. ENTER the lower of the two following positions: [Ref: 8.2.7]

• Position calculated in Step 6.14.3.c.1

• 170 steps on Control Bank D 6.14.4. IF the position determined in Step 6.14.3 is higher than the control rod withdrawal limit at 0% power from Curve Book Figure 2-13, ENTER the withdrawal limit from Figure 2-13 as the Max Rod Height instead of the position determined in Step 6.14.3. -END OF SECTION-

OSP-SF-00005 Rev. 019 Page 17 of 22 CONTINUOUS USE 7.0 RESTORATION None

8.0 REFERENCES

8.1. Implementing 8.1.1. ODP-ZZ-00016, Reactor Operator Watchstation Practices And Logs 8.1.2. T/S LCO 3.1.6 8.1.3. T/S SR 3.1.6.1 8.1.4. T/S LCO 3.4.2 8.2. Developmental 8.2.1. Curve Book: Table 1-8, Figure 2-13, Figure 13-1 8.2.2. ETP-ZZ-00015, Preparation, Review, Approval and Control of the Curve Book 8.2.3. ETP-ZZ-00012, Inverse Count Rate Ratio 8.2.4. Nuclear Design Report 8.2.5. CAR 200303622 8.2.6. CAR 200303929 8.2.7. CAR 200207983 8.2.8. CAR 200509793 9.0 RECORDS Records generated by this procedure are filed with the appropriate work authorizing document. 9.1. Attachment 1, Estimated Critical Position Calculation OSP-SF-00005 Rev. 019 Page 18 of 22 CONTINUOUS USE 10.0 SUMMARY OF CHANGES Page(s) Section or Step Number Description 4, 6, 7, 8, 9 4.6, 6.1.1, 6.2.1.b, 6.3.1.b, 6.4.1.b, 6.5.1.b, 6.5.2.b Added steps to explain Attachment 2 usage. Per CARS 201200291 and 201204504 17 8.1.1 Added Reference 22 Attachment 2 Added attachment. Per CARS 201200291 and 201204504

OSP-SF-00005 Rev. 019 Page 19 of 22 CONTINUOUS USE Attachment 1 Estimated Critical Position Calculation Sheet 1 of 3 Person Completing Initials/PIN Date & Time

__________________________ _____________ _______________

__________________________ _____________ _______________

STEP 6.1.1 Shutdown Date _______ Time _______

6.1.2 Startup Date _______ Time _______

6.1.3 Burnup EFPD _______ NOTE Recalculate the ECP if the reactor has been shutdown less than 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />, and the estimated time of criticality will differ from the actual time of criticality by greater than one hour. 6.2 Pre-Shutdown Reactivity From Rods 6.2.1 Controlling Bank _______

6.2.1 Step Counter _______

6.2.2 Controlling Bank Rod Reactivity (-) ______pcm 6.3 Critical Boron Concentrations 6.3.1 Critical Boron Concentration ______ppm 6.3.2 ______PCNDR Section 7

______Boron sample 6.4 Power Defect 6.4.1 Power level before shutdown _______%

6.4.2 Total Power Defect (-) ______pcm 6.5 Fission Products At Shutdown 6.5.1 Xenon reactivity (-) ______pcm 6.5.2 Samarium reactivity (-) ______pcm 6.6 Total Reactivity At Time Of Shutdown __________________ 6.6.1 Algebraic sum of Steps: 6.2.2, 6.4.2, 6.5.1, and 6.5.2 (-) ______pcm OSP-SF-00005 Rev. 019 Page 20 of 22 CONTINUOUS USE Attachment 1 (Cont'd.) Sheet 2 of 3 6.7 Fission Products At Startup 6.7.1 Xenon reactivity (-) ______pcm 6.7.2 Samarium reactivity (-) ______pcm 6.8 Temperature At Startup 6.8.1 Anticipated RCS avg temp at startup ______°F 6.8.2 Temp difference from 557°F ( ) ______°F 6.8.3 Isothermal Temp Coefficient ( ) ______pcm/°F 6.8.4 Temperature reactivity (Step 6.8.2 X 6.8.3) ( ) ______pcm 6.9 Desired Critical Rod Height 6.9.2 IRW with bank D at 170 steps (-) ______pcm 6.9.3 Step 6.9.2 + (-)200 pcm or more (IRW at desired Rod height) (-) ______pcm 6.9.4 Critical rod height ______steps 6.10 Desired Critical Boron Concentration 6.10.2 Desired startup boron concentration ______ppm 6.10.3 Boron change from last critical (Step 6.10.2 - 6.3.1) ( ) ______ppm 6.10.4 Differential Boron Worth (-) ______pcm/ppm 6.10.5 Reactivity change due to boron (Step 6.10.3 X 6.10.4) ( ) ______pcm 6.11 Total Reactivity 6.11.1 ECP correction factor from Table 1-8 ( ) ______pcm

__________________ 6.11.2 Reactivity at startup (6.7.1 + 6.7.2 + 6.8.4 + 6.11.1

+ 6.9.3 or 6.10.5) ( ) ______pcm 6.11.3 Reactivity difference (6.6.1 - 6.11.2) ( ) ______pcm 6.12 Critical Boron Concentration 6.12.2 Differential boron worth (-) ______pcm/ppm 6.12.3 Boron change (6.11.3 / 6.12.2) ( ) ______ppm 6.12.4 Required critical boron concentration (6.12.3 + 6.3.1) ______ppm OSP-SF-00005 Rev. 019 Page 21 of 22 CONTINUOUS USE Attachment 1 (Cont'd.) Sheet 3 of 3 6.13 Critical Rod Height 6.13.2 Control bank _______ at _______ Steps Minimum Rod Height 6.14.1 Remaining control bank reactivity from 6.9.3 or 6.11.3 ( ) ______pcm - 500 pcm 6.14.2.a Step 6.14.1 - 500 pcm ( ) ______pcm 6.14.2.c/d Minimum Rod Height Control Bank _______ at _______ Steps Maximum Rod Height 6.14.3 Remaining control bank reactivity from 6.9.3 or 6.11.3 ( ) ______pcm + 500 pcm 6.14.3.a Step 6.14.1 + 500 pcm ( ) ______pcm 6.14.3.b/6.14.3.c.2/6.14.4 Maximum Rod Height Control bank _______ at _______ Steps

Remarks: ______________________________________________________________________________________

______________________________________________________________________________________________

______________________________________________________________________________________________

______________________________________________________________________________________________

______________________________________________________________________________________________

___________________________ ___________________________ ___________________________

Performed by IV Performed By Approved By (Reactor Engineer) (Reactor Engineer) (Senior Reactor Operator)

OSP-SF-00005 Rev. 019 Page 22 of 22 CONTINUOUS USE Attachment 2 Input Guidelines For Estimated Critical Position Calculation Sheet 1 of 1 DATA POINT TYPE OF REACTOR SHUTDOWN Controlled Shutdown Reactor Trip/Rapid Shutdown Time of Shutdown Time when 10-8 data was taken. Note 1 Time of trip or commencement of shutdown. Critical Boron Conc.

Critical Rod Height Controlling Bank From 10-8 data. Note 1 From most recent RO turnover entry or midnight entry, whichever is most recent. Power Level Prior to Shutdown Use 0%. Note 1 Enter power at time of trip or commencement of shutdown. Xenon Iodine Samarium Promethium Use poison concentrations at "Time of Shutdown" from XEPRED run or from curve book. Will need to account for power descension causing xenon and samarium buildup. Use poison concentrations from midnight ODP-ZZ-00016 Control Room Computer Log printout if power was constant from midnight until trip. Otherwise do XEPRED run.

Note 1: If available, reference reactivity data should be taken from equilibrium conditions prior to 10-8 data. In this case, input data will be from the equilibrium conditions.

CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE JPM No: RSA-2 KSA No: GEN 2.1.25 Revision:

July 2013 KSA Rating:

4.2 Job Title:

SRO Task Title:

Determine the volume and RMCS control settings for raising RWST level Validation Time: 16 minutes Learning Objective: T61.0110.6, LP 11, Obj P

, IDENTIFY the BTRS MCB controls, alarms and indications and DESCRIBE how each is used to predict, monitor or control changes in the BTRS System.

The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY

[ ] UNSATISFACTORY

Reason, if UNSATISFACTORY:

Evaluators Signature:

Date:

Task Performer:

Location of Performance:

Control Room Simulator/Lab Plant Classroom X

Method of Performance:

Simulated Performed X

Alternate Path:

__ ____ Time Critical:

___ ___

Student Handouts: OTN-BG-0002 RWST Level/Volume Curve Tank Book Curve Book Straight Edge Calculator

References:

OTN-BG-00002, "Reactor Makeup Control and Boron Thermal Regeneration System"

JPM NO: RSA-2, Rev 1 PAGE 1 of 3 Initial Conditions:

The unit is coming out of a refueling outage.

A significant leak occurred during the refuel pool draindown process.

RWST level is 92%.

RWST Boron Concentration is 2375 PPM.

BAST concentration is 7000 ppm

Initiating Cues:

You have been directed to determine the volume addition required to establish the RWST level to 98% and the Reactor Makeup Control System settings to maintain RWST boron concentration at it's current value with a makeup flow rate of 90 GPM

Task Standard:

Upon completion of this JPM, the Applicant will have determined the Volume addition and controls settings within the specified range.

START TIME:

STOP TIME:

JPM NO: RSA-2, Rev 1 JPM TASK STEP ELEMENT PERFORMANCE STANDARD SCORE PAGE 2 of 3 1. Obtain a verified working copy of OTN-BG-00002 and determines that Section 5.5

- MANUAL MODE OF RMCS OPERATION applies.

Applicant obtained working copy of OTN-BG-00002

S U Comments:

2. *Determine the volume to be added. Refers to RWST Level/Volume S U Comments:

3. *Determines RMCS settings based upon required blended flow rates Refers to Figure 7

-2 and determines:

-FK-111 potentiometer setting 5.63

+/-.1 -FK-110 potentiometer setting 7.63

+/-.1 S U Comments:

4. The JPM is complete Record stop time on Page 1 S U Comments:

Denotes Critical Step

Initial Conditions

The unit is coming out of a refueling outage. A significant leak occurred during the refuel pool draindown process.

RWST level is 92%.

RWST Boron Concentration is 2375 PPM.

BAST concentration is 7000 ppm

Initiating Cues

You have been directed to determine the volume addition required to establish the RWST level to 98% and the Reactor Makeup Control System settings to maintain RWST boron concentration at it's current value with a makeup flow rate of 90 GPM

Provide to Examiner when complete:

Volume to be added

___________

Reactor Makeup Control System settings: ___________________________

Page 1 of 71 CONTINUOUS USE

OTN-BG-00002 REACTOR MAKEUP CONTROL AND BORON THERMAL REGENERATION SYSTEM MINOR Revision 041

OTN-BG-00002 Rev. 041 REACTOR MAKEUP CONTROL AND BORON THERMAL REGENERATION SYSTEM TABLE OF CONTENTS Section Page Number Page 2 of 71 CONTINUOUS USE 1.0 PURPOSE ...................................................................................................................................... 4 2.0 SCOPE ........................................................................................................................................... 4 3.0 PRECAUTIONS AND LIMITATIONS ....................................................................................... 4 3.1. Precautions .......................................................................................................................... 4 3.2. Limitations........................................................................................................................... 5 3.3. General Notes ...................................................................................................................... 5 4.0 PREREQUISITES ......................................................................................................................... 7 5.0 PROCEDURE INSTRUCTIONS ................................................................................................. 8 5.1. Automatic Mode Of RMCS Operation ................................................................................. 8 5.2. Dilute Mode Of RMCS Operation ........................................................................................ 9 5.3. Alternate Dilute Mode Of RMCS Operation ...................................................................... 11 5.4. Borate Mode Of RMCS Operation ..................................................................................... 13 5.5. Manual Mode Of RMCS Operation To CCP Suction (VCT) .............................................. 15 5.6. Manual Mode Of RMCS Operation (RWST-RHUT-BTRS) ............................................... 17 5.7. BTRS Operation - Boration ................................................................................................ 20 5.8. BTRS Operation - Dilution ................................................................................................ 24 5.9. BTRS Operation - Borate To Dilute Mode Change ............................................................ 28 5.10. BTRS Operation - Dilute To Borate Mode Change ............................................................ 31 5.11. Flushing BTRS Demineralizers Using RCS Letdown Flow ................................................ 34 5.12. Flushing BTRS Demineralizers Using Reactor Makeup Water ........................................... 36 5.13. Pressure Testing BTRS With Reactor Makeup Water ......................................................... 41 5.14. Immediate Boration To Support Plant Shutdown ................................................................ 44 5.15. Restoration Of The SW Side Of CVCS Chiller Unit From Dry Layup Condition ............... 46 5.16. Placing The SW Side Of CVCS Chiller Unit In Dry Layup Condition ................................ 48 5.17. Restoration Of Chilled Water Side Of CVCS Chiller Unit From Dry Layup Condition ...... 50 5.18. Placing The Chilled Water Side Of CVCS Chiller Unit In Dry Layup Condition ................ 53 5.19. Removing BTRS From Service For Maintenance ............................................................... 55 5.20. Filling And Venting BTRS Following Maintenance Using Letdown Or Rx M/U Water ..... 56

6.0 REFERENCES

............................................................................................................................ 61 6.1. Implementing ..................................................................................................................... 61 6.2. Developmental ................................................................................................................... 61 OTN-BG-00002 Rev. 041 REACTOR MAKEUP CONTROL AND BORON THERMAL REGENERATION SYSTEM TABLE OF CONTENTS Section Page Number Page 3 of 71 CONTINUOUS USE 7.0 RECORDS ................................................................................................................................... 62 7.1. QA Records ....................................................................................................................... 62 7.2. Commercial Records .......................................................................................................... 62 8.0 SUMMARY OF CHANGES ....................................................................................................... 63 ATTACHMENT 1, BTRS Performance Data/Status Log......................................................................... 64 ATTACHMENT 2, RCS Letdown Flow - BTRS Demineralizer Flushing Data ....................................... 65 ATTACHMENT 3, Reactor Makeup Water - BTRS Demineralizer Flushing Data .................................. 66 ATTACHMENT 4, Volume Control Tank Level Control System ............................................................ 67 ATTACHMENT 5, BTRS Controls For BG HIS-27 Indication ............................................................... 68 ATTACHMENT 6, Dilute Mode Of RMCS Operation ............................................................................ 69 ATTACHMENT 7, Alternate Dilute Mode Of RMCS Operation ............................................................. 70 ATTACHMENT 8, Borate Mode Of RMCS Operation ........................................................................... 71 Checklist 1, Removing the Chiller Unit Service Water Headers from Dry Lay-up Checklist 2, Placing the Chiller Unit Service Water Headers in Dry Lay-up Checklist 3, Locked Valve Restoration Checklist 4, Restoration From Dry Layup Of BTRS Chiller Chill Water Side OTN-BG-00002 Rev. 041 Page 4 of 71 CONTINUOUS USE REACTOR MAKEUP CONTROL AND BORON THERMAL REGENERATION SYSTEM 1.0 PURPOSE To provide instructions for the operation of the Reactor Makeup Control System (RMCS) and the Boron Thermal Regeneration System (BTRS). 2.0 SCOPE This procedure addresses all modes of RCS boration and dilution and also includes:

• Flushing BTRS Demineralizers

• Pressure testing BTRS Demineralizers

• Immediate Boration

• Establishing & Securing From Dry Layup in the CVCS Chiller Unit

• Removing BTRS from Service for Maintenance

• Restoring BTRS to Service 3.0 PRECAUTIONS AND LIMITATIONS 3.1. Precautions 3.1.1. The boric acid storage tank level should not be reduced below the minimum required by FSAR 16.1.2.6, if in MODES 1 through 4 or FSAR 16.1.2.5, if in MODES 5 and 6. Plant MODE Contained Volume (gal) % Level in One Tank 1, 2, 3, or 4 17,658 70 5 or 6 2,968 10 3.1.2. Whenever a difference of 50 ppm exists, the pressurizer spray should be operated by placing the backup heaters on to equalize the boron concentration in the RCS and pressurizer. 3.1.3. Prior to make up being added to the refueling canal, RCS or Spent Fuel Pool, with all four RCPs secured, recirculation flow should be checked through the RCS (RHR flow greater than or equal to 1000 gpm) or the concentration of the make up should be greater than or equal to 2000 ppm. 3.1.4. At all times when boration/dilution via BTRS is initiated or in progress, the Reactor Coolant Filter must be in service with BGV8421, CVCS RX CLNT FLTR BYP ISO, CLOSED, to prevent possible resin leakage from entering the RCS.

OTN-BG-00002 Rev. 041 Page 5 of 71 CONTINUOUS USE 3.1.5. When placing a BTRS bed into service after an extended period of time or when the bed boron concentration is suspect, letdown flow should be diverted to the RHUT until the desired trend in boron concentration is observed by the Boron Concentration Monitoring System, (BCMS), or chemistry sample. 3.1.6. The recirculation return line to the RWST is non-seismic. To ensure the RWST remains OPERABLE in MODES 1 through 4, no other systems, with the exception of the SI pumps in standby, are aligned to the RWST return header when performing Section 5.6 aligned to the RWST. [Ref: 6.2.13] 3.1.7. Prior to establishing M/U flow for flushing a BTRS Demineralizer bed, BG FY-111B, COMBINED M/U & BA COUNTER, must be reset and the counter set to the maximum amount of water that Radwaste can receive. It is important to stop letdown flow through the letdown reheat heat exchanger prior to stopping M/U flow. This will allow cooling of the letdown reheat heat exchanger. 3.1.8. During Reactor Makeup Control System operation, it is permissible to place one of the Boric Acid Transfer Pumps in Pull To Lock. This will allow for maintenance of level in one of the Boric Acid Storage Tanks to prevent Annunciator 37B, BA TKS LEV LO. 3.1.9. When setting BG FY-111B, COMBINED M/U & BA COUNTER, and BG FY-110B, BA COUNTER, allowances should be made in the setpoint to compensate for instrument inaccuracies and isolation valve closure times on total flow delivered. For instance, the accuracy of both the boric acid integrator BG FY-110B and the total makeup flow integrator BG FY-111B is +/- one count. This equates to +/- 0.1 gal for BG FY-110B and +/- 1.0 gal for BG FY-111B. Differences in setpoint and total flow delivered are also dependent on the amount of time it takes for valves to close and isolate flow once the integrator setpoint has been reached. 3.2. Limitations Under normal conditions, the RMCS should operate in the AUTOMATIC mode. When used in modes other than AUTOMATIC, the system should be returned to AUTOMATIC upon completion of the evolution. 3.3. General Notes 3.3.1. BG HC-387, BTRS DEMIN BYPASS CTRL, should be adjusted to maintain a constant flow through the BTRS Demineralizer beds. This will allow more accurate results to be obtained for operator aid development. 3.3.2. Demineralizer flushing may be stopped or interrupted as required by plant conditions. However, to minimize the frequency of flushing operations, the Demineralizer should be flushed for the duration determined by the BG System Engineer.

OTN-BG-00002 Rev. 041 Page 6 of 71 CONTINUOUS USE 3.3.3. A new BTRS Demineralizer bed should be flushed in accordance with OTN-BG-00001 ADD05, Operation of the BTRS Demineralizer System, prior to placing the bed into service for the first time. 3.3.4. The BTRS Chiller Unit and Pumps are normally NOT in service. a. The Service Water Inlet and Outlet Headers are in a dry lay-up condition until the Chiller Unit is required for service. This requires a fill and vent of service water headers prior to the Chiller Unit being placed in service. A dry lay-up condition requires the inlet and outlet service water isolation valves to be LOCKED CLOSED with various vents and drains OPENED. b. The Chill Water side of the BTRS Chiller is also placed in dry lay-up condition until the Chiller Unit is required for service. Power is removed from the pumps and chiller unit. Some drains and vents are left OPEN with FME screens installed. 3.3.5. During Startup testing of the BTRS system, the following noted items were documented:

a. Operation of BTRS in the Borate mode following an extended period of time in the Dilute mode can initially produce BTRS effluent of approximately 200 ppm greater than the RCS boron concentration. b. If the Demineralizers are saturated when boration begins, or if the Demineralizers have been recently flushed before starting a dilution, the maximum anticipated change in RCS boron concentration via BTRS is approximately 100 ppm. Under either condition, the maximum change will require 8-10 hours for the Demineralizers to become saturated. c. Demineralizer inlet temperature as indicated on BG TI-381, LTDN RH HX TUBE SIDE OUTLET TEMP CTRL TEMP IND, should go to between 40°F to 60°F within approximately 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after BTRS has been placed in the Dilute mode, when BTRS is originally at ambient conditions (80°F). This is due to the time required to cool down the associated heat exchangers and piping. d. Demineralizer inlet temperature, as indicated on BG TI-381, should go to between 135°F and 145°F within approximately 15 minutes after BTRS has been placed in the Borate mode, when BTRS is originally at ambient conditions (80°F). e. When BTRS is in the Borate mode for more than 30 minutes at a time, Demineralizer inlet temperature, as indicated on BG TI-381, may begin to oscillate +8 to -10°F from the setpoint value.

OTN-BG-00002 Rev. 041 Page 7 of 71 CONTINUOUS USE Step 3.3.5 Cont'd f. During Borate mode of operation, to prevent the Demineralizer inlet temperature from reaching the BTRS TEMP HI DIVERT alarm setpoint of 156°F or the BTRS TEMP HI alarm setpoint of 150°F, it may be necessary to lower the setpoint on BG TK-381A, LTDN DIVERT FLOW CTRL, to prevent the oscillations. 3.3.6. Attachment 4, Volume Control Tank Level Control System, provides information on the setpoints and controls of the VCT level. 3.3.7. Attachments 6 through 8 are provided to assist in normal shiftly dilutions/borations of the RCS. It is the intent that the cover page of this procedure and applicable Attachments 6, 7, or 8 be copied for the intended shiftly dilutions/borations discussed at the beginning of shift brief. Copies should be made of the quantity discussed for the incremental dilutions/borations during the shift. 4.0 PREREQUISITES 4.1. WHEN required, ENSURE the following:

• Reactor Makeup Water System is available to supply the RMCS.

• Sufficient boric acid of proper concentration is available to supply the RMCS.

• The Service Water System is available to supply the CVCS Chiller Unit during BTRS operation.

• The CVCS Chiller Surge Tank is within the normal operating range. 4.2. Prior to make up being added to the refueling canal, RCS or Spent Fuel Pool, with all four RCPs secured, MAKE a URO Log entry documenting that either recirculation flow through the RCS (RHR flow) is greater than or equal to 1000 gpm, or that the boron concentration of the make up is greater than or equal to 2000 ppm. 4.3. IF making up to the RWST per Section 5.6 in MODES 1 through 4, ENSURE no other systems, with the exception of the SI pumps in standby, are aligned to the RWST return header. -END OF SECTION-OTN-BG-00002 Rev. 041 Page 8 of 71 CONTINUOUS USE 5.0 PROCEDURE INSTRUCTIONS NOTE All control switches are on Panel RL001 or RL002 unless otherwise noted. BG FK-111, REACTOR M/U WTR FLOW CTRL, defaults to 120 gpm when the Reactor Mode Selector Switch is in AUTO. BGHCV0387, BTRS DEMINS BYP HV, is interlocked such that BGHCV0387 can NOT be taken out of the bypass position unless one of the BTRS Demineralizer Inlet valves is open. This section is sequenced such that this interlock is NOT challenged. 5.1. Automatic Mode Of RMCS Operation NOTE Automatic mode of RMCS controls VCT level between 30% and 50% 5.1.1. DETERMINE the desired boric acid flow rate for blended flow required using Curve Book, Figure 7-2, Reactor Makeup Control System Nomographs - Blended Flow for 120 gpm AUTO Makeup and Manual Reduced Flow Rates, or equivalent. 5.1.2. PLACE BG HS-26, RCS M/U CTRL, in STOP. 5.1.3. PLACE BG HS-25, RCS M/U CTRL SEL, in AUTO. 5.1.4. SET BG FK-110, BA FLOW CTRL, at the desired flow rate and PLACE the controller in AUTO. 5.1.5. PLACE BG FK-111, REACTOR M/U WTR FLOW CTRL, in AUTO. 5.1.6. PLACE BG HS-26, RCS M/U CTRL, in RUN. -END OF SECTION-OTN-BG-00002 Rev. 041 Page 9 of 71 CONTINUOUS USE 5.2. Dilute Mode Of RMCS Operation NOTE A "Nominal 120 gpm Dilution" should be performed per Attachment 6 instead of this section. 5.2.1. DETERMINE the desired dilution volume and flow rate using the following (as applicable):

• Curve Book, Figure 7-5, Reactor Makeup Control System Nomographs - Boron Dilution

• Curve Book, Figure 7-6, Reactor Makeup Control System Nomographs - Boron Dilution Rate

• Curve Book, Figure 7-8, Reactor Makeup Control System Nomographs - Boron Dilution and Boron Addition

• The shiftly Reactivity brief

• Using OpsReactivityCalc software 5.2.2. PLACE BG HS-26, RCS M/U CTRL, in STOP. 5.2.3. PLACE BG HS-25, RCS M/U CTRL SEL, in DIL. 5.2.4. SET BG FK-111, REACTOR M/U WTR FLOW CTRL, at the desired dilution flow rate and PLACE the controller in AUTO. NOTE When setting BG FY-111B, allowance should be made in the setpoint to compensate for instrument inaccuracies and isolation valve closure times on total flow delivered. (Step 3.1.9 contains more information, if required.) 5.2.5. SET BG FY-111B, COMBINED M/U & BA FLOW COUNTER, to deliver the desired amount of makeup water. 5.2.6. PLACE BG HS-26, RCS M/U CTRL, in RUN. 5.2.7. IF desired, using BG FK-111, ADJUST the flow rate as required by plant conditions. 5.2.8. IF desired to stop the dilution flow before BG FY-111B automatically stops it, PLACE BG HS-26, RCS M/U CTRL, in STOP.

OTN-BG-00002 Rev. 041 Page 10 of 71 CONTINUOUS USE 5.2.9. WHEN dilution is complete, RESTORE from the Dilute Mode as follows: a. PLACE BG HS-26, RCS M/U CTRL, in STOP. b. PLACE BG HS-25, RCS M/U CTRL SEL, in AUTO. c. ENSURE BG FK-110, BA FLOW CTRL, is set to the desired concentration for the current RCS boron concentration. d. PLACE BG HS-26, RCS M/U CTRL, in RUN. -END OF SECTION-OTN-BG-00002 Rev. 041 Page 11 of 71 CONTINUOUS USE 5.3. Alternate Dilute Mode Of RMCS Operation NOTE A "Nominal 120 gpm Alternate Dilution" should be performed per Attachment 7 instead of this section. 5.3.1. DETERMINE the desired dilution volume and flow rate using the following (as applicable):

• Curve Book, Figure 7-5, Reactor Makeup Control System Nomographs - Boron Dilution

• Curve Book, Figure 7-6, Reactor Makeup Control System Nomographs - Boron Dilution Rate

• Curve Book, Figure 7-8, Reactor Makeup Control System Nomographs - Boron Dilution and Boron Addition

• The shiftly Reactivity brief

• Using OpsReactivityCalc software 5.3.2. PLACE BG HS-26, RCS M/U CTRL, in STOP. 5.3.3. PLACE BG HS-25, RCS M/U CTRL SEL, in ALT DIL. 5.3.4. SET BG FK-111, REACTOR M/U WTR FLOW CTRL, at the desired dilution flow rate and PLACE the controller in AUTO. NOTE When setting BG FY-111B, allowance should be made in the setpoint to compensate for instrument inaccuracies and isolation valve closure times on total flow delivered. (Step 3.1.9 contains more information if required.) 5.3.5. SET BG FY-111B, COMBINED M/U & BA FLOW COUNTER, to deliver the desired amount of makeup water.

OTN-BG-00002 Rev. 041 Page 12 of 71 CONTINUOUS USE NOTE In the Alternate Dilute Mode, a portion of the dilution flow goes directly to the charging pump suction; therefore, the effects on reactivity will be seen sooner and occur more rapidly. 5.3.6. PLACE BG HS-26, RCS M/U CTRL, in RUN. 5.3.7. IF desired, using BG FK-111, ADJUST the flow rate as required by plant conditions. 5.3.8. IF desired to stop the dilution flow before BG FY-111B automatically stops it, PLACE BG HS-26, RCS M/U CTRL, in STOP. 5.3.9. WHEN dilution is complete, RESTORE from the Alternate Dilute Mode as follows:

a. PLACE BG HS-26, RCS M/U CTRL, in STOP. b. PLACE BG HS-25, RCS M/U CTRL SEL, in AUTO. c. ENSURE BG FK-110, BA FLOW CTRL, is set to the desired concentration for the current RCS boron concentration. d. PLACE BG HS-26, RCS M/U CTRL, in RUN. -END OF SECTION-OTN-BG-00002 Rev. 041 Page 13 of 71 CONTINUOUS USE 5.4. Borate Mode Of RMCS Operation NOTE A "Normal Frequently Performed Boration" should be performed per Attachment 8 instead of this section. 5.4.1. DETERMINE the desired dilution volume and flow rate using the following (as applicable):

• Curve Book, Figure 7-2, Reactor Makeup Control System Nomographs - Blended Flow for 120 gpm AUTO Makeup and Manual Reduced Flow Rates

• Curve Book, Figure 7-3, Reactor Makeup Control System Nomographs - Boron Addition

• Curve Book, Figure 7-4, Reactor Makeup Control System Nomographs - Boron Addition Rate

• Curve Book, Figure 7-6, Reactor Makeup Control System Nomographs - Boron Dilution Rate

• Curve Book, Figure 7-8, Reactor Makeup Control System Nomographs - Boron Dilution and Boron Addition

• The shiftly Reactivity brief

• Using OpsReactivityCalc software 5.4.2. PLACE BG HS-26, RCS M/U CTRL, in STOP. 5.4.3. PLACE BG HS-25, RCS M/U CTRL SEL, in BOR. 5.4.4. SET BG FK-110, BA FLOW CTRL, at the desired boron flow rate and PLACE the controller in AUTO. NOTE When setting BG FY-110B, allowance should be made in the setpoint to compensate for instrument inaccuracies and isolation valve closure times on total flow delivered. (Step 3.1.9 contains more information if required.) 5.4.5. SET BG FY-110B, BA FLOW COUNTER, to deliver the desired amount of boron. 5.4.6. PLACE BG HS-26, RCS M/U CTRL, in RUN.

OTN-BG-00002 Rev. 041 Page 14 of 71 CONTINUOUS USE 5.4.7. IF desired, using BG FK-110, ADJUST the flow rate as required by plant conditions. 5.4.8. IF desired to stop the boration flow before BG FY-110B automatically stops it, PLACE BG HS-26, RCS M/U CTRL, in STOP. 5.4.9. WHEN boration is complete, RESTORE from the Boration Mode as follows: a. PLACE BG HS-26, RCS M/U CTRL, in STOP. b. PLACE BG HS-25, RCS M/U CTRL SEL, in AUTO. c. ENSURE BG FK-110, BA FLOW CTRL, is set to the desired concentration for the current RCS boron concentration. d. PLACE BG HS-26, RCS M/U CTRL, in RUN. -END OF SECTION-OTN-BG-00002 Rev. 041 Page 15 of 71 CONTINUOUS USE 5.5. Manual Mode Of RMCS Operation To CCP Suction (VCT) 5.5.1. DETERMINE the desired boric acid and makeup water flow rates for blended flow using Curve Book, Figure 7-2, Reactor Makeup Control System Nomographs - Blended Flow for 120 gpm AUTO Makeup and Manual Reduced Flow Rates. 5.5.2. PLACE BG HS-26, RCS M/U CTRL, in STOP. 5.5.3. PLACE BG HS-25, RCS M/U CTRL SEL, in MAN. 5.5.4. SET BG FK-110, BA FLOW CTRL, at the desired boron flow rate and PLACE the controller in AUTO. 5.5.5. SET BG FK-111, REACTOR M/U WTR FLOW CTRL, at the desired flow rate and PLACE the controller in AUTO. NOTE When setting BG FY-111B, allowance should be made in the setpoint to compensate for instrument inaccuracies and isolation valve closure times on total flow delivered. (Step 3.1.9 contains more information if required.) 5.5.6. SET BG FY-111B, COMBINED M/U & BA COUNTER, to deliver the desired amount of makeup water. 5.5.7. SET BG FY-110B, BA COUNTER, sufficiently high to ensure boric acid flow continues throughout manual makeup. 5.5.8. PLACE BG HIS-111B, MAKEUP TO VCT INLET, in CLOSE. 5.5.9. OPEN BG HIS-110B, MAKEUP TO VCT OUTLET.

OTN-BG-00002 Rev. 041 Page 16 of 71 CONTINUOUS USE CAUTION BG FK-110, BA FLOW CTRL, is normally in AUTO in the Full Open position. During manual makeup to the VCT with low RCS boron concentrations, boric acid will inject at 40 gpm until BG FK-110 throttles back flow, resulting in adding more boron than required. 5.5.10. IF operating near end of cycle with low RCS boron concentration, PERFORM the following

a. PLACE BG FK-110, BA FLOW CTRL, in MANUAL b. REDUCE output to the approximate boric acid addition rate in gpm. (Late in the core cycle this may be close to zero demand.)

NOTE Steps 5.5.10.c and 5.5.11 should be performed concurrently. c. PLACE BG-FK-110, BA FLOW CTRL, in AUTO. 5.5.11. PLACE BG HS-26, RCS M/U CTRL, in RUN. 5.5.12. WHEN the makeup addition is complete, PLACE BG HS-26, RCS M/U CTRL, in STOP. 5.5.13. PLACE the following in AUTO:

• BG HIS-110B, MAKEUP TO VCT OUTLET

• BG HIS-111B, MAKEUP TO VCT INLET 5.5.14. RESTORE the RMCS to AUTO per Section 5.1. -END OF SECTION-OTN-BG-00002 Rev. 041 Page 17 of 71 CONTINUOUS USE 5.6. Manual Mode Of RMCS Operation (RWST-RHUT-BTRS) 5.6.1. ENSURE VCT level is sufficient for expected plant operating conditions for the duration of the makeup. 5.6.2. IF makeup is required to the Spent Fuel Pool, Refer To OTN-EC-00001, Fuel Pool Cooling And Cleanup System. 5.6.3. DETERMINE the desired boric acid and makeup water flow rates for blended flow using Curve Book, Figure 7-2, Reactor Makeup Control System Nomographs - Blended Flow for 120 gpm AUTO Makeup and Manual Reduced Flow Rates. 5.6.4. PLACE BG HS-26, RCS M/U CTRL, in STOP. 5.6.5. PLACE BG HS-25, RCS M/U CTRL SEL, in MAN. 5.6.6. SET BG FK-110, BA FLOW CTRL, at the desired boron flow rate and PLACE the controller in AUTO. 5.6.7. SET BG FK-111, REACTOR M/U WTR FLOW CTRL, at the desired flow rate and PLACE the controller in AUTO. NOTE When setting BG FY-111B, allowance should be made in the setpoint to compensate for instrument inaccuracies and isolation valve closure times on total flow delivered. (Step 3.1.9 contains more information if required.) 5.6.8. SET BG FY-111B, COMBINED M.U & BA COUNTER, to deliver the desired amount of makeup water. 5.6.9. SET BG-FY-110B, BA COUNTER, sufficiently high to ensure boric acid flow continues throughout manual makeup. 5.6.10. PLACE the following in CLOSE:

• BG HIS-110B, MAKEUP TO VCT OUTLET

• BG HIS-111B, MAKEUP TO VCT INLET

OTN-BG-00002 Rev. 041 Page 18 of 71 CONTINUOUS USE 5.6.11. OPEN the appropriate valve(s) below to align the Boric Acid Blender Outlet to the desired location: NOTE BGV0192, M/U TO BA BLENDING TEES HDR ISO, and BGV0034, RX M/U WTR TO BTRS ISO, should be entered in the Locked Component Deviation List if performance of this procedure is terminated or postponed prior to restoration of these valves to the LOCKED CLOSED position.

• Makeup to RWST

• BGV0192, M/U TO BA BLENDING TEES HDR ISO (AB-2000 Rm 1318)

• BGV0195, M/U TO RWST HDR ISO (AB-2000 Rm 1318)

• Makeup to RHUT

• BGV0192, M/U TO BA BLENDING TEES HDR ISO (AB-2000 Rm 1318)

• HEV0027, BA BLEND TEE TO RECYC EVAP FEED DEMIN IN (AB-2000 Rm1318)

• Makeup to BTRS

• BGV0192, M/U TO BA BLENDING TEES HDR ISO (AB-2000 Rm 1318)

• BGV0034, RX M/U WTR TO BTRS ISO (AB-1974 Rm 1105) 5.6.12. IF adding water to the RWST, NOTIFY Chemistry that sampling is required. 5.6.13. PLACE BG HS-26, RCS M/U CTRL, in RUN.

OTN-BG-00002 Rev. 041 Page 19 of 71 CONTINUOUS USE 5.6.14. WHEN the makeup addition is complete:

a. PLACE BG HS-26, RCS M/U CTRL, in STOP. b. RESTORE any components that were manipulated in Step 5.6.11 as follows:

• CLOSE and LOCK BGV0192, M/U TO BA BLENDING TEES HDR ISO.

• CLOSE BGV0195, M/U TO RWST HDR ISO.

• CLOSE HEV0027, BA BLEND TEE TO RECYC EVAP FEED DEMIN IN.

• CLOSE and LOCK BGV0034, RX M/U WTR TO BTRS ISO. c. RESTORE the RMCS to AUTO per Section 5.1. d. PLACE the following in AUTO:

• BG HIS-110B, MAKEUP TO VCT OUTLET

• BG HIS-111B, MAKEUP TO VCT INLET

e. PERFORM Checklist 3, Locked Valve Restoration. f. IF makeup was added to the RWST, PERFORM the following: NOTE RWST recirc time requirements are determined by Chemistry per CSP-ZZ-07620, Borated Water Sources (BAST-A, BAST-B and RWST). 1. IF makeup was added to the RWST, NOTIFY Chemistry to sample within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the recirc time being met. 2. PLACE the RWST in a recirculation lineup in accordance with OTN-EC-00001, Fuel Pool Cooling And Cleanup System. -END OF SECTION-OTN-BG-00002 Rev. 041 Page 20 of 71 CONTINUOUS USE 5.7. BTRS Operation - Boration 5.7.1. IF the BTRS bed to be placed into service is a new resin bed, ENSURE it has been flushed per OTS-BG-00006, Flushing BTRS Demineralizers. CAUTION Normal alignment for Chiller Unit is service water inlet and outlet headers and chill water side in dry lay-up condition with various vents and drains open. 5.7.2. IF the Chiller Unit is in dry lay-up condition, PERFORM the following:

• Section 5.15 (to fill and vent the Chiller Unit service water headers)

• Section 5.17 (to fill and vent the Chiller Unit chilled water side) 5.7.3. ENSURE Service Water is available to the Chiller unit. 5.7.4. Using the Plant Curve Book as needed, DETERMINE the required increase in boron concentration. NOTE It is preferred to use Step 5.7.6 for startup of BTRS, since it allows startup of the Chiller and establishes the desired Chilled Water Loop temperatures prior to aligning the BTRS valves and sending CVCS flow through the BTRS piping. 5.7.5. PLACE the BTRS in the Borate Lineup in accordance with either Step 5.7.6 or 5.7.7 below. 5.7.6. IF desired, STARTUP the Chilled Water Loop and PREPARE BTRS for operation in the Borate Mode by performing the following:

a. SET demand on BG HC-387, BTRS DEMIN BYPASS CTRL, at 100% (to ensure BG HCV-387 is fully open). b. ENSURE either of the following CVCS Chiller Pump control switches is in RUN, and the other pump control switch is in STOP:

• BG HIS-23, CVCS CHILLER PUMP A

• BG HIS-24, CVCS CHILLER PUMP B

c. WHEN BG FI-375, CVCS CHILLER SYS FLOW, has stabilized, PLACE BG HIS-21, CVCS CHILLER UNIT, in AUTO.

OTN-BG-00002 Rev. 041 Page 21 of 71 CONTINUOUS USE Step 5.7.6 Cont'd d. WHEN BG TI-379, CVCS CHILLER SURGE TANK TEMP is between 40°F and 50°F:

1. Refer To Night Orders or the current BTRS Performance Data/Status Log (Attachment 1) for guidance and DETERMINE which Demineralizer(s) to use for the Borate Mode. 2. OPEN the inlet valve for the selected BTRS Demineralizer(s) and CLOSE the inlet valves for the other Demineralizers:

• BG HIS-7010A, BTRS DEMIN A INLET VLV

• BG HIS-7010B, CATION DEMIN INLET VLV

• BG HIS-7010D, BTRS DEMIN D INLET VLV

• BG HIS-7010E, BTRS DEMIN E INLET VLV

e. PLACE BG TK-381A, LTDN DIVERT FLOW CTRL, in MANUAL and SET to zero. 5.7.7. IF Step 5.7.6 was NOT performed, PREPARE the BTRS for operation in the Borate Mode as follows:

a. ENSURE demand on BG HC-387, BTRS DEMIN BYPASS CTRL, is set at 100% (to ensure BG HCV-387 is fully open). b. ENSURE one of the following CVCS Chiller Pump control switches is in AUTO, and the other is in STOP:

• BG HIS-23, CVCS CHILLER PUMP A

• BG HIS-24, CVCS CHILLER PUMP B

c. ENSURE BG HIS-21, CVCS CHILLER UNIT, is in AUTO. d. Refer To Night Orders or the current BTRS Performance Data/Status Log (Attachment 1) for guidance and DETERMINE which Demineralizer(s) to use for the Borate Mode. e. OPEN the inlet valve for the selected BTRS Demineralizer(s) and CLOSE the inlet valves for the other Demineralizers:

• BG HIS-7010A, BTRS DEMIN A INLET VLV

• BG HIS-7010B, CATION DEMIN INLET VLV

• BG HIS-7010D, BTRS DEMIN D INLET VLV

• BG HIS-7010E, BTRS DEMIN E INLET VLV

f. PLACE BG TK-381A, LTDN DIVERT FLOW CTRL, in MANUAL and SET to zero.

OTN-BG-00002 Rev. 041 Page 22 of 71 CONTINUOUS USE 5.7.8. Using BG HIS-8245, CVCS DEMIN OUTLET VLV, ENSURE BGHV8245 is OPEN. 5.7.9. PLACE BG HIS-27, BTRS CTRL, in BORATE. NOTE Attachment 5, BG HIS-27 BTRS Controls, shows the input into the lights for the DILUTE, OFF and BORATE switch positions. [Ref: 6.2.9] 5.7.10. CHECK the white BORATE light on BG HIS-27 ON. 5.7.11. Using BG HIS-8245, CVCS DEMIN OUTLET VLV, CLOSE BGHV8245. 5.7.12. PLACE BG TK-381A, LTDN DIVERT FLOW CTRL, in AUTO, and ENSURE it is set below 7.0. 5.7.13. IF the boron concentration of the BTRS bed or piping is known (or suspected) to be different from the current RCS boron concentration:

a. PLACE BG HIS-112A, LTDN DIVERT TO VCT & RHR, in HUT. b. WHEN the desired trend in boron concentration is observed by BCMS or chemistry sample, PLACE BG HIS-112A, LTDN DIVERT TO VCT & RHR, in VCT. 5.7.14. WHEN BG TI-381, BTRS DEMIN INLET TEMP, stabilizes between 135°F and 145°F: a. WITHIN 5 minutes before the start of boration, RECORD the data required in Block 1 of Attachment 1. b. ADJUST BG HC-387, BTRS DEMIN BYPASS CTRL, to obtain the desired boration rate. c. RECORD the data required in Block 1A of Attachment 1. 5.7.15. WHEN the desired boron concentration has been established: a. RECORD the data required in Block 2 of Attachment 1 (required within 5 minutes before completion of the boration). b. SET demand on BG HC-387, BTRS DEMIN BYPASS CTRL, at 100% (to ensure BG HCV-387 is fully open). c. RECORD the data required in Block 2A of Attachment 1.

OTN-BG-00002 Rev. 041 Page 23 of 71 CONTINUOUS USE NOTE Attachment 1 should be retained at the Reactor Operator's desk until the data sheet is filled. When filled, the original copy should be forwarded to the BG System Engineer and a copy retained for reference for the next boration/dilution. The normal alignment of BTRS is with flow through BGHCV0387. 5.7.16. IF the BTRS mode is to be changed from Borate to Dilute, Go To Section 5.9. 5.7.17. IF normal alignment with flow through BGHCV0387 is desired, N/A Step 5.7.18. 5.7.18. WHEN no additional boration is desired, as determined by the SM/CRS: a. Using BG HIS-8245, CVCS DEMIN OUTLET VLV, OPEN BGHV8245. b. PLACE BG HIS-27, BTRS CTRL, in OFF. c. ADJUST the RMCS as required by plant conditions. d. IF desired to place the Chiller Unit in a Dry Lay-up condition, PERFORM the following:

• Section 5.16 (to drain the Chiller Unit service water headers)

• Section 5.18 (to drain the Chiller Unit chilled water side) -END OF SECTION-OTN-BG-00002 Rev. 041 Page 24 of 71 CONTINUOUS USE 5.8. BTRS Operation - Dilution 5.8.1. IF the BTRS bed to be placed into service is a new resin bed, ENSURE it has been flushed per OTS-BG-00006, Flushing BTRS Demineralizers. CAUTION Normal alignment for Chiller Unit is service water inlet and outlet headers and chill water side in dry lay-up condition with various vents and drains open. 5.8.2. IF the Chiller Unit is in dry lay-up condition, PERFORM the following:

• Section 5.15 (to fill and vent the Chiller Unit service water headers)

• Section 5.17 (to fill and vent the Chiller Unit chilled water side) 5.8.3. ENSURE Service Water is available to the Chiller Unit. 5.8.4. Using the Plant Curve Book as needed, DETERMINE the required increase in boron concentration. NOTE If the BTRS Demineralizers have been flushed or have had new resin installed, the initial RCS dilution rate will be more rapid than normally observed.

Step 5.8.6 is the preferred method to use for startup of BTRS, since it allows startup of the Chiller and establishes desired Chilled Water Loop temperatures prior to aligning the BTRS valves and sending CVCS flow through the BTRS piping. 5.8.5. PLACE the BTRS in the Dilute lineup in accordance with either Step 5.8.6 or 5.8.7 below. 5.8.6. IF desired, STARTUP the Chilled Water Loop and PREPARE the BTRS for operation in the Dilute Mode by performing the following:

a. SET demand on BG HC-387, BTRS DEMIN BYPASS CTRL, at 100% (to ensure BG HCV-387 is fully open). b. ENSURE either of the following CVCS Chiller Pump control switches is in RUN, and the other pump control switch is in STOP:

• BG HIS-23, CVCS CHILLER PUMP A

• BG HIS-24, CVCS CHILLER PUMP B

OTN-BG-00002 Rev. 041 Page 25 of 71 CONTINUOUS USE Step 5.8.6 Cont'd c. WHEN BG FI-375, CVCS CHILLER SYS FLOW, has stabilized, PLACE BG HIS-21, CVCS CHILLER UNIT, in RUN. d. WHEN BG TI-379, CVCS CHILLER SURGE TANK TEMP is between 40°F and 50°F:

1. Refer To Night Orders or the current BTRS Performance Data/Status Log (Attachment 1) for guidance and DETERMINE which Demineralizer(s) to use for the Borate Mode. 2. OPEN the inlet valve for the selected BTRS Demineralizer(s) and CLOSE the inlet valves for the other Demineralizers:

• BG HIS-7010A, BTRS DEMIN A INLET VLV

• BG HIS-7010B, CATION DEMIN INLET VLV

• BG HIS-7010D, BTRS DEMIN D INLET VLV

• BG HIS-7010E, BTRS DEMIN E INLET VLV 5.8.7. IF Step 5.8.6 was NOT performed, PREPARE the BTRS for operation in the Dilute Mode as follows:

a. SET demand on BG HC-387, BTRS DEMIN BYPASS CTRL, at 100% (to ensure BG HCV-387 is fully open). b. ENSURE ONE of the following CVCS Chiller Pump control switches is in AUTO, and the other pump control switch is in STOP:

• BG HIS-23, CVCS CHILLER PUMP A

• BG HIS-24, CVCS CHILLER PUMP B

c. ENSURE BG HIS-21, CVCS CHILLER UNIT, is in AUTO. d. Refer To Night Orders or the current BTRS Performance Data/Status Log (Attachment 1) for guidance and DETERMINE which Demineralizer(s) to use for the Dilute Mode. e. OPEN the inlet valve for the selected BTRS Demineralizer(s) and CLOSE the inlet valves for the other Demineralizers:

• BG HIS-7010A, BTRS DEMIN A INLET VLV

• BG HIS-7010B, CATION DEMIN INLET VLV

• BG HIS-7010D, BTRS DEMIN D INLET VLV

• BG HIS-7010E, BTRS DEMIN E INLET VLV 5.8.8. Using BG HIS-8245, CVCS DEMIN OUTLET VLV, ENSURE BGHV8245 is OPEN.

OTN-BG-00002 Rev. 041 Page 26 of 71 CONTINUOUS USE 5.8.9. PLACE BG HIS-27, BTRS CTRL, in DILUTE. NOTE Attachment 5, BG HIS-27 BTRS Controls, shows the input into the light for the DILUTE, OFF, and BORATE switch positions. [Ref: 6.2.9] 5.8.10. CHECK the white DILUTE light on BG HIS-27 ON. 5.8.11. Using BG HIS-8245, CVCS DEMIN OUTLET VLV, CLOSE BGHV8245. 5.8.12. IF the boron concentration of the BTRS bed or piping is known (or suspected) to be different from the current RCS boron concentration:

a. PLACE BG HIS-112A, LTDN DIVERT TO VCT & RHR, in HUT. b. WHEN the desired trend in boron concentration is observed by BCMS or chemistry sample, PLACE BG HIS-112A, LTDN DIVERT TO VCT & RHR, in VCT. 5.8.13. WHEN BG TI-381, BTRS DEMIN INLET TEMP, stabilizes between 40°F and 60°F: a. WITHIN 5 minutes before the start of dilution, RECORD the data required in Block 1 of Attachment 1. b. ADJUST BG HC-387, BTRS DEMIN BYPASS CTRL, to obtain the desired dilution rate. c. RECORD the data required in Block 1A of Attachment 1. 5.8.14. WHEN the desired boron concentration has been established: a. RECORD the data required in Block 2 of Attachment 1 (required within 5 minutes before completion of the dilution). b. SET demand on BG HC-387, BTRS DEMIN BYPASS CTRL, at 100% (to ensure BG HCV-387 is fully open). c. RECORD the data required in Block 2A of Attachment 1.

OTN-BG-00002 Rev. 041 Page 27 of 71 CONTINUOUS USE NOTE Attachment 1 should be retained at the Reactor Operator's desk until the data sheet is filled. When filled, the original copy should be forwarded to the BG System Engineer and a copy retained for reference for the next boration/dilution. The normal alignment of BTRS is with flow through BGHCV0387. 5.8.15. IF the BTRS Mode is to be changed from Dilute to Borate, Go To Section 5.10. 5.8.16. IF normal alignment with flow through BGHCV0387 is desired, N/A Step 5.7.18. 5.8.17. WHEN no additional dilution is desired, as determined by the SM/CRS: a. Using BG HIS-8245, CVCS DEMIN OUTLET VLV, OPEN BGHV8245. b. PLACE BG HIS-27, BTRS CTRL, in OFF. c. ADJUST the RMCS as required by plant conditions. d. IF desired to place the Chiller Unit in a Dry Lay-up condition, PERFORM the following:

• Section 5.16 (to drain the Chiller Unit service water headers)

• Section 5.18 (to drain the Chiller Unit chilled water side) -END OF SECTION-OTN-BG-00002 Rev. 041 Page 28 of 71 CONTINUOUS USE 5.9. BTRS Operation - Borate To Dilute Mode Change NOTE This section should be performed whenever BTRS is used for load follow operations due to Maintenance or ambient conditions. 5.9.1. ENSURE the BTRS is aligned per Section 5.7 5.9.2. IF the BTRS bed to be placed into service is a new resin bed, ENSURE it has been flushed per OTS-BG-00006, Flushing BTRS Demineralizers. 5.9.3. SET demand on BG HC-387, BTRS DEMIN BYPASS CTRL, at 100% (to ensure BG HCV-387 is fully open). 5.9.4. ENSURE either of the following CVCS Chiller Pump control switches is in RUN, and the other pump control switch is in STOP:

• BG HIS-23, CVCS CHILLER PUMP A

• BG HIS-24, CVCS CHILLER PUMP B 5.9.5. ENSURE BG HIS-21, CVCS CHILLER UNIT, is in RUN. 5.9.6. Using BG HIS-8245, CVCS DEMIN OUTLET VLV, ENSURE BGHV8245 is OPEN. 5.9.7. PLACE BG HIS-27, BTRS CTRL, in DILUTE. 5.9.8. CHECK the white DILUTE light on BG HIS-27 ON. NOTE Attachment 5, BG HIS-27 BTRS Controls, shows the input into the lights for the DILUTE, OFF and BORATE switch positions. [Ref: 6.2.9] 5.9.9. Using BG HIS-8245, CVCS DEMIN OUTLET VLV, CLOSE BGHV8245. 5.9.10. Refer To Night Orders or the current BTRS Performance Data/Status Log (Attachment 1) for guidance and DETERMINE which Demineralizer(s) to use for the Dilute Mode.

OTN-BG-00002 Rev. 041 Page 29 of 71 CONTINUOUS USE 5.9.11. OPEN the inlet valve for the selected BTRS Demineralizer(s) and CLOSE the inlet valves for the other Demineralizers:

• BG HIS-7010A, BTRS DEMIN A INLET VLV

• BG HIS-7010B, CATION DEMIN INLET VLV

• BG HIS-7010D, BTRS DEMIN D INLET VLV

• BG HIS-7010E, BTRS DEMIN E INLET VLV 5.9.12. WHEN BG TI-381, BTRS DEMIN INLET TEMP, stabilizes between 40°F and 60°F: a. WITHIN 5 minutes before beginning the dilution, RECORD the data required in Block 1 of Attachment 1. b. ADJUST BG HC-387, BTRS DEMIN BYPASS CTRL, to obtain the desired dilution rate. c. RECORD the data required in Block 1A of Attachment 1. 5.9.13. WHEN the desired boron concentration has been established: a. RECORD the data required in Block 2 of Attachment 1 (required within 5 minutes before completion of the dilution). b. SET demand on BG HC-387, BTRS DEMIN BYPASS CTRL, at 100% (to ensure BG HCV-387 is fully open). c. RECORD the data required in Block 2A of Attachment 1. NOTE Attachment 1 should be retained at the Reactor Operator's desk until the data sheet is filled. When filled, the original copy should be forwarded to the BG System Engineer and a copy retained for reference for the next boration/dilution. The normal alignment of BTRS is with flow through BGHCV0387. 5.9.14. IF normal alignment with flow through BGHCV0387 is desired, N/A Step 5.9.15.

OTN-BG-00002 Rev. 041 Page 30 of 71 CONTINUOUS USE 5.9.15. WHEN no additional boration is desired, as determined by the SM/CRS: a. Using BG HIS-8245, CVCS DEMIN OUTLET VLV, OPEN BGHV8245. b. PLACE BG HIS-27, BTRS CTRL, in OFF. c. ADJUST the RMCS as required by plant conditions. d. IF desired to place the Chiller Unit in a Dry Lay-up condition, PERFORM the following:

• Section 5.16 (to drain the Chiller Unit service water headers)

• Section 5.18 (to drain the Chiller Unit chilled water side) -END OF SECTION-OTN-BG-00002 Rev. 041 Page 31 of 71 CONTINUOUS USE 5.10. BTRS Operation - Dilute To Borate Mode Change NOTE This section should be performed whenever BTRS is used for load-follow operations due to Maintenance or ambient conditions. 5.10.1. ENSURE the BTRS is aligned per Section 5.8. 5.10.2. IF the BTRS bed to be placed into service is a new resin bed, ENSURE it has been flushed per OTS-BG-00006, Flushing BTRS Demineralizers. 5.10.3. SET demand on BG HC-387, BTRS DEMIN BYPASS CTRL, at 100% (to ensure BG HCV-387 is fully open). 5.10.4. ENSURE ONE of the following CVCS Chiller Pump control switches is in RUN, and the other pump control switch is in STOP:

• BG HIS-23, CVCS CHILLER PUMP A

• BG HIS-24, CVCS CHILLER PUMP B 5.10.5. ENSURE BG HIS-21, CVCS CHILLER UNIT, is in RUN. 5.10.6. Using BG HIS-8245, CVCS DEMIN OUTLET VLV, ENSURE BGHV8245 is OPEN. 5.10.7. PLACE BG TK-381A, LTDN DIVERT FLOW CTRL, in MANUAL and SET to zero. 5.10.8. PLACE BG HIS-27, BTRS CTRL, in BORATE. NOTE Attachment #5, BG HIS-27 BTRS Controls, shows the input into the light for the DILUTE, OFF and BORATE switch positions. [Ref: 6.2.9] 5.10.9. CHECK the white BORATE light on BG HIS-27 ON. 5.10.10. Using BG HIS-8245, CVCS DEMIN OUTLET VLV, CLOSE BGHV8245. 5.10.11. Refer To Night Orders or the current BTRS Performance Data/Status Log (Attachment 1) for guidance and DETERMINE which Demineralizer(s) to use for the Borate Mode.

OTN-BG-00002 Rev. 041 Page 32 of 71 CONTINUOUS USE 5.10.12. OPEN the inlet valve for the selected BTRS Demineralizer(s) and CLOSE the inlet valves for the other Demineralizers:

• BG HIS-7010A, BTRS DEMIN A INLET VLV

• BG HIS-7010B, CATION DEMIN INLET VLV

• BG HIS-7010D, BTRS DEMIN D INLET VLV

• BG HIS-7010E, BTRS DEMIN E INLET VLV 5.10.13. PLACE BG TK-381A, LTDN DIVERT FLOW CTRL, in AUTO, and ENSURE it is set below 7.0. 5.10.14. WHEN BG TI-381, BTRS DEMIN INLET TEMP, stabilizes between 135°F and 145°F: a. WITHIN 5 minutes before beginning a boration, RECORD the data required in Block 1 of Attachment 1. b. ADJUST BG HC-387, BTRS DEMIN BYPASS CTRL, to obtain the desired boration rate. c. RECORD the data required in Block 1A of Attachment 1. 5.10.15. WHEN the desired boron concentration has been established: a. RECORD the data required in Block 2 of Attachment 1 (required within 5 minutes before completion of the boration). b. SET demand on BG HC-387, BTRS DEMIN BYPASS CTRL, at 100% (to ensure BG HCV-387 is fully open). c. RECORD the data required in Block 2A of Attachment 1. NOTE Attachment 1 should be retained at the Reactor Operator's desk until the data sheet is filled. When filled, the original copy should be forwarded to the BG System Engineer and a copy retained for reference for the next boration/dilution. The normal alignment of BTRS is with flow through BGHCV0387. 5.10.16. IF normal alignment with flow through BGHCV0387 is desired, N/A Step 5.10.17.

OTN-BG-00002 Rev. 041 Page 33 of 71 CONTINUOUS USE 5.10.17. WHEN no additional boration is desired, as determined by the SM/CRS: a. Using BG HIS-8245, CVCS DEMIN OUTLET VLV, OPEN BGHV8245. b. PLACE BG HIS-27, BTRS CTRL, in OFF. c. ADJUST the RMCS as required by plant conditions. d. IF desired to place the Chiller Unit in a Dry Lay-up condition, PERFORM the following:

• Section 5.16 (to drain the Chiller Unit service water headers)

• Section 5.18 (to drain the Chiller Unit chilled water side) -END OF SECTION-OTN-BG-00002 Rev. 041 Page 34 of 71 CONTINUOUS USE 5.11. Flushing BTRS Demineralizers Using RCS Letdown Flow NOTE When it has been determined that the BTRS Demineralizers are saturated and continued dilution of the RCS is desired, the Demineralizer may be flushed to the Boron Recycle System. 5.11.1. CONTACT Chemistry to ensure that BTRS effluent samples will be taken on intervals of 30 to 60 minutes during Demineralizer flushing. 5.11.2. SET demand on BG HC-387, BTRS DEMIN BYPASS CTRL, at 100% (to ensure BG HCV-387 is fully open). CAUTION VCT level should be monitored closely during BTRS flushing. 5.11.3. Using BG HIS-8245, CVCS DEMIN OUTLET VLV, ENSURE BGHV8245 is OPEN. 5.11.4. PLACE BG HIS-27, BTRS CTRL, in BORATE. NOTE Attachment #5, BG HIS-27 BTRS Controls, shows the input into the light for the DILUTE, OFF and BORATE switch positions. [Ref: 6.2.9] 5.11.5. CHECK the white BORATE light on BG HIS-27 ON. NOTE It is desirable to flush one Demineralizer Bed at a time. The other Demineralizers should be isolated by closing their respective inlet Isolation valve. 5.11.6. Refer To Night Orders or the current BTRS Performance Data/Status Log (Attachment 1) for guidance and DETERMINE which Demineralizer(s) to use for the Borate Mode.

OTN-BG-00002 Rev. 041 Page 35 of 71 CONTINUOUS USE 5.11.7. OPEN the inlet valve for the selected BTRS Demineralizer(s) and CLOSE the inlet valves for the other Demineralizers:

• BG HIS-7010A, BTRS DEMIN A INLET VLV

• BG HIS-7010B, CATION DEMIN INLET VLV

• BG HIS-7010D, BTRS DEMIN D INLET VLV

• BG HIS-7010E, BTRS DEMIN E INLET VLV 5.11.8. Using BG HIS-8245, CVCS DEMIN OUTLET VLV, CLOSE BGHV8245. 5.11.9. WHEN BG TI-381, BTRS DEMIN INLET TEMP, stabilizes between 135°F and 145°F: a. SET BG HC-387, BTRS DEMIN BYPASS CTRL, at 0% (to close BGHCV387 and divert total letdown flow to the BTRS Demineralizers). b. PLACE BG HIS-112A, LTDN DIVERT TO VCT & RHR, in HUT. c. INFORM Chemistry that BTRS flushing has begun. d. RECORD the data required on Attachment 2, BTRS Flushing Data, now and at 30 to 60 minute intervals during the flush. e. WHEN the Demineralizers appear to be flushed as indicated by the data recorded on Attachment 2, (with reference to General Note 3.3.2), FORWARD the completed copy of Attachment #2 to the BG System Engineer. f. WHEN the Demineralizers have been rinsed, as indicated by the Boron Concentration Measurement System or effluent samples, PERFORM the following:

1. SET demand on BG HC-387, BTRS DEMIN BYPASS CTRL, at 100% (to fully open BGHCV0387). 2. Using BG HIS-8245, CVCS DEMIN OUTLET VLV, OPEN BGHV8245. 3. PLACE BG HIS-27, BTRS CTRL, in OFF. 4. ADJUST the RMCS as required by plant conditions. 5. PLACE BG HIS-112A, LTDN DIVERT TO VCT & RHR, in AUTO. -END OF SECTION-OTN-BG-00002 Rev. 041 Page 36 of 71 CONTINUOUS USE 5.12. Flushing BTRS Demineralizers Using Reactor Makeup Water NOTE When it has been determined that the BTRS Demineralizers are saturated, the BTRS System may be isolated to allow flushing boron from the Demineralizers to the Boron Recycle System. Since Reactor Makeup Water from the Boric Acid Blending Tee is being used to flush the Demineralizers, no boration via the BA Blending Tee should be performed during Steps 5.12.18 through 5.12.27. 5.12.1. INFORM Chemistry that BTRS effluent samples will be taken on intervals of 30 to 60 minutes during Demineralizer flushing. 5.12.2. ENSURE BG HIS-8245, CVCS DEMIN OUTLET VLV, is in OPEN. 5.12.3. ENSURE BG HIS-27, BTRS CTRL, is in OFF. 5.12.4. PLACE BG HS-26, RCS M/U CTRL, in STOP. 5.12.5. PLACE BG HS-25, RCS M/U CTRL SEL, in DIL. 5.12.6. PLACE the following in CLOSE:

• BG HIS-110A, BA TO BA BLENDING TEE

• BG HIS-110B, MAKEUP TO VCT OUTLET

• BG HIS-111B, MAKEUP TO VCT INLET 5.12.7. SET demand on BG HC-387, BTRS DEMIN BYPASS CTRL, at 100% (to ensure BG HCV-387 is fully open). 5.12.8. ENSURE the following are in STOP:

• BG HIS-23, CVCS CHILLER PUMP A

• BG HIS-24, CVCS CHILLER PUMP B

• BG HIS-21, CVCS CHILLER UNIT

OTN-BG-00002 Rev. 041 Page 37 of 71 CONTINUOUS USE 5.12.9. CLOSE the applicable valves for the Demineralizers which will NOT be flushed and OPEN the applicable valve for the Demineralizer to be flushed.

• BG HIS-7010A, BTRS DEMIN A INLET VLV

• BG HIS-7010B, CATION DEMIN INLET VLV

• BG HIS-7010D, BTRS DEMIN D INLET VLV

• BG HIS-7010E, BTRS DEMIN E INLET VLV NOTE The following step prevents BGHV7054 from opening when BG HIS-0027 is placed in BORATE. CAUTION Performance of Steps 5.12.10 and 5.12.12 isolates BTRS from the CVCS. No RCS boration/dilution is possible due to BTRS operation in this lineup. 5.12.10. Using BG HIS-7054, BTRS INLET VLV, CLOSE BGHV7054. NOTE If performance of this procedure is terminated or postponed prior to restoration of the following valves to the LOCKED CLOSED position, they should be entered in the Locked Component Deviation List:

• BGV0192, M/U TO BA BLENDING TEES HDR ISO

• BGV0034, RX M/U WTR TO BTRS ISO 5.12.11. UNLOCK and OPEN BGV0192, M/U TO BA BLENDING TEES HDR ISO (in VCT Valve Room). 5.12.12. CLOSE BG7053, CVCS MOD HX HDR ISO TO RX CLNT FLTR (SE corner Rm 1105). 5.12.13. ADJUST BG TK-381A, LTDN DIVERT FLOW CTRL, to 7.0 (corresponds to 140°F). 5.12.14. NOTIFY Chemistry to ensure BTRS effluent samples are taken during performance of Steps 5.12.24 through 5.12.27.c to determine when no additional flushing is required.

OTN-BG-00002 Rev. 041 Page 38 of 71 CONTINUOUS USE 5.12.15. NOTIFY Radwaste that BTRS Demineralizer Flushing is starting. 5.12.16. UNLOCK and OPEN BGV0034, RX M/U WTR TO BTRS ISO (Rm 1105). 5.12.17. OPEN BGV0060, BTRS TO RECYC EVAP FEED DEMIN IN HDR ISO. NOTE Since Reactor Makeup Water from the Boric Acid Blending Tee is being used to flush the Demineralizers, no boration via the BA Blending Tee should be performed during Steps 5.12.18 through 5.12.27. 5.12.18. PLACE BG TK-381A, LTDN DIVERT FLOW CTRL, in MANUAL and SET to zero. 5.12.19. PLACE BG HIS-27, BTRS CTRL, in BORATE. NOTE The Borate white light will not energize due to BGHV7054 being CLOSED. Valve position per Attachment 5 is required. 5.12.20. ENSURE position of all valves listed on Attachment 5 (except BGHV7054) in the Borate position. 5.12.21. ADJUST BG FK-111, REACTOR M/U WTR FLOW CTRL, to 5.0 (corresponds to 80 gpm). CAUTION Step 5.12.22 implements P&L Step 3.1.7. 5.12.22. RESET BG FY-111B, COMBINED M/U & BA COUNTER, and SET it to the maximum amount of water that Radwaste can receive. NOTE The following step will commence M/U flow. 5.12.23. PLACE BG HS-26, RCS M/U CTRL, in RUN.

OTN-BG-00002 Rev. 041 Page 39 of 71 CONTINUOUS USE 5.12.24. Slowly RAISE the output of BG TK-381A, LTDN DIVERT FLOW CTRL, to raise the letdown reheat heat exchanger outlet temperature at BG TI-381, BTRS DEMIN INLET TEMP, to between 135°F and 145°F. 5.12.25. WHEN the temperature at BG TI-381 is at the desired value and stable: a. PLACE BG TK-381A in AUTO. b. RECORD the BG FY-111B totalizer reading on Attachment #3. c. Using BG HC-387, BTRS DEMIN BYPASS CTRL, slowly CLOSE BGHCV0387 to commence flushing the Demineralizer. d. INFORM Chemistry that BTRS flushing has begun and to obtain the data required on Attachment 3 at 30 to 60 minute intervals during the flush. NOTE In this lineup, automatic high temperature protection is not available for the Demineralizers. If BG TI-381 temperature exceeds 156°F, letdown may divert to the VCT. e. MONITOR BG TI-381, BTRS DEMIN INLET TEMP, periodically to ensure the reactor makeup flushing water temperature does not exceed 145°F. 5.12.26. WHEN the Demineralizers appear to be flushed as indicated by the data recorded on Attachment 3 and referencing step 3.3, FORWARD the completed copy of Attachment 3 to the BG System Engineer. 5.12.27. WHEN the Demineralizer flushing is complete PERFORM the following: a. PLACE BG TK-381A in MANUAL. NOTE The following step will stop LTDN Flow to the LTDN Reheat Hx. b. Using BG TK-381A, slowly CLOSE BG TCV-381B while monitoring temperature drop on BG TI-381. c. SET demand on BG HC-387, BTRS DEMIN BYPASS CTRL, at 100% (to fully open BG HCV-387). d. PLACE BG HIS-27, BTRS CTRL, in OFF.

OTN-BG-00002 Rev. 041 Page 40 of 71 CONTINUOUS USE Step 5.12.27 Cont'd e. CLOSE BGV0060, BTRS TO RECYC EVAP FEED DEMIN IN HDR ISO. f. PLACE BG HS-26, RCS M/U CTRL, in STOP. g. ADJUST BG FK-111, REACTOR M/U WTR FLOW CTRL, to 7.5 (corresponds to 120 gpm). h. CLOSE and LOCK BGV0034, RX M/U WTR TO BTRS ISO. i. OPEN BG7053, LTDN DIVERT FLOW CTRL. j. CLOSE and LOCK BGV0192, M/U TO BA BLENDING TEES HDR ISO. k. RESTORE the BTRS Demineralizers to the normal lineup by ensuring the following valves are open, or in the desired lineup for BTRS operation:

• BG HIS-7010A, BTRS DEMIN A INLET VLV

• BG HIS-7010B, CATION DEMIN INLET VLV

• BG HIS-7010D, BTRS DEMIN D INLET VLV

• BG HIS-7010E, BTRS DEMIN E INLET VLV

l. PLACE BG HIS-7054, BTRS INLET VLV, in AUTO. m. ADJUST the RMCS as required by plant conditions. n. PLACE the following valves handswitches in AUTO:

• BG HIS-111B, MAKEUP TO VCT INLET

• BG HIS-110A, BA TO BA BLENDING TEE

• BG HIS-110B, MAKEUP TO VCT OUTLET

o. PERFORM Checklist 3, Locked Valve Restoration. -END OF SECTION-OTN-BG-00002 Rev. 041 Page 41 of 71 CONTINUOUS USE 5.13. Pressure Testing BTRS With Reactor Makeup Water NOTE This section of the procedure should follow major maintenance on BTRS System. Since Reactor Makeup Water from the Boric Acid Blending Tee is being used to pressurize the system, no boration via the BA Blending Tee should be performed during performance of this section. 5.13.1. Using BG HIS-8245, CVCS DEMIN OUTLET VLV, ENSURE BGHV8245 is OPEN. 5.13.2. PLACE BG HIS-27, BTRS CTRL, in OFF. 5.13.3. PLACE BG HS-26, RCS M/U CTRL, in STOP. 5.13.4. PLACE BG HS-25, RCS M/U CTRL SEL, in MAN. 5.13.5. PLACE the following in CLOSE:

• BG HIS-110A, BA TO BA BLENDING TEE

• BG HIS-110B, MAKEUP TO VCT OUTLET

• BG HIS-111B, MAKEUP TO VCT INLET 5.13.6. SET demand on BG HC-387, BTRS DEMIN BYPASS CTRL, at 100% (to ensure BG HCV-387 is fully open). 5.13.7. ENSURE the following are in STOP:

• BG HIS-23, CVCS CHILLER PUMP A

• BG HIS-24, CVCS CHILLER PUMP B

• BG HIS-21, CVCS CHILLER UNIT 5.13.8. IF desired, CLOSE the BTRS Demineralizer Isolation valves using the following:

• BG HIS-7010A, BTRS DEMIN A INLET VLV

• BG HIS-7010B, CATION DEMIN INLET VLV

• BG HIS-7010D, BTRS DEMIN D INLET VLV

• BG HIS-7010E, BTRS DEMIN E INLET VLV

OTN-BG-00002 Rev. 041 Page 42 of 71 CONTINUOUS USE CAUTION Performance of Steps 5.13.9 and 5.13.11isolates BTRS from the CVCS. 5.13.9. Using BG HIS-7054, BTRS INLET VLV, CLOSE BGHV7054. NOTE If performance of this procedure is terminated or postponed prior to restoration of the following valves to their LOCKED CLOSED position, they should be entered in the Locked Component Deviation List:

• BGV0192, M/U TO BA BLENDING TEES HDR ISO

• BGV0034, RX M/U WTR TO BTRS ISO 5.13.10. UNLOCK and OPEN BGV0192, M/U TO BA BLENDING TEES HDR ISO (in VCT Valve Room). 5.13.11. CLOSE BG7053, CVCS MOD HX HDR ISO TO RX CLNT FLTR (SE corner Rm 1105). NOTE Step 5.13.12 will prevent letdown flow through the letdown reheat heat exchanger. This MUST be done to prevent boiling of the pressure test fluid. 5.13.12. ADJUST BG TK-381A, LTDN DIVERT FLOW CTRL, to 0. 5.13.13. UNLOCK and OPEN BGV0034, RX M/U WTR TO BTRS ISO, (Rm 1105). 5.13.14. PLACE BG HIS-27, BTRS CTRL, in BORATE. 5.13.15. IF the BG HIS-27 Borate light is not ON, ENSURE position of valves by other indications in accordance with Attachment 5. 5.13.16. Using BG HIS-111A, REACTOR M/U WTR TO BA BLENDING TEE, manually OPEN BGFCV0111A and ESTABLISH flow to the BTRS System. 5.13.17. MONITOR BG FY-111B, COMBINED M/U & BA FLOW COUNTER, to determine the amount of Reactor Makeup Water added to the system.

OTN-BG-00002 Rev. 041 Page 43 of 71 CONTINUOUS USE 5.13.18. WHEN an inspection has been made of the BTRS Valve Room (Aux. Bldg, 1974, Room 1105), PERFORM the following:

a. Using BG HIS-111A, REACTOR M/U WTR TO BA BLENDING TEE, CLOSE BGFCV0111A. b. PLACE BG HIS-27, BTRS CTRL, in OFF. c. PLACE the following in AUTO:

• BG HIS-7054, BTRS INLET VLV

• BG HIS-110A, BA TO BA BLENDING TEE

• BG HIS-110B, MAKEUP TO VCT OUTLET

• BG HIS-111B, MAKEUP TO VCT INLET

d. ADJUST the RMCS as required by plant conditions. e. ENSURE the following valves are OPEN or in the desired lineup for BTRS Operation:

• BG HIS-7010A, BTRS DEMIN A INLET VLV

• BG HIS-7010B, CATION DEMIN INLET VLV

• BG HIS-7010D, BTRS DEMIN D INLET VLV

• BG HIS-7010E, BTRS DEMIN E INLET VLV

f. ADJUST BG TK-381A, LTDN DIVERT FLOW CTRL, to 6.5 and ENSURE it is in AUTO. g. CLOSE and LOCK BGV0034, RX M/U WTR TO BTRS ISO, (Rm 1105). h. OPEN BG7053, LTDN DIVERT FLOW CTRL, (Rm 1105). i. CLOSE and LOCK BGV0192, M/U TO BA BLENDING TEES HDR ISO (Rm 1318). j. PERFORM Checklist 2, Placing the Chiller Unit Service Water Headers in Dry Lay-up. -END OF SECTION-OTN-BG-00002 Rev. 041 Page 44 of 71 CONTINUOUS USE 5.14. Immediate Boration To Support Plant Shutdown 5.14.1. ENSURE the water plan or Chemistry is referenced to determine the source of boric acid for boration of the RCS. 5.14.2. ENSURE one of the Charging Pumps is in operation in accordance with OTN-BG-00001, Chemical And Volume Control System. 5.14.3. IF it is desired to borate from the Boric Acid Storage Tanks, PERFORM the following:

a. START at least one Boric Acid Transfer Pump using the following handswitch:

• BG HIS-5A, BA TRANSFER PUMP A

• BG HIS-6A, BA TRANSFER PUMP B

b. Using BG HIS-8104, EMERG BORATE TO CHG PUMP SUCT, OPEN BGHV8104. c. ENSURE greater than 30 gpm flow is indicated on BG FI-183A, EMERG BORATE FLOW. d. WHEN boration from the Boric Acid Storage Tanks is complete: 1. STOP any operating Boric Acid Transfer Pump using:

• BG HIS-5A, BA TRANSFER PUMP A

• BG HIS-6A, BA TRANSFER PUMP B

2. Using BG HIS-8104, EMERG BORATE TO CHG PUMP SUCT, CLOSE BGHV8104. 3. EQUALIZE charging pump suction header and RCS boron concentrations as follows: [Ref: 6.2.11]

a) ALLOW the running charging pump to continue flowing to the RCS for at least 30 minutes. b) IF plant conditions allow, FLUSH the suction header of the non running charging pumps per OTN-BG-00001, Chemical And Volume Control System. c) IF a charging pump can NOT be flushed at this time, ENSURE a Caution Tag is placed on the affected charging pump hand switch warning of high boron concentrations and the need to flush the charging pump suction header per OTN-BG-00001, Chemical And Volume Control System.

OTN-BG-00002 Rev. 041 Page 45 of 71 CONTINUOUS USE 5.14.4. IF it is desired to borate from the RWST, PERFORM the following: a. IF CCP A is in operation, using BN HIS-112D, CCP A SUCT FROM RWST, OPEN BNLCV112D. b. IF CCP B is in operation, using BN HIS-112E, CCP B SUCT FROM RWST, OPEN BNLCV112E. c. ENSURE the applicable valve indicates OPEN using:

• BN HIS-112D, CCP A SUCT FROM RWST

• BN HIS-112E, CCP B SUCT FROM RWST

d. Using BG HIS-112B, VCT OUTLET VLV, CLOSE BGLCV112B. e. Using BG HIS-112C, VCT OUTLET VLV, CLOSE BGLCV112C. f. WHEN Boration from the RWST is complete:

1. Using BG HIS-112C, VCT OUTLET VLV, OPEN BGLCV112C. 2. Using BG HIS-112B, VCT OUTLET VLV, OPEN BGLCV112B. 3. ENSURE both VCT outlet valves are OPEN using:

• BG HIS-112C, VCT OUTLET VLV

• BG HIS-112B, VCT OUTLET VLV

4. CLOSE both RWST suction valves using:

• BN HIS-112D, CCP A SUCT FROM RWST

• BN HIS-112E, CCP B SUCT FROM RWST

5. EQUALIZE charging suction header and RCS boron concentrations as follows: [Ref: 6.2.11]

a) ALLOW the running charging pump to continue flowing to the RCS for at least 30 minutes. b) IF plant conditions allow, FLUSH the suction header of the non running charging pumps per OTN-BG-00001, Chemical And Volume Control System. c) IF a charging pump can NOT be flushed at this time, ENSURE a Caution Tag is placed on the affected charging pump hand switch warning of high boron concentrations and the need to flush the charging pump suction header per OTN-BG-00001, Chemical And Volume Control System. -END OF SECTION-OTN-BG-00002 Rev. 041 Page 46 of 71 CONTINUOUS USE 5.15. Restoration Of The SW Side Of CVCS Chiller Unit From Dry Layup Condition 5.15.1. CLOSE the following vents and drains on Checklist 1, Removing the Chiller Unit Service Water Headers from Dry Lay-up.

• EAV0083, CVCS CHL SERV WTR IN VENT

• EAV0169, CVCS CHL UNIT SERV WTR SPLY HDR DRN

• EAV0084, CVCS CHL SERV WTR OUT VENT

• EAV0171, CVCS CHL UNIT SERV WTR RTN HDR DRN

• BGV0411, CVCS CHL UNIT SERV WTR RTN VENT

• BGV0412, CVCS CHL UNIT SERV WTR RTN DRN

• BGV0304, CVCS CHL UNIT SERV WTR SPLY TEST CONN

• BGV0413, CVCS CHL UNIT SERV WTR SPLY DRN

• BGV0305, CVCS CHL UNIT SERV WTR RTN TEST CONN NOTE With the Chiller Unit shutdown, BGFC5010, CVCS CHILLER UNIT COND SERV WTR OUT FLOW CTRL could be opened or closed. Filling and venting the service water inlet and outlet headers will be performed as though this valve were CLOSED. 5.15.2. UNLOCK and SLOWLY OPEN the EAV0168, CVCS CHL SERV WTR IN ISO and ALLOW the inlet header to fill up to BGFC5010, CVCS CHILLER UNIT COND SERV WTR OUT FLOW CTRL. 5.15.3. VENT the header from EAV0083, CVCS CHL SERV WTR IN VENT. 5.15.4. UNLOCK and SLOWLY OPEN EAV0170, CVCS CHL SERV WTR OUT ISO and ALLOW the inlet header to fill up to BGFC5010, CVCS CHILLER UNIT COND SERV WTR OUT FLOW CTRL.

OTN-BG-00002 Rev. 041 Page 47 of 71 CONTINUOUS USE NOTE If performance of this procedure is terminated or postponed prior to restoration of the following valves to the LOCKED CLOSED position they should be entered in the Locked Component Deviation List:

• EAV0168, CVCS CHL SERV WTR IN ISO

• EAV0170, CVCS CHL SERV WTR OUT ISO 5.15.5. VENT the header from the following valves:

• EAV0084, CVCS CHL SERV WTR OUT VENT

• BGV0411, CVCS CHL UNIT SERV WTR RTN VENT 5.15.6. COMPLETE Checklist 1, Removing the Chiller Unit Service Water Headers from Dry Lay-up. -END OF SECTION-OTN-BG-00002 Rev. 041 Page 48 of 71 CONTINUOUS USE 5.16. Placing The SW Side Of CVCS Chiller Unit In Dry Layup Condition 5.16.1. CLOSE and LOCK the following valves, (CB-1974 Rm-3101 N Center Of Room, 7' Up):

• EAV0168, CVCS CHL SERV WTR IN ISO

• EAV0170, CVCS CHL SERV WTR OUT ISO 5.16.2. PLACE drain rigs on the following drain valves:

• BGV0412, CVCS CHL UNIT SERV WTR RTN DRN, (AB-1974 Rm-1102, NW of Chl Unit next to N wall)

• BGV0413, CVCS CHL UNIT SERV WTR SPLY DRN, (AB-1974 Rm-1102, East of Chil Unit)

• EAV0169, CVCS CHL UNIT SERV WTR SPLY HDR DRN, (CB-1974, Rm-3101)

• EAV0171, CVCS CHL UNIT SERV WTR RTN HDR DRN, (CB-1974, Rm-3101) 5.16.3. OPEN the following drain valves:

• BGV0412, CVCS CHL UNIT SERV WTR RTN DRN, (AB-1974 Rm-1102 NW of Chl Unit next to N wall)

• BGV0413, CVCS CHL UNIT SERV WTR SPLY DRN, (AB-1974 Rm-1102 East of Chil Unit)

• EAV0169, CVCS CHL UNIT SERV WTR SPLY HDR DRN, (CB-1974 Rm-3101)

• EAV0171, CVCS CHL UNIT SERV WTR RTN HDR DRN, (CB-1974 Rm-3101) 5.16.4. OPEN the following vent valves:

• EAV0083, CVCS CHL SERV WTR IN VENT, (AB-1974 Rm-1102 West Of BTRS Chiller 15ft Up Over Walk Zone)

• EAV0084, CVCS CHL SERV WTR OUT VENT, (AB-1974 Rm 1102 West Of BTRS Chiller 15 Ft Up Over Walk Zone)

• BGV0411, CVCS CHL UNIT SERV WTR RTN VENT, (AB-1974 Rm-1102 NW Of Chl Unit Near Wall 9' High)

OTN-BG-00002 Rev. 041 Page 49 of 71 CONTINUOUS USE 5.16.5. WHEN draining is complete, REMOVE the drain rigs from the following valves:

• BGV0412, CVCS CHL UNIT SERV WTR RTN DRN, (AB-1974 Rm-1102 NW of Chl Unit next to N wall)

• BGV0413, CVCS CHL UNIT SERV WTR SPLY DRN, (AB-1974 Rm-1102 East of Chil Unit)

• EAV0169, CVCS CHL UNIT SERV WTR SPLY HDR DRN, (CB-1974 Rm-3101)

• EAV0171, CVCS CHL UNIT SERV WTR RTN HDR DRN, (CB-1974 Rm-3101) 5.16.6. COMPLETE Checklist 2, Placing the Chiller Unit Service Water Headers in Dry Lay-up. -END OF SECTION-OTN-BG-00002 Rev. 041 Page 50 of 71 CONTINUOUS USE 5.17. Restoration Of Chilled Water Side Of CVCS Chiller Unit From Dry Layup Condition 5.17.1. REMOVE tags. 5.17.2. REMOVE the FME screens and CLOSE the following valves:

• BGV0409, CVCS CHL SRG TK OUT DRN

• BGV0414, CVCS LTDN CHL HX CHILLED WTR IN HDR DRN

• BGV0417, CVCS LTDN CHL HX CHILLED WTR OUT DRN 5.17.3. REMOVE the FME screens and INSTALL venting hoses for the following vents:

• BGV0419, CVCS CHL SRG TK IN VENT

• BGV0410, CVCS CHL UNIT IN VENT 5.17.4. Slowly THROTTLE BGV0070, DI WTR TO CVCS CHL SRG TK ISO, to begin filling the system. NOTE When CVCS Chiller Surge Tank level instrumentation has been vented and placed in service by I&C, vent line monitoring may be replaced by monitoring computer points BGL0380H, BTRS CHL SRG TK, and BGL0380L, BTRS CHL SRG TK. 5.17.5. Continuously MONITOR the CVCS Chiller Surge Tank vent line 368-HBD-2" and CLOSE BGV0070, DI WTR TO CVCS CHL SRG TK ISO, if any water is observed. 5.17.6. Continuously MONITOR BGLI0380, CVCS CHILL SURGE TK LEVEL - - LEVEL IND., and maintain level between 55 to 75 % using BGV0070, DI WTR TO CVCS CHL SRG TK ISO. 5.17.7. REQUEST I&C vent BGLT0380, CVCS CHL SURGE TK LVL XMTR. 5.17.8. MONITOR BGV0410, CVCS CHL UNIT IN VENT, and CLOSE the valve when a solid stream of water has been observed for at least two (2) minutes. 5.17.9. INSTALL venting hoses for the following vents:

• BGV0418, CVCS LTDN CHL HX CHILLED WTR OUT VENT

• BGV0415, CVCS LTDN CHL HX CHILLED WTR IN VENT

OTN-BG-00002 Rev. 041 Page 51 of 71 CONTINUOUS USE 5.17.10. WHEN surge tank level has been established, VENT at the following locations until a solid stream of water has been observed for at least two (2) minutes:

• BGV0418, CVCS LTDN CHL HX CHILLED WTR OUT VENT

• BGV0415, CVCS LTDN CHL HX CHILLED WTR IN VENT 5.17.11. ENSURE the following valves are closed:

• BGV0418, CVCS LTDN CHL HX CHILLED WTR OUT VENT

• BGV0415, CVCS LTDN CHL HX CHILLED WTR IN VENT

• BGV0410, CVCS CHL UNIT IN VENT

• BGV0419, CVCS CHL SRG TK IN VENT 5.17.12. RAISE surge tank level on BGLI0380, CVCS CHILL SURGE TK LEVEL - - LEVEL IND., to 80 to 82 % using BGV0070, DI WTR TO CVCS CHL SRG TK ISO. 5.17.13. ENSURE BGV0070, DI WTR TO CVCS CHL SRG TK ISO, is closed. 5.17.14. CLOSE the following breakers:

• PG19NBF5, FDR BKR TO PBG01A CVCS CHILLER PMP A

• PG20NCF4, FDR BKR TO PBG01B CVCS CHILLER PMP B

• PG2003, FDR BKR TO SBG02 CVCS CHILLER UNIT 5.17.15. Using one of the following, START a chiller pump and run for up to one (1) minute:

• BG HIS-23, CVCS CHILLER PUMP A

• BG HIS-24, CVCS CHILLER PUMP B 5.17.16. WHEN the chiller pump has been stopped, VENT at the following locations until a solid stream of water has been observed for at least two (2) minutes:

• BGV0410, CVCS CHL UNIT IN VENT

• BGV0418, CVCS LTDN CHL HX CHILLED WTR OUT VENT

• BGV0415, CVCS LTDN CHL HX CHILLED WTR IN VENT 5.17.17. ENSURE surge tank level on BGLI0380, CVCS CHILL SURGE TK LEVEL - - LEVEL IND., is 80 to 82 % using BGV0070, DI WTR TO CVCS CHL SRG TK ISO.

OTN-BG-00002 Rev. 041 Page 52 of 71 CONTINUOUS USE 5.17.18. Using one of the following, START the chiller pump NOT started in Step 5.17.15 and run for up to one (1) minute:

• BG HIS-24, CVCS CHILLER PUMP B

• BG HIS-23, CVCS CHILLER PUMP A 5.17.19. WHEN the second chiller pump has been stopped, VENT at the following locations until a solid stream of water has been observed for at least two (2) minutes:

• BGV0410, CVCS CHL UNIT IN VENT

• BGV0418, CVCS LTDN CHL HX CHILLED WTR OUT VENT

• BGV0415, CVCS LTDN CHL HX CHILLED WTR IN VENT 5.17.20. WHEN BGLI0380, CVCS CHILL SURGE TK LEVEL - - LEVEL IND., is between 55 to 82 %, CLOSE BGV0070, DI WTR TO CVCS CHL SRG TK ISO. 5.17.21. REMOVE venting hoses and INSTALL caps on the following vents:

• BGV0418, CVCS LTDN CHL HX CHILLED WTR OUT VENT

• BGV0415, CVCS LTDN CHL HX CHILLED WTR IN VENT

• BGV0410, CVCS CHL UNIT IN VENT

• BGV0419, CVCS CHL SRG TK IN VENT 5.17.22. PERFORM Checklist 4, Restoration From Dry Layup Of BTRS Chiller Chill Water Side. -END OF SECTION-OTN-BG-00002 Rev. 041 Page 53 of 71 CONTINUOUS USE 5.18. Placing The Chilled Water Side Of CVCS Chiller Unit In Dry Layup Condition [Ref: 6.2.10] NOTE Chilled Water should NOT be drained to the DRW sumps. Drains should be routed to the SLW sump in the north east corner of the Aux Building. This will require approximately 300 feet of hose. 5.18.1. CONTACT Chemistry to determine if any special requirements are needed for dry layup. 5.18.2. ENSURE the following breakers are OPEN:

• PG19NBF5, FDR BKR TO PBG01A CVCS CHILLER PMP A

• PG20NCF4, FDR BKR TO PBG01B CVCS CHILLER PMP B

• PG2003, FDR BKR TO SBG02 CVCS CHILLER UNIT 5.18.3. ENSURE BGV0070, DI WTR TO CVCS CHL SRG TK ISO, is closed. 5.18.4. ROUTE a drain hose "header" from the Chiller Pumps to the SLW sump. 5.18.5. CONNECT drain hoses from the following drains to the "drain header":

• BGV0409, CVCS CHL SRG TK OUT DRN

• BGV0500, CVCS CHL PMP A DISCH DRN

• BGV0501, CVCS CHL PMP B DISCH DRN

• BGV0414, CVCS LTDN CHL HX CHILLED WTR IN HDR DRN

• BGV0417, CVCS LTDN CHL HX CHILLED WTR OUT DRN 5.18.6. OPEN BGV0409, CVCS CHL SRG TK OUT DRN. 5.18.7. AFTER the CVCS Chiller Surge Tank has mostly drained, OPEN the following drains:

• BGV0500, CVCS CHL PMP A DISCH DRN

• BGV0501, CVCS CHL PMP B DISCH DRN

• BGV0414, CVCS LTDN CHL HX CHILLED WTR IN HDR DRN

• BGV0417, CVCS LTDN CHL HX CHILLED WTR OUT DRN

OTN-BG-00002 Rev. 041 Page 54 of 71 CONTINUOUS USE 5.18.8. Slowly OPEN the following vents to ensure the system is drained:

• BGV0419, CVCS CHL SRG TK IN VENT

• BGV0410, CVCS CHL UNIT IN VENT 5.18.9. Using a container, DRAIN the residual water from the impellers of the Chiller Pumps by opening the following:

• BGV0302, CVCS CHL PMP A DRN

• BGV0303, CVCS CHL PMP B DRN 5.18.10. CONNECT an air line for Service Air to vent BGV0410, CVCS CHL UNIT IN VENT. 5.18.11. ENSURE the drain hose going into the SLW Sump is secured to NOT move. 5.18.12. Slowly THROTTLE the air line to no more than two (2) turns open. 5.18.13. ALLOW air to blow through the piping for approximately one (1) hour. 5.18.14. CLOSE the air line and REMOVE the air hose. 5.18.15. ENSURE the following are closed:

• BGV0302, CVCS CHL PMP A DRN

• BGV0303, CVCS CHL PMP B DRN 5.18.16. CLOSE the following valves and REMOVE their drain hoses:

• BGV0500, CVCS CHL PMP A DISCH DRN

• BGV0501, CVCS CHL PMP B DISCH DRN 5.18.17. REMOVE the drain hoses and INSTALL FME screens for the following valves:

• BGV0409, CVCS CHL SRG TK OUT DRN

• BGV0414, CVCS LTDN CHL HX CHILLED WTR IN HDR DRN

• BGV0417, CVCS LTDN CHL HX CHILLED WTR OUT DRN 5.18.18. INSTALL FME screens for the following vents:

• BGV0419, CVCS CHL SRG TK IN VENT

• BGV0410, CVCS CHL UNIT IN VENT 5.18.19. HANG Tags -END OF SECTION-OTN-BG-00002 Rev. 041 Page 55 of 71 CONTINUOUS USE 5.19. Removing BTRS From Service For Maintenance 5.19.1. Using BG HIS-8245, CVCS DEMIN OUTLET VLV, ENSURE BGHV8245 is open. 5.19.2. ENSURE BG HIS-27, BTRS CTRL, is in OFF. 5.19.3. Using BG HIS-7054, BTRS INLET VLV, CLOSE BGHV7054. 5.19.4. CLOSE BG7053, CVCS MOD HX HDR ISO TO RX CLNT FLTR (AB-1975 Rm 1105, SE corner). 5.19.5. CLOSE BG7001, CVCS MOD HX TO LTDN CHL HX HDR UPSTRM ISO (AB-1975 Rm-1105, NW Corner Of Rm Against West Wall) 5.19.6. VENT and DRAIN as required to perform maintenance. -END OF SECTION-OTN-BG-00002 Rev. 041 Page 56 of 71 CONTINUOUS USE 5.20. Filling And Venting BTRS Following Maintenance Using Letdown Or Rx M/U Water NOTE It takes approximately 400 to 500 gallons to fill the BTRS system. If BTRS demin Beds are drained that would add to the total gallons. (A BTRS Bed is approximately 200 gals if it is filled with resin.) 5.20.1. IF using letdown, ENSURE VCT level is sufficient to support refilling the portion of BTRS that was drained. 5.20.2. Using BG HIS-8245, CVCS DEMIN OUTLET VLV, ENSURE BGHV8245 is OPEN. 5.20.3. Using BG HIS-7054, BTRS INLET VLV, PLACE BGHV7054 in CLOSE. 5.20.4. ENSURE BG7053, CVCS MOD HX HDR ISO TO RX CLNT FLTR, is CLOSED (SE corner AB 1974 Rm 1105). 5.20.5. OPEN BG7001, CVCS MOD HX TO LTDN CHL HX HDR UPSTRM ISO (AB-1975 Rm-1105, NW Corner Of Rm Against West Wall). NOTE BGV0056, CVCS BTRS DEMINS TO NUC SAMP SYS HDR ISO, remains closed during fill and vent to prevent water hammer of the sample system. 5.20.6. ENSURE BGV0056, CVCS BTRS DEMINS TO NUC SAMP SYS HDR ISO, is CLOSED. 5.20.7. PLACE BG HIS-27, BTRS CTRL, in DILUTE. NOTE The white DILUTE light will not be lit due to BGHV7054 being closed. Computer points should be used to verify valves positions. BGUV7022 will have to be verified locally. 5.20.8. CHECK the white DILUTE light on BG HIS-27 is off.

OTN-BG-00002 Rev. 041 Page 57 of 71 CONTINUOUS USE 5.20.9. CONFIRM valve positions using the following computer points:

• Using BGZ7002A, CHECK BGUV7002A, CVCS MOD HX TO LTDN CHL HX HDR CTRL VLV, OPEN.

• Using BGZ7002B, CHECK BGUV7002B, LTDN CHL HX TO LTDN REHEAT HX HDR CTRL VLV, OPEN.

• Using BGZ7040, CHECK BGUV7040, CVCS LTDN CHL HX TO RX CLNT FLTR HDR CTRL VLV, CLOSED.

• Using BGZ7041, CHECK BGUV7041, CVCS LTDN CHL HX BYP HDR CTRL VLV, CLOSED.

• Using BGZ7045, CHECK BGUV7045, CVCS BTRS DEMINS OUT CTRL VLV, NOT CLOSED.

• Using BGZ7046, CHECK BGUV7046, CVCS BTRS DEMINS IN BYP CTRL VLV, NOT OPEN.

• Using BGZ7056, CHECK BGUV7056, CVCS BTRS DEMINS HDR CTRL VLV, OPEN.

• Using BGZ7057, CHECK BGUV7057, CVCS BTRS DEMINS OUT BYP CTRL VLV, CLOSED.

• Using BGZ7054, CHECK BGHV7054, CVCS MOD HX BTRS IN ISO HV, CLOSED.

• Using BGZ0381A, CHECK BGTCV0381A, CVCS LTDN DIVERT FLOW TCV A, NOT OPEN.

• Using BGZ0381B, CHECK BGTCV0381B, LTDN DIVERT BYP TCV B, NOT CLOSED. 5.20.10. Locally CONFIRM BGUV7022, CVCS MOD HX TO RX CLNT FLTR CTRL VLV, OPEN. NOTE Failing open BGUV7057 provides a flowpath to refill the BTRS Demin inlet header while in the DILUTE mode. 5.20.11. CLOSE BGUV7057V1, AIR SPLY ISO FOR BG-UV-7057, and BLEED air to fail open BGUV7057.

OTN-BG-00002 Rev. 041 Page 58 of 71 CONTINUOUS USE 5.20.12. IF using Letdown to refill the BTRS:

a. Slowly THROTTLE OPEN BG7053, CVCS MOD HX HDR ISO TO RX CLNT FLTR, (SE corner AB 1974 Rm 1105), until flow is heard. b. During the BTRS refill, IF the VCT requires filling, PERFORM the following: 1. CLOSE BG7053, CVCS MOD HX HDR ISO TO RX CLNT FLTR. 2. Manually FILL the VCT using applicable parts of this procedure. 3. Slowly THROTTLE OPEN BG7053, CVCS MOD HX HDR ISO TO RX CLNT FLTR, (SE corner AB 1974 Rm 1105), until flow is heard. NOTE Step 5.20.13 can be performed in parallel with Steps 5.20.14 and 5.20.15 to complete the BTRS Fill and Vent. 5.20.13. IF using Rx M/U water to refill the BTRS, MAKEUP to BTRS using Section 5.6, Manual Mode of RMCS Operation (RWST-RHUT-BTRS). NOTE In the following step, venting is only required for the portion of the BTRS that was drained. Suggested vents to use are the first six in the list. 5.20.14. Thoroughly VENT the system using the appropriate valves below:

• BGV0552, CVCS BTRS DEMINS OUT BGUV7045 UPSTRM VENT

• BGV0295, CVCS BTRS DEMIN E PRI SLUICE WTR RTN DRN

• BGV0499, CVCS BTRS DEMINS BYP VENT

• BGV0383, MB DEMINS TO MOD HX VENT

• BGV0425, CVCS LTDN CHL HX BYP HDR VENT

• BGV0395, BTRS DEMINS OUT HDR BGUV7045 DNSTRM VENT

• BGV0294, CVCS BTRS DEMIN D PRI SLUICE WTR RTN DRN

• BGV0292, CVCS BTRS DEMIN B PRI SLUICE WTR RTN DRN

• BGV0393, CVCS BTRS DEMINS BYP HDR VENT

OTN-BG-00002 Rev. 041 Page 59 of 71 CONTINUOUS USE Step 5.20.14 Cont'd

• BGV0386, CVCS MOD HX TO LTDN CHL HX HDR VENT

• BGV0401, CVCS LTDN CHL HX TO RX CLNT FLTR HDR VENT

• BGV0389, LTDN CHL HX TO LTDN REHEAT HX HDR VENT

• BGV0391, CVCS LTDN REHEAT HX OUT TO BTRS DEMINS HDR VENT

• BGV0291, CVCS BTRS DEMIN A PRI SLUICE WTR RTN DRN

• BGV0397, CVCS MOD HX TO RX CLNT FLTR OUT VENT 5.20.15. WHEN venting is complete, ENSURE any of the following that were used for venting are CLOSED and CAPPED:

• BGV0552, CVCS BTRS DEMINS OUT BGUV7045 UPSTRM VENT

• BGV0295, CVCS BTRS DEMIN E PRI SLUICE WTR RTN DRN

• BGV0499, CVCS BTRS DEMINS BYP VENT

• BGV0383, MB DEMINS TO MOD HX VENT

• BGV0425, CVCS LTDN CHL HX BYP HDR VENT

• BGV0395, BTRS DEMINS OUT HDR BGUV7045 DNSTRM VENT

• BGV0294, CVCS BTRS DEMIN D PRI SLUICE WTR RTN DRN

• BGV0292, CVCS BTRS DEMIN B PRI SLUICE WTR RTN DRN

• BGV0393, CVCS BTRS DEMINS BYP HDR VENT

• BGV0386, CVCS MOD HX TO LTDN CHL HX HDR VENT

• BGV0401, CVCS LTDN CHL HX TO RX CLNT FLTR HDR VENT

• BGV0389, LTDN CHL HX TO LTDN REHEAT HX HDR VENT

• BGV0391, CVCS LTDN REHEAT HX OUT TO BTRS DEMINS HDR VENT

• BGV0291, CVCS BTRS DEMIN A PRI SLUICE WTR RTN DRN

• BGV0397, CVCS MOD HX TO RX CLNT FLTR OUT VENT NOTE WHEN opening BG7053, CVCS MOD HX HDR ISO TO RX CLNT FLTR, there maybe a small VCT level drop due to pressurizing the system. 5.20.16. FULLY OPEN BG7053, CVCS MOD HX HDR ISO TO RX CLNT FLTR. 5.20.17. OPEN BGUV7057V1, AIR SPLY ISO FOR BG-UV-7057, and ENSURE BGUV7057, CVCS BTRS DEMINS OUT BYP CTRL VLV, is closed.

OTN-BG-00002 Rev. 041 Page 60 of 71 CONTINUOUS USE 5.20.18. OPEN BGV0056, CVCS BTRS DEMINS TO NUC SAMP SYS HDR ISO. 5.20.19. PLACE BG HIS-7054, BTRS INLET VLV, in AUTO. 5.20.20. IF Reactor Makeup Water was used to fill the system, ENSURE a proper flush is performed. 5.20.21. WHEN desired, PLACE the BTRS system in service using OTN-BG-00001 ADD05, Operation of the BTRS Demineralizer System. -END OF SECTION-OTN-BG-00002 Rev. 041 Page 61 of 71 CONTINUOUS USE

6.0 REFERENCES

6.1. Implementing 6.1.1. CSP-ZZ-07620, Borated Water Sources (BAST-A, BAST-B and RWST) 6.1.2. OTN-EC-00001, Fuel Pool Cooling And Cleanup System 6.1.3. OTN-BG-00001, Chemical And Volume Control System 6.1.4. OTN-BG-00001 ADD05, Operation of the BTRS Demineralizer System 6.1.5. OTS-BG-00006, Flushing BTRS Demineralizers 6.1.6. ODP-ZZ-00004, Locked Component Control 6.1.7. Curve Book, Figure 7-2, Reactor Makeup Control System Nomographs - Blended Flow for 120 gpm AUTO Makeup and Manual Reduced Flow Rates 6.1.8. Curve Book, Figure 7-3, Reactor Makeup Control System Nomographs - Boron Addition 6.1.9. Curve Book, Figure 7-4, Reactor Makeup Control System Nomographs - Boron Addition Rate 6.1.10. Curve Book, Figure 7-5, Reactor Makeup Control System Nomographs - Boron Dilution 6.1.11. Curve Book, Figure 7-6, Reactor Makeup Control System Nomographs - Boron Dilution Rate 6.1.12. Curve Book, Figure 7-8, Reactor Makeup Control System Nomographs - Boron Dilution and Boron Addition 6.1.13. Checklist 1, Removing the Chiller Unit Service Water Headers from Dry Lay-up 6.1.14. Checklist 2, Placing the Chiller Unit Service Water Headers in Dry Lay-up 6.1.15. Checklist 3, Locked Valve Restoration 6.1.16. Checklist 4, Restoration From Dry Layup Of BTRS Chiller Chill Water Side 6.2. Developmental 6.2.1. M-22BG01 6.2.2. M-22BG02 OTN-BG-00002 Rev. 041 Page 62 of 71 CONTINUOUS USE 6.2.3. M-22BG03 6.2.4. M-22BG04 6.2.5. M-22HE01 6.2.6. M-23BG12 6.2.7. FSAR 16.1.2.2 6.2.8. FSAR 16.1.2.5 6.2.9. CAR 199803251, During Performance Of A Retest On BGTCV0381B, An Unexpected Leak Occurred 6.2.10. CARS 199901416 6.2.11. CARS 200308549, Reactivity Management Near Miss while starting 'B' CCP 6.2.12. CARS 200606374 6.2.13. CARS 201010145 6.2.14. 8809D57 S041 7.0 RECORDS 7.1. QA Records 7.1.1. Curve Book, Figure 7-5, Reactor Makeup Control System Nomographs - Boron Dilution 7.1.2. Curve Book, Figure 7-6, Reactor Makeup Control System Nomographs - Boron Dilution Rate 7.1.3. Curve Book, Figure 7-8, Reactor Makeup Control System Nomographs - Boron Dilution and Boron Addition 7.1.4. Checklist 1, Removing the Chiller Unit Service Water Headers from Dry Lay-up 7.1.5. Checklist 2, Placing the Chiller Unit Service Water Headers in Dry Lay-up 7.1.6. Checklist 3, Locked Valve Restoration 7.1.7. Checklist 4, Restoration From Dry Layup Of BTRS Chiller Chill Water Side 7.2. Commercial Records 7.2.1. Data acquired in Attachment 1, 2 or 3 will be filed in the system files as a commercial record.

OTN-BG-00002 Rev. 041 Page 63 of 71 CONTINUOUS USE 8.0 SUMMARY OF CHANGES Page(s) Section or Step Number Description 5 Old step 3.1.7 Deleted precaution on RWST recirc time. Recirc time is controlled by CSP-ZZ-07620. 19 5.6.14.f.1 note Reworded note to state that recirc time requirements are determined by Chemistry per CSP-ZZ-07620. 61 and 62 6.1.1 and old steps 6.2.7 and 6.2.8 Added CSP-ZZ-07620 as a reference. Deleted RFR 017192A and UOTCR 96-152 as references.

OTN-BG-00002 Rev. 041 Page 64 of 71 CONTINUOUS USE Attachment 1 BTRS Performance Data/Status Log Sheet 1 of 1 Block 1A - Desired flow established through BTRS Demineralizer Time flow established through BTRS Demineralizer BTRS Demin flow BG FI-385 As desired Block 2 - Data recorded, in the given order, prior to completion of Dilution/Boration BTRS Demin Inlet Temp BG TI-381 50 +/- 10°F / 140 +/- 5°F BTRS Demin Outlet Temp BG TI-389 (Note 1) BTRS Outlet Temp BG TI-386 95 +/- 5 °F / 95 +/- 5°F Block 2A - Flow secured through BTRS Demineralizers Time BTRS demin bypassed Latest RCS C B Demineralizer in Service Circle letter A D E A D E A D E A D E A D E REMARKS:

NOTE 1: Optimum performance should exist when the outlet temperature reaches 50

+/- 10°F for the Dilute mode, or 140

+/- 5 °F for the Borate mode. These conditions will NOT be reached unless continuous flow to the Demineralizer has existed for at least 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. However, as long as the outlet temperature raises for dilution and lowers for boration, the system is functioning properly. PARAMETER Instrument Desired Temp Range Dilute / Borate DATA DATE Block 1 - Data recorded, in the given order, prior to Dilution/Boration via BTRS BTRS Demin Inlet Temp BG TI-381 50 +/- 10°F / 140 +/- 5°F BTRS Demin Outlet Temp BG TI-389 (Note 1) BTRS Outlet Temp BG TI-386 95 +/- 5 °F / 95 +/- 5°F OTN-BG-00002 Rev. 041 Page 65 of 71 CONTINUOUS USE Attachment 2 RCS Letdown Flow - BTRS Demineralizer Flushing Data Sheet 1 of 1 DATE: ____________________________ Demineralizer being flushed ____________

Performed by: ____________________________________________________________ Time of data acquisition Effluent boron concentration Elapsed time Time of data acquisition Effluent boron concentration Elapsed time

BG FI-132, LTDN HX OUTLET FLOW ______________ gpm OTN-BG-00002 Rev. 041 Page 66 of 71 CONTINUOUS USE Attachment 3 Reactor Makeup Water - BTRS Demineralizer Flushing Data Sheet 1 of 1 DATE: ____________________________ Demineralizer being flushed ____________

Performed by: ____________________________________________________________ Time of data acquisition Effluent boron concentration Elapsed time Time of data acquisition Effluent boron concentration Elapsed time Final Totalizer reading: __________________

Initial Totalizer reading: __________________ Total water used: ______________________

OTN-BG-00002 Rev. 041 Page 67 of 71 CONTINUOUS USE Attachment 4 Volume Control Tank Level Control System Sheet 1 of 1 LCV 112C/E OPEN LCV 112E SHUT LCV 112C OTN-BG-00002 Rev. 041 Page 68 of 71 CONTINUOUS USE Attachment 5 BTRS Controls For BG HIS-27 Indication Sheet 1 of 1 COMPONENT Equipment status required to energize the BG HIS-27 white light with the switch in the indicated position: BG HIS-27, BTRS CTRL DILUTE OFF BORATE BGUV7002A, CVCS MOD HX TO LTDN CHL HX HDR CTRL VLV OPEN CLOSED CLOSED BGUV7002B, LTDN CHL HX TO LTDN REHEAT HX HDR CTRL VLV OPEN CLOSED CLOSED *BGUV7022, CVCS MOD HX TO RX CLNT FLTR CTRL VLV OPEN CLOSED CLOSED BGUV7040, CVCS LTDN CHL HX TO RX CLNT FLTR HDR CTRL VLV CLOSED OPEN OPEN BGUV7041, CVCS LTDN CHL HX BYP HDR CTRL VLV CLOSED OPEN OPEN BGUV7045, CVCS BTRS DEMINS OUT CTRL VLV OPEN OPEN CLOSED BGUV7046, CVCS BTRS DEMINS IN BYP CTRL VLV CLOSED CLOSED OPEN BGUV7056, CVCS BTRS DEMINS HDR CTRL VLV OPEN CLOSED CLOSED BGUV7057, CVCS BTRS DEMINS OUT BYP CTRL VLV CLOSED OPEN OPEN BGHV7054, CVCS MOD HX BTRS IN ISO HV OPEN CLOSED OPEN BGTCV0381A, CVCS LTDN DIVERT FLOW TCV A CLOSED CLOSED Not Required BGTCV0381B, LTDN DIVERT BYP TCV B OPEN OPEN Not Required

• Valve position for BGUV7022 does NOT input into the plant computer. Local position verification is required.

OTN-BG-00002 Rev. 041 Page 69 of 71 CONTINUOUS USE Attachment 6 Dilute Mode Of RMCS Operation Sheet 1 of 1 NOTE This attachment provides direction for frequently performed, nominal 120 gpm dilutions. 1. PLACE BG HS-26, RCS M/U CTRL, in STOP. 2. PLACE BG HS-25, RCS M/U CTRL SEL, in DIL. 3. RESET BG FY-111B, COMBINED M/U & BA FLOW TOTALIZER, to 000. NOTE When setting BG FY-111B, allowance should be made in the setpoint to compensate for instrument inaccuracies and isolation valve closure times on total flow delivered. (Step 3.1.9 contains more information if required.) 4. ENSURE BG FY-111B is set to deliver the desired amount of makeup water. 5. PLACE BG HS-26, RCS M/U CTRL, in RUN. 6. WHEN the desired amount of water has been added, PLACE BG HS-26, RCS M/U CTRL, in STOP. 7. IF required, PERFORM the following: a. PLACE BG HS-25, RCS M/U CTRL SEL, in AUTO. b. PLACE BG HS-26, RCS M/U CTRL, in RUN.

OTN-BG-00002 Rev. 041 Page 70 of 71 CONTINUOUS USE Attachment 7 Alternate Dilute Mode Of RMCS Operation Sheet 1 of 1 NOTE This attachment provides direction for frequently performed, nominal 120 gpm alternate dilutions. 1. PLACE BG HS-26, RCS M/U CTRL, in STOP. 2. PLACE BG HS-25, RCS M/U CTRL SEL, in ALT DIL. 3. RESET BG FY-111B, COMBINED M/U & BA FLOW TOTALIZER, to 000. NOTE When setting BG FY-111B, allowance should be made in the setpoint to compensate for instrument inaccuracies and isolation valve closure times on total flow delivered. (Step 3.1.9 contains more information if required.) 4. ENSURE BG FY-111B is set to deliver the desired amount of makeup water. 5. PLACE BG HS-26, RCS M/U CTRL, in RUN. 6. WHEN the desired amount of water has been added, PLACE BG HS-26, RCS M/U CTRL, in STOP. 7. IF required, PERFORM the following: a. PLACE BG HS-25, RCS M/U CTRL SEL, in AUTO. b. PLACE BG HS-26, RCS M/U CTRL, in RUN.

OTN-BG-00002 Rev. 041 Page 71 of 71 CONTINUOUS USE Attachment 8 Borate Mode Of RMCS Operation Sheet 1 of 1 NOTE This attachment provides direction for frequently performed, nominal borations. 1. PLACE BG HS-26, RCS M/U CTRL, in STOP. 2. PLACE BG HS-25, RCS M/U CTRL SEL, in BOR. 3. RESET BG FY-110B, BA COUNTER, to 000. NOTE When setting BG FY-110B, allowance should be made in the setpoint to compensate for instrument inaccuracies and isolation valve closure times on total flow delivered. (Step 3.1.9 contains more information if required.) 4. ENSURE BG FY-110B is set to deliver the desired amount of boron. 5. PLACE BG HS-26, RCS M/U CTRL, in RUN. 6. WHEN the desired amount of borated water has been added, PLACE BG HS-26, RCS M/U CTRL, in STOP. 7. IF required, PERFORM the following: a. PLACE BG HS-25, RCS M/U CTRL SEL, in AUTO. b. PLACE BG HS-26, RCS M/U CTRL, in RUN.

CALLAWAY PLANT JOB PERFORMANCE MEASURE JPM No: RSA-3 KSA NO: GEN2.2.12 Revision:

KSA RATING:

KSA Rating:

4.1 Job Title: SRO Task Title

Review CCP Surveillance for Operability Validation Time:

20 minutes

Learning Objective: T61.003A-6, LP A22, Obj A.2.a, PERFORM the following as they pertain to APA

-ZZ-00340, Surveillance Program Administration: DESCRIBE: SM responsibilities regarding the Surveillance Program

The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY

[ ] UNSATISFACTORY

Reason, if UNSATISFACTORY:

Evaluators Signature:

Date:

Task Performer:

Location of Performance:

Control Room Simulator/Lab Plant Classroom X

Method of Performance:

Simulated Performed X

Alternate Path:

__ ____ Time Critical:

___ ___

Student Handouts:

Copy of OSP

-BG-P005B Completed copy of Attachment 2, System Performance Data Sheet, from OSP

-BG-P005B.

References:

OSP-BG-P005B "Centrifugal Charging Pump B Inservice Test

- Group B" TECHNICAL SPECIFICATIONS 3.5.2

JPM NO: RSA-3 Rev 1 Page 1 of 3 Initial Conditions:

C allaway is at 100% Power. The Reactor Operator has just completed the Group B operational readiness of CCP B from OSP-BG-P005B "Centrifugal Charging Pump B Inservice Test

- Group B".

Initiating Cues:

You are an extra SRO on shift. The Shift Manager (SM) has given you Attachment 2 of OSP-BG-P005B "Centrifugal Charging Pump B Inservice Test

- Group B" to review

. Inform the SM when your review is complete and include any actions required that need to be taken.

Write down required actions, if any, on your cue sheet and return to the Examiner.

Task Standard:

Upon completion of this JPM, the Operator will have determined that CCP B is INOPERABLE and that it must be restored to OPERABLE STATUS within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

START TIME:

STOP TIME:

JPM NO: RSA-3 Rev 1 TASK NUMBER - ELEMENT STANDARD SCORE Page 2 of 3 1. Obtain a verified working copy of OSP

-BG-P005B Applicant obtained working copy of OSP-BG-P005B S U Comments:

2. Review completed copy of Attachment 2 of OSP-BG-P005B. Applicant reviewed completed copy of Attachment 2 of OSP-BG-P005B. S U Comments:

3. *Identifies the data in step 6.1.27 (Pump Differential Pressure) was calculated incorrectly Applicant identified that the number for Pump Differential Pressure should be 2396 psid instead of 2416 psid S U Comments:

4. *Identifies the data in step 6.1.27 (Pump Differential Pressure) is less than the Tech Spec Limit of 2400 psid Applicant identified that the Pump Differential Pressure is less than the Tech Spec limit of 2400 psid S U Comments:

JPM NO: RSA-3 Rev 1 TASK NUMBER - ELEMENT STANDARD SCORE Page 3 of 3 5. *Informs Shift Manager that that CCP B is INOPERABLE and that it must be restored to OPERABLE STATUS within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in accordance with T/S LCO 3.5.2 Applicant informed SM that CCP B is INOPERABLE and that it must be restored to OPERABLE STATUS within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

Review APA

-ZZ-00340 "Surveillance Program Administration" S U Comments:

CUE: If the applicant does not state the T/S ask them:

"What T/S needs t o be entered and what actions that need to be taken?"

6. The JPM is complete Record stop time on Page 1 S U Comments:

Denotes Critical Step

Initial Conditions:

C allaway is at 100% Power. The Reactor Operator has just completed the Group B operational readiness of CCP B from OSP-BG-P005B "Centrifugal Charging Pump B Inservice Test

- Group B".

Initiating Cues:

You are an extra SRO on shift.

The Shift Manager (SM) has given you Attachment 2 of OSP-BG-P005B "Centrifugal Charging Pump B Inservice Test

- Group B" to review. Inform the SM when your review is complete and include any actions required that need to be taken.

Write down required actions, if any, on your cue sheet and return to the Examiner.

Page 1 of 25 CONTINUOUS USE

OSP-BG-P005B CENTRIFUGAL CHARGING PUMP B INSERVICE TEST - GROUP B MINOR Revision 048

OSP-BG-P005B Rev. 048 CENTRIFUGAL CHARGING PUMP B INSERVICE TEST - GROUP B TABLE OF CONTENTS Section Page Number Page 2 of 25 CONTINUOUS USE 1.0 PURPOSE ...................................................................................................................................... 3 2.0 SCOPE ........................................................................................................................................... 3 3.0 ACCEPTANCE CRITERIA ......................................................................................................... 4 3.1. Pump Test Data.................................................................................................................... 4 3.2. Check Valve Tests ............................................................................................................... 4 4.0 PRECAUTIONS AND LIMITATIONS ....................................................................................... 5 5.0 PREREQUISITES ......................................................................................................................... 6 5.1. Initial Conditions ................................................................................................................. 6 5.2. Test Equipment .................................................................................................................... 7 6.0 PROCEDURE INSTRUCTIONS ................................................................................................. 8 6.1. CCP B Inservice Test Pump Run.......................................................................................... 8 6.2. BGV0605 Open Test And BGV0091 Closure Test ............................................................. 14 6.3. BGV0589 Check Valve Open Test ..................................................................................... 15 7.0 RESTORATION ......................................................................................................................... 18

8.0 REFERENCES

............................................................................................................................ 19 8.1. Implementing ..................................................................................................................... 19 8.2. Developmental ................................................................................................................... 20 9.0 RECORDS ................................................................................................................................... 20 10.0 SUMMARY OF CHANGES ....................................................................................................... 21 ATTACHMENT 1, CCP PBG05B Test Flow Path .................................................................................. 22 ATTACHMENT 2, System Performance Data Sheet ............................................................................... 23 ATTACHMENT 3, CCP B Suction Pressure Calculations ....................................................................... 24 ATTACHMENT 4, Maintenance Rule Functionality Brief ...................................................................... 25

Checklist 1, CCP PBG05B Restoration

OSP-BG-P005B Rev. 048 Page 3 of 25 CONTINUOUS USE CENTRIFUGAL CHARGING PUMP B INSERVICE TEST - GROUP B 1.0 PURPOSE 1.1. This procedure demonstrates the Group B operational readiness of Centrifugal Charging Pump B (CCP B) per APA-ZZ-00356, Pump and Valve Inservice Testing Program. 1.2. This procedure performs the open testing of BGV0095, BGV0589, BGV0605 and the close testing of BGV0091. 1.3. This procedure obtains pump spin up time for use in ITP-ZZ-00004, Response Time Testing Program, on a 36 month cycle. 2.0 SCOPE 2.1. The Group B operational readiness of CCP B is proved by development of a differential pressure between 2400 and 2899 psid on a frequency described in APA-ZZ-00356, Pump and Valve Inservice Testing Program. 2.2. The following check valve tests are performed:

• BGV0095, CCP B DISCH TO SEAL WTR HX CHECK - open safety test

• BGV0589, CCP B DISCH TO SEAL WTR INJ FLTRS HDR CHECK - open safety test

• BGV0605, CCP B DISCH BGFCV0121 UPSTEAM CHECK - open non-safety test

• BGV0091,CCP A DISCH TO SEAL WTR HX CHECK - closed non-safety test 2.3. Pump spin up time is the elapsed time from initiation of the start signal to obtaining a discharge pressure greater than 2405 psig. This response time test is normally performed once per 36 months. 2.4. The Centrifugal Charging Pump B room cooler is checked and documented for an automatic start when the Centrifugal Charging Pump B is started.

OSP-BG-P005B Rev. 048 Page 4 of 25 CONTINUOUS USE 3.0 ACCEPTANCE CRITERIA 3.1. Pump Test Data 3.1.1. Differential pressure is within the Normal Range as specified on Attachment 2, System Performance Data Sheet, per T/S SR 3.5.2.4, T/S SR 3.5.3.1, FSAR 16.1.2.3.1, and FSAR 16.1.2.4.1. 3.1.2. The Centrifugal Charging Pump B Room Cooler automatically starts when the Centrifugal Charging Pump B is started within the requirements of ODP-ZZ-00002, Equipment Status Control. 3.1.3. If pump spin up time is measured, the pump obtains the required discharge pressure from initiation of start signal as specified on Attachment 2. This partially satisfies T/S SR 3.3.2 1.C#10, T/S SR 3.3.2 1.D#10, T/S SR 3.3.2 1.E#10, FSAR 16.3.2.1.1, and FSAR 16.3-2, Table items 2a, 3a and 4a. 3.2. Check Valve Tests 3.2.1. BGV0095, CCP B DISCH TO SEAL WTR HX CHECK, is demonstrated open by pump differential pressure being in the Normal Range as specified on Attachment 2. 3.2.2. BGHV8111, B CCP DISCH MINIFLOW TO SEAL WTR HX ISO, pipe temperature is in the Normal Range as specified on Attachment 2. 3.2.3. BGV0605, CCP B DISCH BGFCV0121 UPSTREAM CHECK, is demonstrated open by initiating flow through the normal charging header as specified on Attachment 2. 3.2.4. BGV0589, CCP B DISCH TO SEAL WTR INJ FLTRS HDR CHECK, is demonstrated open by passing the required seal injection flow as specified on Attachment 2. 3.2.5. BGV0091, CCP A DISCH TO SEAL WTR HX CHECK, is demonstrated closed by meeting back leakage criteria specified on Attachment 2.

OSP-BG-P005B Rev. 048 Page 5 of 25 CONTINUOUS USE 4.0 PRECAUTIONS AND LIMITATIONS 4.1. If performing in MODE 1, 2, or 3, T/S LCO 3.5.2 and FSAR 16.1.2.4 are applicable. 4.2. If performing in MODE 4, 5 or 6, FSAR 16.1.2.3 is applicable. 4.3. If performing in MODE 4, T/S LCO 3.5.3 is applicable. 4.4. A pretest brief should be held to familiarize the appropriate personnel with the required testing this procedure dictates and with the Maintenance Rule Functionality requirements in Attachment 4. 4.5. IF the data falls in the Required Action Range:

4.5.1. The SM/CRS declares the component INOPERABLE and takes the required actions in accordance with Technical Specifications and APA-ZZ-00340, Surveillance Program Administration. 4.5.2. The SM/CRS checks the validity of the data (i.e., by immediately rerunning the test, evaluating test instruments and conditions, conferring with test personnel, or other methods). 4.6. When measured pump test parameters that fall outside the Normal Range have resulted from an identified systematic error such as improper system lineup or inaccurate instrumentation, the test shall be rerun after correcting the error. 4.7. If testing is terminated or temporarily postponed at some point prior to the locked valve being returned to its normal locked position, the altered valve shall be logged in the Locked Component Deviation List per ODP-ZZ-00004, Locked Component Control. 4.8. PBG05B, CCP B, should NOT be run at less than 60 gpm. 4.9. PBG05B, CCP B, should NOT be run at less than 130 gpm for more than 30 minutes. 4.10. RCP Seal injection flow must be maintained between 8 and 13 gpm for each RCP. 4.11. Prior to starting a CCP, the associated Auxiliary Lube Oil Pump should be started per OTN-BG-00001, Chemical And Volume Control System, to ensure proper CCP sleeve bearing lubrication is present before pump loading occurs. [Ref: 8.2.7] 4.12. After a CCP is secured, the associated Auxiliary Lube Oil Pump should be stopped per OTN-BG-00001, Chemical And Volume Control System. [Ref: 8.2.7] 4.13. If testing is required during Cold Shutdown, the reactor vessel should be open to atmosphere.

OSP-BG-P005B Rev. 048 Page 6 of 25 CONTINUOUS USE 4.14. If testing is required with the vessel head installed during Cold Shutdown, the discharge of the charging pump must NOT be opened unless transferring charging pumps for normal charging alignment. FSAR 5.2.2.10.4 [Ref: 8.1.13] 4.15. If CCP B has been made incapable of injection per T/S LCO 3.4.12, then CCP B should be aligned per OSP-BG-00002, Verify One Centrifugal Charging Pump Incapable Of Injection Into RCS. 4.16. If charging is required, then CCP A or the NCP should be in service supplying normal Charging/Seal Injection per OTN-BG-00001, Chemical And Volume Control System. 4.17. An FPIP (based on Master FPIP MFP-00826) should be implemented any time a CCP is run. This requires a Fire Watch to implement compensatory measures due to impact on capability of post fire safe shutdown. 4.18. After pump testing conditions are stable, the pump must be run for at least two (2) minutes prior to taking pump performance data. 5.0 PREREQUISITES 5.1. Initial Conditions 5.1.1. ENSURE SM/CRS has reviewed Technical Specifications for any LCO Action Statements that may be entered should any component tested be declared INOPERABLE. 5.1.2. ENSURE SM/CRS has reviewed the applicable activities and plant conditions which must exist prior to procedure performance. 5.1.3. ENSURE a job brief has been held and the actions in Attachment 4 were discussed with the Maintenance Rule Dedicated Operator. 5.1.4. ENSURE CCP B suction is lined up to the Volume Control Tank or the RWST. 5.1.5. ENSURE the method for communications between Control Room and local operator in pump room has been established. 5.1.6. WHEN plant is in MODE 4 with any RCS cold leg temperature less than or equal to 275°F, MODE 5 or MODE 6 with the reactor vessel head on, ENSURE Cold Over Pressure Mitigation System (COMS) is in effect per T/S LCO 3.4.12. 5.1.7. INFORM RP CCP B will be placed into operation.

OSP-BG-P005B Rev. 048 Page 7 of 25 CONTINUOUS USE NOTE This pump is run on recirc during performance of this procedure, the recirc returns to the suction of all the charging pumps so if boron concentration in this pump differs from RCS then core reactivity will be changed. [Ref: 8.2.1 and 8.2.2] 5.1.8. ENSURE the difference in boron concentrations between the RCS and CCP B is managed per OTN-BG-00001, Chemical And Volume Control System. 5.1.9. ENSURE a flowmeter, supplied by Engineering, is installed on piping upstream of BGV0091, CCP A DISCH TO SEAL WTR HX CHECK, to record back leakage in Section 6.2. 5.1.10. ENSURE a FPIP for PBG05B, CCP B, is in effect. 5.2. Test Equipment 5.2.1. ENSURE the following is available:

• Pyrometer

• Stopwatch, required only if pump spin up time is to be measured

• 25 feet of 3/8" tubing to be used for venting

• Poly vent bottle 5.2.2. ENSURE all M&TE is within their calibration due date and RECORD ID number and calibration due date on Attachment 2. -END OF SECTION-OSP-BG-P005B Rev. 048 Page 8 of 25 CONTINUOUS USE 6.0 PROCEDURE INSTRUCTIONS NOTE When pump spin up time measurement is required, a separate PM0903516 specifying measurement of pump spin up time will be issued, normally once per 36 months. Steps pertaining to measurement of pump spin up time may be marked N/A at all other times. 6.1. CCP B Inservice Test Pump Run CAUTION If COMS is in effect, only one CCP is allowed to be capable of injection to the RCS. 6.1.1. IF COMS is in effect, ENSURE CCP B is aligned in accordance with the applicable section of OSP-BG-00002, Verify One Centrifugal Charging Pump Incapable Of Injection Into RCS. 6.1.2. ENSURE Train B of CCW is in service per OTN-EG-00001, Component Cooling Water System. 6.1.3. RECORD tank to be used on Attachment 2:

• TBG05, CVCS VOL CTRL TK

• TBN01, REFUELING WATER STORAGE TANK

OSP-BG-P005B Rev. 048 Page 9 of 25 CONTINUOUS USE 6.1.4. RECORD initial level for tank being used from applicable indicator listed below on Attachment 2.

a. TBG05, CVCS VOL CTRL TK

• BG LI-185, VCT LVL

• BG LI-112, VCT LEV b. TBN01, REFUELING WATER STORAGE TANK

• BN LI-930, RWST PROT A LEV IND

• BN LI-931, RWST PROT B LEV IND

• BN LI-932, RWST PROT A LEV IND

• BN LI-933, RWST PROT B LEV IND 6.1.5. IF using the VCT, RECORD pressure indicated on BG PI-115, VCT PRESS, from TBG05, CVCS VOL CTRL TK, on Attachment 2. NOTE The Auxiliary Lube Oil Pump should be allowed to run for at least five (5) minutes prior to starting associated CCP. 6.1.6. PLACE BG HIS-2AX, CCP B AUX L-0 PUMP, in AUTO to START PBG03B. 6.1.7. CHECK BG HIS-2AX, CCP B AUX L-0 PUMP, RUN light is on. 6.1.8. Using the appropriate handswitch, ENSURE valves listed below are in their designated position:

• BG HIS-8111, CCP B RECIRC VLV, OPEN

• BG HIS-8357B, CCP B TO RCP SEALS, CLOSED

• EM HIS-8803B, BORON INJ HDR CVCS INLET VLV, CLOSED 6.1.9. Using one of the following, CHECK SGL12B, AUX BLD CCP B RM CLR, status:

• Computer point GLQ0026, CCP RM CLR 12B FAN

• GLHS0192, START/STOP PUSHBUTTON FOR SGL12B 6.1.10. IF SGL12B is running, using GLHS0192, START/STOP PUSHBUTTON FOR SGL12B, STOP SGL12B, AUX BLD CCP B RM CLR.

OSP-BG-P005B Rev. 048 Page 10 of 25 CONTINUOUS USE 6.1.11. IF COMS is in effect, Go To Step 6.1.13. 6.1.12. IF CCP A is supplying charging, PERFORM the following:

a. STATION a Maintenance Rule Dedicated Operator in communication with the Control Room to OPEN BG8483C, CCP B DISCH BGFCV0121 UPSTRM ISO, to restore system to functional should a valid signal occur. b. ENSURE BG8483C, CCP B DISCH BGFCV0121 UPSTRM ISO, is unlocked and closed. [Ref: 8.1.13] 6.1.13. IF NCP is supplying normal charging, PLACE BG FK-121, CCP DISCH FLOW CTRL, in MANUAL and CLOSE BGFCV0121, CVCS CCP A&B DISCH TO REGEN HX FCV. CAUTION Pipe temperature just upstream of BGHV8111, B CCP DISCH MINIFLOW TO SEAL WTR HX ISO, should be continuously monitored for the first five (5) minutes of pump operation. If pipe remains cool after 1 to 2 minutes, it is an indication of no recirculation flow and the pump should be shut off immediately to prevent damage to pump. 6.1.14. Using pyrometer, MEASURE pipe temperature just upstream of BGHV8111, B CCP DISCH MINIFLOW TO SEAL WTR HX ISO, and RECORD on Attachment 2. NOTE Fire Watch is required when CCP is running. 6.1.15. STATION Step 5.1.10 FPIP Fire Watch.

OSP-BG-P005B Rev. 048 Page 11 of 25 CONTINUOUS USE NOTE Steps 6.1.16 and 6.1.17 may be performed concurrently. The Control Room Operator should count down (i.e. 3, 2, 1, mark) to the pump start initiation for the local operator to begin timing. CAUTION Starting the CCP could affect core reactivity due to the recirc flow path going back to the suction of all the pumps. 6.1.16. IF pump spin up time is to be measured using PM0903516, MEASURE the elapsed time from pump start initiation to greater than or equal to 2405 psig indicated on BGPI0119, CVCS CCP B DISCH PRESS IND. 6.1.17. PERFORM one of the following to start the pump:

a. IF OSP-SA-0017B, Train B SIS-CSAS Slave Relay Test, (PM0903412) is being performed concurrently, START CCP B per the instructions in that procedure. b. Using BG HIS-2A, CCP B, START CCP B. 6.1.18. IF performed, RECORD pump spin-up time on PM0903516 and Attachment 2. 6.1.19. PERFORM the following:

• IF SGL12B, AUX BLD CCP B RM CLR, is running CIRCLE Yes on Attachment 2.

• IF SGL12B, AUX BLD CCP B RM CLR, is NOT running, CIRCLE No on Attachment 2 and NOTIFY the SM/CRS to evaluate using ODP-ZZ-00002, Equipment Status Control. 6.1.20. ENSURE BG HIS-2AX, CCP B AUX L-0 PUMP, RUN light is off and the STOP light is on after a reasonable time following start of the CCP. [Ref: 8.2.7] 6.1.21. IF the Aux Lube Oil Pmp remained in service, NOTIFY system engineer. 6.1.22. RECORD BGPI0020, CCP MTR 5B FLTR DISCH L/O PRESS IND, on Attachment 2. 6.1.23. CONTINUE with data collection steps while pipe temperature monitoring is recorded in the next step.

OSP-BG-P005B Rev. 048 Page 12 of 25 CONTINUOUS USE NOTE Normally, the pipe temperature should rise to between 100 and 130°F and stabilize. If CCW temperature is below usual temperature due to cold weather, the pipe temperature may be as much as five (5) degrees below this normal range and is acceptable. [Ref: 8.2.6] CAUTION If pipe remains cool, it is an indication of no recirculation flow and the pump should be stopped immediately. If pipe gets over 160°F, it is an indication of not enough recirculation flow, the pump should be stopped and the recirculation flow path investigated. 6.1.24. At approximately five (5) minute intervals for the first 15 minutes of pump operation, MEASURE pipe temperature just upstream of BGHV8111, CCP B DISCH MINIFLOW ISO VLV, and RECORD on Attachment 2. NOTE Pressure indication may be subject to rapid fluctuations. If this occurs, BGV0093, CCP B SUCT BGPI0188 ROOT, should be slowly closed until readings stabilize prior to recording pressure. 6.1.25. OBTAIN suction pressure from BGPI0188, CCP PMP B SUCTION PRESS IND, and RECORD on Attachment 2. 6.1.26. OBTAIN discharge pressure from BGPI0119, CVCS CCP B DISCH PRESS IND, and RECORD on Attachment 2. 6.1.27. CALCULATE the pump differential pressure by subtracting suction pressure from the discharge pressure and RECORD on Attachment 2. 6.1.28. IF COMS is in effect, PERFORM the following:

• Using BG HIS-2A, CCP B, STOP CCP B.

• RELEASE the Step 5.1.10 FPIP Fire Watch.

OSP-BG-P005B Rev. 048 Page 13 of 25 CONTINUOUS USE 6.1.29. IF CCP A is supplying normal charging, PERFORM the following: a. PLACE BG FK-121, CCP DISCH FLOW CTRL, in MANUAL. b. CONTROL charging flow. c. OPEN and LOCK BG8483C, CCP B DISCH BGFCV0121 UPSTRM ISO. d. RELEASE the Maintenance Rule Dedicated Operator. 6.1.30. IF Section 6.2 and 6.3 will NOT be performed, PERFORM the following: a. Using BG HIS-2A, CCP B, STOP CCP B. b. PLACE BG HIS-2AX, CCP B AUX L-0 PUMP, to the STOP position. c. IF appropriate, TERMINATE the FPIP of Step 5.1.10. d. Go To Section 7.0 RESTORATION. -END OF SECTION-OSP-BG-P005B Rev. 048 Page 14 of 25 CONTINUOUS USE 6.2. BGV0605 Open Test And BGV0091 Closure Test 6.2.1. IF COMS is in effect, ENSURE the appropriate section of OSP-BG-00002, Verify One Centrifugal Charging Pump Incapable Of Injection Into RCS, has been completed to swap charging pump capable of injection to the RCS PRIOR to continuation of this procedure. 6.2.2. INITIATE shifting charging supply from pump currently supplying normal charging to charging supply from CCP B per OTN-BG-00001, Chemical And Volume Control System. 6.2.3. WHEN the shift to CCP B is complete, RECORD flow through BGV0605, CCP B DISCH BGFCV0121 UPSTEAM CHECK, as shown on BG FI-121A, CHG HDR FLOW, on Attachment 2. 6.2.4. RECORD the back leakage through BGV0091, CCP A DISCH TO SEAL WTR HX CHECK, as shown on the flow meter upstream of BGV0091, on Attachment 2. 6.2.5. IF NOT performing Section 6.3, RESTORE charging supply alignment as directed by the SM/CRS per OTN-BG-00001, Chemical And Volume Control System. -END OF SECTION-OSP-BG-P005B Rev. 048 Page 15 of 25 CONTINUOUS USE 6.3. BGV0589 Check Valve Open Test 6.3.1. ENSURE CCP B is supplying normal charging/seal injection per OTN-BG-00001, Chemical And Volume Control System. CAUTION

• IF BGV0100 is allowed to remain closed for more than two (2) minutes, unless Step 6.3.3.a is performed, the reduced charging flow may cause a decrease in pressurizer level that can reduce RCS pressure to less than the LCO 3.4.1.a DNB limit.

• Energizing Pressurizer Heaters will cause an outsurge from the Pressurizer that may result in a reactivity change. 6.3.2. IF a VT2 inspection of BGV0100, CVCS SEAL WTR INJ FLTRS IN ISO, will be performed while it is closed, ENERGIZE a BU Heater group per OTN-BB-00005, Pressurizer and Pressurizer Pressure Control.

OSP-BG-P005B Rev. 048 Page 16 of 25 CONTINUOUS USE NOTE When closing BGV0100, the greatest decrease in RCP seal flow will occur near the end of valve travel. While closing BGV0100, if higher flow letdown orifice is in service and BG HC-182 is throttled closed to maintain seal flow greater than 32 gpm, Pressurizer level may be observed to lower with BGFCV0121 full open. While closing BGV0100 and opening BG HIS-8357B, it will be necessary to monitor and maintain the following parameters using BG HC-182 and BG FK-121 to keep Pressurizer and VCT levels relatively stable:

• Seal flow between 32 and 52 gpm on BG FI-215A or BG FI-215B

• Combined flow on BG FI-121A and BG FI-215A or BG FI-215B maintained greater than 70 gpm to meet CCP minimum flow requirements. When BGV0100 is closed BG FI-121A will indicate charging flow only, and BG FI-215A or BG FI-215B, will indicate RCP seal flow only.

• Pressurizer level within 5 % of program

• Pressurizer pressure 2225 to 2250 psig

• Letdown Regen HX outlet temperature less than 385 ºF on BG TI-127 6.3.3. PERFORM the following steps to provide RCP seal flow through the alternate seal injection line:

a. MONITOR and MAINTAIN parameters listed in the above note. b. Slowly OPEN BG HIS-8357B, CCP B TO RCP SEALS

. c. UNLOCK and CLOSE BGV0100, CVCS SEAL WTR INJ FLTRS IN ISO. d. WHEN BGV0100, CVCS SEAL WTR INJ FLTRS IN ISO, is fully closed, RECORD RCP seal flow using BG FI 215A, CHG PUMP TO RCP SEAL FLOW, or BG FI 215B, CHG PUMP TO RCP SEAL FLOW, on Attachment 2. e. Slowly OPEN BGV0100, CVCS SEAL WTR INJ FLTRS IN ISO. f. Slowly CLOSE BG HIS-8357B, CCP B TO RCP SEALS. g. WHEN Pressurizer level is restored to program, ADJUST BG HC-182, CHG HDR BACK PRESS CTRL, to attain 32 gpm RCP seal flow or as desired on BG FI-215A, CHG PUMP TO RCP SEAL FLOW, or BG FI-215B, CHG PUMP TO RCP SEAL FLOW.

OSP-BG-P005B Rev. 048 Page 17 of 25 CONTINUOUS USE 6.3.4. IF energized per Step 6.3.2, DE-ENERGIZE BU Heaters per OTN-BB-00005, Pressurizer and Pressurizer Pressure Control. 6.3.5. IF ISF-SB-0A33A, SSPS Train B Slave Relay K624, K626, K604, K711, & K743 Test, is to be performed, REQUEST I&C perform the procedure at this time. 6.3.6. ENSURE all pump related test data has been recorded on Attachment 2 AND REVIEWED by the Reactor Operator. 6.3.7. RESTORE charging/seal injection alignment as directed by the SM/CRS per OTN-BG-00001, Chemical And Volume Control System. 6.3.8. IF CCP B is secured, ENSURE the following are performed:

• PLACE BG HIS-2AX, CCP B AUX L-0 PUMP, to the STOP position. [Ref: 8.2.7]

• IF appropriate, TERMINATE the FPIP of Step 5.1.10. -END OF SECTION-OSP-BG-P005B Rev. 048 Page 18 of 25 CONTINUOUS USE 7.0 RESTORATION 7.1. INITIATE restoration of equipment per Checklist 1, CCP PBG05B Restoration. 7.2. INITIATE performance of independent verification of equipment status per Checklist 1, CCP PBG05B Restoration. NOTE Steps 7.3 through 7.8 may be performed in any order. 7.3. At NG02ADR1, FDR BKR TO SGL12B B CCP RM COOLER, using GLHS0192, START/STOP PUSHBUTTON FOR SGL12B, STOP SGL12B. 7.4. IF CCW pumps were started, as directed by the CRS/SM, STOP any CCW pumps that were started to support pump run. 7.5. ENSURE the Actual Value condition is evaluated against the acceptance/functional criteria and that the SM/CRS is immediately notified if the Actual Value condition is out of tolerance. 7.6. IF NCP is supplying normal charging, ENSURE BG FK-121, CCP DISCH FLOW CTRL, is set at 25 % and in AUTO. 7.7. IF both CCPs are secured, ENSURE the CCPs suction is vented per OTN-BG-00001 ADD02, Shifting from one of the CCPs to the NCP. 7.8. UPDATE Status Board for current boron concentration of the CCP. -END OF SECTION-OSP-BG-P005B Rev. 048 Page 19 of 25 CONTINUOUS USE

8.0 REFERENCES

8.1. Implementing 8.1.1. APA-ZZ-00340, Surveillance Program Administration 8.1.2. APA-ZZ-00356, Pump and Valve Inservice Testing Program 8.1.3. ISF-SB-0A33A, SSPS Train B Slave Relay K624, K626, K604, K711, & K743 Test 8.1.4. ITP-ZZ-00004, Response Time Testing Program 8.1.5. ODP-ZZ-00002, Equipment Status Control 8.1.6. ODP-ZZ-00004, Locked Component Control 8.1.7. OSP-BG-00002, Verify One Centrifugal Charging Pump Incapable Of Injection Into RCS 8.1.8. OSP-SA-0017B, Train B SIS-CSAS Slave Relay Test 8.1.9. OTN-BB-00005, Pressurizer and Pressurizer Pressure Control 8.1.10. OTN-BG-00001 ADD02, Shifting from one of the CCPs to the NCP 8.1.11. OTN-BG-00001, Chemical And Volume Control System 8.1.12. OTN-EG-00001, Component Cooling Water System 8.1.13. COMN 1401 8.1.14. FSAR 5.2.2.10.4 8.1.15. FSAR 16.1.2.3 8.1.16. FSAR 16.1.2.3.1 8.1.17. FSAR 16.1.2.4 8.1.18. FSAR 16.1.2.4.1 8.1.19. FSAR 16.3.2.1.1 8.1.20. FSAR 16.3-2, Table items 2a, 3a and 4a 8.1.21. T/S LCO 3.4.12 OSP-BG-P005B Rev. 048 Page 20 of 25 CONTINUOUS USE 8.1.22. T/S LCO 3.5.2 8.1.23. T/S LCO 3.5.3 8.1.24. T/S SR 3.3.2 1.C#10 8.1.25. T/S SR 3.3.2 1.D#10 8.1.26. T/S SR 3.3.2 1.E#10 8.1.27. T/S SR 3.5.2.4 8.1.28. T/S SR 3.5.3.1 8.1.29. Checklist 1, CCP PBG05B Restoration 8.2. Developmental 8.2.1. CARS 199901812 8.2.2. CARS 199903408 8.2.3. CARS 199903524 8.2.4. CARS 200306153 8.2.5. CARS 200402614 8.2.6. CARS 200704247 8.2.7. RFR 016691B 8.2.8. PM0901017 8.2.9. PM0901003 8.2.10. PM0903412 8.2.11. PM0903516 9.0 RECORDS 9.1. Attachment 2, System Performance Data Sheet (Filed with the appropriate Work Authorizing Document.) 9.2. Checklist 1, CCP PBG05B Restoration OSP-BG-P005B Rev. 048 Page 21 of 25 CONTINUOUS USE 10.0 SUMMARY OF CHANGES Page(s) Section or Step Number Description 5 4.5 Combined old Steps 4.5, 4.6, and 4.7 to give clear direction should data fall in the Required Action Range. Per CARS 201206883 6 4.18 Added step about running stable for two minutes before taking pump performance data. Per CARS 201206883

OSP-BG-P005B Rev. 048 Page 22 of 25 CONTINUOUS USE Attachment 1 CCP PBG05B Test Flow Path Sheet 1 of 1

OSP-BG-P005B Rev. 048 Page 23 of 25 CONTINUOUS USE Attachment 2 System Performance Data Sheet Sheet 1 of 1 Person Performing (Print)

Initials/PIN Date Started:

Date Completed:

Tank TBG05 TBN01 Steps 6.1.14 and 6.1.24 (normal temp range is 100 to 130°F)

Step 6.1.18 Calculated Pump Spin-up Time: ______ ( 5 sec)

Time Pipe Temp °F Step 6.1.3 - Tank to be used (

3) T=00 _______ _________

Step 6.1.19 - CCP B Room Cooling Fan started as Step 6.1.4 - Initial Level T+05 _______ _________

required:YES / NO (circle one)

Step 6.1.5 - Initial Press T+10 _______ _________

Step 6.1.22 T+15 _______ _________

Lube Oil Inlet Pressure: BGPI0020 ______ ( 15 psig)

Suction pressure (psig) (Step 6.1.25) Discharge pressure (psig) (Step 6.1.26) Pump Differential Pressure (psid) (Step 6.1.27) Required Action Range (High)

> 2899 Actual Value Normal Range 14.4 to 82.4 2400 to 2899 Required Action Range (Low)

< 2400 Tech Spec Limit 2400 Baseline 44.5 2680 2635.5 Valve Verificatio n Flowrate Step 6.2.3 BGV0605 BGFI0121A Step 6.2.4 BGV0091 Flow meter upstream of BGV0091 < 12 gpm Step 6.3.3.d BGV0589 BGFI0215A or BGFI0215B 32 gpm M&TE Data ID Numbers Cal Due Dates

OSP-BG-P005B Rev. 048 Page 24 of 25 CONTINUOUS USE Attachment 3 CCP B Suction Pressure Calculations Sheet 1 of 1 Per J-24BG40 and J-07P16, BG PI-188 is at 1976' 7 1/2". Instruction manual M-721-0093 gives Net Positive Suction Head (NPSH) required equals 16 feet. M-23BG02 gives pump suction nozzle elevation at 1979' 7". Pump can take suction from the RWST or the VCT. The VCT has the limiting suction pressure characteristics. J-U8000 gives the following setpoints:

VCT Hi Pressure Alarm (BG-PAHL-115) = 65 psig VCT Lo Pressure Alarm (BG-PAHL-115) = 5 psig VCT Hi Level Alarm (BG-LAHL-149) = 97%

VCT Lo Level Alarm (BG-LAHL-149) = 22%

Westinghouse Precautions, Limitations, and Setpoints document (PLS) gives BG- 8120, VCT relief valve, setpoint at 75 psig. M-23BG04 gives VCT full at 2013' 8 3/8". The PLS also states that BG LT-149 is calibrated to a 75" span extending from the lower tap to a point 75" above the lower tap. Per J-24BG12, the lower instrument tap is at 2003' 9 1/2". From this, 97% is calculated to be at 2009' 10 1/4" and 22% to be at 2005' 2". 0-150 psig

+/- 2% FS pressure gauges give

+/- 3 psig accuracy. Add or subtract this as appropriate. Using the above information:

Low Action Range From NPSH required 1979' 7" + 16' - 1976' 7 1/2" = 8.21 psig

-3.0 psig 5.21 psig <5.2 psig Low Alert Range From VCT low alarm for pressure and level 2005' 2" - 1976' 7 1/2" = 27' 2 1/2" =11.78 psig + 5 psig = 17.35 psig

-3.0 psig 14.35 psig 5.2 -14.4 psig High Action Range From maximum VCT level and pressure 2013' 8 3/8" - 1976' 7 1/2' = 35' 8 7/8" = 15.47 psig + 75 psig = 91.00 psig + 3.0 psig 94.00 psig >94.00 psig High Alert Range From VCT high alarm for pressure and level 2009' 10 1/4" - 1976' 7 1/2' = 31' 10 3/4" = 13.8 psig + 65 psig = 79.4 psig + 3.0 psig 82.4 psig 82.4 -94.0 psig Normal Range From Low Alert Range and High Alert Range 14.4-82.4 psi

OSP-BG-P005B Rev. 048 Page 25 of 25 CONTINUOUS USE Attachment 4 Maintenance Rule Functionality Brief Sheet 1 of 1

While Safety Systems are thought of as those systems designed to mitigate design basis accidents, not all mitigating systems have the same risk importance. Those systems that have a higher risk importance are monitored for unavailability time, which is when the system is not functional as related to Maintenance Rule unavailability indicator.

Actions taken to maintain system functionality such as taking credit for actions by the Reactor Operator in the Control Room or a stationed Maintenance Rule Dedicated Operator do NOT make the system operable. Crediting these actions only maintains Maintenance Rule Functionality so the system does not accrue Unavailability hours.

Actions may be credited if they are simple and may be performed in a short time frame. If actions are being credited, and if required to be relieved or leave the area, the operator involved must perform a turnover of the listed functionality actions in event of a valid demand of the system or secure from the test and restore system functionality.

Functionality Actions for OSP-BG-P005B:

Use of a Maintenance Rule Dedicated Operator:

When BG8483C, CCP B DISCH BGFCV0121 UPSTRM ISO, is closed, CCP B is NOT functional unless a Maintenance Rule Dedicated Operator is stationed in the vicinity of BG8483C to restore system to functional should a valid signal occur.

During restoration, the Maintenance Rule Dedicated Operator is released when BG8483C is opened and locked open.

CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE JPM No: RSA-4 rev 1 KSA No: GEN 2.3.4 Revision:

July 2013 KSA Rating:

3.7 Job Title:

SRO Task Title:

Determine Maximum Allowable Stay Time. Validation Time: 12 minutes Learning Objective: T61.01106.C.2, DESCRIBE the management policy regarding radiation exposure as defined in APA

-ZZ-01000, Callaway Plant Radiation Protection Program

The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY

[ ] UNSATISFACTORY

Reason, if UNSATISFACTORY:

Evaluators Signature:

Date:

Task Performer:

Location of Performance:

Control Room Simulator/Lab Plant Classroom X

Method of Performance:

Simulated Performed X

Alternate Path:

___ ___ Time Critical:

___ ___

Student Handouts

RWP 300501 "Routine" Survey CA

-M-20130702-3 "1111 RHR Pump Room Title: A & Pump Platform"

.

References:

RWP 300501 "Routine" Survey CA

-M-20130702-3 "1111 RHR Pump Room Title: A & Pump Platform"

. APA-ZZ-01000 "CALLAWAY ENERGY CENTER RADIATION PROTECTION PROGRAM"

JPM NO: RSA-4, Rev 1 Page 1 of 2 Initial Conditions:

A leak has developed in the RHR Pump "A" room cooler that requires isolating the room cooler

. You have been directed to close RHR Pump "A" room cooler isolation valves EFV0037 and EFV0038.

Initiating Cues:

Determine maximum allowable stay time to close the two valves and isolate the leak before a dosimeter limit is exceeded.

Task Standard:

Stay time identified as 2.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> based upon exceeding maximum dose

.

START TIME:

STOP TIME:

JPM NO: RSA-4, Rev 1 JPM TASK STEP ELEMENT PERFORMANCE STANDARD SCORE Page 2 of 2 1. Reviews RWP and survey maps required for task Provide the applicant with a copy of RWP 300501 "Routine", and Survey CA-M-20130702-3 "1111 RHR Pump Room Title: A & Pump Platform"

. S U Comments:

2. *Identifies the dose limit per the RWP Applicant identified the dose limit per RWP 300501 "Routine" is 11 mrem S U Comments:

3. *Identifies the dose rate near the valves to be operated

. Applicant identified that the dose rate near isolation valves EFV0037 and EFV0038 is 4 mrem/hr S U Comments:

4. *Identifies the maximum stay time Applicant identified the maximum stay time is 2.75 hr or 165 minutes 11 mrem / (4 mrem/hr) =

2.75hr .73333 hr x (60 min/ hr) = 165 minutes S U Comments:

5. The JPM is complete Record stop time on Page 1 S U Comments:

Critical Step

Initial Conditions:

Initial Conditions:

A leak has developed in the RHR Pump "A" room cooler that requires isolating the room cooler

. You have been directed to close RHR Pump "A" room cooler isolation valves EFV0037 and EFV0038.

Initiating Cues:

Determine maximum allowable stay time to close the two valves and isolate the leak before a dosimeter limit is exceeded.

Operations and Radwaste Routine Activities Including WPA, Technician Rounds, and Shipping Activities.

Includes All Activities Previously Assigned to RWP Numbers

200501 OSPPROC and

300501 OSPPROC.

NO ACCESS TO SATELLITE RCA'S ON THIS RWP.

FOR ACCESS TO SATELLITE RCA'S, USE

300501 MISCL.

System Component: VARIOUS

Job Location: RCA

Status: Active

Begin Date: 03/22/2013 00:00

Expire Date:

General Requirements

RP Coverage Type: Intermittent

RWP Type: General

Dose Projection (mrem): 775

Level 2 Brief Required: No

Authorization Required: No

Single Use: No

Electronic Dosimeter Alarm Settings:

Dose: 11 mrem

Rate: 100 mrem/hr

Radiological Conditions

Radiological Condition Comments

Radiological Impact Rating

Dose Rates (mrem/hr)

Contact  :

General Area: See Surveys

Travel Path  :

Contamination (DPM/

100 cm 2

)

Internal  :

External  :

General Area: See Surveys

Radiological conditions vary by

Room/Area.

Airborne radioactivity is not anticipated.

Areas will be posted as required.

Review current survey data and area

postings prior to entry.

3 Page 1 of 3

07/29/2013 07:39

Radiation Work Permit

300501ROUTINE Rev 04

Special Instructions for Workers

Dosimetry:

• OSLD and Electronic Dosimeter.

Protective Clothing/Equipment:

• Full set of Protective Clothing in Contaminated Areas.

• Partial PC's allowed for tours, inspections, and work allowed by RP.

...No climbing, crawling, or kneeling in Partial PCs.

• Lab Coat and Gloves in contaminated Fume Hoods, Sinks, Cabinets, and when handling radioactive

samples except discharge system samples.

Contact RP Prior to:

• Breach, drain, or vent of a contaminated system. (Discuss Noble Gas Release Potential)

• Entry into an area not normally surveyed or accessed.

• Accessing areas greater than

8 ft above floor / work platform.

• Work requiring a change to radiological postings or boundaries.

• Evolutions that will/could change radiological conditions.

• Handling contaminated hoses or vent rigs.

• Opening drums, containers, or other packages of RAM to assess the need for additional Protective

Clothing.

Work Practices:

• Check Electronic Dosimeter every

15 minutes, or more often as needed, to prevent receiving a Dose

Alarm.

• Contain or clean up all liquid leakage.

• Handle drain covers/strainers as contaminated materials.

• Bag or seal contaminated hose ends as soon a practical to prevent contamination spread.

• To access satellite RCA's use RWP

300501 MISCL.

Limitations:

• No entry to Locked High RadiationAreas or High Contamination Areas.

• No entry to Airborne Radioactivity Areas except as follows:

• Entry to posted Airborne Radioactivity Areas is permitted if:

...Area is posted due to Noble Gas.

...Total DAC (per CA

0387

) is <

0.3 DAC Total.

• Contact RP to determine DAC information.

• No Handling items >

5000 mRem/hr.

• No access to Satellite RCA'S on this RWP.

• Use RWP

391120 EMERGENCY for access to RCA during emergencies.

Special Instructions for RP Technician

With failed fuel, large amounts of noble gas can be released while venting primary systems.

...Discuss compensatory actions such as running hoses to ventilation, slower vent rates, etc.

(CAR 200706674

)

Page 2 of 3

07/29/2013 07:39

Radiation Work Permit

300501ROUTINE Rev 04

Special Memos

Level 1

ALARA brief required (pre-work discussion of RWP requirements with RP):

• Shiftly prior to accessing a High Radiation Area.

Access to East RW Yard from RW NE door to perform work requires RP Supervision approval.

Follow requirements of HTP-ZZ-

01203 Section

6.3.3 when accessing Radwaste Yard via RW Northeast door.

Stop, place work in safe condition and Notify RP if:

• Work area dose rates or contamination levels exceed ranges listed in the RWP (or in referenced survey

maps),

exceed ranges discussed in RCA entry briefs, or dose rates exceed

800 mRem/hour.

• Abnormal conditions become evident.

• Scope of work changes.

• Accumulated Dose Alarm is received.

• Unanticipated Dose Rate Alarm or Continuous Dose Rate Alarm is received.

Revision

04

Changed Rate Alarm set point back to

100 mRem/hr.

Page 3 of 3

07/29/2013 07:39

Radiation Work Permit

300501ROUTINE Rev 04

VSDS Standard Map Survey H210.0001 Survey CA-M-20130702-3 General Information 1111 RHR Pump Room A & Pump Platform Title:Survey Date/Time:

07/02/2013 16:00 Survey Type:

Quarterly Counted By:

Lindstrom, Jonathan Lead Surveyor:

Work Order/Task #:

Rx % Pwr:

100%RWP #:300101ROUTINE PIN:100390Approved by: Hurla, Gerald W, 07/03/2013 Status:PIN: 2883 Ready for Review by: Lindstrom, Jonathan, 07/02/2013 PIN: 100390 Dose Rate (DR) Object Prefixes/Suffixes

• = Contact

+ = 30cm Gen Area Gen. Area HS = Hot Spot Dose Rates with Prefixes:

Dose Rates with No Prefixes:

Default Prefixes:

Default Suffixes:

"n" = Neutron

"b" = Beta

"c" = Corrected Postings Legend CA=Contaminated Area RA=Radiation Area Location Description

1. Map Locations File Name Image Description Location Code Bldg/Area Name 1 1111 AB 1974 V1111 RESIDUAL HEAT REMOVAL PUMP ROOM A AB2 1111A AB 1974 V1111A RHR PUMP A PLATFORM AB Instruments Used

1. ModelSerial #TypeInstrument Instrument Inst1 RO-2 ION-4108-HP D2 Model 177 CRM-4150-HP CSurvey #: CA-M-20130702 PDF Generated On: 07/03/2013 15:51 Page 1 of 5 H210.0001 VSDS Standard Map Survey Map: 1Date/Time: 07/02/2013 16:00 Survey #: CA-M-20130702-3 RESIDUAL HEAT REMOVAL PUMP ROOM A DRR changed from 0-70 mRem/hr to 0-30 mRem/hr due to the current dose rates.

Comments:

Quarterly Type:RWP #: 300101ROUTINE Reactor Power = 100%

Symbol Legend (for example only)

Unless otherwise noted, dose rates in mrem/hr.

Air Samples & Wipes SmearsSummary of Highest Readings (All available values may not be listed)4) 6000 dpm/100 cm2/gWipe 3) 4000 cpm/Wipe b/gStatus: Approved by: Hurla, Gerald W, 07/03/2013 Lead Surveyor: Lindstrom, Jonathan Location Code: AB 1974 Bldg/Area Name: 1111 Location

Description:

AB Survey #: CA-M-20130702 PDF Generated On: 07/03/2013 15:51 Page 2 of 5 Image File: V1111 H210.0001 VSDS Standard Map Survey Data Point Details

1. NotesTypeInst.ValueUnitsPositionSurvey #: CA-M-20130702-3 Map: 1 - RESIDUAL HEAT REMOVAL PUMP ROOM A 1DR gN/A2mrem/hr2DR gN/A2.0mrem/hr3DR gN/A2mrem/hr4DR gN/A5mrem/hr5DR gN/A15mrem/hr6DR gN/A7mrem/hr7DR gN/A5mrem/hr8DR gN/A4mrem/hr9DR gN/A4mrem/hr10DR gN/A3mrem/hr11DR gN/A* 14mrem/hrN/A+ 10mrem/hr12DR gN/A2mrem/hr13DR gN/A5mrem/hr14DR gN/A4mrem/hr15DR gN/A5mrem/hr16DR gN/A18mrem/hr17DR gN/A10mrem/hr18DR gN/A4mrem/hr1SmearN/Ab/g <1000dpm/100 cm2 2SmearN/Ab/g <1000dpm/100 cm2 3SmearN/Ab/g 3000dpm/100 cm2 4SmearN/Ab/g 6000dpm/100 cm2 5SmearN/Ab/g <1000dpm/100 cm2 6SmearN/Ab/g <1000dpm/100 cm2 7SmearN/Ab/g <1000dpm/100 cm2 8SmearN/Ab/g <1000dpm/100 cm2 9SmearN/Ab/g 1000dpm/100 cm2 10SmearN/Ab/g <1000dpm/100 cm2 11SmearN/Ab/g <1000dpm/100 cm2 12SmearN/Ab/g <1000dpm/100 cm2 1Wipeb/g 300cpm/Wipe2Wipeb/g 200cpm/Wipe3Wipeb/g 4000cpm/Wipe4Wipeb/g 2000cpm/WipeTextDRR 0-30 mRem/hr HS 1111-1NoteText60/12PostingRACASurvey #: CA-M-20130702 PDF Generated On: 07/03/2013 15:51 Page 3 of 5 Image File: V1111 H210.0001 VSDS Standard Map Survey Map: 2Date/Time: 07/02/2013 16:00 Survey #: CA-M-20130702-3 RHR PUMP A PLATFORM Comments:

Quarterly Type:RWP #: 300101ROUTINE Reactor Power = 100%

Symbol Legend (for example only)

Unless otherwise noted, dose rates in mrem/hr.

Air Samples & Wipes SmearsSummary of Highest Readings (All available values may not be listed)3) <1000 dpm/100 cm2 b/gWipe 1) <100 cpm/Wipe b/gStatus: Approved by: Hurla, Gerald W, 07/03/2013 Lead Surveyor: Lindstrom, Jonathan Location Code: AB 1974 Bldg/Area Name: 1111A Location

Description:

AB Survey #: CA-M-20130702 PDF Generated On: 07/03/2013 15:51 Page 4 of 5 Image File: V1111A H210.0001 VSDS Standard Map Survey Data Point Details

1. NotesTypeInst.ValueUnitsPositionSurvey #: CA-M-20130702-3 Map: 2 - RHR PUMP A PLATFORM 1DR gN/A5mrem/hr2DR gN/A5mrem/hr1SmearN/Ab/g <1000dpm/100 cm2 2SmearN/Ab/g <1000dpm/100 cm2 3SmearN/Ab/g <1000dpm/100 cm2 1Wipeb/g <100cpm/WipeSurvey #: CA-M-20130702 PDF Generated On: 07/03/2013 15:51 Page 5 of 5 Image File: V1111A CALLAWAY ENERGY CENTER JOB PERFORMANCE MEASURE

JPM No: RSA5 KSA No: GEN 2.4.41 Revision:

July 2013 KSA Rating:

4.6 Job Title:

SRO Task Title:

Knowledge of the emergency action level thresholds and classifications:

Initiate RERP implementation to include event classification and initial offsite notification.

Validation Time: No greater than 30 minutes (Time Critical)

Learning Objective: T61.0110, LP

-76, Obj C, Identify initial classifications and potential escalations when plant conditions change and Obj D, For a given Emergency Declaration, demonstrate the use of Sentry computer to make the required notifications

The performance of this task was evaluated against the standards contained in this JPM and determined to be:

[ ] SATISFACTORY

[ ] UNSATISFACTORY Reason, if UNSATISFACTORY:

Evaluators Signature:

Date:

Task Performer:

Location of Performance:

Control Room Simulator/Lab X Plant Classroom

Method of Performance:

Simulated Performed X

Alternate Path: ___ ___ Time Critical:

___ X___

Student Handouts

EIP-ZZ-00102, Emergency Implementing Actions, Rev 48

References:

EIP-ZZ-00101, Classification of Emergencies, Rev 47 EIP-ZZ-00101, ADD 1, EAL Classification Matrix, Rev 3 EIP-ZZ-00102, Emergency Implementing Actions, Rev 48

JPM NO: RSA-5, Rev 1 PAGE 1 of 3 Initial Conditions:

Given the following plant conditions:

The Plant has been at 100% for 3 days following a Refueling Outage Annunciator 76D, SFP LEVEL HILO, alarms EC LI-39A, SFP LEV, is lowering Annunciator 62D, AREA RAD HIHI, alarms

-RE-37, Fuel Pool Bridge Crane Rad, indicates 660 mr/hr and rising

-RE-38, Spent Fuel Pool Area Rad, indicates 630 mr/hr and rising

-RE-27 and 28, Fuel/Aux BLDG Normal Exhaust and Emergency Exhaust System, have risen to their HI HI setpoint and actuated a Fuel Building Ventilation Isolation Signal (FBVIS).

-RE-21B, Unit Vent Air Exh Radiation, indicates radiation level has risen to 6.3 E+7 Ci/sec, and is stable

. Non-essential personnel are evacuated from the Fuel Building Initiating Cue:

You have been provided the combined EAL attachments and directed to determine the Emergency Event Classification, complete the Sentry Notification Form and then perform the notification of off

-site agencies within the required time limits.

This JPM is Time Critical.

(THIS IS A DRILL)

Task Standard:

Upon completion of this JPM, the operator will have determined the event classification to be a Site Area Emergency based on EAL RS 1.1, Offsite dose resulting from an actual or imminent release of gaseous radioactivity exceeds 100 mRem TEDE or 500 mRem thyroid CDE for the actual or projected duration of the release. The operator will then complete the Sentry Notification Form and send it within 15 minutes of the event classification time. Total time shall not exceed 30 minutes but the second 15 minute clock started at the EAL classification time on .

START TIME:

STOP TIME:

JPM NO: RSA-5, Rev 1 JPM TASK STEP ELEMENT PERFORMANCE STANDARD SCORE PAGE 2 of 3 1. Obtain a verified working copy of EIP

-ZZ-00101, Classification of Emergencies, ADD1 Wall Chart, and combined EAL attachments Applicant obtained working copies of procedures S U Comments:

• 2. Using the given conditions and Addendum 1, determine the appropriate emergency classification: Site Area Emergency Applicant declared a Site Area Emergency, RS 1.1, Offsite dose resulting from an actual or imminent release of gaseous radioactivity exceeds 100 mRem TEDE or 500 mRem thyroid CDE for the actual or projected duration of the release.

, within 15 minutes of start S U Comments:

Time of Declaration (Start of new 15 min clock) *3. Notify Facility Personnel Announce the Emergency Classification, the Declaration Time and the Cause EIP-ZZ-00102, ATT 5, EC Flowchart Applicant notified facility personnel S U Comments:

• 4. Notify Onsite Personnel Complete Attachment 1

- Sound the Emergency Alarm EIP-ZZ-00102, ATT 5, EC Flowchart Applicant notified onsite personnel S U Comments:

JPM NO: RSA-5, Rev 1 JPM TASK STEP ELEMENT PERFORMANCE STANDARD SCORE PAGE 3 of 3 *5. Is Emergency an Alert or Higher? EIP-ZZ-00102, ATT 5, EC Flowchart Applicant determined emergency was an Site Area emergency S U Comments:

• 6. Have SAS activate callout per KOA-ZZ-00200 using the appropriate message, if not already activated at a lower classification EIP-ZZ-00102, ATT 5, EC Flowchart Applicant had SAS activate callout per KOA-ZZ-00200. Examiner Cue: SAS has been notified to activate callout S U Comments:

• 7. Is Emergency a General Emergency EIP-ZZ-00102, ATT 5, EC Flowchart Applicant determined emergency was not a General Emergency S U Comments:

• 8. Notify offsite agencies by completing and sending the Sentry notification form EIP-ZZ-00102, ATT 5, EC Flowchart Applicant filled out the Sentry notification form and sent it to the offsite agencies within 15 minutes of completing the EAL classification IAW the key Examiner CUE If asked:

A release evaluation is in progress S U Comments:

Time Notification Sent (Completion time of 2nd 15 min clock)

9. The JPM is complete Record stop time on Page 1 S U Comments:

Critical Step

(THIS IS A DRILL)

Initial Conditions:

Given the following plant conditions:

The Plant has been at 100% for 3 days following a Refueling Outage Annunciator 76D, SFP LEVEL HILO, alarms EC LI-39A, SFP LEV, is lowering Annunciator 62D, AREA RAD HIHI, alarms

-RE-37, Fuel Pool Bridge Crane Rad, indicates 660 mr/hr and rising

-RE-38, Spent Fuel Pool Area Rad, indicates 630 mr/hr and rising

-RE-27 and 28, Fuel/Aux BLDG Normal Exhaust and Emergency Exhaust System, have risen to their HI HI setpoint and actuated a Fuel Building Ventilation Isolation Signal (FBVIS).

-RE-21B, Unit Vent Air Exh Radiation, indicates radiation level has risen to 6.3 E+7 Ci/sec, and is stable

. Non-essential personnel are evacuated from the Fuel Building Initiating Cue:

You have been provided the combined EAL attachments and directed to determine the Emergency Event Classification, complete the Sentry Notification Form and then perform the notification of off

-site agencies within the required time limits.

This JPM is Time Critical.

(THIS IS A DRILL)

Page 1 of 12 INFORMATION USE

EIP-ZZ-00101 CLASSIFICATION OF EMERGENCIES ADMINISTRATIVE CORRECTION Revision: 048

EIP-ZZ-00101 Rev. 048 CLASSIFICATION OF EMERGENCIES TABLE OF CONTENTS Section Page Number Page 2 of 12 INFORMATION USE 1.0 PURPOSE ...................................................................................................................................... 3 2.0 SCOPE ........................................................................................................................................... 3 3.0 RESPONSIBILITIES .................................................................................................................... 3 4.0 PREREQUISITES ......................................................................................................................... 3 5.0 PROCEDURE INSTRUCTIONS ................................................................................................. 4

6.0 REFERENCES

.............................................................................................................................. 8 6.1. Implementing ....................................................................................................................... 8 6.2. Developmental ..................................................................................................................... 8 7.0 RECORDS ................................................................................................................................... 10 8.0 DEFINITIONS ............................................................................................................................ 10 9.0 SUMMARY OF CHANGES ....................................................................................................... 11 ATTACHMENT 1, Emergency Action Level Category / Sub-Category Overview .................................. 12 EIP-ZZ-00101 Addendum 1, Emergency Action Level Classification Matrix EIP-ZZ-00101 Addendum 2, Emergency Action Levels Technical Bases Document

EIP-ZZ-00101 Rev. 048 Page 3 of 12 INFORMATION USE CLASSIFICATION OF EMERGENCIES 1.0 PURPOSE This procedure provides guidelines for classification of emergencies at the Callaway Plant. 2.0 SCOPE 2.1. Establishes indications for determining conditions at which specific emergency classifications are to be declared. 2.2. This procedure is initiated when:

• Alarms, abnormal instrument readings, or reports of conditions that indicate an emergency situation (either real or potential) have occurred.

• A subsequent action step in a plant operating off-normal, or Emergency Procedure which refers to this procedure for classification of the indicated plant conditions. 3.0 RESPONSIBILITIES 3.1. Shift Manager Upon classification of an emergency, assumes the position of Emergency Coordinator and initiates emergency actions including making Protective Action Recommendations to authorities responsible for implementing off-site emergency measures. Assigns on-shift personnel to emergency duties as deemed necessary, and notifies the EDO of the emergency. Continues as Acting Emergency Coordinator until relieved by the EDO. When relieved, the Shift Manager will resume normal duties in directing Plant Operations activities from the Control room. [Ref: 6.2.18, 6.2.8] 3.2. Emergency Coordinator Responsible for directing overall emergency response on-site. Initially, the Shift Manager assumes the responsibilities of Emergency Coordinator. At the ALERT (or higher) emergency classification levels, the EDO will relieve the Shift Manager and assume the Emergency Coordinator duties. The Emergency Coordinator directs the Emergency Response Organization from the TSC after relieving the Shift Manager. [Ref: 6.2.23, 6.2.8] 3.3. Plant Personnel Responsible for immediately reporting any abnormal condition or event to the Shift Manager. 4.0 PREREQUISITES None -END OF SECTION-EIP-ZZ-00101 Rev. 048 Page 4 of 12 INFORMATION USE 5.0 PROCEDURE INSTRUCTIONS NOTE Initial classification should take place as soon as possible but NOT greater then 15 minutes after recognition of initiating conditions. The primary tool for determining the emergency classification level is Emergency Action Level Classification Matrix wall chart (EIP-ZZ-00101 Addendum 1, Emergency Action Level Classification Matrix) located at key locations. The user of the Matrix may (but is not required to) consult EIP-ZZ-00101 Addendum 2, Emergency Action Levels Technical Bases Document in order to obtain additional/clarifying information concerning the EALs under classification consideration. 5.1. Shift Manager - WHEN abnormal or emergency conditions (real or potential) occur, PERFORM the following to ensure that appropriate actions are taken for the safe and proper operation of the plant. [Ref: 6.2.25]

• Use Emergency Procedures.

• Reference EIP-ZZ-SK001, Response to Security Events.

• Update Security.

• Dispatch the Fire Brigade, other personnel.

• Take other actions, as needed. NOTE Instrumentation listed in the Emergency Action Level Classification Matrix wall chart, are the primary means of determining conditions; if these are inoperative, others indications may be substituted. 5.2. Shift Manager - Using indications available (alarms, readings, reports, etc.) and the Emergency Action Level Classification Matrix wall chart, DETERMINE the appropriate emergency classification: [Ref: 6.2.23]

EIP-ZZ-00101 Rev. 048 Page 5 of 12 INFORMATION USE NOTE Emergency Classification can also be based upon projected conditions/indications to ensure adequate measures are taken to mitigate any consequences of the emergency. [Ref: 6.2.22] The majority of the EALs provide very specific thresholds and the Emergency Coordinator must remain alert to events or conditions that lead to the conclusion that exceeding the EAL threshold is imminent. If, in the judgment of the Emergency Coordinator, an imminent situation is at hand, the classification should be made as if the thresholds have been exceeded. While this is particularly prudent at the higher emergency classes (as the early classification may provide for more effective implementation of protective measures), it is nonetheless applicable to all emergency classes. Explicit EALs specifying use of Emergency Coordinator judgment are given in the Hazards and Fission Product Barrier Degradation categories. The plant operating MODE that exists at the time that the event occurs (prior to any protective system or operator action is initiated in response to the condition) should be compared to the MODE applicability of the EALs. If a lower or higher plant-operating MODE is reached before the emergency classification is made, the declaration shall be based on the MODE that existed at the time the event occurred. If additional events occur, the declaration shall be based on the MODE that existed at the time the new event occurred. This logic is applied to determine the plant-operating MODE, EAL categories (C, F, S) and EAL Classification Matrix (Hot/Cold) applicability. 5.2.1. SELECT the applicable EAL Classification Matrix wall chart (Hot for MODES 1, 2, 3 or 4; Cold for MODES 5, 6 or De-fueled). NOTE The left side of the EAL Classification Matrix is identical on both pages of the wall chart, and lists EALs that are applicable under any plant-operating MODE. The right side of the Hot EAL Classification Matrix, lists EALs that are applicable under MODES 1, 2, 3 and 4. The right side of the Cold EAL Classification Matrix lists EALs that are applicable only under MODES 5, 6 and De-fueled. Attachment 1 shows an overview of EAL Classifications and Sub-Classifications. 5.2.2. SCAN the left column of the EAL Classification Matrix and LOCATE the EAL category and subcategory that are most applicable to available indications. 5.2.3. From left-to-right, READ across the category/subcategory row. 5.2.4. FIND the corresponding EAL with the most severe classification level that is appropriate to the actual indication(s). There may be more than one. 5.2.5. REPEAT Steps 5.2.1 through 5.2.4 as necessary to ensure all classifiable EALs are identified.

EIP-ZZ-00101 Rev. 048 Page 6 of 12 INFORMATION USE 5.3. IF extra personnel are desired when NO conditions exist that in his opinion warrant an emergency declaration, the Shift Manager may have the SAS operator ACTIVATE the Emergency Callout System per KOA-ZZ-00200, Activation of the Callaway Plant Emergency Callout System using one of the following messages:

• Message #2 for duty Rapid Responders.

• Message #10 for all available Rapid Responders, ERO Coordinators, and engineers

. 5.4. WHEN conditions exist that in their opinion warrants the declaration, the Emergency Coordinator has the option to DECLARE an UNUSUAL EVENT, ALERT, SITE AREA EMERGENCY or GENERAL EMERGENCY using the Judgment EALs (EAL HU6.1 through HG6.1 or the Table F-1, Fission Product Barrier, Judgment Loss/Potential Loss thresholds.)

NOTE Occasionally, a licensee discovers that a condition existed which met the emergency plan criteria but no emergency was declared and the basis for the emergency class no longer exists at the time of this discovery. This may be due to a rapidly concluded event or an oversight in the emergency classification made during the event or it may be determined during a postevent review. Frequently, in cases of this nature, which were discovered after the fact, licensees have declared the emergency class, immediately terminated the emergency class and then made the appropriate notifications. However, the NRC staff does not consider actual declaration of the emergency class to be necessary in these circumstances; an ENS notification (or an ENS update if the event was previously reported but mis-classified) within one hour of the discovery of the undeclared (or mis-classified) event provides an acceptable alternative. 5.5. DECLARE the most severe emergency classification that corresponds to the condition derived from review of the EAL Classification Matrix. NOTE Initial notifications to State and Local Agencies are required to be initiated and acknowledged within 15-minutes after declaration of the emergency classification. 5.6. Shift Manager/Emergency Coordinator - PERFORM the necessary emergency implementing actions as outlined in EIP-ZZ-00102, Emergency Implementing Actions to ensure the proper response is taken to implement the Callaway Plant Radiological Emergency Response Plan. 5.7. IF necessary, CONTACT the EDO to discuss emergency actions. 5.8. Shift Manager/Emergency Coordinator - RECLASSIFY the emergency as conditions dictate in accordance with this procedure.

EIP-ZZ-00101 Rev. 048 Page 7 of 12 INFORMATION USE 5.9. This procedure may be exited when Event Closeout or Plant Recovery has been declared in accordance with EIP-ZZ-00260, Event Closeout/Plant Recovery. -END OF SECTION-EIP-ZZ-00101 Rev. 048 Page 8 of 12 INFORMATION USE

6.0 REFERENCES

6.1. Implementing 6.1.1. APA-ZZ-01003, Off-Site Dose Calculation Manual 6.1.2. CDP-ZZ-01100, Atmospheric Hazard Control 6.1.3. CDP-ZZ-08100, Post Accident Sampling Guidelines 6.1.4. EIP-ZZ-00101 Addendum 1, Emergency Action Level Classification Matrix 6.1.5. EIP-ZZ-00101 Addendum 2, Emergency Action Levels Technical Bases Document 6.1.6. EIP-ZZ-00102, Emergency Implementing Actions 6.1.7. EIP-ZZ-00260, Event Closeout/Plant Recovery 6.1.8. EIP-ZZ-01211, Management Action Guides for Nuclear Emergencies (MAGNEM) 6.1.9. EIP-ZZ-SK001, Response to Security Events 6.1.10. Emergency operations Procedure E-0 6.1.11. FRC.2, Core Cooling 6.1.12. FRH.1, Heat Sink 6.1.13. HTP-ZZ-07010, Alternate Method to Obtain CHARMS Reading. 6.1.14. KOA-ZZ-00200, Activation of the Callaway Plant Emergency Callout System 6.1.15. ODP-ZZ-00025, Emergency Operating Procedure Usage 6.1.16. OTO-RK-00001, Loss of Control Room Alarms 6.1.17. OTO-SG-00001, Seismic Event 6.1.18. OTO-ZZ-00001, Control Room Inaccessibility 6.1.19. OTO-SK-00001, Plant Security Event - Hostile Intrusion 6.1.20. OTO-SK-00002, Plant Security Event - Aircraft Threat 6.2. Developmental 6.2.1. 10CFR50 Appendix E EIP-ZZ-00101 Rev. 048 Page 9 of 12 INFORMATION USE 6.2.2. 10CFR50.34 6.2.3. 10CFR50.54 6.2.4. APA-ZZ-00703, Fire Protection Operability Criteria and Surveillance Requirements 6.2.5. BB-162 Rev. 000 6.2.6. BB-179 Rev. 000 6.2.7. Callaway Plant Final Safety Analysis Report 6.2.8. Callaway Plant Radiological Emergency Response Plan 6.2.9. Callaway Plant Technical Specifications 6.2.10. Comm. 20606, UNLRC 867 NRC Inspection Report 84010-A8 6.2.11. Comm. 41525, UE letter to NRC - Alert for S/G tube rupture 6.2.12. Comm. 43073, ULNRC 2998 6.2.13. Comm. 50110, EP response actions for security based events 6.2.14. Emergency Action Level (EAL) Descriptions 6.2.15. EPCI-98-01, EAL Bases Calculation 6.2.16. FSAR CN 00-065, GTRE59/60 Alert and High Alarm Computer Setpoints 6.2.17. NEI 99-01, Methodology for Development of Emergency Action Levels 6.2.18. NUREG 0654 Rev 1, Criteria for Preparation and Evaluation of Radiological Response Plans and Support of Nuclear Power Plants 6.2.19. NUREG 1022 Rev. 2, Event Reporting Guidelines 6.2.20. NUREG 0818, Emergency Action Levels for Light Water Reactors 6.2.21. Reg. Guide 1.101, Emergency Planning and Preparedness for Nuclear Power Reactors 6.2.22. RERP Section 4 6.2.23. RERP Section 5.1.1 6.2.24. RERP Section 5.2.1 6.2.25. RERP Section 6.2 EIP-ZZ-00101 Rev. 048 Page 10 of 12 INFORMATION USE 6.2.26. ULNRC 05189 6.2.27. EAL Technical Bases Document 6.2.28. NEI 99-01 Revision 4, Methodology for Development of Emergency Action Levels, January 2003 6.2.29. NUMARC/NESP-007 Rev. 2, Methodology for Development of Emergency Action Levels, "Questions and Answers" 6.2.30. NRC Regulatory Issue Summary (RIS) 2003-18, Supplement 2, Use of Nuclear Energy Institute (NEI) 99-01, Methodology for Development of Emergency Action Levels Revision 4, Dated January 2003 (December 12, 2005) 6.2.31. NRC Bulletin 2005-02 Emergency Preparedness and Response Actions for Security-Based Events 7.0 RECORDS None 8.0 DEFINITIONS Emergency Classifications

• UNUSUAL EVENT - Events are in progress or have occurred which indicate a potential degradation of the level of safety of the plant or indicate a security threat to facility protection has been initiated. No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occurs. [Ref: 6.2.8, 6.2.26, 6.2.13]

• ALERT - Events are in progress or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant or a security event that involves probable life threatening risk to site personnel or damage to site equipment because of Hostile Action. Any releases are expected to be limited to small fractions of the EPA Protective Action Guideline exposure levels. [Ref: 6.2.8, 6.2.26, 6.2.13]

• SITE AREA EMERGENCY - Events are in progress or have occurred which involve an actual or likely major failures of plant functions needed for protection of the public or Hostile Actions that result in intentional damage or malicious acts; (1) toward site personnel or equipment that could lead to the likely failure of or: (2) that prevent effective access to equipment needed for the protection of the public. Any releases are NOT expected to result in exposure levels which exceed EPA Protective Action Guideline exposure levels beyond the site boundary. [Ref: 6.2.8, 6.2.26, 6.2.13]

• GENERAL EMERGENCY - Events are in progress or have occurred which involve actual or imminent substantial core degradation or melting with potential for loss of containment integrity or Hostile Action that result in an actual loss of physical control of the facility. Releases can be reasonably expected to exceed EPA Protective Action Guideline exposure levels offsite for more than the immediate site area. [Ref: 6.2.8, 6.2.26, 6.2.13]

EIP-ZZ-00101 Rev. 048 Page 11 of 12 INFORMATION USE 9.0 SUMMARY OF CHANGES Page(s) Section or Step Number Description 6 Note Added acknowledgement to notification.

EIP-ZZ-00101 Rev. 048 Page 12 of 12 INFORMATION USE Attachment 1 Emergency Action Level Category / Sub-Category Overview Sheet 1 of 1 EAL Category EAL Subcategory Any Operating MODE: R - Abnormal Rad Release / Rad Effluent 1 - Offsite Rad Conditions 2 - Onsite Rad Conditions H - Hazards 1 - Natural & Destructive Phenomena 2 - Fire or Explosion 3 - Toxic, Corrosive, Asphxiant & Flammable Gas 4 - Security 5 - Control Room Evacuation 6 - Judgment Hot Conditions: S - System Malfunction 1 - Loss of Power 2 - RTS Failure 3 - Inability to Reach or Maintain Shutdown Conditions 4 - Instrumentation / Communications 5 - Fuel Clad Degradation 6 - RCS Leakage 7 - Inadvertent Criticality F - Fission Product Barrier Degradation None Cold Conditions: C - Cold Shutdown / Refuel System Malfunction 1 - Loss of Power 2 - RCS Level 3 - RCS Temperature 4 - Communications 5 - RCS Leakage 6 - Inadvertent Criticality 7 - Fuel Clad Degradation

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