ML111990273

Initial Exam 2011-301 Draft Administrative JPMs

ML111990273
Person / Time
Site:	Farley
Issue date:	07/02/2011
From:	NRC/RGN-II
To:	Southern Nuclear Operating Co
References
50-348/11-301, 50-364/11-301
Download: ML111990273 (180)

Text

FNP HLT-34 ADMIN Page 1 of 14 A1.l.A SRO and RO Conduct of Operations ADMIN G2.1.7 TITLE: Critical Safety Function Status Tree Evaluation.

EVALUATION LOCATION: D SIMULATOR LICONTROL ROOM I1CLASSROOM PROJECTED TIME: 10 MIN SIMULATOR IC NUMBER: N/A LI ALTERNATE PATH LI TIME CRITICAL LI PRA JPM DIRECTIONS:

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

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

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

Correctly assess and determine the status of ALL CSFs and then determine which FRP is required to be implemented using FNP-l-CSF-0.O.

Examinee:

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

EXAMINER:

Developer Billy Thornton Date: 2/7/201 1 NRC Approval SEE NUREG 1021 FORM ES-301-3

FNPHLT-34ADMIN A1.1.A Page2ofl4 CONDITIONS When I tell you to begin, you are to MONITOR AND EVALUATE CRITICAL SAFETY FUNCTION STATUS TREES. The conditions under which this task is to be performed are:

a. Unit 1 tripped from 100% power.

b. A Safety Injection occurred 30 minutes ago.

c. The crew is performing actions in EEP- 1, Loss of Reactor or Secondary Coolant.

d. The SPDS computer is NOT available for monitoring Critical Safety Functions.

e. You have been directed to manually monitor the Critical Safety Functions using CSF-0.0, Critical Safety Function Status Trees on Unit 1.

f. Document each CSF evaluation on FNP-1-CSF-O.O by circling the final colored ball and procedure that applies, and report the FRP that is required to be implemented, if any.

g. Plant conditions are given in the attached Table 1.

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

EVALUATION CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

START TIME

1. Evaluate CSF-0. 1. POWER RNG LESS THAN 5% - S / U YES BOTH 1NT RNG SUR ZERO OR NEGATIVE NO Determines that an Orange condition exists to go to FRP-S. 1.

2. Evaluate CSF-0.2. FIFTH HOTTEST CORE EXIT S / U TC LESS THAN 1200°F -YES RCS SUBCOOLING FROM CORE EXIT TCS GRTR THAN 16°F{45°F} YES Determines that this CSF is SAT.

FNPHLT-34ADMIN A1.1.A Page3ofl4 EVALUATION CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

3. Evaluate CSF-0.3. NAR RNG LVL N AT LEAST S / U ONE SG GRTR THAN 31%{48%} NO -

TOTAL AFW FLOW TO ALL SOS GRTR THAN 395 GPM -

YES PRESS N ALL SOS LESS THAN 1129 PSIGYES NAR RNG LVL IN ALL SGS LESS THAN 82% YES -

PRESS N ALL SGS LESS THAN 1075 PSIG YES -

NAR RNG LVL TN ALL SGS GRTR THAN 31% NO -

Determines that a Yellow condition exists to go to FRP-H.5.

• 4. Evaluate CSF-O.4. TEMP DECR N ALL CL IN LAST 60 MN LESS THAN 100°FNO ALL RCS PRESS CL TEMP (TN LAST 60 MN) POINTS TO RIGHT OF LIMIT A YES -

ALL RCS CL TEMPS IN LAST 60 MIN GRTR THAN 250°F -

NO Determines that an Orange condition exists to go to FRP-P. 1.

FNPHLT-34ADMIN A1.1.A Page4of 14 EVALUATION CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

5. Evaluate CSF-O.5. CTMT PRESS LESS THAN 54 PSIG YES CTMT PRESS LESS THAN 27 PSIG YES CTMT SUMP LVL LESS THAN 7.6 FT. YES BOTH CTMT RAD LESS THAN 2 R/hr. YES Determines that this CSF is SAT.

6. Evaluate CSF-O.6. PRZR LVL LESS THAN 92% -

YES PRZR LVL GRTR THAN 15% -

NO Determines that a Yellow condition exists to go to FRP-1.2.

7. Determines FRP entry requirements. Determines that FRP-S. 1 is required to be implemented.

(CUE: After evaluation of CSF 0.0, What FRP, if any, is required to be implemented?)

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

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

FNPHLT-34ADMIN A1.1.A Page5of 14 GENERAL

REFERENCES:

1. FNP-1-CSF-0.0, VER 17.0 2.KA:G2.l.7 RO (4.4) SRO (4.7)

GENERAL TOOLS AND EQUIPMENT:

1. FNP-1-CSF-0.0, VER 17.0 Critical ELEMENT justification:

STEP Evaluation 1 Critical: Task completion: required to properly evaluate CSF-0. 1 to determine that an Orange path condition exists. This is the highest priority FRP for the conditions given. If this is not evaluated properly, a transition to a lower level procedure could occur, and the highest priority FRP would not be implemented.

2-6 Critical: Task completion: Actions are required to evaluate each CSF properly to complete task successfully. This CSF evaluation should determine the CSF color and procedure, if any, that apply.

7 Critical: Task completion: required to detennine that FRP-S. 1 is to be implemented.

COMMENTS:

UNIT 1 8/29/2007 08:33 FNP-1 -CSF-O.1 SUBCRITICALITY Candidate is only required to annotate the circle for GO TO the applicable FRP or that , FRP-S.1 the CSF is SAT.

I NO J POWER RNG I

- LESS THAN GO TO 5% I FRP-S.2

( YES

) II I

BOTH INT RNG SUR NO BOTH INT (NO RNG SUR

) MORE NEGATIVE THAN -0.2 ZERO OR YES NEGATIVE DPM YES CSF SAT NO BOTH SOURCE RNG ENERGIZED YES GOTO FRP-S.2 BOTH NO SOURCE RNG SURZERO OR NEGATIVE YES Page 1 of I

8/29/2007 08:33 UNIT 1 FNP-1-CSF-O.2 CORE COOLING Revision 17 Candidate is only required to annotate the circle for the applicable FRP or that GOTO the CSF is SAT. I FRP-C.1 GO TO p FRP-C.2 I

GO TO FRP-C.3 Page 1 of 1

8/29/2007 08:33 TTNJIT I FNP-1-CSF-O.3 HEAT SINK Revision 17 GO TO Candidate is only FRP-H.1 required to annotate the circle for the applicable FRP0r that the CSF is SAT.

GO TO FRP-H.2 GOTO FRP-H.3 GO TO FRP-H.4 CSF SAT Page 1 of 1

8/29/2007 08:33 UNIT I FNP-1-CSF-O.4 INTEGRITY Revision 17 CD ci) 0 w

0::

D ci) ci) w a

U)

C) 0::

COLD LEG TEMPERATURE (°F)

GO TO FRP-P.1 GO TO FRP-P.2 Candidate is only required to annotate the circle for the applicable FRP0r that the CSF is SAT.

CSF SAT JFRPPl GOTO FRP-P.2 CSF SAT CSF SAT Page 1 of 2

TJi\Ji I 8/29/2007 08:33 FNP-1-CSF-0.4 INTEGRITY Revision 17 INTEGRITY RCS PRESSURE - TEMPERATURE CRITERIA 3000 a a a a 2050 a

D C,,

C,)

w 1500 INTEGRITY w

RED PATH GREEN z C)

PATH PATH REGION REGION w

1000 (I)

C-)

500 0

190 225230 250255 180 205 280 305 330 RCS COLD LEG WIDE RANGE TEMPERATURE (°F)

Page 2 of 2

8/29/2007 08:33 J1\T[T I FNP-1-CSF-O.5 CONTAINMENT Revision 17 I

CTMT PRESS LESS THAN54 NO cJ PSIG > At LEAST ONE NO CTMT SPRAY PUMP RUNNING Candidate is only (FLOW>1000 GPM) YES required to (h GO TO annotate the circle for the applicable FRP or that the CSF 4

is SAT. CTMT NO SUMP LVL 1

LESS CTMT THAN 7.6 NO PRESS LESS THAN27 PSIG ) GO TO FRP-Z.1 GO TO

• FRP-Z.2 I r CTMT NO SUMP LVL LESS THAN 7.6 FT. )

GO TO FRP-Z.3 BOTH NO CTMT RAD LESS THAN2RI(

hr. >

CSF Page 1 of 1

8/29/2007 08:33 UNJT 1.

FNP-1-CSF-O.6 INVENTORY Revision 17 GO TO FRP-I.3 ALL NO UPPER HEAD AND PLENUM LVLS EQUAL 100% YES a

GO TO FRP-i1 NO PRZR LVL LESS THAN 92%

)

Candidate is only required to annotate PRZRLVL GRTR THAN NO

)

the circle for the 15%

applicable FRPor YES GO TO that the CSF is SAT. FRP-I.3 ALL NO UPPER HEAD AND PLENUM LVLS EQUAL 100% YES CSF L SAT Page 1 of 1

HLT34ADMIN Exam A1.1A HANDOUT Page 1 of2 CONDITIONS When I tell you to begin, you are to MONITOR AND EVALUATE CRITICAL SAFETY FUNCTION STATUS TREES. The conditions under which this task is to be performed are:

a. Unit 1 tripped from 100% power.

b. A Safety Injection occurred 30 minutes ago.

c. The crew is performing actions in EEP-1, Loss of Reactor or Secondary Coolant.

d. The SPDS computer is NOT available for monitoring Critical Safety Functions.

e. You have been directed to manually monitor the Critical Safety Functions using CSF-0.0, Critical Safety Function Status Trees on Unit 1.

f. Document each CSF evaluation on FNP-l-CSF-O.O by circling the final colored ball and procedure that applies, and report the FRP that is required to be implemented, if any.

g. Plant conditions are given in the attached Table 1.

HLT34ADMIN Exam A1.1A HANDOUT Page 2 of 2 Table 1

___________ INSTRUMENT Parameter Channel! or Channel II or Channel Ill Channel IV Train A Train B Power Range NI 0% 0% 0% 0%

Intermediate Range SUR +0.2 DPM +0.25 DPM Intermediate Range NI 8 AMPS 3.0x10 8 AMPS 3.2x10 Source Range SUR 0 DPM 0 DPM Source Range NI 0 CPS 0 CPS RCS Pressure 1575 psig 1550 psig MCB Core Exit TIC Monitor 329°F 325°F in TMAX mode PRZR level 2% 4% 5%

CTMT Pressure 0 psig 0 psig 0 psig 0 psig RCS Subcooling 250°F 250°F CTMT Emergency Sump Levels 0 inches 0 inches CTMT Radiation 24 mR I Hr 31 mR I Hr RCSLo0pI RCSLo0p2 RCSL0op3 Parameter SG NR Level 20% 0% 20%

(all_channels)

AFW flow 325 GPM 0 GPM 340 GPM SG Pressure 800 psig 25 psig 820 psig (all_channels)

RCS WR Cold Leg Temperature 420°F 240°F 425°F RCP status Off Off Off

UNIT 1 FNP-1-CSF-0 8/29/2007 08:33 8-29-2007 Revision 17 FARLEY NUCLEAR PLANT CRITICAL SAFETY FUNCTION PROCEDURE FNP-1-CSF-0 CRITICAL SAFETY FUNCTION STATUS TREES S

A F

PROCEDURE USAGE REQUIREMENTS-per FNP-O-AP-6 SECTIONS E T

Continuous Use ALL Y Reference Use R E

Information Use L L A T

E D

Approved:

Jim L. Hunter (for)

Operations Manager Date Issued: 09/14/07

1r 8/29/2007 08:33 FNP1CSF-O li1S ii 1 CRITICAL SAFETY FUNCTION STATUS TREES Revision 17 Table of Contents Procedure Contains Number of Pages Body 2 FNP-l-CSF-O.1 1 FNP-l-CSF-O.2 1 FNP-l-CSFO.3 1 FNP-l-CSF-O.4 2 FNP-1-CSF-O.5 1 FNP-1-CSF-O.6 1 Page 1 of 1

-v 8/29/2007 08:33 FNP-1-CSF-O LJLJ1T 1 CRITICAL SAFETY FUNCTION STATUS TREES Revision 17 A. Purpose This procedure provides actions required to evaluate the status of the Critical Safety Functions.

B. Symptoms or Entry Conditions I. This procedure is entered when monitoring of the Critical Safety Functions is required from FNP-1-EEP-O. REACTOR TRIP OR SAFETY INJECTION, step 23.

II. This procedure is entered when the operator transfers from the guidance of FNP1-EEP-O, REACTOR TRIP OR SAFETY INJECTION to any other recovery guideline.

Page 1 of 2

8/29/2007 08:33 U IN I I i FNP-l-CSF-O CRITICAL SAFETY FUNCTION STATUS TREES Revision 17 Step Action/Expected Response Response NOT Obtained III I I Check at least one control room IPC SPDS console - Operable.

1.1 Verify no HOST LINK DOWN 1.1 Proceed to step 3.2.

message on the IPC title bar.

2 Check SPDS TOP LEVEL page.

2.1 Click SPDS button on top toolbar.

NOTE: Suspect critical safety functions are indicated by the color magenta.

2.2 Verify no Critical Safety 2.2 Monitor Critical Safety Functions - SUSPECT. Function which is SUSPECT using FNP-1-CSF-O.1 through

[1 Subcriticality FNP-1-CSF-O.6 as appropriate.

[] Core Cooling

[1 Heat Sink

[1 Integrity 1 Containment

[] Inventory 3 Monitor Critical Safety Functions.

3.1 Monitor Critical Safety Functions with SPDS Application on IPC.

OR 3.2 Monitor Critical Safety Functions using FNP-1-CSF--O.1 through FNP-1-CSF-O.6

-END Page 2 of 2

UNIT 1 8/29/2007 08:33 FNP-1-CSF-O.1 SUBCRITICALITY Revision 17 GO TO FRP-S.1 GO TO

. IFRPS.1 I

NO I POWER RNG S LESS THAN GO TO 5% S FRP-S.2 YES I

I L

BOTH INT RNGSUR NO BOTH INT NO MORE RNG SUR NEGATIVE ZERO OR THAN -0.2 YES NEGATIVE DPM YES L

CSF SAT NO BOTH SOURCE RNG ENERGIZED YES

.., GOTO FRP-S.2 BOTH NO SOURCE RNG SURZERO OR NEGATIVE YES Page 1 of I

TJNTT1 8/29/2007 08:33 FNP-1-CSF-O.2 CORE COOLING Revision 17 GOTO FRP-C.1 GOTO

• FRP-C.2 FIFTH I HOTTEST NO CORE EXIT

-ø TC LESS FIFTH NO THAN YES 12000 F HOTTEST CORE EXIT TC LESS THAN 700° YES RCS SUBCOOLING NO GO TO FROM CORE FRP-C.3 0 EXIT TCS GRTR THAN YES 16° F {45° F)

I O CSF SAT Page 1 of I

8/29/2007 08:33 UNI1. I FNP-1-CSF-O.3 HEAT SINK Revision 17 GO TO I I FRP-H.1 TOTAL AFW NO FLOW TO ALL SGS GRTR THAN 395 GPM YES L

GO TO FRP-H.2 NAR RNG LVLINAT NO PRESS IN NO LEAST ONE ALL SGS SG GRTR LESS THAN THAN 31% YES 1129 PSIG YES

{48%}

• GO TO FRP-H.3 NARRNG NO LVL IN ALL SGS LESS THAN 82% YES

• GO TO FRP-H.4 PRESS IN NO ALL SGS LESS THAN 1075 PSIG YES S GO TO FRP-H5 NARRNG NO LVL IN ALL SGS GRTR THAN 31%

{48%} YES I1c SAT Page 1 of I

8/29/2007 08:33 FNP-1-CSF-O.4 INTEGRITY Revision 17 U) a LU 2050 D

U)

(I)

LU a-U)

C.)

190 225 250 280 COLD LEG TEMPERATURE (°F) GO TO FRP-P. I I

ALL RCS PRESS-- NO CL TEMP (IN GO TO LAST6OMIN)

POINTS TO I

_ iJ FRP-P.1 RIGHT OF YES LIMIT A ALLRCSCL NO TEMPS IN GO TO L LAST6OMIN GRTR THAN FRP-P.2 2500 F YES -

ALLRCSCL NO TEMPS IN L LAST6OMIN GRTR THAN 280° F YES CSF TEMP DECR NO SAT IN ALL CL IN LAST6OMIN LESS THAN 100° F YES FRPP1 ALL RCSCL NO r

TEMPS GRTR THAN 250° F YES NO -

RCS PRESS LESS THAN GO TO 450 PSIG FRP-P.2 YES ALL RCS NO TEMPS I

GRTR THAN 325° F YES O CSF SAT I

Page 1 of 2 G CSF SAT

I FN I T I 8/29/2007 08:33 FNP-1-CSF-0.4 INTEGRITY Revision 17 INTEGRITY RCS PRESSURE - TEMPERATURE CRITERIA 3000----- ---

2560 I_______________

2500 ---------------

4%

2050 2000 Ui D

U) 1*..I Cl)

Ui 0

Ui 1500 INTEGRITY SI INTEGRITY INTEGRITY -

- INTEGRI-TY----

CD YELLOW GREEN z U) 0 RED PATH I ORANGE PATH PATH PATH Ui 1000 REGION

/ REGION REGION REGION U)

C.)

nn 0

180

/

190 205 225 230 250 255 RCS COLD LEG WIDE RANGE TEMPERATURE (°F) 280 305 330 Page 2 of 2

8/29/2007 08:33 TJNJT 1.

FNP-1-CSF-0.5 CONTAINMENT Revision 17 GOTO 1

F RP-Z.1 I

CTMT PRESS NO Gc LESS THAN 54 YES PSIG At LEAST ONE NO CTMT SPRAY PUMP RUNNING (FLOW>1 000 GPM) YES 1 I (h 4

CTMT NO SUMP LVL LESS CTMT THAN 76 NO PRESS LESS THAN 27 YES GOTO PSIG FRP-Z.1

• _ (h GO TO CTMT NO SUMPLVL LESS THAN 7.6 GOTO FRP-Z.3 BOTH NO CTMTRAD LESS THAN 2 RI YES hr.

CSF SAT Page 1 of I

8/29/2007 08:33 TJNTT 1 FNP-1-CSF-O.6 INVENTORY Revision 17 GO TO FRP-13 ALL NO UPPER HEAD AND PLENUM LVLS EQUAL 100% YES GO TO FRP-L1 NO PRZR LVL

- LESS THAN 92%

YES GO TO FRP-I.2 NO PRZR LVL

- GRTR THAN 15%

YES GOTO FRP-I.3 ALL NO UPPER HEAD III AND PLENUM LVLS EQUAL 100% YES CSF SAT Page 1 of I

FNP HLT-34 ADMIN Page 1 of 5 A1.2.S SRO only Conduct of Operations ADMIN G2.1.4 TITLE: Determine Aptive License Status.

EVALUATION LOCATION: LI SIMULATOR LI CONTROL ROOM lI CLASSROOM PROJECTED TIME: 30 MIN SIMULATOR IC NUMBER: N/A LI ALTERNATE PATH LI TIME CRITICAL LI PRA JPM DIRECTIONS:

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

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

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

Correctly assess and determine the Active or Inactive License status of Plant Operators.

Examinee:

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

EXAMINER:

Developer Billy Thornton Date: 2/7/2011 NRC Approval SEE NUREG 1021 FORM ES-301-3

FNP HLT-34 ADMIN Al .2.S Page 2 of 5 CONDITIONS When I tell you to begin, you are to DETERMINE THE ACTIVE OR INACTIVE STATUS OF LICENSED OPERATORS. The conditions under which this task is to be performed are:

a. An RO is required to fill the OATC position on January 31, 2011.

b. Three off shift ROs are available.

c. All three are current in LOCT (Licensed Operator Continuing Training) and have had a medical exam as required to maintain an active license.

d. None of the three have worked any shifts since December 31, 2010.

e. The three operators work history is as follows:

• Operator A - License was active on October 1, 2010.

10/02/10 worked 1900-0700 as Unit 2 OATC 10/04/10 worked 1900-0700 as Unit 1 UO 10/05/10 worked 1900-0700 as Unit 1 OATC 11/14/10 worked 0700-1900 as Unit 2 UO 11/17/10 worked 0700-1900 as Unit 2 UO

• Operator B - License was active on October 1, 2010.

10/28/10 worked 0700-1900 as Unit 1 UO 11/03/10 worked 0700-1900 as Unit 1 UO 11/05/10 worked 0700-1900 as an on shift Extra 11/14/10 worked 1900-0700 as Unit 1 OATC 12/05/10 worked 0700-1900 as Unit 1 UO

• Operator C - License was inactive on October 1, 2010.

From 10/12/2010 thru 10/16/2010 worked 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> under the direction of the Unit 1 OATC and completed all requirements for license reactivation.

11/15/10 worked 0700-1900 as Unit 2 OATC 12/04/10 worked 0700-1900 as Unit 2 OATC 12/16/10 worked 0700-1900 as Unit 1 UO 12/17/10 worked 0700-1900 as Unit 1 OATC

f. You have been directed to determine the Active or Inactive status of the three off shift ROs on January 31, 2011, in accordance with NMP-TR-406, Active License Maintenance.

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

EVALUATION CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

TIME

FNPHLT-34ADMIN A1.2.S Page3of5 EVALUATION CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

• 1. Evaluate the status of Operator A. Operator A is determined to have S / U ACTIVE license status based on working at least 5 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shifts during the calendar quarter October 1 December 31, in a position requiring an active license and required by Tech Specs. This operator worked 6 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shifts during that quarter. Step 6.5.2.1 of NMP -TR-406.

• 2. Evaluate the status of Operator B. Operator B is determined to have S / U INACTIVE license status. This operator worked 5 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shifts during the calendar quarter October 1 December 31, but one of those shifts was NOT in a position required by Tech Specs (1 1/05/2010 working as an on shift Extra). Step 6.5.2.1 of NMP -TR 406.

• 3. Evaluate the status of Operator C. Operator C is determined to have S / U ACTIVE license status. This operator reactivated his license during the calendar quarter of October 1-December 31, 2010.

When a license is reactivated, it is considered active for that quarter without working any additional shifts. When a licensed operator has met the requirements for an active license in a quarter he is available and considered active for the next quarter. Step 6.6.1 and 6.6.8 of NMP -TR-406.

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

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

FNP HLT-34 ADMIN Al .2.S Page 4 of 5 GENERAL

REFERENCES:

1. NMP-TR-406, VER 1.0

2. NMP-TR-406-F01, VER 1.0

3. NMP-TR-406-F02, VER 1.0

4. NMP-TR-406-F03, VER 1.0

5. KA: G2.1.4 RO 3.3 SRO 3.8 GENERAL TOOLS AND EQUIPMENT:

1. NMP-TR-406, VER 1.0

2. NMP-TR-406-F01, VER 1.0

3. NMP-TR-406-F02, VER 1.0

4. NMP-TR-406-F03, VER 1.0 Critical ELEMENT justification:

STEP Evaluation 1 Critical: Task completion: required to properly evaluate the active or inactive status of Operator A.

2 Critical: Task completion: required to properly evaluate the active or inactive status of Operator B.

3 Critical: Task completion: required to properly evaluate the active or inactive status of Operator C.

COMMENTS:

The following procedures will be provided to the students:

1. NMP-TR-406, VER 1.0

2. NMP-TR-406-F01, VER 1.0

3. NMP-TR-406-F02, VER 1.0

4. NMP-TR-406-F03, VER 1.0

FNPHLT-34ADMIN A1.2.S HANDOUT Pg 1 of 1 CONDITIONS When I tell you to begin, you are to DETERMINE THE ACTIVE OR INACTIVE STATUS OF LICENSED OPERATORS. The conditions under which this task is to be performed are:

a. An RO is required to fill the OATC position on January 31, 2011.

b. Three off shift ROs are available.

c. All three are current in LOCT (Licensed Operator Continuing Training) and have had a medical exam as required to maintain an active license.

d. None of the three have worked any shifts since December 31, 2010.

e. The three operators work history is as follows:

• Operator A - License was active on October 1, 2010.

10/02/10 worked 1900-0700 as Unit 2 OATC 10/04/10 worked 1900-0700 as Unit 1 UO 10/05/10 worked 1900-0700 as Unit 1 OATC 11/14/10 worked 0700-1900 as Unit 2 UO 11/17/10 worked 0700-1900 as Unit 2 UO

• Operator B - License was active on October 1, 2010.

10/28/10 worked 0700-1900 as Unit 1 UO 11/03/10 worked 0700-1900 as Unit 1 UO 11/05/10 worked 0700-1900 as an on shift Extra 11/14/10 worked 1900-0700 as Unit 1 OATC 12/05/10 worked 0700-1900 as Unit 1 UO

• Operator C - License was inactive on October 1, 2010.

From 10/12/2010 thru 10/16/2010 worked 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> under the direction of the Unit 1 OATC and completed all requirements for license reactivation.

11/15/10 worked 0700-1900 as Unit 2 OATC 12/04/10 worked 0700-1900 as Unit 2 OATC 12/16/10 worked 0700-1900 as Unit 1 UO 12/17/10 worked 0700-1900 as Unit I OATC

f. You have been directed to determine the Active or Inactive status of the three off shift ROs on January 31, 2011, in accordance with NMP-TR-406, Active License Maintenance.

Operator A status - (Active I Inactive)

Operator B status - (Active / Inactive)

Operator C status - (Active I Inactive)

Southern Nuclear Operating Company I Nuclear I I NMP-TR-406 I UTMEflN COPAPANY Management I License Administration Version 1.0 I Procedure I Page 1 of 21 I Procedure Owner: Robert J. Brown I Fleet Training Manager / Corporate Approved By: Original signed by Brad Deen for R. J. Brown / 08/27/2010 (Procedure Owners Signature) (Date)

Effective Dates: 10/01/2010 10/01/2010 10/01/2010 10/01/2010 Corporate FNP HNP VEGP PRB Not Required This Standardization process control NMP is under the oversight of the Training Peer Team.

Writer(s): Brad Deen Derwood Tootle George Gunn David Hall Dale Moran Randy Odom Brian Reed PROCEDURE USAGE REQUIREMENTS SECTIONS Procedure must be open and readily available at the Continuous Use: work location. Follow procedure step by step unless otherwise_directed_by_the_procedure.

Procedure or applicable section(s) available at the work Reference Use:

location for ready reference by person performing steps.

Information Use: Available on site for reference as needed. ALL

Southern Nuclear Operating Company Nuclear NMP-TR-406 SUTHERN. Management License Administration Version 1.0 CO?PANY Procedure Page 2 of 21 Procedure Version Description Version Number Version Description 1.0 Initial issue of procedure

Southern Nuclear Operating Company I Nuclear I NMP-TR-406 I UTHERN Management I License Administration Version 1 .0 I CPAPANY Procedure I Page3of2l I Table of Contents Page 1.0 Purpose 4 2.0 Applicability 4 3.0 References 4 4.0 Definitions 5 5.0 Responsibilities 6 6.0 Procedure 7 7.0 Records 15 8.0 Commitments 15 Attachment 1 Nuclear Regulatory Commission Medical Restriction Change Letter 16 Attachment 2 Routine Nuclear Regulatory Commission License Medical Examination Flowpath 17 Attachment 3 Medical Condition Flowpath 18 Attachment 4 Medical Conditions List 19 Attachment 5 License Renewal Letter 20 r

Attachment 6 License Termination Letter 21

Southern Nuclear Operating Company Nuclear I I NMP-TR-406 I

SOUTHERN Management I License Administration Version 1.0 I

COFPANV Procedure I Page 4 of 21 1.0 Purpose This procedure establishes the processes for maintaining Nuclear Regulatory Commission (NRC) licenses including the following:

• Active Licensed Duties

• Biennial Licensed Operator Medical Examination

• Evaluation of Changes in the Physical Conditions of Licensed Operators

• License Renewal

• Maintenance of an Active License

• License Reactivation

• Reactivation of a Senior Reactor Operator for Supervising Core Alterations

• Maintenance of a Senior Reactor Operator Licenses Reactivated to Supervise Core Alterations

• Respirator Glasses

• No Solo Operation 2.0 Applicability This procedure is applicable to all individuals holding or pursuing a Reactor Operator (RO) or Senior Reactor Operator (SRO) license.

3.0 References 3.1 ANSI 3.4, 1983, Medical Certification and Monitoring of Personnel Requiring Operator Licenses for Nuclear Power Plants 3.2 10 CFR 50, Domestic Licensing of Production and Utilization Facilities 3.3 10 CFR 55, Operators Licenses 3.4 10 CFR 55.4, Operators Licenses Definitions 3.5 10 CFR 55.25, Incapacitation because of Disability or Illness 3.6 Meeting Summary NRC Region II Annual Training Managers Conference, Tom Peebles to George Hairston, June 2, 1995 3.7 NEI 99-02, Regulatory Assessment Performance Indicator Guideline 3.8 NMP-TR-406-F01, Active License Maintenance

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3.9 NMP-TR-406-F02, Senior Reactor Operator Reactivation for Core Alterations 3.10 N MP-TR-406-F03, License Reactivation Documentation 3.11 NRC Information Notice IN 91-08, Medical Examinations for Licensed Operators 3.12 NRC Information Notice IN 94-14 including Supplement 1, Failure to Implement Requirements for Biennial Medical Examinations and Notification to the NRC of Changes in Licensed Operator Medical Conditions 3.13 NRC Information Notice 97-66, Failure to Provide Special Lenses for Operators Using Respirator or Self-Contained Breathing Apparatus During Emergency Operations 3.14 NRC Information Notice 99-05, Inadvertent Discharge of Carbon Dioxide Fire Protection System and Gas Migration 3.15 NRC Form 396, Certification of Medical Examination by Facility Licensee 3.16 NRC Form 398, Personal Qualification Statement Licensee 3.17 NUREG 1021, Operator Licensing Examiner Standards for Power Reactors 3.18 NUREG 1262, Answers to Questions at Public Meetings Regarding Implementation of Title 10, Code of Federal Regulations, Part 55 on Operators License 3.19 Regulator Issue Summary (RIS) 2007-29, Clarified Guidance for Licensed Operator Watch-Standing Proficiency 3.20 U.S. Nuclear Regulatory Commission Regulatory Guide 1 .134, Medical Evaluation of Licensed Personnel at Nuclear Power Plants 3.21 SH-GEN-039, NRC Licensed Operator Physical Examination 4.0 Definitions 4.1 Learning Management System (LMS)

A Learning Management System refers to a database maintained by the Training Department and is used to administer computer-based instruction and to determine individual qualification status.

4.2 No Solo No Solo refers to a licensee with a special NRC license restriction. For example, a typical restriction requires that another person, capable of summoning assistance, be present when the licensee is manipulating controls. Specific requirements may vary and are described in NUREG 1021 as follows:

An RO who is at risk of sudden incapacitation may have a no-solo restriction that requires another licensed operator to be in view when the restricted operator is performing control manipulations, and someone capable of summoning assistance to be present at all other times while the restricted operator is performing licensed duties. The analogous SRO restriction would require another licensed operator to be in view when the restricted operator

Southern Nuclear Operating Company j

UTHERN CiPANV Nuclear Management Procedure I

License Administration NMP-TR-406 Version 1.0 Page6of2l is performing control manipulations, and another senior operator to be present on site at all other times while the restricted operator is performing SRO licensed duties or someone I

capable of summoning assistance to be present at all other times while the restricted operator is performing RO licensed duties.

5.0 Responsibilities 5.1 The Southern Nuclear Fleet Training Manager is the Corporate Functional Area Manager (CFAM) who shall be accountable for the governance and oversight of this procedure.

5.2 The Site Vice President or Senior Management Representative Onsite shall be responsible for approving NRC Forms and Letters.

5.3 The Training Department Manager is the Site Functional Area Manager (SFAM) who shall be accountable for performance in the use of this procedure.

5.4 The Operations Department Manager shall be accountable to maintain oversight and ensure that License Operators are properly qualified prior to performing Licensed Operator duties.

5.5 The Medical Service Group shall be responsible for the following:

• The completion of the License Operator physical examinations.

• Determining when a physical examination is due and electronically notifying the Licensed Operator.

• Completing appropriate sections of NRC Form 396.

• Determining if a medical condition requires a restriction to be added to a license.

• Updating medical items in the Learning Management System (LMS).

• Notifying the Operations Training Group and supervision of any discovered or reported change in medical condition that impacts a License Operators License.

• Initiating a Condition Report to evaluate a medical condition that may result in a License restriction change.

5.6 The Operations Training Group/Operations Training Coordinator shall be responsible for the following:

• The processing of NRC Forms.

• Updating the LMS when there is a change to a Licensed Operators status or training has been completed.

• Tracking of license maintenance hours.

5.7 The Licensed Operator shall be responsible for the following:

• Contacting Medical Services to schedule physical examinations.

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• Notifying their Supervisor and Medical Services of any change in physical condition.

• Ensuring they are qualified prior to performing Licensed Operator duties.

6.0 Procedure 6.1 Active Licensed Duties 10 CFR 55.4 defines actively performing the functions of an Operator or Senior Operator to mean that a licensed operator has a position on the shift crew that requires the individual to be licensed as defined in the facilitys technical specifications, and that the Licensed Operator carries out and is responsible for the duties covered by that position.

For purposes of this procedure, actively performing the functions of an Operator or Senior Operator (i.e., active licensed duties) is defined as follows:

• On-shift as Operator at the controls (OATC)

• On-shift as Unit Operator (UO)

• On-shift as Shift Supervisor (SS)

• On-shift as Shift Manager (SM)

• Supervision of core alterations as SRO 6.2 Biennial Licensed Operator Medical Examination (Refer to Attachment 2)

Biennial is a time period equal to 730 days with the flexibility that the examination can be any time during the anniversary month and therefore slightly longer than 730 days. Every licensed individual shall have a biennial medical examination as follows:

6.2.1 The Medical Services Group shall determine who is due for a physical by running a Trainee Learning Needs Requirement Report in the LMS. The LMS or Medical Service Group shall notify the Licensed Operators of the required medical examination using a memo or electronic mail.

6.2.2 The Licensed Operator shall contact the Medical Services Group and schedule their medical examination to ensure that the exam is completed by the last day of the month in which the medical examination is due.

6.2.3 The Medical Services Consultant shall ensure the physician completes the medical examination. The physician shall document the findings on the Medical Examination Report (MER).

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6.2.4 The Medical Services Consultant shall complete the appropriate sections of the Licensed Operators NRC Form 396 and forward it to the Operations Training Group.

If the Medical Services Consultant marks restriction change from previous submittal on the NRC Form 396, the Medical Services Consultant shall notify the Operations Training Group within five (5) working days of the medical examination. Upon completion of the NRC Form 396, the Medical Services Group shall create a learning event for the individual for item S-MEDNRC in the LMS for the date the exam was completed.

6.2.5 The Operations Training Group shall review the completed NRC Form 396 for restriction changes from any previous submittal. If a restriction has changed, the Site Vice President shall sign the NRC Form 396. The NRC Form 396, and a letter explaining the changes, shall be mailed to the NRC per 10 CFR 55.25 within 30 days of the determination by the physician that the restriction has changed. Training shall transmit a copy of the completed Form to Document Control. The Operations Training Group shall keep a copy of the completed NRC Form 396 for the duration of the Licensed Operators license plus two (2) years. Notification of a restriction change will be via a telephone call to Line Management followed by a written memo to the affected Licensed Operator and to Operations Management. Attachment us provided as an example.

6.2.6 If there is no restriction change, the Operations Training Group shall route the NRC Form 396 to the Site Vice President for signature. The Form shall then be transmitted to Document Control. The Operations Training Group shall keep a copy of the completed NRC Form 396 for the duration of the Licensed Operators license plus two (2) years.

6.3 Evaluation of Changes in the Physical Conditions of Licensed Operators (Refer to Attachment 3) 6.3.1 Any Licensed Operator shall notify their Supervisor and the Medical Services Group of any change in their physical or mental condition. The following changes, refer to Attachment 4 for a list of examples, include, but are not limited to:

• Wearing corrective lenses

• Taking prescription medicine

• High blood pressure

• Surgery

• Any condition that restricts the range of motion of an extremity (e.g., back, neck, shoulder, etc.)

• Any mental health condition (i.e., depression, anxiety, etc.) or treatment for drug or alcohol abuse.

• Any condition evaluated by ANSI 3.4, 1983

Southern Nuclear Operating Company I Nuclear I I NMP-TR-406 I I

I SUTHERN CAPNV Management Procedure I License Administration Version 1.0 Page 9of21 I 6.3.2 The Supervisor shall notify the Operations Training Group and the Medical Services Consultant of any change in the Licensed Operators physical condition.

6.3.3 The Medical Services Consultant shall initiate an evaluation of the reported condition for changes in the Licensed Operators license or for removal from active licensed duties, if necessary. In addition, the Medical Services Consultant shall generate a Condition Report to ensure timely notification made to NRC.

6.3.4 If the condition results in the need for a permanent change in the Licensed Operators license, the Medical Services Consultant shall complete NRC Form 396 and forward it to the Operations Training Group.

6.3.5 If a restriction has changed, the Operations Training Group shall forward the NRC Form 396 to the Site Vice President for signature. After the Site Vice President approves the NRC Form 396, the approved (i.e., signed) Form and accompanying letter explaining the changes shall be mailed to the NRC. The 10 CFR 55.25 requires this notification be complete within 30 days of the determination by the physician that the restriction has changed. Training shall retain a copy of the completed Form 396.

The Operations Training Group shall keep a copy of the completed NRC Form 396 for the duration of the individuals license plus two (2) years. Notification of a restriction change to the appropriate department will be via a memo or electronic mail.

6.3.6 The Operations Training Group shall notify Operations Management and the individual, via an electronic or hard copy memo, if the condition requires removal from active licensed duties as defined in this procedure. In addition, a learning event shall be entered in the LMS. In the Comment section, record that the block is due to medical status hold.

6.3.7 The Medical Services Consultant shall notify the Licensed Operator and their Supervisor, per the applicable Medical Services Group procedures, if the condition results in a temporary restriction that does not require removal from active licensed duties.

6.3.8 When the physician restores the Licensed Operator to active licensed duties, then the Medial Services Consultant shall notify the Operations Training Group. The Operations Training Group shall notify the Licensed Operator and their Supervisor via a memo or electronic mail that the Licensed Operator is restored to active licensed duties. A learning event shall be entered in the LMS. In the comment section, record that the medical hold is removed.

6.4 License Renewal The Operations Training Group shall initiate renewal of a Licensed Operators license as required by 10 CFR 55 as follows:

6.4.1 The Operations Training Group shall determine whose license is due for renewal by running a Trainee Learning Needs Requirement Report in the LMS.

6.4.2 The Operations Training Group shall complete the renewal application per the instructions on NRC Form 398 and NUREG 1021 and then forward the application to the Licensed Operator for their review and signature.

Southern Nuclear Operating Company I Nuclear I I NMP-TR-406 I SUTHERN COFPANY Management I License Administration f Version 1 .0 I I Procedure Page 10 of 21 I 6.4.3 After the Licensed Operator signs the NRC Form 398, they shall return it to the Operations Training Group who will then route the NRC Form 398 and the individuals most recent NRC Form 396 to the Training Manager for review and approval.

6.4.3.1 The Training Manager shall sign the NRC Form 396 after the individual and then send the signed form to the Site Vice President.

6.4.4 The Operation Training Group shall mail the original and two (2) copies of the NRC Form 398 and the NRC Form 396, along with a cover letter to the NRC, per 10 CFR 55, at least 30 days prior to expiration of the Licensed Operators license. Refer to Attachment 5 for a sample cover letter.

6.4.5 When the license renewal has been signed and mailed to the NRC in a timely manner (i.e., at least 30 days prior to expiration) the Operations Training Group shall create a learning event for the Licensed Operator for the appropriate item in the LMS for the date the license renewal was submitted.

6.4.6 Upon receipt of the license, renewal from the NRC the Operations Training Group shall edit the learning event for the Licensed Operator for the appropriate item in the LMS for the date the license was effective.

6.5 Maintenance of an Active License Only a Licensed Operator with an active license shall be allowed to manipulate the controls or supervise the manipulation of the controls of the reactor.

6.5.1 Per NUREG 1262 Q. 293, a newly Licensed Operator is considered to have met the proficiency requirements for an active license for the initial calendar quarter in which the license was issued.

6.5.1.1 Upon receipt of a new license, a learning event shall be created for the Licensed Operator to give credit for proficiency.

6.5.2 NUREG 1021 states:

In accordance with 10 CFR 55.53 (e), licensed operators are required to maintain their proficiency by actively performing the functions of an operator or senior operator on at least seven 8-hour or five 12-hour shifts per calendar quarter. This requirement may be completed with a combination of complete 8- and 12-hour shifts (in a position required by the plants technical specifications) at sites having a mixed shift schedule, and watches shall not be truncated with the minimum quarterly requirement (56 hours6.481481e-4 days <br />0.0156 hours <br />9.259259e-5 weeks <br />2.1308e-5 months <br />) is satisfied. Overtime may be credited if the overtime work is in a position required by the plants technical specifications. Overtime as an extra helper after the official watch has been turned over to another watch stander does not count toward proficiency time.

6.5.2.1 Maintenance of an active license requires that an individual spend seven (7) eight-hour shifts or five (5) twelve-hour shifts in a position that requires the license per the Technical Specifications (i.e., OATC, UO, SS, SM, or SRO during Core Alterations as defined in Technical Specifications) in a calendar quarter.

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I I

License Administration I NMP-TR-406 Version 1.0 Page 11 of 21 If an individual stands a combination of complete 12 or eight-hour shifts that total 56 hours6.481481e-4 days <br />0.0156 hours <br />9.259259e-5 weeks <br />2.1308e-5 months <br /> in the quarter, this requirement is satisfied. A shift of less than eight (8)

I hours does not count toward the 56-hour total. If an individual spends this shift time in a position that only requires an RO license (i.e., UO, OATC), then they are an active RO only. If they spend this time in an SRO position (i.e., SS, SM) they are an active SRO. If they spend this time as SRO in charge of fuel handling during Core Alterations, they are an active SRO only for supervising Core Alterations.

6.5.2.3 In order to maintain the supervisory portion of the SRO license active, a SRO must stand at least one (1) complete watch per calendar quarter in an SRO-only supervisory position. The remainder of complete watches required in a calendar quarter may be performed in either a credited SRO or RO position. These shifts must be on a unit that has fuel in the vessel. If a Licensed SRO stands all of their required proficiency watches in an SRO position, the RO portion of the license is still considered active. Performing the required number of shifts per calendar quarter on a single unit maintains the license active for all similar units on an individuals license.

6.5.3 The active Licensed Operator shall complete NMP-TR-406-F01 once per quarter to document these proficiency hours and forward the form to the Operation Training Coordinator.

6.5.4 The Operations Department Training Coordinator or designee shall maintain a record of these hours and create a learning event for each Licensed Operator who meets the SRO requirement or for each Licensed Operator who meets the RO requirement.

Failure to meet the time requirements for hours on-shift places that level of license (i.e., RO, SRO) in an Inactive status. The Licensed Operator shall not be allowed to stand shift in a position that requires that level of license until they have completed reactivation per this procedure. Operations supervision and the Licensed Operator shall be notified by the Operations Training Group or the Operations Training Coordinator if the Licensed Operators license is placed in an Inactive condition.

6.5.5 An active license requires an Licensed Operator maintain medical certification and must:

6.5.5.1 Maintain medical certification for respirator use per the applicable Safety and Health procedure.

6.5.5.2 Have dosimetry issued.

6.5.5.3 Have contacts or respirator glasses readily available to correct vision to within the limits of ANSI 3.4, 1983 6.5.6 The following training requirements must be met to be in an active status:

6.5.6.1 Current in Licensed Operator Continuing Training (LOCT) as demonstrated by showing qualification complete in the LMS.

6.5.6.2 Current in respirator medical per the LMS qualifications S-MEDRES49 or S MEDRES5O.

Southern Nuclear Operating Company Nuclear NMP-TR-406 saUTIiLRr.I. Management License Administration Version 1.0 CQ?APANY Procedure Page 12 of 21 6.5.6.3 Current in respirator training per the LMS qualification.

6.5.6.4 Current in self-contained breathing apparatus (SCBA) training per the LMS.

If a Licensed Operator fails to meet the respirator or training requirements above, they may be removed from a shift position that requIres an active license until the requirement is met. The Operations Training Group shall notify Operations Management of the required removal from active licensed duties via a telephone call to Line Management followed by a written memo.

6.6 License Reactivation NOTE All items shall be completed within the same quarter.

In order to reactivate an RO or SRO license, 10 CFR 55 paragraph 55.53(f) requires:

6.6.1 Before resumption of functions authorized by a license issued under this part, an authorized representative of the facility shall certify the following:

That the licensee has completed a minimum of 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> of shift functions (i.e., UO or OATC for RO; SS or SM for SRO) under the direction of an Operator or Senior Operator (i.e., SS or SM) as appropriate and in the position to which the individual will be assigned. The 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> must have included a complete tour of the plant and all required shift turnover procedures. The 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> must be on a unit that has fuel in the vessel and be performed in the same calendar quarter. Refer to 2.14 page 78, question 277 of NUREG 1262.

6.6.2 The above means that the individual will stand shift with the person in the stated position. The individual reactivating may only be separate from the person who signs for the time credited for infrequent (i.e., 1-2 times in a shift) brief periods. The Plant Tour is part of the 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> of shift functions. At least one shift turnover at the beginning of shift and one at the end of shift must be observed.

6.6.3 Only one individual per licensed position may reactivate under the direction and in the presence of a Licensed Operator or Senior Operator.

6.6.4 The Licensee reactivating shall ensure entries are made in the Control Room Operator Log for the time period involved in reactivation. Plant Tours shall also be documented in the Control Room Operator Log.

6.6.5 Complete NMP-TR-406-F03 of this procedure and return it to the Lead Instructor Operations Continuing Training or the Training Supervisor Operations.

6.6.6 Operations Training Supervision shall forward the form to the Operations Manager for approval.

6.6.7 After the Operations Manager or designee approves the reactivation form, it shall be returned to the Operations Training Group. Training shall then create a learning event in the LMS for Reactivation. Training shall transmit the original to Document Control.

Southern Nuclear Operating Company Nuclear NMP-TR-406 SUTHERN. Management License Administration Version 1 .0 CPANY Procedure Page 13 of 21 6.6.8 The Licensed Operator does not have to stand any more shifts through the end of the quarter in which they reactivated.

6.6.9 The license will remain active until the Licensed Operator fails to meet the requirements of this procedure to maintain an active license.

6.6.10 All items of NMP-TR-406-F03, up to and including the Operations Managers signature for reactivation approval, shall be completed within the same calendar quarter.

6.7 Reactivation of a Senior Reactor Operator for Supervising Core Alterations NOTE Reactivation of the Core Alterations license is only good for one refueling outage and the license shall be de-activated in LMS at the end of the refueling outage.

In order to reactivate a SRO license for supervising Core Alterations only, NUREG 1021 states:

The NRCs requirements regarding the conduct of under-instruction or training watches are reflected in 10 CFR 55.13, which allows trainees to manipulate the controls of a facility under the direction and in the presence of a licensed operator or senior operator... This position is also evident in the responses to Questions 252 and 276 in NUREG 1262, Answers to Questions at Public Meetings Regarding Implementation of Title 10, Code of Federal Regulations, Part 55 on Operators Licenses, which indicate that a trainees activities are to be closely monitored by the responsible person.

6.7.1 If a facility licensee needs to reactivate a regular SRO license for the purpose of supervising refueling activities, the Operator must complete one of the following two (2) options:

6.7.1.1 Option 1 Review core alterations training material, or receive Instructor lead training, and perform evaluated job performance measures (JPMs). This option will ideally be completed no more than one (1) week prior to a refueling outage.

6.7.1.2 Option 2 The Operator must complete one shift under direction on the refueling floor, as discussed above, and the facility licensee must ensure that the Operator is administratively restricted from performing full SRO duties. Only one individual at a time may reactivate under the direction and in the presence of the Senior Operator in charge of refueling.

6.7.2 The individual reactivating shall ensure entries are made in the Control Room Operator Log for the time period involved in reactivation.

6.7.3 Complete NMP-TR-406-F02 of this procedure and return it to the Operations Training Group.

6.7.4 After the requirements of NMP-TR-406-F02 are completed Training shall transmit the original to Document Control.

Southern Nuclear Operating Company I Nuclear I I NMP-TR-406 SOUTHERN Management License Administration Version 1 .0 I Procedure Page l4of 21 I 6.8 Respirator Glasses 6.8.1 Any Licensed Operator whose license is restricted to corrective lenses shall have contacts or respirator glasses readily available to correct their vision to within the limits of ANSI 3.4, 1983 while performing licensed duties.

6.8.2 When a Licensed Operator is initially restricted to corrective lenses, Operations shall be notified by the Operations Training Group via a memo or electronic mail, and this memo will state the need for respirator lenses or contacts.

6.8.3 It shall be the responsibility of the Licensed Operator to ensure that the respirator glasses or contacts will bring them into compliance with the requirements of ANSI 3.4, 1983.

6.9 No Solo Operation 6.9.1 If a Licensed Operators license is amended to No Solo Operation, then the No-Solo requirements shall be met for them to perform active license duties.

6.9.2 A No Solo SRO may be Fueling Handling Supervisor as long as the crew is made aware of the content and implication of the No Solo restriction. However, another SRO shall be onsite and someone capable of summoning the SRO shall be in view of the No Solo SRO.

6.10 Nuclear Regulatory Commission Correspondence 6.10.1 Correspondence to the NRC related to licensee medical condition change, recommended license restriction change, or license renewal applications shall be dispatched in a manner that provides verification of receipt. The verification documentation shall be included in the disposition of Condition Report or Action Item.

6.10.2 When verification is received that correspondence has been delivered, it is recommended that a follow-up phone call be made to confirm.

6.11 License Termination 6.11 .1 When an individual no longer requires a license, the NRC shall be requested in 30 days to terminate the individuals license. Refer to Attachment 6 for a sample letter.

6.11.2 The Operations Training Supervisor or Designee shall initiate a Condition Report once notified to terminate an Operator License to track the 30 day notification.

6.11 .3 The Operations Training Supervisor or Designee shall ensure that LMS is updated.

Southern Nuclear Operating Company I Nuclear I NMP-TR-406 I SUTNRN COAPANV Management License Administration Version 1 .0 I I Procedure I Page 15 of 21 I 7.0 Records 7.1 All records shall be maintained per appropriate site procedures.

QA Non-QA Record Generated R-Type records (X) records (X)

X Active License Maintenance TRO.001 Senior Reactor Operator Reactivation for TRO 001 Core Alterations X License Reactivation Documentation TRO.001 8.0 Commitments 8.1 Farley None 8.2 Hatch None 8.3 Vogtle None

Southern Nuclear Operating Company I Nuclear I NMP-TR-406 I UTHRN Management I License Administration Version 1 .0 I f CPNY Procedure Page 16 of 21 I Attachment I Nuclear Regulatory Commission Medical Restriction Change Letter Sample XXXXX (insert name of Regional Administrator, Region II)

The Regional Administrator, Region II United States Nuclear Regulatory Commission 245 Peachtree Center Avenue, NE Suite 1200 Atlanta, Georgia 30303-1257 Attention: Mr. )(XXX XXXXX: (insert name of Chief, Operations Branch)

Dear XXXXX:

(Insert name of Regional Administrator, Region II)

This letter is to inform you that NAME, docket number 55-)(XX)(X and license number OP-XXXXX-X, has had a change in his medical condition as indicated on the attached per ANSI/ANS 3.4, 1983.

This information is regarded as Privacy Act Information and should be treated as such.

Sincerely, x x. xxxxxx Site Vice President JRJ/DDH:las cc: Site Training Manager (without attachments)

Site Occupational Health Svcs. Lead Spc. (without attachments)

INDIVIDUAL (with attachments)

Southern Nuclear Operating Company I Nuclear I I NMP-TR-406 I I

I SOUThERN CO#PANY Management Procedure I License Administration Version 1.0 Page l7of 21 I C Attachment 2 Routine Nuclear Regulatory Commission License Medical Examination Flowpath Medical Consultant completes Physician portion of NRC Form 396 Operations Training Group notifies the NRC within 30 days

Southern Nuclear Operating Company I Nuclear I NMP-TR-406 I SOUTHERN Management ii License Administration Version 1 O I I Procedure Page 18 of 21 I Attachment 3 Medical Condition Flowpath Medical Review Officer (MRO) evaluates Medical Consultant conditions and determines if Removal from documents evaluation Duty or Restriction Change Individual allowed to return to a Licensed Active Duty LMS Item is removed

Southern Nuclear Operating Company Nuclear NMP-TR-406 SOUTIiERN. Management License Administration Version 1.0 COPPANV Procedure Page l9of 21 Attach ment 4 Medical Conditions List Intra-company Correspondence TO: Licensed Operators Listed below are some of the Medical Conditions that Licensed Operators shall be aware of that can or may have an affect on their license status and require evaluation by Medical Services:

NOTE: These guidelines not all-inclusive and are based on ANSIIANS 3.4-1983. There are many situations and conditions that could affect a person and the licensee should remember that he or she is the one ultimately responsible for the Safe Operation of the Nuclear Power Plant. Any change in your medical condition shall be reported to the Medical Department.

NOTE: Please contact the Medical Services Consultant or the Lead Instructor Operations Continuing Training at any time if you have questions concerning the above.

1. Asthma

2. Emphysema

3. Heart Attack or any other heart condition including High Blood Pressure

4. Diabetes (Use of insulin shall disqualify Operator for Solo Operation)

5. Medical conditions requiring frequent or continued use of steroids (i.e., Lupus, Arthritis, or any other Collagen disorder)

6. Severe recurrent dermatitis (e.g., skin rashes) which could interfere with the wearing of personal protective equipment or decontamination procedures

7. Any abnormal blood work (i.e., blood studies that might indicate Anemia, infection, etc.)

8. Any form of cancer

9. Seizures (A history of Epilepsy shall disqualify the Operator for Solo Operation)

10. Depression, anxiety attacks, etc.

1 1. Any prescription medication NOTE: Medications that can be taken safely and without adverse side affects by one person may have the opposite effect on another, thus evaluating the effect of medication must be done on an individual basis.

12. Any medication taken that could have an effect on an Operators ability to perform (i.e.,

cold medication such as Drixoral, Actifed, etc. that could cause drowsiness, pain medication such as Tylenol #3, Demerol, Darvocet, etc. tranquilizers and anti-depressants such as Elavil, Sinequan, Prozac, Xanax, etc.; antihistamines such as Benadryl, Atarax, etc., and narcotics.

13. Any change in vision (i.e., new corrective lenses, prescription, being told by a doctor that corrective lenses are needed, Radial Keratotomy, etc.)

14. Any loss of mobility (i.e., sprained ankle, which may cause an Operator to need crutches, a hand or wrist splint/cast, etc.)

15. Sleep Apnea

16. Any other condition that could affect an Operators ability to perform under normal, abnormal, and emergency conditions.

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I Attachment 5 License Renewal Letter Sample May 2, 2005 XXXX (insert name of Regional Administrator, Region II)

The Regional Administrator, Region II United States Nuclear Regulatory Commission 245 Peachtree Center Avenue, NE Suite 1200 Atlanta, Georgia 30303-1257 Attention: Mr. XXXX X)O(XX: (insert name of Chief, Operations Branch)

Dear XXXXX:

(insert name of Regional Administrator, Region II)

Please find attached the Personal Qualification Statement--Licensee, NRC Form 398 and the Certification of Medical Examination by Facility Licensee, NRC Form 396, for Mr. Xxx Xxxxxxx Docket number 55-X)(XXX, license number SOP-XXXXX-X, and Mr. Xxxx X. Xxxxx, Docket number 55-XXXXX, and license number OP-XXXXX-X.

If you have any questions about these documents, please contact Training Supervision at XXX-)(XX xXxX.

Sincerely, X.X. XXXXXX Site Vice President JRJ/DDH:las Enclosure cc: Site Training Manager (without attachments)

File

Southern Nuclear Operating Company I Nuclear NMPTR4O6 SQUTHflN Management I License Administration Version 1 .0 Procedure I Page 21 of 21 I Attachment 6 License Termination Letter Sample June 28, 2010 Mr. XXXXX XXXXXXX Regional Administrator, Region II United States Nuclear Regulatory Commission 245 Peachtree Center Ave., NE, Suite 1200 Atlanta, GA 30303-1257 Attention: Mr. XXXXX XXXXXXX

Dear Mr. XXXXXX:

This letter is to notify you that Southern Nuclear has determined that the individual listed below no longer has a need to maintain an operating license and therefore request that his license be terminated.

Mr. XXXX XXXX Docket 55-XXXXX License OP-XXXXX If you should have any questions regarding this matter, please contact Training Supervision at XXX XXX-XXXX.

Sincerely, xxXXxxx Site Vice President cc: Lead Instructor Continuing File

Southern Nuclear Operating Company Nuclear NMP-TR-406-F01 SOUTHERNIS Management Active License Maintenance Version 1.0 COMPANY Form Page 1 of 1 Name:

NOTE: In order to maintain the supervisory portion of a Senior Reactor Operator (SRO) active license, a SRO must stand at least one complete watch (i.e., an 8 or 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift) per calendar quarter in an SRO-only supervisory position. The remainder of the complete watches in a calendar quarter may be performed in either a credited Reactor Operator (RO) or SRO position.

Year:

nd 2

fl .St Quarter (01/01 03/31) fl Quarter (04/01 06/30) rd 3 th 4

Quarter (07/01 09/30) LI Quarter (1 0/01 12/31)

Time On-shift (Technical Specifications Positions)*

Shift Manager, Shift Supervisor, RO (OATC), RO (UO), Fuel Handling Supervisor*

Hours Date Position Unit I have completed the required license maintenance activities (e.g., applicable medical notifications, proficiency time, and respirator updates) in accordance with NMP-TR-406.

Licensed Operators Signature Date I NOTE: Forward the completed form to the Operations Training Coordinator or designee.

The minimum hours on-shift have been met and the individuals below have actively performed the function of an Operator or Senior Operator for five (5) 12-hour shifts or seven (7) 8-hour shifts and shall maintain an Active License through the Quarter, Year and the LMS has been updated.

Operations Training Coordinator or designee Date TRO.001

Southern Nuclear Operating Company SaUTHmRN Nuclear Management I Senior Reactor Operator Reactivation for I NMP-TR-406-F02 Version 1 .0 Core Alterations Form Page 1 of 3 Name:

Part I Qualifications

1. The individual has a valid Senior Reactor Operator license on the appropriate Unit.

Training Department Representative Date Verified

2. The individual is current in the License Operator Continuing Training (LOCT) program.

Training Department Representative Date Verified

3. The individual has completed a medical examination per NMP-TR-406 (i.e., the Learning Management System (LMS) qualification S-MEDNRC current) and is not removed from active licensed duties for medical reasons.

Training Department Representative Date Verified

4. If an individual is restricted to corrective lenses on their license that individual shall verify that the glasses or contacts are readily available and they must be worn when filling a position that requires an active license for supervising Core Alterations.

Individual Signature Date Verified TRNO.001

Southern Nuclear Operating Company I THERN Nuclear Management Senior Reactor Operator Reactivation for NMP-TR-406-F02 Version 1 .0 II Core Alterations CPA4Y Form Page2of3 I Name:

Part II Training and Evaluation I NOTE: Option I or Option 2 shall be performed. The Option not selected will be marked Not Applicable.

Option I

1. The individual received training or reviewed the training material for performing Core Alterations.

Individual Signature Date Verified

2. The individual successfully completed the evaluated job performance measures (JPMs).

Training Department Representative Date Verified Option 2

1. The individual shall complete one shift under direction supervising Core Alterations on the refueling floor. An entry shall be made in the Control Room Operator Log to document the shift.

The signature below means that the individual stood a shift, including turnover at beginning and end of shift, with the person signing. Supervising SROs can have no more than one individual reactivating at a time.

Supervising Senior Reactor Operator Date Verified TRNO.001

Southern Nuclear Operating Company Nuclear NMP-TR-406-F02 Senior Reactor Operator Reactivation for

£UTMRN Management Version 1 .0 Core Alterations A Form Page 3 of 3 Name:

Part Iii Approval and Documentation

1. I understand that I cannot per[orm any other duties requiring an active license other than supervising Core Alterations.

Individual Signature Date Verified

2. Reactivation Approved Operations Manager Date Verified

3. Documentation

a. The LMS item has been updated.

Operations Training Coordinator or designee Date Verified I NOTE: Forward this Form to the Operations Training Department.

b. The LMS item has been verified.

Training Department Representative Date Verified TRNO.001

Name LMS ID Position: [] Reactor Operator LI Shift Supervisor [1 Shift Manager NOTE: To qualify a Plant Operator who has recently obtained an SRO license, if the re activation is in calendar quarter in which the SRO license was obtained, Sections 1.0 and 2.0 of this form are not required. Refer to NUREG 1262, Q. 293.

NOTE: Refer to NMP-TR-406, Section 6.6 for guidance.

Part 1.0 40 Hours under Supervision Section I Hours Date Qualified Persons Signature Section II Participate in a minimum of one shift turnover at the beginning of shift and one at the end of shift Turnover Date Qualified Persons Signature Beginning of Shift End of Shift TRO.OO1

Part 2.0 Plant Tours Complete INOTE: Tours are part of the required 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> per 10 CFR 55.53 (f)(2).

NOTE: Part 2.0 contains sections to be completed for Plants Farley, Hatch, and Vogtle.

Complete the section for the applicable site and mark the other two sections Not Applicable.

Licensee Signature Date Plant Tour with an Active License at the Same or Higher Level for the position for which you are activating. These Tours shall be recorded in the Control Room Operator Log. The Plant Tour should include, but not be limited to, areas listed for each major structure identified in this section. Areas in both Units, where applicable, should be included in the Tour. The qualified person shall sign to document the Tour was completed.

NOTE: The completed Tours shall include all Rounds Areas and shall also be included as part of the 40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> re-activation.

Section I Plant Farley Qualified Person Conducting Tour Areas . Date Signature Non-Rad Auxiliary Building (DC Swgr Rooms, Rod Control Equipment Room, 4160 Swgr Rooms, CCW HX Room, AFW Pump Rooms, MSVR, CR HVAC Room, Cable Spreading_Room)

Rad-Side Auxiliary Building (Chg Pump Rooms, RHR Pump Rooms, RHR HX Room, Penetration Rooms, CS Pump Rooms, SFP and SEP_Pump_Room, Filter_Room)

Turbine Building (All_elevations)

DG Bldg/Outside Tanks Areas (All DG Rooms, Day Tank Rooms, Swgr Rooms, View RMWST, TWST, CST)

SWIS, RWIS, Fire Pump House (Pump and Swgr Rooms in the Intake Structures, Fire Pump Rooms)

Additional areas listed below selected by the Shift Manager:

TRO.001

C Section II Plant Hatch Areas Qualified Person Conducting Tour Date Signature Unit 1 and Unit 2 Reactor Bldg. 228, 185, 158, 130, and Diagonal Areas Unit 1 and Unit 2 Turbine Bldg. 164, 130, and 112 Control Bldg. 130 and 112 Intake Structure and Diesel Building Additional areas listed below selected by the Shift Manager:

Section III Plant Voqtle Qualified Person Conducting Tour Areas . Date Signature Turbine_Building Auxiliary_Building Control Building Outside_Building Additional areas listed below selected by the Shift Manager:

Part 3.0 License Continuing Training Satisfactory Operations Training Supervisor or designee Date TRO.001

Part 4.0 Respirator Qualification Satisfactory Including Self-Contained Breathing Apparatus (SCBA)

Operations Training Supervisor or designee Date Part 5.0 Medical Status Satisfactory Operations Training Supervisor or designee Date Part 6.0 Confirm that the LMS Allows Re-activation Operations Training Supervisor or designee Date Part 7.0 ClassificationlEmergency Notification Network (ENN) Job Performance Measure Shift Supervisor/Shift Manager Only, if not done within the last 12 months. Credit may be granted based on successful simulator or drill performance.

Operations Training Supervisor or designee Date CAUTION: COMPLETION OF THIS DOCUMENT DOES NOT CONSTITUTE PERMISSION TO PERFORM LICENSE DUTIES. A SHIFT ELEGIBITY LETTER MUST BE ISSUED STATING THIS INDIVIDUAL IS ELEIGIBLE TO STAND SHIFT.

Part 8.0 Operations Manager Approval Check the appropriate position:

Position: Reactor Operator Shift Supervisor Shift Manager Operations Manager Date TRO.OO1

FNP HLT-34 ADMIN Page 1 of 5 A2.1.R RO only Equipment Control ADMIN G2.2.41 TITLE: Determine Isolation Boundaries for a CCW Pump Check Valve.

EVALUATION LOCATION: LISIMULATOR LICONTROL ROOM I]CLASSROOM PROJECTED TIME: 30 MTN SIMULATOR IC NUMBER: N/A LIALTERNATE PATH LI TIME CRITICAL L]PRA JPM DIRECTIONS:

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

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

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

• Identify the components and positions required to isolate, vent, and drain a section of piping in preparation for maintenance on a CCW discharge check valve.

• Identify the proper sequence of isolation.

Examinee:

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

EXAMINER:

Developer Billy Thornton Date: 2/8/201 1 NRC Approval SEE NUREG 1021 FORM ES-30i-3

FNPHLT-34ADMIN A2.1.R Page2of5 CONDITIONS When I tell you to begin, you are to DETERMINE ISOLATION BOUNDARIES FCR A CCW PUMP CHECK VALVE. The conditions under which this task is to be performed are:

a. Unit 1 is in Mode 4.

b. lB CCW pump is aligned to B Train.

c. 1C CCW pump was shut down due to a large leak on Q1P17VOO1C, CCW PUMP 1C DISCHARGE CHECK VALVE.

d. The 1 C CCW pump has been Tagged Out electrically.

e. The eSOMS Tagging computer program is not available.

f. You have been directed to manually prepare a Tag Out Listing for isolation of the check valve and draining of the system for repair of the check valve.

g. The Tag Out Listing should identify the proper components to be operated, correct positioning action, and correct sequence of operation.

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

EVALUATION CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

START TIME

1. Determines that 1C CCW PUMP DISCH ISO, VOO2C CLOSED

- S I U VOO2C is required to be closed first to isolate the (See Tag Out sheet) high pressure portion from the lower pressure portions of the system.

2. Determines that the three other isolation V278C CLOSED S / U flowpaths should be closed next. V1O9C CLOSED V144C CLOSED (Sequence of isolation of these valves does not matter.

See Tag Out sheet)

I Note to Evaluator: Steps 3 through 5 may be performed in any order. I

3. Determines that V281C is required to be open to V281C OPEN S / U drain the section between discharge check valve (See Tag Out sheet)

(QVOOIC) and isolation valve (QVOO2C).

FNP HLT-34 ADMIN A2.1.R Page 3 of 5 EVALUATION CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

4. Determines that at least one drain valve is opened V157F OPEN

- S/U to drain the pump section of piping. (All drain V157E OPEN valves may be opened to facilitate draining, but at (Either of these valves or both of least one drain is required to satisfy the Critical these valves may be opened, but at portion of this step.) least one is required.)

(Sequence of opening these valves does not matter.

See Tag Out sheet)

5. Determines that at least one vent valve is opened V279C -OPEN S/U to vent the system. (All vent valves may be V156F OPEN opened to facilitate venting, but at least one vent V156C OPEN is required to satisfy the Critical portion of this (Any one of these valves or all of step.) these valves may be opened, but at least one is required.)

(Sequence of opening these valves does not matter.

See Tag Out sheet)

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

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

FNP HLT-34 ADMIN A2.1 .R Page 4 of 5 GENERAL

REFERENCES:

1. FNP-1-SOP-23.OA, VER 10.0

2. D175002 SHEET 1

3. NMP-AD-003, VER 13.0

4. NMP-AD-003-001, VER 2.0

5. NMP-AD-003-002, VER 6.0

6. NMP-AD-003-F02, VER 1.0

7. KA: G2.2.41 RO 3.5 SRO 3.9 GENERAL TOOLS AND EQUIPMENT:

1. FNP-1-SOP-23.OA, VER 10.0

2. D175002 SHEET 1

3. NMP-AD-003, VER 13.0

4. NMP-AD-003-001, VER 2.0

5. NMP-AD-003-002, VER 6.0

6. NMP-AD-003.-F02, VER 1.0

7. Handout TO for 1 C CCW pump electrical

8. Handout for Candidate NMP-AD-003-F02 Tagout Listing Critical ELEMENT lustification:

STEP Evaluation 1 Critical: Task completion: required to determine that the discharge valve should be closed first to isolate the high pressure portion of the system.

2 Critical: Task completion: required to determine that all other isolation valves that would isolate the discharge check valve from the rest of the CCW system are to be closed next, prior to opening vents and drains.

3 Critical: Task completion: required to open drain valve QV28 1 C to prevent pressurization of piping in case of leakby of the discharge isolation valve.

4 Critical: Task completion: required to determine that at least one drain valve in the pump section of piping is to be opened to allow proper drainage for maintenance.

5 Critical: Task completion: required to determine that at least one vent valve is to be opened to vent the system to allow proper drainage for maintenance.

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FNPHLT-34ADMIN A2.1.R HANDOUT Page 1 of 1 CONDITIONS When I tell you to begin, you are to DETERMiNE ISOLATION BOUNDARIES FOR A CCW PUMP CHECK VALVE. The conditions under which this task is to be performed are:

a. Unit 1 is in Mode 4.

b. lB CCW pump is aligned to B Train.

c. 1C CCW pump was shut down due to a large leak on Q1P17VOO1C, CCW PUMP 1C DISCHARGE CHECK VALVE.

d. The 1 C CCW pump has been Tagged Out electrically.

e. The eSOMS Tagging computer program is not available.

f. You have been directed to manually prepare a Tag Out Listing for isolation of the check valve and draining of the system for repair of the check valve.

g. The Tag Out Listing should identify the proper components to be operated, correct positioning action, and correct sequence of operation.

Southern Nuclear Clearance: #: FOR TRAINING USE ONLY Tagout: #: HLT-34 NRC EXAM Tag Equipment Placement Restoration Num Type Equipment ID st 1 nd 2

Verif Seq Configuration Verif Seq Configuration 1 Description/Location Notes Venf Venf Notes Verif Vent 1-DT- DT IC CCW MCB handswitch CV I STOP/AUTO BT HF 11- Q1 P1 7HS3307CA-A 30,000 1-DT- DT 1C CCW Hot Shutdown Panel CV 2 REMOTE BT HF 11- Local/Remote Switch 30,001 Qi P1 7HS3307CC-A 1-DT- DT 1C CCW Pump 4160V breaker CV 3 RACKED OUT BT HF 11- Q1R15BKRDFO4 30,002

I I I I IU 11 . I DAIS 000001C 3 7205 SV I F 202 01) oT AT

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001 MIS 6911121 11 LOOSE V BETOW TEE 00661207101 002700 7. TO TUE 12191 P210 IS FINE COMPlETE ((5101102119 LIM6S. RIFLE TO OWOOMO RISTISUIWNT [021(0 6111103.

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Southern Nuclear Clearance: #: FOR TRAINING USE ONLY Tagout: #: HLT-34 NRC EXAM Tag Equipment Placement Restoration Num Type Eguirment ID Verif Seq Conficiuration 1st nl Venf Seq Configuration 1 Description/Location Notes Venf Verif Notes Verif Verif 1c 1J,

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I 02/15/2011 (s:48 1 cd2l Active Procedure: FNP-1-SOP-230A, COMPONENT COOLING WATER SYSTEM Type: SOP, Unit: 1, Revision: 10 Step: 1.00 4160V Bus 1G - Ui AB-N/R-121- Switchgear Room Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1R15BKRDGO4 COMPONENT COOLING WATER 4160V BUS 1G. RACKED IN iv PUMP 1A 52-DGO4 U1-AB-N/R-l21-SWGR RM Notes: 76 Q1R15BKRDGO5 COMPONENT COOLING WATER 4160V BUS 1G RACKED IN PUMP lB 52-DGO5 (B TRAIN)

U1-AB-N/R-121-SWGR RM IV L Notes: 76, 77 Step: 1.10 4160V Bus 1 F - Ui AB-NIR-139- Switchgear Room Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1R15BKRDFO5 COMPONENTCOOLINGWATER 416OVBUS1F- RACKEDIN IV PUMP lB 52-DFO5 (A TRAIN) U1-AB-N/R-139-SWGR RM j Notes: 77 Q1R15BKRDFO4 COMPONENT COOLING WATER 4160V BUS iF RACKED IN IV PUMP 1C 52-DFO4 U1-AB-N/R-139-SWGR RM Step: 1.20 MCC 1U - Ui AB-RAD-139- Elec Pen Room Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1RI7BKRFUD4 MKUP TO CCW FROM RMW 1U MCC Q1R17BOO8-A,

- CLOSED IV Q1P17MOV3O31A UNIT 1, 139RAD ELEC.PENE.ROOM Q1R17BKRFUE3 CCW TO 1A RHR HX 1U MCC Q1R17BOO8-A,

- CLOSED IV Q1P17MOV3185A UNIT 1, 139RAD ELEC.PENE.ROOM Q1R17BKRFUI3 MKUP TO CCW FROM DW STOR 1U MCC Q1R17BOO8-A,

- CLOSED IV TKQ1P17MOV3O3OA UNIT 1, 139RAD ELEC.PENE.ROOM Q1R17BKRFUS4 CCWTO1BSFPHX 1UMCC-Q1R17BOO8-A, CLOSED Q1P17MOV3O94B UNIT 1, 139RAD IV 1 ELEC.PENE.ROOM 0p Step: 1.30 MCC lv - UI AB-RAD-139- Elec Pen Room Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1R17BKRFVD2 CCWTOSECONDARYHXS 1VMCC- CLOSED IV Q1P17MOV3O47 Q1R17BOO9-B,UNIT1, 139 RAD EL EC P EN E. ROOM Q1R17BKRFVD3 CCW TO 1A SFP HX iv MCC- CLOSED IV Q1P17MOV3O94A Q1R17BOO9-B,UNIT 1, 139 RAD ELEC.PENE.ROOM

u1211512b11 T3J% 1 2of21 Active Procedure: FNP-1-SOP-23.OA, COMPONENT COOLING WATER SYSTEM Type: SOP, Unit: 1, Revision: 10 Step: 1.30 MCC1V-U1AB-RAD-139-ElecPenRoom Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1R17BKRFVG4 MKEUP TO CCW FROM DW IV MCC CLOSED STOR TK Q1P17MOV3O3OB Q1R17BOO9-B,UNIT 1, iv I 139 RAD ELEC.PENE.ROOM Q1R17BKRFVG5 MKUPTOCCWFROMRMW 1VMCC- CLOSED IV Q1P17MOV3O31B Q1R17BOO9-B,UNIT 1, 139RAD ELEC.PENE.ROOM Q1R17BKRFVU4 CCWTO1BRHRHX 1VMCC- CLOSED Iv Q1P17MOV3185B Q1RI7BOO9-B,UNIT 1, 139 RAD ELEC.PENE. ROOM Step 1 40 UI AB N/R 100 CCW HX Room Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1R18A0004A lB CCW PUMP 4 Ky DISCONNECTSWITCH1A Ui 100 NON-RAD RM 185 ALIGNED PER NOTE 579 iv 7[

Notes: 579 Q1R18A0004A-A-HTR1 DISC SWITCH SPACE HTR BKR lB CCW PUMP 4KV CLOSED IV DISC.SW.Q1R18A0004A-A, IN LOWER COMPT Notes: 391 Step: 1.50 U1-AB-N/R-100- CCW HX Room Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1R18A0004B CCW PUMP lB 4KV DISC SW lB Ui 100 NON-RAD RM 185 ALIGNED PER NOTE IV 580 Notes: 580 Q1R18A0004B-B-HTR1 DISCSWITCHSPACEHTRBKR 1BCCWPUMP4KV CLOSED IV DISC.SW. Q1R18A0004B-B, IN LOWER COMPT Notes: 392 Step 1 60 Aux Bldg 83 Floor Drain Tank Room Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials N1P17V162 CCWRELHDRDRN AUXBLDG83-FLOOR CLOSED&CAPPED IV DRAIN TANK RM 11:5 PagE

112/15/2011 8:48 Active Procedure: FNP-1-SOP-23.OA, COMPONENT COOLING WATER 1 3 of 21 SYSTEM Type: SOP, Unit: 1, Revision: 10 Step: 1.70 Aux Bldg 83 - lB RHR Pump Room Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17V236A 1BRHRPUMPSEALHXCCW AUXBLDG83-1BRHR OPEN IV OUTLET FIS-3062B ROOT PUMP RM Q1P17V236B lB RHR PUMP SEAL HX CCW AUX BLDG 83 lB RHR OPEN OUTLET FIS-3062B ROOT PUMP RM IV J .._._______________

Q1P17V256 lB RI-IR PUMP SEAL HX CCW AUX BLDG 83 lB RHR CLOSED & CAPPED OUTLET VT PUMP RM IV L Q1P17V915B 1BRHRPUMPSEALCOOLER AUXBLDG83-1BRHR CCW INLET DRN PUMP RM CLOSED&CAPPED IV [

Q1P17V916B lB RHR PUMP SEAL COOLER AUX BLDG 83 lB RHR CCW OUTLET DRN PUMP RM CLOSED & CAPPED IV I Q1P17V917B lB RHR PUMP SEAL COOLER AUX BLDG 83 - lB RHR CLOSED & CAPPED IV CCW INLET VENT PUMP RM Q1P17V9188 lB RHR PUMP SEAL COOLER AUX BLDG 83 - lB RI-fR CLOSED & CAPPED IV CCW OUTLET VENT PUMP RM Step 1 80 Aux Bldg 83 1A RHR Pump Room Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17V235A 1A RHR PUMP SEAL HX CCW AUX BLDG 83 OUTLET FIS-3062A ROOT PUMP RM

- 1A RHR OPEN IV [ II Q1P17V235B 1ARHRPUMPSEALHXCCW AUXBLDG83-1ARHR OPEN IV OUTLET FIS-3062A ROOT PUMP RM Q1P17V915A 1ARHRPUMPSEALCOOLER AUXBLDG83 - 1ARHR CLOSED&CAPPED IV CCW INLET DRN PUMP RM Q1P17V916A 1A RHR PUMP SEAL COOLER AUX BLDG 83 1A RHR CCW OUTLET DRN PUMP RM CLOSED & CAPPED IV I

Step: 1.90 Aux Bldg 83 - Corridor Outside RHR HX Room Equip operaMi: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17V19O 1BRHRHXCCWOUTLETDRN AUXBLDG83-CORRIDOR OUTSIDE RHR CLOSED&CAPPED IV J HX RM Q1P17V237A 18 RHR HX CCW OUTLET AUX BLDG 83 - OPEN IV Q1PI7FISH3445B ROOT CORRIDOR OUTSIDE RHR HX RM Q1P17V237B lB RHRHXCCWOUTLET Q1P17FISH3445B ROOT AUX BLDG 83 -

CORRIDOR OUTSIDE RHR OPEN IV H -I - IL  :

HX RM

02/15/2011 8:48 I.T1%rcr I of 21 Active Procedure: FNP-1-SOP-23.OA, COMPONENT COOLING WATER SYSTEM Type: SOP, Unit: 1, Revision: 10 Step: 1.90 Aux Bldg 83 - Corridor Outside RHR HX Room Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17VO26B lB RHR PUMP SEAL HX CCW AUX BLDG 83 - OPEN & SEALED iv OUTLET ISO CORRIDOR OUTSIDE RHR HX RM Notes: 275 Q1P17VO25B 1BRHRPUMPSEALHXCCW AUXBLDG83- OPEN IV PRESS REG INLET ISO CORRIDOR OUTSIDE RHR .

HX RM Q1P17PCV3404B-AIRSUPPLY 1BRHRPUMPSEALHXCCW AUXBLDG83- AIRCUTIN IV PRESS REG CORRIDOR OUTSIDE RHR HX RM Q1P17V28OB PRESS REG Q1P17PCV34O4B AUX BLDG 83 OPEN IV CONT SUPP ISO CORRIDOR OUTSIDE RHR HX RM Q1P17V151B 1BRHRPUMPSEALHXCCW AUXBLDG83- OPEN IV PRESS REG OUTLET ISO CORRIDOR OUTSIDE RHR HX RM Q1P17V184 1BRHRPUMPSEALHXCCW AUXBLDG83 CLOSED&CAPPED IV INLET LINE DRN CORRIDOR OUTSIDE RHR HX RM Q1P17V152B 1BRHRPUMPSEALHXCCW AUXBLDG83- CLOSED IV PRESS REG BYP CORRIDOR OUTSIDE RHR HX RM Step 2 00 Aux Bldg 83 RHR Hx Room Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17VO26A 1A RHR PUMP SEAL HX CCW AUX BLDG 83 - RHR HX OPEN & SEALED IV OUTLET ISO RM Notes: 275 Q1P17VO29A CCW TO 1A RHR HX AUX BLDG 83 - RHR HX CLOSED IV (Q1P17MOV3185A) RM Notes: 345 Q1P17V188 1A RHR PUMP SEAL HX CCW OUTLET VT AUX BLDG 83 RM

- RHR HX CLOSED & CAPPED IV IiI QIP17V124B lB RHR HX CCW INLET DRN AUX BLDG 83 - RHR HX CLOSED & CAPPED IV RM QIP17V23OB 1BRHRHXCCWINLETPI-3057B AUXBLDG83-RHRHX OPEN IV ROOT RM Q1P17V125B 1BRHRHXCCWVT AUXBLDG83-RHRHX CLOSED&CAPPED IV RM

02115!211 8:48 I.J1 1 (5olf21 Active Procedure: FNP-1-SOP-23.OA, COMPONENT COOLING WATER SYSTEM Type: SOP, Unit: 1, Revision: 10 Step: 2.00 Aux Bldg 83 - RHR Hx Room Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17V231B 1BRHRHXCCWOUTLET AUXBLDG83-RHRHX OPEN IV PI-3060B ROOT RM Q1P17VO28B lB RHR HX CCW OUTLET ISO AUX BLDG 83 - RHR HX OPEN & SEALED iv RM Notes: 275 Q1P17VO29B CCWTO 1BRHRHX (Q1P17MOV3185B)

AUXBLDG83-RHRHX RM CLOSED IV fl.VflIV I Notes: 345 Q1P17V185 1BRHRHXCCWOUTLETVT AUXBLDG83-RHRHX CLOSED&CAPPED iv L Q1P17V124A 1ARHRHXCCWINLETDRN AUXBLDG83-RHRHX CLOSED&CAPPED iv RM Q1P17V23OA 1ARHRHXCCWINLETP1-3057A AUXBLDG83 -RHRHX OPEN Iv ROOT RM Q1P17V125A 1A RHR HX CCW VT AUX BLDG 83 - RHR HX CLOSED & CAPPED iv LZ.ZZJ Q1P17V231A 1ARHRHXCCWOUTLET AUXBLDG83-RHRHX OPEN iv V PI-3060A ROOT RM Q1P17VO28A 1ARHRHXCCWOUTLETISO AUXBLDG83 -RHRHX RM OPEN&SEALED iv L Notes: 275 Q1P17PCV34O4A-A1RSUPPLY 1ARHRPUMPSEALHXCCW AUXBLDG83 -RHRHX AIRCUTIN iv Ij V PRESS REG RM Q1P17V28OA PRESS REG 3404A CONT SUPP AUX BLDG 83 RHR HX OPEN IF V V IV V

V ISO RM Q1P17V151A I :5 1A RHR PUMP SEAL HX PRESS REG OUTLET ISO AUX BLDG 83 RM

- RI-IR HX OPEN IV I 1L Q1P17V189 1A RHR PUMP SEAL HX CCW INLET LINE DRN AUX BLDG 83 RM

- RHR HX CLOSED & CAPPED iv I V V

. V Q1P17V152A 1ARHRPUMPSEALHXCCW PRESS REG BYP AUXBLDG83-RHRHX RM CLOSED IV I V Q1P17VO25A lA RHR PUMP SEAL HX CCW PRESSREGINLET AUX BLDG 83 RM

- RHR HX OPEN IV I V VVVVV Q1Pl7V238A 1ARHRHXCCWOUTLET Q1P17F1SH3445A ROOT AUXBLDG83 -RHRHX RM OPEN IV I II Q1P17V238B 1ARHRHXCCWOUTLET AUXBLDG83 -RHRHX Q1P17F1SH3445A ROOT RM OPEN IV I

0211 512b1 i 8:48 TJj9 1 6 of 21 Active Procedure: FNP-1-SOP-23.OA, COMPONENT COOLING WATER SYSTEM Type: SOP, Unit: 1, Revision: 10 Step: 210 Aux Bldg 100 - Liquid Waste Panel Area Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Qi P17V182 CHGPUMPS&1BSFPHXCCW AUXBLDG100 -LIQUID RTN LINE VT WASTE PANELAREA CLOSED&CAPPED IV L Q1P17V261 CHGPUMPS&1BSFPHXCCW AUXBLDG100-LIQUID CLOSED&CAPPED IV RTNLINEDRN WASTE PANELAREA Q1P17V187 CHG PUMPS & lB SFP HX CCW SUPP LINE VT AUX BLDG 100 LIQUID WASTE PANEL AREA

- CLOSED & CAPPED IV r Q1P17V262 CHG PUMPS & lB SFP HX CCW AUX BLDG 100 LIQUID

- CLOSED & CAPPED IV SUPP LINE DRN [__

WASTE PANEL AREA Step: 2.20 Aux Bldg 100 - Chemical Drain Tank Room Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17V183 SEC HXS CCW SUPP LINE VT AUX BLDG 100 - CLOSED & CAPPED IV CHEMICAL DRAIN TANK RM Q1P17V265 SEC HXS CCW RTN LINE VT AUX BLDG 100 - CLOSED & CAPPED IV CHEMICALDRAINTANK RM Step: 2.30 Aux Bldg 100 - Corridor Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17HV2229-AIR SUPPLY CCW SUPP TO SAMPLE CLRS AUX BLDG 100 - AIR CUT IN IV CORRIDOR Q1P17HV2229-JACK CCW SUPP TO SAMPLE CLRS AUX BLDG 100 - FULL OUT IV (HAND JACK) CORRIDOR Q1P17HV2229 CCW SUPP TO SAMPLE CLRS AUX BLDG 100 - OPEN IV CORRIDOR Q1P17V286 INLETISOFORHV-2229CCWTO AUxBLDGloo.:Y, OPEN IV SAMPLE CLRS CORRIDOR N1P17V202 CCW SUPP TO SAMPLE CLR AUX BLDG 100 - CLOSED & CAPPED IV DRN CORRIDOR Q1P17V287 CCW RTN FROM SAMPLE CLRS AUX BLDG 100 - 65-75 GPM & SEALED IV CORRIDOR Notes: 275, 289 N1P17V2O1 CCW RTN FROM SAMPLE CLRS DRN AUX BLDG 100-CORRIDOR CLOSED & CAPPED IV [

Q1P17VO31 LTDNHXCCWINLETISO AUXBLDG100 OPEN IV 1 -

g CORRIDOR

021151211 3:48 jjri 1 7of21 Active Procedure: FNP-1-SOP-23.OA, COMPONENT COOLING WATER SYSTEM Type: SOP, Unit: 1, Revision: 10 Step 230 Aux Bldg 100 Corridor Equip Operator Id: Equip

Description:

Equip LoCation: Required Config: Actual Config: Verification: Initials Q1P17V260 SEAL WTR HX CCW INLET DRN AUX BLDG 100 - CLOSED & CAPPED IV CORRIDOR Q1P17V034 SEALWTRHXCCWINLETISO AUXBLDG100-CORRIDOR OPEN iv T Q1P17V253A LTDN HXCCWOUTLET Fi-3074 AUX BLDG 100- OPEN iv ROOT CORRIDOR Q1P17V253B LTDN HX CCW OUTLET Fi-3074 AUX BLDG 100- OPEN iv ROOT CORRIDOR Q1P17VO33A LTDNHXCCWINLETTEMP AUX BLDG 100- OPEN iv I:

CONTISO CORRIDOR Q1P17TV3083-AIR SUPPLY LTDN HX CCW TEMP CONT AUX BLDG 100 CORRIDOR

- AIR CUT IN iv 1 Q1P17TV3083-JACK LTDN HX CCW TEMP CONT AUX BLDG 100 (HANDJACKDEVICE) CORRIDOR

- NEUTRAL POSITION &

SEALED iv S E

Q1P17VO33B LTDN HX CCW OUTLET TEMP AUX BLDG 100 - OPEN & SEALED iv CONT ISO CORRIDOR Notes: 275 Q1P17V123 LTDN HX CCW TEMP CONT BYP AUX BLDG 100 - CLOSED IV CORRIDOR Notes: 9 Q1P17V252A SEAL WTR HX CCW OUTLET AUX BLDG 100 - OPEN IV FI-3O77ROOT CORRIDOR Q1P17V252B SEAL WTR HX CCW OUTLET AUX BLDG 100 - OPEN IV  :

FI-3077 ROOT CORRIDOR Q1P17V036 SEAL WTR HX CCW OUTLET ISO AUX BLDG 100 - 2 314 TURNS OPEN & iv V CORRIDOR SEALED Notes: 275 11:5 RJ(J(

Q1P17V037 SEAL WTR HX CCW OUTLET ISO AUX BLDG 100 CORRIDOR

- OPEN iv I I V V Q1P17V254 LTDN HX CCW TEMP CONT BYP DRN AUX BLDG 100 CORRIDOR

- CLOSED & CAPPED iv ri .V5.V!SVI SV V

Q1P17HV3O96B CCWTOEVAPPKGS&H2 Ui 100 RAD-SIDE, OPEN IV V RECOMB OVERHEAD, OUTSIDE DOOR TO CHG PUMP HALLWAY QIPI7HV3O96B-AIR SUPPLY CCW TO EVAP PKGS & H2 AUX BLDG 100 - AIR CUT IN IV RECOMB CORRIDOR

021151211 (5:48 1 8ot21 Active Procedure: FNP-1-SOP-23.OA, COMPONENT COOLING WATER SYSTEM Type: SOP, Unit: 1, Revision: 10 Step: 2.30 Aux Bldg 100 - Corridor Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17HV3096B-JACK CCW TO EVAP PKGS & H2 Ui 100 RAD-SIDE, COLLAR DISENGAGED RECOMB (MANUAL JACKING OVERHEAD, OUTSIDE AND LOCKSCREW IV I

DEVICE) DOOR TO CHG PUMP TIGHT HALLWAY Q1P17HV3O96A CCW FROM EVAP PKGS & H2 RECOMB AUX BLDG 100 CORRIDOR - A OPEN IV  :

1 Q1P17HV3O96A-AIR SUPPLY CCW FROM EVAP PKGS & H2 AUX BLDG 100 AIR CUT IN RECOMB CORRIDOR IV L  :

Q1P17HV3096A-JACK CCW FROM EVAP PKGS & H2 AUX BLDG 100- COLLAR DISENGAGED RECOMB (MANUAL JACKING CORRIDOR AND LOCKSCREW IV II DEVICE) TIGHT Step 2 35 Aux Bldg 100 Letdown Hx Room Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17V133 LTDNHXCCWINLETLINEDRN AUXBLDG100-LETDOWN HX RM CLOSED IV 1 Q1P17V134 LTDN HX CCW OUTLET VT AUX BLDG 100 LETDOWN HX RM

- CLOSED & CAPPED IV [ L Step 240 Aux Bldg 100 Seal Water Hx Room Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17V131 SEAL WTR HX CCW DRN AUX BLDG 100 - SEAL CLOSED & CAPPED IV WATERHXRM Q1P17V132 SEAL WTR HX CCW OUTLET VT AUX BLDG 100 - SEAL CLOSED & CAPPED IV WATERHXRM Step 250 Aux Bldg 100 Charging Pump Hallway Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17V192 CHG PUMP CCW DRN AUX BLDG 100 - CLOSED & CAPPED IV CHARGING PUMP HALLWAY CHG PUMP CCW HDR DRN Q1P17V137C AUX BLDG 100 CHARGING PUMP

- CLOSED & CAPPED IV II HALLWAY Q1PI7VO22C CHG PUMP CCW HDR DRN AUX BLDG 100 - CLOSED & CAPPED IV CHARGING PUMP Q1P17VO24D 11:5; CHGPUMPSCCWDRN I HALLWAY AUXBLDG100-CHARGING PUMP HALLWAY CLOSED&CAPPED IV . .

Y2I15I2O11 (3:48 UN1 Active Procedure: FNP-1-SOP-23.0A, COMPONENT COOLING WATER SYSTEM fl 9 of 21 Type: SOP, Unit: 1, Revision: 10 Step 250 Aux Bldg 100 Charging Pump Hallway Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17VO23D CHG PUMPS CCW DRN AUX BLDG 100 - CLOSED & CAPPED IV CHARGING PUMP HALLWAY Q1P17V137A CHG PUMPS CCW DRN AUX BLDG 100 CHARGING PUMP

- CLOSED & CAPPED IV HI HALLWAY Q1P17VO23A CHG PUMPS CCW DRN AUX BLDG 100 - CLOSED & CAPPED IV CHARGING PUMP HALLWAY Q1P17VO24A CHGPUMPSCCWDRN AUXBLDG100 - CLOSED&CAPPED iv CHARGING PUMP HALLWAY BY DOOR 162 Q1P17V186 1A CHG PUMP CCW INLET DRN AUX BLDG 100 - CLOSED & CAPPED IV CHARGING PUMP HALLWAY Q1P17VO22A CHG PUMPS CCW DRN AUX BLDG 100 - CLOSED & CAPPED IV CHARGING PUMP HALLWAY BY DOOR 162 Step 255 Aux Bldg 100 Contaminated Storage Room 172 Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17V191 CHGPUMPCCWDRN AUXBLDG100 CONTAMINATED

- CLOSED&CAPPED IV H STORAGE ROOM 182 Step 2 60 Aux Bldg 121 Piping Penetration Room Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17V167 RCPS CCW SUPP TEST CONN 121 PIPING CLOSED&CAPPED IV (PENE 42) PENETRATION RM 11: I iuj Q1P17V165 RCPS OIL CLR CCW RTN LINE VT (PENE 44)

AUX BLDG 121 PIPING PENETRATION RM

- CLOSED & CAPPED IV H Q1P17V249A RCPS OIL CLR CCW FI-3044 ROOT AUX BLDG 121 PIPING PENETRATION RM

- OPEN IV I V  :

Q1P17V249B RCPS OIL CLR CCW FI-3044 ROOT AUX BLDG 121 PIPING PENETRATION RM

- OPEN IV E Q1P17V1O1 RCPS OIL CLR CCW RTN ISO AUX BLDG 121 PIPING

- OPEN IV PENETRATION RM

0211512U11 8:48 TJ}J 1 F lOot 21 Active Procedure: FNP-1-SOP-23.OA, COMPONENT COOLING WATER SYSTEM Type: SOP, Unit: 1, Revision: 10 Step 2 60 Aux Bldg 121 Piping Penetration Room Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17V1O7 RcpSTHRMBARRCCwRTN ISO (PENE 43)

AUXBLDG121-PIPING PENETRATION RM OPEN iv H Notes: 9 Q1P17V25OA RCPS THRM BARR CCW Fl-3045 AUX BLDG 121 PIPING OPEN ROOT PENETRATION RM iv H Q1P17V2505 RCPS THRM BARR ccw FI-3045 AUX BLDG 121 PIPING

- OPEN IV ROOT PENETRATION RM Q1P17V173 RCPSTHRMBARRCCWRTN AUXBLDG121-PIPING CLOSED&CAPPED IV TEST CONN PENETRATION RM Q1P17VO81 Exc LTDN & RCDT HXS RTN ISO (PENE 46) ccw AUX BLDG 121 PIPING PENETRATION RM

- OPEN IV [II Q1P17HV3067-AIR SUPPLY CCW FROM EXC LTDN/RCDT HXS AUX BLDG 121 PIPING PENETRATIONRM

- AIR CUT IN IV I4t1 r Q1P17HV3067 CCW FROM EXC LTDN/RCDT AUX BLDG 121 PIPING

- OPEN IV HXS PENETRATION RM Q1P17HV3067-JACK ccw FROM EXC LTDN/RCDT AUX BLDG 121 PIPING

- NEUTRAL POSITION & IV HXS (HAND JACK DEVICE) PENETRATION RM SEALED Notes: 275 Q1P17HV3095-AIRSUPPLY CCWTOEXCLTDN/RCDTHXS AUXBLDG121-PIPING PENETRATION RM AIRCUTIN IV

• JL Q1P17HV3095 CCWTOEXCLTDN/RCDTHXS AUXBLDG121-PIPING OPEN IV (PENE45) PENETRATIONRM Q1P17HV3095-JACK CCWTOEXCLTDN/RCDTHXS AUXBLDG121 -PIPING NEUTRALPOSITION& IV (HAND JACK DEVICE) PENETRATION RM SEALED -

Notes: 275 Q1P17V16O EXC LTDN & RCDT HXS CCW AUX BLDG 121 PIPING

- CLOSED, CAPPED & IV RTN LINE TEST CONN PENETRATION RM SEALED Q1P17V166 EXC LTDN & RCDT HXS CCW SUPP LINE TEST CONN AUX BLDG 121 PIPING PENETRATION RM

- CLOSED, CAPPED &

SEALED IV II41II Q1P17V164 CCW DISCH RCP OIL CLR TEST 121 PIPING CLOSED, CAPPED & - IV CONN PENETRATION RM SEALED Q1P17V168 RCPS CCW SUPP TEST CONN 121 PIPING CLOSED, CAPPED & IV PENETRATION RM SEALED Q1P17V161 CCWDISCHEXCLTDN&RCDT HXS DRN AUXBLDG121-PIPING PENETRATION RM CLOSED&CAPPED IV j IL 11*c)

Q1P17V251A EXCLTDN&RCDTHXSCCW AUXBLDG121 PIPING OPEN IV FI-3066 ROOT PENETRATION RM

02115!211 8:48 TJrt-I 1 F 11 of 21 Active Procedure: FNP-1-SOP-230A, COMPONENT COOLING WATER SYSTEM Type: SOP, Unit: 1, Revision: 10 Step: 260 Aux Bldg 121 - Piping Penetration Room Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17V251B ExcLTDN&RcDTHxsccw AUXBLDG121-PIPING OPEN iv FI-3066 ROOT PENETRATION RM Step: 270 Aux Bldg 139 chemistry Lab (above false ceiling)

Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials N1P17V172A SAMPLEHXCCWFI-3O36ROOT AUXBLDG139-CHEMISTRY LAB (ABOVE OPEN iv IIL]I:  ::H V FALSE CEILING)

N1P17V172B SAMPLE HX ccw Fl-3036 ROOT AUX BLDG 139 - OPEN Iv CHEMISTRY LAB (ABOVE FALSE CEILING)

Step: 2.80 Aux Bldg 139 - Control Panel Outside PRF Room Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17HV2229-VLV H/S CCW SUPP TO SAMPLE CLRS AUX BLDG 139 - AUTO v CONTROL PANEL V OUTSIDE PRF RM Q1P17HV2229-VLV IND CCW SUPP TO SAMPLE CLRS AUX BLDG 139 - OPEN IV V*

CONTROL PANEL V V OUTSIDE PRF RM Q1P17HV2229-NORM/BLOCK SW CCW SUPP TO SAMPLE CLRS AUX BLDG 139 - NORMAL IV  :

(KEY SWITCH) CONTROL PANEL V

OUTSIDE PRF RM V

Aux Bldg 121 Waste Evaporator Package Room V

Step: 2.90 -

Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials N1P17V161 TESTCONN AUXBLDG121-ASTE CLOSED&CAPPED IV V EVAPORATORPKGRM N1P17V063 j5 TESTCONN AUXBLDG121-WASTE CLOSED&CAPPED iv EVAPORATOR PKG RM Step: 3.00 Aux Bldg 155- 1ASFPHXRo0m Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials QIP17VOI4A 1A SEP HX CCW DRN AUX BLDG 155 - IA SEP CLOSED IV HX RM Q1P17VO15A 1ASFPHXOUTLETLINEVT AUXBLDG155-1ASFP HXRM CLOSED&CAPPED IV V ViI Q1P17V228A 1A SFP HX CCW FI-3080A ROOT AUX BLDG 155 - 1A SFP OPEN IV HXRM

0211512011 Active TIN 51 1 F 12 of 21 Procedure: FNP-1-SOP-23.OA, COMPONENT COOLING WATER SYSTEM Type: SOP, Unit: 1, Revision: 10 Step: 3.00 Aux Bldg 155 - 1A SFP HX Room Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17V228B 1A SEP HX CCW Fl-3080A ROOT AUX BLDG 155 1A SFP HX RM

- OPEN iv II Q1P17VO16A 1A SEP HX CCW OUTLET ISO AUX BLDG 155 - 1A SFP 14-35 DEG OPEN & IV HX RM SEALED I Notes: 275 Q1P17VO11A CCWTO 1ASFP HX AUX BLDG 155- 1ASEP OPEN iv (Q1P17MOV3O94A) HX RM Step 3 10 Aux Bldg 175 lB SFP HX Room Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17VO15B lB SEP HX CCW OUTLET LINE VT AUX BLDG 175 lB SEP CLOSED & CAPPED HXRM iv L___________________

Q1P17V229A 1BSEPHXCCWEI-3O8OBROOT AUXBLDG175 -1BSEP HXRM OPEN IV Ii Q1P17V229B lB SEP HX CCW EI-3080B ROOT AUX BLDG 175- lB SEP OPEN IV HXRM tep 3 20 Aux Bldg 155 Corridor Drumming Area Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17VO14B lB SEP HX CCW DRN AUX BLDG 155 - CLOSED & CAPPED IV CORRIDOR DRUMMING ..

AREA Q1P17VO16B lB SFP HX CCW OUTLET ISO AUX BLDG 155 CORRIDOR DRUMMING

- 14-35 DEG OPEN &

SEALED IV I AREA Notes: 275 Q1P17VO11B CCWTO1BSEPHX AUXBLDG155- OPEN IV (Q1P17MOV3O94B) CORRIDORDRUMMING AREA Step 330 CTMT 129 North Wall Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17V162 CCWSUPPLINETOEXC LTDN/RCDT HXS TEST CONN CTMT 129-PENETRATIONS 45 AND CLOSED&CAPPED IV J 46 Q1P17HV3443-AIR SUPPLY CCW EROM EXC LTDN/RCDT CTMT 129- AIR CUT IN IV HXS PENETRATIONS 45 AND 11:5 46 age

02115/2011 8:48 TJfJ 1 Active Procedure: FNP-1-SOP-23.OA, COMPONENT COOLING WATER SYSTEM Type: SOP, Unit: 1, Revision: 10 Step 330 CTMT 129 North Wall Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17HV3443 CCW FROM EXC LTDN/RCDT HXS CTMT 129 -

PENETRATIONS 45 AND OPEN IV I H 46 Q1P17HV3443-JACK CCW FROM EXC LTDN/RCDT HXS (HAND JACK DEVICE)

CTMT 129 -

PENETRATIONS 45 AND NEUTRAL POSITION IV I 46 Step: 3.40 CTMT 105 Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17V079 RCDTHXCCWINLETISO CTMT 105 OPEN IV III:

Q1P17VO8O RCDT HX CCW OUTLET ISO CTMT 105 4 1/8 TURNS OPEN &

SEALED IV I Notes: 275 Q1P17V13O RCDT HX CCW INLET LINE DRN CTMT 105 CLOSED & CAPPED IV :i r Q1P17V257 RCDT HX CCW DRN CTMT 105 CLOSED & CAPPED IV I:I Q1P17V129 RCDTHXCCWVT CTMT 105 CLOSED&CAPPED IV 4f4 Q1P17V174 RCDT HX CCW OUTLET LINE TEST CONN CTMT 129 NEAR PENE 25 CLOSED & CAPPED IV I Step 3 50 Aux Bldg 100 CCW Hx Room -

Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17V221A 1ACCWPUMPSUCTPI-3308A ROOT AUXBLDG100 -CCWHX RM OPEN IV II Q1P17V1O9A 1A CCW PUMP SUCT AUX BLDG 100 - CCW HX OPEN IV RM Q1P17V279A 1A CCW PUMP SUCT LINE VT AUX BLDG 100 - CCW HX CLOSED & CAPPED IV J Q1P17V156A 1ACCWPUMPVT AUXBLDG100CCWHX CLOSED&CAPPED IV  :

RM Qi P17V156D 1A CCW PUMP VT AUX BLDG 100 - CCW HX CLOSED & CAPPED IV RM Q1P17V157A 1ACCWPUMPDRN AUXBLDG100-CCWHX CLOSED&CAPPED IV RM Q1P17V157B 1A CCW PUMP DRN AUX BLDG 100 - CCW HX CLOSED & CAPPED IV

02/15/2011 3:48 UNT1 Active Procedure: FNP-1-SOP-23.OA, COMPONENT COOLING WATER F 140121 SYSTEM Type: SOP, Unit: 1, Revision: 10 Step: 3.50 Aux Bldg 100 - CCW Hx Room Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Qi P17V144A 1A CCW PUMP MINI-FLOW AUX BLDG 100 - CCW HX OPEN IV RM Q1P17V278A 1A CCW PUMP CHEM MIXING AUX BLDG 100 - CCW HX CLOSED IV [9 ISO RM Q1P17V21O 1A CCW PUMP MINI-FLOW VT AUX BLDG 100 CCW HX

- CLOSED & CAPPED IV RM Q1P17V258A 1A CCW PUMP REL HDR DRN AUX BLDG 100 - CCW HX CLOSED & CAPPED IV RM Q1P17V222A 1A CCW PUMP DISCH PI-3035A AUX BLDG 100 - CCW HX OPEN IV  :

ROOT RM Qi P17V281A 1A CCW PUMP DISCH HDR DRN AUX BLDG 100 - CCW HX CLOSED & CAPPED IV RM 01 P17VOO2A 1A CCW PUMP DISCH ISO AUX BLDG 100 - CCW HX OPEN IV RM L Q1P17V1O9B lB CCW PUMP SUCT AUX BLDG 100 - W HX OPEN IV RM Q1P17V279B lB CCW PUMP SUCT LINE VT AUX BLDG 100 - CCW HX CLOSED & CAPPED IV RM Q1P17V221B 18 CCW PUMP SUCT P1-33088 AUX BLDG 100 - CCW HX OPEN IV ROOT RM Q1P17V156B 18 CCW PUMP VT AUX BLDG 100 - CCW HX CLOSED & CAPPED IV RM Q1P17V156E lB CCW PUMP VT AUX BLDG 100 - CCW HX CLOSED & CAPPED IV RM Q1P17V157C lB CCW PUMP DRN AUX BLDG 100 - CCW HX CLOSED & CAPPED IV RM Q1P17V157D lB CCW PUMP DRN AUX BLDG 100 - CCW HX CLOSED & CAPPED IV RM Qi P17V144B lB CCW PUMP MINI-FLOW AUX BLDG 100 - CCW HX OPEN IV RM Q1P17V278B lB CCW PUMP CHEM MIXING ISO AUX BLDG 100 RM

- CCW HX CLOSED IV --.1----.--..

Q1P17V178 lB CCW PUMP MINI-FLOW VT AUX BLDG 100 - CCW HX CLOSED & CAPPED IV RM Q1P17V258B 11:5 lB CCW PUMP REL HDR DRN 100 FT UNIT 1 AUX BLDG CLOSED & CAPPED IV dLJ()

SOUTH CCW HX RM 185 BY lB CCW PUMP

211512011 (3:48 Active Procedure: FNP-1-SOP-23.OA, COMPONENT UWT 1 F 15of21 COOLING WATER SYSTEM Type: SOP, Unit: 1, Revision: 10 Step: 3.50 Aux Bldg 100 - CCW Hx Room Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Qi P17V281 B lB CCW PUMP DISCH HDR DRN AUX BLDG 100 RM

- CCW HX CLOSED & CAPPED IV EZZI _z-z]

Qi P17V222B lB COW PUMP DISCH Pl-3035B ROOT AUX BLDG 100 RM

- CCW HX OPEN IV I zi1 Qi PI7VOO2B lB CCW PUMP DISCH ISO AUX BLDG 100 -..CCW HX OPEN RM Q1P17V1O9C 1C CCW PUMP SUCT ISO AUX BLDG 100 CCW HX OPEN RM 1

1C CCW PUMP SUCT LINE VT Q1P17V279C AUX BLDG 100 RM

- CCW HX CLOSED & CAPPED IV I. -EZZi 1C CCW PUMP SUCT PI-3308C Q1P17V221C ROOT AUX BLDG 100 RM

- CCW HX OPEN IV E1 I I Q1P17V1 560 1C CCW PUMP VT AUX BLDG 100 RM

- CCW HX CLOSED & CAPPED IV Ei :*

1C CCW PUMP VT Q1P17V156F AUX BLDG 100 RM

- COW HX CLOSED & CAPPED IV L1I __-1 Qi P17V157E 1C CCW PUMP DRN AUX BLDG 100 - CCW HX CLOSED & CAPPED IV RM Q1P17V157F 1C CCW PUMP DRN AUX BLDG 100 RM

- CCW HX CLOSED & CAPPED IV EZi Q1P17V1 440 1C CCW PUMP MINI-FLOW AUX BLDG 100 RM

- W FIX OPEN IV riI I Q1P17V179 1C CCW PUMP MINI-FLOW VT AUX BLDG 100 - CCW FIX CLOSED & CAPPED IV RM Q1P17V278C 1C CCW PUMP CHEM MIXING AUX BLDG 100 - CCW HX CLOSED IV r i ISO RM I _JL I I .i Qi P1 7V258C 1C CCW PUMP REL HDR DRN AUX BLDG 100 RM

- CCW HX CLOSED & CAPPED IV --. I Qi P17V222C 1C CCW PUMP DISCH PI-3035C ROOT AUX BLDG 100 RM

- CCW HX OPEN IV IWI Ql P17VOO2C 1C COW PUMP DISCH ISO AUX BLDG 100 RM

- CCW FIX OPEN IV L__ZEZ Q1P17V11OA CCW FROM lB RHR HX AUX BLDG 100 - CCW HX OPEN IV RM Notes: 9 Q1P17VOI7A CCW FROM 1A SFP HX AND CHG AUX BLDG 100 - COW FIX OPEN IV PUMPS RM

0211512011 8:48 1 F16c121 Active Procedure: FNP-1-SOP-23.OA, COMPONENT COOLING WATER SYSTEM Type: SOP, Unit: 1, Revision: 10 Step: 3.50 Aux Bldg 100 - CCW Hx Room -

Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: - Initials Q1P17V11OB CCWPUMPSSUCTHDRXCONN AUXBLDG100 -CCWHX CLOSED iv RM Notes: 9, 290 Q1P17V1 1OC CCW PUMPS SUCT HDR XCONN AUX BLDG 100 - CCW HX CLOSED iv RM Notes: 9, 290 Q1P17V11OD CCWPUMPSSUCTHDRXCONN AUXBLDG100 -CCWHX OPEN iv RM [

Notes: 9, 290 Q1P17V11OE CCWPUMPSSUCTHDRXCONN AUXBLDG100-CCWHX OPEN iv RM [_____

Notes: 9, 290 Q1P17VO17B CCWFROM1BSFPHXANDCHG AUXBLDG100-CCWHX OPEN iv PUMPS RM -

Q1P17V281C 1C CCW PUMP DISCH HDR DRN AUX BLDG 100 - CCW HX CLOSED & CAPPED iv RM Q1P17V11OF CCW FROM 1A RHR lix AUX BLDG 100 - CCW HX OPEN iv RM Q1P17VOO4A CCWINLETTO1ACCWHX AUXBLDG100-CCWHX RM OPEN iv L II Q1P17VOO3A CCW PUMPS DiSCH HDRXCONN AUX BLDG 100 -CCWHX CLOSED iv RM Notes: 9, 291 Q1P17VOO3B CCW PUMPS DISCH HDR XCONN AUX BLDG 100 - CCW HX CLOSED iv RM Notes: 9, 291 Q1P17VOO4B CCW INLET TO lB CCW HX AUX BLDG 100 - CCW HX OPEN iv RM Q1P17VOO3C CCWPUMPSDISCHHDRXCONN AUXBLDG100-CCWHX OPEN iv RM Notes: 9, 291 Q1P17VOO3D CCW PUMPS DISCH HDR XCONN AUX BLDG 100 RM

- CCW HX OPEN iv I Notes: 9, 291 Q1P17VOO4C 1t5 CCWINLETTO1CCCWHX AUXBLDG100-CCWHX RM OPEN Iv I IL

02/15/2011 UNT 1 Active Procedure: FNP-1-SOP-23.OA, COMPONENT COOLING WATER SYSTEM F 17of21 Type: SOP, Unit: 1, Revision: 10 Step: 3.50 Aux Bldg 100 - CCW Hx Room Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17V223A 1A CCW HX CCW INLET FT-3043A AUX BLDG 100 CCW HX OPEN ROOT RM iv I Q1P17V223B 1A CCW HX CCW INLET FT-3043A AUX BLDG 100 - CCW HX OPEN iv ROOT RM Q1P17V177 1A CCW HX CCW INLET VT AUX BLDG 100 RM

- CCW HX CLOSED & CAPPED v r Q1P17V226A 1ACCW HX CCW INLET Pi-3038A AUX BLDG 100 CCW HX OPEN IV LZ_Z1 Q1P17VOO5A 1A CCW HX CCW DRN AUX BLDG 100 - CCW HX CLOSED & CAPPED iv RM Q1P17VOO7A 1ACCWHXCCWVT AUXBLDG100 -CCWHX CLOSED&CAPPED iv RM Q1P17VOO5B 1ACCWHXCCWDRN AUX BLDG 100 -CCWHX CLOSED & CAPPED iv [______

Q1P17V227A 1A CCW HX CCW OUTLET AUX BLDG 100 PI-3041A ROOT RM

- CCW HX OPEN IV H Q1P17VOO8A 1A CCW HX CCW OUTLET ISO AUX BLDG 100 CCW HX OPEN iv RM Notes: 292 Q1P17VO1OA BTRN CCWSUPP ISO AUXBLDG100-CCWHX OPEN iv RM Q1P17VOO9A CCW SUPP HDR XCONN AUX BLDG 100 - CCW HX CLOSED iv RM Notes: 9, 291 Q1P17VO12A CCWSUPPTO1ASFPHXAND AUXBLDG100 -CWHX OPEN iv CHG PUMPS RM Q1P17V224A 1BCCWHXCCW1NLETFT-3043B AUXBLDG100-CCWHX OPEN IV Q1P17V224B 1BCCWHXCCW1NLETFT-3043B AUXBLDG100-WHX ROOT RM OPEN IV [

Q1P17V18O lB CCW HX CCW INLET VT AUX BLDG 100 - CCW HX CLOSED & CAPPED IV RM Q1P17V226B lB CCW HX CCW INLET PI-3038B AUX BLDG 100 - CCW HX OPEN IV ROOT RM Q1P17VOO5C lB CCW HX CCW DRN AUX BLDG 100 RM

- CCW HX CLOSED & CAPPED iv ]

02/15/2011 ( 8:48 1 UNW F 18c121 Active Procedure: FNP-1-SOP-23.OA, COMPONENT COOLING WATER SYSTEM Type: SOP, Unit: 1, Revision: 10 Step: 3.50 Aux Bldg 100 CCW Hx Room Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Qi P17VOO7B 1BCCWHXCCWVT AUXBLDG100 -CCWHX CLOSED&CAPPED Iv RM Qi P17V005D lB CCW HX CCW DRN AUX BLDG 100 - CCW HX CLOSED & CAPPED Iv RM .

Qi P17V227B lB CCW HX CCW OUTLET PI-3041B ROOT AUX BLDG 100 RM CCW HX OPEN Iv L i Q1P17VOO8B 1BCCWHXCCWOUTLETISO AUXBLDG100-CCWHX CLOSED Iv RM Notes: 293 Q1P17VOO9B CCW SUPP HDR XCONN AUX BLDG 100 - CCW HX CLOSED Iv I II I RM Notes: 9, 291 Q1P17VOO9C CCW SUPP HDR XCONN AUX BLDG 100 - CCW HX OPEN iv [  :

RM Notes: 9, 291 Q1P17V181 1C CCW HX CCW INLET VT AUX BLDG 100 - CCW HX CLOSED&C,, -

Iv zZ II RM QI P17V225A 1C CCW HX CCW INLET FI-3043C AUX BLDG 100 - CCW HX OPEN I Iv ROOT RM Qi P17V225B 1C CCW HX CCW INLET FI-3043C AUX BLDG 100 CCW HX OPEN Iv 1 .1 ROOT RM Qi P17V226C 1C CCW HX CCW INLET PI-3038C AUX BLDG 100 - CCW HX OPEN Iv L I ROOT RM Qi P17VOO5E 1C CCW HX CCW DRN AUX BLDG 100 RM

- CCW HX CLOSED & CAPPED Iv U I Qi P17VOO7C 1CCCWHXCCWVT AUX BLDG 100 - CCW HX CLOSED & CAPPED Iv RM Q1P17VOO5F 1C CCW HX CCW DRN AUX BLDG 100 - CCW HX CLOSED & CAPPED Iv RM Q1P17V227C 1C CCW HX CCW OUTLET PI-3041C ROOT AUX BLDG 100 RM

- CCW HX OPEN Iv II I QIPI7VOO8C IC CCW HX CCW OUTLET ISO AUX BLDG 100 - CCW HX OPEN IV RM Notes: 294 Q1 P17VOO9D 11:5 CCWSUPPHDRXCONN BLDG 100 -CCWHX$PEN IV LZZZ1 Notes: 9, 291

02/15/2011 8:48 Active Procedure: FNP-1-SOP-23.OA, COMPONENT UNT 1 F 190121 COOLING WATER SYSTEM Type: SOP, Unit: 1, Revision: 10 Step: 3.50 Aux Bldg 100 - CCW Hx Room Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17VO10B A TRN CCW SUPP ISO AUX BLDG 100 - CCW HX OPEN iv  :

RM Q1P17VO12B CCW SUPP TO lB SEP HX AND AUX BLDG 100 CCW HX OPEN CHG PUMPS RM iv H Q1P17V1I6 CCWSRGTKATRNMKUPISO AUXBLDG100-CCWHX OPEN IV RM j Q1P17V12O CCW SRG TK B TRN MKUP ISO AUX BLDG 100 - CCW HX OPEN IV RM Q1P17V175 CCWSRGTKATRNMKUPLINE AUXBLDG100-CCWHX CLOSED&CAPPED iv DRN RM Q1P17V176 CCWSRGTKBTRNMKUPLINE AUXBLDG100-CCWHX CLOSED&CAPPED iv DRN RM N1P11VO45 CCW SRG TK DEMIN INLET ISO AUX BLDG 100 - CCW HX OPEN iv RM Q1P17VO3O CCWTOSECHXS AUXBLDG100 -CCWHX OPEN iv (Q1P17MOV3O47) RM Q1P17V117A MKUPTOCCWFROMRMW AUXBLDG100-CCWHX CLOSED iv (Q1P17MOV3O31A) RM Q1P17V121A MKUPTOCCWFROMDWSTOR AUXBLDG100-CWHX CLOSED iv TK(Q1P17MOV3O3OA) RM Q1P17V117B MKUPTOCCWFROMRMW AUXBLDG100 -CCWHX CLOSED iv (Q1P17MOV3O31B) RM Q1P17V121B MKUP TO CCW FROM DW STOR AUX BLDG 100 - CCW HX CLOSED iv TK(Q1P17MOV3O3OB) RM Step: 3.60 Aux Bldg 175 - CCW Surge Tank Room Equip Operati: Equip

Description:

Equip Location: -fiequired Config: Actual Config: Verification: ,

1 lnitiaI N1P17V179 CCWSRGTKDWHOSECONN AUXBLDG175 -CCW CLOSED&CAPPED iv SURGE TANK RM Q1P17V113A CCWSRGTKATRN DRN AUX BLDG 175 -CCW CLOSED IV SURGE TANK RM Q1P17V1I3B CCWSRGTKBTRNDRN AUX BLDG 175-CCW CLOSED&CAPPED iv SURGETANKRM Q1P17V112A CCWSRGTKL1-3027B&D ROOT AUX BLDG 175 -CCW OPEN iv SURGE TANK RM Q1P17V1 12B CCW SRG TK Li-3027B&D ROOT AUX BLDG 175 CCW

- OPEN iv SURGETANKRM

02/15/2011 UNT1 Active Procedure: FNP-1-SOP-23.OA, COMPONENT COOLING WATER SYSTEM F 20of21 Type: SOP, Unit: 1, Revision: 10 Step: 3.60 Aux Bldg 175 - CCW Surge Tank Room Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17V112C CCWSRGTKLI-3027A&CROOT AUXBLDG175 -CCW OPEN SURGETANKRM iv L IL Q1P17V112D CCW SRG TK Li-3027A&C ROOT AUX BLDG 175 CCW

- OPEN Iv [-E;.

SURGE TANK RM Qi P17V1 14 CCW SRG TK CHEM ADD AUX BLDG 175 CCW CLOSED & CAPPED SURGETANKRM IV L Q1P17RV3028-AIRSUPPLY CCWSRGTKAIRVT AUXBLDG 175 -cCW AIRCUTIN SURGE TANK RM IV ii Q1P17RV3028 CCW SRG TK AIR VT AUX BLDG 175 CCW

- OPEN Iv SURGETANKRM Q1 P17RV3028-JACK CCW SRG TK AIR VT (HAND AUX BLDG 175 CCW NEUTRAL POSITION IV r.

j ..:

JACKDEVICE) SURGETANKRM ...-..-, ... I Q1P17V285A CCWSRGTKLI-3O27AUPPER AUX BLDG 175 -CCW OPEN IV ROOT SURGETANKRM .....

Q1P17V285B CCW SRG TK LI-3027B UPPER AUX BLDG 175 CCW

- OPEN IV t::...-. . ..

ROOT SURGETANKRM Q1P17V285C CCWSRGTKLI-3O27CUPPER AUXBLDG175-CCW 1

ROOT SURGE TANK RM OPEN IV I .

zJErI Q1P17V285D CCW SRG TK LI-3027D UPPER AUX BLDG 175 CCW

- OPEN IV ROOT SURGETANKRM Step 370 Main Control Board Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17RV3028-MCB H/S CCW SRG TK VT MAIN CONTROL BOARD OPEN IV Q1P17HV3O96B&A-MCB H/S CCW TO/FROM EVAP PKGS & H2 Ui MCB OPEN / AUTO IV RECOMB Q1P17HV3O96B&A .

Q1P17MOV3185A-MCB H/S CCW TO 1A RHR HX Ui MCB CLOSE / MID POS. IV Q1P17MOV3185A FU-E3 Notes: 345 Q1P17MOV3185B-MCBH/S CCWTO 1BRHRHX Ui MCB CLOSE/MIDPOS. IV Q1PI7MOV3185B FV-U4 Notes; 345 Q1P17MOV3O94A-MCB H/S CCW TO 1A SFP HX Ui MCB OPEN / MID POS. IV . .j Q1P17MOV3O94A FV-D3 Q1P17MOV3O94B-MCBH/S CCWTO 1BSFPHX Ui MCB OPEN/MIDPOS. IV QIP17MOV3O94B FU-S4 . .

0211512011 3:48 F 21 of 21 Active Procedure: FNP-1-SOP-23.OA, COMPONENT COOLING WATER SYSTEM Type: SOP, Unit: 1, Revision: 10 Step 3 70 Main Control Board Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17M0V3047-MCB H/S CCW TO SECONDARY HXS Ui MCB Q1P17MOV3O47 FV-D2 OPEN /AUTO iv H Q1P17MOV3O31A-MCBH/S MKUPTOCCWFROMRMW Ui MCB CLOSE/MIDPOS. iv Q1P17MOV3O31A FUD4 Q1P17MOV3O3OA-MCB H/S MKUP TO CCW FROM DW STOR Ui MCB CLOSE! MID POS. IV TK Q1P17MOV3O3OA FU-I3 Q1P17MOV3O31B-MCB H/S MKUP TO CCW FROM RMW Ui MCB CLOSE! MID POS.

Q1P17MOV3O31B FV-G5 IV L -

IL IAtB H/S 1

Q1P17MOV303O MKUP TO CCW FROM DW STOR TK Q1P17MOV3O3OB FV-G4 Ui MCB CLOSE / MID POS. IV El Li1l Q1P17HV3067-MCB H/S CCW FROM EXC LTDN/RCDT Ui MCB OPEN I AUTO IV HXS Q1P17HV3067 Q1P17HV3443-MCB H/S CCW FROM EXC LTDN/RCDT Ui MCB OPEN/AUTO IV &.,

HXS Q1P17HV3443 Qi P17HV3095-MCB H/S CCW TO EXC LTDN/RCDT HXS Q1P17HV3095 Ui MCB OPEN / AUTO IV .

. 1 Note# Note Text:

9 For outage return to service, coordinate with SS and stroke vlv a minimum of 1 turn. Submit CR for problems.

76 Alternate DC control power located in Hot Shutdown Panel.

77 Only the BKR for the TRN that the pump is aligned to will be racked in. The other BKR will be racked out.

275 Set for CCW flow balance. S/S permission needed prior to changing the position of this seal wired valve.

289 as shown on Fl-3036 290 May be in opposite position if 1 B CCW pump aligned to B train.

291 May be in opposite position if miscellaneous header on B train.

292 May be in opposite position if lB CCW Hx on service and aligned to B Train.

293 May be in opposite position if lB CCW Hx on service and aligned to either A Train or B Train.

294 May be in opposite position if lB CCW Hx on service and aligned to A Train.

345 May be open if RHR system on service or if CCW pump on associated train not running.

391 Disc switch QI RI8A0004A space heater power supply bkr is Ni R19LOO1J-BKR1 1.

392 Disc switch Q1R18A0004B space heater power supply bkr is NIR19LOO1J-BKR13.

579 Disconnect is required to be Closed when component is aligned to A Train. Disconnect is required to be Open when component is aligned to B Train.

580 Disconnect is required to be Closed when component is aligned to B Train. Disconnect is required to be Open when component is aligned to A Train.

FNP HLT-34 ADMIN Page 1 of 7 A2.1.S SRO only Equipment Control ADMIN G2.2.41 TITLE: Determine Isolation Boundaries for a CCW Pump Check Valve.

EVALUATION LOCATION: LJSIMULATOR LCONTROL ROOM I1CLASSROOM PROJECTED TIME: 30 MTN SIMULATOR IC NUMBER: N/A LIALTERNATE PATH LI TIME CRITICAL L]PRA JPM DIRECTIONS:

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

2. The SRO-only portion of this task is designed to be implemented after completion of the RO portion of this TASK.

3. There are Two Handouts (#1 and #2); Handout #2 precedes Handout #1 to permit issuing the Handouts in the anticipated sequence: Last page = first task.

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

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

• Identify the components and positions required to isolate, vent, and drain a section of piping in preparation for maintenance on a CCW discharge check valve.

• Identify the proper sequence of isolation.

• SRO-only: Identify the applicable LCO Action Statements, Required Actions and Completion Times required by the given conditions.

Examinee:

Overall JPM Performance: Satisfactory 1 Unsatisfactory D Evaluator Comments (attach additional sheets if necessary)

EXAMINER:

Developer Billy Thornton Date: 2/8/20 1 1 NRC Approval SEE NUREG 1021 FORM ES-301-3

FNPHLT-34ADMIN A2.1.S Page2of7 CONDITIONS When I tell you to begin, you are to DETERMiNE ISOLATION BOUNDARIES FOR A CCW PUMP CHECK VALVE. The conditions under which this task is to be performed are:

a. Unit 1 is in Mode 4.

b. lB CCW pump is aligned to B Train.

c. 1C CCW pump was shut down due to a large leak on Q1P17VOO1C, CCW PUMP 1C DISCHARGE CHECK VALVE.

d. The 1 C CCW pump has been Tagged Out electrically.

e. The eSOMS Tagging computer program is not available.

f. You have been directed to manually prepare a Tag Out Listing for isolation of the check valve and draining of the system for repair of the check valve.

g. The Tag Out Listing should identify the proper components to be operated, correct positioning action, and correct sequence of operation.

When the above actions are completed, evaluate Tech Spec and TRM requirements using the following additional information:

a. All RCPs are secured.

b. All Steam Generator Wide Range Levels are 70% and decreasing with draining in progress.

c. lB RHR pump is running.

Based on these conditions, evaluate Tech Spec and TRM requirements and perform the following:

List all TECH SPEC and TRM CONDITIONS, REQUIRED ACTIONS, and COMPLETION TIMES for LCOs not met, if any.

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

EVALUATION CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

START TIME

1. Determines that 1C CCW PUMP DISCH ISO, VOO2C CLOSED

- S / U VOO2C is required to be closed first to isolate the (See Tag Out sheet) high pressure portion from the lower pressure portions of the system.

• 2. Determines that the three other isolation V278C CLOSED S / U flowpaths should be closed next. V109C CLOSED V144C CLOSED (Sequence of isolation of these valves does not matter.

See Tag Out sheet)

FNP HLT-34 ADMIN A2.1.S Page 3of7 EVALUATION CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

Note to Evaluator: Steps 3 through 5 may be performed in any order. I

3. Determines that V281C is required to be open to V281C -OPEN S / U drain the section between discharge check valve (See Tag Out sheet)

(QVOO1C) and isolation valve (QVOO2C).

4. Determines that at least one drain valve is opened V157F OPEN

- S/U to drain the pump section of piping. (All drain V157E OPEN valves may be opened to facilitate draining, but at (Either of these valves or both of least one drain is required to satisfy the Critical these valves may be opened, but at portion of this step.) least one is required.)

(Sequence of opening these valves does not matter.

See Tag Out sheet)

5. Determines that at least one vent valve is opened V279C -OPEN S/U to vent the system. (All vent valves may be V156F OPEN opened to facilitate venting, but at least one vent V156C OPEN is required to satisfy the Critical portion of this (Any one of these valves or all of step.) these valves may be opened, but at least one is required.)

(Sequence of opening these valves does not matter.

See Tag Out sheet)

FNP HLT-34ADMIN A2.1.S Page4of7 EVALUATION CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

SRO PORTION BELOW

6. Evaluates Tech Specs Determines that an LCO exists for: S I U 3.7.7 Component Cooling Water (CCW) System CONDITION A One CCW train inoperable.

REQUIRED ACTION A. I Restore CCW train to OPERABLE status in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

In addition, per a note in REQUIRED ACTION A. 1-Enter applicable Conditions and Required Actions of LCO 3.4.6, RCS LoopsMODE 4, for Residual heat removal loops made inoperable by CCW.

(LCO 3.4.6 may be evaluated before 3.7.7. This is acceptable as long as both are evaluated.)

FNP HLT-34 ADMIN A2.1 .S Page 5 of 7 EVALUATION CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

7. Evaluates Tech Specs Determines that an LCO exists for: S / U 3.4.6 RCS LoopsMODE 4 CONDITION B One required RHR loop inoperable.

AND Two required RCS loops inoperable.

REQUIRED ACTION B. 1 -

Be in Mode 5 in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

(LCO 3.4.6 may be evaluated before 3.7.7. This is acceptable as long as both are evaluated.)

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

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

GENERAL

REFERENCES:

1. FNP-1-SOP-23.OA, VER 10.0

2. D175002 SHEET 1

3. NMP-AD-003, VER 13.0

4. NMP-AD-003-001, VER 2.0

5. NMP-AD-003-002, VER 6.0

6. NMP-AD-003-F02, VER 1.0

7. KA: G2.2.41 RO 3.5 SRO 3.9 G2.2.40 SRO 4.7 GENERAL TOOLS AND EqUIPMENT:

1. FNP-1-SOP-23.OA, VER 10.0

2. D175002 SHEET 1

3. NMP-AD-003, VER 13.0

4. NMP-AD-003-001, VER 2.0

5. NMP-AD-003-002, VER 6.0

6. NMP-AD-003-F02, VER 1.0

7. Handout TO for IC CCW pump electrical

8. Handout for Candidate NMP-AD-003-F02 Tagout Listing

9. Technical Specifications, Bases, TRM, and TRM bases

FNP HLT-34 ADMIN A2.1 .S Page 6 of 7 Critical ELEMENT justification:

STEP Evaluation 1 Critical: Task completion: required to determine that the discharge valve should be closed first to isolate the high pressure portion of the system.

2 Critical: Task completion: required to determine that all other isolation valves that would isolate the discharge check valve from the rest of the CCW system are to be closed next, prior to opening vents and drains.

3 Critical: Task completion: required to open drain valve QV281C to prevent pressurization of piping in case of leakby of the discharge isolation valve.

4 Critical: Task completion: required to determine that at least one drain valve in the pump section of piping is to be opened to allow proper drainage for maintenance.

5 Critical: Task completion: required to determine that at least one vent valve is to be opened to vent the system to allow proper drainage for maintenance.

6 Critical: Task completion: required to determine Tech Spec entry and application for conditions.

7 Critical: Task completion: required to determine Tech Spec entry and application for conditions.

COMMENTS:

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CCW System 3.7.7 3.7 PLANT SYSTEMS 3.7.7 Component Cooling Water (CCW) System LCO 3.7.7 Two CCW trains shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CCW train A.1 NOTE inoperable. Enter applicable Conditions and Required Actions of LCO 3.4.6, RCS LoopsMODE 4, for residual heat removal loops made inoperable by Cow.

Restore CCW train to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A not ANt2 met.

B.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> Farley Units 1 and 2 3.7.7-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

CCW System 3.7.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.7.1 NOTE Isolation of CCW flow to individual components does not render the CCW System inoperable.

Verify each accessible CCW manual, power 31 days operated, and automatic valve in the flow path servicing safety related equipment, that is not locked, sealed, or otherwise secured in position, is in the correct position.

SR 3.7.7.2 Verify each CCW automatic valve in the flow path 18 months that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal.

SR 3.7.7.3 Verify each CCW pump starts automatically on an 18 months actual or simulated actuation signal.

Farley Units 1 and 2 3.7.7-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

RCS LoopsMODE 4 3.4.6 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.6 RCS LoopsMODE 4 LCO 3.4.6 Two ioops consisting of any combination of RCS loops and residual heat removal (RHR) loops shall be OPERABLE, and one loop shall be in operation.

NOTES

1. All reactor coolant pumps (RCPs) and RHR pumps may not be in operation for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> period provided:

a. No operations are permitted that would cause reduction of the RCS boron concentration; and

b. Core outlet temperature is maintained at least 10°F below saturation temperature.

2. No RCP shall be started with any RCS cold leg temperature 325° F unless:

a. The secondary side water temperature of each steam generator (SG) is < 50°F above each of the RCS cold leg temperatures; or

b. The pressurizer water volume is less than 770 cubic feet (24%

of wide range, cold, pressurizer level indication).

APPLICABILITY: MODE 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required RCS loop A.1 Initiate action to restore a Immediately inoperable, second loop to OPERABLE status.

AN Two RHR loops inoperable.

Farley Units 1 and 2 3.4.6-1 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2)

RCS LoopsMODE 4 3.4.6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. One required RHR loop B.1 Be in MODE 5. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> inoperable.

AND Two required RCS loops inoperable.

C. Required RCS or RHR C.1 Suspend all operations Immediately loops inoperable, involving a reduction of RCS boron concentration.

OR AND No RCS or RHR loop in operation. C.2 Initiate action to restore Immediately one loop to OPERABLE status and operation.

SURVEILLANCE_REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.6.1 Verify one RHR or RCS loop is in operation. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.4.6.2 Verify SG secondary side water levels are 75% 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (wide range) for required RCS loops.

SR 3.4.6.3 Verify correct breaker alignment and indicated power 7 days are available to the required pump that is not in operation.

Farley Units 1 and 2 3.4.6-2 Amendment No. 147 (Unit 1)

Amendment No. 138 (Unit 2)

FNPHLT-34ADMIN A2.1S HANDOUT Pglofl C CONDITIONS When I tell you to begin, you are to DETERMINE ISOLATION BOUNDARIES FOR A CCW PUMP CHECK VALVE. The conditions under which this task is to be performed are:

a. Unit 1 is in Mode 4.

b. lB CCW pump is aligned to B Train.

c. 1C CCW pump was shut down due to a large leak on Q1P17VOO1C, CCW PUMP 1C DISCHARGE CHECK VALVE.

d. The 1 C CCW pump has been Tagged Out electrically.

e. The eSOMS Tagging computer program is not available.

f. You have been directed to manually prepare a Tag Out Listing for isolation of the check valve and draining of the system for repair of the check valve.

g. The Tag Out Listing should identify the proper components to be operated, correct positioning action, and correct sequence of operation.

When the above actions are completed, evaluate Tech Spec and TRM requirements using the following additional information:

a. All RCPs are secured.

b. All Steam Generator Wide Range Levels are 70% and decreasing with draining in progress.

c. lB RHR pump is running.

Based on these conditions, evaluate Tech Spec and TRM requirements and perform the following:

List all TECH SPEC and TRM CONDITIONS, REQUIRED ACTIONS, and COMPLETION TIMES for LCOs not met, if any.

Southern Nuclear rating Company Nuclear NMP-AD-003-F02 SOUTHERN A COMPANY Management Tagout Tag Listing Version 1.0 Form Page 1 of 1 Clearance: #: FOR TRAINING USE ONLY Tagout: #: HLT-34 NRC EXAM Tag Equipment Placement Restoration jst Num Type Equipment ID Verif Seq Configuration 2 Verif Seq Configuration 1 Description/Location Notes VenT VenT Notes Verif Verif 1-DT- DT IC CCW MCB handswitch CV I STOP/AUTO BT HF 11- Qi P1 7HS3307CA-A 30,000 1-DT- DT 1C CCW Hot Shutdown Panel CV 2 REMOTE BT HF 1 1- Local/Remote Switch 30,001 Q1 P1 7HS3307CC-A 1-DT- DT 1C CCW Pump 4160V breaker CV 3 RACKED OUT BT HF 11- Q1R15BKRDFO4 30,002

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0-0 . 2 01 2 PT 090000

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TI TI 040 2 DC SPENT FUEL e3,L&02A I 1/2 X 1 060000 0(01 21100I000ER RITES 8025 3/ I. HALVE 0 165100000 HInT 4100 TO CLOSE.

14181 EOC0009000 3/4 001100 COMPONENT COOING oo I I I 041031 t 2. VALUE 0051 0104090 OPEN STOlEN RAR 002164 OSE.

PUUP QTPTTPCOTRV0 3. TIlTS 480110 FURIOSIED 60000 P0060,00 UNiT.

065850 2 DFW4 0_Il 0 1TI ROD 30000 000050 O FOR P020 05(02 SEE 0041. 01700010 SHEETS 002.

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01 _2 PT 1100090 9. FOR PR0060S FLOOR StE 0660. 6016020 s I 090-103 000288% 6. LOCATE VALUES IN COW POMP ROOM.

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7. 001415 VALVE 4*1ST 06 LOCATED AT LEAST N 00010 TIC TOP OF THE LOOP SOIL BOTTOM OF LOOP 0000 0 050156 MUST COTETO ST LEAST 6 BELOW TIlE COI#IECIDI 06272C 0o5290 TO TIlE 9016 PIPE.

8. FOR COMPLETE IHSIRUMEI4T NOMHERS. 00690 TO INSTRUMENT 104100 6115003.

P1 /*1A 001100 . SPOIlT lIEU POOL 0. GAL NUMBERS 100 VENT. 00014 09*0 0,4510040011 no TEAT 000009010 LINES ON EOLIPMENT, OP TO RATE 102500005 THE C 302580 0*0200 II J50 0001511 ROOT OlIVES:

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10. FOR 019090 00401$TWE*M 19 VITO 0.60 01402 ROOT 040005. StE OPEC. 0611692, PAR, 11,5.1 161.

0 3/00 IT. ALL 00945 ORE PTLMPND 60 THE PORTABLE 0041 POMPNO 0* COMPONENT 0000090 690120 06131 P049 IC 1

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14. VOLVE 0 TI1ROTTLES TO 6505 1PM 0010 SEAlED.

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O2i15I2O1 3:15 TJ1N.I 1 1 o121 Active Procedure: FNP-1-SOP-23.OA, COMPONENT COOLING WATER SYSTEM Type: SOP, Unit: 1, Revision: 10 Step: 1.00 4160V Bus 1G - Ui AB-N/R-121- Switchgear Room Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1R15BKRDGO4 COMPONENT COOLING WATER 4160V BUS 1G - RACKED IN IV PUMP 1A 52-DGO4 U1-AB-N/R-121-SWGR RM Notes: 76 Q1R15BKRDGO5 COMPONENT COOLING WATER PUMP lB 52-DG05 (B TRAIN) 4160V BUS 1G -

IJ1-AB-NIR-121-SWGR RM RACKED IN iv [

Notes: 76, 77 Step: 1.10 416OVBu51F-U1 AB-N/R-139-SwitchgearRoom Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1R15BKRDFO5 COMPONENT COOLING WATER 4160V BUS iF - RACKED IN IV PUMP lB 52-DFO5 (A TRAIN) U1-AB-N/R-139-SWGR RM Notes: 77 01 Ri 5BKRDFO4 COMPONENT COOLING WATER PUMP 1C 52-DFO4 4160V BUS iF U1-AB-N/R-i39-SWGR RM RACKED IN IV [

Step: 1.20 MCC 1U - Ui AB-RAD-139- Elec Pen Room Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1R17BKRFUD4 MKUP TO CCW FROM RMW Q1P17MOV3O3IA 1U MCC Q1R17BOO8-A, UNIT 1. 139RAD CLOSED IV [ I ELEC.PENE.ROOM Q1R17BKRFUE3 CCWTO1ARHRHX Q1P17MOV3185A 1UMCC-Q1R17BOO8-A, UNIT1,139RAD CLOSED IV H ELEC.PENE.ROOM Qi R17BKRFUI3 MKUP TO CCW FROM DW STOR 1 U MCC Qi Ri 7B008-A,

- CLOSED IV TKQ1P17MOV3O3OA UNIT 1, 139RAD [_

ELEC.PENE.ROOM Q1R17BKRFUS4 CCWTO lB SFP HX 1IJ MCC Q1R17BOO8-A,

- CLOSED IV Q1P17MOV3O94B UNIT 1, 139 RAD ELEC.PENE.ROOM Oic Step: 1.30 MCC 1V - Ui AB-RAD-139- Elec Pen Room Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1R17BKRFVD2 CCWTO SECONDARY HXS 1VMCC CLOSED IV Qi P17MOV3047 Qi R17B009-B,UNIT 1, 139 RAD ELEC .PENE. ROOM Q1R17BKRFVD3 CCW TO 1A SFP HX lv MCC - CLOSED IV 01 P17M0V3094A 01 R17B009-B,UNIT 1 139RAD ELEC.PENE.ROOM

TTKffi 1 0211512011 3:15 (

iJI( I 2of21 Active Procedure: FNP-1-SOP-230A, COMPONENT COOLING WATER SYSTEM Type: SOP, Unit: 1, Revision: 10 Step: 1.30 MCC lv Ui AB-RAD-139- Elec Pen Room Equip Operator Id: [quip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials 01 Ri 7BKRFVG4 MKEUP TO CCW FROM DW lv MCC - CLOSED Iv STORTKQ1P17MOV3O3OB Q1R17BOO9-B,UNIT 1, 139 RAD ELEC.PENE.ROOM 01 Ri 7BKRFVG5 MKUP TO CCW FROM RMW iv MCC - CLOSED iv 01 P17MOV3O31 B Qi R17B009-B,UNIT 1, 139RAD ELEC .PENE. ROOM Q1R17BKRFVU4 CCWTO1BRHRHX IVMCC- CLOSED Q1P17MOV3185B Q1R17BOO9-B,UNIT 1, Iv L 11 139RAD ELEC. PEN E.ROOM Step: 1.40 U1-AB-N/R-100-CCWHXRoom Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1R18A0004A lB CCW PUMP 4 KV Ui 100 NON-RAD RM 185 ALIGNED PER NOTE iv DISCONNECT SWITCH 1A 579 Notes: 579 Q1R18A0004A-A-HTR1 DISC SWITCH SPACE HTR BKR lB CCW PUMP 4KV CLOSED IV DISC.SW. Q1R18A0004A-A, IN LOWER COMPT Notes: 391 Step: 1.50 Ui-AB-N/R-iOO-CCWHXRoom Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1R18A0004B CCW PUMP lB 4KV DISC SW lB Ui 100 NON-RAD RM 185 ALIGNED PER NOTE 580 IV [

Notes: 580 Q1R18A0004B-B-HTR1 DISCSWITCHSPACEHTRBKR 1BCCWPUMP4KV DISC.SW. Q1R18A0004B-B, CLOSED IV H IN LOWER COMPT Notes: 392 Step 1 60 Aux Bldg 83 Floor Drain Tank Room Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials N1P17V162 CCWRELHDRDRN AUXBLDG83-FLOOR CLOSED&CAPPED DRAIN TANK RM IV IL 12:1 PagE

02/15/2011 3:15 IJ1\tjI 1 Th 3 of 21 Active Procedure: FNP-1-SOP-23.OA, COMPONENT COOLING WATER SYSTEM Type: SOP, Unit: 1, Revision: 10 Step: 1.70 Aux Bldg 83 - lB RHR Pump Room Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17V236A lB RHR PUMP SEAL HX CCW lB RHR OUTLET FIS-3062B ROOT AUX BLDG 83 PUMP RM

- OPEN iv I Q1P17V236B 1BRHRPUMPSEALHXCCW OUTLET FIS-3062B ROOT AUXBLDG83 PUMP RM

- 1BRHR OPEN iv  : :1 Q1P17V256 lB RHR PUMP SEAL HX CCW OUTLET VT AUX BLDG 83 PUMP RM

- lB RHR CLOSED & CAPPED iv I QIPI7V915B lB RHR PUMP SEAL COOLER AUXBLDG83-1BRHR CLOSED&CAPPED CCW INLET DRN PUMP RM IV L________________

Q1P17V916B lB RHR PUMP SEAL COOLER AUX BLDG 83 - lB RHR CLOSED & CAPPED iv CCW OUTLET DRN PUMP RM Q1P17V917B 1BRHRPUMPSEALCOOLER CCWINLETVENT AUXBLDG83-1BRHR PUMPRM CLOSED&CAPPED iv [ ]

Q1P17V918B lB RHR PUMP SEAL COOLER AUX BLDG 83 lB RHR CLOSED & CAPPED CCW OUTLET VENT PUMP RM iv Z

Step: 1,80 Aux Bldg 83 - 1A RHR Pump Room Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17V235A 1ARHRPUMPSEALHXCCW OUTLET F1S-3062A ROOT AUXBLDG83-1ARHR PUMP RM OPEN iv I Q1P17V235B 1ARHRPUMPSEALHXCCW AUXBLDG83-1ARHR OPEN iv OUTLET F1S-3062A ROOT PUMP RM ,

Q1P17V915A 1ARHRPUMPSEALCOOLER AUXBLDG83-1ARHR CLOSED&CAPPED iv CCW INLET DRN PUMP RM Q1P17V916A 1A RHR PUMP SEAL COOLER CCW OUTLET DRN AUX BLDG 83 PUMP RM

- 1A RHR CLOSED & CAPPED IV r ii Step 1 90 Aux Bldg 83 Comdor Outside RHR HX Room

,;oi Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17V19O 1BRHRHXCCWOUTLETDRN AUXBLDG83-CORRIDOR OUTSIDE RHR CLOSED &CAPPED IV II1 HX RM Q1P17V237A 1BRHRHXCCWOUTLET AUXBLDG83- OPEN IV Q1P17F1SH3445B ROOT CORRIDOR OUTSIDE RHR HX RM Q1P17V237B lB RHR HX CCW OUTLET Q1P17FISH3445B ROOT AUX BLDG 83 -

CORRIDOR OUTSIDE RHR OPEN IV 1 HX RM

0211512011 (3:15 TJJ\rT 1 Active Procedure: FNP-1-SOP-23.OA, COMPONENT COOLING WATER SYSTEM Type: SOP, Unit: 1, Revision: 10 Step: i9o Aux Bldg 83 - Corridor Outside RHR HX Room Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17VO26B 1BRHRPUMPSEALHXCCW AUXBLDG83 - OPEN&SEALED IV OUTLETISO CORRIDOROUTSIDERHR HX RM Notes: 275 Q1P17V025B 1BRHRPUMPSEALHXCCW AUXBLDG83- OPEN IV PRESS REG INLET ISO CORRIDOR OUTSIDE RHR HXRM Q1P17PCV34O4B-AIR SUPPLY lB RHR PUMP SEAL HXCCW PRESS REG AUXBLDG83-CORRIDOR OUTSIDE RHR AIRCUTIN Iv r IL HX RM Q1P17V28OB PRESS REG Qi P17PCV34O4B AUX BLDG 83 - OPEN iv CONT SUPP ISO CORRIDOR OUTSIDE RHR .

HX RM Q1P17V151B lB RHR PUMP SEAL HXCCW AUX BLDG 83- OPEN IV PRESS REG OUTLET ISO CORRIDOR OUTSIDE RHR HX RM Q1P17V184 1BRHRPUMPSEALHXCCW AUXBLDG83- CLOSED&CAPPED iv INLET LINE DRN CORRIDOR OUTSIDE RHR HX RM Q1P17V152B lB RHR PUMP SEAL HX CCW AUX BLDG 83 - CLOSED iv

• PRESS REG BYP CORRIDOR OUTSIDE RHR HX RM Step 200 Aux Bldg 83 RHR Hx Room Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17V026A 1A RHR PUMP SEAL HX CCW AUX BLDG 83 - RHR HX OPEN & SEALED IV OUTLET ISO RM Notes: 275 Q1P17VO29A CCW TO lA RHR HX AUX BLDG 83 - RHR HX CLOSED iv (Q1P17MOV3185A) RM Notes: 345 Q1P17V188 1ARHRPUMP SEAL HX CCW AUX BLDG 83 - RHR HX CLOSED & CAPPED iv Q1PI7V124B lB RHR HX CCW INLET DRN AUX BLDG 83 RM

- RHR FIX CLOSED & CAPPED iv IJII Q1P17V23OB lB RHR HX CCW INLET P13057B AUX BLDG 83 - RHR HX OPEN IV ROOT RM Q1P17V125B 1BRHRHXCCWVT AUXBLDG83-RHRHX RM CLOSED&CAPPED iv L________________

02/15/2011 F 3:15 JiJb5[ 1 5of21 Active Procedure: FNP-1-SOP-23.OA, COMPONENT COOLING WATER SYSTEM Type: SOP, Unit: 1, Revision: 10 Step: 2.00 AuxBIdg83 - RHRHxRoom Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17V231B 1BRHRHXCCWOUTLET AUXBLDG83-RHRHX OPEN iv PI-3060B ROOT RM Q1P17VO28B lB RHR HX CCW OUTLET ISO AUX BLDG 83 - RHR HX OPEN & SEALED iv  :

RM Notes: 275 Q1P17VO29B CCWTO1BRHRHX AUXBLDG83-RHRHX CLOSED iv (Q1P17MOV3185B) RM Notes: 345 QlP17V185 lB RHR HX CCW OUTLET VT AUX BLDG 83 - RHR HX CLOSED & CAPPED iv RM Q1P17V124A 1ARHRHXCCWINLETDRN AUXBLDG83-RHRHX CLOSED&CAPPED iv -c.SVc. -< -

RM Q1P17V23OA 1A RHR HX CCW INLET PI-3057A AUX BLDG 83 ROOT RM

- RHR HX OPEN iv I Q1P17V125A 1A RHR HX CCW VT AUX BLDG 83 - RHR HX CLOSED & CAPPED iv RM Q1P17V231A 1ARHRHXCCWOUTLET AUXBLDG83-RHRHX OPEN iv PI-3060A ROOT RM Q1P17VO28A 1A RHR HX CCW OUTLET ISO AUX BLDG 83 - RHR HX OPEN & SEALED ..-:.

RM Notes: 275 Q1P17PCV34O4A-A1RSUPPLY 1ARHRPUMPSEALHXCCW AUXBLDG83-RHRHX AIRCUTIN IV PRESSREG RM Q1P17V28OA PRESS REG 3404A CONT SUPP AUX BLDG 83 - RHR HX OPEN IV ISO RM Q1P17V151A 1A RHR PUMP SEAL HX PRESS AUX BLDG 83 - RHR HX OPEN IV REG OUTLET ISO RM j I2 I Q1P17V189 1A RHR PUMP SEAL HX CCW AUX BLDG 83 - RHR HX CLOSED & CAPPED IV INLET LINE DRN RM Q1P17V152A 1ARHRPUMPSEALHXCCW PRESSREGBYP AUXBLDG83-RHRHX RM CLOSED Iv I Q1PI7VO25A 1A RHR PUMP SEAL HX CCW AUX BLDG 83 - RHR HX OPEN IV PRESS REG INLET RM Q1P17V238A 1ARHRHXCCWOUTLET AUXBLDG83-RHRHX OPEN IV Q1P17F1SH3445A ROOT RM Q1P17V238B 1A RHR HX CCW OUTLET AUX BLDG 83 RHR HX OPEN Q1P17FISH3445A ROOT RM IV J___________________

TT1b Y

4 F I 0211512011 3:15 tJ I( 6of21 Active Procedure: FNP-1-SOP-23.OA, COMPONENT COOLING WATER SYSTEM Type: SOP, Unit: 1, Revision: 10 Step: 2.10 Aux Bldg 100 - Liquid Waste Panel Area Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17V182 CHGPUMPS&1BSFPHXCCW RTNLINEVT AUXBLDG100-LIQUID WASTEPANELAREA CLOSED&CAPPED iv r Q1P17V261 CHGPUMPS&1BSFPHXCCW AUXBLDG100-LIQUID CLOSED&CAPPED iv RTN LINE DRN WASTE PANEL AREA Q1P17V187 CHGPUMPS&1BSFPHXCCW AUXBLDG100-LIQUID CLOSED&CAPPED SUPPLINEVT WASTEPANELAREA IV [

Q1P17V262 CHG PUMPS & lB SFP HX CCW AUX BLDG 100 LIQUID CLOSED & CAPPED SUPPLINEDRN WASTEPANELAREA iv 11 Step 220 Aux Bldg 100 Chemical Drain Tank Room Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17V183 SECHXSCCWSUPPLINEVT AUXBLDG100- CLOSED&CAPPED CHEMICAL DRAIN TANK IV L RM Q1P17V265 SEC HXS CCW RTN LINE VT AUX BLDG 100 CHEMICAL DRAIN TANK CLOSED & CAPPED IV 1 ri RM Step: 2.30 Aux Bldg 100 - Corridor Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17HV2229-AIRSUPPLY CCWSUPPTOSAMPLECLRS AUXBLDG100 - AIRCUTIN IV CORRIDOR Q1P17HV2229-JACK CCW SUPP TO SAMPLE CLRS AUX BLDG 100 - FULL OUT IV I (HAND JACK) CORRIDOR Q1P17HV2229 CCW SUPP TO SAMPLE CLRS AUX BLDG 100 OPEN CORRIDOR IV I Q1P17V286 INLETISOFORHV-2229CCWTO AUXBLDG100 - OPEN IV SAMPLE CLRS CORRIDOR N1P17V202 CCW SUPP TO SAMPLE CLR AUX BLDG 100 - CLOSED & CAPPED IV DRN CORRIDOR Q1P17V287 CCW RTN FROM SAMPLE CLRS AUX BLDG 100 - 65-75 GPM & SEALED IV CORRIDOR Notes: 275, 289 N1P17V2O1 CCW RTN FROM SAMPLE CLRS DRN AUX BLDG 100 CORRIDOR

- CLOSED & CAPPED IV L IL Q1P17VO31 2[

LTDN HX CCW INLET ISO AUX BLDG 100 CORRIDOR

- OPEN IV fl:

02/1512011 3:15 UNf Active Procedure: FNP-1-SOP-23.OA, COMPONENT COOLING WATER 1 ,,\

of 21 SYSTEM Type: SOP, Unit: 1, Revision: 10 Step: 2.30 Aux Bldg 100 - Corridor Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17V260 SEAL WTR HX CCW INLET DRN AUX BLDG 100 CORRIDOR

- CLOSED & CAPPED iv L iI__________

Q1P17V034 SEAL WTR HX CCW INLET ISO AUX BLDG 100 - OPEN IV CORRIDOR Q1P17V253A LTDNHXCCWOUTLETFI-3074 AUXBLDG100- .,, OPEN IV ROOT CORRIDOR.-

Q1P17V253B LTDNHXCCWOUTLETFI-3074 AUXBLDG100- OPEN Iv ROOT CORRIDOR Q1P17VO33A LTDNHXCCWINLETTEMP AUXBLDG100- OPEN IV CONT ISO CORRIDOR Q1P17TV3083-AIRSUPPLY LTDNHXCCWTEMPCONT AUXBLDG100- AIRCUTIN IV CORRIDOR Qi P1 7TV3083-JACK LTDN HX CCW TEMP CONT (HAND JACK DEVICE)

AUX BLDG 100 CORRIDOR NEUTRAL POSITION &

SEALED IV I$i:

Q1PI7VO33B LTDN HX CCW OUTLET TEMP AUX BLDG 100 -.

OPEN & SEALED IV CONT ISO CORRIDOR Notes: 275 Q1P17V123 LTDN HX CCW TEMP CONT BYP AUX BLDG 100 CORRIDOR

- CLOSED IV L Notes: 9 Q1P17V252A SEALWTRHXCCWOUTLET FI-3077 ROOT AUX BLDG 100 CORRIDOR

- OPEN IV r Q1P17V252B SEAL WTR HXCCWOUTLET AUX BLDG 100- OPEN IV FI-3077 ROOT CORRIDOR SEALWTRHXCCWOUTLETISO Q1P17V036 AUXBLDG100..

CORRIDOR 23/4TURNSOPEN&

SEALED IV IL Notes: 275 l?1.

Q1P17V037 SEALWTRHXCCWOUTLETISO AUXBLDG100 CORRIDOR

- OPEN Iv I I[

LTDN HX CCW TEMP CONT BYP Q1P17V254 DRN AUX BLDG 100 CORRIDOR

- CLOSED & CAPPED IV L______ -

Q1PI7HV3O96B CCW TO EVAP PKGS & H2 Ui 100 RAD-SIDE, OPEN IV RECOMB OVERHEAD, OUTSIDE DOOR TO CHG PUMP HALLWAY Q1P17HV3O96B-AIR SUPPLY CCW TO EVAP PKGS & H2 AUX BLDG 100 - AIR CUT IN IV RECOMB CORRIDOR

02/15/2011 3:15 Active Procedure: FNP-1-SOP-23.OA, COMPONENT 1

UN 8cg121 COOLING WATER SYSTEM Type: SOP, Unit: 1, Revision: 10 Step: 2.30 Aux Bldg 100 - Corridor Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17HV3O96B-JACK CCWTOEVAPPKGS&H2 Ui 100 RAD-SIDE, RECOMB (MANUAL JACKING OVERHEAD, OUTSIDE COLLAR DISENGAGED AND LOCKSCREW iv [ -

DEVICE) DOOR TO CHG PUMP TIGHT HALLWAY Q1P17HV3O96A CCW FROM EVAP PKGS & H2 AUX BLDG 100 OPEN RECOMB CORRIDOR IV L________

Q1P17HV3O96A-AIR SUPPLY CCW FROM EVAP PKGS & H2 AUX BLDG 100 AIR CUT IN IV .

RECOMB CORRIDOR Q1P17HV3O96A-JACK CCW FROM EVAP PKGS & H2 AUX BLDG 100 - COLLAR DISENGAGED IV RECOMB (MANUAL JACKING CORRIDOR AND LOCKSCREW DEVICE) TIGHT Step 235 Aux Bldg 100 Letdown Hx Room .

Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17V133 LTDNHXCCWINLETLINEDRN AUXBLDG100-LETDOWN HX RM CLOSED IV L II Q1P17V134 LTDN HX CCW OUTLET VT AUX BLDG 100 - CLOSED & CAPPED IV LETDOWN HX RM -

Step: 2.40 Aux Bldg 100 - Seal Water Hx Room Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17V131 SEALWTRHXCCWDRN AUXBLDG100-SEAL CLOSED&CAPPED IV WATERHXRM Q1P17V132 SEALWTRHXCCWOUTLETVT AUX BLDG 100 -SEAL CLOSED&CAPPED IV WATERHXRM Step: 2.50 Aux Bldg 100 - Charging Pump Hallway Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17V192 CHG PUMP CCW DRN AUX BLDG 100 CHARGING PUMP

- CLOSED & CAPPED IV L:; ,

HALLWAY Q1P17\/i37C CHG PUMP CCW HDR DRN W

AUX BLDG 100-CHARGING PUMP CLOSED & CAPPED IV II HALLWAY Q1PI7VO22C CHG PUMP CCW HDR DRN AUX BLDG 100 - CLOSED & CAPPED IV CHARGINGPUMP --

HALLWAY Q1P17VO24D 121 CHG PUMPS CCW DRN AUX BLDG 100 CHARGING PUMP

- CLOSED & CAPPED IV II HALLWAY

0211512011 1 3:15 ijrq Active Procedure: FNP-1-SOP-23.OA, COMPONENT COOLING WATER SYSTEM 1 9 of 21 Type: SOP, Unit: 1, Revision: 10 Step 2 50 Aux Bldg 100 Charging Pump Hallway Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17VO23D CHG PUMPS CCW DRN AUX BLDG 100 - CLOSED & CAPPED IV 1 CHARGING PUMP I HALLWAY Q1P17V137A CHGPUMPSCCWDRN AUXBLDG100 CHARGING PUMP

- CLOSED&CAPPED IV [ -

1 I

HALLWAY Q1P17VO23A CHG PUMPS CCW DRN AUX BLDG 100 - CLOSED & CAPPED IV CHARGING PUMP HALLWAY Q1P17VO24A CHGPUMPSCCWDRN AUX BLDG 100- CLOSED &CAPPED IV CHARGING PUMP -

HALLWAY BY DOOR 162 Q1P17V186 1ACHGPUMPCCWINLETDRN AUXBLDG100- CLOSED&CAPPED IV CHARGING PUMP HALLWAY Q1P17VO22A CHG PUMPS CCW DRN AUX BLDG 100 - CLOSED & CAPPED IV CHARGING PUMP HALLWAY BY DOOR 162

-q Step: 2.55 Aux Bldg 100 - contaminated Storage Room 172 Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17V191 CHG PUMP CCW DRN AUX BLDG 100 - CLOSED & CAPPED IV CONTAMINATED STORAGE ROOM 182 Aux Bldg 121 Piping Penetration Room Step: 2.60 -

iir Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17V167 RCPS CCW SUPP TEST CONN 121 PIPING CLOSED & CAPPED IV (PENE 42) PENETRATION RM 12.1 ... Iiqr Q1P17V165 RCPS OIL CLR CCW RTN LINE AUX BLDG 121 PIPING

- CLOSED & CAPPED IV VT (PENE 44) PENETRATION RM Q1P17V249A RCPS OIL CLR CCW Fl-3044 ROOT AUX BLDG 121 PIPING PENETRATION RM

- OPEN IV I .

Q1P17V249B RCPS OIL CLR CCW FI-3044 AUX BLDG 121 PIPING

- OPEN IV ....,.

ROOT PENETRATION RM . -.

QIP17V1O1 RCPS OIL CLR CCW RTN ISO AUX BLDG 121 PIPING

- OPEN IV PENETRATION RM

02/1512011 (3:15 JJJ 1 F1O ol 21 Active Procedure: FNP-1-SOP-23.OA, COMPONENT COOLING WATER SYSTEM Type: SOP, Unit: 1, Revision: 10 Step 2 60 Aux Bldg 121 Piping Penetration Room Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17V1O7 RCPSTHRMBARRCCWRTN AUXBLDG121-PIPING OPEN ISO (PENE 43) PENETRATION RM iv ii Notes: 9 Q1P17V25OA RCPS THRM BARR CCW FI-3045 AUX BLDG 121 PIPI?4G OPEN ROOT PENETRATION RM IV I Q1P17V25OB RCPS THRM BARR CCW FI-3045 AUX BLDG 121 PIPING OPEN ROOT PENETRATION RM IV [_ ]L Q1P17V173 RCPS THRM BARR ccw RTN AUX BLDG 121 PIPING CLOSED & CAPPED IV TEST CONN PENETRATION RM Q1P17VO81 EXCLTDN&RCDTHXSCCW AUXBLDG121-PIPING OPEN RTN ISO (PENE 46) PENETRATION RM IV IL Q1P17HV3067-AIR SUPPLY CCW FROM EXC LTDN/RCDT AUX BLDG 121 - PIPING AIR CUT IN IV HXS PENETRATION RM Q1P17HV3067 CCW FROM EXC LTDN/RCDT HXS AUX BLDG 121- PIPING PENETRATIONRM OPEN IV [*..;: L.fl Q1P17HV3067-JACK CCW FROM EXC LTDN/RCDT AUX BLDG 121- PIPING NEUTRAL POSITION & IV HXS (HAND JACK DEVICE) PENETRATION RM SEALED Notes: 275 Q1P17HV3095-AIRSUPPLY CCWTOEXCLTDN/RCDTHXS AUXBLDG121-PIPING AIRCUTIN IV PENETRATION RM Q1P17HV3095 CCWTOEXCLTDN/RCDTHXS AUXBLDG121 -PIPING (PENE 45) PENETRATION RM OPEN IV I Q1P17HV3095-JACK CCW TO EXC LTDN/RCDT HXS AUX BLDG 121 PIPING

- NEUTRAL POSITION & IV (HAND JACK DEVICE) PENETRATION RM SEALED Notes: 275 Q1P17V16O EXCLTDN&RCDTHXSCCW AUXBLDG121-PIPING CLOSED,CAPPED& IV RTN LINE TEST CONN PENETRATION RM SEALED .

Q1P17V166 EXC LTDN & RCDT HXS CCW AUX BLDG 121 - PIPING CLOSED, CAPPED & IV SUPP LINE TEST CONN PENETRATION RM SEALED .

Q1P17V164 CCW DISCH RCP OIL CLR TEST CONN 121 PIPING PENETRATION RM CLOSED, CAPPED &

SEALED IV  :}I Q1P17V168 RCPSCCWSUPPTESTCONN 121 PIPING PENETRATION RM CLOSED, CAPPED&

SEALED IV I:...

II.

Q1P17V161 CCW DISCH EXC LTDN & RCDT AUX BLDG 121 PIPING

- CLOSED & CAPPED IV

. HXS DRN PENETRATION RM ,

12-1_

Q1P17V251A EXCLTDN&RCDTHXSCCW AUXBLDG12I-PIPING OPEN IV FI-3066 ROOT PENETRATION RM .

0211512011 JJJ?J 1 F 11 of 21 Active Procedure: FNP-1-SOP-23.OA, COMPONENT COOLING WATER SYSTEM Type: SOP, Unit: 1, Revision: 10 Step: 2.60 Aux Bldg 121 - Piping Penetration Room Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17V251B EXC LTDN & RCDT HXS CCW AUX BLDG 121 PIPING

- OPEN IV FI-3066 ROOT PENETRATION RM Step: 2.70 Aux Bldg 139 - Chemistry Lab (above false ceiling)

Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials N1P17V172A SAMPLE HX CCW FI-3036 ROOT AUX BLDG 139 OPEN CHEMISTRY LAB (ABOVE IV L FALSE CEILING)

N1P17V172B SAMPLEHXCCWFI3O36ROOT AUXBLDG139 OPEN IV CHEMISTRY LAB (ABOVE FALSE CEILING)

Step: 2.80 Aux Bldg 139 - Control Panel Outside PRF Room Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17HV2229-VLV H/S CCW SUPP TO SAMPLE CLRS AUX BLDG 139 - AUTO IV V CONTROL PANEL OUTSIDE PRF RM CCW SUPP TO SAMPLE CLRS Q1P17HV2229-VLV IND AUX BLDG 139 OPEN J

IV CONTROL PANEL:

OUTSIDE PRF RM Q1P17HV2229-NORM/BLOCK SW CCW SUPP TO SAMPLE CLRS AUX BLDG 139 - NORMAL IV *

(KEY SWITCH) CONTROL PANEL OUTSIDE PRF RM Step 2 90 Aux Bldg 121 Waste Evaporator Package Room Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials NIPI7V161 TEST CONN AUX BLDG 121 WASTE

- CLOSED & CAPPED IV EVAPORATOR PKG RM N1P17V063 12J TESTCONN AUXBLDG121-WASTE CLOSED&CAPPED IV EVAPORATOR PKG RM Step: 3.00 Aux Bldg 155 - 1A SFP HX Room Equip Operator Id: Equip

Description:

Equip Location: Required Conflg: Actual Config: Verification: Initials Q1 P17VO14A 1A SFP HX CCW DRN AUX BLDG 155 - 1A SFP CLOSED IV HXRM Q1P17VO15A 1ASFPHXOUTLETLINEVT AUXBLDG155-1ASFP CLOSED&CAPPED IV HX RM Q1P17V228A 1A SEP HX CCW FI-3080A ROOT AUX BLDG 155 1A SFP OPEN HXRM IV L zi Lt_______

0211512011 (3:15 I F12ot21 Active Procedure: FNP-1-SOP-23.OA, COMPONENT COOLING WATER SYSTEM Type: SOP, Unit: 1, Revision: 10 Step: 3.00 Aux Bldg 155 - 1A SFP HX Room Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17V228B 1ASFPHXCCWFI-3O8OAROOT AUXBLDG155-1ASFP HXRM OPEN iv [ ;:*:]I Q1P17VO16A 1A SEP HX CCW OUTLET ISO AUX BLDG 155 - 1A SEP 14-35 DEG OPEN & IV HX RM SEALED Notes: 275 Q1P17VO11A CCWTO1ASEPHX AUXBLDG155-1ASEP (Q1P17MOV3O94A) HX RM OPEN iv VIL__

Step: 3.10 Aux Bldg 175- lB SEP HX Room Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17VO15B lB SEP HX CCW OUTLET LINE VT AUX BLDG 175 - lB SEP CLOSED & CAPPED IV HXRM Q1P17V229A lB SEP HX CCW EI-3080B ROOT AUX BLDG 175- lB SEP OPEN IV HXRM lB SEP HX CCW EI-3080B ROOT Q1P17V229B AUX BLDG 175 HX RM

- lB SEP OPEN IV I Step 3 20 Aux Bldg 155 Comdor Drumming Area Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17VO14B lB SEP HX CCW DRN AUX BLDG 155 CORRIDOR DRUMMING

- CLOSED & CAPPED IV L AREA Q1P17VO16B 1BSEPHXCCWOUTLETISO AUXBLDG155-CORRIDOR DRUMMING 14-35DEGOPEN&

SEALED IV II AREA Notes: 275 Q1P17VO11B CCWTO1BSFPHX AUXBLDG155- OPEN IV (Q1P17MOV3O94B) CORRIDOR DRUMMING AREA ep: 3.30 CTMT 129 - North Wall Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17V162 CCW SUPP LINE TO EXC CTMT 129 - CLOSED & CAPPED IV LTDN/RCDT HXS TEST CONN PENETRATIONS 45 AND 46 Q1P17HV3443-AIR SUPPLY CCWFROMEXCLTDN/RCDT CTMT 129- AIR CUT IN IV HXS PENETRATIONS 45AND 12.1 46 age

/ TTXYT 1 0211512011 1 3:15 jJf 1 1 F 13ot21 Active Procedure: FNP-1-SOP-23.OA, COMPONENT COOLING WATER SYSTEM Type: SOP, Unit: 1, Revision: 10 Step 330 CTMT 129 North Wall Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: - Initials Q1P17HV3443 CCW FROM EXC LTDN/RCDT CTMT 129 - OPEN IV HXS PENETRATIONS45AND 46 Q1P17HV3443-JACK CCW FROM EXC LTDN/RCDT CTMT 129 - NEUTRAL POSITION iv HXS (HAND JACK DEVICE) PENETRATIONS 45 AND 46 Step: 3.40 CTMT 105 Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17V079 RCDTHXCCWINLETISO CTMT1O5 OPEN IV Q1P17VO8O RCDTHXCCWOUTLETISO CTMT1O5 41/8TURNSOPEN& IV SEALED Notes: 275 Q1P17V13O RCDTHXCCWINLETLINEDRN CTMT1O5 CLOSED&CAPPED IV L__._

Q1P17V257 RCDT HX CCW DRN CTMT 105 CLOSED & CAPPED IV L Q1P17V129 RCDT HX CCW VT CTMT 105 CLOSED & CAPPED IV Q1P17V174 RCDTHXCCWOUTLETLINE CTMT129NEARPENE25 CLOSED&CAPPED IV TEST CONN Step: 3.50 Aux Bldg 100 - CCW Hx Room Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17V221A IACCWPLJMPSUCTPI-3308A AUXBLDG100 -CCWHX OPEN IV ROOT RM Q1P17V1O9A 1ACCWPUMPSUCT AUXBLDG100-+/-WHX OPEN IV I*1L_

Q1P17V279A 12 1. 1A CCW PUMP SUCT LINE VT AUX BLDG 100 - CCW HX CLOSED & CAPPED IV RM Q1P17V156A 1ACCWPUMPVT AUXBLDG100 -CCWHX CLOSED&CAPPED IV RM QIP17VI5GD IACCWPUMPVT AUXBLDG100-CCWHX CLOSED&CAPPED IV RM Q1P17V157A 1A CCW PUMP DRN AUX BLDG 100 RM

- CCW HX CLOSED & CAPPED IV 1II Q1P17V157B 1A CCW PUMP DRN AUX BLDG 100 - CCW HX CLOSED & CAPPED IV RM

I 0211512011 1 3:15 jJ I( F 14c121 Active Procedure: FNP-1-SOP-23.OA, COMPONENT COOLING WATER SYSTEM Type: SOP, UnIt: 1, Revision: 10 Step: 3.50 Aux Bldg 100 - CCW Hx Room Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17V144A 1A CCW PUMP MINI-FLOW AUX BLDG 100 RM

- CCW HX OPEN IV [

Q1P17V278A 1A CCW PUMP CHEM MIXING AUX BLDG 100 CCW HX CLOSED ISO RM IV I I Q1P17V210 1A CCW PUMP MINI-FLOW VT AUX BLDG 100 CCW HX CLOSED & CAPPED RM IV ..JI I Qi P17V258A 1A CCW PUMP REL HDR DRN AUX BLDG 100 CCW HX CLOSED & CAPPED RM IV . IL-.I Qi P17V222A 1A CCW PUMP DISCH PI-3035A AUX BLDG 100 CCW HX OPEN ROOT RM IV . I Qi P17V281A 1A CCW PUMP DISCH HDR DRN AUX BLDG 100 RM

- CCW HX CLOSED & CAPPED IV I**  :. :.:I . .

. I Q1P17VOO2A 1A CCW PUMP DISCH ISO AUX BLDG 100 - CCW HX OPEN IV RM Q1P17V1O9B lB CCW PUMP SUCT AUX BLDG 100 RM

- CCW HX OPEN IV [*iII . I Q1P17V279B lB CCW PUMP SUCT LINE VT AUX BLDG 100 CCW HX CLOSED & CAPPED RM IV EZ____

Qi P17V221 B lB CCW PUMP SUCT PI-3308B AUX BLDG 100 CCW HX OPEN ROOT RM IV LJ Q1P17V156B lB CCW PUMP VT AUX BLDG 100 RM

- CCW HX CLOSED & CAPPED IV [ I Q1P17V156E lB CCW PUMP VT AUX BLDG 100 RM

- CCW HX CLOSED & CAPPED IV [ :1 Q1P17V157C lB CCW PUMP DRN AUX BLDG 100 RM

- CCW HX CLOSED & CAPPED IV II Q1P17V157D lB CCW PUMP DRN AUX BLDG 100 - CCW HX CLOSED & CAPPED IV RM Q1P17V144B lB CCW PUMP MINI-FLOW AUX BLDG 100 - CCW HX OPEN IV RM 01 P17V278B WPUMPCHEMMIXIN AUX BLDG 100 RM

- CCW HX CLOSED IV II Q1P17V178 lB CCW PUMP MINI-FLOW VT AUX BLDG 100 RM

- CCW HX CLOSED & CAPPED IV . II Q1P17V258B 12:1 13 CCW PUMP REL HDR DRN 100 FT UNIT 1 AUX BLDG CLOSED & CAPPED IV age SOUTH CCW HX RM 185 BY lB CCW PUMP

0211512011 (3:15 UNT1 Active Procedure: FNP-1-SOP-230A, COMPONENT COOLING WATER SYSTEM F 15o121 Type: SOP, Unit: 1, Revision: 10 Step: 3.50 Aux Bldg 100 - CCW Hx Room Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17V281B lB CCW PUMP DISCH HDR DRN AUX BLDG 100 RM

- CCW HX CLOSED & CAPPED IV I r I Q1P17V222B lB CCW PUMP DISCH Pl-3035B AUX BLDG 100 ROOT RM

- CCW HX OPEN IV EZI__

Q1P17VOO2B lB CCW PUMP DISCH ISO AUX BLDG 100 - CCW HX OPEN IV Q1P17V1O9C 1C CCW PUMP SUCT ISO AUX BLDG 100 - CCW HX OPEN IV RM Qi P17V279C 1C CCW PUMP SUCT LINE VT AUX BLDG 100 - CCW HX CLOSED & CAPPED IV RM Q1P17V221C 1C CCW PUMP SUCT PI-3308C AUX BLDG 100 ROOT RM

- CCW HX OPEN IV I II I Q1P17V156C 1C CCW PUMP VT AUX BLDG 100 - CCW HX CLOSED & CAPPED IV RM Q1P17V156F 1C CCW PUMP VT AUX BLDG 100 - CCW HX CLOSED & CAPPED IV RM Q1P17V157E 1C CCW PUMP DRN AUX BLDG 100 - CCW HX CLOSED & CAPPED IV RM Q1P17V157F 1C CCW PUMP DRN AUX BLDG 100 CCW HX CLOSED & CAPPED RM IV E____

Qi P17V144C 1C CCW PUMP MINI-FLOW AUX BLDG 100 - CCW HX OPEN IV RM Q1P17V179 1C CCW PUMP MINI-FLOW VT AUX BLDG 100 - CCW HX CLOSED & CAPPED IV RM Qi P17V278C 1C CCW PUMP CHEM MIXING AUX BLDG 100 ISO RM

- CCW HX CLOSED IV I II

19. 1 Qi P17V258C 1C CCW PUMP REL HDR DRN AUX BLDG 100 RM

- CCW HX CLOSED & CAPPED IV :rlEZ Q1P17V222C 1C CCW PUMP DISCH PI-3035C ROOT AUX BLDG 100 RM

- CCW HX OPEN IV L I;i Q1P17VOO2C 1C CCW PUMP DISCH ISO AUX BLDG 100 RM

- CCW HX OPEN IV I ii Q1P17V11OA CCW FROM lB RHR HX AUX BLDG 100 CCW HX OPEN RM IV I Notes: 9 Q1P17VO17A CCW FROM 1A SEP HX AND CHG AUX BLDG 100 -CCWAX OPEN PUMPS RM IV [ H

0211512011 13:15 Active Procedure:

urrTi FNP-1-SOP-23.OA, COMPONENT COOLING WATER SYSTEM F 16o121 Type: SOP, Unit: 1, Revision: 10 Step: 3.50 Aux Bldg 100 - CCW Hx Room Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17V11OB CCW PUMPS SUCT HDRXCONN AUX BLDG 100 - CCW HX CLOSED Iv :j Notes: 9, 290 Q1P17V11OC CCW PUMPS SUCT HDR XCONN AUX BLDG 100 RM

- CCW HX CLOSED iv I I:

Notes: 9, 290 Q1P17V11OD CCW PUMPS SUCT HDR XCONN AUX BLDG 100 - CCW HX OPEN iv l I RM Notes: 9, 290 Q1P17V11OE CCWPUMPSSUCTHDRXCONN AUXBLDG100-CCWHX OPEN iv RM Notes: 9, 290 Q1P17VO17B CCW FROM lB SFP HX AND CHG AUX BLDG 100 - CCW HX OPEN IV PUMPS RM Q1P17V281C 1C CCW PUMP DISCH HDR DRN AUX BLDG 100 - CCW HX CLOSED & CAPPED iv RM Q1P17V11OF CCW FROM 1A RHR HX AUX BLDG 100 - CCW HX OPEN iv Q1P17VOO4A CCWINLETTO1ACCWHX AUXBLDG100 -CCWHX OPEN RM Q1P17VOO3A CCW PUMPS DISCH HDR XCONN AUX BLDG 100 RM

- CCW HX CLOSED iv ItW Notes: 9, 291 Qi P17VOO3B CCWPUMPSDISCHHDRXCONN AUXBLDG100-CCWHX RM CLOSED iv I Notes: 9, 291 Qi P17VOO4B CCW INLET TO lB CCW HX AUX BLDG 100 - CCW HX OPEN iv RM Q1P17VOO3C CCW PUMPS DISCH HDR XCONN AUX BLDG 100 - CCW HX OPEN iv RM -

Notes: 9, 291 01 P17VOO3D CCWPUMPSD1SCHHDRXCONN AUXBLDG100-CCWHX OPEN iv RM Notes: 9, 291 Q1P17VOO4C CCWINLETTO1CCCWHX AUXBLDG100-CCWHX OPEN iv 12:1 RM age

0211 5I21 I 3:15 JJ J\Sr 1 F l 7 oIl 21 Active Procedure: FNP-1-SOP-23.OA, COMPONENT COOLING WATER SYSTEM Type: SOP, Unit: 1, Revision: 10 Step: 3.50 Aux Bldg 100 - CCW hx Room Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17V223A 1ACCWHXCCWINLETFT-3043A AUXBLDG100-CCWHX OPEN ROOT RM iv L II Q1P17V223B 1ACCWHXCCWINLETFT-3043A AUXBLDG100-CCWHX OPEN iv ROOT RM Q1P17V177 1ACCWHXCCWINLETVT AUXBLDGIOO WHX CLOSED&CAPPED RM iv IL Q1P17V226A 1A CCW HX CCW INLET PI-3038A AUX BLDG 100 ccw HX OPEN ROOT RM iv fr. L_

Q1P17VOO5A 1A CCW HX CCW DRN AUX BLDG 100 - CCW HX CLOSED & CAPPED lv :Ej RM Q1P17VOO7A 1ACCWHXCCWVT AUXBLDG100-CCWHX RM CLOSED&CAPPED iv L Q1P17VOO5B 1A CCW HX CCW DRN AUX BLDG 100 - CCW HX CLOSED & CAPPED iv RM Q1P17V227A 1A CCW HX CCW OUTLET AUX BLDG 100 CCW HX OPEN iv Pi-3041A ROOT RM Q1P17VOO8A 1A CCW HX CCW OUTLET ISO AUX BLDG 100 RM

- CCW HX OPEN iv I Notes: 292 Q1P17VO1OA B TRN CCW SUPP ISO AUX BLDG 100 - CCW HX OPEN iv j I Q1P17VOO9A CCWSUPPHDRXCONN AUXBLDG100-CCWHX CLOSED iv Notes: 9, 291 CCWSUPPTO1ASFPHXAND Q1P17VO12A CHG PUMPS AUXBLDG100 -CCWHX RM OPEN iv iI Q1P17V224A 121 1BCCW HX CCW INLET FT-3043B AUX BLDG 100 CCW HX OPEN iv Q1P17V224B 1BCCWHXCCWINLETFT-3043B AUXBLDG100 -CCWHX ROOT RM OPEN iV I H Q1P17V18O 1BCCWHXCCWINLETVT AUXBLDG100-CCWHX CLOSED&CAPPED iv RM Q1P17V226B 1BCCWHXCCW1NLETP1-3038B AUXBLDG100 -CCWHX OPEN iv ROOT RM Q1P17VOO5C lB CCW HX CCW DRN AUX BLDG 100 RM

- CCW HX CLOSED & CAPPED iv It

02115!211 JJ]N(_ci 1 F18cf21 Active Procedure: FNP-1-SOP-23.OA, COMPONENT COOLING WATER SYSTEM Type: SOP, Unit: 1, Revision: 10 Step: 3.50 Aux Bldg 100 - CCW Hx Room Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17V0O7B 1BCCWHXCCWVT AUXBLDG100 -CCWHX CLOSED&CAPPED iv RM Q1P17VOO5D lB CCW HX CCW DRN AUX BLDG 100 - CCW HX CLOSED & CAPPED iv RM Q1P17V227B lB CCW HX CCW OUTLET AUX BLDG 100 - CCW HX OPEN iv P1-30416 ROOT RM Q1P17VOO8B 1BCCWHXCCWOUTLETISO AUXBLDG100 -CCWHX CLOSED iv RM -_____

Notes: 293 Q1P17VOO9B CCW SUPP HDR XCONN AUX BLDG 100 - CCW HX CLOSED iv RM Notes: 9, 291 Q1P17VOO9C CCWSUPPHDRXCONN AUXBLDG100 -CCWHX RM OPEN iv L - II Notes: 9, 291 Q1P17V181 1CCCWHXCCWINLETVT AUXBLDG100CCWHX CLOSED&CAPPED RM IV 1L Q1P17V225A 1C CCW HX CCW INLET FI-3043C AUX BLDG 100 CCW HX OPEN ROOT RM iv . I Q1P17V2258 1CCCW HX CCW INLET FI-3043C AUX BLDG 100 - CCW HX OPEN iv . I Q1P17V226C 1CCCWHXCCW1NLETP1-3038C AUXBLDG100-CCWHX OPEN iv ROOT RM Q1P17VOO5E 1C CCW HX CCW DRN AUX BLDG 100 - CCW HX CLOSED & CAPPED iv Q1P17VOO7C 1C CCW HX CCW VT AUX BLDG 100 RM

- CCW HX CLOSED & CAPPED IV 1 Q1P17VOO5F 1C CCW HX CCW DRN AUX BLDG 100 - CCW HX CLOSED & CAPPED iv RM Q1P17V227C 1C CCW HX CCW OUTLET AUX BLDG 100 CCW HX OPEN Pi-3041C ROOT RM iv L__Z1 L Q1P17VOO8C 1C CCW HX CCW OUTLET ISO AUX BLDG 100 - CCW HX OPEN IV ..

jj j-..;:.j RM Notes: 294 Q1P17VOO9D 121 CCWSUPPHDRXCONN AUXBLDG100-CCWHX RM OPEN iv  :::.::flage Notes: 9, 291

0211512011 3:15 UNT1 Active Procedure: FNP-1-SOP-23.OA, COMPONENT COOLING WATER SYSTEM F19 of 21 Type: SOP, Unit: 1, Revision: 10 Step: 3.50 Aux Bldg 100 - CCW Hx Room Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17VO1OB ATRNCCWSUPPISO AUXBLDG100-CCWHX OPEN IV  :

RM Q1P17VO12B COW SUPP TO 1BSFPHXAND AUX BLDG 100 -CCWHX OPEN CHGPUMPS RM iv *1 Q1P17V116 COW SRG TKATRN MKUP ISO AUX BLDG 100 - CCW HX OPEN iv RM Q1P17V12O CCWSRGTKBTRNMKUPISO AUXBLDG100-CCWHX OPEN IV RM Q1P17V175 COW SRG TK A TRN MKUP LINE AUX BLDG 100 ccw HX CLOSED & CAPPED DRN RM IV L Q1P17V176 COW SRG TK B TRN MKUP LINE DRN AUX BLDG 100 RM

- CCW HX CLOSED & CAPPED IV I N1P11VO45 COW SRG TK DEMIN INLET ISO AUX BLDG 100 RM

- CCW HX OPEN IV 1 Q1P17VO3O COW TO SEC HXS AUX BLDG 100 -CCW HX OPEN IV (Q1P17M0V3047) RM Qi P17V1 1 7A MKUP TO COW FROM RMW AUX BLDG 100 - CCW HX CLOSED IV rH (Q1P17MOV3O31A) RM Q1P17V121A MKUP TO COW FROM DW STOR AUX BLDG 100 - W HX CLOSED IV TK(Q1P17MOV3O3OA) RM Q1P17V117B MKUP TO COW FROM RMW AUX BLDG 100 - CCW HX CLOSED IV (Q1P17MOV3O31B) RM Q1P17V121B MKUP TO COW FROM DW STOR TK(Q1P17MOV3O3OB)

AUX BLDG 100 RM

- OCW HX CLOSED IV L J[J Step: 3.60 Aux Bldg 175 - CCW Surge Tank Room Equip Operati: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: 1 InitiJ Ni P17V179 COW SRG TK DW HOSE CONN AUX BLDG 175 CCW

- CLOSED & CAPPED IV SURGE TANK RM Q1P17V113A OOWSRGTKATRNDRN AUXBLDG175-CCW CLOSED IV SURGETANKRM Q1P17V113B OCWSRGTKBTRNDRN AUXBLDG175-CCW SURGE TANK RM CLOSED&CAPPED IV L COWSRGTKLI-3027B&D ROOT Q1P17V112A AUX BLDG 175 -CCW SURGE TANK RM OPEN IV I II Q1P17V112B CCWSRGTKLI-3027B&DROOT AUXBLDG175-CCW OPEN IV SURGETANKRM .

02/15/21111 (3:15 JJj7[ 1 F 20 of 21 Active Procedure: FNP-1-SOP-23.OA, COMPONENT COOLING WATER SYSTEM Type: SOP, Unit: 1, Revision: 10 Step: 3.60 Aux Bldg 175 - CCW Surge Tank Room Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17V112C CCWSRGTKLI-3027A&C ROOT AUXBLDG 175 -CCW SURGE TANK RM OPEN iv L ii Q1P17V112D CCWSRGTKLI-3027A&C ROOT AUX BLDG 175 -CCW SURGETANKRM OPEN iv  :-lI Q1PI7V114 CCWSRGTKCHEMADD AUXBLDG175 -CCW CLOSED&CAPPED SURGE TANK RM iv II Q1P17RV3028-AIR SUPPLY CCW SRG TK AIR VT AUX BLDG 175 CCW

- AIR CUT IN IV SURGETANKRM Q1P17RV3028 CCWSRGTKAIRVT AUX BLDG 175 -CCW OPEN IV SURGE TANK RM Q1P17RV3028-JACK CCW SRG TK AIR VT (HAND AUX BLDG 175 -CCW NEUTRAL POSITION IV JACK DEVICE) SURGE TANK RM Q1P17V285A CCW SRG TK LI-3027A UPPER AUX BLDG 175 CCW

- OPEN IV ROOT SURGE TANK RM Q1P17V285B CCW SRG TK LI-3027B UPPER AUX BLDG 175 CCW

- OPEN IV ROOT SURGETANKRM Q1 P17V285C 12.1 CCW SRG TK LI-3027C UPPER AUX BLDG 175 CCW OPEN IV ROOT SURGE TANK RM j

Q1P17V285D CCW SRG TK LI-3027D UPPER AUX BLDG 175 CCW ROOT SURGE TANK RM

- OPEN IV L 1 Step 3 70 Ma,n Control Board Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials Q1P17RV3028-MCB H/S CCWSRGTKVT MAIN CONTROL BOARD OPEN IV j Ii Qi P17HV3096B&A-MCB H/S CCW TO/FROM EVAP PKGS & H2 Ui MCB OPEN / AUTO IV -*

RECOMBQ1P17HV3O96B&A Q1P17MOV3185A-MCBH/S CCWTO1ARHRHX Ui MCB Q1P17MOV3185A FU-E3 CLOSE/MID POS. IV IE Notes: 345 Q1P17MOV3185B-MCBH/S CCWTO1BRHRHX Ui MCB CLOSE/MIDPOS. IV Q1P17MOV3I85B FV-U4 Notes: 345 Q1P17MOV3O94A-MCBH/S CCWTO1ASFPHX Ui MCB OPEN/MID POS. IV Q1P17MOV3O94A FV-D3 Q1P17MOV3O94B-MCBH/S CCWTO1BSFPHX Q1P17MOV3O94B FU-S4 Ui MCB OPEN/MID POS. IV L

0211512011 3:15 F 21 of2l Active Procedure: FNP-l-SOP-23.OA, COMPONENT COOLING WATER SYSTEM Type: SOP, Unit: 1, Revision: 10 Step: 3.70 Main Control Board Equip Operator Id: Equip

Description:

Equip Location: Required Config: Actual Config: Verification: Initials 01 P17MOV3O47-MCB H/S ccw TO SECONDARY HXS Ui MCB OPEN / AUTO iv Q1P17M0V3047 FV-D2 ... ..

Q1P17MOV3O31A-MCB H/S MKUP TO CCW FROM RMW Ui MCB CLOSE! MID POS. IV Q1P17MOV3O31A FU-D4 . .. .

Q1P17MOV3O3OA-MCB H/S MKUP TO CCW FROM DW STOR Ui MCB CLOSE! MID POS. IV ... .. . .

TK Q1P17MOV3O3OA FU-l3 ..

Q1P17MOV3O31B-MCB H!S MKUP TO CCW FROM RMW Ui MCB CLOSE / MID POS. IV .

Q1P17MOV3O31B FV-G5 .... .

Q1P17MOV3O3QItBH!S MKUPTOCCWFROMDWSTOR Ui MCB CLOSE/MID POS. IV .:

TK Q1P17MOV3O3OB FV-G4 .

Q1P17HV3O67-MCB H/S CCW FROM EXC LTDN/RCDT Ui MCB OPEN /AUTO IV HXS Q1P17HV3O67 ..

Q1P17HV3443-MCB H/S CCW FROM EXC LTDN/RCDT Ui MCB OPEN/AUTO lv HXS Q1P17HV3443 Q1P17HV3095-MCB H/S CCW TO EXC LTDN/RCDT HXS Ui MCB OPEN / AUTO IV -,

Q1P17HV3O95 Note # Note Text:

9 For outage return to service, coordinate with SS and stroke vlv a minimum of 1 turn. Submit CR for problems.

76 Alternate DC control power located in Hot Shutdown Panel.

77 Only the BKR for the TRN that the pump is aligned to will be racked in. The other BKR will be racked out.

275 Set for CCW flow balance. S/S permission needed prior to changing the position of this seal wired valve.

289 as shown on Fl-3036 290 May be in opposite position if 18 CCW pump aligned to B train.

291 May be in opposite position if miscellaneous header on B train.

292 May be in opposite position if lB CCW Hx on service and aligned to B Train.

293 May be in opposite position if lB CCW Hx on service and aligned to either A Train or B Train.

294 May be in opposite position if lB CCW Hx on service and aligned to A Train.

345 May be open if RHR system on service or if CCW pump on associated train not running.

391 Disc switch Qi Ri 8A0004A space heater power supply bkr is Ni Ri 9LOOi J-BKR1 1.

392 Disc switch Q1RI8A0004B space heater power supply bkr is N1R19LOO1J-BKRI3.

579 Disconnect is required to be Closed when component is aligned to A Train. Disconnect is required to be Open when component is aligned to B Train.

580 Disconnect is required to be Closed when component is aligned to B Train. Disconnect is required to be Open when component is aligned to A Train.

FNP HLT-34 ADMIN Page 1 of 7 A3.1.A RO and SRO Radiation Control ADMIN G2.3.4 TITLE: DETERMINE DRESSOUT REQUIREMENTS, TOTAL PROJECTED DOSE AND DETERMINE IF A RCP OIL ADDITION CAN BE PERFORMED WITHOUT EXCEEDING ANY RADIOLOGICAL LIMITS.

EVALUATION LOCATION: D SIMULATOR LICONTROL ROOM I1CLASSROOM PROJECTED TiME: 20 MIN SIMULATOR IC NTJMBER: N/A D ALTERNATE PATH D TIME CRITICAL D PRA JPM DIRECTIONS:

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

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

TASK STANDARD: Upon successfhl completion of this JPM, the examinee will review an RWP, Radiological Survey Map and perform the following for adding oil to the 2A RCP:

• Identifj the Protective Clothing requirements.

• Total projected dose for a job.

• Determination if the task can or cannot be performed without exceeding any radiological limits on a single entry, and if NOT then state the reason.

Examinee:

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

EXAMINER:

Developer I Billy Thornton I Date: 2/9/2011 NRC Approval SEE NUREG 1021 FORM ES-301-3

FNP HLT-34 ADMIN A3.1A Page 2 of 7 CONDITIONS When I tell you to begin, you are to DETERMINE DRESSOUT REQUIREMENTS, TOTAL PROJECTED DOSE AND DETERMINE IF A RCP OIL ADDITION CAN BE PERFORMED WITHOUT EXCEEDING ANY RADIOLOGICAL LIMITS. The conditions under which this task is to be performed are:

1. RxPoweris 10%.

2. You will be adding oil to the 2A RCP.

3. All needed tools, oil, and equipment have been staged at 2A RCP.

4. All necessary permissions to access the area and perform the task have been acquired.

5. Your accumulated dose for this year to date is 1650 mRem.

6. Based on previous actions to stage the materials for the job, the TOTAL round-trip TRANSIT dose will be 10 mRem.

7. The TOTAL time at the JOB site will be 30 minutes.

8. The Job will be completed by one team on one entry.

9. ASSUME NEUTRON DOSE Exposure NEGLIGABLE.

10. Using the RWP 11-9490 and the Survey Map of the 2A RCP work area provided, you are to determine and document your conclusions on the table below the following information:

a. Your Protective Clothing requirements.

b. Total projected dose from gamma.

c. If you can or cannot perform the task without exceeding any limits, if not, then state the reason.

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

EVALUATION CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

START TIME

FNP HLT-34 ADMIN A3.1A Page 3 of 7 EVALUATION CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

1. Determines dressout requirements. References the RWP and S / U determines dressout is dependent upon the contamination levels.

Reviews the survey map and identifies that the contamination levels are <50,000 dpm/lOOcm2 Documents the following dressout requirements:

Single coveralls or equivalent, booties, one set rubber shoe-covers, and one set of gloves.

2. Calculates total projected dose. Reviews the survey map and S / U identifies that the General Area dose rate for the job site is 390 mR/hr.

Calculates dose received while performing the job, and adds the dose received during transit to and from the job.

Documents the total of 205 mRem Total dose calculation: Dose at jobsite + Dose in transit = Total dose 30 minutes

• 390 mReml hr

• 1 hr/60 minutes = 195 mRem (dose at jobsite) {no range}

Dose during transit is given in the Conditions = 10 mRem total {no range}

195 mRem (dose atjobsite) + 10 mRem (dose during transit) = 205 mRem Total dose {no range}

FNP HLT-34 ADMIN A3.1A Page 4 of 7 EVALUATION CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

3. Determine if any dose limits will be exceeded by Determines if allowable dose S I U performing the task. limits will be exceed:

Admin dose limit o 1855mR<2000mR.

RWP Task dose limit o 205mR>200mR RWP Task dose rate limit o 390 rnRlhr < 500 mRlhr Documents that the job can NOT be performed.

ANNUAL limit (2000 mR annually): 1650 accumulated) + 205 = 1855 mR {no range}

205 mR 200mr from RWP 5 mR over the RWP accumulated dose limit. {no range}

4. States the reason for the task as NOT permitted IDENTIFIES that the RWP Task S / U dose limit is exceeded.

R WP task Dose limit 200 mR is exceeded by 5 mR Alternatively, one might state that there is insufficient exposure margin (350 mr). IF this is cited as the reason, follow-up CUE:

Can an individual with NO year to date DOSE perform the task?

IF NO, then CUE: Why not?

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

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

FNP HLT-34 ADMIN A3.1A Page 5 of 7 GENERAL

REFERENCES:

1. FNP-0-M-001, VER 18.0

2. KA: G2.3.4 RO 3.2 SRO 3.7 G2.3.7 RO 3.5 SRO 3.6 GENERAL TOOLS AND EQUIPMENT:

Calculator Containment Survey Maps 1 maps (2A RCP cubicle)

Containment RWP 11-9490 (For Training USE ONLY)

Health Physics Manual, FNP-0-M-001, Version 18.0.

Critical ELEMENT justification:

STEP Evaluation

1. Critical: Task completion: required to determine dress out requirements for performing work in Containment, from the Radiation Work Permit.

2. Critical: Task completion: required to determine dose rates from HP survey map and required to perform calculation to determine the total projected dose.

3. Critical: Task completion: required to determine if any dose limits will be exceeded and finds out the task can NOT be done within limits.

4. Critical: Task completion: required to identify which limit is exceeded. This is an evaluation mechanism to objectively asses the REASON for NOT permitting task completion.

FNP HLT-34 ADMIN A3.1A Page 6 of 7 KEY HIGEST Dose Rates encountered at the work location Standard Coveralls:

Dressout requirements: Single coveralls or equivalent, hood, booties, one set rubber shoe-covers, and one set of gloves.

Total projected dose from

• 205 mRem {no range}

gamma (CIRCLE ONE)

Can you complete this task without exceeding any limits?

YES REASON, if applicable: *RWp task Dose limit 200 mR

FNPHLT-34ADMIN A3.1A HANDOUT Pg 1 of 1 CONDITIONS When I tell you to begin, you are to DETERMINE DRESSOUT REQUIREMENTS, TOTAL PROJECTED DOSE AND DETERMINE IF A RCP OIL ADDITION CAN BE PERFORMED WITHOUT EXCEEDING ANY RADIOLOGICAL LIMITS. The conditions under which this task is to be performed are:

1. RxPoweris 10%.

2. You will be adding oil to the 2A RCP.

3. All needed tools, oil, and equipment have been staged at 2A RCP.

4. All necessary permissions to access the area and perform the task have been acquired.

5. Your accumulated dose for this year to date is 1650 mRem.

6. Based on previous actions to stage the materials for the job, the TOTAL round-trip TRANSIT dose will be 10 mRem.

7. The TOTAL time at the JOB site will be 30 minutes.

8. The Job will be completed by one team on one entry.

9. ASSUME NEUTRON DOSE Exposure NEGLIGABLE.

10. Using the RWP 11-9490 and the Survey Map of the 2A RCP work area provided, you are to determine and document your conclusions on the table below the following information:

a. Your Protective Clothing requirements.

b. Total projected dose from gamma.

c. If you can or cannot perform the task without exceeding any limits, if not, then state the reason.

HIGEST Dose Rates encountered at the work location Dressout requirements:

Total projected dose from gamma (CIRCLE ONE)

Can you complete this task without exceeding any limits?

YES NO REASON, if applicable:

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FNP HLT-33 ADMIN Page 1 of 8 A4.1.R Emergency Plan G2.4.43 RO CRO-362 TITLE: Make Initial Notifications As Required for an Emergency EVALUATION LOCATION: I1SIMULATOR LICONTROL ROOM LICLASSROOM PROJECTED TIME: 20 MN SIMULATOR IC NUMBER: N/A LIALTERNATE PATH ITIME CRITICAL LIPRA JPM DIRECTIONS:

1. This task will be done in the simulator area where the Southern Link phones can be accessed.

2. The Candidate will have 15 minutes from the start time to complete the initial notifications and then time to activate the ERO call-out system.

3. The evaluator, upon commencement of the JPM, shall fill in data on the and NMP-EP- 111, Figure 1 then provide both NMP-EP-1 10 Checklist 2, NMP-EP-1 10 Table 1, and EIP-8.3 table 1 to the candidate.

TASK STANDARD: Required for successful completion of this JPM:

. Complete the ERO callout system per EIP-8.3 Table 1.

. Initiate notification using the Emergency Notification Network (ENN) to at least ONE state agency within 15 minutes.

. Complete NMP-EP-l11, Emergency Notifications, Checklist 2.

Examinee:

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

EXAMINER:

Developer Howard Fitzwater 2/7/1 1 NRC Approval SEE NUREG 1021 FORM ES-301-3

FNPHLT-34ADMIN A4.1.R Page2of8 CONDITIONS When I tell you to begin, you are to MAKE INITIAL NOTIFICATIONS AS REQUIRED FOR AN EMERGENCY AND ACTIVATE THE EMERGENCY CALLOUT SYSTEM. The conditions under which this task is to be performed are:

a. A General Emergency has just been declared by the Shift Manager due to an event on Unit 1.

b. The Emergency Notification form has been electronically approved and transmitted.

c. The Shift Manager has provided you with the following:

1. FNP-EIP-8.3, Table 1, Information For Emergency Response Notification System Activation

2. NMP-EP- 111 Table 1, Applicable Agencies for SNC Emergency Notification

3. NMP-EP-1 11, Figure 1, Emergency Notifications

4. NMP-EP-111 Checklist 2, Emergency Notifications Electronic Method

d. The Shift Manager has directed you to:

• PERFORM the initial ENN notification over the Southern LINC ENN.

- USE the SOUTHERN LINC and actually perform this function.

- The SOUTHERN LINC will be selected to WIDE AREA TRN ENN on the display.

• ACTIVATE the ERO callout system per EIP-8.3, Table 1.

- USE the HANDS FREE SPEAKER for the phone call.

e. This JPM contains time critical elements.

The Evaluator MUST enter the following Dates and Times on the Notification Form.

• LINE 10: DECLARATION TIME/DATE; use time at which the JPM is started.

• LINE 12: Shutdown at Time TIME/DATE; use declaration time minus 10 minutes.

• LINE 17: APPROVAL Time/DATE; use time at which the JPM is started

• NOTIFIED BY: add candidates NAME.

INITIATING CUE, You may begin.

EVALUATION CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

TIME CRITICAL ELEMENT and JPM START TIME UP TO 15 MINUTES NOTE:

• The time it takes to complete element 2 through 3 is time critical and is required to be completed within 15 minutes of the declaration time which is the start time of the JPM.

• Element 1 can be accomplished after the initial notification.

• Element 1 can be verified as completed successfully via the callback that occurs to the Simulator phone.

FNPHLT-34ADMIN A4.1.R Page3of8 EVALUATION CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

• 1. Initiate the ERO callout system per EJP-8.3 From any plant telephone dial the S I U Table 1 provided by the Shift Manager. number specified on the table to contact the ERO callout system.

prompts that the system would provide: When prompted, Enter the S I U Enter the scenario activation password, SCENARIO ACTIVATION followed by the pound sign. PASSWORD (12345 6789#)

you have entered (#entered). Is that correct?

Enter 9 for yes, or 6 for no If entered correctly, Enters 9 Else enters 6 and returns to the Enter the scenario activation number, followed previous. S I U by the pound sign.

Enters the SCENARIO ID you have entered (#entered). Is that correct? (74685#).

Enter 9 for yes, or 6 for no If entered correctly, Enters 9 press 3 to build the scenario Else enters 6 and returns to the previous. S / U the scenario is building When directed enters 3.

Cue. The security tower called and reports that the ERO callout system called and delivered message 3.

CAUTION: . Ensure that no actual transmissions to emergency agencies occur.

o WIDE AREA, TRN ENN should be used in lieu of WIDE AREA, FEP ENN

2. Verify the Southern LINC ENN Radio being Red light on power supply is lit S I U used is turned on and selected to the WIDE and radio is actually turned on.

AREA, TRN ENN Checks alignment to WIDE AREA, TRN ENN NOTE: Element 3 & 4, ROLL CALL, are NOT required to be completed. IF the candidate elects to skip ROLL CALL, proceed to element 5

FNP HLT-34 ADMIN A4.1 .R Page 4 of 8 EVALUATION CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

3. (NMP-EP-111 Checklist 2, STEP 1-3.b.) Press group pushbutton, verify S I U Initiate Roll Call using the Emergency display shows WIDE AREA, TRN Notification Network (ENN). ENN. An Instructor will be on the other Southern LINC ENN Radio.

See below for student announcement.

Press PTT, wait for the chirp and announce This is a DRILL message. This is [NAME] AT Plant Farley. An EMERGENCY HAS BEEN DECLARED. PLEASE ENSURE YOU ARE LOGGED INTO WEBEOC AND STBANDBY TO CONFIRM RECEIPT OF AN EMERGENCY MESSAGE.

Release the PTT pushbutton.

4. (NMP-EP-111 Checklist 2, STEP 3.c.) SEE BOOTH RESPONSE S I U Call each facility by name (see Table 1) and FORM FOR CUES.

confirm they are in standby.

• 5 (NMP-EP-111 Checklist 2 STEP 8) The candidate reads the following S / U Contact each agency by name (see Table 1) script and then calls for each state and use the following script to ask each agency in each category the agency to verify receipt of the emergency instructor will say the following:

message:

Press PTT, wait for the chirp and announce This is a DRILL message. This is [NAME] AT Plant Farley. EMERGENCY NOTIFICATION MESSAGE NUMBER ONE (1) HAS BEEN TRANSMIFEDTO YOU ELECRONICALLY BY WEBEOC. DID YOU RECEIVE THE MESSAGE?

Release the PTT pushbutton.

CUE: SEE BOOTH RESPONSE FORM FOR CUES.

TIME CRITICAL ELEMENT STOP When confirmation of receipt by the first State TIME AGENCY is received the Critical Element time stops.

• 6 (NMP-EP-111 Checklist 2 STEP 9) RECORDS the time and date on S / U Record the TIME (HH:MM) and DATE the EN FORM (mmldd/yy) when the first agency acknowledges electronic notification on the message confirmation portion of the EN Form (either electronic or manual). This time is the notification time.

FNPHLT-34ADMIN A4.1.R Page5of8 EVALUATION CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

• 7 (NMP-EP-111 Checklist 2 STEP 10) Contacts one agency in each state S / U Contact one agency in each state by name on Table 1, and records names.

(see Table 1) for the applicable site AND record the name of each agency person confirming receipt on the message CUE: SEE BOOTH confirmation portion of the EN Form (either RESPONSE FORM FOR CUES.

electronic or manual).

TIME Terminate JPM after completion of all Critical elements CRITICAL ELEMENTS: Critical Elements are denoted with an Asterisk (*) preceding the element number.

GENERAL

REFERENCES:

1. NMP-EP-lll,V2.O

2. FNP-O-EIP-8.3, V14.O

3. KAs: G2.4.43 RO-3.2 SRO-3.8 GENERAL TOOLS AND EQUIPMENT:

PROVIDED by examiner:

1. NMP-EP- 111 Table 1

2. NMP-EP-1 11 Checklist 2

3. FNP-EIP-8.3, Table 1, with steps 1 & 2 marked complete

4. NMP-EP- 111, Figure 1 with proper date and times added.

COMMENTS:

Element 1 can be actually performed, using Speaker phone to confirm NO actual actuation is made.

IF Element 1 is reverted to an actual perform, replace Bullet #2 for the Initial conditions item c with the following:

• ACTIVATE the ERO callout system per EIP-8.3, Table 1.

- USE the HANDS FREE SPEAKER for the phone call.

Alternatively it can be simulated. If reverted to simulate use the following to replace bullet #2.

• ACTTVATE the ERO callout system per EIP-8.3, Table 1.

- SIMULATE the phone call. DO NOT actually press any buttons on the telephone.

FNP HLT-34 ADMIN A4.1 .R Page 6 of 8 STEP Evaluation 1 Critical: Task completion: required to properly complete the task as assigned. Call out can only be performed in this manner.

2 Not critical: this is a task that will be performed prior to the task start and the phone will already be in this mode.

3-4 Not critical: Roll call is not required or expected since the Emergency Notification form has been electronically approved and transmitted.

5 Critical: Task completion: required to properly complete the notification of one state agency in each state.

6 Critical: Task completion: required to properly document the receipt of the ENN form.

7 Critical: Task completion: One agency in each state is required to be contacted per EP-ill Table 1.

FNPHLT-34ADMIN A4.1.R Page7of8 SOUTHERN LINC Phone talker communication GUIDE Give this to the Instructor performing phone talker duties ROLL CALL (if implemented)

1. 3-4 ALABAMA EMA, Houston County EMA, Georgia EMA at Atlanta EOC and Early County EMA will respond. NO other stations are manned.

ALABAMA EMA, John Brown is on the line.

Alabama Radiation Control (ARC) at Montgomery EOC, Nancy Wiilis is on the line.

Alabama Radiation Control at Alabama Forward EOC, Joe Lawson is on the line.

Houston County EMA, Steve Smith is on the line.

Georgia EMA at Atlanta EOC, Ed Stern is on the line.

Georgia EMA at Georgia Forward EOC, Pam Brown is on the line.

Early County EMA, Chuck Terry is on the line.

1. 5-7 THE first agency questioned for receipt will only respond with I have received message number 1 and will require the candidate to request the name. AFTER the first NAME has been requested, then the RESPONSE will include the name:

First agency response: I have received message number one.

When the name is requested, then provide the applicable name.

ALABAMA EMA, John Brown has received message number one.

Alabama Radiation Control (ARC) at Montgomery EOC, Nancy Wiilis has received message number one.

Alabama Radiation Control at Alabama Forward EOC, Joe Lawson has received message number one.

Houston County EMA, Steve Smith has received message number one.

Georgia EMA at Atlanta EOC, Ed Stern has received message number one.

Georgia EMA at Georgia Forward EOC, Pam Brown has received message number one.

Early County EMA, Chuck Terry has received message number one.

FNP HLT-34ADMIN A4.1.R HANDOUT Page 1 of 1 CONDITIONS When I tell you to begin, you are to MAKE INITIAL NOTIFICATIONS AS REQUIRED FOR AN EMERGENCY AND ACTIVATE THE EMERGENCY CALLOUT SYSTEM. The conditions under which this task is to be performed are:

a. A General Emergency has just been declared by the Shift Manager due to an event on Unit 1.

b. The Emergency Notification form has been electronically approved and transmitted.

c. The Shift Manager has provided you with the following:

5. FNP-EIP-8.3, Table 1, Information For Emergency Response Notification System Activation

6. NMP-EP- 111 Table 1, Applicable Agencies for SNC Emergency Notification

7. NMP-EP-111, Figure 1, Emergency Notifications

8. NMP-EP-ll I Checklist 2, Emergency Notifications Electronic Method

d. The Shift Manager has directed you to:

• PERFORM the initial ENN notification over the Southern LTNC ENN.

- USE the SOUTHERN LINC and actually perform this function.

- The SOUTHERN LINC will be selected to WIDE AREA TRN ENN on the display.

• ACTIVATE the ERO callout system per EIP-8.3, Table 1.

- USE the HANDS FREE SPEAKER for the phone call.

e. This JPM contains time critical elements.

NUCLEAR POWER PLANT EMERGENCY NOTIFICATION FORM

1. DRILL ACTUAL EVENT MESSAGE # I INITIAL FOLLOW-UP NOTIFICATION: TIME DATE / / AUTHENTICATION #

SITE: Farley Nuclear Plant Confirmation Phone # (334 ) 814-4662

4. EMERGENCY ØUNUSUAL EVENT ALERT DSITE AREA EMERGENCY GENERAL EMERGENCY CLASSIFICATION:

BASED ON EAL# RGI EAL DESCRIPTION:

Offsite dose resulting from an actual or imminent release of gaseous radioactivity exceeds 1,000 mR TEDE or 5000 mR Thyroid CDE for the actual or irojected duration of the release usinQ actual meteoroloav.

5. PROTECTIVE ACTION RECOMMENDATIONS: NONE EJ EVACUATE SHELTER A, B5, C5, J5, KS 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.

EJ OTHER

6. EMERGENCY RELEASE:

9 None Is Occurring 9Has Occurred

7. RELEASE SIGNIFICANCE: 9Not applicable 9Within normal operating limits Above normal operating limits 9Under Evaluation

8. EVENT PROGNOSIS: 9improving StabIe QDegrading

9. METEOROLOGICAL DATA: Wind Direction from 335 degrees Wind Speed 3.4 mph*

(* May not be available for Initial Notifications)

Precipitation NONE

• Stability Class*

EEl EJ EJ EEJ EJ 1 DECLARATION 9 TERMINATION Time Date 5 / I 11 AFFECTED UNIT(S):

9 9

12. Unit Status: Ui 0  % Power Shutdown at: Time Date 5 I / 11 (Unattected Unit(s) tetus Not -tequired tor Initial Notifications)

EJ U2  % Power Shutdown at: Time Date

13. REMARKS: A PUFF release is occurrinq.

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

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

14. RELEASE CHARACTERIZATION: TYPE: 9Elevated 9Mixed 9Ground UNITS: Ci Ci/sec iiCi/sec MAGNITUDE: Noble Gases: lodines: Particulates: Other:

FORM:9Airborne Start Time: Date: / Stop Time: Date Liquid Start Time: Date: I Stop Time: Date I /

15. PROJECTION PARAMETERS: Projection Period: Hours Estimated Release Duration: Hours Projection performed: Time Date I I

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

Site boundary 2 Miles 5 Miles 10 Miles APPROVED BY: W. T. Door

Title:

Emergency Director Time: Date: 5i / 11 NOTIFIED BY: RECEIVED BY: Time: Date: I (To be completed by receiving organizaiton)

Checklist 2 Emergency Notifications Electronic Method (page 1 of 4)

NOTES: 1) To expedite availability of WebEOC in an emergency, the crew - -

members responsible for completing Figure 1 and making electronic notifications should login to WebEOC as soon as possible utilizing Attachment 3 and remain logged-in.

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 by the ED. The EN form is transmitted when OK is selected following selection of the APPROVAL button. Do not delay EN form preparation or transmittal to complete Roll Call.

Upon receiving direction to prepare/transmit an Emergency Declaration Message:

1. Obtain a copy of Table 1.

2. Establish contact on the ENN by performing a roll call of the applicable agencies. Each agency should be contacted. Check off each agency on Table 1 as acknowledgement is obtained.

( 3. Roll call:

a. Read the following script:

[Select one] THIS IS A [D DRILL D ACTUAL EMERGENCY] MESSAGE.

THIS IS [YOUR NAME] AT

[Select one] [DPlant FARLEY D Plant HATCH D Plant VOGTLE].

AN EMERGENCY HAS BEEN DECLARED. PLEASE ENSURE YOU ARE LOGGED INTO WEBEOC AND STANDBY TO CONFIRM RECEIPT OF AN EMERGENCY MESSAGE.

[Select one] THIS IS A [D DRILL D ACTUAL EMERGENCY] MESSAGE.

b. Call each facility by name (see Table 1) and confirm they are in standby.

c. IF time allows THEN agencies not contacted by the ENN should be contacted using the phone numbers provided in Table 1.

Southern Nuclear Operating Company Nuclear NMP-EP-1 11 SOUTHERN Management Emergency Notifications Version 2.0 Instruction Page 15 of 47 Checklist 2 - Emergency Notifications - Electronic Method (page 2 of 4)

4. IF not already completed THEN complete the electronic notification form in accordance with instructions provided in Figure 3 Flowchart for Initial Emergency Notifications (preferred) or Figure 4 Flowchart for Follow-Up Notifications (preferred), as appropriate. 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.

5. WHEN the Emergency Notification form has been electronically approved and transmitted, THEN confirm receipt of the notification using Figure 5 Emergency Notification Receipt Confirmation or the remainder of this checklist as guidance.

6. IF ROLL CALL of the applicable Table 1 agencies is not complete THEN terminate roll call.

7. (Vogtle Only) IF any agency requires message authentication THEN authenticate the message as follows:

a. Enter the code provided by the requesting agency.

b. Select GET AUTHENTICATION CODE.

c. Provide the authentication code supplied by the system to the agency requiring authentication verbally over the ENN.

8. Contact each agency by name (see Table 1) and use the following script to ask each agency to verify receipt of the emergency message:

[Select one] THIS IS A [D DRILL D ACTUAL EMERGENCY] MESSAGE.

THIS IS [YOUR NAME]

AT

[Select one] [DPIant FARLEY D Plant HATCH D Plant VOGTLE].

EMERGENCY NOTIFICATION, MESSAGE NUMBER [MESSAGE NUMBER] HAS BEEN TRANSMITTED TO YOU ELECTRONICALLY [either WebEOC or Fax]. DID YOU RECEIVE THE MESSAGE?

9. Record the TIME (HH:MM) and DATE (mm!dd/yy) when the first agency acknowledges electronic notification on the message confirmation portion of the EN Form (either electronic or manual). This time is the notification time.

10. Contact each agency by name (see Table 1) for the applicable site AND record the name of each agency person confirming receipt on the message confirmation portion of the EN Form (either electronic or manual).

11. Select SAVE.

12. After confirming receipt by other agencies, IF an agency does not receive the EN form electronically, THEN read lines 1 through line 13 and line 17 for initial notifications (or lines 1 through 17 for a follow-up notification) for the agency not in receipt.

1 Southern Nuclear Operating Company I Nuclear I I NMP-EP-111 I I

SOUTHERN COMPANY Management I Emergency Notifications Version 2.0 I I Instruction I .

Page 16 of 47 I Checklist 2 - Emergency Notifications - Electronic Method (page 3 of 4)

13. Continue by asking: DO YOU HAVE ANY QUESTIONS CONCERNING THE 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.

14. IF requested by an agency to read any portion of the EN Form, THEN read the requested portions of the EN Form.

15. After all questions have been resolved print the completed EN form.

Southern Nuclear Operating Company I

I SOUTHERN COMPANY Nuclear Management I Instruction I

I Emergency Notifications Checklist 2 Emergency Notifications Electronic Method (page 4 of 4)

I NMP-EP-111 Version 2.0 Page 17 of 47 1 Continuing Action

1. Continue by asking: DO YOU HAVE ANY QUESTIONS CONCERNING THE 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 agency cannot be reached via the ENN, use an alternate method (e.g.,

commercial telephone line and the number provided in the emergency response telephone directory) to contact the individual station directly.

3. If multiple agencies cannot be reached via the ENN, then go to the applicable sites Back-up Communication Systems (Table 1) for offsite notifications.

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 11 SOUTHERN Management Emergency Notifications Version 2.0 Instruction Page 42 of 47 Table I - Applicable Agencies for SNC Emergency Notification (page 1 of 3)

Farley:

1. Primary Notification System: ENN SoLINC

2. Back-up Communication systems (1) Comlabs, (2) Commercial Telephone, (3) Radio, (4) Satellite phone INITIAL ACK FOLLOW-UP CONTACT NAME Alabama (at least one in preferred order)

Alabama EMA (AEMA)**

ENN (1306), OPX (6619), (205-280-2312, 205- D Alabama EMA 280-2310)

Alabama Radiation Control (ARC) at Montgomery EOC ARC at Montgomery ENN (1305), OPX (6628), (334-206-5391), (334 EOC 324-0076)

Alabama Radiation Control at Alabama Forward ARC at Alabama EQC Forward EOC ENN (1307), OPX 6621), (334-793-1565)

Houston County EMA or 91 1 Center** Houston County ENN (1307), OPX (6621) (334-794-9720, 334- EMA 793-9655, 334-677-4807/4808)

Georgia (at least one in preferred order)

Georgia EMA at Atlanta EOC** Georgia EMA at ENN (1304), OPX (6629) (404-635-7200) Atlanta EOC

. . Georgia EMA at Georgia EMA at Georgia Forward EOC D Georgia Forward ENN (1308) OPX (6626), (229-723-4826) EOC Early County EMA or 91 1 Center**

D Early County EMA ENN(1308) OPX (6622) (229-723-3577, 3578, 4826)

Denotes agency is a 24 Hour Warning Point

SHARED INFORMATION FOR EMERGENCY RESPONSE NOTIFICATION SYSTEM ACTIVATION 0 Obtain the SCENARIO ACTIVATION PASSWORD and the SCENARIO IDENTIFICATION NUMBERS from the Unit 2 Shift Supervisor, the SAS Operator, or the Security Shift Foreman.

SCENARIO ACTIVATION PASSWORD:_123456789 Operations Shift Manager, Shift Supervisor or Emergency Director determine the message to be sent from step 11.

Message Number: 3 SCENARIO IDENTIFICATION NUMBER:__74685

3. Call the Farley Emergency Callout System in Dothan at 9-702-2548 and follow the phone instructions to activate a scenario. If the Farley Emergency Callout System cannot be activated at this number then, go to step 9 to activate the backup system.

4. When the system requests it, input the SCENARIO ACTIVATION PASSWORD obtained in step 1 and the SCENARIO IDENTIFICATION NUMBER associated with the message number determined in step 2.

5. When directed press the three key on the phone to activate the scenario.

6. When the system informs you that the scenario is building hang up the phone.

7. If there was a problem activating the Farley Emergency Callout System then, go to step 9 to activate the backup system.

8. When the Farley Emergency Callout System or the backup activates, the following will occur:

8.1 Emergency Response Organization pagers will be activated with the (800) number.

8.2 The SFM in the SAS should call the Shift Clerk when the ERO pager is activated.

8.3 The system will also call the Shift Clerk. The call from the SAS and this phone call allows verification that the system has activated.

8.4 For eight to ten minutes, the system will accept calls from individuals that have called in from the pager activation.

8.5 After eight to ten minutes the system will continue to accept inbound calls and will also call all of the individuals in the database that have not responded to the 800 number.

8.6 As individuals call in or are called, they will have to identify themselves by entering their employee number, receive the message selected in step 2, respond if they are coming to the plant and enter the number of minutes if they are coming to the plant.

T 1 PA 1 2 Version 14

12/01/10 14:10:05 iNFORMATION FOR EMERGENCY RESPONSE NOTIFICATION SYSTEM ACTIVATION 8.7 Every 15 minutes for the duration of the callout, a printout will be sent to the Shift Clerks office and/or the fax machine in the TSC listing the people that have responded.

9. If the system has failed to activate, call the backup system at (800) 475-9705. Enter the company ID code of 1044 and proceed as described in steps 4 through 7.

10. If both systems have failed to activate, proceed to FNP-0-EIP-8.3, step 11, to manually callout the emergency response staff.

Message Numbers Message 1 EMERGENCY CALL OUT Scenario Identification Number:________________________

THIS IS NOT A DRILL, I repeat THIS IS NOT A DRILL. This is a callout of the Farley Emergency Response Organization due to a declared emergency. Respond to your Emergency Response Facility as quickly and safely as possible. THIS IS NOT A DRILL.

Message 2 SECURITY EVENT CALL OUT Scenario Identification Number:________________________

THIS IS NOT A DRILL, I repeat THIS IS NOT A DRILL. This is a call-out of the Farley Emergency Response Organization. An emergency has been declared at the plant due to a security event. If responding from off site, the TSC staff should respond to the Emergency News Center in Dothan as quickly and safely as possible. If you are currently on site, do not try to leave the plant or report to your emergency response facility. Follow the directions issued over the plant public address system. THIS IS NOT A DRILL Message 3 DRILL CALL OUT Scenario Identification Number: 74685 THIS IS A DRILL, I repeat THIS IS A DRILL. This is a call-out of the Farley Emergency Response Organization due to a drill or exercise. Respond to your Emergency Response Facility as quickly and safely as possible. THIS IS A DRILL Message 4 COMMUNICATIONS TEST Scenario Identification Number:________________________

THIS IS A DRILL, I repeat THIS IS A DRILL. This is a communication test of the Farley Emergency Response Organization. An emergency classification has not been declared.

There is no required activation. Do not physically report to your designated Emergency Response Facility. This is a communication test only. THIS IS A DRILL.

P 2 Version 14

HLT-34 ADMIN JPM A4.1 .S Page 1 of 7 A4.1.S SRO Emergency Plan ADMIN G2.4.44 TITLE: Provide an updated Protective Action Recommendation (PAR).

EVALUATION LOCATION: D SIMULATOR LICONTROL ROOM I1CLASSROOM PROJECTED TIME: 15 MN SIMULATOR IC NUMBER: N/A

• ALTERNATE PATH 1 TIME CRITICAL LI PRA JPM DIRECTIONS:

1. This task will be conducted individually in any setting in which all the necessary references are available.

2. Provide the candidate a copy of Message Number 001 for the event in progress.

3. Provide the candidate a copy of the Partially prepared Message Number 002, that does not contain LINE 5 data, nor does it contain approval signatures or notification information.

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

5. This task is TIME CRITICAL.

CAUTION: A KEY is included and precedes the student handout. CARE must be taken when providing the Student HANDOUT as to not also include the KEY.

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

• Correctly assess the necessary changes in the PARs.

• Complete the ENN FORM LINE 5, providing a PAR recommendation to the ED within 15 minutes from beginning of task.

Examinee:

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

EXAMINER:

HLT-34ADMINJPM A4.1S Page2of7 CONDITIONS

( When I tell you to begin, you are to PROVIDE AN UPDATED PROTECTIVE ACTION RECOMMENDATION (PAR). The conditions under which this task is to be performed are:

a. Unit 1 has declared a General Emergency based on EAL# FGI; FG1: Loss of ANY Two Barriers AND Loss or Potential Loss of Third Barrier.

b. A radioactive release is occurring from the IA SG, which has a tube rupture and is faulted outside of Containment.

c. FRP-H.1, Loss of Heat Sink, is in progress.

d. Dose Assessment is provided that dose at site boundary will be:

o <1 R TEDE at site boundary and o <5RThyroidCDE

e. The IPC function EP WEATHER is not available.

f. Wind direction and speed has changed.

g. The current MET Tower data is as follows:

o Wind Direction from 045 degrees.

o Wind Speed 4.5 mph*.

o Precipitation none.

o AT value is -0.25°F.

h. The ENN Form has been manually completed by another operator with the exception of LINE 5.

i. You are required to develop the PARS per NMP-EP-1 12, Attachment 1, INITIAL ACTIONS, AND complete the following documentation:

o NMP-EP-112, Attachment 5, PAR Worksheet.

o Line 5 of the Emergency Notification Form message #002.

j. This task has TIME CRITICAL elements.

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

EVALUATION CHECKLIST RESULTS:

ELEMENTS: STANDARDS: (CIRCLE)

CRITICAL TIME START

1. Attachment 1 step A. 1 & A.2, S / U And ATTACHMENT 5 step 1. Determines PAR 2 is applicable.

Reviews P&Ls and Utilizes ATTACHMENT 5 to document previously affected ZONES.

Review conditions and Attachment 1 Flowchart to determine PAR 2 remains in effect.

Documents on Attachment 5 Documents ATTACHMENT 5 PAR 2 Check box.

HLT-34 ADMIN JPM A4.1 .S Page 3 of 7 EVALUATION CHECKLIST RESULTS:

Q ELEMENTS: STANDARDS: (CIRCLE)

2. Attachment 1 step A.3: S / U And ATTACHMENT 5 Step 2 & 3. Identifies zones A, B5, C5 and D5 are the affected ZONES for the Utilizes ATTACHMENT 2 Table 1 to determine NEW wind direction.

affected Zones for the new wind direction of 045 degrees.

3. Attachment 1 step A.4: S I U And ATTACHMENT 5 step 3 & CAUTION DOCUMENTS on ATTACHMENT 5 zones A, B5, IDENTIFIES on the TABLE the following C5, D5, J5 and K5 are the ZONES are affected: ZONES to be evacuated.

A NOTE: the same zones from B5 message #001 are included in C5 addition to D5 D5 J5 Documents PAR B & D are KS applicable.

4. Attachment 1 step A.S: S / U And ATTACHMENT 5 DOCUMENTS ON LINE 5 of ENN Form message #002 On the ENN Form for the selected PAR:

• Select block 5.B and record the Evacuate Select block 5.B and records on zones OR select block 5.C and record the line 5B: zones A, B5, C5, D5, J5 Shelter zones and K5.

• Select block S.D

• IF PAR 4 is selected, THEN additionally select Select block 5.D.

block S.E Other and provide Affected Sectors and To Miles CRITICAL TIME STOP Terminate when all elements of the task have been completed.

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

HLT-34ADMINJPM A4.1.S Page4of7 GENERAL

REFERENCES:

1. NMP-EP-112, V 1.0

2. NMP-EP-110,V1.0

2. KA: G2.4.44 SRO (4.4)

GENERAL TOOLS AND EQUIPMENT:

NMP-EP-1 12 INITIAL NOTIFICATION message #001.

Partially completed INITIAL NOTIFICATION message #002.

Critical ELEMENT justification:

STEP Evaluation 1 Not critical: this task will be performed during evaluation of PARs, but student is not required to state that PAR 2 is required.

2 Critical: Task completion, Required to properly assess the PAR. Inclusion of extra ZONES is considered FAILURE criteria.

• Improper completion of this element could result in more zones being impacted than necessary.

• Step 6.2.4 warns against expanding the evacuation ZONES as a greater risk to the public.

3 Critical: Task completion, Required to properly assess the PAR.

• As noted in Cautions of Attachment 1 step 3 and Attachment 5, PAR Revisions MUST include previous PARs 4 Critical: Task completion, Required to properly assess the PAR.

• As noted in Cautions of Attachment 1 step 3 and Attachment 5, PAR Revisions MUST include previous PARs COMMENTS:

HLT-34 ADMIN JPM A4.1.S Page 5 of 7 KEY LINE 5 of ENN message #002

5. PROTECTIVE ACTION RECOMMENDATIONS: A None EvacuateZONES: A, B5, C5, PS, K5, J5 Shelter ZONES:

Advise Remainder of EPZ to Monitor Local Radio/TV Stations/Tone Alert Radios for D

1 Additional Information and Consider the use of KI (potassium iodide) in accordance with State plans and policy.

Other:

Attachment 5 PAR worksheet Wind direction from ENN Line 5 [C]

Shelter Zones Advise remainder of EPZ to Monitor Local Radio/TV Stations /Tone Alert PAR1 ENN line 5 [Dj Radios. Consider the use of KI (Potassium Iodide) in accordance with State Plans and Policy zPAR2 Wind direction from ENN Line Shelter Zones ENN line 5 5 [C]

[D]

A,B5,C5,D5,K5,J5 Advise remainder of EPZ to Monitor Local Radio/TV Stations /Tone Alert Radios. Consider the use of KI (Potassium Iodide) in accordance with State Plans and Policy Wind direction from ENN Line 5 [C]

Shelter Zones Advise remainder of EPZ to Monitor Local Radio/TV Stations /Tone Alert PAR 3 ENN line 5 [DJ Radios. Consider the use of 1(1 (Potassium Iodide) in accordance with State Plans and Policy Wind direction from ENN Line 5 [C]

Shelter Zones Advise remainder of EPZ to Monitor Local Radio/TV Stations /Tone Alert PAR 4 ENN line 5 [DI Radios. Consider the use of KI (Potassium Iodide) in accordance with State Plans and Policy Evacuate Affected Sectors to ENN Line 5 [E] miles

HLT-34ADMINJPM A4.1.S HANDOUT Page 1 of 1 CONDITIONS When I tell you to begin, you are to PROVIDE AN UPDATED PROTECTIVE ACTION RECOMMENDATION (PAR). The conditions under which this task is to be performed are:

a. Unit 1 has declared a General Emergency based on EAL# FG1; FG1: Loss of ANY Two Barriers AND Loss or Potential Loss of Third Barrier.

b. A radioactive release is occurring from the 1A SG, which has a tube rupture and is faulted outside of Containment.

c. FRP-H.1, Loss of Heat Sink, is in progress.

d. Dose Assessment is provided that dose at site boundary will be:

o <1 R TEDE at site boundary and o <5RThyroidCDE

e. The IPC function EP WEATHER is not available.

f. Wind direction and speed has changed.

g. The current MET Tower data is as follows:

o Wind Direction from 045 degrees.

o Wind Speed 4.5 mph*.

o Precipitation none.

o AT value is -0.25°F.

h. The ENN Form has been manually completed by another operator with the exception of LINE 5.

i. You are required to develop the PARS per NMP-EP-1 12, Attachment 1, INITIAL ACTIONS, AND complete the following documentation:

o NMP-EP-1 12, Attachment 5, PAR Worksheet.

o Line 5 of the Emergency Notification Form message #002.

j. This task has TIME CRITICAL elements.

NUCLEAR POWER PLANT EMERGENCY NOTIFICATION FORM

1. DRILL ACTUAL EVENT MESSAGE# I A INITIAL FOLLOW-UP NOTIFICATION TIME 20 mm ago DATE 5 i Today / II AUTHENTICATION #

C SlTE: Farley Nuclear Plant Confirmation Phone # (334 ) 814-4662

4. EMERGENCY ØUNUSUAL EVENT ALERT QSITE AREA EMERGENCY GENERAL EMERGENCY CLASSIFICATION:

BASED ON EAL# FGI EAL DESCRIPTION:

Loss of ANY Two Barriers AND Loss or Potential Loss of Third Barrier

5. PROTECTIVE ACTION RECOMMENDATIONS: ENONE EVACUATE A, B5, C5, J5, K5 EJ SHELTER Advise Remainder of EPZ to Monitor Local Radio/TV Stations/Tone Alert Radios for Additional Information and Consider the use of KI (potassium iodide) in accordance with State plans and policy.

i: OTHER

6. EMERGENCY RELEASE: ØNone ls Occurring Has Occurred

7. RELEASE SIGNIFICANCE: 9Not applicable ØWlthin normal operating limits Above normal operating limits QUnder Evaluation

8. EVENT PROGNOSIS: Improving StabIe C Degrading

9. METEOROLOGICAL DATA: Wind Direction from 335 degrees Wind Speed 3.4 mpt

(* May not be available for Initial Notifications)

Precipitation NONE

• Stability Class*

E1 EEJ EI EJ EEI EJ In. DECLARATION TERMINATION Time 30 mins ago Date 5 / today/ 11 AFFECTED UNIT(S):

12. Unit Status: Ui 0  % Power Shutdown at: Time 60 mins ago Date 5 / today / II (Unattected Unit(s) Status Not Kequired br Initial Notifications) U2  % Power Shutdown at: Time Date / /

13. REMARKS:

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

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

14. RELEASE CHARACTERIZATION: TYPE: EElevated Mixed Ground UNITS: Ci Ci/sec lJCi/sec MAGNITUDE: Noble Gases: lodines: Particulates: Other:

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

Liquid Start Time: Date: I I Stop Time: Date / /

15. PROJECTION PARAMETERS: Projection Period: Hours Estimated Release Duration: Hours Projection performed: Time Date I /

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

Site boundary 2 Miles 5 Miles (17. APPROVED BY:

10 Miles W. T. Door

Title:

Emergency Director Time: 25minsago Date: ltoday 5 / 11 NOTIFIED BY: J.T. Kelso RECEIVED BY: Time: Date:

(To be completed by receiving organizaiton)

NUCLEAR POWER PLANT EMERGENCY NOTIFICATION FORM

1. DRILL ACTUAL EVENT MESSAGE # 2 INlTIAL FOLLOW-UP NOTIFICATION: TIME DATE / I AUTHENTICATION #

SITE: Farlev Nuclear Plant Confirmation Phone # (334 814-4662

4. EMERGENCY ØUNUSUAL EVENT ØALERT QSITE AREA EMERGENCY GENERAL EMERGENCY CLASSIFICATION:

BASED ON EAL# FGI EAL DESCRIPTION:

Loss of ANY Two Barriers AND Loss or Potential Loss of Third Barrier

5. PROTECTIVE ACTION RECOMMENDATIONS: NONE EVACUATE SHELTER EJ 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 i:

6. EMERGENCY RELEASE: None ls Occurring Has Occurred

7. RELEASE SIGNIFICANCE: 9Not applicable Within normal operating limits Above normal operating limits Øunder Evaluation

8. EVENT PROGNOSIS: lmproving StabIe Degrading

9. METEOROLOGICAL DATA: Wind Direction from 45 degrees* Wind Speed 4.5 mph*

(* May not be available for Initial Precipitation NONE

• Stability Class*

EI EJ EJ E1 EEJ EJ Notifications)

DECLARATION TERMINATION Time 30 mins ago Date 5 / today! 11 AFFECTED UNIT(S):

J Unit Status: ui 0  % Power Shutdown at: Time 60 mins ago Date 5 / today I 11 (Unattected Unit(s) Status Not Required br lnitia Notifications) U2 100  % Power Shutdown at: Time Date

13. REMARKS: Follow-up notification for PAR Change following a change in wind direction.

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

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

14. RELEASE CHARACTERIZATION: TYPE: EElevated Mixed Ground UNlTS:Ci CiIsec iJCiI5ec MAGNITUDE: Noble Gases: lodines: Particulates: Other:

FORM:EAirborne Start Time: Date: Stop Time: Date / /

Liquid Start Time: Date: I / Stop Time: Date I /

15. PROJECTION PARAMETERS: Projection Period: Hours Estimated Release Duration: Hours Projection performed: Time Date I I

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

Site boundary 2 Miles 5 Miles C17. APPROVED BY:

10 Miles

Title:

Time: Date: I NOTIFIED BY: RECEIVED BY: Time: Date: I /

(To be completed by receiving organizaiton)

Southern Nuclear Operating Company Emergency NMP-EP-112 souy Implementing Protective Action Recommendations Version 1.0 Procedure Page 1 of 18 Procedure Owner: Chris Boone I Fleet Emergency Preparedness Manager / Corporate (Print: Name I Title / Site)

Approved By: Original signed by Christopher E. Boone on 09/24/2010 (Peer Team Champion/Procedure Owners Signature I Date)

Effective Dates: 09/27/2010 09/27/2010 11/08/2010 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 at Continuous 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: 12/1/2010

Southern Nuclear Operatinci Company Emergency NMP-EP-112 SOUT 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: 12/1/2010

Southern Nuclear Operating Company Emergency NMP-EP-1 12 SOUTHERN Implementing Protective Action Recommendations Version 1.0 MPNY Procedure Page3ofl8 TABLE OF CONTENTS 1.0 PURPOSE 4 2.0 APPLICABILITY 4

3.0 REFERENCES

4 4.0 DEFINITIONS 5 5.0 RESPONSIBILITIES 6 6.0 PRECAUTIONS AND LIMITATIONS 6 7.0 PROCESS DESCRIPTION 8 8.0 RECORDS 8 9.0 COMMITMENTS 8 ATTACHMENT 1 - ACTION CHECKLIST FOR PAR DEVELOPMENT 9 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: 12/1/2010

Southern Nuclear Operating Company Emergency NMP-EP-1 12 SOUTHERN Implementing Protective Action Recommendations Version 1.0 Procedure Page4ofls 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-92-001, 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 2003-1 2, Clarification of NRC Guidance for Modifying Protective Actions 3.6 NUREG-0654/FEMA REP 1, Supplement 3 3.7 NRC RIS 2004-1 3, 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: 12/1/2010

Southern Nuclear Operating Company Emergency NMP-EP-1 12 SOUTHERN Implementing Protective Action Recommendations Version 1.0 Procedure Page5ofl8 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: 12/1/20 10

Southern Nuclear Operating Company Emergency NMP-EP-1 12 SOUTHERN Implementing Protective Action Recommendations Version 1.0 Procedure Page6ofl8 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: 12/1/2010

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: 12/1/2010

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: 12/1/2010

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 10 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. ci 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

• Selectblock5.D

• IF PAR 4 selected THEN additionally select block 5.E Other and provide Affected Sectors and To Miles.

Printed: 12/1/2010

Southern Nuclear Operating Company Emergency NMP-EP-1 12 SOUTHERN Implementing Protective Action Recommendations Version 1.0 Procedure Page lOof 18 Continuing Activity Attachment 1 (Page 2 of 3)

Action Checklist for PAR Development (Cont)

B. SUPPLEMENTAL ACTIONS Please Check

1. Continue assessment actions applying applicable Precautions & limitations.

2. IF a release is in progress THEN 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 10 miles: ci

• IL a release is in progress and dose assessment calculations indicate a possible need to issue PARs beyond 10 miles, THEN 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 10 miles.

• IF dose assessment calculations indicate the need to recommend actions beyond 10 miles, THEN consult with affected State agency(s) to compare!

validate model assumptions prior to issuing PARs beyond 10 miles.

4. jf conditions requiring PAR 1 entry are eliminated or dose projections change such that additional PARs are required THEN return to the Initial Actions section. Once conditions requiring PAR change are available, PARs should be developed as soon as possible. (The expectation for development is 15 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 15 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 action recommendations after adequate data becomes available.

6. Utilize real time meteorological and effluent radiation monitor readings in continuing assessment activities. IF radiation monitor readings provide sufficient data for assessment, THEN, it is NOT appropriate to wait for field monitoring data to become available to confirm or expand a PAR within the 10-mile EPZ.

7 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.

Printed: 12/1/2010

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 (Page 3 of 3)

Has a AFF RELEA.

neral Emergenc In Progress or Been PAR1 een Declared YES Terminated That Is >YES SHELTER NProjected to ExceedZ 0 2 mile radius And downwind to 5 miles NO NO Advise Remainder of EPZ to Monitor Local I CONTINUE Radio/TV Stations/

ASSESSMENT e or Plant EvenN TARs for Additional L Return to START Underway Making N-YES*

Evacuation Information Consider the use of KI angero,z PAR2 in accordance with EVACUATE State plans and policy NO 0 2 mile radius And downwind to Refer to site specific 5 miles Table I or computer program for affected Advise Remainder of e Conditions Make zones

-YES*

EPZ to Monitor Local Evacuation Radio/TV Stations/ tDo°wn Dangerous CONTINUE TARs for Additional ASSESSMENT Information Return to START NO Consider the use of KI in accordance with State plans and policy PAR3

%ave Doses EVACUATE Beyond the SN o 5 mile radius Refer to site specific c YES+

Table 1 or computer 0 NO Been Projected to And downwind to program for affected PAGcy Exceed V 10 miles zones Advise Remainder of EPZ to Monitor Local Radio/TV Stations/

TARs for Additional Information V

Have Doses Consider the use of KI CONTINUE Beyond 10 Miles in accordance with AS SES SMENT NO Been Projected to State plans and policy Return to START Exceed I PAGs* Refer to site specific Table 1 or computer program for affected YES zones V

PAR4 Evaluate the Need for PARs *pAGs Beyond 10 Miles Refer to

• 1000mREMTEDEor Table 2

• 5000 mREM Thyroid CDE Printed: 12/1/2010

Southern Nuclear Operating Company Emergency NMP-P-1 12 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 AFFECTED FROM (degrees) ZONES ZONES N, > 349 - 11 A, B5, C5, J5, K5 A, B5, C5, D5, E5, F5, I, J5, K5, BlO, 010, K10 NNE, >1134 A, B5, CS, D5, K5 A, B5, 05, 05, E5, F10, 010, D10 NE, >34 56 A, B5, C5, D5 A, B5, C5, D5, 15, J5, ClO, D10 ENE, >5679 A, C5, D5, E5 A, B5, C5, 5, F55J5, K5, 010, D10, ElO E, >79-1 01 A, D5, E5, F5 A.B5, C5, D5,EW5, 15, J5, K5, 010, D10, ElO ESE, >101 124 A, D5, E5, F5 CS, D5, E5, K5, D10, ElO, FlO L

SE, >124-1 46 A, E5, F5 A, B5, C5, D5, E5, ES, 15, J5, K5, ElO, FlU SSE, >146 - 169 A, ES, F5,L , B5, C5,tF5, IS, J5, K5, ElO, ElO, GlO S, >169 - 191 A, E5, F5, I5 5i ES, F5, 15, J5, K5, FlU, GlO, H10 irS SSW, >191 - 214 A, F5, 5 , BS, C5, D5, ES, F5, 15, J5, KS, FlU, Gb, H10, 110 Sw, >214-236 A, F5, A, BS, 05, D5, ES, ES, IS, J5, KS, FlU, GlO, H10, 110, J \

V W36-29 A, 15, - A, B5, 05, D5, E5, F5, IS, J5, KS, GlO, H10, 10, iio W, >259 281 A, 15, J5 A, BS, 05, D5, ES, F5, 15, JS, KS, H10, 110, J10, K10 WNW, >281 30 its, J5, K5 A, B5, C5, D5, ES, F5, 15, J5, K5, 110, J10, KiD NW, >304 326 - A, BS, J5, K5 A, B5, CS, D5, E5, F5, 5, J5, K5, BlO, J10, K10 NNW, >326 349 A, BS, 05, J5, K5

- A, B5, CS, D5, E5, F5, 15, JS, K5, BiD, K10 Printed: 12/1/2010

Southern Nuclear Operating Company Emergency NMP-EP-1 12 SOUTHERN Implementing Protective Action Recommendations Version 1.0 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 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).

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 F WIND DIRECTION FROM (degrees) AFFETEDSECTORS N, >349-11 d H,J,K k -

NNE,>1134 J,K,L NE, >3456 . K,L,M ENE,>56i $ L,M,N E,>79-1O1 M,N,P

. r ESE,>1O1124 r N,P,Q SE, >124-1 46 P, Q, R SSE, >146 169-7 Q, R, A S,>169-191 R,A,B

W,>191 -214 A,B,C SW, >214-236 B, C, D WSW, >236-259 C, D, F W, >259 281 D, F, F WNW, >281 304 E, F, G NW,>304-326 F,G,H NNW, >326 349 - G, H, J Printed

12/1/2010

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Southern Nuclear Operating Company Emergency NMP-EP-1 12 SOUTHERN Implementing Protective Action Recommendations Version 1.0 r,,. Procedure Page 15 of 18 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). ,

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 SECTOR N, >349-Il H,J,K NNE,>1134 J,K,L NE,>3456 K,L,M ENE,>5679 L,M,N 79-101 M, N, P ESE,>lOI124 N,P,Q

>124-146 P, Q, R SSE, >146 169- Q, R, A wP EjPfi,>169-191 R,A,B 4 j SW,>191 -214 A,B,C SW, >214-236 B, C, D WSW, >236-259 C, D, E kr 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: 12/1/2010

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Southern Nuclear Operating Company Emorgoncy NMP-EP-1 12 SOUTHERN Implementing Protective Action Recommendations Version 1.0 I! 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.

Distance (miles) + 5 miles = Evacuation Distance (miles) 4

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).

4. Check Line 5, Item E A

Other on the Emergency Notificatorm and record the recommended sectors and distance range in miles for Evacuation. (Note:Wefer to 50 mile IPZ map as necessary)

PAR&

WIND DIRECTION FROM (degrees) AFFE* ED SECTOFS N, >349-Il H,J,K NNE,>11-3t J,K,L NE, >3456 p

ENE, >56 79 L,M,N

-101 M,N,P ESE,1.1 N,P,Q SE, >124-146 P, Q, R

>146-169 Q,R,A A S,>169-191 R,A,B SSW, >191 -214 A, B, C SW, >214-236 B, C, D W, >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: 12/1/2010

Southern Nuclear Operating Company Emergency NMP-EP-1 12 SOUTHERN Implementing Protective Action Recommendations Version 1.0 Procedure Page 18 of 18 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.

I CAUTION: 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 5.C and record the Shelter zones

• Select block S.D

• IF PAR 4 is selected, THEN additionally select block 5.E Other and provide Affected Sectors and To Miles Wind direction from ENN Line 5 [C]

Shelter Zones Advise remainder of EPZ to Monitor Local Radio/TV Stations PAR I 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 PAR2 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 PAR3 ENN Line 5 [0]  !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!

ENN Line 5 [D] Tone Alert Radios. Consider the use of Kl (Potassium Iodide) in PAR 4 accordance with State Plans and Policy ENN Line 5 [E] Evacuate Affected Sectors to OTHER Approval:

Emergency Director DatelTime Printed: 12/1/2010