Text

2011-08-FINAL-Operating Test
	ML11284A126
Person / Time
Site:	Arkansas Nuclear
Issue date:	08/26/2011
From:	; NRC Region 4
To:	; Entergy Operations
References
	50-313/11-302, ES-301, ES-301-1 50-313/11-302
	Download: ML11284A126 (297)
	v • d • e

ES)c?J o -iv

ADMINISTRATIVE JOB PERFORMANCE MEASURE TUQI: A1JPM-RO-RCS3 Page lof5 UNIT: 1 REV# 1 DATE:

TUOI NUMBER: A1JPM-RO-RCS3 SYSTEM/DUTY AREA: ADMINISTRATIVE TOPIC - CONDUCT OF OPERATIONS TASK: PERFORM RCS LEAK RATE DETERMINATION WHEN RCS LEAKAGE IS BEING RETURNED TO RCS JTA#: ANO1-RO-RCS-SURV-37 KAVALUERO: 3.9 SRO: 4.0 KA

REFERENCE:

2.1.23 APPROVED FOR ADMINISTRATION TO: RO: X SRO: X TASK LOCATION: INSIDE CR: X OUTSIDE CR:_______ BOTH:_______

SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE:____________ SIMULATOR: PERFORM LAB:_______________

POSITION EVALUATED: RO:_________ SRO:_________

ACTUAL TESTING ENVIRONMENT: SIMULATOR: X PLANT SITE:_____ LAB:____

TESTING METHOD: SIMULATE:_______ PERFORM:_________

APPROXIMATE COMPLETION TIME IN MINUTES: 15 MINUTES REFERENCE(S): 1103.013, Chq. 034, SurIement2 EXAMINEES NAME:_______________________ SSN -

EVALUATORS NAME:

THE EXAMINEES 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 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 TUOI: A1JPM-RO-RCS3 Page 2of5 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall review the Briefing Checklist System Walkthrough portion of OP 1064023 Attachment 6 with the examinee.

JPM INITIAL TASK CONDITIONS: The plant is at 100% power operations. RCS leak rate Determination per 1103.013, Supplement 2, RCS Leak Rate Determination When RCS Losses Are Being Returned To RCS is in progress. Plant computer program LKRT1 is inoperable. Plant computer tabular log RCS Leak Rate Data is active. The leak rate determination was commenced on the previous shift at 0016. All initial data has been obtained and recorded.

TASK STANDARD: The examinee has correctly calculated non-returnable leak rate per 1103.013. Supp. 2.

TASK PERFORMANCE AIDS: 1103.013 Supplement 2 and plant computer RCS Leak Rate Data tabular log sheet.

NOTE: This JPM is a modified version of AIJPM-RO-RCS2.

ADMINISTRATIVE JOB PERFORMANCE MEASURE TUOI: A1JPM-RO-RCS3 Page 5of5 EXAMINEES COPY JPM INITIAL TASK CONDITIONS:

The plant is at 100% power operations.

RCS leak rate determination per 1103.013, Supplement 2, RCS Leak Rate Determination When RCS Losses Are Being Returned To RCS, is in progress.

Plant computer program LKRT1 is inoperable.

Plant computer tabular log RCS Leak Rate Data is active.

The leak rate determination was commenced on the previous shift at 0016. All initial data has been obtained and recorded.

INITIATING CUE:

The CRS has directed you to complete the calculation for non-returnable leak rate in accordance with 1103.013, Supplement 2, Steps 2.1.3 through 2.1.10 using a stop time of 09:39:38.

The last valid T-1 11 fill rate is 0.045 gpm.

The final T-1 11 running timer value is 021999.

ARKANSAS NUCLEAR ONE (ANO) - UNIT I DATE: TODAY TIME: 10:05 UNIT NO. I TABULAR LOG LEAK PAGE I OF I TIME LI0OIB XTAVE LI248 XPP LI0O2B TAVE PP LI05I 09:25:35 215 840 578.66 68.168 100.021 220.267 578.89 100.052 5876.89 0926:36 214.046 578.66 68.920 100.021 220.503 578.63 100.008 5874.91 09:27:36 214.257 578.66 68.357 100.021 220.982 578.66 100.178 5874.46 09.28:36 214.028 578.66 69.807 100.021 221.191 578.53 100.177 5875.89 0929:36 214.027 578,66 69.143 100.021 221.745 578.54 100.125 5874.69 09.30:36 215.160 578.65 69.010 100.021 221.883 578.59 100.121 5876.83 09:31:36 215.903 578.65 69.896 99.994 221.641 578.70 99.949 5876.53 09:32:37 2 16.298 578.65 69. 795 99.994 220.857 578.74 99.911 5875.56 09:33:37 216.816 578.65 69.183 99.994 220.872 578.73 99.782 587672 09:34:37 215 104 578.65 69.276 99,994 220.826 578.78 99.839 5874.82 09:35:37 215.422 578.71 69.152 99.994 221.223 578.81 99.803 5876.90 09:36:37 215.968 578.71 68.021 99.994 221.426 578.72 99.914 5877.11 09:37:37 216.400 578.71 68.895 99.929 220.183 578.64 99.824 5875.28 09:38:38 216.775 578.71 68.788 99.929 219.625 578.58 99.797 5877.13 09:39:38 216.017 578.71 68.663 99.929 219.323 578.57 100.083 5875.31 09:40:38 216.419 578.71 68.558 99.929 219.482 578.51 99.797 5874.66 09:41:38 215.856 578.71 68.446 99.929 220.221 578.53 99.887 5875.99 09:42:38 215.721 578.77 68.340 99.929 220.687 578.62 99.947 5874.77 0943:38 214.464 578.77 68.307 100.033 221.087 578.57 99.923 5876.31 0944:39 214.985 578.77 68.714 100.033 221.387 578.66 99.886 5876.79 0945:39 214.186 578.77 68.87 I 100.033 221.864 578.63 99.820 5876.51 09.46:39 214.583 578.77 67.634 100.033 221.286 578.75 99.846 587609 09:47:39 215.781 578.77 67.796 100.033 220.677 578.80 99.897 5874.51 0948:39 215.367 578.77 67.659 100.033 221.167 578.81 100.025 5874.82 09:49:39 215.450 578.61 68.527 99.888 221.387 578.83 100.071 5875.25 09:50:40 216.185 578.61 68.402 99.888 220.607 578.86 100.028 5874.63 09:51.40 216.463 578.61 68.277 99.888 220.270 578.85 100.147 5874.88 09:52:40 216.461 578.61 69.151 99.888 220.085 578.82 100.037 5874.99 0953:40 215.484 578.61 69.013 99.888 219.926 578.83 100.128 5875.59 09:54:40 215.062 578.61 69.903 99.888 220.267 578.80 100.012 5875.12 09:55:40 215.060 578.64 69.177 99.997 220.503 578.81 100.014 5875.08

ENTERGY OPERATIONS INCORPORATED ARKANSAS NUCLEAR ONE DOCUMENT NO. CHANGE N TITLE: RCS LEAK DETECTION WORK PLAN EXP. DATE NIA SAFETY-RELATED IPTE SET # YES N0 QYES ZNO TEMP MOD LEVEL OF USE DYES NO CONTINUOUS Q REFERENCE Q INFORMATIONAL PROGRAMMATIC EXCLUSION PER EN-LI-100 DYES__NO When you see these TRAPS Get these TOOLS Time Pressure Effective Communication Distractionllnterruption Questioning Attitude Multiple Tasks Placekeeping Over Confidence Self Check Vague or Interpretive Guidance Peer Check First ShiftlLast Shift Knowledge Peer Pressure Procedures ChangelOff Normal Job Briefing Physical Environment Coaching Mental Stress (Home or Work) Turnover VERIFIED BY DATE I TIME FORM TITLE: FORM NO. CHANGE NO.

VERIFICATION COVER SHEET i000.006A 054

SUPPLEMENT 2 Page 1 of 11 RCS LEAK RATE DETERMINATION WHEN RCS LOSSES ARE BEING RETURNED TO RCS This procedure assures the RCS leak rate is within Tech Spec limits by satisfying the criteria of section 3.0. Leakage exceeding the limrts of section 3.0, evaluated as cusafe or non-isolable shall in-mediately be reported to the Shift Manager and a C.ridition Peport written. Reference TS 3.4.13 and TRM 3.4.5 for Required Actions.

This supplement (or Supplement 1) is performed once per calendar day and will satisfy SR 3.4.13.1. This supn-lement is not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after esabiishment of steady state operation at or near operating pressure per INTIAL CONDITIONS Verify water is not being added to or removed from RCS or MU System by the following:

Makeup or Chemical Addition from sources outside of the MU System or Reactor Coolant System, except for Zinc Injection.

Sampling of the RCS or MU System.

Venting or draining from the RCS or MU System.

4 Changing RCS, MU System, or Zinc Injection components in-service, i.e., pumps, filters, coolers, pump stroke,

- etc.

Boration or dilution.

Verify at least one of the following, listed in order of preference, available to provide leak rate data:

Plant Computer OR SPDS available for data gathering.

1.2 The following indications operabie Ant, P-wer Range Indicator

NI5, N16, NII r Nf0 nt r I C-Av In i r f I I?

r1r i-I

PROC.!WORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 61 of 74 RCS LEAK DETECTION L 1103.013 SUPPLEMENT 2 CHANGE: 034 Page 2 of 11 IF Zinc Inectron s :n-servce, THEN obtain current Zinc Inj race from Station Log, Plant Status Board OR Chemistry, OTHERWISE, enter zero for Zinc Inj rate at steps 2. .9 AND 2. 2.

1.3.1 IF recorded in GPH, THEN divide Zinc Inj rate by 60 to obtain GPM.

1.3.2 Record Zinc Inj rate in gpm in steps 2.1.9 AND 2.1.22.

Review the following limits and precautions.

RCS, MU System, and Zinc Injection components inservice shall NOT be changed during leak rate determination, and these systems shall be maintained in steady state condition.

To insure the most accurate determination of the RCS leak rate, the following requirements should be met:

he initial and final values of reactor power, RCS T-ave and pressurizer level, should be as close to identical as possible.

Digital values Lsing the same srgnal source for initial and final values should be used if available.

0 Routine daily leak rate determinations shall be performed over the maximum time practical, 67 hours7.75463e-4 days 0.0186 hours 1.107804e-4 weeks 2.54935e-5 months where possible, but for at least one hour.

Changes to Reactor Building Ventilation should NOT be performed.

If practical, 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months should elapse from the time pressurizer boron equalization is terminated until the beginning of the leakrate determination.

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PROC/WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 63 of 747 1103.013 RCS LEAK DETECTION CHANGE: 034 SUPPLEMENT 2 Page 4 of 11 Ailow Vacuum tegasifier Drain Pumps P43A, P-43B) to pump down to autora:ic cutoff point, then enter data under FINAL column on Table 2.1.1.

Table 2.1.1 Total Losses Data T Mm.

Date/Time: //b Date/Time: /o3 =

ONVERSISN EQUIVALENT VARIABLE INITIAL FINAL CHANGE FACTOR LOSS (GAL)

Pressurizer Level ( Q /7. 3 ( ) (--12.40;

(-102.44)

TAV (OF)

MU Tank 7l??) ) = (+30.86)

Level (HO)

Reactor Power (-) ( 9.?36 ( ) = (9.15)

Reactor Power Squared (p > ) 997 ( ) (+0.083)

Tlll last valid running timer -

= T-lll fill rate Should be Quench Tank -

= zero TOTAL LOSSES 2.1.4 Compute NTIAL and FINAL Reactor Power Squared values and enter in Table 2.1.1 2.1.5 Calculate CHANGE in each variable and enter in Table .l.1.

2.1.6 Multiply CHANGE values by CONVERSION FACTOR and enter under EQUIVALENT LOSS.

2.1.7 Add EQUIVALENT LOSS values algebraically to determine TOTAL

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-u nre:urnar.e leak rav ANE aooon: for Zonc re:icn as follows:

PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: I PAGE: 64 of 74 1103.013 RCS LEAK DETECTION CHANGE: 034 SUPPLEMENT 2 Page 5 of 11 2.1.10 Enter nonreturnable leak rate value in section 3.0.

2.1.11 Obtain known leakage from the following source(s) arid enter in Table 2.1.2 as applicable:

NOTE RCP seal leakage is not considered because it is being returned to RCS via Quench Tank.

A. Identified leakage sources from RCS Leak Test, Supplement 5 to Plant Preheatup and Precritical Checklist (1102.001), performed during most recent plant startup. Do not use leakages <0.01 gpm.

B. Leakage sources >0.01 gpm which have been identified since the last plant startup and evaluated per Supplement 3 to this procedure.

C. IF Red Train RP1 is inservice, THEN include known leakage through P36A/B Suction Stop Check Isol Prom BWST (BW-3)

D. IF Green Train HPI is inservice, THEN BW-3 known leakage is 0.0 gpm.

Table 2.1.2 Known Zea)age Data Location Measured Rate Leakage via BW-3 (IF Green Train HPI in-service, THEN 0.0 gpm) gpm Other sources (explain) gpm gpm

. gpm TOTAL KNOWN LEAK RACE: gpo 2 . . A.id L1EAC.JI.. K 2 P.ATE e r m.L TOTAL KNOWN LEAK RATE Nonreturnable leak rate (sectIon 3.0) gpo ncwn leak rate TebZe 2.1.2; gpo Cn:denc:f led leak raTe rpm

SUPPLEMENT 2 Page 6 of 11 2.1.15 Calculate Unidentified leak Rate TS, for comparison to the 1.0 gpm Tech Spec limit.

Unidentifzed leak rate (step 2.1.13) ( gpm)

Leakage via BW-3 (Table 2.1.2) + ( gpm Unidentified leak rate TS ( gpm) 2.1.16 Enter Unidentified leak rate - TS, in section 3.0.

NOTE Following steps determine total leak rate. Do not pump the Quench Tank to the Makeup Tank during this leak rate check.

2.1.17 Enter initial data required in Table 2.1.3 - Total Losses Data.

Check (V) data source used:

Pressurizer Level T-ave ()

Preferred: L1001B Preferred: XTAVE Backup: L1002B Backup: SPDS TAVRC1 SPDS LPZR1G Controlling T-ave SPDS LPZRIR Indicator (TI-1032)

PZR Level (LIS-1002)

Makeup Tank Level Reactor Power (v)

Preferred: L1248 Preferred: XPP Bakup: SPDS L1240 Barkup: SPDS NIILP Level Re order f r SPDS NI2LP MU Thnk LR-124a Any P jer Range inirat NI NI-U, N r NI-S I. ar ol rave lec r ,

TURN rU er E INAL a r. bA e .1 .

A. Leak race ieerrLcatin has rn for >1 h r.

B. PressurIzer level, baye, and Rx power values are apprxiraey equal to initial values.

2.1.19 Compute INITIAL and FINAL Reactor Power Squared values and ener in Table 2.1.3.

.1. LIt P l i r r

SUPPLESIENT 2 Page 7 of l under 2.1.21 Multioly CHANGE values by CONVERSION FACTOR and enter EQUIVALE NT LOSS in Table 2.1.3.

ine TOTAL 2.1.22 Add EQUIVALENT LOSS values algebraically to determ LOSSES.

ng 2.1.23 Determine test T in minutes and enter in the olIowi locations:

Tacle 2.1.3

Section 3.0 Table 2.1.3 Total Losses Data Start Stop AT = Mm.

Date/Time: Date/Time:

CONVERSION EQUIVALENT FINAL CHANGE FACTOR LOSS (GAL)

VARIABLE INITIAL Pressurizer (+12.40)

) ) ) ) =

Level (HO) -

) ) - C C (-102.44)

TAV (°F)

MU Tank (+30.86)

( ) ( )

Level (HO) -

Reactor (-9.15)

C ( C =

Power C -

Reactor Power (+0.083)

Squared (Pr) C C - ) C =

TOTAL LOSSES 2.1.24 Find otal PCS losses ANL acccnt for Zinc Injecticn as toll ows:

3a., Zr.o IOj t1 PO 1ss qpr, TOTAL LCSCFS, AT mm.

I PROC 1WORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 67 of 1103.013 RCS LEAK DETECTION CHANGE: 034 SUPPLEMENT 2 Page 8 of 11 RB Sump Fill Rate Determination 2.2.1 Update RB Sump Fillrate.xls (spreadsheet maintained by control room staff) with data from the most recent sump level step change from SPDS.

NOTE A valid RB Sump fillrate must begin with initial data at least two step changes following a RB Sump draining evolution. May have to use a filirate prior to a sump draining evolution A. Record the most recent valid RB Sump fillrate in Section 3.0.

2.3 RB Air Monitor Reading Evaluation from the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Unit 1 WCO Logsheet )OPSA3) , record the highest valid reading observed for the following in section 3.0:

RB ATMOS Particulate Monitor )Rl7460)

RB ATMOS Gaseous Monitor (RI-746l)

NOTE ROS Leakrate Excel spreadsheet performs the necessary calculations and comparisons of RCS leakrate data and will provide a flag to the operator when an Action Level has been exceeded.

2.4 IF this is the daily leak rate, THEN record data from Section 3.0 in the RCS Leakrate Excel spreadsheet and continue this section.

IF this is not the daily leak rate, THEN N/A steps 2.5 thru 2.7, and 2.9, and perform step 2.8.

2.5 IF RCS Leakrate Excel spreadsheet indicates that a Tier One, Tier Two or Tier Three Action Level has been exceeded, THEN refer to RCS Leakage Trend Analysis section for actions to be taken.

TpRocw01K PLAN NO PROCEDUREIWORK PLAN TITLE: PAGE: 68 of 74 I 1103.013 RCS LEAK DETECTION SUPPLEMENT 2 CHANGE: 034 Page 9 of 11 NOTE 5-day RB Sump averages are N/A until the 6th day that data is available e.g. 6th day after an outage).

2.6 From the RCS Leakrate Excel spreadsheet, obtain RB Sump fill rate 5day average: gpm.

(4.31) 2.7 IF RB sump fill rate exceeds the 5-day average by >0.1 gpm, THEN perform the following:

2.7.1 Notify Chemistry to obtain RB sump sample in an effort to determine the source of the rise in fill rate.

2.7.2 IF sample results indicate source of the rise in fill rate is Service Water, THEN initiate steps to perform RB entry to inspect accessible areas.

2.7.3 verify a Condition Report is initiated.

2.°.4 Determine whether performing Leakage Investigation in accordance with Attachment A of this procedure is appropriate.

2.8 SEQ perform the following:

Review and verify correct all calculations entered in this supplerrent.

IF applicable, THEN review and verify correct all calculations on the RCS Leakrate Excel spreadsheet.

IF arplicable, Tf-)EN run the Tier Actior Level maro tc cheok values on the R°S Zeekra:e Ex el spre hhee.

Rev w2 ir 2 vr, 2 iL h JR

PROC.IWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 69 of 74 1103.013 RCS LEAK DETECTION CHANGE: 034 SUPPLEMENT 2 Page 10 of 11 3.2 ACTEPTANCE CRITERIA 3.1 Record values observed during leak rate determination and compare with Limiting Range For Omerability.

IS LATh NITHIN TEST MEASURED LIMITING RANGE INSTRUMENT LIMITING RANGE?

QUANTITY VALUES FOP OPERABILITY (YES, NO, OR N/A)

Nonreturnable N/A <10 gpm YES NO Leak Rate gpm Unidentified N/A N/A N/A Leak Rate gpm Unidentified N/A <1 gpm YES NO Leak Rate - TS gpm RB Sump N/A N/A N/A Fill Rate gpm Total RCS N/A <30 gpm N/A Losses gpm PMS computer Test AT >60 minutes YES NO or clock mm RI-46O RI-7460 N/A Daily High cpm RI-7461 RI-746l N/A N/A Daily High rpm 3.2 IF NO is circled in above table, OR there is any leakage evaluated as unsafe, OR nonisolable leakage from a Reactor Coolant System strength boundary, THEN immediately notify the Shift Manager and verify Condition Report initiated.

Performed by Date/Time Date/Time Date/Time

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UNIT: I REV# 1 DATE:

TUOI NUMBER: AIJPM-RO-PMS32 SYSTEM/DUTY AREA: ADMINISTRATIVE TOPIC - CONDUCT OF OPERATIONS TASK: OPERATE THE PLANT COMPUTER JTA#: ANO1-RO-PMS-NORM-7 KAVALUERO: 3.0 SRO: 3.0 KA

REFERENCE:

2.1.19 APPROVED FOR ADMINISTRATION TO: RO: X SRO: X TASK LOCATION: INSIDE CR: X OUTSIDE CR:_______ BOTH:_______

SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE:____________ SIMULATOR: PERFORM LAB:_______________

POSITION EVALUATED: RO:_________ SRO:_________

ACTUAL TESTING ENVIRONMENT: SIMULATOR: X PLANT SITE:_____ LAB:____

TESTING METHOD: SIMULATE:________ PERFORM:_________

APPROXIMATE COMPLETION TIME IN MINUTES: 5 MINUTES REFERENCE(S): 1105.010 EXAMINEES NAME:__________________________ LOGON ID EVALUATORS NAME:

THE EXAMINEES 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 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.

THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

Prior to administration, ensure the Examinee has been briefed using Appendix E of NUREG-1 021.

JPM INITIAL TASK CONDITIONS: The plant is at 100% power operations.

TASK STANDARD: The examinee has disabled the CRD P-8 Motor Temperature computer point Ti P08 from alarm per 1105.01 0.

TASK PERFORMANCE AIDS: 1105.01 0, Plant Monitorirtq System

INITIATING CUE:

The CRS directs you to disable from alarm plant computer point Ti P08 for CRD P-B Motor Temperature per 1105.010, Plant Computer Operation.

CRITICAL ELEMENTS (C): 2, 3, 4, 5 (C) I PERFORMANCE CHECKLIST I STANDARD I N/A I SAT I UNSK EXAMINER NOTE: When asked, inform candidate permission is granted to disable point Ti P08.

1. Obtain CRSISM permission to Obtained permission to disable disable point, computer point Ti P08.

EXAMINER NOTE: An acceptable method to bring up the DATABASE MAINTENANCE screen is to type in the expert command DBM and then Enter. This action can be performed to accomplish the standard for steps 1 & 2.

(C) 2. Type in Turn On Code DPFA and Entered DPFA on the keyboard and enter. depressed the enter key.

(C) 3. Depress F2. Depressed F2 (white keys) key.

(C) 4. Type in desired point and enter. Typed Ti P08 and depressed the enter key.

(C) 5. Pressed Y and enter to save Depressed the Y key and depressed changes. the enter key on the keyboard to save changes.

6. Print Points Disabled From Alarm Printed Points Disabled From Alarm report. report as follows:

A. Typed in Turn On Code PDFA and depressed enter key.

B. Depressed enter key to send report to print queue.

C. Stated he would update the PDFA report maintained in the Control Room.

7. Verify WR/WO submitted for Stated he would verify that a WR/WO repair/restoration of disabled point, was submitted for repair/restoration of point Ti P08 and would include words to effect to restore point to alarm.

EXAMINER NOTE: WHEN the Enter work item number prompt comes up, THEN Inform the candidate to enter his initials and hit Enter.

END

EXAMINEES COPY JPM INITIAL TASK CONDITIONS:

The plant is at 100% power operations.

INITIATING CUE:

The CRS directs you to disable from alarm plant computer point Ti P08 for CRD P-8 Motor Temperature per 1105.010, Plant Computer Operation.

AJ ID I c) 11

ADMINISTRATIVE JOB PERFORMANCE MEASURE TUOI: A1JPM-RO-HCRD4 Page 1 of 4 UNIT: 1 REV# 2 DATE:

TUOI NUMBER: A1JPM-RO-HCRD4 SYSTEM/DUTY AREA: ADMINISTRATIVE TOPIC - EQUIPMENT CONTROL TASK: Perform Independent Review of a Prepared Tagout JTA#: ENS-OPER-PTAG-ADMIN--3 KAVALUE RO: 4.1 SRO: 4.3 KA

REFERENCE:

2.2.13 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: PERFORM POSITION EVALUATED: RO X SRO:

ACTUAL TESTING ENVIRONMENT:

PLANT SITE: SIMULATOR: Classroom: PERFORM TESTING METHOD: SIMULATE: PERFORM: X APPROXIMATE COMPLETION TIME IN MINUTES: 30 MINUTES REFERENCE(S): EN-OP-102 Rev 13, OP-1106.016, P&ID M-204 Sh 2 EXAMINEES NAME: SSN EVALUATORS NAME:

THE EXAMINEES 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 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 TUOI: A1JPM-RO-HCRD4 Page 2 of 4 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

Prior to administration, ensure the Examinee has been briefed using Appendix E of NUREG 1021.

JPM INITIAL TASK CONDITIONS:

Main Feedwater Pump Seal Supply Strainer F-56A-I needs to be tagged out for maintenance.

The eSOMS Clearance Module is unavailable and the Shift Manager has authorized the use of paper forms for the tagout.

The clearance for F-56A-1 was prepared on the previous shift.

Indus Assist Suite is unavailable also.

TASK STANDARD:

The examinee has correctly identified critical task errors on the prepared tagout per EN-OP 102, Protective and Caution Tagging.

TASK PERFORMANCE AIDS:

EN-OP-I 02-01 Attach 9.2, Tagout Cover Sheet EN-OP-102-01 Attach 9.3, Tagout Tags Sheet Portion of M-204, sht. 2

ADMINISTRATIVE JOB PERFORMANCE MEASURE TUOI: A1JPM-RO-HCRD4 Page 3 of 4 INITIATING CUE:

You have been directed by the Shift Manager to perform an independent review of the prepared tagout forms. Identify all discrepancies (if any) noted in your review.

CRITICAL ELEMENTS (C) 2 (C) PERFORMANCE CHECKLIST STANDARD N/A SAT I UNS fAT NOTE: Provide examinee with a copy of 1000.027B Clearance Removal Authorization Form.

1. Review the prepared Tagout Examinee reviewed Clearance Forms Removal Authorization Form.

2. Identify errors. Examinee identified the critical (C) errors:

1. Restoration sequence is incorrect. Drain valve CS-2908-2 is last manipulation instead of first. (critical)

2. Outlet valve CS-121A-1 is restored to the OPEN position instead of CLOSED per the tagout coversheet and OP-I 106.016 Att A.

(critical)

3. Drain valve CS-2908-1 is outside the isolation boundary and should not be included in tagout. (critical)

4. The Attribute value for Category E Component?

is marked Yes instead of No. (non-critical)

END

ADMINISTRATIVE JOB PERFORMANCE MEASURE TUOI: A1JPM-RO-HCRD4 Page 4 of 4 EXAMINEES COPY JPM INITIAL TASK CONDITIONS:

Main Feedwater Pump Seal Supply Strainer F-56A-1 needs to be tagged out for maintenance.

The eSOMS Clearance Module is unavailable and the Shift Manager has authorized the use of paper forms for the tagout.

The clearance for F-56A-1 was prepared on the previous shift.

Indus Assist Suite is unavailable also.

INITIATING CUE:

You have been directed by the Shift Manager to perform an independent review of the prepared tagout forms. Identify all discrepancies (if any) you discover during your review.

NUCLEAR N0N-QuALIViRELATED EN-OP-102-O1 REV.7 Entergy j MANAGEMENT MANUAL INFORMATIONAL USE PAGE 6 OF 27 Protective and Caution Tagging Forms & Checklist ATTACHMENT 9.2 TAGOUT COVER SHEET Clearance: MANUAL Tagout: CS-001-F-56A-1 Component to be worked: FILTER F-56A-1 MAIN FW PUMP ST

==

Description:==

Clean andlor replace F-56A-1.

References:

M-204 Sht 2, P&ID Condensate and Feedwater OP-1106.016, Condensate, Feedwater and Steam System Operation Placement lnst:

Ensure F-56A-2 is in service before hanging tag out.

Hazards:

CRAFT: Strainer is a high energy system (greater than 500 psig condensate water) with only single valve isolation. There is a drain on the strainer housing that is tagcied open.

OPS: Check boundaries are not leaking by before making tag out ready for work by verifying no water leaking from the drain.

Restoration lnst:

Verify no leaks on strainer housing when pressurizing system while clearing tags.

F-56A-2 will remain in service following maintenance on F-56A-1.

The inlet va!ve is restored OPEN and outlet valve is restored CLOSED.

Attribute Description Attribute Value Tagout Common per OP-102 All 9.2 Sect 8? No System meets Definition of High Energy? Yes See Tagout Details Category E Component? Yes Vent I Drain Required? Yes See Tagout Details Tagout Walkdown per OP-102 Performed by Preparer Tech Spec Impact? None Compensatory Actions Reg? Yes See Tagout Details Verify positions by controlled procedure Yes Work Order Number Description 00234376-01 Clean and/or replace F-56A-1

NUCLEAR N0N-QuALIW RELATED EN-OP-I 02-01 REV.7 Ento-rm, Y

MANAGEMENT MANUAL INFORMATIONAL USE PAGE 7 OF 27 Protective and Caution Tagging Forms & Checklist Status Description User Verification Date Prepared Prepared Joe Sizzling 5/2/11 Technica Reviewed Reviewed Approved Approved Tags Verified Hung Tags Verified Hung Removal Approved Removal Approved Tags Verified Removed Tags Verified Removed

NUCLEAR MANAGEMENT NoN-QuALiTY RELATED EN-OP-102-O1 REV. 7 Lritergy MANUAL INFORMATIONAL USE PAGE 8oF27 Protective and Caution Tagging Forms & Checklist ATTACHMENT 93 TAG0UT TAGS SHEET CLEARANcE: MANUAL_________ TAG0uT: CS-OO1-F-56A-1 Tag Tag Equipment Place. Place. Rest. 1st Rest. 2nd Placement)

Serial Type Equipment Description Place. Placement I St Verif 2nd Verif Rest. Restoration Verif Verif Removal N Equipment Location Seq. Configuration Date/Time Date/Time Seq. Configuration Date/Time Date/Time Tag Notes 76 Danger S-29O8-2 3 Open 4 Closed eal Supply Filter F-56A-1 Drain B-386 NW of A MEW Pump 77 Danger S-121A-1 1 Closed 2 Open

eal Supply Filter E-56A-1 Outlet B-386 NW of A MEW Pump 78 Danger S-12OA-1 2 Closed 3 Open

eal Supply Filter F-56A..l Inlet B-386 NW of A MEW Pump 79 Danger S-29O8-1 4 Open I Closed

)rain after CS-121A-2 B-386 NW of A MEW Pump

a riTi t

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AIJPM-NRC-ADMINRWPI Page 1 of 4 ADMINISTRATIVE JOB PERFORMANCE MEASURE UNIT: 1 REV# I DATE:

TUOI NUMBER: A1JPM-NRC-ADMINRWPI SYSTEM/DUTY AREA: ADMINISTRATIVE TOPIC Radiation Control TASK: Ability to comply with radiation work permit requirements JTA#: ANO1-RO-MUP-NORM-13 KA VALUE RO: 3.5 SRO: 3.6 KA

REFERENCE:

2.3.7 APPROVED FOR ADMINISTRATION TO: RO: X SRO: X TASK LOCATION: INSIDE CR: X OUTSIDE CR:_______ BOTH:_______

SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE:____________ SIMULATOR:_______ Classroom: X POSITION EVALUATED: RO: X SRO: X ACTUAL TESTING ENVIRONMENT: SIMULATOR:________ PLANT SITE:_____ Classroom: X TESTING METHOD: SIMULATE:_______ PERFORM: X APPROXIMATE COMPLETION TIME IN MINUTES: 10 MINUTES REFERENCE(S): RWP 2011-1002 EXAMINEES NAME:___________________________ SSN - -

EVALUATORS NAME:

THE EXAMINEES 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 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.

AIJPM-NRC-ADMINRWPI Page 2 of 4 ADMINISTRATIVE JOB PERFORMANCE MEASURE THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall review the Briefing Checklist System Walkthrough portion of OP 1064023 Attachment 6 with the examinee.

INITIAL PLANT CONDITIONS

100% power steady state.

Maintenance requires your assistance in the lower T-36 Valve Gallery.

Your total dose for the year is currently 1950 mR.

The dose rate in the area is 105 mR/hr.

TASK STANDARD:

Use the attached RWP, 2011-1002 Task 1.

Using the above information determine your MAXIMUM stay time in the lower valve gallery.

TASK PERFORMANCE AIDS: RWP 2011-1002 SIMULATOR SETUP: NA

AIJPM-NRC-ADMINRWPI Page 3 of 4 ADMINISTRATIVE JOB PERFORMANCE MEASURE INITIATING CUE:

Use the attached RWP, 2011-1 002 Task 1.

Using the above information determine your MAXIMUM stay time in the lower valve gallery.

CRITICAL ELEMENTS (C): 2 and 4 (C) PERFORMANCE CHECKLIST STANDARD N/A SAT UNSA

1. Recognize the dose limit per Examinee identifies that the RWP the RWP is 20 mR. Dose Alarm is set at 20 mR Student may also identify that the Dose Rate Alarm is set at 200 mR/hr.

2. Determine stay time based on (C) the given dose in the area not to exceed RWP limit of 20 mR.. Examinee determines that the RWP Dose Alarm limit is set at 20 mR which would allow him to stay 1 1.4 20 mR X 60 mm = 11.4 minutes minutes.

105 mR/hr 1 hr Student may also identify that the Dose Rate Alarm is set at 200 mR/hr.

3. Determine stay time based on the given dose in the area not to exceed annual dose limits. Examinee determines stay time based on Annual Dose Limit of 2000 mR would allow him to stay for 28.5 50 mR X 60 mm = 28.5 minutes minutes.

105 mR/hr 1 hr

4. Determine maximum stay time Examinee identifies that the RWP (C) based on the given dose in the Dose Alarm is the most limiting and area. the MAXIMUM stay time is 1 1.4 minutes.

END

AIJPM-NRC-ADMINRWPI Page 4 of 4 ADMINISTRATIVE JOB PERFORMANCE MEASURE EXAMINEES COPY JPM INITIAL TASK CONDITIONS:

100% power steady state.

Maintenance requires your assistance in the lower T-36 Valve Gallery.

Your total dose for the year is currently 1950 mR.

The dose rate in the area is 105 mRlhr INITIATING CUE:

Use the attached RWP, 2011-1002 Task 1.

Using the above information determine your MAXIMUM stay time in the lower valve gallery.

Entergy intergy Arkansas Nuclear One THE pOWER OF PEOPLE RADIOLOGICAL WORK PERMIT RSVP

Title:

(WI R.\ FIONS \( I I\ tilES UNI F-I RWP No.:

201 I 1(102 Rev. 0!

Comments: 4 41 1 114 (h( . h ui I i uu RWP Type: (iEN[R \1.

RWP Status: Be2in Date: Close On Date:

A.(TIVF 1/41201 I Prepared By: \I( (1 1l.AF1, ARI IS \I Job Supervisor: Randall Walters Estimated Dose: Estimated Hours: Actual Dose: Actual Hours:

525 flu cm I X7500 F) nrcm 4.5 I Locations Buildings Elevations L()\V Il\lI RAI)\VAS11 11(01 DIN(,

Rooms 354 NON-L0CK1:I) hIGH RAI)IA liON AREA OLD RAI)\V \STI BUILF)IN(i 54 NON-lO(KEI) F1l(ill RA[)I A.TTON A RF A OLTSll)F CON FROL[T[) At ( ESS A.Ii OUTSIDE (ONTRt)LLI:l) A((ESS UN IT I Al XILIARY BUILDING il L NON-LO(KLI) 111(111 RADL\ liON ARt- A Radiological Conditions Value t Stucar data i in clpm 100 cm2 unless oihcus ise noted I K 40K DPM: I 00( M2 (jeneral area gamma dose rates arc in mrem hour unless uthctsi s 0. I 24)4)

MllIIREM. 1101 R Tasks Task Description I ( )PERATIONS ACFI VII [5 UNIT-I Status 2 OPI RAT IONS TRAINI-F. A( TIVITIIS UNIT-I Actise Active Requirements Requirement Groups NA. Requirement Descriptions Additional Instructions Instruction I:

Instruction 2:

Instruction 3:

Instruction 4:

Instruction 5:

Approvals ApprjIe Ne De SI \R S RES IF\\

\IC( I ((All. SFU IS \l R\VP PRIPART R 0! 04 20! I

\IC( LII. \II, ARlis M RP S[PfRVNOR 01 04 2011 54 \RVF1 JR. ST \NLEV [)

0! 04 20! 1 Attachments N\

1/5201 I 9:50:53AM Page 1 of I

Enterqv Entergy Arkansas Nuclear One THE POWER OF PEOPLE RADIOLOGICAL WORK PERMIT Task Number: 1 RWPNo.:

20111002 Rev.: 01 Task

Description:

OPERAtIONS ACTIVITIES (lT_l Task Status: Aenie Estimate Dose: tS6(t tb) Estimate Hours: I 3.500.b()

HiRad: Yes f Hot Particle:

Locked HiRad: No Alarm Settings 1

H 1-Contamination:

Dose Alarm (mrem) 20.00 Dose Rate (mrem/hr) 200.00 Requirements Requirement Groups Requirement Descriptions (ontainitiation (ontiol All materials are required to he sureyed in a small articles monitor or hand ft sked h

R P t, it h R P Supet i stir apprn al PRI ( )R To uncondit ona I release Fri im a Radiologically Control led Area.

IF the RCA is a satellite R( A and a Contamination Area is entered, [ I uN the radisorker should perform a shole body frisk and proceed to the nearest it hole both contamination monitor (PCM I B or equisalcnU.

II the RC A is a satellite R( A stith no itliole body contamitiattoil monitor aiailab le.

[I IFN the radii ot ker should: a) perform a hand and kot frisk. h) IF the frisk indicates contatitination is present. 11 UN contact 1W. ct IF the frisk [)( )FS NOT indicate the presence of eon raininat ion. 1 111 N proceed to the nearest is hole hotly contamination monitor and gamma sensitis e monitor.

Noti[y RP prioi to eposirto a contaminated surface or opening a contaminated system.

Obey the monitoring instructions posted at the RCA exit point Use RP approsed mats or pads ishen kneeling. siting or hiring in cotitamninamed areas With R P appros al, reaching across a conta mina non boundary is perrni tied using streeons silos Cs ( )R cotton liners ii ith ubhcr gloxes. When reaching into the area of dgher contamination. silos es must be rernosed when hands are returned to the losvci es ci side of the boundary 1)osiimtetrr Reqi.nreinents H )R V5 (iRK IN 11l( ill R \1)i \TI( )\ AR hAS ifrour stork conditions ire OR ii in ill ciuse hearing Inparirtent such as stork in a high noise area. use of a cotinimunica tiotis headset. etc.) 1 iON the use ifan [Al) imitpimfymg des ice (PA\lt m mequired If:ii F \l) dose ilat in ecitis t ) Sesiire Vsirk 2j ltnmnecl;ately lease the R( \.

Natty RI.

Lii I \l) slse lute ulut ifl oc.tits. I Scenic Vs irk 2 i Back mit of the immeihale :n ci until thc il,n in le,ut s. ) Ntjt others in rout is ark dcii 4 t [nnhtcdtutel\

not I t\ RP fir (Iii hLt il1rtlrtllis.

Pc ill alir cheek rio F \F) Fhis cheek stild he perulo ned inre tieqitetitir iii areas islieme oui ihihtr to teat is dinttrnsfied.

While body Di R and F Al) requited for cnn s Ennineering ( onnols \\lieo u,ing tenipo dry hoses to sent or drain a ridmoactise systent. ensure the hose is labeled hr idioaetis e system ue onir k hen \entmg ot di aining. litollitor the late of system drain to ensure he rate ofdraiti does \4) F eseeed the eapaeitr of the floor di tin.

I r us Re (iictil I I De \\,iItin \ie.m sshcnescr pshie lllmmnii/e C\i sire PmL ui. Rq i diR \ml mmlm bcs \ iij ( ( i5 s\s jmmd \mtm ( imiki ),t tist id

i. u : (HR :, -

( 1, II) I ti It t (s

15 2011 9:51:28AM Page 1 of 4

Entergv En1ergy Arkansas Nuclear One POWER OP PEOPLE RADIOLOGICAL WORK PERMIT Task Number: 1 RWP No.:

20111002 Rev.: 01 R P ( i ri erage \ ( at 3 Ad sanced Radsi orker may enter posted lit gh Radiat ion Areas using a gamma sensit ise RP instrument to monitor dose rates. (NOTE

\n FA f) is N( )T an appropriate surey iflsti unlent I HRA \I1RA entry require s ContiflUous RP eo\erage.)

( ontact RP Super\ isor or RP tech prior to entry to en fy adequa te RP ens erage and contamination controls tar your si ork actis ny RP is not I eqiiirc d 10 be notitied br entries to the Ansiliary Building to pertorm routine acttsitics that do not insolve High Radiation Areas, Contaminat ion Areas, overhead entry or system breaches.

Entry into I ugh Radial ion Areas requires a radiological hriet from RP. AND an electronic alarming dosimeter (I Al) t to meet Tech Spec monito ring requirements.

Initial Intermittent RP coverage is tequired liar entry into High Radiation Areas, Notify R P sshen pet farming operations acti it es si hich could change plant radiimlogica conditions. For esaniple sentiug draining radmaetic system perfiar

s. mning degas or decay heat sb utdi iss ii emil i rig operations. ( ir i ither non out inc system time t ri ins Radiological ( ondimions ( ontact Radsvastc Personnel for radiological conditions in the Radwa stc Buildings.

Radiological conditions should he resiessed to ensure asaren ess oteonditloiN in your v urk area This intiarmat ion can be obtat ned from either a Status Board or RP personnel, Respi awry Protccnon Based on historical and current data, time airborne radioac tivity is less than 30 percent ota l)A( Respiratory protection is not required unless otherw ise directed by RP Supers ision Special Radiological Requirements (ritical Step Prior to moseineut olirradiated fuel or other irradiated materials. nutit RP Shifi Tech or RP Supers isor that nmosement of fuel irradiated con ponents is going to occur D( ) NC) I inir%c fuel or in adiated components near cask loading gate or tilt pi gate sshen the adjacent pit is drained as this can result in high general area dose rates.

The prerequisite for a secondary resitt transfer include I) Secure the fill head such that changes in pressure w ill not cause a spill 21 Conduct xsalkd a oss n (pretranstirj to etisuic that hose connections and leak intcgm ity is satistic tory ) (onstruct a berm suthcient to contain the material being trans1irred.

Stop Work ( ritci in (ritical Step Indications either from local samples or remote indication ((AM t of airborne radioactis ity in quantities in cveess of ) percen t ota DAC.

( ritual Step Radiatioti dose rates in the immediate area ate greater thati the I \l) d se rate :11 arm set point

( tutical Step \\ nik mnsots ne alpha ontanuunation gucitLr than or equal to too lpiiu I tJ(mun2 ( \s NI) I he o urkLd oii a ( ,cncral R\\

P Additional Instructions Instruction 1:

Instruction 2:

Instruction 3:

Instruction 4:

Instruction 5:

Attachments 15 2011 9:51:28AM Page 2 of 4

I 1

Ct 5

R cy

I c-1 b

I

ADMINISTRATIVE JOB PERFORMANCE MEASURE TUOI: A1JPM-SRO-TREND Page lof4 UNIT: 1 REV# 1 DATE:

TUOI NUMBER: A1JPM-SRO-TREND SYSTEM/DUTY AREA: ADMINISTRATIVE TOPIC - CONDUCT OF OPERATIONS TASK: QUARTERLY CHECK OF TREND DATA JTA#: ANO-SRO-ADMIN-NORM-48 KAVALUERO: 3.9 SRO: 4.2 KA

REFERENCE:

2.1.25 APPROVED FOR ADMINISTRATION TO: RO:______ SRO: X TASK LOCATION: INSIDE CR: X OUTSIDE CR:_______ BOTH:_______

SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE:_____________ SIMULATOR: PERFORM LAB:_______________

POSITION EVALUATED: RO:______ SRO:_________

ACTUAL TESTING ENVIRONMENT: SIMULATOR: X PLANT SITE:_________ LAB:_______

TESTING METHOD: SIMULATE:________ PERFORM:_________

APPROXIMATE COMPLETION TIME IN MINUTES: 10 MINUTES REFERENCE(S): 1015.006, Chq. 008 EXAMINEES NAME:___________________________ LOGON ID EVALUATORS NAME:

THE EXAMINEES 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 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 TUQI: A1JPM-SRO-TREND Page 2of4 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAM INEE:

The examiner shall review the Briefing Checklist System Walkthrough portion of OP 1064.023 Attachment 6 with the examinee.

JPM INITIAL TASK CONDITIONS: The plant is at 100% power.

TASK STANDARD: The examinee has reviewed the attached Reactor Building Spray Pump Data, identified the abnormal differential pressure trend, and identified that a condition report should be initiated as a minimum corrective action.

TASK PERFORMANCE AIDS: Reactor Buildina Sorav Pumø P-35A trend data and 1015.006.

ADMINISTRATIVE JOB PERFORMANCE MEASURE TUQI: A1JPM-SRO-TREND Page 3of4 INITIATING CUE:

The Shift Manager directs you to conduct a Quarterly Review of Reactor Building Spray Pump P-35A data per 1015.006.

CRITICAL ELEMENTS (C) 2, 3 (C) PERFORMANCE CHECKLIST STANDARD N/A SAT UNSAT

1. Review Reactor Building Spray Examinee reviewed Reactor Building Pump P-35A data. Spray Pump P-35A data.

(C) 2. Identify abnormal trend in pump 1. Examinee identified the drop of differential pressure. Reactor Building Spray Pump P 35A differential pressure over the last 3 surveillance tests.

EXAMINER NOTE: Once Candidate identifies abnormal trend, cue Candidate to discuss corrective actions.

A discussion is all that is required. Candidate only needs to identify technical issues, not editorial issues.

(C) 3. Take appropriate corrective action. Examinee identified he would initiate a condition report (critical).

Other corrective actions may be listed such as (non-critical):

. MAI for corrective maintenance (WR)

. Engineering Request (ER)

. Re-analysis of normal or limiting ranges per 1ST Program Implementation (5120.260)

. Expansion of trending program to other parameters, components or frequency

Change in operating practice

Upgrading test frequency

Condition Report based on declining trend

Contact System Engineer END

ADMINISTRATIVE JOB PERFORMANCE MEASURE TUQI: A1JPM-SRO-TREND Page 4of4 EXAMINEES COPY JPM INITIAL TASK CONDITIONS:

The plant is at 100% power.

INITIATING CUE:

The Shift Manager directs you to conduct a Quarterly Review of Reactor Buildi ng Spray Pump P-35AcIata per 1015.006.

ENTERGY OPERATIONS INCORPORATED ARKANSAS NUCLEAR ONE TITLE: OPERATIONS EQUIPMENT TRENDING DOCUMENT NO. CHANGE NO.

PROGRAM 101 5.006 008 WORK PLAN EXP. DATE N/A SET# SAFETY-RELATED IPTE DYES NO DYES NO TEMP MOD LEVEL OF USE DYES NO D CONTINUOUS Q REFERENCE

_INFORMATIONAL PROGRAMMATIC EXCLUSION PER EN-LI-100 DYES__NO When you see these TRAPS Get these TOOLS Time Pressure Effective Communication Distractionllnterruption Questioning Attitude Multiple Tasks Placekeeping Over Confidence Self Check Vague or Interpretive Guidance Peer Check First ShiftlLast Shift Knowledge Peer Pressure Procedures ChangelOff Normal Job Briefing Physical Environment Coaching Mental Stress (Home or Work) Turnover VERIFIED BY I DATE TIME FORM TiTLE: FORM NO. CHANGE NO.

VERIFICATION COVER SHEET 1000.006A 054

PROC/WORK PLAN NO, PROCEDURE/WORK PLAN TITLE: PAGE: 1 of 10 1015.006 OPERATIONS EQUIPMENT TRENDING PROGRAM CHANGE: 008 TABLE OF CONTENTS SECTION PAGE 1.0 PURPOSE 2 2.0 SCOPE 2

3.0 REFERENCES

2 4.0 BEF1NITIONS 3 5.0 RESPONSIBILITIES 4 6.0 REQUIREMENTS 4 ATTACEIMENT A - UNIT ONE TRENDED COMPONENTS 7 ATTACHMENT B - UNIT TWO TRENDED COMPONENTS 9

PROC.IWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 2 of 10 1015.006 OPERATIONS EQUIPMENT TRENDING PROGRAM CHANGE: 008 1.0 PURPOSE This procedure establishes guidelines and instructions for establishing and administering an Operations Department equipment trending program. Monitoring arid review of equipment trends from surveillance and periodic tests is performed to indicate system degradation and potential equipment failure.

2.0 SCOPE The Operations equipment trending program may include the quantitative results of surveillance and periodic tests performed by the Operations Department on safety related equipment. This testing is dictated by the requirements of each units Technical Specifications and ASME ON Code. In addition other information or components may be included as deemed appropriate by the Operations Manager.

3.0 REFERENCES

3.1 REFERENCES

USED IN PROCEDURE PREPARATION 3.1.1 ANO Unit Technical Specifications 3.1.2 INPO Good Practice MA-302, Trend Analysis 3.1.3 ASME 3M Code, 2002 Edition, 2003 81 Addenda (Unit 1) 3.1.4 ASME ON Code, 2004 Edition (Unit 2)

3.2 REFERENCES

USED IN CONJUNCTION WITH THIS PROCEDURE 3.2.1 ASME ON Code, 2002 Edition, 2003 Edition, Winter 81 Addenda (Unit 1) 3.2.2 ASME ON Code, 2004 Edition (Unit 2) 3.2.3 ANO Unit 1 Technical Specifications 3.2.4 ANO Unit 2 Technical Specifications 3.2.5 1104 Series Operating Procedures 3.2.6 1305 Series Operating Procedures 3.2.7 1102.001, Plant PreHeatup and PreCritical Checklist 3.2.2 1106.06, Emergency Feeiwaer System Operations 3.2.9 2104 Series Operang Procedures 3.2.10 2305 Series Operating Procedures 3.2.11 2102.001, Plant Pre-Heatup and PreCritical Checklist 3.2.12 2106.006, Emergency Feedwater System Operations 3.2.13 1000.009, Surveillance Test Program Control 3 .2.14 101.C9, Master Test Control List

PROC.IWORK PLAN NO. PROCEDIJREIWORK PLAN TITLE: PAGE: 3 of 10 1015.006 OPERATIONS EQUIPMENT TRENDING PROGRAM CHANGE: 008 3.3 NRC COMMITMENTS NONE 4.0 DEFINITIONS 4.1 Periodic Test A test that must be performed at a specified time frequency.

4.2 Surveillance Test A periodic test required by Technical Specifications or applicable ASME Code requirements. Also included are tests meeting other commitments or requirements or desired by Operations.

4.3 Test Frequency Required or recommended time intervals for a specific test as determined by Technical Specifications, ASME Code or as desired by Operations.

4.4 Trending The observation and evaluation of data collected at specified time intervals to facilitate identification of deteriorating equipment.

4.5 Abnormal Trend An abnormal or degrading trend condition is defined as: A change in measured or observed data that does not conform to expected/normal values after accounting for method of operation, seasonal environmental changes, or maintenance activity. Degrading trends can occur very rapidly or slowly depending on equipment related factors such as speed, size, load and the severity of possible damage. The reaction to an observed trend should be based on how rapidly it is occurring and whether it could affect the mission time of safety related equipment. Conservative and/or prudent responses in support of personnel, nuclear and equipment safety shall always be our goal.

PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 4 of 10 1015.006 OPERATIONS EQUIPMENT TRENDING PROGRAM CHANGE: 008

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5.0 RESPONSIBILITIES 5.1 Operations Manager shall have overall responsibility for the application of this procedure to those Operations tests where trending would be expected to enhance system reliability.

5.2 In addition, Operations Manager shall be responsible for the following:

5.2.1 Identification of components and their parameters for trending.

5.2.2 Collection, compilation and analysis of data.

5.3 The onshift SRO/SE shall be responsible for entering trended data acquired during his shift, evaluating that data for abnormalities and initiating corrective action based on data analysis. This action may be accomplished by his designee.

6.0 REQUIREMENTS 6.1 Identification of components and parameters to be trended.

6.1.1 Equipment required to be tested by the Operations Department per the unites Technical Specifications and ASME Code shall be considered for inclusion in the trending program.

6.1.2 Additional equipment components may be added as needs are demonstrated based on equipment performance.

6.1.3 Parameters for pump trending include 1ST data. Typically this includes discharge pressure (or differential pressure), flow, bearing temperature, driver bearing temperatures.

6.1.4 A typical parameter for valve trending under the 1ST program include stroke time to its emergency safeguards actuated position if deemed appropriate.

6.1.5 Reactor coolant system and generator hydrogen leak rates shall also be considered for inclusion in the trending program.

6.1.6 For diesel generators, typical parameters include engine starting time, zey vibration points and other parameters frrmm diesel lcqs ha may indicae developing abuoroal Inca.

6.l. Attachnens A and B sperify the coripcnnts and parameters required to be trended. Other ccmpcnents or parameters may be trendec as deemed appropriate by operational experience.

PROC.IWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 5 of 10 1015.006 OPERATIONS EQUIPMENT TRENDING PROGRAM CHANGE: 008 6.1.8 Primary emphasis should be placed on those parameters which have significant operational impact on the function of systems or components.

6.2 Frecuency of Trending 6.2.1 The normal frequency shall be that required by the units Technical Specifications or ASME Code.

6.2.2 IF post maintenance proof of operability or special tests are run, THEN the data gathered should be included.

IF maintenance or modifications result in significant change in trended data, THEN make note of the maintenance or modification on the trend chart.

6.2.3 IF no specific frequency is required, THEN it may be specified by the Operations Manager based on similar equipment or demonstrated performance.

6.2.4 Trending should be accomplished prior to forwarding the surveillance or periodic test to the CRS or SM for review.

6.3 Organization of Data 6.3.1 Trend charts (data plot forms) for the current year should be maintained in a database (hard copy or electronic) available for review by control room personnel.

6.3.2 Charts shall indicate normal values arid limiting values where applicable (usually from the surveillance procedure)

These values are specified for safety related equipment based on ASME Codes or Technical Specifications. Limits for other equipment may be based on operational experience.

6.3.3 Trend charts should be annotated with sufficient comments to explain any irregularities or changes in data trends.

6.4 Review of Data 6.4.1 Data should be entered by the an-shift senior reactor cperazcr or the Snift Engineer.

Reviow f data shouLd be performed as surveillanues are camp led.

PROC.IWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 6 of 10 1015.006 OPERATIONS EQUIPMENT TRENDING PROGRAM CHANGE: 008 NOTE Changes to the operating log limits for the minimum or maximum values on Tech Spec, Q, F or S equipment or their required support systems, can be modified to implement procedural limits, otherwise an Engineering Request (ER) is required.

6.4.3 Appropriate corrective action shall be taken based on reviews of trends. Typical corrective actions include, but are not limited to, the following:

WR/WO for corrective maintenance

Engineering Request (ER)

Re-analysis of normal or limiting ranges lAW Engineering Code Programs (ENDC-120)

Expansion of trending program to other parameters, components or frequency

Change in operating practice

Upgrading test frequency

Condition Report based on declining trend

PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 7 of 10 1015.006 OPERATIONS EQUIPMENT TRENDING PROGRAM CHANGE: 008 ATTACHMENT A Page 1 of 2 UNIT ONE TRENDED COMPONENTS COMPONENT PROCEDURE PARAMETERS ID Name 1104.002 P-36A Primary Makeup Pump AP, Vibration Supp 3 1104.002 P-u6B Primary Makeup Pump AP, Vibration Supp 4 1104.002 P-36C Primary Makeup Pump AP, Vibration Supp 5 1104.004 DH Removal Pump AP, Vibration P-4A Supp 1 1104.004 P-34B DH Removal Pump AP, Vibration Supp 2 1104.005 P-35A RB Spray Pump p, Vibration 1104.005 P-J5B RB Spray Pump L\P, Vibration Supp 1104.029 P-4A Service Water Pump AP, Flow, Vibration Supp 1 1104.029 P4B Service Water Pump AP, Flow, Vibration Supp 2 1104.029 P-4C Service Water Pump AP, Flow, Vibration Supp 3 1104.032 Discharge Pressure, Vibration P-6A Electric fire Pump Current, Supp 1

. 1104.032 Oil Pressure, Temperature ,Discharge P-6B Dresel Fire Pump Pressure, Vibration Supp 2 1106.006 P-7A EFW Pump AP, Flow, Vibration Supp 12 1106.006 n7B EW Pump AP, Flow, Vibration Supp 11 Fuel Pressure, Lube Oil Pressure,

, 1104.036 Temperature, Turbo searing Lube Oil t mo. sl men Z]pp 1 Pressire, Fuel Filter AP, Starr Time, tLbration, P16A(B) Vibrations Fuel Pressure, Lube Oil Pressure, 1104.036 Temperature, Turbo Bearing Lube Oil EtC #2 Emerg. Doesel Gen.

Supp 2 Pressure, Fuel Folter AD, Start Time, Vibration, P16A(B) Vibrations 1106.002 K-l Main Generator Hydrogen Leakrate Supp 1

PROC.IWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: BoflO 1015.006 OPERATIONS EQUIPMENT TRENDING PROGRAM CHANGE: 008 ATTACHMENT A Page 2 of 2 COMPONENT PROCEDURE PAP.PJ4ETERS ID Name 1106.006 CV-2645 P-7A to SC-A Open/close stroke time Supp_12 1106.006 CV-2646 P-7B to SCA Open/close stroke time Supp_11 1106.006 CV-2647 ?-7A to SCS Open/close stroke time Supp_12 1106.006 CV2648 P-7B to SGB Open/close stroke time Supp 11 1104.004 CV-1432 E-35B Bypass Close stroke time Supp2 1104.004 CV1433 E-35A Bypass Close stroke time Suppl 1104.046 Security Diesel Oil Pressure, Oil Temperature Supp2 RCS 1103.013 Leak Rate RB Sump 1103.013 Fill Rate

OP-li 04.006 Supp 3 Reactor Building Spray Pump P-35A Motor Brg Vibration 0140 0.120 0.100 0080 S

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0.040 0.020 0 000 I

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ADMINISTRATIVE JOB PERFORMANCE MEASURE TUQI: A1JPM-SRO-HCRD4 Page 1 of 4 UNIT: 1 REV# 1 DATE:

TUOI NUMBER: A1JPM-SRO-HCRD4 SYSTEM/DUTY AREA: ADMINISTRATIVE TOPIC - EQUIPMENT CONTROL TASK: AUTHORIZE A TAGOUT JTA#: ENS-OPSU-PTAG-ADMIN-4 KAVALUE RO: 4.1 SRO: 4.3 KA

REFERENCE:

2.2.13 APPROVED FOR ADMINISTRATION TO: RO: SRO: X TASK LOCATION: INSIDE CR: OUTSIDE CR: Classroom: X SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE: SIMULATOR: Classroom: PERFORM POSITION EVALUATED: RO_______ SRO: X ACTUAL TESTING ENVIRONMENT:

PLANT SITE: SIMULATOR: Classroom: PERFORM TESTING METHOD: SIMULATE: PERFORM: X APPROXIMATE COMPLETION TIME IN MINUTES: 30 MINUTES REFERENCE(S): EN-OP-102 Rev 13, OP-1106.016, P&ID M-204 Sh 2 EXAMINEES NAME: SSN -

EVALUATORS NAME:

THE EXAMINEES 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 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 TUOI: A1JPM-SRO-HCRD4 Page 2 of 4 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

Prior to administration, ensure the Examinee has been briefed using Appendix E of NUREG 1021.

JPM INITIAL TASK CONDITIONS:

Main Feedwater Pump Seal Supply Strainer F-56A-1 needs to be tagged out for maintenance.

The eSOMS Clearance Module is unavailable and the Shift Manager has authorized the use of paper forms for the tagout.

The clearance for F-56A-1 was prepared and reviewed on the previous shift.

Indus Assist Suite is unavailable also.

TASK STANDARD:

The examinee has correctly identified critical task errors on the prepared tagout per EN-OP 102, Protective and Caution Tagging.

TASK PERFORMANCE AIDS:

EN-OP-102-01 Attach 9.2, Tagout Cover Sheet EN-OP-i 02-01 Attach 9.3, Tagout Tags Sheet Portion of M-204, sht. 2

ADMINISTRATIVE JOB PERFORMANCE MEASURE TUOI: A1JPM-SRO-HCRD4 Page 3 of 4 INITIATING CUE:

You have been directed by the Shift Manager to approve the prepared tagout forms. Identify all discrepancies (if any) found during your review.

CRITICAL ELEMENTS (C) 2 (C) PERFORMANCE CHECKLIST STANDARD N/A SAT UNS AT NOTE: Provide examinee with a copy of 1000.027B Clearance Removal Authorization Form.___________________________

1. Review the Prepared Tagout Examinee reviewed Clearance Forms Removal Authorization Form.

2. Identify administrative errors. Examinee identified the critical (C) errors:

1. Restoration sequence is incorrect. Drain valve CS-2908-2 is last manipulation instead of first. (critical)

2. Outlet valve CS-121A-1 is restored to the OPEN position instead of CLOSED per the tagout coversheet and OP-i 106.016 Att A.

(critical)

3. Drain valve CS-2908-1 is outside the isolation boundary and should not be included in tagout. (critical)

4. The Attribute value for Category E Component?

is marked Yes instead of No. (non-critical)

END

ADMINISTRATIVE JOB PERFORMANCE MEASURE TUOI: A1JPM-SRO-HCRD4 Page 4 of 4 EXAMINEES COPY JPM INITIAL TASK CONDITIONS:

Main Feedwater Pump Seal Supply Strainer F-56A-1 needs to be tagged out for maintenance.

The eSOMS Clearance Module is unavailable and the Shift Manager has authorized the use of paper forms for the tagout.

The clearance for F-56A-1 was prepared and reviewed on the previous shift.

Indus Assist Suite is unavailable also.

INITIATING CUE:

You have been directed by the Shift Manager to approve the prepared tagout forms.

identify all discrepancies (if any) noted during your review.

NUCLEAR NON-QUALITY RELATED EN-OP-102-O1 REV.7 Entergy MANAGEMENT MANUAL INFORMATIONAL USE I

PAGE 6 OF 27 Protective and Caution Tagging Forms & Checklist ATTACHMENT 9.2 TAG0uT COVER SHEET Clearance: MANUAL Tagout: CS-00I-F-56A-I Component to be worked: FILTER F-56A-I MAIN FW PUMP ST

Description:

Clean and/or replace F-56A-1.

References:

M-204 Sht 2, P&lD Condensate and Feed water OP-Il 06.016, Condensate, Feedwater and Steam Syst em Operation Placement lnst:

Ensure F-56A-2 is in service before hanging tag out.

Hazards:

CRAFT: Strainer is a high energy system (greater water) with only single valve isolation. There is a drain than 500 psig condensate that is tagged open. on the strainer housing OPS: Check boundaries are not leaking by before work by verifying no water leaking from the drain making tag out ready for Restoration lnst:

Verify no leaks on strainer housing when pressurizi tags. ng system while clearing F-56A-2 will remain in service following maintenan The inlet valve is restored OPEN and outlet valv ce on F-56A-I.

e is restored CLOSED.

Attribute Description Tagout Common per OPOt9ç_ Attribute Value ystem meets Definition of High Energy? No Yes See Tagout Detads Category E Component?

Vent / Drain Required? Yes Taqout Walkdown per OP-102 Performed by Preparer Tech Spec Impact?

None --

(ompensatory Actions Req? Yes See [aqout Details Verify positions by controlled procedure Yes Work Order Number Description 00234376-01 Clean and/or replace F-56A-1

NUCLEAR NON-QUALITY RELATED

EN-OP-I 02-01 REV.7 Enterm j

, MANAGEMENT INFORMATIONAL USE MANUAL PAGE 7 OF 27 Protective and Caution Tagging Forms & Checklist Status Description User Verificátión Prepared Date Prepared Joe Sizzling 5/2/11 Technical Reviewed Reviewed Approved Ben There 5/2/1 1 Approved Tags Verified Hung Tags Verified Hung Removal Approved Removal Approved Tags Verified Removed Tags Verified Removed

NUCLEAR MANAGEMENT N0N-QuALErY RELATED EN-OP-102-O1 REV. 7 hitergy MANUAL INFORMATIONAL USE PAGE 8oF27 Protective and Caution Tagging Forms & Checklist ATTACHMENT 9.3 TAG0uT TAGS SHEET CLEAFNcE: _MANUAL__________ TAGOuT: CS-OO1 -F-56A-1 Tag Tag Equipment Place. Place. Rest. 1st Rest. 2nd Placement!

Serial Type Equipment Description Place. Placement 1 St Verif 2nd Verif Rest. Restoration Verif Verif Removal No. Eguipment Location Sq Configuration Date/Time Date/Time Seq. Date/Time Date/Time Tag Notes 76 Danger S-2908-2 3 Open 4 Closed eal Supply Filter F-56A-1 Drain 8-386 NW of A MFW Pump 77 Danger S-121A-1 1 Closed 2 Open eal Supply Filter F-56A-1 Outlet rB-386 NW of A MFW Pump 78 Danger DS-120A-1 2 Closed 3 Open eal Supply Filter F-56A-1 Inlet rB-386 NW of A MFW Pump Danger S-2908-1 4 Open I Closed

)rain after CS-121A-2 IB-386 NW of A MFW Pump

A cy ADMINISTRATIVE JOB PERFORMANCE MEASURE TUOI: A1JPM-SRO-PAR2 Page 1 of 5 UNIT: 1 REV# 0 DATE:

TUOI NUMBER: A1JPM-SRO-PAR2 SYSTEM/DUTY AREA: ADMINISTRATIVE TOPIC EMERGENCY PROCEDURES/PLAN TASK: DETERMINE A PROTECTIVE ACTION RECOMMENDATION JTA#: ANO-SRO-EPLAN-EMERG-301 KA VALUE RO: 2.4 SRO: 4.4 KA

REFERENCE:

2.4.44 APPROVED FOR ADMINISTRATION TO: RO:___________ SRO: X TASK LOCATION: INSIDE CR: X OUTSIDE CR:_______ BOTH:_______

SUGGESTED TESTING ENVIRONMENT AND METHOD (PERFORM OR SIMULATE):

PLANT SITE:_________ SIMULATOR: PERFORM LAB:_________

POSITION EVALUATED: RO: N/A SRO: X ACTUAL TESTING ENVIRONMENT: SIMULATOR: X PLANT SITE:_ LAB:_

TESTING METHOD: SIMULATE:________ PERFORM:_________

APPROXIMATE COMPLETION TIME IN MINUTES: 15 MINUTES (TIME CRITICAL)

REFERENCE(S): 1903.011 Chg. 038 EXAMINEES NAME:_______________________ LOGON ID EVALUATORS NAME:

THE EXAMINEES 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 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 TUOI: A1JPM-SRO-PAR2 Page2of5 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall review the Briefing Checklist System Walkthrough portion of OP 1064.023 Attachment 6 with the examinee.

JPM INITIAL TASK CONDITIONS:

A large break LOCA has occurred on Unit One 30 minutes ago.

The ENS has been activated but the TSC and the EOF are NOT operational.

A General Emergency has been declared per EAL 1.7, Loss of or challenge to all 3 Fission Product Barriers, two minutes ago.

This is NOT the first notification to the State of Arkansas.

Fuel failure is estimated to be 20%.

A release is in progress and the duration is projected to be greater than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Wind direction is from 145 degrees.

The Initial Dose Assessor reports dose rates are projected to be 2.7 Rem TEDE at 5 miles and 0.6 Rem TEDE at 6.5 miles.

There are NO known impediments to evacuation.

This is NOT a fast breaker.

TASK STANDARD: Within 15 minutes, the examinee has correctly chosen to recommend PAR 4 with an evacuation of zones G K M N 0 P, PAR 2 with an evacuation of zones R Q (provided by Initial Dose Assessor), and the remainder of the 10 mile EPZ to go indoors and listen to emergency broadcasts.

TASK PERFORMANCE AIDS: 1903.011 Attachment 6

ADMINISTRATIVE JOB PERFORMANCE MEASURE TUOI: A1JPM-SRO-PAR2 Page3of5 INITIATING CUE:

You are the Shift Manager in the Control Room and as the EOF Director you must recommend a Protective Action Recommendation.

CRITICAL ELEMENTS (C) 2 (C) PERFORMANCE CHECKLIST STANDARD N/A SAT UNS AT

1. Consult Attachment 6 of Turned to Attachment 6 of 1903.011, Emergency 1903.011, Protective Action Response/Notifications. Recommendations (PARs) for General Emergency.

NOTE: Act as the Initial Dose Assessor for the candidate. WHEN candidate asks, or is at this point, THEN hand to candidate the additional cue sheet where the Initial Dose Assessor projects zones R and Q will exceed EPA Protective Action Guidelines (PAGs).

(C) 2. Recommend PAR based on Within 15 minutes of JPM start, event conditions. selected PAR No. 4 and PAR No. 2 due to GE and EPA PAGs projected to be exceeded 5-10 miles downwind.

Indicated, due to wind direction of145°,zonesGKMNOP, along with zones R Q (from Initial Dose Assessor) should be evacuated and zones in the remainder of the 10 mile EPZ should remain indoors and listen to emergency broadcasts.

END

ADMINISTRATIVE JOB PERFORMANCE MEASURE TUOI: A1JPM-SRO-PAR2 Page5of5 EXAMINEES COPY (HAND TO CANDIDATE WHEN CANDIDATE ASKS OR IS OBSERVED TO BE AT POINT OF IDENTIFYING ZONES)

CUE:

The Initial Dose Assessor projects zones R and Q will exceed EPA Protective Action Guidelines (PAG5).

ADMINISTRATIVE JOB PERFORMANCE MEASURE TUOI: A1JPM-SRO-PAR2 Page 4 of 5 EXAMINEES COPY JPM INITIAL TASK CONDITIONS:

A large break LOCA has occurred on Unit One 30 minutes ago.

The ENS has been activated but the TSC and EOF are NOT operational.

A General Emergency has been declared per EAL 1.7, Loss of or Challenge to all 3 Fission Product Barriers, two minutes ago.

This is NOT the first notification to the State of Arkansas.

Fuel failure is estimated to be 20%.

A release is in progress and the duration is projected to be greater than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Wind direction is from 145 degrees.

The Initial Dose Assessor reports dose rates are projected to be 2.7 Rem TEDE at 5 miles and 0.6 Rem TEDE at 6.5 miles.

There are NO known impediments to evacuation.

This is NOT a fast breaker.

INITIATING CUE:

You are the Shift Manager in the Control Room and as the EOF Director you must recommend a Protective Action Recommendation.

NOTE: THIS IS A TIME CRITICAL JPM.

ENTERGY OPERATIONS INCORPORATED ARKANSAS NUCLEAR ONE DOCUMENT NO. CHANGE NO.

TITLE: Emergency Response/Notifications 040 1903.011 WORK PLAN EXP. DATE REACTIVITY IMPACT c

N/A []YES []INPR NO SAFETY-RELATED IPTE SET # DYES []NO E]YES NO TEMP MOD LEVEL OF USE QYES NO J CONTINUOUS REFERENCE D INFORMATIONAL PROGRAMMATIC EXCLUSION PER EN-LI-100 IJYES__NO When you see these TRAPS Get these TOOLS Time Pressure Effective Communication Distraction/Interruption Questioning Attitude Multiple Tasks Placekeeping Overconfidence Self Check Vague or Interpretive Guidance Peer Check First Shift/Last Shift Knowledge Peer Pressure Procedures Change/Off Normal Job Briefing Physical Environment Coaching Mental Stress (Home or Work) Turnover VERIFIED BY I DATE I TIME FORM TITLE: FORM NO. CHANGE NO.

VERIFICATION COVER SHEET 1OOOOO6A 055

PROC/WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 55 of 73 1903.011 EMERGENCY RESPONSE/NOTIFICATIONS CHANGE: 040 Page 1 of 9 ATTACHMENT 6 PROTECTIVE ACTION RECOMMENDATIONS (PARs) FOR GENERAL EMERGENCY Table of Contents PAGE No.

ANO Protective Action Recommendation(s) Discussion/Guidance 2 PAR Flow Chart A Guide for Determining PARs 3 PAR No. 1 Evacuate 2 Mile Radius and 2-5 Miles Downwind 4 PAR No. 2 Dose Assessment EPA PAGs (1 Rem TEDE; 5 Rem CT Dose) Exceeded Evacuate 2 Mile Radius and 2-5 Miles Downwind 5 PAR No. 3 Shelter 2 Mile Radius and 2-5 Miles Downwind 6 PAR No. 4 Dose Assessment EPA PAGs (1 Rem TEDE; 5 Rem CT Dose) Exceeded Evacuate 2 Mile Radius and 2-10 Miles Downwind 7 PAR No. 5 Dose Assessment EPA PAG5 (1 Rem TEDE; 5 Rem CT Dose) Exceeded Evacuate/Shelter Areas Outside the 10-mile EPZ 8 PAR No. 6 - Wind Shift PAR Determination 9

PROC.!WORK PLAN NO. PROCEDIJREIWORK PLAN TITLE: PAGE: 56 of 73 1903.011 EMERGENCY RESPONSEINOTIFICATIONS CHANGE: 040 Page 2 of 9 ATTACHMENT 6 PROTECTIVE ACTION RECOMMENDATIONS (PARs) FOR GENERAL EMERGENCY Discussion This attachment provides instructions for the assessment and initiation of Protective Action Recommendations (PARs) following the declaration of a General Emergency classification. Offsite response agencies shall be notified of Protective Action Recommendation within 15 minutes. Revisions to Protective Action Recommendations may be based upon:

current plant conditions

projected offsite dose assessment

forecasted/actual wind shifts Evacuation is the preferred method for protecting the public within the ANO 10-mile Emergency Planning Zone (EPZ) as a result of a radiological emergency event at ANO. However, some circumstances may warrant a protective action of shelter when evacuation cannot be performed due to impediments and/or severe weather conditions. Individuals responsible for determining PARs at ANO should consider all circumstances when developing protective actions.

The Arkansas Department of Health (ADH) will be notified of the ANO protective action recommendations and are responsible for determining and issuing a Protective Action Advisory (PM) to the County Judges (Conway, Johnson, Logan, Pope and Yell counties). Arkansas law places the responsibility for issuing protective actions to the public with the County Judges which will have both a Protective Action Recommendation and a Protective Action Advisory available for decision making. At a General Emergency classification, the Arkansas Department of Health, at a minimum, will issue a default Protective Action Advisory of evacuate a 5-mile radius and evacuate 5-10 miles downwind and the remaining EPZ to remain indoors and listen to emergency broadcasts. At a General Emergency classification, ANO, at a minimum, will issue a default Protective Action Recommendation (PAR) of evacuate a 2-mile radius and evacuate 2-5 miles downwind and the remaining EPZ to remain indoors and listen to emergency broadcasts. The ADH Protective Action Advisory encompasses a larger area than that recommended by federal guidance and the ANO General Emergency classification PAR. Be aware of this difference between the ANO protective action recommendation and the ADH protective action advisory should a question arise. ANO PARs meet all of the EPA/NRC recommended regulatory guidance and are consistent with the rest of the nuclear industry.

Guidance Involving Wind Shifts within the 10-mile EPZ If wind shifts are occurring or are predicted to occur within the 10-mile EPZ, guidance is provided on PAR No. 6 within this attachment.

Use of the PAR Flowchart in Attachment 6 A PAR Flowchart is included on Page 3 of this attachment. This flowchart should be used initially and at the beginning of each PAR evaluation to help determine the correct PAR to issue based on plant conditions, release status, evacuation impediments and offsite dose assessment.

PROCJWORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 57 of 73 1903.011 EMERGENCY RESPONSEINOTIFICATIONS CHANGE: 040 Page 3 of 9 ATTACHMENT 6 PROTECTIVE ACTION RECOMMENDATIONS (PARs) FOR GENERAL EMERGENCY PAR Flow Chart (A Guide for Determining PARs)

YES NOTE NO Wind Shifts are forecasted, THEN PAR No. 6 shall be reviewed pNO to assist with final PAR determination.

Can release durahon be accurately determined YES AND wdl the release be of short duration (Puff Release xl hr )1 4, NO Are EPA Protective Action Guidelines iPAGs) protected to be esceeried NO (obtain from Dose Assessment) 1 REM TEDE OR 5 REM Child Thyroid CDE 4, YES YES Are there known impediments to evacuation YES Are there known impediments to evacuation?

Jr NO exceeded at C 5 miles 4, NO IL PADs THEN Combine PAR 1 and PAR 2 PAR 3 PAR 1 Minimum Shelter 2 Mile Radius / 2-5 Evacuate 2 Mile Radius / 2-5 Miles Mi vs Downwind Include Zones from Downwind Dose Assessment (PAR 2(

IL PADs exceeded at 5 miles THEN Combine PAR 4 and PAR 2 Are EPA Protective Act on Guidel nex Make Notifications to State and local projected to be exceeded outside the PAR 5 governments immediately upon PAR IS mile EPZ? YES Recommend Evacuation/Sheltering of determination (obtain from Dose Assessment) - additional affected areas outside the 1 REM TEDE 10 mile EPZ Re-evaluate PAR criteria every 15 DR minutes 5 REM Child Thyroid CDE NO I t

PROCJWORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 58 of 73 1903.011 EMERGENCY RESPONSEINOTIFICATIONS CHANGE: 040 Page 4 of 9 ATTACHMENT 6 PROTECTIVE ACTION RECOMMENDATIONS (PARs)

FOR GENERAL EMERGENCY PAR No. 1 EVACUATE NOTE State and local governments must be notified within 15 minutes of PARs or changes to PARs using Form 1903 .01 1-Y.

1. Entry Conditions General Emergency Declared

2. Recommend the followinci Protective Action Recommendations:

Recommend evacuation of 2 mile radius and 2-5 miles downwind. Recommend the remainder of the 10 mile EPZ to go indoors and listen to the emergency broadcast for this event. Include any previously evacuated zones with this PAR. 2Q NOT change any previously evacuated zones to shelter or go indoors on this PAR.

Determine the affected zones for the PAR from the chart given below.

Wind Direction (from) Evacuate Zones Zones to go indoors 348.75to11.25 GU HIJKLMNOPQRST 11.25to33.75 GRU WIJKLMNOPQST 33.75to56.25 GRU HIJKLMNOPQST 56.25to78.75 GRU HIJKLMNOPQST 78.75to101.25 GNOR HIJKMPQSTU 1O1.25to123.75 GNOR HI]KLMPQSTU 123.75to 146.25 GKNO HIJLMPQRSTU 146.25to168,75 GKNO HIJLMPQRSTU 168.75to191.25 GKN HIJLMOPQRSTU 191.25to213.75 GK HIJLMNOPQRSTU 213.75to236.25 GK HIJLMNOPQRSTU 236.25to258,75 GHK IJLMNOPQRSTU 258.75to281.25 GHK IJLMNOPQRSTU 281.25to303.75 GHKU IJLMNOPQRST 303.75to326.25 GHU IJKLMNOPQRST 326.25to348.75 GHU IJKLMNOPQRST

3. Reassess PARs every 15 minutes until downgrade or recovery phase is entered.

PROC.IWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 59 of 73 1903.011 EMERGENCY RESPONSEINOTIFICATIONS CHANGE: 040 Page 5 of 9 ATTACHMENT 6 PROTECTIVE ACTION RECOMMENDATIONS (PARS)

FOR GENERAL EMERGENCY PAR No 1 2 EVACUATE NOTE State and local governments must be notified within 15 minutes of PARs or changes to PARs using Form 1903.01 1-Y.

1. Entry Conditions General Emergency declared AND Dose Assessment projects EPA Protective Action Guidelines (PAG5) exceeded 1 Rem TEDE OR 5 Rem Child Thyroid CDE

2. Recommend the following Protective Action Recommendation:

NOTE If there are known impediments to evacuation, then consider sheltering of the affected zones versus evacuation.

2.1 IF PAGs are exceeded at 5 miles THEN recommend the following PAR:

EVACUATE zones from PAR 4

EVACUATE any additional 1 ZONES projected by dose assessment to exceed the EPA PAG5 (obtain from dose assessment).

Remainder of the 10 mile EPZ to go indoors and listen to the Emergency Broadcasts 2.2 IF PAG5 are exceeded at < 5 miles, THEN recommend the following PAR:

EVACUATE zones from PAR 1

EVACUATE any additional 1 ZONES projected by dose assessment to exceed the EPA PAG5 (obtain from dose assessment).

Remainder of the 10 mile EPZ to go indoors and listen to the Emergency Broadcasts

3. Include any previously evacuated zones on this PAR. DO NOT change any previously evacuated zones to shelter or go indoors on this PAR.

4. Reassess PARs every 15 minutes until downgrade or recovery phase is entered.

Dose assessment PARs will be initially provided by the Initial Dose Assessor in the Control Room. When the Dose Assessment Team (DAT) becomes operational in the EOF, the DAT will provide this information.

PROC.IWORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 60 Of 73 1903.011 EMERGENCY RESPONSEINOTIFICATIONS CHANGE: 040 Page 6 of 9 ATTACHMENT 6 PROTECTIVE ACTION RECOMMENDATIONS (PARS)

FOR GENERAL EMERGENCY PAR No. 3 Shelter NOTE State and local governments must be notified within 15 minutes of PARs or changes to PARs using Form 1903.01 1-Y.

1. Entry Conditions General Emergency declared AND Known Impediments to Evacuation exist.

OR Offsite Release is a Puff Release (< 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months in duration)

2. Recommend the following Protective Action Recommendation:

Recommend sheltering a 2 mile radius 2-5 miles downwind. Recommend the remainder of the 10-mile EPZ to go indoors and listen to the emergency broadcast for this event. Determine the affected zones for the PAR from the chart given below. Include any zones recommended for evacuation by Dose Assessment. DO NOT change any previously evacuated zones to shelter or go indoors on this PAR.

Determine the affected zones for the PAR from the chart given below.

WincfDiretion Shelter Zones Zones to go indoors 348.75to11.25 GU HIJKLMNOPQRST 11.25to33.75 GRU HIJKLMNOPQST 33.75to56.25 GRU HIJKLMNOPQST 56.25to78.75 GRU HIJKLMNOPQST 78.75to101.25 GNOR HIJKLMPQSTU 1O1.25to123.75 GNOR HIJKLMPQSTU 123.75to146.25 GKNO HIJLMPQRSTU 146.25to168.75 GKNO HIJLMPQRSTU 168.75to191.25 GKN HIJLMOPQRSTU 191.25to213.75 GK HIJ LM NOPQRSTU 213.75to236.25 GK HI] LM NOPQRSTU 236.25to258.75 GHK IJLMNOPQRSTU 258.75to281.25 GHK IJLM NOPQRSTU 281.25to303.75 GHKU IJLMNOPQRST 303.75to326.25 GHU I] KLMNOPQRST 326.25to348.75 GHU Ii KLMNOPQRST

3. PARs must be reassessed every 15 minutes until downgrade or recovery phase is entered.

PROC 1WORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 61 of 73 1903.011 EMERGENCY RESPONSE!NOTIFICATIONS CHANGE: 040 Page 7 of 9 ATTACHMENT 6 PROTECTIVE ACTION RECOMMENDATIONS (PARs)

FOR GENERAL EMERGENCY PAR No. 4 EVACUATE NOTE State and local governments must be notified within 15 minutes of PARs or changes to PARs using Form 1903.011-Y.

1. Entry Conditions General Emergency Declared AND EPA Protective Action Guidelines (PAGs) are projected to be exceeded 5-10 miles downwind.

1 Rem TEDE OR 5 Rem Child Thyroid CDE

2. Recommend the followinci Protective Action Recommendation:

Recommend evacuation of 2 mile radius and 2-10 miles downwind. Recommend that the remainder of the 10-mile EPZ go indoors and listen to the emergency broadcasts for this event. Include any previously evacuated zones with this PAR. ,Q NOT change any previously evacuated zones to shelter or go indoors on this PAR.

Determine the affected zones for the PAR from the chart given below.

Wind Direction (from) Evacuate Zones Zones to go Indoors 348.75to11.25 GUST HIJKLMNOPQR 11.25to33.75 GQRSU F-IIJKLMNOPT 33.75to56.25 GQRSU HIJKLMNOPT 56.25to78.75 GQRSU HI)KLMNOPT 78.75to101.25 GNOPQR HIJKLMSTU 1O1.25to123.75 GNOPQR HIJKLMSTU 123.75to146.25 GKMNOP HIJLQRSTU 146.25to168.75 GKMNOP HIJLQRSTU 168.75to191.25 GKMNP HIJLOQRSTU 191.25 to 213.75 G KLM Ii NO P Q R ST U 213.75to236,25 GJKLM HINOPQRSTU 236.25to258.75 GHIJKLM NOPQRSTU 258.75to281.25 GHIJKL MNOPQRSTU 281.25to303.75 GHIJKU LMNOPQRST 303.75to326.25 GHIJSTU KLMNOPQR 326.25to348,75 GHISTU JKLMNOPQR

3. Reassess PARs every 15 minutes until downgrade or recovery phase is entered.

PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 62 of 73 1903.011 EMERGENCY RESPONSE/NOTIFICATIONS CHANGE: 040 Page 8 of 9 ATTACHMENT 6 PROTECTIVE ACTION RECOMMENDATIONS (PARs)

FOR GENERAL EMERGENCY PAR No. 5 Outside the 10 Mile EPZ NOTE Protective Action Recommendations beyond the 10-mile EPZ shall be coordinated with State and local government officials.

1. Entry Conditions General Emergency declared AND EPA Protective Action Guidelines (PAG5) are projected to be exceeded outside the 10-mile EPZ.

1 Rem TEDE OR 5 Rem Child Thyroid CDE

2. Recommend the following Protective Action Recommendation:

Recommend evacuation of the affected areas. If known impediments to evacuation exist consider sheltering of the affected area.

Use dose assessment personnel to determine the affected sector(s) and downwind distances and then use the chart below to determine the affected area(s) to evacuate.

Affected Sector(s) Evacuate/Shelter Sectors Distance from Site 1 16, 1, 2 10 miles to (Determined by Dose Assessment) 2 1, 2, 3 10 miles to (Determined by Dose Assessment) 3 2, 3, 4 10 miles to (Determined by Dose Assessment) 4 3, 4, 5 10 miles to (Determined by Dose Assessment) 5 4, 5, 6 10 miles to (Determined by Dose Assessment) 6 5, 6, 7 10 miles to (Determined by Dose Assessment) 7 6, 7, 8 10 miles to (Determined by Dose Assessment) 8 7, 8, 9 10 miles to (Determined by Dose Assessment) 9 8, 9, 10 10 miles to (Determined by Dose Assessment) 10 9, 10, 11 10 miles to (Determined by Dose Assessment) 11 10, 11, 12 10 miles to (Determined by Dose Assessment) 12 11, 12, 13 10 miles to (Determined by Dose Assessment) 13 12, 13, 14 10 miles to (Determined by Dose Assessment) 14 13, 14, 15 10 miles to (Determined by Dose Assessment) 15 14, 15, 16 10 miles to (Determined by Dose Assessment) 16 15, 16, 1 10 miles to (Determined by Dose Assessment)

3. Reassess PARs every 15 minutes until downgrade or recovery phase is entered.

PROC/WORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

PAGE: 63 of 73 1903.011 EMERGENCY RESPONSEINOTIFICATIONS CHANGE: 040 Attachment 6 Page 9 of 9 Protective Action Recommendations for General Emerg ency PAR No. 6 Wind Shift PAR Determination NOTE A wind shift is defined as any change in 10-minute averag ed wind direction that affects t offsite protective action zones that are 2-5 or 5-10 miles downwind.

1. Entry Conditions General Emergency Declared AND Previous PAR has been issued AND Actual/Forecasted Wind Shift

2. if the conditions in A through C below are met, THEN revise PARs based on dose assessment results only. Go to Step 4.

A. Plant conditions are well understood çj changes can be reasonably predicted.

B. Radiological releases have a high degree of predictability in terms of isotopic composition, release pathway, and release rate.

C. Meteorological conditions for the projected duration of the release are well understood.

3. if the conditions described in A through C above are g met an actual wind shift occurs forecasted to occur within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , THEN Q, is STEP 1 Wind Direction Transition Area: Evacuate any additional zones projected to exceed the EPA PAGs (obtain from dose assessment).

STEP 2 Final Wind Direction: Revise the current PAR to includ e any downwind zones using the table below. If conditions warrant, evacuation out to 10 miles may be necessary. Refer to PAR 5, as needed, to determine those areas located outside of the 10-mile EPZ.

Wind Direction (from) 2-5 Miles Downwind Zones 5-10 Miles Downwind 348.75to11.25 Zones U ST 11.25 to 33.75 RU QS 33.75to56.25 RU QS 56.25 to 7875 RU QS 78.75to101.25 NOR PQ 101.25 to 123.75 N0R PQ 123.75 to 146.25 K N0 M P 146.25 to 168.75 KN 0 M P 168.75to191.25 KN MP 191.25 to 213.75 K L M_____________________________

213.75 to 236.25 K 3 LM 236.25 to 258.75 H K 3 LM 258.75 to 281.25 H K 3 L 281.25to303.75 HKU 3 303.75 to 326.25 H U 3 ST 326.25 to 348.75 H U ST

4. Reassess PARs every 15 minutes until downgrade or recovery phase is entered.

ES-301 Control Roomlln-Plant Systems Outline Form ES-301 -2 Facility: Arkansas Nuclear One Unit 1 Date of Examination: 08/29/2011 Exam Level: RO SRO-I SRO-U Operating Test No.: 1 Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)

System I JPM Title Type Code*

Funcn a.

A1JPM-RO-A0P37 Respond to Continuous Rod 1 Withdrawal AlL/N/S Reactivity 001 AA1 .05 (RO 4.3ISRO 4.2) Control SRO-U b.

A1JPM-RO-RPSO9 Respond to Annunciator K08-C3, 7 RPS TROUBLE, due to NI power supply failure EN/N/S 015 A2.01 (RO 3.5/SRO 39) Instrumentation SRO-U C.

2 A1JPM-RO-MUPO1 Isolate Letdown, Restore Makeup and Seal Injection Reactor Coolant System 004 A4.06 (RO 3.6/SRO 3.1) Inventory SRO-U Control d.

A1JPM-RO-EOP15 Perform Reactor Trip Immediate 6 Actions with a Loss of DOl AID/S Electrical 058 AA1 .01 (RO 3.4/SRO 3.5) e.

A1JPM-RO-HYDO4 Place Hydrogen Recombiner M- M/S Containment 55B in Operation Integrity 028 A4.01 (RO 4.0/SRO 4.0)

f. 3 A1JPM-RO-PZRO5 Respond to Low RCS Pressure Reactor due to Stuck Open Spray Valve AID/P/S Pressure 010 A3.02 (RO 3.6/SRO 3.5) Control Page 1 of 2

ES-301 Control Roomlln-Plant Systems Outline Form ES-301-2

9. 4 A1JPM-RO-EOPO8 Perform Actions required to correct Heat Removal Degraded Power (EFW System Operation) D/S From Reactor 061 A1.02 (RO 3.3/SRO 3.6) Core (Secondary) h.

8 A1JPM-RO-ICWO2 Perform Switching of ICW Pumps (P-33A/B/C) D/S Plant Service Systems 008 A2.01 (RO 3.3/SRO 3.6)

I. 4 A1JPM-RO-EFWO2 Manual Control of Emergency Feedwater Pump P-7A at the Turbine Heat Removal D/E/R From Reactor 061 A2.05 (RO 3.1/SRO 3.4) Core SRO-U (Secondary)

A1JPM-RO-ED022 lnverter Yl 1 Shutdown with RS1 Supplied from Y-1 1 Alternate AC Source 6 D/E 062 A4.07 (RO 3.1/SRO 3.1) Electrical SRO-U k.

9 A1JPM-RO-GRWO1 Commence Waste Gas Decay Tank Release D/R Reactivity Release 071 .A4.26 (RO 3.1/SRO 3.9)

@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 (4)! 4-6 I 2-3 (2>

(C)ontrol room (D)irect from bank 9 (8) I 8 I 4 (3)

(E)mergency or abnormal in-plant 1 (1) I 1 / 1 (1)

(EN)gineered safety feature - / - I 1 (2)(control room system)

(L)ow-PowerlShutdown 1 (1)I 11>_i (I)

(N)ew or (M)odifled from bank including 1 (A) 2 (3) I 2 I 1 (2)

(P)revious 2 exams 3 (2)! 3 I 2 (1) (randomly selected)

(R)CA 1 (1) / 1 I 1 (2)

(S)imulator Page 2 of 2

Page 1 of 5 JOB PERFORMANCE MEASURE Unit: 1 Rev# 1 Date:

JPM ID: A1JPM-RO-A0P37 System/Duty Area: Emergency and Abnormal Operations Task: Respond to Continuous Rod Withdrawal JTA# ANO1-RO-AOP-OFFNORM-15 KA Value RO 4.3 SRO 4.2 KA

Reference:

001 AA1 .05 Approved For Administration To: RO X SRO X Task Location: Inside CR X Outside CR Both Suggested Testing Environment and Method (Perform or Simulate):

Plant Site: Simulator: Perform Lab:

Position Evaluated: RO: SRO:

Actual Testing Environment: Plant Site Simulator Lab Testing Method: Perform Simulate Approximate Completion Time in Minutes: 2 Minutes Reference(s): 1203.003 Control Rod Malfunction Action Section 9 Continuous Control Rod Motion Examinees Name: KCN:

Evaluators Name:

The Examinees 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 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 JPM ID: A1JPM-RO-A0P37 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner should verify that the examinee has been briefed per the JPM Examination Briefing Sheet EN-TQ-1 14 .5.

JPM INITIAL TASK CONDITIONS:

The reactor is -5% power. ICS is in manual with CRD Diamond panel in AUTO. Control rods are withdrawing continuously.

TASK STANDARD:

Actions taken as required to stop continuous rod motion as prescribed in AOP 1203.003 Section 9Continuous Rod Motion section.

- - This is an ALTERNATE PATH JPM***

TASK PERFORMANCE AIDS:

Copy of 1203.003 Section 9 Simulator Setup: 5% power The following commands active IMF RD269 (Continuous Rod Withdrawal)

IOR Dl_1CC001919 FALSE IOR DOJCCOO19G11 (1 0) FALSE IOR DO_ICCOO19W18 (1 0) TRUE Attach trigger I to desired button on remote control Simulator in FREEZE until examinee says ready to begin task.

Page 3 of 5 JPM ID: A1JPM-RO-A0P37 INITIATING CUE: The CRS/SM directs you to respond to a Continuous Control Rod Withdrawal per 1203.003 Section 9, Simulator in FREEZE until examinee ready to begin task.

C PERFORMANCE CHECKLIST STANDARDS N/A SAT UNSAT 1 Verify the Reactor Demand H/A On panel C03, ICS Reactor Demand H/A station MANUAL. station verified in MANUAL POSITIVE CUE:

Reactor Demand H/A station in MANUAL (White Light On)

2. Verify the Diamond Panel in On the Diamond panel the MAN-AUTO MANUAL button is depressed and the MAN lamp is illuminated.

POSITIVE CUE:

Diamond Panel station in MANUAL (MAN light backlit)

3. Determine of Rod Motion stops On Diamond panel, OUT motion light is checked and on C03 and/or C13, rod POSITIVE CUE: position is monitored and determined OUT motion light is OFF on the that rod motion continues.

Diamond Panel. Group 7 Rods have stopped moving.

NEGATIVE CUE:

OUT motion light is ON on the Diamond Panel. Group 7 Rods continue to travel inward.

4. Check SY lamp energizing and de- On Diamond panel, status of SY lamp is energizing. checked POSITIVE CUE:

SY lamp is off

5. Verify the Diamond Panel in On the Diamond panel MAN lamp is MANUAL. illuminated.

POSITIVE CUE:

Diamond Panel station in MANUAL (MAN light backlit)

CONTINUED

Page 4 of 5 JPM ID: A1JPM-RO-A0P37 INSTRUCTORS CUE For this JPM, the GROUP-AUXIL button is defeated to provide the desired results. The assigned button on the simulator remote control must be depressed as the examinee depresses the GROUP-AUXIL button to provide the expected response (GROUP lamp off and AUXIL lamp on)

6. Set GROUP-AUXIL switch to On the Diamond panel, the GROUP AUXIL. AUXIL button is depressed and the AUXIL lamp is illuminated POSITIVE CUE:

AUXIL lamp is backlit on the GROUP AUXIL switch.

7. Set the SPEED SELECTOR to JOG On the Diamond Panel, the SPEED SELECTOR switch is rotated to the JOG POSITIVE CUE: position.

Speed selector switch is selected to JOG.

8. Place the manual command switch On the Diamond Panel, the manual in the INSERT position for 3 command switch (T-Handle) is placed in seconds AND return the manual insert for 3 seconds and then returned command to neutral to normal POSITIVE CUE:

Manual command switch is placed in INSERT for 3 seconds and returned to neutral.

9. Determine of Rod Motion stops On Diamond panel, OUT motion light is checked and on C03 and/or C13, rod POSITIVE CUE: position is monitored and determined OUT motion light is OFF on the that rod motion continues.

Diamond Panel. Group 7 Rods have stopped moving.

NEGATIVE CUE:

OUT motion light is ON on the Diamond Panel. Group 7 Rods continue to travel inward.

10. Trip the Reactor. On panel C03. the reactor trip Pushbutton has been depressed.

C POSITIVE CUE:

The reactor has been tripped INSTRUCTORS CUE When the reactor is tripped, the instructor will notify the Examinee the JPM is complete.

END

Page 5 of 5 JPM ID: A1JPM-RO-A0P37 INITIAL CONDITIONS:

The reactor is -5% power. ICS is in manual with CRD Diamond panel in AUTO. Control rods are withdrawing continuously.

INITIATING CUE:

The CRSISM directs you to respond to a Continuous Control Rod Withdrawal per 1203.003 Section 9.

ENTERGY OPERATIONS INCORPORATED ARKANSAS NUCLEAR ONE DOCUMENT NO. CHANGE NO.

TITLE: CONTROL ROD DRIVE MALFUNCTION 1203.003 024 ACTION WORK PLAN EXP. DATE NIA SAFETY-RELATED IPTE SET# DYES EINO E2YES NO TEMP MOD LEVEL OF USE E1YES NO CONTINUOUS REFERENCE INFORMATIONAL PROGRAMMATIC EXCLUSION PER EN-LI-100 EYES NO When you see these TRAPS Get these TOOLS Time Pressure Effective Communication Distractionllnterruption Questioning Attitude Multiple Tasks Placekeepi ng Over Confidence Self Check Vague or Interpretive Guidance Peer Check First ShiftiLast Shift Knowledge Peer Pressure Procedures ChangelOff Normal Job Briefing Physical Environment Coaching Mental Stress (Home or Work) Turnover VERIFIED BY DATE TIME FORM TITLE: FORM NO. CHANGE NO.

VERIFICATION COVER SHEET 1000.006A 054

CHANGE 1203M03 CONTROL ROD DRIVE MALFUNCTION ACTION 024 PAGE 42 of 48 SECTION 9 CONTINUOUS CONTROL ROD MOTION Verify the following:

Reactor demand HIA station in MANUAL.

Diamond panel in MANUAL.

A. IF rod motion stops, THEN GO TO ICS Abnormal Operation (1203.001).

2. IF SY lamp is energizing and de-energizing (indicating control rod or group motion),

THEN set SPEED SELECTOR switch to RUN.

A. IF control rod motion stops, THEN contact I&C and SYE for assistance.

3. IF control rod motion continues, THEN perform the following:

A. Verify diamond panel in MANUAL.

B. Set GROUP-AUXIL switch to AUXIL.

C. Set SPEED SELECTOR switch to JOG.

D. Place manual command switch in the INSERT for 3 seconds AND return manual command to neutral.

4. IF control rod motion continues THEN perform the following:

A. Trip reactor.

B. Refer to Emergency Operating Procedure (1202.XXX).

Page 1 of 6 JOB PERFORMANCE MEASURE Unit: 1 Rev # 1 Date:

JPM ID: A1JPM-RO-RPS09 System/Duty Area: Reactor Protection System Task: Respond to Annunciator K08-C3, RPS TROUBLE, due to NI power supply failure JTA# ANO1-RO-AOP-OFFNORM-164 KA Value RO 3.5 SRO 3.9 KA Reference 015 A2.O1 Approved For Administration To: RO X SRO X Task Location: Inside CR: X Outside CR: Both:

Suggested Testing Environment And Method (Perform Or Simulate):

Plant Site: Simulator: Perform Lab:

Position Evaluated: RO: X SRO: X Actual Testing Environment: Simulator: Plant Site: Lab Testing Method: Simulate: Perform:

Approximate Completion Time In Minutes: 20 Minutes Reference(S): 1202.012G, 1203.021, 1105.001 Examinees Name: KCN:

Evaluators Name:

The Examinees 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 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 6 JPM ID: A1JPM-RO-RPSO9 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner should verify that the examinee has been briefed per the JPM Examination Briefing Sheet EN-TQ-114 .5.

JPM INITIAL TASK CONDITIONS:

Plant is operating at 100% power. Annunciator alarm K08-C3 has just been received. N15 indication on C03 is indicating 0%. All other power range indicators are reading normal at -100%.

TASK STANDARD:

Steps 1 and 2 of K08-C3 Annunciator Corrective Action in 1203,012G complete and 1203.021, Section 1 Loss of Neutron Flux Distribution, complete through step 3.2.1.C.

TASK PERFORMANCE AIDS:

1203.012G, K08-C3 Annunciator Corrective Action 1203.021, Loss of Neutron Flux Indication 1105.001 Section 10.0, Placing a RPS Channel in Manual Bypass Simulator Setup:

100% Power

Obtain RPS channel bypass key available

- NOTE The key checkout process is not simulated in the simulator. The evaluator will have the RPS channel bypass key available and will provide it to the examinee when requested.

Create batch files containing to following. (Substitute actual file names where appropriate.)

Batch File #1 Batch File #2 NI-S Power supply failure AA1SpGRPSPWR2.txt IMF Nl236 DOR AO_RPSA49 A

Nl-5 FAILS Lo DMF Nl236 IOR AO_RPSA49 0 A

NI-5 Power supply voltage goes to 0 VDC TRGSET 1 ku2590r7 A

Set Nl-5 PS reset toggle switch to trigger 1 trg 1 Batch File #2 A

Nl-5 RESTORED and PS returns to 600VDC

Initiate batch file #1 to activate failure

Simulator may remain in run

NI-S power supply and NI-S indication will return when the reset button on the power supply is depressed (Batch File #2).

Page 3of6 JPM ID: A1JPM-RO-RPS09 INITIATING CUE: The CRS/SM directs you to respond to Annunciator K08-C3 and perform the required actions.

CRITICAL ELEMENTS (c): 2,9, 11, 17 C j PERFORMANCE CHECKLIST STANDARD N/A SAT EXAMINER NOTE:

This JPM requires the examinee to use more than one procedure. Provide the procedures as they are cued in the JPM.

1. Check nuclear instrumentation on C03 for low On panel C03, checked and readings determined that NI5 has failed to 0% and Nl6-NI8 are all reading normal at -100%.

POSITIVE CUE:

Nl5 reading 0%

2. Transition to 1203.021, Loss of Neutron Flux Stated leaving the ACA to Indication AOP perform the actions of 1203.021, Loss of Neutron Flux Indication, C POSITIVE CUE: Section 1.0.

Referred to 1203.021, Section 1.0, Loss of One or More Power Range NI Channels EXAMINER CUE:

Provide a copy of 1203.021, Loss of Neutron Flux Indication AOP to the examinee

3. Verify the failed instrument does not affect reactor On panel C03, checked reactor power input to ICS power stable and less than 100%.

POSITIVE CUE:

Reactor power stable at <100%

4. Check for normal supply voltage to failed power In the A channel RPS left side range channel at power supply module in cabinet, checked power supply associated RPS cabinet, voltage for NI 5. Identified that the voltage was reading below 600 VDC and in the red zone.

NEGATIVE CUE:

The indicator is in the red zone and below 600VDC.

EVALUATOR NOTE:

At this point, the operator may notify the CRS/SM of his findings.

As the CRS/SM, direct the operator to RESET the NI-5 power supply.

ReferredtoOPll05.001,

5. Place RPS A channel in Channel Bypass lAW section 10.0, Placing a RPS 1105.001, NI and RPS Operating Procedure. Channel in Manual Bypass. j____________

EXAMINER CUE:

Provide a copy of 1105.001, NI and RPS Operating Procedure, Section 10 to the examinee

Page 4 of 6 C PERFORMANCE CHECKLIST STANDARD UN N/A SAT SAT

6. Verify no other RPS Channel (B, C, D) in Manual Bypass.

NOTE: Looked in the RPS cabinet in the Due to the unique design in the Ui simulator, back of the control room and

. all channel indications are located in one RPS verified no manual (or channel) cabinet, bypass lamps are lit or verified that K08-D3 (RPS Channel POSITIVE CUE: Bypass) annunciator is clear.

No manual (or channel) bypass lamps are lit K08-D3 RPS Channel Bypass is NOT in alarm.

7. Verify no EFIC Channel in Maintenance Bypass that does not correspond to the RPS Channel to be On the EFIC cabinets, verified placed in Manual Bypass. that Maintenance lamps are dim (not flashing) for any POSITIVE CUE: channel or verified that K12-F7 Maintenance lamps dim (not flashing) for EFIC (EFIC CH MAINT BYPASS) cabinets or K12-F7 EFIC CH MAINT BYPASS not in annunciator clear.

alarm.

8. Compare Plant Computer point N1I56HI to N1I78HI.

Using PMS, compared Plant POSITIVE CUE: Computer point Nll56Hl to The difference between N1I56HI and N1I78HI is <1%. N1I78HI.

9. Place the SASS Neutron Flux selector switch on C03 in the Y position.

On panel C03, ICS Selector C Switch, Neutron Flux switch POSITIVE CUE:

ICS Selector Switch, Neutron Flux (HS509) is (HS-509) in the Y position.

selected to Y position.

10. Obtain the RPS Manual Bypass key from the SM.

POSITIVE CUE: Obtained the RPS Manual Give the RPS Manual Bypass key to the examinee. Bypass key.

EXAMINER NOTE:

When the exam inee asks for the Manual Bypass key, provide it to the examinee.

11. In the RPS cabinet, place the key switch for the appropriate channel on the selected Rx Trip module to the bypass position. In the RPS cabinet, inserted the key into the key switch in the A POSITIVE CUE: Reactor Trip module and placed A RPS Manual Bypass key switch in BYPASS the switch in the bypass position.

POSITION.

12. Verify the manual bypass lamps on the Rx Trip Verified the Manual Bypass lamp module and the indicating panel go on bright, on the Rx Trip Module went BRIGHT and the Manual Bypass POSITIVE CUE: lamp on the indicating panel for Rx Trip Module Manual Bypass lamps ON BRIGHT. A RPS went BRIGHT. j_________________

EXAMINER NOTE:

The RPS channel will not be tripped.

Page 5 of 6 UN C PERFORMANCE CHECKLIST STANDARD N/A SAT SAT

13. Verify Auxiliary Relay lamps for Man. Bypass to Verified Auxiliary Relay lamps EFIC and Man. Bypass to Ann. are on bright, for Manual Bypass to EFIC Manual Bypass to annunciator POSITIVE CUE:

are on bright.

Manual Bypass to EFIC and Manual Bypass to Annunciator Auxiliary Relay lamps ON BRIGHT.

14. Verify the associated EFIC channel Maintenance On the EFIC cabinet, the Bypass light is flashing.

Maintenance Bypass light for the A EFIC channel is verified to POSITIVE CUE:

be flashing.

A EFIC Maintenance Bypass Light is FLASHING.

15. Verify annunciator RPS CHANNEL BYPASSED (K08-D3) is in alarm.

On K08, verified the annunciator POSITIVE CUE:

is in alarm for RPS CHANNEL K08-D3 is in alarm.

BYPASSED.

NEGATIVE CUE:

K08-D3 is NOT in alarm.

EXAMINER NOTE:

At this point the examinee should transition back to 1203.021.

16. Check power supply ON/OFF switch ON In the A RPS left side cabinet, checked that the power supply ON/OFF switch on the power POSITIVE CUE: supply module labeled Detector NI-S power supply ON/OFF switch In the ON position P.S. NI-S in the ON position.

17. Depress power supply RESET switch to RESET position In the A RPS left side cabinet, depressed the power supply POSITIVE CUE: RESET switch on the power supply module.

Nl-5 power supply RESET switch placed in RESET EXAMINER NOTE

The examinee may check proper NI indication in multiple locations including NI-S upper and lower chamber indications in the A RPS cabinet, NI-5 power indications on C03, or by observing the value of PMS point N1IS.

Any or all of these are acceptable.

In the A RPS left side cabinet.

18. Check that the power supply to NI5 is restored and checked the power supply Nl5 is indicating properly, module for NIS is indicating between S90-610 VDC AND POSITIVE CUE:

NI-S Upper and Lower Chamber NI-S power supply module is indicating 60O VDC AND RPS Module indications read NI-5 Upper and Lower Chamber RPS Module indications read 50% OR 50% OR NI-S indication on C03 is reading 100% QRPIant NI-5 indication on C03 reading 100%

Plant Computer Point N1IS reads 100% Computer Point N1I5 reads 100%

EXAMINER NOTE

When the examinee has verified that NI-S indications have returned to normal, inform the examinee that the JPM is complete.

END

Page 6 of 6 JPM ID: A1JPM-RO-RPSO9 INITIAL CONDITIONS:

Plant is operating at 100% power.

Annunciator alarm K08-C3 has just been received.

N15 indication on C03 is indicating 0%.

All other power range indicators are reading normal at 100%.

INITIATING CUE:

The CRSISM directs you to respond to Annunciator K08-C3 and perform the required actions.

ENTERGY OPERATIONS INCORPORATED ARKANSAS NUCLEAR ONE DOCUMENT NO CHANGE NO.

TITLE: ANNUNCIATOR K08 CORRECTIVE ACTION WORK PLAN EXP. DATE NIA SAFETY-RELATED IPTE SET # DYES LINO LIVES NO TEMP MOD LEVEL OF USE DYES NO CONTINUOUS

[J REFERENCE LI INFORMATIONAL PROGRAMMATIC EXCLUSION PER EN-LI-100 LIVES__NO When you see these TRAPS Get these TOOLS Time Pressure Effective Communication Distractionulnterru ption Questioning Attitude Multiple Tasks Placekeeping Over Confidence Self Check Vague or Interpretive Guidance Peer Check First ShiftlLast Shift Knowledge Peer Pressure Procedures ChangelOff Normal Job Briefing Physical Environment Coaching Mental Stress (Home or Work) Turnover VERIFIED BY DATE I TIME FORM TITLE: FORM NO. CHANGE NO.

VERIFICATION COVER SHEET 1000.006A 054

I

[ 1 PROC.IWORK PLAN NO. PROCEDUREIWORK PLAN TITLE:

PAGE: 24 of 62 1203.012G ANNUNCIATOR K08 CORRECTIVE ACTION CHANGE: 038 Page 1 of 2 Location: Cl3 Device and Setpoint: N/A 1.0 OPERATOR ACTIONS

1. Check nuclear instrumentation on C03 for low readings.

Intermediate Range (NI-3, NI4)

Power Range (NI-5 thru NI-8)

2. IF power range is reading incorrectly or is failed OR intermediate range detector is reading incorrectly or is failed, THEN CO TO Loss of Neutron Flux Indication (1203.021)

3. Have I&C investigate and repair failed detector power supply.

4. IF power range is NOT failed low AND intermediate range channel is NOT failed low, THEN check for RPS channel trip as follows:

A. Observe trip lights at RPS cabinets. Amber light will be on bright for tripped RPS channel.

B. Determine condition that caused channel trip.

C. IF desired, THEN place tripped channel in manual bypass per Placing a RPS Channel in Manual Bypass section of NI & RPS Operating Procedure (1105.001)

D. Initiate steps, as required, to determine reason for channel trip.

E. IF necessary, THEN initiate steps to make repairs.

5. Reference TS 3.3.1 for operability requirements.

6. To clear alarm:

A. Restore high voltage to detector.

B. Place tripped channel in manual bypass per Placing a RES Channel in Manual Bypass section of NI & RPS Operating Procedure (1105.001)

C. Reset tripped channel.

i PROCJWORK PLAN NO PROCEDURE/WORK PLAN TITLE: I PAGE: 25 of 62 j 1203.012G ANNUNCIATOR K08 CORRECTIVE ACTION CHANGE: 038 K08-C3 Page 2 of 2 2.0 PROBABLE CAUSES NOTE This annunciator has reflash capability. If the alarm window is lit solid dre to one cause and another cause actuates, the alarm will go to fast flash with an audible alarm.

Any power range detector (NI-5 thru NI-8) power supply failure

Any intermediate range (NIS or NI-4) detector power supply failure

Any NI-3 or NI-4 auxiliary power supply failure

Any RPS channel (1 thru 4) trip

3.0 REFERENCES

Schematic Diagram Annunciator K08 (E-458, sheet 2)

ENTERGY OPERATIONS INCORPORATED ARKANSAS NUCLEAR ONE TITLE: LOSS OF NEUTRON FLUX INDICATION DOCUMENT NO. CHANGE NO.

1203.021 010 WORK PLAN EXP. DATE TC EXP. DATE N!A NIA SET# SAFETY-RELATED IPTE EYES LINO DYES NO TEMP ALT LEVEL OF USE DYES NO CONTINUOUS C REFERENCE LI INFORMATIONAL PROGRAMMATIC EXCLUSION PER EN-LI-100 DYES__NO When you see these TRAPS Get these TOOLS Ti me Pressure Effective Communication DistractionIlnterruption Questioning Attitude Multiple Tasks Placekeeping Over Confidence Self Check Vague or Interpretive Guidance Peer Check First ShiftlLast Shift Knowledge Peer Pressure Procedures Change/Off Normal Job Briefing Physical Environment Coaching Mental Stress (Home or Work) Turnover VERIFIED BY DATE TIME FORM TITLE: FORM NO. CHANGE NO.

VERIFICATION COVER SHEET 1000.006A 053

PROC.IWORK PLAN NO. PROCEDLJREIWORK PLAN TITLE:

PAGE: 1 of 8 1203.021 LOSS OF NEUTRON FLUX INDICATION CHANGE: 010 TABLE OP CONTENTS SECTION PAGE 1.0 Loss of One or More Power Range NI Channels 2 2.0 Loss of One or More Intermediate Range NI Channels in Mode 2 5 3.0 Loss of One or More Source Range NI Channels in Modes 2 through 5 7

I 1

PROC/WORK PLAN NO. PROCEDURE/WORK PLAN TITLE:

PAGE: 2 of 8 f 1203.021 LOSS OF NEUTRON FLUX INDICATION CHANGE: 010 SECTION 1 LOSS OF ONE OR MORE POWER RANGE NI CHANNELS 1.0 SYMPTOMS 1.1 Power range indication reading incorrectly.

1.2 Annunciator alarm on any of the following:

A. RPS TROUBLE (K08-C3)

B. UNIT MASTER IN TRACK (K07-Al)

C. FEEDWATER IS REACTOR LIMITED (K0/-C2) 1.3 Large neutron error indicated.

2.0 IMMEDIATE ACTION NONE 3.0 FOLLOW-UP ACTIONS 3.1 IF NI failure affects reactor power input to ICS, THEN perform the following:

3.1.1 Place Diamond and Reactor Demand stations in MANUAL and stabilize reactor power at less than 100°c using available nuclear instrumentation.

3.1.2 Verify feedwater stabilizes T-ave while monitoring reactor coolant pressure.

3.2 Check for normal supply voltage (590 to 610 VDC) to failed power range channel(s) at P.S. module in associated RPS cabinet.

3.2.1 IF normal voltage is not indicated, THEN reset power supply for detector(s) as follows:

A. Place affected channel in channel bypass per NI & RPS Operating Procedure (1105.001), Placing a RPS Channel in Manual Bypass section. Refer to TS 3.3.1 Condition A.

B. Check power supply ON/OFF switch ON.

NOTE Resetting power supply to power range detector(s) will cause voltage spikes and neutron power signal spikes, which may trip associated RPS channel.

C. Depress power supply RESET switch to RESET position.

i PROCJWORK PLAN NO.

1203.021 I PROCEDURE/WORK PLAN TITLE:

LOSS OF NEUTRON FLUX INDICATION PAGE: 3 of 8 CHANGE: 010 SECTION 1 LOSS OF ONE OR MORE POWER RANGE NI CHANNELS (Continued)

D. IF power range indication returns to normal, THEN verify all trip bistables are reset per Resetting RPS Channels After Channel Trip section of 1105.001.

1. Return channel bypass to normal per Removing a RPS Channel From Manual Bypass section of 1105.001 and continue plant operations.

NOTE If failed instrument has failed high, the output of the High Auctioneer to ICS will also be high. Failed input to the High Auctioneer can be removed by placing the Power Range Test Module to Test Operate position.

3.3 IF one power range channel has failed, THEN refer to Refer to TS 3.3.1 for guidance on bypassing or operation with an inoperable function.

3.3.1 IF desired to place affected channel in channel bypass, THEN perform NI & RPS Operating Procedure (1105.001),

Placing a RPS Channel in Manual Bypass section. Refer to TS 3.3.1 Condition A.

3.3.2 IF the channel is bypassed, THEN the channel trip module may be reset as follows:

A. Place the Power Range Test Module in TEST OPERATE.

B. For all bistables with Output State and/or Output Memory lamps on bright, perform the following:

Depress and release the Output State switch.

Depress and release the Output Memory Reset switch.

C. Ensure the Building Pressure contact buffer is reset (both Input State lamps are off)

D. Reset the applicable Channel Reactor Trip Module.

[

PROC/WORK PLAN NO, PROCEDURE/WORK PLAN TITLE:

PAGE: 4 of 8 1203.021 LOSS OF NEUTRON FLUX INDICATION CHANGE: 010 SECTION 1 LOSS OF ONE OR MORE POWER RANGE NI CHANNELS (Continued)

E. On all RPS Channels, verify the applicable Subsystem lamps are on dim on the following:

Channel A Reactor Trip module

Channel A Cabinet Indicating Panel

Channel B Reactor Trip module

Channel B Cabinet Indicating Panel

Channel C Reactor Trip module

Channel C Cabinet Indicating Panel

Channel D Reactor Trip module

Channel D Cabinet Indicating Panel 3.4 IF two power range channels have failed, THEN place one of the affected RPS channels in a tripped condition per Placing a channel in a tripped condition section of 1105.001. Refer to TS 3.3.1 Condition B.

3.5 IF all power range channels have failed, AND no onscale indication of neutron flux is available, THEN trip reactor and refer to Reactor Trip (1202.001) 3.6 IF three or more power range channels have failed, AND on-scale indication of neutron flux is available, THEN refer to TS 3.3.1 Conditions C and D.

3.7 Notify Shift Manager to implement Emergency Action Level Classification (1903.010)

PROC.IWORK PLAN NO. I PROCEDUREIWORK PLAN TITLE:

PAGE: 5 of 8 1203.021 LOSS OF NEUTRON FLUX INDICATION CHANGE: 010 SECTION 2 LOSS OF ONE OR MORE INTERMEDIATE RANGE NI CHANNELS IN MODE 2 1 . 0 SYMPTOMS Intermediate range indication reading incorrectly.

1.2 RPS TROUBLE (K08-C3) alarm.

1.3 CRD WITHDRAWAL INHIBITED (K08-A2) alarm.

2.0 IMMEDIATE ACTION NONE 3.0 FOLLOW-UP ACTIONS NOTE If all 4 of the following conditions apply, there is no onscale indication of neutron flux:

Three of four power range instruments are 5% power,

No intermediate range instrument is >l01 -amps,

No source range instrument is <l0 cps,

Reactor Power Wide Range Recorder (NR502) is inoperable.

3.1 IF no on-scale indication of neutron flux is available, THEN trip reactor and refer to Emergency Operating Procedure (1202.XXX Series)

CAUTION Reactor condition must be such that delays which are necessary to perform the following steps will not result in reactor going critical due to xenon, etc.

3.2 Check the failed intermediate range channel(s) power supply voltages at detector P.S. modules in associated RPS cabinets:

Detector power supply: 595 to 605 VDC

Auxiliary power supply: 17 to 23 VEC 3.2.1 IF normal voltage is not indicated, THEN reset power supplies as follows:

A. Check detector power supply toggle switch ON.

B. Check auxiliary power supply toggle switch ON.

I

[

PROC.IWORK PLAN NO. PROCEDUREIWORK PLAN TITLE:

PAGE: 6 of 8 1203.021 LOSS OF NEUTRON FLUX INDICATION CHANGE: 010 SECTION 2 LOSS OF ONE OR MORE INTERMEDIATE RANGE NI CHANNELS IN MODE 2 (Continued)

NOTE Resetting intermediate range channel power supplies will cause voltage spikes and neutron power signal spikes, which may alarm annunciators CRD WITHDRAWAL INHIBITED (K08-A2) and HI SUR ROD HOLD (K08B2)

C. Depress both toggle switches to RESET position.

D. IF intermediate range indication returns to normal, THEN continue plant operations.

3.3 IF only one intermediate range channel is operable, OR 2 of 4 power range instrument channels indicate >55 power, THEN continue plant operations (TS 3.3.10) 3.4 IF all three of the following conditions are met,

Both intermediate range channels have failed,

3 of 4 power range instruments indicate 5,

Reactor Power Wide Range Recorder (NR502) is available, THEN perform the following:

NOTE Plant temperature changes which result in positive reactivity additions are allowed provided the temperature change is accounted for in the Shutdown Margin calculations (TS 3.3.10 Condition A)

Refer to TS 3.3.10.

Immediately suspend operations involving positive reactivity changes.

Initiate a shutdown in order to have all CRD trip breakers open (Mode 3) within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

IF reactor power is >2, THEN perform applicable steps of Power Reduction and Plant Shutdown (1102.016).

Concurrently with reactor shutdown, monitor reactor power using NR-502.

A. WHEN lE-4 log reactor power on NR502 is reached, THEN observe that source range indicators come on scale.

3.5 Notify Shift Manager to implement Emergency Action Level Classification (1903.010)

i PLAN NO.

I PROCEDURE/WORK PLAN TITLE:

PAGE: 7 of 8 f 1203.021 LOSS OF NEUTRON FLUX INDICATION SECTION 3 CHANGE: 010 LOSS OF ONE OR MORE SOURCE RANGE NI CHANNELS IN MODES 2 THROUGH 5 1.0 SYMPTOMS 1.1 Source range indication reading incorrectly.

1.2 CRD WITHDRAWAL INHIBITED (K08-A2) alarm.

2.0 IMMEDIATE ACTION NONE 3.0 FOLLOW-UP ACTIONS NOTE If all 4 of the following conditions apply, there is no on-scale indication of neutron flux:

Three of four power range instruments are 5% power,

No intermediate range instrument is >l0 amps,

No source range instrument is <10 cps,

Reactor Power Wide Range Recorder (NR-502) is inoperable.

3.1 IF no onscale indication of neutron flux is available, THEN trip reactor AND perform Reactor Trip (1202.001) in conjunction with this procedure.

3.2 IF only one source range channel is operable, OR 1 of 2 intermediate range channels indicates >l0b0 amps, THEN continue plant operations (TS 3.3.9) 3.3 IF both source range instruments fail, AND both intermediate range channels indicate lC amps, THEN perform the following:

NOTE Plant temperature changes which result in positive reactivity additions are al towed provided the temperature change is accounted for in the Shutdc*vjn Marqn calculations.

3.3.1 Refer to TS 3.3.9 Condition A.

3.3.2 Immediately suspend operations involving positive reactivity changes.

3.3.3 Immediately initiate a shutdown and insert all control rods.

3.3.4 Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months verify CRD trip breakers open.

rPROCJWORK PLAN NO.

1203.021 PROCEDUREIWORK PLAN TITLE:

LOSS OF NEUTRON FLUX INDICATION SECTION 3 LOSS OF ONE OR MORE SOURCE RANGE NI CHANNELS I PAGE:

CHANGE:

IN MODES 2 THROUGH 5 8 of 8 010 (continued) 3.3.5 Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter, verify reactor >l.5t k/k shur down per Reactivity Balance Calculation (1103.015) 3.4 Notify Shift Manager to implement Emergency Action Level Classification (1903.010)

ENTERGY OPERATIONS INCORPORATED ARKANSAS NUCLEAR ONE TITLE: NI & RPS OPERATING PROCEDURE DOCUMENT NO. CHANGE NO.

WORK PLAN EXP, DATE REACTIVITY IMPACT N!A DYES INPR DNO SAFETY-RELATED IPTE SET # EYES DNO DYES NO TEMP MOD LEVEL OF USE DYES NO CONTINUOUS D REFERENCE D INFORMATIONAL PROGRAMMATIC EXCLUSION PER EN-LI-i 00 DYES__ZNO When you see these TRAPS Get these TOOLS Time Pressure Effective Communication Distraction/Interruption Questioning Attitude Multiple Tasks Placekeeping Overconfidence Self Check Vague or Interpretive Guidance Peer Check First ShiftlLast Shift Knowledge Peer Pressure Procedures ChangelOff Normal Job Briefing Physical Environment Coaching Mental Stress (Home or Work) Turnover VERIFIED BY DATE I TIME FORM TITLE: FORM NO. CHANGE NO.

VERIFICATION COVER SHEET 1000.006A 055

i PROC/WORK PLAN NO.

( PROCEDURE/WORK PLAN TITLE: I PAGE: 14 of 37 1105.001 NI & RPS OPERATING PROCEDURE CHANGE: 025 10.0 Placing a RPS Channel in Manual Bypass r NOTE Only one RPS Channel may be placed in Manual Bypass at a time.

10.1 Determine which RPS Channel is to be placed in Manual Bypass AND verify no other RPS Channel in Manual Bypass.

CAUT ION Placing a RPS Channel in Manual Bypass will remove any non-corresponding EFIC Channel from Maintenance Bypass causing possible EFIC actuation.

ICALSTEfl 10.2 Verify no EFIC Channel in Maintenance Bypass that does NOT correspond to the RPS Channel to be placed in Manual Bypass.

10.3 Place SASS Neutron Flux selector switch (HS509) on C03 in the X or Y position as follows:

10.3.1 Compare Plant Computer point N1I56HI to N1I78HI.

A. IF Plant Computer is NOT available, THEN compare the highest of NI-S and NI-6 to the highest of NI-7 and NI-8 on C03.

10.3.2 IF the difference between the compared values is >15, THEN place the following stations in manual per Transferring ICS Control Stations to HAND section of Integrated Control System (1105.004)

Diamond Panel

Rx Demand H/A station 10.3.3 IF placing RPS Channel A OR B in Manual Bypass, THEN place Neutrcn Flux selector switch (HS509) to the Y position.

10.3.4 IF Placing RPS Channel C OR D in Manual Bypass, THEN place Neutron Flux selector switch (HS-509) to the X position.

10.3.5 IF ICS H/A stations were placed in manual for this step, THEN stations may be returned to auto per ICS Operating Procedure (1105.004), Transferring ICS Control Stations to Auto section.

10.4 Obtain the RPS Manual Bypass key from the Shift Manager.

PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE:

PAGE: 15 of 37 1105.001 NI & RPS OPERATING PROCEDURE CHANGE: 025 10.5 Place key switch on the selected Rx Trip module to the bypass position (rotate key switch clockwise) 10.5.1 Check Manual Bypass lamps go on bright on the following:

Rx Trip Module

Indicating Panel 10.5.2 IF the channel is tripped, THEN check the following:

Protective Subsystem Trip lamps on dim on the following:

Tripped RPS Cabinet Rx Trip module Tripped RPS Cabinet Indicating Panel Protective Subsystem lamps Remaining RPS Cabinets Rx Trip modules Remaining RPS Cabinets Indicating Panel Frotective Subsystem lamps 10.5.3 Auxiliary Relay lamps on bright for the following:

Man. Bypass to EPIC

Man. Bypass to Ann.

10.5.4 Associated EFIC channel Maintenance Bypass light is flashing.

10.5.5 Annunciator RPS CHANNEL BYPASSED (K08-D3) in alarm.

Page 1 of 6 JOB PERFORMANCE MEASURE Unit: 1 Rev# 9 Date:

JPM ID: A1JPM-RO-MUP01 System/Duty Area: Makeup and Purification Task: Isolate Letdown, Restore Makeup and Seal Injection JTA# ANO1-RO-EOP-EMERG-55 KA Value RO 3.6 SRO 3.1 KA

Reference:

004 A4.06 Approved For Administration To: RO X SRO X Task Location: Inside CR X Outside CR Both Suggested Testing Environment and Method (Perform or Simulate):

Plant Site: Simulator: Perform Lab:

Position Evaluated: RO: SRO:

Actual Testing Environment

Plant Site Simulator Lab Testing Method: Perform Simulate Approximate Completion Time in Minutes: 15 Minutes Reference(s): 1202.001 Reactor Trip (step 9) and 1202.012 RT-1 Restore normal Makeup and Seal Injection Examinees Name: KCN:

Evaluators Name:

to be:

The Examinees performance was evaluated against the standards contained in this JPM and is determined Satisfactory: Unsatisfactory:

Performance Checklist Comments:

Start Time Stop Time Total Time

Signed Date

Signature indicates this JPM has been compared to its apphcable procedure by a qualified individual (not the examinee) and is current with that revision.

Page 2 of 6 JPM ID: A1JPM-RO-MUPO1 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall review the Briefing Checklist System Walkthrough portion of OP 1064.023 Attachment 6 with the examinee.

JPM INITIAL TASK CONDITIONS:

The reactor has just tripped

Immediate actions are complete NOTE: The examinee is to check the operating HPI pump supplying normal Makeup and Seal Injection post reactor trip.

The examinee will find that the operating HPI pump is off. The examinee will then have to perform the contingencies of 1202.001 Step 9.

SIMULATOR SETUP: Trip the reactor from any at power IC and then turn off the running (OP HPI) HPI pump.

This is an ALTERNATE PATH JPM TASK STANDARD:

Previously running HPI pump running with seal injection and normal makeup re-established per RT-1.

TASK PERFORMANCE AIDS:

Copy of 1202.001 step 9 (Check OP HPI pump supplying normal Makeup and Seal Injection) and 1202.0 12 RT-1 (Restore normal Makeup and Seal Injection).

Page 3 of 6 JPM ID: A1JPM-RO-MUPO1 INITIATING CUE: The CRS/SM directs you to perform the required actions of 1202001 Reactor Trip procedure starting at step 9.

C PERFORMANCE CHECKLIST STANDARD N/A SAT

1. Check OP HP! pump supplying normal Makeup and Seal Injection.

Identified that the Operating HP!

pump is OFF.

POSITIVE CUE:

OP HP! Pump is OFF.

EXAMINER CUE:

If the Examinee attempts to perform other steps of the Reactor Trip EOP such as floating steps during this JPM, inform the examinee that another operator is performing the task(s).

2. Isolate Letdown Isolated letdown by closing CV-POSITIVE CUE: 1221 (Letdown Coolers Outlet) using handswitch on C16 by CV-1221 green light only ON CV-1214 and CV1216 closing CV-1214 and CV-1216 green lights only ON. using handswitches on C18 (Letdown Cooler Outlet valves).

3. CloseRC Pump Seals Total INJ Flow control valve Placed in HAND by depressing (CV-1207). the white pushbutton on C04 and closed CV-1207, Observed POSITIVE CUE: position indicator reads zero.

CV-1207 indicates closed.

4. Close Pressurizer Level Control valve (CV-1235). Placed in HAND by depressing the white pushbutton on C04 C POSITIVE CUE: and closed CV-1 235. Observed CV-1235 indicates closed, valve demand reads zero.

5. Verify RCP Seal INJ Block CV-1206 closed. On C04, verified CV-1 206 closed.

POSITIVE CUE:

Green light only ON.

NEGATIVE CUE:

Red light ON.

6. Verify RCS Makeup Block valves CV-1233 and CV- On C16 and C18 verified CV 1234 open. 1233 and CV-1234 open.

POSITIVE CUE:

CV-1233 and CV-1234 red lights ON, green lights OFF.

Page 4 of 6 C PERFORMANCE CHECKLIST N/A SAT SAT

7. Verify both HPI RECIRC valves CV-1 300 and 1301 On C16 and C18, verified CV-open or fully open CV-1 235. 1300 and CV-1 301 are open (also acceptable if fully opened POSITIVE CUE: CV-1235 instead).

J CV-1 300 and CV-1 301 red lights ON, green lights OFF.

EXAMINER CUE:

. Inform Examinee to use the OP HPI Pump for restart.

8. Verify P-36B Bus Select MOD Control and P-64B Verified P-36B Bus Select MOD Transfer Switch selected to energized bus (NOTE: this Control and P-64B Transfer step may be N/A if P-36B is not the OP HPI Pump). Switch on C18 selected to POSITIVE CUE: energized bus.

P-36B Bus Select MOD Control and P-64B Transfer Switch selected to energized bus.

9. Start AUX Lube Oil Pump for OP HPI pump (P-64A, Started AUX Lube Oil Pump for B or C). the OP HPI Pump (P64A, B or C) using handswitch on C16 or POSITIVE CUE: C18. Observed red light ON C Red light ON. above handswitch.

NEGATIVE CUE:

Green light ON.

10. Start OP HPI Pump (P36A, B or C). Started OP HPI Pump (P36A, B, or C) using handswitch on C16 POSITIVE CUE: orCl8. Observed red light ON C Red light ON. above handswitch NEGATIVE CUE:

Green light ON.

1 1. Stop AUX Lube Oil Pump for the OP HPI Pump just Stopped AUX Lube Oil Pump for started (P-64A, B or C). the OP HPI Pump (P-64A, B or C) using handswitch on C16 or POSITIVE CUE: C18. Observed green light ON Green light ON. above handswitch.

12. Place CV-1206 in OVRD. Placed CV-1 206 in OVRD using the NORMAL/OVRD pushbutton C POSITIVE CUE: on C04. Observed OVRD light OVRDlightON. ON.

13. Open CV-1206. Opened CV-1206 using handswitch located on C04.

C POSITIVE CUE: Observed red light ON above Red light ON. handswitch.

Page 5 of 6 C PERFORMANCE CHECKLIST STANDARD N/A SAT EXAMINER CUE:

If this JPM is being simulated inform Examinee that RCP Seal Bleedoff temps are < 180°F

14. Open CV-1207 slowly to achieve 30-40 gpm RCP Slowly opened CV-1207 using Seal Total INJ Flow, manual toggle switch on C04.

Established 30-40 gpm seal POSITIVE CUE: injection flow. Observed FLOW CV-1207 indicates open, FLOW light ON. light ON.

C NEGATIVE CUE:

Flow light OFF.

NOTE:

FLOW light should come ON above CV-1 206 OVRD light when seal injection flow is 22 gpm.

15. Place CV-1207 in AUTO. Placed CV-1207 in automatic position by depressing the red POSITIVE CUE: AUTO pushbutton on C04.

Red light ON. Observed red light ON at CV 1207 controller.

16. Adjust Pressurizer Level Control Setpoint to 100. Set CV-1235 (Pressurizer Level Control valve) setpointto 100 C POSITIVE CUE: using the setpoint dial on C04.

CV-1235 setpoint is 100.

17. Place CV-1235 (Pressurizer Level Control valve) Placed CV-1235 in automatic controller in AUTO position. position by depressing the red pushbutton on C04.

AUTO POSITIVE CUE: Observed red light ON at valve Red AUTO light ON. controller.

END

Page 6 of 6 JPM ID: A1JPM-RO-MUPO1 INITIAL CONDITIONS:

The reactor has just tripped.

Immediate actions are complete INITIATING CUE:

The CRS/SM directs you to perform the required actions of 1202.001 Reactor Trip procedure starting at step 9.

ENTERGY OPERATIONS INCORPORATED ARKANSAS NUCLEAR ONE

DOCUMENT NO. CHANGE NO.

TITLE. REACTOR TRIP 1202.001 031 WORK PLAN EXP. DATE NIA SAFETY-RELATED IPTE SET # EYES DNO DYES NO TEMP MOD LEVEL OF USE DYES NO CONTINUOUS D REFERENCE D INFORMATIONAL PROGRAMMATIC EXCLUSION PER EN-LI-100 DYES__NO When you see these TRAPS Get these TOOLS Time Pressure Effective Communication Distractionllnterruption Questioning Attitude Multiple Tasks Placekeeping Over Confidence Self Check Vague or Interpretive Guidance Peer Check First ShiftlLast Shift Knowledge Peer Pressure Procedures ChangelOff Normal Job Briefing Physical Environment Coaching Mental Stress (Home or Work) Turnover VERIFIED BY I DATE TIME FORM TITLE: FORM NO. CHANGE NO.

VERIFICATION COVER SHEET 1000.006A 054

CHANGE 1202.001 REACTOR TRIP 031 PAGE 8 of 25 INSTRUCTIONS CONTINGENCY ACTIONS

8. (Continued) CAUTION The following step will result in load shed of non-vital 4160V buses Al and A2.

NOTE SU2 is considered available ifthe following conditions are met:

. AUTO X-FMR energized from 500KV

. AUTO X-FMR aligned to SU2

. Unit 2 buses aligned to SU2

SU2 V REG 3% reduction disabled b) IF SU2 only is available, THEN energize bus from SU2 (use SYNC switch).

(1) IF non-vital 4160V bus feeder breaker fails to close, THEN attempt to reset breaker anti-pump feature by taking handswitch to PULL-TO-LOCK AND releasing.

9. Check OP HPI pump supplying normal 9, Perform the following:

Makeup and Seal Injection.

A. Isolate Letdown by closing either:

Letdown Coolers Outlet (CV-l221)

OR Letdown Cooler Outlets (CV-12l4 and 1216).

B. Restore normal Makeup and Seal Injection (RT-l).

ENTERGY OPERATIONS INCORPORATED ARKANSAS NUCLEAR ONE DOCUMENT NO. CHANGE NO.

TITLE: REPETITIVE TASKS WORKPLAN EXR DATE N/A SAFETY-RELATED IPTE SET # YES flNO DYES N TEMP MOD LEVEL OF USE DYES NO CONTINUOUS Li REFERENCE Li iNFORMATIONAL PROGRAMMATIC EXCLUSION PER EN-LI-b DYES__NO When you see these TRAPS Get these TOOLS Time Pressure Effective Communication Distraction/Interruption Questioning Attitude Multiple Tasks Placekeeping Over Confidence Self Check Vague or Interpretive Guidance Peer Check First ShiftlLast Shift Knowledge Peer Pressure Procedures Change/Off Normal Job Briefing Physical Environment Coaching Mental Stress (Home or Work) Turnover VERIFIED BY I DATE F TIME FORM TITLE: FORM NO. CHANGE NO.

VERIFICATION COVER SHEET 1000.006A 054

j [HANGE 1202012 I REPETITIVE TASKS I 009 PAGE 1 of 84 Page 1 of 2 RESTORE NORMAL MAKEUP AND SEAL INJECTION

1. Place RC Pump Seals Total INJ Flow (CV-1207) in HAND Jfl close.

2. Place Pressurizer Level Control (CV-1 235) in HAND AND close.

3. Verify RCP Seal INJ Block (CV-1 206) closed.

4. Verify RCS Makeup Blocks open:

CV-1233

CV-1234

5. Verify of the following:

Both HPI Recirc Blocks open:

CV1300 CV-1301

Pressurizer Level Control (CV-1235) fully open.

6. E HPI Pump (P36B) will be used, THEN verify the following selected to energized bus:

P36B Bus Select MOD Control

P64B Transfer Switch

7. Start AUX Lube Oil pump for OP or STBY HPI pump.

8. Start OP or STBY HPI pump.

9. Stop AUX Lube Oil pump.

10. Place RCP Seal INJ Block (CV-I 206) in OVRD AND open.

11. IF RCP Seal Bleedofftemps are 180°F, THEN slowly open RC Pump Seals Total INJ Flow (CV-I 207) until RCP Seals Total INJ Flow is 30 to 40 gpm.

A. Place RC Pump Seals Total NJ Flow (CV-1207) in AUTO.

1202.012 RTI Rev 7-6-10

CHANGE 1202.012 REPETITIVE TASKS 009 PAGE 2 of 84 Page 2 of 2 RESTORE NORMAL MAKEUP AND SEAL INJECTION

12. IF RCP Seal Bleedoff temps are >180°F, THEN slowly open RC Pump Seals Total (NJ Flow (CV-1 207) until RCP Seals Total INJ Flow is 8 to 12 gpm.

A. Record current time B. Maintain 8 to 12 gpm total flow 30 minutes.

C. After 30 minutes, slowly open RC Pump Seals Total (NJ Flow (CV-1207) until 30 to 40 gpm total flow is reached.

1) Place RC Pump Seals Total INJ Flow (CV-1207) in AUTO.

13. WHEN RCP Seals Total INJ Flow light is on (above 22 gpm),

THEN return RCP Seal INJ Block (CV-1206) OVRD pushbutton to normal (OVRD light off).

14. Adjust Pressurizer Level Control Setpoint to 100.

A. IF HPI Recirc Blocks (CV-1300 and CV-1 301) are open, THEN place Pressurizer Level Control (CV-1235) in AUTO.

END 1202.012 RT1 Rev 7-6-10

Page 1 of 5 JOB PERFORMANCE MEASURE Date:

6 Rev #

1 Unit:

JPM ID: A1JPM-RO-EOP15 System/Duty Area: Abnormal and Emergency Operations Task: Perform Reactor Trip Immediate Actions with a Loss of DOl JTA# ANO1-RO-AOP-OFFNORM-326 KAVaIueRO 3.4 SRO 3.5 KA

Reference:

058AA1.O1 Approved For Administration To: RO X SRO X Task Location: Inside CR X Outside CR Both Suggested Testing Environment and Method (Perform or Simulate):

Plant Site: Simulator: Perform Lab:

Position Evaluated: RO: SRO:

Actual Testing Environment: Plant Site Simulator Lab Testing Method: Perform Simulate Approximate Completion Time in Minutes: 3 Minutes Reference(s): 1202.001 Reactor Trip and 1203.036 Loss of 125V DC Section 1 Loss of DOl Examinees Name: KCN:

Evaluators Name:

The Examinees 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 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 JPM ID: A1JPM-RO-EOP15 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

Sheet EN-TQ-1 14 The examiner should verify that the examinee has been briefed per the JPM Examination Briefing .5.

JPM INITIAL TASK CONDITIONS:

The reactor has just tripped from 100% power and you are the only control board operator present.

TASK STANDARD:

Alternate Loss of DOl recognized and Dli power swapped to emergency source. This is a faulted JPM.

Success Path used due to loss of DO1.

TASK PERFORMANCE AIDS:

1202.001 Reactor Trip immediate actions and 1203.036 Loss of 125V DC Section 1 Loss of DOl.

SUGGESTED SIMULATOR SETUP:

DOl. Freeze the Have the simulator at power operations (>55% power) and then insert malfunction for a Loss of simulator as soon as the reactor trips. Go to run when the examinee is ready to take his first action.

Page 3 of 5 JPM ID: Al JPM-RO-EOP1 5 r Trip.

INITIATING CUE The CRS/SM directs you to perform immediate actions for a Reacto UN STANDARD N/A SAT C PERFORMANCE CHECKLIST SAT

1. Manually trip the reactor. Verify all rods inserted and reactor power dropping. Depressed reactor trip pushbutton on panel C03 and verified rods POSITIVE CUE: inserted/power dropping.

All rod bottom lights ON for groups 1-7, reactor power lowering.

2. Manually trip the Turbine. Verify Turbine throttle and governor valves closed. Depressed turbine trip pushbutton on COl and identified that the C FAULTED CUE: turbine did not trip due to a loss of Governor and throttle valves are all open. Turbine trip DOl.

solenoid power available light is off. Breaker position indications on left side of ClO are off.

INSTRUCTOR NOTE:

ore, 1203.036 may be Transferring Dli to the emergency power supply is a follow-up action of 1203.036. Theref in the role of CRS to direct the examinee to referenced for this step. When the examinee identifies the loss of DOl act transfer Dii to its emergency power supply.

At ClO, transferred 125 VDC

3. Transfer Dl 1 to its emergency power supply. panel Dl 1 to its emergency supply by momentarily placing C 125 VDC Panel Dii Power POSITIVE CUE: Supply Select switch to EMERG Dl 1 is powered from D02. position. (Rotate Switch in the Clockwise direction)

4. If SG pressure is <900 psig, then actuate MSLI for If SC pressure dropped below affected SC(s) AND actuate EFW. 900 psig, actuated MSLI for affected SC(s) and EFW on the POSITIVE CUE: remote matrices on C09, SC pressures at 1000 psig.

Page 4 of 5 JPM ID: A1JPM-RO-EOP15 STANDARD N/A SAT C PERFORMANCE CHECKLIST at 600 psig SG pressure NOTE: Step 4 above is NOT a critical step because EFIC will automatically actuate MSLI/EFW will trip and terminate the which will terminate the overcooling event. IF the examinee transfers Dli to D02 the turbine overcooling event in step 3 of this JPM.

5. Check adequate sub cooling margin. On panel C04 or on ICCMDS display on panel C19, POSITIVE CUE: observed/verified that SCM is SCM at 65°F and rising, adequate (>30°F).

Note: The examiner should cue the JPM is over after SCM is verified adequate.

END

Page 5 of 5 JPM ID: A1JPM-RO--EOP15 INITIAL CONDITIONS:

The reactor has just tripped from 100% power and you are the only control board operator present.

INITIATING CUE:

The CRSISM directs you to perform immediate actions for a Reactor Trip.

ENTERGY OPERATIONS INCORPORATED ARKANSAS NUCLEAR ONE TITLE: LOSS OF 125V DC DOCUMENT NO. CHANGE NO.

WORK PLAN EXP. DATE REACTIVITY IMPACT N!A DYES DINPR NO SAFETY-RELATED IPTE SET # DYES ONO DYES ØNO TEMP MOD LEVEL OF USE DYES NO CONTINUOUS U REFERENCE U INFORMATIONAL PROGRAMMATIC EXCLUSION PER EN-LI-i 00 DYES__NO When you see these TRAPS Get these TOOLS Time Pressure Effective Communication Distractionhl nterru ption Questioning Attitude Multiple Tasks Placekeeping Overconfidence Self Check Vague or Interpretive Guidance Peer Check First ShiftlLast Shift Knowledge Peer Pressure Procedures ChangelOff Normal Job Briefing Physical Environment Coaching Mental Stress (Home or Work) Turnover VERIFIED BY I DATE I TIME FORM TITLE: FORM NO. CHANGE NO.

VERIFICATION COVER SHEET 1000.006A 055

I PROC.IWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: I PAGE: 2 of 44 1203.036 LOSS OF 125V DC CHANGE: 010 SECTION 1 LOSS OF DOl 1 . C SYMPTOMS 1.1 Low DC voltage alarms:

(alarms inoperable if generator output breakers open)

001 UNDERNOLTAGE (MCI-Ar

011 LOSS OF VOLTAGE (K0lB7)

RAI LOSS OP VOLTAGE. (K01-CG

DOl TROUBLE (N01D7)

Hi DC CONTROL POWER OFF (K02-B4)

Al DC CONTROL POWEP OFF (K02C6

A3 DC CONTROL POWER OFF (K02-D6)

SU I L.O. RELAY DC FAILURE (K02DI)

SC 2 L.O. PSELAY DC FAILURE (K02E3)

GENERATOR L.O. RELAY DC FAILURE (K04-D8)

TURBINE L .0. RELAY DC FAILURE K04B5)

EOS SYSTEM TROUBLE (K04-C5) 1.2 Loss of breaker position indicator lights for plant buses on left side of C1j.

1.3 Trip Solenoid Power Available light on COl NOT lit.

2 0. IMMEDIATE ACTION NONE

3. 0 FOLLOWUP ACTIONS 3.1 At Cii, transfer Ill to EMERG SUPPLY D02.

1.2 ZF reactor trips, CF-EN cerforn the foliccino:

3.2.1 IF SO pressure is <900 psig, THEN perform the following on BOtH SOs:

Actuate NELl

Actuate EFW 3.2.2 Perform Ri6.

3.2.3 Perform Emergency Operating .Procedures (l202.XXX) in conjunction with this procedure,

i PROC IWORK PLAN NO.

I PROCEDUREIWORK PLAN TITLE: PAGE: 3 of 44 1203.036 LOSS OF 125V DC CHANGE: 010 SECTION 1 -- LOSS OF DOl (continued; 3.3 Notify SM to implement Emergency Action Level Classification (1903.010)

IF transfer of DII is NOT successful, THEN attempt local transfer of DII to 502, while continuing.

3.5 IF reactor is NOT tripped, THEN GO TO step 7.0.

3.6 IF transfer of DII is successful, THEN GO TO step 4.0.

IF transfer of DII is NOT successful, THEN perform the following:

3.7.1 Dispatch an operator to perform Attachment I, while continuing.

3.7.2 IF Generator Output bkrs (5114 and 5118) do NOT trip, THEN GO TO step 2.0.

3.7.3 IF Generator Output bkrs (5114 and 5118) trip, THEN GO TO step 6.0.

0 IF transrer of 011 is successful, THEN perform the following:

4.1 IF HEW actuates, THEN throttle P7B EFW Isolations as necessary to limit flow.

SGA SGB 072670 EFW P7H ISOL 072626 Perform RT5.

4.2 Verify Condenser Vacuum Pump (C-5A OR C-5B) running.

4.3 IF Spent Fuel Cooling is lost, THEN perform .0 Spent Fuel Poo.l Emergencies (1203. 050) with this rrooedurs. .INPC lEE 102 Eec 4 IHEN GO TO step 7.0 for restoration.

i I I 1

PROC.IWORK PLAN NO. PROCEDUREIWORK PLAN TITLE:

PAGE: 4 of 44 1203.036 LOSS OF 125V DC CHANGE: 010 SECTION 1 LOSS OF DOl (continued) 5.0 IF transfer of DII is NOT successful AND Generator Output Breakers do NOT trip, THEN perform the following:

5.1 At 010, transfer A2 and H2 to an available EU Xfmr as follows:

NOTE

EU 1 is preferred.

EU 2 Load Shedding is inoperable during a loss of 001.

5.1.1 IF EU 1 is available, THEN GO TO step 5.1.3.

5.1.2 IF ONLY EU 2 is available, THEN perform the following:

Notify operator performing Attachment 1 that breaker operations from Control Room are commencing.

At 019, trip VCH1B Power Supply breaker (A208)

At 002, trip Condensate Pump P2B.

At 012, trip Circ Water Pumps P-3B AND P-3D.

At 012, trip Heater Drain Pump P-8B.

Refer to EU 2 Transformer Loading Restrictions, Attachment E of Electrical System Operations (1107.001)

Notify Unit 2 of intent to use EU 2.

PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: I PAGE: 5 of 44 1203.036 LOSS OF 125V DC CHANGE: 010 SECTION 1 -- LOSS OF DOl (continued) 5.1.3 Turn ON SYNC switch for desired SU Xfmr feeder to A2, either:

Startup Xfmr #1 Feed to A2 (A2l3)

OR

Startup Xfmr #2 Feed to A2 (A211)

Verify synchroscope at 12 oclock.

CAUT ION

High circulating currents may trip bus lockout relay if both feeder breakers remain closed.

SYNC switch must be off to verify feeder breaker opens.

With SYNC switch on, red light for feeder breaker position goes out even if breaker does not trip.

5.1.5 Perform the following:

A. Close desired SU Xfmr feeder to A2 AND allow control switch to return to NORMALAFTERCLOSE position.

B. Turn OFF SYNC switch.

C. Verify Unit Aux Xfmr Feed to A2 (A2l2) trips.

1. IF A2l2 does NOT immediately open, THEN trip it.

5.1.6 Turn ON SYNC switch for desired SD Xfmr feeder to H2, either:

Startup Xfmr #1 Feed to H2 (H-25)

OR

Startup Xfmr #2 Feed to P2 (H23)

Verify synchroscope at 12 oclock.

PROCJWORK PLAN NO.

I PROCEDUREIWORK PLAN TITLE:

PAGE: 6 of 44 1203.036 LOSS OF 125V DC CHANGE: 010 SECTION 1 -- LOSS OF 001 (continued)

CAUTION

High circuiating currents may trip bus lockout relay if both feeder breakers remain closed.

SYNC switch must be off to verify feeder breaker opens.

With SYNC switch on, red light for feeder breaker position goes out even if breaker does NOT trip.

5.1.8 Perform the following:

A. Close desired SU Xfmr feeder to H2 AND allow control switch to return to NORMALAFTERCLOSE position.

B. Turn OFF SYNC switch.

C. Verify Unit Aux Xfmr Feed to H2 (H24) trips.

1. iF H24 does NOT immediately open, THEN trip it.

5.2 Manually transfer Al to available SD Xfmr as follows.

CAUTION Operation with the turbine tripped and generator motoring for extended period will result in turbine blade overheating.

5.2.1 Turn ON SYNC switch for desired SD Xfmr feeder to Al, either:

Startup Xfmr #1 Feed to Al (All3)

OR

Startup Xfmr #2 Feed to Al (Alll)

Verify RUNNING voltage and INCOMING voltage match.

Verify synchroscope at 12 oclock position.

-U 0

C)

<0> H-NJ 0 CDONJ oo 01 (51 H C) Nt 01 LJ H C)

H-CO 0 -U NJ (51 NJ H 0 HNJ a) xH-

>NJ z CD ONJ Z HO OH- 0 CDOO 0 0 oH 1(51> C) 01 0 CD 0 H lxix o IHINJ H H H H H NJ CD H- 0 NJ N) x(0 x xix C) 1010 -ZNJ - C) H<H H NJ <N Di C) NJ NJ H o 1 01 C)

COO OOCD NJ NJO (5 HNJ ONJ 000 ONJO 0 H- 0<

O HHH C) <C o

-CO H-NJ H CDOH- 0 ) (DO OH 001 H 000 H- CO 1 rn 0110 H (DO NJ l> ct) () DiO HO xx C) HH- xx HO Di H HO <C NJ ONJ C) 0 CD (<101 HO H H (DO H-C OH H )

OH HI

<00 HOC) - CD ((H CD ((NJ H- HO o H- O H- 0 0 NJ H- 0 0 NJ HO CD HO o < 0 ONJ (DO H >

H- H NJ H CO HO H 010 OH 0 CD o<o Z OH- H O H- H NJ H >0 CD 00 NJH HNJC 1H 00 0 O NJ DC -0< 0 O <0 (DO H H H CD <C H- 0 CD Cl) r HH <OCDH- H H- H <0 H m 0 0 (51 C) (0 0 CD H H 0 H CD OH H HO OH Di (0NJ H CJH (CD H 0 0 NJ <OH H CDNJ o (DC 0 -CC 0 H-In cn CD(0O 1101 NJ OH- (DO Di HNJ OOH 00

Ci CON HO Hi 0 OH- DiCDH NJ(D (I HN HNJ HO. HH 011.3 00 o (DO H 1

FD 1 H

H -<0 H C) 0fr3 C) H-NJ OH C 0 CD NJ01 <0 H 0 C)NJ H NJZ 0 O -O 0 00 NJH O NJNJ C NJ Ci CD H

-0CC) O

C CD O CD C H H- 0 0

<0(0 NJ(j) >(D 0 0 H (1)0 0) NJH CD NJ NJ 00 0 CD H-O H -NJ H NJH (<C HO H NJ H 01<0 H C NJ CNJ 0 00 0 H 0 NJ ONJ Cl 0 Di O H H- (D NJ0 H ). >

NJH- 0 H- <0 0 0 NJ lCD C) HH <C 0 NIH ci NJH hi 00 01 00 NJ 0 CD NJ NJ NJ 0 0 CD 0 H NJ 0< 0 ON) 0 01 CX) 0 ci o 0 0 o (i o 0 H C) 0 H H X >

NJ o O CD >0 01 o 00 H cC Z m

((NJ o 0 <0 0 S NJ NJ <1< rn H O H H- NJ H H H O HC) O CD 0 001 o NJ

o -

PROC.IWORK PLAN NO. PROCEDUREIWORK PLAN TITLE:

PAGE: 8 of 44 1203.036 LOSS OF 125V DC CHANGE: 010 SECTION 1 - LOSS OF DOl continued) 6.6 li transfer of DII is NOT successful AND Generator Oucout Breakers Trip, THEN perform the foilowinc:

6.1 Check that 002 starts and energizes A4.

6.2 Trip running RCPs.

NOTE Due to loss of inverters supplying RSI and RS3, two ESAS Anaiog Channels trip and cause all even Digital Channels to trip. Odd Channels cannot trip, due to loss of power.

6.3 Override inadvertent ES actuation as follows:

6.3.1 Check RCS press >1590 psig and RB press c4 psig (18.7 psia) to verify ES actuation is inadvertent.

6. 3 2

. Override each actuated component using VAN pushbutton.

A. Stop RB Spray pump (P35B).

B. Stop LPI pump (P34B)

C. Place overridden components in desired position.

6.4 Place all SOP Seal Bleed off (Alternate Bath to Quench Tank) handsuitches in CLOSE (SV1270, 1271, 1272, & 1273) 6.5 At 010, verify MCC B55 & 56 powered from HO.

6.6 Control RCS makeup as follows:

6.6.1 IF P36C OR P36B from A4 was the OP PSI pump, THEN perform the following:

A. Override AND open RCS Makeup Block (CV1234)

B. Slowly o*pen PER Level Control (CVl235)

I. Ad :s: seocoon to lii PHI mpa;e on THEN override AND operate HPI valves (C71228, I22, 1284,

& 1285) as necessary to maintain PER level.

[ I PROC 1WORK PLAN NO. PROCEDUREIWORK PLAN TITLE:

PAGE: 9 f 44 1203.036 LOSS OF 125V DC CHANGE: 010 SECTION 1 LOSS OF DOl (continued) 6.2 Verif* a Service Later Surn 545 CR P4C( restarts on A4.

6.8 Verify EEL 6tA oPerating with SC ievels rising cc Natural Circulation setpoint (312) j NOTE

. SC I is preferred.

SC 2 Load Shedding is inoperable during a loss of P01.

[_

6.9 At ClO, transfer A2 and P2 to an available SC Xfmr as follows:

6.9.2 IF SC I is available, THEN GO TO step 6.9.3.

6.9.2 IF ONLY SU 2 is available, tHEN perform the foliowing:

Notify operator performing Attachment 1 that breaker operations from Control Room are commencing.

At C19, trip VCHIB Power Supply breaker (A208)

At v, trio ConOensate ovimp

At C12, trip Circ Water Pumps P3B AND P-3D.

At 712, trip Heater Drain Pump 885.

Refer to SC 2 Transformer Loading Restrictions, Attachment E of Electrical System Operations (1107.001)

Notify Unit 2 of intent to use SC 2 Xfmr.

PROC.IWORK PLAN NO. PROC EDUREIWORK PLAN TITLE:

PAGE: 10 of 44 1203.036 LOSS OF 125V DC CHANGE: 010 SECTION 2 LOSS OF 001 continued 6.9.3 Turn ON SYNC switch for desired SC Xfmr feeder to A2, either:

Startup Xfmr 2 Feed to A2 (0213)

OR

Startup Xfmr #2 Feed to A2 (0211) 6.9.4 Verify tripped Coit Aux Xfmr Feed to A2 (A212).

6.9.5 Close desired 513 Xfmr feeder to A2, either:

Startup Xfmr #1 Feed to A2 (A2l3)

OR

Startup Xfmr #2 Feed to A2 (A2l1) 6.9.6 Turn OFF SYNC switch.

6.9.7 Restart ICW Pumps (FatE on nonnucear _oop, 2a3C on nuclear 6.9.8 Verify Condenser Vacuum Ruing (13-50 OR C-53) running.

6.9.9 Turn ON SYNC switch for desired SC Xfmr feeder to H2, either:

Startup Xfmr #1 Peed to H2 25; OR

Startup Xfmr #2 Feeo to H2 (H23) 6.9.10 Verify tripped Unit Aux Xfmr Feed to H2 (H24) 6.9.12 Close desired SC Xfmr feeder to H2.

6.9.12 Turn OFF SYNC switch.

6.9.13 WHEN RCP services are available, THEN refer to Reactor Coolant Pump and Notor Emergency (1203.031), Sinultaneous Loss of Seal Inlection and Seal Cooling Flow section to start RCPs (P32B and P32D)

NOTE will energize the odd ESAS digotal channels, causing an inadvertent actuation of ES unless disabled.

6.10 Check RCS press >1590 pslc and RB press <4 psig (18.7 gala) to verify ES actuation is NOT rieeoed.

6.10.1 IF ES is NOT needed, THEN olsabie odd P505 digital channels by opening breaker for ESAS Digital Subsystem No. 1 (8.514)

PROC.IWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 11 of 44 1203.036 LOSS OF 125V DC CHANGE: 010 SECTION 1 - LOSS OF DOl (continued) 6.11 WHEN loads have been stripped from Al and A3, THEN direct operator to manually close desired SU Xfmr feeder to Al, either:

Startup Xfmr Feed to Al A113)

OR

Startup Xfmr 42 Feed to Al (AIll) 6.12 Reset tripped ES Analog Subsystem Trip Bistables:

Analog CM 1 (CBS)

Analog Cl-I 2 (C89)

Analog OH 3 (C90) 6.13 Restore power to ES Digifal Subsystem No, 1 by closing breaker RS14.

6.14 Reset tripped ES Digital Subsystems using reset PB(s) on 004.

6.15 Direct operator to manually start a SW pump on AS:

Service Water Pump (P4A) (A302)

OR

Service Water Pump (P45) (ASOS; 6.16 IF P36C is ES SF1 pump, THEN restore RCP seal Injection and PZR level control by aligning P36C as the OP HPI pump per Makeup Purification System Operation (1104.002).

6.17 IF Spent Fuel Cooling is lost, THEN perform Unit 1 Spent Fuel Pool Emergencies (1203.050) in conjunction with this procedure. (INFO IER 112 Rec 4) 6.r vu-itt pant 0000101005 staou-oze, THEN GO TO step 7.0 for restoration.

0,7 Sestoratlon ceteroone :a:so too oss Ot 2:01 an-i zn:tzate oorre:t:ce action.

7.2 Refer tc. Battery and 125W DC Distribution (1107.004) to determin.e eguipment that has lost power.

7.3 Refer to Emergency Feedwater Initiation and Control (1105.005),

Operability section for determining operability of EFW system.

PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: PAGE: 12 of 44]

1203.036 LOSS OF 125V DC CHANGE: 010 SECTION 1 LOSS OF 001 (continued)

CAUTION ElI power supply transfer results in a momentary loss of power to the distribution nanel.

operatrng, waZt trro.

IF operating, condenser vacuum pump C-LA will trip.

heEL power os restored to Dli, THEN transfer Dll to NORMAL SUPPLY.

7.5 WHEN power is restored to DOl, THEN return the following inverters to normal operation per Inverter and 120V Vital AC Distribution (1107.003).

Place Inverter Yll CR Y15 in service supplying RS

Place inverter Yl3 OP. Y15 in service supplying R53 Verify LOS Channel A (SY6650) reset.

7.6.1 Verify LOS SYSTEM TROUBLE (1<04CD) clear.

Page 1 of 5 JOB PERFORMANCE MEASURE Date:

1 Unit: 1 Rev#

TUOI NUMBER: A1JPM-RO-HYDO4 System/Duty Area: Hydrogen Recombiner and Purge Control System Task: Place Hydrogen Recombiner M55B in Operation JA# ANO1-RO-RBH2-NORM--1 KA Value RO 4.0 SRO 4.0 KA Reference 028 A4.01 Approved For Administration To: RO SRO Task Location: Inside CR: Outside CR: El Both: El Suggested Testing Environment And Method (Perform Or Simulate #):

Plant Site: Simulator#: Perform Lab:

Position Evaluated: RO: SRO:

Actual Testing Environment: Simulator #: Plant Site: Lab Testing Method: Simulate: Perform:

Approximate Completion Time In Minutes: 15 Minutes Reference(s): 1104031, Chg. 024 Examinees Name: KCN:

Evaluators Name:

The Examinees 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 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 TUOI NUMBER: A1JPM-RO-HYDO4 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall review the Briefing Checklist System Walkthrough portion of OP 1064.023 Attachment 6 with the examinee.

JPM INITIAL TASK CONDITIONS:

A LOCA has occurred. Containment hydrogen concentration is 2.1%. Both hydrogen recombiners are shutdown.

Containment pressure is 20.0 psia. Pre-LOCA containment temperature was 92°F.

TASK STANDARD:

Hydrogen recombiner M55B in operation at power setting of 53.0 KW to 55.0 KW on Jl-1001 TASK PERFORMANCE AIDS:

1104.031, section 8.0 and Att. B

Page 3 of 5 TUOI NUMBER: A1JPM-RO-HYDO4 INITIATING CUE: The CRS/SM directs you to place both hydrogen recombiners (M55A/B) in standby and then place M55B in operation.

NOTE: Your task is complete when the power you have determined for recombiner operation is achieved.

CRITICAL ELEMENTS (C): 2, 7, 8 C PERFORMANCE CHECKLIST STANDARD N/A SAT

1. Verify power adjust potentiometers are set at zero. Verified power adjust potentiometers set to zero on POSITIVE CUE: C26 (if not already at zero used Power adjust potentiometers for M55AIB are set at zero knurled knob on power adjust on C26. potentiometers on C26 and turned to the left and set at zero using HS-7472 and HS-7473).

2. Turn hydrogen recombiners M55A and M55B on. Turned on hydrogen recombiners M55A and M55B POSITIVE CUE: using HS-7470 and HS-7471 on c M55A/B red lights ON. C26.

NEGATIVE CUE:

M55A/B green lights ON.

3. Select thermocouple #1, 2 or 3 to input to Thermocouple #1, 2 or 3 recombiner temperature indicators TI-2300 and TI- selected to input to TI-2300 and 2301. TI-2301 using handswitches HS

4. 7474 and H S-7475 on C26.

POSITIVE CUE:

Thermocouple #1, 2 or 3 selected as desired to input to TI-2300 and TI-2301.

5. Increase power to 5 KW. Slowly adjusted potentiometers clockwise until power on JI-1 000 POSITIVE CUE: and JI-l 001 on C26 indicated 5 Power on JI-1 000 and JI-lOOl indicates 5KW. KW.

INSTRUCTOR NOTE:

Inform examinee that ten minutes have elapsed after one minute at 10 1KW.

6. Slowly increase power to 10 KW and record initial Increased power to 10 KW time. using power adjust potentiometers on C26.

POSITIVE CUE: Recorded time 10 1KW was Power is at 10 1KW on JI-1 000 and JI-lOOl. achieved.

INSTRUCTOR NOTE:

Inform examinee that taking data every 30 minutes on Attachment E will be simulated.

7. Slowly increase power to 20 1KW on M55B and hold Increased power on M55B to for 5 minutes. 20 KW using power adjust potentiometer on C26.

POSITIVE CUE:

Power at 20 KWon JI-lOOl.

INSTRUCTOR NOTE:

Inform examinee that five minutes have elapsed after one minute at 20 KW.

Page 4 of 5 TUOI NUMBER: A1JPM-RO-HYDO4 C PERFORMANCE CHECKLIST STANDARD N/A SAT

8. Determine power required from Attachment B Determined Recombiner power c based on containment pressure (20.0 psia and to be from 53.0 to 55.0 KW 92°F Pre-LOCA containment temperature). using Attachment B of 1104.031.

9. Slowly increase power to 53.0-55.0 KW range. Power increased to 53.0 to 55.0 KW range using power adjust POSITIVE CUE: potentiometer on C26.

Hydrogen concentration dropping on QI-7459 and C M55B maintaining power at determined value.

NEGATIVE CUE:

Hydrogen concentration rising or steady on QI-7459.

END

Page 5 of 5 TUQI NUMBER: A1JPM-RO-HYDO4 INITIAL CONDITIONS:

A LOCA has occurred.

Containment hydrogen concentration is 2.1%.

Both hydrogen recombiners are shutdown.

Containment pressure is 20.0 psia.

Pre-LOCA containment temperature was 92° F.

INITIATING CUE:

The CRSISM directs you to place both hydrogen recombiners (M55AIB) in standby and then place M55B in operation.

Note: Your task is complete when the power you have determined for recombiner operation is achieved.

Page 1 of 5 JOB PERFORMANCE MEASURE Unit: 1 Rev # 3 Date:

JPM ID: A1JPM-RO-PZRO5 System/Duty Area: PRESSURIZER Task: Respond to Low RCS Pressure due to Stuck Open Spray Valve JTA# ANO1-RO-AOP-OFFMORM-1 15 KA Value RO 3.6 SRO 3.5 KA

Reference:

010 A3.02 Approved For Administration To: RO X SRO X Task Location: Inside CR X Outside CR Both Suggested Testing Environment and Method (Perform or Simulate):

Plant Site: Simulator: Perform Lab:

Position Evaluated: RO: SRO:

Actual Testing Environment: Plant Site Simulator Lab Testing Method: Perform Simulate Approximate Completion Time in Minutes: 15 Minutes Reference(s): 1203.012H Annunciator K09 corrective Action K09-C1; 1203.015 Pressurizer systems Failure Examinees Name: KCN:

Evaluators Name:

The Examinees 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 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 JPM ID: A1JPM-RO-PZRO5 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall review the Briefing Checklist System Walkthrough portion of OP 1064023 Attachment 6 with the examinee.

JPM INITIAL TASK CONDITIONS:

The Reactor is at -38% power with 3 RCPs running, D RCP is secured.

SUGGESTED SIMULATOR SETUP: Have the Spray valve stuck open CV-1 008 and have the spray valve isolation valve CV-1009 failed open. Spray valve should be open slightly and have RCS pressure going down slowly with all PZR heaters on. RCS pressure Hi/Lo alarm, K09-C1 should come in shortly after placing the simulator in RUN.

SETUP NOTE: REMOVE ANY CAUTION CARDS THAT MAY EXIST ON RCP OIL PUMP HANDSWITCHES PRIOR TO STARTING JPM.

Simulator should remain in FREEZE until candidate is ready. Then start simulator THIS IS AN ALTERNATE PATH JPM TASK STANDARD:

Trip Reactor and Stop C RCP to stop RCS pressure decrease. Tripping the reactor must be performed prior to reaching the RPS low pressure set point. Stopping C RCP should be done prior to reaching ESAS trip set point of 1590 psig.

TASK PERFORMANCE AIDS:

Copy of 1203.015 section 6 Pressurizer Spray Valve (CV-1008) and 1203.012H Annunciator K09 corrective action for K09-C1 window RCS Pressure Hi/La

Page 3 of 5 JPM ID: A1JPM-RO-PZRO5 INITIATING CUE: The CRS/SM directs you to respond to new Annunciator alarms.

CRITICAL ELEMENTS (C): 9, 14 C PERFORMANCE CHECKLIST STANDARD N/A SAT EXAMINER NOTE:

This JPM requires the examinee to use more than one procedure. Provide the procedures as they are cued in the JPM.

Annunciator K09-C1 will alarm shortly after placing the simulator in RUN.

When asked, provide applicant the ACA procedure ONLY.

1 Confirm alarm by comparing RC pressure indications Identified that all RCS pressure on C04. indicators are going down.

POSITIVE CUE:

All RCS pressure indicators are going down.

2. Refer to COLR figures for RC Pressure Limits. COLR limits may not be referenced during Press Transient POSITIVE CUE: Or RC Pressure Limits Checked. COLR RC Press. Limits reviewed.

3. Verify all Pressurizer heaters are on. Identifies all Pressurizer heaters POSITIVE CUE: are on.

All pressurizer heaters are on.

4. Verify Pressurizer Spray (CV 1008) closed. Identified Pressurizer Spray (CV 1008) open. Attempted to close NEGATIVE CUE: Pressurizer Spray (CV-1008) and Pressurizer Spray (CV 1008) open. valve will not close

5. Verify ERV (PSV-i 000) closed. Verified ERV (PSV-1 000) closed.

POSITIVE CUE:

ERV (PSV-i 000) closed.

EXAMINER CUE:

When asked, provide applicant AOP procedure.

6. Refers to Pressurizer Systems failure 1203.015. Refers to Pressurizer Systems Failure 1203.015 Section 6 POSITIVE CUE: Pressurizer Spray valve (CV Hand student Pressurizer Systems failure 1203.015. 1008) Failure.

7. Close Pressurizer Spray Isolation valve CV-1 009. Attempted to close Pressurizer Spray isolation valve (CV 1009)

Negative CUE: and valve will not close.

Pressurizer Spray Isolation valve CV-1 009 open.

8. Verify all Pressurizer heaters are on. Verified all Pressurizer heaters POSITIVE CUE:

All pressurizer heaters are on.

Page 4 of 5 C PERFORMANCE CHECKLIST STANDARD N/A SAT

9. Trip Reactor. Student Trips Reactor verifies all POSITIVE CUE: rods are inserted and Reactor power is going down. This must C Reactor tripped, be done prior to reaching an automatic RPS set point of low RCS pressure 1800 psig.

10. Verify Turbine is tripped. Verified all throttle and governor valves are shut.

POSITIVE CUE:

Turbine is tripped.

1 1. Verify Sub Cooling Margin is adequate. Verified SCM is >30 degrees F.

POSITIVE CUE:

SCM is adequate.

12. Start C RCP HP Oil Lift pump (P63C). Starts C RCP HP Oil Lift pump P63C and due to caution tag POSITIVE CUE: start P-80 RCP HP Oil Lift pump (P63C) starts and due to caution tag start P-80

13. Start C RCP Backstop Lube Oil pump (P81C) Starts C RCP Backstop Lube Oil pump (P81C)

POSITIVE CUE:

RCP Backstop Lube Oil pump (P81C) starts.

14. Stop C RCP (P-32C). Stopped C RCP (P-32C) prior I- to RCS pressure drops below POSITIVE CUE: 1590 psig ESAS set point.

C RCP (P-32C) stops.

EXAMINER NOTE:

Tell student JPM is complete.

END

Page 5 of 5 JPM ID: A1JPM-RO-PZRO5 INITIAL CONDITIONS:

The Reactor is at 38% power with 3 RCPs running, D RCP is secured.

INITIATING CUE:

The CRSISM directs you to respond to new Annunciator alarms.

ENTERGY OPERATIONS INCORPORATED ARKANSAS NUCLEAR ONE DOCUMENT NO. CHANGE TITLE: CONTAINMENT HYDROGEN CONTROL WORK PLAN EXP. DATE NIA SAFETY-RELATED HTE SET # YES NO OYES NO TEMP MOD LEVEL OF USE I YES UNO CONTiNUOUS 1

Q REFERENCE I INFORMATIO1AL PROGRAMMATIC EXCLUSION PER EN-LI-I 00 UYES__NO When you see these TRAPS Get these TOOLS Time Pressure Effective Communication D istractionllnterruption Questioning Attitude Multiple Tasks Placekeeping

Over Confidence Self Check Vague or Interpretive Guidance Peer Check First ShiftlLast Shift Knowledge Peer Pressure Procedures ChangelOff Normal Job Briefing Physical Environment Coaching Mental Stress (Home or Work) Turnover VERIFIED BY DATE TIME =

FORM TITLE: FORM NO. CHANGE Nd.

VERIFICATION COVER SHEET 1000.006A 054 j

PROC.IWORK PLAN NO. PROCEDUREIWORK PLAN TITLE:

PAGE: 9 of 69 f 1104.031 CONTAINMENT HYDROGEN CONTROL CHANGE: 024 CAUT ION Hydrogen recorrbiner, M55A or N553, shoulo be olaced in operation following a COCA as soon as rime permits and moan be it. operation before hydrogen concentration reaches 3.C as indicated on the highest reading H analyzer.

8.0 Placing Hydrogen Recombiner (M55A or M55B) in Operation NOTE

Both M55A and 8155B are placed in standby, then either may be placed in operation.

The term siowly used in this section means raising potentiometer settings slowly enough to witness KB rise without overshooting the target setting.

8.1 Place both M55A and M55B in standby as follows.

Place M55A in standby by performing the following:

Vernv Power Aous: Potentoomener Is set at zero M55A.

B. Start M55A by placing HS-7470 in ON.

C. Select onermocouple #1, 2, or 3 (HS7474 to input to uiba temperature \23i)

P. Slowly turn power adjust potentiometers clockwise to raise power to 5 KB as indicated on M55A Power S. Slowly raise power to 10 KW.

1. Record initial time at 10 KB:

2. Maintain I0 KM output for standby service.

rPROC.IWORK PLAN NO.

1104.031 PROCEDUREIWORK PLAN TITLE:

8.1.2 CONTAINMENT HYDROGEN CONTROL I PAGE:

CHANGE:

Piece MS5B in standby by performine the following:

10 of 69 024 A. Verify Power Adjust Potentiometer is set at zero for M55B.

B. Start M55B by placing HS7471 in ON.

C. Select thermocouple 41, 2, or 3 cHS74r5) to input to M55B Teoperaruze (112301 D. Slowly turn power adjust potentiometers clockwise to raise power to 5 KM as indicated on M55B Power (JI-lOOl)

S. Slowly raise power to 10 KB.

Becoro inotoa tome at iC KB:

2. Maintain 10 KM output for standby service.

AUT ION Hydrogen Recombiner, M55A or M553, should be placed in operation following a 8.2 Place recombiners in operation as follows:

8.2.1 Place M55A inservice by performiro the following:

A. During heatup, monitor and record all three thermocouple temperatures every 30 minutes on Attachment 0.

B. Verify M55A has been at 10 KM for at least 10 minutes.

C. Slowly raise power to 20 KM AND hold for 5 minutes.

I. lerernine rower reou red from Pecombirer Power M55A1 Versus Containment Pressure, Attachment B of tois procedure, page 1 of 2, based on containment pressure.

1. KM setting Pecombiner power >15 KM and temperature >1450°F may cause heater failure.

CAUTION

2. Slowly raise power to the value decermined above.

I PROC.IWORK PLAN NO.

I PROCEDURE/WORK PLAN TITLE:

I PAGE: 11 of 69 j 1104.031 CONTAINMENT HYDROGEN CONTROL CHANGE: 024 E. Verify proper recombiner operation by observing the foliowing:

NOTE

Hydrogen concentration reduction is the longterm, primary method of verification.

H concentr.ation reduction shall be used regardless of recombiner tower or temperature ondlcatlor. as the veritication of proper recomorner operatron.

Hydrogen concentration stable or dropping at I Hydrogen (Qi-7457 and QI-7459)

Recorabiner maintaining power at value determined NOTE

Thermocouples are non-Q and will not be reliable indicators in a post-iOtA environment.

Recombiner temperature can aid in trending recombiner operation. The following steps are provided as guidelines.

Recombiner temperature may be plotted on Attachment C for verifying thermocouple operation ar.d estimatrng tome when recombination temperature will be reached.

F. Establish validity of temperature indication by comparing AT between thermocouples.

I. IF all three thermocouples fall within a 60°F oar>,

THEN average the three temperatures.

2. IF no two thermocouples are within 60°F of each ccc r, THEN therrcc.couples should be considered inaccurate.

3. IF difference of the three temperatures >60°F, AND two temoeratures are within 60°F, C. Monitor for indication that recombiner operating temperature of 1225°F has been reached.

I PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE:

I PAGE: 12 of 69 1104.031 CONTAINMENT HYDROGEN CONTROL CHANGE: 024 NOTE Valid thermocouples show a ramp rise in temperature with H concentration >2%,

indioatinp recombiriation temperature has been reached and recombination is takino place.

H. IF hydrogen concentration is >2%,

TIEN monitor for a ramp rise in temperature.

I. After four hours of fuli power operation, log data in Attachment D once per hour.

8.2.2 Place M55B in-service by performing the following:

A. During heatup, monitor and record au three thermocouple temperatures every 30 minutes on Attachment E.

B. Verify M55B has been at 10 KB for at least 10 minutes.

C. Slowly raise power to 20 KB AND hold for 5 minutes.

D. Determine power required from Recombiner Power (M55B>

Versus Containment Pressure Attachment B of this procedure, page 2 cf 2, based on containment pressure.

setting Recorrbiner power >75 KB and temperature >1450°F may cause heater failore.

CAUTION

2. Slowly raise power to the value determined above.

E. Verify proper recombiner operation by observing the NOTE

Hydrogen concentration reduction is the long-term, primary method of verification.

reatt rroess rcDerpceror

Hydrogen concentration stable or dropping at Horogen Ql457 arc QZ7459

Recornbiner maintaining power at value determined in step 8.2.2.2.

[ 1 PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE:

1104.031 CONTAINMENT HYDROGEN CONTROL PAGE:

CHANGE:

13 of 69 024 1

NOTE

Thermocouples are non-Q and will not be reliabie indicators in a post-LOCA environment.

Reoombiner temperature can aid in trending recombiner operation. The following steps are provided as guidelines.

Recombiner temperature may be plotted on Attachment C for verifying thermocouple operation and estimating time when recombination temperature will be reached.

F. Establish validity of temperature indication by comparing T between thermocouples.

1. IF all three thermocouples fall within a 60°F band, THEN average the three temperatures.

2. iF no two thermocouples are within 60°F of each other, THEN thermocouples should be considered inaccurate.

3. IF difference of the three temperatures >60°F, AND two temperatures are within 60°F, THEN average the closest two.

0. Monitor for indication that recombiner operating temperature of 1225°F has been reached.

MOTE Valid thermocouples s.how a ramp rise in temperature with H concentration t2-,

indicating recombination temperature has been reached and recombinatio n is taking place.

H. IF hdrooen conoentration is >2, THEN monitor for a ramp rise in temperature.

I. After four nours of full power operation, log data in Attaonment 6 once per noir.

IF proper power setting causes average valid temperature to exceed 1450°F OR inservice xecnroniner has insufficient capacitI, THEN piece standby recombiner inservooe.

8.2.4 Do NOT lower recombiner power based on extreme temperature.

Maintain power until standby recombiner is heated to operating temperature of l225°F.

8.3 Monitor Hydrogen Samplers (Cl78 and C179) to verify recombiner(s) maintainino or lowering hydrogen concentration.

i PROC.IWORK PLAN NO.

1104.031 I PROCEDIJRE!WORK PLAN TITLE:

CONTAINMENT HYDROGEN CONTROL PAGE: 14 of 69 CHANGE: 024 Recorabiner power >5 KM and temoerature >1450°F may cause heater failure.

CAUTION NOTE A power change of 4 Kb will change temoerature approximately 75F.

8.3.1 2 concentration has risen by >0.5% in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months H

OR ab concentration >3.02, THEN raise recombiner rower setting by 4 KM above the previous setting.

NOTE A change in containment pressure will require an adjustment to recornbiner power.

8.4 Monitor containment pressure.

8.4 .1 WHEN pressure changes, THEN adjust recombiner power to new value from Attachment S.

8.5 WHEN no longer required, THEN perform the following to secure Hydrogen Recorabiner:

8.5.5 Perform the following to secure M55A:

A. Lower power to zero.

B. Secure M55A by placing HS-74 0 to OFF.

C. Leave a thermocouple selected as input to M55A Temperature (112300) 8.5.2 Perform the following to secure 14553:

A. Lower power to zero.

S. Secure MISS by olaclra 1174>1 to OFF.

7. Leave a thermocouple selecteo as input to 14555 Temperattre (TI230l)

j PROC.IWORK PLAN NO. PROCEDLJREIWORK PLAN TITLE:

I PAGE: 23 of 69 1104.031 CONTAINMENT HYDROGEN CONTROL CHANGE: 024 ATTACP2ENT B Page 2 of 2 RECOMBINER POWER (M-55B)

VERSUS CONTAINMENT PRESSURE 75 60°F 1900F 70 1 120°F 65 /

/

60 I

55 7/

7/

50

- /

45 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 Post-LOCA Containment Pressure (0.2 psia increments)

Note: Use pre- LOCA average Reactor Building Temperature from SPDS (TAVRB1) from history file if available. Otherwise use logs.

Page 1 of 5 JOB PERFORMANCE MEASURE Unit: 1 Rev # 3 Date:

JPM ID: A1JPM-RO-PZR05 System/Duty Area: PRESSURIZER Task: Respond to Low RCS Pressure due to Stuck Open Spray Valve JTA# ANO1-RO-AOP--OFFMORM-1 15 KA Value RO 3.6 SRO 3.5 KA

Reference:

010 A3.02 Approved For Administration To: RO X SRO X Task Location: Inside CR X Outside CR Both Suggested Testing Environment and Method (Perform or Simulate):

Plant Site: Simulator: Perform Lab:

Position Evaluated: RO: SRO:

Actual Testing Environment: Plant Site Simulator Lab Testing Method: Perform Simulate Approximate Completion Time in Minutes: 15 Minutes Reference(s): 1203.012H Annunciator K09 corrective Action K09-C1; 1203.015 Pressurizer systems Failure Examinees Name: KCN:

Evaluators Name:

The Examinees 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 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 JPM ID: A1JPM-RO-PZRO5 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner shall review the Briefing Checklist System Walkthrough portion of OP 1064.023 Attachment 6 with the examinee.

JPM INITIAL TASK CONDITIONS:

The Reactor is at -38% power with 3 RCPs running, D RCP is secured.

SUGGESTED SIMULATOR SETUP: Have the Spray valve stuck open CV-1 008 and have the spray valve isolation valve CV-1009 failed open. Spray valve should be open slightly and have RCS pressure going down slowly with all PZR heaters on. RCS pressure Hi/Lo alarm, K09-C1 should come in shortly after placing the simulator in RUN.

SETUP NOTE: REMOVE ANY CAUTION CARDS THAT MAY EXIST ON RCP OIL PUMP HANDSWITCHES PRIOR TO STARTING JPM.

Simulator should remain in FREEZE until candidate is ready. Then start simulator THIS IS AN ALTERNATE PATH JPM TASK STANDARD:

Trip Reactor and Stop C RCP to stop RCS pressure decrease. Tripping the reactor must be performed prior to reaching the RPS low pressure set point. Stopping C RCP should be done prior to reaching ESAS trip set point of 1590 psig.

TASK PERFORMANCE AIDS:

Copy of 1203.015 section 6 Pressurizer Spray Valve (CV-1008) and 1203.012H Annunciator K09 corrective action for K09-C1 window RCS Pressure Hi/Lo

Page 3 of 5 JPM ID: A1JPM-RO-PZRO5 INITIATING CUE: The CRS/SM directs you to respond to new Annunciator alarms.

CRITICAL ELEMENTS (c): 9, 14 C PERFORMANCE CHECKLIST STANDARD N/A SAT EXAMINER NOTE:

This JPM requires the examinee to use more than one procedure. Provide the procedures as they are cued in the JPM.

Annunciator K09-C1 will alarm shortly after placing the simulator in RUN.

When asked, provide applicant the ACA procedure ONLY.

1. Confirm alarm by comparing RC pressure indications Identified that all RCS pressure on C04. indicators are going down.

POSITIVE CUE:

All RCS pressure indicators are going down.

2. Refer to COLR figures for RC Pressure Limits. COLR limits may not be referenced during Press Transient POSITIVE CUE: Or RC Pressure Limits Checked. COLR RC Press. Limits reviewed.

3. Verify all Pressurizer heaters are on. Identifies all Pressurizer heaters POSITIVECUE: areon.

All pressurizer heaters are on.

4. Verify Pressurizer Spray (CV 1008) closed. Identified Pressurizer Spray (CV 1008) open. Attempted to close NEGATIVE CUE: Pressurizer Spray (C V-i 008) and Pressurizer Spray (CV 1008) open. valve will not close

5. Verify ERV (PSV-i000) closed, Verified ERV (PSV-i 000) closed.

POSITIVE CUE:

ERV (PSV-i000) closed.

EXAMINER CUE:

When asked, provide applicant AOP procedure.

6. Refers to Pressurizer Systems failure 1203.015. Refers to Pressurizer Systems Failure 1203.015 Section 6 POSITIVE CUE: Pressurizer Spray valve (CV Hand student Pressurizer Systems failure 1203.01 5. 1008) Failure.

7. Close Pressurizer Spray Isolation valve CV-i 009. Attempted to close Pressurizer Spray isolation valve (CV 1 009)

Negative CUE: and valve will not close.

Pressurizer Spray Isolation valve CV-i 009 open.

8. Verify all Pressurizer heaters are on. Verified all Pressurizer heaters POSITIVE CUE:

[Afl pressurizer_heaters are on.

Page 4 of 5 C PERFORMANCE CHECKIJST STANDARD N/A SAT

9. Trip Reactor. Student Trips Reactor verifies all POSITIVE CUE rods are inserted and Reactor power is going down. This must C Reactor tripped, be done prior to reaching an automatic RPS set point of low RCS pressure 1800 psig.

10. Verify Turbine is tripped. Verified all throttle and governor valves are shut.

POSITIVE CUE:

Turbine is tripped.

1 1. Verify Sub Cooling Margin is adequate. Verified SCM is >30 degrees F.

POSITIVE CUE:

SCM is adequate.

12. Start C RCP HP Oil Lift pump (P63C). Starts C RCP HP Oil Lift pump P63C and due to caution tag POSITIVE CUE: start P-80 RCP HP Oil Lift pump (P63C) starts and due to caution tag start P-80

13. Start C RCP Backstop Lube Oil pump (P81 C) Starts C RCP Backstop Lube Oil pump (P81C)

POSITIVE CUE:

RCP Backstop Lube Oil pump (P81C) starts.

14. Stop C RCP (P-32C). Stopped C RCP (P-32C) prior to RCS pressure drops below C POSITIVE CUE: 1590 psig ESAS set point.

C RCP (P-32C) stops.

EXAMINER NOTE:

Tell student JPM is complete.

END

Page 5 of 5 JPM ID: A1JPM-RO-PZRO5 INITIAL CONDITIONS:

The Reactor is at 38% power with 3 RCPs running, D RCP is secured.

INITIATING CUE:

The CRSISM directs you to respond to new Annunciator alarms.

ENTERGY OPERATIONS INCORPORATED ARKANSAS NUCLEAR ONE DOCUMENT NO CHANGE NO.

TITLE: ANNUNCIATOR K09 CORRECTIVE ACTION WORK PLAN EXP. DATE NIA SAFETY-RELATED IPTE SET # DYES LINO EIYES NO TEMP MOD LEVEL OF USE DYES NO CONTINUOUS 0 REFERENCE U INFORMATIONAL PROGRAMMATIC EXCLUSION PER EN-LI-100 DYES__NO When you see these TRAPS Get these TOOLS Time Pressure Effective Communication Distractionhlnterruption Questioning Attitude Multiple Tasks Placekeeping Over Confidence Self Check Vague or Interpretive Guidance Peer Check First Shift/Last Shift Knowledge Peer Pressure Procedures ChangelOff Normal Job Briefing Physical Environment Coaching Mental Stress (Home or Work) Turnover VERIFIED BY DATE I TIME FORM TITLE: FORM NO. CHANGE NO.

VERIFICATION COVER SHEET 1000.006A 054

PROC.!WORK PLAN NO. PROCEDURE!WORK PLAN TITLE:

I PAGE: 5 of 64 1203.012H ANNUNCIATOR K09 CORRECTIVE ACTION CHANGE: 040 Sage 1 of 2 Location: C14 Device and Seopolno: RC S RC Pressure Loop A Narrow Ranoe PS-l023) 2255 psig PRESSURE or <2055 psig HI/IC AC ressure Loop B Narrow Range PSlimb, 22z5 psig Or <2055 psig Alarm: K09Cl 1.0 OPERATOR ACTIONS NOTE The following indicators should read nearly alike except during three RCP operation.

1. Confirm alarm by comparing AC pressure indications on C04.

. RC Pressure Narrow Range Loop A recorder )PR1023)

. RC Pressure Narrow Range Loop 3 recorder (PR1038)

. AC Pressure Wide Range Loop B recorder PI1041)

. AC Pressure Wide Range Loop B indicator (PR1042)

NOTE A malfunctioning pressure instrument can insert an erroneous trip signal to the RPS.

2. Refer to COLA Figures for PC pressure limits.

3. IF PC pressure is confirmed low, THEN perform the following:

A. Verify all pressurizer heaters on.

B. Verify Pressurizer Spray )CV1008) closed.

C. Verify ERV (PSVl000) closed.

D. Refer to Pressurizer Systems Failure (1203.015)

4. IF AC pressure is confirmed high, THEN oerform the following:

A. Ver:fu Pressurozer Stray C/I008: omen.

C. Refer to Pressurizer Sysrems Failure .1203.015; 5.. IF transient is caused by ICS malfunction, OR ICS instrument failure THEN take manual control of affected 0/0 station ANI refer to Abnormal Operation I203.0l1

6. Refer oo SASS MISMATCH K07B.4 (1203. Ol2F)

PROC.IWORK PLAN N

O. PROCEDURE

IWORK PLAN TITLE:

PAGE: 6 of 64 1203012H ANNUNCIATOR K09 CORRECTIVE ACTION CHANGE: 040 1409Cl Sage 2 of 2 2.0 PROBABLE CAUSES

Malfunctioning pressure instrument

ICE malfunction

3.0 REFERENCES

Window Arrangement Annunciator FOP (E459, sheets 04)

ENTERGY OPERATIONS INCORPORATED ARKANSAS NUCLEAR ONE DOCUMENT NO. CHANGE NO.

TITLE: PRESSURIZER SYSTEMS FAILURE WORK PLAN EXP. DATE NIA SAFETY-RELATED IPTE SET # DYES DNa DYES NO TEMP MOD LEVEL OF USE DYES NO CONTINUOUS D REFERENCE D INFORMATIONAL PROGRAMMATIC EXCLUSION PER EN-LI-100 DYES__NO When you see these TRAPS Get these TOOLS Time Pressure Effective Communication Distraction/Interruption Questioning Attitude Multiple Tasks Placekeeping Over Confidence Self Check Vague or Interpretive Guidance Peer Check First ShiftlLast Shift Knowledge Peer Pressure Procedures Change/Off Normal Job Briefing Physical Environment Coaching Mental Stress (Home or Work) Turnover VERIFIED BY DATE I TIME FORM TITLE: FORM NO. CHANGE NO.

VERIFICATION COVER SHEET 1000.006A 054

CHANGE 1203.015 PRESSURIZER SYSTEMS FAILURE 016 PAGE 16 of 24 SECTION 6-- PRESSURIZER SPRAY VALVE (CV-1008) FAILURE ENTRY CONDITIONS One or more of the following:

CV-1008 closed when it should be open.

Normal operation: Opens 2205 psig Closes 2155 psig

- Power >80% and MFP trip: Opens 2080 psig Closes 2030 psig

CV-1008 open when it should be closed.

Abnormal change in RC pressure.

RC pressure transmitter failure which is selected for RC pressure control.

F 1203.015 PRESSURIZER SYSTEMS FAILURE CHANGE 016 PAGE 17 of 24 SECTION 6-- PRESSURIZER SPRAY VALVE (CV-1008) FAILURE INSTRUCTIONS

1. IF failed open, THEN place Pressurizer Spray Control switch in HAND AND attempt to close CV-1008 (modulating valve).

NOTE CV-1009 torque switch can be overridden in the OPEN or CLOSE direction by holding the hand switch in the respective position.

A. IF CV-1 008 will NOT close, THEN close Pressurizer Spray Isolation Valve (CV-1009).

B. Verify Pressurizer heaters return RCS pressure to normal.

CAUTION Pressurizer spray shall not be used if the temperature difference between the Pressurizer and the spray fluid is >430°F (TRM 3.4.3). Closing CV-1 009 isolates the CV-1008 bypass spray C. IF necessary, THEN control spray flow by cycling Pressurizer Spray Isolation Valve (CV-1 009) open and closed.

D. IF both CV-1008 and CV-1 009 do NOT close RCS pressure is dropping, THEN perform the following:

1) Verify all PZR heaters ON.

2) Immediately begin reducing load to 40% at 10%/mm per Rapid Plant Shutdown (1203.045).

3) IF 4 RCPs are running BOTH of the following conditions are met:

Load is reduced to 675 MWe (75% load)

Reactor power is 75%,

THEN perform the following:

a. Start C RCP HP Oil Lift Pump (P-63C) and C RCP Backstop Lube Oil Pump (P-81C).

b. Stop C RCP (P-32C).

c. WHEN zero speed is indicated, THEN stop P-63C and P-81C.

(continued)

j CHANGE I 1203.015 PRESSURIZER SYSTEMS FAILURE 016 PAGE 18 of 24 SECTION 6 -- PRESSURIZER SPRAY VALVE (CV-1008) FAILURE I NOTE In Modes 1 and 2, operation with only one RCP in each loop causes entry into TS 3.4.4 L Condition A.

4) if 3 RCPs running AND all of the following conditions are met:

Load is reduced to 360 MWe (40% load)

Reactor power is 55%,

C and D RCPs in-service THEN perform the following:

a) Start C RCP HP Oil Lift Pump (P-63C) and C RCP Backstop Lube Oil Pump (P-81 C).

b) Stop C RCP (P-32C).

c) WHEN zero speed is indicated, THEN stop P-63C and P-81C.

d) Enter TS 3.4.4 Condition A.

5) IF 3 RCPs running, AND D RCP is secured, THEN perform the following:

a) Trip Reactor.

b) Secure P-32C as follows:

(1) Start C RCP HP Oil Lift Pump (P-63C) and C RCP Backstop Lube Oil Pump (P-81C).

(2) Stop C RCP (P-32C).

(3) WHEN zero speed is indicated, THEN stop P-63C and P-81C.

c) Perform Reactor Trip (1202.001) while continuing with this procedure.

d) Enter TS 3.4.5 Condition A.

6) WHEN conditions permit a reactor building entry, THEN attempt to manually close either CV-1008 or CV-1009.

E. Contact Ops Manager.

(continued)

CHANGE 1203.015 PRESSURIZER SYSTEMS FAILURE 016 PAGE 19 of 24 SECTION 6 -- PRESSURIZER SPRAY VALVE (CV-1008) FAILURE

2. IFfailed closed, THEN hold the plant at steady state conditions.

A. IF CV-1008 is energized, THEN place Pressurizer Spray Control Mode switch in HAND AND attempt to cycle CV-1008 (a modulating valve) open and closed.

B. Write a Condition Report to evaluate continued operation of the plant with inoperable Spray Valve.

C. Contact Ops Manager AND consider one or both of the following:

1) IF CV-1 008 will NOT open, THEN commence a shutdown per Power Reduction and Plant Shutdown (1102.016) and Plant Shutdown and Cooldown (1102.010).

To prevent lifting of relief valves, reduce power slowly while shutting down.

RC pressure can be regulated by manual control of Pressurizer heaters.

2) WHEN conditions permit a reactor building entry, THEN perform the following:

a. Close CV-1009 from C04.

b. Attempt to manually open CV-1008 in reactor building.

CAUTION Pressurizer spray shall not be used if the temperature difference between the Pressurizer and the spray fluid is >430°F (TRM 34.3). Closing CV-1 009 isolates the CV-1008 bypass spray flow.

c. IF CV-1 008 can be opened, THEN control RCS pressure and spray line temperature by cycling CV-1009 open and closed.

3. IF an RC pressure transmitter which is selected for control has failed or is failing, THEN GO TO Annunciator K07 Corrective Action (1 203.01 2F), SASS Mismatch (K07-B4).

4. Refer to RCS Pressure, Temperature and Flow DNB Surveillance Limits of the ANOI COLR (TS 3.4.1).

END

Page 1 of 5 JOB PERFORMANCE MEASURE Unit: 1 Rev# 4 Date:

JPM ID: A1JPM-RO-EOPO8 System/Duty Area: Emergency and Abnormal Operations Task: Perform Actions required to correct Degraded Power (EFW System Operation)

JTA# ANO1-RO-EOP-EMERG.-35 & ANO1-SRO-EOP-EMERG-32 KA Value RO 3.3 SRO 3.6 KA Reference 061 Al 02 Approved For Administration To: RO X SRO X Task Location: Inside CR: X Outside CR: Both:

Suggested Testing Environment And Method (Perform or Simulate):

Plant Site: Simulator: Perform Lab:

Position Evaluated: RO: SRO:

Actual Testing Environment: Simulator: Plant Site: Lab Testing Method: Simulate: Perform:

Approximate Completion Time In Minutes: 10 Minutes Reference(s): 1202.007 Degraded Power Examinees Name: KCN:

Evaluators Name:

The Examinees 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 Date:

Signed Signature below indicates the material utilized during 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 JPM ID: A1JPM-RO-EOPO8 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner should verify that the examinee has been briefed per the JPM Examination Briefing Sheet EN-TQ-1 14 .5.

JPM INITIAL TASK CONDITIONS:

Degraded Power conditions exist. EFW is NOT available and HPI cooling is inadequate.

TASK STANDARD:

Both EFW pumps suction are aligned to the SW system AND EFW system aligned to feed OTSGs from the Service Water System.

TASK PERFORMANCE AIDS:

1202.007 Degraded Power Step 67A-F.

Page 3 of 5 JPM ID: A1JPMRO-EOPO8 INITIATING CUE: The CRS/SM directs you to feed both OTSGs with Service Water per step 67 of 1202.007 Degraded Power.

UN C PERFORMANCE CHECKLIST STANDARD N/A SAT SAT

1. Direct an operator to close the minimum recirc ..

isolation valves for P-7A and P-7B (FW-1 lA/B).

Notified an operator to close FW-1 1A and FW-1 1 B.

POSITIVE CUE:

Operator reports that FW-1 1A and FW-1 1 B are closed.

On C09, operated the ATM

2. Depressurize both OTSGs to zero psig.

Dump Control System C (Atmospheric Dump Isolation POSITIVE CUE: Both OTSG pressures are at 0 psig.

and Control Valves) to depressurize the OTSGs to NEGATIVE CUE: Both OTSGs are at 200 psig.

Opsig.

3. Start third Service Water Pump.

POSITIVE CUE: ALL three-service water pumps in Started third Service Water service. (Red lights indicated on panel C16 and C18.

Pump.

NEGATIVE CUE: Green light on for one service water pump.

4. Open the EFW Service Water Loop I and II On C09, opened CV-3850 Isolations (CV-3850 and CV-3851).

and CV-3851. Indicated by c the red lights ON and green POSITIVE CUE: Red lights on.

lights OFF above HS-3850 and HS-3851.

NEGATIVE CUE: green lights on.

On C09, placed HS-2800

5. Place P-7A and P-7B suction select switches to the and HS-2802 to the SW SW position.

position.

Indicated by the green lights CUE: CV-2800 and CV-2802 green lights POSITIVE ON and red lights OFF for ON.

CV-2800 and CV-2802 AND the red lights ON and green NEGATIVE CUE: lights for CV-2800, CV-2802, CV-lights OFF for CV-2803 and 2803 and CV-2806 did not change status.

CV-2806.

On C09, opened CV-2670,

6. Open EFW isolation valves (CV-2670 and CV-227 CV-2627, CV-2620 and CV-for SG A. CV-2620 and CV-2626 for SG B),

2626 in manual.

C Indicated by red lights ON POSITIVE CUE: Red lights ON.

and green lights OFF above HS-2670, HS-2627, HS NEGATIVE CUE: Green light(s)ON.

2620 and HS-2626..

Page 4 of 5 UN C PERFORMANCE CHECKLIST STANDARD N/A SAT SAT

7. Open EFW control valves (CV-2645 and CV-2646 On C09, opened CV-2645, for SG A CV-2647 and CV-2648 for SG B).

CV-2646, CV2647 and CV 2648 in manual.

C POSITIVE CUE: EFW flow to both OTSGs indicated on Indicated by 100% on scale C09.

above HIC-2645, HIC-2646, NEGATIVE CUE: no flow indicated on C09. (K02-HIC-2647 and HIC-2648.

D4/F6).

When all EFW control valves are open, Notify the exam inee that the JPM is complete

Page 5 of 5 JPM ID: A1JPM-RO-EOPO8 INITIAL CONDITIONS:

Degraded Power conditions exist.

EFW is NOT available AND HPI cooling is inadequate.

INITIATING CUE:

The CRSISM directs you to feed both OTSGs with Service Water per step 67 of 1202.007 Degraded Power.

ENTERGY OPERATIONS INCORPORATED ARKANSAS NUCLEAR ONE TITLE: DEGRADED POWER DOCUMENT NO. CHANGE NO.

WORK PLAN EXP. DATE NIA SAFETY-RELATED IPTE SET # DYES DYES DNO N0 TEMP MOD LEVEL OF USE DYES NO CONTINUOUS Q REFERENCE D INFORMATIONAL PROGRAMMATIC EXCLUSION PER EN-LI-100 DYES__NO When you see these TRAPS Get these TOOLS Time Pressure Effective Communication Distraction/Interruption Questioning Attitude Multiple Tasks Placekeeping Over Confidence Self Check Vague or Interpretive Guidance Peer Check First Shift/Last Shift Knowledge Peer Pressure Procedures ChangelOff Normal Job Briefing Physical Environment Coaching Mental Stress (Home or Work) Turnover VERIFIED BY I DATE TIME FORM TITLE: FORM NO. CHANGE NO.

VERIFICATION COVER SHEET 1000.006A 054

1202.007 DEGRADED POWER I CHANGE 1 j 009 PAGE 33 of 64 I INSTRUCTIONS CONTINGENCY ACTIONS

65. IF CET temps are superheated AND moving away from the saturation line, THEN GO TO 1202.005, INADEQUATE CORE COOLING procedure while attempting to restore buses per step 71 of this procedure.

66. f EFW is expected to become available before CET temps indicate superheated, THEN RETURN TO step 62.

NOTE

Service Water feed alone may only slow the rate of heatup.

SG level will not be established if feed is from service water.

67. IFno EFW is available, THEN feed SGs with Service Water via EFW system as follows:

A. Dispatch an operator to close Minimum RECIRC ISOL for P-7A and B (FW-11A and B).

B. Operate ATM Dump Control System to B. IF ATM Dump ISOL valve is de-energized, depressurize SGs to 0 psig. THEN dispatch an operator to hand jack associated ATM Dump CNTRL Valve fully SGA SGB open (Refer to Alternate Shutdown CV-2676 ATM Dump CV-2619 (1203.002), Exhibit A).

ISOL CV-2668 ATM Dump CV-2618 CNTRL C. Perform the following to start the third C. GO TO step 67.D.

Service Water pump:

1) IF ESAS has actuated, THEN verify one pair of Service Water Crossties open.

P4A to P4B CV3644 & 3646 P4B to P4C CV-3640 & 3642

2) Start third Service Water pump D. Open EFW SERV VVTR Loop I and II Isolations (CV-3850 and 3851).

(67. CONTINUED ON NEXT PAGE)

E 1I CHANGE I 1202.007 ILDEGRADED POWER 009 PAGE 34 of 64 INSTRUCTIONS CONTINGENCY ACTIONS

67. (Continued).

E. Take P-7A and B SUCT Select switches to SW.

F. Open all EFW ISOL and EFW CNTRL valves in MANUAL while maintaining EFW flow to each SG 200 gpm.

(modulating valves).

68. Check CET temps begin to drop. 68. Hold at this point until one of the following conditions is met, while attempting to restore buses per step 71.

A. IF EFW becomes available, THEN GO TO step 70.

B. IF CET temps begin to drop, THEN GO TO 1202.011, HPI COOLDOWN while attempting to restore buses per step 71 of this procedure.

C. IF CET temps are superheated AND moving away from the saturation line, THEN GO TO 1202.005, INADEQUATE CORE COOLING procedure while attempting to restore buses per step 71 of this procedure.

69. GO TO 1202.011, HPI COOLDOWN while attempting to restore buses per step 71 of this procedure.

70. IF EFW becomes available, THEN perform the following:

A. Dispatch an operator to open Minimum RECIRC SQL for P7A and B (FW-11A and B).

(70. CONTINUED ON NEXT PAGE)

Page 1 of 4 JOB PERFORMANCE MEASURE Unit:

1 Rev #

9 Date:

JPM ID: A1JPM-RO-ICWO2 System/Duty Area: Intermediate Cooling Water Task: Perform Switching of ICW Pumps (P-33AIBIC)

JTA# ANO1 -RO-ICW-NORM-27 KA Value RO 3.3 SRO 3.6 KA

Reference:

008 A2.01 Approved For Administration To: RO X SRO X Task Location: Inside CR X Outside CR Both Suggested Testing Environment and Method (Perform or Simulate):

Plant Site: Simulator: Perform Lab:

Position Evaluated: RO: SRO:

Actual Testing Environment: Plant Site Simulator Lab Testing Method: Perform Simulate Approximate Completion Time in Minutes: 10 Minutes Reference(s): 1104028 Section 10.0 Examinees Name: KCN:

Evaluators Name:

The Examinees 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 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 4 JPM ID: A1JPM-RO-ICWO2 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner should verify that the examinee has been briefed per the JPM Examination Briefing Sheet EN-TQ-114 .5.

JPM INITIAL TASK CONDITIONS:

Unit 1 is at 100% power steady state conditions. The lAO reports that P-33A has high vibrations and is making an unusual noise. P-33A and P-33C ICW Pumps are presently in service. P-33B lOW pump has NOT been drained.

TASK STANDARD:

P-33B ICW Pump supplying non-nuclear lOW, lOW Pump P-33A is secured.

TASK PERFORMANCE AIDS:

1104.028 Section 10.0

Page 3 of 4 JPM ID: Al JPM-RO-ICWO2 INITIATING CUE: The CRS/SM directs you to start P-33B ICW Pump and then secure P-33A ICW pump using 1104.028 Section 10.0.

C PERFORMANCE CHECKLIST STANDARD N/A SAT UNSAT

1. Open ICW Pumps (P-33A to P-33B)

Suction Crossconnect valve CV-2240.

POSITIVE CUE:

has red light ON and green Opened CV-2240 on panel C09.

CV-2240 NEGATIVE CUE:

CV-2240 has green light ON and red light OFF,

2. Open ICW Pumps (P-33A to P-33B)

Discharge Crossconnect valve CV-2238.

POSITIVE CUE:

C CV-2238 has red light ON and green Opened CV-2238 on panel C09.

light OFF.

NEGATIVE CUE:

CV-2238 has green light on and red light off.

INSTRUCTOR CUE: Inform Examinee that P-33B ICW Pump has been vented.

3. Start ICW Pump P-33B.

POSITIVE CUE: Started lOW Pump P-33B using C Red light ON green light OFF for P-33B. handswitch on panel 009.

NEGATIVE CUE:

Green light ON red light OFF for P-33B.

4. Stop ICW Pump P-33A.

POSITIVE CUE:

Waited -3 minutes and then placed light ON red light OFF for P-33A.

Green the handswitch for ICW Pump P-33A in the trip/stop position.

NEGATIVE CUE:

Red light ON green light OFF for P-33A.

5. Verify flow is normal on ICW Coolers Inlet Flow Non-Nuc indicator (FI-2218) on C09. Verified normal ICW flow on Fl-221 8 on 009 for the Non-Nuclear loop.

POSITIVE CUE:

Flow is 1800-2000 gpm on Fl-2218.

END

Page 4 of 4 JPM ID: A1JPM-RO-ICWO2 INITIAL CONDITIONS:

Unit I is at 100% power steady state conditions. The lAO reports that P-33A has high vibrations and is making an unusual noise. P-33A and P-33C ICW Pumps are presently in service. P-33B ICW pump has NOT been drained.

INITIATING CUE:

The CRSISM directs you to start P-33B ICW Pump and then secure P-33A ICW pump using 1104.028 Section 10.0.

Page 1 of 4 JOB PERFORMANCE MEASURE Unit: 1 Rev# 10 Date:

JPM ID: A1JPM-RO-EFWO2 System/Duty Area: Emergency Feedwater Task: Manual Control of Emergency Feedwater Pump P-7A at the Turbine JTA# ANO1 -RO-EFW-NORM-7 KA Value RO 3.1 SRO 3.4 KA

Reference:

061 A2.05 Approved For Administration To: RO X SRO X Task Location: Inside CR Outside CR X Both Suggested Testing Environment and Method (Perform or Simulate):

Plant Site: Simulate Simulator: Lab:

Position Evaluated: RO: SRO:

Actual Testing Environment: Plant Site X Simulator Lab Testing Method: Perform Simulate Approximate Completion Time in Minutes: 10 Minutes Reference(s): 1106.006 EFW Pump Operation Exhibit C (Manual Control of EFW Pump P-7A)

Examinees Name: KCN:

Evaluators Name:

The Examinees 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 Date

Signature indicates this JPM has been compared to its applicable procedure by a qualified individual (not the exarninee) and is current with that revision.

Page 2 of 4 JPM ID: A1JPM-RO-EFW02 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner should verify that the examinee has been briefed per the JPM Examination Briefing Sheet EN-TQ-114 .5.

JPM INITIAL TASK CONDITIONS:

EFW Pump Turbine K3 tripped on overspeed due to a loss of electric signal to the speed controller.

Power is unavailable to the speed controller/turbine control cabinet.

P-7A turbine has been reset per Exhibit A (EFW Pump P-7A Overspeed Trip Reset).

INSTRUCTOR NOTE: FYI EFW Pump Turbine K3 steam admission valves are closed and the trip throttle valve is opened in 1106.006 Exhibit A.

TASK STANDARD:

EFW Pump P-7A running per section 1.0 of 1106.006 Exhibit C (at -14OO discharge pressure).

TASK PERFORMANCE AIDS:

Copy of 1106.006 Exhibit C (Manual Control of EFW Pump P-7A).

Page 3 of 4 JPM ID: Al JPM-RO-EFWO2 INITIATING CUE: The CRS/SM directs you to manually start EFW Pump P-7A and control at approximately 1400 psig discharge pressure per 1106.006 Exhibit C.

TRANSITION NOTE:

. Proceed to EFW pump room on 335 elevation in Controlled Access of Auxiliary Building.

1. Close EFW Turbine K3 Trip/Throttle Valve (CV- Closed CV-6601A by rotating hand 6601A). wheel in close direction C (clockwise).

POSITIVE CUE:

Handwheel does NOT move any further in the clockwise direction.

2. Request control room to open EFW Turbine K3 Called control room and requested Steam Admission valve (CV-2613 or CV-2663). CV-2613 or CV-2663 to be c opened.

NEGATIVE CUE:

Control Room reports unable to open steam admission valves INSTRUCTOR CUE When the operator simulates notifying the control room to open CV-261 3 or CV-2663, tell him that there is no power available to CV-2613 or CV-2663 and direct him as the CRS to open CV-2613 manually.

3. Open CV-2613 Manually Engaged manual handwheel and rotated handwheel in the counter c POSITIVE CUE: clockwise direction until it stopped.

CV-261 3 indicates open locally Verified stem rises on the valve by observing the stem as the valve is opened.

4. Open EFW Turbine K3 Trip/Throttle valve (CV- Slowly opened CV-6601A (counter 6601A). clockwise) until approximately 1400 psig discharge pressure was CUE: attained.

POSITIVE Pump discharge pressure is approximately 1400 psig.

NEGATIVE CUE:

Pump discharge pressure is approximately 500 psig.

5. Monitor turbine speed indication (if available) to Checked turbine speed locally at ensure turbine does not exceed 3776 RPM or approximately 3650 RPM pump discharge pressure at -1400 psig. monitored pump discharge pressure indication and maintained POSITIVE CUE: at -1400 psig.

Turbine speed is 3650 RPM or pump discharge re1400si.

END

Page 4 of 4 JPM ID: A1JPM-RO-EFWO2 INITIAL CONDITIONS:

EFW Pump Turbine K3 tripped on over speed due to a loss of electric signal to the speed controller.

Power is unavailable to the speed controllerlturbine control cabinet.

P-7A turbine has been reset per Exhibit A (EFW Pump P-7A Overspeed Trip Reset).

INITIATING CUE:

The CRSISM directs you to manually start EFW Pump P-7A and control at approximately 1400 psig discharge pressure per 1106.006 Exhibit C.

ENTERGY OPERATIONS INCORPORATED ARKANSAS NUCLEAR ONE DOCUMENT NO. CHANGE NO.

TITLE: ICW SYSTEM OPERATING PROCEDURE WORK PLAN EXP. DATE N/A SAFETY-RELATED IPTE SET # EYES ONO EIYES NO TEMP MOD LEVEL OF USE YES QN0 CONTINUOUS D REFERENCE INFORMATIONAL PROGRAMMATIC EXCLUSION PER EN-LI-I 00 L:JYES__NO When you see these TRAPS Get these TOOLS Time Pressure Effective Communication Distractionhlnterruption Questioning Attitude Multiple Tasks Placekeeping Over Confidence Self Check Vague or Interpretive Guidance Peer Check First ShiftiLast Shift Knowledge Peer Pressure Procedures ChangelOff Normal Job Briefing Physical Environment Coaching Mental Stress (Home or Work) Turnover VERIFIED BY I DATE I TIME FORM TITLE: FORM NO. CHANGE NO.

VERIFICATION COVER SHEET 1000.006A 054

rPROC.IWORK PLAN NO.

1104.028 PROCEDUREIWORK PLAN TITLE:

ICW SYSTEM OPERATING PROCEDURE NOTE I PAGE:

CHANGE:

and RCP 31 of 118 029 StopPing an 1CM pump can cause CRC SU??LY FILTER zP Hi MOB-Il MOTOR COOLING FLOW LO (K08-E6) 10.0 Switching 1CM Pumps (P33A, B, or C)

CAUT ION When switching 1CM Pump alignment, running both Dumps lfl parallel for 3 minutes reduces the possibility of trapped air causing a system transient.

NOTE The ton-Nuclear loop normally has a higher activity level than the nuclear loop. If both loops are crossconnected via the 1CM Surge Tank drain line, Non-Nuclear loop process monitor activity will lower and nuclear loop process monitor activity will rise, possibly to the alarm setpoint.

10.1 IF desired to start P33B AND secure P33A, WHEN P-33A and P33C are running, THEN perform the following:

CAUTION

During filling of P33A 1CM pump following maintenance, air entrained in the 1CM system following venting was carried throughout the system resulting air binding of 1CM components. CR-ANO12006-00612

Restoration of an 1CM pump following maintenance with ONLY one train of CR0 cooling available should he evaluated prior to starting. Air ertraineo in the 1CM PUmP discharge can degrade CEO cooling flow.

Leakage between 1CM loops car foul CRC Filters. When there is leakage between i.oops, raise monitoring cf CR0 Pre-filters (F61A & B) and Cooling Mater Filters (F20A & B;

Opening the 1CM pump discharge crossconnect valves) prior to opening the suction crossconnect valve (s can result in cverfiowing the Nuclear 1CM Surge tank due tu pressure differences in the 1CM loops.

nas ceen urainec, A. Verify tne towlng uacres mcsei:

1CM Purrc FISP Disch lscl 1CMSB

wurro cS3 auc: stI

1CM Pump PSIB Vent (ICMl191

1CM Pump -33B Oisch Line Drain (1CMlI leA)

1CM Pump P-SIB Suct Line Drain

)ICMl177B)

B. Periodically monitcir 1CM erpansion tank level during refill,

PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE:

PAGE: 32 of 118 1104.028 ICW SYSTEM OPERATING PROCEDURE CHANGE: 029 C. Slowly open ICWlB.

0. Throttle open ICWll77A.

F. WHEN air is vented, THEN close ICWll77A.

F. Open ICF-3B.

S. oent a_ or Inc CPu Cocoon system components per Venting CRC Coolinc System Components, exniblt of thos procedure.

10.1.2 IF desi. red, TI-lEN install plug on the ICW surge ranks drain lone.

A. Open the followiny valves:

ION Surge 1k T37A Crc, to Aux Plop (1CW-130A)

ICIJ Surge 1k 1BIB Crc to Aux Bldg )ICW-133B) 10.1.3 Open A/B crossconnect valves.:

A. ION Bumps Suction Crossconnect cCV2240)

B. ICE Pumps Discharge Crossconnect (CV-2238) 10.1.4 Vent P33B as necessary by opening ICE Pump P33B Vent (ICW-119l)

A. Close ICWll9l.

10.1.5 Start P-33B.

A. IF CRD cooling pumps indicate air binding (i.e.

lowering pump discharge pressure, flow oscillations or standby pump start),

THEN perform Venting CRD Cooling System Components, exhibit of this procedure.

NOTE P ressure and flow instlvull ties from stopping P33A in the next step can cause a CRD cooling pump (P79A/B) to autostart.

10.1.6 EHF.1.J P33B has run at least 3 minutes, THEN stop P-33A.

10.1.7 Ve.rify flow is normal )lv000 gpm) on ICE Coolers Inlet Flow NonWoo (FI2218) )CO9) 10.1.8 IF desired, THFN station operator to monitor ICE Surge Tanks for

PROC.IWORK PLAN NO. PROCEDURE/WORK PLAN TITLE: I PAGE: 33 of 118 1104.028 ICW SYSTEM OPERATING PROCEDURE CHANGE: 029

[

10.2 IF desired to start ICW pump P33B AND secure P33C, WHEN P33A and P-33C are running, THEN perform the following:

CAUTION

During filling of P-33A ICW pump following maintenance, air entrained in the ICW system following venting was carried throughout the system resulting air binding of ICW components. CR-ANO-l-200600612

Restoration of an ICW pump following maintenance with ONLY one train of CRD cooling available should be evaluated prior to starting. Air entrained in the ICW pump discharge can degrade CRD cooling flow.

Leakage between ICW loops can foul CRD Filters. When there is leakage between ioops, raise monitoring of CRD Pre-filters (F6lA & B) and CR0 Cooling Water Filters )F20A & B)

Opening the ICW pump discharge cross-connect valve(s) prior to opening the suction cross-connect valve(s) can result in overflowing the Nuclear ICW Surge Tank due to pressure differences in the ICW loops.

10.2.1 IF P33B has been drained, THEN perform the following:

A. Verify the following valves closed:

ICW Pump P33B Disch Isol (ICW3B)

ICW Pump P33B Suct Isol )ICWIB)

ICW Pump P33B Vent )ICW-1191)

ICW Pump P33B Disch Line Drain )ICW-1177A)

ICW Pump P33B Suct Line Drain )ICW-ll77B)

B. Periodically monitor ICW expansion tank level during refill.

C. Slowly open ICW-lB.

0. Throttle open ICW-l177A.

E. WHEN air **is vented, THEN close ICW-ll77A.

F. Open ICW3B.

C. Vent all of the CRD Cooling system components per Venting CR0 Cooling System Components, exhibit of this procedure.

10.2.2 IF desired, THEN install plug on the ICW surge tanks drain line.

A. Open the following valves:

ICW Surge Tk T-37A Pm to Aux Bldg (ICW-l3OA)

ION Susge Tk T-37B Dmn to Aux Bldg (1CW-130H)

I PROC.IWORK PLAN NO. PROCEDUREIWORK PLAN TITLE:

PAGE: 34 of 118 1104.028 ICW SYSTEM OPERATING PROCEDURE CHANGE: 029 10.2 .3 er- 8/C crossccnnect valves:

0 Q

A. ICY Pumps Suction Crossconnect (CV-2241)

B. ICY Pumps Discharge Crossconnect (CV2239) 10.2 .4 Vent P33B as necessary by opening ICY Pump P33B Vent 1

)ICW1191 A. Close ICWll9l.

10.2.5 Start P-33B.

A. IF CRD cooling pumps indicate air binding (i.e.

lowering pump discharge pressure, flow oscillations or standby pump start>,

THEN perform Venting CEO Cooling System Components, exhibit of this procedure.

10.2.6 WHEN P33B has run at least 3 minutes, THEN stop P-33C.

lC.2. Verify flow is normal H2000 gem) on ICY Coolers Inlet Flow Nuclear (P12219) (C09) 10.2.8 IF desired, THEN station operator to monitor ICY Surge Tanks for overflow.

10.3 IF desired to start ICY Pump P33A AND secure P33B, WHEN P333 and p33C are running, THEN perform the following:

CAUT ION

During filling of P-33A ICY pump following maintenance, air entrained in the ICY system following venting was carried throughout the system resulting air binding of ICY components. CRANOl2006006l2

Restoration of an ICY pump following maintenance with ONLY one train of CRC cooling available should be evaluated prior to starting. Air entrained in the ICY pump discharge can degrade CR0 cooling flow.

10. 3.1 IF P33A has been drained, THEN perform the fol lowing:

A. Verrl; tne Iollowon vazves coseo:

IC uo l Ds:- lso IC

ICY Pump P33A Suct Isol (ICYlA)

_a eump eai- ent - rC5 s3

ICY Pump P33A tisch line Drain ICYI 17 6A)

ICY Pump P33A Suct Line Drain (I Cwll76B)

B. Period.ical.1 y monitor ICY exoansion. tank level duri.n refill.

I PROC IWORK PLAN NO.

I PROCEDURE/WORK PLAN TITLE: I PAGE: 35 of 118 1104.028 ICW SYSTEM OPERATING PROCEDURE CHANGE: 029 C. Slowly open ICW-1A.

D. Throttle open ICWll76A.

F. WHEN air is vented, THEN close ICWll76A.

F. Goon ZCW-3A.

C. Vent all of the CRC Cooling system components per Venting CRD Cooling System Components, exhibit of tars procedore.

10.3.2 Vent P33A as necessary by opening Non-Nuc ICW Pump P33A Vent (ICWl193)

A. Close ICWl193.

10.3.3 Start P33A.

A. IF CRD cooling pumps indicate air binding (i.e.

lowering pump discharge pressure, flow oscillations or standby pump start),

Tr perform Venting CR0 Cooling System Components, exhibit of this procedure.

10.3.4 WHEN P33A nas run at least 3 minutes, THEN stop P-33B.

10.3.5 Verify flow is normal (2000 gpm) on ICW Coolers Inlet Plow Non-Nuc (FI-22l8) (COB) 10.3.6 Close A/B crossconnect valves:

A. ICW Pumps Discharge Crossconnect (CV-2238)

B. ICW Pumps Suction Crossconnect (CV2240(

10.3.7 IF Installed, THEN perform the following to remove the vlug installed on the ICW surge tanks drain line:

toe toow:no varves:

urge ow own to rx Bog L7l,

ICW Surge Tk T37B Drn to Aux Bldg (ICW130B)

B. Remove plug from ICW surge tanks drain line.

i PROC.IWORK PLAN NO. PROCEDURE!WORK PLAN TITLE: I PAGE: 36 of 118 I 1104.028 ICW SYSTEM OPERATING PROCEDURE CHANGE: 029 10.4 IF desired to start lCd Pump P33C AND secure P33B, WHEN P-33A and P-33B are running, THEN perform the following:

CAUT ION During filling of P33A ICE pump following maintenance, air entrarned in the ICE system following venting was carried throughout the system resulting air bindiug of ICE components. CRANOi2006006I2 10.4.1 IF 33C has been drained, THEN perform the following:

A. Verify the following valves closed:

ICE Pump P33C Disch 1501 lCW-3C)

ICE Pump P33CSuct Isol (lCW1C)

ICE Pump P33C Vent ICW_1194

ICE Purno P-33C Disch Line Drain ICW1178A)

ICE Pump P33C Soot Line Drain (ZCWll78B)

B. Periodically monitor ICE expansion tank level during refill.

C. Slowly open ICW-lC.

0. Throttle open ICWll78A.

H. WHEN air is vented, THEN close ICWll78A.

F. Open ICW-3C.

G. Vent all of the CR0 Cooling System Components per Venting CRD Cooling System Components, exhibit of this procedure.

PROC.IWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: I PAGE: 37 of 118 I 1104.028 10.4.2 ICW SYSTEM OPERATING PROCEDURE CHANGE:

Vent P-33C as necessary by opening Nuc ICW Pump P-33C Vent 029 L:1CW1194)

. Close CW+/-l94.

10.4.0 Start P33C.

A. IF CR2 cooling pumps indicate air binding (i.e.

lowering pump discharge pressure, flow oscillations or standby pump start>,

THEN perform Venting CRC Cooling System Components, exhibit of this procedure 10.4.4 WHEN P33C has run at least 3 minutes, THEN stop P-33B.

10.4.5 Verify flow is normal (-2000 gpm) on ICW Coolers Inlet Flow Nuclear (P1-2219) (C09) 10.4.6 Close B/C Crossconnect Valves:

A. ICW Pump Discharge Crossconnect (CV2239)

B. ICW Pump Suction Crossconnect (CV2241) 10.4.7 IF installed, THEN perform the following to remove the plug installed on the ICW surge tanks drain line:

A. Close the following valves:

ICW Surge CE T-37A Cm to Aux Bldg )1CW-l3OA)

ION Surge Tk T37B Cm to Aux Bldg ICWl3OB)

B. Remove plug from ICW surge tanks drain line.

Page 1 of 5 JOB PERFORMANCE MEASURE 1 Rev # 11 Date:

Unit:

JPM ID: A1JPM-RO-EFWO2 System/Duty Area: Emergency Feedwater Task: Manual Control of Emergency Feedwater Pump P-7A at the Turbine JTA# ANO1-RO-EFW-NORM-7 KA Value RO 3.1 SRO 3.4 KA

Reference:

061 A2.05 Approved For Administration To: RO X SRO X Task Location: Inside CR Outside CR X Both Suggested Testing Environment and Method (Perform or Simulate):

Plant Site: Simulate Simulator: Lab:

Position Evaluated: RO: SRO:

Actual Testing Environment: Plant Site X Simulator Lab Testing Method: Perform Simulate Approximate Completion Time in Minutes: 10 Minutes Reference(s): 1106.006 EFW Pump Operation Exhibit C (Manual Control of EFW Pump P-7A)

Examinees Name: KCN:

Evaluators Name:

The Examinees 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 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 JPM ID: A1JPM-RO-EFWO2 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner should verify that the exam inee has been briefed per the JPM Examination Briefing Sheet EN-TQ-1 14 .5.

JPM INITIAL TASK CONDITIONS:

EFW Pump Turbine K3 tripped on overspeed due to a loss of electric signal to the speed controller.

Power is unavailable to the speed controller/turbine control cabinet.

P-7A turbine has been reset per Exhibit A (EFW Pump P-7A Overspeed Trip Reset).

INSTRUCTOR NOTE: FYI EFW Pump Turbine K3 steam admission valves are closed and the trip throttle valve is opened in 1106.006 Exhibit A.

TASK STANDARD:

EFW Pump P-7A running per section 1.0 of 1106.006 Exhibit C (at -1400 discharge pressure).

TASK PERFORMANCE AIDS:

Copy of 1106.006 Exhibit C (Manual Control of EFW Pump P-7A).

Page3of5 JPM ID: A1JPM-RO-EFWO2 INITIATING CUE: The CRS/SM directs you to manually start EFW Pump P-7A and control at approximately 1400 psig discharge pressure per 1106.006 Exhibit C.

C PERFORMANCE CHECKLIST STANDARD N/A SAT EXAMINER NOTE:

. Potential question that can be asked during this JPM...

Q Where are emergency flashlights available?

A Alternate Shutdown Locker located in the Control Room Extension Foyer TRANSITION NOTE:

. Proceed to EFW pump room on 335 elevation in Controlled Access of Auxiliary Building.

1. Close EFW Turbine K3 Trip/Throttle Valve (CV- Closed CV-6601A by rotating hand 6601A). wheel in close direction (clockwise).

C POSITIVE CUE:

Handwheel does NOT move any further in the clockwise direction and plate is in contact with the upper limit switch.

2. Request control room to open EFW Turbine K3 Called control room and requested Steam Admission valve (CV-2613 or CV-2663). CV-2613 or CV-2663 to be c opened.

NEGATIVE CUE:

Control Room reports unable to open steam admission valves INSTRUCTOR CUE

When the operator simulates notifying the control room to open CV-261 3 or CV-2663, tell him that there is no power available to CV-261 3 or CV-2663 and direct him as the CRS to open CV-261 3 manually.

3. Open CV-2613 Manually Engaged manual handwheel and rotated handwheel in the counter C POSITIVE CUE: clockwise direction until it stopped.

CV-2613 indicates open locally Verified stem rises on the valve by observing the stem as the valve is opened.

4. Open EFW Turbine K3 Trip/Throttle valve (CV- Slowly opened CV-6601A (counter 6601A). clockwise) until approximately 1400 psig discharge pressure (P1-POSITIVE CUE: 2911A) was attained.

discharge pressure (Pl-2911A) is approximately Pump 1400 psig.

NEGATIVE CUE:

Pump discharge pressure (P1-291 1A) is approximately 500 psig.

Page 4 of 5 C PERFORMANCE CHECKLIST STANDARD N/A SAT

5. Monitor turbine speed indication (if available) to Checked turbine speed locally (SI ensure turbine does not exceed 3776 RPM or 6602) at approximately 3650 RPM pump discharge pressure at 1400 psig. or monitored pump discharge pressure indication (P1-29 1 1A) and POSITIVE CUE: maintained at 1400 psig.

Turbine speed is 3650 RPM as indicated on the REED TACHOMETER (SI-6602) and pump discharge pressure (PI-2911A) 1400 psig. Speed indication on local panel (Sl-6601A) indicates 0 rpm END

Page 5 of 5 JPM ID: A1JPM-RO-EFWO2 INITIAL CONDITIONS:

EFW Pump Turbine K3 tripped on over speed due to a loss of electric signal to the speed controller.

Power is unavailable to the speed controllerlturbine control cabinet.

P-7A turbine has been reset per Exhibit A (EFW Pump P-7A Overspeed Trip Reset).

INITIATING CUE:

The CRS/SM directs you to manually start EFW Pump P-7A and control at approximately 1400 psig discharge pressure per 1106.006 Exhibit C.

p ENTERGY OPERATIONS INCORPORATED ARKANSAS NUCLEAR ONE DOCUMENT NO. CHANGE NO.

TITLE: EMERGENCY FEEDWATER PUMP 1106.006 080 OPERATION WORK PLAN EXP. DATE N/A SAFETY-RELATED IPTE SET# ZYES 1JN0 YES QNO TEMP MOD LEVEL OF USE DYES DNO CONTINUOUS REFERENCE Q INFORMATIONAL PROGRAMMATIC EXCLUSION PER EN-LI-100 EYES NO When you see these TRAPS Get these TOOLS Time Pressure Effective Communication Distractionll nterruption Questioning Attitude Multiple Tasks Placekeeping Over Confidence Self Check Vague or Interpretive Guidance Peer Check First Shift/Last Shift Knowledge Peer Pressure Procedures Change/Off Normal Job Briefing Physical Environment Coaching Mental Stress (Home or Work) Turnover VERIFIED BY DATE TIME FORM TVTLE: FORM NO. CHANGE NO.

VERIFICATION COVER SHEET 1000.006A 054

PROCJWORK PLAN NO. PROCEDUREJWORK PLAN TITLE: PAGE: 86 of 217 1106.006 EMERGENCY FEEDWATER PUMP OPERATION CHANGE: 080 1106.006 04 / 03 / 04 EXHIBIT C Page 1 of 2 MANUAL CONTROL OF EMERGENCY FEEDWATER PUMP P-7A NOTE Loss of electrical signal to the speed controller or loss of control oil pressure wili aow nra Turosne Hi Coy Servo CV6rb to traver tuli open and cause an overspeed trip of the turbine.

1.0 IF EFW Pump Turbine K3 tripped either on lOSS of electric signal to speed controller OR on loss of control oil pressure AND fault cannot be corrected, THEN turbine speed may be manually controlled as follows:

1.1 Reset trip per Exhibit A, Emergency Feedwater Pump P-7A Overspeed Trip Reset.

1.2 Close EFW Turbine K3 Trip/Throttle Valve (CV660lA) by turning handwheel fully clockwise.

1.3 Oten EFW Pump Turbine K3 Steam Admission Valve (CV2613 or CV2663) 1.4 Slowly open CV660lA by turning handwheel counterclockwise until desired turbine speed or discharge pressure is reached.

I CAUTION Exceeding turbine speed of 3776 RPM may result in excessive discharge pressure with P7A suction aligned to Service Water.

1.5 Monitor turbine speed OR pump discharge pressure.

1.5.1 Throttle CV660lA as necessary to maintain pump discharge pressure -1400 psic at EFW in7A Discharqe Pressure P128I1A OR as directed by ccntrol room personnel.

IF turbine speed indication is available, THEN control turbine speed in650 RPM.

1,5.3 WHEN failure is corrected, THEN sloul: rpen Cin66IIA fully while Ironitoring for proper turn to oreen: nonoono on 1.5.4 Verify P7A TURBINE TRIP (K12-B5) clear.

j PROC.IWORK PLAN NO. PROCEDUREIWORK PLAN TITLE: I PAGE: 87 of 217 1106.006 EMERGENCY FEEDWATER PUMP OPERATION I CHANGE: 080 1106.006 04 / 03 / 04 Page 2 of 2 MANUAC CONTROL OF EMERGENCE FEEDWATER PUMP P7A 2.0 IF EFW Pump Turbine K3 is in operation, AID manuai control is being taken to avoid i055 of P-7A due to anticipated loss of control power, THEN perform the foilowing:

NOTE The following step wili result In a PtA IIiRETNE TRIP (Kl2B5, alarm.

2.1 Slowiy throttle closed on DEW Turbine K3 Trip/Throttle Valve (CV-660lA), until EFW Turbine K3 Gov Servo (CV660lB) is full open, AND EFW P7A Discharge Pressure (PI2811A) drops slightly.

2.2 Notify control room personnel of the following:

Manual control of P-in has been established

. EFW P7A Turbine Control Power breaker (02130) may be opened, if required CAUTION Exceeding turbine speed of 3776 RPM may result in excessive discharge pressure with P7A suction aligned to Service Water.

2.3 Monitor ourhine speed or oump discharge pressure.

Tnrootle CV-66UIA as necessary to maintain pump discharge pressure l400 psig at RPM P7A Discharge Pressure (PI281lA) OR as directed by control room personnel.

2.3.2 IF turbine speed indication is available, THEN control turbine speed --3650 RPM.

2.4 WHEN failores are correctea AND control power Is revalned, tHEN nerforn the followlnc:

2.4.1 Verify breaker D2.J.30 is do Slowly open CV660lA fully while monitoring for proper speed control by the governor valve.

A. Close CV660lA 3/4 turn to prevent binding on heatun.

Page 1 of 5 JOB PERFORMANCE MEASURE Unit: 1 Rev # 2 Date:

JPM ID: A1JPM-RO-ED022 System/Duty Area: Electrical Distribution System Task: Inverter Yl 1 Shutdown with RS1 Supplied from Y-1 I Alternate AC Source JTA# ANO1-RO-120AC-NORM-1 1 KA Value RO 3.1 SRO 3.1 KA

Reference:

062 A4.07 Approved For Administration To: RO X SRO X Task Location: Inside CR Outside CR X Both Suggested Testing Environment and Method (Perform or Simulate):

Plant Site: Simulate Simulator: Lab:

Position Evaluated: RO: SRO:

Actual Testing Environment: Plant Site X Simulator Lab Testing Method: Perform Simulate X Approximate Completion Time in Minutes: 10 Minutes Reference(s): 1107.003 Section 8.6 Examinees Name: KCN:

Evaluators Name:

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

Satisfactory: Unsatisfactory:

Performance Checklist Comments:

Stop Time Total Time Start Time

Signed 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 JPM ID: A1JPM-RO-ED022 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner should verify that the examinee has been briefed per the JPM Examination Briefing Sheet EN-TQ-114 .5.

JPM INITIAL TASK CONDITIONS:

Plant is in Cold Shutdown MODE 5. Electricians are standing by in their shop if needed.

TASK STANDARD:

Inverter Y-1 1 is shutdown and inverter loads are being supplied from Alternate AC Power Source.

TASK PERFORMANCE AIDS:

1107.003 Inverter and 120V Vital AC Distribution, Section 8.6.

Page 3 of 5 JPM ID: Al JPM-RO-ED022 INITIATING CUE: The CRS/SM directs you to perform Inverter Yl 1 Shutdown with RS1 to remain in service supplied from Yl 1 Alternate Source. The CRS/SM has entered all applicable TS Conditions and associated time clocks.

CRITICAL STEPS: 2, 4, 5, 6 C PERFORMANCE CHECKLIST STANDARD N/A SAT UNSAT 1 Check lnverter Yl 1 UNIT IN SYNC Verified Yl 1 UNIT IN SYNC light ON light is ON and frequency is between and frequency between 59.7 and 59.7 and 60.3 hertz. 60.3 hertz.

POSITIVE CUE:

Yl 1 unit in Sync light (GREEN) is ON and frequency on meter (El) is 60 hertz.

2. Shift inverter Yl 1 to the alternate Depressed Yl 1 ALTERNATE AC source. SOURCE TO LOAD push-button (PB-ll0l).

C POSITIVE CUE:

Inverter Yl 1 ALTERNATE SOURCE TO LOAD push-button (PB-llOl) depressed.

EXAMINER NOTE: The following is additional information, is not provided by the procedure, and is not part of the standard. After performance of the previous step, the Inverter should have this indication:

- IN SYNC (green) ON Si IN NORMAL SOURCE POSITION (green) ON

- INVERTER SUPPLYING LOAD (green) OFF

- ALT SOURCE SUPPLYING LOAD (amber) ON

- Si IN ALT SOURCE POSITION (amber) OFF

- Yl 1 TO RSI (amber) ON

- ALL meters remain the same

3. At inverter Yl 1 verify ALTERNATE Verified alternate source supplying SOURCE SUPPLYING LOAD light load by observing ALTERNATE ON and INVERTER SUPPLYING SOURCE SUPPLYING LOAD light LOAD light OFF, ON and INVERTER SUPPLYING LOAD light OFF.

POSITIVE CUE:

Alternate source supplying load light (AMBER) ON and inverter supplying load light (GREEN) OFF.

NEGATIVE CUE:

Inverter supplying load light (GREEN)

ON and alternate source supplying load light (AMBER) OFF.

Page 4 of 5 C PERFORMANCE CHECKLIST STANDARD N/A SAT UNSAT EXAMINER NOTE: The following is additional information, is not provided by the procedure, and is not part of the standard. After performance of the following step, the Inverter should have this indication:

- IN SYNC (green) ON

- Si IN NORMAL SOURCE POSITION (green) OFF

- INVERTER SUPPLYING LOAD (green) OFF

- ALT SOURCE SUPPLYING LOAD (amber) ON

- Si IN ALT SOURCE POSITION (amber) ON

- Yli TO RS1 (amber) ON

- ALL meters remain the same

4. Place Yl 1 manual selector switch Placed the Yl 1 manual selector (HS-1122) in the ALTERNATE switch (bottom switch) to the SOURCE TO LOAD position. ALTERNATE SOURCE TO LOAD C position.

POSITIVE CUE:

Yl 1 manual selector switch (HS 1122) is in the ALTERNATE SOURCE TO LOAD position.

E)(AMINER NOTE: After performance of the following step, Inverter indication does NOT change.

5. Open InverterYll INVERTER InverterYll INVERTER OUTPUT OUTPUT breaker on front of Inverter breaker was moved to the open Yl 1. position.

C POSITIVE CUE:

Inverter Output breaker (B2) indicates open.

EXAMINER NOTE: The following is additional information, is not provided by the procedure, and is not part of the standard. After performance of the following step, the Inverter should have this indication:

All lights remain the same

- Yl 1 120VDC INPUT goes to zero

- Yl I FREQUENCY OUTPUT might go to some value other than 60 ALL other meters remain the same since they are downstream of the manual selector switch or indicate Alternate Source status.

6. Open inverterYil DC INPUT lnverterYii DC INPUT breakerwas breaker on front of Inverter Yl 1. moved to the open position.

C POSITIVE CUE:

DC INPUT breaker (Bi) indicates open and Inverter Output Volt Meter (V2) indicates zero.

END

Page 5 of 5 JPM ID: A1JPM-RO-ED022 INITIAL CONDITIONS:

Plant is in Cold Shutdown MODE 5. Electricians are standing by in their shop if needed.

INITIATING CUE:

The CRSISM directs you to perform Inverter Yl I Shutdown with RSI to remain in service supplied from Yll Alternate Source.

The CRSISM has entered all applicable TS Conditions and associated time clocks.

PROCJWORK PLAN NO. PROCEDUREIWORK PLAN TITLE:

I PAGE: 50 of 247 1107.003 INVERTER AND 120V VITAL AC DISTRIBUTION CHANGE: 020 CAUTION hoproper breaker oper atcon can resut OSS of power to a vital 120V AC panel that could cause a plant trip or upset.

NOTE

In Modes 14, maintainint ASI energized from inverter Alternate Source reourres entry onto Ta .b. / Conartoon F.

If in Mode 5 or 6, any TS component required by TS 3.8.10 which is supplied by an Inverter on Alternate Source, requires entry into TS 3.8.8 Condition A.

Steps n this section are expected to bring in alarm RS1 INVERTER TROUBLE KOl-A5.

Due to past problems with inverter transfers, it is recommended that Electrical Maintenance personnel are present for routine inverter transfers.

8.6 Inverter Yll Shutdown with RS1 to Remain in Service Supplied from Yll Alternate Source Enter applicable TS Condition and associated zime clock.

8.6.2 IF RSl NOT on Yll Alternate Source, THEN perform the following to transfer RSl to Yll Alternate Source:

A. Check Inverter Yll UNIT IN SYNC light is ON b direct observation OR Electrical Maintenance verification.

B. Check Inverter Yll frequency is between 59.7 and 60.3 hertz.

I CAUTION Transferrinc cut of sync can caose loss of load. If UNIT IN SYNC hoff is NOT on, Electrical Maintenance assistance is required.

C. Depress Yl 1 AITEP..NATE SOURCE TO LOAD pushbutton C. Check Yll ALTERNATE SOURCE SUPELIZNG LOAD light ON by direct observation OR Electrical Maintenance verification.

F. Check Yll INVERTER SUPPLYING LOAD light off.

PROC.!WORK PLAN NO. PROCEDUREIWORK PLAN TITLE:

PAGE: 51 of 247 1107.003 INVERTER AND 120V VITAL AC DISTRIBUTION CHANGE: 020 NOTE

If ALTERNAtE SOURCE SUPPLYING LOAD light is on, the load remains on Alternate Source regardless of position of manual selector switch.

If manual selector switch is in ALTERNATE SOURCE TO LOAD position, the load remains on Alternate Source regardless of position of static switch.

8.6.3 Place Yll manual selector switch (HS1122) in ALTERNATE SOURCE TO LOAD position.

NOTE

Idle inverters should be shut down to minimize extra heat generation in the room.

Idle inverters may remain energized for maintenance activities.

8.6.4 Perform the following to shutdown Inverter Yll:

A. Open Inverter Yll INVERTER OUTPUT breaker on front of Inverter Yll.

B. Open Inverter Yll DC INPUT breaker on front of Inverter Yll.

Eiectrical or N/A

Page 1 of 5 JPM ID: A1JPM-RO-GRWO1 JOB PERFORMANCE MEASURE Unit: 1 Rev # 2 Date:

JPM ID: A1JPM-RO-GRWO1 System/Duty Area: Gaseous Radwaste I Radioactivity Release Task: Commence Waste Gas Decay Tank Release JA# ANO1-WCO-GZO1-NORM-1 1 KAValueRO 3.1 SRO 3.9 KAReference 071 A426 Approved For Administration To: RO X SRO x Task Location: Inside CR: Outside CR: X Both:

Suggested Testing Environment And Method (Perform Or Simulate #):

Plant Site: Simulate Simulator: Lab:

Position Evaluated: RO: SRO:

Actual Testing Environment: Simulator: Plant Site: x Lab Testing Method: Simulate: X Perform:

Approximate Completion Time In Minutes: 15 Minutes Reference(s): 1104.022, Chg. 033-01-0, Att. C Examinees Name: KC N:

Evaluators Name:

The Examinees 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 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 JPM ID: A1JPM-RO-GRWO1 THE EXAMINER SHALL REVIEW THE FOLLOWING WITH THE EXAMINEE:

The examiner should verify that the examinee has been briefed per the JPM Examination Briefing Sheet EN-TQ-114 .5.

JPM INITIAL TASK CONDITIONS:

The Shift Chemist has returned Gaseous Release Permit 1GW-201 1-002 to the Control Room for T-18A Waste Gas Decay Tank.

TASK STANDARD:

Release commenced per 1104.022, Att. C, at flow rate specified.

TASK PERFORMANCE AIDS:

1104022, Att. C, Completed and place-kept through step 4.3.1.

Page3of5 JPM ID: A1JPM-RO-GRWO1 INITIATING CUE: The CRS directs you to commence T-18A release beginning with step 4.3.2 of 1104.022, Att. C.

CRITICAL ELEMENTS (c): 1 3, 6 and 7 C PERFORMANCE CHECKLIST STANDARD N/A SAT

1. Open T-1 8A outlet valve. Operator opened T-1 8A outlet valve, GZ-13A.

POSITIVE CUE:

GZ-1 3A open (stem out) and verified by second operator.

2. Verify other decay tank outlet isolations closed. Operator verified outlet valves GZ-1 3B/C/D closed.

POSITIVE CUE:

GZ-1 3B/C/D closed.

EXAMINER NOTE:

. IF a Hold Card is present on GZ-15, tell the examinee to ignore the Hold Card for the purpose of this JPM.

3. Open CV-4820 outlet isolation GZ-15. Operator opened CV-4820 outlet isolation GZ-15.

C POSITIVE CUE:

GZ-15 is open (stem out).

TRANSITION NOTE:

. The examinee should proceed to the 354 elevation.

4. Notify control room of intent to begin release. Operator contacted control room and informed them of intent to POSITIVE CUE: begin release.

Control Room notified.

5. Record release data. Operator recorded in Att. C Release number, start time, date POSITIVE CUE: and tank being released and Data recorded and chart recorders marked. marked chart recorders with same information. Operator will contact control room and have them mark RR-4830 (Process Radiation Monitor Effluent Recorder).

EXAMINER CUE:

. Inform the examinee that annunciator Ki 15-CS, WASTE GAS DECAY TK HDR PRESS HI is in alarm.

6. Hold HS-4820 in the open position Operator placed HS-4820 in OPEN position and held it.

POSITIVE CUE:

c HS-4820 is held in the OPEN position

Page4of5 JPM ID: A1JPM-RO-GRWO1 C PERFORMANCE CHECKLIST STANDARD NIA SAT EXAMINER CUE:

When the examinee opens CV-4820 using HIC-4820 (while holding HS-4820), inform the examinee that Ki 1 5-C5, WASTE GAS DECAY TK HDR PRESS HI alarm is clear. (at this point the examinee may release HS-4820)

7. Open discharge header flow control valve. Operator opened CV-4820 and established release flow rate POSITIVE CUE: listed on preliminary report.

CV-4820 (using HIC-4820 on C115) opened and data recorded. Annunciator Ki 1 5-C5 is clear and HS-4820 has been released.

C NEGATIVE CUE:

Inform the examinee that the initial flow rate is greater than the allowed flow rate on the preliminary report.

If negative cue provided then the exam inee should adjust the flow controller (HIC-4820 on Cli 5) for CV 4820 to throttle the valve closed and reduce the flow rate.

EXAMINER NOTE:

Remaining steps are continuous action steps until release is complete.

END

Page5of5 JPM ID: A1JPM-RO-GRWO1 INITIAL CONDITIONS:

The Shift Chemist has returned Gaseous Release Permit IGW-2011-002 to the Control Room for T-18A Waste Gas Decay Tank.

A Pre-Job brief has been conducted and a second operator is available for verification of reach rod operated valves.

INITIATING CUE:

The CRS directs you to commence T-18A release beginning with step 4.3.2 of 1104.022, Aft. C.

ENTERGY OPERATIONS INCORPORATED ARKANSAS NUCLEAR ONE DOCUMENT NO. CHANGE N TITLE: GASEOUS RADWASTE SYSTEM WORK PLAN EXP. DATE NIA SAFETY-RELATED IPTE SET # EYES DNO DYES NO TEMP MOD LEVEL OF USE DYES NO CONTINUOUS Q REFERENCE D INFORMATIONAL PROGRAMMATIC EXCLUSION PER EN-LI-100 DYES__NO When you see these TRAPS Get these TOOLS Time Pressure Effective Communication Distraction/interruption Questioning Attitude Multiple Tasks Placekeeping Over Confidence Self Check Vague or Interpretive Guidance Peer Check First Shift/Last Shift Knowledge Peer Pressure Procedures Change/Off Normal Job Briefing Physical Environment Coaching Mental Stress (Home or Work) Turnover VERIFIED BY I DATE TIME FORM TITLE: FORM NO. CHANGE NO.

VERIFICATION COVER SHEET 1000.006A 054

PROC/WORK PLAN NO.

I PROCEDURE/WORK PLAN TITLE: I PAGE: 44 of 52 f 1104.022 GASEOUS RADWASTE SYSTEM ATTACHMENT C CHANGE: 035 Page 1 of 9 GASEOUS RELEASE PERMIT PERMIT # /vJZc(/ CO (Assigned by Chemistry) 7a-Z3oJ Date INITIALS

44) REQUEST (Operations) 5r-Waste Gas Decay Tank (circle one) : LA T-l8B T-18C T-l8D Initial tank pressure NOTE 2it-If plant and tank conditions permit, short-lived gaseous activity should be held for a minimum of 30 days to allow for decay.

Ensure tags have been hung on tank to be released per Waste Gas Decay Tanks (T18A thru D) section of this procedure.

Date tags hung: IZ Duration tags hung: 7days IF shortlived gaseous activity is present, THEN perform one of the following:

Hold tank contents for a minimum of 30 days.

AtExplain why tank contents must be released in <30 days.

Check Gaseous Radwaste Process Monitor (RI4830) available by one of the fcllowing methods (ODCM App.i, 2.2-2.l.a)

IF monitor cocnt rate is l000 rpm, THEN select CHECK SOURCE on RI-4830 and verify that the monitor responds to check source with a count rate rise >100 rpm.

IF monitor count rate >1000 cpm, THEN verify that count rate is <8.9E6.

IF neither 1.5.1 nor 1.5.2 can be satisfied, THEN RI-4830 shall be considered unavailable for this release.

PROC IWORK PLAN NO PROCEDUREIWORK PLAN TITLE: I PAGE: 45 of 52 1104.022 GASEOUS RADWASTE SYSTEM CHANGE: 035 j

ATTACHMENT C Page 2 of 9 Shift Manager/CRS Approval 72 SM/CRS Submitt,4t Chemst, for ,alysis by: Date 7-// Time ANALYSIS (Chemistry)

Sample of 9nk for gamma spectroscopy obtained by:

Record M&TE number L4eQ-OZGo Cal Expiration Date NOTE If an independent sample and analysis is needed per step , independent sampling and analysis may be performed concurrently with the following steps.

)

Gamma spectroscopy performed by:

Gamma spectroscopy report reviewed by:

IF Gaseous Radwaste (RI-4830) is inoperable OR is unavailable (per steps or . 1),

THEN perform the following:

OTHERWISE mark N/A. (ODCM App.1, Table 2.21)

An independent sample shall be obtained and analyzed.

Independent sample and analysis performed by:

Date An independent verification of computer input data shall be performed. Independent verification performed by:

Date Preliminary release repcr: generated by: Jv1L L;-1 Tank pressure at which release is to be terminated by:_

SPING 2 serpoinc value(s) adjusted per 1634.051 and Form 1604.O5lE by:

Preliminary report returned to operations by:

Gate Time

I PROC.!WORK PLAN NO. ( PROCEDURE/WORK PLAN TITLE: I PAGE: 46 of 521 1104.022 GASEOUS RADWASTE SYSTEM CHANGE: 035 ATTACHMENT C Page 3 of 9 1VERIFiCATION OF TECH SPEC COMMITMENTS (Operations)

.1 Verify Waste Gas Decay Tank circled in rr 1.1 is the same tank as:

Tank that was sampled in . 1. and Same tank as listed on preliminary report.

Verify appropriate signature on preliminary report.

Verify no other Unit 1 gaseous release in progress.

Verify Radwaste Area Exhaust Fan (VEF-8A or VEF-8B) running (circle one)

Verify SPING 2 Radwaste Area (RX-9825) status is Normal on RDACS (ODCM App. 1, 2.2-2.2.a, b, and c)

/

IF Gaseous Radwaste (RI-4830) is operable AND is available, THEN verify proper operation of the associated interlocks and the Gaseous Waste DISCH Flow (FR-4831) as follows:

(ODCM App.l, Table 2.2-1).

OTHERWISE mark r 3,. N/A and GO TO

/ .

. J Check Gaseous Ractwaste Process Monitor (RI-4830) available by one of the following nethods (ODCM App.l, 2.2-2.l.a):

IF monitor count rate is l000 cpm, THEN select CHECK SOURCE on RI-4830 AND verify that the monitor responds to check source with a count rate rise >100 cpm.

IF monitor count rate >1000 cpm, THEN verify that count rate is <8.9E6.

IF neither A nor B above can be satisfied, THEN RI4830 shall be considered unavailable AND N/A the remaicder of this step.

3 .2 Verfy tank outlet valves closed:

T-l8A Outlet Isolation (GZ-l3A)

I Tl8B Outlet Isolation (GZl3B) 7Tl8C Outlet Isolation (GZ13C)

T-l8D Outlet Isolation (GZ-13D)

Verify Station Vent Discharge Valve (CV4830)

Verify FR-4831 indicates system flow from T-17

f PROC/WORK PLAN NO. I PROCEDUREIWORK PLAN TITLE: PAGE: 47 of 52 1104.022 GASEOUS RADWASTE SYSTEM CHANGE: 035 ATTACHMENT C Page 4 of 9 Open T-l8s Discharge to Gaseous Radwaste Discharge Header Flow Control Valve (CV-4820)

Verify ABVH Diversion to T17 (CV4806) closed.

Place RI-4830 in CHECK SOURCE.

IF necessary, THEN lower alarm setpoint until high alarm is received.

Verify Gaseous Radwaste Disch Isol (CV-4830) closes.

Verify CV4820 closes.

A. Lower HIC-4820 to 0% open.

Verify CV-4806 opens.

Verify system flow on FR483l is --0.

Verify appropriate alarms on control panels.

I WASTE GAS DISCHARGE LINE RAD HI (Kl15-B5)

Gaseous Radwaste Monitor (RI4830) alarm PROCESS MONITORS HIGH RAD (KlO-B2)

RADWASTE GAS PANEL TROUBLE (K09-D5)

Reset RI4830.

Open CV-4830.

Verify system flow on FR483l indicates purge flow.

Close CV-4806 Clear alarms.

A/il IF RI-4830 is inoperable, OR is unavailable, THEN perform the following:

Open CV-4830.

Close CV-4806.

4frZ

2. has been performed.

PROC.IWORK PLAN NO. PROCEDURE!WORK PLAN TITLE: PAGE: 48 of 52 1104.022 GASEOUS RADWASTE SYSTEM CHANGE: 035

[

ATTACHMENT C Page 5 of 9 Shift Manager/CRS approval to proceed with release:

NOTE Simultaneous radioactive gaseous releases are not permitted.

SM/ CRS Unit 1 j 7 x.. SM / CRS Unit 2 4.0 RELEASE (Operations>

IF Gaseous Radwaste (RI-4830) is operable AND is available, THEN erform the following:

41) Record RI-4830 pre-release, as-found setpoint: cpm.

Record Setpoint from preliminary report:

Setpoint: cpm IF setpoint from preliminary report is <50,000 cpm, THEN 50,000 cpm should be used as this release setpoint.

Adjust setpoint to cpm (from preliminary report, or 50,000 cprrt, whichever is greater>

Licensed Operator, other than individual who initially set RI4830 setpoint independently verify correct RI-4830 setpoint from preliminary report. ,

Independent verification by 4 Verify T-l8s Discharge to Gaseous Radwaste Discharge Header Flow Control Valve (CV4820) closed.

Align T18 for release as follows:

Remove tag on the T-l8 outlet valve.

i PROC/WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: PAGE: 49 of 52 1104.022 GASEOUS RADWASTE SYSTEM CHANGE: 035 ATTACHMENT C Page 6 of 9 NOTE The following step can cause the alarm T-l8 DISCHARGE LINE PRESSURE HIGH and is expected for this alignment. Alarm should clear when release starts.

4.3.2 Open the outlet valve of the tank to be released. Check tte (V) valve that is opened.

Tl8A Outlet Isolation (GZl3A)

TlBB Outlet Isolation (GZl3B)

Tl8C Outlet Isolation (GZl3C)

Tl8D Outlet Isolation (GZl3D) 4.3.3 Verify other outlet isolations closed.

4.3.4 IF Gaseous Radwaste (RI4830) is inoperable OR is unavailable, THEN perform independent verification of (ODCM App.l, Table 2.21).

Independent verification 4.4 Open CV4820 Outlet Isol (GZl5) 4.5 Notify control room of intent to begin release.

4.6 Record the following data:

Permit Number

Release

Release Start Time

Date

Tank being released 4.6.1 Mark the same data on the following recorders:

Gaseous Waste DISCH Flow (FR-483l)

Process Radiation Monitoring Effluent Recorder (RR4830)

I PROC/WORK PLAN NO.

1104.022 PROCEDURE/WORK PLAN TITLE:

GASEOUS RADWASTE SYSTEM PAGE: 50 of 52 CHANGE: 035 ATTACHMENT C Page 7 of 9 NOTE If T-l8 DISCHARGE LINE PRESSURE HIGH alarm is present, then HS4820 must be held in the open position while operating HIC4820. When alarm is clear, then 35-4820 may be released.

4.7 While monitoring FR4831, slowly operate HI04820 to open CV4820 and establish the release flow rate listed on the prelinnary report:

< _j _cfm (00CM App.l, 2.2-2.l.b) 4.8 IS CV-4830 trips closed during release due to high 4 radiation, THEN this release shall be terminated per Waste Gas Discharge Line Radiation High (1203.006).

NOTE An empty and isolated T18 can pressurize during a release due to pressure in the discharge header leaking back through a discharge valve that is not gas tight. To ensure that the second T-18 was pressurized from the releasing tank it must meet the following criteria:

Initial TlB pressure was O psig.

Pressure rise began when release path aligned.

No other venting or no Waste Gas Compressor operation was in progress.

No other T-lS experienced a coincident pressure drop.

Under this condition the release may continue.

4.9 WHEN tank pressure is -

(value listed in ccp 2, of this attachment),

THEN terminate release as follows:

4.9.1 Close CV4820.

4.9.2 Verify flow rate on FR483l drops to the approxil ate flow setup for T-l7 purge.

4.9.3 Close CV-4820 Outlet Isol (GZ-l5) 4.10 Notify control room that release is complete.

4.11 Record the following data:

Time release completed

Date

Release permit number 4.11.1 Mark same data on the following recorders:

FR483l

RR4830

i PROCJWORK PLAN NO.

1104.022 PROCEDURE/WORK PLAN TITLE:

GASEOUS RADWASTE SYSTEM PAGE: 51 of 52 CHANGE: 035 ATTACHMENT C Page 8 of 9 4.12 Close outlet valve of tank that was released.

Check (V) the valve that is closed:

GZl3A GZl3B GZ--l3C GZl3D 4.13 Remove tag from inlet valve of tank that was released.

4.14 Record final tank pressure 4.15 Pressurize tank released to 2 psig with N 2 as follows:

4.15.1 Place N 2 to T18s regulator (PCV4805) into service as follows:

A. Open the following valves:

PCV4805 Irlet Valve 2 (N 48051)

PCV4805 Outlet Valve (N48052) 2 B. Set PCV4805 at l5l8 psig.

4.15.2 Momentarily open N 2 supply to tank.

Check (V) the valve that is opened:

T18A N 2 Inlet Isol (N 2 l5)

TlBB 2 N Inlet Isol 16) 7 (N

Tl8C 1 N Inlet Isol 17) 2 (N

Tl83 2 N Inlet Isol l8) 2 (N

A. Close the T-l8 N2 Inlet Isol opened above.

4.15.3 IF nitrogen to Tl8s is no longer required, THEN close the following valves:

PCV4805 Inlet Valve (N 2 4805l)

PCV4805 Outlet Valve (N 4

2 8O52)

I PROC/WORK PLAN NO. PROCEDURE/WORK PLAN TITLE: I PAGE: 52 of 521 1104.022 GASEOUS RADWASTE SYSTEM CHANGE: 035 ATTACHMENT C Page 9 of 9 4.16 Purge and restore RE4830 as follows:

4.16.1 Raise Waste Gas Surge Tank (T-17) pressure to greater than atmospheric but below 16.9 psia to avoid start of Waste Gas Compressor (C9A or C-9B) by slightly opening PCV-48l2 Bypass Valve 48123) 2 (N

4.16.2 IF RE4830 was operable for this release AND RE-4830 has been purged to minimum reading, THEN perform one of the following:

Adjust alarm setpoint to the as-found setpoint recorded previously for this release, or

Adjust to new setpoint by performing Radiation Monitoring System Check and Test (1305.001) Supplement 5 for RI4830.

4.16.3 Verify N48l23 closed.

4.16.4 Check PCV48l2 maintains Tl7 pressure greater than atmospheric pressure.

A. IF PCV4812 does NOT maintain adequate T-17 p re S Sure, THEN verify WR/WO initiated to check setpo2nt.

Performed by Ops Accepted by __________________

_________________ SM/CRS 4.17 Permit and preliminary report returned to Chemistry for final analysis of data.

5.0 SPING Restoration (Chemistry) 5.1 Adjust SPINC 2 setpoint per Form l604.O5lE.

Chemistry Supervisor Date

Appendix D Simulator Outline Form ES-D-1 Facility: ANO-1 Scenario No.: 1 Op-Test No.: 2011-1 Examiners: Operators:

Initial Conditions:

80% Power

. 250 EFPD

. Need to Drain RB Sump

. RB fire alarm exhibit posted Turnover:

. 80% Power

. 250 EFPD

. Need to Drain RB Sump to 40%. This is not the first draining of the month and sampling is not required.

Event Event Event No. Maif No Type* Description C-(BOP) Perform Draining of the Reactor Building Sump per 1 CV4400 C-(SRO) 1104.014 with failure of CV-4400 to close.

TS (Technical Specification 3.6.3, Reactor Building Isolation Valves) 2 RC464 Small RCS leak in HPI line (C HPI Line)

) (Technical Specification 3.4.13, ROS Leakage.)

TS 3 Unit Load Demand fails to respond 4 Power reduction/ Plant Shutdown 5 Dl_A1 1 3R C-(BOP) Al 12 fails to open automatically during transfer of auxiliaries M- ALL > RCS leakrate rises requiring Rx Trip and loss of Subcooling 6 RC464 Margin. Trip all running Reactor Coolant Pumps within 2 CT minutes of a Loss of Subcooling Margin.

7 CV063 C-(BOP) ES HPI pump trips post ESAS actuation C-(SRO)Ts (Technical Specification 3.5.2, ECCS Operating)

CT (N)ormal, (R)eactivity, (l)nstrument, (C)omponent, (M)ajor 2011-1 Scenario 1 Page 1 of 10

Appendix 0 Simulator Outline Form ES-D-1 Scenario 1-Objectives

1) Evaluate individual ability to perform Draining of the Reactor Building Sump

2) Evaluate individual ability to identify and respond to excess RCS leakage inside the reactor building

3) Evaluate individual ability to perform a plant power reduction

4) Evaluate individual ability to identify and respond to Integrated Control System component failure

5) Evaluate individual ability to perform electrical breaker operations

6) Evaluate individual ability to identify and respond to failures associated with electrical breaker operations

7) Evaluate individual ability to identify and respond conditions requiring reactor trip based on RCS leakage

8) Evaluate individual ability to perform reactor trip immediate actions

9) Evaluate individual ability to identify and respond to a loss of subcooling margin

10) Evaluate individual ability to identify and respond to an ESAS actuation

11) Evaluate individual ability to identify and respond to a HPI pump trip

12) Evaluate individual ability to recognize when conditions require the entry into technical specifications conditions 2011-1 Scenario 1 Page2oflo

Appendix D Simulator Outline Form ES-D-1 SCENARIO I - NARRATIVE The crew will assume plant responsibility at 80% power. The SRO will direct draining of the Reactor Building Sump per 1104.014. Sump Drain valve CV-4400 will fail in the open position requiring the operator to close CV-4446 to stop the draining of the Reactor Building Sump. The inoperability of CV-4400 will require entry into a 48 completion time per Technical Specification 3.6.3 Condition A C-(BOP) C-(SRO) TS A small RCS leak will develop in the C HPI line and result in excessive leakage of reactor coolant into the reactor building. The crew should identify the excessive leakage and the SRO should enter 1203.039 Excess RCS Leakage ADP. This will require the crew to quantify the leakage and commence a plant shutdown to take the unit off line. The SRO will direct the power reduction using 1203.045, Rapid Plant Shutdown AOP. Technical Specification 3.4.13.A, RCS Operational LEAKAGE, should be referenced by the SRO due to unidentified leakage> 1 gpm.

C-(ATC) C-(SRO) TS When the ATC attempts to lower power using the Unit Load Demand HAND/AUTO station (ULD), the toggle on the ULD will fail to respond requiring the SG/Rx Demand HAND/AUTO station taken to HAND to reduce power. C-(ATC) C-(SRO) Rate of change for the power reduction will be directly controlled by the ATC. R-(ATC)

When power is <50% the BOP should be directed to transfer auxiliaries to Startup #1 transformer (SU1). During the transfer, A-i 12, Unit Aux Feeder Breaker to Al Bus will fail to open automatically requiring the SOP to open it manually. C-(BOP)

Prior to reactor shutdown, the leak in the RCS will get much larger resulting in an uncontrolled loss of RCS inventory. This will require the reactor to be tripped along with ESAS actuation and a loss of subcooling margin. M-(ALL) The crew will complete immediate actions of 1202.001 Reactor Trip EOP and the SRO will transition to 1202.002 Loss of Subcooling Margin EOP.

Reactor Coolant Pumps must be tripped immediately upon loss of subcooling margin but at least within 2 minutes of the loss of subcooling margin. C-(BOP) CT After ESAS actuates the BOP will commence performance of RT-10 for verification of proper ESAS actuation.

The ES HPI pump will trip resulting in a single train of HPI in service. RCS pressure will be >600

so in accordance with RT-10 guidance the highest HPI flow will be required to be throttled to within 20 gpm of the next highest flow rate. The SRO should reference Technical Specification 3.52.A, ECCS Operating, due to loss of one train of ECCS. C-(BOP) C-(SRO) TS, CT 2011-1 Scenario I Page 3 of 10

Appendix D Simulator Outline Form ES-D-1 Simulator Instructions for Scenario I Recall IC 2 Load batch file R02011_1 .txt and use triggers to activate malfunctions.

AULD Fails to Respond OR DI_I000009R FALSE OR Dl_ICC0009L FALSE AUnit Aux to Al fails to open automatically during transfer of auxiliaries IOR Dl_A1I3R FALSE ALeak on C HPI line over 60 seconds (Trigger 1)

IMF RC464 (1 0) 0.05 60 ATrip the C HPI Pump (Trigger 2)

IMF CV063 (2 0)

ACV 4400 fails OPEN IMFCV4400(30)i_______________

Event No. [ Time MaIf. No.

Value!

Ramp Time Event Description Perform Draining of the Reactor Building 1 0 1/

Trigger 3 Sump per 1104.014 with failure of CV-N/A 4400 to close.

2 12 Mm Trigger 1 Small RCS leak in HPI line (C HPI Line) 60sec.

3 18 Mm FALSE!

Preloaded Unit Load Demand fails to respond 4 18 Mm N/A N/A Power reduction! Plant Shutdown

<50% pwr. FALSE! Al 12 fails to open automatically during 5 Prel ° aded 35 Mm N/A transfer of auxiliaries 6 45 Mi IMF RC464 RCS leakrate rises requiring Rx Trip 7 55 Mm Trigger 2 N/A ES HPI pump trips post ESAS actuation 2011-1 Scenario I Page4of 10

Appendix 0 Required Operator Actions Form ES-D-2 Op-Test No.: 201 1-1 Scenario No.: 1 Event No.: 1 Event

Description:

Drain RB sump to AB sump using 1104.014 step 8.1 and failure of CV-4400 to close.

Time_[ Position Applicants Actions or Behavior T=0 BOP Conduct pre-job brief with SRO BOP Notify RP of intent to drain RB sum p.

Open the following valves:

BOP

RB Sump to AUX Sump (CV 4446) (HS-4446)

RB Sump to AUX Sump (CV 4400) (HS-4400)

When RB sump level reaches desired level (40%), close CV 4400 by BOP placing HS-4400 in the close position.

Identify failure of CV-4400 to close and that sump level continues to lower.

BOP (Red light ON and Green Light OFF for CV-4400 and RB sump level continues to lower)

BOP Report failure of CV-4400 to the SRO.

Close CV-4446 by placing HS-4446 in the close position and verify that CV BOP 4446 indicates closed by Red Light OFF and Green light ON and Reactor Building_Sump_level has stabilized.

Identify Technical Specification applicable SRO TS (3.6.3 Condition A, due to failure of one Reactor Building penetration valve inoperable. [48 hour completion time to isolate the flow path.])

EXAMINER NOTE This event is complete when CV-4446 is closed and Tech Spec action statement is entered OR As directed by the Lead Evaluator 2011-1 Scenario I Page5of 10

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 1 Event No.: 2 Event

Description:

Small RCS leak in HPI line (C HPI Line)

Time Position Applicants Actions or Behavior Tt12 ATC Identify and report annunciator K10 B2, Process Monitor, is in alarm.

Identify the Process Monitor alarm as RC Leak Detector using the BOP plant computer.

Estimate/Quantify the RCS leakage by performing a simple mass ATC/BOP balance Estimate/Quantify the RCS leakage by performing a simple mass SRO balance Direct the BOP to OPEN the BWST Outlet valve for the operating HPI SRO pump On panel C18, OPEN the BWST Outlet valve CV1 407 for the A HPI BOP pump SRO Direct the ATC to reduce letdown flow.

ATC On panel C04, Reduced letdown flow SRO Direct the BOP to perform RT-9 to maximize RB Cooling BOP Obtain and perform RT-9 Determine that plant shutdown is required based on RCS leakage.

SRO Reference Technical Specification 3.4.1 3.A, RCS Operational LEAKAGE, TS due to unidentified leakage> 1 gpm. (18 hour2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months completion time to reduce leakage within limits)

EXAMINER NOTE This event will continue for the duration of the scenario OR As directed by the Lead Ev&uator 2011-1 Scenario 1 Page6oflo

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 1 Event No.: 3 & 4 Event

Description:

Unit Load Demand fails to respond; Power reduction! Plant Shutdown

[_Time Position Applicants Actions or Behavior Determines that the ULD is not responding. Notifies the SRO that the ULD is not responding and that the SG!RX Demand station will have to be used to ATC lower power. Places SG/RX Demand HAND/AUTO station in HAND and incrementally lowers power using the toggle switch on the SG/RX Demand.

At <75% stop Heater Drain Pumps (P8A and P8B)

(SRO may elect to keep the P8s running based upon P8 flow.)

If Heater Drain Pumps are secured then the SRO will direct:

Verify Hi Lvl Dump Isolations open:

BOP

CV-3041A (at B-3252)

CV-3037A (at B-4252)

Verify Low Level Condenser Spray CV-2907 and CV-2868 (HS 2907 on C02) open.

As time permits during the power reduction, refer to Contingency Reactivity Plans and Exhibit A (Operation of APSR Group) of Power ATC Operation (1 102.004)

(This may not occur depending on operator response time and scenario time line.)

At <50%, direct the BOP operator to transfer plant auxiliaries to SU1 SRO transformer NOTE: The next event will occur during the performance this action SRO Direct the ATC to remove one MFW pump from service.

Secure one MEW pump as follows:

a Verify Main Eeedwater Block Valves (CV-2625 and CV-2575) closed.

OPEN Eeedwater Pumps Discharge Crosstie (CV-2827)

ATC a Place desired MEW pump H/A station in HAND.

a Slowly decelerate pump to minimum speed, verifying other MFWP is maintaining flow to both loops.

a TRIP the desired MFWP Close associated Eeedpump Recirc valve.

EXAMINER NOTE This event will continue until reactor is tripped OR As directed by the Lead Evaluator 2011-1 Scenario 1 Page7oflo

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 1 Event No.: 5 Event

Description:

A112 fails to open automatically during transfer of auxiliaries Time Position Applicants Actions or Behavior T=35

(<50% BOP Obtain procedure 1107.001 for Startup Transformer Operation PWR)

BOP BOP Verify breakers to be operated are in the remote position BOP Check that SU 1 Transformer is considered operable.

BOP For breaker A-113, turn Synchronize switch on.

BOP Verify synchroscope between 1 1 and 1 oclock.

Close A-113 AND allow control switch to return to BOP NORMAL-AFTER-CLOSE position.

BOP Turn Synchronize switch off.

BOP Verify breaker A-112 opens.

BOP Identify that breaker A-i 12 does not open automatically Trip breaker A-112 using the handswitch on ClO before the feeder breakers BOP trip due to timed overcurrent.

BOP Notify the SRO that breaker A-i 12 failed to open automatically Continue the transfer of electrical buses from Unit Aux. Transformer to BOP SU#1 Transformer EXAMINER NOTE This event is complete when Al, A2, Hi, and H2 buses have been transferred OR As directed by the Lead Evaluator 2011-i Scenario 1 Page 8 of 10

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 1 Event No.: 6 Event

Description:

RCS leakrate rises requiring Rx Trip Time Position Applicants Actions or Behavior ATC Identify and report the RCS leak rate has gotten worse ATC Determine that HPI is needed to maintain RCS inventory SRO Direct the crew to trip the Reactor and carryout immediate actions.

ATC Trip the reactor using the Manual Rx. Trip pushbutton on C03 SRO Obtain the Reactor Trip EOP and provide direction to the crew.

ANY Report that subcooling margin is inadequate SRO Transition to the Loss of Subcooling Margin EOP Check elapsed time since loss of adequate SCM AND perform the following:

BOP a IF 2 minutes have elapsed, THEN trip all RCPs.

CT

Initiate full HPI (RT 3).

(criteria RCPs must be tripped within 2 minutes of losing Subcooling Margin to prevent core uncovery if RcPs are lost.>

If ESAS actuation occurs prior to initiation of full HPI, Verify actuation per BOP RT-1 0 ATC Verify proper EFW actuation and control per RT 5.

EXAMINER NOTE This event will continue until termination OR As directed by the Lead Evaluator

[

2011-1 Scenario 1 Page9of 10

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 201 1-1 Scenario No.: 1 Event No.: 7 Event

Description:

ES HPI pump trips post ESAS actuation Time Position I Applicants Actions or Behavior T=55 ANY Identify and report that the ES actuated HPI Pump has tripped.

BOP Verify running HPI pump is still providing HPI flow to the RCS Identify and report that HPI flow through the C HPI line is >20 gpm BOP higher than the remaining flows SRO Direct HPI flow be throttled in accordance with RT-10 After verification that RCS pressure is >600 psig, throttle the C HPI flow to within 20 gpm of the next highest flow by taking the HPI control valve BOP to MANUAL and closing CV-1219 (modulating) to within 20 gpm of the CT next highest flow.

(criteria With on HPI pump running and RCS pressure> 600 psig, the highest HPI flow must be throttled to within 20 gpm of the next highest flow to ensure adequate HPI flow to the core. This is done as part of RT-1 0, therefore this will be done prior to declaring RT-1 0 complete for successful completion of this task.)

Reference Technical Specification 3.5.2.A, ECCS Operating, due to loss SRO of one train of ECCS. (72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months completion time to restore ECCS train to TS operable status)

TERMINATION CUE When HPI has been throttled on the C HPI line and RCS pressure is stable OR As directed by the Lead Evaluator End of Scenario 1 2011-1 Scenario 1 Page 10 of 10

Appendix D Scenario Outline Form ES-D-1 Facility: ANO-1 Scenario No.: 2 Op-Test No.: 2011-1 Examiners: Operators:

Initial Conditions:

. 40% Power

. 250 EFPD

. Both MEW Pumps in service

. Ready to commence power escalation

. P7B EFW pump fails to auto-start and cannot be manually started from handswitch

. RPS Reactor Trips Failed Turnover:

40% Power

250 EEPD

. Both MEW Pumps in service

Need to Place P-36B in service and secure P-36A due to small oil leak on P-36A that is scheduled for repair

. Ready to commence power escalation Event Event Event Maif. No. Type* Description No.

N-(BOP) Swap running makeup pumps. Place P36B in service and 1 N/A N-(SRO) place P36A in standby.

2 N/A R-(ATC) Power escalation 3 CV6604 Gland Seal Regulator Failure 4 TR572 SG Startup Range level instrument fails downscale slowly C-(BOP) P-4C SW pump trips 5 co P4C C-(SRO)Ts (Technical Specification 3.7.7.A, One SWS loop inoperable.)

MEW pump trip w/ failure of discharge cross-tie valve to TRPAMFW M-ALL 6 open requires reactor trip. RPS is failed and will not cause CV2827 CT a trip.

Remaining main feedwater pump trips resulting in EFW TRPBMFW C-(ATC) actuation. Electric EFW pump fails to autostart and will 7 P7B C-(SRO)Ts not start from the handswitch.

FW617 (Technical_Specification_3.7.5.B,_One_EFW_train_inoperable)

EFW steam driven pump trips on overspeed resulting in M-(ALL) TS overheating condition. EFW pump P7A reset and EFW 8 CV6601 CT flow restored.

(Technical Specification 3,7.5,D, Two EFW trains inoperable)

(N)orma), (R)eactivity, (l)nstrument, (C)omponent, (M)ajor 2011-1 Scenario 2 Page 1 of 16

Appendix D Scenario Outline Form ES-D-1 Scenario 2- Objectives

1) Evaluate individual ability to perform placing the standby makeup pump in service and securing the operating makeup pump.

2) Evaluate individual ability to perform a plant power escalation.

3) Evaluate individual ability to recognize and respond to a failure of the Gland Seal Regulator.

4) Evaluate individual ability to recognize and respond to CS input failure.

5) Evaluate individual ability to recognize and respond to Service Water Pump trip.

6) Evaluate individual ability to recognize and respond a loss of Steam Generator Feed.

7) Evaluate individual ability to identify and respond to conditions requiring reactor trip based on Loss of Steam Generator Feed

8) Evaluate individual ability to perform reactor trip immediate actions

9) Evaluate individual ability to perform verification of EFW actuation

10) Evaluate individual ability to identify and respond to EFW pump Trip/Autostart Failure 1 1) Evaluate individual ability to identify and respond to an overheating condition due to a loss of all feedwater.

12) Evaluate individual ability to perform recovery and restoration of Emergency Feedwater 201 1-1 Scenario 2 Page 2 of 16

Appendix D Scenario Outline Form ES-D-1 SCENARIO 2- NARRATIVE The crew will assume plant responsibility at 40% power. The SRO will direct swap of the operating makeup pump by placing P-36B in service and securing P-36A.

After the makeup pump swap is complete the SRO will direct power escalation using normal operations procedure 1102.004 Power Operations.

When the power escalation has commenced, the main gland seal regulator will fail resulting in loss of steam to the main turbine gland seals. This will require the BOP to respond using ACA 1203.012D for K05. This will result in a lowering condenser vacuum. The BOP will be required to throttle open the regulator bypass valve, CV-6606 to restore gland seal pressure.

During power escalation the A Steam Generator Startup Level (NNI-X) instrument will fail resulting in a false input signal to the ICS system. The SRO will direct required action using 1203.001 ICS Abnormal Operations AOP. The ATC will be required to place designated stations into HAND and stabilize the plant until a valid signal can be selected and ICS placed back into AUTO.

Once lOS is placed back into AUTO, the C service water (SW) pump will trip. The SRO will direct actions using 1203.01 21 K10 ACA. The BOP should verify the B SW pump aligned to the appropriate bus and then start the B SW pump to restore proper SW flows and pressures.

The SRO should reference Technical Specification 3.7.7.A, One SWS loop inoperable.

After SW has been restored, the A Main Feedwater (MFW) pump will trip resulting in a plant runback to 40% power. The MFW pump discharge cross tie valve will fail to open resulting in total loss of feed to the A steam generator. The crew should recognize the loss of feed and the SRO should direct tripping the unit. RPS is failed and will not cause a reactor trip. The SRO will enter 1202.001, Reactor Trip EOP and the crew will perform reactor trip immediate actions.

Upon the reactor trip, the remaining feedwater pump (B) will trip resulting in a total loss of main feedwater. EFW should automatically initiate on loss of both MFW pumps. P-7B, electric driven EFW pump will fail to start and will not start manually. The crew should address P-7B failure using ACA 1203.012K. The ATC will verify EFW actuation using RT-5 of 1202.012. The SRO should reference Technical Specification 3.7.5.B, for one EFW train inoperable.

Shortly after starting, P-7A EFW pump will overspeed trip. The crew should recognize overheating entry conditions and the SRO should direct operations using 1202.004 Overheating EOP. The crew should dispatch the waste control operator (WCO) to investigate the status of P 7A. The WOO will report that the trip/throttle valve for P-7A is tripped but there are no obvious problems with P-7A. The crew should direct the WOO to reset P-7A using 1106.006 Exhibit A.

The SRO should reference Technical Specification 3.7.5.D, for two EFW trains inoperable.

When the WOO reports P-7A reset, the crew should restore EFW to both steam generators using RT-16 of 1202.012.

2011-1 Scenario 2 Page3of 16

Appendix D Scenario Outline Form ES-D-1 Simulator Instructions for Scenario #

Recall IC 126 Load batch file R02011_2.txt and use triggers to activate malfunctions.

AFeedwater Pump x-tie valve failed closed IMF CV2827 0 AP7B EFW Pump fails and wont start IRF C0_P7B OFF IMF FW617 ARPS will not trip IMF RP246 IMF RP247 IMF RP248 IMF RP249 AP7A will trip on overspeed (Trigger 6)

IMF CV6601 (6 0)1 AFail GS Regulator low (Trigger 1)

IMF CV6604 (1 0)0.08 10 AFail A SG SU range level inst (X) low (Trigger 2)

IMF TR572 (2 0) 0 30 ATrip the C SW pump (Trigger 3)

IRF C0_P4C (3 0) OFF ATrip the A MFW Pump (Trigger 4)

IRF TRPAMFW (4 0) TRIP ATrip the B MFW Pump when the reactor trips Trigger 5)

IRF TRPBMFW (5 0) TRIP TRGSET 4 q3201 Oad AReset P-7A Trip/Throttle Valve (Trigger 7)

IRF RESP7A (7 0) RESET Event Time Malt, No.

Value/ F Event Description No. Ramp Time Swap running makeup pumps. Place P36B in 1 0 N/A N/A service and place P36A in standby.

2 15 Mm. N/A N/A Power Escalation 3 25 Mm. Trigger 1 0.08/10 sec Gland Seal Regulator Failure SG Startup Range level instrument fails 4 30 Mm. Trigger 2 0/30 sec downscale slowly 5 50 Mm. Trigger 3 OFF! N/A P-4C SW Pump trips MFW pump trip w/failure of discharge cross-Trigger 4 tie valve to open requires reactor trip/RPS 6 60 Mm. TRIP/ N/A Preloaded fails.

Remaining main feedwater pump trips Trigger 5 resulting in EFW actuation. Electric EFW 7 60 Mm. TRIP! N/A Preloaded pump fails to autostart and will not start from the handswitch.

EFW steam driven pump trips on overspeed 8 65 Mi Trigger 6 RESET! N/A resulting in overheating condition. EFW pump P7A rest and EFW flow restored.

2011-1 Scenario 2 Page 4 of 16

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 2 Event No.: 1 Event

Description:

Swap running makeup pumps. Place P36B in service and place P36A in standby.

Time Position Applicants Actions or Behavior Direct the BOP to shift running makeup pumps to P-36B running and T=O SRO P-36A Standby Pump. (P-36C remains ES Pump)

Obtain procedure 1104.002 and refer to section 9.0 for Makeup Pump BOP Operation.

BOP Contact field operator to check P-36B shaft stopped.

NOTE: Check valve testing will not be required for this evolution BOP Verify P-36B Bus MOD (A-8) selected to bus A-3.

Verify P-64B Transfer Switch is selected to B57 by performing the following:

Observe indicating lights under P-645 handswitches.

BOP

Contact field operator to locally verify red power supply selected as indicated by the three-spoked manual operating lever on the left side of P-64B disconnect (B-801).

BOP Start Aux Lube Oil Pump (P-64B) for P-36B.

BOP WHEN P-64B has run for one minute, THEN start P-36B.

BOP Stop P-64B.

Event 1 Continued on Next Page 2011-1 Scenario 2 Page5of 16

Appendix 0 Required Operator Actions Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 2 Event No.: 1 Event

Description:

Swap running makeup pumps. Place P36B in service and place P36A in standby Time Position I Applicants Actions or Behavior BOP Start Aux Lube Oil Pump (P-64A) for P-36A.

BOP Stop P-36A.

BOP Contact the field operator to check P-36A shaft has stopped.

BOP WHEN P-64A has run for at least one minute, THEN stop P-64A.

Change pump status tags as follows:

BOP

OP Pump tag above P-36B handswitch (C18).

STBY Pump tag above P-36A handswitch.

EXAMINER NOTE This event is complete when P-36B is running and P-36A is stopped OR As directed by the Lead Evaluator 2011-1 Scenario 2 Page 6 of 16

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 2 Event No.: 2 Event

Description:

Power escalation Time J_Position Applicants Actions or Behavior T=1 5 SRO Direct the crew to begin power escalation at 30%/Hr.

ATC Verify or set the ICS rate of change module for 0.5%/min.(30%/hr) or less Begin power escalation by raising the Unit Load Demand to desired ATC value Verify plant response (control rods, Rx. Power, feedwater demand and ATC flow)

BOP Verify turbine load changes and maintains proper steam header pressure EXAMINER NOTE: Output memory lights in B, C & D RPS channels are not modeled.

EXAMINER CUE Notify the Examinee performing the RPS manipulations to assume the Output Memory Lamps have been reset for B, C & D channels and that the lamps are dim.

BOP Verify RPS bistable reset for Turbine Trip <43%

EXAMINER NOTE This event is complete when the next event occurs OR As directed by the Lead Evaluator 2011-1 Scenario 2 Page 7 of 16

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-1 Scenario No: 2 Event No.:3 Event

Description:

Gland Seal Regulator Failure Time Position Applicants Actions or Behavior Identify and announce Gland Seal Pressure #3, 4, 5, 6 Brng Lo alarms r=25 ANY on K05-B4, C4, D4, E4.

Obtain Annunciator Corrective Action 1203.012D for K05 and refer to any of BOP the GS Pressure Lo corrective actions.

ANY Report condenser vacuum lowering Refer to Loss of Vacuum AOP, 1203.016 NOTE: Prompt action by the crew may resolve the vacuum issue using the SRO Annunciator Corrective Action, and therefore the SRO may not refer to this procedure.

Open Gland Sealing Steam Main Regulator Bypass (CV-6606) located on BOP panel C12 until alarms clear.

Monitor Gland Seal header pressure on panel 012 and make adjustments to BOP the regulator bypass as necessary to control pressure at desired value.

EXAMINER NOTE This event is complete when GS pressure is restored and condenser vacuum is recovering OR As directed by the Lead Evaluator 2011-1 Scenario 2 Page 8of 16

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 1 Event No.: 4 Event

Description:

SG Startup Range level instrument fails downscale slowly Time Position Applicants Actions or Behavior T=30 ATC Identify and report annunciator K07 B4, SASS Mismatch, in alarm, ATCIBOP Identify the A SG Startup Level indication causing SASS M/M alarm Refer to 1203.012F, Annunciator Corrective Action for K07, or SRO 1203.001, ICS Abnormal Operations.

Direct the ATC to place the H/A station for the A MEW pump in SRO HAND ATC Place the A MEW pump H/A station in HAND Direct the ATC to place the startup and low load valve H/A stations for SRO the A SG in HAND Place the H/A stations for the A SG startup and low load valves in ATC HAND Identify Technical Specification applicable SRO TS (3.7,3 Condition C and D due to One Low Load and One Startup Feedwater Control valve inoperable [72 hour completion time to close or isolate valves or restore operability.])

If desired, direct the ATC to place the EW Loop Demand H/A stations to SRO HAN D ATC If directed, place the EW Loop Demand H/A stations to HAND Event 4 Continued on Next Page 2011-1 Scenario 2 Page 9 of 16

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 2 Event No.: 4 Event

Description:

SG Startup Range level instrument fails downscale slowly Time Position I Applicants Actions or Behavior Direct the ATC to select the good (Y) A SG Startup Level instrument for SRO indication.

On panel C03, select the good (Y) instrument for A SG Startup Level ATC indication.

Verify the selected instrument indicates the proper startup level and the A ATC OTSG Level LO alarm clears.

Direct the ATC and BOP to place ICS in AUTO per 1105.004, ICS SRO Operations.

EXAMINER NOTE This event is complete when the good SG Startup Level instrument (Y) has been selected and plant is stabilized OR As directed by the Lead Evaluator 2011-1 Scenario 2 Page 10 of 16

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 2 Event No.: 5 Event

Description:

P-4C SW pump trips Time Position Applicants Actions or Behavior T=50 ANY Identify and announce Service water pump trip alarm on K10.

Dispatch the field operator to investigate the tripped pump and check ANY strainer DIP status

, Refer to 1203.0121, Annunciator Corrective Action for K10-A3, SRO B

1 OP SERVICE WATER PUMP TRIP.

BOP Verify service water bay levels >332 feet using SPDS or PDS.

SRO Direct the BOP to start the standby SW pump (P-4B)

Verify P-4B Bus Select MOD Control switch on panel C18 is selected to BOP Bus A4.

BOP Verify P-4B MOD closed on bus A4.

BOP Verify P-4B to P-4C Crossties (CV-3640 and CV-3642) are open.

BOP Start standby pump P-4B from panel C16, Identify Technical Specification applicable SRO (3.7.7 Condition A, due to one SWS loop inoperable. [72 hour completion time to restore TS SWS loop to operable statusj)

Technical Specification action can be exited after P-4B SW pump is started.

Place the P-4C handswitch in normal-after-stop or PULL_TOLOCK BOP position to clear the alarm Event 5 Continued on Next Page 2011-1 Scenario 2 Page 11 of 16

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 2 Event No.: 5 Event

Description:

P-4C SW pump trips Time I Position Applicants Actions or Behavior Refer to Service Water Operation procedure, 1 104.029, for the current pump SRO configuration alignment.

SRO Direct the BOP to swap B55/B56 power to bus B6.

Swap B55/B56 to bus B6 using ES Electrical System Operation, BOP 1107.002.

Identify that Technical Specification 3.7.7 can be exited after P-4B Service SRO Water Pump is started EXAMINER NOTE This event is complete when P-4B is started and alarm is cleared OR As directed by the Lead Evaluator 2011-1 Scenario 2 Page 12 of 16

Appendix 0 Required Operator Actions Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 2 Event No.:6 & 7 Event

Description:

MEW pump trip w/ failure of discharge cross-tie valve to open requires reactor trip. RPS is failed. Remaining main feedwater pump trips resulting in EFW actuation.

Electric EFW pump fails to autostart and will not start from the handswitch.

Time j Position Applicants Actions or Behavior Identify and announce A Main feedwater pump turbine trip alarm on 1=60 ANY K07-A7 SRO Refer to Loss of Steam Generator Eeed (1203.027).

Verify the Feedwater Pumps Discharge Crosstie valve (CV-2827) is ATC opening on panel C03 Attempt to open the Eeedwater Pumps Discharge Crosstie valve (CV ATC 2827) by momentarily placing hand switch (HS-2827) on C03 in the OPEN position Report the Feedwater Pumps Discharge Crosstie valve (CV-2827) on ANY panel 003 failed to open SRO Direct the ATC to Trip the Reactor and carryout immediate actions.

Trip the reactor by depressing the Rx. Trip PB on C03 prior to the RPS trip setpoint being reached.

(Criteria Due to RPS being failed, the reactor will not trip automatically. Loss of ATC

... I feedwater flow to the B SG, RCS pressure will begin to rapidly rise. The reactor should be tripped at an RCS pressure of 2355 psig to complete this task successfully.)

Refer to the Reactor Trip EOP, 1202.001, and provide direction to the SRO crew.

SRO Verify the immediate actions for the Rx. Trip have been performed.

ANY Identify and report the remaining main feedwater pump has tripped SRO Direct the ATC to actuate EFW.

Manually actuate EFW at C09 using EFIC Train A and B matrices, both ATC Bus 1 and 2 Event 6 & 7 Continued on Next Page 2011-1 Scenario 2 Page 13 of 16

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 201 1-1 Scenario No.: 2 Event No. :6 & 7 Event

Description:

MFW pump trip wI failure of discharge cross-tie valve to open requires reactor trip. RPS is failed. Remaining main feedwater pump trips resulting in EFW actuation.

Electric EFW pump fails to autostart and will not start from the handswitch.

Time Position_[ Applicants Actions or Behavior ATC Verify proper EFW actuation using RT-5 Identify and report that the electric driven EFW pump, P-7B, failed to ATC Autostart Verify EFW Pump, P-7A, running and the associated EFW flow control ATC valves are opening.

Verify both EFW pushbuttons on both Train A Matrix AND Train B, ATC Matrix depressed Identify Technical Specification applicable SRO (3.7.5 Condition B, One EFW train inoperable AND Operability section of Emergency TS Feedwater Initiation and Control [1105.005] for EFW Pump [P-7A, P-7B] Operability Requirements. [72 hour completion time to restore EFW train to operable status])

Dispatch field operator to P-7B electrical cabinet, A-31 1, and check for ANY tripped protection relays.

NOTE: Booth operator call as field operator and report No protective relays tripped on breaker A-311 ATC Attempt to start P-7B from C09 using the handswitch EXAMINER NOTE This event will continue for the duration of the scenario 2011-1 Scenario2 Page 14 of 16

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 2 Event No.:8 Event

Description:

EFW steam driven pump trips on overspeed resulting in overheating condition. EFW pump P7A reset and EFW flow restored.

Time I Position Applicants Actions or Behavior T=65 ANY Identify and announce that P-7A, steam driven EFW pump, has tripped.

SRO Transition to Overheating EOP Dispatch field operator to reset P-7A overspeed trip using Emergency SRO Feedwater Pump Operation (1106.006), Exhibit A.

BOP Reduce running RCPs to one per loop Close Main Feedwater Isolation valves to prevent feeding with Condensate ATC/BOP pump as SG boils dry (CV-2630 and 2680).

ATC/BOP Place EFW CNTRL valves in HAND AND close ATC/BOP Verify EFW Pump P7B in PULL-TO-LOCK Place EFW Pump Turbine K3 Steam Admission Valves (CV-2613 and ATC/BOP CV-2663) in MANUAL AND close.

NOTE: Booth operator call as WCO and report that the steam driven EFW pump, P-7A has been reset and is ready for start.

SRO Direct the ATC or BOP to perform RT-16 to refill dry steam generators.

Open either EFW Pump Turbine K3 Steam Admission valve ATC/BOP (CV-2613 or CV-2663).

Place affected SG(s) EFW CNTRL valves in VECTOR OVERRIDE ATC/BOP (CV-2645 and CV-2647)

Event 8 Continued on Next Page 2011-1 Scenario 2 Page 15 of 16

Appendix D Required Operator Actions Form ES-D-2 Op-Test No.: 2011-1 Scenario No.: 2 Event No.: 8 Event

Description:

EFW steam driven pump trips on overspeed resulting in overheating condition. EFW pump P7A reset and EFW flow restored.

Time Position I Applicants Actions or Behavior Place affected SG(s) EFW ISOL valves in MANUAL AND verify open ATC/BOP (modulating valves) (CV-2627 and CV-2620)

Adjust affected SG(s) EFW CNTRL valve(s) in HAND as necessary to ATC/BOP maintain flow to each SG 450 gpm.

(Criteria Due to the steam generators being dry, manual control of the EFW control CT valves is necessary to prevent EFW from feeding at full flow. EFW must be manually throttled to a value of 45Ogpm to prevent overcooling the reactor coolant system.)

Operate Turbine Bypass Valves as necessary to stabilize RCS temperature ATC or establish desired cooldown rate as directed by SRO.

Identify Technical Specification applicable SRO (3.7.5 Condition D, Two EFW trains inoperable due EFW isolation valves placed in 1S MANUAL [Immediate completion time to initiate action to restore EFW train to operable status,])

TERMINATION CUE This scenario is complete when EFW is re-established to the SGs and primary to secondary heat transfer in progress OR As directed by the Lead Evaluator 2011-1 Scenario 2 Page 16 of 16

ML11284A126

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