ML111990569
| ML111990569 | |
| 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: ML111990569 (112) | |
Text
FNP HLT-34 ADMI N Page 1 of 25 A.I.aAdmin a RO/SRG Conduct of Operatiorn ADMIN G2.1.7 TITLE: Critical Safety Function Status Tree Evaluation.
EVALUATION LOCATION: SIMULATOR LICONTROL ROOM I1CLASSROOM PROJECTED TIME: 10 MIN SIMULATOR IC NUMBER: N/A El ALTERNATE PATH LI TIME CRITICAL El 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:
o Correctly assess and determine the status of ALL CSFs and then determine which FRP is required to be implemented using FNP-1-CSF-0.0.
Examinee:
Overall JPM Performance: Satisfactory D Unsatisfactory D Evaluator Comments (attach additional sheets if necessary)
EXAMINER:
Developer Billy Thornton Date: 2/7/20 1 1 NRC Approval SEE NUREG 1021 FORM ES-301-3
FNP HLT-34 ADMIN A.1 .a Page 2 of 25 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. Plant conditions are given in the attached Table 1.
- c. A Safety Injection occurred 30 minutes ago.
- d. The crew is performing actions in EEP-l, Loss of Reactor or Secondary Coolant.
- e. The SPDS computer is NOT available for monitoring Critical Safety Functions.
- f. You have been directed to manually monitor the Critical Safety Functions using CSF-0.0, Critical Safety Function Status Trees on Unit 1.
- g. Perform the following:
- Document each CSF evaluation on FNP-1-CSF-O.O by circling the final colored ball indicating the CSF status.
- Report the FRP that is required to be implemented, if any.
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 TNT 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.
FNP HLT-34 ADMIN A.1.a Page 3 of 25 EVALUATION CHECKLIST RESULTS:
ELEMENTS: STANDARDS: (CIRCLE)
- 3. Evaluate CSF-0.3. NAR RNG LVL IN AT LEAST S / U ONE SG GRTR THAN 31%{48%}- NO TOTAL AFW FLOW TO ALL SGS GRTR THAN 395 GPM -
YES PRESS IN ALL SGS LESS THAN 1129 PSIG-YES NAR RNG LVL IN ALL SGS LESS THAN 82% YES -
PRESS IN 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 IN 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 TN LAST 60 MN GRTR THAN 25 0°F -
NO Determines that an Orange condition exists to go to FRP-P.1.
FNP HLT-34 ADMIN A.1 .a Page 4 of 25 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 2R!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-I.2.
- 7. Determines FRP entry requirements. Determines that FRP-S. 1 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.
FNP HLT-34 ADMIN A.1.a Page 5 of 25 GENERAL
REFERENCES:
- 1. FNP-l--CSF-0.0,VER 17.0
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 determine that FRP-S. 1 is to be implemented.
COMMENTS:
UNIT I 8/29/2007 08:33 FNP-1-CSF-O1 SUBQRITICAUTY Revision 17 Candidate is only required to annotate the circle for GOTO the applicable FRP or that FRP-S.1 the CSF is SAT.
c GO TO FRP-S.2 CSF SAT GO TO FRP-S.2 CSF SAT Page 1 Of I
8/29/2007 08:33 UNIT I FNP-1-CSF-O.2 CORE COOLING Revision 17 Candidate is only required to annotate the circle for the applicable FRPcr that GO TO the CSF is SAT. FRP-C.1
- FRP2 GO TO FRP-C.3 Page 1 of I
8/29/2007 08:33 uNIT I FNP-1 -CSF-0.3 HEAT SINK Revision 17 GOTO Candidate is only FRP-H.1 required to annotate the circle for the applicable FRP or that the CSF is SAT.
GO TO FRP-H.2 GO TO FRP-H.3 GO TO FRP-HA CSF SAT Page 1 Of 1
TTNTT 1 8/29/2007 08:33 FNP-1-CSF-04 INTEGRITY Revision 17 GO TO FRP-P.1 ALL RCS PRESS-- NO CL TEMP IN LAST6OMIN POINTS TO RIGHT OF YES LIMIT A q ALLRCSCL4 TEMPSIN NO
) GO TO LAST 60 MIN FRP-P.2 Candidate is only GRTR THAN required to 2500 F YES annotate the circle for the applicable ALLRCSCL NO TEMPS IN FRPor that the CSF L LAST6OMIN is SAT. GRTR THAN 20°F YES CSF TEMP EC NO INALLCLII LAST6OMIN
) SAT LESS THAN 100°F YES i1h GOTO FRP-P.1 ALLRCSCL NO TEMPS GRTR THAN 250° F YES NO RCS PRESS r LESS THAN 450 PSIG YES GO TO FRP-P.2 NO ALLRCS TEMPS GRTR THAN 325° F I CSF SAT YES b_i I CSF SAT Page 1 of 2
8/29/2007 08:33 IJNIT I FNP-1-CSF-0.4 INTEGRITY Revision 17 IRITY RCS PRESSURE TEMPERATURE CRITERIA 3000 2560
=
2050 2000 w
D U)
(1) w 1500 ITRJLY LLTV uJ INTEGRITY INTEGR[ (
(9 (9 YELLOW GREEN z (1) RED PATH ORANGE P TH REGION PATH PATH REGIO REGION REGION uJ U
1000 U)
C) 500 0
180
/
190 205 225230 250255 RCS COLD LEG WIDE RANGE TEMPERATURE (°F) 280 305 330 Page 2 of 2
8/29/2007 08:3 3 TJNIT I FNP-1-CSF-0.5 CONTAINMENT Revision 17 GOTO FFRI- .1 I
CTMT NO GOTO PRESS b FRP- .1 LESS THAN54 ( YES A LEAST ONE NO PSIG CTMT SPRAY PUMP RUNNING Candidate is only FLO 1000 GPM YES required to GO TO annotate the circle FRP- .2 for the applicable FRPorthatthe CSF is SAT. CTMT NO SUMPL L LESS CTMT THAN 7.6 YES PRESS NO FT.
LESS THAN 27 PSIG ) GO TO FRP- .1 GO TO
=
r dIF FRP- .2 CTMT NO SUMPL L LESS THAN 7.6
)
GO TO 14 BOTH FRP- .3 NO CTMTRA LESS THAN 2 R H
Page 1 of I
8/29/2007 08:33 FN P-I -CSF-O.6 IN ENTORY Candidate is only required to annotate the circle for the applicable FRPi GOTO that the CSF is SAT. FRP-L3 Page 1 of I
HLT34ADMtN Exam A.1.a 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 peiformed are:
- a. Unit 1 tripped from 100% power.
- b. Plant conditions are given in the attached Table 1.
- c. A Safety Injection occurred 30 minutes ago.
- d. The crew is performing actions in EEP-1, Loss of Reactor or Secondary Coolant.
- e. The SPDS computer is NOT available for monitoring Critical Safety Functions.
- f. You have been directed to manually monitor the Critical Safety Functions using CSF-0.0, Critical Safety Function Status Trees on Unit 1.
- g. Perform the following:
Document each CSF evaluation on FNP-1-CSF-O.O by circling the final colored ball indicating the CSF status.
- Report the FRP that is required to be implemented, if any.
HLT34ADMIN Exam AA.a HANDOUT Page 2 of 2 Table 1 INSTRUMENT Channellor II Channellior Parameter TrainA Ij Train B Channel Ill ChannellV Power Range NI 0% 0% 0% 0%
Intermediate Range SUR ÷0.2 DPM +0.25 DPM Intermediate Range NI 3.Oxl .8 AMPS 3.2x1 0.8 AMPS Source Range SUR 0 DPM 0 DPM Source Range NI 0 CPS 0 CPS RCS Pressure 1575 psig 1 550 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 Subcoolirig 250°F 250°F CTMT Emergency Sump Levels 0 inches 0 inches CTMT Radiation 24 mR I Hr 31 mR I Hr RCS Loop I RCS Loop 2 RCS Loop 3 Parameter SGNRLeveI 20% 0% 20%
(all_channels)
AFW flow 325 GPM 0 GPM 340 GPM SG Pressure 800 psig 25 psig 820 psi 9
(all_channels)
RCS WR Cold Leg Temperature 420°F 240°F 425°F RCP status Off Off Off
UNIT I FNP-1 CSF 0 8/29/2007 08:33 8-29-2007 Revision 17 FARLEY NUCLEAR PLANT CRITICAL SAFETY FUNCTION PROCEDURE FNP 1 CSF-O CRITICAL SAFETY FUNCTION STATUS TREES S
A F
PROCEDURE USAGE REQUIREMENTS-per FNP 0 AP-6 SECTIONS E T
Continuous Use ALL Y Reference Use R E
Information Use L A
T E
D Approved:
Jim L. Hunter (for)
Operations Manager Date Issued: 09/14/07
8/29/200708:33 LJiNII I FNP-1 CSF-O CRITICAL SAFETY FUNCTION STATUS TREES Revision 17 Table of Contents Procedure Contains Number of Pages Body 2 FNP 1-CSF-O.1 1 FNP 1 CSFO.2 1 FNP 1 CSF-O.3 1 FNP 1CSF-O.4 2 FNP-1-CSF-O.5 1 FNP 1-CSF-O.6 1 Page 1 of 1
8/29/2007 08:33 FNP-1-CSF-O U-iN II I 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 FNP-1-EEP-O, REACTOR TRIP OR SAFETY INJECTION to any other recovery guideline.
Page 1 of 2
8/29/2007 08:33 ENP-1-CSF-0 I.JNIT I 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.
2.1 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-l-CSF 0.1 through
[1 Subcriticality FNP l-CSF-0.6 as appropriate.
[1 Core Cooling
[1 Heat Sink
[] 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 0.1 through FNP-l-CSF-0.6 END Page 2 of 2
UNIT I 8/29/2007 08:33 FNP-1-CSF-G.1 1 SUBCRLTICALITY RevisiQn 17 GO TO FRP-S.1 GO TO FRP-S. I NO POWER RNG LESS THAN GO TO 5% FRP-S.2 YES L
BOTH INT RNGSUR NO BOTH INT NO MORE RNG SUR NEGATIVE ZERO OR THAN -0.2 YES NEGATIVE DPM YES L BOTH SOURCE RNG ENERGIZED NO YES GO TO FRP-S.2 4
BOTH NO SOURCE RNG SURZERO OR NEGATIVE YES Page 1 of I
8/29/2007 08:3 3 I UNIT I I FNP-1-CSF-O.2 CORE COOLING Revision 17 GO TO
, FRP-C.1 GO TO IçØFRPC.2 FIFTH HOTTEST NO CORE EXIT TC LESS FIFTH NO THAN YES 12000 F HOTTEST CORE EXIT RCS I
NO TC LESS THAN 700° YES SUBCOOLING GO TO FROM CORE FRP-C.3 EXIT TCS GRTR THAN YES 16° F {45° F)
8/29/2007 08:33 UNIT I FNP-1-CSF-O.3 HEAT SINK Revision 17 Fl TOTAL AFW NO FLOW TO ALL SGS GRTR THAN 395 GPM YES L
GO TO FRP-H.2 NAR RNG LVLINAT NO PRESSN NO LEAST ONE ALL SGS SG GRTR LESS THAN THAN 31% YES 1129 PSIG YES
{48%}
4 GOTO FRP-H.3 NARRNG NO LVL IN ALL SGS LESS THAN 82% YES GOTO FRP-H.4 PRESS IN NO ALL SGS LESS THAN 1075 PSIG YES I GOTO FRP-H.5 NARRNG NO LVL IN ALL SGS GRTR THAN 31%
{48%} YES Page 1 of I
8/29/2007 08:33 UNIT I FNP-1-CSF-O.4 INTEGRITY Revision 17 CD 256 a) 0 Ui 205 D
C,)
a)
Ui a)
-) C 190 225 250 280 COLD LEG TEMPERATURE (°F)
GO TO FRP-P.1 ALL RCS PRESS-- NO CL TEMP (IN GOTO LAST6OMIN) FRP-P1 POINTS TO RIGHT OF YES LIMIT A ALLRCSCL NO TEMPS IN GO TO L LAST6OMIN FRP-P.2 GRTR THAN 250° F YES ALLRCSCL NO TEMPS IN L LAST6UMIN GRTR THAN 280° F YES CSF TEMP DECR NO IN ALL CL IN SAT LAST6OMIN LESS THAN 1000 F YES
=1 ALLRCSCL NO TEMPS GRTR THAN 250° F YES NO RCS PRESS r LESS THAN 450 PSIG YES GO TO FRP-P.2 ALLRCS NO TEMPS GRTR THAN 325° F YES 0 CSF SAT I CSF SAT Page 1 of 2
8/29/2007 08:33 UNIT I FNP-1-CSF-04 INTEGRITY Revision 17 INTEGRITY RCS PRESSURE TEMPERATURE CRITERIA 3000-w D
C,)
U) w w
0 z
Ui 0
C.)
190 225230 250255 180 205 280 305 330 RCS COLD LEG WIDE RANGE TEMPERATURE (°F)
Page 2 of 2
8/29/2007 08:33 I UNIT I I FNP-1-CSF-O.5 CONTAINMENT Revision 17 GO TO FRP-Z1 CTMT NO PRESS LESS =
THAN 54 YES PSIG At LEAST ONE NO CTMT SPRAY PUMP RUNNING (FLOW>1 000 GPM) YES CTMT 4T :
NO
- 1 GOTO SUMPLVL LESS CTMT THAN 76 NO PRESS LESS THAN 27 YES GO TO PSIG FRP-Z1 CTMT NO 11 GOTO SUMPLVL LESS THAN 7.6 YES FT.
- GO TO FRP-Z3 BOTH NO CTMTRAD LESS THAN 2 R/ YES hr.
CSF 0
SAT Page 1 of I
8/29/2007 08:33 UNIT I FNP-1-CSF-O.6 !NVENTORY 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-12 NO PRZR LVL GRTR THAN 15%
YES GOTO FRP-L3 ALL NO UPPER HEAD AND PLENUM LVLS EQUAL 100% YES Page 1 of I
FNP HLT-34 ADMN Page 1 of 6
- A.1.b Admin b SRO only Conduct rf Operations ADMIN G2J.4 TITLE: Determine Active License Status.
EVALUATION LOCATION: SIMULATOR D CONTROL ROOM 1I CLASSROOM PROJECTED TIME: 30 MIN SIMULATOR IC NUMBER: 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 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: 2/7/201 1 NRC Approval SEE NUREG 1021 FORM ES-301-3
FNPHLT-34ADMIN A.1.b.SRO Page2of6 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 RUs are available.
- c. All three are cuffent 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 RO s 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)
START TIME
FNPHLT-34ADMIN A.1.b.SRO Page3of6 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 I Terminate when all elements of the task have been completed. I CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk (*) before the element number.
FNP HLT-34 ADMIN A.1 .b. SRO Page 4 of 6 GENERAL
REFERENCES:
- 1. NMP-TR-406, VER 1.0
- 2. NMP-TR-406-F0 1, VER 1.0
- 3. NMP-TR-406-F02, VER 1.0
- 4. NMP-TR-406-F03, VER 1.0
- 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
FNP HLT-34 ADMJN A.1 b. SRO Page 5 of 6 KEY Operator A status - ACTIVE (Active / Inactive)
Operator B status - INACTIVE (Active / Inactive)
Operator C status - ACTIVE (Active / Inactive)
FNPHLT-34ADMIN A.1.bSRO HANDOUT Pg lof I CONDITIONS When I tell you to begin, you are to DETERMIISTE 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.
Operator A status - (Active / Inactive)
Operator B status - (Active / Inactive)
Operator C status - (Active / Inactive)
HLT-34 ADMIN JPM A.1 .b RO Page 1 of 10 A:Lb Admin b RO only Conduct of Operations ADMIN 006A1.02 TITLE: Determine Required Volume, Controller Settings And Integrator Settings For A Makeup To The RWST.
EVALUATION LOCATION: LI SIMULATOR LICONTROL ROOM I1CLASSROOM PROJECTED TIME: 20 MIN SIMULATOR IC NUMBER: N/A LI ALTERNATE PATH LI TIME CRITICAL LI PRA JPM DIRECTIONS:
- 1. Initiation of task may be in group setting, evaluation performed individually upon completion.
- 2. Requiring the examinee to acquire the required references may or may not be included as part of the 1PM, however it is recommended to allow access to the TRAINING REFERENCE DISK.
TASK STANDARD: Upon successful completion of this JPM, the examinee will:
- Determine the required Volume to be added to the RWST.
- Determine the settings required for the Boric Acid and Reactor Makeup Water Flow Integrators.
- Determine the setting Boric Acid flow controller potentiometer setting.
Examinee:
Overall JPM Performance: Satisfactory Unsatisfactory D Evaluator Comments (attach additional sheets if necessary)
EXAMINER:
HLT-34ADMtNJPM A.1.bRO Page2oflo CONDITIONS When I tell you to begin, you are DETERMINE REQUIRED VOLUME, CONTROLLER SETTINGS AND INTEGRATOR SETTINGS FOR A MAKEUP TO THE RWST. The conditions under which this task is to be performed are:
- a. Unit 1 is at 100% power and stable.
- b. RWST Level is at 37.7 feet.
- d. On Service BAT concentration is 7001 ppm.
- e. RWST Purification (Recirc) is NOT on-service.
- f. The Reactivity Spreadsheet is not available.
- g. You have been directed to calculate the values required by SOP-2.3 steps 4.2.3.2 4.2.3.8 necessary to maintain current RWST boron concentration and raise level to 39.5 feet.
- h. Report the following values and settings on the table below:
- 1. The volume required to raise level in the RWST to 39.5 feet.
- 2. The necessary integrator settings for both of the following:
- a. FIS 113, BORIC ACID BATCH INTEG
- b. FIS-168, TOTAL FLOW BATCH INTEG
- 3. The required potentiometer setting of FK-113, BORIC ACID MKUP FLOW, to makeup to the RWST at a reduced flow of 60 gpm total flow.
INITIATING CUE: IF you have no questions, you may begin.
EVALUATION CHECKLIST RESULTS:
ELEMENTS: STANDARDS: (CIRCLE)
START TIME NOTE:
- The candidate may use either curve 31A or Curve 3lB to determine Volume added to the RWST. It is unlikely that Curve 31 A will be used, however the RANGE is provided in the event it is used.
step
- For blended flow set the Boric Acid Integrator to the desired amount of acid and the Total 4.2.4.3 Flow Integrator to the desired amount of reactor makeup water PLUS the boric acid for the NOTE: total amount.
- 1. Step 4.2.3.2, DETERMINE [...] the quantity Calculates total volume and setting S / U
[...j: ofFIS-168.
Determines volume needed using RWST Tank
- Calculates total volume curve 3lB is 22,378 gallons. addition= 22378 gals 49 1064-468686 =22378 If CRV3 IA used: Range provided if CRV3 1A is (ax) + Yintcrcept frange of 4Oft lvi: 490K to 510K) used instead.
(500K 0)gal
[RANGE: 22050 to 22950J]
[(39.5 ft) (37.7 ft)]
(40 0)ft
= 22.5Kf22.OSK to 22.95K)
HLT-34 ADMIN JPM A.1.b RD Page 3 of 10 EVALUATION CHECKLIST RESULTS:
ELEMENTS: STANDARDS: (CIRCLE)
- 2. Step 4.2.3.2,(contd) Determine [...j USES Figure 1, to determine S/U concentration (boric acid, reactor makeup water, Boric acid Flow and FK- 113 Pot or blend) of makeup by one of the following: set point for 120 gpm total Flow
- Reactivity Briefing Sheet Figure 1 Either Page 1 (41.1 gpm)
- Nornographs Or Page 3 (41.14 gpm).
Boric Acid flow 41.14 gprn fRANGE: 41.1 to 41.14}
FK-113 pot setpoint 10.29 turns.
rd 3
step bullet 4.2.4.3
- When making up to the RWST The boric acid flow rate should be such that it will finish NOTE: first and the last thing in the line will be reactor makeup water.
Evaluator Due to the procedural guidance requiring the Boric Acid to end prior to the completion of the NOTE: ADDIITON, then the FK-113 set point identified SHOULD be set to a HIGHER value than that calculated in element 3 to inject the boron faster.
- 3. FIGURE 1 NOTE: Calculate the BORIC ACID S/U NOTES: FIOWRATE for a concentration
- Due to characteristics of the reactor makeup of 2400 ppm at 60 GPM.
system piping, the maximum obtainable boric acid flow is less than 40 gpm.
41.14 gprn
= 20.57 gpm
- Numbers corresponding to boric acid flow (120/60) approaching or greater than 40 gpm are useful tRANGE: 20.55 to 21 gpmj only for calculating the boric acid flow corresponding to a blended flow of less than Calculate FK-1 13 setpoint 120 gpm. 10.29 turns
= 5.145 turns
- Example: 2500 ppm 42.9 gpm with a pot setting (120/60) of 10.7 for a blended flow of 120 gprn. tRANGE: 5.14 to 5.15 turns) 2500 ppm 42.9/2 gpm with a pot setting of 10.7/2 for a blended flow of 120/2 gpm.
2500 ppm 21.45 gpm with a pot setting of 5.35 for a blended flow of 60 gpm.
HLT-34ADMINJPM A.1.bRO Page4ofl0 EVALUATION CHECKLIST RESULTS:
ELEMENTS: STANDARDS: (CIRCLE)
- 4. Calculates the duration of the blended addition at Total duration of addition S I U the given flowrate to fill the RWST the calculated 22378 gal
= 372.97 mins amount: 60 gpm o Calculated total volume 22378 gals (RANGE: 367.5 to 382.5)
[RANGE: (22050 to 22950)1
- GIVEN Flowrate = 60 gprn step 2 bullet 4.2.4.3
- For blended flow set the Boric Acid Integrator to the desired amount of acid and the Total NOTE: Flow Integrator to the desired amount of reactor makeup water PLUS the boric acid for the total amount.
- 5. Calculates the TOTAL Boron Volume: FIS-1 13 Calculates Total Boron Volume 5 / U setting and setting for FIS- 1 13:
- Calculated total time 372.97 mins 372.97 mins x 20.57 ppm (RANGE: 367.5 to 382. 5)] = 7672.0 gal
. Calculated the BORIC ACID F1OWRATE = (RANGE: 7552.1 to 8032 gal) 20.57 gpm (RANGE: 20.55 to 21 gpm) (see alternate means below)
NOTE:
Resultant RWST concentration at end with given ranges and level= 22378 gal:
7552.1 gal 2398.32 ppm 8032 gal 2405 ppm Alternative calculation:
CRMUWSTVRMUW + CBATVBoration + CRWSTVRWST = CfinalVfinal yields Since: CRMUWST = 0.00 ) CRMUWSTVRMUW = 0 ONLY unknown then is VBOratiOn Therefore FIS-1 13:
= Y)
VBoration 7671. 361 Gallons of boron (Range: 7558. 92 to 7867.45)
CBAT
HLT-34ADMNJPM A.1.bRO Page5oflo EVALUATION CHECKLIST RESULTS:
ELEMENTS: STANDARDS: (CIRCLE)
STOP I Terminate when all elements of the task have been completed. I CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk (*) before the element number.
GENERAL
REFERENCES:
- 1. FNP-1-SOP-2.3, V56.0
- 2. KA; 02.1.23 RO 4.3 SRO 4.4 004A4.04 RO 3.2 SRO 3.6 004A4.15 RO 3.6 SRO 3.7 006A1.02 RO 3.0 SRO 3.6 006A1.ll RO 3.1 SRO 3.4 GENERAL TOOLS AND EOUIPMENT:
Calculator FNP-SOP-2 .3 RWST curves CRV31A and CRV31B Individual may ask for**
Unit 1 MCB M/A Station Curves
HLT-34ADMINJPM A.1.bRO Page6oflO Critical ELEMENT justification:
STEP Evaluation 1 Critical: Task completion, This is the calculation which determines FIS-168 setting and total volume, and required for the calculation of all subsequent values.
2 NOT Critical: This is an intermediate step to acquire the proper values of subsequent critical elements, and can be acquired using alternative calculations/methods; this is the procedurally directed action.
3 Critical: FK-113 pot setting is part of the task objective.
FK-1 13 pot setting calculated values identified are those that would create a blended flow for the duration of the addition. The selected set point may be identified to be HIGHER which is desired by the procedure. A higher value is NOT a CRITICAL task failure since flow (pump capacity) and volume (FIS-113) is limited to prevent making the RWST inoperable due to HIGH boron concentration.
- IF, however, FK-1 13 value is excessively LOW, it is possible to make the RWST inoperable by dilution.
4 NOT Critical: This is an intermediate step to acquire the proper values of subsequent critical elements.
5 Critical: Critical: FIS-113 flow totalizer setting is part of the task objective.
Failure to properly set this could result in the RWST becoming INOPERABLE.
COMMENTS:
HLT-34ADMINJPM A.1.bRO Page7ofl0 KEY Volume addition 22378 required Gallons (22050 to 22950)
FIS-168, TOTAL
- 22378 FLOW BATCH Gallons llTEG, setting (22050 to 22950)
FIS-113, BORIC
- 7672 ACID BATCH INTEG, setting Gallons (RANGE 7552.1 to 8032.0 gal)
FK-113, BORIC
- ACID MKUP FLOW, controller 5.145 TURNS setpoint (RANGE: 5.14 to 5. 4 NOTE 1 turns)
NOTE 1: FK-113 pot setting calculated values (range: 5.14 to 5i5} identified are those that would create a blended flow for the duration of the addition. The selected set point may be HIGHER which is desired by the procedure.
HLT-34ADMINJPM Ai.bRO HANDOUT Page lofi CONDITIONS When I tell you to begin, you are DETERMINE REQUIRED VOLUME, CONTROLLER SETTINGS AND INTEGRATOR SETTINGS FOR A MAKEUP TO THE RWST. The conditions under which this task is to be performed are:
- a. Unit I is at 100% power and stable.
- b. RWST Level is at 37.7 feet.
- d. On Service BAT concentration is 7001 ppm.
- e. RWST Purification (Recirc) is NOT on-service.
- f. The Reactivity Spreadsheet is not available.
- g. You have been directed to calculate the values required by SOP-2.3 steps 4.2.3.2 4.2.3.8 necessary to maintain current RWST boron concentration and raise level to 39.5 feet.
- h. Report the following values and settings on the table below:
- 1. The volume required to raise level in the RWST to 39.5 feet.
- 2. The necessary integrator settings for both of the following:
- c. FIS 113, BORIC ACID BATCH INTEG
- d. FIS-l68, TOTAL FLOW BATCH INTEG
- 3. The required potentiometer setting of FK- 113, BORIC ACID MKUP FLOW, to makeup to the RWST at a reduced flow of 60 gpm total flow.
- 1. Volume addition required Gallons 2.
- a. FIS-168, TOTAL FLOW BATCH INTEG, Gallons setting
- b. FIS-113, BORIC ACID BATCH INTEG, setting Gallons
- 3. FK-113, BORIC ACID MKUP FLOW, controller setpoint TURNS
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10/08/10 10:21:11 FNP-1-SOP-2.3 NOTE: The following two steps are not required if operation in a mode other than automatic is required.
4.2.2.22 Position the MKUP MODE SEL SWITCH to AUTO.
4.2.2.23 Position the MKUP MODE CONT SWITCH to START.
CAUTION: Avoid operations that could result in RCS volume changes. Makeup to the VCT from the blender will not be available while making up to the RWST.
NOTE:
- Due to system interconnections, the RWST Purification Loop (Recirculation) should not be in operation using the Refueling Water Purification Pump while making up to the RWST. However, it is permissible to makeup while BARS is in operation.
- IF makeup to the RWST is due to BARS operation, THEN to minimize dilution of the RWST, boron concentration of the blended flow should be greater than or equal to the BARS reject flow concentration.
- IF desired to flush the line of acid following makeup, THEN remember to perform step 4.2.3.20 at an appropriate time prior to reaching the Total Flow Integrator setpoint.
4.2.3 Makeup to Refueling Water Storage Tank (RWST) 4.2.3.1 Verify the RWST capable of receiving makeup.
4.2.3.2 Determine both the quantity and concentration (boric acid, reactor makeup water, or blend) of makeup by one of the following:
- Reactivity Briefing Sheet
- Figure 1
- Nomographs Version 56.0
10/08/10 10:21:11 FNP-1-SOP-2.3 4.2.3.3 IF the final boron concentration in the RWST is going to differ from the initial, THEN use the following formulas or the reactivity briefing sheets to determine the amount of water or acid to be added.
= CI- CF (TJ)
= CI- CF To borate the RWST: VA (VI)
CF-CA To determine final boron concentration:
CF [CI x VI] + [CA x VA]
VF Where:
VA Volume of water or acid added to the RWST VI Initial water volume in RWST VF = Final water volume in RWST CI = Initial boron concentration in RWST CF = Final boron concentration in RWST CA = Boron concentration added to RWST 4.2.3.4 IF the RWST Purification (Recirc) is On-Service, THEN secure the Refueling Water Purification Pump.
Version 56.0
10/08/10 10:21:11 FNP-1-SOP-2.3 NOTE:
- When blended flow concentration of 2000 PPM is required, the makeup system may not be able to deliver boric acid flow for 120 gpm total flow.
necessary, THEN the Total Flow may be set for < 120 gpm and the Boric Acid Flow rate adjusted proportionally to Total Flow.
- For blended flow set the Boric Acid Integrator to the desired amount of acid and the Total Flow Integrator to the desired amount of reactor makeup water PLUS the boric acid for the total amount.
- When making up to the RWST The boric acid flow rate should be such that it will finish first and the last thing in the line will be reactor makeup water.
- The Boric Acid and/or Total Flow Batch Integrators ONLY need to be verified when changed. This should be documented with an Autolog Entry.
- Flow rates greater than 60 gpm may cause BARS to trip due to high permeates pressure.
4.2.3.5 auto operation is desired THEN set FK-113 to the calculated flow rate obtained in step 4.2.3.2 or 4.2.3.3.
4.2.3.6 Set the boric acid batch integrator to the calculated quantity value obtained in step 4.2.3.2 or 4.2.3.3.
- For boric acid only set the boric acid integrator to the desired value and RMW TO BLENDER Q1E21FCV1 l4B (Q1E21V345) should be taken to close to ensure that only acid flow is obtained.
- For reactor makeup water only set the boric acid integrator to 1.
4,2,3.7 j auto operation is desired THEN set FK-168 to the calculated flow rate obtained in step 4.2.3.2 or 4.2.3.3, 4.2.3.8 Set the total flow batch integrator to the calculated quantity value obtained in step 4.2.3.2 or 4.2.3.3.
- For boric acid only set the total flow integrator to 1 and RMW TO BLENDER Q1E21FCV1 14B (Q1E21V345) should be taken to close to ensure that only acid flow is obtained.
- For reactor makeup water only set the boric acid integrator to 1 and the total flow integrator to the desired value.
4.2.3.9 Position the MKUP MODE CONT SWITCH to STOP.
4.2.3.10 Position the MKUP MODE SEL SWITCH to MAN.
4.2.3.11 Open blender discharge to RWST valve 1-CVC-V8434 (Ni E2 1 V23 8).
Version 56.0
10/08/10 10:21:11 FNP- 1 -SOP-2.3 4.2.3.12 Open blender miscellaneous discharge isolation valve l-CVC-V-8432 (Q1E21V237).
4.2.3.13 Place MKUP TO CHG PUMP SUCTION HDR Q1E21FCV1 13B (Q1E21V337) in the CLOSED position.
4.2.3.14 Place MKUP TO VCT Q1E21FCV1 l4A (Q1E21V339) in the CLOSED position.
4.2.3.15 IF making up to the RWST is due to the depletion of boron by the BARS system and it is desired to make-up with boric acid only, THEN close RMW TO BLENDER valve Q1E21FCV114B (Q1E21V345).
NOTE: Makeup may be stopped at any time by positioning the MKUP MODE CONT SWITCH to STOP.
4.2.3.16 Position the MKUP MODE CONT SWITCH to START.
4.2.3.17 lB RMW PUMP is running and not required for current plant operations, THEN position the lB RMW PUMP switch in STOP.
NOTE: Steps 4.2.3.18 and 4.2.3.19 may be performed in either order and as required throughout the makeup evolution.
4.2.3.18 Adjust FK- 168 in manual as required to deliver the desired total flow as indicated on FI-168 or FTO 168 on IPC.
4.2.3.19 Adjust FK-1 13 in auto or manual as required to deliver the desired boric acid flow as indicated on Fl- 113 or FTO 113 onIPC.
4.2.3.20 IF desired to flush the acid from the line, THEN at the appropriate time to conclude the makeup with RMW only:
4.2.3.20.1 Verify RMW TO BLENDER valve Q1E21FCV114B (Q1E21V345) open.
4.2.3.20.2 Close BORIC ACID TO BLENDER valve Q1E21FCVI 13A (Q1E21V354)
Version 56.0
10/08/10 10:21:11 FNP- 1 -SOP-2.3 TABLE 1 NOMOGRAPH CORRECTION FACTORS Plant Conditions Correction Factor Pressure T (AVG) Pressurizer Level (K)
(psig) (°F) (See Note) 2235 547-570 Normal Operating 1.00 1600 500 No-Load 1.05 1200 450 No-Load 1.10 800 400 No-Load 1.16 400 350 No-Load 1.18 400 300 No-Load 1.20 400 300 Solid Water 1.35 400 200 No-Load 1.28 400 200 Solid Water 1.40 400 100 Solid Water 1.47 NOTE:CORRECTION FACTORS ARE APPLIED AS FOLLOWS:
(a) Boron Addition and Dilution Total Volume Nomographs V(Corrected) = K x Vomograph)
(b) Boron Addition and Dilution Rate Nomographs dc 1 dc (Corrected) = x (Nomograph) dt K dt Page 1 of 1 Version 56.0
10/08/10 10:21:11 FNP-1-SOP-2.3 FIGURE 1 RCS BORON 4% BORIC CONCENTRATION ACID FLOW (PPM) (GPM) 0 0.0 100 1.71 200 3.4 300 5.1 400 6.9 500 8.6 600 10.3 700 12.0 800 13.7 900 15.4 1000 17.1 1100 18.9 1200 20.6 1300 22.3 1400 24.0 1500 25.7 1600 27.4 1700 29.1 1800 30.9 1900 32.6 2000 34.3 2100 36.0 2200 37.7 2300 39.4 2400 41.1 2500 42.9 BLENDED FLOW BASED ON 120 GPM AUTO MAKEUP Page 1 of 3 Version 56.0
10/08/10 10:21:11 FNP-1-SOP-2.3 FIGURE 1 Coolant 4 wt. % / FK-113 Coolant 4 wt. % / FK-113 Coolant 4 wt. % / FK-113 Boron 7000 ppm Pot Set Boron 7000 ppm Pot Set Boron 7000 ppm Pot Set Conc Boric acid Point Conc Boric acid Point Conc Boric acid Point (ppm) flow (gpm) (ppm) flow (gprn) (ppm) flow (gpm) 10 0.17 0.04 510 8.74 2.19 1010 17.31 4.33 20 0,34 0.09 520 8.91 2.23 1020 17.49 4.37 30 0,51 0.13 530 9.09 2.27 1030 17.66 4.41 40 0.69 0.17 540 9.26 2.31 1040 17.83 4.46 50 0.86 0.21 550 9.43 2.36 1050 18.00 4.50 60 1.03 0.26 560 9.60 2.40 1060 18.17 4.54 70 1.20 0.30 570 9.77 2.44 1070 18.34 4.59 80 1.37 0.34 580 9.94 2.49 1080 18.51 4.63 90 1.54 0.39 590 10.11 2.53 1090 18.69 4.67 100 1.71 0.43 600 10.29 2.57 1100 18.86 4.71 110 1.89 0.47 610 10.46 2.61 1110 19.03 4.76 120 2.06 0.51 620 10.63 2.66 1120 19.20 4.80 130 2.23 0.56 630 10.80 2.70 1130 19.37 4.84 140 2.40 0.60 640 10.97 2.74 1140 19.54 4.89 150 2,57 0.64 650 11.14 2.79 1150 19.71 4.93 160 2.74 0.69 660 11.31 2.83 1160 19.89 4.97 170 2.91 0.73 670 11.49 2.87 1170 20.06 5.01 180 3.09 0.77 680 11.66 2.91 1180 20.23 5.06 190 3.26 0.81 690 11.83 2.96 1190 20.40 5.10 200 3.43 0.86 700 12.00 3.00 1200 20.57 5.14 210 3.60 0.90 710 12.17 3.04 1210 20.74 5.19 220 3.77 0.94 720 12.34 3.09 1220 20.91 5.23 230 3.94 0.99 730 12.51 3.13 1230 21.09 5.27 240 4.11 1.03 740 12.69 3.17 1240 21.26 5.31 250 4.29 1.07 750 12.86 3.21 1250 21.43 5.36 260 4.46 1.11 760 13.03 3.26 1260 21.60 5.40 270 4.63 1.16 770 13.20 3.30 1270 21.77 5.44 280 4.80 1.20 780 13.37 3.34 1280 21.94 5.49 290 4.97 1.24 790 13.54 3.39 1290 22.11 5.53 300 5.14 1.29 800 13.71 3.43 1300 22.29 5.57 310 5.31 1.33 810 13.89 3.47 1310 22.46 5.61 320 5.49 1.37 820 14.06 3.51 1320 22.63 5.66 330 5.66 1.41 830 14.23 3.56 1330 22.80 5.70 340 5.83 1.46 840 14.40 3.60 1340 22.97 5.74 350 6.00 1.50 850 14.57 3.64 1350 23.14 5.79 360 6.17 1.54 860 14.74 3.69 1360 23.31 5.83 370 6.34 1.59 870 14.91 3.73 1370 23.49 5.87 380 6.51 1.63 880 15.09 3.77 1380 23.66 5.91 390 6.69 1.67 890 15.26 3.81 1390 23.83 5.96 400 6.86 1.71 900 15.43 3.86 1400 24.00 6.00 410 7.03 1.76 910 15.60 3.90 1410 24.17 6.04 420 7.20 1.80 920 15.77 3.94 1420 24.34 6.09 430 7.37 1.84 930 15.94 3.99 1430 24.51 6.13 440 7.54 1.89 940 16.11 4.03 1440 24.69 6.17 450 7.71 1.93 950 16.29 4.07 1450 24.86 6.21 460 7.89 1.97 960 16.46 4.11 1460 25.03 6.26 470 8.06 2.01 970 16.63 4.16 1470 25.20 6.30 480 8.23 2.06 980 16.80 4.20 1480 25.37 6.34 490 8.40 2.10 990 16.97 4.24 1490 25.54 6.39 500 8.57 2.14 1000 17.14 4.29 1500 25.71 6.43 BLENDED FLOW BASED ON 120 GPM AUTO MAKEUP Page 2 of 3 Version 56.0
10/08/10 10:21:11 FNP-1-SOP-2.3 FIGURE 1 Coolant 4 wt. % I FK- 113 Coolant 4 wt. % / FK- 113 Coolant 4 wt. % / FK- 113 Boron 7000 ppm Pot Set Boron 7000 ppm Pot Set Boron 7000 ppm Pot Set Cone Boric acid Point Cone Boric acid Point Cone Boric acid Point (ppm) flow (gpm) (ppm) flow (gpm) (ppm) flow (gpm) 1510 25.89 6.47 1840 31.54 7.89 2170 37.20 9.30 1520 26.06 6.51 1850 31.71 7.93 2180 37.37 9.34 1530 26.23 6.56 1860 31.89 7.97 2190 37.54 9.39 1540 26.40 6.60 1870 32.06 8.01 2200 37.71 9.43 1550 26.57 6.64 1880 32.23 8.06 2210 37.89 9.47 1560 26.74 6.69 1890 32.40 8.10 2220 38.06 9.51 1570 26.91 6.73 1900 32.57 8.14 2230 38.23 9.56 1580 27.09 6.77 1910 32.74 8.19 2240 38.40 9.60 1590 27.26 6.81 1920 32.91 8.23 2250 38.57 9.64 1600 27.43 6.86 1930 33.09 8.27 2260 38.74 9.69 1610 27.60 6.90 1940 33.26 8.31 2270 38.91 9.73 1620 27.77 6.94 1950 33.43 8.36 2280 39.09 9.77 1630 27.94 6.99 1960 33.60 8.40 2290 39.26 9.81 1640 28.11 7.03 1970 33.77 8.44 2300 39.43 9.86 1650 28.29 7.07 1980 33.94 8.49 2310 39.60 9.90 1660 28.46 7.11 1990 34.11 8.53 2320 39.77 9.94 1670 28.63 7.16 2000 34.29 8.57 2330 39.94 9.99 1680 28.80 7.20 2010 34.46 8.61 2340 40.11 10.03 1690 28.97 7.24 2020 34.63 8.66 2350 40.29 10.07 1700 29.14 7.29 2030 34.80 8.70 2360 40.46 10.11 1710 29.31 7.33 2040 34.97 8.74 2370 40.63 10.16 1720 29.49 7.37 2050 35.14 8.79 2380 40.80 10.20 1730 29.66 7.41 2060 35.31 8.83 2390 40.97 10.24 1740 29.83 7.46 2070 35.49 8.87 2400 41.14 10.29 1750 30.00 7.50 2080 35.66 8.91 2410 41.31 10.33 1760 30.17 7.54 2090 35.83 8.96 2420 41.49 10.37 1770 30.34 7.59 2100 36.00 9.00 2430 41.66 10.41 1780 30.51 7.63 2110 36.17 9.04 2440 41.83 10.46 1790 30.69 7.67 2120 36.34 9.09 2450 42.00 10.50 1800 30.86 7.71 2130 36.51 9.13 2460 42.17 10.54 1810 31.03 7.76 2140 36.69 9.17 2470 42.34 10.59 1820 31.20 7.80 2150 36.86 9.21 2480 42.51 10.63 1830 31.37 7.84 2160 37.03 9.26 2490 42.69 10.67 2500 42.86 10.71 NOTES: Due to characteristics of the reactor makeup system piping, the maximum obtainable boric acid flow is less than 40 gpm.
The boric acid flow controller FK 113 should be set at no less than 4 gpm. Operation below this limit will result in unstable operation. Ref. step 3.15.
Numbers corresponding to boric acid flow approaching or greater than 40 gpm are useful only for calculating the boric acid flow corresponding to a blended flow of less than 120 gpm.
Example: 2500 ppm 42.9 gpm with a pot setting of 10.7 for a blended flow of 120 gpm.
2500 ppm 42.9/2 gpm with a pot setting of 10.7/2 for a blended flow of 120/2 gpin.
2500 ppm 21.45 gpin with a pot setting of 5.35 for a blended flow of 60 gpin.
BLENDED FLOW BASED ON 120 GPM AUTO MAKEUP Page 3 of 3 Version 56.0
10/08/10 10:21:11 FNP-1-SOP-2.3 FIGURE 2 r 600 t500 L soo 2500 H (70oo_Cf 2100 L
300 8.33 7000-C 200 I
0 2000 w
900
- C)
C)
C) 100 b90 1500 600 80 c_) 70 C)
C) C) 60 C)
C) 50 300 o 1000 I 30 150 [ 20 500 100 The mass, M, for the above formula can be obtained from the Boron/Dilution table for the appropriate RCS temp.
Figure 2. Boron Addition Refer to Table 1 for Correction Factors Page 1 of 1 Version 56.0
10/08/10 10:21:11 FNP-1-SOP-2.3 FIGURE 3 100 500 L0 300 35 30 27 I000 -
4 J 200 2t1
-o
(_)
= C) 21 (7000-C) dt M iso s
-J 0 a C). 1500 5 100 12 90 II 80 10 I I Ir C-.)
0-. L_QOO 70 11 8
60 L_
2500 L
30 L The mass, M, for the above formula the Boron/Dilution table for the can be obtained from appropriate RCS temp.
Figure 3. Soon Addition Rate Refer to Table 1 for Correction Factors Page 1 of 1 Version 56.0
10/08/10 10:21:11 FNP-1-SOP-2.3 FIGURE 4 tc V I
\
1 fc 50 I
50 60 100 80 I00 300 200 500 boo 10 15 500 20 30 3000 50 00
-boo boo 150 300 200! 10,000 500 2000 801000 3000 PP4 BORON DILUTION 50,000 PPM BORON 1 (C Cf)
IN COOLANT DILUTION
)
1 (C WATER GAL.
()
The mass, N, for the above formula can be obtained from the Boron/Dilution table for the appropriate RCS temp.
Fgure 4 oron Dfl&jtion Refer to Table 1 For Corrccori Factors Page 1 of 1 Version 56.0
10/08/1010:21:11 FNP-1-SOP-2.3 FIGURE 5 3000 500 2000 300 150 1500 200 1000 100 100 70 90 5O 80 500 500 CY t40 dt 70 30 60 20
[
IS 50 200 7
5 100 80 3 30 60 2 50 4O 20 COOLANT DILUflON RATE PP4/HR (dc/dt) IS PPM BORON DILUTOT4 WATER IM COOLM1T FLOW, GPM (c) (Y)
The mass, M, for the above formula can be obtained from the Boron/Dilution table for the appropriate RCS temp.
Fgure 5. Baron DilutTon Rate Refer o Table 1 for Correcto Factors Page 1 of 1 Version 56.0
FNP HLT-34 ADMIN Page 1 of 7 A.2 Adxnin e SRO only Equipment-Control ADMIN G2.241 TITLE: Determine Isolation Boundaries for a CCW Pump Check Valve.
EVALUATION LOCATION: LI SIMULATOR LICONTROL ROOM I1CLASSROOM PROJECTED TIME: 30 MN 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 performed after completion of the RO portion of this TASK. All conditions are given in the handout. The candidate should complete the Tagout listing first, then perform the Tech Spec evaluation. Both portions should be completed for the examinee to have completed this task.
- 3. Requiring the exarninee to acquire the required materials may or may not be included as part of the 1PM.
TASK STANDARD: Upon successful completion of this 1PM, 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 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-301-3
FNP HLT-34 ADMIN A2 SRO Page 2 of 7 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 peiformed are:
- a. Unit 1 is in Mode 4.
- b. lB CCW pump is aligned to B Train.
- c. IC CCW pump was shut down due to a large leak on Q1P17VOOIC, CCW PUMP 1C DISCHARGE CHECK VALVE.
- d. The 1C 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. V1O9C CLOSED V144C CLOSED (Sequence of isolation of these valves does not matter.
See Tag Out sheet)
FNP HLT-34 ADMIN A2 SRO Page 3 of 7 EVALUATION CHECKLIST RESULTS:
ELEMENTS: STANDARDS: (CIRCLE)
L Note to Evaluator: Steps 3 through 5 may be performed in any order.
- 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)
(QVOOI C) 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 satisf,i 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-34 ADMIN A.2 SRO Page 4 of 7 EVALUATION CHECKLIST RESULTS:
ELEMENTS: STANDARDS: (CIRCLE)
SRO PORTION BELOW
- 6. Evaluates Tech Specs Determines that an LCO exists for: S / U 3.7.7 Component Cooling Water (CCW) System CONDITION A One CCW train inoperable.
REQUIRED ACTION A. 1 -
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 A.2 SRO 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. I 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
- 1. FNP-1-SOP-23.OA, VER 10.0
- 2. D175002 SHEET I
- 3. NMP-AD-003, VER 13.0
- 4. NMP-AD-003-00I, 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
FNP HLT-34 ADMIN A.2 SRO Page 6 of 7 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 1C 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:
C)
NOTE 6 2:
Co 18 QV11 OE (Ff IAIN. FLOW ORIFICE BY PUMP MFGR L 6 HBC64 3/4 F
QVOO4C 18 HBC 157E 1D COMPONENT COOLING PUMP Q1P17PDO1CA QVO17B
,$QV11QF I 4eA%ffl# A
Southern Nuclear Operating Company I Nuclear I NMP-AD-003-F02 I SOUTHERNA COMPANY Management I Tagout Tag Listing Version 1.0 I I
I Form I Page 1 of 1 I LClearance: #: FOR TRAINING USE ONLY KEY I Tagout: #: HLT-34 NRC EXAM Tag Equipment Placement Restoration St 1 ii Num Type Eciuipment ID Verif Seq Configuration Venf Seq Configuration 1 Description/Location Notes Vetif Venf Notes Verif Verif 1C CCW PUMP DISCH ISO I CLOSED Qi P17VOO2C IC CCW PUMP CHEM MIXING ISO 2 CLOSED Q1P17V278C 1CCCWPUMPSUCTISO 3 DLOSED Q1P17V1O9C 1C CCW PUMP MINI-FLOW 4 CLOSED Q1P17V144C 1C CCW PUMP DISCH HDR DRN 5 OPEN Q1P17V281C 1CCCWPUMPDRN 6 OPEN Q1P17V157F 1CCCWPUMPDRN 7 OPEN Q1P17VI57E 1CCCWPUMPSUCTLINEVT 8 OPEN Qi P1 7V279C 1CCCWPUMPVT 9 OPEN Q1P17V156F 1CCCWPUMPVT 10 OPEN Q1P17V156C
FNPHLT-34ADMIN A.2SRO HANDOUT Pg 1 of 1 CONDITIONS When I tell you to begin, you are to DETERMFNE 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. IC CCW pump was shut down due to a large leak on Q1P17VOO1C, CCW PUMP 1C DISCHARGE CHECK VALVE.
- d. The 1C 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 Operating Company I Nuclear I NMP-AD-003-F02 1 I
SOUTHERNA COMPANY Management I Tagout Tag Listing Version 1.0 I ESY11d Form Page 1 of 1 I Clearance: #: FOR TRAINING USE ONLY Tagout: #: HLT-34 NRC EXAM Tag Equipment Placement Restoration Num Type Eciuirment ID Verif Seq Configuration 1st 2 Venf Seq Configuration 1 Description/Location Notes Veilf Verif Notes Verif Verf 1-DT- DT 1C COW MCB handswitch CV 1 STOP/AUTO BT HF 1 1- Qi P17HS33O7CA-A 30,000 1-DT- DT IC CCW Hot Shutdown Panel CV 2 REMOTE BT HF 1 1- Local/Remote Switch 30,001 Qi P1 7HS3307CC-A 1-DT- DT 10 CCW Pump 4160V breaker CV 3 RACKED OUT BT HF 11- Q1R15BKRDFO4 30,002
Southern Nuclear Operating Company Nuclear II NMP AD 003 F02 1 I SOUTHERNA I COMPANY Management Form I Tagout Tag Listing Version 1 O Page 1 of 1 1 I
Clearance: #: FOR TRAINING USE ONLY Tagout: #: HLT-34 NRC EXAM Tag Equipment Placement Restoration Num Type Equipment ID Verif Seq Configuration 1st Verif Seq Configuration 1 Description/Location Notes Verif Veilf Notes Verif Veril
I I / I I I (U ___I (o IRS 00011010] VENT 10301100.
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- 0. VALVE MAST REMAIN OPETA WHEN RAN NOT 40 USE
- 3. 0140 VALVE FORNTSIIED 101111 PWCMVSE ElMS.
ST D \1ST I l4 TED 4. REM P1 I0 ALE-END SEE 0100. 04150011 SHEETS 1112.
1
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- 7. REUEF VALVE WillS BE LTATSO AT LEVST 6 ABOVE THE TOP OP TIlE LOOP S1V. 11011010 OF LOOP SPIlL NOTE 0 0127110
/ OVEISI 2SV VIUST 0016140 VT LEAST V BALI/IT THU CONNECTION TO TIlE 111111 PIPE.
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VVIIUEI ft0WOR1/CE 0102 04 0TTIoT FOR PEIIP50IME AS POINT 0150111000 lINE 111110111 EOR HEAT EXTVANVRRSSIAE 60 HEAT ERE1VENVER II EA:O-:1 oi 1 12 1,1 LO;-
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I
- 10. ALL DRAINS MAE WOVPED 11H TIlL PORTHOLE RIO 413111 110 15 COIIPORTIVT CDCXJIS 51341161 DETBI P/MT e!40 1110114100 4 4_A (NTPITPEOA II) 10 IRE 6111100 TANK.
(SEAE SCAlER)
- 10. HVL 11110 AIlS SOLVE IIOIAER0 ATE PREFIXED BA OVISTA
/79(1 I 50I/ NRC 055 0/0216 I 0 I/O RED I TIEETW, HOCTI 2 HOD, OTP1T OR TIIPIY.
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5oop CO P0140111 000LI /5 15 T 2V2211 5S 0AOM 5
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L I/4.VF2Ti --
IA. VIEVE IS THROTTLED TO EDOS GRIT OTIS OERVEO.
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FNP HLT-34 ADMIN Page 1 of 5 A.2 Admin e RO inly Equipment Control ADMIN G22A1 TITLE: Determine Isolation Boundaries for a CCW Pump Check Valve.
EVALUATION LOCATION: LSIMULATOR LICONTROL ROOM IICLASSROOM PROJECTED TIME: 30 MIN SIMULATOR IC NUMBER: N/A L]ALTERNATE PATH LI TIME CRITICAL LIPRA JPM DIRECTIONS:
- 1. Initiation of task may be in group setting, evaluation performed individually upon completion.
2, Requiring the exarninee to acquire the required materials may or may not be included as part of theJPM.
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.
. Identifi the proper sequence of isolation.
Examinee:
Overall JPM Performance: Satisfactory 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-301-3
FNP HLT-34 ADMIN A.2 RO Page 2 of 5 CONDITIONS When I tell you to begin, you are to DETERMII4E 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. lC CCW pump was shut down due to a large leak on Q1P17VOO1C, CCW PUMP 1C DISCHARGE CHECK VALVE.
- d. The 1C 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 / 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 fiowpaths should be closed next. V1O9C CLOSED V144C CLOSED (Sequence of isolation of these valves does not matter.
See Tag Out sheet) j Note to Evaluator: Steps 3 through 5 may be performed in any order.
- 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).
FNP HLT-34 ADMIN A.2 RO 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
) 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 A.2 RO 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
- 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 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 QV28 1C 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.
COMMENTS:
C-)
NOTE 6 Co 18 QV11 MIN. FLOW ORIFICE BY PUMP MFGR. 1D L 4 HBD61 0 3/
0 a
F 18 HBC QV157E 1D COMPONENT CQOUNG PUMP Q1P17POO1CA QVO17B
ØQV1 1OF
Southern Nuclear Operating Company I Nuclear I NMP-ADOO3-FO2 I I
SOUTHERNA COMPANY Management I Tagout Tag Listing Version 1.0 I E&YrWr1d Form I Page 1 of 1 I Clearance: #: FOR TRAINING USE ONLY KEY Tagout: #: HLT-34 NRC EXAM Tag Equipment Placement Restoration Num Type Equipment ID Verif Seq Configuration l Veilf Seq Configuration 1 Description/Location Notes Verif Venf Notes Verif Vent 1C CCW PUMP DISCH ISO 1 CLOSED Qi P17VOO2C 1C CCW PUMP CHEM MIXING ISO 2 CLOSED Q1P17V278C 1CCCW PUMP SUCT ISO 3 DLOSED Q1P17V1O9C 1C CCW PUMP MINI-FLOW 4 CLOSED Q1P17V144C 1C CCW PUMP DISCH HDR DRN 5 OPEN QIP17V28IC 1CCCWPUMPDRN 6 OPEN Qi P17V157F 1C CCW PUMP DRN 7 OPEN Q1P17V157E 1CCCWPUMPSUCTLINEVT 8 OPEN Q1P17V279C 1CCCW PUMP VT 9 OPEN Q1P17V156F 1CCCWPUMPVT 10 OPEN Q1P17V156C
FNP HLT-34 ADMIN A.2 RO HANDOUT Page lofi 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. IC CCW pump was shut down due to a large leak on Q1PI7VOO1C, CCW PUMP 1C DISCHARGE CHECK VALVE.
- d. The 1C 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 Operating Company I
SOUTHERNA Management I Tagout Tag Listing N MPAD-OO3-FO2 Version 1.0 I I
COMPANY Form I Page 1 of 1 I Clearance: #: FOR TRAINING USE ONLY Tagout: #: HLT-34 NRC EXAM Tag Equipment Placement Restoration Num Type Eguipment ID Verif Seq Configuration st 1 nd 2
Verif Seq Configuration I Description/Location Notes f Verf Notes Verif Verif 1-DT- DT 10 COW MCB handswitch CV 1 STOP/AUTO BT HF 11- Qi P17HS3307CA-.A 30,000 1-DT- DT IC CCW Hot Shutdown Panel CV 2 REMOTE BT HF 1 1- Local/Remote Switch 30,001 Qi P1 7HS3307CC-A 1-DT- DT 10 CCW Pump 4160V breaker CV 3 RACKED OUT BT HF 11- Q1R15BKRDFO4 30,002
Southern Nuclear Operating Company I Nuclear I NMP-ADQO3-FQ2 I I
SOUTHERNA COMPANY
£rSrrWrId Management Form I Tagout Tag Listing Version 1 O Page 1 of 1 I
I Clearance: #: FOR TRAINING USE ONLY Tagout: #: HLT-34 NRC EXAM Tag Equipment Placement Restoration t
1 nd 2
Num Type Equipment ID Verif Seq Configuration Venf Seq Configuration 1 Description/Location Notes Venf Venf Notes Verif Verif
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FNP HLT-34 ADMIN Page 1 of 9 Ai Admn d RO/SiO Radiation Control ADMIN G2.3.4 TITLE: DETERMINE DRESSOUT REQUIREMENTS, TOTAL PROJECTED DOSE AND DETERMINE IF AN RCP OIL ADDITION CAN BE PERFORMED WITHOUT EXCEEDING ANY RADIOLOGICAL LIMITS.
EVALUATION LOCATION: LI SIMULATOR LICONTROL ROOM EICLASSROOM PROJECTED TIME: 20 M1N 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 review an RWP, Radiological Survey Map and perform the following for adding oil to the 2A RCP:
- Identify 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 D Unsatisfactory D Evaluator Comments (attach additional sheets if necessary)
EXAMINER:
Developer Billy Thornton Date: 2/9/201 1 NRC Approval SEE NUREG 1021 FORM ES-301-3
FNP HLT-34 ADMIN A.3 ROISRO Page 2 of 9 CONDITIONS When I tell you to begin, you are to DETERMINE DRESSOUT REQUIREMENTS, TOTAL PROJECTED DOSE AND DETERMINE IF AN 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 necessaiy 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 NEGLIGIBLE.
- 10. Using 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:
- 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.
INITIATING CUE: IF you have no questions, you may begin.
EVALUATION CHECKLIST RESULTS:
ELEMENTS: STANDARDS: (CIRCLE)
START TIME
FNP HLT-34 ADMIN A.3 ROISRO Page 3 of 9 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 mRem/ 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 A.3 ROISRO Page 40.9 EVALUATION CHECKLIST RESULTS:
ELEMENTS: STANDARDS: (CIRCLE)
- 3. Determine if any dose limits will be exceeded by Determines if allowable dose S / U performing the task. limits will be exceed:
Admin dose limit o 1855 mR <2000 mR.
RWP Task dose limit o 205 mR>200mR RWP Task dose rate limit o 390 mR/hr < 500 mR/hr Documents that the job can NOT be performed.
ANNUAL limit (2000 mR annually): 1650 accumulated) + 205 = 1855 niR {no range}
205 niR 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 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 A.3 RO/SRO Page 5 of 9 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 EOUIPMENT:
Calculator Containment Survey Maps 1 maps (2A RCP cubicle)
Containment RWP 11-9490 (For Training USE ONLY)
Health Physics Manual, FNP-0-M-00l, 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 A.3 RO/SRO Page 6 of 9 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
FNP HLT-34 ADMIN A.3 RO/SRO HANDOUT Pglofl CONDITIONS When I tell you to begin, you are to DETERMINE DRESSOUT REQUIREMENTS, TOTAL PROJECTED DOSE AND DETERMINE IF AN 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 NEGLIGIBLE.
- 10. Using 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:
- 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.
HuGEST 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:
Plant Farley RditIOIIj 11-9490 Work Permit FOR TRAINING USE ONLY Activities by Operations in support of the U2 EMERGENT CONTAINMENT L iRY to include work in Job High Radiation Areas and other work classified as Medium Risk INSIDE THE BIOWALL. CAUTION:
Descriplion This RWP cannot be used for entries into Alpha Level 3 Areas.
Location U2 CONTAINMENT HP Coverage Authorization Briefing 5/112011 611P011 CONTINUOUS INDIVIDUAL INDIVIDUAL Job Supv. G. Ohmstede Radiological Conditions TASKS AIRBORNE LEVELS: LESS THAN 4 DAC HOURS PER DAD Alarms ENTRY Description Raten CONTAMINATION: < 500,000 DPM/IOOCM2 BETA GAMMA, CTMT ACTIVITIES (NON HIGH RAD LESS THAN ALPHA LEVEL 3 AREAS) 50 100 RAD LEVELS: LESS < 1.0 REM/HR CTMT ACTIVITIES (HIGH RAD AREAS)
Dosimetry TLD and DAD Protective Clothing Requirements AS NOTED IN INSTRUCTIONS BELOW Respirators NOT REQUIRED/NOT ALLOWED
. ...s RWP involves work identified as Radiologically Risk Significant activities.
/0 entries allowed inside the 105 Missile Barrier >15% Power. Entry inside the 105 Missile Barrier following Rx Trip and/or at a Power levels of approval of both the ED and the Health Physics Supenisor.
1 workers must receive an Initial RWP Briefing prior to using this RWP for the FIRST time.
to commencing work, individuals will receive a High Rad briefing for every posted High Radiation Area to be entered.
DAD alarm values may be adjusted by a SNC HP ANSI 3.1 or higher qualified individual based on expected conditions but can not exceed the limits for this RWP, and requires Health Physics Supervisors permission.
n exposure on this RWP is expected to be <5 Rem/hr Whole Body and/or <500 mRem/Worker/entry, then Stay time Calculation Sheets are not Stay times will be controlled by DADs and Neutron exposure limits.
Technician providing job coverage shall ensure Neutron calculation worksheets (DOS form 933) are completed for entries made in a Neutron idiation area.
r to entry ensure each worker has an adequate exposure margin. Account for any accumulated Neutron Exposure.
exceeding the Accumulated Dose Alarm, worker(s) shall exit the RCA. Upon receipt of the Dose Rate Alarm, back out of the area until the sics.
5 rnonitong Neutron Dose rates and exposure. Uhe Technician shall periodically intbrn the workers of their n exposure and have the group exit the area prior to reaching 90 mRem Neutron. Maximum Neutron Dose Rate is 450 mrenviiour.
essout requirements for areas>50,000 dpm/lOOcm2 beta/gamma: Double coveralls or equivalent, hood, booties,two sets rubber shoecovers. and sets of ploves.
)ressout requirements for areas 50,000 dpmll00cm2 beta/gamma: Single coveralls or equivalent, hood, booties, one set rubber shoecovers. and one FOR TRAINING USE ONLY 5/1/2011 12:00:00AM by NRC Prepared NRC EXAM TEAM APPROVED EXAM WRITER
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HLT-34 ADMIN JPM A.4 SRO Page 1 of 28 A.4 Admin e SRO only - Emergency Plan ADMIN G2.4.44 TITLE: Provide an updated Protective Action Recommendation (PAR).
EVALUATION LOCATION: L SIMULATOR LICONTROL ROOM ICLASSROOM PROJECTED TIME: 15 MIN SIMULATOR IC NUMBER: N/A
- 1. This task can be conducted individually or in a group setting in which all the necessary references are available.
- 2. Provide the candidate the HANDOUT page and a copy of Message Number 001 to allow for familiarization with the task for the event in progress. Since this is a Time Critical task, allow the candidate time to review and understand the task.
- 3. When the candidate understands his task, provide the candidate a copy of the partially prepared Message Number 002 (partially prepared requiring the candidate to complete line 5) and the procedure NMP-EP-112, and allow him to begin. This starts the time critical time.
- 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 1PM, 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-34 ADMIN JPM A.4 SRO Page 2 of 28 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# FG 1; 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 Contaimnent.
- c. FRP-H.l, 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 <5 R Thyroid CDE
- 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-l 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.
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 A.4 SRO Page 3 of 28 EVALUATION CHECKLIST RESULTS:
ELEMENTS: STANDARDS: (CIRCLE)
- 2. Attachment 5 step 2: S / U Records 045 in the PAR 2 Records the 15 minute average wind direction section for Wind direction.
from for the selected PAR.
- 3. Attachment 1 step A.3: S / U And ATTACHMENT 5 Step 3. Identifies zones A, BS, C5 and P5 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.
- 4. Attachment 1 step A.4: S / U And ATTACHMENT 5 step 3 & CAUTION DOCUMENTS on ATTACHMENTS zones A, B5, Utilizes ATTACHMENT 5 to document CS, P5, J5 and KS are the previously affected ZONES ui currently ZONES to be evacuated.
affected zones.
NOTE: the same zones from IDENTIFIES on ATTACHMENTS the following message #001 are included in ZONES are affected: addition to the ones identified for the current wind direction (J5 &
A KS).
BS C5 D5 JS KS S. Attachment 1 step A.S: S / U And ATTACHMENT 5 DOCUMENTS ON IJNE S of ENN Form message #002 On the ENN Form for the selected PAR:
- Select block S.B and record the Evacuate Select block 5.B and records on zones OR select block 5.C and record the line SB: zones A, B5, CS, D5, J5 Shelter zones and K5.
- Select block S.D
- IF PAR 4 is selected, THEN additionally select Select block S.D.
block 5 .E Other and provide Affected Sectors and To Miles CRITICAL TIME STOP
HLT-34 ADMIN JPM A.4 SRO Page 4 of 28 EVALUATION CHECKLIST RESULTS:
ELEMENTS: STANDARDS: (CIRCLE) j Terminate when all elements of the task have been completed.
I CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk (*) before the element number.
GENERAL
REFERENCES:
- 1. NMPEP-1 12, V 1.0
- 2. NMP-EP-1 10, V1.0
- 2. KA: G2.4.44 SRO (4.4)
GENERAL TOOLS AND EQUIPMENT:
NMP-EP-l 12 IIITIAL NOTIFICATION message #00 1.
Partially completed INITIAL NOTIFICATION message #002.
HLT-34 ADMIN JPM A.4 SRO Page 5 of 28 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 Not critical: this task will be performed to document wind direction on a PAR WORKSHEET, but the critical actions of this task will be to use the information to properly evaluate PARS.
3 Not critical: this task will be performed to properly assess the new PAR evacuation zones, and will be documented on a PAR WORKSHEET, but the critical actions of this task will be to use this information to properly complete the Emergency Notification Form.
4 Not critical: this task will be performed to properly assess and document the new PAR evacuation zones along with the previous evacuation zones, and will be documented on a PAR WORKSHEET, but the critical actions of this task will be to use this information to properly complete the Emergency Notification Form 5 Critical: Task completion, Required to properly document the PARs on line 5 of the Emergency Notification Form. This form would be transmitted to the EMAs of Alabama and Georgia, and is the official document. All other documents are worksheets used to determine the information to be provided to the EMAs, COMMENTS:
NUCLEAR POWER PL1NT EMERGENCY NOTIFICATION FORM
- 1. DRILL A11JAL EVENT IANSWER KEY MESSAGE# 2
- 2. INITIAL *FOLLOWUP NOTIFICATION: TIME DATE I I AUTHENTICATION #
- 3. SITE: Farley Nuclear Plant Confirmation Phone # (334 ) 814-4662
- 4. EMERGENCY ØUNUSUAL EVENT ALERT SITE 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 A, B5, C5, D5, K5, J5 SHELTER Advise Remainder of EPZ to Monitor Local RadioITV Stations)Tone Alert Radios for Additional Information and Consider the use of KI (potassium iodide) in accordance with State plans and policy.
IJ OTHER 6, EMERGENCY RELEASE: ØNone Is Occurring QHas Occurred
- 7. RELEASE SIGNIFICANCE: GNot applicable Within normal operating limits Above normal operating limits Under Evaluation
- 8. EVENT PROGNOSIS: lmproving *Stable Degrading
- 9. METEOROLOGICAL DATA: Wind Direction from 45 degrees* Wind Speed 4.5 rnph
(* May not be available for Initial Notifications)
Precipitation NONE
- Stability Class*
EJ EJ i::::i i:
- i:i i:i
- 10. DECLARATION jJ TERMINATION Time Date I I
- 11. AFFECTED UNIT(S):
- 12. Unit Status: Ui 0 % Power Shutdown at: Time 90 mins ago Date 5 / today / 11 (Unaffected Unit(s) Status Not Required tor inta t
Notifications) U2 100 % 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: Evated ØMixed Ground UNlTS:Ci Ci/sec iiCiIsec MAGNITUDE: Noble Gases: lodines: Particulates: Other:
FORM:ØAirborne Start Time: Date: i Stop Time: Date I I Liquid Start Time: Date: I Stop Time: Date I I
- 15. PROJECTION PARAMETERS: Projection Period: Hours Estimated Release Duration: Hours Projection performed: Time Date
Site boundary 2 Miles 5 Miles 10 Miles
- 17. APPROVED BY:
Title:
Time: Date:
NOTIFIED BY: RECEIVED BY: Time: Date: I I (To be completed by receiving organizaiton)
HLT-34 ADMIN JPM A.4 SRO 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# FG 1; FGI: 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.l, 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 <5 R Thyroid CDE
- 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- 112, 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.
NUCLEAR POWER PLANT EMERGENCY NOTIFICATION FORM
- 1. DRILL ØACTUAL EVENT -
MESSAGE # I
- 2. *INITIAL FOLLOW-UP NO11FICATI ON: TIME 20 mins ago DATE 5 / today / 11 AUTHENTICATION #
- 3. SITE: Farley Nuclear Plant Confirmation Phone # (334 ) 814-4662
- 4. EMERGENCY ØUNUSUAL EVENT ALERT SITE 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 A, B5, 05, J5, K5 J 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.
E OTHER
- 3. EMERGENCY RELEASE: None Is Occurring CHas Occurred
- 7. RELEASE SIGNIFICANCE: ØNot applicable Within normal operating limits *Above normal operating limits SUnder Evaluation
- 8. EVENT PROGNOSIS: ØlmProving Stable Degrading
- 9. METEOROLOGICAL DATA: Wind Direction from 335 degrees Wind Speed 3.4 mph*
(* May not be available for Initial
- Precipitation NONE Stability Class*
Notifications) i:i El El El
- 10. DECLARATION TERMINATION Time 30 mins ago Date 5 / today! 11 11.
12.
AFFECTED UNIT(S):
Unit Status:
- Ui 0 % Power Shutdown at: Time 60 mins ago Date 5 / today! 11 (Unaffected Unit(s) Status Not Required tor Initial Notifications) U2 % Power Shutdown at: Time Date I El
- 13. REMARKS:
FOLLOW-UP INFORMATION (Lines 14 through 16 Not Required for Initial Notifications)
EMERGENCY RELEASE DATA. NOT REQUIRED IF LINE GA IS SELECTED.
- 14. RELEASE CHARACTERIZATION: TYPE: ElElevated ElMixed ElGround UNITS: ElCi ElIJCi/sec ElCi/sec MAGNITUDE: Noble Gases: lodines: Particulates: Other:
FORM:ElAirborne StartTime: Date: / / StopTime: Date I I Liquid Start Time: Date: / / Stop Time: Date / I
- 15. PROJECTION PARAMETERS: Projection Period: Hours Estimated Release Duration: Hours Projection performed: Time Date / I
Site boundary 2 Miles 5 Miles 10 Miles
- 17. APPROVED BY: W. T. Door
Title:
Emergency Director Time: 25minsago Date: S/today /
NOTIFIED BY: J. T. Kelso RECEIVED BY: Time: Date: I /
(To be completed by receiving organizaiton)
Southern Nuclear Operating Company 5OOTHERN EmrgenGy Implementing
[ Protective Action Recommendations NMP-EP-412 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) OR ground level release (PWR).
- 3. Use the applicable Site Specific PAR table (Table 1 or 2) to determine the affected zones.
I CAUTION: I 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] JTone 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 Kl (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 [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!
ENN Line 5 [D] Tone Alert Radios. Consider the use of KI (Potassium Iodide) in PAR 4 accordance with State Plans and Policy ENN Line 5 [E] Evacuate Affected Sectors to OTHER Approval:
Emergency Director DatelTime Printed: 12/1/2010
NUCLEAR POWER PLANT EMERGENCY NOTIFICATION FORM
- 1. cYRILL AGTUAL EVEI\ff MSSAd ft 2 -
- 2. EINITIAL FOLLOW-UP NOTIFICATION: TIME DATE / / AUTHENTICATION #
- 3. SITE: Farley Nuclear Plant Confirmation Phone # (334 >814-4662
- 4. EMERGENCY ØUNUSUAL EVENT DALERT 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 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: GNone Is Occurring Has Occurred
- 7. RELEASE SIGNIFICANCE: ØNot applicable Within normal operating limits Above normal operating limits Under Evaluation
- 8. EVENT PROGNOSIS: Ølmproving Stable Degrading
- 9. METEOROLOGICAL DATA: Wind Direction from 45 degrees* Wind Speed 4.5 mph*
(* May not be available for Initial Notifications)
Precipitation NONE
- Stability Class*
El EJ EJ El EEJ i:i
- 10. DECLARATION TERMINATION Time Date
- 11. AFFECTED UNIT(S):
fJ
- 12. Unit Status: Ui 0 % Power Shutdown at: Time 90 mins ago Date 5 I today / 11 (Unaffected Unt(s) Status Not Nequired for India Notifications) U2 100 % Power Shutdown at: Time Date
- 13. REMARKS:
FOLLOW-UP INFORMATION (Lines 14 through 16 Not Required for Initial Notificatiolisi EMERGENCY RELEASE DATA. NOT REQUIRED IF LINE 6A IS SELECTED.
- 14. RELEASE CHARACTERIZATION: TYPE: Elevated Mixed Ground UNITS:ECi Ci/sec ElhiCi/sec MAGNITUDE: Noble Gases: Iodines: Particulates: Other:
FORM:Airborne StartTime: Date: I I StopTime: Date I /
Liquid Start Time: Date: / I Stop Time: Date I I
- 15. PROJECTION PARAMETERS: Projection Period: Hours Estimated Release Duration: Hours Projection performed: Time Date I I
Site boundary 2 Miles 5 Miles 10 Miles
- 17. APPROVED BY:
Title:
Time: Date: I NOTIFIED BY: RECEIVED BY: Time: Date: I /
(To be completed by receiving organizaiton)
Southern Nuclear Operatrnq Company Emergency NMP-EP-112 SOUA Implementing Protective Action Recommendations Version 1.0 Procedure Page 1 of 18 Procedure Owner: Chris Boone / Fleet Emergency Preparedness Manager I Corporate (Print: Name / Title / Site)
Approved By: Original signed by Christopher E. Boone on 09/24/2010 (Peer Team Champion/Procedure Owners Signature / 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 VogUe 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 Operating Company Emergency NMP-EP-112 50UT4 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
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 Corn pany Emergency NMP-EP-1 12 QUTHLRN rmplementing Protective Actidn Recommendations Version 1 .O Procedure Page 4 of 18 1.0 PURPOSE This procedure provides guidelines for determining Protective Action Recommendations (PARs) which will be communicated to offsite authorities during a General Emergency.
PARs are provided as an input to the protective action decision making process for the development of protective action orders. Protective action orders are communicated to the general public by offsite authorities to avoid or reduce the exposure incurred from an accident condition that results in a significant radiological effluent release or has the potential for a release based on degraded plant conditions.
2.0 APPLICABILITY Protective actions are recommended to offsite authorities to avoid or reduce the radiological exposure that may be incurred by the public from an accident condition that results in a significant radiological effluent release or has the potential for a release based on degraded plant conditions.
This procedure is performed, as required, during drills, exercises, and declared emergencies following declaration of a General Emergency. Attachments 2, 3, and 4 are sitespecific. Non-applicable site attachments may be removed and discarded to ensure usage of the correct site-specific attachment.
3.0 REFERENCES
3.1 NRC IN 83-28, Protective Actions Based on Plant Conditions 3.2 EPA-400-R-92-001, 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 2003-12, Clarification of NRC Guidance for Modifying Protective Actions 3.6 NUREG-0654/FEMA REP 1, Supplement 3 3.7 NRC RIS 2004-13, Consideration of Sheltering in Licensees Range of Protective Action Recommendations, August 2, 2004 3.8 NRC RIS 2004-13, Supplement 1, Consideration of Sheltering in Licensees Range of Protective Action Recommendations, Dated Aug. 2004, March 10, 2005 3.9 NRC RIS 2005-08, Endorsement of NEI Guidance Range of Protective Actions for Nuclear Power Plant Incidents, June 6, 2005 Printed: 12/1/2010
Southern Nuclear Operating Company Emergency I NMPEP1I2 1
I i
COMPANY Implementing Procedure [ Protective Action ecommendations Version 1.0 Page 5 of 18 I 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: 12/1/2010
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: 12/1/20 10
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.
6.55 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 2 Evacuate to 2 miles and 5 mile downwind zones
- PAR 3 Evacuate to 5 miles and 10 mile downwind zones
- 3. For PAR 1, 2, and 3, determine the affected zones using Site specific Table
- 1. An electronic program may also be used.
NOTE: Once conditions requiring a PAR change are available, PARs should be developed as soon as possible. (The expectation for development is 15 minutes after the change in conditions.)
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 5.0 and record the Shelter zones
- Select block 5.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-l 12 5QUTHRN Implementing - Protective Action Recommendations Version 1.0 Procedure Page 10 of 18 Continuing Activity Attachment 1 (Page 2 of 3)
Action CheckNst for PAR Development (Cont)
B. SUPPLEMENTAL ACTIONS Please Check
- 1. Continue assessment actions applying applicable Precautions & limitations.
- 2. H 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.
For PAR 4, determine the affected sectors using Site specific Table 2. The following considerations apply when developing PARs beyond 10 miles:
- IF 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, jf 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. IF conditions requiring PAR I 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 SeUTHF Implementing Protective Action Recommendations Version 1.0
,EINY Procedure Page 11 of 18 Attachment 1, Flowchart (Page 3 of 3)
Has a Z1UFF RELEAS.
neral Emergenc V In Progress or Been PAR1 Been Declared YES Tenninated That Is > YES SHELTER NProjected to Exceed/V 0 2 mile radius And downwind to 5 miles NO NO Advise Remainder of EPZ to Monitor Local CONTINUE s a Known Radio/TV Stations!
ASSESSMENT or Plant Event TARs for Additional
<K Underway Making N>-YES*
L Return to START Evacuation Information Consider the use of KI PAR2 in accordance with EVACUATE State plans and policy NO 0 2 mile radius And downwind to Refer to site specific 5 miles Table 1 or computer program for affected Advise Remainder of e Conditions Make zones
-YES*
EPZ to Monitor Local Evacuation Radio/TV Stations! Dangerous CONTINUE TARs for Additional tDoKn0 ASSESSMENT Information Return to START NO Consider the use of KJ in accordance with State plans and policy PAR3
%ave Doses EVACUATE Beyond the SBN. 0 5 mile radius Refer to site specific -
Table 1 or computer 0 NO < Been Projected to >YES+ And downwind to Exceed 10 miles program for affected PAGs zones Advise Remainder of EPZ to Monitor Local Radio/TV Stations!
TARs for Additional Information Have Doses Consider the use of K]
CONTINUE Beyond 10 Miles in accordance with ASSESSMENT NO Been Projected to State plans and policy Return to START Exceed PAGs* Refer to site specific Table 1 or computer program for affected YES zones
-f----
PAR4 Evaluate the Need for PARs *PAG5 Beyond 10 Miles Refer to
- 1000 mREM TEDE or Table 2
- 5000 rnREM Thyroid CDE Printed: 12/1/2010
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- Emergency I NMR-EP-1 12 I
I SOUTHERN COMPANY Implementing I Protective Action Recommendations Version 1.0 Procedure I 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 WIND DIRECTION FROM (degrees) AFFECTED SECTORS N, >349-11 H, J, K NNE, >11 34 J, K, L NE, >3456 K,L,M ENE, >5679 L,M,N E, >79-101 M,N,P ESE, >101 124 N,P,Q SE, >124-146 P,Q,R SSE, >146 169 - Q,R,A S, >169 191
- R,A,B SSW, >191 -214 A,B,C SW, >214-236 B,C,D WSW, >236-259 C,D,E W, >259281 D, F, F WNW, >281 304 F, 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 I Emergency I NMP-EP-112 I I
I 5OUTHERN COMPANY Implementing Procedure II Protective Action Recommendations Version 1.0 Page 15 of 18 I
I 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 SECTORS N, >349-11 H, J, K NNE,>1l34 J,K,L NE,>3456 K,L,M ENE, >56 79 L, M, N E,>79-1O1 M,N,P ESE, >101 124 N, P, Q SE.>124-146 P,Q,R SSE, >146 - 169 Q, R, A S,>169-191 R,A,B SSW,>191 -214 A,B,C SW, >214-236 B,C,D WSW. >236-259 C. D. E W, >259 281 D, E, F WNW, >281 304 E, F, G NW,>304-326 F,G,H NNW. >326 - 349 G, H, J Printed: 12/112010
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Southern Nuclear Operating Company I SOUTHERN Emrgoncy Implementing I I NMPEP412 I Protective Action Recommendations Version 1.0 I COMPANY Procedure Page 17 of 18 Attachment 4 Table 2 PLANT VOGTLE GUIDANCE FOR PARS BEYOND THE 10 MILE EPZ
- 1. Calculate the Evacuation Distance by determining the maximum Projected Distance where MIDAS dose projections exceed PAGs and adding 5 miles to the projected distance.
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 SECTORS N, >349-11 H, J, K NNE, >1134 J, K, L NE, >3456 K,L,M ENE, >5679 L,M,N E, >79-1 01 M,N,P ESE,>101124 N,P,Q SE, >124-146 P,Q,R SSE, >146 169 - Q,R,A S >169 191- R,A,B SSW, >191 -214 A,B,C SW, >214-236 B,C,D WSW, >236-259 C,D,E W, >259 281 D, F, F WNW, >281 304 F, F, G NW, >304 326 - F, G, H NNW, >326 349 - G, H, J Printed: 12/1/2010
Southern Nuclear Operating Company
. 4 EmrgnGy - NMP-EP-112 SOUTHERN2 Implementing Protective Action Recommendations Version 1.0 V 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) OR 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:
e Select block 5.B and record the Evacuate zones OR select block 5.C and record the Shelter zones
- Select block 5.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 A Advise remainder of EPZ to Monitor Local Radio/TV Stations P R 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] JTone 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 [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!
ENN Line 5 [D] Tone Alert Radios. Consider the use of KI (Potassium Iodide) in PAR 4 accordance with State Plans and Policy ENN Line 5 [E] Evacuate Affected Sectors to OTHER Approval:
Emergency Director DatelTime Printed: 2l1I2O1 0