Text

AN1-2020-04 Draft Operating Test
	ML20233A922
Person / Time
Site:	Arkansas Nuclear
Issue date:	06/05/2020
From:	Greg Werner; Operations Branch IV
To:	; Entergy Operations
References
	ES-301-1
	Download: ML20233A922 (402)
	v • d • e

ES-301 Administrative Topics Outline Form ES-301-1 Facility: ANO Unit 1 Date of Examination: 3/30/2020 Examination Level: RO SRO Operating Test Number: 1 Administrative Topic (see Note) Type Describe activity to be performed Code*

A1 Calculate Minimum Required Boron to Maintain Conduct of Operations R,D Shutdown Margin K/A - 2.1.43, Importance Rating 4.1 A1JPM-RO-RBAL3 A2 Perform Time to Boil / Core Uncovery Conduct of Operations R,M Estimation K/A - 2.1.25, Importance Rating 3.9 A1JPM-RO-TTB A3 Perform Service Water Surveillance Equipment Control R,N A1JPM-RO-SURV3 K/A - 2.2.12, Importance Rating 3.7 A4 Ability to comply with Radiation Work Permit Radiation Control R,D,P requirements K/A - 2.3.7, Importance Rating 3.5 A1JPM-RO-ADMIN-RWP3 NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

Type Codes and Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs and RO retakes)

(N)ew or (M)odified from bank ( 1)

(P)revious 2 exams ( 1, randomly selected)

ES-301 Administrative Topics Outline Form ES-301-1 Facility: ANO Unit 1 Date of Examination: 3/30/2020 Examination Level: RO SRO Operating Test Number: 1 Administrative Topic (see Note) Type Describe activity to be performed Code*

A5 Review Calculated Minimum Required Boron to Conduct of Operations R,D Maintain Shutdown Margin K/A - 2.1.43, Importance Rating 4.3 A1JPM-SRO-RBAL3 A6 Review Time to Boil / Core Uncovery Estimation Conduct of Operations R,M A1JPM-SRO-TTB K/A - 2.1.25, Importance Rating 4.2 A7 Determine Operability of SW and Apply T.S.

Equipment Control R,N A1JPM-SRO-ADMINSW K/A - 2.2.37, Importance Rating 4.6 A8 Ability to comply with Radiation Work Permit Radiation Control R,D requirements K/A - 2.3.7, Importance Rating 3.6 A1JPM- SRO-ADMIN-RWP3 A9 Classify an Emergency Event Emergency Plan R,N A1JPM-SRO-EAL18 K/A - 2.4.41, Importance Rating 4.6 NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

Type Codes and Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs and RO retakes)

(N)ew or (M)odified from bank ( 1)

(P)revious 2 exams ( 1, randomly selected)

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: ANO Unit 1 Date of Examination: 3/30/2020 Exam Level: RO SRO-I SRO-U Operating Test Number: 1 Control Room Systems: 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U System/JPM Title Type Code* Safety Function S1. Perform RCS Boration BATCH Feed Method D/S 1 004 A4.07 (RO 3.9 / SRO 3.7)

RO S2. Perform actions required for Reactor Building Sump Blockage A/EN/L/N/S 2 006 A2.02 (RO 3.9 / SRO 4.3)

RO / SRO-I / SRO-U S3. Respond to Pressurizer ERV Failure A/L/N/S 3 010 A2.03 (RO 4.1 / SRO 4.2)

RO / SRO-I S4. Initiate Common Feedwater N/L/S 4S E04 EA1.1 (RO 4.4 / SRO 4.2)

RO / SRO-I S5. Place Hydrogen Recombiner M55B in Operation D/L/P/EN/S 5 028 A4.01 (RO 4.0/SRO 4.0)

RO / SRO-I / SRO-U S6. Synchronize and Load #1 EDG with a failure of the load switch A/D/P/S 6 064 A2.05 (RO 3.1 / SRO 3.2)

RO / SRO-I S7. Bypass MSLI L/N/S 7 E02 EA1.1 (RO 4.0 / SRO 3.6)

RO / SRO-I S8. Reactor Building Purge Gaseous Release L/N/S 9 071 A1.06 (RO 2.5 / SRO 2.8)

RO / SRO-I

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 In-Plant Systems:* 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U A/D/L P1. Perform ICS Startup 4S 041 A4.01 (RO 2.9 / SRO 3.1)

RO / SRO-I / SRO-U A/D/E P2. Manual Actuation of Halon System #3 8 086 A4.06 (RO 3.2 / SRO 3.2)

RO / SRO-I / SRO-U L/N/R P3. Perform Decay Heat System Auxiliary Spray Alignment prior to 3 Sump Recirculation 006 A4.05 (RO 3.9 / SRO 3.8)

RO / SRO-I / SRO-U

All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions, all five SRO-U systems must serve different safety functions, and in-plant systems and functions may overlap those tested in the control room.

Type Codes Criteria for R /SRO-I/SRO-U (A)lternate path 5/5 /3 (C)ontrol room (D)irect from bank 5/4/3 (E)mergency or abnormal in-plant 1/1/1 (EN)gineered safety feature 2 / 2 / 2 (control room system)

(L)ow-Power/Shutdown 8/8/3 (N)ew or (M)odified from bank including 1(A) 6/6/3 (P)revious 2 exams 2 / 2 / 1 (randomly selected)

(R)CA 1/1/1 (S)imulator

ADMINISTRATIVE JOB PERFORMANCE MEASURE A1JPM-RO-RBAL3 Page 1 of 6 UNIT: 1 REV # 1 DATE: ______________________________

TUOI NUMBER: A1JPM-RO-RBAL3 SYSTEM/DUTY AREA: ADMINISTRATIVE TOPIC - CONDUCT OF OPERATIONS TASK: ESTIMATE BORON CONCENTRATION REQUIRED TO MAINTAIN SHUTDOWN MARGIN DURING COOLDOWN USING RHOBAL PROGRAM JTA#: ANO1-RO-OPROC-NORM-70 KA VALUE RO: 4.1 SRO: 4.3 KA

REFERENCE:

2.1.43 APPROVED FOR ADMINISTRATION TO: RO: x SRO:

TASK LOCATION: INSIDE CR: OUTSIDE CR:_________ BOTH:____X____

SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE:_______________ SIMULATOR: CLASS ROOM:__PERFORM___

POSITION EVALUATED: RO:___X ___ SRO:___________

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE:____ CLASS ROOM:__X___

TESTING METHOD: SIMULATE:_________ PERFORM:___X______

APPROXIMATE COMPLETION TIME IN MINUTES: 10 MINUTES REFERENCE(S): 1103.015, Rev. 061 and Rhobal computer program EXAMINEE'S NAME:________________________________ LOGON ID ____________________

EVALUATOR'S NAME:__________________________________________________________________

THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:

SATISFACTORY:________________ UNSATISFACTORY:_________________

PERFORMANCE CHECKLIST COMMENTS:

____________ Start Time ____________ Stop Time ____________ Total Time SIGNED _Robert Possage_______________________________ DATE: _______________________

SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.

ADMINISTRATIVE JOB PERFORMANCE MEASURE A1JPM-RO-RBAL3 Page 2 of 6 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall ensure that the examinee has been briefed on NUREG 1021 Appendix E.

JPM INITIAL TASK CONDITIONS: The plant is preparing for shutdown prior to a refueling outage. EFPD = 475. RCS Tave = 555°F. APSR at 0%. Desired final RCS Tave = 185°F Cooldown is scheduled to commence later today.

TASK STANDARD: The examinee has calculated the minimum required Boron concentration to maintain shutdown margin during cooldown using RHOBAL and determined the value to be between 615 to 645 ppm.

TASK PERFORMANCE AIDS: Personal computer with RHOBAL program available.

ADMINISTRATIVE JOB PERFORMANCE MEASURE A1JPM-RO-RBAL3 Page 3 of 6 INITIATING CUE:

The Control Room Supervisor directs you to calculate the Minimum Required Boron concentration to maintain shutdown margin during cooldown using 1103.015, Reactivity Balance Calculation and the RHOBAL program.

(C) PERFORMANCE CHECKLIST STANDARD SAT UNSAT N/A NOTE: Examinee may start in the Poison menu or in the Shutdown Margin menu.

Either way, the examinee must establish a power history.

(C) 1. Activate Shutdown Margin Clicked (or Alt S via keyboard) on pull down menu. on Shutdown Margin in menu ____ ____ ___

bar. _

(C) 2. Run program to determine Performed the following Boron concentration required actions: ____ ____ ___

to maintain shutdown margin.

Clicked on Worksheet 5, _

"Boron Concentration Required to Maintain SDM during Cooldown or Heatup.

Entered 475 for Cycle Burnup in EFPD.

Entered 0 for all CRA positions.

Entered 555 for RCS Average Temperature in degrees F.

Entered 185 for Final Desired RCS Average Temperature in degrees F.

NOTE: Step 3 may be performed prior to step 1 via the Poison menu.

ADMINISTRATIVE JOB PERFORMANCE MEASURE A1JPM-RO-RBAL3 Page 4 of 6 (C) PERFORMANCE CHECKLIST STANDARD SAT UNSAT N/A

3. Activate Xenon and Clicked (or Alt P via keyboard)

Samarium menu. on Xenon and Samarium in ____ ____ ___

menu bar. _

(C) 4. Enter power history. Performed the following actions: ____ ____ ___

Entered 100% Power _

Level

Entered 475 for Burnup

Clicked on At power equilibrium concentrations.

Clicked on INITIALIZE POISONS button.

Close "Xenon and Samarium" menu.

(C) 5. Determine required Boron Noted the required Boron conc concentration. from Table or Figure B6 to be ____ ____ ___

631. _

Accept 615 to 645.

END

ADMINISTRATIVE JOB PERFORMANCE MEASURE A1JPM-RO-RBAL3 Page 5 of 6 KEY JPM INITIAL TASK CONDITIONS:

The plant is preparing for startup after a refueling outage.

EFPD = 475

RCS Tave = 555°F

Final RCS Tave = 185°F

APSR are at 0 %

Cooldown is scheduled to commence later today.

INITIATING CUE:

The SM/CRS directs you to calculate Minimum Required Boron concentration to maintain shutdown margin during heatup using 1103.015, Reactivity Balance Calculation and the RHOBAL program.

____631 (615 - 645)___ ppmB

ADMINISTRATIVE JOB PERFORMANCE MEASURE A1JPM-RO-RBAL3 Page 6 of 6 EXAMINEES COPY JPM INITIAL TASK CONDITIONS:

The plant is preparing for startup after a refueling outage.

EFPD = 475

RCS Tave = 555°F

Final RCS Tave = 185°F

APSR are at 0 %

Cooldown is scheduled to commence later today.

INITIATING CUE:

The SM/CRS directs you to calculate Minimum Required Boron concentration to maintain shutdown margin during heatup using 1103.015, Reactivity Balance Calculation and the RHOBAL program.

__________________________ ppmB

A1JPM-RO-TTB PAGE 1 OF 10 UNIT: 1 REV #: 2 DATE:

SYSTEM/DUTY AREA: Conduct of Operations TASK: Perform Time to Boil and Time to Core Uncovery Calculations JTA#: ANO1-RO-DHR-NORM-204 KA VALUE RO: 3.9 SRO: 4.2 KA

REFERENCE:

2.1.25 APPROVED FOR ADMINISTRATION TO: RO: X SRO:

TASK LOCATION: INSIDE CR: OUTSIDE CR: X BOTH:

SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: SIMULATOR: Classroom: Perform POSITION EVALUATED: RO: X SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: Classroom: X TESTING METHOD: SIMULATE: PERFORM: X APPROXIMATE COMPLETION TIME IN MINUTES: 20 Minutes REFERENCE(S): 1015.002 EXAMINEE'S NAME: Logon EVALUATOR'S NAME:

THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:

SATISFACTORY: UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Stop Total Time Time Time SIGNED: Robert Possage DATE:

SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.

A1JPM-RO-TTB PAGE 2 OF 10 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall ensure that the examinee has been briefed on NUREG 1021 Appendix E.

JPM INITIAL TASK CONDITIONS:

Plant shutdown for refueling.

RCS level is being drained to 376 in preparation for Reactor head removal.

Time after shutdown = 65 hours7.523148e-4 days 0.0181 hours 1.074735e-4 weeks 2.47325e-5 months .

Both OTSG primary manways are removed.

Nozzle dams are NOT installed.

RCS Temperature is 120°F.

Plant computer is inoperable due to power supply maintenance.

TASK STANDARD:

Calculated the following:

1) In step 2.2, used Figure 1 and determined Decay Heat Correction Factor to be 1.28 - 1.32 (1.3 +/- 0.2)

2) In step 3.2, used Figure 2A and determined Time to Boil is 28.8 - 31.0 minutes (29.9 +/- 1.1)

3) In step 4.2, used Figure 4A and determined time to core uncovery is 268.6 - 290.4 minutes (279.5 +/- 10.9)

3) In step 5.2, determined estimated heatup rate to be 2.84 - 3.32 °F/minute (3.08 +/- 0.24)

4) In step 6.0, determined makeup rate to be 65 to 70 gpm. (Graph readability - 68 actual value)

TASK PERFORMANCE AIDS:

1015.002, Decay Heat Removal and LTOP System Control 1015.002B, Calculation of Time to Boil/Core Uncovery Estimate SIMULATOR SETUP:

NA EXAMINER'S NOTES:

A1JPM-RO-TTB PAGE 3 OF 10 INITIATING CUE:

CRS directs you to perform time to boil and time to core uncovery calculations using 1015.002B, Calculation of Time to Boil/Core Uncovery Estimate, through step 6.0.

(C) PERFORMANCE CHECKLIST STANDARD SAT UNSAT N/A NOTE The figures referred to in this form are the figures of, Graphs Used To Determine RCS Time to Boil/Core Uncovery Estimates, Attachment C of this procedure.

1.0 Record the following data: Examinee recorded the data on the paper copy of 1015.002B, (See key) using the initial conditions given ____ ____ ____

on the Examinee Copy. (See key) 2.0 2.1 Decay Heat Correction Examinee recorded 1.0 in the Factor space provided since refueling ____ ____ ____

has not commenced per the Record fraction of spent fuel initial conditions. (See key) assemblies in core______

(obtain from Reactor Engineering) (1.0 if prior to refueling) 2.2 C Using Figure 1 of Attachment Examinee referred to Figure 1 C, Graphs Used To (Page 54 of 135) and determined ____ ____ ____

Determine RCS Time to based on 65 hours7.523148e-4 days 0.0181 hours 1.074735e-4 weeks 2.47325e-5 months after Boil/Core Uncovery shutdown (given in initial Estimates, DETERMINE conditions) the Correction Factor Decay Heat Correction should be 1.3.

Factor Band of 1.28 - 1.32 (See key)

NOTE NOTE Examinee read and place kept Step 5.8 in the definitions Note. Examinee determined the section defines the RCS as RCS is opens since the initial ____ ____ ____

OPEN if a Steam Generator conditions stated both OTSG Primary Manway is removed primary manways are removed.

and unobstructed by filter or ventilating devices.

(See key) 3.1 Using the appropriate figure from Attachment C, OBTAIN Examinee referred to Figure 2A uncorrected Time to Boil. (Page 55 of 135) and determined ____ ____ ____

based on 65 hours7.523148e-4 days 0.0181 hours 1.074735e-4 weeks 2.47325e-5 months after LOG uncorrected Time to shutdown (given in initial Boil: _____________ conditions) the Uncorrected Time to Boil should be 23 minutes.

(See Key)

A1JPM-RO-TTB PAGE 4 OF 10 (C) PERFORMANCE CHECKLIST STANDARD SAT UNSAT N/A 3.2 Multiply by Decay Heat Examinee multiplied 23 value C Correction Factor from step (step 3.1.3) by 1.3 (step 2.2) and ____ ____ ____

2.2: determined time to boil should be 29.9 minutes.

(See key)

(See key) 28.8 - 31.0 minutes (29.9 +/-

1.1) 4.1 Examinee referred to Figure 4A Using the appropriate (Page 59 of 135) and determined figure from Attachment C, based on 65 hours7.523148e-4 days 0.0181 hours 1.074735e-4 weeks 2.47325e-5 months after ____ ____ ____

OBTAIN uncorrected Time shutdown (given in initial To Core Uncovery: conditions) the Uncorrected Time to Core Uncovery RCS Open, RV Head On should be 215 minutes.

LOG uncorrected Time To (See key)

Core Uncovery: __________

210 - 220 minutes (215 +/- 5)

(See key) 4.2 Multiply by Decay Heat Examinee multiplied 215 minutes C

Correction Factor from step (step 4.1.5) by 1.3 (step 2.2) and ____ ____ ____

2.2: determined time to core (See key) uncovery should be 279.5 minutes (See key) 268.6 - 290.4 minutes (279.5 +/-

10.9) 5.1 Using Figure 6 of Attachment Examinee referred to Figure 6 C, DETERMINE uncorrected and determined the Uncorrected heatup rate ______°F/min. RCS Heatup Rate should be 4.0 o ____ ____ ____

F/min.

5.2 Divide by Decay Correction Examinee divided 4 oF/min (step Factor from step 2.2: 5.1) by 1.3 (step 2.2) and C determined heatup rate to be (See key) ____ ____ ____

3.08 °F/minute.

(See key) 2.84 - 3.32 °F/minute (3.08 +/-

0.24) 6.0 Using Figure 7A or 7B of Examinee referred to Figure 7A Attachment C, RECORD (based on initial conditions giving required makeup rate: time after shutdown in hours) and C _________ gpm ____ ____ ____

determined makeup rate to be 68 gpm.

(See key) 65 to 75 gpm

A1JPM-RO-TTB PAGE 5 OF 10 (C) PERFORMANCE CHECKLIST STANDARD SAT UNSAT N/A END

A1JPM-RO-TTB PAGE 6 OF 10 KEY CALCULATION OF RCS TIME TO BOIL/CORE UNCOVERY ESTIMATE PAGE 1 OF 4 1.0 RECORD the following data:

Time after reactor shutdown ___ 65_____ hours or days (CIRCLE one)

RCS level ___376___

RCS Pressure ____0____

o

RCS temperature __120 f___ (referred to as T1 on Att C figures) 2.0 Decay Heat Correction Factor 2.1 RECORD fraction of spent fuel assemblies in core __ 1.0_____

(fraction of spent fuel assemblies in core is obtained from Reactor Engineering or value of 1.0 is used if prior to refueling) 2.2 Using Figure 1 of Attachment C, Graphs Used To Determine RCS Time to Boil/Core Uncovery Estimates, DETERMINE Decay Heat Correction Factor :

Correction Factor Decay Heat Fraction of Spent Fuel =

Correction Factor Assemblies in Core

(___1.3____) = __1.3_____

( 1.0 )

A1JPM-RO-TTB PAGE 7 OF 10 KEY CALCULATION OF RCS TIME TO BOIL/CORE UNCOVERY ESTIMATE PAGE 2 OF 4 NOTE

Reactor Coolant System open is contained in the Definitions section of this procedure.

If the status of the RCS (open or intact) is unknown the RCS will be considered open for Time to Boil determination.

3.0 Determining Time to Boil:

3.1 Using the appropriate figure from Attachment C, OBTAIN uncorrected Time to Boil.

3.1.1 IF RCS is open, THEN USE ONE of the following:

Figure 2A for RCS temp 40°F to 140°F

Figure 2B for RCS temp 140°F to 200°F 3.1.2 IF RCS is intact, THEN USE ONE of the following::

Figure 3A for RCS temp 40°F to 140°F

Figure 3B for RCS temp 140°F to 300°F 3.1.3 LOG uncorrected Time to Boil: ___23______

3.2 MULTIPLY uncorrected Time to Boil by Decay Heat Correction Factor:

Uncorrected Time Decay Heat Time to boil in X =

to Boil in minutes Correction Factor minutes X =

(__23__) (__1.3__) __29.9___

A1JPM-RO-TTB PAGE 8 OF 10 KEY CALCULATION OF RCS TIME TO BOIL/CORE UNCOVERY ESTIMATE PAGE 3 OF 4 4.0 Determining Time To Core Uncovery:

4.1 Using the appropriate figure from Attachment C, OBTAIN uncorrected Time To Core Uncovery:

4.1.1 IF Incore Instrument guide tubes are breached AND RV Head is installed, THEN ASSUME a conservative initial RCS level of 369.5' and USE ONE of the following:

Figure 4A for RCS temp 40°F to 140°F

Figure 4B for RCS temp 140°F to 200°F 4.1.2 IF RCS is open with nozzle dams removed, THEN USE ONE of the following:

Figure 4A for RCS temp 40°F to 140°F

Figure 4B for RCS temp 140°F to 200°F 4.1.3 IF EITHER SG has nozzle dam installed, THEN USE ONE of the following:

Figure 4C for RCS temp 40°F to 140°F

Figure 4D for RCS temp 140°F to 200°F 4.1.4 IF RCS is intact, THEN USE ONE of the following:

Figure 5A for RCS temp 40°F to 140°F

Figure 5B for RCS temp 140°F to 240°F

Figure 5C for RCS temp 240°F to 340°F 4.1.5 LOG uncorrected Time To Core Uncovery: ____215______

4.2 MULTIPLY uncorrected Time To Core Uncovery by Decay Heat Correction Factor:

Uncorrected time to Decay Heat Time to Core Core Uncovery in X Correction Factor = Uncovery in minutes minutes

(_215_) X (_1.3__) = _279.5_

A1JPM-RO-TTB PAGE 9 OF 10 KEY CALCULATION OF RCS TIME TO BOIL/CORE UNCOVERY ESTIMATE PAGE 4 OF 4 5.0 Determining Time To Core Uncovery:

5.1 Using Figure 6 of Attachment C, DETERMINE uncorrected heatup rate

__4.0____°F/min.

5.2 DIVIDE by Decay Heat Correction Factor:

Uncorrected Heatup Rate Estimated Heatup

=

Decay Heat Correction Factor Rate in °F/min

(____4_______) = ___3.08____

( 1.3 )

6.0 Using Figure 7A or 7B of Attachment C, RECORD required makeup rate: __68____ gpm 7.0 IF Time to Boil is significantly less than previous Time to Boil estimate AND in Mode 5 or 6, THEN REEVALUATE ANY containment closure estimates for ALL outstanding items on the Containment Closure Breach List.

8.0 UPDATE the Status Board with the new data.

Performed by _______________________________ Date __________ Time __________

Calculations Reviewed/

Confirmed by CRS or SM: _______________________ Date __________ Time ________

A1JPM-RO-TTB PAGE 10 OF 10 EXAMINEEES COPY JPM INITIAL TASK CONDITIONS:

Given the following Plant conditions:

Plant shutdown for refueling.

RCS level is being drained to 376 in preparation for Reactor head removal.

Time after shutdown = 65 hours7.523148e-4 days 0.0181 hours 1.074735e-4 weeks 2.47325e-5 months .

Both OTSG primary manways are removed.

Nozzle dams are NOT installed.

RCS Temperature is 120°F.

Plant computer is inoperable due to power supply maintenance.

INITIATING CUE:

CRS directs you to perform time to boil and time to core uncovery calculations using Form 1015.002B, Calculation of Time to Boil/Core Uncovery Estimate, through step 6.0.

Document the results on the attached 1015.002B form.

1015.002 page 130 of 135 CALCULATION OF RCS TIME TO BOIL/CORE UNCOVERY ESTIMATE PAGE 1 OF 4 1.0 RECORD the following data:

Time after reactor shutdown __________ hours or days (CIRCLE one)

RCS level __________

RCS Pressure __________

RCS temperature __________ (referred to as T1 on Att C figures) 2.0 Decay Heat Correction Factor 2.1 RECORD fraction of spent fuel assemblies in core __________

(fraction of spent fuel assemblies in core is obtained from Reactor Engineering or value of 1.0 is used if prior to refueling) 2.2 Using Figure 1 of Attachment C, Graphs Used To Determine RCS Time to Boil/Core Uncovery Estimates, DETERMINE Decay Heat Correction Factor :

Correction Factor Decay Heat Fraction of Spent Fuel =

Correction Factor Assemblies in Core

(__________) = ___________

( )

FORM TITLE: FORM NO. REV.

CALCULATION OF TIME TO BOIL/CORE UNCOVERY ESTIMATE 1015.002B 066

1015.002 page 131 of 135 CALCULATION OF RCS TIME TO BOIL/CORE UNCOVERY ESTIMATE PAGE 2 OF 4 NOTE Reactor Coolant System open is contained in the Definitions section of this procedure.

If the status of the RCS (open or intact) is unknown the RCS will be considered open for Time to Boil determination.

3.0 Determining Time to Boil:

3.1 Using the appropriate figure from Attachment C, OBTAIN uncorrected Time to Boil.

3.1.1 IF RCS is open, THEN USE ONE of the following:

Figure 2A for RCS temp 40°F to 140°F Figure 2B for RCS temp 140°F to 200°F 3.1.2 IF RCS is intact, THEN USE ONE of the following::

Figure 3A for RCS temp 40°F to 140°F Figure 3B for RCS temp 140°F to 300°F 3.1.3 LOG uncorrected Time to Boil: _____________

3.2 MULTIPLY uncorrected Time to Boil by Decay Heat Correction Factor:

Uncorrected Time Decay Heat Time to boil in X =

to Boil in minutes Correction Factor minutes X =

(______) (______) ________

FORM TITLE: FORM NO. REV.

CALCULATION OF TIME TO BOIL/CORE UNCOVERY ESTIMATE 1015.002B 066

1015.002 page 132 of 135 CALCULATION OF RCS TIME TO BOIL/CORE UNCOVERY ESTIMATE PAGE 3 OF 4 4.0 Determining Time To Core Uncovery:

4.1 Using the appropriate figure from Attachment C, OBTAIN uncorrected Time To Core Uncovery:

4.1.1 IF Incore Instrument guide tubes are breached AND RV Head is installed, THEN ASSUME a conservative initial RCS level of 369.5' and USE ONE of the following:

Figure 4A for RCS temp 40°F to 140°F Figure 4B for RCS temp 140°F to 200°F 4.1.2 IF RCS is open with nozzle dams removed, THEN USE ONE of the following:

Figure 4A for RCS temp 40°F to 140°F Figure 4B for RCS temp 140°F to 200°F 4.1.3 IF EITHER SG has nozzle dam installed, THEN USE ONE of the following:

Figure 4C for RCS temp 40°F to 140°F Figure 4D for RCS temp 140°F to 200°F 4.1.4 IF RCS is intact, THEN USE ONE of the following:

Figure 5A for RCS temp 40°F to 140°F Figure 5B for RCS temp 140°F to 240°F Figure 5C for RCS temp 240°F to 340°F 4.1.5 LOG uncorrected Time To Core Uncovery: _____________

4.2 MULTIPLY uncorrected Time To Core Uncovery by Decay Heat Correction Factor:

Uncorrected time to Decay Heat Time to Core Core Uncovery in X Correction Factor = Uncovery in minutes minutes

(______) X (______) = ________

FORM TITLE: FORM NO. REV.

CALCULATION OF TIME TO BOIL/CORE UNCOVERY ESTIMATE 1015.002B 066

1015.002 page 133 of 135 CALCULATION OF RCS TIME TO BOIL/CORE UNCOVERY ESTIMATE PAGE 4 OF 4 5.0 Determining Time To Core Uncovery:

5.1 Using Figure 6 of Attachment C, DETERMINE uncorrected heatup rate ______°F/min.

5.2 DIVIDE by Decay Heat Correction Factor:

Uncorrected Heatup Rate Estimated Heatup

=

Decay Heat Correction Factor Rate in F/min

(____________) = ___________

( )

6.0 Using Figure 7A or 7B of Attachment C, RECORD required makeup rate: _________ gpm 7.0 IF Time to Boil is significantly less than previous Time to Boil estimate AND in Mode 5 or 6, THEN REEVALUATE ANY containment closure estimates for ALL outstanding items on the Containment Closure Breach List.

8.0 UPDATE the Status Board with the new data.

Performed by _______________________________ Date __________ Time __________

Calculations Reviewed/

Confirmed by CRS or SM: _______________________ Date __________ Time __________

FORM TITLE: FORM NO. REV.

CALCULATION OF TIME TO BOIL/CORE UNCOVERY ESTIMATE 1015.002B 066

PAGE: 53 of 135 1015.002 DECAY HEAT REMOVAL AND LTOP SYSTEM CONTROL CHANGE: 066 ATTACHMENT C PAGE 1 OF 16 GRAPHS USED TO DETERMINE RCS TIME TO BOIL/CORE UNCOVERY ESTIMATES This attachment is used with Form 1015.002B, Calculation of RCS Time To Boil/Core Uncovery Estimate when required.

Assumptions used in developing the curves are as follows:

Infinite time at 100% power.

All decay heat is transferred to the coolant or core components.

No heat loss from the system.

Surge line volume neglected.

No makeup from outside sources.

Correction shall be made for the fraction of spent fuel assemblies after refueling.

Reactor vessel head is on.

Boiling occurs at or near atmospheric pressure when the RCS is open.

Boiling occurs at 448°F when the RCS is intact.

Index of figures:

Figure 1 Decay Heat Correction Factors Figure 2A Uncorrected Time to Boil; RCS open, 40°F to 140°F Figure 2B Uncorrected Time to Boil; RCS open, 140°F to 200°F Figure 3A Uncorrected Time to Boil; RCS intact, 40°F to 140°F Figure 3B Uncorrected Time to Boil; RCS intact, 140°F to 300°F Figure 4A Uncorrected Time to Core Uncovery; RCS open, 40°F to 140°F Figure 4B Uncorrected Time to Core Uncovery; RCS open, 140°F to 200°F Figure 4C Uncorrected Time to Core Uncovery; RCS open, nozzle dams installed 40°F to 140°F Figure 4D Uncorrected Time to Core Uncovery; RCS open, nozzle dams installed 140°F to 200°F Figure 5A Uncorrected Time to Core Uncovery; RCS intact, 40°F to 140°F Figure 5B Uncorrected Time to Core Uncovery; RCS intact, 140°F to 240°F Figure 5C Uncorrected Time to Core Uncovery; RCS intact, 240°F to 340°F Figure 6 Uncorrected RCS Heatup Rate Figure 7A Required Makeup Rate; Hours after Shutdown Figure 7B Required Makeup Rate; Days after Shutdown

PAGE: 54 of 135 1015.002 DECAY HEAT REMOVAL AND LTOP SYSTEM CONTROL CHANGE: 066 ATTACHMENT C PAGE 2 OF 16 Figure 1 Decay Heat Correction Factors 3.4 3.2 3.0 Time in Days 2.8 2.6 2.4 2.2 Correction Factor 2.0 1.8 1.6 Time in Hours 1.4 1.2 1.0 0.8 0.6 0.4 0 5 10 15 20 25 30 35 40 45 50 55 60 65 70 75 80 85 90 Time After Shutdown

PAGE: 55 of 135 1015.002 DECAY HEAT REMOVAL AND LTOP SYSTEM CONTROL CHANGE: 066 ATTACHMENT C PAGE 3 OF 16 Figure 2A Uncorrected Time to Boil RCS Open 55 o

T1=40 F 50 o

T1=60 F 45 o

40 T1=80 F 35 o T1=100 F Time to Boil (min.)

30 o

T1=120 F 25 o

T1=140 F 20 15 10 5

365 367 369 371 373 375 377 379 381 383 420 385 RCS Level (ft.)

PAGE: 56 of 135 1015.002 DECAY HEAT REMOVAL AND LTOP SYSTEM CONTROL CHANGE: 066 ATTACHMENT C PAGE 4 OF 16 Figure 2B Uncorrected Time to Boil RCS Open 24 22 o T1=140 F 20 18 o

16 T1=160 F Time to Boil (min.)

14 12 o

10 T1=180 F 8

6 o

4 T1=200 F 2

0 365 367 369 371 373 375 377 379 381 383 420 RCS Level (ft.)

PAGE: 57 of 135 1015.002 DECAY HEAT REMOVAL AND LTOP SYSTEM CONTROL CHANGE: 066 ATTACHMENT C PAGE 5 OF 16 Figure 3A Uncorrected Time to Boil RCS Intact 150 o

140 T1=40 F o

T1=60 F 130 o

T1=80 F 120 o

T1=100 F o

110 T1=120 F Time to Boil (min.)

o T1=140 F 100 90 80 70 60 50 40 365 367 369 371 373 375 377 379 381 383 420 RCS Level (ft.)

PAGE: 58 of 135 1015.002 DECAY HEAT REMOVAL AND LTOP SYSTEM CONTROL CHANGE: 066 ATTACHMENT C PAGE 6 OF 16 Figure 3B Uncorrected Time to Boil RCS Intact 110 o

T1=140 F 100 o

T1=160 F 90 o T1=180 F o

80 T1=200 F o

T1=220 F 70 Time to Boil (min.)

o T1=240 F o

60 T1=260 F o

T1=280 F 50 o

T1=300 F 40 30 20 10 365 367 369 371 373 375 377 379 381 383 420 RCS Level (ft.)

PAGE: 59 of 135 1015.002 DECAY HEAT REMOVAL AND LTOP SYSTEM CONTROL CHANGE: 066 ATTACHMENT C PAGE 7 OF 16 FIGURE 4A UNCORRECTED TIME TO CORE UNCOVERY RCS OPEN, RV HEAD ON 650 T1=40 F T1=60 F 600 T1=80 F 550 TIME TO CORE UNCO VERY (10 m inute increm ents) 500 T1=100 F T1=120 F 450 T1=140 F 400 350 300 250 200 150 100 50 0

365 370 375 380 385 390 395 400 405 410 415 420 RCS LEVEL (1 foot increments)

PAGE: 60 of 135 1015.002 DECAY HEAT REMOVAL AND LTOP SYSTEM CONTROL CHANGE: 066 ATTACHMENT C PAGE 8 OF 16 FIGURE 4B UNCORRECTED TIME TO CORE UNCOVERY RCS OPEN, RV HEAD ON 600 T1=140 F 550 T1=160 F 500 T1=200 F TIME TO CORE UNCOVERY (10 minute increments) 450 400 T1=180 F 350 300 250 200 150 100 50 0

365 370 375 380 385 390 395 400 405 410 415 420 RCS LEVEL (1 foot increments)

PAGE: 61 of 135 1015.002 DECAY HEAT REMOVAL AND LTOP SYSTEM CONTROL CHANGE: 066 ATTACHMENT C PAGE 9 OF 16 Figure 4C Uncorrected Time to Core Uncovery RCS Open, Nozzle Dams Installed 500 o

T1=40 F o

T1=60 F 400 T1=80oF o

T1=100 F Time to Core Uncovery (min.)

300 T1=120oF o

T1=140 F 200 100 0

365 375 385 395 405 RCS Level (ft.)

PAGE: 62 of 135 1015.002 DECAY HEAT REMOVAL AND LTOP SYSTEM CONTROL CHANGE: 066 ATTACHMENT C PAGE 10 OF 16 Figure 4D Uncorrected Time to Core Uncovery RCS Open, Nozzle Dams Installed 400 o

T1=140 F o

T1=160 F 300 T1=200oF Time to Core Uncovery (min.)

o T1=180 F 200 100 0

365 375 385 395 405 RCS Level (ft.)

PAGE: 63 of 135 1015.002 DECAY HEAT REMOVAL AND LTOP SYSTEM CONTROL CHANGE: 066 ATTACHMENT C PAGE 11 OF 16 FIGURE 5A UNCORRECTED TIME TO CORE UNCOVERY RCS INTACT, RV HEAD ON 800 750 700 650 TIME TO CORE UNCOVERY (10 minute increments) 600 T1=40 F 550 T1=60 F 500 450 T1=80 F T1=100 F 400 350 T1=120 F 300 T1= 140 F 250 200 150 100 50 0

360 365 370 375 380 385 390 395 400 405 410 415 420 RCS LEVEL (1 foot increments)

PAGE: 64 of 135 1015.002 DECAY HEAT REMOVAL AND LTOP SYSTEM CONTROL CHANGE: 066 ATTACHMENT C PAGE 12 OF 16 FIGURE 5B UNCORRECTED TIME TO CORE UNCOVERY RCS INTACT, RV HEAD ON 700 650 600 550 TIME TO CORE UNCOVERY (10 minute increments) 500 T1=140 F 450 T1=160 F 400 T1=180 F 350 T1=200 F 300 T1=220 F 250 T1=240 F 200 150 100 50 0

360 365 370 375 380 385 390 395 400 405 410 415 420 RCS LEVEL (1 foot increments)

PAGE: 65 of 135 1015.002 DECAY HEAT REMOVAL AND LTOP SYSTEM CONTROL CHANGE: 066 ATTACHMENT C PAGE 13 OF 16 FIGURE 5C UNCORRECTED TIME TO CORE UNCOVERY RCS INTACT, RV HEAD ON 600 T1=240 F 550 500 T IM E T O C O R E U N C O V E R Y (10 m inu te increm e nts) 450 400 T1=260 F T1=280 F 350 T1=300 F 300 T1=320 F 250 T1=340 F 200 150 100 50 0

360 365 370 375 380 385 390 395 400 405 410 415 420 RCS LEVEL (1 foot increments)

PAGE: 66 of 135 1015.002 DECAY HEAT REMOVAL AND LTOP SYSTEM CONTROL CHANGE: 066 ATTACHMENT C PAGE 14 OF 16 Figure 6 Uncorrected RCS Heatup Rate 10.0 9.0 o

T1=400 F 8.0 o T1=300 F o

T1=200 F 7.0 o

T1=100 F RCS Heatup Rate ( F/min.)

6.0 o

5.0 4.0 3.0 2.0 1.0 0.0 365 367 369 371 373 375 377 379 381 383 420 RCS Level (ft.)

PAGE: 67 of 135 1015.002 DECAY HEAT REMOVAL AND LTOP SYSTEM CONTROL CHANGE: 066 ATTACHMENT C PAGE 15 OF 16 Figure 7A Required Makeup Rate 260 240 220 200 Required Makeup (gpm) 180 160 RCS Pressure = 0 psig 140 RCS Pressure = 100 psig RCS Pressure = 200 psig 120 RCS Pressure = 300 psig RCS Pressure = 400 psig 100 RCS Pressure = 500 psig 80 60 0 10 20 30 40 50 60 70 80 90 100 Hours After Shutdown

PAGE: 68 of 135 1015.002 DECAY HEAT REMOVAL AND LTOP SYSTEM CONTROL CHANGE: 066 ATTACHMENT C PAGE 16 OF 16 Figure 7B Required Makeup Rate 120 110 100 90 Required Makeup (gpm) 80 70 RCS Pressure = 0 psig RCS Pressure = 100 psig 60 RCS Pressure = 200 psig RCS Pressure = 300 psig 50 RCS Pressure = 400 psig RCS Pressure = 500 psig 40 30 20 0 10 20 30 40 50 60 70 80 90 100 Days After Shutdown

A1JPM-RO-SURV3 PAGE 1 OF 4 UNIT: 1 REV #: 0 DATE:

SYSTEM/DUTY AREA: Equipment Control TASK: Perform Service Water Pump Test (P-4A/B/C)

JTA#: ANO1-RO-SWACW-SURV-43 KA VALUE RO: 3.7 SRO: 4.1 KA

REFERENCE:

2.2.12 APPROVED FOR ADMINISTRATION TO: RO: X SRO:

TASK LOCATION: INSIDE CR: OUTSIDE CR: BOTH: X SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: SIMULATOR: CLASSROOM: Perform POSITION EVALUATED: RO: X SRO:

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE: CLASSROOM: X TESTING METHOD: SIMULATE: PERFORM:

APPROXIMATE COMPLETION TIME IN MINUTES: 15 Minutes REFERENCE(S): 1104.029 EXAMINEE'S NAME: LOGON:

EVALUATOR'S NAME:

THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:

SATISFACTORY: UNSATISFACTORY:

PERFORMANCE CHECKLIST COMMENTS:

Start Stop Total Time Time Time SIGNED: Robert Possage DATE:

SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.

A1JPM-RO-SURV3 PAGE 2 OF 4 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall ensure that the applicant has been briefed on NUREG 1021 Appendix E.

JPM INITIAL TASK CONDITIONS:

Plant is shutdown with refueling in progress.

1104.029 Supplement 1 in progress completed up to Step 2.13 P-4A has been running for 3 minutes.

TASK STANDARD:

Calculated / Perform the following:

1) P-4A actual differential pressure of 87.5 psid (86.5 to 88.5 psid)

2) P-4A baseline differential pressure of 97.5 psid (96 to 98 psid)

3) Circled NO in Table 3 TASK PERFORMANCE AIDS:

1104.029 Supplement 1 SIMULATOR SETUP:

NA EXAMINER'S NOTES:

A1JPM-RO-SURV3 PAGE 3 OF 4 INITIATING CUE:

CRS directs you to perform Steps 2.14 - 2.20 and any actions required by Section 3.0.

PERFORMANCE CHECKLIST STANDARDS SAT UNSAT N/A NOTE: Provide examinee with a copy of the in progress surveillance.

1. Applicant reviewed 1104.029, Review 1104.029, Supplement 1. ____ ____ ____

Supplement 1.

2. Applicant calculates Actual Pump Calculate Actual Pump Diff Diff Pressure using Table 2 Data (C) Pressure using data from and equation provided in ____ ____ ____

Table 2 and record value in 1104.0029 supplement 1.

Table 3.

80 psig + 7.5 psig = 87.5 psig

3. Applicant Plots calculated diff Plot test value on P-4A Pump pressure value on P-4A Pump Curve. Curve. ____ ____ ____

4.

Find the value of Baseline Applicant Finds baseline Pump Diff Press and record Differential pressure using SW in Table 3. Loop 1 flow from Table 2 and ____ ____ ____

P-4A Pump Curve.

5.

Calculate P-4A Deviation Applicant Calculates Deviation (C) from Baseline and Record in from Baseline using provided Table 3. equation in 1104.029 supplement 1.

97.5 psid - 87.5 psid = 10 psid 6.

(C) Evaluate P-4A Actual Pump Applicant circles NO on Table 3 Differential Pressure, for Data Within Limiting Range.

compare to LIMITING RANGE FOR OPERABILITY

7. Applicant may discuss declaring Complete Section 3.0 pump inoperable, notifying SM, writing Condition Report, initiating corrective action, and referring to ____ ____ ____

Tech Specs.

NOTE:

The SM or CRS will consult Tech Specs; it is the ROs responsibility to report the inoperability of P-4A only. Service Water operability will be determined by the SM/CRS.

Inform the Applicant that steps 2.21 - 2.49 will be completed by another operator.

A1JPM-RO-SURV3 PAGE 4 OF 4 PERFORMANCE CHECKLIST STANDARDS SAT UNSAT N/A NOTE: Provide examinee with a copy of the in progress surveillance.

END EXAMINEEES COPY JPM INITIAL TASK CONDITIONS:

Given the following Plant conditions:

Plant is shutdown with refueling in progress.

Service Water Pump P-4A Test in accordance with 1104.029 Supplement 1 is in progress, completed through step 2.13.

P-4A has been running for 3 minutes.

INITIATING CUE:

CRS directs you to perform Steps 2.14 - 2.20 and any actions required by Section 3.0.

2.21 through 2.49 will be completed by another operator.

PAGE: 311 of 551 1104.029 SERVICE WATER AND AUXILIARY COOLING SYSTEM CHANGE: 120 SUPPLEMENT I PAGE 9 OF 27 KEY

2. WHEN flow has been stable for at least two minutes, THEN:

COMMENCE P-4A Motor Bearing vibration data collection per Vibrometer Data sheet.

RECORD the following Measured Values in Table 2:

Loop I Press: SPDS/Alt Test Inst Loop I Press: P1-3608 SW Loop I Flow: SPDS/ALT Test Inst A SW Bay Level: SPDS Suction Pressure: SPDS Local Discharge Press: Local P1-3611/Alt Test Inst 2.14 CALCULATE Actual Pump Duff Pressure (APA) using the following values as recorded in Table 2:

Local Disch Press + Suction Pressure LPA 80 + 7.5 87.5 2.15 RECORD Actual Pump Duff Pressure (t.PA) in Table 3.

2.16 Using Actual Pump Duff Press (APA) and SW Loop I Flow, PLOT test value on P-4A Pump Curve.

2.17 Using the Baseline on the P-4A Pump Curve and using SW Loop I Flow, FIND the value of Baseline Pump Duff Press (APB).

2.18 RECORD Baseline Pump Duff Press (tXPB) in Table 3.

PAGE: 312of551 1104.029 SERVICE WATER AND AUXILIARY COOLING SYSTEM CHANGE: 120 SUPPLEMENT I PAGE 10 OF 27 KEY NOTE P-4A Deviation From Baseline could be a negative number. For trending purposes, the negative sign is included.

2.19 CALCULATE P-4A Deviation From Baseline using data from Table 3:

. P-4A Deviation psi)

(APa (APA psi)

From Baseline

=

97.5 87.5 10 2.20 RECORD P-4A Deviation From Baseline in Table 3 including negative sign, if applicable.

NOTE Bearing temperature is considered stable when three consecutive readings at ten-minute intervals vary no more than 3%.

¶ IE this test is to prove operability after significant maintenance, THEN:

2.21.1 CONTINUE test until motor bearing temperatures are stable.

2.21.2 RECORD stable motor bearing temperatures in Table 4.

IE this test is NQI being performed to prove operability after significant maintenance, THEN MARK motor bearing temperatures in Table 4 N/A.

2.23 WHEN P-4A Motor Bearing vibration data is collected, THEN RECORD data in Table 5.

I 1104.029 SERVICE WATER AND AUXILIARY COOLING SYSTEM PAGE: 323 of 551 CHANGE: 120 L

SUPPLEMENT I PAGE 21 OF 27 KEY TABLE 2 Test Quantity Instrument Measured Acceptable Limiting Range Is Data Within Values Normal Range For Operability Limiting Range SW Loop I Press Alt Test_Inst 7$. 6 psig N/A N/A N/A P 1-3608 L psig SW Loop I Flow Anst tJ2 N/A N/A N/A SPD A SW Bay Level Callevel 33, LI feet N/A > 332 feet Suction Press Cled N/A N/A N/A tion_Pres Local Discharge Press Local P1-361 ltrestmf N/A N/A N/A psig Table 2 data gathered by: initial date KEY TABLE 3 Test quantity Measured Acceptable I Limiting Range Is Data Within Values Normal Range For Operability Limiting Range?

Actual Pump Duff Press Acceptable Normal and Limiting Range (APA) 87.5 values are per P-4A Pump Curve YES NO Baseline Pump Duff Press (APe) 97.5 psi N/A N/A N/A P-4A Deviation From psi N/A Baseline 10 N/A N/A Table 3 data gathered by: initial date TABLE 4 Test Quantity Measured Acceptable Limiting Range Is Data Within Instrument Values Normal Range For Operability Limiting Range Mtr Upper Brg TE-3651 Temp (P1284 or TR-3651) il/A °F <180°F N/A N/A MtrLowerBrg TE-3652 Temp (P1285 or TR-3651) °F <180°F N/A N/A Table 4 data gathered by: initial dZ

PAGE: 325 of 551 1104.029 SERVICE WATER AND AUXILIARY COOLING SYSTEM CHANGE: 120 SUPPLEMENT I PAGE 23 OF 27 KEY TABLE 9 Test Measured Acceptable Limiting Valve DES# Normal Range If within Direction Stroke Time Value for Initial Date (nearest 1/10 sec) Limiting (sec) Operability Value SG-5 Close sec 147.1 - 199.0 225.0 SG-1 Open sec 154.0-208.2 235.4 (__j SG-3 Open sec 157.9-213.7 241.5 (..J CV-3644 Open sec 48.0 64.8

- 73.3 (__)

CV-3646 Open sec 39.2 53.0

- 59.9 (__J 3.6 IF NO is circled in Table 2, 3 or 5, THEN:

DECLARE P-4A inoperable.

NOTIFY the Shift Manager.

INITIATE a Condition Report.

INITIATE corrective action.

REFERENCE Tech Spec for applicable conditions.

3.7 i.E ANY measured value in Table 2, 3, 4 or 5 does NOT fall within the Acceptable Normal Range, THEN INITIATE corrective action.

PAGE: 327 of 551 1104.029 SERVICE WATER AND AUXILIARY COOLING SYSTEM CHANGE: 120 SUPPLEMENT I KEY PAGE 25 OF 27 P-4A Pump Curve 115 Baseline iting 110

- Aceptable Normal Range Limiting Range 105 Comprehensive Limit 100 95 90 NN 0

a 85 rtingj I Range I NNN E

a-80 75 70 EEEEEEIEE 65 4ç 60 55 z::z:::::z::z:::::::N 50 4000 4500 5000 5500 6000 6500 7000 7500 Pump Flow (gpm)

PAGE: 303 of 551 1104.029 SERVICE WATER AND AUXILIARY COOLING SYSTEM CHANGE: 120 SUPPLEMENT I PAGE 1 OF 27 SERVICE WATER PUMP P-4A TEST

{4.2.2}

This test demonstrates operability of Service Water Pump (P-4A) and its discharge check valve by running the pump at rated flow and exercising the check valve. This test also demonstrates operability of SW system flow path motor-operated valves by exercising the valves a complete cycle and measuring stroke times to required safety function positions. This test satisfies ANO 1ST program requirements 10 CFR 50.55a(f). Reference Values for 1ST Components are contained in Appendix B. 18-month testing requirements are contained in Supp. 8.

This supplement tests both red and green train components. Test method has been evaluated and determined to be acceptable.

The steps in this section may be performeGfrrder with the substeps performed in the order specified.

1.0 INITIAL CONDITIONS CHECK the purpose of this test:

fr43 Regularly scheduled quarterly test B) Operability test following significant maintenance (DESCRIBE maintenance performed in section 4.0).

C) Other (DESCRIBE in section 4.0).

IF test is to prove operability following significant maintenance, THEN NOTIFY System Engineer to determine necessity to perform Attachment C Service Water Pump Reference Values Determination.

1. ffi during this test a valve stroke time is .4QI within Acceptable Normal Range AND stroke time is within Limiting Value for Operability, THEN prior to changing system alignment, REFER TO Appendix A, Operability, Failure of Valve Stroke to Meet Acceptable Normal Range and PERFORM ONE of the following:

RETEST valve.

DECLARE valve inoperable.

Ør ENSURE system aligned per 3305.001, Ops System Alignment Tests, System Alignment Confirmation section.

CHECK motor oil level per Service Water Pump Motor P-4AIB/C Lube Oil Check, Exhibit J of 1107.001, Electrical System Operations.

OBTAIN vibrometer from Predictive Maintenance Lab.

W RECORD vibrometer M&TE# and Cal Due Date in Acceptance Criteria, section 3.0, at Table 5.

PAGE: 304 of 551 1104.029 SERVICE WATER AND AUXILIARY COOLING SYSTEM CHANGE: 120 SUPPLEMENT I PAGE 2 OF 27 ENSURE two currently calibrated stopwatches available.

RECORD stopwatch DES# and cal due date in section 3.0.

WHEN timing valve strokes, THEN:

IDENTIFY the stopwatch providing stroke time.

RECORD initial and date.

If test data taken under proper test conditionside the Limiting Range for Operability, the component being tested is declared inoperable for conservatism, even if instrument mis-calibration is suspected.

I.E SPDS is specified in instrument column for recording test data and SPDS instrumentation is NOT available, THEN PERFORM EITHER of the following:

POSTPONE this surveillance.

INSTALL appropriate alternate instruments.

IF alternate test instruments are used for an instrument other than local discharge pressure indicator, THEN:

1.10.1 ENSURE test instrument(s) meet the following requirements:

Calibration is current.

Test instrument accuracy is +/-2% of full scale or better.

Range of Analog test instrument is less than 3 times normal process value.

Range of Digital test instrument is scaled so that normal process value remains less than 70% of full scale.

1.10.2 OBTAIN Independent Verification instrument(s) meet the requirements stated above for:

Cal Due Date

Accuracy

Range I.V. by:

PAGE: 305 of 551 1104.029 SERVICE WATER AND AUXILIARY COOLING SYSTEM CHANGE: 120 SUPPLEMENT I PAGE 3 OF 27 4A10.3 ENSURE instrument column in section 3.0 is annotated to show the instrument number used and the cal due date.

1.10.4 ENSURE alternate instrument use is documented with appropriate explanation of reason(s) in Supervisor Review and Analysis section.

1.10.5 INSTALL alternate test instrument(s) at SPDS transmitter local instrument connection.

1.10.6 OBTAIN independent verification instrument(s) is(are) installed at SPDS transmitter local instrument connection.

l.V. by 1.10.7 WHEN alternate test instrument(s) are aligned, THEN MAINTAIN instruments attended.

IF SW Pump P-4A Disch Press (P1-3611) is unavailable, THEN:

1.11.1 OBTAIN alternate analog test instrument meeting the following requirements:

Calibration is current.

Test instrument accuracy

+/-0.5% of full scale or better for pump dP (suction, discharge).

Range of ANALOG test instrument is less than 3 times normal process value.

1.11.2 OBTAIN independent verification instrument(s) meet the requirements stated above for:

Cal due date

Accuracy

Range l.V. by

PAGE: 306 of 551 1104.029 SERVICE WATER AND AUXILIARY COOLING SYSTEM CHANGE: 120 SUPPLEMENT I PAGE 4 OF 27 4b41 1.3 RECORD alternate test instrument M&TE number and cal due date in step 3.0.

1.11.4 ANNOTATE in Supervisor Review and Analysis section, alternate test instrument used for pump discharge pressure for gauge unavailable, etc.

1.11.5 INSTALL alternate test instrument as follows:

A. ENSURE test connection valve between SW Pump P-4A Discharge PS-361 I Isol (SW-361 1 E) and PS-361 I closed.

B. INSTALL alternate test instrument at test connection between SW Pump P-4A Discharge PS-3611 Isol (SW-361 I E) and PS-3611.

C. POSITION alternate test instrument at same elevation as SW Pump P-4A Disch Press (P1-3611).

1.11.6 OBTAIN independent verification of alternate test instrument installation.

l.V. by 1.11.7 WHEN alternate test instrument(s) are aligned, THEN MAINTAIN instruments attended.

NOTIFY the following that dual train (red and green) testing will be performed during the performance of this supplement:

If manned, CCC.

If manned, CRSA.

Shift Manager or Operations Management.

PAGE: 307 of 551 I 104.029 SERVICE WATER AND AUXILIARY COOLING SYSTEM CHANGE: 120 SUPPLEMENT I PAGE 5 OF 27 2.0 TEST METHOD ENSURE A and B SW bays crosstied via A/B SW Bay Crosstie (SG-3) and aligned to the lake via Lake Supply to A SW Bay (SG-1).

IE C SW bay is in service AND aligned to the lake via Lake Supply to C SW Bay (SG-2)

AND B/C SW Bay Crosstie (SG-4) available, THEN ENSURE SG-4 is open.

ENSURE the following valves are open to cross-connect SW loops at ICW coolers:

Loop I Supply to ICW Coolers (CV-3820)

Loop II Supply to ICW Coolers (CV-3811)

SW Loops I & II Crossconnect (SW-5)

SW Loops I & II Crossconnect (SW-6)

IF SW Pump (P-4A) is NOT in service, THEN:

2.4.1 ENSURE SW Pump P-4B to P-4C Crossties open:

P-4B to P-4C Crosstie (CV-3640)

P-4B to P-4C Crosstie (CV-3642) 2.4.2 if desired by CRS/SM to minimize SW Pressure rise due to starting third SW Pump, THEN PERFORM ONE or more of the following:

A. if adjusting SW pressure with SW-4026A, THEN:

1. RECORD as-found percent open indication:

2. THROTTLE SW-4026A to obtain SW Loop pressures 65 to 85 psig.

3. RECORD as-left SW-4026A percent open indication:

B if adjusting SW pressure with SW-4026B, THEN while counting turns, THROTTLE SW-4026B to obtain SW Loop pressures 65 to 85 psig.

RECORD number of turns operated:

C. jf CRS desires to place additional SW loads into service, THEN RECORD additional SW loads:

PAGE: 308 of 551 1104.029 SERVICE WATER AND AUXILIARY COOLING SYSTEM CHANGE: 120 SUPPLEMENT I PAGE 6 OF 27 MAKE a plant announcement that a Service Water pump will be started.

2.4.4 START SW Pump (P-4A).

2.4.5 CHECK P-4A packing leakoff.

2.4.6 IF ALL 3 service water pumps are operating, THEN:

A. STOP SW Pump (P-4B).

B. CHECK for reverse rotation of SW Pump (P-4B).

C. IF reverse rotation indicated, THEN:

1. MAKE an entry in Category E/Locked Component Log for P-4B Disch Isol (SW-2B).

2. UNLOCK and CLOSE P-4B Disch Isol (SW-2B).

3. DECLARE SW Pump (P-4B) and P-4B Disch Ck (SW-1B) inoperable.

4. REFER TO Technical Specifications.

D. NOTIFY Chemistry to stop Chemical Injection to B SW Bay.

2.4.7 IF SW pressure adjustment was performed in step 2.4.2 AND CRS desires to make SW pressure adjustment, THEN PERFORM ONE of the following to restore SW pressure:

A. IF adjusting SW pressure with SW-4026A, THEN:

1. THROTTLE SW-4026A to obtain SW Loop pressures 65 to 85 psig.

2. RECORD as-left SW-4026A percent open indication:

B. if adjusting SW pressure with SW-4026B, THEN while counting turns, THROTTLE SW-4026B to obtain SW Loop pressures 65 to 85 psig.

. RECORD number of tums operated:

C. IF CRS desires to remove additional SW loads from service, THEN RECORD SW loads removed:

PAGE: 309 of 551 1104.029 SERVICE WATER AND AUXILIARY COOLING SYSTEM CHANGE: 120 SUPPLEMENT I PAGE 7 OF 27 48 if SW Pump (P-4A) will remain in service at the completion of this test, THEN NOTIFY Chemistry to realign Chemical Injection.

Stroke test of Loop II Supply to ICW Coolers (CV-381 1):

While measuring stroke time, CLOSE CV-381 1.

RECORD CV-381 1 closing stroke time in Table 1.

OPEN Loop II Supply to ICW Coolers (CV-381 1).

NOTE Normally, P-4A to P-4B Crossties (CV-3644 and CV-3646) are open and steps 2.7 and 2.8 will be marked N/A.

¶ IF P-4A to P-4B Crosstie (CV-3644) is closed, THEN PERFORM the following to stroke test CV-3644 open:

2.7.1 While measuring stroke time, OPEN CV-3644.

2.7.2 RECORD CV-3644 opening stroke time in Table 9.

IF P-4A to P-4B Crosstie (CV-3646) is closed, THEN PERFORM the following to stroke test CV-3646 open:

2.8.1 While measuring stroke time, OPEN CV-3646.

2.8.2 RECORD CV-3646 opening stroke time in Table 9.

Closed stroke test of P-4A to P-4B Crosstie (CV-3646)

While measuring stroke time, CLOSE CV-3646.

RECORD CV-3646 closing stroke time in Table 1:

Closed stroke test of P-4A to P-4B Crosstie (CV-3644):

While measuring stroke time, CLOSE CV-3644.

RECORD CV-3644 closing stroke time in Table 1:

PAGE: 310 of 551 1104.029 SERVICE WATER AND AUXILIARY COOLING SYSTEM CHANGE: 120 SUPPLEMENT I PAGE 8 OF 27 Actual SW/ACW flow of less than 1500 gpmwiuse SPDS flow indication to indicate 0 gpm.

From SPDS Diagnostic Display or SPDS point F3902, CHECK SW Loop I flow is 4000 gpm or greater.

IF SW Loop I flow is less than 4000 gpm, THEN:

A. IF RB Cooling will be placed into service to raise SW Loop I flow, THEN CHECK Service Water biocide injection system in service (allowed exception: system unavailable with lake temperature less than 60°F or greater than 80°F).

B. PLACE idle load(s) into service to raise SW Loop I flow to 4000 gpm or greater.

I 1. LIST load(s) placed into service below:

C. IF additional load(s) are added, THEN:

1. MONITOR component temperatures closely.

2. ADJUST cooling water flows as necessary. 4 IF alternate test instrument is installed for SW Pump P-4A Disch Press (P1-3611),

THEN:

2.12.1 OPEN test connection valve isolating disch press alternate test instrument at PS-361 1.

2.12.2 MAINTAIN alternate test instrument attended unless isolated.

PAGE: 311 of 551 1104.029 SERVICE WATER AND AUXILIARY COOLING SYSTEM CHANGE: 120 SUPPLEMENT I PAGE 9 OF 27

2. WHEN flow has been stable for at least two minutes, THEN:

COMMENCE P-4A Motor Bearing vibration data collection per Vibrometer Data sheet.

RECORD the following Measured Values in Table 2:

Loop I Press: SPDS/Alt Test Inst Loop I Press: P1-3608 SW Loop I Flow: SPDS/ALT Test Inst A SW Bay Level: SPDS Suction Pressure: SPDS Local Discharge Press: Local P1-3611/Alt Test Inst 2.14 CALCULATE Actual Pump Duff Pressure (APA) using the following values as recorded in Table 2:

Local Disch Press + Suction Pressure LPA

+

2.15 RECORD Actual Pump Duff Pressure (t.PA) in Table 3.

2.16 Using Actual Pump Duff Press (APA) and SW Loop I Flow, PLOT test value on P-4A Pump Curve.

2.17 Using the Baseline on the P-4A Pump Curve and using SW Loop I Flow, FIND the value of Baseline Pump Duff Press (APB).

2.18 RECORD Baseline Pump Duff Press (tXPB) in Table 3.

PAGE: 312of551 1104.029 SERVICE WATER AND AUXILIARY COOLING SYSTEM CHANGE: 120 SUPPLEMENT I PAGE 10 OF 27 NOTE P-4A Deviation From Baseline could be a negative number. For trending purposes, the negative sign is included.

2.19 CALCULATE P-4A Deviation From Baseline using data from Table 3:

. P-4A Deviation psi)

(APa (APA psi)

From Baseline

=

2.20 RECORD P-4A Deviation From Baseline in Table 3 including negative sign, if applicable.

NOTE Bearing temperature is considered stable when three consecutive readings at ten-minute intervals vary no more than 3%.

¶ IE this test is to prove operability after significant maintenance, THEN:

2.21.1 CONTINUE test until motor bearing temperatures are stable.

2.21.2 RECORD stable motor bearing temperatures in Table 4.

IE this test is NQI being performed to prove operability after significant maintenance, THEN MARK motor bearing temperatures in Table 4 N/A.

2.23 WHEN P-4A Motor Bearing vibration data is collected, THEN RECORD data in Table 5.

PAGE: 313of 551 1104.029 SERVICE WATER AND AUXILIARY COOLING SYSTEM CHANGE: 120 SUPPLEMENT I PAGE 11 OF 27 2.24 CHECK SW Loop I flow 5600 gpm or greater.

2.24.1 IF SW Loop I flow is less than 5600 gpm, THEN:

A. IF RB Cooling will be placed into service to raise SW Loop I flow, THEN CHECK Service Water biocide injection system in service (allowed exception: system unavailable with lake temperature is less than 60°F or greater than 80°F).

B. PLACE idle load(s) into service to raise SW Loop I flow to 5600 gpm or greater.

1. LIST load(s) placed into service below:

C. IF additional load(s) are added, THEN:

1. MONITOR component temperatures closely. p

2. ADJUST cooling water flows as necessary.

2.25 RECORD the following:

Open stroking of P-4A Disch Ck (SW-lA) in Table 6.

Flow rate: gpm

Flow instrument:

2.26 IF additional load(s) were added in order to raise SW flow for this test, THEN RESTORE load(s) listed in steps 2.11.1.B and 2.24.1.B to original status.

PAGE: 314 of 551 1104.029 SERVICE WATER AND AUXILIARY COOLING SYSTEM CHANGE: 120 SUPPLEMENT I PAGE 12 OF 27 2.27 Closed stroke test of A/B SW Bay Crosstie (SG-3):

NOTE Any delay during the performance of the following series of steps could result in lowering B SW Bay level.

CAUTION With SW Bay Level starting at 332 feet or less and SW Flow 8000 gpm or greater, SW pump NPSH limits could be exceeded during suction transfer from Lake to Pond. This could result in pump damage.

2.27.1 ENSURE A and B SW Bay Levels are above 332 feet.

2.27.2 While measuring stroke time, CLOSE SG-3.

2.27.3 jf SW Pump P-4B is in service AND B/C SW Bay Crosstie (SG-4) is closed, THEN OPEN Pond Supply to B SW Bay (SG-6).

2.27.4 RECORD SG-3 closing stroke time in Table 7.

NOTE Any delay during the performance of the following series of steps will result in lowering A SW Bay level.

2.28 Closed stroke test of Lake Supply to A SW Bay (SG-1):

2.28.1 While measuring stroke time, CLOSE SG-1.

2.28.2 RECORD SG-1 closing stroke time in Table 7.

SUPPLEMENT I PAGE 13 OF 27 NOTE Aligning a SW Pump suction to Emergency Cooling Pond will cause the ECP level to drop.

2.29 Open stroke test of Pond Supply to A SW Bay (SG-5):

2.29.1 While measuring stroke time, OPEN SG-5.

2.29.2 IF SG-5 fails to operate, THEN:

A. PERFORM ONE of the following:

OPEN Lake Supply to A SW Bay (SG-1).

OPEN A/B SW Bay Crosstie (SG-3).

B. E Pond Supply to B SW Bay (SG-6) is closed, THEN ENSURE B/C SW Bay Crosstie (SG-4) open.

2.29.3 RECORD SG-5 open stroke time in Table 7.

CAUTION Sediment can enter pump suction when going on Emergency Cooling Pond.

I 2.30 MONITOR SW Pump (P-4A) discharge pressure and strainer AP while in this configuration.

2.31 WHEN 15 minutes of operation on Emergency Cooling Pond has elapsed, THEN RECORD the following:

A SW Bay Level on ECP in Table 8.

Loop I flow from either SPDS Diagnostic Display or SPDS point F3902.

SW Loop I flow gpm

PAGE: 316 of 551 1104.029 SERVICE WATER AND AUXILIARY COOLING SYSTEM CHANGE: 120 SUPPLEMENT I PAGE 14 OF 27 NOTE Any delay during the performance of the following series of steps will result in lowering A SW Bay level.

2.32 Closed stroke test of Pond Supply to A SW Bay (SG-5):

2.32.1 While measuring stroke time, CLOSE SG-5.

2.23.2 RECORD SG-5 close stroke time in Table 9.

2.33 Open stroke test of Lake Supply to A SW Bay (SG-1):

2.33.1 While measuring stroke time, OPEN SG-1.

2.33.2 IF SG-1 fails to operate, THEN:

A. PERFORM ONE of the following:

OPEN Pond Supply to A SW Bay (SG-5).

OPEN A/B SW Bay Crosstie (SG-3).

B. IF Pond Supply to B SW Bay (SG-6) is closed, THEN ENSURE B/C SW Bay Crosstie (SG-4) open.

2.33.3 RECORD SG-1 open stroke time in Table 9.

NOTE Any delay during the performance of the following series of steps will result in lowering B SW Bay level.

2.34 Open stroke test of A/B SW Bay Crosstie (SG-3):

2.34.1 E SW Pump (P-4B) is in service supplied from the ECP, THEN CLOSE Pond Supply to B SW Bay (SG-6).

2.34.2 While measuring stroke time, OPEN SG-3.

2.34.3 RECORD SG-3 open stroke time in Table 9.

2.35 ffl P-4A to P-4B Crosstie (CV-3644) was N.QI open stroke tested in step 2.7, THEN:

2.35.1 While measuring stroke time, OPEN CV-3644.

2.35.2 RECORD CV-3644 opening stroke time in Table 9.

PAGE: 317 of 551 1104.029 SERVICE WATER AND AUXILIARY COOLING SYSTEM CHANGE: 120 SUPPLEMENT I PAGE 15 OF 27 2.36 E P-4A to P-4B Crosstie (CV-3646) was 4.QI open stroke tested in step 2.8, THEN:

2.36.1 While measuring stroke time, OPEN CV-3646.

2.36.2 RECORD CV-3646 opening stroke time in Table 9.

2.37 ENSURE P-4A to P-4B Crosstie valves open:

P-4A to P-4B Crosstie (CV-3644)

P-4A to P-4B Crosstie (CV-3646)

NOTE Powering SW Pumps P-4B and P-4C from opposite buses satisfies Tech Spec requirements for train separation.

CAUTION If three SW pumps are operating due to high SW system heat loads, a delay in the subsequent steps to restart SW Pump P-4A can cause overheating of SW system loads.

2.38 IF in Mode 14 AND SW Pumps P-4B and P-4C are operable, THEN:

2.38.1 CHECK P4B Bus Select MOD Control selected to A3.

2.38.2 IF P4B Bus Select MOD Control selected to A4, THEN:

A. ENSURE SW Pump P-4C in service.

B. ENSURE SW Pump P-4B is secured.

C. ENSURE BOTH SW Pump P-4B supply breakers are open:

On C18, A-303 indicates open

On C16, A-403 indicates open D. TRANSFER P4B Bus Select MOD Control to A3.

E. PERFORM 1107.002, ES Electrical System Operation, Transfer MCC B55156 to B5 section.

PAGE: 318of 551 1104.029 SERVICE WATER AND AUXILIARY COOLING SYSTEM CHANGE: 120 SUPPLEMENT I PAGE 16 OF 27 2.38.3 IF desired by CRS/SM to minimize SW Pressure rise due to starting third SW Pump, THEN PERFORM ONE or more of the following:

A. jf adjusting SW pressure with SW-4026A, THEN:

1. RECORD as-found percent open indication:

2. THROTTLE SW-4026A to obtain SW Loop pressures 65 to 85 psig.

3. RECORD as-left SW-4026A percent open indication:

B ffl adjusting SW pressure with SW-4026B, THEN while counting turns, THROTTLE SW-4026B to obtain SW Loop pressures 65 to 85 psig.

. RECORD number of turns operated:

C. IE CRS desires to place additional SW loads into service, THEN RECORD additional SW loads:

2.38.4 ENSURE SW Pumps P-4B and P-4C in service.

2.38.5 ENSURE SW Crosstie valves open:

P-4A to P-4B Crosstie (CV-3644)

P-4A to P-4B Crosstie (CV-3646)

P-4B to P-4C Crosstie (CV-3640)

P-4B to P-4C Crosstie (CV-3642)

PAGE: 319 of 551 1104.029 SERVICE WATER AND AUXILIARY COOLING SYSTEM CHANGE: 120 SUPPLEMENT I PAGE 17 OF 27 NOTE Stopping of P-4A pump shaft confirms seating of P-4A Disch Check (SW-IA).

2.38.6 STOP SW Pump (P-4A).

2.38.7 CHECK SW Pump (P-4A) shaft stops.

2.38.8 IF reverse rotation indicated, THEN:

A. MAKE an entry in Category E/Locked Component Log for P-4A Disch Isol (SW-2A).

B. UNLOCK and CLOSE P-4A Disch Isol (SW-2A).

C. DECLARE SW Pump (P-4A) and P-4A Disch Ck (SW-lA) inoperable.

D. REFER TO Technical Specifications.

2.38.9 RECORD closing of P-4A Disch Ck (SW-lA) in Table 6.

2.38.10 IF desired by CRS/SM, THEN RESTART SW Pump (P-4A).

NOTE In Mode 5, 6 or defueled, only one SW pump is required to be operating.

2.39 IF plant is in Mode 5, 6 or defueled AND plant conditions allow stopping P-4A, THEN PERFORM the following to stop P-4A:

2.39.1 IF in Mode 6, THEN REFER TO Refueling Operations (TS 3.9) to determine SW pump requirements.

2.39.2 IF a single SW Pump will be in operation in the subsequent steps, THEN CHECK SW flow is less than 8000 gpm.

2.39.3 ENSURE SW Pump P-4B or P-4C in service.

PAGE: 320 of 551 1104.029 SERVICE WATER AND AUXILIARY COOLING SYSTEM CHANGE: 120 SUPPLEMENT I PAGE 18 OF 27 2.39.4 ENSURE SW Crosstie valves open:

P-4A to P-.4B Crosstie (CV-3644)

P-4A to P-4B Crosstie (CV-3646)

P-4B to P-4C Crosstie (CV-3640)

P-4B to P-4C Crosstie (CV-3642)

NOTE Stopping of P-4A pump shaft confirms seating of P-4A Disch Check (SW-lA).

2.39.5 STOP SW Pump (P-4A).

2.39.6 CHECK SW Pump (P-4A) shaft stops.

2.39.7 E reverse rotation indicated, THEN:

A. MAKE an entry in Category E/Locked Component Log for P-4A Disch lsol (SW-2A).

B. UNLOCK and CLOSE P-4A Disch Isol (SW-2A).

C. DECLARE SW Pump (P-4A) and P-4A Disch Ck (SW-lA) inoperable.

D. REFER TO Technical Specifications.

2.39.8 RECORD closing of P-4A Disch Check (SW-IA) in Table 6.

2.39.9 if desired by CRS/SM, THEN RESTART SW Pump (P-4A).

2.40 if plant is in Mode 5, 6 or defueled AND plant conditions prevent stopping P-4A, THEN:

MARK SW-lA closure N/A in Table 6.

INITIATE a Condition Report to document that SW-IA requires 1ST stroke.

2.41 RETURN system to desired pump configuration per Pump Rotation section of this procedure.

2.42 ENSURE that sluice gates and cross-ties are aligned as required by Table 9.1.4 of this procedure.

PAGE: 321 of 551 1104.029 SERVICE WATER AND AUXILIARY COOLING SYSTEM CHANGE: 120 SUPPLEMENT I PAGE 19 OF 27 2.43 IE SW pressure adjustment was performed in step 2.38.3 AND CRS desires to make SW pressure adjustment, THEN PERFORM ONE or more ot the following to restore SW pressure:

2.43.1 jf adjusting SW pressure with SW-4026A, THEN:

A. THROTTLE SW-4026A to obtain SW Loop pressures 65 to 85 psig.

B. RECORD as-left SW-4026A percent open indication:

2.43.2 E adjusting SW pressure with SW-4026B, THEN while counting turns, THROTTLE SW-4026B to obtain SW Loop pressures 65 to 85 psig.

. RECORD number of turns operated:

2.43.3 IF CRS desires to remove additional SW loads from service, THEN RECORD SW loads removed:

2.44 ffi alternate test instrument installed for P-4A Disch Press (P1-361 1),

THEN:

2.44.1 ENSURE test connection valve between SW Pump P-4A Discharge PS-36 11 Isol (SW-361 I E) and PS-36 11 closed.

2.44.2 REMOVE test instrument.

2.44.3 ENSURE SW-361 IE is open.

2.45 IF alternate test instruments are installed, THEN REMOVE alternate test instruments.

Independent Verification by 2.46 SRO REVIEW ALL calculations and CONFIRM correct.

Reviewed and confirmed by:

2.47 RECORD and REVIEW required trend data.

Recorded and reviewed by:

2.48 IF trend graphs are available, THEN ATTACH copies of graphs.

2.49 UPDATE plant risk software to reflect final SW system alignments (including SW Pump P-4B power alignment).

PAGE: 322 of 551 1104.029 SERVICE WATER AND AUXILIARY COOLING SYSTEM CHANGE: 120 SUPPLEMENT I PAGE 20 OF 27 3.0 ACCEPTANCE CRITERIA 3.1 RECORD Stopwatch information:

DES #: 041S Cal Due Date DES#: 05/ Cal Due Date 3.2 COMPARE Measured Values/Stroke Times with Acceptable Normal Range and Limiting Value for Operability.

3.3 IDENTIFY if Measured Value/Stroke Time is within Limiting Value for Operability.

3.4 if alternate test instrument is used for discharge pressure, THEN RECORD alternate test instrument info below:

M&TE # iLl/A Cal Due Date 3.5 COMPARE measured values observed during P-4A testing with Acceptable Normal Range and Limiting Value for Operability.

I 1104.029 SERVICE WATER AND AUXILIARY COOLING SYSTEM PAGE: 323 of 551 CHANGE: 120 L

SUPPLEMENT I PAGE 21 OF 27 TABLE 2 Test Quantity Instrument Measured Acceptable Limiting Range Is Data Within Values Normal Range For Operability Limiting Range SW Loop I Press Alt Test_Inst 7$. 6 psig N/A N/A N/A P 1-3608 L psig SW Loop I Flow Anst tJ2 N/A N/A N/A SPD A SW Bay Level Callevel 33, LI feet N/A > 332 feet Suction Press Cled N/A N/A N/A tion_Pres Local Discharge Press Local P1-361 ltrestmf N/A N/A N/A psig Table 2 data gathered by: initial date TABLE 3 Test quantity Measured Acceptable I Limiting Range Is Data Within Values Normal Range For Operability Limiting Range?

Actual Pump Duff Press Acceptable Normal and Limiting Range (APA) values are per P-4A Pump Curve YES NO Baseline Pump Duff Press (APe)

N/A N/A N/A psi P-4A Deviation From Baseline psi N/A N/A N/A Table 3 data gathered by: initial date TABLE 4 Test Quantity Measured Acceptable Limiting Range Is Data Within Instrument Values Normal Range For Operability Limiting Range Mtr Upper Brg TE-3651 Temp (P1284 or TR-3651) il/A °F <180°F N/A N/A MtrLowerBrg TE-3652 Temp (P1285 or TR-3651) °F <180°F N/A N/A Table 4 data gathered by: initial dZ

PAGE: 324 of 551 1104.029 SERVICE WATER AND AUXILIARY COOLING SYSTEM CHANGE: 120 SUPPLEMENT I PAGE 22 OF 27 Vibrometer M&TE # Cal Due Date TABLE 5 Test Quantity Measured Acceptable Limiting Range Is Data Within Location Values Normal Range For Operability Limiting Range?

Motor Radial Point 1 on Upper Brg Vib Motor Map <0.287 in/sec <0.69 in/sec YES NO in/sec Motor Radial Point 2 on Upper Brg Vib Motor Map <0.325 in/sec <0.7 in/sec YES NO in/sec Motor Axial Point 3 on Upper Brg Vib Motor Map <0.242 in/sec <0.582 in/sec YES NO in/sec Table 5 data gathered by: initial date TABLE 6 Test Limiting Value (V) If Within Limiting Valve Initial Date Direction For Operability Range Full stroke confirmed by SW-lA Open SWLooplflow (J S600gpm SW-lA Closureconfirmedby Closed P-4A pump_shaft_stopping TABLE 7 Measured Acceptable Limiting Test (v) If within Valve DES# Stroke Time Normal Range Value for Initial Date Direction Limiting Value (nearest 1/10 sec) (sec) Operability SG-3 Close sec 151.8 205.4

- 232.2 (J SG-1 Close sec 151.2 204.5

- 231.2 (J SG-5 Open sec 147.7 - 199.9 225.9 (____

TABLE 8 Test Quantity I Instrument I Measured Values I Acceptable I Limiting Range Normal Range For Operability Is Data Within Limiting Range A SW Bay SPDS/ I I I I

feet N/A N/A N/A Level on ECP Alt Test Inst I Table 8 data gathered by: initial date

PAGE: 325 of 551 1104.029 SERVICE WATER AND AUXILIARY COOLING SYSTEM CHANGE: 120 SUPPLEMENT I PAGE 23 OF 27 TABLE 9 Test Measured Acceptable Limiting Valve DES# Normal Range If within Direction Stroke Time Value for Initial Date (nearest 1/10 sec) Limiting (sec) Operability Value SG-5 Close sec 147.1 - 199.0 225.0 SG-1 Open sec 154.0-208.2 235.4 (__j SG-3 Open sec 157.9-213.7 241.5 (..J CV-3644 Open sec 48.0 64.8

- 73.3 (__)

CV-3646 Open sec 39.2 53.0

- 59.9 (__J 3.6 IF NO is circled in Table 2, 3 or 5, THEN:

DECLARE P-4A inoperable.

NOTIFY the Shift Manager.

INITIATE a Condition Report.

INITIATE corrective action.

REFERENCE Tech Spec for applicable conditions.

3.7 i.E ANY measured value in Table 2, 3, 4 or 5 does NOT fall within the Acceptable Normal Range, THEN INITIATE corrective action.

PAGE: 326 of 551 1104.029 SERVICE WATER AND AUXILIARY COOLING SYSTEM CHANGE: 120 SUPPLEMENT I PAGE 24 OF 27 3.8 E measured value is outside Limiting Value/Range in Table 1, 6, 7, or 9, THEN:

DECLARE that valve inoperable.

NOTIFY Shift Manager.

INITIATE a Condition Report.

INITIATE corrective action.

REFERENCE Tech Spec for applicable conditions.

3.9 IF ANY measured stroke time does QI fall within the Acceptable Normal Range, THEN:

3.9.1 Immediately RETEST valve or DECLARE valve inoperable.

3.9.2 REFER TO Appendix A, Operability of this procedure for additional guidance.

Performed by: Print Name Signature Initial Date

PAGE: 327 of 551 1104.029 SERVICE WATER AND AUXILIARY COOLING SYSTEM CHANGE: 120 SUPPLEMENT I PAGE 25 OF 27 P-4A Pump Curve 115 Baseline iting 110

- Aceptable Normal Range Limiting Range 105 Comprehensive Limit 100 95 90 NN 0

a 85 rtingj I Range I NNN E

a-80 75 70 EEEEEEIEE 65 4ç 60 55 z::z:::::z::z:::::::N 50 4000 4500 5000 5500 6000 6500 7000 7500 Pump Flow (gpm)

PAGE: 328 of 551 1 104029 SERVICE WATER AND AUXILIARY COOLING SYSTEM CHANGE: 120 SUPPLEMENT I PAGE 26 OF 27 Motor Map (3)

Motor Upper Bearing Axial (2)

Motor Upper Bearing Radial (1)

Motor Upper Bearing Radial In

\\\ /

//

POINT VELOCITY Data Collected By NO (in/sec)

Date I

2 Vibrometer M&TE #

Calibration Due Date 3

PAGE: 329 of 5 1104.029 SERVICE WATER AND AUXILIARY COOLING SYSTEM CHANGE: 120 SUPPLEMENT I PAGE 27 OF 27 4.0 SUPERVISOR REVIEW AND ANALYSIS (circle one) 4.1 Do all measured values recorded in the Acceptance Criteria fall within the specified Limiting Range/Value For Operability? YES NO 4.2 Do all measured values recorded in the Acceptance Criteria section fall within the Acceptable Normal Range?

(CIRCLE N/A if the only values outside the Acceptable Normal range are also outside the Limiting RangeNalue for Operability) YES NO N/A 4.3 IF NO is answered to 4.1, THEN PERFORM the following corrective actions:

ENSURE LCO Tracking Record is completed.

ENSURE Condition Report initiated.

4.4 IF NO is answered to 4.2, THEN PERFORM the following corrective actions:

ENSURE Condition Report has been initiated.

COMPLETE 1000.009A, Surveillance Test Program Revision Request to raise the test frequency.

For pumps: The test frequency shall be doubled.

For valves: The test frequency is monthly.

4.5 IF answer to either 4.1 or 4.2 is NO, THEN DESCRIBE the action taken below:

4.6 Has this equipment been proven operable per the Acceptance Criteria? YES NO 4.7 Have all the administrative requirements of this test been satisfied (i.e., all initial blocks initialed or marked N/A, all data entered, cal due dates listed, applicable signature spaces signed, etc.)? YES NO Supervisor Date

Page 1 of 5 A1JPM-RO-ADMIN-RWP3 UNIT: 1 REV # 2 DATE: ______________________________

JPM ID: A1JPM-RO-ADMIN-RWP3 SYSTEM/DUTY AREA: ADMINISTRATIVE TOPIC - Radiation Control TASK: Ability to comply with radiation work permit requirements JTA#: ANO1-RO-DHR-NORM-2 KA VALUE RO: 3.5 SRO: 3.6 KA

REFERENCE:

2.3.7 APPROVED FOR ADMINISTRATION TO: RO: X SRO:

TASK LOCATION: INSIDE CR: OUTSIDE CR:_________ CLASSROOM: X SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE:_____________ SIMULATOR: Classroom: ________X_______

POSITION EVALUATED: RO:____X______ SRO:___________

ACTUAL TESTING ENVIRONMENT: SIMULATOR: PLANT SITE:______ Classroom:__X___

TESTING METHOD: SIMULATE:_________ PERFORM:___X________

APPROXIMATE COMPLETION TIME IN MINUTES: 15 MINUTES REFERENCE(S): RWP 2020-1002, P-34A survey map, EXAMINEE'S NAME:_______________________________ Logon ID: ___________________

EVALUATOR'S NAME:__________________________________________________________________

THE EXAMINEE'S PERFORMANCE WAS EVALUATED AGAINST THE STANDARDS CONTAINED IN THIS JPM AND IS DETERMINED TO BE:

SATISFACTORY:________________ UNSATISFACTORY:_________________

PERFORMANCE CHECKLIST COMMENTS:

____________ Start Time ____________ Stop Time ____________ Total Time SIGNED __Robert Possage ______________________________ DATE: _______________________

SIGNATURE INDICATES THIS JPM HAS BEEN COMPARED TO ITS APPLICABLE PROCEDURE BY A QUALIFIED INDIVIDUAL (NOT THE EXAMINEE) AND IS CURRENT WITH THAT REVISION.

Page 2 of 5 A1JPM-RO-ADMIN-RWP3 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall ensure that the examinee has been briefed per NUREG 1021 Appendix E.

INITIAL PLANT CONDITIONS

Decay Heat Removal Pump P-34A has indications of a leak on the pump inboard seal.

The SM/CRS has directed you to quantify the leakage from the P-34A seal.

This is NOT an emergency

Your total dose for the year is currently 1950 mrem.

You are a qualified CAT 3 Advanced Rad Worker.

RWP, 20201002 Task 1 governs the planned activity TASK STANDARD:

Using the above information, applicant determined:

Remaining available dose is 50 mR

MAXIMUM stay time at the P-34A pump inboard seal area is 10.0 minutes. (8-10 minutes are acceptable)

Required protective clothing requirements are single set of anti-Cs.

TASK PERFORMANCE AIDS: RWP 2020-1002, P-34A survey map .

SIMULATOR SETUP: NA

Page 3 of 5 A1JPM-RO-ADMIN-RWP3 INITIATING CUE:

Use the attached RWP, 2020-1002 Task 1.

Using the above information, determine the MAXIMUM stay time at the P-34A pump inboard seal area for the WCO entry.

(C) PERFORMANCE STEP PERFORMANCE STANDARD SAT UNSAT N/A

1. Reviews P-34A Pump survey Examinee determined dose rate of map to determine dose rates in 115 mR/hr at the inboard pump seal.

the vicinity of the inboard pump seal. _____ _____ _____

(C) 2. Determines remaining Examinee determined remaining allowable dose. allowable dose is 50 mR 2000 mR - 1950 mR = 50 mR (C) 3. Determines stay time based on Examinee determined stay time the given dose in the pump based on RWP limits of 20 mrem inboard seal area not to would allow him to stay at the pump exceed the RWP limits. inboard seal area for 10.0 minutes (8 - 10 minutes).

20 mR X 60 min = 10.0 minutes 120 mR/hr 1 hr (C) 4. Reviews P-34A Pump survey Examinee identified the map for contamination smear contamination levels are > 1000 data to determine the dpm/100 cm 2 but less than 100,000 _____ _____ _____

protective clothing (PC) dpm/100 cm 2; therefore, a single set requirements for this task. of Anti-Cs is required to enter into the P-34A pump room.

END

Page 4 of 5 A1JPM-RO-ADMIN-RWP3 ANSWER KEY JPM INITIAL TASK CONDITIONS:

Decay Heat Removal Pump P-34A has indications of a leak on the pump inboard seal.

The SM/CRS has directed you to quantify the leakage from the P-34A seal.

Your total dose for the year is currently 1950 mrem.

You are a qualified CAT 3 Advanced Rad Worker.

INITIATING CUE:

Refer to the attached RWP, 20201002 Task 1 and the P-34A pump room survey map.

Using the above information, determine:

Your remaining available dose for the year based on ANO administrative limits.

2000 mrem - 1950 mrem = 50 mrem remaining

Your MAXIMUM stay time at the P-34A pump inboard seal area.

20 mR X 60 min = 10.0 minutes (8-10 minutes) (C) 120 mR/hr 1 hr

Your Protective Clothing requirements:

Single set of Anti-Cs (C)

Page 5 of 5 A1JPM-RO-ADMIN-RWP3 EXAMINEES COPY JPM INITIAL TASK CONDITIONS:

Decay heat Removal Pump P-34A has indications of a leak on the pump inboard seal.

The SS/CRS has directed you to quantify the leakage from the P-34A seal.

This is NOT an emergency

Your total dose for the year is currently 1950 mrem.

You are a qualified CAT 3 Advanced Rad Worker.

INITIATING CUE:

Refer to the attached RWP, 20201002 Task 1 and the P-34A pump room survey map.

Using the above information, determine:

Your remaining available dose for the year based on ANO administrative limits.

Your MAXIMUM stay time at the P-34A pump inboard seal area.

Your Protective Clothing requirements:

Survey: ANO-1606-0004 ANO Thursday, June 30, 2016 Template: 1a1-05_jpg Page 1 of 1 Details Smear Data (DPM/100cm2) 1 20000 DPM Unit: 1 2 25000 DPM Building: RAB 3 30000 DPM Elevation: 317 4 35000 DPM Room: 13 RxPwr: 100 LAS Data (ccpm/LAS)

Template: 1a1-05_jpg 1 6000 ccpm/LAS Frequency: 10CFR50.75G Decomm 2 <100 ccpm/LAS Survey Date: 08/22/2016 3/25/202015:58 3 <100 ccpm/LAS Status: In-Progress 4 <100 ccpm/LAS Rwp: 20161001 20201002 B/G to Alpha Ratio Hydro Inj Rate: NA Surveyed By: Harrell, John Alpha Data (DPM/100cm2) Badge: 20970 Reviewed By:

DPM Notes:

Instruments Used Instrument: LM-177 CHP-CR-148 100 Cal Due Date: 5/31/2020 7/31/2016 SrcChk Date: 6/29/2016 4/30/2020 DC & Bkg: NA NA MDA: NA 120 Instrument: 9-3 CHP-DR-331 120 Cal Due Date: 12/31/2016 5/31/2020 SrcChk Date: 4/30/2020 6/29/2016 DC & Bkg: NA NA MDA: NA 105

Entergy Arkansas Nuclear One RADIOLOGICAL WORK PERMIT

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Consult Posted Copy for Official Radiological Work Permit Information RWP

Title:

OPERATIONS ACTIVITIES UNIT-1 (Bulk Work) RWP No.:

20201002 Rev. 00 Comments:

20201002*

RWP Type: GENERAL RWP Status: Begin Date: Close On Date:

ACTIVE 1/1/2020 12/31/2020 Prepared By: KOWALEWSKI, JACOB J Job Supervisor: Unit 1 Operations Shift Supervisor Estimated Dose: Estimated Hours: Actual Dose: Actual Hours:

900 mrem 14,500.00 39 mrem 494.46 Locations Buildings Elevations Rooms LOW LEVEL RADWASTE BUILDING 354 NON-LOCKED HIGH RADIATION AREA OLD RADWASTE BUILDING 354 NON-LOCKED HIGH RADIATION AREA OUTSIDE CONTROLLED ACCESS ALL OUTSIDE CONTROLLED ACCESS UNIT 1 AUXILIARY BUILDING ALL NON-LOCKED HIGH RADIATION AREA Radiological Conditions Description Value Unit Smear data is in dpm/100 cm2 unless otherwise noted. <1K - 40K DPM/100CM2 General area gamma dose rates are in mrem/hour unless otherwise noted. 0.2 - 200 MILLIREM/HOUR Tasks Task Description Status 1 OPERATIONS ACTIVITIES UNIT-1 Active 2 OPERATIONS TRAINEE ACTIVITIES UNIT-1 Active Requirements Requirement Groups Requirement Descriptions N/A Additional Instructions Instruction 1:

Instruction 2:

Instruction 3:

Approvals Approver Title Name Date ALARA REVIEW KOWALEWSKI, JACOB J 12/04/2019 RWP PREPARER LAQUE, NICHOLAS J 12/03/2019 RP SUPERVISOR FOLEY, CHRISTOPHER J 12/05/2019 Attachments N/A 1/13/2020 3:03:32PM Page 1 of 7

Entergy Arkansas Nuclear One RADIOLOGICAL WORK PERMIT

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Consult Posted Copy for Official Radiological Work Permit Information RWP No.: 20201002 Task Number: 1 Rev.: 00 Task

Description:

OPERATIONS ACTIVITIES UNIT-1 Task Status: Active Estimate Dose: 850.00 Estimate Hours: 13,500.00 Hot Particle: Hi-Contamination:

Hi-Rad: Yes Yes Locked Hi-Rad: No Yes Alarm Settings Dose Alarm (mrem) 20.00 Dose Rate (mrem/hr) 200.00 Requirements Requirement Groups Requirement Descriptions Contamination Control All materials are required to be surveyed in a small articles monitor or hand frisked by RP (with RP Supervisor approval) PRIOR TO unconditional release from a Radiologically Controlled Area.

IF the RCA is a satellite RCA with no whole body contamination monitor available, THEN the radworker should: a) perform a hand and foot frisk. b) IF the frisk indicates contamination is present, THEN contact RP. c) IF the frisk DOES NOT indicate the presence of contamination, THEN proceed to the nearest whole body contamination monitor and gamma sensitive monitor.

If the RCA is a satellite RCA, and a "Contamination Area" is entered, the radworker will perform a whole body frisk. The radworker must then clear ARGOS (or PCM-1B) AND GEM-5 (or PM-7).

Notify RP prior to exposing a contaminated surface or opening a contaminated system.

Obey the monitoring instructions posted at the RCA exit point Upon exit of an RCA, whole body monitoring is required utilizing a whole body contamination monitor (ARGOS or equivalent). A whole body gamma monitor must also be cleared (GEM 5 or equivalent).

Upon exiting areas posted as "Contamination Area", perform a hand and foot frisk at the designated frisker location.

Use RP approved mats or pads when kneeling, sitting or laying in contaminated areas.

Use face shield for activities that have increased risk of facial contamination. These activities include working with contaminated components overhead, or having a body position that presents the potential for facial contamination.

With RP approval, reaching across a contamination boundary is permitted using surgeon's gloves OR cotton liners with rubber gloves. When reaching into the area of higher contamination, gloves must be removed when hands are returned to the lower level side of the boundary.

Dosimetry Requirements FOR WORK IN HIGH RADIATION AREAS - If your work conditions are in OR will cause hearing impairment (such as work in a high noise area, use of a communications headset, etc.) THEN the use of an SRD amplifying device (PAM) is required.

If an SRD dose alarm occurs: 1) Secure Work. 2) Immediately leave the RCA. 3)

Notify RP.

If an SRD dose rate alarm occurs: 1) Secure Work. 2) Back out of the immediate area until the alarm clears. 3) Notify others in your work crew. 4) Immediately notify RP for further instructions.

Periodically check your SRD. This check should be performed more frequently in areas where your ability to hear is diminished.

Whole body DLR and SRD required for entry.

1/13/2020 3:03:32PM Page 2 of 7

Entergy Arkansas Nuclear One RADIOLOGICAL WORK PERMIT

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Consult Posted Copy for Official Radiological Work Permit Information RWP No.: 20201002 Task Number: 1 Rev.: 00 Requirements Requirement Groups Requirement Descriptions Engineering Controls Consider having a HEPA Ventilation unit or HEPA vacuum in service prior to the start of a potential airborne radioactivity causing evolution.

When venting or draining, monitor the rate of system drain to ensure the rate of drain does NOT exceed the capacity of the floor drain.

Refer to TEDE Screening Document for guidance concerning contamination levels and confinement factors necessary to maintain airborne radioactivity levels <30% DAC.

Surface wetting, misting, or encapsulation should be considered to reduce the risk of airborne radioactivity.

Exposure Reduction Minimize crew size to reduce overall exposure for the job.

Move components to a low dose area for work when practical.

Use Low Dose Waiting Areas whenever possible to minimize exposure.

Remove unnecessary personnel from affected areas when moving material with dose rates of concern.

Protective Requirements Entry into Contamination Areas require single Anti-Cs.

Entry into High Contamination Areas require double Anti-Cs .

The outer layer of protective clothing is to be water repellent when working with water or wet components.

With RP approval prior to each entry, partial Protective Clothing (booties, rubber shoe covers, cotton liners, and rubber gloves) may be worn in lieu of a full set of PCs to access a Contamination Area (CA) where the known contamination is less than or equal to 10,000 dpm / 100 cm2. Any activities that require kneeling, sitting, climbing, or leaning against surfaces will require the use of full PCs.

RP Coverage Entry into High Radiation Areas requires a radiological brief from RP, AND an electronic alarming dosimeter (SRD) to meet Tech Spec monitoring requirements.

Notify RP when performing operations activities which could change plant radiological conditions. For example venting/draining radioactive systems, performing degas or decay heat/shutdown cooling operations, or other non routine system functions.

Radiation Worker Self-Briefing - WHEN the following conditions are met, THEN the worker may enter the RCA without directly interfacing with RP (the following radiological conditions must be true): 1) dose rate in work area and travel path <25 mrem/hr and area is not posted HRA 2) work area contamination levels are <10K dpm/100 cm2 AND area is not posted HCA 3) work is not in Alpha Level 2 or 3 area 4 area is not posted Airborne Radioactivity Area 5) access above 7' above floor is not required 6) work is not abrasive (cutting, welding, grinding etc) 7) work does not involve movement of radioactive material from RA, HRA, or LHRA 8) no opening of contaminated containers 9) no breach of contaminated systems 10) The work does not involve system operation, such as opening a valve that may allow radioactive material transfer through a pipe. ***If any of the Self-Brief criteria cannot be met, THEN, contact RP prior to starting work.***

Radiological Conditions Dose rates may increase as the water level is lowered.

Radiological conditions should be reviewed to ensure awareness of conditions in your work area. This information can be obtained from either a Status Board or RP personnel.

RP should monitor for dose gradients and relocate dosimetry as necessary using guidance from EN-RP-204. Contact ALARA if relocation is warranted.

Respiratory Protection Based on historical and current data, the airborne radioactivity is less than 30 percent of a DAC. Respiratory protection is not required unless otherwise directed by RP Supervision.

1/13/2020 3:03:32PM Page 3 of 7

Entergy Arkansas Nuclear One RADIOLOGICAL WORK PERMIT

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Consult Posted Copy for Official Radiological Work Permit Information RWP No.: 20201002 Task Number: 1 Rev.: 00 Requirements Requirement Groups Requirement Descriptions Special Radiological Requirements The prerequisite for a secondary resin transfer include 1) Secure the fill head such that changes in pressure will not cause a spill. 2) Conduct a walkdown (pre-transfer) to ensure that hose connections and leak integrity is satisfactory. 3) Construct a berm sufficient to contain the material being transferred.

Stop Work Criteria Critical Step - If UNEXPECTED alpha contamination > or equal to 500 dpm/100cm2 is detected, Then stop work and follow the guidance in EN RP 122.

Critical Step - Indications either from local samples or remote indication (CAM) of airborne radioactivity in quantities in excess of 30 percent of a DAC.

Critical Step - Loss of control of radioactive material such that loose surface contamination exceeds area postings.

Critical Step - RWP package contains TEDE Screening. Inability to remain within the bounds for contamination levels and confinement factors (specified in the TEDE Screening) will require that work be stopped.

Critical Step - Radiation dose rates in the immediate area are greater than the SRD dose rate alarm set point.

Additional Instructions Instruction 1:

Instruction 2:

Instruction 3:

Instruction 4:

Instruction 5:

Attachments N/A 1/13/2020 3:03:32PM Page 4 of 7

Entergy Arkansas Nuclear One RADIOLOGICAL WORK PERMIT

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Consult Posted Copy for Official Radiological Work Permit Information RWP No.: 20201002 Task Number: 2 Rev.: 00 Task

Description:

OPERATIONS TRAINEE ACTIVITIES UNIT-1 Task Status: Active Estimate Dose: 50.00 Estimate Hours: 1,000.00 Hot Particle: Hi-Contamination:

Hi-Rad: Yes Yes Locked Hi-Rad: No Yes Alarm Settings Dose Alarm (mrem) 15.00 Dose Rate (mrem/hr) 150.00 Requirements Requirement Groups Requirement Descriptions Contamination Control All materials are required to be surveyed in a small articles monitor or hand frisked by RP (with RP Supervisor approval) PRIOR TO unconditional release from a Radiologically Controlled Area.