Text

301 Draft Administrative JPMs
	ML13347B136
Person / Time
Site:	Vogtle
Issue date:	12/11/2013
From:	; NRC/RGN-II
To:	; Southern Nuclear Operating Co
References
	V-NRC-JP-1 491 5-HL17
	Download: ML13347B136 (180)
	v • d • e

_______

RO Job Performance Measure A Facility: Vogtle Task No: V-LO-TA-63005 Task

Title:

Perform AFD Monitoring JPM No: V-NRC-JP-1 491 5-HL17 K/A: G2.1 .7 RO 4.4 SRO 4.7 Examinee: Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance Actual Performance Classroom Plant Read to the examinee:

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

Initial Conditions: Unit 1 has recently recovered from a load rejection. The unit is at 70% power. Annunciator ALB1O-F06 is lit.

l&C has reported that the AFD monitor alarm ALB1 0-F06 is inoperable.

Initiating Cue: The SS directs you to perform 14915-1 Data Sheet 6 for AFD monitoring using the data supplied.

Task Standard: AFD monitoring per 14915-1 Data Sheet 6 performed correctly.

Req uired Materials: 14915-1, Data Sheet 6 Unit 1 Plant Technical Data Book Tab 6.0 Calculator This JPM is a reuse from Exam 2011-301. The JPM number was V-NRC-JP-1 9105-004.

Time Critical Task: No Validation Time: 15 minutes 2

Performance Information Critical steps denoted with an asterisk

Step 1 Determine upper and lower limits of AFD from PTDB-1 Tab 6.0.

Standard: Candidate fills in date and power level 70% and records the value of the doghouse limit at 70%. Upper limit +19.5% +/- 0.5% (calculated value is 19.6%) Lower limit -24% +/- 0.5%.

Comment:

Step 2 Record indicated Axial Flux Difference for each operable Excore Channel.

Standard: Candidate records Delta Flux values for all channels.

Comment:

Step 3 Verify the Axial Flux Difference is within limits of PTDB-1 Tab 6.0.

Standard: Candidate verifies that three are within limits and initials or signs Verified block to complete the surveillance satisfactory.

Comment:

3

Step 4 With the indicated AFD outside of the above required limits on 2 or more channels and with THERMAL POWER greater than or equal to 50% of RATED THERMAL POWER, reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 30 minutes.

Standard: This step does not apply.

Comment:

Terminating cue: Student returns initiating cue sheet.

4

DATA SHEET 6 (ANSWER KEY)

DATA SHEET 6 Sheet2of4 AXIAL FLUX DIFFERENCE WITH AFD MONITOR ALARM INOPERABLE Date Todays date Power ZQ%

Upper Limit = +195% +/- O5% (from PTDB Tab 6.0)

Lower Limit = 24% +/-05%

TIME 1-NI-41C 1-NI-42C 1-NI-43C 1-NI-44C VERIFIED Current -15% 22% -25% -15% nittaIs time 5

Verification of Completion Job Performance Measure No: V-NRC-JP-1 491 5-HL1 7 Examinees Name:

Examiners Name:

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners signature and date:

6

Initial Conditions: Unit 1 has recently recovered from a load rejection. The unit is at 70% power. Annunciator ALB1 0-F06 is lit.

l&C has reported that the AFD monitor alarm ALB1 0-F06 is inoperable.

Initiating Cue: The SS directs you to perform 14915-1 Data Sheet 6 for AFD monitoring using the data supplied.

NI Channel Reading lNl-41B 70%

1N-42B 68%

1 N-43B 70%

1N-44B 70%

Delta Flux Channel 1N-41C -15%

1 N-42C -22%

1 N-43C -25%

1N-44C -15%

Approved By I Procedure Number Rev S. E. Prewitt Vogtle Electric Generating Plant I 14915-1 47.4 bate Approved 3/25/2010 SPECIAL CONDITiONS SURVEILLANCE LOGS 1 Page Number 1 of 42 SPECIAL CONDITIONS SURVEILLANCE LOGS I PROCEDUREuSAGEREQUIREMENTS SECTIONS E Cotjnu Use: Procedure must be open and readily available ALL at the work location. Follow procedure step by step unless otherwise directed.

Reference Use: Procedure or applicable section(s) available at NONE the work location for ready reference by person performing steps.

Information Use: Available on plant site for reference as needed. NONE Printed January 11,2012 at 18:08

Approved By

Procedure Number Rev S. E. Prewitt I Vogtle Electric Generating Plant 14915-1 474 Date Approved Page Number 3/25/2010 SPECIAL CONDITIONS SURVEILLANCE LOGS 2 of 42 TABLE OF CONTENTS PAGE 1.0 PURPOSE 3 2.0 APPLICABILITY 3 3.0 PRECAUTIONS AND LIMITATIONS 3 4.0 PREREQUISITES AND INITIAL CONDITIONS 3 5.0 INSTRUCTIONS 3 6.0 ACCEPTANCE CRITERIA 3 7.0 EVALUATION AND REVIEW 4

8.0 REFERENCES

5 Printed January 11, 2012 at 18:08

Approved By [ 4 - /

Procedure Number Rev S E Prewitt j Vogtle Electric Generating Plant 14915-1 47 4 Date Approved - Page Number SPECIAL CONDITIONS SURVEILLANCE LOGS 3/25/2010 3 of 42 1.0 PURPOSE 1 .1 To provide logs and instructions for performing surveillances required to be performed only under special conditions and, or increased frequency.

1 .2 To provide logs and instructions for the performance of the following surveillances when Plant Computer is inoperable;

a. Data Sheet 3, Rod Group Alignment Limits With Rod Position Deviation Monitor Inoperable.

b. Data Sheet 6, Axial Flux Difference With AFD Monitor Alarm Inoperable, C. Data Sheet 1 1 Power Level Monitoring.

d. With the plant computer inoperable, 1 -FT-i 2835 is out of service and ODCM Table 3-i should be referenced for required actions to be performed. (Chemistry responsibility)

e. Verify operability ofthe HFASA per 14423, Source Range Analog Channel Operational Test.

2.0 APPLICABILITY This procedure is applicable in all modes.

3.0 PRECAUTIONS AND LIMITATIONS Out of tolerance data shall be circled in red and reported immediately to the Shift Supervisor (55).

4.0 PREREQUiSITES AND INITIAL CONDITIONS The plant is in an applicable mode and a special condition as listed on Table 1 exists.

5.0 iNSTRUCTIONS Complete the data sheet(s) specified on Table 1 for the required special condition surveillance(s).

6.0 ACCEPTANCE CRITERIA The acceptance criteria for each surveillance is verified on the applicable data sheets.

Printed January 11, 2012 at 18:09

N/

Approved By Procedure Number Rev S E Prewitt Vogtle Electric Generating Plant 14915-1 47 4 Date Approved Page Number 3/25/2010 SPECIAL CONDITIONS SURVEILLANCE LOGS 4 of 42 7.0 EVALUATiON AND REVIEW 7.1 TEST PURPOSE Special Condition(s):

Data Sheet(s) completed (Circle Appropriate Sheets):

1 2 3 4a 4b 5 6 7 8 9 10 11 12 13 14 15 16 17 18 7.2 Results obtained through the performance of this procedure meet the ACCEPTANCE CRITERIA of Section 6.0.

DYES DNO 7.3 IF no was checked, immediately notify the SS and initiate action in accordance with the actions specified on the data sheet(s) not meeting the acceptance criteria.

7.4 Comments (include any abnormal conditions and corrective actions taken):

Test Completed and SS Notified:

Supervisory Review:

Signature Date Time Printed January 11, 2012 at 18:09

Approved By . , Procedure Number Rev S E Prewitt Vogtle Electric Generating Plant i 491 5-1 47 4 Date Approved Page Number 3/25/2010 SPECIAL CONDITIONS SURVEILLANCE LOGS 17 of 42 DATA SHEET 6 Sheet 1 of 4 AXIAL FLUX DIFFERENCE WITH AFD MONITOR ALARM INOPERABLE 1 . Determine upper and lower limits of AFD from PTDB-1 Tab 6.0.

2. Record indicated Axial Flux Difference for each operable Excore Channel

a. At least once every hour.

b. At least once every hour until the AFD monitor alarm is updated after restoration.

3. Verify the Axial Flux Difference is within limits of PTDB-1 Tab 6.0.

4. With the indicated AFD outside of the above required limits on 2 or more channels and with THERMAL POWER greater than or equal to 50% of RATED THERMAL POWER, reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 30 minutes.

Printed January 11, 2012 at 18:09

Approved By L Procedure Number Rev S E Prewitt $ Vogtle Electric Generating Plant A 14915-1 47 4 Date Approved I Page Number 3/25/2010 SPECIAL CONDITIONS SURVEILLANCE LOGS 18 of 42 L

DATA SHEET 6 Sheet2of4 AXIAL FLUX DIFFERENCE WITH AFD MONITOR ALARM INOPERABLE Date Power Upper Limit = (from PTDB Tab 6.0)

Lower Limit =

TIME 1-NI-41C 1-NI-42C 1-NI-43C 1-NI-44C VERIFIED Shift Supervisor Review: I I Initial Date Time Printed January 11, 2012 at 18:09

Approved By ;* £: Procedure Number Rev Vogtle Electric Generating Plant S. E. Prewitt .

14915-1 47.4 Date Approved Page Number 3/25/2010 SPECIAL CONDITIONS SURVEILLANCE LOGS 19 of 42 DATA SHEET 6 Sheet 3 of 4 TIME 1-NI-41C 1-NI-42C 1-NI-43C 1-NI-44C VERIFIED Shift Supervisor Review: / /

Initial Date Time Printed January 11,2012 at 18:09

Approved By I I Procedure Number Rev S. E. Prewitt I Vogtle Electric Generating Plant 114915-1 47.4 Date Approved I Page Number 3/25/2010 I SPECIAL CONDITIONS SURVEILLANCE LOGS 20 of 42 DATA SHEET 6 Sheet 4 of 4 TIME 1-NI-41C 1-NI-42C 1-NI-43C 1-NI-44C VERIFIED Shift Supervisor Review: I /

Initial Date Time Printed January 11, 2012 at 18:09

-.% , 4 TAO.

Vogtle Electric Generating Plant Date pprov d Page Number

/1 Plant Technical Data Book Unit I i of 1 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER Axial Flux Difference Limits As A Function Of Rated Thermal Power UNIT 1 CYCLE 17 100) (+10, 100)

%RTP TARGET AFD %

r UNACCEPTABLE 100 90 80 0.6

-0.5

-OPERA11ON 70 -0.4 I 60 -0.4 50 -0.3 40 -0.2 30 -0.2 20 -0.1 15 -0.1 ACCEPTABLE I I I I I I III a) . OPERATION L UNACCEPTABLE OPERATION 0 TI 1

E 4:

I-

0 a) 1

(-30, 50) (+26, 50)

DOGHOUSE BREAKPOINTS PTE:

150:100 .

RE W Y/ T :

7/

50% *

(/(f

-30.0 +26.0

-40 -35 -30 -25 -20 -15 -10 -5 0 5 10 15 20 25 30 35 40 AXIAL FLUX DIFFERENCE (% Delta I)

Printed August 10, 201 1 at 8:59

SRO Job Performance Measure A Facility: Vogtle Task No: V-LO-TA-63005 Task

Title:

Evaluate Inoperable AFD Monitor Alarm JPM No: V-NRC-JP-14915-HL17 K/A: G2.1 .7 (SRO 4.7)

Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance Actual Performance Classroom Simulator Plant Read to the examinee:

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

Note to examiner: Hand out the Cue Sheet ONLY Initial Conditions: Unit 1 has recently recovered from a load rejection. The unit is at 70% power. Annunciator ALB1 O-F06 is lit.

I&C has reported that the AFD monitor alarm ALB1 O-F06 is inoperable.

Initiating Cue: You are the SS. Determine the Tech Spec required actions and perform any necessary surveillances for the AFD monitor alarm inoperability using the data supplied.

1

Task Standard: Inoperable AFD monitor alarm ALB1O-F06 is evaluated and applicable actions taken (AFD calculated and LCO evaluated).

Required Materials: 14915-1, Data Sheet 6 Unit 1 Plant Technical Data Book Tab 6.0 17010-c Annunciator Response procedure for window ALB1 0-F06 Tech Specs, Tech Spec Bases, COLR calculator This JPM is a reuse from Exam 2011-301. The JPM number was V-NRc-JP-1 4915-004.

Time critical Task: No Validation Time: 15 minutes 2

Performance Information Critical steps denoted with an asterisk

Determine surveillance required to be performed.

CUE: If asked: Provide the ARP 17010-C copy for window ALB1O-F06.

CUE: When asked: Provide 14915-1 Data Sheet 6.

Standard: Candidate determines AFD must be determined for each OPERABLE excore channel within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months using 14915-1 Data Sheet 6.

Comment:

Step 1 Determine upper and lower limits of AFD from PTDB-Unit 1 Tab 6.0.

Standard: Candidate fills in date and power level 70% and records the value of the doghouse limit at 70% Upper limit +19.5% +/- 0.5% (calculated value is 19.6%) Lower limit -24% +/- 0.5%.

Comment:

3

Step 2 Record indicated Axial Flux Difference for each operable Excore Channel.

Standard: Candidate records Delta Flux values for all channels.

Comment:

Step 3 Verify the Axial Flux Difference is within limits of PTDB-Unit 1 Tab 6.0.

Standard: Candidate verifies that two are not within limits and does NOT initial or sign the Verified block to complete the surveillance signifying it is unsatisfactory. Initial or signature with a note that the results are unsat would also be acceptable.

Comment:

Step 4 Determine required action.

With the indicated AFD outside of the above required limits on 2 or more channels and with THERMAL POWER greater than or equal to 50% of RATED THERMAL POWER, reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 30 minutes.

Standard: Candidate should report the above action must be done.

Comment:

Terminating cue: Student returns initiating cue sheet.

4

DATA SHEET 6 (ANSWER KEY)

DATA SHEET 6 Sheet 2of4 AXIAL FLUX DIFFERENCE WITH AFD MONITOR ALARM INOPERABLE Date Todays date Power ZQ%

Upper Limit= +/-19.5% +/-0.5% (from PTDB Tab 6.0)

Lower Limit = -24% +/- 05%

TIME 1-NI-41C 1-NI-42C 1-NI-43C 1-NI-44C VERIFIED Current -25% -20% -22% -25% Note I time 5

Verification of Completion Job Performance Measure No: V-NRC-JP-1 491 5-HL1 7 Examinees Name:

Examiners Name:

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners signature and date:

6

Initial Conditions: Unit 1 has recently recovered from a load rejection. The unit is at 70% power. Annunciator ALB1 0-F06 is lit.

l&C has reported that the AFD monitor alarm ALB1 0-F06 is inoperable.

Initiating Cue: You are the SS. Determine the Tech Spec required actions and perform any necessary surveillances for the AFD monitor alarm inoperability using the data supplied.

NI Channel Reading N41 70%

N42 68%

N43 70%

N44 70%

Delta Flux Channel N41C -25%

N42C -20%

N43C -22%

N44C -25%

Approved By . . Procedure Number Rev J.B. Stanley Vogtle Electric Generating Plant 17010-1 50 Date Approved ANNUNCIATOR RESPONSE PROCEDURES FOR ALB 1 0 ON PANEL 1 Cl Page Number 08/16/2011 ONMCB 65 of 66 WINDOW F06 ORIGIN SETPOINT DELTA FLUX YC-1140 PlantTechnical DEVIATION Data Book, Tab 6 1.0 PROBABLE CAUSE

1. Xenon transient

2. Control rod motion

3. Thermal power transient

4. Loss of Power Range Detector voltage.

5. IPC Failure 2.0 AUTOMATiC ACTIONS NONE 3.0 iNITIAL OPERATOR ACTIONS NOTE The Delta Flux Deviation Program satisfies the requirement for Verify AFD within limits for each OPERABLE excore channel in Technical Specifications SR 3.2.3.1.

NONE Printed January 11,2012 at 18:12

Approved By Procedure Number Rev J B Stanley Vogtle Electric Generating Plant i i 701 0-1 50 Date Approved ANNUNCIATOR RESPONSE PROCEDURES FOR ALB 1 0 ON PANEL 1 Cl Page Number 08/16/2011 ONMCB 66 of 66 WINDOW F06 (Continued) 4.0 SUBSEQUENT OPERATOR ACTIONS NOTE This annunciator comes in immediately upon exceeding the limits for acceptable operation.

1 . With Reactor Power greater than 50% check differential flux indications and if two or more are outside the limits, perform the following:

a. Restore the indicated AFD to within the limits, or

b. Reduce Thermal Power to less than 50% of Rated Thermal Power within 30 minutes.

2. Thermal Power shall not be increased above 50% of Rated Thermal Power until the indicated AFD is within the limits specified by the COLR.

3. if loss of Power Range Detector voltage is determined, Go To 1 8002-C, I

Nuclear Instrumentation System Malfunction.

4. Refer To Technical Specification LCO 3.2.3.

5. i.E alarm is inoperable, begin recording differential flux in accordance with 1 491 5-1 Special Condition Surveillance Logs (Technical Specifications SR 3.2.3.1).

6. Refer To Plant Computer alarm summary display for additional information relating to this alarm.

5.0 COMPENSATORY OPERATOR ACTIONS Initiate Data Sheet 6 of 14915-1, Special Condition Surveillance Logs END OF SUB-PROCEDURE

REFERENCES:

Technical Specification Section LCO 3.2.3 Printed January 11,2012 at 18:12

I Procedure Number Rev I

Approved By S. E. Prewitt Vogtle Electric Generating Plant 114915-1 47.4 Date Approved Page Number 3/25/2O1 0 SPECIAL CONDITIONS SURVEILLANCE LOGS 1 of 42 I

SPECIAL CONDITIONS SURVEILLANCE LOGS PROCEDUREUSAGEREQUIREMENTS SECTIONS Continuous Use: Procedure must be open and readily available ALL at the work location. Follow procedure step by step unless otherwise directed.

Reference Use: Procedure or applicable section(s) available at NONE the work location for ready reference by person performing steps.

Information Use: Available on plant site for reference as needed. NONE Printed January 11, 2012 at 18:08

Approved By I Procedure Number Rev S. E. Prewitt Vogtle Electric Generating Plant 114915-1 47.4 1

Date Approved 3/25/2010 1 SPECIAL CONDITIONS SURVEILLANCE LOGS j Page Number 2 of 42 TABLE OF CONTENTS PAGE 1.0 PURPOSE 3 2.0 APPLICABILITY 3 3.0 PRECAUTIONS AND LIMITATIONS 3 4.0 PREREQUISITES AND INITIAL CONDITIONS 3 5.0 INSTRUCTiONS 3 6.0 ACCEPTANCE CRITERIA 3 7.0 EVALUATION AND REVIEW 4

8.0 REFERENCES

5 Printed January 11, 2012 at 18:08

Approved By . . Procedure Number Rev S. E. Prewitt Vogtle Electric Generating Plant 14915-1 47.4 Date Approved Page Number 3/25/2010 SPECIAL CONDITIONS SURVEILLANCE LOGS 3 of 42 1.o PURPOSE 1 .1 To provide logs and instructions for performing surveillances required to be performed only under special conditions and, or increased frequency.

1 .2 To provide logs and instructions for the performance of the following surveillances when Plant Computer is inoperable;

a. Data Sheet 3, Rod Group Alignment Limits With Rod Position Deviation Monitor Inoperable.

b. Data Sheet 6, Axial Flux Difference With AFD Monitor Alarm Inoperable, C. Data Sheet 1 1 Power Level Monitoring.

d. With the plant computer inoperable, 1 -FT-i 2835 is out of service and ODCM Table 3-i should be referenced for required actions to be performed. (Chemistry responsibility)

e. Verify operability of the HFASA per 1 4423, Source Range Analog Channel Operational Test.

2.0 APPLICABILITY This procedure is applicable in all modes.

3.0 PRECAUTIONS AND LIMITATIONS Out of tolerance data shall be circled in red and reported immediately to the Shift Supervisor (55).

4.0 PREREQUISITES AND INITIAL CONDITIONS The plant is in an applicable mode and a special condition as listed on Table 1 exists.

5.0 iNSTRUCTIONS Complete the data sheet(s) specified on Table 1 for the required special condition surveillance(s).

6.0 ACCEPTANCE CRITERIA The acceptance criteria for each surveillance is verified on the applicable data sheets.

Printed January 11,2012 at 18:09

Approved By . . Procedure Number Rev S. E. Prewitt Vogtle Electric Generating Plant 14915-1 47.4 Date Approved Page Number b3/25/2010 SPECIAL CONDITIONS SURVEILLANCE LOGS 4 of 42 7.0 EVALUATiON AND REVIEW 7.1 TEST PURPOSE Special Condition(s):

Data Sheet(s) completed (Circle Appropriate Sheets):

1 2 3 4a 4b 5 6 7 8 9 10 11 12 13 14 15 16 17 18 7.2 Results obtained through the performance of this procedure meet the ACCEPTANCE CRITERIA of Section 6.0.

DYES DNO 7.3 IF no was checked, immediately notify the SS and initiate action in accordance with the actions specified on the data sheet(s) not meeting the acceptance criteria.

7.4 Comments (include any abnormal conditions and corrective actions taken):

Test Completed and SS Notified:

Supervisory Review:

Signature Date Time Printed January 11,2012 at 18:09

F Approved By . C Procedure Number Rev Is. E. Prewitt Vogtle Electric Generating Plant 14915-1 47.4 1 Date Approved SPECIAL CONDITIONS SURVEILLANCE LOGS Page Number 17 of 42 312512010 C

DATA SHEET 6 Sheet 1 of 4 AXIAL FLUX DIFFERENCE WITH AFD MONITOR ALARM INOPERABLE 1 . Determine upper and lower limits of AFD from PTDBI Tab 6.0.

2. Record indicated Axial Flux Difference for each operable Excore Channel

a. At least once every hour.

b. At least once every hour until the AFD monitor alarm is updated after restoration.

3. Verify the Axial Flux Difference is within limits of PTDB-1 Tab 6.0.

4. With the indicated AFD outside of the above required limits on 2 or more channels and with THERMAL POWER greater than or equal to 50% of RATED THERMAL POWER, reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 30 minutes.

Printed January 11, 2012 at 18:09

Approved By I Procedure Number Rev S. E. Prewitt Vogtle Electric Generating Plant 14915 l

1 c

Date Approved 3/25/2010 SPECIAL CONDITIONS SURVEILLANCE LOGS DATA SHEET 6 I Page Number 18 of 42 Sheet 2 of 4 AXIAL FLUX DIFFERENCE WITH AFD MONITOR ALARM INOPERABLE Date Power Upper Limit = (from PTDB Tab 6.0)

Lower Limit =

TIME 1-NI-41C 1-NI-42C 1-NI-43C 1-NI-44C VERIFIED Shift Supervisor Review: I /

Initial Date Time Printed January 1 1 201 2 at 18:09

I Procedure Number Rev Approved By S. E. Prewiff Vogtle Electric Generating Plant A 14915-1 47.4

-S Date Approved 3/25/2O1 0 [ SPECIAL CONDITIONS SURVEILLANCE LOGS Page Number 19 of 42 DATA SHEET 6 Sheet 3 of 4 TIME 1-NI-41C 1-NI-42C 1-NI-43C 1-NI-44C VERIFIED Shift Supervisor Review: _/

Initial Date Time Printed January 1 1 201 2 at 18:09

1 Procedure Number Rev Approved By S. E. Prewitt J Vogtle Electric Generating Plant A 114915-1 47.4 Date Approved 3/25/2O1O I SPECIAL CONDITIONS SURVEILLANCE LOGS I Page Number 20 of 42 DATA SHEET 6 Sheet 4 of 4 TIME 1-NI-41C 1-NI-42C 1-NI-43C 1-NI-44C VERIFIED Shift Supervisor Review: /

Initial Date Time Printed January 11, 2012 at 18:09

A

, Electric Generating Plant g TAO.

Date pprov /7 Page Number 8,2/o/6ii Plant Technical Data Book Unit I i ot i AXIAL FLUX DIFFERENCE LliTS AS A FUNCTION OF RATED THERMAL POWER Axial Flux Difference Limits As A Function Of Rated Thermal Power UNiT I CYCLE 17 hi, I

-40 35 -30 25 -20 10 -5 0 5 10 15 20 25 30 35 40 AXIAL FLUX DIFFERENCE (% Delta I)

Printed August 10, 201 1 at 8:59

-,., _2 A TAO.

Vogtle Electric Generating Plant Date pprov d Page Number

)i/ ii PlantTechnicalDataBook Unit I lof 1 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF RATED THERMAL POWER Axial Flux Difference Limits As A Function Of Rated Thermal Power UNIT I CYCLE 17

(-15, 100) j-+io: 100)

I %RTP TARGET AFD %

100 -0.6 90 -0.5 UNACCEPTABLE 80 -0.5 OPERATION 70 -0.4 60 -0.4 50 -0.3 40 -0.2 30 -0.2 20 -0.1 15 -0.1 CCEPTABLE IIiIIIIIlIIIIlI DPERA1ION jHUNACCEPTABLE (DOATIfM TARGET L1 I-+1+I+++4I-44 4 4-+4*

,[

T Ii I I

(-30, 0) -4#++14+4 I -

S 50) -1 IIIIIIII III i* 111111 f-t+++ 4 4 + +-t f + +++ 4 4 4 I- f +I fI+++ 4 + + +-I f + f f+++ 4 4 4 t- f tIF++t-t++ +1 II+ f+t+ t 4I-f+I

+

DOGHOUSE BREAKPOiNTS 100% PFORMDBY/DATE: 1 1 11

-15.0 +10.0 --

50% RE)W1fY/IATE: I

-30.0 +26.0

-4/_ha-, -s.- 87 (,/(f Hii

-40 35 -30 25 f 1U14L U 1 UH

-20 -15 -10 -5 0 5 10 15 20 25 30 35 40 AXIAL FLUX DIFFERENCE (% Delta I)

PrInted August 1 0, 201 1 at 8:59

RO Admin Job Performance Measure B Facility: Vogtle Task No: V-LO-TA-27003 Task

Title:

Ke Determination for Shutdown Banks withdrawn JPM No: V-NRC-JP-14005-HL17 K/A

Reference:

G2.1 .25 RO 3.9 SRO 4.2 Examinee:

NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Perlormance Actual Per1ormance Classroom Simulator Plant Read to the examinee:

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

Initial Conditions: The crew is performing a reactor startup following a trip from 100% power, steady state conditions.

Initiating Cue: Using the data below, the SS has directed you to Determine Keff for withdrawal of the Shutdown Banks using 14005-1.

Reactor Trip occurred 35 hours4.050926e-4 days 0.00972 hours 5.787037e-5 weeks 1.33175e-5 months ago:

Current Plant Conditions The following values are from Rx Engineering Boron Concentration 1400 ppm Cycle Burnup 1250 MWD/MTU Tavg 557°F Axial Offset Reactivity Correction 0 pcm All rods are inserted Boron-free Xenon plus Samarium Worth 2350 pcm ECP Boron Concentration 1400 ppm ECC Control Rod Position 120 steps CBD

Task Standard: KEFF calculated with the shutdown banks withdrawn..

Required Materials: 1. 14005-1, Shutdown Margin And KEFF Calculations Ver 27.0

2. PTDB Tab 1.0 for Cycle 17 General

References:

None Time Critical Task: No Validation Time: 15 minutes 2

Performance Information Critical steps denoted with an asterisk 1 4005-1 Data Sheet 3 selected.

Standard: Candidate selects Data Sheet 3.

Comment:

Sheet 1 of Data Sheet 3 completed.

Standard: Candidate completes Sheet 1 as indicated on KEY from plant conditions given.

Comment:

0

Sheet 2 of Data Sheet 3 completed.

Standard: Candidate completes Sheet 2 using the PTDB as indicated on KEY.

Step J.1 obtained from Table 1 .5.4-Ti BOL value.

Step J.2 obtained from Table 1 .5.1-T2 at CBD =120.

Step J.3 obtained from plant conditions.

Step J.4 completed from J.i, J.2, J.3 and math performed.

Step J.5 completed from J.4 and math performed.

Comment:

Terminating cue: Candidate returns cue sheet and completed Data sheet 3.

3

KEY DATA SHEET 3 Sheet 1 of 2 KEFF WITH SHUTDOWN BANKS WITHDRAWN G. CONDITIONS PRIOR TO ENTERING MODE 3 (SUBCRITICALITY)

G.1 Mode 3 declared Date Current dat..S.3Tours Time ..

G .2 Cycle Burnup I 250 MWD/MTU (from Reactor Engineering)

G.3 Power Level 100 %

H. NTROJEQTED CONpITION (circle one)

H.1 Date N/A Time N/A (If this Keff is being calculated for projected conditions, then enter the projected time.)

H.2 Core Average Temperature 557 +/-1 °F H.3 Length of Shutdown 35 hours4.050926e-4 days 0.00972 hours 5.787037e-5 weeks 1.33175e-5 months H.4 Estimated Critical Boron Concentration (ECC) at (H.3) hours after Mode 3 entry 1400 ppm H.5 Estimated Critical Position (ECP) at (H.3) hours after Mode 3 entry CBC 228 CBD 120 0

4

KEY

. J. KEFF CALCULATION DATA SHEET 3 Sheet2of2 NOTE For all calculations, record the ABSOLUTE VALUES of the reactivity values obtained from the PTDB.

J.1 Cumulative Control Rod Worth for D+C+B+A Configuration at HZP and Burnup (G.2) (PTDB TAB 1.5.4-Ti) +3039 pcm J.2 Integral Rod Worth BOL, MOL or EOL at ECP (H.5) and Burnup (G.2) [If the Length of Shutdown (H.3) is less than 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months OR greater than 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , then USE HZP, HFP-Eq-Xe PTDB TAB 1.5.1 -T2, T5, or T8. If the Length of Shutdown (H.3) is between 4 and 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , then USE HZP, HZP-Peak-Xe PTDB TAB 1.5.1 -T3, T6, or T9.] + 366 pcm J.3 Axial Offset Reactivity Correction (From Reactor

) Engineering) +O_pcm J.4 Shutdown Reactivity:

(J.1) (J.2) (J.3) =

3039- 366- 0 = (+) 2673 pcm J.5 Keff: 1.0000/ [1.0000 + ((J.4)/1 00,000)] =

1.0000/ [1.0000 + (2673 /100,000)1 = + 0.974 ACCEPTANCE CRITERIA Keff (J.5) shall be less than +0.99.

EYES LINO Completed By: SIGNA TURE CURRENT DATE/TiME Signature Date/Time Verified By:

Signature Date/Time 5

Verification of Completion Job Performance Measure No. V-NRC-J P-i 4005-H Li 7 Examinees Name:

Examiners Name:

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:________________________________

Response

Result: Satisfactory/Unsatisfactory Examiners signature and date:

6

Initial Conditions: The crew is performing a reactor startup following a trip from 100% power, steady state conditions.

Initiating Cue: Using the data below, the SS has directed you to Determine Kett for withdrawal of the Shutdown Banks using 14005-1.

Reactor Trip occurred 35 hours4.050926e-4 days 0.00972 hours 5.787037e-5 weeks 1.33175e-5 months ago.

Current Plant conditions:

Boron Concentration 1400 ppm Tavg 557°F Current Rod Height All rods are inserted ECP Boron Concentration 1400 ppm ECC Control Rod Position 120 steps CBD The following values are from Rx Engineering:

Cycle Burnup 1250 MWD/MTU Axial Offset Reactivity Correction 0 pcm Boron-free Xenon plus Samarium Worth 2350 pcm

SRO Admin Job Performance Measure B Facility: Vogtle Task No: V-LO-TA-27003 Task

Title:

Keff Determination for Shutdown Banks withdrawn JPM No: V-NRC-JP-14005-HL17 K/A

Reference:

G2.1 .25 RO 3.9 SRO 4.2 Examinee: NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance Actual Pertormance Classroom Simulator Plant Read to the examinee:

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

Initial Conditions: The crew is performing a reactor startup following a trip from 100% power, steady state conditions.

Initiating Cue: Using the data below, the SS has directed you to Determine Keff for withdrawal of the Shutdown Banks using 14005-1.

Reactor Trip occurred 35 hours4.050926e-4 days 0.00972 hours 5.787037e-5 weeks 1.33175e-5 months ago:

Current Plant Conditions The following values are from Rx Engineering Boron Concentration 1400 ppm Cycle Burnup 1250 MWD/MTU Tavg 557°F Axial Offset Reactivity Correction 0 pcm All rods are inserted Boron-free Xenon plus Samarium Worth 2350 pcm ECP Boron Concentration 1400 ppm ECC Control Rod Position 120 steps CBD

Task Standard: KEFF calculated with the shutdown banks withdrawn..

Required Materials: 1. 14005-1, Shutdown Margin And KEFF Calculations Ver27.0

2. PTDB Tab 1.0 for Cycle 17 General

References:

None Time Critical Task: No Validation Time: 15 minutes 2

Performance Information Critical steps denoted with an asterisk 14005-1 Data Sheet 3 selected.

Standard: Candidate selects Data Sheet 3.

Comment:

Sheet 1 of Data Sheet 3 completed.

Standard: Candidate completes Sheet 1 as indicated on KEY from plant conditions given.

Comment:

0 Sheet 2 of Data Sheet 3 completed.

Standard: Candidate completes Sheet 2 using the PTDB as indicated on KEY.

Step J.1 obtained from Table 1 .5.4-Ti BOL value.

Step J.2 obtained from Table 1 .5.1-T2 at CBD =120.

Step J.3 obtained from plant conditions.

Step J.4 completed from J.i, J.2, J.3 and math performed.

Step J.5 completed from J.4 and math performed.

Comment:

Terminating cue: Candidate returns cue sheet and completed Data sheet 3.

3

KEY DATA SHEET 3 Sheet 1 of 2 O KEFF WITH SHUTDOWN BANKS WITHDRAWN G. CONDITIONS PRIOR TO ENTERING MODE 3 (SUBCRITICALITY)

G 1

. Mode 3 declared Date Time current time G.2 Cycle Burnup 1250 MWD/MTU (from Reactor Engineering)

G.3 Power Level 100 %

H. NTRO[ECTED CONDITlO (circle one)

Hi Date N/A Time N/A (If this Keff is being calculated for projected conditions, then enter the projected time.)

H.2 Core Average Temperature 557 +/-1 °F H.3 Length of Shutdown 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months H.4 Estimated Critical Boron Concentration (ECC) at (H.3) hours after Mode 3 entry 1400Z ppm H.5 Estimated Critical Position (ECP) at (H.3) hours after Mode 3 entry CBC228_CBDJ2p 4

KEY DATA SHEET 3 Sheet2of2 J. KEFF CALCULATION NOTE For all calculations, record the ABSOLUTE VALUES of the reactivity values obtained from the PTDB.

J.1 Cumulative Control Rod Worth for D+C+B+A Configuration at HZP and Burnup (G.2) (PTDB TAB 1 .5.4-Ti) +339 pcm J.2 Integral Rod Worth BOL, MOL or EOL at ECP (H.5) and Burnup (G.2) [If the Length of Shutdown (H.3) is less than 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months OR greater than 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , then USE HZP, HFP-Eq-Xe PTDB TAB 1.5.1-T2, T5, or T8. If the Length of Shutdown (H.3) is between 4 and i2 hours, then USE HZP, HZP-Peak-Xe PTDB TAB i.5.i-T3, T6, orT9.] + 366 pcm J.3 Axial Offset Reactivity Correction (From Reactor Engineering) +Q__pcm J.4 Shutdown Reactivity:

(J.i) (J.2) (J.3) =

3O39 366 0 = (+)__2673pcm J.5 Keff: 1.0000 / [1.0000 + ((J.4)/i 00,000)] =

1.0000 / [1.0000 + (2672, /100,000)] = + 0.974 ACCEPTANCE CRITERIA Keff (J.5) shall be less than +0.99.

EYES LINO Completed By: SiGNATURE CURRENT DATEiTIME Signature Date/Time Verified By:

Signature Date/Ti me 5

Verification of Completion Job Performance Measure No. V-NRC-JP-14005-HL17 Examinees Name:

Examiners Name:

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:________________________________

Response

Result: Satisfactory/Unsatisfactory Examiners signature and date:

6

Initial Conditions: The crew is performing a reactor startup following a trip from 100% power, steady state conditions.

Initiating Cue: Using the data below, the SS has directed you to Determine K for withdrawal of the Shutdown Banks using 14005-1.

Reactor Trip occurred 35 hours4.050926e-4 days 0.00972 hours 5.787037e-5 weeks 1.33175e-5 months ago.

Current Plant conditions:

Boron Concentration 1400 ppm Tavg 557°F Current Rod Height All rods are inserted ECP Boron Concentration 1400 ppm ECC Control Rod Position 120 steps CBD The following values are from Rx Engineering:

Cycle Burnup 1250 MWD/MTU Axial Offset Reactivity Correction 0 pcm Boron-free Xenon plus Samarium Worth 2350 pcm

RO Admin Job Performance Measure C Facility: Vogtle Task No: V-LO-TA-63004 Task

Title:

Determine Tagging Requirements JPM No: V-NRC-JP-NMP-AD-003-HL17 K/A

Reference:

G2.2.13 RO 4.1 SRO 4.3 Examinee: NRC Examiner:

Facility Evaluator: Date:_______________

Method of testing:

Simulated Performance Actual Performance Classroom Read to the examinee:

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

Initial Conditions: Unit 1 is at 100% Power. A planned outage for Containment Spray Pump (CSP) Train A is required to replace the pump seals.

All electrical components and associated handswitches requiring Tagout for the CSP A work will be tagged under another referenced Tagout.

All pump motor cooling water required for Tagout for the CSP A work will be tagged under another referenced Tagout.

Initiating Cue: Determine the appropriate boundary points and required positions of components to isolate the fluid boundary and drain CSP A, 1-1 206-P6-OO1.

1

Task Standard: Boundary points for isolation and drains for CSP A are determined.

Required Materials: Provide following references to candidate NMP-AD-003, Equipment Clearance and Tagging Ver. 14.0 NMP-AD-003-002 Tagout Standards Ver. 7.0 P&ID 1X4DB131 Ver. 35.0 Provide to candidate if requested.

1 X4DROO3 Ver. 1.0 Fill and Vent Diagram For Containment Spray System General

References:

none Time Critical Task: No Validation Time: 30 minutes 2

Performance Information Critical steps denoted with an asterisk References NMP-AD-003, NMP-AD-003-002, and P&ID 1 X4DB1 31.

Standard: Candidate uses references.

Comment:

Determines the following components and positions are required to isolate and drain fluid boundary for CSP A.

Standard:

Candidate correctly identifies the listed points to tag out CSP as listed below.

The ones in BOLD are the critical points.

The description should describe valve function.

The description listed is expected description.

The lineup description is listed in parentheses.

The additional drains may be added but are not required.

3

Component Description Required Position Number 1-HV-9001A CSP A Pump Discharge Isolation Valve CLOSED (CNMT SPRAY ISO) 1-HV-9017A CSP A RWST Suction Isolation Valve CLOSED (CNMT SPRAY PUMP A RWST SUCT ISO VLV) 1-HV-9003A CSP A CNMT Sump Suction Isolation CLOSED Valve (CNMT SPRAY PUMP A CNMT SUMP SUCT ORC) 1 -1 206-U4-1 1 5 1 HV-9003A Bypass Line Isolation Valve CLOSED (CNMT SPRAY PUMP TRAIN A SUMP SUPPLY HV 9003A BYP) 1-1206-U4-006 CSP A RWST Test line Isolation Valve CLOSED Or (CNMT SPRAY PUMP TRAIN A TEST FLOWPATH ISOLATION)

Locked Closed 1-1206-U4-034 CSP A Discharge to Eductor Isolation CLOSED Valve Or Locked Closed (CNMT SPRAY SPRAY ADD TK DISCH ISO TO EDUCTOR 1) 1-1206-U4-109 CSP A Pump Casing Drain Valve OPEN (CNMT SPRAY PUMP TRAIN A DISCHARGE CASING DRAIN) 1-1206-U4-112 CSP A Pump Casing Drain Valve OPEN (CNMT SPRAY PUMP TRAIN A SUCTION CASING DRAIN) 1-1206-U4-108 CSP A Pump Casing Vent Valve UNFLANGE/OPEN or (CNMT SPRAY PUMP TRAIN A CASE VENT) UNCAPIOPEN 1 -1 206-X4-1 08 CSP A Header Vent Valve UNCAP/OPEN (CNMT SPRATY HEADER TRAIN A VENT) 1 -1 206-U4-002 CSP A Suction Drain Valve OPEN (CNMT SPRAY PUMP TRAIN A SUCTION FLOOR DRAIN ISO) 1-1206-X4-005 CSP A RWST Supply Drain Valve UNCAP/OPEN (CNMT SPRAY PUMP TRAIN A RWST SUPPLY DRN TO FLOOR) 1-1206-X4-009 CSP A Suction Vent Valve OPEN (CNMT SPRAY PUMP TRAIN A SUCTION PRESS TEST ROOT) 4

1-1 206-X4-026 CSP A Discharge Drain Valve UNCAP/OPEN (CNMT SPRAY PUMP TRAIN A DISCHARGE LINE DRAIN) 1-1206-X4-013 CSP A Discharge to Eductor Drain Valve UNCAP/OPEN (CNMT SPRAY PUMP TRAIN A DISCHARGE TO EDUCTOR DRN) 1-1 206-X4-035 CSP A Header Drain Valve UNCAP/OPEN (CNMT SPRAY HEADER TRAIN A DRAIN) 1-1 206-U4-O1 1 CSP A Discharge Flush Conn Isolation UNFLANGE/OPEN or CLOSED (CNMT SPRAY PUMP TRAIN A DISCH FLUSH CONN ISO)

Comment:

Terminating cue: Candidate informs SS of completion of the identified points to Tagout Containment Spray Pump A or returns the cue sheet.

5

Verification of Completion Job Performance Measure No. V-N RC-J P-NMP-AD-003-HL1 7 Examinees Name:

Examiners Name:

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:_______________________

Response

Result: Satisfactory/Unsatisfactory Examiners signature and date:

Initial Conditions: Unit 1 is at 100% Power. A planned outage for Containment Spray Pump (CSP) Train A is required to replace the pump seals.

All electrical components and associated handswitches requiring Tagout for the CSP A work will be tagged under another referenced Tagout.

All pump motor cooling water required for Tagout for the CSP A work will be tagged under another referenced Tagout.

Initiating Cue: Determine the appropriate boundary points and required positions of components to isolate the fluid boundary and drain CSP A, 1-1 206-P6-OO1.

Component Number Description Required Position

0 uo!!sod peilnbeH uoiidijosea iaqwn iueuodwo

SRO Admin Job Performance Measure C Facility: Vogtle Task No: V-LO-TA-63004 Task

Title:

Determine Tagging Requirements JPM No: V-NRC-JP-NMP-AD-003-HL17 KlA

Reference:

G2.2.13 R04.1 SRQ4.3 Examinee: NRC Examiner:

Facility Evaluator: Date:_______________

Method of testing:

Simulated Pertormance Actual Periormance Classroom Note to Examiner: There is a second cue sheet on Page 7.

Read to the examinee:

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

Initial Conditions: Unit 1 is at 100% Power. A planned outage for Containment Spray Pump (CSP) Train A is required to replace the pump seals.

All electrical components and associated handswitches requiring Tagout for the CSP A work will be tagged under another referenced Tagout.

All pump motor cooling water required for Tagout for the CSP A work will be tagged under another referenced Tagout.

Initiating Cue: Determine the appropriate boundary points and required positions of components to isolate the fluid boundary and drain CSP A, 1-1 206-P6-OO1.

Task Standard: Boundary points for isolation and drains for CSP A are determined. LCO, required actions, and completion times are determined.

Required Materials: Provide following references to candidate NMP-AD-003, Equipment Clearance and Tagging Ver. 14.0 NMP-AD-003-002 Tagout Standards Ver. 7.0 P&ID 1X4DB131 Ver. 35.0 Tech Specs Provide to candidate if requested.

1 X4DROO3 Ver. 1.0 Fill and Vent Diagram For Containment Spray System General

References:

none Time Critical Task: No Validation Time: 30 minutes 2

Performance Information Critical steps denoted with an asterisk References NMP-AD-003, NMP-AD-003-002, and P&ID 1 X4DB1 31.

Standard: Candidate uses references.

Comment:

Determines the following components and positions are required to isolate and drain fluid boundary for CSP A.

Standard:

Candidate correctly identifies the listed points to tag out CSP as listed below.

The ones in BOLD are the critical points.

The description should describe valve function.

The description listed is expected description.

The lineup description is listed in parentheses.

The additional drains may be added but are not required.

3

Component Description Required Position Number 1-HV-9001A CSP A Pump Discharge Isolation Valve CLOSED (CNMT SPRAY ISO) 1-HV-9017A CSP A RWST Suction Isolation Valve CLOSED (CNMT SPRAY PUMP A RWST SUCT ISO VLV) 1-HV-9003A CSP A CNMT Sump Suction Isolation CLOSED Valve (CNMT SPRAY PUMP A CNMT SUMP SUCT ORC) 1 -1 206-U4-1 1 5 1 HV-9003A Bypass Line Isolation Valve CLOSED (CNMT SPRAY PUMP TRAIN A SUMP SUPPLY HV 9003A BYP) 1 -1 206-U4-006 CSP A RWST Test line Isolation Valve CLOSED Or (CNMT SPRAY PUMP TRAIN A TEST FLOWPATH ISOLATION)

Locked Closed 1-1206-U4-034 CSP A Discharge to Eductor Isolation CLOSED Valve Or Locked Closed (CNMT SPRAY SPRAY ADD TK DISCH ISO TO EDUCTOR 1) 1-1206-U4-109 CSP A Pump Casing Drain Valve OPEN (CNMT SPRAY PUMP TRAIN A DISCHARGE CASING DRAIN) 1-1206-U4-112 CSP A Pump Casing Drain Valve OPEN (CNMT SPRAY PUMP TRAIN A SUCTION CASING DRAIN) 1-1206-U4-108 CSP A Pump Casing Vent Valve UNFLANGE/OPEN or (CNMT SPRAY PUMP TRAIN A CASE VENT) UNCAP/OPEN 1-1206-X4-108 CSP A Header Vent Valve UNCAP/OPEN (CNMT SPRATY HEADER TRAIN A VENT) 1 -1 206-U4-002 CSP A Suction Drain Valve OPEN (CNMT SPRAY PUMP TRAIN A SUCTION FLOOR DRAIN ISO) 1-1 206-X4-005 CSP A RWST Supply Drain Valve UNCAP/OPEN (CNMT SPRAY PUMP TRAIN A RWST SUPPLY DRN TO FLOOR) 1-1 206-X4-009 CSP A Suction Vent Valve OPEN (CNMT SPRAY PUMP TRAIN A SUCTION PRESS TEST ROOT) 4

1-1 206-X4-026 CSP A Discharge Drain Valve UNCAP/OPEN (CNMT SPRAY PUMP TRAIN A DISCHARGE LINE DRAIN) 1-1 206-X4-O1 3 CSP A Discharge to Eductor Drain Valve UNCAP/OPEN (CNMT SPRAY PUMP TRAIN A DISCHARGE TO EDUCTOR DRN) 1-1 206-X4-035 CSP A Header Drain Valve UNCAP/OPEN (CNMT SPRAY HEADER TRAIN A DRAIN) 1-1 206-U4-O1 1 CSP A Discharge Flush Conn Isolation UNFLANGE/OPEN or CLOSED (CNMT SPRAY PUMP TRAIN A DISCH FLUSH CONN ISO)

Comment:

Terminating cue: Candidate informs SS of completion of the identified points to Tagout Containment Spray Pump A or returns the cue sheet.

When Candidate returns first cue sheet give the candidate the cue sheet on Page 7.

Initial Conditions: Unit 1 is at 100% Power. A planned outage for Containment Spray Pump (CSP) Train A is required to replace the pump seals.

All electrical components and associated handswitches requiring Tagout for the CSP A work will be tagged under another referenced Tagout.

All pump motor cooling water required for Tagout for the CSP A work will be tagged under another referenced Tagout.

Initiating Cue: You are the Shift Supervisor authorizing the tagouts for this outage. Determine the Tech Spec LCO(s), required actions, and completion times (if any) that result from authorizing this work.

5

Candidate determines the Tech Spec LCO(s), required actions, and completion times.

Standard: Candidate determines the following (bolded items are critical):

LCO 3.6.6 Two containment spray trains and two containment cooling trains shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One containment spray A.1 Restore containment 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months s*

train inoperable. spray train to OPERABLE status. AND 6 days from discovery of failure to meet the

. LCO*

B. One containment B.1 Restore containment 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months cooling train inoperable, cooling train to OPERABLE status. AND 6 days from discovery of failure to meetthe LCO C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time notmet. AND C.2 Be in MODE 5. 84 hours9.722222e-4 days 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months For the VEGP Unit 2 June 23, 2008 entry into Technical Specification 3.6.6, the Containment Spray Pump B may be inoperable for a period not to exceed 7 days.

6

Initial Conditions: Unit us at 100% Power. A planned outage for Containment Spray Pump (CSP) Train A is required to replace the pump seals.

All electrical components and associated handswitches requiring Tagout for the CSP A work will be tagged under another referenced Tagout.

All pump motor cooling water required for Tagout for the CSP A work will be tagged under another referenced Tagout.

Initiating Cue: You are the Shift Supervisor authorizing the tagouts for this outage. Determine the Tech Spec LCO(s), required actions, and completion times (if any) that result from authorizing this work.

7

Verification of Completion Job Performance Measure No. V-NRC-JP-NMP-AD-003-HL1 7 Examinees Name:

Examiners Name:

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:_______________________

Response

Result: Satisfactory/Unsatisfactory Examiners signature and date:

Initial Conditions: Unit 1 is at 100% Power. A planned outage for Containment Spray Pump (CSP) Train A is required to replace the pump seals.

All electrical components and associated handswitches requiring Tagout for the CSP A work will be tagged under another referenced Tagout.

All pump motor cooling water required for Tagout for the CSP A work will be tagged under another referenced Tagout.

Initiating Cue: Determine the appropriate boundary points and required positions of components to isolate the fluid boundary and drain CSP A, 11206-P6-001.

Component Number Description Required Position

UOI!SOd PGJ!flbeH uo!ld!Josea ieqwn pieuodwo 0

RO Job Performance Measure D Facility: Vogtle TaskNo: N/A Task

Title:

Determine Posting Requirements JPM No: V-NRC-JP-00930-HL17 K/A

Reference:

K/A: G2.3.13 RO 3.4 SRO 38 Examinee: NRC Examiner:_________

Facility Evaluator:

Method of testing:

Simulated Performance Actual Perlormance Classroom Simulator Plant Read to the examinee:

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

Initial Conditions: A line is plugged with CVCS demin resin in Aux Bldg RA-28.

The resin plug is estimated to be 10 feet long. The dose rate at the room entrance is 500 mr/hr which is 4 feet from the line.

See attached room map.

Initiating Cue: Determine the appropriate posting required at the entry to the room.

Task Standard: Determine proper HP posting for the room.

Required Materials: 1. HP survey map

2. Procedure 00930-C, Radiation And Containment Control Ver 26.0

3. Tech Specs General

References:

None Time Critical Task: No Validation Time: 10 minutes 2

Performance Information Critical steps denoted with an asterisk Calculate the dose at one foot.

As distance (4ft) is less than half of source length (1 Oft),

Use line source equation D =l 1

2 where l = closest source intensity 12= farthest source intensity 1 = closest distance D

2 = farthest distance D

Standard: Candidate calculates l = 500 mr/hr x (4) = 2000 mr/hr 1

2000 mr/hr at one foot.

Comment:

Determine posting requirement Standard: Candidate determines Locked High Radiation Area based on dose at one foot greater than 1000 mr/hr.

Comment:

Terminating cue: Student returns initiating cue sheet 3

Verification of Completion Job Performance Measure No. V-NRC-JP-00930-HL1 7 Examinees Name:

Examiners Name:

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners signature and date:

4

Initial Conditions: Initial Conditions: A line is plugged with CVCS demin resin in Aux Bldg RA.28. The resin plug is estimated to be 10 feet long.

The dose rate at the room entrance is 500 mr/hr which is 4 feet from the line.

See attached room map.

Initiating Cue: Determine the appropriate posting required at the entry to the room.

e 1d U!S>j (8vxvI) NIVHG G]1 G]XI1/\i SDAD AH]11VD IA1VA

Approved By Procedure Number Rev C R Dedrickson Vogtle Electric Generating Plant j 00930-C 26 Date Approved Page Number 08/05/2009 RADIATION AND CONTAMINATION CONTROL 1 of 28 PRB REVIEW REQUIRED RADIATION AND CONTAMINATION CONTROL PROCEDURE USAGE REQUIREMENTS- SECTIONS Continuous Use: Procedure must be open and readily available at the work location. Follow procedure step by step unless otherwise directed.

Reference Use: Procedure or applicable section(s) available at the work location for ready reference by person performing steps.

Information Use: Available on plant site for reference as needed. ALL Printed January 12, 2012 at 10:42

Approved By *

Procedure Number Rev C R Dedrickson VOgtIe Electric Generating Plant 00930-C 26 Date Approved Page Number 08/05/2009 RADiATION AND CONTAMINATION CONTROL 2 of 28 1 .0 PURPOSE(1 984301 253) (1985303534)

This procedure establishes requirements and responsibilities for monitoring and controlling exposure to radiation and contamination. It includes criteria for Radiation Controlled Areas, the Radiation Work Permit (RWP) system, sampling and surveys, shielding, and the Self Monitoring process as follows:

4.0 REQUiREMENTS 5.0 PROCEDURE 5.1 POSTiNG 5.2 RADIATiON WORK PERMIT 5.3 CONTAMiNATION CONTROLS 5.4 PERSONNEL MONITORING 5.6 SURVEYS AND SAMPLING 5.7 SHIELDING 5.8 SELF MONITORING 2.0 DEFINITiONS 2.1 AiRBORNE RADIOACTIVITY AREA (1 985306088) (1993327366)

A room, enclosure, or area in which airborne radioactive materials, composed wholly or partly of licensed material, exist in concentrations:

a. To such a degree that an individual present in the area without respiratory protection equipment could exceed, during the hours an individual is present in a week, an intake of 0.6 percent of the annual limit on intake (ALl) or 12 Derived Air Concentrations (DAC)-hours.

OR

b. An area should be considered an Airborne Radioactivity Area when the airborne activity reaches 0.3 DACs for isotopes which have a classification other than submersion, and 1 00% of the DAC limits for isotopes which have a classification of submersion. DAC limits are specified in 1 OCFR2O Appendix B, Table I, Column 3.

2.2 ANNUAL LiMIT ON INTAKE (ALl)

The derived limit for the amount of radioactive material taken into the body of an adult worker by inhalation or ingestion in a year. ALl values for intake by ingestion and by inhalation of selected radionuclides are given in 1 OCFR2O, Appendix B, Table 1, Columns 1 and 2. (1993327366)

Printed January 12, 2012 at 10:42

Approved By V J Procedure Number Rev C R Dedrickson -

Vogtle EIectricqeneratIØg Plant jQO93O-C 26 Date Approved Page Number 08/05/2009 1 RADIATION AND CONTAMINATION CONTROL 3 of 28 2.3 CONTAMINATED AREAS, MATERIALS AND EQUIPMENT Any area where loose surface contamination exceeds the following limits shall be posted as a Contaminated Area. Items exceeding the following measurements will be posted as radioactive material and handled in accordance with Procedure 00960-C, Control of Radioactive Material. (1984301315) 2.3.1 Fixed Surface Radioactive Contamination (contamination embedded in material surface)

Beta-gamma 1 00 cpm above background as measured with an HP-21 0 probe or equivalent or as specified by HP procedures for other instruments.

Alpha 50 cpm above background as measured with an alpha survey meter.

2.3.2 Loose Surface Radioactive Contamination (removable contamination)

Beta-gamma 1000 dpm/100 cm 2 Alpha 20 dpm/100 cm 2 2.4 CONTROLLED AREA Any area outside of the restricted area but inside the site boundary, access to which can be limited for any reason.

2.5 DERIVED AIR CONCENTRATION (DAC)

The concentration of a given radionuclide in air which, if breathed by the reference man for a working year of 2000 hours0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months , results in an intake of one ALl.

DAC values are given in 10CFR2O, Appendix B, Table 1, Column 3.

(1993327366) 2.6 HIGH RADIATION AREA Any area, accessible to individuals, in which radiation levels from radiation sources external to the body could result in an individual receiving a dose equivalent in excess of 100 mrem/hr at 30 cm (12 inches) from the radiation source or from any surface which the radiation penetrates. (2000341553)

(1985306089)

Printed January 12, 2012 at 10:42

Approved By Procedure Number Rev C R Dedrickson Vogtle Electric Generating Plant 00930-C 26 Date Approved Page Number 08/05/2009 RADiATION AND CONTAMINATION CONTROL 4 f 28 2.7 HOT PARTICLES Hot particles are discrete radioactive particles that are characterized by intense emissions of beta particles, X-rays and gamma rays. For the purpose of hot particle control, a hot particle will be defined as an extremely localized count rate (RM-14 with HP-210 probe, or equivalent) of 250,000 cpm or more emanating from a discrete particle.

2.8 HOT PARTICLE BUFFER AREA (HPBA)

An area, free of hot particles, surrounding a Hot Particle Control Area (HPCA).

Hot particles are not expected in this area; however, this area is surveyed frequently to determine that hot particles are not transported out of the HPCA.

2.9 HOT PARTICLE CONTROL AREA A work area where hot particles are known to be present. An HPCA may be a room, a roped off area or a containment used to confine hot particle contamination.

2.10 HOT SPOTS Components or items having localized contact readings in excess of 100 mrem/hr and more than 5 times the general area dose rates.

2.11 LOCKED HIGH RADIATION AREA Any area accessible to individuals, in which radiation levels external to the body could result in an individual receiving a dose equivalent equal to or in excess of 1 000 mrem/hr at 30 cm (1 2 inches) from the radiation source or from any surface which the radiation penetrates. (2000341553) 2i2 RADIATION AREA Any area, accessible to individuals, in which radiation levels could result in an individual receiving a dose equivalent in excess of 5 mrem/hr at 30 cm (12 inches) from the radiation source or from any surface which the radiation penetrates. (2000341 553) (1985306090) 2.13 RADIATION CONTROLLED AREA (RCA)

Any area which contains or potentially contains radiation, contamination, or radioactive materials in quantities or levels sufficient to require posting of protective measures.

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Approved By - Procedure Number Rev C R Dedrickson Vogtle Electric Genertiflg Plant 00930-C 26 Date Approved Page Number 08/05/2009 RADIATION AND CONTAMINATION CONTROL 5 of 28 2.1 4 RADIOACTIVE MATERIALS AREA A radioactive materials area is any area or room in which radioactive material is used or stored and which contains radioactive material in an amount exceeding 1 0 times the quantity of such material specified in 1 OCFR2O, Appendix C. This does not apply to materials contained within process equipment or materials in transport that are packaged and labeled in accordance with Department of Transportation (DOT) regulations. (1 985306086) (1985306087) 2.15 RADIATION WORKER Plant personnel assigned duties inside Radiation Control Areas.

2.16 RESTRICTED AREA Any area to which access is limited by the licensee for the purpose of protection of individuals against undue risks from exposure to radiation and radioactive materials. The area inside an RCA is a restricted area. Others may be defined as needed.

2.17 SELF MONITORING Radiation and Contamination monitoring performed by qualified Radiation Workers for themselves only.

2.18 SURVEYS AND SAMPLING 2.18.1 The measurement of radiation levels, concentrations, surface area concentrations or quantities of radioactive material and the use of the results of these measurements to evaluate potential exposures and doses.

2.18.2 Survey is also an evaluation of the radiological conditions and potential hazards incident to the production, use, transfer, release, disposal, or presence of radioactive material or other sources of radiation. When appropriate, such an evaluation includes a physical survey of the location of radioactive material and measurements or calculations of levels of radiation, concentrations or quantities of radioactive material present.

2.19 VERY HIGH RADIATION AREA Any area, accessible to individuals, in which radiation levels from radiation sources external to the body could result in an individual receiving an absorbed dose in excess of 500 rads in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months at 1 meter (3 feet) from a radiation source or 1 meter from any surface that the radiation penetrates.

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Approved By . . Procedure Number Rev C R Dedrickson j Vogtle Electric Generating Plant 00930-C 26 Date Approved Page Number 08/05/2009 RADIATiON AND CONTAMINATION CONTROL 6 of 28 3.0 RESPONSiBILITIES 3.1 HEALTH PHYSICS MANAGER The Health Physics Manager is responsible for ensuring the Health Physics Section performs the following:

3. 1 1

. Reviews radiation safety incidents and approves corrective action.

3.1 .2 Establishes and maintains a radiation and contamination control program which includes appropriate procedures and instructions.

3.1 .3 Establishes and maintains a Radiation Work Permit (RWP) system to control and minimize exposure to radiation and contamination. (1984302057) 3.1 .4 Assigns HP Personnel as appropriate to the Maintenance Performance Teams.

3.1 .5 Performs and documents radiation and contamination surveys, air sampling, and analysis, and reviews plant areas to ensure that all areas with existing or potential high radiation exposure rates are properly posted and controlled.

(1985307052) 3.1 .6 Classifies, posts, barricades, and controls ingress and egress to Radiation Controlled Areas to control radiation exposure and spread of contamination.(1984301 951) (1985307052) 3.1 .7 Determines protective clothing requirements and stay times.

3.1 .8 Requests and verifies installation of shielding.

3.1 .9 Supervises and monitors decontamination of personnel, equipment and facilities.

3. 1 1 0

. Establishes controls for use and disposition of contaminated materials and equipment.

3.1 .1 1 Performs maintenance, calibrations, and surveillances on assigned HP instrumentation and equipment.

3.1.12 Performs trend analysis on radiation and contamination exposure controls.

Recommends actions necessary to correct adverse trends. (1999340604)

(2000340662) 3.1.13 Maintains control and limitations for Self Monitoring Program.

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Approved By Procedure Number Rev C R Dedrickson ) Vogtle Electric Generating Plant 00930-C 26 Date Approved Page Number 08/05/2009 RADiATION AND CONTAMINATION CONTROL 7 of 28 S

3.1 .14 Ensures the Plant Training and Emergency Preparedness Department is notified of changes in the use of protective clothing so that General Employee Training remains current.

3.1 .15 Actively participates in the Training Advisory Committee to maintain all training current and relative to plant demands.

3.2 PLANT SUPERVISION 3.2.1 Ensure that supervised personnel comply with rules, regulations and procedures associated with radiation safety and comply with RWPs. (1984301983) 3.2.2 Request RWPs to support work in Radiation Controlled Areas if not already requested by the Performance Team work planner.

3.2.3 Notify HP promptly when radiological problems occur and interface with HP to resolve deficiencies.

3.2.4 Ensure that the work area has been cleaned up and restored to normal conditions after work evolution is completed.

3.2.5 Ensure appropriate individuals receive Self Monitoring training.

3.2.6 Ensure individuals complete Job Performance Measures (JPMs) sign off criteria.

3.3 PLANT PERSONNEL 3.3.1 Practice radiation safety and maintain their radiation exposure As Low As Reasonably Achievable (ALARA).

3.3.2 Comply with all radiation protection rules, regulations and procedures.

Supervisors are responsible for ensuring their employees follow all radiation protection rules, regulations and procedures.

3.3.3 Read and comply with RWP requirements whenever their duties require the use ofan RWP.

3.3.4 Individuals are responsible for surveying themselves for contamination when crossing a local control point or the main access control point. (1984301969) 3.3.5 if contamination is found, the individual notifies HP Personnel for decontamination. (1984301969)

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Procedure Number Rev C.R.Dedrickson Vogtle Electric Generating Plant 00930-C 26 Page Number 08/05/2009 RADiATION AND CONTAMINATION CONTROL 28 3.3.6 Know their current exposure status.

3.3.7 Perform Self Monitoring within established procedures and limits, if qualified.

3.4 PLANT TRAINING AND EMERGENCY PREPAREDNESS MANAGER The Plant Training and Emergency Preparedness Manager is responsible for ensuring the Training Department performs the following:

3.4.1 Establishes and maintains a Self Monitoring training program.

3.4.2 Maintains records for personnel who have completed Self Monitoring training.

3.4.3 Keeping other plant sections informed on personnel who are Self Monitoring qualified.

4.0 REQUiREMENTS 4.1 PERSONNEL REQUIREMENTS 4.1 .1 All personnel shall receive indoctrination and training in radiation and contamination control requirements in accordance with approved plant procedures, commensurate with their work assignments.

4.1 .2 HP Personnel shall receive additional training in radiation safety in accordance with approved plant procedures.

4.1 .3 Prior to performing Self Monitoring personnel will receive specific training.

4.1 .4 Personnel performing Self Monitoring must have specific JPMs signed off to be qualified to perform Self Monitoring tasks.

4.2 ENTRY/EXiT (1984301955) (1985305100) 4.2.1 Personnel will normally access and exit RCAs through the designated access control points determined by Health Physics.

4.2.2 Personnel access to areas of unknown radiological conditions will normally be restricted until survey data is established by Health Physics personnel.

4.2.3 Entrance and access to a High Radiation Area shall be controlled by a specific RWP. (1985307052) 4.2.4 Access to containment buildings is controlled by HP and areas are surveyed to establish allowable working periods. Telemetry may be used in place of stay times.

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Approved By Procedure Number Rev C R Dedrickson Vogtle Electric Generating Plant 00930-C 26 Date Approved Page Number 08/05/2009 RADIATION AND CONTAMINATION CONTROL 9 of 28 4.2.5 Any individual, or group of individuals, permitted to enter a High Radiation Area shall be continuously provided with or accompanied by one or more of the following: (1 985306646) (1 985306649) (1 995329954) (1995329955)

a. Radiation monitoring device(s) which continuously indicates the radiation dose rate in the area.

b. Radiation monitoring device(s) which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas is permitted after the dose rate level has been made known to personnel.

C. An individual qualified to implement Health Physics procedures, equipped with a radiation dose rate monitoring device and who will be responsible for providing positive control over activities within the area while performing periodic radiation surveillance as specified by the Health Physics Manager, or designee, in the RWP.

NOTE If an escort is required, only Health Physics Personnel are qualified to perform escort duties in Locked High Radiation Areas.

4.2.6 In addition to the requirements for a High Radiation Area, access of personnel into a Locked High Radiation Area (> 1 000 mrem/h) shall be under an approved, specific RWP, that shall specify the dose rate levels in the immediate work areas and the maximum allowable stay times for individuals in those areas.

4.2.6.1 Specific RWPs may govern entry into many Locked High Radiation Areas, therefore, ALARA briefings will clarify RWP requirements for dose rate specifications in the immediate work area.

4.2.6.2 In lieu of the stay time specification of the RWP, direct or remote (such as closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities being performed within the area.

4.2.7 In addition to the requirements for a Locked High Radiation Area, access of personnel into a Very High Radiation Area must receive prior written approval from the Health Physics Manager, or designee.

4.2.7.1 A Health Physics escort is required for entry.

4.2.7.2 In the event of a declared emergency the Emergency Director may grant access to a Very High Radiation Area.

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Approved By Procedure Number Rev C R Dedrickson VogUe Electric Generating Plant 00930-C 26 Date Approved Page Number 08/05/2009 RADIATION AND CONTAMINATION CONTROL io of 28 5.0 PROCEDURE 5.1 POSTiNG The following precautions and limitations apply to postings used to identify or delineate Radiation Controlled Areas:

5.1 .1 Radiological warning signs, ropes or barricades shall be placed in such a manner as to alert personnel of the hazard upon approach.

5.1.1.1 Removal or repositioning of signs, ropes or barriers is prohibited unless authorized by Health Physics personnel.

5.1 .1 .2 Signs, ropes, and barricades may be placed in areas of low or no, radiological hazard, if appropriate, for the purpose of access control. (1999340604)

(2000340661) 5.1 .1 .3 Radiological posting signs shall have a yellow background with a purple, magenta, or black radiation symbol.

5.1 .1 .4 Ropes and barrier tape used for radiological warnings shall be yellow and magenta. The exception to the required color is when chain is used as a barrier, provided the chain is identified as a radiological barrier.

5.1 .1 .5 Signs, ropes, and other material of the conventional yellow and magenta color shall not be used for any purpose other than radiological control marking, unless approved by HP Supervision and controlled by Procedure 00960-C.

5.1.1.6 To the extent practicable, measured radiation levels and locations of sources should be posted at the entry into any radiation or high radiation area.

5.1.1.7 Use of handwritten signs shall be minimized.

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Procedure Number Rev C.R.Dedrickson Vogtle Electric Generating Plant 00930-C 26 Date Approved Page Number 08/05/2009 RADIATION AND CONTAMINATION CONTROL i i of 28 5.1 .2 Radiation Controlled Area 5.1 .2.1 Each Radiation Controlled Area shall have all personnel access points and doors posted with a sign bearing the radiation symbol and the words:

CAUTION Radiation Controlled Area RWP Required For Entry Dosimetry Required For Entry 5.1 .22 In addition to the requirements of Step 5.1 .2.1 all areas posted as an RCA (except those areas exempted by the Health Physics Manager, or designee) shall have the exit doors and pathways posted with the words:

CAUTION All Personnel and Materials Must Be Surveyed Before Leaving This Area 5.1 .2.3 The use of tape bearing the words Radiation Controlled Area may be used in addition to required signs.

5.1 .2.4 Areas may be specifically posted with the words Radiation Controlled Area, RWP and Dosimetry Required For Entry if HP Supervision deem that potential exists for a change of conditions requiring greater awareness of hazards in the area to be entered.

5.1 .3 Radiation Area (2000341 553) (1985306090) 5.1 .3.1 Each radiation area shall be conspicuously posted with a sign, or signs, bearing the radiation symbol and the words:

CAUTION Radiation Area 5.1.3.2 The RWP will define entry requirements for these areas.

5.1.3.3 Posting boundaries for Radiation Areas are determined by radiation surveys.

These surveys will be made at a distance of 30 cm (12 inches) from the radiation source of from any surface the radiation penetrates.

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Approved By Procedure Number Rev C R Dedrickson Vogtle Electric Generating Plant 00930-C 26 Date Approved Page Number 08/05/2009 RADiATION AND CONTAMiNATION CONTROL 12 of 28 5.1 .4 High Radiation Area (2000341 553) (1985306089) 5.1 .41 Each High Radiation Area shall be conspicuously posted with a sign, or signs, bearing the radiation symbol and the words: (1985307052)

DANGER High Radiation Area Health Physics Escort Required or Alarming Dosimeter Required RWP Required for Entry Per 10CFR2O.1902(b) High Radiation Area signs may use either the word CAUTION or DANGER. Danger is the wording selected for use at Vogtle, Hatch, and Farley.

5.1 .4.2 Posting boundaries for High Radiation Areas are determined by radiation surveys. These surveys will be made at a distance of 30 cm (12 inches) from the radiation source or from any surface the radiation penetrates.

5.1 .4.3 Each entrance or access point into a High Radiation Area shall be locked, except during periods when access to the areas is required, with positive control over each individual entry, or provide continuous direct or electronic surveillance that is capable of preventing unauthorized entry.

5.1 .4.4 In lieu of the controls specified in Section 5.1 .4.3, each High Radiation Area in which the radiation exposure rate is greater than 100 mrem/h and less than 1000 mrem/h shall be barricaded and conspicuously posted as directed above.

(1985307052) 5.1.4.5 Individuals who have successfully completed HP self-monitoring training are qualified to provide their own escort in High Radiation Areas.

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Approved By Procedure Number Rev C R Dedrickson 7 VogtleElectric GeneratingPiant 00930-C 26 Date Approved Page Number 08/05/2009 RADIATION AND CONTAMINATION CONTROL i 3 of 28 5.1.5 Locked High Radiation Area (2000341553) (1985306649) (1995329955) 5.1 .5.1 Each Locked High Radiation Area shall be locked in such a manner as to prevent unauthorized entry and not prevent exit from the area. Those areas, where no enclosure can be reasonably constructed, shall be roped off and a flashing light installed as a warning device. Areas meeting the above requirements shall be conspicuously posted with a sign, or signs, bearing the radiation symbol and the words: (1985307052) (1995330004)

DANGER Locked High Radiation Area Health Physics Escort Required Alarming Dosimeter Required RWP Required For Entry 5.1 .5.2 Posting boundaries for High Radiation Areas are determined by radiation surveys. These surveys will be made at a distance of 30 cm (12 inches) from the radiation source or from any surface the radiation penetrates.

5.1 .5.3 Control of keys for Locked High Radiation Areas will be by Operations or Health Physics Supervision in accordance with Procedure 00008-C, Plant Lock And Key Control.

5.1.6 Very High Radiation Area (1985306649) (1995329955) 5.1 .6.1 Each Very High Radiation Area shall meet all of the access and posting controls which apply to Locked High Radiation Areas and an HP escort is required for area entry.

5.1 .6.2 Each Very High Radiation Area shall be conspicuously posted with a sign, or signs, bearing the radiation symbol and the words:

GRAVE DANGER Very High Radiation Area Health Physics Escort Required Alarming Dosimeter Required RWP Required for Entry 5.1.6.3 Very High Radiation Area boundaries will be determined by surveys made at a distance of 1 meter (3 feet).

5.1.6.4 Control of keys for Very High Radiation Areas will be in accordance with Procedure 00008-C.

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Approved By . Procedure Number Rev C R Dedrickson VogtleElectricGenerating Plant -

00930-C 26 Date Approved Page Number 08/05/2009 RADIATION AND CONTAMINATION CONTROL 14 of 28 5.1.7 Hot Spots 5.1 .7.1 Each identified hot spot should be conspicuously posted with a sign bearing the radiation symbol and the words:

Hot Spot 5.1.7.2 In addition to the requirements of Step 5.1.7.1, each Hot Spot should be documented via the Heath Physics Departments computerized survey system.

The related survey information should be marked on the corresponding room or area survey status sign.

5.1 .7.3 Do not apply hot spot stickers by use of adhesive backing due to the possibility of chloride contamination. Use approved tape or other means to affix the sticker to the desired location.

5.1 .8 Contaminated Areas, Materials, Equipment and Personnel.

5.1 .8.1 Each contaminated area shall be conspicuously posted with a sign, or signs, bearing the radiation symbol and the words:

CAUTION Contaminated Area 5.1 .8.2 Areas, or rooms, posted as contaminated areas will be defined (by barrier, tape, etc) at the entrance/exit point of the area and a step-off pad, placed as soon as practicable, to prevent the spread of contamination.

5.1 .8.3 The RWP will define entry requirements.

5.1.8.4 All personnel should take measures to minimize the spread of higher contamination to low or uncontaminated areas.

5.1.8.5 Materials, equipment and personnel shall be considered contaminated if they exceed the limits of Subsection 2.3. Materials and equipment shall be labeled in accordance with 00960-C, Control of Radioactive Materials. Personnel shall be decontaminated.

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Approved By \

4 Procedure Number Rev C R Dedrickson Vogtle Electric Generatirg Plant 00930-C 26 Date Approved Page Number 08/05/2009 RADiATION AND CONTAMINATION CONTROL 15 of 28 5.1 .8.6 Areas that are potentially contaminated shall be controlled as contaminated areas.

5.1 .8.7 Contaminated Areas may be defined with yellow and magenta ribbon, tape, or rope.

5.1 .8.8 Contaminated Areas should be decontaminated as soon as practicable.

5.1 .8.9 Areas where activities, such as opening a potentially contaminated system, grinding or machining on potentially contaminated surfaces, are performed, shall be controlled as Contaminated Areas.

5. 1 .8. 1 0 Materials taken into Contaminated Areas should be minimized to only those necessary to perform the work.

5.1 .9 Airborne Radioactivity Areas (1985306088) 5.1 .9.1 Each Airborne Radioactivity Area shall be conspicuously posted with a sign, or signs, bearing the radiation symbol and the words:

CAUTION Airborne Radioactivity Area Notify Health Physics Prior to Entry 5.1 .9.2 Entrances into these areas will be controlled by a specific RWP.

5.1 .9.3 Posting may also be required for any work evolution likely to cause airborne contamination such as initial opening of reactor systems, grinding, welding, burning or operating air-operated equipment in contaminated areas.

5.1.10 Radioactive Materials Area (1985306086) (1985306087) 5.1 .10.1 Each Radioactive Materials Area shall be conspicuously posted with a sign, or signs, bearing the radiation symbol and the words:

CAUTION Radioactive Material 5.1.10.2 In addition to the requirements of Step 5.1.11.1, containers containing radioactive material shall be clearly marked with signs, or stickers, bearing the radiation symbol and the words:

CAUTION Radioactive Material Printed January 12, 2012 at 10:42

Approved By . . Procedure Number Rev C.R.Dedrickson VogUe Electric Generating Plant 00930-C 26 Date Approved Page Number 08/05/2009 RADiATION AND CONTAMINATION CONTROL i 6 of 28 5 1 1 0.3

. Posting of radioactive material containers should have the contact radiation dose marked on the sign or wrapping, in accordance with Health Physics procedures.

5. 1 1 0.4

. For the purpose of this procedure, the radioactive material container may be a plastic bag or suitable wrapping.

5.1 .1 1 Hot Particle Control Area 5.1 .1 1 .1 Each Hot Particle Control Area (HPCA) shall be conspicuously posted with a sign, or signs, bearing the radiation symbol and the words:

CAUTION Hot Particle Control Area Health Physics Escort Required 5.1 .1 1 .2 Areas, or rooms, posted as Hot Particle Control Areas will be defined (by barrier, tape, etc) (such as yellow and magenta rope, tape or ribbon) at the entrance/exit point and a step-off pad(s) placed as soon as practicable to prevent the spread of hot particles.

5.1 .1 1 .3 Each Hot Particle Buffer Area (HPBA) shall be conspicuously posted with a sign, or signs, bearing the radiation symbol and the words:

CAUTION Hot Particle Buffer Area Increased HP Surveillance Required 5.1.12 Radiological Status Sheets/Boards Highly frequented radiation areas, as designated by HP Supervision, should be posted by HP to indicate radiation levels. Results may be specified as ranges.

5.2 RADIATION WORK PERMIT (RWP) (1999340604) 5.2.1 The RWP specifies radiation safety requirements for each job and assures worker briefings are given. The RWP also provides a mechanism for evaluating person-rem expenditures on each job. Procedure 43007-C, Issuance, Use And Control Of Radiation Work Permit, specifies the details of the RWP program.

5.2.2 HP shall establish and maintain a Radiation Work Permit system to control and minimize radiation exposure during operation and maintenance at VEGP. An RWP is required for any entry into an RCA and must be reviewed daily by each worker prior to entry. (1999340604) (2000340662)

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Approved By Procedure Number Rev C R Dedrickson Vogtle Electric Generating Plant 00930-C 26 Date Approved Page Number 08/05/2009 RADiATION AND CONTAMINATION CONTROL 17 of 28 5.2.3 Radiation Work Permits shall provide radiological controls that address specific conditions of the job and areas for the purpose of worker protection. Protective clothing and/or radiological control requirements (i.e., respiratory protection) shall be established by RWP and modified only by authorized Health Physics personnel. (1 984301 975) (1 999340604) (2000340661) (2000340662) 5.2.4 Health Physics personnel or plant supervision may stop the job whenever radiological conditions change or work practices are inconsistent with the pre-job planning and/or RWP. If this occurs, then:

a. HP Supervision must be notified and appropriate changes made in the approach to the job, if practicable. Subject changes will be reflected on the RWP.

b. Stop work actions and subsequent changes in job controls must be documented in the ALARA Review Package.

5.2.5 HP Supervision or the Shift Supervisor may authorize entry with an urgent, or emergency, RWP when critical immediate action is required.

5.2.5.1 In this case, however, HP shall provide continuous coverage to ensure radiation safety practices are followed. The job shall be documented after its completion.

5.2.5.2 Supply kits and Emergency Preparedness kits will be strategically located throughout the plant and will contain equipment and materials for emergency response.

5.2.6 General Radiation Work Permit 5.2.6.1 The General RWP is used for the performance of routine duties and surveillance work. General RWPs will not be issued for work in high radiation areas, areas of significant loose contamination, or areas requiring a specific job survey by Health Physics prior to entry. (1984301305) 5.2.6.2 General RWPs specify basic radiation safety requirements such as minimum protective clothing, dosimetry, respiratory protection, access restrictions, and the type or extent of work that is authorized.

5.2.6.3 Records of entries shall be specified by name, elapsed time and incremental dose, and maintained on a daily basis.

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Approved By c\,

Procedure Number Rev C R Dedrickson Vogtle Electric Generating Plant 4 j 00930-C 26 Date Approved Page Number 08/05/2009 RADIATION AND CONTAMINATION CONTROL i 8 of 28 5.2.7 Specific Radiation Work Permits The Specific RWP is used for the performance of a specific job in specific locations or areas. The Specific RWP is active for the duration of the job and may be modified on the basis of surveys. Surveys shall be performed as required to support RWP authorized work.

5.2.8 HP should review active RWPs on a routine basis.

5.2.9 When a job is in a high radiation area, HP Supervision may determine that performing pre-job RWP surveys would not be consistent with ALARA. The RWP may then be initiated prior to surveys being taken. However, HP shall enter the areas with the work crew and perform the appropriate surveys while the job is being done. The survey data will be recorded on the RWP and radiological controls adjusted as necessary.

5.2.10 The RWP should be posted atthe job location or main HP control point.

5.2.1 1 Personnel authorized to make an entry on a Specific RWP requiring a pre-job briefing should be specified by name or section. Records of entries will be maintained in accordance with step 5.2.6.3.

5.2.1 2 Issuance of Radiation Work Permits 5.2.12.1 Personnel should initiate an RWP by notifying Health Physics at least 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months before job performance is required to allow sufficient time to generate the RWP and perform an ALARA review. Exceptions to the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months should be considered for planned maintenance. For planned maintenance activities Health Physics should be notified 1 4 days prior to the start of the activities.

5.2.12.2 HP reviews the work to be performed and specifies radiological controls to minimize exposure to personnel.

5.2.12.3 If pre-job planning is required, it shall be performed in accordance with VEGP procedures.

5.2.12.4 HP shall approve the RWP. HP Supervision shall sign all RWPs. A copy of the RWP may be included in the Work Order (WO) package. However, the posted RWP shall be reviewed daily prior to use in order that changes to radiological conditions may be noted.

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ApprovedBy ., *:

Procedure Number Rev C.R.Dedrickson Vogtle Electric Generating Plant 00930-C 26 Date Approved Page Number 08/05/2009 RADIATiON AND CONTAMINATION CONTROL 19 of 28 5.2.13 Termination Of Radiation Work Permits 5.2.13.1 Specific RWPs shall be terminated or suspended whenever the job is completed or canceled, or whenever significant changes in radiological conditions occur.

The job supervisorlTLlATL should inform HP of RWPs to be terminated.

5.2.13.2 General RWPs shall be terminated whenever significant changes in radiological conditions occur or at the end of each calendar year. General RWPs shall be reviewed by Health Physics Supervision each calendar quarter.

5.2.13.3 HP should ensure thatterminated RWPs are clearly identified as terminated.

5.2.13.4 HP should also ensure that terminated RWPs are removed from the job location and/or control points and returned to the Health Physics office.

5.2.13.5 Specific RWPs may be suspended after consultation with either Work Planning of the Work Group Supervisor. For efficiency or record processing purposes Health Physics may, at its discretion, determine that an RWP needs to remain open. (2003002525) 5.2.13.6 Any RWP will be terminated unless Health Physics has been apprised of the need for suspending the RWP or Health Physics has made a determination, at its discretion, that the RWP should remain in an active or suspended state.

(2003002525) 5.3 CONTAMiNATION CONTROLS 5.3.1 Use Of Protective Clothing (PC) 5.3.1 .1 Personnel shall wear and use protective clothing in a manner consistent with the training each has received.

5.3.1 .2 HP shall ensure that PCs are commensurate with the levels and state of the contamination expected for the area entered. These requirements can only be modified by qualified Health Physics personnel. (1984301946) 5.3.1 .3 Outer street clothing and jewelry should be removed prior to donning PCs.

Violations of this policy may result in the confiscation of contaminated clothing and personal effects. While outside separate dressing areas, men and women will be expected to remain modestly attired in the workplace. Loose fitting, non-revealing garments, such as scrubs or a pair of gym shorts and a T-shirt, are considered appropriate. Tight fitting, revealing undergarments are not acceptable attire.

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Approved By . . Procedure Number Rev C R Dedrickson ,v Vogtle Electric Generating Plant )-C 26 Date Approved 08/05/2009 RADIATION AND CONTAMINATION CONTROL 20 of 28 5.3.1 .4 The use of protective clothing for purposes other than contamination control is prohibited. Protective clothing should be distinctly marked or colored to facilitate control. Yellow plastics used for contamination control shall not be used as uncontrolled clothing for use in protection from the elements (e.g., raingear).

5.3.1 .5 Protective clothing is stored in accordance with Procedure 92015-C, Transient Combustibles Control.

5.3.2 Control Of Radioactive Contamination (1984301315) 5.3.2.1 HP shall establish controls to ensure that the spread of contamination during work is minimized.

5.3.2.2 These controls shall include, but are not limited to consideration of the following:

a. Engineered Controls

b. Special Training

c. Job Planning

d. Monitoring of Materials and Equipment 5.3.2.3 Step-off pads will be used to control entrance and exit from a contaminated area, to minimize the spread of contamination from an area.

5.3.2.4 Multiple step-off pads (two or more) may be used in areas of high contamination.

5.4 PERSONNEL MONITORING 5.4.1 Personnel monitoring shall be performed in a manner consistent with the training each has received.

5.4.2 A full whole body frisk shall be perlormed by all personnel when exiting the RCA access control point or at other areas designated by HP. Whole body monitors should be used as primary means of surveying when provided.

5.4.3 The HP Manager, or designee may exempt the whole body survey requirement for exit from Radiation Controlled Areas where sealed radioactive material is stored, after surveys verify the escape of radioactive material is unlikely to occur under normal conditions.

5.4.4 Personnel exiting contaminated areas are responsible for surveying themselves when they cross a local control point equipped with either friskers or personnel contamination monitors.

Printed January 12, 2012 at 10:42

Approved By . . Procedure Number Rev C R Dedrickson Vogtle Electric Generating Plant ; 00930-C 26 Date Approved 08/05/2009 I RADIATION AND CONTAMINATION CONTROL Page Number 21 of 28 5.45 Personnel exiting contaminated areas should frisk their hands and feet at the nearest frisker location and notify HP if contamination is found.

5.4.6 After performing a hands and feet frisk, personnel should proceed to the nearest personnel contamination monitor for a whole body survey. This survey is to be performed prior to the individual putting on street clothes.

5.4.7 When exiting contaminated areas, hand carried tools and materials (e.g.,

clipboards, notebooks, pencils, etc.), shall be frisked for beta-gamma contamination by HP Personnel unless a red tool bag has been provided (outside the contaminated area in accordance with HP procedures) for their return.

5.4.8 HP shall be notified immediately whenever contamination is detected on any individual or their personal articles. At no time are individuals to perform self decontamination without HP Personnel present.

5.4.9 Personnel decontamination should be performed when the results of personnel monitoring exceed 1 00 cpm above background per probe area when using an HP-21 0 probe or equivalent. Exceptions may be warranted if isotopic identification demonstrates that the material is short lived (e.g., Rb-88, Cs-i 38).

HP Supervision shall approve the exceptions.

5.4.10 HP shall directly supervise the decontamination of contaminated individuals. HP shall use approved methods of decontamination and document personnel contamination and decontamination effectiveness. Medical assistance may be required when contamination cannot be removed by use of approved methods.

5.4.1 1 Whenever internal contamination is suspected, bioassays shall be performed in accordance with Procedure 00940-C, Bioassay Program.

5.4.12 HP shall control, on an individual basis, the use of contaminated or radioactive articles and maintain possession of contaminated personal articles until sufficient radioactive decay or decontamination bring items into compliance with Procedure 00960-C or until items are discarded.

Printed January 12, 2012 at 10:42

Approved By ; * *

Procedie Number Rev C R Dedrickson Vogtle Electric Generating Plant 00930-C 26 Date Approved Page Number 08/05/2009 RADiATION AND CONTAMiNATiON CONTROL 22 of 28 5.5 DECONTAMINATiON OF MATERIALS AND FACILITIES (1984301315) 5.5.1 HP should evaluate the generation of additional radwaste and additional exposure to personnel against the benefits of reduced personnel exposure and contamination levels when prescribing the methods and extent of decontamination efforts.

5.5.2 HP shall ensure that only approved decontamination methods and permissible chemicals are used. Chemistry Personnel should be consulted to identify permissible chemicals.

5.5.3 HP will be notified of all spills. HP may approve methods for immediate cleanup of small spills (e.g. Chemistry spilling Reactor Coolant Sample). 2003201146 5.6 RADIATION AND CONTAMINATION SURVEYS (1 999340604) (2000340661) 5.6.1 HP shall perform radiation and contamination surveys in accordance with HP Department Procedures to mark and confirm Radiation Controlled Areas, and unrestricted area boundaries, to determine if abnormal radiation levels exist, and to determine extent and magnitude of radiation and contamination levels so that personnel radiation exposure can be maintained ALARA. (1984301951)

(1 985305365) (1985307052) 5.6.2 Controls for release of potentially contaminated or activated materials or facilities for unrestricted use are addressed in Procedure 00960-C.

5 .6 .3 Protective cloth ing and gloves will be worn when sam pling rad ioactive systems.

(1984301314) 5.6.4 HP shall perform radiation and contamination surveys, as required, to support the operation and maintenance of VEGP.

5.6.5 HP conducts surveys during performance of critical steps. Examples of such critical steps include: Opening of radioactive systems and certain grinding, welding or machining operations on contaminated equipment.

5.6.6 When unusual exposures have occurred, surveys shall be performed to determine the cause. Corrective actions shall be instituted to minimize further personnel exposure.

Printed January 12, 2012 at 10:42

Approved By *: . . Procedure Number Rev C R Dedrickson Vogtle Electric Generating Plant 00930-C 26 Date Approved Page Number 08/05/2009 RADIATION AND CONTAMINATION CONTROL 23 of 28 5.6.7 Plant personnel shall notify Health Physics when radiation and contamination surveys are required. Examples include but are not limited to, the following activities:

a. At predetermined task steps, requiring a re-evaluation of radiological conditions in active work areas and adjacent areas, whenever operations are performed that have the potential for changing radiation levels.

b. As necessary to control the spread of loose surface contamination whenever operations are performed that have been known to result in, or are expected to result in, the spread of contamination.

c. Upon initial entry to vaults, tanks and voids containing radioactive piping or components.

d . U pon opening of contam mated or potentially contam mated systems.

e. For picking up, receiving or opening packages containing radioactive material.

f. Prior to the need for modification of shielding.

g. Prior to handling radioactive sources, i.e., incore fission detectors.

h. Release of facilities or equipment for unrestricted use.

i. Prior to removal of any posted Radiation Control Area boundary.

j. Whenever smoke removal equipment (portable or installed) is used in the RCA. (1985306168) 5.6.8 HP shall perform airborne radioactivity surveys in accordance with HP Department Procedures to provide a basis for the selection of respiratory protection equipment, the degree of engineering controls to be implemented for a particular task, and assurance that regulatory requirements are met.

(1984301975) 5.7 SHIELDING 5.7.1 Temporary shielding shall be evaluated and controlled per Procedure 41006-C, Temporary Shielding.. When determined to be necessary, shielding will be provided to control doses to within the limits of applicable regulation.

5.7.2 Addition, deletion, or modification of permanent shielding shall be controlled per Procedure 00400-C, Plant Design Control.

Printed January 12, 2012 at 10:42

Approved By Procedure Number Rev Vogtle Electric Generating Plant C R Dedrickson 00930-C 26 Date Approved Page Number 08/05/2009 RADIATiON AND CONTAMINATION CONTROL 24 of 28 5.8 SELF MONITORING 58.1 Only personnel specifically trained and qualified under the VEGP RAD WORKERS SELF MONITORING Training may perform Self Monitoring.

5.8.2 Personnel trained and qualified under Plant Hatch or Plant Farley Rad Workers Self Monitoring training may be exempted from the VEGP training requirement for Self Monitoring 5.8.3 Personnel will consult with HP if there is any question on their qualification to perform the task.

5.8.4 Notify HP for instruction when personnel contamination is detected.

5.8.5 Radiation and Contamination Limits in Tables 1 & 2 included in this procedure will be followed.

5.8.6 Refer to Table 3, Self Monitoring Controls Checklist, for additional instructions.

6.0 REFERENCES

6.1 PROCEDURES 6.1 .1 00008-C, Plant Lock And Key Control 6.1.2 00100-C, Quality Assurance Records Administration 6.1 .3 00400-C, Plant Design Control 6.1 .4 00940-C, Bioassay Program 6.1 .5 00960-C, Control Of Radioactive Material 6.1 .6 00970-C, Respiratory Protection Program 6.1.7 41006-C, Temporary Shielding 6.1.8 43000-C, Radiation And Contamination Surveys 6.1.9 43002-C Airborne Radioactivity Sampling And Evaluation 6.1.10 43007-C, Issuance, Use And Control Of Radiation Work Permits 6.1.11 92015-C, Use, Control and Storage Of Flammable/Combustible Materials Printed January 12, 2012 at 10:42

Approved By ;eumber Rev C.R.Dedrickson Vogtle Electric Generating Plant - 26 Date Approved Page Number 08/05/2009 RADIATION AND CONTAMINATION CONTROL 62 1 OCFR2O, Standards For Protection Against Radiation 6.3 VEGP Rad Workers Self Monitoring Training 6.4 COMMITMENTS, OPEN ITEMS AND ACTION ITEMS 6.4.1 Commitments 1 984301 253, 1 984301 305, 1 984301 31 4, 1 984301 31 5, 1984301946, 1 984301 951 , 1 984301 955, 1 984301 969, 1 984301 975, 1984301983, 1984302057, 1985303534, 1985305100, 1985305365, 1985306086, 1 985306087, 1 985306088, 1 985306089, 1 985306090, 1985306168, 1985306646, 1985306649, 1985307052, 1993327366, 1995329954, 1995329955, 1995330004, 1999340604, 2000340661, 2000340662, 2000341553 6.4.2 Applicable Condition Reports or Action Items 2003002525, 2003201146 END OF PROCEDURE TEXT Printed January 12, 2012 at 10:42

Approved By I Procedure Number Rev C.R.Dedrickson Vogtle Electric Generating Plant A I 26 Date Approved Page Number 08/05/2009 RADIATION AND CONTAMINATION CONTROL 26 of 28 TABLE 1 DOSE RATE GUIDELINES FOR SELF MONITORING QUALIFIED INDIVIDUALS EXPECTED DOSE WORKER REQUIREMENTS DOSE RATE (INTEGRATED DOSE) m rem

<1000 mrem/hr <100 mrem None

>100 mrem Obtain HP support

>1000 mrem/hr Obtain briefing on area dose rates and authorization on RWP Obtain entry requirements Symbol Meaning less than greater than equal to or greater than equal to or less than Printed January 12, 2012 at 10:42

Approved By ProcedureNumberRev C.R.Dedrickson Vogtle Electric Generating Plant : 00930-C 26 Date Approved Page Number 08/05/2009 RADIATION AND CONTAMINATION CONTROL TABLE 2 CONTAMINATION LEVEL GUIDELINES FOR SELF MONITORING QUALIFIED INDIVIDUALS CONTAMINATION TASK DRESS HEALTH PHYSICS LEVELS DESCRIPTION REQUIREMENTS SUPPORT s 000 dpm/1 00cm 1 2 None None None

>1000 dpm/lOOcm 2 No breach, climbing or Booties and Gloves None

<10,000 dpm/lOOcm 2 kneeling. Tasks permitted include walkdowns, inspections, equipment setup, chemistry sampling, etc.)

Breach of system Full PCs Contact HP prior to Facial PCs contaminated system breach Climbing, equipment None setup involving kneeling ortight areas

>10,000 2 dpm/lOOcm No breach or climbing. Lab coat, booties, None

<50,000 dpm/lOOcm 2 Tasks permitted include and gloves walkdowns, inspections, equipment setup, chemistry sampling, operation rounds, etc.)

Breach of system Full PCs (single), Contact HP prior to Breathing Zone air contaminated system sample, Facial PCs breach for climbing, airborne, and splash protection Climbing, equipment None setup involving kneeling or tight areas

>50,000 dpm/lOOcm 2 Valve CM/PM, Full PCs (single). Area setup, ventilation

<300,000 repacking, or line-up, Facial PCs, BZs, as setup, Herculite, etc.

dpm/1 00cm 2 rotate blind flanges, required remove boron, etc.

>300,000 Contact HP dpm/1 00cm 2

Symbol Meaning

> greater than

equal to or less than Printed January 12, 2012 at 10:42

Approved By C.R.Dedrickson Vogtle Electric Generating Plant v /4 Date Approved 100930-c 26 08/05/2009 I RADIATION AND CONTAMINATION CONTROL Page Number 28 of 28 TABLE 3 SELF MONITORING CONTROLS CHECKLIST Prior to initiating Self Monitoring in a Radiation Controlled Area, perform the following steps:

1 . Review the assigned RWP.

2. When utilizing Self Monitoring, the following must be perlormed:

a. Review the latest HP Routine Surveys for the area where work is to be performed.

b. If the dose and contamination levels are outside the limits set for Self Monitoring in Tables 1 and 2 of this procedure, or if maintenance will require breach i ng of a potentially contam mated system contact H P prior tobeginningwork.

NOTE Dress requirements will be determined by the latest survey data and should be reevaluated after the initial Self Monitoring Survey is performed.

3. Obtain the appropriate dose and contamination monitoring instrumentation and perform an initial survey of the area where work is to be performed. If the measurements taken are within the limits established by this procedure, work may proceed.

4. Monitor dose and contamination levels during the work process.

5. Perform exit survey. If the dose or contamination levels have increased during the work process, notify HP and document the survey results.

Printed January 12, 2012 at 10:42

SRO Job Performance Measure D Facility: Vogtle Task No: N/A Task Title : Determ i ne Posti ng Requirements JPM No: V-NRC-JP-00930-HL17 K/A

Reference:

K/A: G2.3.13 RO 3.4 SRO 3.8 Examinee: NRC Examiner:_________

Facility Evaluator:

Method of testing:

Simulated Performance Actual Performance Classroom Simulator Plant Note to Examiner: There is a second cue sheet on Page 5.

Read to the examinee:

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

Initial Conditions: A line is plugged with CVCS demin resin in Aux Bldg RA-28.

The resin plug is estimated to be 10 feet long. The dose rate at the room entrance is 500 mr/hr, which is 4 feet from the line.

See attached room map.

Initiating Cue: Determine the appropriate posting required at the entry to the room.

Task Standard: Determine proper HP posting for the room.

Required Materials: 1. HP survey map

2. Procedure 00930-C, Radiation And Containment Control Ver 26.0

3. Tech Specs General

References:

None Time Critical Task: No Validation Time: 10 minutes 2

Performance Information Critical steps denoted with an asterisk Calculate the dose at one foot.

As distance (4ft) is less than half of source length (1 Oft),

Use line source equation 2 =l 1

l D

where, l = closest source intensity 12= farthest source intensity 1 = closest distance D

2 = farthest distance D

Standard: Candidate calculates I = 500 mr/hr x (4) = 2000 mr/hr 1

2000 mr/hr at one foot.

Comment:

Determine posting requirement Standard: Candidate determines Locked High Radiation Area based on dose at one foot greater than 1000 mr/hr.

Comment:

Terminating cue: Student returns initiating cue sheet 3

When Candidate returns first cue sheet give the candidate the cue sheet on Page 5.

Initial Conditions: A line is plugged with CVCS demin resin in Aux Bldg RA-28.

The resin plug is estimated to be 10 feet long. The dose rate at the room entrance is 500 mr/hr, which is 4 feet from the line.

See attached room map.

Initiating Cue: Based on your posting requirement determination, determine the administrative control section(s) that are required by Tech Specs (if any).

4

Initial Conditions: A line is plugged with CVCS demin resin in Aux Bldg RA-28.

The resin plug is estimated to be 10 feet long. The dose rate at the room entrance is 500 mr/hr, which is 4 feet from the line.

See attached room map.

Initiating Cue: Based on your posting requirement determination, determine the administrative control section(s) that are required by Tech Specs (if any).

5

Determine Tech Spec administrative controls Standard: Candidate references Tech Spec 5.7 and determines for a Locked High Radiation Area 5.7.1 and 5.7.2 and 5.7.3 apply.

5.7.1 Pursuantto 10 CFR 20, paragraph 20.1601(c), in lieu ofthe requirements of 10 CFR 20.1601, each high radiation area, as defined in 10 CFR 20, in which the intensity of radiation is > 100 mrem/hr but < 1000 mrem/hr, shall be barricaded and conspicuously posted as a high radiation area, and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP). Individuals qualified in radiation protection procedures (e.g., Health Physics Technicians) or personnel continuously escorted by such individuals may be exempt from the RWP issuance requirement during the performance of their assigned duties in high radiation areas with exposure rates 1 000 mrem/hr, provided they are otherwise following plant radiation protection procedures for entry into such high radiation areas.

Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

a. A radiation monitoring device that continuously indicates the radiation dose rate in the area.

b. A radiation monitoring device that continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been established and personnel are aware of them.

c. An individual qualified in radiation protection procedures with a radiation dose rate monitoring device, who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by Health Physics supervision in the RWP.

5.7.2 In addition to the requirements of Specification 5.7.1 areas with radiation levels 1 000 mrem/hr shall be provided with locked or continuously guarded doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of Operations or health physics supervision. Doors shall remain locked except during periods of access by personnel under an approved RWP that shall specify the dose rate levels in the immediate work areas and the maximum allowable stay times for individuals in those areas. In lieu of the stay time specification of the RWP, direct or remote (such as closed circuit TV cameras) continuous surveillance may be made by personnel qualified in 6

radiation protection procedures to provide positive exposure control over the activities being performed within the area.

5.7.3 For individual high radiation areas within radiation levels of> 1000 mrem/hr, accessible to personnel, that are located within large areas such as reactor containment, where no enclosure exists for purposes of locking, or that cannot be continuously guarded, and where no enclosure can be reasonably constructed around the individual area, that individual area shall be barricaded and conspicuously posted, and a flashing light shall be activated as a warning device.

Comment:

Terminating cue: Student returns initiating cue sheet 7

Verification of Completion Job Performance Measure No. V-NRC-JP-00930-HL17 Examinees Name:

Examiners Name:

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners signature and date:

8

Initial Conditions: A line is plugged with CVCS demin resin in Aux Bldg RA-28.

The resin plug is estimated to be 10 feet long. The dose rate at the room entrance is 500 mr/hr which is 4 feet from the line.

See attached room map.

Initiating Cue: Determine the appropriate posting required at the entry to the room.

VALVE GALLERY CVCS MIXED BED DEMIN (1AXA28)

Resin Plug 10 FT.

ALPHA SURVEY REQUtRED Count 10% of smears for alpha for routine survey and/or breach of system

Approved By Procedure Number Rev C R Dedrickson Vogtle Electric Generating Plant 00930-C 26 Date Approved Page Number 08/05/2009 RADIATION AND CONTAMINATION CONTROL 1 of 28 PRB REVIEW REQUIRED RADIATION AND CONTAMINATION CONTROL PROCEDURE USAGE REQUIREMENTS- SECTIONS Continuous Use: Procedure must be open and readily available at the work location. Follow procedure step by step unless otherwise directed.

Reference Use: Procedure or applicable section(s) available at the work location for ready reference by person performing steps.

Information Use: Available on plant site for reference as needed. ALL Printed January 12, 2012 at 10:42

Approved By :

Procedure Number Rev C.R.Dedrickson Vogtle Electric Generating Plant 00930-C 26 Date Approved Page Number 08/05/2009 RADIATION AND CONTAMINATION CONTROL 2 of 28 1 .0 PURPOSE(1 984301 253) (1985303534)

This procedure establishes requirements and responsibilities for monitoring and controlling exposure to radiation and contamination. It includes criteria for Radiation Controlled Areas, the Radiation Work Permit (RWP) system, sampling and surveys, shielding, and the Self Monitoring process as follows:

4.0 REQUIREMENTS 5.0 PROCEDURE 5.1 POSTING 5.2 RADIATION WORK PERMIT 5.3 CONTAMINATION CONTROLS 5.4 PERSONNEL MONITORING 5.6 SURVEYS AND SAMPLING 5.7 SHIELDING 5.8 SELF MONITORING 2.0 DEFINITIONS 2.1 AIRBORNE RADIOACTIVITY AREA (1 985306088) (1993327366)

A room, enclosure, or area in which airborne radioactive materials, composed wholly or partly of licensed material, exist in concentrations:

a. To such a degree that an individual present in the area without respiratory protection equipment could exceed, during the hours an individual is present in a week, an intake of 0.6 percent of the annual limit on intake (ALl) or 1 2 Derived Air Concentrations (DAC)-hours.

OR

b. An area should be considered an Airborne Radioactivity Area when the airborne activity reaches 0.3 DACs for isotopes which have a classification other than submersion, and 100% of the DAC limits for isotopes which have a classification of submersion. DAC limits are specified in 1 OCFR2O Appendix B, Table I, Column 3.

2.2 ANNUAL LIMIT ON INTAKE (ALl)

The derived limit for the amount of radioactive material taken into the body of an adult worker by inhalation or ingestion in a year. ALl values for intake by ingestion and by inhalation of selected radionuclides are given in 1 OCFR2O, Appendix B, Table 1, Columns 1 and 2. (1993327366)

Printed January 12, 2012 at 10:42

Approved By \ Procedure Number Rev C R Dedrickson Date Approved Vogtle ElectricGeneratingPlant 4 00930-C Page Number 26 08/05/2009 RADIATION AND CONTAMINATION CONTROL 3 of 28 2.3 CONTAMINATED AREAS, MATERIALS AND EQUIPMENT Any area where loose surface contamination exceeds the following limits shall be posted as a Contaminated Area. Items exceeding the following measurements will be posted as radioactive material and handled in accordance with Procedure 00960-C, Control of Radioactive Material. (1984301315) 2.3.1 Fixed Surface Radioactive Contamination (contamination embedded in material surface)

Beta-gamma 1 00 cpm above background as measured with an HP-21 0 probe or equivalent or as specified by HP procedures for other instruments.

Alpha 50 cpm above background as measured with an alpha survey meter.

2.3.2 Loose Surface Radioactive Contamination (removable contamination)

Beta-gamma >1 000 dpm/1 00 cm 2

Alpha >20 dpm/100 cm2 2.4 CONTROLLED AREA Any area outside of the restricted area but inside the site boundary, access to which can be limited for any reason.

2.5 DERIVED AIR CONCENTRATION (DAC)

The concentration of a given radionuclide in air which, if breathed by the reference man for a working year of 2000 hours0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months , results in an intake of one ALl.

DAC values are given in 10CFR2O, Appendix B, Table 1, Column 3.

(1993327366) 2.6 HIGH RADIATION AREA Any area, accessible to individuals, in which radiation levels from radiation sources external to the body could result in an individual receiving a dose equivalent in excess of 100 mrem/hr at 30 cm (12 inches) from the radiation source or from any surlace which the radiation penetrates. (2000341553)

(1985306089)

Printed January 12, 2012 at 10:42

Approved By < Procedure Number Rev Vogtle Electric Generating Plant C R Dedrickson 1j 00930-C 26 Date Approved Page Number 08/05/2009 RADiATION AND CONTAMINATION CONTROL 4 of 28 2.7 HOT PARTiCLES Hot particles are discrete radioactive particles that are characterized by intense emissions of beta particles, X-rays and gamma rays. For the purpose of hot particle control, a hot particle will be defined as an extremely localized count rate (RM-14 with HP-210 probe, or equivalent) of 250,000 cpm or more emanating from a discrete particle.

2.8 HOT PARTICLE BUFFER AREA (HPBA)

An area, free of hot particles, surrounding a Hot Particle Control Area (HPCA).

Hot particles are not expected in this area; however, this area is surveyed frequently to determine that hot particles are not transported out of the HPCA.

2.9 HOT PARTICLE CONTROL AREA A work area where hot particles are known to be present. An HPCA may be a room, a roped off area or a containment used to confine hot particle contamination.

2.10 HOT SPOTS Components or items having localized contact readings in excess of 100 mrem/hr and more than 5 times the general area dose rates.

2.11 LOCKED HIGH RADIATION AREA Any area accessible to individuals, in which radiation levels external to the body could result in an individual receiving a dose equivalent equal to or in excess of 1 000 mrem/hr at 30 cm (1 2 inches) from the radiation source or from any surface which the radiation penetrates. (2000341553) 2.12 RADiATION AREA Any area, accessible to individuals, in which radiation levels could result in an individual receiving a dose equivalent in excess of 5 mrem/hr at 30 cm (12 inches) from the radiation source or from any surface which the radiation penetrates. (2000341 553) (1985306090) 2.13 RADiATION CONTROLLED AREA (RCA)

Any area which contains or potentially contains radiation, contamination, or radioactive materials in quantities or levels sufficient to require posting of protective measures.

Printed January 12, 2012 at 10:42

Approved By . . .. Procedure Number Rev C R Dedrickson [ Vogtle Electric Generating Plant 00930-C 26 Date Approved Page Number 08/05/2009 RADIATION AND CONTAMINATION CONTROL 5 of 28 2.1 4 RADIOACTIVE MATERIALS AREA A radioactive materials area is any area or room in which radioactive material is used or stored and which contains radioactive material in an amount exceeding 1 0 times the quantity of such material specified in 1 OCFR2O, Appendix C. This does not apply to materials contained within process equipment or materials in transport that are packaged and labeled in accordance with Department of Transportation (DOT) regulations. (1985306086) (1985306087) 2.15 RADIATION WORKER Plant personnel assigned duties inside Radiation Control Areas.

2.16 RESTRICTED AREA Any area to which access is limited by the licensee for the purpose of protection of individuals against undue risks from exposure to radiation and radioactive materials. The area inside an RCA is a restricted area. Others may be defined as needed.

2.17 SELF MONITORING Radiation and Contamination monitoring performed by qualified Radiation Workers for themselves only.

2.18 SURVEYS AND SAMPLING 2.18.1 The measurement of radiation levels, concentrations, surface area concentrations or quantities of radioactive material and the use of the results of these measurements to evaluate potential exposures and doses.

2.18.2 Survey is also an evaluation of the radiological conditions and potential hazards incident to the production, use, transfer, release, disposal, or presence of radioactive material or other sources of radiation. When appropriate, such an evaluation includes a physical survey of the location of radioactive material and measurements or calculations of levels of radiation, concentrations or quantities of radioactive material present.

2.19 VERY HIGH RADIATION AREA Any area, accessible to individuals, in which radiation levels from radiation sources external to the body could result in an individual receiving an absorbed dose in excess of 500 rads in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months at 1 meter (3 feet) from a radiation source or 1 meter from any surlace that the radiation penetrates.

Printed January 12, 2012 at 10:42

Approved By . Procedure Number Rev C R Dedrickson Vogtle Electric Generating Plant : 00930-C 26 Date Approved Page Number 08/05/2009 RADIATiON AND CONTAMINATION CONTROL 6 of 28 3.0 RESPONSIBILITIES 3.1 HEALTH PHYSICS MANAGER The Health Physics Manager is responsible for ensuring the Health Physics Section performs the following:

3.1 .1 Reviews radiation safety incidents and approves corrective action.

3.1 .2 Establishes and maintains a radiation and contamination control program which includes appropriate procedures and instructions.

3.1 .3 Establishes and maintains a Radiation Work Permit (RWP) system to control and minimize exposure to radiation and contamination. (1984302057) 3.1 .4 Assigns HP Personnel as appropriate to the Maintenance Performance Teams.

3.1 .5 Performs and documents radiation and contamination surveys, air sampling, and analysis, and reviews plant areas to ensure that all areas with existing or potential high radiation exposure rates are properly posted and controlled.

(1985307052) 3.1 .6 Classifies, posts, barricades, and controls ingress and egress to Radiation Controlled Areas to control radiation exposure and spread of contamination.(1 984301 951) (1985307052)

3. 1 .7 Determines protective clothing requirements and stay times.

3.1 .8 Requests and verifies installation of shielding.

3.1 .9 Supervises and monitors decontamination of personnel, equipment and facilities.

3.1 .1 0 Establishes controls for use and disposition of contaminated materials and equipment.

3.1 .1 1 Performs maintenance, calibrations, and surveillances on assigned HP instrumentation and equipment.

3.1.12 Performs trend analysis on radiation and contamination exposure controls.

Recommends actions necessary to correct adverse trends. (1999340604)

(2000340662) 3.1.13 Maintains control and limitations for Self Monitoring Program.

Printed January 12, 2012 at 10:42

Approved By . ..

Procedure Number Rev C.R.Dedrickson VogUe Electric Generating Plant 00930-C 26 Date Approved Page Number 08/05/2009 RADiATION AND CONTAMINATION CONTROL 7 of 28 3.1 .14 Ensures the Plant Training and Emergency Preparedness Department is notified of changes in the use of protective clothing so that General Employee Training remains current.

3.1 .15 Actively participates in the Training Advisory Committee to maintain all training current and relative to plant demands.

3.2 PLANT SUPERVISION 3.2.1 Ensure that supervised personnel comply with rules, regulations and procedures associated with radiation safety and comply with RWPs. (1984301983) 3.2.2 Request RWPs to support work in Radiation Controlled Areas if not already requested by the Performance Team work planner.

3.2.3 Notify HP promptly when radiological problems occur and interface with HP to resolve deficiencies.

3.2.4 Ensure that the work area has been cleaned up and restored to normal conditions after work evolution is completed.

3.2.5 Ensure appropriate individuals receive Self Monitoring training.

3.2.6 Ensure individuals complete Job Performance Measures (JPMs) sign off criteria.

3.3 PLANT PERSONNEL 3.3.1 Practice radiation safety and maintain their radiation exposure As Low As Reasonably Achievable (ALARA).

3.3.2 Comply with all radiation protection rules, regulations and procedures.

Supervisors are responsible for ensuring their employees follow all radiation protection rules, regulations and procedures.

3.3.3 Read and comply with RWP requirements whenever their duties require the use ofan RWP.

3.3.4 Individuals are responsible for surveying themselves for contamination when crossing a local control point or the main access control point. (1984301969) 3.3.5 If contamination is found, the individual notifies HP Personnel for decontamination. (1984301969)

Printed January 12, 2012 at 10:42

Approved By Procedure Number Rev C R Dedrickson Vogtle Electric Generating Plant 00930-C 26 Date Approved Page Number 08/05/2009 -

RADIATION AND CONTAMINATION CONTROL 8 of 28 3.3.6 Know their current exposure status.

3.3.7 Perform Self Monitoring within established procedures and limits, if qualified.

3.4 PLANT TRAINING AND EMERGENCY PREPAREDNESS MANAGER The Plant Training and Emergency Preparedness Manager is responsible for ensuring the Training Department performs the following:

3.4.1 Establishes and maintains a Self Monitoring training program.

3.4.2 Maintains records for personnel who have completed Self Monitoring training.

3.4.3 Keeping other plant sections informed on personnel who are Self Monitoring qualified.

4.0 REQUIREMENTS 4.1 PERSONNEL REQUIREMENTS 4.1.1 All personnel shall receive indoctrination and training in radiation and contamination control requirements in accordance with approved plant procedures, commensurate with their work assignments.

4.1.2 HP Personnel shall receive additional training in radiation safety in accordance with approved plant procedures.

4.1 .3 Prior to performing Self Monitoring personnel will receive specific training.

4.1 .4 Personnel performing Self Monitoring must have specific JPMs signed off to be qualified to perform Self Monitoring tasks.

4.2 ENTRY/EXIT (1984301955) (1985305100) 4.2.1 Personnel will normally access and exit RCAs through the designated access control points determined by Health Physics.

4.2.2 Personnel access to areas of unknown radiological conditions will normally be restricted until survey data is established by Health Physics personnel.

4.2.3 Entrance and access to a High Radiation Area shall be controlled by a specific RWP. (1985307052) 4.2.4 Access to containment buildings is controlled by HP and areas are surveyed to establish allowable working periods. Telemetry may be used in place of stay times.

Printed January 12, 2012 at 10:42

rApproved By Procedure Number Rev

[rDate c R Dedrickson Approved Vogtle Electric Generating Plant 00930-C Page Number 26 RADIATiON AND CONTAMINATION CONTROL L08/05/2009 9 of 28 4.2.5 Any individual, or group of individuals, permitted to enter a High Radiation Area shall be continuously provided with or accompanied by one or more of the following: (1 985306646) (1 985306649) (1 995329954) (1995329955)

a. Radiation monitoring device(s) which continuously indicates the radiation dose rate in the area.

b. Radiation monitoring device(s) which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas is permitted after the dose rate level has been made known to personnel.

c. An individual qualified to implement Health Physics procedures, equipped with a radiation dose rate monitoring device and who will be responsible for providing positive control over activities within the area while performing periodic radiation surveillance as specified by the Health Physics Manager, or designee, in the RWP.

NOTE If an escort is required, only Health Physics Personnel are qualified to perform escort duties in Locked High Radiation Areas.

4.2.6 In addition to the requirements for a High Radiation Area, access of personnel into a Locked High Radiation Area (> 1000 mrem/h) shall be under an approved, specific RWP, that shall specify the dose rate levels in the immediate work areas and the maximum allowable stay times for individuals in those areas.

4.2.6.1 Specific RWPs may govern entry into many Locked High Radiation Areas, therefore, ALARA briefings will clarify RWP requirements for dose rate specifications in the immediate work area.

4.2.6.2 In lieu of the stay time specification of the RWP, direct or remote (such as closed circuit TV cameras) continuous surveillance may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities being performed within the area.

4.2.7 In addition to the requirements for a Locked High Radiation Area, access of personnel into a Very High Radiation Area must receive prior written approval from the Health Physics Manager, or designee.

4.2.7.1 A Health Physics escort is required for entry.

4.2.7.2 In the event of a declared emergency the Emergency Director may grant access to a Very High Radiation Area.

Printed January 12, 2012 at 10:42

Approved By . . 1: Procedure Number Rev C R Dedrickson Vogtle Eicrrc Generating PIant 00930-C 26 Date Approved Page Number 08/05/2009 -

RADIATION AND CONTAMINATION CONTROL io of 28 5.0 PROCEDURE 5.1 POSTING The following precautions and limitations apply to postings used to identify or delineate Radiation Controlled Areas:

5.1 .1 Radiological warning signs, ropes or barricades shall be placed in such a manner as to alert personnel of the hazard upon approach.

5.1.1.1 Removal or repositioning of signs, ropes or barriers is prohibited unless authorized by Health Physics personnel.

5.1 .1 .2 Signs, ropes, and barricades may be placed in areas of low or no, radiological hazard, if appropriate, for the purpose of access control. (1999340604)

(2000340661) 5.1 .1 .3 Radiological posting signs shall have a yellow background with a purple, magenta, or black radiation symbol.

5.1 .1 .4 Ropes and barrier tape used for radiological warnings shall be yellow and magenta. The exception to the required color is when chain is used as a barrier, provided the chain is identified as a radiological barrier.

5.1 .1 .5 Signs, ropes, and other material of the conventional yellow and magenta color shall not be used for any purpose other than radiological control marking, unless approved by HP Supervision and controlled by Procedure 00960-C.

5.1.1.6 To the extent practicable, measured radiation levels and locations of sources should be posted at the entry into any radiation or high radiation area.

5.1.1.7 Use of handwritten signs shall be minimized.

Printed January 12, 2012 at 10:42

Approved By $ Procedure Number Rev C R Dedrickson Vogtle Electric Generating Plant 00930-C 26 Date Approved Page Number 08/05/2009 RADIATION AND CONTAMINATION CONTROL i i of 28 5.1 .2 Radiation Controlled Area 5.1 .2.1 Each Radiation Controlled Area shall have all personnel access points and doors posted with a sign bearing the radiation symbol and the words:

CAUTION Radiation Controlled Area RWP Required For Entry Dosimetry Required For Entry 5.1 .2.2 In addition to the requirements of Step 5.1 .2.1 all areas posted as an RCA (except those areas exempted by the Health Physics Manager, or designee) shall have the exit doors and pathways posted with the words:

CAUTION All Personnel and Materials Must Be Surveyed Before Leaving This Area 5.1 .2.3 The use of tape bearing the words Radiation Controlled Area may be used in addition to required signs.

5.1 .2.4 Areas may be specifically posted with the words Radiation Controlled Area, RWP and Dosimetry Required For Entry if HP Supervision deem that potential exists for a change of conditions requiring greater awareness of hazards in the area to be entered.

5.1 .3 Radiation Area (2000341 553) (1985306090) 5.1 .3.1 Each radiation area shall be conspicuously posted with a sign, or signs, bearing the radiation symbol and the words:

CAUTION Radiation Area 5.1 .3.2 The RWP will define entry requirements for these areas.

5.1.3.3 Posting boundaries for Radiation Areas are determined by radiation surveys.

These surveys will be made at a distance of 30 cm (12 inches) from the radiation source of from any surface the radiation penetrates.

Printed January 12, 2012 at 10:42

Approved By I Procedure Number Rev C R Dedrickson Vogtle Electric Generating Plant 00930-C 26 Date Approved Page Number 08/05/2009 RADIATION AND CONTAMINATION CONTROL i 2 of 28 5.1 .4 High Radiation Area (2000341 553) (1985306089) 5.1 4.1 Each High Radiation Area shall be conspicuously posted with a sign, or signs, bearing the radiation symbol and the words: (1985307052)

DANGER High Radiation Area Health Physics Escort Required or Alarming Dosimeter Required RWP Required for Entry Per 10CFR2O.1902(b) High Radiation Area signs may use either the word CAUTION or DANGER. Danger is the wording selected for use at Vogtle, Hatch, and Farley.

5.1 .4.2 Posting boundaries for High Radiation Areas are determined by radiation surveys. These surveys will be made at a distance of 30 cm (12 inches) from the radiation source or from any surface the radiation penetrates.

5.1 .4.3 Each entrance or access point into a High Radiation Area shall be locked, except during periods when access to the areas is required, with positive control over each individual entry, or provide continuous direct or electronic surveillance that is capable of preventing unauthorized entry.

5.1 .4.4 In lieu of the controls specified in Section 5.1 .4.3, each High Radiation Area in which the radiation exposure rate is greater than 100 mrem/h and less than 1000 mrem/h shall be barricaded and conspicuously posted as directed above.

(1985307052) 5.1.4.5 Individuals who have successfully completed HP self-monitoring training are qualified to provide their own escort in High Radiation Areas.

Printed January 12, 2012 at 10:42

Approved By 7 Procedure Number Rev C R Dedrickson Vogtle Electric Generating Plan fl 00930-C 26 Date Approved Page Number 08/05/2009 RADiATiON AND CONTAMINATION CONTROL i 3 of 28 5.1 .5 Locked High Radiation Area (2000341 553) (1 985306649) (1995329955) 5.1 .5.1 Each Locked High Radiation Area shall be locked in such a manner as to prevent unauthorized entry and not prevent exit from the area. Those areas, where no enclosure can be reasonably constructed, shall be roped off and a flashing light installed as a warning device. Areas meeting the above requirements shall be conspicuously posted with a sign, or signs, bearing the radiation symbol and the words: (1985307052) (1995330004)

DANGER Locked High Radiation Area Health Physics Escort Required Alarming Dosimeter Required RWP Required For Entry 5.1 .5.2 Posting boundaries for High Radiation Areas are determined by radiation surveys. These surveys will be made at a distance of 30 cm (12 inches) from the radiation source or from any surface the radiation penetrates.

5.1 .5.3 Control of keys for Locked High Radiation Areas will be by Operations or Health Physics Supervision in accordance with Procedure 00008-C, Plant Lock And Key Control.

5.1.6 Very High Radiation Area (1985306649) (1995329955) 5.1 .6.1 Each Very High Radiation Area shall meet all of the access and posting controls which apply to Locked High Radiation Areas and an HP escort is required for area entry.

5.1 .6.2 Each Very High Radiation Area shall be conspicuously posted with a sign, or signs, bearing the radiation symbol and the words:

GRAVE DANGER Very High Radiation Area Health Physics Escort Required Alarming Dosimeter Required RWP Required for Entry 5.1.6.3 Very High Radiation Area boundaries will be determined by surveys made at a distance of 1 meter (3 feet).

5.1.6.4 Control of keys for Very High Radiation Areas will be in accordance with Procedure 00008-C.

Printed January 12, 2012 at 10:42

Approved By Procedure Number Rev C.R.Dedrickson Vogtle Electric Generating Plant 00930-C 26 Date Approved Page Number 08/05/2009 RADiATION AND CONTAMINATION CONTROL i 4 of 28 5.1.7 Hot Spots 5.1 .7.1 Each identified hot spot should be conspicuously posted with a sign bearing the radiation symbol and the words:

Hot Spot 5.1.7.2 In addition to the requirements of Step 5.1.7.1, each Hot Spot should be documented via the Heath Physics Departments computerized survey system.

The related survey information should be marked on the corresponding room or area survey status sign.

5.1 .7.3 Do not apply hot spot stickers by use of adhesive backing due to the possibility of chloride contamination. Use approved tape or other means to affix the sticker to the desired location.

5.1 .8 Contaminated Areas, Materials, Equipment and Personnel.

5.1 .8.1 Each contaminated area shall be conspicuously posted with a sign, or signs, bearing the radiation symbol and the words:

CAUTION Contaminated Area 5.1 .8.2 Areas, or rooms, posted as contaminated areas will be defined (by barrier, tape, etc) at the entrance/exit point of the area and a step-off pad, placed as soon as practicable, to prevent the spread of contamination.

5.1 .8.3 The RWP will define entry requirements.

5.1.8.4 All personnel should take measures to minimize the spread of higher contamination to low or uncontaminated areas.

5.1.8.5 Materials, equipment and personnel shall be considered contaminated if they exceed the limits of Subsection 2.3. Materials and equipment shall be labeled in accordance with 00960-C, Control of Radioactive Materials. Personnel shall be decontaminated.

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Approved By Procedure Number Rev C R Dedrickson , Vogtle Electric Generating Plant ; 00930-C 26 Date Approved Page Number 08/05/2009 1 RADiATION AND CONTAMINATION CONTROL 15 of 28 5.1 .86 Areas that are potentially contaminated shall be controlled as contaminated areas.

5.1 .8.7 Contaminated Areas may be defined with yellow and magenta ribbon, tape, or rope.

5.1 .8.8 Contaminated Areas should be decontaminated as soon as practicable.

5.1 .8.9 Areas where activities, such as opening a potentially contaminated system, grinding or machining on potentially contaminated surfaces, are performed, shall be controlled as Contaminated Areas.

5.1 .8.10 Materials taken into Contaminated Areas should be minimized to only those necessary to perform the work.

5.1 .9 Airborne Radioactivity Areas (1985306088) 5.1 .9.1 Each Airborne Radioactivity Area shall be conspicuously posted with a sign, or signs, bearing the radiation symbol and the words:

CAUTION Airborne Radioactivity Area Notify Health Physics Prior to Entry 5.1 .9.2 Entrances into these areas will be controlled by a specific RWP.

5.1 .9.3 Posting may also be required for any work evolution likely to cause airborne contamination such as initial opening of reactor systems, grinding, welding, burning or operating air-operated equipment in contaminated areas.

5.1.10 Radioactive Materials Area (1985306086) (1985306087)

5. 1 1 0. 1

. Each Radioactive Materials Area shall be conspicuously posted with a sign, or signs, bearing the radiation symbol and the words:

CAUTION Radioactive Material 5.1.10.2 In addition to the requirements of Step 5.1.11.1, containers containing radioactive material shall be clearly marked with signs, or stickers, bearing the radiation symbol and the words:

CAUTION Radioactive Material Printed January 12, 2012 at 10:42

Approved By I3L Procedure Number Rev C R Dedrickson t VogUe Electric Generating Plant 00930-C 26 Date Approved Page Number 08/05/2009 RADIATION AND CONTAMINATION CONTROL 16 of 28

5. 1 1 0.3

. Posting of radioactive material containers should have the contact radiation dose marked on the sign or wrapping, in accordance with Health Physics procedures.

5. 1 1 0.4

. For the purpose of this procedure, the radioactive material container may be a plastic bag or suitable wrapping.

5.1 .1 1 Hot Particle Control Area 5.1 .1 1 .1 Each Hot Particle Control Area (HPCA) shall be conspicuously posted with a sign, or signs, bearing the radiation symbol and the words:

CAUTION Hot Particle Control Area Health Physics Escort Required 5.1 .1 1 .2 Areas, or rooms, posted as Hot Particle Control Areas will be defined (by barrier, tape, etc) (such as yellow and magenta rope, tape or ribbon) at the entrance/exit point and a step-off pad(s) placed as soon as practicable to prevent the spread of hot particles.

5.1 .1 1 .3 Each Hot Particle Buffer Area (HPBA) shall be conspicuously posted with a sign, or signs, bearing the radiation symbol and the words:

CAUTION Hot Particle Buffer Area Increased HP Surveillance Required 5.1 .1 2 Radiological Status Sheets/Boards Highly frequented radiation areas, as designated by HP Supervision, should be posted by HP to indicate radiation levels. Results may be specified as ranges.

5.2 RADIATION WORK PERMIT (RWP) (1999340604) 5.2.1 The RWP specifies radiation safety requirements for each job and assures worker briefings are given. The RWP also provides a mechanism for evaluating person-rem expenditures on each job. Procedure 43007-C, Issuance, Use And Control Of Radiation Work Permit, specifies the details of the RWP program.

5.2.2 HP shall establish and maintain a Radiation Work Permit system to control and minimize radiation exposure during operation and maintenance at VEGP. An RWP is required for any entry into an RCA and must be reviewed daily by each worker prior to entry. (1999340604) (2000340662)

Printed January 12, 2012 at 10:42

Approved By . . cedure Number Rev C.R.Dedrickson VogtIeElectric Generating Plant - -

26 Date Approved

. age Number 08/05/2009 RADiATION AND CONTAMINATION CONTROL f i 7 of 28 5.2.3 Radiation Work Permits shall provide radiological controls that address specific conditions of the job and areas for the purpose of worker protection. Protective clothing and/or radiological control requirements (i.e., respiratory protection) shall be established by RWP and modified only by authorized Health Physics personnel. (1 984301 975) (1 999340604) (2000340661) (2000340662) 5.2.4 Health Physics personnel or plant supervision may stop the job whenever radiological conditions change or work practices are inconsistent with the pre-job planning and/or RWP. If this occurs, then:

a. HP Supervision must be notified and appropriate changes made in the approach to the job, if practicable. Subject changes will be reflected on the RWP.

b. Stop work actions and subsequent changes in job controls must be documented in the ALARA Review Package.

5.2.5 HP Supervision or the Shift Supervisor may authorize entry with an urgent, or emergency, RWP when critical immediate action is required.

5.2.5.1 In this case, however, HP shall provide continuous coverage to ensure radiation safety practices are followed. The job shall be documented after its completion.

5.2.5.2 Supply kits and Emergency Preparedness kits will be strategically located throughout the plant and will contain equipment and materials for emergency response.

5.2.6 General Radiation Work Permit 5.2.6.1 The General RWP is used for the performance of routine duties and surveillance work. General RWPs will not be issued for work in high radiation areas, areas of significant loose contamination, or areas requiring a specific job survey by Health Physics prior to entry. (1984301305) 5.2.6.2 General RWPs specify basic radiation safety requirements such as minimum protective clothing, dosimetry, respiratory protection, access restrictions, and the type or extent of work that is authorized.

5.2.6.3 Records of entries shall be specified by name, elapsed time and incremental dose, and maintained on a daily basis.

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Approved By i Procedure Number Rev C R Dedrickson Vogtle Electric Generating Plant 00930-C 26 Date Approved Page Number 08/05/2009 RADIATiON AND CONTAMINATION CONTROL i 8 of 28 5.2.7 Specific Radiation Work Permits The Specific RWP is used for the performance of a specific job in specific locations or areas. The Specific RWP is active for the duration of the job and may be modified on the basis of surveys. Surveys shall be performed as required to support RWP authorized work.

5.2.8 HP should review active RWPs on a routine basis.

5.2.9 When a job is in a high radiation area, HP Supervision may determine that performing pre-job RWP surveys would not be consistent with ALARA. The RWP may then be initiated prior to surveys being taken. However, HP shall enter the areas with the work crew and perform the appropriate surveys while the job is being done. The survey data will be recorded on the RWP and radiological controls adjusted as necessary.

5.2.10 The RWP should be posted atthe job location or main HP control point.

5.2.1 1 Personnel authorized to make an entry on a Specific RWP requiring a pre-job briefing should be specified by name or section. Records of entries will be maintained in accordance with step 5.2.6.3.

5.2.12 issuance of Radiation Work Permits 5.2.12.1 Personnel should initiate an RWP by notifying Health Physics at least 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months before job performance is required to allow sufficient time to generate the RWP and perform an ALARA review. Exceptions to the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months should be considered for planned maintenance. For planned maintenance activities Health Physics should be notified 1 4 days prior to the start of the activities.

5.2.12.2 HP reviews the work to be performed and specifies radiological controls to minimize exposure to personnel.

5.2.12.3 If pre-job planning is required, it shall be performed in accordance with VEGP procedures.

5.2.12.4 HP shall approve the RWP. HP Supervision shall sign all RWPs. A copy of the RWP may be included in the Work Order (WO) package. However, the posted RWP shall be reviewed daily prior to use in order that changes to radiological conditions may be noted.

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Approved By Procedure Number Rev C R Dedrickson VogUe Electric Generating Plant 00930-C 26 Date Approved Page Number 08/05/2009 RADIATiON AND CONTAMINATION CONTROL 19 of 28 5.2.13 Termination Of Radiation Work Permits 5.2.13.1 Specific RWPs shall be terminated or suspended whenever the job is completed or canceled, or whenever significant changes in radiological conditions occur.

The job supervisorlTLlATL should inform HP of RWPs to be terminated.

5.2.13.2 General RWPs shall be terminated whenever significant changes in radiological conditions occur or at the end of each calendar year. General RWPs shall be reviewed by Health Physics Supervision each calendar quarter.

5.2.13.3 HP should ensure thatterminated RWPs are clearly identified as terminated.

5.2.13.4 HP should also ensure that terminated RWPs are removed from the job location and/or control points and returned to the Health Physics office.

5.2.13.5 Specific RWPs may be suspended after consultation with either Work Planning of the Work Group Supervisor. For efficiency or record processing purposes Health Physics may, at its discretion, determine that an RWP needs to remain open. (2003002525) 5.2.13.6 Any RWP will be terminated unless Health Physics has been apprised of the need for suspending the RWP or Health Physics has made a determination, at its discretion, that the RWP should remain in an active or suspended state.

(2003002525) 5.3 CONTAMINATION CONTROLS 5.3.1 Use Of Protective Clothing (PC) 5.3.1 .1 Personnel shall wear and use protective clothing in a manner consistent with the training each has received.

5.3.1 .2 HP shall ensure that PCs are commensurate with the levels and state of the contamination expected for the area entered. These requirements can only be modified by qualified Health Physics personnel. (1984301946) 5.3.1.3 Outer street clothing and jewelry should be removed prior to donning PCs.

Violations of this policy may result in the confiscation of contaminated clothing and personal effects. While outside separate dressing areas, men and women will be expected to remain modestly attired in the workplace. Loose fitting, non-revealing garments, such as scrubs or a pair of gym shorts and a T-shirt, are considered appropriate. Tight fitting, revealing undergarments are not acceptable attire.

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Approved By $ Procedure Number Rev C R Dedrickson AP Vogtle Electric Generating Plant %é 00930-C 26 Date Approved Page Number 08/05/2009 RADiATION AND CONTAMINATION CONTROL 20 of 28 5.3.1 .4 The use of protective clothing for purposes other than contamination control is prohibited Protective clothing should be d istinctly marked or colored to facilitate control. Yellow plastics used for contamination control shall not be used as uncontrolled clothing for use in protection from the elements (e.g., raingear).

5.3.1 .5 Protective clothing is stored in accordance with Procedure 92015-C, Transient Combustibles Control.

5.3.2 Control Of Radioactive Contamination (1984301315) 5.3.2.1 HP shall establish controls to ensure that the spread of contamination during work is minimized.

5.3.2.2 These controls shall include, but are not limited to consideration of the following:

a. Engineered Controls

b. Special Training

c. Job Planning

d. Monitoring of Materials and Equipment 5.3.2.3 Step-off pads will be used to control entrance and exit from a contaminated area, to minimize the spread of contamination from an area.

5.3.2.4 Multiple step-off pads (two or more) may be used in areas of high contamination.

5.4 PERSONNEL MONITORING 5.4.1 Personnel monitoring shall be performed in a manner consistent with the training each has received.

5.4.2 A full whole body frisk shall be performed by all personnel when exiting the RCA access control point or at other areas designated by HP. Whole body monitors should be used as primary means of surveying when provided.

5.4.3 The HP Manager, or designee may exempt the whole body survey requirement for exit from Radiation Controlled Areas where sealed radioactive material is stored, after surveys verify the escape of radioactive material is unlikely to occur under normal conditions.

5.4.4 Personnel exiting contaminated areas are responsible for surveying themselves when they cross a local control point equipped with either friskers or personnel contamination monitors.

Printed January 12, 2012 at 10:42

Approved By *

Procedure Number Rev Vogtle Electric Generating Plant C R Dedrickson 00930-C 26 Date Approved Page Number 08/05/2009 RADIATiON AND CONTAMINATION CONTROL 21 of 28 5.4.5 Personnel exiting contaminated areas should frisk their hands and feet at the nearest frisker location and notify HP if contamination is found.

5.4.6 After performing a hands and feet frisk, personnel should proceed to the nearest personnel contamination monitor for a whole body survey. This survey is to be performed prior to the individual putting on street clothes.

5.4.7 When exiting contaminated areas, hand carried tools and materials (e.g.,

clipboards, notebooks, pencils, etc.), shall be frisked for beta-gamma contamination by HP Personnel unless a red tool bag has been provided (outside the contaminated area in accordance with HP procedures) for their return.

5.4.8 HP shall be notified immediately whenever contamination is detected on any individual or their personal articles. At no time are individuals to perform self decontamination without HP Personnel present.

5.4.9 Personnel decontamination should be performed when the results of personnel monitoring exceed 1 00 cpm above background per probe area when using an HP-210 probe or equivalent. Exceptions may be warranted if isotopic identification demonstrates that the material is short lived (e.g., Rb-88, Cs-i 38).

HP Supervision shall approve the exceptions.

5.4.iO HP shall directly supervise the decontamination of contaminated individuals. HP shall use approved methods of decontamination and document personnel contamination and decontamination effectiveness. Medical assistance may be required when contamination cannot be removed by use of approved methods.

5.4.i 1 Whenever internal contamination is suspected, bioassays shall be performed in accordance with Proced u re 00940-C Bioassay Program.

5.4.12 HP shall control, on an individual basis, the use of contaminated or radioactive articles and maintain possession of contaminated personal articles until sufficient radioactive decay or decontamination bring items into compliance with Procedure 00960-C or until items are discarded.

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Approved By & Procedure Number Rev C R Dedrickson Vogtle Electric Generating Plant 00930-C 26 Date Approved Page Number 08/05/2009 RADiATION AND CONTAMINATION CONTROL 22 of 28 5.5 DECONTAMINATiON OF MATERIALS AND FACILITIES (1984301315) 5.5.1 HP should evaluate the generation of additional radwaste and additional exposure to personnel against the benefits of reduced personnel exposure and contamination levels when prescribing the methods and extent of decontamination efforts.

5.5.2 HP shall ensure that only approved decontamination methods and permissible chemicals are used. Chemistry Personnel should be consulted to identify permissible chemicals.

5.5.3 HP will be notified of all spills. HP may approve methods for immediate cleanup of small spills (e.g. Chemistry spilling Reactor Coolant Sample). 2003201146 5.6 RADiATION AND CONTAMINATION SURVEYS (1 999340604) (2000340661) 5.6.1 HP shall perform radiation and contamination surveys in accordance with HP Department Procedures to mark and confirm Radiation Controlled Areas, and unrestricted area boundaries, to determine if abnormal radiation levels exist, and to determine extent and magnitude of radiation and contamination levels so that personnel radiation exposure can be maintained ALARA. (1984301951)

(1 985305365) (1985307052) 5 .6 .2 Controls for release of potentially contam mated or activated materials or facilities for unrestricted use are addressed in Procedure 00960-C.

5.6.3 Protective clothing and gloves will be worn when sampling radioactive systems.

(1984301314) 5.6.4 HP shall perform radiation and contamination surveys, as required, to support the operation and maintenance of VEGP.

5.6.5 HP conducts surveys during performance of critical steps. Examples of such critical steps include: Opening of radioactive systems and certain grinding, welding or machining operations on contaminated equipment.

5.6.6 When unusual exposures have occurred, surveys shall be performed to determine the cause. Corrective actions shall be instituted to minimize further personnel exposure.

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Approved By P;$ Procedure Number Rev C R Dedrickson ] Vogtle Electric Generating Plant 00930-C 26 Date Approved Page Number 08/05/2009 RADIATION AND CONTAMINATION CONTROL 23 of 28 5.6.7 Plant personnel shall notify Health Physics when radiation and contamination surveys are required. Examples include but are not limited to, the following activities:

a. At predetermined task steps, requiring a re-evaluation of radiological conditions in active work areas and adjacent areas, whenever operations are performed that have the potential for changing radiation levels.

b. As necessary to control the spread of loose surface contamination whenever operations are pertormed that have been known to result in, or are expected to result in, the spread of contamination.

c. Upon initial entry to vaults, tanks and voids containing radioactive piping or components.

d . U pon opening of contam mated or potentially contam mated systems.

e. For picking up, receiving or opening packages containing radioactive material.

f. Prior to the need for modification of shielding.

g. Prior to handling radioactive sources, i.e., incore fission detectors.

h. Release of facilities or equipment for unrestricted use.

i. Prior to removal of any posted Radiation Control Area boundary.

j. Whenever smoke removal equipment (portable or installed) is used in the RCA. (1985306168) 5.6.8 HP shall perform airborne radioactivity surveys in accordance with HP Department Procedures to provide a basis for the selection of respiratory protection equipment, the degree of engineering controls to be implemented for a particular task, and assurance that regulatory requirements are met.

(1984301975) 5.7 SHIELDING 5.7.1 Temporary shielding shall be evaluated and controlled per Procedure 41006-C, Temporary Shielding.. When determined to be necessary, shielding will be provided to control doses to within the limits of applicable regulation.

5.7.2 Addition, deletion, or modification of permanent shielding shall be controlled per Procedure 00400-C, Plant Design Control.

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Approved By I . . rocedure Number Rev C.R.Dedrickson Vogtle EIectrc Generating Plant 00930-C 26 Date Approved Page Number 08/05/2009 RADIATiON AND CONTAMINATION CONTROL 24 of 28 5.8 SELF MONITORING 5.8.1 Only personnel specifically trained and qualified under the VEGP RAD WORKERS SELF MONITORING Training may perlorm Self Monitoring.

5.8.2 Personnel trained and qualified under Plant Hatch or Plant Farley Rad Workers Self Monitoring training may be exempted from the VEGP training requirement for Self Monitoring 5.8.3 Personnel will consult with HP if there is any question on their qualification to perform the task.

5.8.4 Notify HP for instruction when personnel contamination is detected.

5.8.5 Radiation and Contamination Limits in Tables 1 & 2 included in this procedure will be followed.

5.8.6 Refer to Table 3, Self Monitoring Controls Checklist, for additional instructions.

6.0 REFERENCES

6.1 PROCEDURES 6.1.1 00008-C, Plant Lock And Key Control 6.1.2 00100-C, Quality Assurance Records Administration 6.1.3 00400-C, Plant Design Control 6.1.4 00940-C, Bioassay Program 6.1.5 00960-C, Control Of Radioactive Material 6.1.6 00970-C, Respiratory Protection Program 6.1.7 41006-C, Temporary Shielding 6.1.8 43000-C, Radiation And Contamination Surveys 6.1.9 43002-C Airborne Radioactivity Sampling And Evaluation 6.1.10 43007-C, Issuance, Use And Control Of Radiation Work Permits 6.1.11 92015-C, Use, Control and Storage Of Flammable/Combustible Materials Printed January 12, 2012 at 10:42

Approved By . . Procedure Number Rev C.R.Dedrickson Vogtle Electric Generating Plant 00930-C 26 Date Approved Page Number 08/05/2009 RADIATION AND CONTAMINATION CONTROL 25 of 28 6.2 10CFR2O, Standards For Protection Against Radiation 6.3 VEGP Rad Workers Self Monitoring Training 6.4 COMMiTMENTS, OPEN ITEMS AND ACTION ITEMS 6.4.1 Commitments 1 984301 253, 1 984301 305, 1 984301 31 4, 1 984301 31 5, 1984301946, 1 984301 951 , 1 984301 955, 1 984301 969, 1 984301 975, 1984301983, 1 984302057, 1 985303534, 1 9853051 00, 1 985305365, 1985306086, 1985306087, 1985306088, 1985306089, 1985306090, 1985306168, 1985306646, 1985306649, 1985307052, 1993327366, 1995329954, 1995329955, 1995330004, 1999340604, 2000340661, 2000340662, 2000341553 6.4.2 Applicable Condition Reports or Action items 2003002525, 2003201146 END OF PROCEDURE TEXT Printed January 12, 2012 at 10:42

Approved By 1\ 4 Procedure Number Rev C R Dedrickson Vogtle Electric Generating Plant 26 Date Approved Pc; 08/05/2009 RADIATION AND CONTAMINATION CONTROL I 26 of 28 TABLE 1 DOSE RATE GUIDELINES FOR SELF MONITORING QUALIFIED INDIVIDUALS EXPECTED DOSE WORKER REQUIREMENTS DOSE RATE (INTEGRATED DOSE) m rem

<1000 mrem/hr <100 mrem None

>100 mrem Obtain HP support

>1000 mrem/hr Obtain briefing on area dose rates and authorization on RWP Obtain entry requirements Symbol Meaning

< less than

> greater than

> equal to or greater than

< equal to or less than Printed January 12, 2012 at 10:42

Approved By Procedure Number Rev C.R.Dedrickson Vogtle Plant 00930-C 26 Date Approved Page Number 08/05/2009 RADIATION AND CONTAMINATION CONTROL 27 of 28 TABLE 2 CONTAMINATION LEVEL GUIDELINES FOR SELF MONITORING QUALIFIED INDIVIDUALS CONTAMINATION TASK DRESS HEALTH PHYSICS LEVELS DESCRIPTION REQUIREMENTS SUPPORT

1 000 dpm/1 00cm 2 None None None

>1000 dpm/lOOcm 2 No breach, climbing or Booties and Gloves None

<10,000 dpm/lOOcm 2 kneeling. Tasks permitted include walkdowns, inspections, equipment setup, chemistry sampling, etc.)

Breach of system Full PCs Contact HP prior to Facial PCs contaminated system breach Climbing, equipment None setup involving kneeling or tight areas

>10,000 2 dpm/lOOcm No breach or climbing. Lab coat, booties, None

<50,000 dpm/1 00cm 2 Tasks permitted include and gloves walkdowns, inspections, equipment setup, chemistry sampling, operation rounds, etc.)

Breach of system Full PCs (single), Contact HP prior to Breathing Zone air contaminated system sample, Facial PCs breach for climbing, airborne, and splash protection Climbing, equipment None setup involving kneeling or tight areas

>50,000 2 dpm/lOOcm Valve CM/PM, Full PCs (single). Area setup, ventilation

<300,000 repacking, or line-up, Facial PCs, BZs, as setup, Herculite, etc.

dpm/1 00cm 2 rotate blind flanges, required remove boron, etc.

>300,000 Contact HP dpm/1 00cm 2

Symbol Meaning

> greater than

equal to or less than Printed January 12, 2012 at 10:42

Approved By Procedure Number Rev C.R.Dedrickson Vogtle Electric nrating Plant 00930-C 26 Date Approved Page Number 08/05/2009 RADIATION AND CONTAMINATION CONTROL 28 of 28 TABLE 3 SELF MONITORING CONTROLS CHECKLIST Prior to initiating Self Monitoring in a Radiation Controlled Area, perform the following steps:

1. Review the assigned RWP.

2. When utilizing Self Monitoring, the following must be performed:

a. Review the latest HP Routine Surveys for the area where work is to be performed.

b. If the dose and contamination levels are outside the limits set for Self Monitoring in Tables 1 and 2 of this procedure, or if maintenance will requi re breaching of a potentially contam mated system contact H P prior to beginning work.

NOTE Dress requirements will be determined by the latest survey data and should be reevaluated after the initial Self Monitoring Survey is performed.

3. Obtain the appropriate dose and contamination monitoring instrumentation and perform an initial survey of the area where work is to be performed. If the measurements taken are within the limits established by this procedure, work may proceed.

4. Monitor dose and contamination levels during the work process.

5. Perform exit survey. If the dose or contamination levels have increased during the work process, notify HP and document the survey results.

Printed January 12, 2012 at 10:42

SRO Admin Job Performance Measure E Facility: Vogtle Task No: V-LO-TA-40005 Task

Title:

Complete EN Form With Offsite Protective Action Recommendations JPM No: V-NRC-JP-NMP-EP-112-HL17 K/A

Reference:

G2.4.44 SRO4.4 Examinee:

NRC Examiner:

Facility Evaluator: Date:

Method of testing:

Simulated Performance Actual Performance__________________

Classroom Simulator Plant

Read to the examinee:

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

THIS IS A TIME CRITICAL JPM Initial Conditions: A General Emergency has just been declared for Unit 1 due to a loss of Fuel Cladding and RCS fission product barriers and potential loss of the Containment fission product barrier.

This is the first declaration made.

Unit 1 was shutdown 20 minutes ago.

WebEOC is not functional.

Heavy rains have caused wide spread flooding in the CSRA area with several bridges in Burke County washed out and many roads impassable. Heavy rains are continuing.

No elevated radiation conditions exist on any plant effluent monitors.

Meteorological conditions are those on the Classification Determination provided.

The ENN communicator has completed roll call per NMP-EP-1 11 checklist 3.

Initiating Cue: Based on the information given, the Emergency Director directs you to, Manually complete the Emergency Notification form for approval.

2

Task Standard: EN form completed with PAR 1 determined recommendations documented.

. Required Materials: The following materials to be provided to the Candidate:

1 . NMP-EP-1 1 1 Emergency Notifications Ver 4.0 Attachment 1 part 1 Guidance for initial EN Form completion.

2 NM P- EP-1 1 2 Protective Action Recommendations Verl.0

3. Completed NMP-EP-1 1 0 Checklist 1 Classification Determination.

4. NMP-EP-1 11 Checklist 3 Emergency Notifications- Manual Method with the first two steps completed.

5. NMP-EP-1 11, Figure 1 Emergency Notification Form.

General

References:

None Time Critical Task: YES Validation Time: 15 minutes Critical items on Emergency Notification Form are per Procedure 60201-C, Simulator Training & Documentation, which specifies lines required to be done correctly to be satisfactory performance for Emergency Preparedness NRC Performance Indicator.

3

Performance Information

. Critical steps denoted with an asterisk NMP-EP-1 1 1 Checklist 3, Emergency Notifications

, Manual Method.

Step 1 . Obtain a copy of Table 1 then establish contact on the ENN by performing a roll call of the applicable agencies. Check off each agency on Table 1 as acknowledgement is obtained.

Step 2. Roll call:

a. Read the following script:

Standard: Candidate determines these steps are complete from initial conditions.

Comment:

Step 3. If not already completed, complete the emergency notification form (Figure 1).

Guidance for form completion is provided in Attachment 1 Part 1 Guidance for Initial EN Form completion and Attachment 1, Part 2 Guidance for Follow-up EN Form Completion.

Standard: Candidate selects NMP-EP-1 11 Figure 1 and Attachment 1, Part 1.

Comment:

NMP-EP-1 11, Attachment 1 Part 1 - Guidance for Initial EN Form Completion.

Steps 1, 2, 3, 4 of EN Form Completed.

Standard: Candidate completes Lines 1, 2, 3, 4 on Figure 1 EN form per the attached Figure 1 Key. Only boxes filled in black and highlighted text are Critical for task performance.

Comment:

4

Step 5 Protective Action Recommendations.

Standard: Candidate goes to NMP-EP-1 1 2 Protective Action Recommendations.

Comment:

Determine PARs using NMP-EP-1 1 2, Attachment 1 Flowchart.

Standard: Candidate performs flowchart and determines PAR 1.

Has a General Emergency been declared -YES Puff release in progress (projected to exceed PAGs) NO Known Site or plant Event making Evacuation dangerous NO-Known Offsite conditions make evacuation dangerous YES Comment:

For PAR 1, 2, and 3, determine the affected zones using Attachment 4, Table 1.

Standard: Candidate selects Attachment 4 Table 1.

Selects >326 to 349 row.

Selects PAR 1 and 2 frolumn.

Selects , B5, SRS to 2 mile Attachment 5 Figure 1, PAR WORKSHEET, PAR 1 wind direction from filled.

Comment:

5

Complete PAR Worksheet for ED review and approval.

Standard: Candidate may complete Attachment 5 Figure 1 PAR WORKSHEET. See Key next page.

PAR 1 box checked.

Wind Direction from 3300 entered.

ENN line 5 (C) A, B5, SRS to 2 Miles entered.

Comment:

Step 5 (Back to NMP-EP-1 1 1 , Attachment 1 Part 1 ) Protective Action Recommendations completed on EN form.

Standard: Candidate completes Line 5 on Figure 1 EN form per the attached Figure 1 Key. Only boxes filled in black and highlighted text are Critical for task performance.

Comment:

Steps 6 to 13 of EN Form completed.

Standard: Candidate completes lines 6 to 13 on Figure 1 EN form per the attached Figure 1 Key. Only boxes filled in black and highlighted text are Critical for task performance. Steps 14-16 are blank for an initial notification.

Comment:

Terminating cue: Candidate returns cue sheet and completed NMP-EP-1 11 Figure 1.

6

KEY Attachment 5 Figure 1 PAR WORKSHEET INSTRUCTIONS:

1. Check the box for the applicable PAR (1, 2, 3, or 4).

2. Record the 15 minute average wind direction from for the selected PAR.

Use met instrumentation corresponding to primary release point(s) (BWR) Q ground level release (PWR).

3. Use the applicable Site Specific PAR table (Table 1 or 2) to determine the affected zones.

PAR Revisions must include previous PARs.

I[A1o:J On the ENN Form for the selected PAR:

Select block 5.B and record the Evacuate zones OR select block S.C and record the Shelter zones

Select block S.D

IF PAR 4 is selected, THEN additionally select block S.E Other and provide Affected Sectors and To Miles Wind direction from 3300 N/i ENN Line 5 [C]

Shelter Zones A, B5, SRS to 2 Miles L/\J Advise remainder of EPZ to Monitor Local Radio/TV Stations PAR 1 ENN Line 5 [D] /Tone Alert Radios. Consider the use of KI (Potassium Iodide) in accordance with State Plans and Policy Wind direction from ENN Line 5 [B]

Evacuate Zones Advise remainder of EPZ to Monitor Local Radio/TV Stations PAR 2 ENN Line S [D] [Tone Alert Radios. Consider the use of KI (Potassium Iodide) in accordance with State Plans and Policy Wind direction from ENN Line 5 [B]

Evacuate Zones Advise remainder of EPZ to Monitor Local Radio/TV Stations PAR 3 ENN Line 5 [D] [Tone Alert Radios. Consider the use of KI (Potassium Iodide) in accordance with State Plans and Policy Wind direction from ENNL1ne5[B]

Evacuate Zones Advise remainder of EPZ to Monitor Local Radio/TV Stations/

ENN Line 5 [D] Tone Alert Radios. Consider the use of KI (Potassium Iodide) in PAR 4 accordance with State Plans and Policy ENN Line 5 [E] Evacuate Affected Sectors to OTHER miles Approval: I Emergency Director DatelTime 7

KEY Figure 1 Emergency Notification Form (page 1 of 2)

1. DRILL B ACTUAL EVENT MESSAGE# 1

2. INITIAL B FOLLOW-UP NOTIFICATION: TIME DATE I / AUTHENTICATION #_____

3. SITE:

Confirmation Phone # 1-706-826-3652 (SIM)

VOflTI P UNUSUAL EVENT j ALERT SITE AREA EMERGENCY GENERAL EMERGENCY CLASSIFICATION:

BASED ON EAL# FG1 EAL DESCRIPTION Loss of Two FissBarners and Potential loss of the Third Fission PWuct Barrier

5. PROTECTIVE ACTION RECOMMENDATIONS: 1 NONE B EVACUATE SHELTER !RB5 SRS to 2 mi1e 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 Is Occurring Has Occurred

7. RELEASE SIGNIFICANCE: Not applicable j Within normal operating jj Above normal operating II Under evaluation limits limits

8. EVENT PROGNOSIS: Improving Stable Degrading

9. METEOROLOGICAL DATA: Wind Direction from jQ degrees* Wind Speed mph*

(*May not be available for Initial Stability Class*

Rain

Precipitation j j Notifications) *

10. DECLARATION EI TERMINATION Time Date .....j T24Y I

11. AFFECTED UNIT(S):

12. UNIT STATUS: Ul % Power Shutdown at Time _T-20min.. Date .....j_Today_/............

(Unaffected Unit(s) Status Not Required for Initial Notifications) EI U2 % Power Shutdown at Time Date I I

13. REMARKS: None or clarifying 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 iCiIsec MAGNITUDE: Noble Gases:__________ lodines:___________ Particulates:__________ Other:

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

Liquid Start Time Date //.....Stop Time Date _L....L......

15. PROJECTION PARAMETERS: Projection period: Estimated Release Duration Projection performed: Time Date I / 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 completed by receiving organization) 8

Verification of Completion Job Performance Measure No. V-NRC-JP-NMP-EP-112-HL17 Examinees Name:

Examiners Name:

Date Performed:

Number of Attempts:

Time to Complete:

Question Documentation:

Question:

Response

Result: Satisfactory/Unsatisfactory Examiners signature and date:

9

THIS IS A TIME CRITICAL JPM Initial Conditions: A General Emergency has just been declared for Unit 1 due to a loss of Fuel Cladding and RCS fission product barriers and potential loss of the Containment fission product barrier.

This is the first declaration made.

Unit 1 was shutdown 20 minutes ago.

WebEOC is not functional at all facilities.

Heavy rains have caused wide spread flooding in the CSRA area with several bridges in Burke County washed out and many roads impassable. Heavy rains are continuing.

No elevated radiation conditions exist on any plant effluent monitors.

Meteorological conditions are those on the Classification Determination provided.

The ENN communicator has completed roll call per NMP-EP 111 checklist 3.

Initiating Cue: Based on the information given, the Emergency Director directs you to, Manually complete the Emergency Notification form for approval.

Southern Nuclear Operating Company I SOUTHERNKS COMPANY Fyto&eYouWld Checklist 3 Emergency Implementing Procedure Emergency Notifications Emergency Notifications Manual Method (page 1 of 2)

NMP-EP-1 11 Version 4.0 Page 18 of 47 J Transmission of Emergency Notification Message Manual Method NOTES:

1) For notification time purposes (either initial or follow-up notifications) notification time is the time which line 4 of the notification form (Figure 1) is read.

2) The ED should be notified if during the notification process ALL stations fail to respond to the roll call OR a back-up communication system for any agency is being used.

3) The EN Form should be transmitted as soon as it is APPROVED. Do not delay transmittal to complete a Roll Call. Once the EN Form is transmitted, confirm receipt.

Upon receiving direction to prepare to transmit an Emergency Notification Message Obtain a copy of Table 1 then establish contact on the ENN by performing a roll call of the applicable agencies. Check off each agency on Table 1 as acknowledgement is obtained.

,@5 Roll call:

a.

Read the following script:

[Select one] THIS IS A DRILL D ACTUAL EMERGENCY] MESSAGE THIS IS [YOUR NAME] ENN Communicator AT

[Select one] DPlant FARLEY D Plant HATCH Plant VOGTLE AN EMERGENCY HAS BEEN DECLARED FOR EVENTS AFFECTING

[Select one] [Unit 1 D Unit 2 D THE SITE]

PLEASE OBTAIN A BLANK EMERGENCY NOTIFICATION FORM AND STANDBY TO RECEIVE AN EMERGENCY MESSAGE

b. Call each facility by name (see Table 1) and confirm they are standing-by to copy an emergency message.

If not already completed, complete the emergency notification form (Figure 1). Guidance for form completion is provided in Attachment 1, Part 1 Guidance for Initial EN Form completion and Attachment 1, Part 2 Guidance for Follow-up EN Form Completion.

4. Obtain approval to transmit the emergency notification.

Southern Nuclear Operating Company Emergency NMP-EP-1 11 SOUTHERNA Implementing Emergency Notifications Version 4.0 COMPANY ThjtSYoWid Procedure Page 19 of 47 Checklist 3 Emergency Notifications Manual Method (page 2 of 2)

Transmission of Emergency Notification Message Manual Method

5. Transmit the EN Form data verbally utilizing the ENN. Read the notification form (line by line) allowing ample time for the recipient to transfer the verbal data onto a blank form.

Record the NOTIFICATION time (HH:MM) on the message confirmation portion of the EN Form when line 4 of the EN Form is read.

6. Continue by asking:

DO YOU HAVE ANY QUESTIONS CONCERNING THE EMERGENCY NOTIFICATION MESSAGE?

Respond to questions as presented. If necessary, continue discussions with individual agencies off-line to prevent delays in future notifications and to limit voice traffic on the ENN that may be distracting to other agencies.

7. Following transmission of the emergency notification, confirm receipt of the emergency notification.

a. Call each facility by name (see Table 1).

b. Complete the confirmation portion of the Emergency Notification Form (Figure 1, page 2) by recording the name of the person contacted and the time that message receipt was confirmed.

Continuing Actions 1 . Continue by asking:

DO YOU HAVE ANY QUESTIONS CONCERNING THE EMERGENCY NOTIFICATION MESSAGE?

Respond to questions as presented. If necessary, continue discussions with individual agencies off-line to prevent delays in future notifications and to limit voice traffic on the ENN that may be distracting to other agencies.

2. If an individual station cannot be reached via the ENN, use the emergency response telephone directory and a commercial telephone line to contact the individual station directly.

3. If multiple agencies cannot be reached via the ENN, then utilize the phone numbers listed in Table 1, Back-up Communication Systems to contact individual stations directly, as appropriate.

4. For ALERT and higher emergency classification, make follow-up notifications at least every hour or when conditions warrant. When requested, notify alternate state and county notification locations.

Southern Nuclear Operating Company Nuclear NMP-EP-1 10 SOUTHERN Management Emergency Classification Determination Version 1.0 COMPANY Procedure Page 1 1 of 20 0

Checklist 1 Classification Determination (page 1 of 1)

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

Initial Actions Completed by 1 . Determine the appropriate Initiating Condition Matrix for classification of the event ED based on the current operating mode:

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

U 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:

ED LOSS POTENTIALLOSS INTACT Fuel Cladding Integrity E U D Reactor Coolant System E D Containment Integrity E E D

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

(select one) FG1 J FS1 11 FA1 C FU1 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# FG1 or lJ None

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

ED Classification Based on lC# Classification Based on lC#

E General FG1 D Alert DSite-Area DNOUE D None N/A Remarks (Identify the specific EAL, as needed): Loss of Two Fission Product Barriers and Potential Loss of the Third Fission Product Barrier

5. Declare the event by approving the Emergency Classification. D E. 93irector Date: / Today / Time: Now Emergency Director

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

Wind Direction (from) Wind Speed . ED Stability Class Precipitation Rain 330° 4 mrh

7. Initiate Checklist 2, Emergency Plan Initiation. ED

Southern Nuclear Operating Company Emergency NMP-EP-1 11 I A COMPANY Implementing Emergency Notifications Version 4.0 jtSYouWIf Procedure Page 22 of 47 Attachment 1 Part 1 Guidance for Initial EN Form Completion (page 1 of 8)

CAUTION: ALL TIMES RECORDED/TRANSMITTED ON EMERGENCY NOTIFICATION FORMS SHOULD BE LOCAL TIME RELATIVE TO THE EVENT (I.E., HNPNEGP: EASTERN, FNP: CENTRAL). DATE AND TIME STAMPS INITIATED ELECTRONICALLY ARE CONTROLLED AUTOMATICALLY.

NOTES: 1 In the event that the Control Room staff cannot complete the emergency notification form electronically, transfer of notification responsibilities should be accomplished as soon as practicable to allow for usage of the electronic form. Electronic completion of the EN form is preferred.

2. A hardcopy of the electronic notification form may be obtained at any time when the print button is displayed. The printed copy will contain the data populated on the form at the time PRINT is selected.

3. The current copy of the emergency notification form may be saved at any time during the form completion process by selecting SAVE DRAFT.

, 1 . Item 1 : MESSAGE NUMBER is automatically assigned during the transmittal process if using the electronic EN Form tool. Message numbers are sequential for the duration of the Event.

2. Item 2: INITIAL will be checked for any notification associated with the declaration and/or change of an emergency classification.

3. Item 3: SITE Confirm the correct site is displayed. The site location is automatically completed based on prior selections.

CONFIRMATION PHONE NUMBER: Select from the drop down list

4. Item 4: EMERGENCY CLASSIFICATION EAL NUMBER: Select from the drop down list EVENT DESCRIPTION: Confirm the brief description of the initiating conditions for the emergency classification declared is auto completed based on the EAL number selected.

The event description block cannot be edited. Additional information or information relative to competing events should be included on line 13, REMARKS.

Southern Nuclear Operating Company Emergency . NMP-EP-1 11 SOUTHERNS Implementing Emergency Notifications Version 4.0 I COMPANY Page 23 of 47 Procedure

. Attachment 1 Part 1 Guidance for Initial EN Form Completion (page 2 of 8)

CAUTION: PARS MUST BE DEVELOPED, APPROVED AND COMMUNICATED ON THE INITIAL GENERAL EMERGENCY NOTIFICATION WITHIN 15 MINUTES OF THE GENERAL EMERGENCY DECLARATION.

CHANGES TO PARS ARE TO BE DEVELOPED AND APPROVED BY THE ED WITHIN 15 MINUTES AFTER A CHANGE IN CONDITIONS WARRANTING THE PAR. THE NOTIFICATION OF THE APPROVED PARS WILL BE TRANSMITTED TO STATE AND LOCAL AUTHORITIES WITHIN 15 MINUTES AFTER THE EDS APPROVAL AS A FOLLOW-UP MESSAGE.

5. Item 5: PROTECTIVE ACTION RECOMMENDATIONS Parts, , and should be completed as delineated in NMP-EP-112. Ifthe recommended L

protective actions change after the initial GENERAL EMERGENCY declaration is transmitted, a follow-up transmission is required to be initiated within 15 minutes. This information should be obtained from the group responsible for PAR development (e.g., the Dose Assessment Staff in either the TSC or the EOF, as appropriate).

6. Item 6: EMERGENCY RELEASE NOTES: 1 The Emergency Director has the discretion to declare that a radiological release is occurring based on plant conditions that indicate a release is in progress. (i.e., A Steam Generator Tube Rupture with an ARV lifting, site specific effluent radiation monitor readings, etc.)

2. Information for items 6, 7, and 9 are obtained from dose assessment (e.g., Dose Assessment Staff in either the TSC or the EOF, as appropriate).

Use the following table to determine the status of a radiological release:

if an abnormal plant condition exists Select the appropriate release status based on the following:

iE THEN:

Dose assessment results (automated or manual) have been completed AND indicate an emergency radiological release is Check L.

Is Occurring underway At least one effluent monitor* is in alarm, AND completed dose Check Is Occurring projection results (automated or manual) are not available* EJ Elevated indications do not exist on any effluent monitor* Check . None Dose assessment results (automated or manual) have been completed âN indicate an emergency radiological release is Check . None NOT underway

. Dose assessment results indicate an emergency radiological release occurred previously AND is no longer underway.

Applicable monitors are listed in Table 3 Check . Has Occurred

Southern Nuclear Operating Company Emergency NMP-EP-111 SOUTHERNW% Implementing Emergency Notifications Version 4.0 COMPANY Page 24 of 47 I

FjioSeYourW& Procedure Attachment 1 Part 1 Guidance for Initial EN Form Completion (page 3 of 8)

7. Item 7: RELEASE SIGNIFICANCE (Monitors are listed in table 3)

Use the following table to determine the release significance:

IE an abnormal plant condition exists AND: THEN:

Elevated indications do not exist on any effluent monitor* Check . Not applicable Elevated indications exist on at least one effluent monitor*

AND no effluent monitors are in alarm AND completed dose Under evaluation Check assessment results (automated or manual) are not E available Item 6B or 6C is marked and NO effluent monitor is or has been in alarm OR has exceeded the specified threshold L

Check Within normal operating limits 6B or 6C is marked and ANY effluent monitor is or has Check j. Above normal been in alarm OR has exceeded the specified threshold operating limits Dose assessment results indicate an emergency Above normal Check radiological release occurred previously AND is no longer .

operating limits underway.

Applicable monitors are listed in Table 3

Southern Nuclear Operating Company 1

i SOUTHERNS COMPANY F,SeYuWid Emergency Implementing Procedure Emergency Notifications NMP-EP-111 Version 4.0 Page 25 of 47

. Attachment 1 Part 1 Guidance for Initial EN Form Completion (page 4 of 8)

8. Item 8: EVENT PROGNOSIS Indicative of plant conditions and the ability to prevent core damage (e.g., improving, stable, or degrading).

Mark box j Improving if mitigation efforts appear successful, progressing toward termination.

Mark box Stable if escalation to a higher classification is unlikely based on current conditions.

Mark box Degrading if escalation to a higher emergency classification or PAR change is likely.

Attachment 1 Part 1 Guidance for Initial EN Form Completion (page 4 of 8)

NOTE: 1. All reported meteorological data should be 15 minute average data.

Data provided for meteorological parameters should be consistent with data utilized for PARs dose projections reported in line 16, if applicable.

2. Inconsistencies in meteorological data utilized for dose projections and the meteorological data reported on emergency notification forms can result in discrepancies in dose assessments performed by SNC and applicable State and Federal agencies.

Southern Nuclear Operating Company Emergency NMP-EP-111 I SOUTHERNE%

COMPANY E,toSywtd Implementing Procedure Emergency Notifications Version 4.0 Page 26 of 47 Attachment 1 Part 1 Guidance for Initial EN Form Completion (page 5 of 8)

9. Item 9: METEOROLOGICAL DATA Record the 15-minute averaged Wind Direction from, Wind Speed and Precipitation values and check the appropriate Stability Class (AT). Sources for meteorological data are listed in Table 4.

FARLEY Stability class AT value Sigma Theta (a8)

A <-1.74 22.5 B -1.74 to <-1.56 17.5 to 22.5 c -1.56to<-1.38 12.5to17.5 D -1.38to<-.46 7.5to 12.5 E -.46to<1.38 3.8to7.5 F 1.38to<3.6 2.1 to 3.8 G 3.6 <2.1 HATCH Differential Temperature (DT)(°F) Sigma Theta (aO)

Primary & Backup Met Primary Met Tower Backup Met Tower Towers Stability Class lOOm-lOm 60m-lOm 45m-lOm 100, 60, 45, & 10 m C A B

<-3.1

-3.1 to<-2.8

<-1.4

-1.4to<-1.3

<-1.2

-1.2to-1.1 22.5

<22.5to 17.5 c -2.8to<-2.4 -1.3to<-1.1 -1.1 to<-O.9 < 17.Sto 12.5 D ?-2.4to<-O.8 -1.1 to<-O.4 ?O.9to<-O.3 <12.Sto?7.5 E ?-O.8to<2.4 ?O.4to<1.1 -O.3to<O.9 <7.5to3.8 F 2.4to<6.5 1.1to<2.9 O.9to<2.5 <3.8to2.1 G 6.5 2.9 ?2.5 <2.1 VOGTLE Stability Class Sigma Theta (ae)

A 22.5 B 17.5 to 22.5 c 12.5to17.5 D 7.5to12.5 E 3.8 to 7.5 F 2.lto3.8 G <2.1

Southern Nuclear Operating Company Emergency . NMP-EP-1 11 I SOUTHERN%i COMPANY FjtoSYW1d Implementing Procedure Emergency Notifications Version 4.0 Page 27 of 47 Attachment 1 Part 1 Guidance for Initial EN Form Completion (page 6 of 8)

10. Item 10: DECLARATION or TERMINATION Enter the time and date (mm/dd/yy) when the current emergency classification was declared or terminated.

11. Item 11: AFFECTED UNIT(S) Check the affected unit or ALL block if both units are affected by the EAL indicated in item 4. For events involving equipment that is common to both units, ALL should be selected.

NOTE: The unaffected units status is not required for initial notifications.

However, the unaffected units status is required for follow-up notifications.

12. Item 12: UNIT STATUS IF the affected unit is operating, THEN indicate the % power. If the affected unit is shutdown, then enter the time (HH:MM) and date of the shutdown.

13. Item 13: REMARKS Record any current information related to the emergency such as significant events which have occurred, significant equipment which is out of service or malfunctioning, events occurring which may impact offsite resources (i.e., dismissal of non-essential personnel, etc), updates on previously reported information (i.e., status of event which previously occurred) and/or additional information that is of lower importance. This section may also be utilized to clarify the EAL description provided in Item 4.

Corrected information from previous notifications may be clarified in this section. For clarity reference previous notification number and line item as appropriate (i.e., line 1 1 of message number 5 incorrectly listed the affected unit as Unit 1. Line 11 of this form reflects the correct information.

For the electronic form, this section is limited to 275 characters. A character count is provided for reference when completing this section.

For Initial Notification or if radiological release or dose assessment information is not available then go to Step 17 APPROVAL NOTE: Lines 14 through 16 (FOLLOW-UP ACTIONS) should be completed and transmitted as soon as dose projection information is available after the onset of any release otherwise, GO to Step 17 APPROVAL.

Southern Nuclear Operating Company Emergency NMP-EP-1 11 I COMPANY Implementing Procedure Emergency Notifications Version 4.0 Page 28 of 47 Attachment 1 Part 1 Guidance for Initial EN Form Completion (page 7 of 8)

14. Item 14: RELEASE CHARACTERIZATION 1 Select the appropriate release point characterization for the affected unit(s).

a. FOR E!+/-E and VEGP: Confirm Ground Level is checked. This selection is auto-selected based on SITE selection of FNP or VEGP.

b. FOR HNP ONLY Mark box if the release is ELEVATED (through the main stack).

Mark box j if the release is GROUND (through the reactor building vents)

Mark box if the release is MIXED (combination of elevated and ground level release)

Consult with the dose assessment staff for the completion of this item.

IF the release type is NOT known, assume that the release is ELEVATED FOR ALL PLANTS

2. Indicate the units of measurement of the release (Ci, Ci/sec or pCi/sec), consult dose assessment.

3. Record the Noble Gas, Particulate and Iodine values from the latest available dose projection. Values reported should be consistent with those contained on the dose projection utilized in the PAR evaluation, as appropriate.

4. Check the appropriate block to indicate the status of Airborne or Liquid release(s) by entering the start time (HH:MM) and if applicable the time (HH:MM) and date (mm/dd/yy) the release stopped. Use the time zone local to the plant.

15. Item 15: PROJECTION PARAMETERS Enter the duration of the dose projection period and the estimated release duration from the latest available dose projection. The value reported should be consistent with that utilized in the PAR evaluation. The default dose PROJECTION PERIOD and ESTIMATED RELEASE DURATION are 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . ACCIDENT TYPEs are provided in Table 2.

16. Item 16: PROJECTED DOSE IF Item 7, RELEASE SIGNIFICANCE, is marked A or B, THEN Enter less than 0.02 mrem (<0.02) for TEDE and Thyroid CDE dose for the site boundary OTHERWISE Enter the data provided from the dose assessment staff.

Enter the projected Total Effective Dose Equivalent (TEDE) and Committed Dose Equivalent (CDE) thyroid dose (in mRem) at site boundary, 2, 5, and 10 miles distances provided by the dose assessment staff. Attachment 1 Part 1 Guidance for Initial EN Form Completion (page 8 of 8)

Southern Nuclear Operating Company Emergency NMP-EP-1 11 I

j Implementing Procedure Emergency Notifications Version 4.0 Page 29 of 47

17. Item 17: Review and Approval

a. Manual Form IF possible, obtain a peer check of the completed form. The Emergency Director must approve the form. Verbal authorization may be given to a delegate such as the EOF Manager to sign on behalf of the ED.

b. Electronic Form NOTE: Obtain concurrence and approval of emergency information from the ED (in the Control Room or TSC) or the EOF Manager (in the EOF), as appropriate, PRIOR to transmission of any message to offsite authorities.

Any changes to the form after approval will require the approvers concurrence. Approval may be verbal or obtained by signature of a hardcopy of the emergency notification form.

1 . Notified By: Enter the name of the individual completing the emergency notification form.

2. Select Validate and follow the instructions provided to correct any Items identified during the validation process.

Following correction of any identified Items, re-select Validate.

3. Select Print to obtain a hardcopy for review/approval. For verbal approvals, no hardcopy is required.

4. Obtain final approval of the ED or EOF Manager, as appropriate.

5. Time/Date: Enter the time (HH:MM) and date (mm/dd/yy) the emergency notification form is approved. The specified format is required to proceed.

NOTE: 1. APPROVAL is available only after satisfactory VALIDATION

2. When completing the notification form electronically, no changes may be made to the current form following electronic approval. A follow-up notification must be completed to convey the changed information.

6. Select Approval WebEOC will prompt you to confirm your approval of the form. Select OK to approve or cancel to continue without approval.

Southern Nuclear Operating Company Emergency NMP-EP-1 II SOUTHERN Implementing Emergency Notifications Version 4.0 Procedure Page 35 of 47 Figure 1 Emergency Notification Form (page 1 of 2) 1DRILL MACTUALEVENT MESSAGE#_____

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

3. SITE: Confirmation Phone # 1-706-826-3652(SIM)

UNUSUAL EVENT j ALERT SITE AREA EMERGENCY GENERAL EMERGENCY CLASSCA]iON:

BASED ON EAL#__________ EAL DESCRIPTION:__________________________________________________

5 PROTECTIVE ACTION RECOMMENDATIONS: NONE EVACUATE SHELTER 1

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 Is Occurring Ij Has Occurred TRELEASESNlFANCEapphcab Wfthinnormal op&atingovenornaI operangr limits limits evaluation

8. EVENT PROGNOSIS: Improving Stable Degrading

9. METEOROLOGICAL DATA: Wind Direction from degrees* Wind Speed for Initial Nmcaon:)* Precipitation Stability Class* j j DECLARATION TERMINATION Time Date I I I . AFFECTED UNIT(S): fl 12.UNITSTATUS: U1 ShutdownatTime Date I I (Unaffected Unit(s) Status Not Required for Initial Notifications) M U2 Power Shutdown at Time Date _I I

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 j Mixed Ground UNITS: Ci j Ci)sec pCi/sec MAGNITUDE: Noble Gases:___________ lodines:____________ Particulates:___________ Other:

FORM: Airborne Start Time Date I /Stop Time Date _/ I Liquid Start Time Date _/ /Stop Time Date _/ /...

I 1 5. PROJECTION PARAMETERS: Projection period: Estimated Release Duration Projection performed: Time Date _/ I 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 Date_/ I

, NOTIFIED BY:

RECEIVED BY: Time (To be completed by receiving organization)

I

Southern Nuclear Operating Company Emergency NMP-EP-1 11 SOUTHERN Implementing Emergency Notifications Version 4.0 f Procedure Page 36 of 47 Figure 1 Emergency Notification Form (page 2 of 2)

GOVERNMENT AGENCIES NOTIFIED Record the name, date and agencies notified:

(name)

(date/time) (agency) 2.

(name)

(date/time) (agency) 3.

(name)

(date/time) (agency) 4.

(name)

(date/time) (agency) 5.

(name)

(date/time) (agency) 6.

(name)

(date/time) (agency) 7.

(name)

(date/time) (agency)

Southern Nuclear Operating Company Emergency NMP-EP-1 12 SOUTANY Implementing Protective Action Recommendations Version 1.0

[,tSYW1d Procedure Page 1 of 18 Procedure Owner: Chris Boone I Fleet Emergency Preparedness Manager I CorDorate (Print: Name I Title I Site)

Approved By: Original signed by Christopher E. Boone on 09/24/2010 (Peer Team Champion/Procedure Owners Signature / Date)

Effective Dates: 09/27/201 0 09/27/201 0 1 1/08/201 0 09/27/2010 Corporate FNP HNP VEGP The individuals listed below are the members of the Peer Team responsible for writing and maintaining this procedure.

Corporate J. D. Grant Plant Farley S. M. Odom Plant Hatch R. W. Ott Plant Vogtle L. E. Mayo PROCEDURE USAGE REQUIREMENTS SECTIONS Procedure must be open and readily available Continuous at the work location. Follow procedure step by Use: step unless otherwise directed by the procedure.

Procedure or applicable section(s) available at Reference Use: the work location for ready reference by person ALL performing_steps.

Information Available on site for reference as needed.

Use:

Printed: 1/11/2012

Southern Nuclear Operating Company Emergency NMP-EP-1 12 souT:ItANY Implementing Protective Action Recommendations Version 1.0 Procedure Page 2 of 18 Revision Description Version Number Revision Description 1.0 This procedure supersedes NMP-EP-109, Protective Actions Recommendations. This procedure has been developed to facilitate the implementation of a fleet approach for the performance of initial emergency actions (e.g., classifications, notification and PARS). No technical changes have been made to the procedure. The procedure has been re-issued with a different procedure number to be consistent with the fleet approach for the performance of activities in response to an event.

Printed: 1/11/2012

Southern Nuclear Operating Company Emergency NMP-EP-1 12 SOUTHERN Implementing Protective Action Recommendations Version 1.0 Procedure Page 3 of 18 TABLE OF CONTENTS 1.0 PURPOSE 4

3.0 REFERENCES

4 4.0 DEFINITIONS 5 5.0 RESPONSIBILITIES 6 ATTACHMENT 2- PLANT FARLEY AFFECTED ZONES FOR PARS 12 ATTACHMENT 3-PLANT HATCH AFFECTED ZONES FOR PARS 14 ATTACHMENT 4- PLANT VOGTLE AFFECTED ZONES FOR PARS 16 ATTACHMENT 5- PAR WORKSHEET 18 Printed: 1/11/2012

Southern Nuclear Operating Company Emergency NMP-EP-1 12 SOUTHERN Implementing Protective Action Recommendations Version 1.0 En(tSvYW1d Procedure Page 4 of 18 1.0 PURPOSE This procedure provides guidelines for determining Protective Action Recommendations (PARs) which will be communicated to offsite authorities during a General Emergency.

PARs are provided as an input to the protective action decision making process for the development of protective action orders. Protective action orders are communicated to the general public by offsite authorities to avoid or reduce the exposure incurred from an accident condition that results in a significant radiological effluent release or has the potential for a release based on degraded plant conditions.

2.0 APPLICABILITY Protective actions are recommended to offsite authorities to avoid or reduce the radiological exposure that may be incurred by the public from an accident condition that results in a significant radiological effluent release or has the potential for a release based on degraded plant conditions.

This procedure is performed, as required, during drills, exercises, and declared emergencies following declaration of a General Emergency. Attachments 2, 3, and 4 are sitespecific. Non-applicable site attachments may be removed and discarded to ensure usage of the correct site-specific attachment.

3.0 REFERENCES

3.1 NRC IN 83-28, Protective Actions Based on Plant Conditions 3.2 EPA-400-R-92-OO1 Manual of Protective Action Guides and Protective Actions for Nuclear Incidents, October, 1991 3.3 NRC IN 91-72, Issuance of a Revision to the EPA Manual of Protective Action Guides and Protective Actions for Nuclear Incidents 3.4 NRC IN 92-08, Revised Protective Action Guidance for Nuclear Incidents 3.5 NRC RIS 2003-12, Clarification of NRC Guidance for Modifying Protective Actions 3.6 NUREG-0654/FEMA REP 1 Supplement 3 3.7 NRC RIS 2004-13, Consideration of Sheltering in Licensees Range of Protective Action Recommendations, August 2, 2004 3.8 NRC RIS 2004-13, Supplement 1, Consideration of Sheltering in Licensees Range of Protective Action Recommendations, Dated Aug. 2004, March 10, 2005 3.9 NRC RIS 2005-08, Endorsement of NEI Guidance Range of Protective Actions for Nuclear Power Plant Incidents, June 6, 2005 Printed: 1/11/2012

Southern Nuclear Operating Company Emergency NMP-EP-1 12 SOUTHERN Implementing Protective Action Recommendations Version 1.0 Procedure Page 5 of 18 4.0 DEFINITIONS 4.1 EPA PROTECTIVE ACTION GUIDELINE (PAG) exposure levels determined by the Environmental Protection Agency for the evacuation of the offsite public following a release of radioactive materials. These levels have been established at one (1 ) Rem TEDE or five (5) Rem CDE Thyroid.

4.2 PROTECTIVE ACTION RECOMMENDATIONS (PARs) shelter, evacuation, monitor, and/or KI recommendations made by SNC to appropriate state agencies.

PARs are made by SNC personnel based on the Attachment 1 Flowchart whenever a General Emergency is declared. Additionally, if in the opinion of the ED, conditions warrant the issuance of PARs, a General Emergency will be declared (SNC will not issue PARs for any accident classified below a General Emergency).

4.3 UNCONTROLLED RELEASE is a radiological effluent release that cannot be immediately stopped via positive control action (Example: Vent stack release from a known or unknown Containment leakage pathway which is not under the control of the shift and requires time to terminate.)

4.4 CONTROLLED RELEASE is a planned radiological effluent release that can be immediately terminated by the licensee (Example: closure of the Post LOCA CTMT vent valves that were manually opened to lower Containment pressure.).

4.5 PUFF RELEASE A controlled release that is projected to exceed the PAGs and will be terminated in less than an hour or an uncontrolled release that was projected to exceed the PAGs and has been terminated.

4.6 TOTAL EFFECTIVE DOSE EQUIVALENT (TEDE) The sum of the deep dose equivalent (for external exposures) and the committed effective dose equivalent (for internal exposures).

4.7 COMMITTED DOSE EQUIVALENT (CDE) The dose equivalent to organs or tissues of reference that will be received from an intake of radioactive material by an individual during the 50-year period following the intake.

4.8 TONE ALERT RADIO (TAR) Radio used to provide emergency information to the public living in the 10 mile emergency planning zone around the sites.

Printed: 1/11/2012

Southern Nuclear Operating Company Emergency NMP-EP-1 12 SOUTHERN Implementing Protective Action Recommendations Version 1.0 Procedure Page 6 of 18 5.0 RESPONSIBILITIES 5.1 The Emergency Director (ED) has the non-delegable responsibility for approving PARs.

5.1 .1 The EOF Manager may sign approval for the ED after receiving verbal approval from the ED.

5.2 Once the TSC is operational, the TSC has responsibility for developing and communicating offsite PARs until relieved of that responsibility by the EOF.

5.3 Approved PARs may be communicated to applicable offsite authorities by the staff in either the Control Room, TSC or EOF as directed by the ED.

6.0 PRECAUTIONS AND LIMITIATIONS 6.1 Evacuation and Shelter Recommendations 6.1 .1 PARs are only applicable when entering a General Emergency.

6.1 .2 Evacuation is the preferred action unless conditions impose a greater risk from the evacuation than from the dose received.

6.1 .3 Shelter is a preferred action when a Puff type release has occurred.

6.1 .4 A plant condition based PAR to shelter a 2-mile radius and 5 miles downwind may be issued when a Puff Release has occurred.

6.1 .5 If onsite plant events are underway which would make evacuation dangerous (such as known hostile action) then sheltering should be considered over evacuation recommendations.

6.1.6 When prior knowledge of offsite impediments to evacuation exist (such as flooding, bridge/road closings, or other travel restrictions), then sheltering should be considered over evacuation recommendations.

6.1.7 A recommendation to evacuate or shelter a partial zone is not allowed.

6.1.8 Once an evacuation recommendation for an area has been given, it should not be reduced to a shelter recommendation.

Printed: 1/11/2012

Southern Nuclear Operating Company Emergency NMP-EP-1 12 SOUTHERN Implementing Protective Action Recommendations Version 1.0 EroSrr1d Procedure Page 7 of 18 6.2 ED Judgment 6.2.1 The ED may elect to modify PARs based on judgment, if conditions warrant.

6.2.2 The ED shall upgrade to a General Emergency if PARs are determined to be needed and not already in a General Emergency.

6.2.3 Protective action guidelines shall not imply an acceptable dose.

6.2.4 PARs are inherently conservative such that expanding the evacuation zone as an added precaution would result in a greater risk from the evacuation than from the radiological consequences of a release. It also would dilute the effectiveness of the offsite resources used to accommodate the evacuation.

6.3 Recommendations Beyond the 10 mile EPZ 6.3.1 Many assumptions exist in dose assessment calculations, involving both source term and meteorological factors, which make computer predictions over long distances less reliable. The ED should use the recommendation of the dose assessment staff when making recommendations beyond 10 miles.

6.3.2 While evaluating the need to develop PAR 4 recommendations, issuance of appropriate PAR 1 2, or 3 recommendations should not be delayed.

6.4 Ingestion Pathway and Relocation Responsibilities 6.4.1 Protective actions taken in areas affected by plume deposition following the release are determined and controlled by offsite governmental agencies. SNC is not expected to develop offsite recommendations involving ingestion or relocation issues following plume passage.

6.4.2 SNC may be requested to provide resources to support the determination of post plume protective actions.

Printed: 1/11/2012

Southern Nuclear Operating Company Emergency NMP-EP-1 12 SOUTHERN Implementing Protective Action Recommendations Version 1.0 Procedure Page 8 of 18 6.5 Continuing Assessment 6.5.1 Weather should not normally influence SNC protective action recommendations for the public except for changes in plume trajectory.

The States and Counties are the most knowledgeable concerning current weather conditions and weather forecast information. The States and Counties may incorporate existing or forecast weather in their decisions regarding implementation of recommended protective actions.

6.5.2 Only the MUTUALY AGREED UPON protective action recommendations specified in Attachment 1 should be recommended unless there are obvious relevant factors (e.g., severe natural phenomena like hurricanes) that probably were not anticipated when the PARs were developed and that would make the standard PAR recommendations impractical or obviously non-conservative. In such events, the ED should use judgment as appropriate.

6.5.3 Actual field readings from Field Monitoring Teams should be compared to dose assessment results and used as a dose projection method to validate calculated PARs and to determine whether the plant or dose based protective actions are adequate.

6.5.4 When available, actual sample data from monitored or unmonitored release points should be utilized in conjunction with other dose assessment and projection methods to validate calculated PARs and to determine whether the plant based protective actions are adequate.

6.5.5 VEGP and FNP off-site dose rates may be significantly higher (up to 10 times) due to volatilization of iodine if a steam generator (SG) water level falls below the break point during a SG tube rupture 7.0 PROCESS DESCRIPTION Guidance is provided in the form of attachments. Attachment 1 Action Checklist for Off-Site PAR Development, Attachment 2, Farley Site Specific Data Sheets, Attachment 3, Hatch Site Specific Data Sheets, Attachment 4 Vogtle Site Specific Data Sheets, and Attachment 5 PAR Worksheet direct the initial and supplemental actions.

8.0 RECORDS Records generated during actual emergencies will be maintained as QA records in accordance with applicable administrative procedure.

9.0 COMMITMENTS Farley None Hatch - 1989301429, 1990303261, 1990303410 Vogtle 1985304693, 1985304906, 1986309134 Printed: 1/11/2012

Southern Nuclear Operating Company Emergency NMP-EP-1 12 SOUTHERN Implementing Protective Action Recommendations Version 1.0 Procedure Page 9 of 18 Attachment 1 Continuing Activity (Page 1 of 3)

Action Checklist for PAR Development NOTE: ONLY THE MUTUALY AGREED UPON PROTECTIVE ACTIONS SPECIFIED BELOW SHOULD BE RECOMMENDED UNLESS THERE ARE OBVIOUS RELEVANT FACTORS (E.G., SEVERE NATURAL PHENOMENA LIKE HURICANES) THAT PROBABLY WERE NOT ANTICIPATED WHEN THE PARS WERE DEVELOPED AND THAT WOULD MAKE THE STANDARD PAR RECOMMENDATIONS IMPRACTICAL OR OBVIOUSLY NON-CONSERVATIVE. IN SUCH EVENTS, THE ED SHOULD USE JUDGMENT AS APPROPRIATE.

A. INITIAL ACTIONS Please Check 1 .

Precautions and Limitations are applicable in development of Protective Action Recommendations (PARs) in subsequent steps. Attachment 5, Figure 1 PAR WORKSHEET, may be used to record affected zones or sectors.

2. Determine General Emergency PARs using the Attachment 1 Flowchart.

. PAR 1 Shelter to 2 miles and 5 mile downwind zones

. PAR 2 Evacuate to 2 miles and 5 mile downwind zones

. PAR 3 Evacuate to 5 miles and 10 mile downwind zones

. PAR 4 Guidance for PARs Beyond the 1 0 Mile EPZ CAUTION - PAR Revisions must include previous PARs

3. For PAR 1 2, and 3, determine the affected zones using Site specific Table 1 An electronic program may also be used.

NOTE: Once conditions requiring a PAR change are available, PARs should be developed as soon as possible. (The expectation for development is 15 minutes after the change in conditions.)

4. Communicate developed PARs to the ED for review and approval.

NOTE: Once PARs are developed they should be communicated to appropriate agencies as soon as possible. (The expectation for communication is 15 minutes after development, as directed by position specific instructions.)

5. Communicate ED approved PARs to offsite agencies using appropriate procedural guidance. On the ENN Form ensure that the following PAR information is selected:

Select block 5.B and record the Evacuate zones OR select block 5.C and record the Shelter zones

Select block5.D

IF PAR 4 selected THEN additionally select block 5.E Other and provide Affected Sectors and To Miles.

Printed: 1/11/2012

EZ Southern Nuclear Operating Company II SOUTHERN Emergency NMP-EP-112 I Implementing Protective Action Recommendations Version 1.0 I Procedure Page 10 of 1 Continuing Activity Attachment 1 (Page 2 of 3)

Action Checklist for PAR Development (Cont)

B. SUPPLEMENTAL ACTIONS Fease Checic

1. Continue assessment actions applying applicable Precautions & limitations.

LI

2. E a release is in progress TliJi it is appropriate to dispatch Field Monitoring Teams (FMT) to downwind and adjacent areas as soon as possible. FMT data should be used to validate calculated exposure rates by comparison with actual field exposure rates to ensure issued PARs remain conservative.

3. For PAR 4, determine the affected sectors using Site specific Table 2. The following considerations apply when developing PARs beyond 1 0 miles: LI

. I.E a release is in progress and dose assessment calculations indicate a possible need to issue PARs beyond 1 0 miles, flii it is appropriate to re perform dose assessment calculations to verify calculation assumptions and accuracy prior to issuing PARs beyond 10 miles.

. Use any available FMT readings, IF available, to validate accuracy of the projection model prior to issuing PARs beyond 1 0 miles.

. LE dose assessment calculations indicate the need to recommend actions beyond 1 0 miles, fliii consult with affected State agency(s) to corn pare!

validate model assumptions prior to issuing PARs beyond 10 miles.

4. if conditions requiring PAR 1 entry are eliminated or dose projections change such that additional PARs are required Tjj.N return to the Initial LI Actions section. Once conditions requiring PAR change are available, PARs should be developed as soon as possible. (The expectation for development is 1 5 minutes after the change in conditions.) Once PARs are developed they should be communicated to appropriate agencies as soon as possible.

(The expectation for communication is 1 5 minutes after development, as directed by position specific instructions.)

5. Apply dose projection results in continuing assessment activities. Dose assessment results should be used to refine (but not reduce) protective LI action recommendations after adequate data becomes available.

6. Utilize real time meteorological and effluent radiation monitor readings in continuing assessment activities. j. radiation monitor readings provide LI sufficient data for assessment, ]JEN it is NOT appropriate to wait for field monitoring data to become available to confirm or expand a PAR within the 10-mile EPZ.

Dose projections are NOT required to support the decision process in development of the plant condition based PARs utilizing the PAR flowchart if no release is in progress. It is expected that a dose projection will be performed as soon as practicable at a General Emergency with a release in progress to determine if PAR change is needed.

Q Printed: 1/11/2012

Southern Nuclear Operating Company Emergency NMP-EP-1 12 SOUTHERN Implementing Protective Action Recommendations Version 1.0 Procedure Page 11 of 18 Attachment 1, Flowchart Is a (Page3of3)

-eraI Emerg V In Progress or Been N. PAR1 BeenDecIaredecIared YES fr Terminated That Is .> YES SHELTER ected to Excee 0 2 mile radius And downwind to 5 miles NO NO Advise Remainder of V _

EPZ to Monitor Local CONTINUE saKn own Radio/TV Stations/

ASSESSMENT or Plant Event TARs for Additional Underway Making N-YE5

Information Return to START 4

Evacuation .7

-_- Consider the use of KI PAR2 in accordance with EVACUATE State plans and policy NO 0 2 mile radius And downwind to Refer to site specific 5 miles Table 1 or computer program for affected

. zones Advise Remainder of e Conditions Make -YES

EPZ to Monitor Local Evacuation Radio/TV Stations/ Dangerous CONTINUE TARs for Additional ASSESSMENT Information D°n°wn Return to START NO Consider the use of KI in accordance with PAR3 State plans and policy

___z%aveDoses EVACUATE Beyond the SN. 0 5 mile radius Refer to site specific 0- NO < Been Projected to >YES

And downwind to Table 1 or computer %%%%%%

Exceed ,Z 10 miles program for affected PAGs*7 zones Advise Remainder of EPZ to Monitor Local Radio/TV Stations/

TARs for Additional Information Have Doses Consider the use of KI CONTINUE Beyond 10 Miles in accordance with ASSESSMENT + NO Been Projected to State plans and policy Return to START Exceed PAG5* Refer to site specific Table 1 or computer program for affected YES V zones PAR4 Evaluate the Need for PARs *PAG5 Beyond 10 Miles - Refer to

1000 mREMTEDE or Table 2

5000 mREM Thyroid CDE Printed: 1/11/2012

Southern Nuclear Operating Company Emergency NMP-EP-112 I SOUTHERN Implementing Protective Action Recommendations Version 1.0 Procedure Page l2of 18 Attachment 2 Table 1 PLANT FARLEY AFFECTED ZONES FOR PROTECTIVE ACTION RECOMMENDATIONS PARland2 PAR3 WIND DIRECTION AFFECTED AFFECTEp FROM (degrees) ZONES ZON*

N, > A, B5, 05, J5,K5 A, B5, 05, D5, E5, F5, 15, J5, K5.B10, ClO, K10 NNE, >T A, B5 C5, D5, K5 A, B5,C5, D5, E5, BlO, ClO, D10 4(

NE, >34 56 A, B5 C5, D5 A, B5, 05, D55, 15, J5, K5, B ClO, D1O 4 : -

1w ENE, >5679 A, 05, D5, E5 . A, B5, 05 D5, FJ5, K5, cio,:bio, ElO

- - ,\ <

, 4 E, >79-101 A, D5, E5, F5 A, B5, 05, D5 5F5, 15, J5, K5, 010, D10, ElO

, K c ;ss<

ESE, >101 124 A, D5 E5 F5 5, 05, D5, E5, F5,1K5, D10, ElO, FlO SE,>124146 A,E5,F5 A,B5&,D5,E5,IJ5,K5,E10,F10 T

Y M SSE, >146 169 A, \ PB5,C5,5, 15, J5, K5, ElO, F1 GlO 2

>169 191 A, E5,F5,I5 II6i4 s >

E5, F5, 15, J5 K5, FlO, Gb, H10 ssw, >191 214 AI5 B5 05, D5 E5, F5, 15, J5, K5, FlO, Gb, H10, 110

\

SW, >2142$36 A, F5, 15, 05, D5, E5, F5, 15, J5, K5, FlO, Gb, H10, 110,

. Vio WV6-2. A, 15, A, B5, 05, D5, E5, F5, 15, J5, K5, Gb, H10, 110, J10 w, >259s A, 15, J5 A B5,C5, D5, E5, F5, 15 J5, K5 H10, 110, J10 K10 WNW, >281 304 , J5, K5 A, B5, C5,D5, E5, F5, 15, J5, K5, 110, J10, K10 NW, >304 326 - A, B5, J5, K5 A, B5, 05, D5, E5, F5, 15, J5, K5, BlO, J10, K10 NNW, >326 349 A, B5, 05, J5, K5

- A, B5, C5, D5, E5, F5, 15, J5, K5, BlO, K10 Printed: 1/11/2012

Nuclear Operating Company Southern Emergency NMP-EP-1 12 SOUTHERN Implementing Protective Action Recommendations Version 1.0 COMPANY Ysld Procedure Page 13 of 18 Attachment 2 Table 2 PLANT FARLEY GUIDANCE FOR PARS BEYOND THE 10 MILE EPZ 1 . Calculate the Evacuation Distance by determining the maximum Projected Distance where MIDAS dose projections exceed PAGs and adding 5 miles to the projected distance.

Projected Distance (miles) + 5 miles = Evacuation Distance (miles)

2. Determine the affected sectors for the current 1 5 minute average (From) wind direction Affected Sectors

3. Recommend Evacuation from 10 miles to the Evacuation Distance (calculated in step 1) for the Affected Sectors (determined in step 2). .

4. Check Line 5, Item E Other on the Emergency Notification Form and record the recm mended sectors and distance range in miles for Evacuation. (No)e: Refer to 50 mile IPZ map as necessary)

PAR4 WIND DIRECTION FROM (degrees) AFFECTED SEcORS N, >349-11 H,J,Kj NNE,>1134 NE, >34 56 43 .:

ENE,>56- ,. L,M,N E, >79-101 M, N, P ESE,>101-124 -;ø N,P,Q

( 6 SE, >124-146 \

p, Q, R SE.-169 Q,R,A E 69 i 1 - R,A,B SSW,>191-214 A,B,C

.:/ SW, !14-236 B, C, D Qg$g&

wSw, >236-259 C, D, E 2Th W, >259 281 D, E, F 881 WNW, >281 304 E, F, G NW, >304 326 - F, G, H NNW, >326 - 349 G, H, J Printed: 1/11/2012

Nuclear Operating Company Southern Emergency NMP-EP-1 12 SOUTHERN A Implementing Protective Action Recommendations Version 1.0 COMPANY Procedure Page 14 of 18 Attachment 3 Table 1 PLANT HATCH AFFECTED ZONES FOR PROTECTIVE ACTION RECOMMENDATIONS PARland2 PAR3 WIND DIRECTION AFFECTED . AFFECTED FROM (degrees) ZONES ZONES N, > 349- 11 A, B5, 05 A, B5, C5, D5, E5, dO, D10, NNE, >11 34 A, B5, C5 A, B5, C5, D5, E5, D1O, ElO, F1OP\

NE, >34 56 A, B5, 05 A, B5, 05, E5, ElO, , GlO ENE, >5679 A, 05 A, B5D5, E5, ElO, FlO, G1O o c E, >79-101 A, C5, D5 5, CD5, E5, FlO, GlO, H1O

$/4 ESE, >101 124 A, 05, D5 A, B5, C55, Gb, 110 SE, >124-146 A,,C5, D5,EG10, H10, 110 SSE, >146 - 169 A, 05, D5, E5 A, j., D5, E5, H10, 110, J10

- :-c- S L LI Z L 5, >169 - 191 A, D5 A, B5, c5b5, E5, 110, J10 SSW, >191 - 214 A, D5, . C5, D5, E5, 110, J10

/ 4 -- a SW, >214-236V E5 A, B5, C5, DE5, J10, Kb, L10 WS\>236-259 P B5, C5, D5, E5, J1O,K10, L10

\ \

\ i \

A, B5, A, B5, C5, D E5, BlO, K10, L10

?

WNW, >281 A, B5, E5 A, B5, 05, D5, E5, BlO, dO, D10, Kb, L10 w N; NW, >304 326 - A, B5 A, B5, C5, D5, E5, BlO, dO, D10

z_

NNW, >326 349 A, B5, C5- A, B5, 05, D5, E5, BlO, dO, D10, ElO

, y Printed: 1/11/2012

I Emergency Southern Nuclear Operating Company NMP-EP-1 12 SOUTHERN Implementing Protective Action Recommendations Version 1.0 COMPANY Procedure Page 15 of 18 0

Attachment 3 Table 2 PLANT HATCH GUIDANCE FOR PARS BEYOND THE 10 MILE EPZ 1 . Calculate the Evacuation Distance by determining the maximum Projected Distance where MIDAS dose projections exceed PAGs and adding 5 miles to the projected distance.

Projected Distance (miles) + 5 miles = Evacuation Distance (miles)

2. Determine the affected sectors for the current 15 minute average (From) wind direction Affected Sectors

3. Recommend Evacuation from 10 miles to the Evacuation Distance (calculated in step 1) for the Affected Sectors (determined in step 2).

A

4. Check Line 5, Item E Other on the Emergency Notification Form and record the recommended sectors and distance range in miles for Evacuation. (Note: Refer to 50 mile IPZ map as necessary)

PAR4 WIND DIRECTION FROM (degrees) AFFECTED SECTOP N,>349-11 % HJK NNE,>1134 J,K,L NE,>3456 KLM ENE,>5679 wi L M N E,>79-1O1 M N P s

ESE>1O1124\. N,P,Q L SE,>124-146 P,Q,R SSE,>146-169 Q R A 4.,4

.1S,>169..i91 Ssw, >191 - 214 R A B A, B, C SW,>214-236 B C D wSw, >236-259 C, D, E w, >259 281 D, E, F WNW, >281 304 E, F, G NW, >304 326

- F, G, H NNW, >326 349

- G, H, J Printed: 1/11/2012

Southern Nuclear Operating Company Emergency NMP-EP-112 SOUTRN, Implementing Protective Action Recommendations Version 1.0 Procedure Page 1 6 of 18 Attachment 4 Table 1 PLANT VOGTLE AFFECTED ZONES FOR PROTECTIVE ACTION RECOMMENDATIONS PARland2 PAR3 WIND DIRECTION AFFECTED AFFECTED FROM (degrees) ZONES ZONES N, > 349 1 1

- A, B5, C5, SRS to 2 Miles A, B5, C5,D5, E5, F5, Bi 0, Cl 0, Dl 0, SRS to 5 Miles NNE, >1 1 34 A, B5, C5, SRS to 2 Miles A, B5, C5, D5, E5, F5, Gb, D10, SRS to 5 Miles NE, >34 56 A, B5, C5, D5, SRS to 2 Miles A, B5, CS, D5, E5, F5, dO, D10, ElO, SRS to 5 Miles ENE >56 79 A C5 D5 E5 SRS to 2 Miles C5 D5 E5 F5 D1O E1F10 SRS to 5 Miles E, >79-101 A, C5, D5, E5, F5, SRS to 2 Miles A, B5,C5, D5, E5, F5, D1O, ElO, FlO, SRS to 5 Miles ESE, >101 124 A, D5, E5, F5, SRS to 2 Miles A, B5, CS, D5 E5, F5, ElO, FlO, G1O,SRS to 5 Miles SE, >124-146 A, D5, E5, F5, SAS to 2 Miles A, B5, C5, D5,E5, F5, ElO, FlO, G1O,SRS to 10 Miles SSE, >146 169 - A, E5, F5, SRS to 5 Miles A, B5, C5, D5, E5, F5, FlO, Gb, SRS to 10 Miles S >169 191 A, F5 SRS to 5 Mile A B5 C5 D5 E5 F5 FlO GlO SRS to 10 Miles 55W >191 214 A F5 SRS to 5 Miles A B5 05 D5 E5 F5 GlO SRS to 10 Miles SW, >214-236 A, SRS to 5 Miles A, B5, C5, D5, E5, F5, SRS to 10 Miles WSW, >236-259 A, SRS to 5 Miles A, B5, C5, D5, E5, F5, H1O, SRS to 10 Miles w, >259 281 A, B5, SRS to 5 Miles A, B5, C5, D5, E5, F5, BlO, H1O, SRS to 10 Miles WNW, >281 304 A, B5, SRS to 5 Miles A, B5, C5, D5, E5, F5, BlO, Gb, H1O, SRS to 10 Miles NW, >304 326 - A, B5, SRS to 5 Miles A, B5, C5, D5, E5, F5, BlO, Gb, H1O, SRS to 10 Miles NNW, >326 349 - A, B5, SRS to 2 Miles A, B5, C5, D5, E5, F5, BlO, dO, D1O, SRS to 5 Miles Printed: 1/11/2012

Nuclear Operating Company Southern Emergency NMP-EP-1 12 SOUTHERN ES Implementing Protective Action Recommendations Version 1.0 COMPANY

,,,, Procedure Page 17 of 18 Attachment 4 Table 2 PLANT VOGTLE GUIDANCE FOR PARS BEYOND THE 10 MILE EPZ 1 . Calculate the Evacuation Distance by determining the maximum Projected Distance where MIDAS dose projections exceed PAGs and adding 5 miles to the projected distance.

Projected Distance (miles) + 5 miles = Evacuation Distance (miles)

2. Determine the affected sectors for the current 15 minute average (From) wind direction ectors 4

Affect

3. Recommend Evacuation from 10 miles to the Evacuation Distance (calculated in step1) for the Affected Sectors (determined in step 2).

4 Check Line 5 Item E Other on the Emergency Notification Form and record the recomrrenged sectors and distance range in miles for Evacuation (NoRefeit 50 mile IPZ map as necessary)

PARAS Ii WIND DIRECTION FROM (degrees) AFFECTED $ECTOR N, > 349 - 11 H, J, K f

, k?

NNE, >11 -3I. K, L

.w NE,>3456 .

ENE, >569 V.- L, M, N

.E>79-1O1.1 M,N,P

) - ?

SE,>io114j v_. S

, N,P,Q a SE, >124-146 p, Q, R SSE,>146-169 Q,R,A 4j)

S9-t91 R,A,B

, \

SSW, >191 - 214 A, B, C o_

>214-236 . B, C, D

p? . ?

Ww, >236-259 C, D, E

?

W,>259281 . . D,E,F

-j WNW, >281 304 E, F, G NW, >304 - 326 F, G, H

. S S

NNW, >326 - 349 G, H, J Printed: 1/11/2012

Southern Nuclear Operating Company Emergency NMP-EP-1 12 SOUTHERN Implementing Protective Action Recommendations Version 1.0 Procedure Page l8of 18 Attachment 5 Figure 1 PAR WORKSHEET INSTR UCTIONS:

1 . Check the box for the applicable PAR (1 2, 3, or 4).

2. Record the 15 minute average wind direction from for the selected PAR.

Use met instrumentation corresponding to primary release point(s) (BWR) Qfl ground level release (PWR).

3. Use the applicable Site Specific PAR table (Table 1 or 2) to determine the affected zones.

PAR Revisions must include previous PARs.

On the ENN Form for the selected PAR:

Select block 5.B and record the Evacuate zones OR select block S.C and record the Shelter zones

SelectblockS.D

IF PAR 4 is selected, THEN additionally select block S.E Other and provide Affected Sectors and To Miles Wind direction from ENN Line 5 [C]

Shelter Zones I Advise remainder of EPZ to Monitor Local Radio/TV Stations PAR ENN Line 5 [D] fTone Alert Radios. Consider the use of KI (Potassium Iodide) in accordance with State Plans and Policy Wind direction from ENN Line 5 [B]

Evacuate Zones Advise remainder of EPZ to Monitor Local Radio/TV Stations PAR2 ENNL1ne5[D] /Tone Alert Radios. Consider the use of KI (Potassium Iodide) in accordance with State Plans and Policy Wind direction from ENN Line S [B]

Evacuate Zones Advise remainder of EPZ to Monitor Local Radio/TV Stations PAR3 ENNLine5[D] /Tone Alert Radios. Consider the use of KI (Potassium Iodide) in accordance with State Plans and Policy Wind direction from ENN Line S [B]

Evacuate Zones Advise remainder of EPZ to Monitor Local Radio/TV Stations!

ENN Line 5 [D] Tone Alert Radios. Consider the use of KI (Potassium Iodide) in PAR 4 accordance with State Plans and Policy ENN Line S [E] Evacuate Affected Sectors to OTHER Approval: I Emergency Director DatelTime Printed: 1/1 1/20 12

ML13347B136

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