Text

Initial Exam 2012-301 Final Administrative JPMs
	ML12214A480
Person / Time
Site:	Farley
Issue date:	07/23/2012
From:	; NRC/RGN-II
To:	; Southern Nuclear Operating Co
Shared Package
ML12214A278	List: ML12214A258; ML12214A297; ML12214A317; ML12214A335; ML12214A347; ML12214A358; ML12214A458; ML12214A461; ML12214A470; ML12214A480; ML12214A487;
References
	Download: ML12214A480 (85)
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FNP ILT-35 ADMIN Page 1 of 7 A.l.a Admin a RO/SRO Conduct of Operations TITLE: Determine maximum RHR flowrate and time to saturation for a loss of RHR event.

EVALUATION LOCATION: SIMULATOR CONTROL ROOM X CLASSROOM PROJECTED TIME: 20 MIN SIMULATOR IC NUMBER: N/A ALTERNATE PATH TIME CRITICAL PRA____

JPM DIRECTIONS:

1. Initiation of task may be in group setting, evaluation performed individually upon completion.

2. Requiring the examinee to acquire the required materials may or may not be included as part of the JPM.

TASK STANDARD: Upon successful completion of this JPM, the examinee will:

Correctly assess and determine the maximum RHR flowrate for the current RCS level.

Correctly assess and determine the time to core boiling for the current core conditions.

Examinee:

Overall JPM Performance: Satisfactory 11 Unsatisfactory D Evaluator Comments (attach additional sheets if necessary)

EXAMINER:

Developer BR Thornton Date: 2/10/12 NRC Approval SEE NUREG 1021 FORM ES-301-3

FNP ILT-35 ADMIN A.1 .a ROISRO Page 2 of 7 CONDITIONS When I tell you to begin, you are to DETERMINE MAXIMUM RHR FLOWRATE AND TIME TO SATURATION FOR A LOSS OF RHR EVENT. The conditions under which this task is to be performed are:

a. The Unit 1 Reactor has been shutdown for 350 hours0.00405 days 0.0972 hours 5.787037e-4 weeks 1.33175e-4 months .

b. Refueling is complete, with 53 new fuel assemblies loaded into the core.

c. An RCS leak had occurred, but it has now been isolated.

d. 1A RHR pump is the only RHR pump running.

e. The 1A RHR pump started cavitating and RHR flow has been lowered to 1300 gpm to stop the cavitation per FNP-1-AOP-12.0, Residual Heat Removal Malfunction.

f. Current RCS level is 122 8.5 and stable.

g. Current RCS temperature is 116°F.

h. A current Shutdown Safety Assessment is not available.

Your task is to perform the following per AOP-12.0:

1) Determine the maximum allowable RHR flowrate.

2) Determine the time to core saturation for a loss of RHR.

INITIATING CUE: IF you have no questions, you may begin.

EVALUATION CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

START TIME

1. Evaluate Figure 1, RCS HOT LEG LEVEL vs 1) Step 7 of AOP-12.0, Maintain S I U RHR INTAKE FLOW To Minimize Vortexing to RCS level to within the determine maximum allowable RHR flowrate. Acceptable Operating Region of Figure 1, RCS HOT LEG LEVEL vs RHR INTAKE FLOW To Minimize Vortexing for the existing RHR flow.

RCS level is 122 8.5.

Determines that maximum RHR flow is < 1800 gpm.

Allowable tolerance: 1600 -

1800 gpm.

FNP ILT-35 ADMIN A.1.a ROISRO Page 3 of 7 EVALUATION CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

2. Determine time to core saturation, determine 2) ATTACHMENT 3, step 1.1. S/U appropriate table of ATTACHMENT 3, TABLE A or TABLE B. Determines that Attachment 3, TABLE B is required per ATTACHMENT 3, step 1.1.2, Time to saturation with one third of the spent fuel replaced with new fuel.

3. Determine time to core saturation, determine 3) ATTACHMENT 3, step 1.3. S/U appropriate table of ATTACHMENT 3 based on initial RCS temperature Determines that page from Table for 100°F Attachment 3, TABLE B for Table for 120°F ASSUMED INITIAL Table for 140°F TEMPERATURE = 120°F is required.

A candidate may interpolate between the Table for 100°F and the Table for 120°F. This is acceptable since the given condition for RCS temperature is 116°F. Using the Table for 120°F is acceptable and is a conservative action.

4. Determine time to core saturation, determine 4) ATTACHMENT 3, step 1.2. S/U appropriate column of ATTACHMENT 3, TABLE B ASSUMED INITIAL

, Determines that page from TEMPERATURE = 120°F: Attachment 3, TABLE B for ASSUMED INITIAL Time to Saturation at midloop (mins) TEMPERATURE = 120°F (a ,

Time to Saturation 3 below flange (mins) candidate may interpolate Time to Saturation full Rx cavity (hours) between the Table for 100°F and the Table for 120°F, see note at JPM step 3) column for Time to Saturation at midloop (mins) is required.

FNP ILT-35 ADMIN A.1 .a ROISRO Page 4 of 7 EVALUATION CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

5. Determine time to core saturation. 5) Using Table B, 120°F only, S / U determines that Time After Shutdown (hours) is 350 hours0.00405 days 0.0972 hours 5.787037e-4 weeks 1.33175e-4 months and minutes to boiling is calculated to be 21.35 minutes.

300 hours0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months = 20.2 minutes 400 hours0.00463 days 0.111 hours 6.613757e-4 weeks 1.522e-4 months = 22.5 minutes 20.2+22.5=42.7 42.7/2 = 21.35 minutes Since the Time After Shutdown chart only shows 300 hours0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months and 400 hours0.00463 days 0.111 hours 6.613757e-4 weeks 1.522e-4 months , the candidate may conservatively take the Table B, 120°F, 300 hours0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months after shutdown for time to boil of 20.2 minutes.

In addition, a candidate may interpolate between the Table for 100°F and the Table for 120°F.

(See next page)

FNP ILT-35 ADMIN A.1 .a ROISRO Page 5 of 7 EVALUATION CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

Table for 1000 initial temperature:

300 hours0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months = 24.7 minutes 400 hours0.00463 days 0.111 hours 6.613757e-4 weeks 1.522e-4 months = 27.5 minutes 24.7 + 27.5 = 52.2 52.2/2 = 26.1 minutes AND Table for 120° initial temperature:

300 hours0.00347 days 0.0833 hours 4.960317e-4 weeks 1.1415e-4 months = 20.2 minutes 400 hours0.00463 days 0.111 hours 6.613757e-4 weeks 1.522e-4 months = 22.5 minutes 20.2 + 22.5 = 42.7 42.7/2 = 21.35 minutes AND Interpolating for 116°F initial temperature:

26.1 21.35 =4.75 minutes (difference) 16/20 X 4.75 = 3.8 minutes (proportion of the difference to be subtracted from the time allowed per the 100°F Table) 26.1 3.8 = 22.3 minutes Allowable tolerance: 20.2 -22.3 minutes.

20.2 minutes for most conservative use of the Tables.

22.3 minutes if calculated by interpolation.

STOP TIME Terminate when all elements of the task have been completed.

CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk (*) before the element number.

FNP ILT-35 ADMIN A.1.a ROISRO Page 6 of 7 GENERAL

REFERENCES:

1. FNP-1-AOP-12.0, v24 2.KA:G2.1.25 RO (3.9) SRO (4.2)

GENERAL TOOLS AND EQUIPMENT:

1. Acquire FNP-1-AOP-12.0, v24

2. Provide FNP-1-AOP-12.0, v24 Figure 1 when!if asked

3. Calculator Critical ELEMENT justification:

STEP Evaluation

1. Critical: Task completion: required to properly determine Maximum RHR flowrate.

2-5 Critical: Task completion: required to properly determine time to core saturation.

COMMENTS:

KEY AOP-12 RCS level is 122 8.5. Determines that Maximum allowable RHR flowrate maximum RHR flow is < 1800 gpm.

Allowable range: 1600 -1800 gpm If the candidate chooses the most conservative use of the tables, 20.2 minutes is acceptable.

If interpolation is performed between the Time to Core Saturation two tables for RCS temp of 116°F, 22.3 minutes is acceptable.

Allowable tolerance: 20.2 -22.3 minutes.

A.ta ROISRO HANDOUT Pg 1 of 1 CONDITIONS When I tell you to begin, you are to DETERMINE MAXIMUM RHR FLOWRATE AND TIME TO SATURATION FOR A LOSS OF RHR EVENT. The conditions under which this task is to be performed are:

a. The Unit 1 Reactor has been shutdown for 350 hours0.00405 days 0.0972 hours 5.787037e-4 weeks 1.33175e-4 months .

b. Refueling is complete, with 53 new fuel assemblies loaded into the core.

c. An RCS leak had occurred, but it has now been isolated.

d. 1A RHR pump is the only RHR pump running.

e. The 1A RHR pump started cavitating and RHR flow has been lowered to 1300 gpm to stop the cavitation per FNP- 1 -AOP- 12.0, Residual Heat Removal Malfunction.

f. Current RCS level is 122 8.5 and stable.

g. Current RCS temperature is 116°F.

h. A current Shutdown Safety Assessment is not available.

Your task is to perform the following per AOP-12.0:

1) Determine the maximum allowable RHR flowrate.

2) Determine the time to core saturation for a loss of RHR.

AOP-12 Maximum allowable RHR flowrate Time to Core Saturation

FNP iLT-35ADMN Page 1 of 8 Ad.b RO Conduct of Operations G2L5 TITLE: IDENTIFY THE ON-SHIFT MANNING REQUIREMENTS FOR THE CONDITIONS PROVIDED.

EVALUATION LOCATION: LI SIMULATOR LI CONTROL ROOM CLASSROOM PROJECTED TIME: 20 MN SIMULATOR IC NUMBER: N/A LI ALTERNATE PATH LI TIME CRITICAL LI PRA JPM DIRECTIONS:

1. Initiation of task may be in group setting, evaluation performed individually upon completion.

2. Requiring the examinee to acquire the required materials may or may not be included as part of the 1PM.

TASK STANDARD: Upon successful completion of this JPM, the examinee will:

Correctly determine if an oncoming Operations crew satisfies the minimum Operations shift staffing requirements of EIP-0.0

Correctly state the minimum required Reactor Operators per FNP-0-SOP-0.0 (TS 5.2.2(a))

Correctly identify the required actions if minimum shift staffing requirements are not satisfied per EIP-0.0 step 4.8.2 AND/OR TS 5.2.2.C.

Exa mince:

Overall JPM Performance: Satisfactory Unsatisfactory D Evaluator Comments (attach additional sheets if necessary)

EXAMINER:

Developer Howard Fitzwater Date: 2/10/20 12 NRC Approval SEE NUREG 1021 FORM ES-301-3

FNP LT-35 ADMN Al b RO Page 2 of 8 CONDITIONS When I tell you to begin, you are to IDENTIFY THE ON-SHIFT MANNING REQUIREMENTS FOR THE CONDITIONS PROVIDED. The conditions under which this task is to be performed are:

a. Both Units are at 100% power.

b. It is Night shift on a holiday, and the Operations Manager has authorized maximizing time off.

c. The table below represents the Operations shift complement that has arrived to receive turnover and their license level/status.

NAME LICENSE status/gual ACTIVE Adam Dual Unit- SRO SM ACTIVE Bob Dual Unit- SRO Charlie Doug ACTIVE Eugene Dual Unit Frank RO INACTIVE Gary Dual Unit- SRO SSS-STA INACTIVE Harry Dual Unit- SRO SS S-Fire Jack Kelly Lisa Not licensed Mike SO Nick Fire Brigade Oscar Pam Not licensed Not Fire Brigade qualified R ogei Fire Protection Administrator Qualified_Shift_Communicator Your task is to PROVIDE a written response to the following:

o IDENTIFY whether or not the operations crew shown in the table above satisfies all of the requirements to take the shift without any additional action or personnel.

o STATE the minimum number of on-shift Reactor Operators required.

o Identify the required actions anytime the requirements for minimum on-shift staffing are NOT met.

fNITIATllTG CUE: You may begin.

FNP (LT-35 ADMIN Ai .b RO Page 3 of 8 EVALUATION CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

START TIME:

1. REVIEW shift Staffing levels per SOP-O.O & *IDENTIFY the MINIMUM S / U EIP-O.O. shill staffing is satisfied by circling YES 12 Ill 1F9 Of TABLE I SMSHWTSTA4FE4G REQUEMENTS on the Emeonerioy Plan table 3 and FNP-*-EJP12.O Position Person Filling Pmition Function Opbostti

Shift Manager I EnercenayDrecon and Ccneol (EniergeonyDirertor)

Flair Operations and Ac snseni of OpeionaiAapecls. Shill SRC)

Unit I Shift I Plant Ogerationo and Asscrsrnena of SOr OperetionslAspects. SS (LAO)

Unit 2 Shift T Nottilcabon! Coninanaicahea The Sunerresor 55 of the ieatt affected unit seJi ethe:aeoftheENhEM conmzuaacator 555. STA 1 Shift Technical Adsssor Coa&Thcmsai Ouaiided Hydraulica. Electrical. Mechanical SSS.Fise 1 FireBrinsdepertheFSAR(Fixe Brigade Brigade Chief) thed OATC Unit I I Plant Operations and Atsossnstnt of OATC Unit 2 1 Plant Operations and ? ser5niettt of Unit Qperatnt I Plant Operations astd Assessment of Unit 112 OtionalAspecis Shift Leant affertedunit UOwill assume Coinnaunicalor the role of the Shill Cssasmumcatot System 3 Plant Operations astd Asseoiment of Operator SOal_________________ Oenalinoai Aspects Operations SOlO_________________

SO ti3 Systems 4 Fire Brigade per the PSAR (Fire Operatoas SO M________________ Brigade nienibecs)

Fire brinade SO5______________

SO Ill______________

SOlO________________

Pace I ofT This TABLE is provided to allow the examiner to follow along during the applicants explanation during the debrief session.

FNP ILT-35 ADMN A.1.b RD Page 4 of 8 EVALUATION CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

2. REVIEW shift Staffing levels per SOP-O.O. *IDENTIFY the MINIMUM S / U number of Reactor Operators necessary to satisfy TS by writing: THREE (3)

3. REVIEW required actions for falling below

IDENTIFY that the required S / U minimum shift Staffing levels per EIPO.O AND action is to:

OR TS 5.2.2.c.

IMMEDIATELY INITIATE action to fill the vacant position within two HOURS.

OR LISTS the TS requirement 5.2.2.(c)

AND/OR the procedural step EIP-O.O paragraph 4.8.2.

FNP ILT-35 ADMIN Ai .b RO Page 5 of 8 EVALUATION CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

ANSWER KEY:

1. Does the crew shown in the table satisfy all of the MINIMUM shift staffing requirements?

NO

2. The minimum required number of Plant/Reactor Operators required on-shift is:

ONE OATC FOR EACH UNIT ANT) ONE UO SHARED BETWEEN THF. UNITS for a 1.otai of THREE(3V it is EQU4LLY accptah!e simply state: THREE (V

3. ANYTIME the minimum on-shift staffing requirements are NOT met the actions required are:

IMMEDIATELY INITIATE ACTION TO FILL THE VACANT POSITION(O wi.thin 2 EJP-O. 0, v2 7 paragraph 4.8.2 states:

The shift crew composition may be one less than the table 1 requzrements for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence of on-duty shft crew members [...]provided immediate action is taken to restore the shift crew composition to within the Table 1 requirements TS 5.22.c states:

Shift crew composition may be less than the minimum requirement of 10 FR 50.54(m,.)(2)(i,) and 5.2.2.a and 5.2.2.g for aperiod of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence of on-dut shift crew members provided immediate action is taken to restore the shifi crew composition to within the minimum requirements.

STOP TIME L Terminate when all elements of the task have been completed.

CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk (*) before the element number.

FNP ILT-35 ADMIN A1.b RO Page 6 of 8 GENERAL

REFERENCES:

1. FNP-O-EIP-O.O, V 27

2. FNP-O-SOP-O.O, V 149.1

2. KA: G2.1.5 RO 2.9 SRO 3.9 GENERAL TOOLS AND EQUIPMENT:

Provide/Acquire:

1. FNP-O-EIP-O.O, V 27

2. FNP-O-SOP-O.O, V 149.1

çrillcal ELEMEistfflcation:

STEP Evaluation

1. CRITICAL: TASK objective 2, CRITICAL: TASK objective

3. CRiTICAL: TASK objective COM1IENTS:

FNPILT-35ADMIN A.1.bRO HANDOUT Page 1 of2 CONDITIONS When I tell you to begin, you are to IDENTIFY THE ON-SHIFT MANNING REQUIREMENTS FOR THE CONDITIONS PROVIDED. The conditions under which this task is to be performed are:

a. Both Units are at 100% power.

b. It is Night shift on a holiday, and the Operations Manager has authorized maximizing time off.

c. The table below represents the Operations shift complement that has arrived to receive turnover and their license level/status.

NAME LICENSE status/gual ACTIVE Adam Dual Unit- SRO SM ACTIVE Bob Dual Unit- SRO Charlie Doug ACTIVE Eugene Dual Unit Frank RO INACTIVE Gary Dual Unit- SRO SSS-STA INACTIVE Harry Dual Unit- SRO SSS-Fire Jack Kelly Lisa Not licensed Mike SO Nick Fire Brigade Oscar Pam Not licensed Not Fire Brigade qualified R ogei Fire Protection Administrator Qualified_Shift_Communicator Your task is to PROVIDE a written response to the following:

o IDENTIFY whether or not the operations crew shown in the table above satisfies all of the requirements to take the shift without any additional action or personnel.

o STATE the minimum number of on-shift Reactor Operators required.

o Identify the required actions anytime the requirements for minimum on-shift staffing are NOT met.

FNPLT-35ADMIN A.1.bRO HANDOUT Page 2 of 2

1. Does the crew shown in the table satisfy all of the MINIMUM Operations shift staffing requirements? YES / NO (circle one)

2. The minimum required number of Reactor Operators required on-shift is:

3. ANYTIME the minimum on-shift staffing requirements are NOT met the actions required are:

FNP HLT35 ADMIN Page 1 of 8 A.2 RO Conduct of Operations ADMIN G2.2.12 Modified CRO-035 TITLE: Perform STP-9.0, RCS Leakage Test EVALUATION LOCATION: SIMULATOR CONTROL ROOM X CLASSROOM PROJECTED TIME: 20 MIN SIMULATOR IC NUMBER: N/A ALTERNATE PATH TIME CRITICAL PRA____

1PM DIRECTIONS:

1. Initiation of task may be in group setting, evaluation performed individually upon completion.

2. Requiring the examinee to acquire the required materials may or may not he included as part of the JPM.

TASK STANDARD: Upon successful completion of this JPM, the examinee will:

Correctly assess and determine RCS leakrate.

Correctly assess and determine if STP-9.0 Acceptance Criteria is met.

Examinee:

Overall JPM Performance: Satisfactory Unsatisfactory D Evaluator Comments (attach additional sheets if necessary)

EXAMINER:

Developer Billy Thornton Date: 2/10/2012 NRC Approval SEE NUREG 1021 FORM ES-301-3

FNP HLT-35 ADM{N A2 RO Page 2 of 8 CONDITIONS When I tell you to begin, you are to PERFORM STP-9.0, RCS LEAKAGE TEST. The conditions under which this task is to be performed are:

a. Unit 1 is stable at 100% power.

b. The RCS leakrate program is unavailable.

c. The plant computer data has been provided on the HANDOUT.

d. Previous RCS leakrate has been 0.00 gpm.

e. STP-9.0, initial conditions, and step 5.1 through 5.3 are complete.

f. References are available to you via the Exam Reference disk.

g. If additional references are desired, quietly notify the proctor.

Your task is to perform the following:

1) Determine RCS leakage per STP-9.0, APPENDIX A, and

- When APPENDIX A is complete, another operator will perform the remainder of the steps in STP-9.0,

2) Determine whether or not RCS leakage Acceptance Criteria is met.

Document your results on the handout.

INITIATING CUE: IF you have no questions, you may begin.

EVALUATION CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

START T1ME

1. Appendix A, step 2.1 Read and record initial

- 1) Records initial readings on data S / U readings on data sheet I. sheet 1.

2. Appendix A, step 2.2 Read and record final

- 2) Records final values on data S / U values on data sheet 1. sheet 1.

CUE IF REQUESTED: Other leakage is 0 gpm.

NOTE: [IF applicant inquires about any other leakage it is 0 gpm. This is information that is obtainable in the plant from turnover, and since there is no other known leakage provided, it may be assumed to be 0 gprn OR it may be requested. Either is acceptablel.

FNP HLT-35 ADMIN A2 RD Page 3 of 8 EVALUATiON CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

3. Appendix A, step 2.4 Calculate identified and 3) Calculation shows: S / U unidentified leakages using the formulas on STP- Identified RCS leakage =

9.0 data sheet 1. Acceptable range 0.04 0.06 gpm Unidentified RCS leakage Acceptable range 1.15 1 .18 gpm

4. Compares actual Leak rates with the Acceptance 4) Determines that: S / U Criteria, and determines that the Unidentified Identified RCS leakage =

Leakage does not meet Acceptance Criteria. Acceptable range 0.04 0.06 gpm Acceptance Criteria is

<10 gpm and is met.

Unidentified RCS leakage =

Acceptable range 1.151.18 gpm Acceptance Criteria is 1 gpm and is NOT met.

STOP TIME I Terminate when all elements of the task have been completed.

CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk (*) before the element number.

FNP HLT-35 ADMN A2 RD Page 4 of 8 GENERAL

REFERENCES:

1. FNP-1-STP-9.0, v5OM

2. Plant tank curves 27A, 27B, 27C, 28A, & 28B 3 KA: 02.2.12 Knowledge of surveillance procedures.

(CFR: 41.10 / 45.13)

IMPORTANCE RO 3.7 SRO 4.1 GENERAL TOOLS AND EQUIPMENT:

1. Copy of FNP-1-STP-9.0, v50.0 that is signed off, up to the step required.

2. Plant tank curves 27A, 27B, 27C, 28A. & 28B

3. Calculator

4. Plant Conditions at 10:00 & 12:00 Critical ELEMENT justification:

STEP Evaluation 1-2 Not Critical: this task will he performed to document the data on Data Sheet 1

but is not critical to performing the RCS leakrate calculation.

3 Critical: Task completion: required to properly determine Identified and Unidentified RCS leakage rate.

4 Critical: Task completion: required to properly determine if Acceptance Criteria of STP-9.0 is met.

COMMENTS:

FNP HLT-35 ADM[N A.2 RO Page 5 of 8 All tolerances based on differences in rounding. For VCT level, one caic was performed rounding to the least significant digits at each step of the calculation, and one was performed using all digits in the calculator until the end of each step of the calculations to round to the least significant digits. For RCDT level, one caic used gallons when the level was rounded to nearest whole % and another caic used gallons when rounded to the nearest half %.

INSTRUMENT NAME INITIAL FINAL FINAL - INITIAL Computer TIME 1000 1200 A = 120 Minutes (MCB)

NCI lOOA No significant change (N-41B, N-42B, PR AVG FLUX 100. 0% 100. 0%

N-43B, N-44B) (< 0.1%)

TE0453 LIQ PRZR TEMP 650. 8 °F 650. 8 °F No significant change (< 1 °F)

(T10453)

PC0482, PT0455, PT0456 or PT0457 PRZR PRESS 2239. 4 2239. 4 No significant change (P1 455, P1 456 (Note 1) psig psig (<5 psig) or P1 457)

TC0484 (preferred),

QR AT= 0 °F TYO4I2K, OR TY0422K, OR RCS TAVG Maximum change of 03°F TY0432K (Note 7) (Note 1) 571. 9 °F 571. 9 °F allowed if TAVG is 545°F or (Average of TI greater, 0.1°F if TAVG is less 412D, 422D & than 545°F.

432D)

RCS Temperature 99. 7 CF (NoteS) N/A B = AT x CF 0 Gal.

Correction Factor OR NA LC 1600 OR Average of LT0459, PRZRLVL 47.8 % 47.8 % C56.3 x 0 %= 0 Gal.

LT0460 & LT0461 (LI-459, 460, 461)

LTO115 D= 14.18 x ()10.3%=

VCTLVL 51.0 % 40.7 %

(LI 115) ()146.0 to 146.1 Gal.

LI 1003 Waste Pnlor 36.4 % 38.1 % E 5.3Oto 7.07 Gal.

RCDT LVL BOP L5261 Pos 6 127.69 *Gal 133.71 *Gal (Enter 0 if negative)

LT0470 PRT LVL 69. 7 % 69. 7 % F = 0 Gal.

(LI 470) (Note 2) NA *Gal NA *Gal (Enter 0 if negative)

TOTAL FLOW 3489 Gal. 3489 Gal. G = 0 Gal. Dilution and FIS 168 BATCH TNTEG NA Gal. NA Gal. Blended Make Tank Curve Book

FNP HLT-35 ADM{N A2 RO Page 6 of 8 KEV (conti uied STP- 1.1) T SI ELT RCS Lake Total Leakage BC-D+G (o )( 0 )( (-)146.Oto(-)146.l)+/-( 0 ) (+L21)to(+l.22)GPM A

( 120 )

Identified Leakage E+F (5.30to7.07)+( 0 ) + 0

= 0.04 0.06 GPM

= A

( 120 ) Other leakage Other Leakage: Source Rate (GPM) 0 0 Total Other Q_gp Unidentified Leakage 1.21 to 1.22 0.04 to 0.06 1.15 to 1.18 GPM Total Leakage Identified Leakage ACCEPTANCE CRITERIA: Identified Leakage 10 gprn Unidentified Leakage 1 gpm ON THE HANDOUT the candidate should document:

Identified RCS Leakage is fl06ri. gpm.

Unidentified RCS Leakage is L15I8o in gpm.

STP-9.0 Acceptance Criteria IS met /

8met.

A2RO HANDOUT Pg 1 of2 CONDITIONS When I tell you to begin, you are to PERFORM STP-9.0, RCS LEAKAGE TEST. The conditions under which this task is to be performed are:

a. Unit 1 is stable at 100% power.

b. The RCS leakrate program is unavailable.

c. The plant computer data has been provided on the HANDOUT.

d. Previous RCS leakrate has been 0.00 gpm.

e. STP-9.0, initial conditions, and step 5.1 through 5.3 are complete.

f References are available to you via the Exam Reference disk.

g. If additional references are desired, quietly notii the proctor.

Your task is to perform the following:

I) Determine RCS leakage per STP-9.0, APPENDIX A, and

- When APPENDIX A is complete, another operator will perform the remainder of the steps in STP-9.0,

2) Determine whether or not RCS leakage Acceptance Criteria is met.

Document your results below:

Identified RCS Leakage is gpm.

Unidentified RCS Leakage is gpm.

STP-9.0 Acceptance Criteria IS met / IS NOT met.

(circle one)

A.2 RO HANDOUT Pg 2 of 2 Plant Conditions at 1000:

INSTRUMENT NAME Computer Points N/A TIME 10:00 NC1100A PR AVG FLUX 100.0 %

TE0453 LIQ PRZR TEMP 650.8 PC0482 PRZR PRESS 2239.4 psig TC0484 RCS TAVG 571.9 LC 1600 PRZR LVL 47.8 %

LTO115 VCT LVL 51.0 %

BOP LS261 Pos 6 36.4 %

RCDT LVL LT0470 69.7 %

PRT LVL TOTAL FLOW 3489 Gal.

FIS 168 BATCH INTEG Plant Conditions at 1200:

INSTRUMENT NAME Computer Points N/A TIME 12:00 NC1100A PR AVG FLUX 100.0 %

TE0453 LIQ PRZR TEMP 650.8 °F PC0482 PRZR PRESS 2239.4 Psig TC0484 RCS TAVG 571.9 LC 1600 PRZR LVL 47.8 %

LTO115 VCT LVL 40.7 %

38.1 BOP LS261 Pos 6 RCDT LVL LT0470 PRT LVL 69.7 %

TOTAL FLOW FIS 168 3489 Gal.

BATCH_INTEG

FNP HLT-35 ADMFN Page 1 of 9 A,2 SRO Conduct of Operations ADMIN G2.2.12 Modified CRO-035 TITLE: Perform STP-9.O, RCS Leakage Test EVALUATION LOCATION: SIMULATOR CONTROL ROOM X CLASSROOM PROJECTED TIME: 25 MIN SIMULATOR IC NUMBER: N/A ALTERNATE PATH TIME CRITICAL PRA____

JPM DIRECTIONS:

1. Initiation of task may be in group setting, evaluation performed individually upon completion.

2. Requiring the examinee to acquire the required materials may or may not be included as part of the JPM.

TASK STANDARD: Upon successful completion of this JPM, the examinee will:

Correctly assess and determine RCS leakrate.

Correctly assess and determine if STP9.O Acceptance Criteria is met.

Examinee:

Overall JPM Performance: Satisfactory Unsatisfactory Evaluator Comments (attach additional sheets if necessary)

EXAMINER:

FNP HLT35 ADMIN A.2 SRO Page 2 of 9 CONDITIONS When I tell you to begin, you are to PERFORM STP-9.0, RCS LEAKAGE TEST. The conditions under which this task is to be performed are:

a. Unit 1 is stable at 100% power.

b. The RCS leakrate program is unavailable.

c. The plant computer data has been provided on the HANDOUT.

d. Previous RCS leakrate has been 0.00 gprn.

e. STP-9.0, initial conditions, and step 5.1 through 5.3 are complete.

f References are available to you via the Exam Reference disk.

g. If additional references are desired, quietly notify the proctor.

Your task is to perform the following:

1) Determine RCS leakage per STP-9.0, APPENDIX A When APPENDIX A is complete, another operator will perform the remainder of the steps in STP9.0.

2) Determine whether the RCS leakage Acceptance Criteria is met, or any required action(s) if it is not met.

Document your results on the handout.

INITIATING CUE: IF you have no questions, you may begin.

EVALUATION CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

START TIME

1. Appendix A, step 2.1 Read and record initial

- 1) Records initial readings on data S / U readings on data sheet 1. sheet 1.

2. Appendix A, step 2.2 Read and record final

- 2) Records final values on data S / U values on data sheet 1. sheet 1.

RUE IF REQUESTED: Other leakage is 0 gpm.

NOTE: [IF applicant inquires about any other leakage it is 0 gpm. This is information that is obtainable in the plant from turnover, and since there is no other known leakage provided, it may be assumed to be 0 gprn OR it may be requested. Either is acceptable].

FNP HLT-35 ADMN A.2 SRO Page 3 of 9 EVALUATION CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

3. Appendix A, step 2.4 Calculate identified and

- 3) Calculation shows: S / U unidentified leakages using the formulas on STP- Identified RCS leakage =

9.0 data sheet 1. Acceptable range 0.04 0.06 gpm Unidentified RCS leakage =

Acceptable range 1 .15 1 .18 gpm

4 Compares actual Leak rates with the Acceptance 4) Determines that: S / U Criteria, and determines that the Unidentified Identified RCS leakage =

Leakage does not meet Acceptance Criteria. Acceptable range 0.04 0.06 gpm Acceptance Criteria is

< 10 gprn and is met.

Unidentified RCS leakage =

Acceptable range 1 .15 I 1 8 gpm Acceptance Criteria is 1 gpm and is NOT met.

FNP HLT-35 ADMtN A2 SRO Page 4 of 9 EVALUATION CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

5. Perform Tech Spec evaluation. 5) Determines that Tech Spec 3.4.13 RAS is entered for unidentified LEAKAGE> 1 gpm.

CONDITION A is in effect for RCS operational LEAKAGE not within limits.

REQUIRED ACTION:

Reduce LEAKAGE to within limits in 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

If LEAKAGE is not within limits in 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , Then -

Be in MODE 3 in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND BE in MODE 5 in 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months is required.

STOP TIME Terminate when all elements of the task have been completed.

CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk (*) before the element number.

FNP HLT-35 ADMN A.2 SRO Page 5 of 9 GENERAL

REFERENCES:

1. FNP-i-STP-9.O, v50.0

2. Plant tank curves 27A, 27B, 27C, 28A, & 28B

3. Tech Specs and Bases, v186 / v53

4. KA: G2.2.12 Knowledge of surveillance procedures.

(CFR: 4L10 / 45.13)

IMPORTANCE RO 3.7 SRO 4.1 GENERAL TOOLS AND EQUIPMENT:

1. Copy of FNP-l-STP-9.0, v50.0 that is signed off, up to the step required.

2. Plant tank curves 27A, 27B, 27C, 28A, & 28B

3. Tech Specs and Bases

4. Calculator

5. Plant Conditions at 10:00 & 12:00 ica1ELNTustification:

STEP Evaluation 1-2 Not Critical: this task will be performed to document the data on Data Sheet 1, but is not critical to performing the RCS leakrate calculation.

3 Critical: Task completion: required to properly determine Identified and Unidentified RCS leakage rate.

4 Critical: Task completion: required to properly determine if Acceptance Criteria of STP-9.0 is met.

5 CHtical: Task completion: required to properly determine Tech Spec requirements, COMMENTS:

This Admin task was evaluated for performing notifications per EIP-8.0 for the SROs. The Corporate Duty Manager is required to be notified, but that is the only requirement. After discussion it was determined that there was little discriminatory value in the E.IP-8.0 notification requirements. The Corporate DM is required to be notified, but Corporate DM notification is required for off normal occurrence: Step 20.9 Other events which are considered at the time of their occurrence to be of possible concern to upper management including but not limited to (A12008204673) basically any off normal event. In addition, it is a procedural requirement to make Corporate DM notifications, but it is open to interpretation as to what is required. If the Corporate DM is not notified, there is no significant consequence.

FNP HLT-35 ADMN A.2 SRO Page 6 of 9 All tolerances based on differences in rounding. For VCT level, one caic was performed rounding to the least significant digits at each step of the calculation, and one was perfonned using all digits in the calculator until the end of each step of the calculations to round to the least significant digits. For RCDT level, one calc used gallons when the level was rounded to nearest whole % and another caic used gallons when rounded to the nearest half %.

INSTRUMENT NAME INITIAL FINAL FINAL - INITIAL Computer TIME 1000 1200 A = 120 Minutes (MCB)

NC1 100A No significant change (N-4lB,N-42B, PRAVGFLUX 100.0% 100.0%

(<0.1%)

N-43B, N-44B)

TE0453 LIQ PRZR TEMP 650. 8 °F 650. 8 °F No significant change (1 °F)

(T10453)

PC0482, PT0455, PT0456 or PT0457 PRZR PRESS 2239, 4 2239. 4 No significant change (P1 455, P1 456 (Note 1) psig psig (<5 psig) or P1 457)

TC0484 (preferred),

Qg AT= 0 °F TYO4I2K, OR TY0422K, OR RCS TAVG Maximum change of 0.3°F TY0432K (Note 7) (Note 1) 571. 9 °F 571. 9 °F allowed if TAVG is 545°F or (Average of TI greater, 0.1°F if TAVG is less 4l2D,422D& than 545°F.

432D)

RCS Temperature 99. 7 CF (Note 5) N/A B = AT x CF = 0 Gal.

Correction Factor OR NA LC 1600 OR Average of LT0459, PRZRLVL 47.8 % 47.8 % C=56.3 x 0 %= 0 Gal.

LT0460 & LT046 I (LI-459, 460, 461)

LTO1 15 D = 14.18 x ()10.3 % =

VCTLVL 51.0 % 40.7 %

(LI 115) (,)146.0 to146.1 Gal.

LI 1003 Waste Pnl or 36.4 % 38.1 % E = 5.30 to 7.07 Gal.

RCDT LVL BOP LS261 Pos 6 127.69 *Gal 133.71 *Gal (Enter 0 if negative)

LT0470 PRT LVL 69. 7 % 69. 7 % F 0 Gal.

(LI 470) (Note 2) NA *Gal NA *Gal (Enter 0 if negnve)

TOTAL FLOW 3489 Gal. 3489 Gal. G 0 Gal. Dilution and FIS 168 BATCH INTEG NA Gal. NA Gal. Blended Makeup

From Tank Curve Book

FNP HLT-35 ADMN A2 SRO Page 7 of 9 KE fto tiiued) . DATA Ill T . Lei ae Total Leakage BC-D+/-G = ( 0 )( 0 )( (-)146.Oto(-)146.1)+( 0 )_ (+l.21)to(+/-l.22)GPM A

( 120 )

Identified Leakage E+F ( 5.30to7.07)+( 0 ) 0 A

( 120 )

+

Other leakage

= 0.04-0.O6GPM Other Leakage: Source Rate (GPM) 0 0 Total Other Qgp Unidentified Leakage 1.21 to 1.22 0.040 to 0.060 1.15 to 1.18 GPM Total Leakage Identified Leakage ACCEPTANCE CRITERiA: Identified Leakage 10 gprn Unidentified Leakage I gpm ON THE hANDOUT the candidate should document:

Identified RCS Leakage is 3 gpm.

Unidentified RCS Leakage is gpm.

Evaluation of STP-9 .0 Acceptance Criteria:

3T met:

spec aDation TS 3,4.13 (ond

A.2 SRO HANDOUT Pg 1 of 2 CONDITIONS When I tell you to begin, you are to PERFORM STP-9.0, RCS LEAKAGE TEST. The conditions under which this task is to be performed are:

a. Unit 1 is stable at 100% power.

b. The RCS Ieakrate program is unavailable.

c. The plant computer data has been provided on the HANDOUT.

d. Previous RCS leakrate has been 0.00 gpm.

e. STP-9.0, initial conditions, and step 5.1 through 5.3 are complete.

f References are available to you via the Exam Reference disk.

g. If additional references are desired, quietly notify the proctor.

Your task it to perform the following:

1) Determine RCS leakage per STP-9.0, APPENDIX A

- When APPENDIX A is complete, another operator will perform the remainder of the steps in STP-9.0.

2) Determine whether the RCS leakage Acceptance Criteria is met, or any required action(s) if it is not met.

Document your results below:

Identified RCS Leakage is gpm.

Unidentified RCS Leakage is gpm.

Evaluation of STP-9 .0 Acceptance Criteria:

A.2SRO HANDOUT Pg 2 of 2 Plant Conditions at 1000:

INSTRUMENT NAME Computer Points N/A TIME 10:00 NC1100A PR AVG FLUX 100.0 %

TE0453 LIQ PRZR TEMP 650.8 °F PC0482 PRZR PRESS 2239.4 psig TC0484 RCS TAVG 571.9 LC 1600 PRZR LVL 47.8 %

LTOI15 VCT LVL 51.0 %

BOP LS261 Pos 6 RCDT LVL 36.4 %

LT0470 PRT LVL 69.7 %

TOTAL FLOW 3489 Gal.

FIS 168 BATCH_INTEG Plant Conditions at 1200:

INSTRUMENT NP14E Computer Points N/A TIME 12:00 NC1100A PR AVG FLUX 100.0 %

TE0453 LIQ PRZR TEMP 650.8 PC0482 PRZR PRESS 2239.4 Psig TC0484 RCS TAVG 571.9 LC 1600 PRZR LVL 47.8 %

LTO115 VCT LVL 40.7 BOP LS261 Pos 6 RCDT LVL 38.1 %

LT0470 PRT LVL 69.7 %

TOTAL FLOW FIS 168 3489 Gal.

BATCH_INTEG

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10/10/11 13 0423 FNP-1-STP 90 FARLEY NUCLEAR PLANT SURVEILLANCE TEST REVIEW SHEET SURVEILLANCE TEST NO. TECHNICAL SPECIFICATION REFERENCE FNP-USTP-9.O SR 3.4.13.1 TITLE MODE(S) REQUIRING TEST:

RCS LEAKAGE TEST 1. 2, 3, 4 TEST RESULTS (TO BE COMPLETED BY TEST PERFORMER)

PERFORMED BY / DATE\TIME (Print) (Signature)

COMPONENT OR TRAIN TESTED (IF APPLICABLE)

ENTIRE STP PERFORMED [ ] FOR SURVEILLANCE CREDIT PARTIAL STP PERFORMED [ ] NOT FOR SURVEILLANCE CREDIT REASON FOR PARTIAL:

TEST COMPLETED: [ ] SATISFACTORY [1 UNSATISFACTORY THE FOLLOWING DEFICIENCIES OCCURRED:

I CORRECTIVE ACTION TAKEN OR INITIATED SHIFT SUPERVISOR! SHIFT SUPPORT SUPERVISOR REVIEW PROCEDURE PROPERLY COMPLETED AND SATISFACTORY PER STEP 9.1 OF FNP-O-AP-5

[1 COMMENTS:

REVIEWED BY / DATE (Print) (Signature)

Reviewer must be AP3 1 Level II certified & cannot be the Performing Individual ENGINEERING SUPPORT SCREENED BY_______________________ DATE GROUP SCREENING (IF APPLICABLE)

COMMENTS:

Version 50.0

10/10/11 13:04:23 FNP-1-STP-9.0 TABLE OF CONTENTS Procedure Contains Number of Pages STRS I Body 10 Appendix A 1 Data Sheet I 2 Page 1 of I Version 50.0

10/10/11 13:04:23 FNP-1-STP-9.0 FARLEY NUCLEAR PLANT UIIT 1 SURVEILLANCE TEST PROCEDURE STP-9.0 RCS LEAKAGE TEST 1.0 PURPOSE The purpose of this procedure is to demonstrate that Reactor Coolant System leakage is within acceptable limits by performing a water inventory balance. Results of the inventory balance are used in the RCS Unidentified Leak Rate Monitoring Program.

NOTE: Asterisked steps (*) are those associated with Acceptance Criteria.

[

2.0 ACCEPTANCE CRITERIA 2.1 Unidentified leakage is I gpm.

2.2 Identified leakage 10 gpm.

NOTE: FNP4-STP9.0 RCS Leakage Test (SR 34.13d) is oniy required to be performed during steady state operation. Al 2004201338 3.0 INITIAL CONDITIONS St 3.1 The version of this procedure has been verified to be the current version.

(OR 1-98-498)

St 3.2 This procedure has been verified to be the correct unit for the task.

(OR 1-98-498)

St 3.3 Reactor power and reactor coolant temperature should be stabilized and held approximately constant for at least 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months prior to and during the test. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months steady state conditions are preferred. (In Mode 3 or 4 not required until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months of steady state operation.)

St 3.4 The pressurizer level and pressure control systems are in automatic or are in manual control and are stable.

Bt The level of the VCT is in the normal operating band high enough to prevent the occurrence of an Auto Makeup during the test.

Bt 3.6 The CVCS system is aligned per FNP-1-SOP-2.1A, CHEMICAL & VOLUME CONTROL SYSTEM.

Version 50.0

10/10/11 13:04:23 FNP-1-STP-9.0 Bt Noti the Shift Chemist and Shift Radiochemist of the perfonnance of the test to ensure that no sampling of the RCS Control Volume (RCS, PZR, CVCS, PRT, RCDT, etc.) will be done during this test.

4.0 PRECAUTIONS AND LIMITATIONS 4.1 Plant stability is the principal factor affecting leak rate accuracy. Any measured parameters that are not in a steady-state condition will adversely affect the accuracy of leak rate results and therefore should be minimized.

4.2 The following items should be considered when performing the RCS leak rate test:

4.2.1 Pressurizer

1. Pressurizer level control system should remain in operation throughout the leak rate test.

2. Pressurizer level should be maintained constant. Target: +1- 0.5%

3. Changes in PZR spray should be minimized during RCS leak rate calculation. Pressurizer spray may affect PZR thermal equilibrium and therefore affect the calculated PZR mass 4.2.2 Reactor Coolant System

1. It is preferred that the plant be steady-state for at least 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months prior to the test when practical for maximum accuracy. (EOL coastdown operation is acceptable.)

2. Reactor power should be maintained constant. Target: +7- 0.1%

3. Tavg should be maintained constant. Target: +7- 0.5°F

4. RCP seal injection and leakoff flow should be maintained constant during the leak rate calculation.

4.2.3 Containment Conditions Containment pressure and temperature should be maintained stable.

Change in containment pressure or temperature may affect leak rate or upset identified leakage collection tank equilibrium.

4.2.4 Measurement Time Interval A longer leak rate time interval (ATime) will provide a more representative leak rate result.

Version 50.0

10/10/11 13:04:23 FNP-1-STP-9.0 4.2.5 Sampling Chemistry should not sample RCS Control Volume (RCS, PZR, CVCS, PRT, RCDT, etc.) during the test.

4.2.6 Identified Leakage Identified leakage collection tanks (PRT, RCDT) should not be pumped during the leak rate test.

4.2.7 RCS Makeup

1. VCT divert valve should be maintained positioned to return letdown to the VCT.

2. Makeups including dilutions and borations will invalidate the test.

a makeup is required, THEN the test should be terminated and performed when plant conditions permit.

3. If charging pump seals are known to leak whether the pump is running or not, the appropriate adjustment should be made to NonReactor Coolant Pressure Boundary Leakage.

4.2.8 IF the RCDT or PRT level indication is invalid, THEN 0 gpm should be used for RCDT or PRT portion of identified leakage unless leakage into the RCDT or PRT is to be determined using another approved method.

4.2.9 The following guidelines should be followed to maximize precision:

IF available, THEN computer points should be used for obtaining data. Otherwise, the available indications are to be read as accurately as possible. Appendix A is provided for use when the IPC cannot supply required data.

For computer points and RCDT level, the data should be entered to include at least one decimal place (i.e., 50. 1 %).

Identified and unidentified leakage rates are to be reported in two decimal places (e.g., 0.01 gpm).

Version 50.0

10/10/1 1 13:04:23 FNP-1-STP-9.0 4.3 IF a leak rate is performed outside the bounds of the following validity checks, THEN the leak rate should be considered invalid. Document reason for invalid result (specify validity check not satisfied), and abort or invalidate test. The result should not be used as input to the baseline statistical data set for the historical mean leak rate. Leak rate test should be repeated or deferred until the plant is in a more stable condition.

Tavg remains constant [+/- 0.5°F] throughout the leak rate time interval.

Pressurizer Level remains constant [+/_ 0.5%].

Reactor Power remains constant [+/_ 0.1%].

VCT divert valve remains in position to return letdown to the VCT.

No sampling was done on the leak rate control volume.

Identified leakage collection tanks have not been pumped (PRT, RCDT).

4.4 To ensure that the STP9.0 Computer Program remains current, the Engineering Support Group should be notified of any revision or TCN to Data Sheet 1.

4.5 Requirements to notify the OPS RCS Leakrate Coordinator 4.5.1 IF more than one leakrate calculation is performed AND logged into the eSOMS Narrative Logs per day, notify the OPS RCS Leakrate Coordinator using one of the following methods:

4.5.1.1 Create an entry into the Logs tab of the Ui RCS ULR Data Analysis spreadsheet.

4.5.1.2 Send an email to the OPS RCS Leakage Rate Coordinator.

4.5.2 The notification to the OPS RCS Leakrate Coordinator should include the following information, at a minimum (CARl 91486):

Date

Time

Reason for performing multiple leakrate calculations Version 50.0

10/10/11 13:04:23 FNP-1-STP-9.0 5.0 INSTRUCTIONS 5.1 Verify RCDT system is aligned as follows:

Bt 5.1.1 Verify RCDT level is in the nonnal op crating band.

Bt 5.1.2 Close RCDT PUMPS DISCH LINE ISO Q1G21HV7136 Bt 5.2 Place VCT HI LVL DIVERT VLV, Q1E21LCV1 iSA, in the VCT position.

NOTE: Makeups including dilutions and borations will invalidate the test.

a makeup is required, THEN the test should be terminated and performed when plant conditions permit.

Bt IF the IPC is unable to supply the data required to perform the RCS leakage measurement, THEN, proceed to APPENDIX A.

NOTE: RCDT in-leakage may be calculated independently of this procedure OR performed concurrently with step 5.5.

5.4 Calculate RCS leakage into the RCDT using the IPC as follows:

5.4.1 Open the RCS Leak Rate application on the IPC Applications Menu.

5.4.2 Enter the RCDT Start Level and press ENTER.

RCDT LVL, LI 1003 Waste Pnl or BOP LS261 Pos 6 NOTE: A time span of at least 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months should be used during normal steady state plant operations, however if plant conditions dictate, a shorter time span may be used. (30 minutes minimum).

5.4.3 Record the time and wait approximately 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . TIME:

5.4.4 Enter the RCDT End Level and press ENTER.

RCDT LVL, LI 1003 Waste Pnl or BOP LS261 Pos 6 5.4.5 Enter total number of minutes in the Time block and press ENTER.

5.4.6 Record RCDT LEAKRATE: gpm Version 50.0

10/10/11 13:04:23 FNP-I -STP-9.0 5.5 Calculate RCS leakage using the IPC as follows:

5.5.1 Open the UNIT 1 RCS LEAKAGE CALC spreadsheet located on the Alarm SDS desktop.

5.5.2 Press REFRESH button on SAIPMS/Win Toolbar.

NOTE: If the time span crosses midnight, the DATE and TIME may be entered for both TIME entries in the format mm/dd/yyyy hh:rnm and the correct delta will be calculated.

5.5.3 Enter current TIME in INITIAL block E13. (Format hh:mm) 5.5.4 Manually type LEAKAGE DATA from Column C into Column E as fNITIAL data.

5.5.5 Manually type VALIDITY DATA from Column C into Column E as INITIAL data.

NOTE: A time span of at least 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months should be used during normal steady state plant operations, however if plant conditions dictate, a shorter time span may be used. (30 minutes minimum).

5.5.6 Wait approximately 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

5.5.7 known in-leakage exists, THEN perform the following:

5.5.7.1 Enter known identified in-leakage source in Cell D19 5.5.7.2 Enter known identified in-leakage leak rate in Cell H19.

5.5.8 known identified leakage exists, THEN perform the following:

5.5.8.1 Enter known identified leakage source in Cell D22 5.5.8.2 Enter known identified leakage leak rate in Cell H22.

5.5.9 Press REFRESH button on SAIPMS/Win Toolbar.

5.5.10 Enter current TIME in FINAL block Fl3.

5.5.11 Press Function Key F9 to refresh calculated values.

Version 50.0

10/10/11 13:04:23 FNP-1-STP-9.0 5.5.12 Check RCDT Leak Rate in Cell H21 is the same value as recorded in step 5.4.6.

5.5.13 Verify VALIDITY DATA DELTA is within limits listed in column H.

5.5.14 Print report and attach to this procedure.

5.6 Check calculated IDENTIFIED and UNIDENTIFIED RCS Leak Rate below acceptance criteria limits.

ACCEPTANCE CRITERIA: Identified Leakage 10 gpm Unidentified Leakage I gpm

/ 5.7 Open RCDT PUMPS DISCH LINE ISO Q1G2 IHV7I 36.

IV

/ 5.8 Place \7CT HI LVL DIVERT VLV, Q1E21LCV1 15A in the AUTO position.

IV Version 50.0

10/10/11 13:04:23 FNP-1-STP-9.0 NOTE:

I A link to the Unit 1 ULR Data Analysis Spreadsheet is located on the Operations Reports web page.

2 Step 5.9.1 requires a peer check 5.9 In the Unit 1 ULR Data Analysis Spreadsheet, perform the following:

5.9.1 In the next available row:

5.9.1.1 Verify current date in the Date Column (Colunm A) 5.9.1.2 Enter time of leak rate determination in the Time Column (Column B) 5,9.1 .3 Enter Unidentified Leak Rate (ULR) in the URL in gpm Column (Column C) 5.9.2 Press Function Key F9 to refresh calculated values.

5.9.3 Press Save button.

NOTE:

I The types of issues referred to in step 5.9.4 include formatting, baseline data, etc.

2 The purpose of step 5.9.4.2 is to allow the OPS RCS Leakrate Coordinator the information needed to evaluate and resolve the issue.

5.9.4 any issues are suspected with the spreadsheet, perform the following (CAR 191486) 5.9.4.1 Notify the Shift Supervisor 5.9.4.2 Create a detailed log entry on the Logs tab in the spreadsheet.

Version 50.0

10/10/11 13:04:23 FNP-1-STP-9.0 5.10 Record 7 Day Avg ULR from ULR Data Analysis Spreadsheet Column E:

gpm 5.11 Ii ULR is SUSPECT as indicated in Column D of the Unit 1 ULR Data Analysis Spreadsheet, THEN perform the following:

5.11.1 Investigate any SUSPECT daily reading by examination of the inputs and/or other reasonable means.

5.11.2 Perform a second STP.-9.0 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months if plant conditions permit.

5.11.3 If the previous measurement is judged to be flawed, the later measurement will be used for the daily surveillance value. If the previous measurement is determined to be valid, the two values will be averaged and the average value will be recorded as the daily surveillance value for that day.

5.12 Determine if ANY Tier One Action Levels have been exceeded:

(Place X in appropriate box.)

One 7 day rolling average of daily Unidentified RCS leak rates> 0.1 gpm.

Nine consecutive daily Unidentified RCS leak rates> baseline mean [ij.

No Tier One criteria exceeded.

5.13 Determine if ANY Tier Two Action Levels have been exceeded:

(Place X in appropriate box.)

Two consecutive daily Unidentified RCS leak rates> 0.15 gpm.

Two of three consecutive daily Unidentified RCS leak rates> [j.t + 2G].

Short Term Total Integrated Unidentified Leakage> 5,000 gallons.

No Tier Two criteria exceeded.

5.14 Determine if ANY Tier Three Action Levels have been exceeded:

(Place X in appropriate box.)

One daily Unidentified RCS leak rate > 0.3 gpm.

One daily Unidentified RCS leak rate> [ji +3oj.

Long Term Total Integrated Unidentified RCS Leakage> 50,000 gallons.

No Tier Three criteria exceeded.

Version 50.0

10/10/11 13:04:23 FNP-1-STP9.0 5.10 Record 7 Day Avg ULR from ULR Data Analysis Spreadsheet Column E:

gpm 5.11 I ULR is SUSPECT as indicated in Column D of the Unit 1 ULR Data Analysis Spreadsheet, THEN perform the following:

5.11.1 Investigate any SUSPECT daily reading by examination of the inputs and/or other reasonable means.

5.11.2 Perform a second STP-9.0 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months if plant conditions permit.

5.1 1.3 If the previous measurement is judged to be flawed, the later measurement will be used for the daily surveillance value. If the previous measurement is determined to be valid, the two values will be averaged and the average value will be recorded as the daily surveillance value for that day.

5.12 Determine if ANY Tier One Action Levels have been exceeded:

(Place X in appropriate box.)

One 7 day rolling average of daily Unidentified RCS leak rates> 0.1 gpm.

Nine consecutive daily Unidentified RCS leak rates> baseline mean [I].

No Tier One criteria exceeded.

5.13 Determine if ANY Tier Two Action Levels have been exceeded:

(Place X in appropriate box.)

Two consecutive daily Unidentified RCS leak rates> 0.15 gpm.

Two of three consecutive daily Unidentified RCS leak rates> [ji + 2].

Short Term Total Integrated Unidentified Leakage> 5,000 gallons.

No Tier Two criteria exceeded.

5.14 Determine if ANY Tier Three Action Levels have been exceeded:

(Place X in appropriate box.)

One daily Unidentified RCS leak rate> 0.3 gpm.

One daily Unidentified RCS leak rate> Di +3Gj.

Long Term Total Integrated Unidentified RCS Leakage> 50,000 gallons.

No Tier Three criteria exceeded.

Version 50.0

10/10/11 13 04 23 FNP-1-STP-9 0 5.15 IF any Tier One. Two OR Three action level is exceeded, THEN perform the following:

5.15.1 Implement NMP-OS-009 RCS Unidentified Leakage Assessment Section 6.2, Response Guidelines.

5.15.2 Contact Chemistry to evaluate sampling containment atmosphere for short-lived isotopes. The evaluation is to include R-1 1/12 trends.

5.15.3 IF determined that containment atmosphere sampling is needed, THEN request Chemistry perform sampling to include:

charcoal & particulate (minimum 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months )

tritium

gases 5.16 IF unidentified leakage is greater than 0.17 gpm, THEN submit a condition report for Engineering Support to evaluate ECCS leakage outside of containment for compliance with GDC- 19 requirements.

6.0 REFERENCES

6.1 P&ID D-175037 RCS, sheet 2 6.2 P&ID D-175039 - CVCS. sheet 2 6.3 P&ID D-175042 Waste Processing System, sheet 1 6.4 WCAP-16423-NP PWROG Standard Process and Methods for Calculating RCS Leak Rate for Pressurized Water Reactors 6.5 WCAP- 16465-NP PWROG Standard RCS Leakage Action Levels and Response Guidelines for Pressurized Water Reactors Version 50.0

10/10/11 13 0423 FNP-USTP-9 0 APPENDIX A RCS LEAKAGE DETERMINATION WITHOUT IPC DATA 1.0 PURPOSE The purpose of Appendix A is to provide a means to calculate RCS leakage when the IPC cannot supply all of the required data in the body of the procedure.

2.0 INSTRUCTIONS NOTE: It is acceptable to use available IPC data with good quality along with MCB indicators. The same instrumentation shall be used for initial and final readings.

2.1 Read and record initial readings on data sheet 1.

NOTE: A time span of at least 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months should be used during normal steady state plant operations, however if plant conditions dictate, a shorter time span may be used. (30 minutes minimum).

2.2 After the desired time span (normally 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ) record final values on data sheet 2.3 IF the RCS leakrate program is to be used, THEN verify that the program is revision 3.

NOTE: if the RCS leakrate program is used, then the remainder of data sheet 1 may he left blank.

2.4 Calculate identified and unidentified leakages using the RCS leakrate program or formulas on data sheet 1.

ACCEPTANCE CRITERIA: Identified Leakage 10 gpm Unidentified Leakage 1 gpm 2.5 IF used for RCS leakrate calculation, THEN attach the computer generated Data Sheet 1 to this procedure.

2.6 Return to step 5.7 in the body of the procedure.

Page 1 of 1 Version 50.0

10/10/11 13:04:23 FNP- 1 -STP-9.0 DATA SHEET I DATA SHEET 1 RCS Leaktrne INSTRUMENT NAME INITIAL FINAL FINAL - INITIAL Computer TIME A= Minutes (MCB)

NCI 100A No significant change (N-41 B. N-42B, PR AVG FLUX 0, N-43B, N-44B) (< 0.1%)

TE0453 LIQ PRZR TEMP °F F No significant change (< 1 CF)

(T10453)

PC0482, PT0455. PT0456 PRZR PRESS or PT0457 (Note 1) psig psig No significant change (. 5 psig)

(P1 455, P1 456 or P1 457)

TC0484 OR AT Average ofTY04l2K, RCS TAVG TY0422K & TY0432K (Note 1 and 7) CF CF Maximum change of 0.3 CF allowed if (Average of TI 412D, 422D TAVG is 545CF or greater, 0.UF if

& 432D) TAVG is less than 545CF.

RCS Temperature CF Correction Factor (Note 5)

N/A B AT X CF Gal.

LC 1600 Q Average of LT0459, PRZR LVL Oo 04 C 56.3 x % Gal.

I.T0460 & LT0461 (Note 7) Maximum change of 0.50/0 (LI-459, 460, 461)

LTO115 (LI_115)

VCTLVL % U D- 14.18x %= Gal.

LI 1003 Waste Pnl or BOP 0 0/

0 LS261 Pos 6 RCDT LVL eGal CGal E Gal. (Enter 0 if negative)

LT0470 PRT LVL %

(LI 470) (Note 2) Gal Gal 5 F Gal. (Enter 0 if negative)

FIS 168 TOTAL FLOW Gal. Gal. G Gal. Dilution and Blended BATCH INTEG Gal. Gal. v1akeup From Tank Curve Book 5

Total Leakage B-C-D+G( )-( )-( )+( GPM A

( ) (Note 6)

Identified Leakage =

E+F

=

(

)+( ), = GPM A

( ) Other leakage (Note 6)

Other Leakage: Source Rate (GPM)

Total Other Unidentified Leakage GPM

= Total Leakage Identified Leakage (Notes 3,4, & 6)

Page 1 of 2 Version 500

10/10/lI 13:04:23 FNP- 1 -STP-9.0 DATA SHEET 1 NOTES: 1 IF TAVG < 530°F, THEN use: PI-402A (PT0402) and P1-403A (PT0403),

1C and 1A Loop RCS WR PRESS (Avg. of Readings) AND TR-410 (TEO41O) and TR-413 (TE0413), RCS COLD AND HOT LEG TEMP (Avg.

of Readings) 2 Calibrated fluke may be used for PRT level determination if deemed necessary.

3 For reporting purposes values between 0.2 and 0 gpm shall be reported as 0 gpm. Values more negative than 0.2 gpm indicate a potential problem and therefore shall be reported as is.

4 Zinc addition will decrease the amount of total unidentified leakage by approximately .005 GPM which is considered an insignificant contribution.

5 Obtain CF from Table 1 using the nearest value of RCS temperature. N/A if RCS Leakrate program is used.

6 Leakage calculations are to be reported in two decimal places (e.g., 0.07 gpm).

7 TC0484 is preferred for RCS Tavg, but an individual loop temperature may be used if desired due to instability in the average reading.

TABLE I RCS Temp Correction RCS Temp Correction Factor (gaU °F) 200 24.3 545 83.5 225 26.6 547 84.5 250 28.9 550 86.1 275 31.2 555 88.8 300 33.5 560 91.7 325 36.6 565 94.8 350 39.8 570 98.2 375 42.9 571 98.9 400 46.0 572 99.7 425 51.4 573 100.5 450 56.7 574 101.2 475 62.1 575 101.9 500 67.4 577.2 103.6 525 76.3 Page 2 of 2 Version 50.0

FNP LT-35ADMN Page 1 of 10 A.3 ADMIN RO Radiation Control TITLE: Determine the Correct RWP, Total Projected Dose And Determine if an Oil Addition and venting can be Performed to the 2A RHR pump without exceeding limits defined.

EVALUATION LOCATION: D SIMULATOR ECONTROL ROOM CLASSROOM PROJECTED TIME: 20 MIN SIMULATOR IC NUMBER: N/A ALTERNATE PATH 0 TIME CRITICAL 0 PRA 1PM DIRECTIONS:

1 Initiation of task may be in group setting, evaluation performed individually upon completion.

2. Requiring the examinee to acquire the required materials may or may not be included as part of the JPM.

TASK STANDARD: Upon successful completion of this JPM, the examinee will perform the following for the task of adding oil to the 2A RHR pump and venting the suction:

Identify the location of Q2E1 lvi OOA

Identify the correct RWP to perform the task.

Calculate the total projected dose for the job.

Determine if the task can or cannot be performed without exceeding Administrative Limits or RWP limits on a single entry, and if NOT then state the reason.

Examinee:

Overall JPM Performance: Satisfactory D Unsatisfactory D Evaluator Comments (attach additional sheets if necessary)

EXAMINER:

Developer GT Ohmstede Date: 2/9/20 12 NRC Approval SEE NUREG 1021 FORM ES-30I-3

FNPILT-35ADMIN A.3R0 Page2oflO CONDITIONS When I tell you to begin, you are to Determine the Correct RWP, Total Projected Dose And Determine if an Oil Addition and venting can be Performed to the 2A RHR pump without exceeding limits defined.

The conditions under which this task is to be performed are:

1. You are a trainee on shifi and will be accomplishing the following task under instruction.

2. You will be draining and adding oil to the 2A RI-JR Pump Motor upper and lower reservoirs and venting the suction of the RHR pump near the encapsulation.

3. All needed tools, oil, and equipment have been staged outside the 2A RI-JR Pump room.

4. All necessary briefings to perform the task have been completed.

5. Your accumulated dose for this year to date is 1260 mRem.

6. Contamination levels: All areas are less than ALPHA 3 levels and < 200 dpmil 00 cm .

2

7. The following tasks are required to be performed:

TASK TIME REQUIRED DOSE RATE 1 Drain and fill the RHR 5 mm 25 mR/hr pump motor (upper reservoir) 2 Drain and fill the RHR 15 mm 60 inRihr pump motor (lower reservoir) 3 Remove pipe cap, attach 25 miii 1 20 mR/hr hose to Q2E1IVIOOA, and open the vent valves, Q2EIIV100A and Q2E1IVIOOB until air free water issues from the vent.

Note: Assume no dose received while traveling between tasks.

8. Your task is to perform all of the following and DOCUMENT your conclusions on the table provided:

a. Identify the location (room) of Q2E 11 Vi OOA, CTMT SUMP TO 2A RI-JR PUMP HDR VENT ISO.

b. Select the correct RWP to use for this task.

c. For yourself ONLY, calculate the Total projected dose to perform this task.

d. Determine whether the task can or cannot be performed without exceeding Administrative Dose Limits or RWP limits. If the task cannot be performed, then state the reason.

INITIATING CUE: IF you have no questions, you may begin.

FNP LT-35 ADMN A3 RO Page 3 of 10 EVALUATION CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

START TIME

1. Identifies the location Q2E11V100A Using MAXIMO, or FNP-2-SOP- S / U 7.OA or other methods, identifies the location of Q2E1 lvi OOA.

e.g.:

83 Foot elevation in the 2A RHR pump room OR Room2l3l

2. Determines R\Tp to use. Reviews the dose rates and S / U identifies that the highest General Area dose rate for the jobs to be performed is 120 mR/hr.

Determines that the task will require a High Radiation Area entry.

References the RWPs and determines that RWP 12-0 101 is a Training RWP, but it cannot be used for a High Radiation Area entry.

Determines that RWP 12-0503 has allowance for OPS Training in High Radiation Areas, and is the correct RWP to use.

Total dose from task calculation:

Dose-upper oil addition + Dose-lower oil addition + Dose-venting = Total dose for the task

1. 5 minutes

25 mRem! hr

1 hr!60 minutes = 2.08 rnRern (dose at jobsite) {2 2.1}

2. 15 minutes

60 mRem/ hr

1 hr/60 minutes = 15 mRem (dose at jobsite) { no range }

3. 25 minutes

120 mRem/ hr

1 hr/60 minutes = 50 mRem (dose at jobsite) { no range }

2.08 + 15 + 50 = Total Dose = 67 to 67.1 mRem total

FNP ILT-35 ADMN A3 RO Page 4 of 10 EVALUATION CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

3. Calculates total projected dose. Calculates dose received while S / U performing the job.

Documents the total of 67 mRem

{RANGE 67 67.1 mRem}

4. Determine if any close limits will be exceeded by Determines if allowable dose S / U performing the task. limits will be exceed:

Admin dose limit Total dose = 1260 + 67.1 =

1327.1 mR 1327.1 mR< Admin close limit of 2000 mR.

RWP Task dose limit 67.1 mR < RWP 12-0503 Task dose limit of 90 mR RWP Task dose rate limit 120 niRihr < RWP 12-0503 Task dose rate limit of 140 inRlhr.

Determines that dose limits of the RWP will not he exceeded.

IDFNTJFJES that the task actions can be completed as assigned by circling YES.

Total ANNUAL dose:

(1260 accumulated)+ 67.1 = 1327.1 mR {1327 1327.1}

FNP Administrative Annual Dose limit from FNP-0-M-001, Southern Nuclear Company Joseph M. Fancy Nuclear Plant Health Physics Manual, is 2000 mR for a Fully Documented Radiation worker.

STOP TIME

[ Terminate when all elements of the task have been completed.

FNP ILT-35 ADMIN A.3 RO Page 5 of 10 CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk (*) before the element number.

GENERAL

REFERENCES:

1. FNP-0-M-001, v18.0

2. KA: 02.3.14 RO 3.4 SRO 3.8 GENERAL TOOLS AND EOUIPMENT:

Calculator RWP 12-0503 and 12-0101 (For Training USE ONLY)

Health Physics Manual, FNP-0-M-001, v18.0.

Critical ELEMENT justification:

STEP Evaluation

1. Critical: Task completion: required to determine proper location for the task given

2. Critical: Task completion: required to determine proper Radiation Work Permit for the task given.

3. Critical: Task completion: required to determine the total projected dose.

4. CriticaL: Task completion: required to identit that the task can be clone within limits permitting task completion.

FNP LT-35 ADMIN A.3 RO Page 6 of 10 KEY Determination of Task Performance Q2EJ1V100A, CTMT SUMP TO 2A RI-JR Pump RM 2A RHR PUMP HDR VENT is acceptate: RM 213U locatecI-(Room)

CORRECT RWP to use (CIRCLE the correct RWP)

67 t.o 67J rnRem Projected dose for this task

{iange of 6767J rnRern}

(CIRCLE ONE)

Can you complete this task without exceeding limits?

ES* NO REASON, if applicable: NA

FNP ILT-35ADMN A3 RD HANDOUT Pg 1 of2 CONDITIONS When I tell you to begin, you are to determine the Correct RWP, Total Projected Dose And Determine if an Oil Addition and venting can be Performed to the 2A RHR pump without exceeding limits defined.

The conditions under which this task is to be performed are:

1. You are a trainee on shift and will be accomplishing the following task under instruction.

2. You will be draining and adding oil to the 2A RHR Pump Motor upper and lower reservoirs and venting the suction of the RHR pump near the encapsulation.

3. All needed tools, oil, and equipment have been staged outside the 2A RHR Pump room.

4. All necessary briefings to perform the task have been completed.

5. Your accumulated dose for this year to date is 1260 mRem.

6. Contamination levels: All areas are less than ALPHA 3 levels and < 200 dpm!l 00 cm .

2

7. The following tasks are required to be performed:

TASK TIME REQUIRED DOSE RATE 1 Drain and fill the RHR 5 mm 25 mR/hr pump motor (upper reservoir) 2 Drain and fill the RHR 15 mm 60 mRlhr pump motor (lower reservoir) 3 Remove pipe cap, attach 25 mm 120 mR/hr hose to Q2E1 1V100A and open the vent valves, Q2E1 1V100A and Q2E1 1V100B until air free water issues from the vent.

Note: Assume no dose received while traveling between tasks.

8. Your task is to perform all of the following and DOCUMENT your conclusions on the table provided:

a. Identify the location (room) of Q2E1 IV100A.

b. Select the correct RWP to use for this task.

c. For yourself ONLY, calculate the Total projected dose to perform this task.

d. Determine whether the task can or cannot be performed without exceeding Administrative Dose Limits or RWP limits. If the task cannot be performed, then state the reason.

FNP LT-35 ADMIN A.3 RO HANDOUT Pg 2 of 2 Determination of Task Performance Q2EIIVIOOA, CTMT SUMP TO 2A RHR PUMP HDR VENT ISO, is located: (Room)

CORRECT RWP to use (CIRCLE the correct RWP) 12-0101 12-0503 Projected dose for this task (CIRCLE ONE)

Can you complete this task without exceedina limits?

YES NO REASON, if applicable:

Plant Fancy UNIT Radiation 120101 REv Work Permit FOR TRAINING USE ONLY 99 Administration;This RWP is designated for administrative departments to include Executive & Senior Management. Security.

Job Information Technology. Fleet Oversight. Safeb and Health, Training, Perfonnance Improvement, and Work Control that invoke Description radiological work categorized as Low Risk AND not specifically addressed by other RWPs. Caution: This RWP cannot be used for entries into Containment, work in High Radiation Areas, Airborne Areas, or posted Alpha Level 2 or Level 3 Contaminated Areas.

Location RADIATION CONTROL AREAS HP Coverage Authorization Briefi 1 1 2012 Start Date End Date l2Ul 2012 INTERMITTENT ALL ALL 12:00AM 11:59PM Job Supv. G. Ohmstede EXT 4758 Radiological Conditions TASKS AIRBORNE LEVELS: < 0.3 DAC PART AND IODINE, <1.0 DAD Alanns Description DAC NOBLE GAS/TRITIUM Dose (inr j Rate(ior3ti CONTAMINATION: 200,000 DPM 100CM2 BETA GAMMA, NRC. INPO, EIC. ACTIVITIES -

LESS THAN ALPHA LEVEL 1 10 RAD LEVELS: LESS < 100 MREM/HR FLEET OVERSIGHT ACTIVITIES 10 50 iuetiy TRAINING AND EP ACTIVITIES 25 50 WORK CONTROL ACTIVITIES 25 50 TLD and DAD SECURITY ACTIVITIES 10 50 Protective Clothing Requirements DRESS REQUIRMENTS AS HP DIRECTS Respirators Usage is Prohibited

[ INSTRUCTIONS There arc certain worker instntctions that are applicable to ALL RWPs. These instructions are provided at the Main RCA entrance.

Worker MUST ensure they understand and comply wills these instructions at all times while working in RCAs ENTRY INTO AREAS WITH KNOWN RADIOLOGICAL CONDITIONS GREATER THAN THOSE SPECIFIED ABOVE IS PROHIBITED AND REQUIRES AUTHORIZATION AND BRIEFING ON THE APPROPRIATE RWP.

Contact Health Physics Prior to entering any Radiation Area posted as Neutron Monitoring Required.

Exposure limits for Neutrots is as follows: 10 mrem per enft> and 50 mremJisour.

The following special instructions ma be deviated from with SNC HP ANSI 3.1 or higher qualified individuals pennission.

Dressout requirements for areas >50,000 dpmni 1 OOcmn2 beta ganuna: Double cm eralls, or I set of Ultra Orex or equivalent, two sets of booties, two sets rubber shoecovers, and two sets gloves.

YOR TRAINING USE ONLY 6/18/2012 12:00:00 AM by NRC Prepared NRC EXAM TEAM APPROVED EXAM WRITER

Radiation Plant Fade [ IJIJTT 12-0503 Rev A ork Permit FOR TRAINING USE ONLY 99 Operilionc: This RMP is designated for Operations Activities involving work in High Radiation Areas and other work lob chi fled as \4cdiuns Radiological Risk not specifically addressed by other RWPs. CAUTION: This RWP cannot he Description usect for entries into Containment. Locked High Radiation Areas. OR work in Alpha Level 3 Areas.

Location H DIATION CONTROL AR! AS HP CoveraRe Auihorivation 11flH I 2i12 H l Start Dttte End Date 1NllRMI Il NI INL)IVIDI.\I. lDR:IDI,\L II 5 AM I. ° PM

.JitiiStl)t\. (i (thiiiteiie 1_\[ 41X J Rac!iological Conditlofls I

,,IRIIORNI. Cl VI [S [SS III N H U IIHURS P.R IAii h:,.

1tecrIni1n I NI RI ii I ONI t iN 0t) 5 DP\i trij( 512 B. [5 U. SIll, I P St VI lix D:uN (PLC F It I CS5 I Ls\ A Pi I.. Ci 1 t AILCsSI 20 70 R;\l) I F \ [15 I ISS lOOP \IRUsI HR lIPS iR,IMMiN (IM it I IlLS 7)

(NON lIP 1 B SD .,RL..xi fl Dosimetry lIPS At [LIT ii OPS I F S \I 5(1(11 RiD ARE A t & itll it I LVI I 5

140 TLD and DAD

)[ P HAD ARFAS1 140

[ Protective Clothing Requirements I DRESS REQUIRMENTS AS HP DIRECTS Respirators I Usage is Conditional per HP INSTRUCTIONS There are certatn worker itatnirtioils ih,t ,,ie appin,nie to ALL RSVP . These intnictions are pros ided at the Main RCA entrance.

5 Worker MUST ensure tlie smdei stand and comply a ith these instructions at all times white a orking in RC As All workeis must receive in Initial RWP Biiefing prim to using this RWP foi the FIRST time.

Prior to commencmg work, individuals will reeeise a High Rad briefing for cveu7 posted High Radiation Area to be eiutcied.

Prior to ronutnenning ins a ork in Neutron Ridi,,tion Areas individuals a ill couutact H altls PIn sins to ens ire appropriate Neutron sisointoring is perfontsed.

Expo ure limits for Neutron is as follows 10 inrein per entry and nO snremihour Health Physics Technician must gust. approsal hefoun are tool or piece ot equipment t raised uch that the item comes out of the water.

Health PhI irs Technician must gise appro al before are aetuvtted or high dose object is brought near tlse surlace of the m t r.

When there is extended work evolutions in the SFP Room th Operations Refueling Sup rvisor should consider placing the SFP on recirc to th deintn.

\onts HP prior to nios ing am fuel oi irradiated coinponeists so that HP can ensutie the nsoseinent null not cause ails possible streamnusg from the light poles to the Si P Triumsfer canal Identified Irr.,diated CML must have a i etries al plan appros ed h the HP Supervisor and can no, be sacuumned to a filter without appros al of HP Radii asIc DAD alann values iuas be adjusted by a SNC HP ANSI 1 ou hiehem qualified individual based on expected eondmuions bitt can not exceed tile iiimmts listed for this RSVP The following special umsstructions may be des iated from wills a SNC 1-hP ANSI 3 1 Os Isigher qualified mdii mdual pennmssson Dressout reqmreioents for aiea, 0 000 dpnx lfi0cin2 beta gamma Double coseralls. or I set ofLItra Oiex or equivalent. two lets of booties. rib sets rubber shoecos ers aisd two sets closes.

FOR TRAINING USE ONLE 618.201212 00:00 AM by NRC Prepared NRC EXAM TEAM APPROVED EXAM WRITER

FNP ILT-35 ADMN Page 1 of 8 A.3 ADMIN SRO Radiation Control TITLE: Determine Emergency Exposure limits for a task and determine if the task can be performed.

EVALUATION LOCATION: LI SIMULATOR LICONTROL ROOM CLASSROOM PROJECTED TIME: 20 MIN SIMULATOR IC NUMBER: N/A LI ALTERNATE PATH LI TIME CRITICAL LI PRA JPM DIRECTIONS:

1. Initiation of task may be in group setting, evaluation performed individually upon completion.

TASK STANDARD: Upon successful completion of this JPM, the examinee will calculate the Maximum dose an individual will receive to operate equipment for protection of the Safety and Health of the public, then determine if the task can be performed without exceeding EDLs.

Examinee:

Overall 3PM Performance: Satisfactory D Unsatisfactory D Evaluator Comments (attach additional sheets if necessary)

EXAMINER:

Developer CT Ohmstede Date: 2/9/2012 NRC Approval SEE NUREG 1021 FORM ES-301-3

FNP ILT-35 ADMIN A.3 SRO Page 2 of 8 CONDITIONS When I tell you to begin, you are to Determine Emergency Exposure limits for a task and determine if the task can be performed.

The conditions under which this task is to be performed are:

1. lB Steam Generator (SG) has a SGTR, 1A and IC SGs have tube leaks and there is fuel failure indicated.

2. A Site Area Emergency has been declared.

3. IA, lB and 1C Atmospheric Relief Valves have failed open and are required to be closed.

4. The Emergency Director (ED) has approved exceeding 1 0CFR2O exposure limits to accomplish this task.

5. The HP Manager has determined that there is no internal hazard present.

6. The team performing the actions will consist of one System Operator (SO) and one Health Physics (HP) Technician. You are to evaluate the task for the SO only.

7. The SO has received 1.26 Rem TEDE this year.

8. The SO is NOT a volunteer.

9. The SO has completed onsite radiation protection training.

10. The following actions are required to be performed:

TASK ESTIMATED TIME DOSE RATE 1 Close PCV-3371A 20 mm 12.0 RIhr 2 Close PCV-3371B 24 mm 40.0 RIhr 3 Close PCV-3371C 21 mm 12.0 RIhr Note: Assume no dose received while traveling between tasks.

Your task, as the ED, is to determine if all of the actions listed above can be performed without exceeding the exposure limit required for the SO to perform these actions, assuming that the actual task completion times are the same as the estimated times listed above.

INITIATING CUE: IF you have no questions, you may begin.

FNP LT-35 ADMIN A3 SRO Page 3 of 8 EVALUATION CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

START TIME

1. Determine dose received while performing task 1 Determine dose received while S / U performing task 1 12.0 R!hr X 1 hr/60 mm X 20 mm = 4.0 R 4 0 Rem

2. Determine dose received while performing task 2 Determine dose received while S / U performing task 2 40.0 R/hr X lhr/60 mm x 24 mm = 16.0 R 16.0 Rem

3. Determine dose received while performing task 3 Determine dose received while S / U performing task 3 12 R/hr X 1 hr/60 mm X 21 mm = 4.2 R 4.2 Rem

4. Determine TOTAL dose received 24.2 Rem S / U Total dose calculation: Dose-task 1 + Dose- task 2 + Dose- task 3 = Total dose 4.0 + 16.0 + 4.2 = Total Dose = 24.2 Rem total

5. Determine the Emergency Exposure Limit for this Emergency Exposure Limits S / U task per EIP-14.0 step 7.12. that can be REQUIRED (non volunteer) to be received is up to 25 Rem TEDE for protection of large populations.

EIP-14.O Emergency doses received do not have to take into account the annual dose to date.

FNP [LT-35 ADMN A.3 SRO Page 4 of 8 EVALUATION CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

6. Determine if the task can be performed without Determines that the task CAN be S / U exceeding emergency exposure limits, performed without exceeding EDLs.

24.2 Rem projected < 25 Rem for Protection of Large Populations EIPl4.O Emergency doses received do not have to take into account the annual close to date.

STOP TIME I Terminate when all elements of the task have been completed.

CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk (*) before the element number.

GENERAL

REFERENCES:

1. FNP-O-EIP-14.O, VER 26.0

2. KA: G2.3.l4 RO 3.4 SRO 3.8 RALTOOLSANDEUIPMENT:

Calculator FNP-0-EIP-14.O, VER 26.0

FNP ILT-35 ADMIN A.3 SRO Page 5 of 8 Comments:

CAUTION EMERGENCY EXPOSURE UMITS SHALL ONLY BE AUTHORIZED BY THE ED 7.12 Emergency situations may transcend the normal requirement of maintaining personnel exposures below I0CFR2O limits, as noted in step 7.10. Emergency exposures shall be minimized to every degree practicable. FNP personnel who have completed the onsite radiation protection training may be required to receive an exposure up to 25 Rem TEDE for the activity and conditions described below.

For those same personnel to receive in excess of 25 Rem, they must voluntarily agree to receive an emergency dose in excess of 25 Rem, but less than 100 Rem. Emergency doses received do not have to take into account the annual dose to date. Persons volunteering to receive in excess of 25 Rem must be made fully aware of the risks involved.

Emergency exposure limits are as follows:

TEDE Dose Activity Condition 10 Rem Protecting Valuable Property Lower Dose Not Practical 25 Rem Life Saving or Protection Lower Dose Not Practical of Large Populations

>25 Rem Life Saving or Protection Volunteers Only That Are

<100 Rem of Large Populations Fully Aware of The Risks Involved Critical ELEMENT justification: 1-3 are critical since if done incorrectly the answer could be correct for the wrong reason.

STEP Evaluation

1. Critical: calculation is required to calculate if EDLs will be exceeded and then to determine correctly if a volunteer will be required.

2. Critical: calculation is required to calculate if EDLs will be exceeded and then to determine correctly if a volunteer will be required.

3. Critical: calculation is required to calculate if EDLs will be exceeded and then to determine correctly if a volunteer will be required.

4. Critical: calculation is required to calculate if EDLs will be exceeded and then to determine correctly if a volunteer will be required.

5. Critical: EIP-14.0 EDLs for this task are up to 25 Rem, not including dose received to date. If EDL of 10 Rem for Protecting Valuable Property is used then the person could NOT do the task since 24.2 Rem will be received.

6. Critical: Determining if the task can be performed with a non volunteer based on the EDLs is required for task completion.

FNP LT-35 ADMIN A.3 SRO Page 6 of 8 Z 7 EDLs What is the Emergency Exposure Limit for the SO to perform the task? 25 Rem (CIRCLE ONE)

Can the SO perform the task without -

exceeding the Emergency Exposure Limit?

YES I NO

FNP ILT-35 ADMN A3 SRO HANDOUT Pg 1 of2 CONDITIONS When I tell you to begin, you are to Determine Emergency Exposure limits for a task and determine if the task can be performed.

The conditions under which this task is to be performed are:

1. lB Steam Generator (SG) has a SGTR, 1A and 1 C SGs have tube leaks and there is fuel failure indicated.

2. A Site Area Emergency has been declared.

3. 1 A, lB and 1 C Atmospheric Relief Valves have failed open and are required to be closed.

4. The Emergency Director (ED) has approved exceeding 1 OCFR2O exposure limits to accomplish this task.

5. The HP Manager has determined that there is no internal hazard present.

6. The team performing the actions will consist of one System Operator (SO) and one Health Physics (HP) Technician. You are to evaluate the task for the SO only.

7. The SO has received 1 .26 Rem TEDE this year.

8. The SO is NOT a volunteer.

9. The SO has completed onsite radiation protection training.

10. The following actions are required to be performed:

TASK ESTIMATED TIME DOSE RATE 1 Close PCV-3371A 20 miii 12.0 RJhr 2 Close PCV-3371B 24 mm 40.0 R/hr 3 Close PCV-3371C 21 mm 12.0 R!hr Note: Assume no dose received while traveling between tasks.

Your task, as the ED, is to determine if all of the actions listed above can be performed without exceeding the exposure limit required for the SO to perform these actions, assuming that the actual task completion times are the same as the estimated times listed above.

FNP ILT-35 ADMIN A3 SRO HANDOUT Pg 2 of 2 EULs What is the Emergency Exposure Limit for the SO to perform the task?

(CIRCLE ONE)

Can the SO perform the task without exceeding the Emergency Exposure Limit?

YES NO

ILT-35ADMINJPM A.4SRO Page lof 10 A.4 Admin SRO only Emergency Plan TITLE: Classify an Emergency Event per NMP-EP.-110, Emergency Classification Determination and Initial Action, and complete Checklist 1, Classification Determination.

EVALUATION LOCATION: LI SIMULATOR LICONTROL ROOM IICLASSROOM PROJECTED TIME: 15 MN SIMULATOR IC NUMBER: N/A LI ALTERNATE PATH [J TIME CRITICAL LI PRA JPM DIRECTIONS:

1. This task can be conducted individually or in a group setting in which all the necessary references are available.

2. This task has TIME CRITICAL elements.

3. Provide the candidate the HANDOUT page and a copy of Checklist 1, Classification Determination, to allow for familiarization with the task for the event in progress.

4. Allow the candidate time to review and understand the task.

5. Then, provide the candidate a copy of the procedure NMP-EP-1 10 AND NMP-EP-l lO-GLOO1, and direct the candidate to begin; This starts the time critical time.

6. When the candidate indicates that he has completed his task, record the time of completion. This ends the TIME CRITICAL portion of the task.

7. Upon completion of EP- 110, Checklist 1, provide a copy of EP- 111, Figure 1 and give the instructions of step 2 of the task to complete EP-1 11, Figure 1, steps 6 and 7.

8. Ensure a clock is in the room in which this task will be conducted.

CAUTION A KEY (2 pages) is included and precedes the student handout CARE must be taken when providing the Student HANDOUT as to not also include the KEY TASK STANDARD: Upon successful completion of this JPM, the examinee will:

Correctly assess the Classification and correctly fill out EP- 110, Checklist 1; which includes line 5; Name, Date and Time. The time is required to be within 15 minutes of the Start Time.

Correctly assess the status of any radioactive release and correctly fill out EP-1 11, Figure 1, steps6&7.

Examinee:

Overall JPM Performance: Satisfactory 11 Unsatisfactory D Evaluator Comments (attach additional sheets if necessary)

EXAMINER:

Developer GT Ohmstede Date: 2/6/2012 NRC Approval SEE NUREG 1021 FORM ES-301-3

ILT-35 ADMIN JPM A.4 SRO Page 2 of 10 CONDITIONS When I tell you to begin, you are to Classify an Emergency Event per NMP-EP-1lO, Emergency Classification Determination and Initial Action, and complete Checklist 1, Classification Determination.

The conditions under which this task is to be performed are:

a. The Site Security Captain reports that there are three people with guns in the Unit 2 Turbine Building and there is an on-going exchange of gunfire with security officers.

b. Unit 1 was tripped from 100% power from the MCB Handswitches.

c. Unit 2 attempted to trip the reactor using the MCB trip switches unsuccessfully.

d. The OATC then successfully opened the CRDM MG set supply breakers and the rods fell into the core.

e. Subsequently, the following conditions are reported on Unit 2:

An RCS leak of 150 gpm has developed.

R-2 is reading 40 mr/hr and is stable.

R-7 is in alarm; it is reading 100 mr/hr and is stable.

No other radiation monitors are in alarm.

f. The current MET Tower data is as follows:

o Wind Direction from 125 degrees.

o Wind Speed 4.5 mph.

o Precipitation none.

o Stability Class E NOTE: The classification should NOT be based on ED discretion Your task is to classify the event, fill out NMP-EP- 110, Checklist 1, Classification Determination Form through step 6.

This task has TIME CRITICAL elements.

Upon completion, report to the proctor that you have finished.

INITIATING CUE: IF you have no questions, you may begin.

Part 2 administer this portion of the JPM after completion of the above task.

CONDITIONS Based on your previously provided conditions, complete steps 6 and 7 of NMP-EP-1 11, Figure 1, Emergency Notification Form (page 1 of 2). This task is NOT TIME CRITICAL.

ILT-35 ADMIN JPM A.4 SRO Page 3 of 10 Ensure the CANDIDATE places the START TIME on the HANDOUT SHEET.

Put that same time in the START CRITICAL TIME block below.

EVALUATION CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

START CRITICAL TIME

1. Applicant completes Steps 2, 3, 4, 5, and 6 of

Fuel Cladding Integrity: S / U Checklist 1 by providing all of the following INTACT critical information (see answer key) and provides

Reactor Coolant System:

the completed Checklist 1 to the proctor within 15 POTENTIAL LOSS minutes.

Containment Integrity:

INTACT

Highest applicable fission product barrier Initiating Condition:

FA I

Highest applicable IC/EAL:

HS4

Classification:

Site Area H54

Name of Applicant, date, and current time

Meteorological Data:

125°F, 4.5 mph, E, none STOP CRITICAL TIME

2. After the applicant has turned in his/her completed

Step 6. Emergency Release: S / U Checklist 1, provide a copy of NMP-EP-111, BoxA None Figure 1, Emergency Notification Form, Page 1 of

Step 7. Release Significance: Box A -

2 and ask the applicant to complete Steps 6 & 7. Not Applicable STOP TIME I Terminate when all elements of the task have been completed.

CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk (*) before the element number.

GENERAL

REFERENCES:

1. NMP-EP-l10 Version 3.0

2. NMP-EP-1 lO-GLO1, Version 2.0

3. KA: G2.4.41 SRO (4.6)

ILT-35ADMINJPM A.4SRO Page4ofl0 GENERAL TOOLS AND EOUIPMENT:

NMP-EP-1 10 NMP-EP-1 10..GLO1 Critical ELEMENT justification:

STEP Evaluation 1 Critical: Task completion; information provided is essential for correct classification and Emergency Notification form being correctly filled out and transmitted.

2 Critical: Task completion; information provided is essential for correct determination of the status of radioactive releases. This is information that is transmitted to the States and Counties.

COMMENTS:

ILT-35ADMINJPM A.4SRO Page5oflO KEY part 1 Southern Nuclear Operating Company Emergency NMP-EP1 10 oumnN Emergency Clasficatin yj>ç and inthaJ Action VCan 2.0

.*. Procedure Page 12of23 Checkilat I - Ctassificatlon Determination (page 1 of I)

NOTE Key Parameters shouki be aflod to stabize to acourately represent plant ndtions piar d sfy ai e.vent Initial Actions Compdeted by

1. DetermIne the appropriate Initiating Condition Matrix for cIasfication of the event ST based on the current operating mode:

HOT IC/EAL Matrix Evakution CIlatt(GO toSp 2) to evatuate tie Barriers)

U COLD 1CAI Matrix Evaluatm Cturt (GO Step 3)

2. Evatuaa tie stat.rs cl the sice1 product barii usng Fuie I

FL Prcxiuct Barrier Evatuelion.

a. S the condition of eath fssm uctbanie:

ST LOSS POTENTI!L LOSS INTACT FAt ALERT Fuel addmg Integrity El El dassication for ReectorCoolant System El El 150 gpm leak. El ST ii. Deteniae the lhest aoiicahle fission product banter Ira1ing Conrtticn (ID):

(selectone) El FGI El FS1 FA1 El FU1 El None ISA2 ALERT lassificatlon 3. Evaluate and determine the highest appbcab4e IC/EAL ung the Matrix Evaluation ST on Unit 2 fç Chart kientified in step 1 ThEN GO to step 4.

Rx Trip issue HS4 or El None

4. Check the hiqhes.t emergency dassification level identified from either step 2b or 3: BT claselfication Badonlc# ctsfaffor Badan DGeeer Site-Area I-1S4 El tIGUE N/A Renarks (Identity the specific EAL. as needed):

5. Declare the event by appredng the Emergency Classification. ST Name of candidate Date: 6 / 19 12 Current time Tmi.y Ofr

6. Obtain Me dogicat Data (not required piar event dezation). sr W,d Diection (frcxn) 125 Mfid 4 Speed

. S StatBty CeasE Pied itation__none

7. InitIate Clieddhi2, Emergency an Ini1iacn.

ILT-35 ADMIN JPM A.4 SRO Page 6 of 10 KEY part 2 Sotahern Nuclear Ooeratlna Comoanv Emergency NMP-EP.4 11 soqnA lnlementing Emcrgoncy Notifications Veron 6.0 ri Procedure Page 36 of 48 Figure 1 = Emergency Notification Form (page 1 of 2) 1.IORILL flACTUALEVENT MESSAGES_____

2.INrnAL UFOI.LOW-tJP NOTiFiCATION: TIME DATE_I__j AUThENTICATIONS____

3. SITE: CotelioPte#____________

UNUSUAL EVENT U ALERT SflE AREA EMERGENCY GENERAL EMERGENCY BASED ON EAL#_________ EAL DESIPTlON____________________________________________

& PROTECT1/E ACTION RECOMMENDATIONS: NDNE UEVtMTE Fi14Fl TFfl fl Athtse Renainde of EPZ toMonl1 Local RadtoflV Stet roe Ae4 Radios for Mdillonal im*rma5on and Cossider e use of K] (potasawn odide) in aeosrdance with S Leplans and po.

U OThER

6. EMERGENCYRELEASE: one Is Ocxurmg Has Oczured

7. RELEASE S1ONFICANCE: <5 pIicable V&bn nennal ooeraan Above normal operasng Under

. RT1_1S blflte

8. EVENT PROGNOSIS: In<ovng SlaNe :)gradg

. METEOROLOGICAL DATA: Wind Dixe<5ien from degrees Wd Speed mpn i0.DECiARATiON UTERMINATK)N Time__________ Detail____

11. AFFECTED UNIT(S):

[]

12. UNIT STAWS: U1 % Pcaa Sttdowm al Time________ Dale (Unae<5ad Uns) Sa5s Not Requfed fr i U U2 % Por S dewn at Tame_________ Date i

13. REMARaS:

FOLIOW4JP INFORMATION (Lines 14 through 16 NotRequired for Initial Notifications)

EftGCY RSLEASc DATA NOT RE(JSl) F UL S A IS SIS.ECT..

14, RELEASE CHARACTERIZATION: rPE: fl Elevated Miaed Ground UNftS:UCi CeciCi1sec MAGNITUDE: Nodla Gases:_______ bthnee:________ Palhioslates_______ Oteer:

FORM: flAirborne S1at Time_______ Date !IStep Time_______ Date _(j_

&artTm,e______ Date I_I Stop Time______ Date _Jj_

i& PROJECTiON PARAMETERS: Prqiecon petiixL I*,ws EstEnated Release Dwan Hours Feten pei$xmed: Time Dale Ii Acddera Te:

16. PROJECTED DOSE: DISTANCE 1EDE (mrern) Adult Thyroid CDE (mrem<

Slte midaiy 2 MIes 5 MIas 10 MIes

17. APPROVED BY: Th1e_________________ Thne Date I I NOTiFiED RECEWED BY: BY: Tine Date_1_J (To be co<tgIeted 1w reeelwio oraarszahorn

ILT-35 ADMIN JPM A.4 SRO HANDOUT 2 Page 1 of 1 CONDITIONS PART 2:

Based on your previously provided conditions, complete steps 6 and 7 of NMP-EP-111, Figure 1, Emergency Notification Form (page 1 of 2). This task is NOT TIME CRITICAL.

Southern Nuclear Operating Company Emergency NMP-EP-1 11 SOUTHERN Implementing Emergency Notifications Version 6.0 Procedure Page 36 of 48 Figure 1 Emergency Notification Form (page 1 of 2) 1.DRILL ACTUALEVENT MESSAGE#

2. INITIAL FOLLOW-UP NOTIFICATION: TIME DATE / I_ AUTHENTICATION #______

3. SITE: Confirmation Phone #__________________

UNUSUAL EVENT ALERT SITE AREA EMERGENCY GENERAL EMERGENCY CLASSCATiON:

BASED ON EAL# EAL DESCRIPTION:___________________________________________________

5. PROTECTIVE ACTION RECOMMENDATIONS: NONE J EVACUATE SHELTER Advise Remainder of EPZ to Monitor Local Radio/TV Stations/Tone Alert Radios for Additional Information and Consider the use of KI (potassium iodide) in accordance with State plans and policy.

OTHER

6. EMERGENCY RELEASE: None B Is Occurring C Has Occurred

7. RELEASE SIGNIFICANCE: Not applicable B Within normal operating C Above normal operating Under limits limits evaluation

8. EVENT PROGNOSIS: Improving j Stable Degrading

9. METEOROLOGICAL DATA: Wind Direction from degrees* Wind Speed alle for Initial Precipitation

Stability Class*

1O.DECLARATlON TERMlNATlON Time Date I I 11.AFFECTEDUNIT(S):

12. UNIT STATUS: Ui Power Shutdown at Time Date I I (Unaffected Unit(s) Status Not Required for Initial Notifications) U2 Power Shutdown at Time Date / /

13. REMARKS:

FOLLOW-UP INFORMATION (Lines 14 through 16 Not Required for Initial Notifications)

EMERGENCY RELEASE DATA NOT REQUIRED IF LINE 6 A IS SELECTED.

14. RELEASE CHARACTERIZATION: TYPE: Elevated Mixed Ground UNITS: Ci j Ci/sec iCi/sec MAGNITUDE: Noble Gases:__________ lodines:____________ Particulates:__________ Other:

FORM: Airborne Start Time Date / /Stop Time Date / /...

Liquid StartTime Date / /StopTime Date / /

15. PROJECTION PARAMETERS: Projection period: Estimated Release Duration Hours Projection performed: Time Date / / Accident Type:

16. PROJECTED DOSE: DISTANCE TEDE (mrem) Adult Thyroid CDE (mrem)

Site boundary 2 Miles 5 Miles 10 Miles

17. APPROVED BY: Title______________________ Time /

NOTIFIED RECEIVED BY: BY: Time /

(To be comoleted by receivinci oraanization

ILT-35ADMINJPM A.4SRO HANDOUT Page 1 of 1 CONDITIONS When I tell you to begin, you are to Classify an Emergency Event per NMP-EP-llO, Emergency Classification Determination and Initial Action, and complete Checklist 1, Classification Determination.

The conditions under which this task is to be performed are:

a. The Site Security Captain reports that there are three people with guns in the Unit 2 Turbine Building and there is an on-going exchange of gunfire with security officers.

b. Unit 1 was tripped from 100% power from the MCB Handswitches.

c. Unit 2 attempted to trip the reactor using the MCB trip switches unsuccessfully.

d. The OATC then successfully opened the CRDM MG set supply breakers and the rods fell into the core.

e. Subsequently, the following conditions are reported on Unit 2:

An RCS leak of 150 gpm has developed.

R-2 is reading 40 mr/hr and is stable.

R-7 is in alarm; it is reading 100 mr/hr and is stable.

No other radiation monitors are in alarm.

f. The current MET Tower data is as follows:

o Wind Direction from 125 degrees.

o Wind Speed 4.5 mph.

o Precipitation none.

o Stability Class E NOTE: The classification should NOT be based on ED discretion Your task is to classify the event, fill out NMP-EP- 110, Checklist 1, Classification Determination Form through step 6.

This task has TIME CRITICAL elements.

Upon completion, report to the proctor that you have finished.

START TIME

Southern Nuclear Operating Company F

SOUTHERNES.

COMPANY Emergency Implementing Procedure I Emergency Classification Determination and Initial Action NMP-EP-110 Version 3.0 Page 12 of 24 Checklist I Classification Determination (page 1 of 1)

NOTE Key Parameters should be allowed to stabilize to accurately represent plant conditions prior jclassifying an event.

Initial Actions Completed by

1. Determine the appropriate Initiating Condition Matrix for classification of the event based on the current operating mode:

Li HOT IC/EAL Matrix Evaluation Chart (GO to Step 2) to evaluate the Barriers)

Li COLD IC/EAL Matrix Evaluation Chart (GO to Step 3)

2. Evaluate the status of the fission product barrier using Figure 1, Fission Product Barrier Evaluation.

a. Select the condition of each fission product barrier:

LOSS POTENTIAL LOSS INTACT Fuel Cladding Integrity Reactor Coolant System Li Containment Integrity Li

b. Determine the highest applicable fission product barrier Initiating Condition (IC):

(select one) Li FGI Li FS1 Li FA1 Li FU1 Li None

3. Evaluate and determine the highest applicable IC/EAL using the Matrix Evaluation Chart identified in step 1 THEN GO to step 4.

IC# or Li None

4. Check the highest emergency classification level identified from either step 2b or 3:

Classification Based on IC# Classification Based on IC#

Li General Li Alert Li Site-Area Li NOUE Li None N/A Remarks (Identify the specific EAL, as needed):________________________________

5. Declare the event by approving the Emergency Classification.

/ / Time:

Emergency Director

6. Obtain Meteorological Data (not required prior to event declaration):

Wind Direction (from)_ Wind Speed_____ Stability Class_ Precipitation__________

7. Initiate Checklist 2, Emergency Plan Initiation.

ML12214A480

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