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| number = ML091480123
| number = ML091480123
| issue date = 05/28/2009
| issue date = 05/28/2009
| title = Farley Initial Exam 2008-301 Draft Administrative JPMs
| title = Initial Exam 2008-301 Draft Administrative JPMs
| author name =  
| author name =  
| author affiliation = NRC/RGN-II
| author affiliation = NRC/RGN-II
Line 15: Line 15:


=Text=
=Text=
{{#Wiki_filter:( HL T-32 ADMIN exam A.1.1 RD Page 1 of 6 A.I.IRO Conduct Of Operations ADMIN 006AI.02
{{#Wiki_filter:}}
* RO TITLE: Determine required quantity of Boric Acid solution and Reactor Makeup water and integrator settings for makeup to the RWST. TASK STANDARD:
Determine the required quantity of Boric Acid and Reactor Makeup water to restore RWST level at the current Boric Acid Concentration, and correctly determine the setting of the Reactor Makeup system integrators and the potentiometer setting for the Boric Acid Flow controller.
PROGRAM APPLICABLE:
SOT SOCT OLT --1L LOCT __ ACCEPTABLEEVALUATIONMETHOD:
SIMULATE DISCUSS EVALUATION LOCATION:
SIMULATOR CONTROL ROOM --.2L CLASSROOM PROJECTED TIME: 20 MIN SIMULATOR IC NUMBER: N/A ALTERNATE PATH TIME CRITICAL PRA __ Examinee:
Overall JPM Performance:
Satisfactory 0 Unsatisfactory 0 Evaluator Comments (attach additional sheets if necessary)
EXAMINER:
________________
_
HLT-32 ADMIN exam A.1.1 RD Page 2 of 6 CONDITIONS When I tell you to begin, you are to determine RWST Makeup quantity, Boric acid concentration, and integrator setting for make up to the RWST per FNP-I-SOP-2.3, Chemical And Volume Control System Reactor Makeup Control System, starting at Step 4.2.3.2 Makeup to Refueling Water Storage Tank (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. c. RWST Boron concentration is at 2400 ppm. d. On Service BAT concentration is 7500 ppm. e. RWST Purification (Recirc) is NOT on-service.
: f. The Reactivity Spreadsheet is not available.
: g. You are the extra plant operator and have been directed by the Shift Supervisor to perform SOP-2.3 steps 4.2.3.2 -4.2.3.6 to: 1. Determine the quantity of blended flow required to raise level in the RWST from 37.7 feet to 39.5 feet while maintaining the current RWST Boron Concentration.
: 2. Determine the integrator settings for:
* FIS 113, BORIC ACID BATCH INTEG
* FIS-168, TOTAL FLOW BATCH INTEG 3. Determine the potentiometer setting to makeup to the RWST at a reduced flow of 60 gpm total flow for:
* FK-113, BORIC ACID MKUP FLOW EVALUATION CHECKLIST ELEMENTS:
STANDARDS:
START TIME I NOTE: This is a classroom setting ADMIN JPM task. *1. Determines Gallons needed per RWST Tank
* Determines RWST Volume at curve 3IB is 22,378 gallons. 39.5 feet=491064 gals
* Determines RWST Volume at 491064 -468686 = 22378 37.7 feet=484848 gals
* Calculates total volume RESULTS: (CIRCLE) addition=
22378 gals S / U 491064 -468686 = 22378 gals [no tolerance:
whole numbers from a table]
HLT-32 ADMIN exam A.1, 1 RO Page 3 of 6 EVALUATION CHECKLIST RESULTS: ELEMENTS:
STANDARDS: (CIRCLE) *2. *3. NOTE: Determines Boric Acid amount from Figure Determines from Figure 1, SOP-1, SOP-2.3, for the current concentration of 2.3 ratio of Boric Acid amount to 2400 ppm. total amount from the ratio of Boric Acid flow to Total Flow. Then calculates total Boric Acid in gallons to obtain total 22,378 gals of blended solution at 2400 ppm:
* 7664-7672 gals Boric Acid Solution S / U PER FIG. 1 PAGE 1: 22378( 41.1) = 7664.465gals 120 PER FIG 1 PAGE 3: 2237s( 41.14) = 7671.924 gals 120 [tolerance:
7664.0-7672 based on using either page 1 or page 3 numbers and rounding to nearest whole number of 7664 or rounding up for conservative 7672 gals.] Determines the totalizer settings for Total Determines totalizer settings are: flow FIS-168, TOTAL FLOW BATCH
* FIS-168=22378 gals S I U INTEG and FIS-113, BORIC ACID
* FIS-I13=7664-7672 gals S/U BATCH INTEG: Based on Figure 1.
* In element 5, FK*113 pot setting* is critical, but the manual position of FIS*168 demand which corresponds to 60 gpm is not critical, since this controller would need to be adjusted while flow was present. There is no corresponding demand that will ensure 60 gpm flow prior to initiating flow and adjusting as necessary.
Examiner NOTE:
* In element 5, IF applicant desires to raise the setpoint above the minimum required, ask them what setpoint they are going to use and ensure it is greater than the minimum required.
HL T -32 ADMIN exam A.1.1 RO EVALUATION CHECKLIST ELEMENTS:
STANDARDS:
*4. Determines the Minimum Flow controller States that FK-168 will need to be potentiometer setting for FK -113, BORIC adjusted in manual to obtain 60 ACID MKUP FLOW for the 60 gpm Total gpm. flow directed by the Shift Supervisor at 2400 ppm Based on Figure 1, states that MINIMUM setting for FK -113 is Page 4 of 6 RESULTS: (CIRCLE) Pot setting of 10.29 according to Figure 1, SOP-2.3 5.145 pot setting*. S / U would correspond to 120 gpm total flow at 2400. Since the Boric Acid Flow Controller
[Tolerance of 5.14 to 5.15 based on pot only goes to 10.0, the total flow must be the accuracy of the pot indication reduced to less than 120 gpm within the which is Y2 the smallest increment capacity of the system. The Shift Supervisor of 0.02. The procedure directs has directed 60 gpm total flow (12012=60) initiating more boric acid flow than in the initial conditions, and the boric acid necessary to ensure the boric acid flow for 120 gpm total flow must be divided flow totalizer reaches the setpoint by 2, and the pot setting must be divided by and stops Boric Acid Flow prior to 2. FK-168 will need to be adjusted in the Total Flow totalizer reaching manual to obtain 60 gpm. its setpoint.
This flushes the Boric Acid from the lines and delivers it Per Fig 1: all to the RWST. There is no 10.29/2=5.145 Boric Acid FK-l13 pot setting procedural requirement to limit the boric acid flow to a specified maximum amount.] 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.
HL T-32 ADMIN exam A.1.1 RO GENERAL
 
==REFERENCES:==
: 1. FNP-1-S0P-2.3 Version 44.0 2. FNP-1-ARP-1.5 EG4, Version 49.0 3. KIA: G2.006A1.02 RO 3.0 SRO 3.6 GENERAL TOOLS AND EQUIPMENT:
Provide: 1. FNP-1-S0P-2.3, Version 44.0 2. Curves 31A & 31B 3. Calculator (or applicant may supply their own calculator)
COMMENTS:
Page 5 of 6 A.1 .1 RO ( 1 Page) HANDOUT CONDITIONS When I tell you to begin, you are to determine RWST Makeup quantity, Boric acid concentration, and integrator setting for make up to the RWST per FNP-l-SOP-2.3, Chemical And Volume Control System Reactor Makeup Control System, starting at Step 4.2.3.2 Makeup to Refueling Water Storage Tank (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. c. RWST Boron concentration is at 2400 ppm. d. On Service BAT concentration is 7500 ppm. e. RWST Purification (Recirc) is NOT on-service.
: f. The Reactivity Spreadsheet is not available.
: g. You are the extra plant operator and have been directed by the Shift Supervisor to perform SOP-2.3 steps 4.2.3.2 -4.2.3.6 to: 1. Determine the quantity of blended flow required to raise level in the RWST from 37.7 feet to 39.5 feet while maintaining the current RWST Boron Concentration.
: 2. Determine the integrator settings for:
* FIS 113, BORIC ACID BATCH INTEG
* FIS-168, TOTAL FLOW BATCH INTEG 3. Determine the potentiometer setting to makeup to the RWST at a reduced flow of 60 gpm total flow for:
* FK-113, BORIC ACID MKUP FLOW 600000 PCB-1-VOLII-CRV31A i Refueling Water Storage Tank Capadly Q1F16T501
: Capadly (Gal) vs. Level (Ft) 500000 --!------Revision 3.0 February 4, 2005 JSJ i 400000 .2 , Approved:
1422--(' '2-1-<'5 ___ ,_ -' ES anager Date ii 300000 u [ c:J 200000 --t--------"-------
.-. -.-----------,---,----
I I -_! _______ .., ___ -;-o 100000 . : .. -.. -.. ---.-._-_.-
..... -. o o 5 10 15 20 25 30 Indicated Level (ft. H20) 35 40 45 Unit i Voh)!tif}
H Curve 31 i$ ,ilM;"',,,,,;!,,,,,, Wa0&#xa3;I" lank Cap(T!1C1ty Q'lFHlT501 T
vo1w,l*! .'" $091'12 T4)(';hnicfll Bit.H!lcifica'tloH SR ;].ti/t.2 li! rntni.tTlurtl oooteined l:l.of@loo w_r vbi.lJrnfJ of 4\,11,{)OO 
( ( 04/07/08 13:33:13 1 T FARLEY NUCLEAR PLANT SYSTEM OPERATING PROCEDURE FNP-I-SOP-2.3 CHEMICAL AND VOLUME CONTROL SYSTEM REACTOR MAKEUP CONTROL SYSTEM FNP-I-SOP-2.3 March 7, 2008 Version 44.0 PROCEDURE USAGE REQUIREMENTS PER FNP-0-AP-6 SECTIONS Continuous Use ALL Reference Use Information Use Approved:
J. L. Hunter (for) Operations Manager Date Issued 04/04/2008 S A F E T Y R E L A T E D 04/07108 13:33:13 FNP-1-S0P-2.3 TABLE OF CONTENTS Procedure Contains Number of Pages Body ........................................................
42 Table 1 ......................................................
1 Figure 1 .....................................................
3 Figure 2 .....................................................
1 Figure 3 .....................................................
1 Figure 4 .....................................................
1 Figure 5 .....................................................
1 Figure 6 .....................................................
1 Appendix A ...............................................
2 Appendix B ...............................................
2 Appendix C ...............................................
2 Appendix D ...............................................
2 ( Page 1 of 1 Version 44.0 04/07/08 13:33:13 1.0 Purpose I 1 FARLEY NUCLEAR PLANT UNIT 1 SYSTEM OPERATING PROCEDURE SOP-2.3 CHEMICAL AND VOLUME CONTROL SYSTEM REACTOR MAKEUP CONTROL SYSTEM FNP-I-S0P-2.3 This procedure provides Initial Conditions, Precautions and Limitations, and Instructions for operation of the Reactor Makeup Control System. Instructions are included in the following sections:
4.1 Automatic Makeup 4.2 Manual Makeup 4.2.1 Makeup to Top of Volume Control Tank 4.2.2 Makeup to Charging Pumps Suction Header 4.2.3 Makeup to Refueling Water Storage Tank (RWST) 4.2.4 Makeup to Recycle Holdup Tanks (RHT) 4.2.5 Makeup to SFP Through Temporary Connection 4.3 Boration 4.4 Dilution 4.5 Combined Boration 1 Dilution 4.6 Verify Reactor Makeup Control System Aligned for Auto Makeup 4.7 Large Volume Boration ofRCS Appendix A Operation of the Chemical and Volume Control System Reactor Makeup Control System with the Makeup Mode Control Switch Inoperable Appendix B Operator Aid for Boration and Dilution Appendix C Operator Aid for Repetitive Boration and Dilution Appendix D Operation of the Chemical and Volume Control System Reactor Makeup Control System with FIS 168 Total Flow Batch Integrator Unreliable  Version 44.0 04/07/08 13:33:13 FNP-I-S0P-2.3 2.0 Initial Conditions 2.1 The chemical and volume control system valves and electrical distribution systems are aligned per System checklist FNP-I-S0P-2.1A, CHEMICAL AND VOLUME CONTROL SYSTEM, with exceptions noted. 2.2 At least one RCP must be running prior to changing the boron concentration in the RCS. (SOER 94-02) (Section 3.0, Precaution and Limitation include additional clarification for this restriction).
2.3 Reactor makeup water is available to the reactor makeup control system per FNP-I-S0P-4.0, REACTOR MAKEUP WATER SYSTEM, if the operation being performed requires reactor makeup water. 2.4 Boric acid is available to the reactor makeup control system per FNP-I-S0P-2.6, CHEMICAL AND VOLUME CONTROL SYSTEM BORIC ACID SYSTEM, if the operation being performed requires boric acid. 3.0 Precautions and Limitations 3.1 The reactor makeup control system should be in automatic and adjusted to supply makeup equal in boron concentration to reactor coolant system concentration, except during reactor coolant system boration or dilution operations, or malfunctions of automatic control. 3.1.1 FK-168 is the MIA station used to control RMW to the blender flow control valve (FCV-114B).
If the MIA station is in AUTO, then the Makeup Mode Selector Switch determines the origin of the set point as follows:
* With the Mode Selector Switch in AUTO, the set point is 120 gpm. The position ofFCV-114B is determined by the difference between actual total flow and an internal set point of 120 gpm.
* With the Mode Selector Switch in MAN, DIL, or ALT DIL, the set point is determined by the potentiometer position. (AI-2005205348) 3.1.2 FK-113 is the MIA station used to control boric acid flow to the blender flow control valve (FCV -113A). When the makeup mode selector switch is in AUTO, FK-I13 (MIA station) will only control FCV-I13A automatically during periods of an AUTO makeup. Once the VCT level reaches 40 percent, the MIA station will shift to manual control. This maintains FK -113 output at the valve demand required for the desired blended boron concentration as determined by MIA station potentiometer setting based on total flow of 120 gpm. FK-I13 should not routinely be left in AUTO since the output will continue to integrate up with no system flow. This would delay the valve response to an auto makeup and result in an over boration. (AI2005205348)  Version 44.0 04/07/08 13:33:13 FNP-1-S0P-2.3 3.2 Actuation of the VeT LVL HI-LO annunciator (DF3) indicates a malfunction or improper operation of the reactor makeup control system. 3.3 The boron concentration in the pressurizer should not be less than that in the ReS loops by more than 50 ppm. Following or during a 5 ppm change of boron concentration in the ReS, the pressurizer spray must be operated to equalize the concentration throughout the system. Automatic operation of the spray should be initiated by manual operation of the pressurizer heaters when there is a steam bubble in the pressurizer.
3.4 Observe the effects of changing Res boron concentration in terms of resulting control rod motion, changes in Tavg, or SIR count rate. Stop boron concentration change operations and take corrective action if control rod motion is excessive or in the wrong direction, or Tave changes without subsequent rod motion. 3.5 WHEN the reactor is in the source range, THEN positive reactivity additions must only be made by one controlled method at a time. 3.6 The flow rate through the reactor coolant system shall be determined to be greater than 3000 gpm prior to the start of and at least once per hour during a dilution of the ReS by verifying at least one Rep is running. NOTE: The following step is intended to prevent the occurrence of dilute pockets of Reactor coolant due to inadequate mixing while in shutdown conditions.
This could occur if the RHR system is the sole source of ReS flow and a boration is made to reach the required shutdown margin (or refueling) boron concentration.
3.7 During shutdown operations, at least one Rep must be running prior to changing the ReS boron concentration unless directed to borate the ReS by any abnormal or emergency operating procedure.
IF the ReS and PRZR boron concentration have been sampled with a Rep running, and verified adequate for refueling and/or shutdown margin, THEN filling or normal makeup to the ReS with water greater than or equal to the refueling and/or shutdown margin concentration is not applicable to this requirement.
IF a boration is required to obtain the required boron concentration, AND no Rep is running, THEN the Shift Supervisor should consider alternate sampling methods to verify boron concentration requirements are satisfied throughout the Res. 3.8 Both units' boric acid blenders should not be supplied with reactor makeup water simultaneously if SOP-4.0 Appendix 2 is in effect. 3.9 Simultaneous running of both RMW pumps can cause one pump to operate near shutoff head condition, which produces abnormal thrust bearing loading and could lead to pre-mature bearing failure. Simultaneous running of both pumps should be minimized. (IR 1-96-062)  Version 44.0 04/07/08 13:33:13 T 1 FNP-1-S0P-2.3 3.10 ZAS injection will result in a continuous RCS dilution by as much as 1.7 gallons per hour, which could result in a rise in TAVG ifnot compensated for by boration, rod insertion, or increasing fission product poison inventory.
3.11 During periods of repetitive boration evolutions, to minimize the number of start/stop cycles on the boric acid pump, the handswitch may be placed in START and allowed to return to AUTO to maintain the boric acid pump running. WHEN it is no longer desired to maintain the boric acid pump running continuously, THEN place the handswitch in STOP and return to AUTO. 3.12 Large batch makeups during power operations to the VCT or Charging pump suction, especially early in core life, can result in unintended reactor power changes. The reactivity affects should be considered when planning batch size. Small batches should be used at any time in core life. (CR2004106233)
Large makeups can also cause seal injection temperature transients which can reduce RCP #1 seal leak off to a point at which seal damage occurs. (CR 2006104054) 3.13 The following list provides precautions and limitations related to VCT pressure reductions and gas accumulation in idle charging pump suctions.
* VCT pressure reductions::::
7 psig can result in gas dissolution sufficient to create idle charging pump suction voiding.
* Any VCT pressure reduction should be :s 5 psig in 4 hours to preclude void formation in charging pump suction piping.
* Pressure reduction rates exceeding preceding limitation should be documented by Condition Report.
* Idle Charging pump suctions should be vented when VCT pressure reduction rate has exceeded preceding limit. Version 44.0 04/07108 13:33:13 FNP-I-S0P-2.3 4.0 Instructions 4.1 Automatic Makeup 4.1.1 Determine the existing RCS boron concentration by sample analysis or from an estimate based on the previous sample. NOTE: ZAS injection will result in a continuous RCS dilution by as much as 1.7 gallons per hour causing the auto makeup to be inadequately set. A slightly higher set point may be required to maintain TAVG. 4.1.2 Verify the following:
4.1.2.1 4.1.2.2 Verify BORIC ACID MKUP FLOW controller FK 113 set up per the following:
A) In Manual B) Potentiometer is set to obtain a makeup value having a boron concentration equal to RCS boron concentration.
The setting is obtained from one of the following: (AI2005205348)
* Reactivity Briefing Sheet
* Figure 1 Verify FK-168 PRI WTR MKUP FLOW controller in Auto. 4.1.3 Position the MKUP MODE CONT SWITCH to STOP. 4.1.4 Position the MKUP MODE SEL SWITCH to AUTO. NOTE: Automatic makeup may be stopped at any time by placing the MKUP MODE CONT SWITCH to STOP. 4.1.5 Position the MKUP MODE CONT SWITCH to START. 4.1.6 IF IB RMW PUMP is running and is not required for current plant conditions, THEN position the IB RMW PUMP handswitch to STOP. Version 44.0 04/07108 13:33:13 FNP-I-SOP-2.3 NOTE: Verify expected Reactivity changes by observing VCT level, Tavg, SR SUR, IR SUR, and Control Rod Motion. Stop the Make-Up System operation and take corrective action if any change is excessive or in the wrong direction.
4.1.7 Verify proper automatic operation of the reactor makeup control system as follows: 4.1.7.1 4.1.7.2 WHEN VCT level decreases to 20%, THEN verify that makeup begins by observing the following: (a) MKUP TO CHG PUMP SUCTION HDR QIE2IFCVI13B (QIE2IV337) open. (b) Boric acid flow on FI -113 and reactor makeup flow on FI-168 are at the pre-selected rates as displayed on MAKEUP FLOW TO CHG/VCT. (c) VCT level increasing.
WHEN VCT level increases to 40%, THEN verify that makeup stops by observing the following: (a) BORIC ACID TO BLENDER QIE21FCVI13A (Q IE21 V354) closed. (b) MKUP TO CHG PUMP SUCTION HDR QIE2IFCVI13B (QIE2IV337) closed. (c) RMW TO BLENDER QIE2lFCV114B (QIE2IV345) closed. (d) Boric acid flow on FI -113 and reactor makeup flow on FI-168 return to zero as displayed on MAKEUP FLOW TO CHG/VCT indicator. Version 44.0 04/07/08 13:33:13 T 1 FNP-1-S0P-2.3 4.2 NOTE: IF waste gas system is shutdown, THEN VeT level should be maintained such that VeT pressure is not lowered to the point where the pressure regulator will admit more Hz or Nz to the VeT. Repeatedly allowing pressure to drop to this point will eventually result in having to start up the waste gas system to remove excess VeT gas. In addition, VeT level changes should be limited to prevent excessive perturbation of the Rep seals. 4.2.1 to Top of Volume Control Tank 4.2.1.1 Verify the VCT capable of receiving makeup. 4.2.1.2 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
* Boron/Dilution Tables
* Nomographs  Version 44.0 04/07/08 13:33:13 T 1 FNP-1-S0P-2.3 NOTE:
* When making up to the VCT use the flow rate from figure 1 or the reactivity briefing sheet.
* Flow rates may be adjusted using the controllers in manual or automatic.
* The boric acid flow should not be through the top of the VCT to keep the nozzle from clogging.
* 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".
* The Boric Acid and/or Total Flow Batch Integrators ONLY need to be verified when changed. This should be documented with an Autolog Entry. 4.2.1.3 Set the boric acid flow controllers and batch integrators to the calculated flow rate and quantity value obtained in step 4.2.1.2.
* For boric acid only set the boric acid integrator to the desired value and RMW TO BLENDER Q1E21FCVl14B (Q1E21 V345) should be taken to close to ensure that only acid flow is obtained.
* For reactor makeup water only set the boric acid integrator to o. 4.2.1.4 Set the reactor makeup water flow controllers and batch integrators to the calculated flow rate and quantity value obtained in step 4.2.1.2.
* For boric acid only set the total flow integrator to 0 and RMW TO BLENDER Q1E21FCVl14B (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 0 and the total flow integrator to the desired value. 4.2.1.5 IF necessary, THEN adjust LK-112 setpoint down to the pot setting corresponding to the desired VCT level to prevent compressing gas space. 4.2.1.6 Position the MKUP MODE CONT SWITCH to STOP. 4.2.1.7 Position the MKUP MODE SEL SWITCH to MAN. 4.2.1.8 Open MKUP TO VCT Q1E21FCV114A (Q1E21V339). Version 44.0 
( 04/07/08 13:33:13 1 T 1 FNP-I-S0P-2.3 NOTE:
* Makeup may be stopped at any time by positioning the MKUP MODE CONT SWITCH to STOP.
* Verify the expected Reactivity changes by observing VCT level, Tavg, SR SUR, IR SUR, and Control Rod Motion. Stop the Make-Up System operation and take corrective action if any change is excessive or in the wrong direction.
4.2.1.9 Position the MKUP MODE CONT SWITCH to START. 4.2.1.1 0 IF IB RMW PUMP is running and not required for current plant conditions, THEN position the IB RMW PUMP switch to STOP. 4.2.1.11 Verify makeup flows indicated on FI-I13 and FI-168 are at the pre-selected rates as displayed on MAKEUP FLOW TO CHGNCT indicator.
4.2.1.12 During or following a change of boron concentration of greater than 5 ppm in the RCS, the pressurizer spray must be operated to equalize the concentration throughout the system. Automatic operation of the spray should be initiated by manual operation of the pressurizer heaters when there is a steam bubble in the pressurizer.
4.2.1.13 Verify makeup automatically stops when batch integrator setpoints are reached by observing the following: ( a) Boric acid flow on FI -113 and reactor makeup flow on FI-168 return to zero as displayed on MAKEUP FLOW TO CHG/VCT indicator. (b) RMW TO BLENDER QIE21FCV114B (QIE21V345) closed. (c) BORIC ACID TO BLENDER QIE21FCVI13A (QIE21V354) closed. Version 44.0 04/07/08 13:33:13 FNP-I-S0P-2.3 4.2.1.13 Return MKUP TO VCT QIE21FCV114A (QIE21 V339) control switch to AUTO. 4.2.1.14 IF required THEN Return RMW TO BLENDER QIE21FCV114B (QIE21V345) control switch to AUTO. NOTE: The Boric Acid and/or Total Flow Batch Integrators ONLY need to be verified when changed. This should be documented with an Autolog Entry. NOTE: 4.2.1.15 Set the boric acid and/or total flow batch integrators to the required quantities as needed for normal system operation.
4.2.1.16 IF the boric acid and/or reactor makeup water flow controllers were adjusted, THEN perform the following: (a) Verify the BORIC ACID MKUP FLOW controller FK 113 is in the MAN position. (AI2005205348) (b) Restore FK-113 controller to the setpoint required for automatic makeup per step 4.1.2. (c) Verify FK-168 PRI WTR MKUP FLOW controller in Auto. 4.2.1.17 IF LK-112 was adjusted, THEN return LK-112 setpoint to that required for current conditions.
The following two steps are not required if operation in a mode other than automatic is required.
4.2.1.18 Position the MKUP MODE SEL SWITCH to AUTO. 4.2.1.19 Position the MKUP MODE CONT SWITCH to START. Version 44.0 04/07/08 13:33:13 FNP-I-SOP-2.3 4.2.2 Makeup to Charging Pumps Suction Header NOTE: IF waste gas system is shutdown, THEN VeT level should be maintained such that VeT pressure is not lowered to the point where the pressure regulator will admit more H2 or N2 to the VeT. Repeatedly allowing pressure to drop to this point will eventually result in having to start up the waste gas system to remove excess VeT gas. In addition, VeT level changes should be limited to prevent excessive perturbation of the Rep seals. 4.2.2.1 Verify VCT capable of receiving makeup. 4.2.2.2 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
* Boron/Dilution Tables
* N omographs  Version 44.0 04/07/08 13:33:13 FNP-I-S0P-2.3 NOTE:
* When making up to the VeT use the flow rate from figure lor the reactivity briefing sheet.
* Flow rates may be adjusted using the controllers in manual or automatic.
* 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 PL US the boric acid for the "total amount".
* The Boric Acid and/or Total Flow Batch Integrators ONLY need to be verified when changed. This should be documented with an Autolog Entry. 4.2.2.3 *
* 4.2.2.4 *
* 4.2.2.5 4.2.2.6 4.2.2.7 4.2.2.8 Set the boric acid flow controllers and batch integrators to the calculated flow rate and quantity value obtained in step 4.2.2.2. For boric acid only set the boric acid integrator to the desired value and RMW TO BLENDER QIE21FCV114B (QIE21 V345) should be taken to close to ensure that only acid flow is obtained.
For reactor makeup water only set the boric acid integrator to O. Set the reactor makeup water flow controllers and batch integrators to the calculated flow rate and quantity value obtained in step 4.2.2.2. For boric acid only set the total flow integrator to 0 and RMW TO BLENDER QIE21FCV114B (QIE21V345) should be taken to close to ensure that only acid flow is obtained.
For reactor makeup water only set the boric acid integrator to 0 and the total flow integrator to the desired value. IF necessary, THEN adjust LK-112 setpoint down to the pot setting corresponding to the desired VCT level to prevent compressmg gas space. Position MKUP MODE CONT SWITCH to STOP. Position the MKUP MODE SEL SWITCH to MAN Open MKUP TO CHG PUMP SUCTION HDR QIE21FCVl13B (QIE21 V337). Version 44.0 04/07/08 13:33:13 T 1 FNP-I-S0P-2.3 NOTE:
* Makeup may be stopped at any time by positioning the MKUP MODE CONT SWITCH to STOP.
* Verify the expected Reactivity changes by observing VCT level, Tavg, SR SUR, IR SUR, and Control Rod Motion. Stop the Make-Up System operation and take corrective action if any change is excessive or in the wrong direction.
4.2.2.9 Position MODE CONT SWITCH to START. 4.2.2.10 IF IB RMW PUMP is running and not required for current plant conditions, THEN position the IB RMW PUMP switch to STOP. 4.2.2.11 Verify boric acid flow on FI-I13 and reactor makeup flow on FI-168 are at the pre-selected rates as displayed on MAKEUP FLOW TO CHGNCT indicator.
4.2.2.12 During or following a change of boron concentration of greater than 5 ppm in the RCS, the pressurizer spray must be operated to equalize the concentration throughout the system. Automatic operation of the spray should be initiated by manual operation of the pressurizer heaters when there is a steam bubble in the pressurizer.
4.2.2.13 Verify makeup automatically stops when batch integrator setpoints are reached by observing the following: (a) Boric acid flow on FI-I13 and reactor makeup flow on FI-168 return to zero as displayed on MAKEUP FLOW TO CHGNCT indicator. (b) RMWTO BLENDERQIE21FCV114B (QIE21V345) closed. (c) BORIC ACID TO BLENDER QIE21FCVI13A (QIE21V354) closed. Version 44.0 
( 04/07/08 13:33:13 FNP-1-S0P-2.3 4.2.2.13 Return MKUP TO CHG PUMP SUCTION HDR Q1E21FCV113B (Q1E21 V337) control switch to AUTO. 4.2.2.14 IF required THEN Return RMW TO BLENDER Q1E21FCV114B (Q1E21 V345) control switch to AUTO. NOTE: The Boric Acid and/or Total Flow Batch Integrators ONLY need to be verified when changed. This should be documented with an Autolog Entry. NOTE: 4.2.2.15 Set the boric acid and/or total flow batch integrators to the required quantities as needed for normal system operation.
4.2.2.16 IF the boric acid and/or reactor makeup water flow controllers were adjusted, THEN perform the following: (a) Verify the BORIC ACID MKUP FLOW controller FK 113 is in the MAN position. (AI2005205348) (b) Restore FK-113 controller to the setpoint required for automatic makeup per step 4.1.2. (c) Verify FK-168 PRI WTR MKUP FLOW controller in Auto. 4.2.2.17 IF LK-112 was adjusted, THEN return LK-112 setpoint to that required for current conditions.
The following two steps are not required if operation in a mode other than automatic is required.
4.2.2.18 Position the MKUP MODE SEL SWITCH to AUTO. 4.2.2.19 Position the MKUP MODE CONT SWITCH to START. Version 44.0 04/07/08 13:33:13 FNP-I-S0P-2.3 4.2.3 Makeup to Refueling Water Storage Tank (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 ofthe 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 4.2.3.17 at an appropriate time prior to reaching the Total Flow Integrator setpoint.
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 44.0 04/07/08 13:33:13 4.2.3.3 4.2.3.4 FNP-l-SOP-2.3 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. To dilute the RWST: VA = CI -CF (VI) CF To borate the RWST: VA = CI -CF (VI) CF-CA To determine final boron concentration:
CF = rCI x VI] + rCA x V AJ 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 IF the RWST Purification (Recirc) is On-Service, THEN secure the Refueling Water Purification Pump. Version 44.0 04/07/08 13:33:13 1 1 FNP-1-S0P-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. IF necessary, THEN the Total Flow may be set for < 120 gpm and the Boric Acid Flow rate adjusted proportionally to Total Flow.
* Flow rates may be adjusted using the controllers in manual or automatic.
* 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. 4.2.3.5 Set the boric acid flow controllers and batch integrators to the calculated flow rate and 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 Q1E21FCV114B (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 O. 4.2.3.6 Set the reactor makeup water flow controllers and batch integrators to the calculated flow rate and quantity value obtained in step 4.2.3.2 or 4.2.3.3.
* For boric acid only set the total flow integrator to 0 and RMW TO BLENDER Q1E21FCV114B (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 0 and the total flow integrator to the desired value. 4.2.3.7 Position the MKUP MODE CONT SWITCH to STOP. 4.2.3.8 Position the MKUP MODE SEL SWITCH to MAN. Version 44.0 04/07/08 13:33:13 1 1 FNP-I-S0P-2.3 4.2.3.9 Open blender discharge to RWST valve 1-CVC-V-8434 (N1E21 V238). 4.2.3.10 Open blender miscellaneous discharge isolation valve 1-CVC-V-8432 (Q1E21V237).
4.2.3.11 Place MKUP TO CHG PUMP SUCTION HDR Q1E21FCVl13B (Q1E21 V337) in the CLOSED position.
4.2.3.12 Place MKUP TO VCT Q1E21FCV114A (Q1E21V339) in the CLOSED position.
4.2.3.13 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. 4.2.3.14 Position the MKUP MODE CONT SWITCH to START. 4.2.3.15 IF 1B RMW PUMP is running and not required for current plant operations, THEN position the 1B RMW PUMP switch in STOP. 4.2.3.16 Verify boric acid flow on FI-l13 and reactor makeup flow on FI -168 are at the pre-selected rates as displayed on MAKEUP FLOW TO CHGNCT indicator.
4.2.3.17 IF desired to flush the acid from the line, THEN at the appropriate time to conclude the makeup with RMW only: (a) Verify RMW TO BLENDER valve Q1E21FCVl14B (Q1E21V345) open. (b) Close BORIC ACID TO BLENDER valve Q1E21FCVl13A (QIE21V354)  Version 44.0 04/07/08 13:33:13 FNP-I-S0P-2.3 4.2.3 .18 Verify makeup automatically stops when batch integrator setpoints are reached by observing the following: ( a) Boric acid flow on FI -113 and reactor makeup flow on FI-168 return to zero as displayed on MAKEUP FLOW TO CHGNCT indicator. (b) RMW TO BLENDER valve QIE21FCV114B (QIE21 V345) closed IF in AUTO. (c) BORIC ACID TO BLENDER valve QIE21FCV113A (QIE21 V354) closed. 4.2.3.19 Close blender miscellaneous discharge isolation valve l-CVC-V-8432 (QIE21V237).
4.2.3.20 Close blender discharge to RWST valve l-CVC-V-8434 (NIE21 V238). 4.2.3.21 Place MKUP TO VCT QIE2lFCV114A (QIE21 V339) in AUTO. 4.2.3.22 Place MKUP TO CHG PUMP SUCTION HDR QIE21FCVI13B (QIE21V337) in AUTO. 4.2.3.23 Verify RMW TO BLENDER valve QIE21FCV114B (QIE21 V345) in AUTO. 4.2.3.24 Verify BORIC ACID TO BLENDER valve QIE21FCVI13A (QIE21V354) in AUTO. Version 44.0 04/07/08 13:33:13 FNP-1-S0P-2.3 NOTE: The Boric Acid and/or Total Flow Batch Integrators ONLY need to be verified when changed. This should be documented with an Autolog Entry. 4.2.3.25 Set the boric acid and/or total flow batch integrators to the required quantities as needed for normal system operation.
4.2.3.26 IF the boric acid and/or reactor makeup water flow controllers were adjusted, THEN perform the following: (a) Verify the BORIC ACID MKUP FLOW controller FK 113 is in the MAN position. (AI2005205348) (b) Restore FK -113 controller to the setpoint required for automatic makeup per step 4.1.2 (c) Verify FK -168 PRI WTR MKUP FLOW controller in Auto. NOTE: The following two steps are not required if operation in a mode other than automatic is required.
4.2.3.27 Position the MKUP MODE SEL SWITCH to AUTO. 4.2.3.28 Position the MKUP MODE CONT SWITCH to START. 4.2.3.29 IF the Refueling Water Purification Pump was secured in Step 4.2.3.4, THEN perform the following: (a) Start the RWP pump. (b) Throttle SFP purification outlet to RWST 1-SFP-V-8793B (N1G31V021B) to establish 100 gpm on the SFP demineralizer FI-654. 4.2.3.30 Independently verify Closed the following:
* Blender Miscellaneous Discharge Isolation valve 1-CVC-V-8432 (Q1E21V237).
* Blender Discharge To RWST valve 1-CVC-V-8434 (N1E21 V238). Version 44.0 04/07/08 13:33:13 1 T 1 FNP-I-S0P-2.3 4.2.4 Makeup to Recycle Holdup Tanks (RHT) NOTE: IF desired to flush the line of acid following makeup, THEN remember to perform step 4.2.4.18 at an appropriate time prior to reaching the Total Flow Integrator setpoint.
4.2.4.1 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 4.2.4.2 IF the final boron concentration in the RHT is going to differ from the initial, THEN use the following formulas or the reactivity briefing sheets to determine the amount of water and/or acid to be added. To dilute the RHT: VA = CI -CF (VI) CF To borate the RHT: VA = CI -CF (VI) CF-CA To use a blend: CB = (CFxVF)-(CIxVI)
VA Where: VA = Amt. of water and/or acid added to the RHT VI = Initial quantity in RHT VF = Final quantity in RHT CI = Initial boron concentration in RHT CF = Final boron concentration in RHT CA = Boron concentration in BAT CB = Boron concentration of blended flow (use Nomographs, Figure 1, OR Reactivity Briefmg Sheet to determine the amount of water and acid required)  Version 44.0 
( 04/07/08 13:33:13 1 T 1 FNP-1-S0P-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. IF necessary, THEN the Total Flow may be set for < 120 gpm and the Boric Acid Flow rate adjusted proportionally to Total Flow.
* Flow rates may be adjusted using the controllers in manual or automatic.
* 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 RHT 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. 4.2.4.3 Set the boric acid flow controllers and batch integrators to the calculated flow rate and quantity value obtained in step 4.2.4.1 or 4.2.4.2.
* F or boric acid only set the boric acid integrator to the desired value and RMW TO BLENDER Q1E21FCVl14B (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 O. 4.2.4.4 Set the reactor makeup water flow controllers and batch integrators to the calculated flow rate and quantity value obtained in step 4.2.4.1 or 4.2.4.2.
* For boric acid only set the total flow integrator to 0 and RMW TO BLENDER Q1E21FCVl14B (Q1E21 V345) should be taken to close to ensure that only acid flow is obtained.
* For reactor makeup water only set the boric acid integrator to 0 and the total flow integrator to the desired value. 4.2.4.5 Verify closed waste condensate pump discharge to RHT's 1-LWP-V-7229 (Q1G21V031) 4.2.4.6 Align RCDT discharge to WHT per the following:
A) Open RCDT Disch to WHT, 1-LWP-V-7137 (Q1G21V009)
(100' PPR). B) Close RCDT pump discharge to RHT iso, 1-CVC-V -8551 (Q1E21V315)
(121' PPR). Version 44.0 
( 04/07/08 13:33:13 4.2.4.7 T 1 FNP-1-S0P-2.3 Align the RHT that will be made up to on service AND secure the previous on service RHT per FNP-1-S0P-2.4, CHEMICAL AND VOLUME CONTROL SYSTEM BORON RECYCLE SYSTEM. 4.2.4.8 Place control switch for recycle evaporator feed demineralizer automatic bypass valve Q1E21TCV250 (Q1E21V361) to FILTER position. (The control switch is located on the liquid waste panel.) 4.2.4.9 Open blender discharge to RHT's valve 1-CVC-V -8553 (Q1E21V280).
4.2.4.10 Open blender miscellaneous discharge isolation valve 1-CVC-V-8432 (Q1E21V237).
4.2.4.11 Position the MKUP MODE CONT SWITCH to STOP. 4.2.4.12 Position the MKUP MODE SEL SWITCH to MAN. NOTE: Makeup may be stopped at any time by positioning the MKUP MODE CONT SWITCH to STOP. 4.2.4.13 Place MKUP TO CHG PUMP SUCTION HDR Q1E21FCV113B (Q1E21V337) in the CLOSED position.
4.2.4.14 Place MKUP TO VCT Q1E21FCV114A (Q1E21V339) in the CLOSED position.
4.2.4.15 Position the MKUP MODE CONT SWITCH to START. 4.2.4.16 IF 1B RMW PUMP is running and not required for current plant conditions, THEN place the 1B RMW PUMP handswitch to STOP. 4.2.4.17 Boric acid flow on FI-113 and reactor makeup flow on FI-168 are at the pre-selected rates as displayed on MAKEUP FLOW TO CHGNCT indicator.
4.2.4.18 IF desired to flush the acid from the line, THEN at the appropriate time to conclude the makeup with RMW only: (a) Verify RMW TO BLENDER valve QIE21FCV114B (QIE21 V345) open. (b) Close BORIC ACID TO BLENDER valve QIE21FCVl13A (Q1E21V354)  Version 44.0 
( ( 04/07/08 13:33:13 1 1 FNP-1-S0P-2.3 4.2.4.19 Verify makeup automatically stops when batch integrator setpoints are reached by observing that boric acid flow on FI-113 and reactor makeup flow on FI-168 return to zero as displayed on MAKEUP FLOW TO CHGNCT indicator.
4.2.4.20 Close blender miscellaneous discharge isolation valve I-CVC-V-8432 (Q1E2IV237).
4.2.4.21 Close blender discharge to RHT's valve 1-CVC-V-8553 (QIE21V280).
4.2.4.22 Place MKUP TO VCT Q1E21FCVl14A (Q1E21 V339) in AUTO. 4.2.4.23 Place MKUP TO CHG PUMP SUCTION HDR Q1E21FCV113B (Q1E21V337) in AUTO. 4.2.4.24 Verify BORIC ACID TO BLENDER valve Q1E21FCVl13A (Q1E2l V354) in AUTO. 4.2.4.25 IF required THEN Return RMW TO BLENDER Q1E21FCVl14B (Q1E2l V345) control switch to AUTO. NOTE: The Boric Acid and/or Total Flow Batch Integrators ONLY need to be verified when changed. This should be documented with an Autolog Entry. 4.2.4.26 Set the boric acid andlor total flow batch integrators to the required quantities as needed for normal system operation.
4.2.4.27 IF the boric acid andlor reactor makeup water flow controllers were adjusted, THEN perform the following: (a) Verify the BORIC ACID MKUP FLOW controller FK 113 is in the MAN position. (AI2005205348) (b) Restore controller FK -113 to the setpoint required for automatic makeup per step 4.1.2. (c) Verify FK-168 PRI WTR MKUP FLOW controller in Auto. Version 44.0 
( 04/07/08 13:33:13 1 FNP-l-SOP-2.3 NOTE: The following two steps are not required if operation in a mode other than automatic is required.
4.2.4.28 Position the MKUP MODE SEL SWITCH to AUTO. 4.2.4.29 Position the MKUP MODE CONT SWITCH to START. 4.2.4.30 Align RCDT discharge to RHT per the following:
* Open RCDT pump discharge to RHT l-CVC-V-855l (QlE2lV3l5)
(121 'PPR).
* Close RCDT disch to WHT l-LWP-V-7137 (QlG2lV009).
(100' PPR) 4.2.4.31 Position control switch for recycle evaporator feed demineralizer automatic bypass valve QlE2l TCV250 (QlE2l V36l) to the DEMIN position until red light is illuminated THEN place handswitch in AUTO position. (The control switch is located on the liquid waste panel.) 4.2.4.32 Remove batched up RHT from service and place another RHT on service IF required per FNP-l-SOP-2.4, CHEMICAL AND VOLUME CONTROL SYSTEM BORON RECYCLE SYSTEM. 4.2.4.33 Independently Verify the following:
* Verify MKUP TO VCT QlE2lFCV114A (QlE2lV339) in AUTO.
* Verify close blender discharge to RHT's valve I-CVC-V-8553 (QlE2IV280).
* Verify open RCDT pump discharge to RHT l-CVC-V-8551 (QIE2IV315)
(121'PPR).
* Verify close RCDT DISCH to WHT l-LWP-V-7137 (QIG21V009).
(100' PPR) Version 44.0 04/07/08 13:33:13 FNP-l-SOP-2.3 4.2.5 Makeup to SFP Through Temporary Connection NOTE: This procedure is intended for situations when normal makeup to the SFP is not available and should not be used for normal makeup to the SFP. IF desired to flush the line of acid following makeup, THEN remember to perform step 4.2.5.14 at an appropriate time prior to reaching the batch integrator setpoint.
4.2.5.1 4.2.5.2 Verify that the SFP is capable of receiving makeup. Verify blender miscellaneous discharge isolation valve l-CVC-V-8432 (QIE21V237) closed. NOTE: The following step will open a section of 2 inch diameter pipe approximately 40 feet long requiring a catch bag routed to the nearest equipment drain be rigged prior to commencing.
4.2.5.3 Remove blind flange from the temporary connection and install temporary hose routed to the SFP. 4.2.5.4 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 44.0 
( 04/07/08 13:33:13 FNP-I-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. IF necessary, THEN the Total Flow may be set for < 120 gpm and the Boric Acid Flow rate adjusted proportionally to Total Flow.
* Flow rates may be adjusted using the controllers in manual or automatic.
* 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 SFP 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. 4.2.5.5 *
* Set the boric acid flow controllers and batch integrators to the calculated flow rate and quantity value obtained in step 4.2.5.4. For boric acid only set the boric acid integrator to the desired value and RMW TO BLENDER QIE21FCV114B (Q1E21 V345) should be taken to close to ensure that only acid flow is obtained.
For reactor makeup water only set the boric acid integrator to O. 4.2.5.6 Set the reactor makeup water flow controllers and batch integrators to the calculated flow rate and quantity value obtained in step 4.2.5.4.
* For boric acid only set the total flow integrator to 0 and RMW TO BLENDER Q1E21FCV114B (Q1E21 V345) should be taken to close to ensure that only acid flow is obtained.
* For reactor makeup water only set the boric acid integrator to 0 and the total flow integrator to the desired value. 4.2.5.7 Position the MKUP MODE CONT SWITCH to STOP. 4.2.5.8 Position the MKUP MODE SEL SWITCH to MAN. 4.2.5.9 Open blender miscellaneous discharge isolation valve 1-CVC-V-8432 (Q1E21V237).
4.2.5.10 Place MKUP to CHG PUMP SUCTION HDR Q1E21FCV113B (Q1E21V337) in the CLOSED position.
4.2.5.11 Place MKUP to VCT Q1E21FCV114A (Q1E21 V339) in the CLOSED position. Version 44.0 
( 04/07/08 13:33:13 1 1 FNP-1-S0P-2.3 NOTE: Makeup may be stopped at any time by positioning the MKUP MODE CONT SWITCH to STOP. 4.2.5.12 Position the MKUP MODE CONT SWITCH to START. 4.2.5.13 IF 1B RMW PUMP is running and not required for current plant conditions, THEN position the 1B RMW PUMP handswitch to STOP. 4.2.5.14 Boric acid flow on FI-l13 and reactor makeup flow on FI-168 are at the pre-selected rates as displayed on MAKEUP FLOW TO CHGNCT indicator.
4.2.5.15 IF desired to flush the acid from the line, THEN at the appropriate time to conclude the makeup with RMW only: (a) Verify RMW TO BLENDER valve Q1E21FCVl14B (Q1E21 V345) open. (b) Close BORIC ACID TO BLENDER valve Q1E21FCVl13A (Q1E21 V354) 4.2.5.16 Verify makeup automatically stops when batch integrator setpoints are reached by observing the following: (a) Boric acid flow on FI -113 and reactor makeup flow on FI-168 return to zero as displayed on MAKEUP FLOW TO CHGNCT indicator. (b) RMW TO BLENDER Q1E21FCVl14B (Q1E21V345) closed. (c) BORIC ACID TO BLENDER Q1E21FCVl13A (Q1E21V354) closed. 4.2.5 .17 Close blender miscellaneous discharge isolation valve 1-CVC-V-8432 (Q1E21V237).
4.2.5.18 Place the following valve control switches to AUTO: (a) MKUP TO CHG PUMP SUCTION HDR Q1E21FCVl13B (Q1E21V337). (b) MKUP TO VCT Q1E21FCV114A (Q1E21V339).
4.2.5.19 Verify BORIC ACID TO BLENDER valve Q1E21FVl13A (Q1E21V354) in AUTO. Version 44.0 
( 04/07/08 13:33:13 1 T 1 FNP-l-SOP-2.3 4.2.5.20 IF required THEN Return RMW TO BLENDER Q1E21FCVl14B (Q1E2l V345) control switch to AUTO. NOTE: The Boric Acid and/or Total Flow Batch Integrators ONLY need to be verified when changed. This should be documented with an Autolog Entry. 4.2.5.21 Set the boric acid and/or total flow batch integrators to the required quantities as needed for normal system operation.
4.2.5.22 IF the boric acid and/or reactor makeup water flow controllers were adjusted, THEN perform the following: (a) Verify the BORIC ACID MKUP FLOW controller FK 113 is in the MAN position. (AI2005205348) (b) Restore controller FK-l13 to the setpoint required for automatic makeup per step 4.1.2. (c) Verify FK-168 PRI WTRMKUP FLOW controller in Auto. NOTE: The following two steps are not required if operation in a mode other than automatic is required.
4.2.5.23 Position the MKUP MODE SEL SWITCH to AUTO. 4.2.5.24 Position the MKUP MODE CONT SWITCH to START. 4.2.5.25 Remove the temporary hose from the temporary connection and install blind flange. 4.2.5.26 Independently Verify the following:
* Verify Closed blender miscellaneous discharge isolation valve l-CVC-V-8432 (QIE21V237).
* RMW TO BLENDER Q1E21FCVl14B (Q1E2l V345) in AUTO.
* BORIC ACID TO BLENDER Q1E21FCVI13A (Q1E21V354) in AUTO. Version 44.0 04/07/08 13:33:13 FNP-1-S0P-2.3 4.3 Boration NOTE: Appendix B, OPERATOR AID FOR BORATION AND DILUTION, may be used without referring to this procedure section under the following conditions:
* Routine boration for temperature control.
* Boration in response to an unplanned or unscheduled power change.
* Scheduled power changes. Figure 6 may be applied at the discretion of the SS when use of the emergency boration flowpath is desired.
*..
... . . .... 4.3.1 During or following a change of boron concentration of greater than 5 ppm in the RCS, the pressurizer spray must be operated to equalize the concentration throughout the system. Automatic operation of the spray should be initiated by manual operation of the pressurizer heaters when there is a steam bubble in the pressurizer.
4.3.2 Determine the existing Reactor Coolant boron concentration by sample analysis or from an estimate based on a previous sample. 4.3.3 Determine the magnitude of the boron concentration increase required from core physics curves or during normal operation, when compensating for xenon or core bumup, the magnitude may be estimated based on time in core life and previous experience.
4.3.4 Determine the volume of boric acid required for boration from the boron addition nomograph, Figure 2, from the borationldilution tables, Reactivity Briefing Sheet or from estimate based on time in core life and previous experience. Version 44.0 04/07/08 13:33:13 T 1 FNP-1-S0P-2.3 NOTE: IF waste gas system is shutdown, THEN VCT level should be maintained such that VCT pressure is not lowered to the point where the pressure regulator will admit more H2 or N2 to the VCT. Repeatedly allowing pressure to drop to this point will eventually result in having to start up the waste gas system to remove excess VCT gas. In addition, VCT level changes should be limited to prevent excessive perturbation of the RCP seals. 4.3.5 IF necessary, THEN adjust LTDN TO VCT FLOW LK 112 setpoint down to the pot setting corresponding to the desired VCT level to prevent compressing the gas space. NOTE: The boric acid flow required to achieve a desired boration rate may be determined from boron addition rate nomograph, Figure 3. 4.3.6 Position the MKUP MODE CONT SWITCH to STOP. 4.3.7 Position the MKUP MODE SEL SWITCH to BOR. NOTE: The Boric Acid and/or Total Flow Batch Integrators ONLY need to be verified when changed. This should be documented with an Autolog Entry. 4.3.8 Set the Boric Acid MKUP Flow Controller and Boric Acid Batch Integrator to the flowrate and quantity values obtained from step 4.3.3 and 4.3.4. NOTE:
* Boration may be stopped at any time by positioning the MKUP MODE CONT SWITCH to STOP.
* Verify the expected Reactivity changes by observing VCT level, Tavg, SR SUR, IR SUR, and Control Rod Motion. Stop the Make-Up System operation and take corrective action if any change is excessive or in the wrong direction.
4.3.9 Position the MKUP MODE CONT SWITCH to START. 4.3.10 Verify proper boration operation by observing the following:
4.3.11
* On service boric acid pump started.
* MKUP TO CHG PUMP SUCTION HDR Q1E21FCVl13B opens.
* BORIC ACID TO BLENDER Q1E21FCVl13A opens.
* Boric acid flow is displayed on FI-l13 MAKEUP FLOW TO CHGNCT. Verify that boration automatically stops when the boric acid batch integrator reaches its setpoint as follows:
* Boric acid flow returns to zero as displayed on FI -113 MAKEUP FLOW TO CHGNCT.
* MKUP TO CHG PUMP SUCTION HDR Q1E21FCVl13B closes.
* BORIC ACID TO BLENDER Q1E21FCVl13A closes. Version 44.0 04/07/08 13:33:13 FNP-I-S0P-2.3 NOTE: The following four steps are not required if operation in a mode other than automatic is preferred.
For example: when frequent borations are required because of changing core conditions it may be desirable to leave the reactor makeup system aligned for the current operational need and minimize system manipulation.
Use appendix C for guidance in repetitive borations.
4.3.12 Position the MKUP MODE SEL SWITCH to AUTO. 4.3.13 Position the MKUP MODE CaNT SWITCH to START. 4.3.14 IF the boric acid and/or reactor makeup water flow controllers were adjusted, THEN perform the following: (a) Verify the BORIC ACID MKUP FLOW controller FK 113 is in the MAN position. (AI2005205348) (b) Restore controller FK -113 to the setpoint required for automatic makeup per step 4.1.2. (c) Verify FK-168 PRI WTR MKUP FLOW controller in Auto. 4.3.15 IF LK 112 setpoint was adjusted per Step 4.3.5, THEN return setpoint to that required for current conditions.
4.4 Dilution NOTE:
* Appendix B, OPERATOR AID FOR BORATION AND DILUTION, may be used without referring to this procedure section under the following conditions:
a) Routine dilution for temperature control. b) Scheduled power changes.
* IF MKUP TO VCT Q1E21FCV114A is not operable, THEN Alternate Dilution is required in step 4.4.8. 4.4.1 During or following a change of boron concentration of greater than 5 ppm in the RCS, the pressurizer spray must be operated to equalize the concentration throughout the system. Automatic operation of the spray should be initiated by manual operation of the pressurizer heaters when there is a steam bubble in the pressurizer.
4.4.2 Determine the existing reactor coolant boron concentration by sample analysis, or from an estimate based on the previous sample. Version 44.0 04/07/08 13:33:13 I 1 FNP-1-S0P-2.3 4.4.3 Determine the magnitude of the boron concentration decrease required from core physics curves or during normal operation, when compensating for xenon or core bumup, the magnitude may be estimated based on time in core life and previous experience.
4.4.4 Determine the volume of reactor makeup water required for dilution from the dilution nomograph, Figure 4, from borationldilution tables, Reactivity Briefmg Sheet or from estimate based on time in core life and previous experience.
NOTE: IF waste gas system is shutdown, THEN VeT level should be maintained such that VeT pressure is not lowered to the point where the pressure regulator will admit more H2 or N2 to the VeT. Repeatedly allowing pressure to drop to this point will eventually result in having to start up the waste gas system to remove excess VeT gas. In addition, VeT level changes should be limited to prevent excessive perturbation of the Rep seals. 4.4.5 IF necessary, THEN adjust LTDN TO VCT FLOW LK 112 setpoint down to the pot setting corresponding to the desired VCT level to prevent compressing the gas space. NOTE:
* The dilution water flow required to achieve a desired dilution rate may be determined from boron dilution rate nomograph, Figure 5.
* The Boric Acid and/or Total Flow Batch Integrators ONLY need to be verified when changed. This should be documented with an Autolog Entry. 4.4.6 Set the PRI WTR MKUP FLOW (RMW) Controller and Total Flow Batch Integrator to the flow rate and quantity values obtained from step 4.4.3 and 4.4.4. 4.4.7 Position the MKUP MODE CONT SWITCH to STOP. Version 44.0 04/07108 13:33:13 I FNP-l-SOP-2.3 NOTE: The use ofthe ALT DIL MODE can affect the ability to control hydrogen concentration in the RCS. 4.4.8 Position the MKUP MODE SEL SWITCH to DIL or ALT DIL. 4.4.9 IF using the AL T DIL MODE AND it is desired to bypass the VCT and dilute straight to the charging pump suction, THEN place MKUP TO VCT valve Q1E21FCVll4A (QIE21 V339) in close. NOTE:
* Dilution may be stopped at any time by positioning the MKUP MODE CONT SWITCH to STOP
* Verify the expected Reactivity changes by observing VCT level, Tavg, SR SUR, IR SUR, and Control Rod Motion. Stop the Make-Up System operation and take corrective action if any change is excessive or in the wrong direction.
4.4.10 Position the MKUP MODE CONT SWITCH to START. 4.4.11 IF IB RMW PUMP is running and not required for current plant conditions, THEN position the IB RMW PUMP handswitch to STOP. 4.4.12 Verify dilution operation by observing the following:
* IF using ALT DIL, MAKEUP TO CHG PUMP SUCTION HDR Q1E21FCV113B opens.
* MKUP TO VCT Q1E21FCVl14A opens, unless bypassing VCT.
* RMW TO BLENDER Q1E21FCVl14B opens.
* Reactor makeup flow is displayed on FI-168 MAKEUP FLOW TO CHG/VCT. Version 44.0 04/07/08 13:33:13 4.4.13 FNP-1-S0P-2.3 Verify dilution automatically stops when the reactor makeup water batch integrator reaches its setpoint as follows:
* Reactor makeup flow returns to zero as displayed on FI-168 MAKEUP FLOW TO CHGNCT.
* MKUP TO VCT Q1E21FCVl14A closes.
* RMW TO BLENDER Q1E21FCVl14B closes.
* IF ALT DIL was used, THEN MAKEUP TO CHG PUMP SUCTION HDR Q1E21FCVl13B closes. 4.4.14 IF VCT bypassed per step 4.4.9, THEN place MKUP TO VCT valve Q1E21FCVl14A (Q1E21 V339) to AUTO. NOTE: The following three steps are not required if operation in a mode other than automatic is preferred.
For example: when frequent dilutions are required because of changing core conditions it may be desirable to leave the reactor makeup system aligned for the current operational need and minimize system manipulation.
Use appendix C for guidance in repetitive dilutions.
4.4.15 Position the MKUP MODE SEL SWITCH to AUTO. 4.4.16 Position the MKUP MODE CONT SWITCH to START. 4.4.17 IF LK 112 setpoint was adjusted per Step 4.4.5, THEN return setpoint to that required for current conditions. Version 44.0 04/07/08 13:33:13 FNP-1-S0P-2.3 4.5 Combined Boration 1 Dilution NOTE: Appendix B, OPERATOR AID FOR BORATION AND DILUTION, may be used without referring to this procedure section under the following conditions:
* Routine borationldilution for temperature control.
* Scheduled power changes. NOTE: Early in the core cycle it is necessary to borate to compensate for burnup of discreet poisons. It is also desirable to maintain the discharge line from the blender clear of acid. This procedure section is designed to accomplish this by borating and then immediately diluting to flush the acid into the charging pump suction. 4.5.1 Determine the volume of boric acid AND reactor makeup water required (to flush the line clear) based on Rx power, TA VG, Reactivity Briefing Sheet, reactivity change due to xenon, time in core life, and/or previous expenence.
NOTE: IF the waste gas system is shutdown, THEN VeT level should be maintained such that VeT pressure is not lowered to the point where the pressure regulator will admit more H2 or N2 to the VeT. Repeatedly allowing pressure to drop to this point will eventually result in having to start up the waste gas system to remove excess VeT gas. In addition, VeT level changes should be limited to prevent excessive perturbation of the Rep seals. 4.5.2 IF necessary, THEN adjust LTDN TO VCT FLOW LK 112 setpoint down to the pot setting corresponding to the desired VCT level to prevent compressing the gas space. 4.5.3 Position the MKUP MODE CaNT SWITCH to STOP. 4.5.4 Position the MKUP MODE SEL SWITCH to BaR. NOTE: The Boric Acid and/or Total Flow Batch Integrators ONLY need to be verified when changed. This should be documented with an Autolog Entry. 4.5.5 Set the Boric Acid Batch Integrator and Total Flow Batch Integrator to the quantities determined in step 4.5.1. 4.5.6 Set the Boric Acid Flow Controller to the desired flow rate. Version 44.0 
( 04/07/08 13:33:13 FNP-I-SOP-2.3 NOTE:
* Boration may be stopped at any time by positioning the MKUP MODE CONT SWITCH to STOP.
* Verify the expected Reactivity changes by observing VCT level, Tavg, SR SUR, IR SUR, and Control Rod Motion. Stop the Make-Up System operation and take corrective action if any change is excessive or in the wrong direction.
4.5.7 Position the MKUP MODE CONT SWITCH to START. 4.5.8 VerifY proper boration operation by observing the following:
4.5.9 4.5.10
* On service boric acid pump started.
* MKUP TO CHG PUMP SUCTION HDR QIE21FCVl13B opens.
* BORIC ACID TO BLENDER QIE21FCVl13A opens.
* Boric acid flow is displayed on FI-I13 MAKEUP FLOW TO CHG/VCT. VerifY that boration automatically stops when the boric acid batch integrator reaches its setpoint as follows:
* Boric acid flow returns to zero as displayed on FI-I13 MAKEUP FLOW TO CHGNCT.
* MKUP TO CHG PUMP SUCTION HDR QIE2IFCVI13B closes.
* BORIC ACID TO BLENDER QIE2IFCVI13A closes. Position the MKUP MODE CONT SWITCH to STOP. NOTE: The use ofthe ALT DIL MODE can affect the ability to control hydrogen concentration in the RCS. 4.5.11 Align the makeup system for flushing as follows:
* Position the MKUP MODE SEL SWITCH to AL T DIL.
* Place MKUP TO VCT valve QIE21FCVl14A (QIE21 V339) in close.
* Set the reactor makeup water flow controller to the desired flow rate. Version 44.0 04/07/08 13:33:13 FNP-I-S0P-2.3 NOTE:
* Boration may be stopped at any time by positioning the MKUP MODE CONT SWITCH to STOP.
* Verify the expected Reactivity changes by observing VCT level, Tavg, SR SUR, IR SUR, and Control Rod Motion. Stop the Make-Up System operation and take corrective action if any change is excessive or in the wrong direction.
4.5.12 Position the MKUP MODE CONT SWITCH to START. 4.5.13 IF IB RMW pump is running and not required for current plant conditions, THEN position the IB RMW PUMP handswitch to STOP. 4.5.14 VerifY proper dilution operation by observing the following:
* MAKEUP TO CHG PUMP SUCTION HDR Q lE21FCVI13B (QIE21V337) opens.
* Reactor makeup flow on FI -168 is at the pre-selected rate as displayed on MAKEUP FLOW TO CHGNCT indicator.
4.5.15 VerifY dilution automatically stops when the total flow batch integrator reaches its setpoint by observing the following:
* Reactor makeup flow on FI -168 returns to zero as displayed on MAKEUP FLOW TO CHGNCT indicator.
* MAKEUP TO CHG PUMP SUCTION HDR QIE21FCVI13B (QIE21V337) closed. Version 44.0 04/07/08 l3:33:l3 FNP-I-S0P-2.3 4.5.16 Place MKUP TO VCT valve QIE21FCV114A (QIE21V339) in AUTO. NOTE: The following four steps are not required if operation in a mode other than automatic is preferred.
4.5.17 Position the MKUP MODE SEL SWITCH to AUTO. 4.5.18 Position the MKUP MODE CONT SWITCH to START. 4.5.19 IF the boric acid and/or reactor makeup water flow controllers were adjusted, THEN perform the following: (a) Verify the BORIC ACID MKUP FLOW controller FK 113 is in the MAN position.(AI2005205348) (b) Restore controller FK -113 to the setpoint required for automatic makeup per step 4.1.2. (c) Verify FK-168 PRI WTR MKUP FLOW controller in Auto. 4.5.20 IF LK 112 setpoint was adjusted in step 4.5.2, THEN return setpoint to that required for current conditions. Version 44.0 04/07/08 13:33:13 FNP-1-S0P-2.3 4.6 Verify Reactor Makeup Control System Aligned for Auto Makeup 4.6.1 Determine the existing RCS boron concentration by sample analysis or from an estimate based on the previous sample. 4.6.2 Verify the following:
4.6.2.1 4.6.2.2 BORIC ACID MKUP FLOW controller FK 113 is in the MAN position and the Potentiometer is set to the value obtained from the blended flow nomographs, Figure 1, or reactivity briefing sheet to obtain makeup value having a boron concentration equal to RCS boron concentration. (AI2005205348)
Verify FK-168 PRI WTR MKUP FLOW controller in Auto. 4.6.3 Position the MKUP MODE CONT SWITCH to STOP. 4.6.4 Verify MKUP TO CHG PUMP SUCTION HDR Q1E21FCVl13B closed with handswitch in the AUTO position.
4.6.5 Verify BORIC ACID TO BLENDER Q1E21FCVl13A closed with handswitch in the AUTO position.
4.6.6 Verify MKUP TO VCT Q1E21FCVl14A closed with handswitch in the AUTO position.
4.6.7 Verify RMW TO BLENDER Q1E21FCVl14B closed with handswitch in the AUTO position.
4.6.8 Verify 1A and 1B BATP secured with the on-service BATP handswitch in the AUTO position 4.6.9 Verify 1A (preferred) or 1B RMWP supplying Reactor Makeup System with water. 4.6.10 IF 1B RMW PUMP is running and is not required for current plant conditions, THEN position the 1B RMW PUMP handswitch to STOP and back to AUTO. 4.6.11 IF 1A RMW PUMP is running and is not required for current plant conditions, THEN position the 1A RMW PUMP handswitch to STOP and back to AUTO. 4.6.12 Position the MKUP MODE SEL SWITCH to AUTO. 4.6.13 Position the MKUP MODE CONT SWITCH to START. Version 44.0 04/07/08 13:33:13 FNP-I-S0P-2.3 4.7 Large Volume Boration ofRCS NOTE: To protect the RCP Seals, increase the monitoring ofthe Seal Injection filter DP, due to the possibility of RCS Crud Burst or other contaminants clogging the Filter. 4.7.1 During or following a change of boron concentration of greater than 5 ppm in the RCS, the pressurizer spray must be operated to equalize the concentration throughout the system. Automatic operation of the spray should be initiated by manual operation of the pressurizer heaters when there is a steam bubble in the pressurizer.
4.7.2 Determine the existing reactor coolant boron concentration by sample analysis or from an estimate based on a previous sample. 4.7.3 Determine the magnitude of the boron concentration increase required from core physics curves or during normal operation, when compensating for xenon or core burnup, the magnitude may be estimated based on time in core life and previous experience.
NOTE: In the following step, the volume of boric acid to be used can be calculated by using the change in level of the on service boric acid tank OR by using the flow rate indicated on FI-110 multiplied by time to obtain gallons. 4.7.4 Determine the volume of boric acid required for boration from the boron addition nomograph, Figure 2, from the borationldilution tables, Reactivity Briefing Sheet or from estimate based on time in core life and . . preVIOUS expenence.
NOTE: IF waste gas system is shutdown, THEN VCT level should be maintained such that VCT pressure is not lowered to the point where the pressure regulator will admit more H2 or N2 to the VCT. Repeatedly allowing pressure to drop to this point will eventually result in having to start up the waste gas system to remove excess VCT gas. In addition, VCT level changes should be limited to prevent excessive perturbation of the RCP seals. 4.7.5 IF necessary, THEN adjust LTDN TO VCT FLOW LK 112 setpoint down to the pot setting corresponding to the desired VCT level to prevent compressing the gas space. 4.7.6 Start a Boric Acid Transfer Pump. Version 44.0 04/07/08 13:33:13 FNP-1-S0P-2.3 INOTE: Boric acid flow may stopped at any time by closing MOV8104. 4.7.7 Open Q1E21MOV8104 EMERG BORATE TO CHG PUMP SUCT to initiate boric acid flow. 4.7.8 Verify proper boric acid flow by flow indicated on FI-11O BORIC ACID EMERG BORATE flow indicator.
4.7.9 After the desired volume of boric acid has transferred, close Q1E21MOV8104 EMERG BORATE TO CHG PUMP SUCT. 4.7.10 Stop the Boric Acid Transfer Pump started in step 4.7.6. 4.7.11 IF LK 112 setpoint was adjusted per Step 4.7.5, THEN return setpoint to that required for current conditions.
5.0 References 5.1 Drawings P&ID -D-175039 -CVCS, sheets 3, 6 and 7 5.2 FSAR Chapter 9.3 5.3 PCN B92-0-8134, Reactor Makeup Water Cross-Tie 5.4 Safety Evaluation
-Revised Operation of the Gaseous Waste Processing System to Allow Non-continuous Purge of the VCT, SECL-93-125, NEL-93-0231 Version 44.0 04/07/08 13:33:13 FNP-1-S0P-2.3 TABLE 1 NOMOGRAPH CORRECTION FACTORS Plant Conditions Correction Factor Pressure T (AVG) Pressurizer Level (K) (psig) COF) (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 Nomograpbs V(Corrected)
= K X V(Nomograph) (b) Boron Addition and Dilution Rate Nomograpbs dc 1 dc -( Corrected) = -x -(Nomograph) dt K dt Page 1 of 1 Version 44.0 04/07/08 13:33:13 FNP-1-S0P-2.3 FIGURE 1 RCSBORON 4% BORIC CONCENTRA nON 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 of3 Version 44.0 04/07/08 13:33:13 FNP-I-SOP-2.3 Coolant 4wt. % / FK-l13 Coolant 4wt. % / FK-113 Coolant 4wt. % / FK-l13 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) 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 of3 Version 44.0 04/07/08 13:33:13 FNP-1-S0P-2.3 Coolant 4wt. % / FK-l13 Coolant 4wt. % / FK-l13 Coolant 4wt. % / FK-l13 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 (gpm) (ppm) flow (gpm) 1510 25.89 6.47 1840 3l.54 7.89 2170 37.20 9.30 1520 26.06 6.51 1850 3l.71 7.93 2180 37.37 9.34 1530 26.23 6.56 1860 3l.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 NOTE:
* Due to characteristics of the reactor makeup system piping, the maximum obtainable boric acid flow is less than 40 gpm .
* 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 12012 gpm. 2500 ppm 21.45 gpm with a pot setting of 5.35 for a blended flow of 60 gpm. BLENDED FLOW BASED ON 120 GPM AUTO MAKEUP Page 3 of3 Version 44.0 04/07/08 13:33:13 FNP-I-SOP-2.3 FIGURE 2 600 4-500 3600 500 4-00 3000 2500 M (7000-C f) VB = 8.33 J n 7000-C i 300 2100 -CD > 200 .....I 1500 oct .-2000 C!) 150 .-(.) (..) -UJ I I-.... z :::> 900 (.) oct .....I ...J 0 0 > 100 :z: 0 0 <.> Q 90 :z: I-<.> 600 80 1500 oct Co Co z <.> 0 70 oct 0.:: 0:: 60 :z: 0 0 0 CD co 0.:: 0 50 c:a 0-0-::E 300 0-4-0 c-1000 30 500 ISO 20 100 The mass, M, for the above formula can be obtained from the BoronlDilution table for the appropriate RCS temp. Figure 2. Boron Addition -Refer to Table 1 for Correction Factors Page 1 of 1 Version 44.0 
( " 04/07/08 13:33:13 T 1 FNP-l-SOP-2.3
--I-z: c( ..J 0 0 z: z: (:) 0::: C> ao :::E: , 0.. 0.. FIGURE 3 100 SOO "0 300 3S 30 27 1000 -200 2" ..... -0 21 -= 500X (7000-C) u 150 -dt M 0::: 18 >< :c -:E :::E IS 0.. CJ 1500 0.. .. 0 UJ 100 ..J ..-12 u. < 0::: 90 II Q :z: 0 (:) 80 10 <I: ..-9 0 Q ,70 0::: 200 9 Q 8 C> ct co z: 60 7 C> 0::: 0 50 co 6 2500 "0 5 30 The mass, M, for the above formula can be obtained from the Boron/Dilution table for the appropriate Res temp. 8o" or1 Addition Rate -Refer to Table 1 for Correction Factors
: 3. Page 1 of 1 Version 44.0 04/07/08 13:33:13 lJO 50 60 8.0 100 200 500 1000* . 2000 3000 PPM BORON IN COOLANT (Cd 1 T FIGURE 4 v -M w 8.33 In 5 to 15 20 30 50 tOo 150 200 300 500 PPM BORON DILUTION (C j -cfl 1 50 100 300 500 1000 3000 . 5000 10,000 -. 30,000 50,000 DILUTION WATER GAL. (V w) FNP-l-SOP-2.3 The mass, M, for the above formula can be obtained from the table for the appropriate Res temp. Figure 4 6oron Dilution -Refer to Table 1 for Corrcc1ion Factors Page 1 of 1 Version 44.0 04/07/08 13:33:13 3000 2COO 1500 1000 500 200 100 80 60 50 PPM BORON I N (C) 500 300 200 150 100 70 10 7 5 .. 3 2 i':J COOLANT DILUTION RATE PPM/HR (de/dt) 1 FIGURES ..... de -= 500 CY dt t4 FNP-1-S0P-2.3 150 100 90 80 70 60 50 30 20 15 DILUTtON WATER FLOW, GPM (Y) The mass, M, for the above formula can be obtained from the .Boron/Dilution table for the appropriate Res temp. Figure S. Boron Dilution Rate -Refer to Table 1 for Correction Factors Page lof 1 Version 44.0 04/07/08 13:33:13 FIGURE 6 USE OF EMERGENCY BORATION FLOWPATH (w/o AOP-27 ENTRY REQUIRED)
: 1. Start a Boric Acid Transfer Pump. 2. Open EMERG BORATE TO CHG PUMP SUCT QIE21MOV8104.
FNP-l-S0P-2.3
: 3. WHEN Boration Complete, THEN Close EMERG BORATE TO CHG PUMP SUeT QIE21MOV8104.
: 4. Secure the Boric Acid Transfer Pump. Ref. FNP-l-SOP-2.3 Ensure operator aid is updated if this figure is revised. Page lof 1 Version 44.0 
( 04/07/08 13:33:13 T APPENDIX A 1 FNP-I-SOP-2.3 Appendix A Operation of the Chemical and Volume Control System Reactor Makeup Control System with the Makeup Mode Control Switch Inoperable 1.0 Purpose Allow makeup to the VCT for Boration or Dilution when the AUTO function is failed. 2.0 Initial Conditions The Makeup Mode Control Switch is failed and plant operations require either Boration or Dilution.
3.0 Precautions and Limitations.
3.1 When selecting FCV-114B and FCV-I13A to OPEN the valves will go to full open, not a throttled position, causing the flowrate to be higher than normaL 3.2 A controlled mixing of boron and RMW will not be possible for a blended flow to the VCT. 3.3 Large batch makeups during power operations to the VCT or Charging pump suction, especially early in core life, can result in unintended reactor power changes. The reactivity affects should be considered when planning batch size. Small batches should be used at any time in core life. (CR20041 06233) 4.0 Instructions NOTE: Flowrate of makeup to the RCS may be indicated on Reactor Makeup Flow Indicator Q1E21FI-168.
If not, flowrate must be estimated by VCT level rise. 4.1 Boration 4.1.1 Determine the amount ofBoration desired 4.1.2 Verify an inservice BATP running. Page 1 of2 Version 44.0 04/07/08 13:33:13 FNP-l-SOP-2.3 Appendix A
* Verify the expected Reactivity changes by observing VCT level, Tavg, SR SUR, IR SUR, and Control Rod Motion. Stop the Make-Up System operation and take corrective action if any change is excessive or in the wrong direction.
4.1.3 Place Boric Acid to Blender QIE21FCVl13A to Open. 4.1.4 Place MKUP TO CHG PUMP SUCTION HDR Q1E21FCVl13B to open. 4.1.5 After desired amount of acid has entered the RCS close MKUP TO CHG PUMP SUCTION HDR Q1E21FCVl13B.
4.1.6 Close BORIC ACID TO BLENDER QIE21FCVl13A.
NOTE: IF repeated borations are expected, THEN the inservice BATP may remain running until after the final boration is completed.
4.1.7 Secure the inservice BATP. 4.2 Dilution 4.2.1 Determine the Amount of Dilution desired. 4.2.2 Verify one RMWP supplying Reactor Makeup System with water. 4.2.3 Place RMW to Blender QIE21FCV l14B to Open.
* Verify the expected Reactivity changes by observing VCT level, Tavg, SR SUR, IR SUR, and Control Rod Motion. Stop the Make-Up System operation and take corrective action if any change is excessive or in the wrong direction.
4.2.4 Place MKUP TO CHG PUMP SUCTION QIE21FCV113B to Open 4.2.5 After desired amount of water has entered the RCS close MKUP TO CHG PUMP SUCTION QIE21FCVl13B.
4.2.6 Close RMW TO BLENDER QIE21FCV114B Page 2 of2 Version 44.0 04/07/08 13:33:13 APPENDIXB FNP-1-S0P-2.3 AppendixB OPERATOR AID FOR BORA TION AND DILUTION 1.0 Boration NOTE: The Boric Acid Integrator ONLY needs to be verified when changed. This should be documented with an Autolog Entry. DODD 1.1 DODD 1.2 DODD 1.3 DODD 1.4 DODD 1.5 DODD 1.6 IF necessary, THEN set the boric acid integrator to the desired quantity.
IF necessary, THEN adjust LTDN TO VCT FLOW LK 112 setpoint as desired. Position the MKUP MODE CONT SWITCH to STOP. Position the MKUP MODE SEL SWITCH to BOR. Position the MKUP MODE CONT SWITCH to START. Verify proper boration operation by observing the following:
* On service boric acid pump started.
* MKUP TO CHG PUMP SUCTION HDR Q1E21FCVl13B opens.
* BORIC ACID TO BLENDER Q1E21FCVl13A opens.
* Boric acid flow is displayed on FI-l13 MAKEUP FLOW TO CHGNCT. o 0 0 0 1.7 Verify the boration automatically stops when the boric acid batch integrator reaches its setpoint as follows:
* Boric acid flow returns to zero as displayed on FI -113 MAKEUP FLOW TO CHGNCT.
* MKUP TO CHG PUMP SUCTION HDR Q1E21FCVl13B closes.
* BORIC ACID TO BLENDER Q1E21FCVl13A closes. o 0 0 0 1.8 If desired to clear the line of acid, perform the applicable steps of Appendix B section 2.0. NOTE: The following three steps are not required if operation in a mode other than automatic is preferred.
Refer to appendix C. o 0 0 0 1.9 Position the MKUP MODE SEL SWITCH to AUTO. o 0 0 0 1.10 Position the MKUP MODE CONT SWITCH to START. o 0 0 0 1.11 IF LK 112 setpoint was adjusted per Step 1.2, THEN return setpoint to that required for current conditions.
Page 1 of2 Version 44.0 Ensure posted operator aid is revised with any revision to this appendix 04/07/08 13:33:13 FNP-I-S0P-2.3 Appendix C APPENDIXC OPERA TOR AID FOR REPETITIVE BORA TION AND DILUTION . durillgrepetitiveoperation of tbe . ...... . .. . . . .. 1.0 Boration NOTE: During periods of repetitive boration evolutions, to minimize the number of start/stop cycles on the boric acid pump, the handswitch may be placed in START and allowed to return to AUTO to maintain the boric acid pump running. WHEN it is no longer desired to maintain the boric acid pump running continuously, THEN place the handswitch in STOP and return to AUTO. DODD 1.1 The Reactor Makeup Control system has been previously aligned for Boration.
DODD 1.2 DODD 1.3 Position the MKUP MODE CONT SWITCH to START. Verify proper boration operation by observing the following:
* On service boric acid pump started.
* MKUP TO CHG PUMP SUCTION HDR QIE21FCVI13B opens.
* BORIC ACID TO BLENDER QIE21FCVI13A opens.
* Boric acid flow is displayed on PI-I13 MAKEUP FLOW TO CHGNCT. o 0 0 0 1.4 Verify the boration automatically stops when the boric acid batch integrator reaches its setpoint as follows: NOTE:
* Boric acid flow returns to zero as displayed on FI -113 MAKEUP FLOW TO CHGNCT.
* MKUP TO CHG PUMP SUCTION HDR QIE21FCVI13B closes.
* BORIC ACID TO BLENDER QIE21FCVI13A closes. WHEN it is no longer desired to maintain the line full of acid, THEN perform the applicable steps of Appendix B section 2.0 to flush the line. o 0 0 0 1.5 IF repetitive borations are no longer required THEN verify the system is aligned for Automatic makeup per steps 1.9 through 1.11 of AppendixB.
Page 1 of2 Version 44.0 Ensure posted operator aid is revised with any revision to this appendix 04/07/08 13:33:13 FNP-1-S0P-2.3 Appendix C 2.0 Dilution o 0 0 0 2.1 The Reactor Makeup Control system has been previously aligned for Dilution or Alternate Dilution.
o 0 0 0 2.2 Position the MKUP MODE CONT SWITCH to START. o 0 0 0 2.3 Verify proper dilution operation by observing the following:
* IF using ALT DIL, MAKEUP TO CHG PUMP SUCTION HDR Q1E21FCVl13B opens.
* MKUP TO VCT Q1E21FCVl14A opens, unless bypassing VCT.
* RMW TO BLENDER Q1E21FCVl14B opens.
* Reactor makeup flow is displayed on FI-168 MAKEUP FLOW TO CHGNCT. o 0 0 0 2.4 Verify the dilution automatically stops when the total flow batch integrator reaches its setpoint by observing the following:
* Reactor makeup flow returns to zero as displayed on FI -168 MAKEUP FLOW TO CHGNCT.
* MKUP TO VCT Q1E21FCVl14A closes or is closed if bypassing the VCT.
* RMW TO BLENDER Q1E21FCVl14B closes.
* IF ALT DIL was used, THEN MAKEUP TO CHG PUMP SUCTION HDR Q1E21FCVl13B closes. o 0 0 0 2.5 IF repetitive dilutions are no longer required THEN verify the system is aligned for Automatic makeup per steps 2.8 through 2.11 of AppendixB.
Page 2 of2 Version 44.0 Ensure posted operator aid is revised with any revision to this appendix 04/07/08 13:33:13 APPENDIXD FNP-I-S0P-2.3 AppendixD Operation of the Chemical and Volume Control System Reactor Makeup Control System with FIS 168 Total Flow Batch Integrator Unreliable 1.0 Purpose Allow makeup to the VCT for a dilution when the AUTO function is failed because FIS-168 Total Flow Batch Integrator is unreliable.
2.0 Initial Conditions 2.1 FIS-168 Total Flow Batch Integrator is failed or unreliable, and plant operations require a dilution.
2.2 The Chemical and Volume Control System is aligned for auto operation.
3.0 Precautions and Limitations 3.1 When selecting FCV-114B to OPEN the valve will go to full open, not a throttled position, causing the flow rate to be higher than normaL 3.2 A controlled mixing of boron and RMW will not be possible for a blended flow to the VCT. 3.3 Large batch make ups during power operations to the VCT or Charging pump suction, especially early in core life, can result in unintended reactor power changes. The reactivity affects should be considered when planning batch size. Small batches should be used at any time in core life. (CR2004106233) 4.0 Instructions NOTE: Flow rate of makeup to the RCS may be indicated on Reactor Makeup Flow Indicator QIE21FI-168.
If not and flow rate is desired, flow rate must be estimated by VCT level rise. 4.1 Dilution 4.1.1 Determine the amount of dilution desired. 4.1.2 Verify one RMWP supplying Reactor Makeup System with water. Page 1 of2 Version 44.0 04/07/08 13:33:13 FNP-I-S0P-2.3 AppendixD
* Verify the expected Reactivity changes by observing VCT level, Tavg, SR SUR, IR SUR, and Control Rod Motion. Stop the Make-Up System operation and take corrective action if any change is excessive or in the wrong direction.
4.1.3 Place RMW to Blender QIE21FCV1l4B to Open. 4.1.4 Place MKUP TO CHG PUMP SUCTION Q1E21FCV113B to Open. 4.1.5 WHEN desired, THEN close MKUP TO CHG PUMP SUCTION QIE21FCV113B.
4.1.6 Close RMW TO BLENDER QIE21FCVl14B.
4.1.7 Place MKUP TO CHG PUMP SUCTION Q1E21FCV113B to AUTO. 4.1.8 Place RMW to Blender Q1E21FCV114B to AUTO. NOTE: The following steps are required to reset the Total Flow Batch Integrator.
4.1.9 Position the MKUP MODE CONT SWITCH to STOP. 4.1.10 Position the MKUP MODE CONT SWITCH to START. Page 2 of2 Version 44.0 
( HL T-32 ADMIN exam A.1.1 SRO Page 1 of 6 A.l.lSRO Conduct Of Operations ADMIN 006Al.02 -SRO TITLE: Determine required quantity of Boric Acid solution and Reactor Makeup water and integrator settings for makeup to the RWST, and determine which TS ACTIONS are required, if any. TASK STANDARD:
Determine the required quantity of Boric Acid and Reactor Makeup water to restore RWST level at the current Boric Acid Concentration, and correctly determine the setting of the Reactor Makeup system integrators and the potentiometer setting for the Boric Acid Flow controller.
Determines that LCO 3.5.4 CONDITION B is in effect, and restoring RWST to greater than 37.9 feet in 1 hour is required.
PROGRAM APPLICABLE:
SOT SOCT OLT LOCT __ ACCEPTABLE EVALUATION METHOD:
SIMULATE DISCUSS EVALUATION LOCATION:
SIMULATOR CONTROL ROOM CLASSROOM PROJECTED TIME: 20 MIN SIMULATOR IC NUMBER: N/A ALTERNATE PATH TIME CRITICAL PRA __ Examinee:
Overall JPM Performance:
Satisfactory 0 Unsatisfactory 0 Evaluator Comments (attach additional sheets if necessary)
EXAMINER:
________________
_
HL T -32 ADMIN exam A.1.1 SRO Page 2 of 6 CONDITIONS When I tell you to begin, you are to determine RWST Makeup quantity, Boric acid concentration, and integrator setting for make up to the RWST per FNP-1-S0P-2.3, Chemical And Volume Control System Reactor Makeup Control System, starting at Step 4.2.3.2 Makeup to Refueling Water Storage Tank (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. c. RWST Boron concentration is at 2400 ppm. d. On Service BAT concentration is 7500 ppm. e. RWST Purification (Recirc) is NOT on-service.
: f. The Reactivity Spreadsheet is not available.
: g. You are the extra Shift Support Supervisor and have been directed by the Shift Supervisor to perform SOP-2.3 steps 4.2.3.2 -4.2.3.6 to: 1. Determine the quantity of blended flow required to raise level in the RWST from 37.7 feet to 39.5 feet while maintaining the current RWST Boron Concentration.
: 2. Determine the integrator settings for:
* FIS 113, BORIC ACID BATCH INTEG
* FIS-168, TOTAL FLOW BATCH INTEG 3. Determine the potentiometer setting to makeup to the RWST at a reduced flow of 60 gpm total flow for:
* FK-113, BORIC ACID MKUP FLOW 4. Determine which TS ACTION(S) is(are) required, if any. EVALUATION CHECKLIST ELEMENTS:
STANDARDS:
_START TIME I NOTE:
* This is a classroom setting ADMIN JPM task. *1. Determines Gallons needed per RWST Tank
* Determines RWST Volume at curve 31B is 22,378 gallons. 39.5 feet=491064 gals
* Determines RWST Volume at 491064-468686
= 22378 37.7 feet=484848 gals
* Calculates total volume RESULTS: (CIRCLE) addition=
22378 gals S I U 491064 -468686 = 22378 gals [no tolerance:
whole numbers from a table]
HL T -32 ADMIN exam A.1.1 SRO Page 3 of 6 EVALUATION CHECKLIST RESULTS: ELEMENTS:
STANDARDS: (CIRCLE) *2. *3. NOTE: Determines Boric Acid amount from Figure Determines from Figure 1, SOP-1, SOP-2.3, for the current concentration of 2.3 ratio of Boric Acid amount to 2400 ppm. total amount from the ratio of Boric Acid flow to Total Flow. Then calculates total Boric Acid in gallons to obtain total 22,378 gals of blended solution at 2400 ppm:
* 7664-7672 gals Boric Acid Solution S / U PER FIG. 1 PAGE 1: 22378( 41.1) = 7664.465gals 120 PER FIG 1 PAGE 3: 22378( 41.14) = 7671.924 gals 120 [tolerance:
7664.0-7672 based on using either page 1 or page 3 numbers and rounding to nearest whole number of 7664 or rounding up for conservative 7672 gals.] Determines the totalizer settings for Total Determines totalizer settings are: flow FIS-168, TOTAL FLOW BATCH
* FIS-168=22378 gals S / U INTEG and FIS-l13, BORIC ACID
* FIS-113=7664-7672 gals S / U BATCH INTEG: Based on Figure 1.
* In element 5, FK-113 pot setting* is critical, but the manual position of FIS-168 demand which corresponds to 60 gpm is not critical, since this controller would need to be adjusted while flow was present. There is no corresponding demand that will ensure 60 gpm flow prior to initiating flow and adjusting as necessary.
Examiner NOTE:
* In element 5, IF applicant desires to raise the setpoint above the minimum required, ask them what setpoint they are going to use and ensure it is greater than the minimum required.
HLT-32 ADMIN exam A.1.1 SRO Page 5 of 6 CRITICAL ELEMENTS:
Critical Elements are denoted with an asterisk (*) before the element number. GENERAL
 
==REFERENCES:==
: 1. FNP-I-SOP-2.3 Version 44.0 2. FNP-I-ARP-1.5 EG4, Version 49.0 3. Tech Specs & Basis Amendment No. 146 (Unit 1), Amendment No. 137 (Unit 2) 4. KIA: G2.006A1.02 RO 3.0 SRO 3.6 GENERAL TOOLS AND EQUIPMENT:
Provide: 1. FNP-I-SOP-2.3, Version 44.0. 2. Curves 3IA & 3IB 3. Calculator (or applicant may supply their own calculator)
: 4. LCO 3.5.4 & Basis. COMMENTS:
A.1.1 SRO (1 Page) HANDOUT CONDITIONS When I tell you to begin, you are to determine RWST Makeup quantity, Boric acid concentration, and integrator setting for make up to the RWST per FNP-I-SOP-2.3, Chemical And Volume Control System Reactor Makeup Control System, starting at Step 4.2.3.2 Makeup to Refueling Water Storage Tank (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. c. RWST Boron concentration is at 2400 ppm. d. On Service BAT concentration is 7500 ppm. e. RWST Purification (Recirc) is NOT on-service.
: f. The Reactivity Spreadsheet is not available.
: g. You are the extra Shift Support Supervisor and have been directed by the Shift Supervisor to perform SOP-2.3 steps 4.2.3.2 -4.2.3.6 to: 1. Determine the quantity of blended flow required to raise level in the RWST from 37.7 feet to 39.5 feet while maintaining the current RWST Boron Concentration.
: 2. Determine the integrator settings for:
* FIS 113, BORIC ACID BATCH INTEG
* FIS-168, TOTAL FLOW BATCH INTEG 3. Determine the potentiometer setting to makeup to the RWST at a reduced flow of 60 gpm total flow for:
* FK-l13, BORIC ACID MKUP FLOW 4. Determine which TS ACTION(S) is(are) required, if any.
600000 PCB-1-VOLlI-CRV31A Refueling Water Storage Tank Capaelly Q1F16T501 Capacity (Gal) vs. Level (Ft) 500000 +-----Revision 3.0 February 4, 2005 JSJ Approved:
i' 400000 .2
.-' ES anager Date "i r------300000 ---1-------
--,,-------
------------------------------------
------------------------------------------------------------
----------------
\ IJ :!. J 200000 100000 o 5 10 15 20 25 30 35 40 45 Indicated Level (ft. H20) 
( Unit i VO!\lme H Curve :3 til hit!1i1U",lf'!!'!Xl Watsf QWl6T50i T oWi! &#xa5;O!W1lB: in gallons'" 00971 2; Tocl,nical SIR :Uk4,2; requires iii il1fnimum OOl'ltalood OOra1eG watillf of 471 ,DOD 
( 04/07/08 13:33:13 FARLEY NUCLEAR PLANT SYSTEM OPERATING PROCEDURE FNP-I-SOP-2.3 CHEMICAL AND VOLUME CONTROL SYSTEM REACTOR MAKEUP CONTROL SYSTEM FNP-I-SOP-2.3 March 7, 2008 Version 44.0 PROCEDURE USAGE REQUIREMENTS PER FNP-0-AP-6 SECTIONS Continuous Use ALL Reference Use Infonnation Use Approved:
: 1. L. Hunter (for) Operations Manager Date Issued 04/04/2008 S A F E T Y R E L A T E D 04/07/08 13:33:13 FNP-1-S0P-2.3 TABLE OF CONTENTS Procedure Contains Number of Pages Body ........................................................
42 Table I ......................................................
1 Figure 1 .....................................................
3 Figure 2 .....................................................
1 Figure 3 .....................................................
1 Figure 4 .....................................................
1 Figure 5 .....................................................
1 Figure 6 .....................................................
1 Appendix A ...............................................
2 Appendix B ...............................................
2 Appendix C ...............................................
2 Appendix D ...............................................
2 ( Page 1 of 1 Version 44.0 
( 04/07/08 13:33:13 1.0 Purpose 1 T 1 FARLEY NUCLEAR PLANT UNIT 1 SYSTEM OPERATING PROCEDURE SOP-2.3 CHEMICAL AND VOLUME CONTROL SYSTEM REACTOR MAKEUP CONTROL SYSTEM FNP-I-S0P-2.3 This procedure provides Initial Conditions, Precautions and Limitations, and Instructions for operation of the Reactor Makeup Control System. Instructions are included in the following sections:
4.1 Automatic Makeup 4.2 Manual Makeup 4.2.1 Makeup to Top of Volume Control Tank 4.2.2 Makeup to Charging Pumps Suction Header 4.2.3 Makeup to Refueling Water Storage Tank (RWST) 4.2.4 Makeup to Recycle Holdup Tanks (RHT) 4.2.5 Makeup to SFP Through Temporary Connection 4.3 Boration 4.4 Dilution 4.5 Combined Boration 1 Dilution 4.6 Verify Reactor Makeup Control System Aligned for Auto Makeup 4.7 Large Volume Boration ofRCS Appendix A Operation of the Chemical and Volume Control System Reactor Makeup Control System with the Makeup Mode Control Switch Inoperable Appendix B Operator Aid for Boration and Dilution Appendix C Operator Aid for Repetitive Boration and Dilution Appendix D Operation of the Chemical and Volume Control System Reactor Makeup Control System with FIS 168 Total Flow Batch Integrator Unreliable  Version 44.0 04/07/08 13:33:13 FNP-I-SOP-2.3 2.0 Initial Conditions 2.1 The chemical and volume control system valves and electrical distribution systems are aligned per System checklist FNP-I-SOP-2.1A, CHEMICAL AND VOLUME CONTROL SYSTEM, with exceptions noted. 2.2 At least one RCP must be running prior to changing the boron concentration in the RCS. (SOER 94-02) (Section 3.0, Precaution and Limitation include additional clarification for this restriction).
2.3 Reactor makeup water is available to the reactor makeup control system per FNP-I-SOP-4.0, REACTOR MAKEUP WATER SYSTEM, if the operation being performed requires reactor makeup water. 2.4 Boric acid is available to the reactor makeup control system per FNP-I-SOP-2.6, CHEMICAL AND VOLUME CONTROL SYSTEM BORIC ACID SYSTEM, if the operation being performed requires boric acid. 3.0 Precautions and Limitations 3.1 The reactor makeup control system should be in automatic and adjusted to supply makeup equal in boron concentration to reactor coolant system concentration, except during reactor coolant system boration or dilution operations, or malfunctions of automatic control. 3.1.1 FK-168 is the MIA station used to control RMW to the blender flow control valve (FCV-114B).
If the MIA station is in AUTO, then the Makeup Mode Selector Switch determines the origin of the set point as follows:
* With the Mode Selector Switch in AUTO, the set point is 120 gpm. The position ofFCV-114B is determined by the difference between actual total flow and an internal set point of 120 gpm.
* With the Mode Selector Switch in MAN, DIL, or ALT DIL, the set point is determined by the potentiometer position. (AI-2005205348) 3.1.2 FK-113 is the MIA station used to control boric acid flow to the blender flow control valve (FCV-I13A).
When the makeup mode selector switch is in AUTO, FK-I13 (MIA station) will only control FCV-I13A automatically during periods of an AUTO makeup. Once the VCT level reaches 40 percent, the MIA station will shift to manual control. This maintains FK-113 output at the valve demand required for the desired blended boron concentration as determined by MIA station potentiometer setting based on total flow of 120 gpm. FK-I13 should not routinely be left in AUTO since the output will continue to integrate up with no system flow. This would delay the valve response to an auto makeup and result in an over boration. (AI2005205348)  Version 44.0 04/07/08 13:33:13 1*.**. , 11 FNP-I-S0P-2.3 3.2 Actuation of the veT LVL HI-LO annunciator (DF3) indicates a malfunction or improper operation of the reactor makeup control system. 3.3 The boron concentration in the pressurizer should not be less than that in the ReS loops by more than 50 ppm. Following or during a 5 ppm change of boron concentration in the ReS, the pressurizer spray must be operated to equalize the concentration throughout the system. Automatic operation of the spray should be initiated by manual operation of the pressurizer heaters when there is a steam bubble in the pressurizer.
3.4 Observe the effects of changing ReS boron concentration in terms of resulting control rod motion, changes in Tavg, or SIR count rate. Stop boron concentration change operations and take corrective action if control rod motion is excessive or in the wrong direction, or Tave changes without subsequent rod motion. 3.5 WHEN the reactor is in the source range, THEN positive reactivity additions must only be made by one controlled method at a time. 3.6 The flow rate through the reactor coolant system shall be determined to be greater than 3000 gpm prior to the start of and at least once per hour during a dilution of the ReS by verifying at least one Rep is running. NOTE: The following step is intended to prevent the occurrence of dilute pockets of Reactor coolant due to inadequate mixing while in shutdown conditions.
This could occur if the RHR system is the sole source of ReS flow and a boration is made to reach the required shutdown margin (or refueling) boron concentration.
3.7 During shutdown operations, at least one Rep must be running prior to changing the ReS boron concentration unless directed to borate the ReS by any abnormal or emergency operating procedure.
IF the ReS and PRZR boron concentration have been sampled with a Rep running, and verified adequate for refueling and/or shutdown margin, THEN filling or normal makeup to the ReS with water greater than or equal to the refueling and/or shutdown margin concentration is not applicable to this requirement.
IF a boration is required to obtain the required boron concentration, AND no Rep is running, THEN the Shift Supervisor should consider alternate sampling methods to verify boron concentration requirements are satisfied throughout the ReS. 3.8 Both units' boric acid blenders should not be supplied with reactor makeup water simultaneously if SOP-4.0 Appendix 2 is in effect. 3.9 Simultaneous running of both RMW pumps can cause one pump to operate near shutoff head condition, which produces abnormal thrust bearing loading and could lead to pre-mature bearing failure. Simultaneous running of both pumps should be minimized. (IR 1-96-062)  Version 44.0 04/07/08 13:33:13 1 FNP-I-S0P-2.3 3.10 ZAS injection will result in a continuous RCS dilution by as much as 1.7 gallons per hour, which could result in a rise in TAVG ifnot compensated for by boration, rod insertion, or increasing fission product poison inventory.
3.11 During periods of repetitive boration evolutions, to minimize the number of start/stop cycles on the boric acid pump, the handswitch may be placed in START and allowed to return to AUTO to maintain the boric acid pump running. WHEN it is no longer desired to maintain the boric acid pump running continuously, THEN place the handswitch in STOP and return to AUTO. 3.12 Large batch makeups during power operations to the VCT or Charging pump suction, especially early in core life, can result in unintended reactor power changes. The reactivity affects should be considered when planning batch size. Small batches should be used at any time in core life. (CR2004106233)
Large makeups can also cause seal injection temperature transients which can reduce RCP #1 seal leak off to a point at which seal damage occurs. (CR 2006104054) 3.13 The following list provides precautions and limitations related to VCT pressure reductions and gas accumulation in idle charging pump suctions.
* VCT pressure reductions 7 psig can result in gas dissolution sufficient to create idle charging pump suction voiding.
* Any VCT pressure reduction should be :5 5 psig in 4 hours to preclude void formation in charging pump suction piping.
* Pressure reduction rates exceeding preceding limitation should be documented by Condition Report.
* Idle Charging pump suctions should be vented when VCT pressure reduction rate has exceeded preceding limit. Version 44.0 
( 04/07/08 13:33:13 FNP-1-S0P-2.3 4.0 Instructions 4.1 Automatic Makeup 4.1.1 Determine the existing RCS boron concentration by sample analysis or from an estimate based on the previous sample. NOTE: ZAS injection will result in a continuous RCS dilution by as much as 1.7 gallons per hour causing the auto makeup to be inadequately set. A slightly higher set point may be required to maintain TAVG. 4 .1.2 Verify the following:
4.1.2.1 4.1.2.2 Verify BORIC ACID MKUP FLOW controller FK 113 set up per the following:
A) In Manual B) Potentiometer is set to obtain a makeup value having a boron concentration equal to RCS boron concentration.
The setting is obtained from one of the following: (AI2005205348)
* Reactivity Briefing Sheet
* Figure 1 Verify FK-168 PRI WTR MKUP FLOW controller in Auto. 4.1.3 Position the MKUP MODE CONT SWITCH to STOP. 4.1.4 Position the MKUP MODE SEL SWITCH to AUTO. NOTE: Automatic makeup may be stopped at any time by placing the MKUP MODE CONT SWITCH to STOP. 4.1.5 Position the MKUP MODE CONT SWITCH to START. 4.1.6 IF 1B RMW PUMP is running and is not required for current plant conditions, THEN position the 1B RMW PUMP handswitch to STOP. Version 44.0 04/07/08 13:33:13 1 T FNP-1-S0P-2.3 NOTE: Verify expected Reactivity changes by observing VCT level, Tavg, SR SUR, IR SUR, and Control Rod Motion. Stop the Make-Up System operation and take corrective action if any change is excessive or in the wrong direction.
4.1.7 Verify proper automatic operation of the reactor makeup control system as follows: 4.1.7.1 4.1.7.2 WHEN VCT level decreases to 20%, THEN verify that makeup begins by observing the following: (a) MKUP TO CHG PUMP SUCTION HDR Q1E21FCV113B (Q1E21V337) open. (b) Boric acid flow on FI -113 and reactor makeup flow on FI-168 are at the pre-selected rates as displayed on MAKEUP FLOW TO CHG/VCT. (c) VCT level increasing.
WHEN VCT level increases to 40%, THEN verify that makeup stops by observing the following: (a) BORIC ACID TO BLENDER Q1E21FCV113A (Q1E21V354) closed. (b) MKUP TO CHG PUMP SUCTION HDR Q1E21FCV113B (Q1E21V337) closed. (c) RMWTO BLENDERQ1E21FCV114B (Q1E21V345) closed. (d) Boric acid flow on FI -113 and reactor makeup flow on FI-168 return to zero as displayed on MAKEUP FLOW TO CHGNCT indicator. Version 44.0 04/07/08 13:33:13 T 1 FNP-I-S0P-2.3 4.2 NOTE: IF waste gas system is shutdown, THEN VeT level should be maintained such that VeT pressure is not lowered to the point where the pressure regulator will admit more Hz or Nz to the VeT. Repeatedly allowing pressure to drop to this point will eventually result in having to start up the waste gas system to remove excess VeT gas. In addition, VeT level changes should be limited to prevent excessive perturbation of the Rep seals. 4.2.1 to Top of Volume Control Tank 4.2.1.1 Verify the VCT capable of receiving makeup.
4.2.1.2 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
* Boron/Dilution Tables
* Nomographs  Version 44.0 04/07/08 13:33:13 FNP-I-S0P-2.3 NOTE:
* When making up to the VCT use the flow rate from figure 1 or the reactivity briefing sheet.
* Flow rates may be adjusted using the controllers in manual or automatic.
* The boric acid flow should not be through the top of the VCT to keep the nozzle from clogging.
* 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".
* The Boric Acid and/or Total Flow Batch Integrators ONLY need to be verified when changed. This should be documented with an Autolog Entry. 4.2.1.3 Set the boric acid flow controllers and batch integrators to the calculated flow rate and quantity value obtained in step 4.2.1.2.
* For boric acid only set the boric acid integrator to the desired value and RMW TO BLENDER QIE21FCV114B (QIE21 V345) should be taken to close to ensure that only acid flow is obtained.
* For reactor makeup water only set the boric acid integrator to o. 4.2.1.4 Set the reactor makeup water flow controllers and batch integrators to the calculated flow rate and quantity value obtained in step 4.2.1.2.
* For boric acid only set the total flow integrator to 0 and RMW TO BLENDER QIE21FCV114B (QIE21 V345) should be taken to close to ensure that only acid flow is obtained.
* For reactor makeup water only set the boric acid integrator to 0 and the total flow integrator to the desired value. 4.2.1.5 IF necessary, THEN adjust LK-112 setpoint down to the pot setting corresponding to the desired VCT level to prevent compressmg gas space. 4.2.1.6 Position the MKUP MODE CONT SWITCH to STOP. 4.2.1.7 Position the MKUP MODE SEL SWITCH to MAN. 4.2.1.8 Open MKUP TO VCT QIE21FCV114A (QIE21 V339). Version 44.0 04/07/08 13:33:13 1 T 1 FNP-I-S0P-2.3 NOTE:
* Makeup may be stopped at any time by positioning the MKUP MODE CONT SWITCH to STOP.
* Verify the expected Reactivity changes by observing VCT level, Tavg, SR SUR, IR SUR, and Control Rod Motion. Stop the Make-Up System operation and take corrective action if any change is excessive or in the wrong direction.
4.2.1.9 Position the MKUP MODE CONT SWITCH to START. 4.2.1.10 IF IB RMW PUMP is running and not required for current plant conditions, THEN position the IB RMW PUMP switch to STOP. 4.2.1.11 Verify makeup flows indicated on FI -113 and FI -168 are at the pre-selected rates as displayed on MAKEUP FLOW TO CHGNCT indicator.
4.2.1.12 During or following a change of boron concentration of greater than 5 ppm in the RCS, the pressurizer spray must be operated to equalize the concentration throughout the system. Automatic operation of the spray should be initiated by manual operation of the pressurizer heaters when there is a steam bubble in the pressurizer.
4.2.1.13 Verify makeup automatically stops when batch integrator setpoints are reached by observing the following: (a) Boric acid flow on FI -113 and reactor makeup flow on FI-168 return to zero as displayed on MAKEUP FLOW TO CHGNCT indicator. (b) RMW TO BLENDER QIE21FCV114B (QIE21V345) closed. (c) BORIC ACID TO BLENDER QIE21FCVI13A (QIE21V354) closed. Version 44.0 04/07/08 13:33:13 1 FNP-1-S0P-2.3 4.2.1.13 Return MKUP TO VCT Q1E21FCV114A (Q1E21V339) control switch to AUTO. 4.2.1.14 IF required THEN Return RMW TO BLENDER QIE21FCV114B (QIE21V345) control switch to AUTO. NOTE: The Boric Acid and/or Total Flow Batch Integrators ONLY need to be verified when changed. This should be documented with an Autolog Entry. NOTE: 4.2.1.15 Set the boric acid and/or total flow batch integrators to the required quantities as needed for normal system operation.
4.2.1.16 IF the boric acid and/or reactor makeup water flow controllers were adjusted, THEN perform the following: (a) Verify the BORIC ACID MKUP FLOW controller FK 113 is in the MAN position. (AI2005205348) (b) Restore FK -113 controller to the setpoint required for automatic makeup per step 4.1.2. (c) Verify FK-168 PRI WTR MKUP FLOW controller in Auto. 4.2.1.17 IF LK -112 was adjusted, THEN return LK-112 setpoint to that required for current conditions.
The following two steps are not required if operation in a mode other than automatic is required.
4.2.1.18 Position the MKUP MODE SEL SWITCH to AUTO. 4.2.1.19 Position the MKUP MODE CONT SWITCH to START. Version 44.0 
( 04/07/08 13:33:13 FNP-I-S0P-2.3 4.2.2 Makeup to Charging Pumps Suction Header NOTE: IF waste gas system is shutdown, THEN VeT level should be maintained such that VeT pressure is not lowered to the point where the pressure regulator will admit more H2 or N2 to the VeT. Repeatedly allowing pressure to drop to this point will eventually result in having to start up the waste gas system to remove excess VeT gas. In addition, VeT level changes should be limited to prevent excessive perturbation of the Rep seals. 4.2.2.1 Verify VCT capable of receiving makeup. 4.2.2.2 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
* BoronlDilution Tables
* Nomographs  Version 44.0 
( 04/07/08 13:33:13 1 1 FNP-l-SOP-2.3 NOTE:
* When making up to the VeT use the flow rate from figure 1 or the reactivity briefing sheet.
* Flow rates may be adjusted using the controllers in manual or automatic.
* 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".
* The Boric Acid and/or Total Flow Batch Integrators ONLY need to be verified when changed. This should be documented with an Autolog Entry. 4.2.2.3 Set the boric acid flow controllers and batch integrators to the calculated flow rate and quantity value obtained in step 4.2.2.2.
* For boric acid only set the boric acid integrator to the desired value and RMW TO BLENDER Q1E21FCVl14B (Q1E2l V345) should be taken to close to ensure that only acid flow is obtained.
* For reactor makeup water only set the boric acid integrator to o. 4.2.2.4 Set the reactor makeup water flow controllers and batch integrators to the calculated flow rate and quantity value obtained in step 4.2.2.2.
* For boric acid only set the total flow integrator to 0 and RMW TO BLENDER Q1E21FCVl14B (Q1E2l V345) should be taken to close to ensure that only acid flow is obtained.
* For reactor makeup water only set the boric acid integrator to 0 and the total flow integrator to the desired value. 4.2.2.5 IF necessary, THEN adjust LK-112 setpoint down to the pot setting corresponding to the desired VCT level to prevent compressing gas space. 4.2.2.6 4.2.2.7 4.2.2.8 Position MKUP MODE CONT SWITCH to STOP. Position the MKUP MODE SEL SWITCH to MAN Open MKUP TO CHG PUMP SUCTION HDR Q1E21FCVl13B (Q1E2l V337). Version 44.0 04/07/08 13:33:13 T 1 FNP-I-S0P-2.3 NOTE:
* Makeup may be stopped at any time by positioning the MKUP MODE CONT SWITCH to STOP.
* Verify the expected Reactivity changes by observing VCT level, Tavg, SR SUR, IR SUR, and Control Rod Motion. Stop the Make-Up System operation and take corrective action if any change is excessive or in the wrong direction.
4.2.2.9 Position MKUP MODE CONT SWITCH to START. 4.2.2.10 IF IB RMW PUMP is running and not required for current plant conditions, THEN position the IB RMW PUMP switch to STOP. 4.2.2.11 Verify boric acid flow on FI-I13 and reactor makeup flow on FI-168 are at the pre-selected rates as displayed on MAKEUP FLOW TO CHGNCT indicator.
4.2.2.12 During or following a change of boron concentration of greater than 5 ppm in the RCS, the pressurizer spray must be operated to equalize the concentration throughout the system. Automatic operation of the spray should be initiated by manual operation of the pressurizer heaters when there is a steam bubble in the pressurizer.
4.2.2.13 Verify makeup automatically stops when batch integrator setpoints are reached by observing the following: ( a) Boric acid flow on FI -113 and reactor makeup flow on FI-168 return to zero as displayed on MAKEUP FLOW TO CHGNCT indicator. (b) RMW TO BLENDER QIE21FCV114B (QIE21V345) closed. (c) BORIC ACID TO BLENDER QIE21FCVI13A (QIE21V354) closed. Version 44.0 04/07/08 13:33:13 FNP-I-S0P-2.3 4.2.2.13 Return MKUP TO CHG PUMP SUCTION HDR QIE21FCVI13B (QIE21 V337) control switch to AUTO. 4.2.2.14 IF required THEN Return RMW TO BLENDER QIE21FCV114B (QIE21 V345) control switch to AUTO. NOTE: The Boric Acid and/or Total Flow Batch Integrators ONLY need to be verified when changed. This should be documented with an Autolog Entry. NOTE: 4.2.2.15 Set the boric acid and/or total flow batch integrators to the required quantities as needed for normal system operation.
4.2.2.16 IF the boric acid and/or reactor makeup water flow controllers were adjusted, THEN perform the following: (a) Verify the BORIC ACID MKUP FLOW controller FK 113 is in the MAN position. (AI2005205348) (b) Restore FK -113 controller to the setpoint required for automatic makeup per step 4.1.2. (c) Verify FK-168 PRI WTR MKUP FLOW controller in Auto. 4.2.2.17 IF LK-112 was adjusted, THEN return LK-112 setpoint to that required for current conditions.
The following two steps are not required if operation in a mode other than automatic is required.
4.2.2.18 Position the MKUP MODE SEL SWITCH to AUTO. 4.2.2.19 Position the MKUP MODE CONT SWITCH to START. Version 44.0 
( 04/07/08 l3:33:l3 FNP-I-SOP-2.3 4.2.3 Makeup to Refueling Water Storage Tank (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 4.2.3.17 at an appropriate time prior to reaching the Total Flow Integrator setpoint.
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 44.0 04/07/08 13:33:13 4.2.3.3 4.2.3.4 ( FNP-l-S0P-2.3 IF the final boron concentration in the R WST 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. To dilute the RWST: VA = CI -CF (VI) CF To borate the RWST: VA = CI -CF (VI) CF-CA To determine final boron concentration:
CF = rCI x VI] + rCA x V AJ 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 IF the RWST Purification (Recirc) is On-Service, THEN secure the Refueling Water Purification Pump. Version 44.0 
( 04/07108 13:33:13 FNP-1-S0P-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. IF necessary, THEN the Total Flow may be set for < 120 gpm and the Boric Acid Flow rate adjusted proportionally to Total Flow.
* Flow rates may be adjusted using the controllers in manual or automatic.
* 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. 4.2.3.5 Set the boric acid flow controllers and batch integrators to the calculated flow rate and 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 QIE21FCVl14B (Q1E21 V345) should be taken to close to ensure that only acid flow is obtained.
* For reactor makeup water only set the boric acid integrator to O. 4.2.3.6 Set the reactor makeup water flow controllers and batch integrators to the calculated flow rate and quantity value obtained in step 4.2.3.2 or 4.2.3.3.
* For boric acid only set the total flow integrator to 0 and RMW TO BLENDER Q1E21FCV114B (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 0 and the total flow integrator to the desired value. 4.2.3.7 Position the MKUP MODE CONT SWITCH to STOP. 4.2.3.8 Position the MKUP MODE SEL SWITCH to MAN. Version 44.0 04/07/08 13:33:13 FNP-I-S0P-2.3 4.2.3.9 Open blender discharge to RWST valve l-CVC-V-8434 (NIE21 V238). 4.2.3.10 Open blender miscellaneous discharge isolation valve l-CVC-V-8432 (QIE21V237).
4.2.3.11 Place MKUP TO CHG PUMP SUCTION HDR QIE2IFCVI13B (QIE21 V337) in the CLOSED position.
4.2.3.12 Place MKUP TO VCT QIE21FCV114A (QIE21V339) in the CLOSED position.
4.2.3.13 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 QIE21FCV114B (QIE21V345).
NOTE: Makeup may be stopped at any time by positioning the MKUP MODE CONT SWITCH to STOP. 4.2.3.14 Position the MKUP MODE CONT SWITCH to START. 4.2.3.15 IF IB RMW PUMP is running and not required for current plant operations, THEN position the IB RMW PUMP switch in STOP. 4.2.3.16 Verify boric acid flow on FI-I13 and reactor makeup flow on FI -168 are at the pre-selected rates as displayed on MAKEUP FLOW TO CHGNCT indicator.
4.2.3 .17 IF desired to flush the acid from the line, THEN at the appropriate time to conclude the makeup with RMW only: (a) Verify RMW TO BLENDER valve QIE21FCV114B (QIE21 V345) open. (b) Close BORIC ACID TO BLENDER valve QIE21FCVI13A (QIE21 V354) Version 44.0 04/07/08 13:33:13 ( FNP-1-S0P-2.3 4.2.3.18 Verify makeup automatically stops when batch integrator setpoints are reached by observing the following: (a) Boric acid flow on FI-l13 and reactor makeup flow on FI-168 return to zero as displayed on MAKEUP FLOW TO CHGNCT indicator. (b) RMW TO BLENDER valve Q1E2lFCV114B (Q1E21V345) closed IF in AUTO. (c) BORIC ACID TO BLENDER valve Q1E21FCVl13A (QIE21V354) closed. 4.2.3.19 Close blender miscellaneous discharge isolation valve 1-CVC-V-8432 (Q1E21V237).
4.2.3.20 Close blender discharge to RWST valve 1-CVC-V-8434 (N1E21 V238). 4.2.3.21 Place MKUP TO VCT Q1E2lFCV114A (QIE2IV339) in AUTO. 4.2.3.22 Place MKUP TO CHG PUMP SUCTION HDR Q1E21FCVl13B (Q1E21 V337) in AUTO. 4.2.3.23 Verify RMW TO BLENDER valve Q1E21FCVl14B (Q1E21V345) in AUTO. 4.2.3.24 Verify BORIC ACID TO BLENDER valve Q1E21FCVl13A (Q1E21V354) in AUTO. Version 44.0 04/07/08 13:33:13 FNP-1-S0P-2.3 NOTE: The Boric Acid and/or Total Flow Batch Integrators ONLY need to be verified when changed. This should be documented with an Autolog Entry. 4.2.3.25 Set the boric acid and/or total flow batch integrators to the required quantities as needed for nonnal system operation.
4.2.3.26 IF the boric acid and/or reactor makeup water flow controllers were adjusted, THEN perfonn the following: (a) Verify the BORIC ACID MKUP FLOW controller FK 113 is in the MAN position. (AI2005205348) (b) Restore FK -113 controller to the setpoint required for automatic makeup per step 4.1.2 (c) Verify FK-168 PRI WTR MKUP FLOW controller in Auto. NOTE: The following two steps are not required if operation in a mode other than automatic is required.
4.2.3.27 Position the MKUP MODE SEL SWITCH to AUTO. 4.2.3.28 Position the MKUP MODE CONT SWITCH to START. 4.2.3.29 IF the Refueling Water Purification Pump was secured in Step 4.2.3.4, THEN perfonn the following: (a) Start the RWP pump. (b) Throttle SFP purification outlet to RWST 1-SFP-V-8793B (N1G31V021B) to establish 100 gpm on the SFP demineralizer FI-654. 4.2.3.30 Independently verify Closed the following:
* Blender Miscellaneous Discharge Isolation valve 1-CVC-V-8432 (Q1E21V237).
* Blender Discharge To RWST valve 1-CVC-V-8434 (N1E21 V238). Version 44.0 04/07/08 13:33:13 FNP-I-S0P-2.3 4.2.4 Makeup to Recycle Holdup Tanks (RHT) NOTE: IF desired to flush the line of acid following makeup, THEN remember to perform step 4.2.4.18 at an appropriate time prior to reaching the Total Flow Integrator setpoint.
4.2.4.1 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
* N omographs 4.2.4.2 IF the final boron concentration in the RHT is going to differ from the initial, THEN use the following formulas or the reactivity briefing sheets to determine the amount of water and/or acid to be added. To dilute the RHT: VA = CI -CF (VI) CF To borate the RHT: VA = CI -CF (VI) CF-CA To use a blend: CB
= (CFxVF)-(CIxVI)
VA Where: VA = Amt. of water and/or acid added to the RHT VI = Initial quantity in RHT VF = Final quantity in RHT CI = Initial boron concentration in RHT CF = Final boron concentration in RHT CA = Boron concentration in BAT CB = Boron concentration of blended flow (use Nomographs, Figure 1, OR Reactivity Briefing Sheet to determine the amount of water and acid required)  Version 44.0 04/07/08 13:33:13 FNP-I-S0P-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. IF necessary, THEN the Total Flow may be set for < 120 gpm and the Boric Acid Flow rate adjusted proportionally to Total Flow.
* Flow rates may be adjusted using the controllers in manual or automatic.
* 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 RHT 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. 4.2.4.3 Set the boric acid flow controllers and batch integrators to the calculated flow rate and quantity value obtained in step 4.2.4.1 or 4.2.4.2.
* For boric acid only set the boric acid integrator to the desired value and RMW TO BLENDER QIE21FCV114B (QIE21V345) should be taken to close to ensure that only acid flow is obtained.
* For reactor makeup water only set the boric acid integrator to O. 4.2.4.4 Set the reactor makeup water flow controllers and batch integrators to the calculated flow rate and quantity value obtained in step 4.2.4.1 or 4.2.4.2.
* For boric acid only set the total flow integrator to 0 and RMW TO BLENDER QIE21FCV114B (QIE21V345) should be taken to close to ensure that only acid flow is obtained.
* For reactor makeup water only set the boric acid integrator to 0 and the total flow integrator to the desired value. 4.2.4.5 Verify closed waste condensate pump discharge to RHT's l-LWP-V-7229 (QIG21V031) 4.2.4.6 Align RCDT discharge to WHT per the following:
A) Open RCDT Disch to WHT, l-LWP-V-7137 (QIG21V009)
(100' PPR). B) Close RCDT pump discharge to RHT iso, 1-CVC-V-8551 (Q1E21V315)
(121' PPR). Version 44.0 04/07/08 13:33:13 FNP-1-S0P-2.3 4.2.4.7 Align the RHT that will be made up to on service AND secure the previous on service RHT per FNP-1-S0P-2.4, CHEMICAL AND VOLUME CONTROL SYSTEM BORON RECYCLE SYSTEM. 4.2.4.8 Place control switch for recycle evaporator feed demineralizer automatic bypass valve Q1E21TCV250 (Q1E21V361) to FILTER position. (The control switch is located on the liquid waste panel.) 4.2.4.9 Open blender discharge to RHT's valve 1-CVC-V-8553 (Q 1E21 V280). 4.2.4.10 Open blender miscellaneous discharge isolation valve 1-CVC-V-8432 (Q1E21V237).
4.2.4.11 Position the MKUP MODE CONT SWITCH to STOP. 4.2.4.12 Position the MKUP MODE SEL SWITCH to MAN. NOTE: Makeup may be stopped at any time by positioning the MKUP MODE CONT SWITCH to STOP. 4.2.4.13 Place MKUP TO CHG PUMP SUCTION HDR Q1E21FCVl13B (Q1E21 V337) in the CLOSED position.
4.2.4.14 Place MKUP TO VCT Q1E21FCV114A (Q1E21V339) in the CLOSED position.
4.2.4.15 Position the MKUP MODE CONT SWITCH to START. 4.2.4.16 IF 1B RMW PUMP is running and not required for current plant conditions, THEN place the 1B RMW PUMP handswitch to STOP. 4.2.4.17 Boric acid flow on FI-l13 and reactor makeup flow on FI-168 are at the pre-selected rates as displayed on MAKEUP FLOW TO CHGNCT indicator.
4.2.4.18 IF desired to flush the acid from the line, THEN at the appropriate time to conclude the makeup with RMW only: (a) Verify RMW TO BLENDER valve QIE21FCVl14B (Q1E21V345) open. (b) Close BORIC ACID TO BLENDER valve Q1E21FCVl13A (Q1E21V354)  Version 44.0 04107/08 13:33:13 _-{fl FNP-1-S0P-2.3 4.2.4.19 Verify makeup automatically stops when batch integrator setpoints are reached by observing that boric acid flow on FI -113 and reactor makeup flow on FI -168 return to zero as displayed on MAKEUP FLOW TO CHGNCT indicator.
4.2.4.20 Close blender miscellaneous discharge isolation valve 1-CVC-V-8432 (Q1E21V237).
4.2.4.21 Close blender discharge to RHT's valve l-CVC-V-8553 (Q1E21V280).
4.2.4.22 Place MKUP TO VCT Q1E21FCVl14A (QIE21 V339) in AUTO. 4.2.4.23 Place MKUP TO CHG PUMP SUCTION HDR QIE21FCVl13B (Q1E21 V337) in AUTO. 4.2.4.24 Verify BORIC ACID TO BLENDER valve QIE21FCVI13A (QIE21V354) in AUTO. 4.2.4.25 IF required THEN Return RMW TO BLENDER QIE21FCV114B (QIE21V345) control switch to AUTO. NOTE: The Boric Acid and/or Total Flow Batch Integrators ONLY need to be verified when changed. This should be documented with an Autolog Entry. 4.2.4.26 Set the boric acid and/or total flow batch integrators to the required quantities as needed for normal system operation.
4.2.4.27 IF the boric acid and/or reactor makeup water flow controllers were adjusted, THEN perform the following: (a) Verify the BORIC ACID MKUP FLOW controller FK 113 is in the MAN position. (AI2005205348) (b) Restore controller FK-I13 to the setpoint required for automatic makeup per step 4.1.2. (c) Verify FK-168 PRI WTR MKUP FLOW controller in Auto. Version 44.0 04/07/08 13:33:13 T 1 FNP-1-S0P-2.3 NOTE: The following two steps are not required if operation in a mode other than automatic is required.
4.2.4.28 Position the MKUP MODE SEL SWITCH to AUTO. 4.2.4.29 Position the MKUP MODE CONT SWITCH to START. 4.2.4.30 Align RCDT discharge to RHT per the following:
* Open RCDT pump discharge to RHT 1-CVC-V-8551 (Q1E21 V315) (121 'PPR).
* Close RCDT disch to WHT 1-LWP-V-7137 (Q1G21V009).
(100' PPR) 4.2.4.31 Position control switch for recycle evaporator feed demineralizer automatic bypass valve Q1E21 TCV250 (Q1E21 V361) to the DEMIN position until red light is illuminated THEN place handswitch in AUTO position. (The control switch is located on the liquid waste panel.) 4.2.4.32 Remove batched up RHT from service and place another RHT on service IF required per FNP-1-S0P-2.4, CHEMICAL AND VOLUME CONTROL SYSTEM BORON RECYCLE SYSTEM. 4.2.4.33 Independently Verify the following:
* Verify MKUP TO VCT Q1E21FCVl14A (Q1E21V339) in AUTO.
* Verify close blender discharge to RHT's valve 1-CVC-V-8553 (Q1E21V280).
* Verify open RCDT pump discharge to RHT 1-CVC-V-8551 (Q1E21V315)
(121 'PPR).
* Verify close RCDT DISCH to WHT 1-LWP-V-7137 (Q1G21V009).
(100' PPR) Version 44.0 04/07/08 13:33:13 FNP-l-SOP-2.3 4.2.5 Makeup to SFP Through Temporary Connection NOTE: This procedure is intended for situations when normal makeup to the SFP is not available and should not be used for normal makeup to the SFP. IF desired to flush the line of acid following makeup, THEN remember to perform step 4.2.5.14 at an appropriate time prior to reaching the batch integrator setpoint.
4.2.5.1 4.2.5.2 Verify that the SFP is capable of receiving makeup. Verify blender miscellaneous discharge isolation valve I-CVC-V-8432 (QIE21V237) closed. NOTE: The following step will open a section of 2 inch diameter pipe approximately 40 feet long requiring a catch bag routed to the nearest equipment drain be rigged prior to commencing.
4.2.5.3 Remove blind flange from the temporary connection and install temporary hose routed to the SFP. 4.2.5.4 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
* N omographs  Version 44.0 04/07/08 13:33:13 FNP-I-S0P-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. IF necessary, THEN the Total Flow may be set for < 120 gpm and the Boric Acid Flow rate adjusted proportionally to Total Flow.
* Flow rates may be adjusted using the controllers in manual or automatic.
* 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 SFP 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. 4.2.5.5 Set the boric acid flow controllers and batch integrators to the calculated flow rate and quantity value obtained in step 4.2.5.4.
* For boric acid only set the boric acid integrator to the desired value and RMW TO BLENDER QIE21FCVl14B (QIE21 V345) should be taken to close to ensure that only acid flow is obtained.
* For reactor makeup water only set the boric acid integrator to O. 4.2.5.6 Set the reactor makeup water flow controllers and batch integrators to the calculated flow rate and quantity value obtained in step 4.2.5.4.
* For boric acid only set the total flow integrator to 0 and RMW TO BLENDER QIE21FCV114B (QIE21V345) should be taken to close to ensure that only acid flow is obtained.
* For reactor makeup water only set the boric acid integrator to 0 and the total flow integrator to the desired value. 4.2.5.7 Position the MKUP MODE CONT SWITCH to STOP. 4.2.5.8 Position the MKUP MODE SEL SWITCH to MAN. 4.2.5.9 Open blender miscellaneous discharge isolation valve l-CVC-V-8432 (QIE21V237).
4.2.5.10 Place MKUP to CHG PUMP SUCTION HDR QIE21FCVl13B (QIE21V337) in the CLOSED position.
4.2.5.11 Place MKUP to VCT QIE21FCV1l4A (QIE21V339) in the CLOSED position. Version 44.0 04/07/08 13:33:13 FNP-I-S0P-2.3 NOTE: Makeup may be stopped at any time by positioning the MKUP MODE CONT SWITCH to STOP. 4.2.5.12 Position the MKUP MODE CONT SWITCH to START. 4.2.5.13 IF IB RMW PUMP is running and not required for current plant conditions, THEN position the IB RMW PUMP handswitch to STOP. 4.2.5.14 Boric acid flow on FI-I13 and reactor makeup flow on FI-168 are at the pre-selected rates as displayed on MAKEUP FLOW TO CHGNCT indicator.
4.2.5.15 IF desired to flush the acid from the line, THEN at the appropriate time to conclude the makeup with RMW only: (a) Verify RMW TO BLENDER valve QIE21FCV114B (QIE21V345) open. (b) Close BORIC ACID TO BLENDER valve QIE21FCVI13A (QIE21 V354) 4.2.5.16 Verify makeup automatically stops when batch integrator setpoints are reached by observing the following: (a) Boric acid flow on FI-I13 and reactor makeup flow on FI-168 return to zero as displayed on MAKEUP FLOW TO CHG/VCT indicator. (b) RMW TO BLENDER QIE21FCV114B (QIE21V345) closed. (c) BORIC ACID TO BLENDER QIE21FCVI13A (QIE21V354) closed. 4.2.5.17 Close blender miscellaneous discharge isolation valve l-CVC-V-8432 (QIE21V237).
4.2.5.18 Place the following valve control switches to AUTO: (a) MKUP TO CHG PUMP SUCTION HDR QIE21FCVI13B (QIE21V337). (b) MKUP TO VCT QIE21FCV114A (QIE21V339).
4.2.5.19 Verify BORIC ACID TO BLENDER valve QIE21FVI13A (QIE21 V354) in AUTO. Version 44.0 
( ( 04107/08 13:33:13 FNP-1-S0P-2.3 4.2.5.20 IF required THEN Return RMW TO BLENDER Q1E21FCVl14B (Q1E21 V345) control switch to AUTO. NOTE: The Boric Acid and/or Total Flow Batch Integrators ONLY need to be verified when changed. This should be documented with an Autolog Entry. 4.2.5.21 Set the boric acid andlor total flow batch integrators to the required quantities as needed for normal system operation.
4.2.5.22 IF the boric acid andlor reactor makeup water flow controllers were adjusted, THEN perform the following: (a) Verify the BORIC ACID MKUP FLOW controller FK 113 is in the MAN position. (AI2005205348) (b) Restore controller FK-l13 to the setpoint required for automatic makeup per step 4.1.2. (c) Verify FK-168 PRI WTR MKUP FLOW controller in Auto. NOTE: The following two steps are not required if operation in a mode other than automatic is required.
4.2.5.23 Position the MKUP MODE SEL SWITCH to AUTO. 4.2.5.24 Position the MKUP MODE CONT SWITCH to START. 4.2.5.25 Remove the temporary hose from the temporary connection and install blind flange. 4.2.5.26 Independently Verify the following:
* Verify Closed blender miscellaneous discharge isolation valve I-CVC-V-8432 (Q1E21V237).
* RMW TO BLENDER Q1E21FCVl14B (Q1E21 V345) in AUTO.
* BORIC ACID TO BLENDER Q1E21FCVl13A (Q1E21V354) in AUTO. Version 44.0 
( 04/07/08 13:33:13 1 T 1 FNP-1-S0P-2.3 4.3 Boration NOTE: Appendix B, OPERATOR AID FOR BORATION AND DILUTION, may be used without referring to this procedure section under the following conditions:
* Routine boration for temperature control.
* Boration in response to an unplanned or unscheduled power change.
* Scheduled power changes. Figure 6 may be applied at the discretion of the SS when use of the emergency boration tlowpath is desired. 4.3.1 During or following a change of boron concentration of greater than 5 ppm in the RCS, the pressurizer spray must be operated to equalize the concentration throughout the system. Automatic operation of the spray should be initiated by manual operation of the pressurizer heaters when there is a steam bubble in the pressurizer.
4.3.2 Determine the existing Reactor Coolant boron concentration by sample analysis or from an estimate based on a previous sample. 4.3.3 Determine the magnitude of the boron concentration increase required from core physics curves or during normal operation, when compensating for xenon or core burnup, the magnitude may be estimated based on time in core life and previous experience.
4.3.4 Determine the volume of boric acid required for boration from the boron addition nomograph, Figure 2, from the borationldilution tables, Reactivity Briefmg Sheet or from estimate based on time in core life and previous experience. Version 44.0 04/07/08 13:33:13 1 FNP-I-S0P-2.3 NOTE: IF waste gas system is shutdown, THEN VCT level should be maintained such that VCT pressure is not lowered to the point where the pressure regulator will admit more Hz or Nz to the VCT. Repeatedly allowing pressure to drop to this point will eventually result in having to start up the waste gas system to remove excess VCT gas. In addition, VCT level changes should be limited to prevent excessive perturbation of the RCP seals. 4.3.5 IF necessary, THEN adjust LTDN TO VCT FLOW LK 112 setpoint down to the pot setting corresponding to the desired VCT level to prevent compressing the gas space. NOTE: The boric acid flow required to achieve a desired boration rate may be determined from boron addition rate nomograph, Figure 3. 4.3.6 Position the MKUP MODE CONT SWITCH to STOP. 4.3.7 Position the MKUP MODE SEL SWITCH to BOR. NOTE: The Boric Acid and/or Total Flow Batch Integrators ONLY need to be verified when changed. This should be documented with an Autolog Entry. 4.3.8 Set the Boric Acid MKUP Flow Controller and Boric Acid Batch Integrator to the flowrate and quantity values obtained from step 4.3.3 and 4.3.4. NOTE:
* Boration may be stopped at any time by positioning the MKUP MODE CONT SWITCH to STOP.
* Verify the expected Reactivity changes by observing VCT level, Tavg, SR SUR, IR SUR, and Control Rod Motion. Stop the Make-Up System operation and take corrective action if any change is excessive or in the wrong direction.
4.3.9 Position the MKUP MODE CONT SWITCH to START. 4.3.10 Verify proper boration operation by observing the following:
* On service boric acid pump started.
* MKUP TO CHG PUMP SUCTION HDR QIE21FCVI13B opens.
* BORIC ACID TO BLENDER QIE21FCVI13A opens.
* Boric acid flow is displayed on FI-I13 MAKEUP FLOW TO CHGNCT. 4.3.11 Verify that boration automatically stops when the boric acid batch integrator reaches its setpoint as follows:
* Boric acid flow returns to zero as displayed on FI -113 MAKEUP FLOW TO CHGNCT.
* MKUP TO CHG PUMP SUCTION HDR QIE2IFCVI13B closes.
* BORIC ACID TO BLENDER QIE21FCVI13A closes. Version 44.0 04/07/08 13:33:13 1 1 FNP-I-S0P-2.3 NOTE: The following four steps are not required if operation in a mode other than automatic is preferred.
For example: when frequent borations are required because of changing core conditions it may be desirable to leave the reactor makeup system aligned for the current operational need and minimize system manipulation.
Use appendix C for guidance in repetitive borations.
4.3.12 Position the MKUP MODE SEL SWITCH to AUTO. 4.3.13 Position the MKUP MODE CONT SWITCH to START. 4.3.14 IF the boric acid and/or reactor makeup water flow controllers were adjusted, THEN perform the following: (a) Verify the BORIC ACID MKUP FLOW controller FK 113 is in the MAN position. (AI2005205348) (b) Restore controller FK-113 to the setpoint required for automatic makeup per step 4.1.2. (c) Verify FK-168 PRI WTR MKUP FLOW controller in Auto. 4.3.15 IF LK 112 setpoint was adjusted per Step 4.3.5, THEN return setpoint to that required for current conditions.
4.4 Dilution NOTE:
* Appendix B, OPERATOR AID FOR BORATION AND DILUTION, may be used without referring to this procedure section under the following conditions:
a) Routine dilution for temperature control. b) Scheduled power changes.
* IF MKUP TO VCT QIE21FCV114A is not operable, THEN Alternate Dilution is required in step 4.4.8. 4.4.1 During or following a change of boron concentration of greater than 5 ppm in the RCS, the pressurizer spray must be operated to equalize the concentration throughout the system. Automatic operation of the spray should be initiated by manual operation of the pressurizer heaters when there is a steam bubble in the pressurizer.
4.4.2 Determine the existing reactor coolant boron concentration by sample analysis, or from an estimate based on the previous sample. Version 44.0 
{ \ 04/07/08 13:33:13 FNP-1-S0P-2.3 4.4.3 Determine the magnitude of the boron concentration decrease required from core physics curves or during normal operation, when compensating for xenon or core burnup, the magnitude may be estimated based on time in core life and previous experience.
4.4.4 Determine the volume of reactor makeup water required for dilution from the dilution nomograph, Figure 4, from borationldilution tables, Reactivity Briefing Sheet or from estimate based on time in core life and previous experience.
NOTE: IF waste gas system is shutdown, THEN VeT level should be maintained such that VeT pressure is not lowered to the point where the pressure regulator will admit more H2 or N2 to the VeT. Repeatedly allowing pressure to drop to this point will eventually result in having to start up the waste gas system to remove excess VeT gas. In addition, VeT level changes should be limited to prevent excessive perturbation of the Rep seals. 4.4.5 IF necessary, THEN adjust LTDN TO VCT FLOW LK 112 setpoint down to the pot setting corresponding to the desired VCT level to prevent compressing the gas space. NOTE:
* The dilution water flow required to achieve a desired dilution rate may be determined from boron dilution rate nomograph, Figure 5.
* The Boric Acid and/or Total Flow Batch Integrators ONLY need to be verified when changed. This should be documented with an Autolog Entry. 4.4.6 Set the PRI WTR MKUP FLOW (RMW) Controller and Total Flow Batch Integrator to the flow rate and quantity values obtained from step 4.4.3 and 4.4.4. 4.4.7 Position the MKUP MODE CONT SWITCH to STOP. Version 44.0 
( 04/07/08 13:33:13 FNP-1-S0P-2.3 NOTE: The use of the AL T DIL MODE can affect the ability to control hydrogen concentration in the RCS. 4.4.8 Position the MKUP MODE SEL SWITCH to DIL or ALT DIL. 4.4.9 IF using the AL T DIL MODE AND it is desired to bypass the VCT and dilute straight to the charging pump suction, THEN place MKUP TO VCT valve QIE2lFCVl14A (Q1E21V339) in close. NOTE:
* Dilution may be stopped at any time by positioning the MKUP MODE CONT SWITCH to STOP
* Verify the expected Reactivity changes by observing VCT level, Tavg, SR SUR, IR SUR, and Control Rod Motion. Stop the Make-Up System operation and take corrective action if any change is excessive or in the wrong direction.
4.4.10 Position the MKUP MODE CONT SWITCH to START. 4.4.11 IF 1B RMW PUMP is running and not required for current plant conditions, THEN position the 1B RMW PUMP handswitch to STOP. 4.4.12 Verify dilution operation by observing the following:
* IF using AL T DIL, MAKEUP TO CHG PUMP SUCTION HDR Q1E21FCV113B opens.
* MKUP TO VCT Q1E21FCV114A opens, unless bypassing VCT.
* RMW TO BLENDER Q1E21FCV114B opens.
* Reactor makeup flow is displayed on FI-168 MAKEUP FLOW TO CHGNCT. Version 44.0 04/07/08 13:33:13 T 1 FNP-I-S0P-2.3 4.4.13 Verify dilution automatically stops when the reactor makeup water batch integrator reaches its setpoint as follows:
* Reactor makeup flow returns to zero as displayed on FI-168 MAKEUP FLOW TO CHGNCT.
* MKUP TO VCT QIE21FCV114A closes.
* RMW TO BLENDER QIE21FCV114B closes.
* IF ALT DIL was used, THEN MAKEUP TO CHG PUMP SUCTION HDR QIE21FCVI13B closes. 4.4.14 IF VCT bypassed per step 4.4.9, THEN place MKUP TO VCT valve QIE21FCV114A (QIE21V339) to AUTO. NOTE: The following three steps are not required if operation in a mode other than automatic is preferred.
For example: when frequent dilutions are required because of changing core conditions it may be desirable to leave the reactor makeup system aligned for the current operational need and minimize system manipulation.
Use appendix C for guidance in repetitive dilutions.
4.4.15 Position the MKUP MODE SEL SWITCH to AUTO. 4.4.16 Position the MKUP MODE CONT SWITCH to START. 4.4.17 IF LK 112 setpoint was adjusted per Step 4.4.5, THEN return setpoint to that required for current conditions. Version 44.0 
( 04/07/08 13:33:13 FNP-1-S0P-2.3 4.5 Combined Boration 1 Dilution NOTE: Appendix B, OPERATOR AID FOR BORATION AND DILUTION, may be used without referring to this procedure section under the following conditions:
* Routine boration/dilution for temperature control.
* Scheduled power changes. NOTE: Early in the core cycle it is necessary to borate to compensate for burnup of discreet poisons. It is also desirable to maintain the discharge line from the blender clear of acid. This procedure section is designed to accomplish this by borating and then immediately diluting to flush the acid into the charging pump suction. 4.5.1 Determine the volume of boric acid AND reactor makeup water required (to flush the line clear) based on Rx power, TAVG, Reactivity Briefing Sheet, reactivity change due to xenon, time in core life, and/or previous expenence.
NOTE: IF the waste gas system is shutdown, THEN VeT level should be maintained such that VeT pressure is not lowered to the point where the pressure regulator will admit more H2 or N2 to the VeT. Repeatedly allowing pressure to drop to this point will eventually result in having to start up the waste gas system to remove excess VeT gas. In addition, VeT level changes should be limited to prevent excessive perturbation of the Rep seals. 4.5.2 IF necessary, THEN adjust LTDN TO VCT FLOW LK 112 setpoint down to the pot setting corresponding to the desired VCT level to prevent compressing the gas space. 4.5.3 Position the MKUP MODE CONT SWITCH to STOP. 4.5.4 Position the MKUP MODE SEL SWITCH to BOR. NOTE: The Boric Acid andlor Total Flow Batch Integrators ONLY need to be verified when changed. This should be documented with an Autolog Entry. 4.5.5 Set the Boric Acid Batch Integrator and Total Flow Batch Integrator to the quantities determined in step 4.5.1. 4.5.6 Set the Boric Acid Flow Controller to the desired flow rate. Version 44.0 04/07/08 13:33:13 1 T 1 FNP-I-S0P-2.3 NOTE:
* Boration may be stopped at any time by positioning the MKUP MODE CONT SWITCH to STOP.
* Verify the expected Reactivity changes by observing VCT level, Tavg, SR SUR, IR SUR, and Control Rod Motion. Stop the Make-Up System operation and take corrective action if any change is excessive or in the wrong direction.
4.5.7 Position the MKUP MODE CONT SWITCH to START. 4.5.8 Verify proper boration operation by observing the following:
* On service boric acid pump started.
* MKUP TO CHG PUMP SUCTION HDR QIE21FCVl13B opens.
* BORIC ACID TO BLENDER QIE21FCVl13A opens.
* Boric acid flow is displayed on FI-l13 MAKEUP FLOW TO CHGNCT. 4.5.9 Verify that boration automatically stops when the boric acid batch integrator reaches its setpoint as follows:
* Boric acid flow returns to zero as displayed on FI -113 MAKEUP FLOW TO CHGNCT.
* MKUP TO CHG PUMP SUCTION HDR QIE2IFCVI13B closes.
* BORIC ACID TO BLENDER QIE2IFCVI13A closes. 4.5.10 Position the MKUP MODE CONT SWITCH to STOP. NOTE: The use of the AL T DIL MODE can affect the ability to control hydrogen concentration in the RCS. 4.5.11 Align the makeup system for flushing as follows:
* Position the MKUP MODE SEL SWITCH to AL T DIL.
* Place MKUP TO VCT valve QIE21FCVI14A (QIE21 V339) in close.
* Set the reactor makeup water flow controller to the desired flow rate. Version 44.0 04/07/08 13:33:13 1 T 1 FNP-1-S0P-2.3 NOTE:
* Boration may be stopped at any time by positioning the MKUP MODE CONT SWITCH to STOP.
* Verify the expected Reactivity changes by observing VCT level, Tavg, SR SUR, IR SUR, and Control Rod Motion. Stop the Make-Up System operation and take corrective action if any change is excessive or in the wrong direction.
4.5.12 Position the MKUP MODE CONT SWITCH to START. 4.5.13 IF 1B RMW pump is running and not required for current plant conditions, THEN position the 1B RMW PUMP handswitch to STOP. 4.5.14 Verify proper dilution operation by observing the following:
* MAKEUP TO CHG PUMP SUCTION HDR Q1E21FCV113B (Q1E21 V337) opens.
* Reactor makeup flow on FI -168 is at the pre-selected rate as displayed on MAKEUP FLOW TO CHGNCT indicator.
4.5 .15 Verify dilution automatically stops when the total flow batch integrator reaches its setpoint by observing the following:
* Reactor makeup flow on FI-168 returns to zero as displayed on MAKEUP FLOW TO CHGNCT indicator.
* MAKEUP TO CHG PUMP SUCTION HDR Q1E21FCV113B (Q1E21 V337) closed. Version 44.0 
( 04107108 13:33:13 FNP-I-S0P-2.3 4.5.16 Place MKUP TO VCT valve QIE21FCV114A (QIE21 V339) in AUTO. NOTE: The following four steps are not required if operation in a mode other than automatic is preferred.
4.5.17 Position the MKUP MODE SEL SWITCH to AUTO. 4.5.18 Position the MKUP MODE CONT SWITCH to START. 4.5.19 IF the boric acid and/or reactor makeup water flow controllers were adjusted, THEN perform the following: (a) Verify the BORIC ACID MKUP FLOW controller FK 113 is in the MAN position.(AI2005205348) (b) Restore controller FK -113 to the setpoint required for automatic makeup per step 4.1.2. (c) Verify FK-168 PRI WTR MKUP FLOW controller in Auto. 4.5.20 IF LK 112 setpoint was adjusted in step 4.5.2, THEN return setpoint to that required for current conditions. Version 44.0 
( 04/07/08 13:33:13 FNP-1-S0P-2.3 4.6 Verify Reactor Makeup Control System Aligned for Auto Makeup 4.6.1 Determine the existing RCS boron concentration by sample analysis or from an estimate based on the previous sample. 4.6.2 Verify the following:
4.6.2.1 4.6.2.2 BORIC ACID MKUP FLOW controller FK 113 is in the MAN position and the Potentiometer is set to the value obtained from the blended flow nomographs, Figure 1, or reactivity briefmg sheet to obtain makeup value having a boron concentration equal to RCS boron concentration. (AI2005205348)
Verify FK-168 PRI WTR MKUP FLOW controller in Auto. 4.6.3 Position the MKUP MODE CONT SWITCH to STOP. 4.6.4 Verify MKUP TO CHG PUMP SUCTION HDR Q1E21FCVl13B closed with handswitch in the AUTO position.
4.6.5 Verify BORIC ACID TO BLENDER Q1E21FCVl13A closed with handswitch in the AUTO position.
4.6.6 Verify MKUP TO VCT Q1E21FCVl14A closed with handswitch in the AUTO position.
4.6.7 Verify RMW TO BLENDER Q1E21FCVl14B closed with handswitch in the AUTO position.
4.6.8 Verify 1A and 1B BATP secured with the on-service BATP handswitch in the AUTO position 4.6.9 Verify 1A (preferred) or 1B RMWP supplying Reactor Makeup System with water. 4.6.10 IF 1B RMW PUMP is running and is not required for current plant conditions, THEN position the 1B RMW PUMP handswitch to STOP and back to AUTO. 4.6.11 IF 1A RMW PUMP is running and is not required for current plant conditions, THEN position the 1A RMW PUMP handswitch to STOP and back to AUTO. 4.6.12 Position the MKUP MODE SEL SWITCH to AUTO. 4.6.13 Position the MKUP MODE CONT SWITCH to START. Version 44.0 
( ( 04/07/08 13:33:13 FNP-I-S0P-2.3 4.7 Large Volume Boration of ReS NOTE: To protect the RCP Seals, increase the monitoring of the Seal Injection fIlter DP, due to the possibility of RCS Crud Burst or other contaminants clogging the Filter. 4.7.1 During or following a change of boron concentration of greater than 5 ppm in the ReS, the pressurizer spray must be operated to equalize the concentration throughout the system. Automatic operation of the spray should be initiated by manual operation of the pressurizer heaters when there is a steam bubble in the pressurizer.
4.7.2 Determine the existing reactor coolant boron concentration by sample analysis or from an estimate based on a previous sample. 4.7.3 Determine the magnitude of the boron concentration increase required from core physics curves or during normal operation, when compensating for xenon or core burnup, the magnitude may be estimated based on time in core life and previous experience.
NOTE: In the following step, the volume of boric acid to be used can be calculated by using the change in level of the on service boric acid tank OR by using the flow rate indicated on FI-110 multiplied by time to obtain gallons. 4.7.4 Determine the volume of boric acid required for boration from the boron addition nomograph, Figure 2, from the borationldilution tables, Reactivity Briefing Sheet or from estimate based on time in core life and . . preVIOUS expenence.
NOTE: IF waste gas system is shutdown, THEN VCT level should be maintained such that VCT pressure is not lowered to the point where the pressure regulator will admit more H2 or N2 to the VCT. Repeatedly allowing pressure to drop to this point will eventually result in having to start up the waste gas system to remove excess VCT gas. In addition, VCT level changes should be limited to prevent excessive perturbation of the RCP seals. 4.7.5 IF necessary, THEN adjust LTDN TO VeT FLOW LK 112 setpoint down to the pot setting corresponding to the desired VeT level to prevent compressing the gas space. 4.7.6 Start a Boric Acid Transfer Pump. Version 44.0 04/07/08 13:33:13 T 1 FNP-1-S0P-2.3 I NOTE: Boric acid flow may stopped at any time by closing MOV8104. 4.7.7 Open QIE21MOV8104 EMERG BORATE TO CHG PUMP SUCT to initiate boric acid flow. 4.7.8 Verify proper boric acid flow by flow indicated on FI-I10 BORIC ACID EMERG BORATE flow indicator.
4.7.9 After the desired volume of boric acid has transferred, close Q1E21MOV8104 EMERG BORATE TO CHG PUMP SUCT. 4.7.10 Stop the Boric Acid Transfer Pump started in step 4.7.6. 4.7.11 IF LK 112 setpoint was adjusted per Step 4.7.5, THEN return setpoint to that required for current conditions.
5.0 References 5.1 Drawings P&ID -D-175039 -CVCS, sheets 3, 6 and 7 5.2 FSAR Chapter 9.3 5.3 PCN B92-0-8134, Reactor Makeup Water Cross-Tie 5.4 Safety Evaluation
-Revised Operation of the Gaseous Waste Processing System to Allow Non-continuous Purge of the VCT, SECL-93-125, NEL-93-0231 Version 44.0 04/07/08 13:33:13 FNP-I-S0P-2.3 TABLE 1 NOMOGRAPH CORRECTION FACTORS Plant Conditions Correction Factor Pressure T (AVG) Pressurizer Level (K) (psig) (OF) (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 Nomograpbs V(Corrected)
= K X V(Nomograph) (b) Boron Addition and Dilution Rate Nomograpbs dc 1 dc -( Corrected) = -x -(Nomograph) dt K dt Page 1 of 1 Version 44.0 04/07/08 13:33:13 FNP-l-S0P-2.3 FIGURE 1 RCSBORON 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 of3 Version 44.0 04/07/08 13:33:13 FNP-I-S0P-2.3 Coolant 4wt. % / FK-I13 Coolant 4wt. % / FK-I13 Coolant 4wt. % / 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 (gpm) (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 &#xa3; 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 of3 Version 44.0 04/07/08 13:33:13 1 FNP-I-S0P-2.3 Coolant 4wt. % / FK-l13 Coolant 4wt. % / FK-113 Coolant 4wt. % / FK-l13 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 NOTE:
* Due to characteristics of the reactor makeup system piping, the maximum obtainable boric acid flow is less than 40 gpm *
* 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 gpm. 2500 ppm 21.45 gpm with a pot setting of 5.35 for a blended flow of 60 gpm. BLENDED FLOW BASED ON 120 GPM AUTO MAKEUP Page 3 of3 Version 44.0 04/07/08 13:33:13 1 FNP-I-SOP-2.3 FIGURE 2 600 3600 500 3000 2500 M (7000-C f) 300 VB = 8.33 In 7000-C j 2100 -CD > 200 -....I 1500 -oct -(.) .. 2000 <!' ISO <.) -UJ
* I-!&sect; .... z 900 (.) oct ....I -....I 0 0 > 100 z: 0 0 (.) 0. 90 -I-Z (.) 600 80 1500 oct 0 0 z: (.) 70 < 0 D:: D:: 60 z: 0 0 0 CQ a) 0::: ::e: 0 50 eo 0-0-X 300 0-1000 30 500 ISO 20 100 The mass, M, for the above formula can be obtained from the BoronIDilution table for the appropriate RCS temp. Figure 2. Boron Addition -Refer to Table 1 for Correction Factors Page 1 of 1 Version 44.0 04/07/08 13:33:13 FNP-l-SOP-2.3
-c,,;) -z: c( ...J 0 0 c,,;), z: z: 0 eo:: 0 CD ::E c.. FIGURE 3 100 500 IJO 300 30 27 1000 -200 24-.... "0 -21 de 500X (7000-C) u "0 -= --dt M 150 18 >< eo:: :c -::It :=s: 15 Q,. Cl 1500 Q,. :::c: 0 "'"' ...J f-100 12 u. <C eo:: 90 II c Z u 0 80 10 c( f-9 c,,;) ,70 2000 c 0: c 8 0 c( CD z: 60 7 0 eo:: 0 50 CD 6 2500 qO 5 30 The mass, H, for the above formula can be obtained from the Boron/Dilution table for the appropriate Res temp.
: 3. Boron Addition Rate -Refer to Table 1 for Correction Factors Page 1 of 1 Version 44.0 04/07/08 13:33:13 1 T FIGURE 4 Vw =
In 50 60 8.0 100 200 500 1000* . 2000 3000 PPM IN COOLANT (C i) 5 to 15 20 30 50 tOO 150 200 300 500 PPM BORON DILUTION (C j -cfl 1 50 100 500 1000 3000 .5000 10,000 30,000 50,000 DILUTION WATER GAL. (V w) FNP-l-SOP-2.3 The mass, M, for the above formula can be obtained from the table for the appropriate Res temp. Figure 4 Boron Dilution -Refer to Table 1 for Corrcc1ion Factors Page 1 of 1 Version 44.0 04/07/08 13:33:13 3000 2000 1500 iooo 500 200 100 PPM BORON IN COOLM4T (C) 80 60 50 1 500 300 200 150 100 70 10 7 5 3 2 COOLANT DILUTION RATE (dC/dt) T 1 FIGURES -. de -= 500 CY dt M FNP-1-S0P-2.3 150 100 90 80 70 60 50 4-0 30 20 15 DILUTtON WATER FLOW, GPM (Y) The mass, H, for the above formula can be obtained from the ,Boron/Dilution table for the appropriate Res temp. Figure S. Boron Dilution Rate -Refer to Table 1 for Correction Factors Page 10f1 Version 44.0 04/07/08 13:33:13 T 1 FIGURE 6 USE OF EMERGENCY BORATION FLOWPATH (w/o AOP-27 ENTRY REQUIRED)
: 1. Start a Boric Acid Transfer Pump. 2. Open EMERG BORATE TO CHG PUMP SUCT QIE21MOV8104.
FNP-l-SOP-2.3
: 3. WHEN Boration Complete, THEN Close EMERG BORATE TO CHG PUMP SUCT QIE21MOV8104.
: 4. Secure the Boric Acid Transfer Pump. Ref. FNP-l-SOP-2.3 Ensure operator aid is updated if this figure is revised. Page lof 1 Version 44.0 04/07/08 13:33:13 1 T APPENDIX A 1 FNP-I-S0P-2.3 Appendix A Operation of the Chemical and Volume Control System Reactor Makeup Control System with the Makeup Mode Control Switch Inoperable 1.0 Purpose Allow makeup to the VCT for Boration or Dilution when the AUTO function is failed. 2.0 Initial Conditions The Makeup Mode Control Switch is failed and plant operations require either Boration or Dilution.
3.0 Precautions and Limitations.
3.1 When selecting FCV-114B and FCV-I13A to OPEN the valves will go to full open, not a throttled position, causing the flowrate to be higher than normal. 3.2 A controlled mixing of boron and RMW will not be possible for a blended flow to the VCT. 3.3 Large batch makeups during power operations to the VCT or Charging pump suction, especially early in core life, can result in unintended reactor power changes. The reactivity affects should be considered when planning batch size. Small batches should be used at any time in core life. (CR2004106233) 4.0 Instructions NOTE: Flowrate of makeup to the RCS may be indicated on Reactor Makeup Flow Indicator QIE21FI-168.
If not, tlowrate must be estimated by VCT level rise. 4.1 Boration 4.1.1 Determine the amount of Boration desired 4.1.2 Verify an inservice BATP running. Page 1 of2 Version 44.0 04/07/08 13:33:13 1 FNP-I-S0P-2.3 Appendix A
* Verify the expected Reactivity changes by observing VCT level, Tavg, SR SUR, IR SUR, and Control Rod Motion. Stop the Make-Up System operation and take corrective action if any change is excessive or in the wrong direction.
4.1.3 Place Boric Acid to Blender QIE21FCV113A to Open. 4.1.4 Place MKUP TO CHG PUMP SUCTION HDR QIE2IFCVI13B to open. 4.1.5 After desired amount of acid has entered the RCS close MKUP TO CHG PUMP SUCTION HDR QIE21FCVI13B.
4.1.6 Close BORIC ACID TO BLENDER Q lE21FCV113A.
NOTE: IF repeated borations are expected, THEN the inservice BATP may remain running until after the final boration is completed.
4.1.7 Secure the inservice BATP. 4.2 Dilution 4.2.1 Determine the Amount of Dilution desired. 4.2.2 Verify one RMWP supplying Reactor Makeup System with water. 4.2.3 Place RMW to Blender QIE21FCV 114B to Open.
* Verify the expected Reactivity changes by observing VCT level, Tavg, SR SUR, IR SUR, and Control Rod Motion. Stop the Make-Up System operation and take corrective action if any change is excessive or in the wrong direction.
4.2.4 Place MKUP TO CHG PUMP SUCTION Q1E21FCVI13B to Open 4.2.5 After desired amount of water has entered the RCS close MKUP TO CHG PUMP SUCTION QIE21FCV113B.
4.2.6 Close RMW TO BLENDER QIE21FCV114B Page 2 of2 Version 44.0 04/07/08 13:33:13 APPENDIXB
',1.',',",','
I FNP-I-S0P-2.3 AppendixB OPERATOR AID FOR BORATION AND DILUTION 1.0 Boration NOTE: The Boric Acid Integrator ONLY needs to be verified when changed. This should be documented with an Autolog Entry. DODD 1.1 DODD 1.2 DODD 1.3 DODD 1.4 DODD 1.5 DODD 1.6 IF necessary, THEN set the boric acid integrator to the desired quantity.
IF necessary, THEN adjust LTDN TO VCT FLOW LK 112 setpoint as desired. Position the MKUP MODE CONT SWITCH to STOP. Position the MKUP MODE SEL SWITCH to BOR. Position the MKUP MODE CONT SWITCH to START. Verify proper boration operation by observing the following:
* On service boric acid pump started.
* MKUP TO CHG PUMP SUCTION HDR QIE21FCVI13B opens.
* BORIC ACID TO BLENDER QIE21FCVI13A opens.
* Boric acid flow is displayed on FI-113 MAKEUP FLOW TO CHGNCT. o 0 0 0 1.7 Verify the boration automatically stops when the boric acid batch integrator reaches its setpoint as follows:
* Boric acid flow returns to zero as displayed on FI-l13 MAKEUP FLOW TO CHGNCT.
* MKUP TO CHG PUMP SUCTION HDR QIE21FCVI13B closes.
* BORIC ACID TO BLENDER Q1E21FCVI13A closes. o 0 0 0 1.8 If desired to clear the line of acid, perform the applicable steps of Appendix B section 2.0. NOTE: The following three steps are not required if operation in a mode other than automatic is preferred.
Refer to appendix C. o 0 0 0 1.9 Position the MKUP MODE SEL SWITCH to AUTO. DODD 1.10 Position the MKUP MODE CONT SWITCH to START. DOD 0 1.11 IF LK 112 setpoint was adjusted per Step 1.2, THEN return setpoint to that required for current conditions.
Page 1 of2 Version 44.0 Ensure posted operator aid is revised with any revision to this appendix 04/07/08 l3:33:l3 1 FNP-1-S0P-2.3 AppendixB OPERATOR AID FOR BORATION AND DILUTION 2.0 Dilution NOTE: The Total Batch Integrator ONLY needs to be verified when changed. This should be documented with an Autolog Entry. D D D D 2.1 IF necessary, THEN set the total batch integrator to the desired quantity. D D D D 2.2 IF necessary, THEN adjust LTDN TO VCT FLOW LK 112 setpoint as desired. D D D D 2.3 Position the MKUP MODE CONT SWITCH to STOP. D D D D 2.4 Align the makeup system for dilution as follows:
* Position the MKUP MODE SEL SWITCH to DIL or ALT DIL.
* IF using ALT DIL AND it is desired to bypass the VCT, THEN place the MKUP TO VCT valve Q1E21FCVl14A in close. D D D D 2.5 Position the MKUP MODE CONT SWITCH to START. D D D D 2.6 Verify proper dilution operation by observing the following:
* IF using ALT DIL, MAKEUP TO CHG PUMP SUCTION HDR Q1E21FCV1l3B opens.
* MKUP TO VCT Q1E21FCVl14A opens, unless bypassing VCT.
* RMW TO BLENDER Q1E21FCV114B opens.
* Reactor makeup flow is displayed on FI-168 MAKEUP FLOW TO CHGNCT. D D D D 2.7 Verify the dilution automatically stops when the total flow batch integrator reaches its setpoint by observing the following:
NOTE:
* Reactor makeup flow returns to zero as displayed on FI -168 MAKEUP FLOW TO CHGNCT.
* MKUP TO VCT Q1E21FCVl14A closes.
* RMW TO BLENDER Q1E21FCVl14B closes.
* IF ALT DIL was used, THEN MAKEUP TO CHG PUMP SUCTION HDR Q1E21FCV1l3B closes. The following four steps are not required if operation in a mode other than automatic is preferred.
Refer to appendIX C. D D D D 2.8 IF VCT was bypassed, THEN verify MKUP TO VCT valve Q1E21FCV114A (Q1E21V339) in AUTO. D D D D 2.9 Position the MKUP MODE SEL SWITCH to AUTO. D D D D 2.10 Position the MKUP MODE CONT SWITCH to START. D D D D 2.11 IF LK 112 setpoint was adjusted l'er Step 2.2, THEN return setpoint to that required for current conditIOns.
Page 2 of 2 Version 44.0 Ensure posted operator aid is revised with any revision to this appendix 04/07/08 13:33:13 1 FNP-I-S0P-2.3 AppendixC APPENDIXC OPERA TOR AID FOR REPETITIVE BORATION AND DILUTION 1.0 Boration NOTE: During periods of repetitive boration evolutions, to minimize the number of start/stop cycles on the boric acid pump, the handswitch maf be placed in START and allowed to return to AUTO to maintain the boric acid pump running. WHEN it is no longer desired to maintain the boric acid pump running continuously, THEN place the handswitch in STOP and return to AUTO. DODD 1.1 The Reactor Makeup Control system has been previously aligned for Boration.
DODD 1.2 DODD 1.3 Position the MKUP MODE CONT SWITCH to START. Verify proper boration operation by observing the following:
* On service boric acid pump started.
* MKUP TO CHG PUMP SUCTION HDR QIE21FCVI13B opens.
* BORIC ACID TO BLENDER QIE21FCVI13A opens.
* Boric acid flow is displayed on FI-I13 MAKEUP FLOW TO CHGNCT. DOD 0 1.4 Verify the boration automatically stops when the boric acid batch integrator reaches its setpoint as follows: NOTE:
* Boric acid flow returns to zero as displayed on FI-I13 MAKEUP FLOW TO CHGNCT.
* MKUP TO CHG PUMP SUCTION HDR QIE21FCVI13B closes.
* BORIC ACID TO BLENDER QIE21FCVI13A closes. WHEN it is no longer desired to maintain the line full of acid, THEN perform the applicable steps of Appendix B section 2.0 to flush the line. DODD 1.5 IF repetitive borations are no longer required THEN verify the system is aligned for Automatic makeup per steps 1.9 through 1. f 1 of AppendixB.
Page 1 of2 Version 44.0 Ensure posted operator aid is revised with any revision to this appendix 04/07/08 13:33:13 1 I FNP-I-SOP-2.3 AppendixC 2.0 Dilution o 0 0 0 2.1 The Reactor Makeup Control system has been previously aligned for Dilution or Alternate Dilution.
o 0 0 0 2.2 Position the MKUP MODE CONT SWITCH to START. o 0 0 0 2.3 Verify proper dilution operation by observing the following:
* IF using AL T DIL, MAKEUP TO CHG PUMP SUCTION HDR QIE21FCVI13B opens.
* MKUP TO VCT QIE21FCV114A opens, unless bypassing VCT.
* RMW TO BLENDER QIE21FCVl f4B opens.
* Reactor makeup flow is displayed on FI-168 MAKEUP FLOW TO CHGNCT. o 0 0 0 2.4 Verify the dilution automatically stops when the total flow batch integrator reaches its setpoint by observing the following:
* Reactor makeup flow returns to zero as displayed on FI-168 MAKEUP FLOW TO CHGNCT.
* MKUP TO VCT QIE21FCV114A closes or is closed if bypassing the VCT.
* RMW TO BLENDER QIE21FCV114B closes.
* IF ALT DIL was used, THEN MAKEUP TO CHG PUMP SUCTION HDR QIE21FCVI13B closes. o 0 0 0 2.5 IF repetitive dilutions are no longer required THEN verify the system is aligned for Automatic makeup per steps 2.8 through 2.11 of Appendix B. Page 2 of 2 Version 44.0 Ensure posted operator aid is revised with any revision to this appendix 
( 04/07/08 13:33:13 APPENDIXD FNP-1-S0P-2.3 AppendixD Operation of the Chemical and Volume Control System Reactor Makeup Control System with FIS 168 Total Flow Batch Integrator Unreliable 1.0 Purpose Allow makeup to the VCT for a dilution when the AUTO function is failed because FIS-168 Total Flow Batch Integrator is unreliable.
2.0 Initial Conditions 2.1 FIS-168 Total Flow Batch Integrator is failed or unreliable, and plant operations require a dilution.
2.2 The Chemical and Volume Control System is aligned for auto operation.
3.0 Precautions and Limitations 3.1 When selecting FCV -114 B to OPEN the valve will go to full open, not a throttled position, causing the flow rate to be higher than normal. 3.2 A controlled mixing of boron and RMW will not be possible for a blended flow to the VCT. 3.3 Large batch make ups during power operations to the VCT or Charging pump suction, especially early in core life, can result in unintended reactor power changes. The reactivity affects should be considered when planning batch size. Small batches should be used at any time in core life. (CR2004106233) 4.0 Instructions NOTE: Flow rate of makeup to the RCS may be indicated on Reactor Makeup Flow Indicator QIE21FI-168.
If not and flow rate is desired, flow rate must be estimated by VCT level rise. 4.1 Dilution 4.1.1 Determine the amount of dilution desired. 4.1.2 Verify one RMWP supplying Reactor Makeup System with water. Page 10f2 Version 44.0 04/07/08 13:33:13 T 1 FNP-I-S0P-2.3 AppendixD
* Verify the expected Reactivity changes by observing VCT level, Tavg, SR SUR, IR SUR, and Control Rod Motion. Stop the Make-Up System operation and take corrective action if any change is excessive or in the wrong direction.
4.1.3 Place RMW to Blender QIE21FCV114B to Open. 4.1.4 Place MKUP TO CHG PUMP SUCTION QIE21FCVI13B to Open. 4.1.5 WHEN desired, THEN close MKUP TO CHG PUMP SUCTION QIE21FCVl13B.
4.1.6 Close RMW TO BLENDER QIE21FCVl14B.
4.1.7 Place MKUP TO CHG PUMP SUCTION QIE21FCVI13B to AUTO. 4.1.8 Place RMW to Blender QIE21FCV114B to AUTO. NOTE: The following steps are required to reset the Total Flow Batch Integrator.
4.1.9 Position the MKUP MODE CONT SWITCH to STOP. 4.1.10 Position the MKUP MODE CONT SWITCH to START. Page 2 of2 Version 44.0 
( 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.4 Refueling Water Storage Tank (RWST) LCO 3.5.4 The RWST shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, 3, and 4. ACTIONS CONDITION REQUIRED ACTION A. RWST boron A.1 Restore RWST to concentration not within OPERABLE status. limits. QB RWST borated water temperature not within limits. B. RWST inoperable for B.1 Restore RWST to reasons other than OPERABLE status. Condition A. C. Required Action and C.1 Be in MODE 3. associated Completion Time not met. AMQ C.2 Be in MODE 5. Farley Units 1 and 2 3.5.4-1 RWST 3.5.4 COMPLETION TIME 8 hours 1 hour 6 hours 36 hours Amendment No. 146 (Unit 1) Amendment No. 137 (Unit 2)
RWST 3.5.4 SURVEILLANCE REQUIREMENTS SR 3.5.4.1 SR 3.5.4.2 SR 3.5.4.3 SURVEILLANCE
-----------------------------NOTE------------------------------
Only required to be performed when ambient air temperature is < 35&deg;F. Verify RWST borated water temperature is 35&deg;F. FREQUENCY 24 hours Verify RWST borated water volume is 471,000 7 days gallons. Verify RWST boron concentration is 2300 ppm and 7 days 2500 ppm. Farley Units 1 and 2 3.5.4-2 Amendment No. 146 (Unit 1) Amendment No. 137 (Unit 2)
RWST B 3.5.4 B 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) B 3.5.4 Refueling Water Storage Tank (RWST) BASES BACKGROUND Farley Units 1 and 2 The RWST supplies borated water to the Chemical and Volume Control System (CVCS) during abnormal operating conditions, to the refueling pool during refueling, and to the ECCS and the Containment Spray System during accident conditions.
The RWST supplies both trains of the ECCS and the Containment Spray System through separate, redundant supply headers during the injection phase of a loss of coolant accident (LOCA) recovery.
A motor operated isolation valve is provided in each header to isolate the RWST from the ECCS once the system has been transferred to the recirculation mode. The recirculation mode is entered when pump suction is manually transferred to the containment sump following receipt of the RWST -Low alarm. Use of a single RWST to supply both trains of the ECCS and Containment Spray System is acceptable since the RWST is a passive component, and passive failures are not required to be assumed to occur coincidentally with Design Basis Events. The switchover from normal operation to the injection phase of ECCS operation requires changing centrifugal charging pump suction from the CVCS volume control tank (VCT) to the RWST through the use of isolation valves. Each set of isolation valves is interlocked so that the VCT isolation valves will begin to close once the RWST isolation valves are fully open. Since the VCT is under pressure, the preferred pump suction will be from the VCT until the tank is isolated.
This will result in a delay in obtaining the RWST borated water. The effects of delay are discussed in the Applicable Safety Analyses section of these Bases. During normal operation in MODES 1, 2, and 3, the residual heat removal (RHR) pumps are aligned to take suction from the RWST. The ECCS and Containment Spray System pumps are provided with recirculation lines that ensure each pump can maintain minimum flow requirements when operating at or near shutoff head conditions.
When the suction for the ECCS and Containment Spray System pumps is transferred to the containment sump, the RWST flow paths must be isolated to prevent a release of the containment sump (continued)
B 3.5.4-1 Revision 0 BASES BACKGROUND (continued)
APPLICABLE SAFETY ANALYSES Farley Units 1 and 2 RWST B 3.5.4 contents to the RWST, which could result in a release of contaminants to the atmosphere and the eventual loss of suction head for the ECCS pumps. This LCO ensures that: a. The RWST contains sufficient borated water to support the ECCS during the injection phase; b. Sufficient water volume exists in the containment sump to support continued operation of the ECCS and Containment Spray System pumps at the time of transfer to the recirculation mode of cooling; and c. The reactor remains subcritical following a LOCA. Insufficient water in the RWST could result in insufficient cooling capacity when the transfer to the recirculation mode occurs. Improper boron concentrations could result in a reduction of SDM or excessive boric acid precipitation in the core following the LOCA, as well as excessive caustic stress corrosion of mechanical components and systems inside the containment.
During accident conditions, the RWST provides a source of borated water to the ECCS and Containment Spray System pumps. As such, it provides containment cooling and depressurization, core cooling, and replacement inventory and is a source of negative reactivity for reactor shutdown (Ref. 1). The design basis transients and applicable safety analyses concerning each of these systems are discussed in the Applicable Safety Analyses section of B 3.5.2, Operating";
B 3.5.3, "ECCS -Shutdown";
and B 3.6.6, "Containment Spray and Cooling Systems." These analyses are used to assess changes to the RWST in order to evaluate their effects in relation to the acceptance limits in the analyses.
The RWST must also meet volume, boron concentration, and temperature requirements for non-LOCA events. The volume is not an explicit assumption in non-LOCA events since the required volume is a small fraction of the available volume. The deliverable volume limit is set by the LOCA and containment analyses.
For the RWST, the deliverable volume is different from the total volume contained ( continued)
B 3.5.4-2 Revision 0 
{ BASES APPLICABLE SAFETY ANALYSES (continued)
Farley Units 1 and 2 RWST B 3.5.4 since, due to the design of the tank, more water can be contained than can be delivered.
The minimum boron concentration is an explicit assumption in the main steam line break (MSLB) analysis to ensure the required shutdown capability.
The minimum boron concentration limit is an important assumption in ensuring the required shutdown capability.
The maximum boron concentration is an explicit assumption in the inadvertent ECCS actuation analysis, although the results are very insensitive to small changes in boron concentrations.
The minimum temperature is an assumption in both the MSLB and inadvertent ECCS actuation analyses.
The MSLB analysis has considered a delay associated with the interlock between the VCT and RWST isolation valves, and the results show that the departure from nucleate boiling design basis is met. The delay has been established as 27 seconds, with offsite power available, or 42 seconds without offsite power. This response time includes 2 seconds for electronics delay, a 10 second stroke time for the RWST valves, and a 15 second stroke time for the VCT valves. For a large break LOCA analysis, the minimum water volume limit of 321,000 gallons and the lower boron concentration limit of 2300 ppm are used to compute the post LOCA sump boron concentration necessary to assure subcriticality.
The large break LOCA is the limiting case since the safety analysis assumes that all control rods are out of the core. A water volume of 506,600 gallons and the upper limit on boron concentration of 2500 ppm are used to determine the maximum allowable time to switch to hot leg recirculation following a LOCA. The purpose of switching from cold leg to hot leg injection is to avoid boron precipitation in the core following the accident.
In the ECCS analysis, the containment spray temperature is assumed to be equal to the RWST lower temperature limit of 35&deg;F. If the lower temperature limit is violated, the containment spray further reduces containment pressure, which decreases the rate at which steam can be vented out the break and increases peak clad temperature.
An upper temperature assumption of 120&deg;F is used in the small break LOCA analysis and containment OPERABILITY analysis.
Exceeding this temperature would result in a higher peak clad temperature, because there would be less heat transfer from the core to the (continued)
B 3.5.4-3 Revision 0 
( BASES APPLICABLE SAFETY ANALYSES (continued)
LCO APPLICABILITY ACTIONS Farley Units 1 and 2 RWST B 3.5.4 injected water for the small break LOCA and higher containment pressures due to reduced containment spray cooling capacity.
For the containment response following an MSLB, the lower limit on boron concentration and the upper assumption on RWST water temperature are used to maximize the total energy release to containment.
The RWST satisfies Criterion 3 of 10 CFR 50.36(c)(2)(ii).
The RWST ensures that an adequate supply of borated water is available to cool and depressurize the containment in the event of a Design Basis Accident (DBA), to cool and cover the core in the event of a LOCA, to maintain the reactor subcritical following a DBA, and to ensure adequate level in the containment sump to support ECCS and Containment Spray System pump operation in the recirculation mode. To be considered OPERABLE, the RWST must meet the water volume, boron concentration, and temperature limits established in the SRs. In MODES 1, 2, 3, and 4, RWST OPERABILITY requirements are dictated by ECCS and Containment Spray System OPERABILITY requirements.
Since both the ECCS and the Containment Spray System must be OPERABLE in MODES 1, 2, 3, and 4, the RWST must also be OPERABLE to support their operation.
Core cooling requirements in MODE 5 are addressed by LCO 3.4.7, "RCS MODE 5, Loops Filled," and LCO 3.4.8, "RCS Loops-MODE 5, Loops Not Filled." MODE 6 core cooling requirements are addressed by LCO 3.9.4, "Residual Heat Removal (RHR) and Coolant Circulation
-High Water Level," and LCO 3.9.5, "Residual Heat Removal (RHR) and Coolant Circulation
-Low Water Level. With RWST boron concentration or borated water temperature not within limits, they must be returned to within limits within 8 hours. Under these conditions neither the ECCS nor the Containment Spray (continued)
B 3.5.4-4 Revision 0 BASES ACTIONS SURVEILLANCE REQUIREMENTS Farley Units 1 and 2 A.1 (continued)
RWST B 3.5.4 System can perform its design function. Therefore, prompt action must be taken to restore the tank to OPERABLE condition.
The 8 hour limit to restore the RWST temperature or boron concentration to within limits was developed considering the time required to change either the boron concentration or temperature and the fact that the contents of the tank are still available for injection.
With the RWST inoperable for reasons other than Condition A (e.g., water volume), it must be restored to OPERABLE status within 1 hour. In this Condition, neither the ECCS nor the Containment Spray System can perform its design function.
Therefore, prompt action must be taken to restore the tank to OPERABLE status or to place the plant in a MODE in which the RWST is not required.
The short time limit of 1 hour to restore the RWST to OPERABLE status is based on this condition simultaneously affecting redundant trains. C.1 and C.2 If the RWST cannot be returned to OPERABLE status within the associated Completion Time, the plant must be brought to a MODE in which the LCO does not apply. To achieve this status, the plant must be brought to at least MODE 3 within 6 hours and to MODE 5 within 36 hours. The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems. SR 3.5.4.1 The RWST borated water temperature should be verified every 24 hours to be above the minimum limit assumed in the accident analyses.
This Frequency is sufficient to identify a temperature change that would approach the limit and has been shown to be acceptable through operating experience. (continued)
B 3.5.4-5 Revision 0 BASES SURVEILLANCE REQUIREMENTS REFERENCES Farley Units 1 and 2 SR 3.5.4.1 (continued)
RWST B 3.5.4 The SR is modified by a Note that eliminates the requirement to perform this Surveillance when ambient air temperature is within the operating limit of the RWST. With ambient air temperature within the limit, the RWST temperature should not exceed the limit. SR 3.5.4.2 The RWST water volume should be verified every 7 days to be above the required minimum level in order to ensure that a sufficient initial supply is available for injection and to support continued ECCS and Containment Spray System pump operation on recirculation.
Since the RWST volume is normally stable and is protected by an alarm, a 7 day Frequency is appropriate and has been shown to be acceptable through operating experience.
SR 3.5.4.3 The boron concentration of the RWST should be verified every 7 days to be within the required limits. This SR ensures that the reactor will remain subcritical following a LOCA. Further, it assures that the resulting sump pH will be maintained in an acceptable range so that boron precipitation in the core will not occur and the effect of chloride and caustic stress corrosion on mechanical systems and components will be minimized.
Since the RWST volume is normally stable, a 7 day sampling Frequency to verify boron concentration is appropriate and has been shown to be acceptable through operating experience.
: 1. FSAR, Chapter 6 and Chapter 15. B 3.5.4-6 Revision 0 HL T-32 ADMIN exam A.1.2SRO&RO Page 1 of 6 A.l.2SRO&RO Equipment Control ADMIN 015A1.04 -SRO & RO TITLE: Perform A Quadrant Power Tilt Ratio Calculation TASK STANDARD:
Determine the Quadrant Power Tilt Ratio by performing the required Surveillance Calculation, STP-7.0, and determine that the upper and lower QPTR values are satisfactory.
PROGRAM APPLICABLE:
SOT SOCT LOCT-X ACCEPTABLE EVALUATION METHOD: PERFORM SIMULATE DISCUSS EVALUATION LOCATION:
CONTROL ROOM PLANT PROJECTED TIME: 20 MIN SIMULATOR IC NUMBER: N/A ALTERNATE PATH TIME CRITICAL PRA Examinee:
Overall JPM Performance:
Satisfactory 0 Unsatisfactory 0 Evaluator Comments (attach additional sheets if necessary)
EXAMINER:
______________
_ 
? ( HL T-32 ADMIN exam A.1.2SRO&RO Page 2 of 6 CONDITIONS
#hen I tell you to begin, you are to PERFORM A QUADRANT POWER TILT RATIO CALCULATION.
The conditions under which this task is to be performed are: a. Reactor power is 100%. b. All PR NI detectors are operable.
: c. You are directed by Shift Supervisor to perform STP-7.0 and determine if the acceptance criteria are met. EVALUATION CHECKLIST ELEMENTS:
--*1. *2. *3. 4. START TIME Obtain normalized currents from Core Physics Curve Book. Record data from power range detector A and detector B. Calculate upper and lower quadrant power tilt ratios. Enter the greater of the upper or lower quadrant power tilt ratio which is the lower. STANDARDS:
Examinee demonstrates where to obtain normalized current values from the provided Data Sheet 1 (Curve 71) and records them on calculation sheet. Values obtained from the provided Data Sheet 2 (as would be indicated on NI-41 , 42, 43, 44 Drawer displays) and recorded.
Upper ratio calculated at 1.004. Lower ratio calculated at 1.011. [no tolerance after rounding to 4 significant digits, since all calculation rounding differences occur at greater than 4 significant digits.] Lower QPTR ratio recorded:
1.01 entered. [Tolerance of 1.01 to 1.011 when rounded to 4 significant digits. Rounding to more digits does not make this unsat as long as rounding to 4 significant digits would be 1.011] RESULTS: (CIRCLE) S I U S I U S/U S I U S I U HLT-32 ADMIN exam A.1.2SRO&RO EVALUATION CHECKLIST ELEMENTS:
STANDARDS:
Page 3 of 6 RESULTS: (CIRCLE) NOTE: PROMPTING OF THE EXAMINEE TO VERBALIZE THE PERFORMANCE OF ELEMENT 5 MAY BE RE UIRED. *5. Assess acceptance criteria met 6. Records power level __ STOP TIME Terminate when power level is recorded.
Determination made that acceptance criteria was met. S / U Current avg power level recorded S / U from initial conditions sheet. CRITICAL ELEMENTS:
Critical Elements are denoted with an asterisk (*) preceding the element number. GENERAL REFERENCES
: 1. FNP-1-STP-7.0, Version 17.0 2. KlAs: 015A1.04 RO-3.5 SRO-3.7 GENERAL TOOLS AND EQUIPMENT Provide: 1. FNP-1-STP-7.0, Version 17.0 2. Calculator (or the Applicant may supply a calculator)
: 3. DATA sheets 1 & 2 of this ADMIN JPM COMMENTS HL T-32 ADMIN exam A.1.2SRO&RO QUADRANT POWER TILT RATIO CALCULATION CALCULATION SHEET -KEY UPPER QUADRANT POWER TILT Channel Detector
* Detector Detector A + A 100% = A Indicated Current Calibrated
__ 1 Current Output Total Average N41B 187.3 160.61 = 1.1662 Number Upper Operable Detector N42B 179.2 154.00 = 1.1636 Upper Calibrated Detectors Output N42B 190.1 164.57 = 1.1551 N44B 178.2 153.56 = 1.1605 Total Detector A Calibrated Output 1 = 4.6454 4 = 1.1613 *Obtained from Curve 71,0% AFD Current LOWER QUADRANT POWER TILT lannel Detector
* Detector Detector B B +B = Calibrated Indicated 100% Output Current Current 1 N41B = Total Average 176.9 156.95 1.1271 Number Lower N42B = Operable Detector 175.9 150.06 1.1722 Lower Calibrated N43B = Detectors Output 203.0 173.91 1.1673 N44B = 183.5 156.98 1.1689 Total Detector B Calibrated Output 1 = 4.6355 4 = 1.1589 *Obtained from Curve 71,0% AFD Current X X X X % Power 100% Record Maximum of Upper Quadrant Tilt Ratio 1.01 Page 4 of 6 Maximum Upper Detector Quadrant A Power Calibrated
= Tilt Output Ratio 1.1662 = 1.0042 Lower Maximum Quadrant Detector B Power Calibrated
= Tilt Output Ratio 1.1722 = 1.0114 :::CEPT ANCE CRITERIA:
Maximum of Upper or Lower Quadrant Power Tilt Ratio does not exceed 1.02 A.1.2SRO & RO (2 Pages) HANDOUT DATA SHEET 1 As obtained from Curve 71: DETECTOR A DETECTOR B 100% 100% CURRENT CURRENT N41 160.61 156.95 N42 154.00 150.06 N43 164.57 173.91 N44 153.56 156.98 DATA SHEET 2 As obtained from NI Drawer meter readings:
DETECTOR A DETECTORB INDICATED CURRENT INDICATED CURRENT N41 187.3 176.9 N42 179.2 175.9 N43 190.1 203.0 N44 178.2 183.5 
( A.1.2SRO & RO (2 Pages) HANDOUT CONDITIONS When I tell you to begin, you are to PERFORM A QUADRANT POWER TILT RATIO CALCULATION.
The conditions under which this task is to be performed are: a. Reactor power is 100%. b. All PR NI detectors are operable.
: c. You are directed by Shift Supervisor to perform STP-7.0 and determine if the acceptance criteria are met.
08111/03 13:06:50 I FARLEY NUCLEAR PLANT FNP-1-STP-7.0 August 2, 2003 Version 17.0 SURVEILLANCE TEST PROCEDURE FNP-1-STP-7.0 QUADRANT POWER TILT RATIO CALCULATION PROCEDURE USAGE REQUIREMENTS PER FNP-0-AP-6 SECTIONS Continuous Use Reference Use Infonnation Use Approved:
TODD YOUNGBLOOD Operations Manager ALL Date Issued 8-4-03 S A F E T Y R E L A T E D 08/11103 13:06:50 FNP-l-STP-7.0 SURVEILLANCE TEST NO. FNP-1-STP-7.0 TITLE FARLEY NUCLEAR PLANT SURVEILLANCE TEST REVIEW SHEET TECHNICAL SPECIFICATION REFERENCE SR 3.2.4.1 MODE(S) REQUIRING TEST: QUADRANT POWER TILT RATIO CALCULATION 1 (>50% Rated Thermal Power) TEST RESULTS (TO BE COMPLETED BY TEST PERFORMER)
PERFORMED BY DATE/TIME COMPONENT OR TRAIN TESTED (if applicable) [ ] ENTIRE STP PERFORMED
[] FOR SURVEILLANCE CREDIT [ ] PARTIAL STP PERFORMED:
[] NOT FOR SURVEILLANCE CREDIT REASON FOR PARTIAL: TEST COMPLETED: [ ] Satisfactory [ ] Unsatisfactory [ ] The following deficiencies occurred: [ ] Corrective action taken or initiated:
SHIFT SUPPORT SUPERVISOR REVIEW REVIEWED BY DATE [ ] Procedure properly completed and satisfactory [ ] Comments:
ENGINEERING SUPPORT SCREENED BY DATE REACTOR ENG. REVIEW (If applicable)
REVIEWED BY DATE [ ] Satisfactory and Approved [] Comments:
Version 17.0 08111/03 13:06:50 1 FNP-1-STP-7.0 TABLE OF CONTENTS Procedure Contains Number of Pages Body ..........................................................
2 Attachment 1 .............................................
1 Attachment 2 .............................................
1 STRS .........................................................
1 Page 1 of 1 
( 08/11103 13:06:50 FNP-l-STP-7.0 FARLEY NUCLEAR PLANT UNIT 1 SURVEILLANCE TEST PROCEDURE STP-7.0 QUADRANT POWER TILT RATIO CALCULATION 1.0 Purpose To determine the quadrant power tilt ratio using power range nuclear instrumentation.
2.0 Acceptance Criteria The quadrant power tilt ratio shall be 1.02. 3.0 Initial Conditions 3.1 The version of the procedure has been verified to be the current version and correct unit for the task. (OR 1-98-498).
NOTE: This STP may be performed at less than 50% power for verification of power range instrument indications.
In this case, the STP is not for surveillance credit. 3.3 Above 50% of rated thermal power. IF DVM is used to collect data, THEN have I&C obtain a Fluke 45 or equivalent with shielded test leads with NO exposed metal connectors.
DVM Serial No. ______ _ Cal. due ________ _ 4.0 Precautions and Limitations 4.1 Reactor power, rod position and reactor coolant temperature should be constant while taking data. 4.2 A QPTR calculation should be done prior to rescaling of Power Range Nuclear Instruments, and after completing the rescaling of ALL Power Ranges Nuclear Instruments.
A QPTR calculation performed between individual Power Range rescaling may provide erroneous results 4.3 If one Power Range NI is inoperable and thermal power is :s 75% RTP, the remaining power range channels can be use for calculating QPTR.(SR 3.2.4.1) 4.4 Above 75% RTP, with one Power Range NI inoperable, QPTR must be determined by SR 3.2.4.2 Version 17.0 
( 08111/03 13:06:50 FNP-1-STP-7.0 5.0 Instructions 4NOTE: QPTR may be determined using detector current meter data with normalized currents from Curve 71A, 71B, 71C, AND 71D, or by using detector currents read by DVM with normalized currents from Curve 71A,71B,71C, AND 71D, DVM data is obtained using Attachment
: 2. 5.1 Obtain normalized currents from Curve 71, and enter on the Calculation Sheet. NOTE: With input from one Power Range Neutron Flux channel inoperable and THERMAL POWER 75% RTP, the remaining three power range channels can be used for calculating QPTR. 5.2 Read detector current meters in NI-41B, 42B, 43B, and 44B POWER RANGE B drawer DETECTOR A and DETECTOR B or have I&C obtain detector currents using Attachment 2 for the desired detectors.
5.3 Enter total number of operable detectors in space provided on the Calculation Sheet. 5.4 Calculate the upper and lower Quadrant Power Tilt Ratios. 5.5 Record the greater of the upper or lower Quadrant Power Tilt Ratio value in the space provided.
ACCEPTANCE CRITERIA:
Maximum value of upper or lower Quadrant Power Tilt Ratio shall be 1.02. 5.6 Record the Power Level (Avg.) in the space provided.
6.0 References 6.1 FSAR -Chapter 4.1. 6.2 Unit 1 Technical Specification 3.2.4 Version 17.0 08/11/03 13:06:50 FNP-I-STP-7.0 ATTACHMENT 1 QUADRANT POWER TILT RATIO CALCULATION CALCULATION SHEET UPPER QUADRANT POWER TILT Chamlel Detector A
* Detector A Detector A Indicated 100% = Calibrated Current Current Output N41B = 1 Total Average N42B = Number Upper Operable Detector X N43B = Upper Calibrated Detectors Output N44B = Total Detector A Calibrated Output 1 X = = *Obtained from Curve 71, 0% AFD Current LOWER QUADRANT POWER TILT Channel Detector B
* Detector B Detector B Indicated 100% = Calibrated Current Current Output N41B = 1 Total Average N42B = Number Lower Operable Detector X N43B = Lower Calibrated Detectors Output N44B = Total Detector B Calibrated Output 1 X = = *Obtained from Curve 71, 0% AFD Current Maximum Detector A Calibrated Output Maximum Detector B Calibrated Output Upper Quadrant = Power Tilt Ratio = Lower Quadrant = Power Tilt Ratio = % Power ________ _ Record Maximum of Upper or Lower Quadrant Tilt Ratio ______ _ ACCEPTANCE CRITERIA:
Maximum of Upper or Lower Quadrant Power Tilt Ratio does not exceed 1.02 Page 1 of 1 Version 17.0 08/11103 13:06:50 FNP-I-STP-7.0 ATTACHMENT 2 USING A DVM TO OBTAIN DETECTOR CURRENT VALUES ACCEPTANCE CRITERIA:
Maximum of Upper or Lower Quadrant Power Tilt Ratio shall be 1.02.USING A DVM TO OBTAIN DETECTOR CURRENT VALUES NOTE: Detector current values may be obtained for as many drawers as required.
Unused spaces in the Table should be marked NA. 1.0 Obtaining NI Detector Currents using a DVM. 1.1 Using a Fluke 45 or equivalent (Do Not use a Fluke 8600) and shielded test leads connect and obtain detector voltage readings as follows: I NOTE: Voltage values should be in the 2 to 3 volt range. JV/A I&C V/A I&C 1.1.1 1.1.2 For Upper Detector connect to TP301 (+) and TP305 (-) and record voltage in appropriate space of table below. For Lower Detector connect to TP302 (+) and TP305 (-) and record voltage in appropriate space of table below. NOTE: To calculate detector currents use the following formula: Measured Detector Voltage x Curve 71 "0% AFD, 100% Current" Value = Calculated Detector Current 2.083 V/A 1.2 Using the 0% AFD, 100% current value from Curve 71, calculate the detector current value and record in appropriate space of table below. N41 N42 N43 N44 Upper Lower Upper Lower Upper Lower Upper Lower Detector Detector Detector Detector Detector Detector Detector Detector DVM DVM DVM DVM DVM DVM DVM DVM Voltage Voltage Voltage Voltage Voltage Voltage Voltage Step 1.1 Calculated Calculated Calculated Calculated Calculated Calculated Calculated Calculated Current Current Current Current Current Current Current Current Step 1.2 Page 1 of 1 Version 17.0 HL T-32 ADMIN exam A.2R Page 1 of 7 A.2R Equipment Control ADMIN 004A2.22 -RO TITLE: Perform an RCS Leakage Test TASK STANDARD:
Perform an RCS Leakage Test by performing the required Surveillance Calculation, STP-9.0, and identify that the RCS leakrate does NOT meet acceptance criteria.
PROGRAM APPLICABLE:
SOT SOCT OLT LOCT---.X ACCEPTABLE EVALUATION METHOD: PERFORM SIMULATE DISCUSS EVALUATION LOCATION:
SIMULATOR CONTROL ROOM --1L CLASSROOM PROJECTED TIME: 20 MIN SIMULATOR IC NUMBER:
ALTERNATE PATH TIME CRITICAL PRA Examinee:
Overall JPM Performance:
Satisfactory 0 Unsatisfactory 0 Evaluator Comments (attach additional sheets if necessary)
EXAMINER:
________________
_
HL T-32 ADMIN exam A.2R Page 2 of 7 CONDITIONS ( When I tell you to begin, you are to perform an RCS Leakage Test. The conditions under which this task is to be performed are: a. The unit is in Mode 1 at 100% power. b. You are directed by the Shift Supervisor to
* determine RCS leakage per STP-9.0, STEPS 5.4 to 5.9 -WHEN step 5.9 is complete, THEN another operator will complete the STP starting at step 5.10
* determine whether or not RCS leakage acceptance criteria is met EVALUATION CHECKLIST ELEMENTS:
STANDARDS:
RESULTS: (CIRCLE) __ START TIME NOTE: A Key is provided at the end of this ADMIN JPM with expected values filled in. The applicant must obtanin some of the values from the Handout and some from curve 28B, RCDT gallons vs.level.
1 *. Step 5.4 Read and record initial readings on Records initial readings on data S I U 2*. 3*. data sheet 1. sheet 1. Step 5.5 Records final values on data sheet 1. Step 5.6 Records the R-ll, R-12, and Ctmt Sump lvl. Readings.
Records final values on data sheet 1. Records the R-ll, R-12, and Ctmt Sump lvl. Readings.
S I U S/U I CUE IF REQUESTED: "Other leakage is 0 gpm". NOTE: [IF applicant inquires about any "other leakage" it is 0 gpm. This is information that is obtainable in the plant from turnover, and since there is no "other known leakage" provided, it may be assumed to be 0 gpm OR it may be requested.
Either is acceptable].
Step 5.7 has already been marked NA in the handout. 4*. Step 5.8 Calculates identified and Calculates identified and S I U unidentified leakages using the formulas on unidentified leakages using the STP-9.0 data sheet 1. formulas on STP-9.0 data sheet 1. 
( HLT-32 ADMIN exam A.2R EVALUATION CHECKLIST ELEMENTS:
5*. 6*. Step 5.9 Marks NA on step: "IF unidentified leakage is more negative than -0.2, THEN re-perform leak rate measurement. " Compares actual Leak rates with the acceptance criteria, and determines that the Unidentified Leakage does not meet acceptance criteria.
STANDARDS:
Marks NA on step 5.9 due to leakrate being positive.
Determines that the Identified leakage MEETS acceptance criteria, but the Unidentified Leakage does Page 3 of 7 RESULTS: (CIRCLE) SIU NOT meet acceptance criteria.
S I U _STOP TIME Terminate JPM when determination of acceptance criteria is complete for leak rate. CRITICAL ELEMENTS:
Critical Elements are denoted with an asterisk (*) before the element number. GENERAL REFERENCES
: 1. FNP-1-STP-9.0, Version 42.0 2. Plant tank curves 27 A, 27B, 27C, 28A, & 28B 3. KIA: 004 A2.22 RO-3.2SRO-3.1 GENERAL TOOLS AND EQUIPMENT Provide: 1. 2. 3. 4. FNP-1-STP-9.0, Version 42.0 Plant tank curves 27A, 27B, 27C, 28A, & 28B Calculator (or the Applicant may supply a calculator)
Plant Conditions at 1000 & 1200 COMMENTS HLT-32 ADMIN exam A.2R Page 4 of 7 KEY: STP-9.0, DATA SHEET 1, RCS Leakage All tolerances based on differences in rounding.
One calc was performed rounding to the least significant digits at each step of the calculation, and one was performed using all digits in the calculator until the end of each step of the calculations to round to the least significant digits. ", INSTRUMENT NAME INITIAL FINAL FINAL -INITIAL Computer TIME 1000 1200 A=120 Minutes (MCB) TE0453 LIQ PRZR TEMP 650.8 of 650.8 of No significant change 1&deg;F) (TI0453) PC0482, PT0455, PT0456 or PT0457 PRZRPRESS 2239.4 2239.4 No significant change (PI 455, PI 456 (Note 1) psig psig psig) or PI 457) TC0484 (preferred), OR = 0 of TY0412K, OR RCSTAVG TY0422K, OR (Note 1) 571.9 of 571.9 of Maximum change of O.3&deg;F TY0432K (Note 7) allowed ifTAVG is 545&deg;F or greater, 0.1 of if TA VG is less (Average ofTI 412D, than 545&deg;F. 422D & 432D) RCS Temperature CF (Note 5) 99.7 N/A B x CF = 0 Gal. Correction Factor OR NA LC 1600 OR Average of LT0459 , PRZRLVL 47.8 % 47.8 % C = 56.3 x 0 % = o Gal. LT0460 & LT0461 (LI-459, 460, 461) LT0115 VCTLVL 51.0 % 37.3 % D = 14.18 x (-)12.7 % = (LI 115) (-)194 to 194.3 Gal. LI 1003 Waste Pnl or RCDTLVL 36.4 % 38.1 % E = 6.01 to 6.02 Gal. BOP LS261 Pos 6 127.69 *Gal 133.71 *Gal (Enter 0 if negative)
LT0470 PRTLVL 69.7 % 69.7 % F= 0 Gal. (LI470) (Note 2) NA *Gal NA *Gal (Enter 0 if negative)
TOTAL FLOW 3489 Gal. 3489 Gal. G = 0 Gal. Dilution and FIS 168 BATCH INTEG NA Gal. NA Gal. Blended Makeup *From Tank Curve Book 
( ( HL T-32 ADMIN exam A.2R Page 5 of 7 KEY (continued):
STP-900, DATA SHEET 1, Res Leakage Total Leakage 8-C-D+G (o )-( 0 )-( (-}194to(-}194.3)+{
: 0) = A = ( 120 ) = (+}1.617 to (+}1.62 GPM (Note 6) Identified Leakage E + F (6.01 to 6.02 ) + ( = = A (120) o ) + 0 = 0.050 no tolerance GPM Other Leakage: Source o Total Other Other leakage (Note 6) Rate (GPM) o U &deg;d &deg;fo d Leak 1.617 to 1.62 0.050 no tolerance 1.567 to 1.57 GPM m entl Ie age = = -------Total Leakage Identified Leakage (Notes 3, 4, & 6) ACCEPT ANCE CRITERIA:
*
* Identified Leakage s 10 gpm Unidentified Leakage s 1 gpm A.2R (2 pages) HANDOUT Plant Conditions at 1000: INSTRUMENT NAME Computer Points N/A TIME 1000 TE0453 LIQ PRZR TEMP 650.8 of PC0482 PRZR PRESS 2239.4 psig TC0484 RCS TAVG 571.9 of LC 1600 PRZR LVL 47.8 % LTOl15 VCT LVL 51.0 % BOP LS261 Pos 6 RCDT LVL 36.4 % *Gal LT0470 PRT LVL 69.7 % *Gal FIS 168 TOTAL FLOW 3489 Gal. BATCH INTEG Plant Conditions at 1200: INSTRUMENT NAME Computer Points N/A TIME 1200 TE0453 LIQ PRZR TEMP 650.8 of PC0482 PRZR PRESS 2239.4 Psig TC0484 RCS TAVG 571.9 of LC 1600 PRZR LVL 47.8 % LTOl15 VCT LVL 37.3 % BOP LS261 Pos 6 RCDT LVL 38.1 % *Gal LT0470 PRT LVL 69.7 % *Gal FIS 168 TOTAL FLOW 3489 Gal. BATCH INTEG CTMT R-11 Particulate 187 CPM Rad Monitor R-12 CTMT Gas Rad 75 CPM Monitor Q1G21LI3282A Ctmt. Sump lvl 18 Inches Q1G21LI3282B Ctmt. Sump lvl 18 Inches A.2R (2 pages) HANDOUT CONDITIONS ( When I tell you to begin, you are to perform an Res Leakage Test. The conditions under which this task is to be performed are: a. The unit is in Mode 1 at 100% power. b. You are directed by the Shift Supervisor to
* determine ReS leakage per STP-9.0, STEPS 5.4 to 5.9 -WHEN step 5.9 is complete, THEN another operator will complete the STP starting at step 5.10
* determine whether or not ReS leakage acceptance criteria is met 08/08/08 09:39:04 FARLEY NUCLEAR PLANT SURVEILLANCE TEST PROCEDURE FNP-I-STP-9.0 RCS LEAKAGE TEST FNP-I-STP-9.0 May 30, 2008 Version 42.0 PROCEDURE USAGE REQUIREMENTS PER FNP-0-AP-6 SECTIONS Continuous Use ALL Reference Use Information Use Approved:
J. L. Hunter (for) Operations Manager Date Issued: 05/30/2008
-------S A F E T Y R E L A T E D 08/08/08 09:39:04 1 I 1 FNP-l-STP-9.0 FARL CLEAR PLANT SURVEILLANCE TEST REVIEW SHEET SURVEILLANCE TEST NO. TECHNICAL SPECIFICATION REFERENCE FNP-I-STP-9.0 SR3.4.13.1 TITLE MODE(S) REQUIRING TEST: RCS LEAKAGE TEST 1,2,3,4 TEST RESULTS (TO BE COMPLETED BY TEST PERFORMER)
PERFORMED BY DATEITIME COMPONENT OR TRAIN TESTED (if applicable) [ ] ENTIRE STP PERFORMED [ ] FOR SURVEILLANCE CREDIT [ ] PARTIAL STP PERFORMED: [ ] NOT FOR SURVEILLANCE CREDIT REASON FOR PARTIAL: TEST COMPLETED: [ ] Satisfactory [ ] Unsatisfactory [ ] The following deficiencies occurred: [ ] Corrective action taken or initiated:
SHIFT SUPERVISOR!
SHIFT SUPPORT SUPERVISOR REVIEW REVIEWED BY DATE [ ] Procedure properly completed and satisfactory [ ] Comments:
ENGINEERING SUPPORT SCREENED BY DATE GROUP SCREENING REVIEWED BY DATE (IF APPLICABLE) [ ] Satisfactory and Approved [] Comments:
Version 42.0 08/08/08 09:39:04 FNP-1-STP-9.0 TABLE OF CONTENTS Procedure Contains Number of Pages STRS .........................................................
1 Body ..........................................................
6 Data Sheet 1 ..............................................
3 ( Page 1 of 1 Version 42.0 08/08/0809:39:04 FNP-1-STP-9.0 FARLEY NUCLEAR PLANT UNIT 1 SURVEILLANCE TEST PROCEDURE STP-9.0 RCS LEAKAGE TEST 1.0 Purpose To determine identified and unidentified reactor coolant system leakage by performance of an RCS water inventory balance. NOTE: Asterisked steps (*) are those associated with Acceptance Criteria.
2.0 Acceptance Criteria 2.1 2.2 NOTE: Unidentified leakage is ::;; 1 gpm. Identified leakage::;;
10 gpm. FNP-I-STP-9.0 RCS Leakage Test (SR 3.4.13.1) is only required to be performed during steady state operation.
AI 2004201338 3.0 Initial Conditions 3.1 3.2 3.3 3.4 3.5 The version of this procedure has been verified to be the current version. (OR 1-98-498)
This procedure has been verified to be the correct unit for the task. (OR 1-98-498)
Reactor power and reactor coolant temperature should be stabilized and held approximately constant for 1 hour prior to and during the test. (In Mode 3 or 4 not required until 12 hours of steady state operation.)
The pressurizer level and pressure control systems are in automatic or are in manual control and are stable. The level of the VCT is in the normal operating band high enough to prevent the occurrence of an Auto Makeup during the test. Version 42.0 
( 08/08/08 09:39:04 FNP-I-STP-9.0 t1A-3.8 The CVCS system is aligned per FNP-I-SOP-2.1A, CHEMICAL & VOLUME CONTROL SYSTEM. Notify the Shift Chemist and Shift Radiochemist of the performance of the test to ensure that no sampling of the RCS or CVCS will be done during this test. IF required for step 5.2, THEN ensure the following instrument is in calibration.
* Calibrated Digital Voltmeter FNP I.D. # Cal Due Date Version 42.0 08/08/08 09:39:04 1 I 1 FNP-1-STP-9.0 4.0 Precautions And Limitations 4.1 No sampling of the RCS or CVCS shall be done during this test. 4.2 Any of the following will render this test void: 4.2.1 Emergency boration 4.2.2 Diversion ofletdown to the recycle holdup tanks. 4.2.3 Make up from any source which does not go through the boric acid blender. 4.2.4 Boration of less than 10 gpm, due to Batch Integrator counter inaccuracies.
4.3 To minimize the inaccuracy introduced into the calculation by RCS temperature changes, RCS temperature should be maintained as follows: 4.3.1 IF RCS temp is < 545 of, THEN the RCS temperature should not change by more than 0.1 OF during the test. 4.3.2 IF RCS temp is 2: 545 OF, THEN the RCS temperature should not change by more than 0.3 OF during the test. 4.3.3 IF required to maintain RCS temperature, THEN control rods, turbine load or boron concentration should be adjusted as necessary.
4.4 The calculation assumes that changes in RCS volume due to PZR temperature 1 pressure fluctuations are negligible.
Pressurizer parameters should be maintained stable to minimize inaccuracy.
4.5 The following guidelines should be followed to maximize precision:
* IF available, THEN computer points should be used for obtaining data. Otherwise, the available indications are to be read as accurately as possible.
* For RCS Tavg, the computer point data should be entered to include three decimal places(i.e., 572.204 OF).
* For other computer points and RCDT level, the data should be entered to include at least one decimal place (i.e., 50.1 %).
* Identified and unidentified leakage rates are to be reported in two decimal places (e.g., 0.07 gpm).
* IF possible, THEN normal makeup to the VCT should be avoided. 4.6 IF the RCDT or PRT level indication is invalid, THEN use 0 gpm for RCDT or PRT portion of identified leakage unless leakage into the RCDT or PRT is to be determined using another approved method. 4.7 To ensure that the STP-9.0 Computer Program remains current, the Engineering Support Group should be notified of any revision or TCN to the Data Sheet 1. Version 42.0 08/08/0809:39:04 FNP-I-STP-9.0 5.0 Instructions 5.1 NOTE: I&C fi.!;\ 5.2 CV 5.3 NOTE: 5.4 NOTE: 5.5 5.6 The RCDT system is aligned as follows: 5.1.1 RCDT level is in the normal operating band. 5.1.2 Close RCDT PUMPS DISCH LINE ISO QIG2IHV7136 The following step is only required if increased accuracy is necessary for determination of leak rate into PRT or the MCB PRT level indicator has a problem. IF required, THEN have I&C connect a calibrated digital voltmeter across the output ofLQY-470, location C5-231. Place VCT HI LVL DIVERT VLV, QIE2ILCVI15A, in the VCT position.
Batch Integrator readings will be taken prior to and at the conclusion of each make up evolution.
Read and record initial readings on data sheet I. A time span of at least 2 hours should be used during normal steady state plant operations, however if plant conditions dictate, a shorter time span may be used. (30 minutes minimum).
After the desired time span (normally 2 hours) record final values on data sheet 1. Record the following readings (recorded for trending purposes):
Rad Monitor R-II CPM Rad Monitor R-12 CPM Ctmt. Sump IvL QIG2ILI3282A Inches Ctmt. Sump IvL QIG21LI3282B Inches Version 42.0 08/08/0809:39:04 FNP-1-STP-9.0 NA 5.7 IF the RCS leakrate program is to be used, THEN verify that the program is revision 3. NOTE: If the RCS leakrate program is used, then the remainder of data sheet 1 may be left blank. *5.8 Calculate identified and unidentified leakages using the RCS leakrate program or formulas on data sheet 1. ACCEPTANCE CRITERIA:
* Identified Leakage 10 gpm
* Unidentified Leakage 1 gpm 5.9 IF unidentified leakage is more negative than -0.2, THEN re-perform leak rate measurement.
_1_ 5.10 Open RCDT PUMPS DISCH LINE ISO Q1G21HV7136.
IV _1_ 5.11 Place VCT HI LVL DIVERT VLV, Q1E21LCV1l5A in the AUTO position.
IV 5.12 IF computer point LC0500 is available, THEN review the RCS leakrate trend (last 30 days if possible) on IPC to determine if any abnormal trends exist. 5.13 IF unidentified leakage is >0.15 gpm, THEN re-perform leak rate measurement to confirm the results. 5.14 IF unidentified leakage is confirmed to be >0.15 gpm, THEN perform the following: (steps may be performed in any order) 5.14.1 Perform inspection to identify the leakage path(s) (AOP-l.O, attachments 2 through 5). 5.14.2 Perform evaluation including any recent maintenance, plant evolutions or filter alignments to locate source of leakage, determine corrective actions and the effects of the leakage. 5.14.3 IF leakage is NOT known to be outside CTMT, THEN request chemistry sample CTMT via R-67 for iron analysis.
5.14.4 Submit CR to document the leakage and actions taken. Version 42.0 08/08108 09:39:04 FNP-1-STP-9.0 I&C _1_ 5.15 IF applicable, THEN have I&C remove the calibrated digital voltmeter IV installed in step 5.2. 5.16 Update OPS home page (ULR Data spreadsheet) with unidentified leakage rate. 5.17 IF used for RCS leakrate calculation, THEN attach the computer generated Data Sheet 1 to this procedure.
6.0 References 6.1 P&ID D-175037 -RCS, sheet 2 6.2 P&ID D-175039 -CVCS, sheet 2 6.3 P&ID D-175042 -Waste Processing System, sheet 1 Version 42.0 08/08/08 09:39:04 INSTRUMENT NAME Computer TIME (MCB) TE0453 LIQ PRZR TEMP (TI0453) PC0482, PT0455, PT0456 or PT0457 PRZRPRESS (PI 455, PI 456 (Note 1) or PI 457) TC0484 (preferred), OR TY0412K, OR TY0422K, OR RCSTAVG TY0432K (Note 7) (Note 1) (Average of TI 412D, 422D & 432D) RCS Temperature CF (Note 5) Correction Factor LC 1600 OR Average ofLT0459, PRZRLVL L T0460 & LT0461 (LI-459, 460, 461) LT0115 VCTLVL (LI 115) LI 1003 Waste Pnl or RCDTLVL BOP LS261 Pos 6 LT0470 PRTLVL (LI 470) (Note 2) FIS 168 TOTAL FLOW BATCH INTEG *From Tank Curve Book DATA SHEET 1 RCS Leakage INITIAL of pSlg of % % % *Gal % *Gal Gal. Gal. Page 1 of3 FINAL of psig of N/A % % %
* Gal % *Gal Gal. Gal. A= FNP-1-STP-9.0 DATA SHEET 1 FINAL -INITIAL Minutes No significant change (s: 1&deg;F) No significant change (:::5 psig) = of Maximum change of 0.3&deg;F allowed ifTAVG is 545&deg;F or greater, 0.1 of if TAVG is less than 545&deg;F. B x CF = Gal. C = 56.3 x %= Gal. D = 14.18 x %= Gal. E= Gal. (Enter 0 if negative)
F= Gal. iEnter 0 if nezative)
G= Gal. Dilution and Blended Makeup Version 42.0 08/08/08 09:39:04 T 1 FNP-I-STP-9.0 DATA SHEET 1 Total Leakage B-C-D+G ( )-( )-( )+( ) GPM = = A ( ) (Note 6) Identified Leakage E+F ( )+( )+ = GPM =--= ) A ( Other leakage (Note 6) Other Leakage: Source Rate (GPM) Total Other Unidentified Leakage = = GPM Total Leakage Identified Leakage (Notes 3, 4, & 6) ACCEPTANCE CRITERIA:
* Identified Leakage ::;; 10 gpm
* Unidentified Leakage::;;
1 gpm Page 2 of3 Version 42.0 08/08/08 09:39:04 NOTES: 1 1 FNP-I-STP-9.0 DATA SHEET 1 I IF TAVG < 530&deg;F, THEN use: PI-402A (PT0402) and PI-403A (PT0403), IC and IA Loop RCS WR PRESS (Avg. of Readings)
AND TR-410 (TE0410) and TR-413 (TE0413), RCS COLD AND HOT LEG TEMP (Avg. of Readings) 2 Calibrated fluke may be used for PRT level determination if deemed necessary.
3 For reporting purposes values between -0.2 and 0 gpm shall be reported as 0 gpm. Values more negative than -0.2 gpm indicate a potential problem and therefore shall be reported as is. 4 If unidentified leakage> 0.9 but < I gpm, test should be reperformed with ZAS secured. At maximum injection rate, ZAS can introduce
-0.03 gpm error into calculation.
5 Obtain CF from Table I using the nearest value of RCS temperature.
N/A if RCS Leakrate program is used. 6 Leakage calculations are to be reported in two decimal places (e.g., 0.07 gpm). 7 TC0484 is preferred for RCS Tavg, but an individual loop temperature may be used if desired due to instability in the average reading. TABLE I RCSTemp Correction Factor Page 3 of3 Version 42.0 
, J HlICNT 0.80 0.50 VCLUHE 0.0 2 i 7 6&#xa3;) \6::::, ':, ,I.:' j (1 :jU':.: LLoNS (x VOLUME II CURVE 27A PRESSURIZER RELIEF TANK CAPACITY CAPACITY (GAL) VS LEVEL (FEET) REV. 1 March 8,1978 GAF APPROVED:
PLf!>+ I){>ld.-cP*.'JJ.1f#
..... ... R t:J;:, <.,. <:::> .. p ('::::> t""C> -..l :t>
l K':E' .,' , " W t 47 1510 C.I!.VJ13 r 5.0 7.0 i 0 ** J 14. ;;;'1 16.0 21. )) 1 ,-, >" . -441. 16 851. 16 .43 10(15.71 1 1 L 1424, 1 1 .10 ,56 24. (1
'1 i 25110 VOLffim II CURVE 27C PRESSURIZER RELIEF TANK CAPACITY TABLE N1B32TOOl CAPACITY (GAL) VS % LEVEL REV. 0 May 7, 1980 GAF APPROVED:
51 .21 54. 55.16 1.45 56.0 57.0 58. ti
.0 .0 61.0 6084.90 64.'J 6411.00 65.0 66.0 .51 67 II 44.0 41 .21 7.3.0 71 II tJ 46.0 4415.(18 47 .* 3 ,-, "":> I::' II { .l. 50,0 4:362, 5(i 51.0 4'374.46 % LEVEL GALLONS .0 i
,;., , :;".
19 VOLUME 11 CUI.VI 2M. UACTOl1l COOLANT DRAIN TANK CAPACITY N1G2lT001
... CAPACITY (GAL) VS LEVEL (FEET) REV 2 June 11, 1986 JMR APPROVED:
...
'i'-s:-ei" DA'rI rm:attCAL .MAMGD. . , . J 4 . 61!1.,. *****8* , .... 10 .12 ! . . t d*
2QO .. GALLONS lDIGHT 0.00 0.25 0.50 0.75 1.00 1.25 1.47 1.72 1.97 2.23 2.47 2.72 VOLL'ME 0.0 L8 4.8 8.6 12.9 17.4 21.4 26.0 30.4 34.6 38.3 41.3 GALLONS 0.0 13.7 38.2 69.0 103.9 141.5 175.1 213.9 251.2 285.7 315.8 339.0 TOTAL VOLUME IN GALLONS 349.9 Unit 1 Volume II Curve 28B Reactor Coolant Drain Tank Capacity . P'8 lIoL:;;"-G<<.V
().. 8/3 NIG2lTOOI Capacity (Gallons) vs % Level Rev. 2, December 14, 1981, C.A.P. Approved:
Technical Superintendent
% LEVEL GALLONS 0.i2! 1.0 4. 5. (; 6.0 7, \) '3 Ii 10 I) 11.0 12 n 1 :;!
* 1.4.0 1::. I) J, 6, (I l?n 1 ::: Ii 0 LL 121 2!)" 21 * .0 24. t:! ,:;'5.0 26.0 H 29 OJ 3iJ e :::q,(t :32.0 ::::4 II 0 :?,: 6
:3'7:: 0 41:0
'i t?i " 1;) 44,,0 1 II 20.45 25.80 27. ::::7 :34 :3? 37.49 16 142 45.65 4j3lt 46 51.:3:3 54.23 G' -, <f .",( ,_I ( III ..!. ':s 68.17 6:3. 66.26 69. :36 72.50 75.67 '7::: It S2.10 :35.:36 '31. 96 '95.
981f66 102. Hi5.45 1 En:; f::::3 115.79 lllj.27 136" 13(.1 1. 4f). 46 144.04 1147 151.21 t'58.41 165.63 16'9.24 \ LE'*/EL 51. 52. &#xa3;1 5:31$ (1 54,(1 55. 56. ;.J 58.0 59. ti 6l1,0 61.&#xa3;1 62. 6:3.t 1 fA.6 155.0 66.8 li (1 68.8 159, () 76. 7llte 72
* t;::i 75.8 76.0 77. >3 791t f,) ;::0. (1 ;::4, (1
.. (i :36.0 1$ fi ;::;9 io) ';:;&#xa3;j. (1 91.0 '14. (; # (1 '36;t f) 97wO a 0 19f1.
194.54 i 1$
If 74 2\)5, 21iSto 223,,14 226"67 237!$1?
244.
247 5() 25b) 254 257,,66 261. 80 ;264.:31 ::67" It :36 :315iE 4E: ::;:; 1 * (i;:: 3;2:21" 64 
( HL T-32 ADMIN exam A.2S Page 1 of 8 A.2S Equipment Control ADMIN 004A2.22 -SRO TITLE: Perform an RCS Leakage Test & determine Tech Spec requirements if applicable.
TASK STANDARD:
Perform an RCS Leakage Test by performing the required Surveillance Calculation, STP-9.0, and identify that the RCS leakrate does NOT meet acceptance criteria, then determine proper Tech Spec TS 3.4.13 CONDITION B for Pressure boundary Leakage. PROGRAM APPLICABLE:
SOT SOCT OLT LOCT --.X ACCEPTABLE EV ALUATION METHOD: PERFORM SIMULATE DISCUSS EVALUATION LOCATION:
SIMULATOR CONTROL ROOM CLASSROOM PROJECTED TIME: 25 MIN SIMULATOR IC NUMBER: NA ALTERNATE PATH TIME CRITICAL PRA Examinee:
Overall JPM Performance:
Satisfactory 0 UnsatisfactoO' 0 Evaluator Comments (attach additional sheets if necessary)
EXAMINER:
________________________________________
_
HLT-32 ADMIN exam A.2S Page 2 of 8 CONDITIONS When I tell you to begin, you are to perform an RCS Leakage Test and identify if any Tech Spec ACTIONS are applicable, and if so, which ACTION(S).
The conditions under which this task is to be performed are: a. The unit is in Mode 1 at 100% power. b. You are directed by the Shift Supervisor to
* determine RCS leakage per STP-9.0, STEPS 5.4 to 5.9 -WHEN step 5.9 is complete, THEN another operator will complete the STP starting at step 5.10
* determine whether or not RCS leakage acceptance criteria is met
* IF acceptance criteria is NOT met, THEN determine proper Tech Spec ACTION(S).
EVALUATION CHECKLIST ELEMENTS:
STANDARDS:
RESULTS: (CIRCLE) START TIME NOTE: A Key is provided at the end of this ADMIN JPM with expected values filled in. The applicant must obtanin some of the values from the Handout and some from curve 28B, RCDT gallons vs. level. 1 *. Step 5.4 Read and record initial readings on Records initial readings on data S I U 2*. 3*. data sheet 1. sheet 1. Step 5.5 Records fmal values on data sheet 1. Step 5.6 Records the R-ll, R-12, and Ctmt Sump Ivl. Readings.
Records final values on data sheet 1. Records the R-ll, R-12, and Ctmt Sump Ivl. Readings.
SIU S I U I CUE IF REQUESTED: "Other leakage is 0 gpm". NOTE: [IF applicant inquires about any "other leakage" it is 0 gpm. This is information that is obtainable in the plant from turnover, and since there is no "other known leakage" provided, it may be assumed to be 0 gpm OR it may be requested.
Either is acceptable].
Step 5.7 has already been marked NA in the handout. 
( HLT-32 ADMIN exam A.2S EVALUATION CHECKLIST Page 3 of 8 ELEMENTS:
STANDARDS:
RESULTS: (CIRCLE) 4*. Step 5.8 Calculates identified and Calculates identified and S / U unidentified leakages using the formulas on unidentified leakages using the 5*. 6*. STP-9.0 data sheet 1. formulas on STP-9.0 data sheet 1. Step 5.9 Marks NA on step: "IF unidentified leakage is more negative than -0.2, THEN re-perform leak rate measurement. " Compares actual Leak rates with the acceptance criteria, and determines that the Unidentified Leakage does not meet acceptance criteria.
Marks NA on step 5.9 due to leakrate being positive.
Determines that the Identified leakage MEETS acceptance criteria, but the Unidentified Leakage does S / U NOT meet acceptance criteria.
S / U NOTE: An inspection to identify the exact source of leakage, possibly requiring a containment entry, OR isolation of the leak will be required to prove that the leakage in NOT pressure boundary, and until it is proved other wise it must be assumed to be pressure boundary leakage. 7*. Determines that Tec h Spec 3.4.13 in NOT met, AND CONDITION B is in effect for "Pressure boundary LEAKAGE exists". _STOP TIME Determines that Tech Spec 3.4.13 in NOT met, AND CONDITION B is in effect for "Pressure boundary LEAKAGE exists". Be in MODE 3 in 6 hours AND BE MODE 5 in 36 hours is required.
S / U S / U S / U Terminate JPM when determination of applicable Tech Spec ACTION is complete for leak rate. CRITICAL ELEMENTS:
Critical Elements are denoted with an asterisk (*) before the element number.
HL T-32 ADMIN exam A.2S GENERAL REFERENCES
: 1. FNP-I-STP-9.0, Version 42.0 2. Plant tank curves 27 A, 27B, 27C, 28A, & 28B 2. KIA: 004 A2.22 RO-3.2SRO-3.1
: 3. Tech Spec 3.4.13 AND Basis GENERAL TOOLS AND EOIDPMENT Provide: 1. 2. 3. 4. 5. COMMENTS FNP-l-STP-9.0, Version 42.0 Plant tank curves 27 A, 27B, 27C, 28A, & 28B Calculator (or the Applicant may supply a calculator)
Plant Conditions at 1000 & 1200 Tech Spec 3.4.13 AND Basis Page 4 of 8 
( HLT-32 ADMIN exam A.2S Page 5 of 8 KEY: STP-9.0, DATA SHEET 1, RCS Leakage All tolerances based on differences in rounding.
One calc was performed rounding to the least significant digits at each step of the calculation, and one was performed using all digits in the calculator until the end of each step of the calculations to round to the least significant digits. INSTRUMENT NAME INITIAL FINAL FINAL -INITIAL Computer TIME 1000 1200 A=120 Minutes (MCB) TE0453 LIQ PRZR TEMP 650.8 OF 650.8 OF No significant change C5 1&deg;F) (TI0453) PC0482, PT0455, PT0456 or PT0457 PRZRPRESS 2239.4 2239.4 No significant change (PI 455, PI 456 (Note 1) psig psig psig) or PI 457) TC0484 (preferred), OR = 0 OF TY0412K,OR RCSTAVG TY0422K,OR (Note 1)
OF OF Maximum change of 0.3 OF TY0432K (Note 7) allowed ifTAVG is 545&deg;F or greater, O.l&deg;F if TAVG is less (Average of TI 412D, than 545&deg;F. 422D & 432D) RCS Temperature CF (Note 5) 99.7 N/A B x CF = 0 Gal. Correction Factor OR NA LC 1600 OR Average ofLT0459, PRZRLVL 47.8 % 47.8 % C=56.3 x 0 %= o Gal. LT0460 & LT0461 (LI-459, 460, 461) LT0115 VCTLVL
% 37.3 % D = 14.18 x (-)12.7 % = (LI115) (-)194 to 194.3 Gal. LI 1003 Waste Pnl or RCDTLVL 36.4 %
% E = 6.01 to 6.02 Gal. BOP LS261 Pos 6 127.69 *Gal 133.71 *Gal (Enter 0 if negative)
LT0470 PRTLVL 69.7 % 69.7 % F= 0 Gal. (LI470) (Note 2) NA *Gal NA *Gal (Enter 0 if negative)
PIS 168 TOTAL FLOW 3489 Gal. 3489 Gal. G = 0 Gal. Dilution and BATCH INTEG NAGal. NA Gal. Blended Makeup *From Tank Curve Book HLT-32 ADMIN exam A.2S Page 6 of 8 KEY (continued):
STP-900, DATA SHEET 1, Res Leakage Total Leakage 8-C-D+G (0 )-( 0 )-( (-)194 to {-)194.3 )+( 0 ) = A = ( 120 ) = {+)1.617 to {+)1.62 GPM (Note 6) Identified Leakage E+F (6.01t06.02)+( = = A (120) o ) + 0 = 0.050 no tolerance GPM Other leakage (Note 6) Other Leakage: Source o Total Other Rate (GPM) o U &deg;d &deg;fo d Leak 1.617 to 1.62 0.050 no tolerance 1.567 to 1.57 GPM m entl Ie age = = -------Total Leakage Identified Leakage (Notes 3,4, & 6) ACCEPTANCE CRITERIA:
*
* Identified Leakage:::;;
10 gpm Unidentified Leakage:::;;
1 gpm A.2S (2 pages) HANDOUT Plant Conditions at 1000: ( INSTRUMENT NAME Computer Points N/A TIME 1000 TE0453 LIQ PRZR TEMP 650.8 of PC0482 PRZR PRESS 2239.4 psig TC0484 RCS TAVG 571.9 of LC 1600 PRZR LVL 47.8 % LTOl15 VCT LVL 51.0 % BOP LS261 Pos 6 RCDT LVL 36.4 % *Gal LT0470 PRT LVL 69.7 % *Gal FIS 168 TOTAL FLOW 3489 Gal. BATCH INTEG Plant Conditions at 1200: INSTRUMENT NAME Computer Points N/A TIME 1200 TE0453 LIQ PRZR TEMP 650.8 of PC0482 PRZR PRESS 2239.4 Psig ( TC0484 RCS TAVG 571.9 of LC 1600 PRZR LVL 47.8 % LTOl15 VCT LVL 37.3 % BOP LS261 Pos 6 RCDT LVL 38.1 % *Gal LT0470 PRT LVL 69.7 % *Gal FIS 168 TOTAL FLOW 3489 Gal. BATCH INTEG CTMT R-11 Particulate 187 CPM Rad Monitor R-12 CTMT Gas Rad 75 CPM Monitor Q1G21LI3282A Ctmt. Sump lvl 18 Inches Q1G21LI3282B Ctmt. Sump lvl 18 Inches A.2S (2 pages) HANDOUT CONDITIONS When I tell you to begin, you are to perform an RCS Leakage Test and identify if any Tech Spec ACTIONS are applicable, and if so, which ACTION(S).
The conditions under which this task is to be performed are: a. The unit is in Mode 1 at 100% power. b. You are directed by the Shift Supervisor to
* determine RCS leakage per STP-9.0, STEPS 5.4 to 5.9 -WHEN step 5.9 is complete, THEN another operator will complete the STP starting at step 5.10
* determine whether or not RCS leakage acceptance criteria is met
* IF acceptance criteria is NOT met, THEN determine proper Tech Spec ACTION(S).
08/08/08 09:39:04 FARLEY NUCLEAR PLANT SURVEILLANCE TEST PROCEDURE FNP-I-STP-9.0 RCS LEAKAGE TEST FNP-I-STP-9.0 May 30, 2008 Version 42.0 PROCEDURE USAGE REQUIREMENTS PER FNP-0-AP-6 SECTIONS Continuous Use ALL Reference Use Information Use Approved:
J. L. Hunter (for) Operations Manager Date Issued: 05/30/2008
-------S A F E T Y R E L A T E D 08/08/08 09:39:04 'r 11 l, I I FNP-l-STP-9.0 FARLEY NUCLEAR PLANT SURVEILLANCE TEST REVIEW SHEET SURVEILLANCE TEST NO. TECHNICAL SPECIFICATION REFERENCE FNP-I-STP-9.0 SR3.4.13.1 TITLE MODE(S) REQUIRING TEST: RCS LEAKAGE TEST 1,2,3,4 TEST RESULTS (TO BE COMPLETED BY TEST PERFORMER)
PERFOR.c\1ED BY DATE/TIME COMPONENT OR TRAIN TESTED (if applicable) [ ] ENTIRE STP PERFORMED [ ] FOR SURVEILLANCE CREDIT [] PARTIAL STP PERFORMED: [ ] NOT FOR SURVEILLANCE CREDIT REASON FOR PARTIAL: TEST COMPLETED: [ ] Satisfactory [ ] Unsatisfactory [ ] The following deficiencies occurred: [ ] Corrective action taken or initiated:
SHIFT SUPERVISOR!
SHIFT SUPPORT SUPERVISOR REVIEW REVIEWED BY DATE [ ] Procedure properly completed and satisfactory
[] Comments:
ENGINEERING SUPPORT SCREENED BY DATE GROUP SCREENING REVIEWED BY DATE (IF APPLICABLE) [ ] Satisfactory and Approved [ ] Comments: ( Version 42.0 08/08/0809:39:04 FNP-I-STP-9.0 TABLE OF CONTENTS Procedure Contains Number of Pages STRS .........................................................
1 Body ..........................................................
6 Data Sheet 1 ..............................................
3 Page 1 of 1 Version 42.0 
( 08/08/08 09:39:04 1 %l FNP-1-STP-9.0 FARLEY NUCLEAR PLANT UNIT 1 SURVEILLANCE TEST PROCEDURE STP-9.0 RCS LEAKAGE TEST 1.0 Purpose To determine identified and unidentified reactor coolant system leakage by performance of an RCS water inventory balance. NOTE: Asterisked steps (*) are those associated with Acceptance Criteria.
2.0 Acceptance Criteria 2.1 Unidentified leakage is ::;; 1 gpm. 2.2 Identified leakage::;;
10 gpm. NOTE: FNP-I-STP-9.0 RCS Leakage Test (SR 3.4.13.1) is only required to be performed during steady state operation.
AI 2004201338 3.0 Initial Conditions 3.1 3.2 3.3 3.4 3.5 The version of this procedure has been verified to be the current version. (OR 1-98-498)
This procedure has been verified to be the correct unit for the task. (OR 1-98-498)
Reactor power and reactor coolant temperature should be stabilized and held approximately constant for 1 hour prior to and during the test. (In Mode 3 or 4 not required until 12 hours of steady state operation.)
The pressurizer level and pressure control systems are in automatic or are in manual control and are stable. The level of the VCT is in the normal operating band high enough to prevent the occurrence of an Auto Makeup during the test. Version 42.0 
( 08/08/08 09:39:04 FNP-I-STP-9.0 t{fr 3.8 The CVCS system is aligned per FNP-I-SOP-2.1A, CHEMICAL & VOLUME CONTROL SYSTEM. Notify the Shift Chemist and Shift Radiochemist ofthe performance of the test to ensure that no sampling ofthe RCS or CVCS will be done during this test. IF required for step 5.2, THEN ensure the following instrument is in calibration.
* Calibrated Digital Voltmeter FNP LD. # Cal Due Date Version 42.0 08/08/08 09:39:04 FNP-I-STP-9.0 4.0 Precautions And Limitations 4.1 No sampling of the RCS or CVCS shall be done during this test. 4.2 Any of the following will render this test void: 4.2.1 Emergency boration 4.2.2 Diversion ofletdown to the recycle holdup tanks. 4.2.3 Make up from any source which does not go through the boric acid blender. 4.2.4 Boration ofless than 10 gpm, due to Batch Integrator counter inaccuracies.
4.3 To minimize the inaccuracy introduced into the calculation by RCS temperature changes, RCS temperature should be maintained as follows: 4.3.1 IF RCS temp is < 545 OF, THEN the RCS temperature should not change by more than 0.1 OF during the test. 4.3.2 IF RCS temp is 2: 545 OF, THEN the RCS temperature should not change by more than 0.3 OF during the test. 4.3.3 IF required to maintain RCS temperature, THEN control rods, turbine load or boron concentration should be adjusted as necessary.
4.4 The calculation assumes that changes in RCS volume due to PZR temperature 1 pressure fluctuations are negligible.
Pressurizer parameters should be maintained stable to minimize inaccuracy.
4.5 The following guidelines should be followed to maximize precision:
* IF available, THEN computer points should be used for obtaining data. Otherwise, the available indications are to be read as accurately as possible.
* For RCS Tavg, the computer point data should be entered to include three decimal places (i.e., 572.204 OF).
* F or other computer points and RCDT level, the data should be entered to include at least one decimal place (i.e., 50.1 %).
* Identified and unidentified leakage rates are to be reported in two decimal places (e.g., 0.07 gpm).
* IF possible, THEN normal makeup to the VCT should be avoided. 4.6 IF the RCDT or PRT level indication is invalid, THEN use 0 gpm for RCDT or PR T portion of identified leakage unless leakage into the RCDT or PR T is to be determined using another approved method. 4.7 To ensure that the STP-9.0 Computer Program remains current, the Engineering Support Group should be notified of any revision or TCN to the Data Sheet 1. Version 42.0 
( 08/08/08 09:39:04 FNP-I-STP-9.0 5.0 Instructions 5.1 NOTE: I&C N!;\ 5.2 CV c.. ,,0-5.3 The RCDT system is aligned as follows: 5.1.1 RCDT level is in the normal operating band. 5.1.2 Close RCDT PUMPS DISCH LINE ISO QIG2IHV7136 The following step is only required if increased accuracy is necessary for determination of leak rate into PRT or the MeB PRT level indicator has a problem. IF required, THEN have I&C connect a calibrated digital voltmeter across the output ofLQY-470, location C5-231. Place VCT HI LVL DIVERT VLV, QIE2ILCVII5A, in the VCT position.
NOTE: Batch Integrator readings will be taken prior to and at the conclusion of each make up evolution.
5.4 Read and record initial readings on data sheet 1. NOTE: A time span of at least 2 hours should be used during normal steady state plant operations, however if plant conditions dictate, a shorter time span may be used. (30 minutes minimum).
5.5 After the desired time span (normally 2 hours) record final values on data sheet 1. 5.6 Record the following readings (recorded for trending purposes):
Rad Monitor R -11 CPM Rad Monitor R-I2 CPM Ctmt. Sump Iv!. QIG2ILI3282A Inches Ctmt. Sump Iv!. QIG2ILI3282B Inches Version 42.0 08/08/08 09:39:04 T 1 FNP-I-STP-9.0 NA 5.7 IF the RCS leakrate program is to be used, THEN verify that the program is revision 3. NOTE: If the RCS leakrate program is used, then the remainder of data sheet 1 may be left blank. *5.8 Calculate identified and unidentified leakages using the RCS leakrate program or formulas on data sheet 1. ACCEPTANCE CRITERIA:
* Identified Leakage::;;
10 gpm _1-IV _1-IV
* Unidentified Leakage::;;
1 gpm 5.9 IF unidentified leakage is more negative than -0.2, THEN re-perform leak rate measurement.
5.10 5.11 5.12 Open RCDT PUMPS DISCH LINE ISO QIG21HV7136.
Place VCT HI L VL DIVERT VL V, Q lE21LCV115A in the AUTO position.
IF computer point LC0500 is available, THEN review the RCS leakrate trend (last 30 days if possible) on IPC to determine if any abnormal trends exist. 5.13 IF unidentified leakage is >0.15 gpm, THEN re-perform leak rate measurement to confirm the results. 5.14 IF unidentified leakage is confirmed to be >0.15 gpm, THEN perform the following: (steps may be performed in any order) 5.14.1 Perform inspection to identify the leakage path(s) (AOP-l.O, attachments 2 through 5). 5.14.2 Perform evaluation including any recent maintenance, plant evolutions or filter alignments to locate source of leakage, determine corrective actions and the effects of the leakage. 5.14.3 IF leakage is NOT known to be outside CTMT, THEN request chemistry sample CTMT via R-67 for iron analysis.
5.14.4 Submit CR to document the leakage and actions taken. Version 42.0 
( 08/08/08 09:39:04 1 FNP-I-STP-9.0 I&C _1_ 5.15 IV IF applicable, THEN have I&C remove the calibrated digital voltmeter installed in step 5.2. 5.16 Update OPS home page (ULR Data spreadsheet) with unidentified leakage rate. 5.17 IF used for RCS leakrate calculation, THEN attach the computer generated Data Sheet 1 to this procedure.
6.0 References 6.1 P&ID D-175037 -RCS, sheet 2 6.2 P&ID D-175039 -CVCS, sheet 2 6.3 P&ID D-175042 -Waste Processing System, sheet I Version 42.0 08/08/08 09:39:04 INSTRUMENT NAME Computer TIME (MCB) TE0453 LIQ PRZR TEMP (TI0453) PC0482, PT0455, PT0456 or PT0457 PRZRPRESS (PI 455, PI 456 (Note 1) or PI 457) TC0484 (preferred), OR TY0412K, OR TY0422K, OR RCSTAVG TY0432K (Note 7) (Note 1) (Average ofTI 412D, 422D & 432D) ( RCS Temperature CF (Note 5) Correction Factor LC 1600 OR Average ofLT0459, PRZRLVL L T0460 & L T0461 (LI-459, 460, 461) LT0115 VCTLVL (LI 115) LI 1003 Waste Pn1 or RCDTLVL BOP LS261 Pos 6 LT0470 PRTLVL (LI 470) (Note 2) FIS 168 TOTAL FLOW BATCH INTEG *From Tank Curve Book DATA SHEET 1 RCS Leakage INITIAL of pSlg of % % %
* Gal % *Gal Gal. Gal. Page 10f3 FINAL of psig of N/A % % % *Gal % *Gal Gal. Gal. A= FNP-I-STP-9.0 DATA SHEET 1 FINAL -INITIAL Minutes No significant change (:s 1&deg;F) No significant change (:s5 psig) = of Maximum change of 0.3&deg;F allowed ifTAVG is 545&deg;F or greater, 0.1 of if TAVG is less than 545&deg;F. B x CF = Gal. C = 56.3 x %= Gal. D = 14.18 x %= Gal. E= Gal. (Enter 0 if negative)
F= Gal. (Enter 0 if negative)
G= Gal. Dilution and Blended Makeup Version 42.0 08/08/08 09:39:04 Total Leakage FNP-I-STP-9.0 DATA SHEET 1 B-C-D+G ( )-( )-( )+( ) =
GPM A () (Note 6) Identified Leakage = __ E+ __ F __
__ =-------GPM A ( ) Other leakage (Note 6) Other Leakage: Source Rate (GPM) Total Other Unidentified Leakage = GPM Total Leakage Identified Leakage (Notes 3, 4, & 6) ACCEPTANCE CRITERIA:
* Identified Leakage 10 gpm
* Unidentified Leakage 1 gpm Page 2 of3 Version 42.0 
( 08/08/0809:39:04 FNP-I-STP-9.0 DATA SHEET 1 NOTES: 1 IF TAVG < 530&deg;F, THEN use: PI-402A (PT0402) and PI-403A (PT0403), 1 C and lA Loop RCS WR PRESS (A vg. of Readings)
AND TR-4l0 (TE04l0) and TR-413 (TE0413), RCS COLD AND HOT LEG TEMP (Avg. of Readings) 2 Calibrated fluke may be used for PRT level determination if deemed necessary.
3 For reporting purposes values between -0.2 and 0 gpm shall be reported as 0 gpm. Values more negative than -0.2 gpm indicate a potential problem and therefore shall be reported as is. 4 If unidentified leakage> 0.9 but < 1 gpm, test should be reperformed with ZAS secured. At maximum injection rate, ZAS can introduce
-0.03 gpm error into calculation.
5 Obtain CF from Table 1 using the nearest value of RCS temperature.
N/A if RCS Leakrate program is used. 6 Leakage calculations are to be reported in two decimal places (e.g., 0.07 gpm). 7 TC0484 is preferred for RCS Tavg, but an individual loop temperature may be used if desired due to instability in the average reading. TABLE 1 Res Temp Page 3 of3 Version 42.0 
" j HEl (i. 0. 1,80 1 .. :{'7 ?(k .< ')i::-.;.A' .
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........ VOLUME II CURVE 27A PRESSURIZER RELIEF TANK CAPACITY CAPACITY (GAL} VS LEVEL (FEET) REV. 1 March 8,1978 GAP APPROVED:
Pa+ fIOlil-cl..v;;'11t mucAL SOmRINTENPE T
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fleV')liS t 47 1510 f ( 
% LEVEL GALLONS 0.103 222.12 272.18 3.8 381.81 4.8 441.16 5.8 58:3.28 6. 568.85 7.8 635.34 :3.(1 785.02 9.0 776.9'9 18.0 85L 16 11.0 '327.43 12.0 1085.71 1:3.8 1885.89 14.8 1167.94 15.8 1251.77 16.8 1337.29 17.8 1424.47 18.0 151:3.28 1'3. (1 1603.42 21. *I i 78:3. 17 22.*1 1882.56 1 1 5i78.22 24.0 2075.11 25.8 2173.14 VOLUME II CURVE 27C PRESSURIZER RELIEF TANK CAPACITY TABLE N1B32T001 CAPACITY (GAL) VS % LEVEL REV. 0 May 7, 1980 GAF APPROVED:
fU-{-V/)l'iJ.."
TECHNICAL SUPERINTENDENT
% LEVEL GALLONS % LEVEL GALLONS 26_ 0 2272.2'3 52.8 5086.3:3 27.8 2372.49 53. *I 51'38.21 28.0 2473,,73 54.8 5389.92 29.8 2575.91 55.0 5421. 45 30. 267:3.98 56.8 5532.79 31.0 2782.92 57
* 564:3.89 32.0 2:387. 7G.1 58.0 5754.6:3 59.8 5865.14 34. *I :3099.49 60.1!1 5975.22 35.8 3206.4:3 61.8 6884.90 36.0 3314.00 62. 6194. 11 :37. *I 3422.18 63 .. to 6:302.82 38.0 3538.89 64. *I 6411.0i21 3'3.0 :3648.10 65.8 6518.57 48.8 :3749.78 66.13 6625.51 41. *I 3859.86 67. 6731. 76 42.0 3970. :32 68.8 6837. 3f'l 43.13 48:31.11 44.0 4192.21 7*1.G 7046.02 45.8 43133.55 71. 0 7' 14',. 0'j 46.0 4415.68 72.0 7251.27 47.8 4526.79 7:3. 0 7:352. 51 48.0 4638.62 74.0 7452.71 49.0 47510.54 75.0 7551.86 58,0 4862.50 51.0 4974.46 77.0 7746.78 % LEVEL GALLONS 78.0 7842.44 81.(1 8121.58 82. 0
:3(1 83.0 :3300_ 53 :34.0 83:37.71 85. (1 847:3.2:3 86.8 8557 *
*I 8873. :34 91.0 :3948.81 92.0 9019.98 94. 0 '3156. '35 VOLUME II ClJI.'R 28A REACTOR COOLANT DRAIN TANK CAPACITY , ........ + ... _ .. NIG21TOOl
... CAPACITY (GAL) VS LEVEL (FEET) . REV 2 June 11, 1986 JMR APPROVED:
...
rr-s--zi' . DATI l;1QPI-10(1) ....... J2@. 14(j) ... 16.. 1 , tV: GALLONS HEIGHT O.()O 0.25 0.50 0.75 1.00 1.25 1.47 1.72 1.97 2.23 2.47 2.72 VOLUME ft' 0.0 1.8 4.8 8.6 12.9 17.4 21.4 26.0 30.4 34.6 38.3 41.3 GALLONS 0.0 13.7 38.2 69.0 103.9 141.5 175.1 213.9 251.2 285.7 315.8 339.0 . .., rotAL VOLUME Hi GALLONS 349.9 **********1*****
************_**,*-,i-**-,********;
... _ ... j ........ ... no . . 3do 320 340 360 . 1 . . . ... ..... ""( ..... .
Unit 1 Volume II Curve 28B Reactor Coolant Drain Tank capacity . ptf; -I-I!ol.:;}
.. 8/j NIG21TOOl Capacity (Gallons) vs % Level Rev. 2, December 14, 1981, C.A.P. Approved:
J -2:'2-a)...
Date LE\lEL (1, ti 1.0 4.0 '5.0 ,(,(I :3. k:i HLO 11.0 1 :::. fa 1. 4. (1 15 y !2t j, 6. (I i 7
* 1 :;:!" (1 1 121 21. If 2:::.0 24.0 2:5 a 26.0 11 t1 2')" () 30. :::::1,0 32"
::,: 6
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:;i6 72.5(1 75.67 S2. 1 85. :36 64 91. 95 9:3 II 66 H32.04 lt 1 5.45 1 8;:; 112_ :32 115. (', 11lj_27 122.7? 12 1 9.81 1::3:3.:35 136.90 140.4f'; 144.
151.21 158.41 J.
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75.0 76n0 ?7 It ei ('?O ::::0. (1 !31 ,
II 0 0 ;:::4.6 ti " li -3 It ):::1
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::: " 5121 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.13 RCS Operational LEAKAGE RCS Operational LEAKAGE 3.4.13 LCO 3.4.13 RCS operational LEAKAGE shall be limited to: a. No pressure boundary LEAKAGE; b. 1 gpm unidentified LEAKAGE; c. 10 gpm identified LEAKAGE; and d. 150 gallons per day primary to secondary LEAKAGE through any one steam generator (SG). APPLICABILITY:
MODES 1, 2, 3, and 4. ACTIONS CONDITION REQUIRED ACTION A. RCS operational A.1 Reduce LEAKAGE to LEAKAGE not within limits within limits. for reasons other than pressure boundary LEAKAGE or primary to secondary LEAKAGE. B. Required Action and B.1 Be in MODE 3. associated Completion Time of Condition A not AND met. B.2 Be in MODES. OR Pressure boundary LEAKAGE exists. OR Primary to secondary LEAKAGE not within limit. Farley Units 1 and 2 3.4.13-1 COMPLETION TIME 4 hours 6 hours 36 hours Amendment No. 163 (Unit 1) Amendment No. 156 (Unit 2) 
( RCS Operational LEAKAGE 3.4.13 SURVEILLANCE REQUIREMENTS SR 3.4.13.1 SR 3.4.13.2 SURVEILLANCE
----------------------------NOTES--------------------------------
: 1. Not required to be performed in MODE 3 or 4 until 12 hours of steady state operation.
: 2. Not applicable to primary to secondary LEAKAGE. Verify RCS operational LEAKAGE is within limits by performance of RCS water inventory balance. -----------------------------NOTE--------------------------------
Not required to be performed until 12 hours after establishment of steady state operation.
Verify primary to secondary LEAKAGE is S 150 gallons per day through anyone SG. FREQUENCY Only required to be performed during steady state operation 72 hours 72 hours Farley Units 1 and 2 3.4.13-2 Amendment No. 163 (Unit 1) Amendment No. 156 (Unit 2)
RCS Operational LEAKAGE B 3.4.13 B 3.4 REACTOR COOLANT SYSTEM (RCS) B 3.4.13 RCS Operational LEAKAGE BASES BACKGROUND Farley Units 1 and 2 Components that contain or transport the coolant to or from the reactor core make up the RCS. Component joints are made by welding, bolting, rolling, or pressure loading, and valves isolate connecting systems from the RCS. During plant life, the joint and valve interfaces can produce varying amounts of reactor coolant LEAKAGE, through either normal operational wear or mechanical deterioration.
The purpose of the RCS Operational LEAKAGE LCO is to limit system operation in the presence of LEAKAGE from these sources to amounts that do not compromise safety. This LCO specifies the types and amounts of LEAKAGE. 10 CFR 50, Appendix A, GDC 30 (Ref. 1), requires means for detecting and, to the extent practical, identifying the source of reactor coolant LEAKAGE. Regulatory Guide 1.45 (Ref. 2) describes acceptable methods for selecting leakage detection systems. The safety significance of ReS LEAKAGE varies widely depending on its source, rate, and duration.
Therefore, detecting and monitoring reactor coolant LEAKAGE into the containment area is necessary.
Quickly separating the identified LEAKAGE from the unidentified LEAKAGE is necessary to provide quantitative information to the operators, allowing them to take corrective action should a leak occur that is detrimental to the safety of the facility and the public. A limited amount of leakage inside containment is expected from auxiliary systems that cannot be made 100% leaktight.
Leakage from these systems should be detected, located, and isolated from the containment atmosphere, if possible, to not interfere with ReS leakage detection.
This LeO deals with protection of the reactor coolant pressure boundary (RePB) from degradation and the core from inadequate cooling, in addition to preventing the accident analyses radiation release assumptions from being exceeded.
The consequences of violating this LeO include the possibility of a loss of coolant accident (LOCA). B 3.4.13-1 Revision 0 BASES RCS Operational LEAKAGE B 3.4.13 APPLICABLE Except for primary to secondary LEAKAGE, the safety analyses do not SAFETY ANALYSES address operational LEAKAGE. However, other operational LEAKAGE is typically seen as a precursor to a LOCA; the amount of leakage can affect the probability of such an event. The safety analysis for an event resulting in steam discharge to the atmosphere assumes that primary to secondary LEAKAGE from all steam generators (SGs) is 1 gpm as a result of accident induced conditions.
The LCO requirement to limit primary to secondary LEAKAGE through anyone SG to less than or equal to 150 gpd (Le. total leakage less than or equal to 450 gpd) is significantly less than the conditions assumed in the safety analysis (with leakage assumed to occur at room temperature in both cases). Farley Units 1 and 2 Primary to secondary LEAKAGE is a factor in the dose releases outside containment resulting from a steam line break (SLB) accident.
To a lesser extent, other accidents or transients involve secondary steam release to the atmosphere, such as a steam generator tube rupture (SGTR). The leakage contaminates the secondary fluid. The FSAR (Ref. 3) analysis for SGTR assumes the contaminated secondary fluid is released via the main steam safety valves. The majority of the activity released to the atmosphere results from the tube rupture. Therefore, the 1 gpm primary to secondary LEAKAGE safety analysis assumption is relatively inconsequential.
The SLB is more limiting for primary to secondary LEAKAGE. The safety analysis for the SLB assumes 500 gpd and 470 gpd primary to secondary LEAKAGE in the faulted and intact steam generators respectively as an initial condition.
The dose consequences resulting from the SLB accident are bounded by a small fraction (Le., 10%) of the limits defined in 10 CFR 100. The RCS specific activity assumed was 0.5 JlCi/gm DOSE EQUIVALENT 1-131 at a conservatively high letdown flow of 145 gpm, with either a pre-existing or an accident initiated iodine spike. These values bound the Technical Specifications values. The RCS operational LEAKAGE satisfies Criterion 2 of 10 CFR 50.36(c)(2)(ii).
B 3.4.13-2 Revision 24 BASES LCO ( Farley Units 1 and 2 RCS Operational LEAKAGE B 3.4.13 RCS operational LEAKAGE shall be limited to: a. Pressure Boundary LEAKAGE No pressure boundary LEAKAGE is allowed, being indicative of material deterioration.
LEAKAGE of this type is unacceptable as the leak itself could cause further deterioration, resulting in higher LEAKAG E. Violation of this LCO could result in continued degradation of the RCPB. LEAKAGE past seals and gaskets is not pressure boundary LEAKAGE. b. Unidentified LEAKAGE c. d. One gallon per minute (gpm) of unidentified LEAKAGE is allowed as a reasonable minimum detectable amount that the containment air monitoring and containment sump level monitoring equipment can detect within a reasonable time period. Violation of this LCO could result in continued degradation of the RCPB, if the LEAKAGE is from the pressure boundary.
Identified LEAKAGE Up to 10 gpm of identified LEAKAGE is considered allowable because LEAKAGE is from known sources that do not interfere with detection of unidentified LEAKAGE and is well within the capability of the RCS Makeup System. Identified LEAKAGE includes LEAKAGE to the containment from specifically known and located sources, but does not include pressure boundary LEAKAGE or controlled reactor coolant pump (RCP) sealleakoff (a normal function not considered LEAKAG E). Violation of this LCO could result in continued degradation of a component or system. Primary to Secondary LEAKAGE Through Any One SG The limit of 150 gpd per each SG is based on the operational LEAKAGE performance criterion in NEI 97-06, Steam Generator Program Guidelines (Ref. 4). The Steam Generator Program operational LEAKAGE performance criterion in NEI 97-06 states, "The RCS operational primary to secondary leakage through any one SG shall be limited to 150 gallons per day." The limit is based on operating experience with SG tube degradation mechanisms that result in tube leakage. The operational leakage rate criterion in conjunction with the implementation of the Steam Generator Program is an effective measure for minimizing the frequency of steam generator tube ruptures.
B 3.4.13-3 Revision 24 BASES APPLICABI LlTY ACTIONS Farley Units 1 and 2 RCS Operational LEAKAGE B 3.4.13 In MODES 1, 2, 3, and 4, the potential for RCPB LEAKAGE is greatest when the RCS is pressurized.
In MODES 5 and 6, LEAKAGE limits are not required because the reactor coolant pressure is far lower, resulting in lower stresses and reduced potentials for LEAKAGE. LCO 3.4.14, "RCS Pressure Isolation Valve (PIV) Leakage," measures leakage through each individual PIV and can impact this LCO. Of the two PIVs in series in each isolated line, leakage measured through one PIV does not result in RCS LEAKAGE when the other is leak tight. If both valves leak and result in a loss of mass from the RCS, the loss must be included in the allowable identified LEAKAGE. Unidentified LEAKAGE or identified LEAKAGE in excess of the LCO limits must be reduced to within limits within 4 hours. This Completion Time allows time to verify leakage rates and either identify unidentified LEAKAGE or reduce LEAKAGE to within limits before the reactor must be shut down. This action is necessary to prevent further deterioration of the RCPB. B.1 and B.2 If any pressure boundary LEAKAGE exists, or primary to secondary LEAKAGE is not within limit, or if unidentified or identified LEAKAGE cannot be reduced to within limits within 4 hours, the reactor must be brought to lower pressure conditions to reduce the severity of the LEAKAGE and its potential consequences.
It should be noted that LEAKAGE past seals and gaskets is not pressure boundary LEAKAGE. The reactor must be brought to MODE 3 within 6 hours and MODE 5 within 36 hours. This action reduces the LEAKAGE and also reduces the factors that tend to degrade the pressure boundary.
The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems. In MODE 5, the pressure stresses acting on the RCPB are much lower, and further deterioration is much less likely. B 3.4.13-4 Revision 24 BASES SURVEILLANCE REQUIREMENTS Farley Units 1 and 2 SR 3.4.13.1 RCS Operational LEAKAGE B 3.4.13 Verifying RCS LEAKAGE to be within the LCO limits ensures the integrity of the RCPB is maintained.
Pressure boundary LEAKAGE would at first appear as unidentified LEAKAGE and can only be positively identified by inspection.
It should be noted that LEAKAGE past seals and gaskets is not pressure boundary LEAKAGE. Unidentified LEAKAGE and identified LEAKAGE are determined by performance of an RCS water inventory balance. The RCS water inventory balance must be met with the reactor at steady state operating conditions and near operating pressure.
The I Surveillance is modified by two Notes. Note 1 states that this SR is not required to be performed in MODES 3 and 4 until 12 hours of steady state operation near operating pressure have been established.
Steady state operation is required to perform a proper inventory balance; calculations during maneuvering are not useful and a Note requires the Surveillance to be met when steady state is established.
For RCS operational LEAKAGE determination by water inventory balance, steady state is defined as stable RCS pressure, temperature, power level, pressurizer and makeup tank levels, makeup and letdown, and RCP seal injection and return flows. An early warning of pressure boundary LEAKAGE or unidentified LEAKAGE is provided by the automatic systems that monitor the containment atmosphere radioactivity and the containment air cooler condensate flow rate. It should be noted that LEAKAGE past seals and gaskets is not pressure boundary LEAKAGE. These leakage detection systems are specified in LCO 3.4.15, "RCS Leakage Detection Instrumentation." Note 2 states that this SR is not applicable to primary to secondary LEAKAGE. This is because LEAKAGE of 150 gpd cannot be measured accurately by an RCS water inventory balance. The 72 hour Frequency is a reasonable interval to trend LEAKAGE and recognizes the importance of early leakage detection in the prevention of accidents.
A Note under the Frequency column states that this SR is required to be performed during steady state operation. ( continued)
B 3.4.13-5 Revision 24 BASES SURVEILLANCE REQUIREMENTS REFERENCES Farley Units 1 and 2 SR 3.4.13.2 RCS Operational LEAKAGE B 3.4.13 This SR verifies that primary to secondary LEAKAGE is less than or equal to 150 gpd through anyone SG. Satisfying the primary to secondary LEAKAGE limit ensures that the operational LEAKAGE performance criterion in the Steam Generator Program is met. If this SR is not met, compliance with LCO 3.4.17, "Steam Generator Tube Integrity," should be evaluated.
The 150 gpd limit is measured at room temperature as described in Reference
: 5. The operational LEAKAGE rate limit applies to LEAKAGE through anyone SG. If it is not practical to assign the LEAKAGE to an individual SG, all the primary to secondary LEAKAGE should be conservatively assumed to be from one SG. The Surveillance is modified by a Note which states that the Surveillance is not required to be performed until 12 hours after establishment of steady state operation.
For RCS primary to secondary LEAKAGE determination, steady state is defined as stable RCS pressure, temperature, power level, pressurizer and makeup tank levels, makeup and letdown, and RCP seal injection and return flows. The Surveillance Frequency of 72 hours is a reasonable interval to trend primary to secondary LEAKAGE and recognizes the importance of early leakage detection in the prevention of accidents.
During normal operation the primary to secondary LEAKAGE is determined using continuous process radiation monitors or radiochemical grab sampling in accordance with EPRI guidelines.
: 1. 10 CFR 50, Appendix A, GDC 30. 2. Regulatory Guide 1.45, May 1973. 3. FSAR, Section 3.1.2.6, 5.2.7,10.4,11.0, 12.0 and 15.0. 4. NEI 97-06, "Steam Generator Program Guidelines." 5. EPRI TR-104788, "Pressurized Water Reactor Secondary Leak Guidelines." B 3.4.13-6 Revision 24 
( HLT-32 ADMIN exam A.3 SRO&RO Page 1 of 6 A.3 SRO&RO Radiation Control ADMIN G2.3.4 -SRO and RO TITLE: Determine If Any Radiation Dose Limits Will Be Exceeded TASK STANDARD:
Calculate Dose expected for two workers, and determine that the job cannot be performed by one worker due to FNP Admin dose limit, and the job cannot be performed by the other worker due to the RWP Digital Alarming Dosimeter (DAD) Alarm limit. PROGRAM APPLICABLE:
SOT SOCT
__ ACCEPTABLE EVALUATION METHOD: PERFORM SIMULATE DISCUSS EVALUATION LOCATION:
SIMULATOR CONTROL ROOM CLASSROOM PROJECTED TIME: 30 MIN SIMULATOR IC NUMBER: ---=..;N=A=--
__ _ ALTERNATE PATH TIME CRITICAL PRA __ Examinee:
Overall JPM Performance:
Satisfactory Cl Unsatisfactory Cl Evaluator Comments (attach additional sheets if necessary)
EXANUNER:
________________
_ 
( HLT-32 ADMIN exam A.3 SRO&RO Page 2 of 6 CONDITIONS When I tell you to begin, you are to DETERMINE IF ANY RADIATION DOSE LIMITS WILL BE EXCEEDED during a containment entry to inspect and take pictures at the lA RCP seal area. The conditions under which this task is to be performed are: a. A power reduction to 12% has been performed on Unit 1. b. The ED and the HP Supervisor on-call have approved personnel entry inside the 105' Missile Barrier. c. The transit route is <2 mrlhr except as noted on the provided survey maps. d. HP has determined the lowest dose route is down the containment stairwell to the 105' level, outside the bio shield, go inside the bio shield at the south east entrance, proceed past the C loop to the A loop area, and ascend the ladder to the A RCP LOWER platform to access the lA RCP Seal area (See survey maps). e. HP estimates that it will take 3 minutes to travel inside the bio shield and ascend the ladder to the lA Rep. f. g. h. i. The workers estimate that it will take 36 minutes at the RCP seal area for the inspection.
NO contact with any RCP Cubical surfaces will be needed for the inspection.
Worker A year to date accumulated dose is 1700 mr. Worker B year to date accumulated dose is 1650 mr. j. The containment survey maps have been marked during the pre-job brief with the expected transit route in red. k. 1. A radiological pre-job brief has been performed.
Your task is to prepare for the seal inspection on the 2A RCP. You are to determine:
1.) what predicted dose both workers will receive, and 2.) if workers A and B will be able to perform the task without exceeding any dose limits. EVALUATION CHECKLIST ELEMENTS:
STANDARDS:
START TIME Calculates dose that 25mr will be received, RESULTS: (CIRCLE)
* 1. Calculates dose that will be received from entry into the bio shield to the RCP. inside the bio shield traveling to the RCP for a S I U total of 50mr for the entry and return trips. (500mrlhr)(3minltrip)(2trips)(lhr/60mins)
=50mr *2. Calculates dose that will be received near the RCP. (450 mrlhr)(36min) (lhr/60mins)=270mr Calculates dose that 270mr will be received by each worker near the RCP. S/U 
( HLT-32 ADMIN exam A.3 SRO&RO EVALUATION CHECKLIST ELE:MENTS:
*3. Calculates total dose that will be received by each worker. 270rrrr+50rrrr=320rrrr
*4. Calculates yearly dose which would be accumulated if the job was performed and dose accumulated as estimated.
320+ 1700=2020rrrr>ADMIN limit 320+1650=1970rrrr<
ADMIN limit, but> DAD limit STANDARDS:
Calculates dose that will be received by each worker during the entire entry for a total of 320rrrr. Calculates the estimated yearly dose after job would be 2020rrrr for worker A and 1,970rrrr for worker B. Page 3 of 6 RESULTS: (CIRCLE) S / U S / U NOTE TO EVALUATOR:
Examinee may indicate that permission from lIP is required for both workers to raise their DAD dose alarm setpoints to greater than 320mr AND/OR an admin dose extension above 1220 mr is required for worker A to perform the job. *5. Determines that the DAD Alarm limit is exceeded by BOTH workers, and the annual admin dose limit would be exceeded by worker A ONLY. _STOP TlME Determines that the DAD limit (above 300rrrr for the job) would be exceeded by BOTH workers, and the ADMIN limit would be exceeded by worker A only (above the limit of 2,000 rrrr). S / U Terminate when both worker doses have been determined and evaluation of limits is complete.
CRITICAL ELEMENTS:
Critical Elements are denoted with an asterisk (*) preceding the element number.
HLT-32 ADMIN exam A.3 SRO&RO Page 4 of 6 GENERAL
 
==REFERENCES:==
: 1. FNP-0-M-001, Version 18.0 2. KA: G2.3.4 RO-3.2 SRO-3.7 GENERAL TOOLS AND EOmPMffiNT Provide: 1. FNP-0-M-001, lIP Manual, Version 18.0 2. Containment Survey Maps 3. RWP 4. Calculator (or the Applicant may supply a calculator)
COMMENTS:
HLT-32 ADMIN exam A.3 SRO&RO Page 5 of 6 KEY: Worker A WorkerB Initial Dose 1700mr 1650mr Trip to pump 3minx500mrlhr
= 25mr 3minx500mrlhr
= 25mr At pump 36minx450mrlhr
= 270mr 36minx450mrlhr
= 270mr Trip from pump 3minx500mrlhr
= 25mr 3minx500mrlhr
= 25mr Total dose for job 320mr 320mr Margin left to 2000mr/qtr admin 300mr 350mr limit Margin left to 300mr DAD limit 300mr 300mr Total IF Job was performed 1700+320=2020mr 1650+320=
1970mr Limiting dose which could be 300mr due to the ADMIN AND 300mr due to the DAD limit received the DAD limits ONLY Worker A cannot perform the task due to exceeding the FNP ADMIN 2000mr/qtr limit, AND the DAD alarm dose limit of 300mr. Worker B cannot perform the task due to exceeding the DAD dose limit of 300mr, but does NOT exceed the FNP ADMIN dose limit of2000mr/qtr.
ONLY with an increased DAD dose limit approval by Health Physics (HP) AND an FNP admin dose limit extension could Worker A perform the job. (must take into account the 25mr on the return trip or it will appear that Worker A can perform the task without exceeding his ADMIN Yearly margin or DAD limit) ONLY with an increased DAD dose limit approval by Health Physics (HP) could Worker B perform the job. (must take into account the 25mr on the return trip or it will appear that Worker B can perform the task without exceeding his DAD dose margin) Limiting dose which could be 300mr due to the ADMIN or 300mr due to the DAD limit received DAD limit A.3SRO & RO (1 page) HANDOUT CONDITIONS When I tell you to begin, you are to DETERMINE IF ANY RADIATION DOSE LIMITS WILL BE EXCEEDED during a containment entry to inspect and take pictures at the 1A RCP seal area. The conditions under which this task is to be performed are: a. A power reduction to 12% has been performed on Unit 1. h. The ED and the HP Supervisor on-call have approved personnel entry inside the 105' Missile Barrier. c. The transit route is <2 mrlhr except as noted on the provided survey maps. d. HP has determined the lowest dose route is down the containment stairwell to the 105' level, outside the bio shield, go inside the bio shield at the south east entrance, proceed past the C loop to the A loop area, and ascend the ladder to the A RCP LOWER platform to access the 1A RCP Seal area (See survey maps). e. HP estimates that it will take 3 minutes to travel inside the bio shield and ascend the ladder to the 1A RCP. f. The workers estimate that it will take 36 minutes at the RCP seal area for the inspection.
: g. NO contact with any RCP Cubical surfaces will be needed for the inspection.
: h. Worker A year to date accumulated dose is 1700 mr. i. Worker B year to date accumulated dose is 1650 mr. j. The containment survey maps have been marked during the pre-job brief with the expected transit route in red. k. A radiological pre-job brief has been performed.
: 1. Your task is to prepare for the seal inspection on the 2A RCP. You are to determine:
1.) what predicted dose both workers will receive, and 2.) if workers A and B will be able to perform the task without exceeding any dose limits.
02/24/0414:13:02 FNP-O-M-OO 1 December 12, 2002 Version 18.0 SOUTHERN NUCLEAR COMPANY JOSEPH M. FARLEY NUCLEAR PLANT HEALTH PHYSICS MANUAL PROCEDURE USAGE REQUIREMENTS PER FNP-0-AP-6 SECTIONS Continuous Use Reference Use Information Use ALL D. E. GRISSETTE Nuclear Plant General Manager S A F E T Y R E L A T E D Date Issued
______ _
02124/04 14:13:02 FNP-O-M-OOI LIST OF EFFECTIVE PAGES VERSION NO. PAGE NO. REV 14 15 16.0 17.0 18.0 19.0 20.0 21.0 22.0 23.0 i X X X X X ii X X X X X 1 X X X X X 2 X X X X X 3 X X X X X 4 X X X X X 5 X X X X X 6 X X X X X 7 X X X X X 8 X X X X X 9 X X X X X 10 X X X X X 11 X X X X X 12 X X X X X 13 X X X X X 14 X X X X X 15 X X X X X 16 X X X X X 17 X X X X X 18 X X X X X 19 X X X X X 20 X X X X X Appendix A, pgs 1-5 X X X X X Page 1 ofl 02/24/0414:13:02 TABLE OF CONTENTS SECTION 1.0 PURPOSE
 
==2.0 REFERENCES==
 
3.0 RESPONSIBILITIES 3.1 INDMDUALS 3.2 SUPERVISORY PERSONNEL 3.3 HEALTH PHYSICS GROUP 3.4 DOSIMETRY SECTION 4.0 RADIATION PROTECTION STANDARDS 4.1 EXPOSURE LIMITS FOR PERSONNEL 4.1.1 OCCUPATIONAL EXPOSURE 4.1.2 INTERNAL EXPOSURE 4.1.3 RADIATION EXPOSURE LIMITS ANNUAL ADMINISTRATIVE EXPOSURE GUIDELINES LIFETIME OCCUPATIONAL EXPOSURE GUIDELINES 4.1.4 ACCUMULATION OF RADIATION EXPOSURE 4.1.5 DOSIMETRY RECORDS 5.0 PERSONNEL MONITORING 5.1 RESPONSIBILITIES 5.2 ISSUE OF DOSIMETRY DEVICES 5.3 PROCESSING TLD'S 5.4 WEARING DOSIMETRY 5.5 MULTIBADGING -i-FNP-0-M-001 Version 18.0 02/24/04 14:13:02 6.0 5.6 BIOASSAY 5.7 MEDICAL EXAMINATIONS RADIATION EXPOSURE CONTROL 6.1 RESPONSIBILITIES 6.2 SPECIAL INSTRUCTIONS 6.3 CLASSIFICATION OF AREAS WITHIN AN RCA 6.4 RADIATION WORK PERMIT 6.5 USE OF TOOLS INSIDE THE RCA 6.6 RADIOACTIVE COMPONENT CONTROL 6.7 RADIOACTIVE WASTE CONTROL 6.8 RADIOLOGICAL PROTECTIVE CLOTHING 6.9 PARTIAL ENTRY INTO A CONTAMINATED AREA 6.10 STEP OFF PADS 6.11 SECURING MATERIALSIEQUIPMENT THAT CROSS CONTAMINATION BOUNDARIES 6.12 RESPIRATORY PROTECTION 6.13 RADIOACTIVE SOURCE CONTROL 6.14 CLIMBING IN THE OVERHEAD INSIDE RCA 7.0 RADIOACTIVE MATERIAL SPILLS APPENDIX A -DEFINITIONS -ii-FNP-O-M-OOI Version 18.0 02/24/04 14:13:02 FNP-0-M-001 HEALTH PHYSICS MANUAL 1.0 Purpose The purpose of the Health Physics Manual is to establish the Administrative controls necessary to ensure Farley Nuclear Plant's (FNP) compliance with applicable regulations, licenses, industry standards and company policy for radiation protection.
The Health Physics Group is responsible for the development and administration of a health physics program to provide effective radiation protection for plant employees, contractors and visitors during operations, maintenance, refueling, and during emergencies.
This manual is supplemented by radiation protection procedures and radiation protection training programs.
Activities for the administration and conduct of the health physics program are included in Administrative Procedure (FNP-0-AP-17), Radiation Control and Protection Procedures (RCPs) and Dosimetry Procedures (DOSs). Terms are defmed in AppendixA.
2.0 References 2.1 10CFR20, Standards for Protection Against Radiation.
2.2 lOCFR19, Notices, Instructions, and Reports to Workers; Inspections.
2.3 Regulatory Guide 8.7, Instructions for Recording and Reporting Occupational Radiation Exposure Data. 2.4 Regulatory Guide 8.27, Radiation Protection Training for Personnel at Light-Water-Cooled Nuclear Power Plants. 2.5 Regulatory Guide 8.8, Information Relevant to Ensuring that Occupational Radiation Exposure at Nuclear Power Stations will be As Low As Is Reasonably Achievable.
2.6 Regulatory Guide 8.10, Operating Philosophy for Maintaining Occupational Radiation Exposures As Low As Practicable.
2.7 NUREG-0041, Manual of Respiratory Protection Against Airborne Radioactive Materials.
2.8 INPO 91-014 Guidelines For Radiological Protection At Nuclear Power Stations.
2.9 FNP-0-AP-90, Alara Policy and Implementation.
2.10 NCRP-91, Recommendations On Limits For Exposure To Ionizing Radiation.
2.11 Southern Nuclear Company, Radiation Protection Policies and Interpretations. Version 18.0 02/24/04 14:13:02 FNP-O-M-OOI 2.12 FNP-O-TCP-15.0, Training Material Development, Revisions and Approvals.
2.13 FNP-O-RCP-O, General Guidance and Special Instructions to Health Physics Personnel.
2.14 FNP-O-DOS-l, Personnel Monitoring.
3.0 Responsibilities The success of the FNP Health Physics Program depends largely on the training, discipline and cooperation of each individual.
The following list some specific responsibilities of individuals, supervisory personnel, the Health Physics Group, and the Dosimetry section. 3.1 Individuals 3.1.1 Take reasonable precautions to avoid unnecessary exposure and minimize those exposures that are considered necessary.
That is, maintain radiation exposure As Low As Reasonably Achievable (ALARA). 3.1.2 Report promptly to Shift Supervisor and HP Supervision all injuries that involve radioactive contamination, sickness or any physical condition which might alter their capability for radiation work. 3.1.3 Report to HP personnel any new or unusual situations which could lead to unnecessary exposure.
3.1.4 Report to HP personnel any unanticipated change in contamination, real or suspected.
3.1.5 Understand their "rights" as defined in lOCFRI9, "Notices, Instructions, and Reports to Workers; Inspections." 3 .1.6 Review and follow the requirements of the Radiation Work Permit under which work is being performed.
3.1.7 Report to HP Supervision or Dosimetry Section any known or anticipated non FNP related radiation exposure such as medical exposure or exposure at site locations, as described in section 4.1.4. 3.1.8 Leave the area and then notify the Control Room if you find any permanently installed plant fixed area radiation monitor or any permanently installed plant fixed air monitor alarming.
If it can be determined that the alarm is not due to a radiological hazard (e.g. Maintenance, Calibration Repair, Outstanding Deficiency Report, etc.), then exiting area and notification is not required. Version 18.0 02124/04 14:13:02 FNP-O-M-OOI 3.1.9 Leave the area and notify HP personnel if you find any HP portable area radiation monitor or any HP portable air monitor alarming.
If it can be determined that the alarm is not due to a radiological hazard (e.g. Maintenance, Calibration Repair, Outstanding Deficiency Report, etc.), then exiting area and notification is not required.
3.1.10 Comments for improving the manual or any part of the Health Physics Program may be submitted at any time to Health Physics Supervision.
3.2 Supervisory Personnel 3.2.1 Ensure that employees under their supervision review radiation hazards in their work area and periodically check employees in the field to ensure that radiation protection measures are being utilized.
3.2.2 Take reasonable steps to ensure jobs are planned to avoid unnecessary exposure of employees.
3.2.3 Personnel will be rotated in so far as practical for uniformity of occupational radiation exposure within each group. 3.2.4 Utilize any available method (e.g. ALARA suggestions, Lesson learn, etc.) to provide input to the ALARA Staff or an ALARA Committee Member concerning suggestions for further reducing personnel dose. 3.2.5 Be alert for new or unusual situations which might lead to unnecessary exposure.
3.3 Health Physics Group 3.3.1 Establish and apply radiation protection standards and practices for ing occupational radiation exposures ALARA. 3.3.2 Inform management of the current radiation exposure via periodic reports. 3.3.3 Collect data and prepare reports on Health Physics related occurrences as described in FNP-0-RCP-10.
*HP will periodically trend data associated with radiological practices to determine if adverse trends are developing.
3.3.4 Report to Shift Supervisor and HP Supervision as soon as possible, known or suspected overexposures due to external radiation or from internal or external contamination.
*NRC Commitment  Version 18.0 
( 02124/04 14:13:02 FNP-0-M-001 3.4 Dosimetry Section 3.4.1 Coordinate the issuing and reading of thermoluminescence dosimeters (TLDs). 3.4.2 Provide exposure reports to supervisors upon their request. 4.0 Radiation Protection Standards This section outlines the maximum permissible exposure to external and internal radiation as set forth in lOCFR20; and Southern Nuclear Company (SNC) administrative limits. The exposure limits and regulations prescribed in this manual shall be applicable to all persons on the Farley Nuclear Plant site. 4.1 Exposure Limits For Personnel 4.1.1 Occupational Exposure -Summation of Internal and External The provisions of 10CFR20 require the calculation ofa "combined" exposure for personnel who receive occupational exposure to internally deposited radionuclides as well as external radiation.
Internal dose is only required to be summed with external exposure when the committed effective dose equivalent for an individual has reached 200 DAC-hrs (Derived Air Concentration
-hours) within a working year, this number is equal to 10% of one ALI (Annual Limit on Intake). However, SNC Policy is that Internal Dose (CEDE), whether determined by WBC (Whole Body Count), DAC-hours, or bioassay will be recorded and reported at a per intake event threshold of 10 mrem (This level is consistent with the sensitivity of the Panasonic TLD systems used at Southern Company nuclear plants). In all cases, the limits specified in 10CFR20 for internal and external exposure serve to keep the total effective dose equivalent to any individual within acceptable limits. 4.1.2 Internal Exposure The plant staff will, as a general practice, use process or other engineering controls, to limit concentrations of radioactive materials in air below the limits defined in 10CFR20.1204.
When it is impracticable to apply process or other engineering controls to limit concentrations of radioactive material in air to less than 30% (for other than noble gases) of the specified regulatory limits, other precautionary measures, such as increased surveillance, reduction in working times, or use of respiratory protective equipment, shall be considered to minimize the intake of radioactive material by personnel entering the area. Version 18.0 02/24/04 14:13:02 FNP-0-M-001 For purposes of evaluating internal exposures which do occur, the following options should be considered.
* Continued tracking of an individuals internal exposure until it is verified the internal exposure is below 10% of the ALI.
* If feasible based on the isotopes involved, a bioassay may be performed.
The results of the bioassay can then be used to determine any applicable dose.
* Appropriate calculations may be performed to determine the applicable dose. This approach is particularly useful when alpha emitting isotopes are involved which may not be detected by Whole Body Count bioassays.
4.1.3 Radiation Exposure Limits The following exposure limits are based upon federal regulations, industry standards, and Company Policy. The maximum permissible radiation dose an occupational worker may receive in the course of their duties shall be limited to the following (this applies to ionizing radiation).
Annual Dose Limits (Whichever is More Limiting)
Maximum Dose in Rem Per Calendar Year 1) 2) 3) 4) 4.1.3.1 4.1.3.2 Total Effective Dose Equivalent (TEDE) Total Organ Dose Equivalent (TODE) Sum of Deep Dose Equivalent and Committed Dose Equivalent to an individual organ or tissue other than lens of eye. Lens dose equivalent (LDE) Shallow dose equivalent to skin of the whole body (SDE-WB) or the skin of any extremity (SDE-EX).
5 50 15 50 During any calendar year the dose to the whole body of any individual shall not exceed 5 rem TEDE or 50 rem TODE and the lifetime exposure limits of 4.1.3.7 must be complied with. Individuals under 18 years of age shall not be badged as radiation workers at Farley Nuclear Plant. Version 18.0 02/24/04 14:13:02 4.1.3.3 4.1.3.4 4.1.3.5 4.1.3.6 ( FNP-O-M-OOI Any employee who discloses that she is or may be pregnant will complete the election form (DOS Form 931 in FNP-0-DOS-2) to accept or decline a prenatal radiation exposure limit of 500 mrem (0.5 rem) for the embryo or fetus for the term of the pregnancy as recommended in IOCFR20.1208.
Members of the general public, including Escorted Visitors that are not considered radiation workers, shall not be allowed to receive more than 100 mrem of exposure from reactor produced sources for the calendar year. A worker must be appropriately respirator qualified, and medically tested if the use of a respiratory protection device is to be utilized.
Appropriate measures shall be taken (e.g. trending ofDAC-hours, bioassay analysis) to ensure personnel do not exceed the limits set forth in 10CFR20, Appendix B, Table I for intake of radionuclides.
Annual Administrative Exposure Guidelines In order to maintain the occupational exposure of personnel ALARA, the following administrative exposure guidelines shall apply. To exceed these guidelines, a dose extension request form must be obtained, completed and signed by the worker and a member of their supervision and authorized by the appropriate personnel as listed in the following table. Version 18.0 02124/04 14:13:02 FNP-0-M-001 FNP Administrative Guidelines 1 Approvals Annnal Dose Guidelines (mrem) Category Required for Dose Extension TEDE TODE LDE SDE-SK, & SDE-EXT Escorted Visitor (Non-Radworked 100 1,000 300 1,000 None Allowed Concurrently Badged 8,10 450 4,500 1,350 4,500 HP Superintendent Declared Pregnant 6,7,8 450/term None Allowed Woman ---Escorted Radiation Worker (ERW)3,4,8,9 500 5,000 1,500 5,000 None Allowed Radiation Workers Less Than Fully Documented 4,8,9 2,000 20,000 6,000 20,000 As Noted Below Radiation Workers Fully Documented 5,8,9 >2,000 >20,000 >6,000 >20,000 HP Manager or Health Physics and Chemistry Manager (or designee)
>4,000 >40,000 >12,000 >40,000 Assistant General Manager (Ops.) or the Nuclear Plant General Manager (or designee)
>4,500 >45,000 >13,500 >45,000 Project Vice President FOOTNOTES:
: 1. The annual dose for an individual shall include any dose that was occupationally received while being employed by any other facility during that year unless the individual is considered an Escorted Visitor at Farley Nuclear Plant. 2. Escorted Visitor (Non-Radiation Worker) includes Visitors, Guests who have not been Radiation Worker trained and whose access to Radiation Control Areas and exposure margins will be limited. 3. Escorted Radiation Workers (ERW) will have been briefed as a radiation worker but have not received Radiation Worker Training.
: 4. "Less Than Fully Documented" means the individual has disclosed their current year and lifetime cumulative dose on a written, signed statement from the individual or the individual's most recent employer or on an up-to-date NRC Form-4. This individual is not eligible for Planned Special Exposure (PSE) jobs. Version 18.0 02/24/04 14:13:02 FNP-O-M-OOI
: 5. "Fully Documented" means that all documentation records have been obtained for the individual and an up-to-date NRC Form 4 has been signed. 6. The dose to the embryo/fetus shall be limited to 50 mrem during the remainder of the pregnancy if the dose to the embryo/fetus is found to exceed 500 mrem, or is within 50 mrem of this dose by the time the woman declares pregnancy.
: 7. Efforts shall be made to avoid substantial variation above a uniform monthly exposure rate to a declared pregnant woman in order to satisfy the NRC limit of 500 mrem during the entire pregnancy.
: 8. Radiation Worker as defined in Appendix A. 9. Radiation Workers may have their annual or lifetime dose limits extended up to the 10CFR20 limits, using appropriate DOS Forms. 10. Concurrently badged personnel are expected to have their dosimetry service terminated at the other Southern Nuclear sites (Hatch, Vogtle) prior to exceeding this limit. 4.1.3.7 Lifetime Exposure Limits Loti t' 0 Ie Ime t' ccupa IOna IE x Josure G &deg;d r Ul e IDes Lifetime Exposure Action to Permit Additional Exposure TEDE Exposure in Rem 1) Follow FNP Administrative Guidelines
< Age in Years and < 50 Rem TEDE Exposure in Rem 1) Health Physics and Chemistry Manager (or designee) approval > Age in Years (complete DOS Form 944) Concurrence is to be based on the need for additional exposure.
: 2) Perform a formal ALARA review of the worker's exposure history annually, while they are badged at your site and their exposure remains greater than their age. 3) Implement ALARA actions deemed necessary to assure lifetime dose will not exceed 75 Rem during worker's employment career. 4) Set individual's TEDE dose limit to 1000 mremlyr. 5) Plant Operations Assistant General Manager approval required to exceed 1000 mremlyr TEDE (DOS Form 943) TEDE Exposure>
50 Rem 1) Nuclear Plant General Manager (or designee) approval required(complete DOS Form 944) 2) All the actions required to exceed age in years (above). 3) NPGM approval required to exceed 1000 mremlyr TEDE (DOS Form 943). TEDE Exposure>
75 Rem 1) Vice President approval required (complete DOS Form 944). 2) All actions required to exceed 50 Rem lifetime.
: 3) Vice President approval required to exceed 1000 mremlyr TEDE (DOS Form 943). TEDE Exposure>
100 Rem It is intended that no worker should receive exposure that will take his lifetime exposure above 100 Rem. Should a situation arise where exposure beyond 100 Rem needs to be considered, Executive Vice President approval in writing is required (complete DOS Form 944). Version 18.0 02124/04 14:13:02 4.1.3.8 FNP-O-M-OOI Planned Special Exposure A planned special exposure must meet all the criteria stated in lOCFR20.1206, and comply with FNP-0-AP-93.
Planned special exposures are limited to 5 Rem TEDE in anyone calendar year. No one individual can receive an accumulated TEDE exposure due to PSEs in excess of25 Rem during the worker's lifetime.
4.1.4 Accumulation of Radiation Exposure 4.1.4.1 4.1.4.2 4.1.4.3 Medical Exposure Each employee is required to notify HP Supervision of therapeutic radiation treatment or diagnostic radiation (excluding annual chest X-rays, X-rays for broken bones, and routine dental X-rays). HP Supervision will determine if the medical exposure will affect the occupational exposure status of any individual.
Radiation Exposure at Off-site Locations An individual assigned to Farley Nuclear Plant who plans to visit other facilities where they may be exposed to radiation is expected to notify the Dosimetry Section prior to departure and as soon as possible upon return. This individual normally obtains a termination whole body count and normally has their dosimetry terminated prior to departure.
Upon return to site, the individual will normally initiate paperwork, as necessary, to restart their dosimetry and get a startup whole body count. Note that exit whole body counts (WBC) performed at plants Hatch andlor Vogtle can serve as an incoming WBC when transfer is directly between these facilities.
Concurrently badged individuals (limited to Southern Nuclear and Southern Company Services employees) are exempt from this requirement for SNC sites. Other Non-Employment Related Exposure An individual shall not cause themselves to be exposed to ionizing radiation for other than medical reasons, when not on the job for SNC, without prior authorization of the General Manager. All exposure (excluding permitted medical exposure as indicated above), including accidental exposure received off the job shall be reported to HP Supervision upon return to work. Version 18.0 
( 02/24/04 14:13:02 FNP-0-M-001 4.1.5 Dosimetry Records Personnel who are to be monitored at FNP as a Radiation Worker shall provide the Dosimetry Section with an up-to-date NRC Form 4 or equivalent signed by the individual or a written statement that includes the names of all facilities that have provided monitoring of occupational exposure for the current year and an estimate of dose received signed by the individual.
5.0 Personnel Monitoring This section describes the types of dosimetry devices which can be worn, and bioassay sampling that may be performed.
5.1 Responsibilities 5.2 5.1.1 It is the responsibility of each radiation worker to wear personnel monitoring devices in the prescribed manner and to assure their safekeeping.
The loss, damage or contamination of any dosimetry requires notification of Health Physics or Dosimetry personnel.
5.1.2 The Health Physics Group will administer the personnel monitoring program consistent with the requirements of lOCFR20. Issue Of Dosimetry Devices 5.2.1 Individuals reporting as a radiation worker at FNP must meet the requirements ofFNP-0-AP-42.
A startup whole body count (if necessary) will be scheduled by the individual's supervision with the dosimetry section, at which time the individual will sign for receipt of their TLD. Personnel are required to undergo a whole body count upon initiation and termination of permanent TLDs unless otherwise authorized by an HP Manager. Note that exit whole body counts at plants Hatch or Vogtle can serve as an incoming whole body count at Farley Nuclear Plant when transfer is directly between facilities (i.e. no other employment involving radioactive material between employments at Southern Company Nuclear plants). 5.2.2 TLDs will be issued on an individual basis by a Dosimetry representative.
5.2.3 Digital alarming dosimeters (DAD) will normally be self-issued from the racks at the RCA entrance and returned to the racks at the RCA entrance.
When necessary, HP may implement an alternate method of Access Control. 5.2.4 Special purpose TLDs will be issued as necessary by a Dosimetry representative (e.g. extremity TLDs, multibadge pack, etc.). Version 18.0 02/24/04 14:13:02 FNP-0-M-001 5.3 Processing TLDs TLDs will normally be processed on a tri-annual basis or as needed. 5.4 Wearing Dosimetry Devices NOTE: Escorted visitors will have only a DAD; they will not have a TLD. 5.4.1 The following requirements are established with regard to wearing dosimetry devices. Dosimetry devices, except extremity dosimeters (fmger rings, etc.) are to be worn on the whole body. The whole body is defmed for purposes of external exposure as the head, trunk, (including male gonads), arms above the elbow, or legs above the knee. There will be occasions when HP directs personnel to reposition their whole body dosimetry devices to a portion of the whole body that is expected to receive the highest dose. Even though it is acceptable to wear dosimetry on the whole body as indicated above, the administrative configuration listed below is more restrictive and represents a good practice as opposed to a minimum requirement.
NOTE: The front side of the human body is defmed to be the half of the human body that is forward of an imaginary plane projected through the middle of the body and parallel to the shoulders.
The following applies to the administrative dosimetry placement area. Dosimetry is normally worn on the front side of the body at or above the thighs and at or below the shoulders. The dosimetry is normally worn in plain view. Except for specialized activities which represent a significant Beta hazard dosimetry may be placed under clothing or in the pocket of protective clothing for contamination control or foreign material exclusion control purposes.
For activities involving a Beta hazard the TLD needs to be worn with the Beta window oriented so as to measure the associated Beta dose. The TLD and the electronic dosimeter will normally be placed in proximity of each other (within approximately 6 inches). 5.4.2 Extremity TLDs are specifically labeled as to a particular extremity (e.g. left hand, right foot, etc.) and must be worn on that extremity, whenever required.
Finger rings may be worn on any finger of the appropriate hand. Feet TLDs will normally be placed on the inside of the appropriate shoe on the bottom. Exceptions to the placement of extremity TLDs must be specified by HP Supervision. Version 18.0 02/24/04 14:13:02 FNP-O-M-OOI 5.4.3 HP will perform periodic observations of compliance with these administrative guidelines.
Failure to meet the administrative guidelines does not represent a violation of requirements, but will be used to determine the need for corrective actions to assure adherence to desired dosimetry configuration standards.
5.5 Multibadging 5.5.1 It is required that a worker's normal whole body TLD be removed before the multibadge pack can be issued to a worker. 5.5.2 Removal of an individual from multibadge status will be performed by Dosimetry upon notification multibadging is no longer required.
5.6 Bioassay 5.6.1 Whole Body Counting 5.6.1.1 5.6.1.2 5.6.1.3 5.6.2 Urinalysis Whole body counting will be used as the primary method for establishing concentrations of internally deposited radionuclides.
Whole body counting of radiation workers will be performed prior to issuing dosimetry and upon termination of dosimetry unless otherwise authorized by HP Supervision.
Special occasion counts may be required by HP when deemed necessary.
Exit whole body counts at plants Hatch or Vogtle can serve as an incoming whole body count provided the individual has had no employments or visits to other nuclear facilities between the work assignments at Southern Nuclear fleet facilities.
Urinalysis may be employed to determine tritium uptakes and to supplement whole body counting when other soluble radionuclides are suspected.
5.6.3 Other Analysis Other analyses of body excreta (i.e. fecal analysis) or tissue (biops) may be performed as deemed necessary by HP Supervision or SNC medical consultants. Version 18.0 
( 02/24/04 14:13:02 FNP-0-M-001 5.7 Medical Examinations The following medical examinations may be required by HP Supervision or FNP medical consultants.
5.7.1 Complete or partial physical for persons involved in incidents where regulatory limits may have been exceeded.
5.7.2 Special testing such as blood count may be required for individuals whose exposure exceeds regulatory limits. 6.0 Radiation Exposure Control This section covers the administrative procedures and radiation protection measures which apply to a Radiation Controlled Area (RCA). 6.1 Responsibilities 6.1.1 It is each individual radiation worker's responsibility to obey applicable Radiation Work Permits and to report to their respective work supervisor and HP personnel any circumstances where there is doubt as to the radiological safety of an operation.
6.1.2 Unexpected radiological deterioration of the work area involving a radiological contamination or radiation dose rate problem etc. must be reported to HP personnel as soon as possible.
6.1.3 It is each workers responsibility to perform their work in such a manner that their exposure is kept ALARA. 6.1.4 It is the Health Physics Group's responsibility to designate areas according to radiological hazards present (e.g. establish Radiological Posting) and prescribe precautionary measures to be taken when working in these areas. 6.1.5 For tasks performed under the Advance Radiation Worker (AR W) program, AR W's are authorized to determine precautionary methods for their own work and perform self monitoring without additional HP assistance as long as they do so in accordance with FNP-O-ACP-lO, Radworker Self Monitoring Guidelines. Version 18.0 02124/04 14:13:02 FNP-0-M-001 6.2 Special instructions NOTE: Plant Management in special cases where the inability to take frequent breaks imposes physical hardships on personnel have allowed fluids to be provided to radworkers due to heat stress (e.g. Containment Cool Room during outage). 6.2.1 Eating, drinking, smoking, or chewing in an RCA is not considered a good practice, and will be administratively monitored.
6.2.2 Unprotected open wounds present on the body will normally be evaluated prior to entry into the RCA such that appropriate actions to prevent internal contamination may be taken. Upon notification, the HP Staff will inspect any questionable wound. There may be cases where certain wounds shall cause Health Physics personnel to restrict a person to less contaminated areas and in some cases wounds may be serious enough to cause an individual to be denied access to the RCA. 6.3 Classification Of Areas Within An RCA NOTE: It may be necessary to temporarily secure access to an area or areas which have developed a radiological hazard by staging an HP representative instead of posting of the area. In this case, the HP representative will maintain positive control of the area to prevent unauthorized entry until it can be posted or the hazard can be secured/removed.
Posting and securing of the area will be done in a timely manner. Each area within the RCA shall be evaluated and conspicuously posted with the appropriate caution signs. The following list the primary radiological po stings that a radworker may see while within the RCA. a. Radiation Area b. High Radiation Area c Radiological Exclusion Area (Locked High Radiation Area) d. Very High Radiation Area e. Airborne Radioactivity Area f. Radioactive Materials Storage Area g. Contaminated Area h. Radiological Restricted Areas Version 18.0 02/24/0414:13:02 FNP-O-M-OOI 6.4 Radiation Work Permit The Radiation Work Permit (R WP) including Special Radiation Work Permit (SR WP) is the fundamental administrative document for providing precautions and other radiological information for use in performing activities within an RCA. All personnel working under the authority of an R WP shall not deviate from the requirements of the RWP unless authorized by HP. In special cases the presence of HP personnel may be substituted for an R WP with the approval of HP Supervision (e.g. HP Foreman, etc.) 6.5 Use Of Tools Inside The RCA 6.5.1 Workers may obtain tools from those assigned to the RCA (e.g. Hot Tool Room, group's tooVequipment storage location inside the RCA, etc). This helps to reduce the amount oftoolslequipment within the RCA and helps to provide a more efficient work environment.
6.5.2 Workers are expected to work carefully using tools so as to control the spread of contamination.
Actions such as wiping tools periodically and at completion of work or bagging tools when not in use may be used to assist in contamination control. 6.5.3 Any tool or material brought into the RCA will be considered potentially contaminated and will not be removed from the RCA until it has been surveyed by a HP Technician or monitored by an automated equipment monitor as allowed by Health Physics. 6.5.4 HP Supervision may authorize a conditional release of tools and items which have fixed contamination.
Such tools must be controlled as directed by HP. 6.5.5 Tools designated for permanent use in the RCA may be identified as for RCA Use Only (e.g. orange paint, stenciled "for RCA use only", etc.), and stored in appropriate storage locations within the RCA. FNP will be transitioning from orange paint to fluorescent pink for consistence with Southern Nuclear Fleet facilities.
6.5.6 Tool(s) that have known contamination levels in excess ofHP procedural guidance need to have HP's concurrence for the tool(s) to be used in clean areas so that proper radiological controls can be implemented.
6.5.7 The worker is responsible for making sure tools used in contaminated areas are handled in such a manner that minimizes the potential of spreading contamination above procedural limits in clean areas of the RCA (e.g. surveyed and/or bagged prior to removal from the area, etc.). Version 18.0 02/24/04 14:13:02 FNP-0-M-001 6.5.8 Tools requiring decontamination will normally be sent to the decontamination room for cleaning or other arrangements can be made with the HP Group to decontaminate the tools (e.g. send to decon area in NF A, immediately wipe down tools, etc.). 6.6 Radioactive Component Control This section applies to radioactive components, valves, fittings, parts, special tools etc, that are contaminated.
It normally does not apply to waste, mops and other miscellaneous contaminated items. 6.6.1 When it is necessary to store a valve or equipment parts removed from a contaminated system, the responsible group must get HP personnel to check the part for radiation and contamination levels and label the item as required by 10CFR20 and plant procedures.
The component may then be placed in an appropriate radioactive materials storage area. 6.6.2 Items covered under this section which need to be released from an RCA to a clean area shall be conditionally released per HP procedures.
6.7 Radioactive Waste Control This section applies to radioactive waste including:
compressible and non-compressible trash, liquid waste from various plant sources and spent resins. 6.7.1 It is considered a good practice to avoid introducing cardboard and wooden boxes into the RCA. If it is necessary to introduce cardboard boxes or wooden boxes for the purpose of safe handling or storage, then the responsible party needs to take the appropriate actions to minimize the potential of cross contamination of the boxes and to have them removed when their need is no longer valid. 6.7.2 Glassware and light bulbs normally need to be placed in specially marked containers or otherwise identified to minimize the potential for injury when sorting activities are performed. Version 18.0 02124/04 14:13:02 FNP-0-M-001 6.7.3 It is a good practice to segregate waste materials for disposal.
This separation of waste materials aides in reducing:
the volume of radioactive waste, the manpower required for handling of radioactive waste, and the radiation exposure of personnel involved in radioactive waste reduction.
Color of Container (e.g. nylon bags. drum) Material to be Deposited Green Potentially clean waste Purple Protective clothing Yellow Contaminated trash 6.8 Radiological Protective Clothing 6.8.1 For work inside the RCA, radiological protective clothing will normally be stated on the appropriate RWP. Radiological Protective clothing may be cloth, paper, plastic or a combination of these materials.
It needs to be worn in the manner that normally precludes inadvertent personnel contamination.
6.8.2 Radiological protective clothing will not be worn outside an RCA except as permitted in HP procedures.
6.9 Partial Entry into a Contaminated Area A partial entry into a contaminated area is sometimes necessary to perform maintenance or operations activities.
The following guidelines must be met when a partial entry is necessary:
6.9.1 Ensure those portions of the body which will be in contact with potentially contaminated components are protected to minimize the potential of becoming contaminated.
6.9.2 After working across a contaminated area boundary, use caution when removing protective material which came in contact with contaminated components/material, and place in the nearest appropriate container. Version 18.0 02/24/0414:13:02 FNP-O-M-OOI 6.10 Step Off Pads (SOPs) SOPs are normally provided at points where protective clothing is normally expected to be removed. In some cases, contaminated areas do not lend themselves to the convenient use of a SOP. When this is the case prior to entering the contaminated area, individuals should consider actions and materials (such as clothing bags) needed when exiting the area. HP will provide temporary arrangements for this type activity upon request. Each person exiting the Contaminated Area needs to use additional caution so that potential of spreading contamination is minimized.
For example use undress procedures as if there was a SOP present. 6.11 Securing Materials/Equipment That Cross Contamination Boundaries It is considered a good expectation to secure items which must cross contamination boundaries (tape or ty-wrap lines, cables, hoses inside and outside the contaminated area to the floor or other structures) so that the lines do not slide back-and-forth between the contaminated and clean areas. This will reduce the potential for accidentally spreading contamination, generating tripping hazards, damaging equipment, etc. 6.12 Respiratory Protection 6.12.1 The primary objective of the FNP respiratory protection program is to minimize the unnecessary intake of radioisotopes, while taking into consideration all aspects of radiological jobs being performed that might normally require the use of respiratory protection.
The use of respirators should be considered ONL Y after it has been documented that the use of engineering controls is not possible as a means for reducing the concentration of radioactive materials in air below the limits defmed in lOCFR20.1204.
The program must also provide protection against oxygen deficient, nuisance, and toxic atmospheres inside RCAs. The respiratory protection program can help meet the requirements of IOCFR20 by reducing overall TEDE exposures, through the use of less respiratory protection devices in some cases. This is normally accomplished by the application of engineering controls such as process, containment, and ventilation equipment and by the preplanning of work. However, it is necessary that some work functions be performed in confined or localized areas where the atmospheric hazards warrant protection and other controls are not feasible.
In these cases, respiratory protection devices may be used to provide the necessary protection (e.g. Inside the steam generator channel-head, due to changing radiological conditions inside the bowl; pulling off insulation can frequently be performed much faster when wearing respirators, thus reducing the overall time and exposure for the work). Version 18.0 02124/0414:13:02 FNP-0-M-001 6.12.2 The HP Group is responsible for administering the radiological respiratory protection program inside RCAs. This includes issue, cleaning, decontamination, inspection, maintenance, sanitizing, repair, and storage of respiratory protection equipment.
The HP Group will determine the radiological hazards associated with each job to ensure the selection and issuance of the proper respiratory devices. HP will maintain records to permit periodic evaluation of the adequacy of the program. The Training Group is responsible for the training and fit testing of personnel for the specific respirators required.
Additionally, the Safety and Health Department is responsible for periodically conducting pulmonary function tests and issuing a list of personnel medically qualified to wear respirators.
6.12.3 Respiratory protection devices will be provided to protect personnel from airborne radioactivity in accordance with 10CFR20.1703 and the FNP ALARA program. The use of Respirators for Radiological Protection will be reviewed by the HP Foreman prior to their issuance in accordance with HP procedures.
Respirators may be used at lower airborne concentrations than specified in IOCFR20 provided they do not increase anticipated TEDE by increasing work duration, limiting mobility restricting vision or by introducing any other physical constraints.
Full face particulate respirators normally are considered for use when cutting or grinding on radioactively contaminated items and full face air supplied respirators normally are considered for use when welding or burning on radioactively contaminated items. These requirements will be evaluated and modified as the radiological work conditions dictate. Personnel who are required to wear respirators must be clean shaven in the area where the mask seals with the face. Facial conditions in the seal area must remain similar to those when the individual was fitted and qualified and the individual must be medically certified able to wear a respirator.
It is each individual's responsibility to notify the HP Group if their facial conditions in the seal area has changed since having been fitted and qualified to wear a respirator (e.g. scar, facial structure change, dentures, etc.). If so, the individual must be recertified by having another respirator fit test performed by the Training Group. 6.12.4 If respiratory protection is required, it is normally specified on the applicable RWP or by a member ofHP Supervision.
Nasal smears are normally taken and analyzed after using a respirator.
A respirator will not be issued to individuals who do not have a current medical certification date. 6.13 Radioactive Source Control Health Physics procedure, FNP-0-RCP-55 gives guidance on the proper handling of radioactive sources used at FNP. Version 18.0 
(' 02/24/04 14:13:02 FNP-O-M-OOI 6.14 Climbing in the Overhead inside RCA The area normally checked when an HP Technician performs a survey is up to a height of approximately eight (8) feet. For this reason, areas higher than -8' in the overhead require a survey before any climbing.
Areas which have permanently installed ladders and/or platforms are routinely surveyed and do not require additional survey unless specifically posted. 7.0 Radioactive Material Spills If you are unsure whether liquid found inside the RCA is radioactive or not, always assume that it is radioactive and do the following:
7.1 Individual 7.1.1 For areas where water is present but no active leak or spill is in progress, verify the water is contained (i.e. not spreading to additional areas) and evaluate the need for HP or HPS support to remove the water. 7 .1.2 Avoid walking through or otherwise spreading the water to additional areas. 7.1.3 If a safety hazard exists, initiate action to prevent personnel injury by having the area posted, coordinating removal of the water, etc. 7.1.4 Stop or confine active spills immediately, if possible.
7.1.5 Notify the Shift Supervisor and HP of any active spills. 7.1.6 Warn personnel concerning active spills until HP personnel arrive. 7.2 Health Physics (Control of Radioactive Material Spill Area(s)) 7 .2.1 Clear personnel from active spill areas and restrict entry until the radiological concern can be identified and proper controls implemented.
7 .2.2 Ensure personnel involved with an active spill situation are properly monitored, recommend necessary steps to return the area to a normal condition and decontaminate personnel as required.
7.2.3 Do not let work resume until the area is returned to an acceptable condition and the cause of the spill is corrected or confined. Version 18.0 02/24/0414:13:02 FNP-0-M-001 APPENDIX A DEFINITIONS
: 1) ADULT Means an individual 18 or more years of age. 2) ALARA As 10w As Reasonably Achievable (ALARA) means making every reasonable effort to maintain exposures to radiation as far below the dose limits in 10CFR20 as is practical, taking into account the state of technology, the economics of improvements relative to: the state oftechnology, benefits to the public health and safety, other societal and socioeconomic considerations, and utilization of nuclear energy and licensed materials in the public interest.
: 3) ANNUAL LIMIT ON INTAKE (ALI) The derived limit for the amount of radioactive material taken into the body of an adult worker by inhalation or ingestion in a year. ALI is the smaller value of intake of a given radionuclide in a year by the reference man which would result in a committed effective dose equivalent of 5 rems or a committed dose equivalent of 50 rems to any individual organ or tissue (ALI values for intake by ingestion and inhalation of selected radionuclides are given in 10CFR20, Appendix B, Table 1, Columns 1 and 2). 4) BIOASSAY Means the determination of kinds, quantities, concentrations, or locations of radioactive material in the human body either by direct measurement (in vivo (whole body count) counting) or by analysis and evaluation of materials excreted or removed from the human body (in vitro counting).
: 5) COMMITTED DOSE EQUIVALENT (CDE) The dose equivalent to an organ or tissue that will be received from an intake of radioactive material by an individual during the 50 year period following the intake. Page 1 of5 Version 18.0 02/24104 14:13:02 FNP-0-M-001 APPENDIX A 6) COMMITTED EFFECTIVE DOSE EQUIVALENT (CEDE) The sum of the products of the weighting factors (w0 applicable to each of the body organs or tissues which are irradiated and the committed dose equivalent (CDE) to these organs or tissues. CEDE = L (wt)(CDE)
: 7) CONCURRENTLY BADGED SNC or Southern Company Services employees who have been approved by management to be currently dosimetry badged at more than one of SNC's nuclear plants. 8) DECLARED PREGNANT WOMAN Means a woman who has voluntarily informed the licensee, in writing, of her pregnancy and the estimated date of conception.
The declaration remains in effect until the declared pregnant woman withdraws the declaration in writing or is no longer pregnant.
: 9) DEEP DOSE EQUIVALENT (DDE) Applies to external whole body exposure and is taken as the dose equivalent at a tissue depth of 1 cm (1000 mg/cm 2). 10) DERIVED AIR CONCENTRATION (DAC) Means the concentration of a given radionuclide in air which, if breathed by an individual (reference man) for a working year of 2,000 hours under conditions of light work (inhalation rate 1.2 cubic meters of airlhour) results in an intake of one ALI. DAC values are given in Table 1, Column 3, of Appendix B to 10CFR20. 11) DERIVED AIR CONCENTRATION
-HOUR (DAC -hour) The product of the concentration of radioactive material in air (expressed as the derived air concentration for each radionuclide) and the time of exposure to that radionuclide, in hours. A licensee may take 2,000 DAC-hours to represent one ALI, equivalent to a committed effective dose equivalent of 5 rem. 12) EMBRYO/FETUS The developing human organism from conception until the time of birth. Page 2 of5 Version 18.0 02124/04 14:13:02 FNP-O-M-OO 1 APPENDIX A 13) ESCORTED RADIATION WORKERS (ERW) A radiation worker that has not completed radiation worker training (but may have completed it at another site or have previously completed it and is now out of date) but have been briefed or trained consistent with the work to be performed.
They will be under the escort of a trained radiation worker for all radiation control area entries. 14) ESCORTED VISITOR An Escorted Visitor is an individual that is not a radiation worker nor are they considered trained with regard to radiation work. An Escorted Visitor may tour the radiation control area, observe work activities and perform minor work tasks which involve minimal association with radioactive materials.
An Escorted Visitor is not permitted to enter high radiation areas, very high radiation areas, contaminated areas or airborne areas. 15) EXPOSURE MARGIN The amount of exposure an individual has remaining before he/she will exceed an annual or lifetime dose limit. 16) EXTERNAL DOSE That portion of the dose equivalent received from radiation sources outside the body. 17) EXTREMITIES The hands, elbows, arms below the elbow, feet, knees and legs below the knees. 18) LENS DOSE EQUIVALENT (LDE) Applies to the external exposure of the lens of the eye and is taken as the dose equivalent at a tissue . 2 depth of 0.3 centimeter (300 mg/cm ). 19) INTERNAL DOSE That portion of the dose equivalent received from radioactive material taken into the body. 20) MEMBER OF GENERAL PUBLIC Means an individual in a controlled or unrestricted area. However, an individual is not a member of the public during any period in which the individual receives an occupational dose. Escorted Visitors allowed to enter the Radiation Controlled Area are considered members of the general public. Page 3 of5 Version 18.0 02/24/04 14: 13:02 FNP-0-M-001 APPENDIX A 21) MINOR An individual less than 18 years of age. 22) OCCUPATIONAL DOSE Dose received by an individual in a restricted area or in the course of employment in which the individual's assigned duties involve exposure to radiation.
Occupational dose does not include dose received from background radiation, as a patient from medical practices, from voluntary participation in medical research programs, or as a member of the general public. 23) PLANNED SPECIAL EXPOSURE (PSE) An infrequent exposure to radiation, separate from and in addition to the routine annual dose limits. PSEs are to be used only under exceptional circumstances, not as a routine method of extending dose limitations.
Approval for a PSE must be obtained in writing from the Executive Vice President before the exposure occurs. 24) RADIATION WORKER -personnel who have completed necessary training or substitute training (as in the case of Escorted Radiation Workers) and are authorized to perform work inside the plant's posted radiation controlled areas. 25) SHALLOW DOSE EQUIVALENT, WHOLE BODY SKIN (SDE, WB) Applies to the external exposure of the skin of the whole body and is taken as the dose equivalent at a tissue depth of 0.007 cm (7 mg/cm 2) averaged over an area of 10 cm 2. 26) SHALLOW DOSE EQUIVALENT, MAXIMUM EXTREMITY (SDE, EX) Applies to the external exposure of the skin of the extremity receiving the highest dose and is taken as the dose equivalent at a tissue depth of 0.007 cm (7 mg/cm 2) averaged over an area of 10 cm 2. 27) TOTAL EFFECTIVE DOSE EQUIVALENT (TEDE) The sum of the deep dose equivalent (for external exposures) and the committed effective dose equivalent (for internal exposures).
: 28) TOTAL ORGAN DOSE EQUIVALENT (TODE) The sum of the deep dose equivalent (for external exposures) and the committed dose equivalent recorded for the maximally exposed internal organ. Page 4 of5 Version 18.0 02/24/04 14:13:02 FNP-0-M-001 APPENDIX A 29) WEEK 7 consecutive days starting on Sunday. 30) WHOLE BODY Those areas of the body consisting of the head, the trunk (including male gonads), arms above the elbow, or legs above the knee. 31) YEAR The period oftime, beginning in January, used to determine compliance with lOCFR2O. The starting date of the year may change provided that the change is made at the beginning of the year and that no day is omitted or duplicated in consecutive years. Page 5 of5 Version 18.0 HL T -32 ADMIN exam A.4SRO Page 1 of 7 A.4SRO Emergency Plan ADMIN G2.4.44-SRO ( TITLE: Evaluate plant conditions during a site area emergency to determine if a follow-up message or an upgrade notification is warranted, and complete all required forms. ( TASK STANDARD:
Classify an emergency event and determine an upgrade from SAE to GE is required, fill out all forms for emergency notification, and initiate correct Protective Action Recommendations (PARS) within the time allowed. PROGRAM APPLICABLE:
SOT SOCT OLT --.1L LOCT __ ACCEPTABLE EVALUATION METHOD: --.1L PERFORM --.1L SIMULATE DISCUSS EVALUATION LOCATION:
---.1L SIMULATOR
--.1L CONTROL ROOM CLASSROOM PROJECTED TIME: 30 MIN SIMULATOR IC NUMBER: N/A ALTERNATE PATH TIME CRITICAL --.1L PRA *THIS JPM IS TIME CRITICAL*
Examinee:
Overall JPM Performance:
Satisfactory 0 Unsatisfactory 0 Evaluator Comments (attach additional sheets if necessary)
EXAMINER:
________________
_ 
( HL T-32 ADMIN exam AASRO Page 2 of 7 CONDITIONS When I tell you to begin, you are to EVALUATE PLANT CONDITIONS DURING A SITE AREA EMERGENCY TO DETERMINE IF A FOLLOWUP MESSAGE OR AN UPGRADE NOTIFICATION IS WARRANTED, AND COl\tlPLETE ALL REQUIRED FORMS. The conditions under which this task is to be performed are: a. Unit 1 was at 100% power when a Large Break LOCA occurred.
: b. A Site Area Emergency (SAE) has been declared for Unit 1, FSI -Loss or Potential Loss of ANY Two Barriers due to:
* Potential loss of the Fuel Clad Barrier (4. RVLS Plenum LEVEL less than 0%).
* Loss of the RCS Barrier (2. RCS sub cooling less than 16&deg;F {less than 45&deg; F Adverse}).
: c. Unit 2 is unaffected and has remained at 100%. d. EIP-9.0, Guideline 2, Site Area Emergency, has been performed up to step D.3. e. The Control Room reports the following current conditions on Unit 1:
* RVLS lights are all red
* RCS subcooling is 12&deg;F
* RE-27 A and RE-27B, Containment Radiation Monitors, are both 100 RIhr and rising.
* RE-14, Plant Vent, RE-21, Vent Stack Particulate, and RE-22, Vent Stack Gas, are in alarm.
* The Shift Radio Chemist has projected dose to be 1.3 REM TEDE at the site boundary.
* Wind Direction
= from 95&deg;.
* Wind Speed = mph. * = +1.5&deg;F. f. Another SRO is standing by to make any requested announcements, callouts, or notifications.
: g. This JPM contains time critical elements.
: h. A pre-job brief is not required.
: 1. You are the ED and are required to evaluate plant conditions and determine which is warranted:
* an upgrade in classification per EIP-9.0, Step 4.0, OR
* a follow-up message per EIP-9.0, Step 6.0, AND then fill out all applicable forms and paperwork.
EXAMINER NOTES: DO NOT START THE TIME UNTIL THE APPLICANT UNDERSTANDS THE TASK.
* An EXAMINER'S KEY is available for all forms
* On Guideline 1, boxes are circled instead of checked on the KEY to ensure the content of the boxes are legible. Circling the boxes, checking inside the boxes, or "x'ing" inside the boxes are all acceptable for the applicant.
EVALUATION CHECKLIST ELEMENTS:
STANDARDS:
RESULTS: (CIRCLE) 
( HLT-32 ADMIN exam A.4SRO EVALUATION CHECKLIST ELEMENTS:
TIME CRITICAL START TIME STANDARDS:
Page 3 of 7 RESULTS: (CIRCLE) NOTE:* THE TIME IT TAKES TO CLASSIFY THE EVENT IS TIME CRITICAL AND MUST BE COlVlPLETED IN 15 MINUTES. *1. Classify the event using Data Sheet 1 from EIP-9.2. Data Sheet 1 completed through step 9, including signature, date and time. Event classified as a GENERAL EMERGENCY
-FGl:
* Fuel clad barrier loss -#5, Containment Radiation Monitoring,
* RCS barrier loss -#2, RCS Leak Rate, and
* CTMT barrier loss -7, Other indications.
__ TIME CRITICAL STOP I START TIME S/U NOTE:
* THE TIME IT TAKES TO COlVlPLETE AND APPROVE THE DECLARATION FORM PER THE FOLLOWING ELEMENTS IS TIME CRITICAL AND MUST BE COMPLETED IN 15 MINUTES. *2. Directs notification of personnel on Directs notification of personnel on site. S I U site. NOTE: ELEMENT 4 WAS ACCOMPLISHED WHEN THE SITE AREA EMERGENCY WAS DECLARED.
EVEN THOUGH THE PROCEDURE STATES TO PERFORM IT, THE APPLICANT MAY REALIZE IT DOESN'T NEED TO BE PERFORMED AGAIN. THERE ARE NO ADVERSE CONSEQUENCES IF PERFORMED AGAIN OR NOT. TIDS IS NOT A CRITICAL STEP. 3. Directs callout the ERO staff. Individual requested to activate the ERO callout system per FNP-O-EIP-8.3, Table 2. S I U (Cue: The request to initiate ERO callout is acknowledged. )
HL T-32 ADMIN exam A.4SRO EVALUATION CHECKLIST Page 4 of 7 RESULTS: ELEMENTS:
STANDARDS: (CIRCLE) NOTE: ACCURATE COMPLETION OF CERTAIN STEPS OF EIP-9.0, GENERAL EMERGENCY NOTIFICATION FORM, IS ESSENTIAL TO ENSURE ADEQUATE NOTIFICATION OF STATE AND LOCAL AGENCIES.
THESE STEPS ARE SHOWN AS THE STANDARDS FOR ELEMENT NUMBER 6 (critical tasks are based on shaded portions of Guideline 1 form which annotate the items which affect EP Performance Indicators (PIs). *4. Complete EIP-9.0, Guideline 1 General Emergency Red Verbal Notification Form. Correct form selected S/U LINE 1 -Indicates Drill OR Actual Event S I U LINE 4 -Indicates General and identifies RG1 as criteria for EAL# S I U LINE 5 -Evaluates PARs and determines that PAR 3 is appropriate, and based on 95&deg; wind direction, the following zones should be evacuated:
A, B5, C5, D5, E5, F5, 15, J5, KS, C10, D10 and E10. S I U NO zones are sheltered S I U LINE 6 -Evaluates emergency release and marks -Is Occuring S I U LINE 9 -Accurately completes met tower wind direction and wind speed data. S I U LINE 10 -Completes declaration time/date
-Matches Step 8 on EIP-9.2 Data Sheet 1 S/U NOTE: IF EXAMINEE ASKS FOR TIME OF SHUTDOWN, SUBTRACT 25 MINUTES FROM THE START OF TIDS TASK AND PROVIDE THAT TIME. LINE 11 -Indicates Unit 1 S I U NOTE: STOP TIME IS AFTER LINE 17 IS COMPLETE: "APPROVED BY" SIGNATURE, TIME AND DATE IS FILLED IN. 
( HL T-32 ADMIN exam A.4SRO EVALUATION CHECKLIST ELEMENTS:
TIME CRITICAL STOP TIME STANDARDS:
Terminate JPM when initial notification form is completed Page 5 of 7 RESULTS: (CIRCLE) CRITICAL ELEMENTS:
Critical Elements are denoted with an Asterisk (*) before the element number. 
( HLT-32 ADMIN exam A.4SRO GENERAL
 
==REFERENCES:==
: 1. FNP-0-EIP-9.0 Version 59 2. FNP-0-EIP-9.2 Version 7 3. NMP-EP-109 Version 2.0 4. KA: G2.4.44 RO-2.4 GENERAL TOOLS AND EOUIPMENT:
Provide: SRO-4.4 1. FNP-0-EIP-9.0, Guideline 1 and Figure 6 2. FNP-0-EIP-9.2, Data Sheet 1 3. NMP-EP-109 Version 2.0 4. Handouts of SAE paperwork already filled out. COMMENTS:
Page 6 of 7 A.4SRO (1 Page) HANDOUT CONDITIONS When I tell you to begin, you are to EVALUATE PLANT CONDITIONS DURING A SITE AREA E:MERGENCY TO DETERMINE IF A FOLLOWUP :MESSAGE OR AN UPGRADE NOTIFICATION IS WARRANTED, AND COMPLETE ALL REQUIRED FORMS. The conditions under which this task is to be performed are: a. Unit 1 was at 100% power when a Large Break LOCA occurred.
: b. A Site Area Emergency (SAE) has been declared for Unit 1, FS1 -Loss or Potential Loss of ANY Two Barriers due to:
* Potential loss of the Fuel Clad Barrier (4. RVLS Plenum LEVEL less than 0%).
* Loss of the RCS Barrier (2. RCS subcooling less than 16&deg;F {less than 45&deg; F Adverse}).
: c. Unit 2 is unaffected and has remained at 100%. d. EIP-9.0, Guideline 2, Site Area Emergency, has been performed up to step D.3. e. The Control Room reports the following current conditions on Unit 1:
* RVLS lights are all red
* RCS subcooling is 12&deg;F
* RE-27A and RE-27B, Containment Radiation Monitors, are both 100 RIhr and rising.
* RE-14, Plant Vent, RE-21, Vent Stack Particulate, and RE-22, Vent Stack Gas, are in alarm.
* The Shift Radio Chemist has projected dose to be 1.3 REM TEDE at the site boundary.
* Wind Direction
= from 95&deg;.
* Wind Speed = mph. * = +1.5&deg;F. f. Another SRO is standing by to make any requested announcements, callouts, or notifications.
: g. This JPM contains time critical elements.
: h. A pre-job brief is not required.
: i. You are the ED and are required to evaluate plant conditions and determine which is warranted:
* an upgrade in classification per EIP-9.0, Step 4.0, OR
* a follow-up message per EIP-9.0, Step 6.0, AND then fill out all applicable forms and paperwork. 
( 09/01/08 15:32:53 FARLEY NUCLEAR PLANT FNP-0-EIP-9.0 August 9, 200T Version 59.0 EMERGENCY PLAN IMPLEMENTING PROCEDURE 9.0 FNP-0-EIP-9.0 EMERGENCY ACTIONS PROCEDURE USAGE REQUIREMENTS PER FNP*O*AP*6 SECTIONS Continuous Use Reference Use ALL Information Use Approved:
WL. Bargeron Plant Manager S A F E T Y R E L A T E D Date Issued
_____ _
09/01108 15:32:53 FNP-0-EIP-9.0 LIST OF EFFECTIVE PAGES Procedure Contains Number of Pages Table of Contents .............................................................
2 Body .................................................................................
5 Appendix 1 .......................................................
2 Guideline 1 .......................................................
8 Guideline 2 .......................................................
8 Guideline 3 .......................................................
7 Guideline 4 .......................................................
8 Table 1 ............................................................
1 Table 2 ............................................................
1 Table 3 ............................................................
1 Table 4 ............................................................
1 Figure 1 ............................................................
1 Figure 2 ............................................................
1 Figure 3 ............................................................
1 Figure 4 ............................................................
3 Figure 5 ............................................................
5 Figure 6 ............................................................
6 Figure 7 ............................................................
1 Page 1 of 1 Version 59.0 09/01108 15:32:53 Section 1.0 2.0 3.0 4.0 5.0 6.0 7.0 Appendix 1 Guideline 1 Guideline 2 Guideline 3 Guideline 4 Table 1 Table 2 Table 3 Table 4 Figure 1 Figure 2 Figure 3 FNP-0-EIP-9.0 EMERGENCY ACTIONS TABLE OF CONTENTS Purpose References General Classify Emergency Perform Actions and Initial Notification Continue Reassessment Terminating The Emergency Classification Onsite and Off Site Staging Areas General Emergency Site Area Emergency Alert Notification of Unusual Event References Emergency Facility Activation Considerations for Emergency Classifications Based on Security Events 1 1 1 2 4 4 5 Information Likely to be Requested by the NRC if an Emergency is Declared 10 Mile Emergency Planning Zone Event Flowpath DELETED Page 1 of2 Version 59.0 
( 09/01108 15:32:53 Figure 4 Figure 5 Figure 6 Figure 7 EMERGENCY ACTIONS TABLE OF CONTENTS PAR UPGRADE NRC NOTIFICATION Emergency Notification FORM FNP-0-EIP-9.0 Emergency Notification Continuation Sheet Page 2 of2 Version 59.0 09/01108 15:32:53 FNP-0-EIP-9.0 EMERGENCY ACTIONS 1.0 Purpose The purpose of this procedure is to provide guidelines for actions, and for notification guidance for a declared emergency.
The classification of emergencies will be performed using FNP-0-EIP-9.2 as directed by this procedure.
Dose assessment will be performed by using FNP-0-EIP-9.1, FNP-0-EIP-9.3 or FNP-0-EIP-9.5 as directed by this procedure.
Development of Protective Action Recommendations (PARs) will be performed using NMP-EP-109 as directed by this procedure.
2.0 References See Table 1. 3.0 General: 3.1 This procedure provides guidance to use FNP-0-EIP-9.2 for the criteria for the classification of an emergency based on plant status and radiological hazards (i.e., direct radiation and inhalation hazards which may result from the passage of a cloud of radioactive material released from the plant). 3.2 Assessment of radioactive liquid releases will be made using the NODE and ALERT criteria of FNP-0-EIP-9.2.
3.3 Definitions:
Definitions that are required for emergency classification are included in EIP-9.2 3.4 Protective Action Recommendation (PAR) guidance is provided in NMP-EP-109 to aid in establishing protective action recommendations.
If the EOF is staffed and responsible for dose assessment, then the EOF will normally develop and recommend PAR upgrades to the Emergency Director.
Once approved by the Emergency Director, PAR upgrades will be communicated to the agencies by EOF if the EOF is responsible for offsite communications.
3.5 If stearn generator water level falls below the break point during a stearn generator tube rupture, off-site dose rate may be significantly higher (up to 10 times) due to volatilization of iodine. 3.6 Initial Notification or upgrade should be made from the Control Room or TSC. It is not necessary to transfer the information to the EOF to make the upgrade notification.
The EOF, if staffed, should be informed as soon as possible. Version 59.0 
( 09/01/08 15:32:53 FNP-0-EIP-9.0 3.7 Communication guidance for making the initial verbal notification is on the Emergency Initial Notification Form, in the appropriate guideline.
3.8 Guidance for when the emergency response facilities should be manned and the level of manning required is included in Table 2. It is recommended that the TSC and the EOF be fully staffed initially at the ALERT level. If the full staff is not required, individuals can be released on a case-by-case basis. 3.9 At the NOUE level or below, it may be desirable to partially staff the TSC in order to relieve the Control Room staff of offsite communications and notifications.
FNP-0-EIP-6.0 provides a listing of positions that should be considered for partial TSC activation.
3.10 EIP-6, Figure 3, provides a list of information that should be considered when updating plant staff over the public address system. 4.0 Classify emergency based on the most severe plant conditions OR projected off-site dose/dose rate conditions, WHICHEVER results in the higher emergency classification.
Figure 2 provides a flowpath for dose assessment methods and plant conditions criteria.
4.1 Plant Conditions Use FNP-0-EIP-9.2 to determine the highest indicated emergency classification based on plant conditions or radiation monitor readings.
4.2 Dose Assessment NOTE: All of the step 4.2 substeps will normally be accomplished by the On Shift Dose Analyst with the exception of step 4.2.6. Step 4.2.6 must be performed by the Shift Supervisor, Shift Manager, or Emergency Director.
4.2.1 Initial evaluation of off-site dose. The On Shift Dose Analyst (Shift Radio Chemist) when asked to perform dose assessment should initially evaluate effluent monitors (R-14, R-21, R-22, R-29, R-60 series, R-15 series R-18 and R-23B) as follows: 4.2.1.1 If there are no effluent radiation monitors that are in alarm or have up-scaled by a factor of 10 or more, And there are no other indications of an off-site radioactive release in progress, Then The On Shift Dose Analyst should report to the ED that there is no indication of a radioactive release based on effluent monitors and NO additional dose assessment per step 4.2 is required.
Continue to perform this assessment periodically not to exceed 30 minutes until the requirement is terminated by the ED. Version 59.0 09/01108 15:32:53 4.2.1.2 FNP-0-EIP-9.0 If any effluent radiation monitor is in alarm or has up-scaled by a factor of 10 or more, Or there are other indications of an off-site radioactive release in progress, Then For initial dose assessment from the TSC, proceed to step 4.2.4. 4.2.2 For dose assessment from the EOF or long term dose assessment from the TSC, go to EIP-9.3, PERSONNEL COMPUTER-AUTOMATED DOSE ASSESSMENT and perform dose assessment using the MIDAS program. Return to step 4.2.6 for evaluation of dose information.
4.2.3 If the MIDAS program is inoperable, then for dose assessment from the EOF or from the TSC, go to EIP-9.1, AUTOMATED DOSE ASSESSMENT and perform dose assessment using the ARDA program to obtain dose information.
Return to step 4.2.6 for evaluation of dose information.
4.2.4 If the ARDA System is operable and has been automatically activated, then go to EIP-9.1, AUTOMATED DOSE ASSESSMENT and perform dose assessment using the ARDA program to obtain dose information.
Return to step 4.2.6 for evaluation of dose information.
4.2.5 If the ARDA system per EIP 9.1, AUTOMATED DOSE ASSESSMENT is NOT operable, then go to EIP-9.3, PERSONAL AUTOMATED DOSE ASSESSMENT and perform dose assessment using the MIDAS program. Return to step 4.2.6 for evaluation of dose information.
NOTE: Evaluating the dose assessment information in Step 4.2.6 must be performed by the Shift Supervisor, Shift Manager, or Emergency Director in the Control Room or TSC, the Dose Assessment Supervisor or EOF Manager in the EOF. 4.2.6 Using the dose information obtained from EIP-9.1 or EIP-9.3, determine the highest indicated emergency classification from the "Radiological" criteria in FNP-0-EIP-9.2.
NOTE: If a General Emergency or site area emergency is indicated in the following step, the Emergency Director should consider directing long term dose assessment be performed from the TSC per step 4.2.2. 4.2.7 If a General Emergency or Site Area Emergency was indicated from step 4.2.6 then go to step 4.3. Version 59.0 09/01/08 15:32:53 FNP-0-EIP-9.0 4.2.8 If a General Emergency or Site Area Emergency was not indicated in step 4.2.6 then continue dose assessment using FNP-0-EIP-9.1 or 9.3. 4.3 Determine the correct emergency classification, declare the emergency at the time the classification was verified, determine PARs and make notifications.
4.3.1 Compare the emergency classifications determined in FNP-0-EIP-9.2, from steps 4.1 and 4.2 to determine the highest required emergency classification and declare the emergency.
Do not wait for dose assessment results from step 4.2 to classify the event if plant conditions require an initial classification or an upgrade classification.
As soon as a criteria for classification has been met, the event should be classified by the Shift Manager or ED and an upgrade can be done later if required.
4.3.2 If a General Emergency classification was determined in step 4.3.1, determine the required protective action recommendations using EP-109. 5.0 Perform actions and initial notification to offsite authorities upon initial entry or upgrade into a classification using the applicable guideline:
Guideline 1, Section II -General Emergency Guideline 2, Section II -Site Area Emergency Guideline 3, Section II -Alert Guideline 4, Section II -Notification of Unusual Event 6.0 Continue reassessment of emergency classification per step 4.0 or 7.0, as appropriate, and transmit follow-up message/periodic update message as follows: 6.1 Transmit Follow-up Messages:
6.1.1 Transmit a follow up message as soon as possible following an initial or upgrade verbal notification Refer to step 6.2 for time limits for other follow-up messages.
Transmit message no later than one hour after the verbal notification has been transmitted over the ENN. The goal should be no longer than 30 minutes. 6.1.2 Use, Figure 6 for guidance in completing and transmitting the "Emergency Message" for Follow Up/Periodic Update. 6.1.3 When performing dose assessment, transcribe dose information from the form being printed on a blank Figure 6 or use the form being printed by MIDAS. Fill in the remaining information.
Transmit follow up message by telecopy. Version 59.0 09/01/08 15:32:53 FNP-0-EIP-9.0 NOTE: EFFORTS WILL BE MADE TO TRANSMIT FOLLOW-UP REPORTS EVERY HALF HOUR. 6.2 Transmit subsequent "Follow Up Message/Periodic Update Message" reports per step 6.1. 6.2.1 At a minimum of once per hour. The hourly requirement may be waived while in a NOVE declaration, if this is agreed to by the state and local agencies.
6.2.2 Following a significant change in dose rate that does not require a change in emergency classification.
6.2.3 Following a significant change in plant conditions that does not require a change in emergency classification.
7.0 TERMINATING THE EMERGENCY CLASSIFICATION 7.1 Termination of an emergency classification shall be done in accordance with FNP-0-EIP-9.2 step 6.4 and FNP-0-EIP-28.0.
7.2 The emergency classification will not normally be downgraded from a higher emergency classification to a lower one. When all criteria for classification have been cleared the classification will be terminated. Version 59.0 
( 09/01/08 15:32:53 FNP-O-EIP-9.0 APPENDIX 1 ONSITE AND OFF SITE STAGING AREAS 1. During security events when there is terrorist activity on site that would prevent off site resources from accessing the site, staging areas have been established off site to assemble these resources for ready access to the site when access becomes available.
: 2. When resources are able to access the site, they may not be able to go directly to the scene where they are needed. On site staging areas have been established on-site to assemble these resources for ready access to the location that they are needed. 3. Off site staging area #1 is located at the Oakey Grove Baptist Church located at the intersection of HC Road 33 and Nuclear Plant Road 4. Off site staging area #2 is located at the West Bank Dam Site Located off of Alabama Highway 95 between Alabama Highway 52 and Nuclear Plant Road. 5 On site staging area #1 is located in upper parking lot at the Training Center. See attached map which can be sent to off site resources.
: 6. On site staging area #2 is located in at the parking lot behind the Engineering Support Building.
See attached map which can be sent to off site resources.
: 7. If it is necessary to use a staging area select the best one to use based on plant conditions, radiological/meteorological and physical hazards. 9. Inform off site resources of the staging area. This can be done by direct contact from the Control Room, TSC or security.
HCEMA should be contacted and request their support in coordinating these activities and communicating with these agencies. Version 59.0 
( 09/01/08 15:32:53 APPENDIX 1 ONSITE AND OFF SITE STAGING AREAS STAGING AREA MAP To off site Staging Area #2 p On Site Staging Area #2 ounty 42 (Nuclear Plant Road)
___ To off site Staging Area #1 On Site Staging Area #1 Switch House D FNP-0-EIP-9.0 N Version 59.0 09/01108 15:32:53 FNP-O-EIP-9.0 GUIDELINE 1 GUIDELINEl GENERAL EMERGENCY I. Purpose of Classification The classification of General Emergency applies to those events which are in progress or have occurred which involve actual or imminent substantial core degradation or melting with potential loss of containment integrity or HOSTILE ACTION that results in an actual loss of physical control of the facility.
The potential for release of radioactive material for the General Emergency classification is more than 1000 Ci of 1-131 equivalent or more than 10 6 Ci of Xe-133 equivalent.
The purpose of the declaration of a General Emergency is to: (a) Initiate predetermined protective actions for the public. (b) Provide continuous assessment of information from licensee and offsite measurement. (c) Initiate additional measures as indicated by event releases or potential releases and, (d) Provide current information for and consultation with offsite authorities and the public. A General Emergency would be declared based on FNP-O-EIP-9.2 II. Emergency Director Actions NOTE: THE SHIFT MANAGER SHALL PERFORM THE DUTIES OF THE EMERGENCY DIRECTOR UNTIL HIS ARRIVAL AND ASSUMPTION OF DUTIES. Initials A. 1. 2. Notify personnel on site If the Plant Emergency alarm has not already been activated, then announce over the public address system "All Plant Personnel Report to Designated Assembly Area," activate the PEA for 30 seconds and repeat the announcement.
Announce the classification, and the condition, request setup of the TSC and OSC and give needed evacuation instructions over plant public address system. Page 1 of 8 Version 59.0 09/01108 15:32:53 GUIDELINE 1 GENERAL EMERGENCY B. Callout the ERO staff FNP-0-EIP-9.0 GUIDELINE 1 1. Activate the ERO callout system per FNP-0-EIP-8.3, Table 2. (Located in the Unit 2 SS desk) NOTE: IF POSSIBLE AND TIME PERMITTING, DISCUSS WITH ALABAMA RADIATION CONTROL AND GEORGIA EMERGENCY MANAGEMENT AGENCY ABOUT THE PARs PRIOR TO ANNOUNCING THEM OVER THE ENN. C Complete Notification form 1. Fill in the General Emergency Initial Notification Form (last pages of this guideline), including developing protective action recommendations per step L. Take into account the zones and evacuation time estimates shown in Figure 1. NOTE: INITIAL NOTIFICATIONS WILL NORMALLY BE MADE BY THE OPERATIONS SHIFT COMMUNICATOR, BUT MAY BE MADE BY OPERATIONS STAFF, TSC STAFF OR OTHER QUALIFIED PERSON USING THE INITIAL NOTIFICATION FORM (LAST PAGES OF THIS GUIDELINE).
NOTE: INITIAL AND UPGRADE CLASSIFICATIONS AND NOTIFICATIONS SHOULD BE PERFORMED BY THE CONTROL ROOM OR THE TSC STAFF, WITH THE EOF INFORMED AS SOON AS POSSIBLE.
D. Initial Notifications
___ 1. Within 15 minutes of declaration, verbally notify the state and local agencies using the General Emergency Initial Notification Form (last pages of this guideline).
___ .2. Verify notifications complete and documented on the General Emergency Initial Notification Form (last pages of this guideline).
___ 3. Complete Figure 6, follow-up message. Instructions for completing the form are available as part of the figure. ___ 4. Within one hour of the General Emergency Initial Notification Form (Verbal Notification) transmittal, fax Figure 6, follow-up message to state and local agencies.
The goal should be within 30 minutes of the verbal notification.
___ 5. Complete Figure 5, NRC notification message. Instructions for completing the form are available in Figure 5. Page 2 of 8 Version 59.0 
( 09/01/08 15:32:53 GUIDELINEl GENERAL EMERGENCY FNP-0-EIP-9.0 GUIDELINE 1 ___ 6. Provide the information on Figure 5, to the NRC as soon as possible, but within one hour of the declaration per the instructions on Figure 5. E. Emergency Organization Notifications
: 1. On-call Emergency Director 2. On-call EOF Manager 3. SNC Duty Manager 4. Notify Security of Emergency, incoming personnel and access restrictions (4611). F. Other Notifications
: 1. Have Regulatory ERDS activated to transmit data to the NRC within one hour of the declaration of the emergency (EIP-8-3, step 10). 2. If personnel injury or fire is involved, refer to FNP-0-EIP-11.0 and 13.0 respectively for additional actions and EIP-8.0 steps 5.0 and 6.0 for additional notification requirements.
: 3. U.S. Army EOD group at Fort Benning, GA, if necessary.
: 4. Savannah River Operations Office, if necessary.
: 5. If there is a security event involved ensure appropriate notifications and actions of FNP-0-AOP-49 and FNP-O-SP 37.0 are performed
: 6. If there is a security event involved and access to the plant from off site is restricted by local law enforcement (LLE) and it is desired to bring a plant employee to the site or additional off site resources such as fire departments or law enforcement then perform the following:
* Contact the Houston County EMA to arrange a route and provide the names of individuals or resources that require access to the plant for relay to LLE.
* In conjunction with Houston County EMA determine on site and off site staging areas for off-site resources using Appendix 1
* Inform the individuals and resources that are coming to the site of the required route to the site. Individuals must have a company picture ID to get through the roadblocks Page 3 of 8 Version 59.0 09/01108 15:32:53 GUIDELINEl GENERAL EMERGENCY G. In Plant Protective Actions 1. Ensure personnel accountability per EIP-10.0.
: 2. Plan and initiate reentry's per EIP-14.0.
: 3. Ensure proper Control Room response.
: 4. Assign an individual to provide periodic plant status updates. FNP-0-EIP-9.0 GUIDELINE 1 5. Assign an individual to maintain a log of important Emergency Director activities.
: 6. Assign an individual to keep a record of all off-site communications.
___ 7. Determine what should be done with a unit that is not affected by the declared emergency.
Consider the effect on the emergency unit, manpower utilization, plant and grid stability, and other relevant factors. ___ 8. In the event of mass casualties refer to FNP-0-EIP-11.0 step 15 to arrange for triage and additional ambulances.
H. Off-Site Support 1. Ensure Field Monitoring teams have been dispatched per EIP-4.0. 2. Provide information to the EOF Manager for use in press releases and recovery planning.
I. Information to Off Site Authorities
: 1. Provide periodic plant status updates, meteorological and dose estimates and release projections based on plant conditions and foreseeable contingencies.
J. Re-Assess plant conditions
: 1. Continue to assess plant and radiological conditions to ensure the correct emergency classification is declared.
: 2. If plant and radiological conditions no longer require the current emergency classification terminate the emergency class using FNP-0-EIP-28.0.
K. Long term concerns 1. Within 8 hours, provide for full TSC and OSC reliefs. Page 4 of 8 Version 59.0 09/01108 15:32:53 GUIDELINE 1 GENERAL EMERGENCY
: 2. Within 16 hours, provide for 24 hour TSC and OSC coverage.
FNP-O-EIP-9.0 GUIDELINE 1 3. If an LOSP has occurred evaluate the event to ensure that an adequate supply of fuel oil is available for the Diesel Generators for 7 days. Refer to REA 00-2337 and FNP-0-SOP-42.0 Figure 1. L. Protective action recommendation guidance 1. Make Protective Action Recommendations (PARs) for all General Emergency declarations in accordance with NMP-EP-109.
If an upgrade to PARS is required after making this notification use figure 4 to transmit the new PARS to the state and county agencies.
Page 5 of 8 Version 59.0 
(' 09/01/08 15:32:53 FNP-0-EIP-9.0 GENERAL EMERGENCY RED VERBAL NOTIFICATION FORM MESSAGE # __ _
NOTIFICATION:
TIME _____ DATE_--'-I
_..:..I __ ,AUTHENTICATION
# N/A 3. SITE: FARLEY NUCLEAR PLANT 4. EMERGENCY CLASSIFICATION:
: 5. PROTECTIVE ACTION RECOMMENDATIONS:
______________________________
__ 6. EMERGENCY RELEASE: 7. RELEASE SIGNIFICANCE: Not applicable I&sect;I Within normal operating limits 8. EVENT PROGNOSIS: Improving I&sect; Stable 9. METEOROLOGICAL DATA: 35 foot elevation preferred Precipitation
__ _ 19 Above normal operating limits 19 Degrading IQI Under evaluation Stability Class I&sect;I 19 IQI I&sect; lEI IQI (
: 12. UNIT STATUS: (Unaffected Unit(s) Status Not Required for Initial Notifications)
: 13. REMARKS: D No additional remarks 17. APPROVED BY: U1 __ % Power Shutdown at Time ______ Date _1 __ 1 __ I&sect;I U2 __ % Power Shutdown at Time Date _1 __ 1 __ D read additional remarks on separate page Title Emergency Director Time ___ .Date_I_I
__
..
form must be correct for the notification to be considered correct. ""''iu",u.ua,,)
.",an"'.." at 001 for the first verbal message. cornmuni,eat()r to making the ENN notification G. __ Line 7 Release Significance.
Mark box A, B, C or D. Normal limits are being exceeded if an effluent monitor listed in step F above is in alarm
* Mark box A if 6A is marked
* Mark box B if 6B or 6C is marked and NO effluent monitor is or has been in alarm.
* Mark box C if 6B or 6C is marked and ANY effluent monitor is or has been in alarm.
* Mark box D if 6B or 6C is marked and it can not be determined if an effluent monitor is or has been in alarm. Page 6 of 8 Version 59.0 09/01108 15:32:53 FNP-0-EIP-9.0 GENERAL EMERGENCY RED VERBAL NOTIFICATION FORM __ Line 8 Event Prognosis.
Mark box A, B or C.
* A should be marked if mitigation efforts appear successful, progressing toward termination/recovery.
* B should be marked if escalation to a higher classification is unlikely based on current conditions.
* C should be marked if escalation to a higher emergency classification or PAR change is likely.
* If stability class is not available it can be calculated from delta temperature from the below table (200' elev. temp, OF -35' elev. temp, OF) Stability Class <-1.74 A -1.74 to <-1.56 B -1.56 to <-1.38 C -1.38 to <-0.46 D -0.46 to < 1.38 E 1.38 t 0 3.60 F >3.60 G L __ Line 12 Fill in the per cent power or the time of shutdown for units involved with the event M. __ Line 13 If additional remarks are required mark the box for additional remarks and write them on a separate paper and have them read over the ENN, or mark the box for no additional remarks N. __ The Emergency Director must sign the form with time and date. O. Within 15 minutes of declaration time, using the ENN contact the state and local agencies listed below. P. __ Verify the Southern LINC ENN Radio being used is turned on Q. __ If the Southern LINC display does not show "WIDE AREA, FEP ENN" when group is pressed in step R, THEN perform the following:
* Press the button with the square until the top line is indicated, then press the arrow buttons until "WIDE AREA" is displayed, then press the button under OK. Press the button with the square until the second line is indicated then press the arrow buttons until "FEP ENN" is displayed, and then press the button under OK. R ___ Press group pushbutton, verify display shows WIDE AREA, FEP ENN. Correct per above step if necessary.
Pickup handset or leave in cradle, press to talk (PIT), wait for the chirp and announce "This is name/title at Farley Nuclear Plant. Please obtain a GENERAL EMERGENCY RED initial notification form and monitor the ENN." Release the PIT. S. __ Contact one state and county agency listed in each of the four boxes below. Indicate the time of initial attempt to contact any Alabama agency. Circle agency actually contacted.
Indicate the name of the individual contacted.
Underlined phone numbers staffed 24 hours a day PIT and request one Alabama agency in the order listed below acknowledge manning of the ENN. State agency name and ask if they are on the line. Release the PIT after each request. ALABAMA State Agencies In preferred order
* Alabama Radiation Control at Montgomery EOC. ENN (1305), OPX (6628), (334-206-5391), (334-324-0076)
* AEMAENN (1306), OPX(6619), (205-280-2312, 205-280-2310)
* Alabama Radiation Control at Alabama Forward EOC, ENN (1307), OPX 6621), (334-793-1565)
* HOUSTON COUNTY ENN (1307), OPX (6621), (334-794-9720,793-9655,677-4807,4808)
Time, ____ Name ___________
0 Page 7 of 8 Version 59.0 09/01108 15:32:53 FNP-0-EIP-9.0 GENERAL EMERGENCY RED VERBAL NOTIFICATION FORM Indicate the time of initial attempt to contact any Georgia agency. Circle agency actually contacted.
Indicate the name of the individual contacted.
Underlined phone numbers staffed 24 hours a day PTf and request one Georgia agency in the order listed below acknowledge manning of the ENN. State agency name and ask if they are on the line. Release the PTf after each request. GEORGIA State Agencies In preferred order
* GEMA at Atlanta EOe, ENN (304), OPX (6629), (404-635-7200)
* GEMA at Georgia Forward EOe, ENN (1308) OPX (6626), (229-723-4826)
* EARLY COUNTY, ENN(308) OPX (6622),(229-723-3577,3578,4826)
Time _____ Name, ___________
-----'Acknowledged 0 Indicate the time of initial attempt to contact Houston County. Indicate the name of the individual contacted.
Underlined phone numbers staffed 24 hours a day PTf and request Houston County acknowledge manning of the ENN. State agency name and ask if they are on the line. Release the PTf after each request. HOUSTON COUNTY
* HOUSTON COUNTY, ENN(1307), OPX (6621), (334-794-9720, 793-9655, 334-677-4807, 4808) Time _____ Name, ___________
----:Acknowledged 0 Indicate the time of initial attempt to contact Early County. Indicate the name of the individual contacted.
Underlined phone numbers staffed 24 hours a day PTT and request Early County acknowledge manning of the ENN. State agency name and ask if they are on the line. Release the PTT after each request. EARLY COUNTY
* EARLY COUNTY, ENN(1308)
OPX (6622), (229-723-3577, 3578, 4826) Time _____ Name ___________
----:Acknowledged 0 T. __ Fill in the date and time on line 2 using the time that the frrst state agency contact ATTEMPT was made U. __ PTf and announce on the ENN "Please prepare to receive a GENERAL EMERGENCY, RED initial notification message with acknowledgment", then slowly read the GE initial notification form over the ENN. Release the PTT after reading two or three lines to allow individuals to respond. V. __ Have the agencies contacted above, acknowledge receipt of the message and fill in the acknowledge checkbox above when they do. W. __ If any required agency could not be contacted on the ENN, then use numbers listed with each agency or in FNP-0-EIP-8.1 to contact them by any available means as soon as possible.
X Fax a copy of the previous page GENERAL EMERGENCY RED VERBAL NOTIFICATION FORM to the State of Florida, EOF using speed dial #10 Y. __ Wait for the Fax report indicating the fax was received then verify the state of Florida has received the Fax by calling. (800-320-0519)
(850-413-9911) Page 8 of 8 Version 59.0 09/01108 15:32:53 FNP-O-EIP-9.0 GUIDELINE 2 GUIDELINE 2 SITE AREA EMERGENCY I. Purpose of Classification The classification of Site Area Emergency applies to those events which are in progress or have occurred involving actual or likely major failures of plant functions needed for protection of the public from radiation or contamination or HOSTILE ACTION that results in intentional damage or malicious acts; (1) toward site personnel or equipment that could lead to the likely failure of or; (2) that prevent effective access to equipment needed for the protection of the public. The potential for release of radioactive material for the Site Area Emergency classification is up to 1000 Ci of 1-131 equivalent, or 10 4 to 10 6 Ci of Xe-133 equivalent.
The purpose of the declaration of a Site Area Emergency is to: (a) Assure that response centers are manned, (b) Assure that monitoring teams are dispatched, (c) Assure that personnel involved in an evacuation effort of near site areas are at their duty stations if the situation worsens, and, (d) Provide current information for and consultation with offsite authorities and the public. (e) A Site Area Emergency would be declared for plant conditions that warrant activation of emergency centers and monitoring teams. A Site Area Emergency would be declared Based on FNP-O-EIP-9.2 II. Emergency Director Actions NOTE: THE SHIFT MANAGER SHALL PERFORM THE DUTIES OF THE EMERGENCY DIRECTOR UNTIL HIS ARRIVAL AND ASSUMPTION OF DUTIES. Initials A 1. 2. Notify personnel on site If the plant emergency alarm has not already been activated, then announce over the public address system, "All plant personnel report to designated assembly areas", activate the PEA for 30 seconds, then repeat announcement.
Announce the condition, request setup of the TSC and OSC, and give needed evacuation instructions over plant public address system. Page 1 of 8 Version 59.0 09101/08 15:32:53 GUIDELINE 2 SITE AREA EMERGENCY B. Callout the ERO staff FNP-0-EIP-9.0 GUIDELINE 2 1. Activate the ERO callout system per FNP-0-EIP-8.3, Table 2. (located in the Unit 2 SS desk) C Complete Notification form 1.. Fill in the SITE AREA Emergency Initial Notification Form (last pages of this guideline).
NOTE: INITIAL NOTIFICATIONS WILL NORMALLY BE MADE BY THE OPERATIONS SHIFT COMMUNICATOR, BUT MAY BE MADE BY OPERATIONS STAFF, TSC STAFF OR OTHER QUALIFIED PERSON USING THE INITIAL NOTIFICATION FORM (LAST PAGES OF THIS GUIDELINE).
NOTE: INITIAL AND UPGRADE CLASSIFICATIONS AND NOTIFICATIONS SHOULD BE DONE FROM THE CONTROL ROOM OR THE TSC, WITH THE EOF INFORMED AS SOON AS POSSIBLE.
D. Initial Notifications
___ 1. Within 15 minutes of declaration verbally notify the state agencies using the Site Area Emergency Initial Notification Form (last pages of this guideline).
___ 2. Verify notifications complete and documented on the Site Area Emergency Initial Notification Form (last pages of this guideline).
___ .3. Complete Figure 6, follow-up message. Instructions for completing the form are available as part of the Figure. ___ 4. Within one hour of the Site Area Emergency Initial Notification Form (Verbal Notification) transmittal, fax Figure 6, follow-up message to state and local agencies.
The goal should be within 30 minutes of the verbal notification.
___ .5. Complete Figure 5, NRC notification message. Instructions for completing the form are available in Figure 5. __ --'6=.. Provide the information on Figure 5, to the NRC as soon as possible, but within one hour of the declaration per the instructions on Figure 5. E. Emergency Organization Notifications
: 1. On-call Emergency Director Page 2 of 8 Version 59.0 09/01/08 15:32:53 GUIDELINE 2 SITE AREA EMERGENCY
: 2. On-call EOF Manager 3. SNC Duty Manager FNP-0-EIP-9.0 GUIDELINE 2 4. Notify Security of Emergency, incoming personnel and access restrictions (4611). F. Other Notifications
: 1. Have Regulatory ERDS activated to transmit data to the NRC within one hour of the declaration of the emergency (EIP 8.3, step 10). 2. If personnel injury or fire is involved, refer to FNP-0-EIP-l1.0 and 13.0 respectively for additional actions and EIP-8.0 steps 5.0 and 6.0 for additional notifications.
: 3. U.S. Army EOD group at Fort Benning, GA, if necessary.
: 4. Savannah River Operations Office, if necessary.
: 5. If there is a security event involved, ensure appropriate notifications and actions ofFNP-0-AOP-49 and FNP-O-SP 37.0 are performed.
: 6. If there is a security event involved and access to the plant from off site is restricted by local law enforcement (LLE) and it is desired to bring a plant employee to the site or additional off site resources such as fire departments or law enforcement then perform the following:
* Contact the Houston County EMA to arrange a route and provide the names of individuals or resources that require access to the plant for relay to LLE.
* In conjunction with Houston County EMA determine on site and off site staging areas for off-site resources using Appendix 1
* Inform the individuals and resources that are coming to the site of the required route to the site. Individuals must have a company picture ID to get through the roadblocks G. In Plant Protective Actions 1. Ensure personnel accountability per EIP-lO.O.
: 2. Plan and initiate reentries per EIP-14.0.
: 3. Ensure proper Control Room response.
: 4. Assign an individual to provide periodic plant status updates. Page 3 of 8 Version 59.0 09/01/08 15:32:53 GIDDELINE2 SITE AREA EMERGENCY FNP-0-EIP-9.0 GUIDELINE 2 5. Assign an individual to maintain a log of important Emergency Director activities.
: 6. Assign an individual to keep a record of all off site communications.
: 7. Determine what should be done with a unit that is not affected by the declared emergency.
Consider the effect on the emergency unit, manpower utilization, plant and grid stability and other relevant factors. ___ 8. In the event of mass casualties refer to FNP-0-EIP-l1.0 step 15 to arrange for triage and additional ambulances.
H. Off Site Support 1. Ensure Field Monitoring teams have been dispatched per EIP-4.0. 2. Provide information to the EOF Manager for use in press releases and recovery planning.
I. Information to Off Site Authorities
: 1. Provide periodic plant status updates, meteorological and dose estimates and release projections based on plant conditions and foreseeable contingencies.
J. Re-Assess plant conditions
: 1. Continue to assess plant and radiological conditions to ensure the correct emergency classification is declared.
: 2. If a higher emergency classification is required immediately go to the appropriate guideline.
: 3. If plant and radiological conditions no longer require the current emergency classification terminate the emergency class using FNP-0-EIP-28.0.
K. Long term concerns 1. Within 8 hours, provide for full TSC and OSC reliefs. 2. Within 16 hours, provide for 24 hour TSC and OSC coverage.
: 3. If an LOSP has occurred evaluate the event to ensure that an adequate supply of fuel oil is available for the Diesel Generators for 7 days. Refer to REA 00-2337 and FNP-0-SOP-42.0 Figure 1. Page 4 of 8 Version 59.0 09/01108 15:32:53 GUIDELINE 2 SITE AREA EMERGENCY L. Protective action recommendation guidance FNP-0-EIP-9.0 GUIDELINE 2 a. Protective Action Recommendations other than NONE should not be made for a Site Area Emergency
.. b. If it is determined that PARs are required, then the emergency classification should be upgraded to a General Emergency Page 5 of8 Version 59.0 09/01/08 15:32:53 FNP-0-EIP-9.0 GUIDELINE 2 GUIDELINE 2 SITE AREA EMERGENCY ORANGE VERBAL NOTIFICATION FORM MESSAGE # __ _ NOTIFICATION:
TIME _____ ,DATE_....J.1
__ 1'-_AUTHENTICATION
# N/A 4. EMERGENCY CLASSIFICATION:
: 5. PROTECTIVE ACTION RECOMMENDATIONS:
: 6. EMERGENCY RELEASE: 7. RELEASE SIGNIFICANCE: Not applicable I&sect;I Within normal operating limits 8. EVENT PROGNOSIS: Improving I&sect; Stable 9. METEOROLOGICAL DATA: 19 Above normal operating limits 19 Degrading IQI Under evaluation 35 foot elevation preferred Precipitation
__ _ Stability Class I&sect;I 19 IQI I&sect; lEI IQI 1
: 12. UNIT STATUS: U1 __ % Power Shutdown at Time ______ Date _1 __ 1 __ (Unaffected Unit(s) Status Not Required for Initial Notifications)
I&sect;I U2 __ % Power Shutdown at Time Date _1 __ 1 __ o read additional remarks on separate page 13. REMARKS: 0 No additional remarks 17. APPROVED BY: Title Emergency Director Time ___ .Date_I_I
__
on this form must be correct for the notification to be considered correct. B. __ Line 1 Number each verbal initial and follow-up messages sequentially starting at 001 for the first verbal message. C. Line 2 Notification time to be ENN communicator* . to making the ENN notification F. __ --" G. __ Line 7 Release Significance.
Mark box A, B, C or D. Normal limits are being exceeded if an effluent monitor listed in step F above is in alarm
* Mark box A if 6A is marked
* Mark box B if 6B or 6C is marked and NO effluent monitor is or has been in alarm.
* Mark box C if 6B or 6C is marked and ANY effluent monitor is or has been in alarm.
* Mark box D if 6B or 6C is marked and it can not be determined if an effluent monitor is or has been in alarm. H. __ Line 8 Event Prognoses.
Mark box A, B or C.
* A should be marked if mitigation efforts appear successful, progressing toward termination/recovery.
* B should be marked if escalation to a higher classification is unlikely based on current conditions.
* C should be marked if escalation to a higher emergency classification or PAR change is likely. Page 6 of 8 Version 59.0 I. 09/01108 15:32:53 GUIDELINE 2 SITE AREA EMERGENCY ORANGE VERBAL NOTIFICATION FORM FNP-0-EIP-9.0 GUIDELINE 2
* If stability class is not available it can be calculated from delta temperature from the below table (200' elev. temp, of -35' elev. temp, OF) Stability Class <-1.74 A -1.74 to <-1.56 B -1.56 to <-1.38 C -1.38 to <-0.46 D -0.46 to < 1.38 E 1.38 t 0 3.60 F >3.60 G L. __ Line 12 Fill in the per cent power or the time of shutdown for units involved with the event M. __ Line 13 If additional remarks are required mark the box for additional remarks and write them on a separate paper and have them read over the ENN, or mark the box for no additional remarks N. __ The Emergency Director must sign the form with time and date. O. Within 15 minutes of declaration time, using the ENN contact the state and local agencies listed below. P. __ Verify the Southern LINC ENN Radio being used is turned on Q. __ If the Southern LINC display does not show "WIDE AREA, PEP ENN" when group is pressed in step R, THEN perform the following:
* Press the button with the square until the top line is indicated, then press the arrow buttons until "WIDE AREA" is displayed, then press the button under OK. Press the button with the square until the second line is indicated then press the arrow buttons until "PEP ENN" is displayed, and then press the button under OK. 1 __ Press group pushbutton, verify display shows WIDE AREA, PEP ENN. Correct per above step if necessary.
Pickup handset or leave in cradle, press to talk (PTT), wait for the chirp and announce "This is name/title at Farley Nuclear Plant. Please obtain a SITE AREA EMERGENCY ORANGE initial notification form and monitor the ENN." Release the PTT. S. __ Contact one state agency listed in each of the two boxes below. Indicate the time of initial attempt to contact any Alabama agency. Circle agency actually contacted.
Indicate the name of the individual contacted.
Underlined phone numbers staffed 24 hours a day PTT and request one Alabama agency in the order listed below acknowledge manning of the ENN. State agency name and ask if they are on the line. Release the PTT after each request. ALABAMA State Agencies In preferred order
* Alabama Radiation Control at Montgomery EOC. ENN (1305), OPX (6628), (334-206-5391), (334-324-0076)
* AEMA ENN (1306), OPX(6619), (205-280-2312,205-280-2310)
* Alabama Radiation Control at Alabama Forward EOC, ENN (1307), OPX 6621), (334-793-1565)
* HOUSTON COUNTY ENN (1307), OPX (6621), (334-794-9720, 793-9655, 677-4807, 4808) Time ____ .Name _____________ .Acknowledged 0 Page 7 of 8 Version 59.0 
( 09101108 15:32:53 GUIDELINE 2 SITE AREA EMERGENCY ORANGE VERBAL NOTIFICATION FORM FNP-0-EIP-9.0 GUIDELINE 2 Indicate the time of initial attempt to contact any Georgia agency. Circle agency actually contacted.
Indicate the name of the individual contacted.
Underlined phone numbers staffed 24 hours a day PIT and request one Georgia agency in the order listed below acknowledge manning of the ENN. State agency name and ask if they are on the line. Release the PIT after each request. GEORGIA State Agencies In preferred order
* GEMA at Atlanta EOC, ENN (1304), OPX (6629), (404-635-7200)
* GEMA at Georgia Forward EOC, ENN (1308) OPX (6626), (229-723-4826)
* EARLY COUNTY, ENN(1308)
OPX (6622),(229-723-3577, 3578,4826)
Time ___ -.cName ____________ .Acknowledged D T . __ Fill in the date and time on line 2 using the time that the fIrst state agency contact ATTEMPT was made U __ PIT and announce on the ENN "Please prepare to receive a SITE AREA EMERGENCY, ORANGE initial notification message with acknowledgment", then slowly read the SAE initial notifIcation form over the ENN. Release the PIT after reading two or three lines to allow individuals to respond. V. __ Have the agencies contacted above, acknowledge receipt of the message and fIll in the acknowledge checkbox above when they do. W. __ If any required agency could not be contacted on the ENN, then use numbers listed with each agency or in FNP-O-EIP-8.1 to contact them by any available means as soon as possible.
X Fax a copy of the previous page SITE AREA EMERGENCY ORANGE VERBAL NOTIFICATION FORM to the State of Florida, EOF using speed dial #10 Y. __ Wait for the Fax report indicating the fax was received then verify the state of Florida has received the Fax by calling. (800-320-0519)
(850-413-9911) Page 8 of 8 Version 59.0 09/01108 15:32:53 FNP-0-EIP-9.0 GUIDELINE 3 GUIDELINE 3 ALERT I. Purpose of Classification The classification of Alert applies to situations in which events are in process or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant or a security event that involves probable life threatening risk to site personnel or damage to site equipment because of hostile action. The potential for release of radioactive material for the Alert classification is up to 10 curies of 1-131 equivalent, or up to 10 4 curies of Xe-133 equivalent.
The purpose of offsite alert is to assure that emergency personnel are readily available to respond if the situation becomes more serious or to perform confirmatory radiation monitoring, if required, and to provide offsite authorities current status information for possible further action. (a) An Alert would be declared for plant conditions that warrant precautionary activation of the technical support center, operations support centers, and the Emergency Operations Facility.
An Alert would be declared based on FNP-O-EIP-9.2 II. Emergency Director Actions NOTE: THE SIDFT MANAGER SHALL PERFORM THE DUTIES OF THE EMERGENCY DIRECTOR UNTIL IDS ARRIV AL AND ASSUMPTION OF DUTIES. A 1. 2. B. 1.. Notify personnel on site If the Plant Emergency alarm has not already been activated, then announce over the public address system "All Plant Personnel Report to Designated Assembly Area," activate the PEA for 30 seconds and repeat the announcement.
Announce the classification and the condition, request setup of the TSC and OSC, and give needed evacuation instructions over plant public address system. Callout the ERO staff Activate the ERO callout system per FNP-0-EIP-8.3, Table 2. (located in the Unit 2 SS desk) C Complete Notification form 1. Fill in the ALERT Initial Notification Form (last pages of this guideline).
Page 1 of7 Version 59.0 09/01108 15:32:53 GUIDELINE 3 ALERT FNP-0-EIP-9.0 GUIDELINE 3 NOTE: INITIAL NOTIFICATIONS WILL NORMALLY BE MADE BY THE OPERATIONS SHIFT COMMUNICATOR, BUT MAY BE MADE BY OPERATIONS STAFF, TSC STAFF OR OTHER QUALIFIED PERSON USING THE INITIAL NOTIFICATION FORM (LAST PAGES OF THIS GUIDELINE).
NOTE: INITIAL AND UPGRADE CLASSIFICATIONS AND NOTIFICATIONS SHOULD BE DONE FROM THE CONTROL ROOM OR THE TSC, WITH THE EOF INFORMED AS SOON AS POSSIBLE.
D. Initial Notifications
___ 1. Within 15 minutes of declaration, verbally notify the state and local agencies using the Alert Initial Notification Form (last pages of this guideline).
__ --'2. Verify notifications complete and documented on the Alert Initial Notification Form (last pages of this guideline).
___ 3. Complete Figure 6, follow-up message. Instructions for completing the form are available as part of the figure. ___ 4. Within one hour of the Alert Initial Notification Form (Verbal Notification) transmittal, fax Figure 6, follow-up message to state and local agencies.
The goal should be within 30 minutes of the verbal notification.
__ Complete Figure 5, NRC notification message. Instructions for completing the form are available in Figure 5. __ -,6=. Provide the information on Figure 5, to the NRC as soon as possible, but within one hour of the declaration per the instructions on Figure 5. E. Emergency Organization Notifications
: 1. On-call Emergency Director 2. On-call EOF Manager 3. SNC Duty Manager 4. Notify Security of Emergency, incoming personnel and access restrictions.
(4611) F. Other Notifications
: 1. Have Regulatory EROS activated to transmit data to the NRC within one hour of the declaration of the emergency (EIP-8.3, step 10) Page 2 of7 Version 59.0 09101/08 15:32:53 GUIDELINE 3 ALERT FNP-O-EIP-9.0 GUIDELINE 3 2. If personnel injury or fire is involved, refer to FNP-0-EIP-11.0 and 13.0 respectively for additional actions and EIP-8.0 steps 5.0 and 6.0 for additional notifications
: 3. U.S. Army EOD group at Fort Benning, GA, if necessary
: 4. Savannah River Operations Office, if necessary
: 5. If there is a security event involved, ensure appropriate notifications and actions ofFNP-0-AOP-49 and FNP-O-SP 37.0 are performed
: 6. If there is a security event involved and access to the plant from off site is restricted by local law enforcement (LLE) and it is desired to bring a plant employee to the site or additional off site resources such as fire departments or law enforcement then perform the following:
* Contact the Houston County EMA to arrange a route and provide the names of individuals that require access to the plant for relay to LLE.
* In conjunction with Houston County EMA determine on site and off site staging areas for off-site resources using Appendix 1
* Inform the individuals and resources that are coming to the site of the required route to the site. Individuals must have a company picture ID to get through the roadblocks G. In Plant Protective Actions 1. Ensure personnel accountability per EIP-10.0.
: 2. Plan and initiate re-entries per EIP-14.0.
: 3. Ensure proper Control Room response 4. Assign an individual to provide periodic plant status updates 5. Assign an individual to maintain a log of important Emergency Director activities
: 6. Assign an individual to keep a record of all off site communications
: 7. Determine what should be done with a unit that is not affected by the declared emergency.
Consider the effect on the emergency unit, manpower utilization, plant and grid stability, and other relevant factors. Page 3 of7 Version 59.0 09/01/08 15:32:53 GUIDELINE 3 ALERT FNP-0-EIP-9.0 GUIDELINE 3 ___ 8. In the event of mass casualties refer to FNP-0-EIP-ll.0 step 15 to arrange for triage and additional ambulances.
H. Off Site Support 1. Ensure Field Monitoring teams have been dispatched per EIP 4.0. 2. Provide information to the EOF Manager for use in press releases and recovery planning I. Information to Off Site Authorities
: 1. Provide periodic plant status updates, meteorological and dose estimates and release projections based on plant conditions and foreseeable contingencies.
J. Re-Assess plant conditions
: 1. Continue to assess plant and radiological conditions to ensure the correct emergency classification is declared.
: 2. If a higher emergency classification is required immediately go to the appropriate guideline
: 3. If plant and radiological conditions no longer require the current emergency classification terminate the emergency class using FNP-0-EIP-28.0.
K. Long term concerns 1. Within 8 hours, provide for full TSC and OSC reliefs 2. Within 16 hours, provide for 24 hour TSC and OSC coverage 3. If an LOSP has occurred evaluate the event to ensure that an adequate supply of fuel oil is available for the Diesel Generators for 7 days. Refer to REA 00-2337 and FNP-0-SOP-42.0 Figure 1. L. Protective action recommendation guidance 1. Protective Action Recommendations are not required.
Block A of line 5 on the notification form should be checked. Page 4 of7 Version 59.0 09/01/08 15:32:53 FNP-0-EIP-9.0 GUIDELINE 3 ALERT YELLOW VERBAL NOTIFICATION FORM 1 ... 11 111_ MESSAGE #_-
NOTIFICATION:
TIME, _____ DATE,_ .... I __ I'--_AUTHENTICATION
# NlA 3. SITE: FARLEY NUCLEAR PLANT 4. EMERGENCY CLASSIFICATION:
: 5. PROTECTIVE ACTION RECOMMENDATIONS:
: 6. EMERGENCY RELEASE: 7. RELEASE SIGNIFICANCE: Not applicable
: 8. EVENT PROGNOSIS:
: 9. METEOROLOGICAL DATA: &sect; Above normal operating limits 19 Degrading
..... 'I!IIlJIiIl IQI Under evaluation 35 foot elevation preferred 1
Precipitation
__ _ Stability Class I&sect;I I&sect; IQI I&sect; lEI I&sect;I * ......aJ_
: 12. UNIT STATUS: (Unaffected Unit(s) Status Not Required for Initial Notifications)
: 13. REMARKS: 0 No additional remarks ,7. APPROVED BY: U1 __ % Power Shutdown at Time _____ Date _1 __ 1 __ I&sect;I U2 __ % Power Shutdown at Time Date _1 __ 1 __ o read additional remarks on separate page Title Emergency Director Time ___ .Date_I_I
__ UJiSUU!;U",U on this form must be correct for the notification to be considered correct. sequenltially "t,.rtiTU.
at 001 for the first verbal message. cornmuni,catc)r the ENN notification G. __ Line 7 Release Significance.
Mark box A, B, Cor D. Normal limits are being exceeded if an effluent monitor listed in step F above is in alarm
* Mark box A if 6A is marked
* Mark box B if 6B or 6C is marked and NO effluent monitor is or has been in alarm.
* Mark box C if 6B or 6C is marked and ANY effluent monitor is or has been in alarm.
* Mark box D if 6B or 6C is marked and it can not be determined if an effluent monitor is or has been in alarm. H. __ Line 8 Event Prognoses.
Mark box A, B or C.
* A should be marked if mitigation efforts appear successful, progressing toward termination/recovery.
* B should be marked if escalation to a higher classification is unlikely based on current conditions.
* C should be marked if escalation to a higher emergency classification or PAR change is likely. Page 5 of7 Version 59.0 
( 09/01/08 15:32:53 GUIDELINE 3 ALERT YELLOW VERBAL NOTIFICATION FORM FNP-0-EIP-9.0
* If stability class is not available it can be calculated from delta temperature from the below table (200' elev. temp, of -35' elev. temp, OF) Stability Class <-1.74 A -1.74 to <-1.56 B -1.56 to <-1.38 C -1.38 to <-0.46 D -0.46 to < 1.38 E 1.38 to 3.60 F >3.60 G L. __ Line 12 Fill in the per cent power or the time of shutdown for units involved with the event M. __ Line 13 If additional remarks are required mark the box for additional remarks and write them on a separate paper and have them read over the ENN, or mark the box for no additional remarks N. __ The Emergency Director must sign the form with time and date. O. Within 15 minutes of declaration time, using the ENN contact the state and local agencies listed below. P. __ Verify the Southern LINC ENN Radio being used is turned on Q. __ If the Southern LINC display does not show "WIDE AREA, FEP ENN" when group is pressed in step R, THEN perform the following:
* Press the button with the square until the top line is indicated, then press the arrow buttons until "WIDE AREA" is displayed, then press the button under OK. Press the button with the square until the second line is indicated then press the arrow buttons until "FEP ENN" is displayed, and then press the button under OK. -< ___ Press group pushbutton, verify display shows WIDE AREA, FEP ENN. Correct per above step if necessary.
Pickup handset or leave in cradle, press to talk (FIT), wait for the chirp and announce ''This is name/title at Farley Nuclear Plant. Please obtain a ALERT YELLOW initial notification form and monitor the ENN." Release the FIT. S. __ Contact one state agency listed in each of the two boxes below. Indicate the time of initial attempt to contact any Alabama agency. Circle agency actually contacted.
Indicate the name of the individual contacted.
Underlined phone numbers staffed 24 hours a day FIT and request one Alabama agency in the order listed below acknowledge manning of the ENN. State agency name and ask if they are on the line. Release the FIT after each request. ALABAMA State Agencies In preferred order
* Alabama Radiation Control at Montgomery EOC. ENN (1305), OPX (6628), (334-206-5391), (334-324-0076)
* AEMA ENN (1306), OPX(6619), (205-280-2312, 205-280-2310)
* Alabama Radiation Control at Alabama Forward EOC, ENN (1307), OPX 6621), (334-793-1565)
* HOUSTON COUNTY ENN (1307), OPX (6621), (334-794-9720, 793-9655, 677-4807, 4808) Time ____ Name ____________
Acknowledged D Page 6 of7 Version 59.0 09/01108 15:32:53 GUIDELINE 3 ALERT YELLOW VERBAL NOTIFICATION FORM FNP-O-EIP-9.0 Indicate the time of initial attempt to contact any Georgia agency. Circle agency actually contacted.
Indicate the name of the individual contacted.
Underlined phone numbers staffed 24 hours a day P1T and request one Georgia agency in the order listed below acknowledge manning of the ENN. State agency name and ask if they are on the line. Release the P1T after each request. GEORGIA State Agencies In preferred order
* GEMA at Atlanta EOe, ENN (1304), OPX (6629), (404-635-7200)
* GEMA at Georgia Forward EOe, ENN (1308) OPX (6626), (229-723-4826)
* EARLY COUNTY, ENN(1308)
OPX (6622),(229-723-3577,3578,4826)
Time, ____ Name ___________
---'Acknowledged 0 T . __ Fill in the date and time on line 2 using the time that the fIrst state agency contact ATTEMPT was made D. __ P1T and announce on the ENN "Please prepare to receive an ALERT, YELLOW initial notification message with acknowledgment", then slowly read the ALERT initial notifIcation form over the ENN. Release the P1T after reading two or three lines to allow individuals to respond. V. ___ Have the agencies contacted above, acknowledge receipt of the message and fIll in the acknowledge checkbox above when they do. W. __ If any required agency could not be contacted on the ENN, then use numbers listed with each agency or in FNP-O-EIP-8.1 to contact them by any available means as soon as possible.
X Fax a copy of the previous page ALERT YELLOW VERBAL NOTIFICATION FORM to the State of Florida, EOF using speed dial #10 Y . __ W ait for the Fax report indicating the fax was received then verify the state of Florida has received the Fax by calling. (800-320-0519)
(850-413-9911) Page 7 of7 Version 59.0 
( 09101/08 15:32:53 FNP-0-EIP-9.0 GUIDELINE 4 GIDDELINE4 NOUE I. Purpose of Classification The classification of Notification of Unusual Event applies to situations in which events are in process or have occurred which could indicate a potential degradation of the level of safety of the plant or indicate a security threat to facility protection has been initiated.
No releases of radioactive material requiring offsite response or monitoring are expected unless further degradation of safety systems occur. (a) A NOTIFICATION OF UNUSUAL EVENT would be required for any plant condition that warrants increased awareness on the part of state and/or local offsite authorities or involve other than normal plant shutdown.
A Notification of Unusual Event would be declared based on FNP-O-EIP-9.2 II. Emergency Director Actions NOTE: THE SIDFT MANAGER SHALL PERFORM THE DUTIES OF THE EMERGENCY DIRECTOR UNTIL HIS ARRIVAL AND ASSUMPTION OF DUTIES. Initials A 1. 2. B. 1.. C 1.. Notify personnel on site Announce the classification and condition and give needed evacuation instructions over plant public address system. Evacuate affected areas of the plant as appropriate.
Callout the ERO staff as appropriate Activate the ERO callout system per FNP-0-EIP-8.3, Table 2. (located in the Unit 2 SS desk) if it is desired to callout the entire TSC and EOF staff. For partial staffing refer to steps El and E2 and the note above E1. Complete Notification form Fill in the NOVE Initial Notification Form (last pages of this guideline).
Page 1 of 8 Version 59.0 09/01108 15:32:53 GUIDELINE 4 NOVE FNP-0-EIP-9.0 GVIDELINE4 NOTE: INITIAL NOTIFICATIONS WILL NORMALLY BE MADE BY THE OPERATIONS SHIFT COMMUNICATOR, BUT MAY BE MADE BY OPERATIONS STAFF, TSC STAFF OR OTHER QUALIFIED PERSON USING THE INITIAL NOTIFICATION FORM (LAST PAGES OF THIS GUIDELINE).
NOTE: INITIAL AND UPGRADE CLASSIFICATIONS AND NOTIFICATIONS SHOULD BE DONE FROM THE CONTROL ROOM OR THE TSC, WITH THE EOF INFORMED AS SOON AS POSSIBLE.
D. Initial Notifications
___ 1. Within 15 minutes of declaration, verbally notify the state and local agencies using the NOVE Initial Notification Form (last pages of this guideline).
___ 2. Verify notifications complete and documented on the NOVE Initial Notification Form (last pages of this guideline).
___ 3. Complete Figure 6, follow-up message. Instructions for completing the form are available as part of the figure. ___ 4. Within one hour of the NOVE Initial Notification Form (Verbal Notification) transmittal, fax Figure 6, follow-up message to state and local agencies.
The goal should be within 30 minutes of the verbal notification.
___ 5. Complete Figure 5, NRC notification message. Instructions for completing the form are available in Figure 5. __ ......;6=.
Provide the information on Figure 5, to the NRC as soon as possible, but within one hour of the declaration per the instructions on Figure 5. E. Emergency Organization Notifications NOTE: TABLE 2 PROVIDES GUIDANCE AS TO THE REQUIRED LEVEL OF ACTIVATION OF THE TSC AND EOF. LEVEL OF ACTIVATION, IF ANY, IS AT THE DISCRETION OF THE EDIEOF MANAGER. SEE EIP-6 FOR GUIDANCE.
THE COMPLETE EOF AND TSC STAFF CAN BE CALLED OUT USING THE ERO CALLOUT SYSTEM PER FNP-O-EIP-8.3, TABLE 2 IF DESIRED. 1. TSC Staff, if activated by the ED 2. EOF Staff, if activated by the EOF Manager Page 2 of 8 Version 59.0 09/01108 15:32:53 GUIDELINE 4 NOUE 3. On-call Emergency Director 4. On-call EOF Manager 5. SNC Duty Manager FNP-0-EIP-9.0 GUIDELINE 4 6. Notify Security of Emergency, incoming personnel and access restrictions (4611). F. Other Notifications
: 1. If personnel injury or fire is involved, refer to FNP-0-EIP-11.0 and 13.0 respectively for additional notifications.
: 2. U.S. Army EOD group at Fort Benning, GA, if necessary
: 3. Savannah River Operations Office, if necessary
: 4. If there is a security event involved, ensure appropriate notifications and actions of FNP-0-AOP-49 and FNP-O-SP 37.0 are performed.
: 5. If there is a security event involved and access to the plant from off site is restricted by local law enforcement (LLE) and it is desired to bring a plant employee to the site or additional off site resources such as fire departments or law enforcement then perform the following:
* Contact the Houston County EMA to arrange a route and provide the names of individuals or resources that require access to the plant for relay to LLE.
* In conjunction with Houston County EMA determine on site and off site staging areas for off-site resources using Appendix 1
* Inform the individuals and resources that are coming to the site of the required route to the site. Individuals must have a company picture ID to get through the roadblocks G. In Plant Protective Actions 1. Ensure personnel accountability per EIP-IO.O, if any areas of the plant were evacuated due to hazardous conditions.
: 2. Plan and initiate re entries per EIP-14.0, if any areas of the plant were evacuated due to hazardous conditions.
: 3. Ensure proper Control Room response.
: 4. Assign an individual to provide periodic plant status updates. Page 3 of8 Version 59.0 09/01/08 15:32:53 GUIDELINE 4 NOUE FNP-0-EIP-9.0 GUIDELINE 4 5. Assign an individual to maintain a log of important Emergency Director activities.
: 6. Assign an individual to keep a record of all off site communications.
: 7. Determine what should be done with a unit that is not affected by the declared emergency.
Consider the effect on the emergency unit, manpower utilization, plant and grid stability, and other relevant factors. ___ 8. In the event of mass casualties refer to FNP-0-EIP-l1.0 step 15 to arrange for triage and additional ambulances.
H. Off-Site Support 1. Ensure Field Monitoring teams have been dispatched per EIP-4.0 if a radiological release is suspected.
: 2. Provide information to the EOF Manager for use in press releases and recovery planning.
I. Information to Off-Site Authorities
: 1. Provide periodic plant status updates, meteorological and dose estimates and release projections based on plant conditions and foreseeable contingencies.
J. Re-Assess plant conditions
: 1. Continue to assess plant and radiological conditions to ensure the correct emergency classification is declared.
: 2. If a higher emergency classification is required immediately go to the appropriate guideline.
: 3. If plant and radiological conditions no longer require the current emergency classification terminate the emergency class using FNP-0-EIP-28.0.
K. Long term concerns 1. Within 8 hours, provide for full TSC and OSC reliefs. 2. Within 16 hours, provide for 24 hour TSC and OSC coverage.
Page 4 of 8 Version 59.0 09/01/08 15:32:53 GUIDELINE 4 NOUE FNP-0-EIP-9.0 GUIDELINE 4 3. If an LOSP has occurred evaluate the event to ensure that an adequate supply of fuel oil is available for the Diesel Generators for 7 days. Refer to REA 00-2337 and FNP-0-SOP-42.0 Figure 1. L. Protective action recommendation guidance 1. Protective Action Recommendations are not required.
Block A of Line 5 on the notification form should be checked. Page 5 of 8 Version 59.0 09/01/08 15:32:53 FNP-0-EIP-9.0 GUIDELINE 4 NOTIFICATION OF UNUSUAL EVENT BLUE VERBAL NOTIFICATION FORM 1. r8I MESSAGE # -_
NOTIFICATION:
TIME, _____ DATE._-J-1
_...r../ __ ,AUTHENTICATION
# N/A 3. SITE: FARLEY NUCLEAR PLANT 4. EMERGENCY CLASSIFICATION:
"".,, >'.L. 'f" 5. PROTECTIVE ACTION RECOMMENDATIONS:
,> ** { i. ' ,. . .",; . ;.:' , .. ',' 6. EMERGENCY RELEASE:
: 7. RELEASE SIGNIFICANCE: Not applicable I&sect;l Within normal operating limits 8. EVENT PROGNOSIS: Improving Stable 9. METEOROLOGICAL DATA:
19 Above normal operating limits &sect; Degrading
>" . ";;';'rr.ph IQI Under evaluation (35 foot elevation preferred)
Precipitation
__ _ Stability Class I&sect;l 19 IQI I&sect; lEI IQI 1
: 12. UNIT STATUS: (Unaffected Unit(s) Status Not Required for Initial Notifications) U1 __ % Power Shutdown at Time ______ Date _1 __ 1 __ 13. REMARKS: D No additional remarks I&sect;l U2 __ % Power Shutdown at Time Date _1 __ 1 __ D read additional remarks on separate page 17. APPROVED BY: Title Emergency Director Time ___ .Date_I_I
__ NOTE: 1'he, infonnation in grey 0Il thisf?rlllmust be the notification to be considered correct. A. __
B. __ Line 1 Number each verbal initial and follow-up messages sequentially starting at 001 for the first verbal message. C. Line 2 Notification time to be com leted b ENN communicator just rior to making the ENN notification .. __
alldab'Qv.e . ;tg e .
G. __ Line 7 Release Significance.
Mark box A, B, C or D. Nonnallimits are being exceeded if an effluent monitor listed in step F above is in alarm
* Mark box A if 6A is marked
* Mark box B if 6B or 6C is marked and NO effluent monitor is or has been in alarm.
* Mark box C if 6B or 6C is marked and ANY effluent monitor is or has been in alarm.
* Mark box D if 6B or 6C is marked and it can not be determined if an effluent monitor is or has been in alarm. H. __ Line 8 Event Prognoses.
Mark box A, B or C.
* A should be marked if mitigation efforts appear successful, progressing toward termination/recovery.
* B should be marked if escalation to a higher classification is unlikely based on current conditions.
* C should be marked if escalation to a higher emergency classification or PAR change is likely. Page 6 of 8 Version 59.0 09/01108 15:32:53 GUIDELINE 4 NOTIFICATION OF UNUSUAL EVENT BLUE VERBAL NOTIFICATION FORM FNP-0-EIP-9.0
* If stability class is not available it can be calculated from delta temperature from the below table ilT (200' elev. temp, of -35' elev. temp, OF) Stability Class <-1.74 A -1.74 to <-1.56 B -1.56 to <-1.38 C -1.38 to <-0.46 D -0.46 to < 1.38 E 1.38 to 3.60 F >3.60 G L. __ Line 12 Fill in the per cent power or the time of shutdown for units involved with the event M. __ Line 13 If additional remarks are required mark the box for additional remarks and write them on a separate paper and have them read over the ENN, or mark the box for no additional remarks N. __ The Emergency Director must sign the form with time and date. O. Within 15 minutes of declaration time, using the ENN contact the state and local agencies listed below. P. __ Verify the Southern LINC ENN Radio being used is turned on Q. __ If the Southern LINC display does not show "WIDE AREA, PEP ENN" when group is pressed in step R, THEN perform the following:
* Press the button with the square until the top line is indicated, then press the arrow buttons until "WIDE AREA" is displayed, then press the button under OK. Press the button with the square until the second line is indicated then press the arrow buttons until "PEP ENN" is displayed, and then press the button under OK. R. __ Press group pushbutton, verify display shows WIDE AREA, PEP ENN. Correct per above step if necessary.
Pickup handset or leave in cradle, press to talk (PTT), wait for the chirp and announce ''This is name/title at Farley Nuclear Plant. Please obtain a Notification Of Unusual Event blue initial notification form and monitor the ENN." Release the PTT. S. __ Contact one state agency listed in each of the two boxes below. Indicate the time of initial attempt to contact any Alabama agency. Circle agency actually contacted.
Indicate the name of the individual contacted.
Underlined phone numbers staffed 24 hours a day PTT and request one Alabama agency in the order listed below acknowledge manning of the ENN. State agency name and ask if they are on the line. Release the PTT after each request. ALABAMA State Agencies In preferred order
* Alabama Radiation Control at Montgomery EOC. ENN (1305), OPX (6628), (334-206-5391), (334-324-0076)
* AEMAENN (1306), OPX(6619), (205-280-2312, 205-280-2310)
* Alabama Radiation Control at Alabama Forward EOC, ENN (1307), OPX 6621), (334-793-1565)
* HOUSTON COUNTY ENN (1307), OPX (6621), (334-794-9720,793-9655,677-4807,4808)
Time ___ ---'Name ____________
-'Acknowledged 0 Page 7 of 8 Version 59.0 
( ( 09/01/08 15:32:53 GUIDELINE 4 NOTIFICATION OF UNUSUAL EVENT BLUE VERBAL NOTIFICATION FORM FNP-0-EIP-9.0 Indicate the time of initial attempt to contact any Georgia agency. Circle agency actually contacted.
Indicate the name of the individual contacted.
Underlined phone numbers staffed 24 hours a day P'IT and request one Georgia agency in the order listed below acknowledge manning of the ENN. State agency name and ask if they are on the line. Release the P'IT after each request. GEORGIA State Agencies In preferred order
* GEMA at Atlanta EOC, ENN (1304), OPX (6629), (404-635-7200)
* GEMA at Georgia Forward EOC, ENN (1308) OPX (6626), (229-723-4826)
* EARLY COUNTY, ENN(1308)
OPX (6622),(229-723-3577,3578,4826)
Time ____ .Name ____________
Acknowledged D T. __ Fill in the date and time on line 2 using the time that the ftrst state agency contact ATTEMPT was made u. __ P'IT and announce on the ENN "Please prepare to receive a Notification Of Unusual Event, BLUE initial notification message with acknowledgment", then slowly read the NOUE initial notification form over the ENN. Release the P'IT after reading two or three lines to allow individuals to respond. V. __ Have the agencies contacted above, acknowledge receipt of the message and ftll in the acknowledge checkbox above when they do. W. __ If any required agency could not be contacted on the ENN, then use numbers listed with each agency or in FNP-O-EIP-8.1 to contact them by any available means as soon as possible.
X Fax a copy of the previous page NOTIFICATION OF UNUSUAL EVENT BLUE VERBAL NOTIFICATION FORM to the State of Florida, EOF using speed dial #10 Y. __ Wait for the Fax report indicating the fax was received then verify the state of Florida has received the Fax by calling. (800-320-0519)
(850-413-9911) Page 80f8 Version 59.0 09/01108 15:32:53 FNP-0-EIP-9.0
* * * * *
* * * * * * * * * * *
* TABLEt REFERENCES Joseph M. Farley Nuclear Plant Emergency Plan FNP-0-RCP-25, Health Physics Activities During a Radiological Accident FNP-0-EIP-9.2, Emergency Classification FNP-0-EIP-29, Long Term Dose Assessment FNP-0-EIP-20, Chemistry and Environmental Support to the Emergency Plan FNP-0-M-007, Emergency Dose Calculation Method FNP-O-TCP-61.0, EMERGENCY ACTION LEVEL TECHNICAL BASIS NMP-EP-I09, Protective Action Recommendations FNP-O-M-Oll, Offsite Dose Calculation Manual EPA "Manual of Protective Action Guides and Protective Actions for Nuclear Incidents" NUREG-0654, "Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants" FNP-0-CCP-641, "Operation of the Plant Vent Stack Monitoring System" NT-86-0014, Gaseous Releases, Emergency Classifications NT 0543, Protective Action Recommendation Policy ALA 88-694, Westinghouse "Potential Radiological Impact of Steam Generator Tube Uncover" FNP-0-CCP-1300, Chemistry and Environmental Activities During a Radiological Accident SCS letter File: ENG 15 94-0466 Log: FP 94-0364, Containment Dose R-27 to DEI Conversion Page 1 of 1 Version 59.0 09/01/08 15:32:53 FNP-0-EIP-9.0 KMERGENCY FACILITY ACTIVATION Unusual Site Area General Event Alert Emergency Emergency Technical
* Activate#
Activate#
Activate Support Center Operations
* Activate#
Activate#
Activate Support Center Emergency
** Activate#
Activate#
Activate Operations Facility APC ** Activate#
Activate#
Activate Corporate Headquarters Emergency
** Activate#
Activate#
Activate News Center NOTE:
* No action, standby or activation at the discretion of the Emergency Director ** No action, standby or activation at the discretion of the Corporate Duty Manager # Activation will be to the extent deemed necessary by the Emergency Director and Corporate Duty Manager { Page 1 of 1 Version 59.0 09/01108 15:32:53 FNP-0-EIP-9.0 TABLE 3 CONSIDERATIONS FOR EMERGENCY CLASSIFICATION BASED ON SECURITY EVENTS IF THERE IS A POTENTIAL HAZARD TO THE SAFETY OF PERSONNEL DUE TO THE SECURITY EVENT THAT IS IN PROGRESS, THE PROVISIONS OF THE EIPs MAY HAVE TO BE MODIFIED TO ENSURE THAT PLANT PERSONNEL ARE PROTECTED.
CONSIDERATION SHOULD BE GIVEN TO THE SAFETY OF PERSONNEL WHO ARE ON SITE AND THOSE WHO WILL BE REPORTING TO THE SITE. THE FOLLOWING LIST DESCRIBES SOME OF THE ACTIONS THAT MIGHT BE DIFFERENT:
: 1. Do not delay declaring the emergency, some specific actions in the guidelines may have to be altered. 2. Contact security for recommendations to determine hazardous areas prior to taking any actions that would move people to different areas of the plant. 3. Ensure that control room or other supervisory personnel do not dispatch personnel to areas of the plant until it has been determined that those areas are safe. 4. If activating the plant emergency alarm (PEA) would put personnel at risk while proceeding to assembly areas, do not activate the alarm. In lieu of the PEA, consider making an appropriate announcement over the plant page with specific instructions such as to remain inside buildings, evacuate specific areas or other appropriate announcements based on security recommendations.
: 5. If having the TSC staff report to the plant site would put them at risk, consider a manual callout of a minimum staff with specific instructions identifying where to report in lieu of using the ERO Callout System to activate.
: 6. Consider use of alternate facilities for the TSC staff. 7. If the ERO Callout system is used to activate the TSC staff, consider using message number 2 to have the TSC staff report to the Emergency News Center. 8. After security reports that the security hazards have been eliminated, return to full implementation of the EIPs as appropriate.
Page 1 of 1 Version 59.0 
" (" 09/01108 15:32:53 FNP-0-EIP-9.0 TABLE 4 INFORMATION LIKELY TO BE REQUESTED BY THE NRC 1F AN EMERGENCY IS DECLARED (NRC INFORMATION NOTICE 98-08) 1. Is there any change to the classification of the event? If so, what is the reason? 2. What is the ongoing/imminent damage to the facility, including affected equipment and safety features?
: 3. Have toxic or radiological releases occurred or been projected, including changes in the release rate? If so, what is the projected onsite and offsite releases and what is the basis of assessment?
: 4. What are the health effect/consequences to onsite/offsite people? How many onsite/offsite people are/will be affected and to what extent? 5. Is the event under control? When was control established, or what is the planned action to bring the event under control? What is the mitigative action underway or planned? 6. 7. 8. 9. What onsite protective measures have been taken or planned? What offsite protective actions have been recommended to state/local officials?
What is the status of State/local/other Federal agencies' responses, if known? If applicable, what is the status of public information activities, such as alarm, broadcast, or press releases (regulatee/state/local/other federal agencies)?
Has a Joint Information Center (Emergency News Center) been activated?
Page 1 of 1 Version 59.0 
( 09/01/08 15:32:53 FNP-0-EIP-9.0 10 MILE EMERGENCY PLANNING ZONE The boxes in each quadrant and at the top of the drawing, represent the time in minutes that it would take to evacuate the zones in that quadrant during a WD (week day), WN (week night), WE (week end) and A W (adverse weather conditions).
The time includes a 15 minute allowance for notification.
Zones 2 Mile Zone A 10 Mile All Sectors 270-360 Quadrant, 100% Evacuation Times Zones WD WN WE 5 Mile 105 90 95 10 mile 115 100 105 180-270 Quadrant, 100% Evacuation Times Zones WD WN WE 5 Mile 100 95 95 10 mile 140 110 115 AW 110 120 AW 105 150 WD WN 95 80 140 115 Figure 1 Page 1 of 1 WE AW 90 95 115 150 000-090 Quadrant, 100% Evacuation Times Zones WD WN WE 5 Mile 105 95 100 10 mile 110 105 110 090-180 Quadrant, 100% Evacuation Times Zones WD WN WE 5 Mile 105 95 100 10 mile 110 100 105 AW 110 120 AW 110 115 Version 59.0 09/01108 15:32:53 FNP-0-EIP-9.0 EVENT FLOWPATH EVENT ASSESS PLANT CONDITIONS NO YES Implement YES Guideline 1 +------c General Emergency Actions YES Implement YES Guideline 2 Site Area Emergency Actions EIP-9.0 NO EIP-9.2 RUI or See Note 1 OFFSITE DOSE ASSESSMENT TSC Flow Path See Note 2 EIP-9.1 YES Manual Start 14-----1 EIP 9.1 or ___ .3 UseEIP9.3 RAI RMS limits l+---------------...3 NO NO YES YES Implement Guideline 3
Alert Actions YES Implement YES Guideline 4+--C NOUE Actions Check for exceeded NO NO L--____
* non-emergency
+-------1 notification EIP-S.O FIGURE 2 Note 1 If there is no MIDAS PC available then automated dose assessment per EIP-9.1 may be used with caution. EIP-9.1 automated dose assessment will not meet all long term dose assessment requirements.
Note 2 For long term dose assessment EIP 9.3 should be used in the TSC.1f there is no MIDAS PC available then automated dose assessment per EIP-9.1 maybe used with caution. EIP-9.1 automated dose assessment will not meet all long term dose assessment requirements.
Version 59.0 09/01/08 15:32:53 FNP-O-EIP-9.0 FIGURE 3 DELETED FIGURE 3 Version 59.0 09/01/08 15:32:53 FNP-0-EIP-9.0 FIGURE 4 _ __ MESSAGE# __ _
UPGRADE NOTIFICATION:
TIME, _____ ,DATE_ .... 'c-_'<.-_AUTHENTICATION
# N/A 3. SITE: FARLEY NUCLEAR PLANT 5. PROTECTIVE ACTION RECOMMENDATIONS CHANGES THE FOLLOWING EVACUATION ZONE RECOMMENDATIONS ARE THE CURRENT UPDATED EVACUATION ZONE RECOMMENDATIONS INCLUDING ANY EVACUATION ZONES THAT WERE PREVIOUSLY RECOMMENDED
--I liB II .. *
* II III , .' IB .. .. iii .. * .. .. .. ,'*,0, III p , *. : iii .... ti .. THE FOLLOWING SHELTERING ZONE RECOMMENDATIONS ARE THE CURRENT UPDATED SHELTERING ZONE RECOMMENDATIONS INCLUDING ANY SHELTERING ZONES THAT WERE PREVIOUSLY RECOMMENDED.
IF A SHELTERING ZONE RECOMMENDATION HAS BEEN CHANGED TO EVACUATION IT WILL NOT BE DISPLAYED.
THE FOLLOWING OTHER RECOMMENDATIONS FOR PROTECTIVE ACTIONS HAVE BEEN ADDED I&sect;OTHER -13. REMARKS: 17. APPROVED BY: F I II! I Title 0 Emergency Director o EOF Manager on this form must be correct for the notification to be considered correct at 00 1 for the first verbal message.
the ENN notification K. __ Line 13 If additional remarks are required write them on line 13. Consider listing the reason for the upgrade. L. __ The Emergency Director Must approve any PAR upgrade. The Emergency Director or the EOF Manager must sign the form. M. Within 15 minutes of PAR UPGRADE time, using the ENN contact the state and local agencies listed below. N. __ Verify the Southern LINC ENN Radio being used is turned on O. __ If the Southern LINC display does not show "WIDE AREA, FEP ENN" when group is pressed in step P, THEN perform the following:
* Press the button with the square until the top line is indicated, then press the arrow buttons until "WIDE AREA" is displayed, then press the button under OK. Press the button with the square until the second line is indicated then press the arrow buttons until "FEP ENN" is displayed, and then press the button under OK. P Press group pushbutton; verify display shows WIDE AREA, FEP ENN. Correct per above step if necessary.
Pickup handset or leave in cradle, press to talk (PTT), wait for the chirp and announce "This is name/title at Farley Nuclear Plant. Please obtain a PAR Upgrade initial notification form and monitor the ENN." Release the PTT. Page 1 of3 Version 59.0 09101108 15:32:53 FNP-0-EIP-9.0 FIGURE 4 Q. __ Contact one state and county agency listed in each of the four boxes below. Indicate the time of initial attempt to contact any Alabama agency. Circle agency actually contacted.
Indicate the name of the individual contacted.
Underlined phone numbers staffed 24 hours a day PTf and request one Alabama agency in the order listed below acknowledge manning of the ENN. State agency name and ask if they are on the line. Release the PTf after each request. ALABAMA State Agencies In preferred order
* Alabama Radiation Control at Montgomery EOC. ENN (1305), OPX (6628), (334-206-5391), (334-324-0076)
* AEMA ENN (1306), OPX(6619), (205-280-2312, 205-280-2310)
* Alabama Radiation Control at Alabama Forward EOC, ENN (1307), OPX 6621), (334-793-1565)
* HOUSTON COUNTY ENN (1307), OPX (6621), (334-794-9720, 793-9655, 677-4807, 4808) Time ___ --'Name ____________ .Acknowledged 0 Indicate the time of initial attempt to contact any Georgia agency. Circle agency actually contacted.
Indicate the name of the individual contacted.
Underlined phone numbers staffed 24 hours a day PTf and request one Georgia agency in the order listed below acknowledge manning of the ENN. State agency name and ask if they are on the line. Release the PTf after each request. GEORGIA State Agencies In preferred order
* GEMA at Atlanta EOC, ENN (1304), OPX (6629), (404-635-7200)
* GEMA at Georgia Forward EOC, ENN (1308) OPX (6626), (229-723-4826)
* EARLY COUNTY, ENN(1308)
OPX (6622),(229-723-3577, 3578, 4826) Time ____ .Name _____________ .Acknowledged 0 Indicate the time of initial attempt to contact Houston County. Indicate the name of the individual contacted.
Underlined phone numbers staffed 24 hours a day PTf and request Houston County acknowledge manning of the ENN. State agency name and ask if they are on the line. Release the PTT after each request. HOUSTON COUNTY
* HOUSTON COUNTY, ENN(1307), OPX (6621), (334-794-9720, 793-9655, 334-677-4807, 4808) Time ___ --'Name. _____________ .Acknowledged 0 Indicate the time of initial attempt to contact Early County. Indicate the name of the individual contacted.
Underlined phone numbers staffed 24 hours a day PTf and request Early County acknowledge manning of the ENN. State agency name and ask if they are on the line. Release the PTf after each request. EARLY COUNTY
* EARLY COUNTY, ENN(1308)
OPX (6622), (229-723-3577, 3578,4826)
Time. ____ .Name _____________ .Acknowledged 0 Page 2 of3 Version 59.0 09/01/08 15:32:53 FNP-0-EIP-9.0 FIGURE 4 T. __ Fill in the date and time on line 2 using the time that the ftrst state agency contact ATTEMPT was made 1J. __ PTT and announce on the ENN "Please prepare to receive a PAR UPGRADE notification message with acknowledgment", then slowly read the PAR UPGRADE notiftcation form over the ENN. Release the PTT after reading two or three lines to allow individuals to respond. V. __ Have the agencies contacted above, acknowledge receipt of the message and ftll in the acknowledge checkbox above when they do. W. __ If any required agency could not be contacted on the ENN, then use numbers listed with each agency or in FNP-O-EIP-S.l to contact them by any available means as soon as possible.
X __ Include the new PARs on the next follow-up message. Page 3 of 3 Version 59.0 09/01/08 15:32:53 FNP-0-EIP-9.0 FIGURE 5 1. For initial and upgrade declarations complete pages two and three of this figure for transmittal to the NRC. Instructions for completing this figure are located on pages four and five. 2. For initial and upgrade declarations notify NRC Headquarters.
Read pages two and three of this figure over the ENS to the NRCOC Immediately after State Notification and within one hour of Declaration.
If the NRC requests it, pages two and three can be faxed to the NRC Contact numbers for the NRC are listed below DENS (301-816-5100; 301-951-0550; 301-415-0550)
DCommercial (1-301-816-5100; 1-301-951-0550; 1-301-415-0550 Daterrime Person contacted date time Page 1 of 5 Version 59.0 09/01/08 15:32:53 FNP-0-EIP-9.0 FIGURE 5
* SIMILAR to NRC FORM 361 U.S. NUCLEAR REGULATORY COMMISSION OPERATIONS CENTER REACTOR PLANT EVENT NOTIFICATION WORKSHEET EN# NRC OPERATION TELEPHONE NUMBER: PRIMARY --301-816-5100, BACKUPS --[1st] 301-951-0550, [2nd] 301-415-0550 and [3rd] 301-415-0553 NOTIFICATION TIME FACILITY OR ORGANIZATION UNIT NAME OF CALLER CALL BACK # ENS 700-221-0807 Commercial
# 334-899-5156 FARLEY NUCLEAR PLANT EVENT TIME & ZONE EVENT DATE POWER/MODE BEFORE POWER/MODE AFTER Central time EVENT CLASSIFICATIONS 1-Hr. Non-Emergency 10 CFR 50.72(b)(1) (v)(A) Safe SID Capability AINA GENERAL EMERGENCY GEN/AAEC TS Deviation ADEV (v)(B) RHR Capability AINB SITE AREA EMERGENCY SITlAAEC 4-Hr. Non-Emergency 10 CFR 50.72(b)(2) (v)(C) Control of Rad Release AINC ALERT ALElAAEC (i) TS Required SID ASHU (v)(D) Accident Mitigatio AIND UNUSUAL EVENT UNU/AAEC (iv)(A) ECCS Discharge to RCS ACCS (xii) Offsite Medical AMED 50.72 NON*EMERGENCY (see next columns) (iv)(B) RPS Actuation (scram) ARPS (xiii) Loss CommlAsmtlResp ACOM PHYSICAL SECURITY (73.71) DDDD (xi) Off site Notification APRE GO-Day Optional 10 CFR 50.73(a)(1)
MATERIAUEXPOSURE B??? 8-Hr. Non-Emergency 10 CFR 50.72(b)(3)
Invalid Specified System AINV Actuation FITNESS FOR DUTY HFIT (ii)(A) Degraded Condition ADEG Other Unspecified Requirement (Identlfy)
OTHER UNSPECIFIED REQMT (see last column) (ii)(B) Unanalyzed Condition AUNA I NONR INFORMATION ONLY NINF iv)(A) Specified System Actuation AESF NONR DESCRIPTION Include: Systems affected.
actuations and their initiating signals. causes. effect of event on plant, actions taken or planned. etc. (Continue on back) NOTIFICA TrONS YES NO WILL BE ANYTHING UNUSUAL OR o YES (Explain above) o NO NRC RESIDENT NOT UNDERSTOOD?
STATE(s) DID ALL SYSTEMS 0 YES ONO (Explain above) LOCAL FUNCTION AS REQUIRED?
OTHER GOV AGENCIES MODE OF OPERATION ESTIMATED INFO ON BACK .M:EDIAIPRESS RELEASE UNTIL CORRECTED:
RESTART DATE: YES 0 NO Page 2 of 5 Version 59.0 09/01108 15:32:53 FNP-0-EIP-9.0 FIGURE 5 ADDITIONAL INFORMATION PAGE20F2 tADIOLOGICAL RELEASES:
CHECK OR FILL IN APPLICABLE ITEMS (specific details/explanations should be covered in event description)
LIQUID RELEASE I I GASEOUS RELEASE UNPLANNED RELEASE I PLANNED RELEASE I ONGOING I I TERMINATED MONITORED I I UN MONITORED OFFSITE RELEASE I T. S. EXCEEDED I RMALARMS I I AREAS EVACUATED PERSONNEL EXPOSED OR CONTAMINATED OFFSITE PROTECTIVE ACTIONS RECOMMENDED
'State release path in description Release Rate (CI/sec) %T.S. LIMIT HOOGUIDE Total Activity (CI) %T.S. LIMIT HOOGUIDE Noble Gas 0.1 Ci/sec 1000 Ci Iodine 10uCi/sec 0.01 Ci Particulate 1 uCi/sec ImCi Liquid (excluding tritium and 10uCi/min 0.1 Ci dissolved noble gases) Liquid (tritium) 0.2 Ci/min SCi Total Activitv PLANT STACK CONDENSER/AIR EJECTOR MAIN STEAM LINE SGBLOWDOWN OTHER RAD MONITOR READINGS ALARM SETPOINTS
% T. S. LIMIT (if applicable)
RCS OR SG TUBE LEAKS: CHECK OR FILL IN APPLICABLE ITEMS: (specific details/explanations should be covered In event description)
LOCATION OF THE LEAK (e.g., SG #, valve, pipe, etc.) LEAK RATE UNITS: gpm/gpd T.S. LIMITS SUDDEN OR LONG-TERM DEVELOPMENT LEAK START DATE TIME COOLANT ACTIVITY PRIMARY SECONDARY AND UNITS: ( " '.1ST OF SAFETY RELATED EQUIPMENT NOT OPERATIONAL EVENT DESCRIPTION (Continued from front) Page 3 of 5 Version 59.0 09/01/08 15:32:53 FNP-0-EIP-9.0 FIGURE 5 INSTRUCTIONS FOR COMPLETING FIGURE 1 NRC REACTOR PLANT EVENT NOTIFICATION WORKSHEET FNP's official notification to the NRC of a declared emergency will be done using this Figure. The NRC Event Notification Worksheet in this figure is similar to the one that the NRC has at the NRCOC. During a declared emergency they will be asking questions from this worksheet.
A copy of this figure may be sent to the NRC by Fax if the communicator desires. The general instructions for completing this form are listed below: 1. Not all of the form is required to be completed; only the information that is available at the time is required to be completed.
The NRC should be informed that this information is not available at the current time. Inform the NRC that the missing information will be provided when it is available.
FORM 361 Page One 2. On the top line of page one the EN# is the event number assigned by the NRC, request this number from the NRC. 3. NOTIFICATION TIME is the time that the official notification using this figure was made to the NRC. 4. Fill in appropriate UNIT number or both as applicable.
: 5. The NAME OF CALLER is the person talking to the NRC at the time that the information on this form is read or faxed to the NRC 6. CALL BACK phone numbers are already filled in unless there are different numbers that you want the NRC to use. 7. EVENT DATE and TIME is the declaration time of the current event. 8. POWERIMODE BEFORE and AFTER. The before information is the power and mode just prior to the current declaration.
The after information is the current power and mode 9. Under EVENT CLASSIFICATION the block for the declared emergency should be checked. Other blocks in that section may be checked if directed by the Emergency Director or EOF Manager. 10. The DESCRIPTION should be similar to the description provided in Figure 6. 11. For NOTIFICATIONS.
complete the information requested.
Refer to the facility management for clarification if the answer is not readily known. 12. FOR ANYTHING UNUSUAL OR NOT UNDERSTOOD indicate plant response that was not as expected and there is no explanation for it. If YES is checked provide explanation in description section. 13. For DID ALL SYSTEMS FUNCTION AS REOUIRED check no if safety systems or systems that are relevant to the event did not perform required function.
If NO is checked provide explanation in description section. 14. MODE OF OPERATION UNTIL CORRECTED:
-fill in TS mode number. 15. ESTIMATED RESTART DATE leave blank unless a firm date is known. 16. ADDITIONAL INFORMATION ON BACK should be checked NO unless the description is too large to fit on page 1 description section Page 4 of 5 Version 59.0 
( 09/01/08 15:32:53 FNP-O-EIP-9.0 FIGURE 5 Page Two 16. RADIOLOGICAL RELEASES check the applicable boxes and complete the data as appropriate only if an emergency radiological release is in progress that by itself would require any emergency classification.
* LIQUID RELEASE 1 GASEOUS RELEASE -one or both based on releases in progress
* UNPLANNED RELEASE or PLANNED RELEASE -check only one based on what caused the release
* ONGOING or TERMINATED
-check ongoing unless all emergency releases are terminated.
* MONITORED or UNMONITORED
-Check monitored unless the release is known not to be monitored by one of the effluent monitors.
* OFFSITE RELEASE and T. S. EXCEEDED -Check both boxes if the release by itself would require any emergency classification bases on ODCM or EDCM.
* RM ALARMS -Check this box if any alarm is in that would cause ARDA to activate.
* AREAS EVACUATED
-Check this box if on site areas have been evacuated due to a radiation problem.
* PERSONNEL EXPOSED OR CONTAMINATED
-Check this box if the exposure or contamination is above 10 CFR 20 limits.
* OFFSITE PROTECTIVE ACTIONS RECOMMENDED
-Check this box if PARs have been recommended and transmitted to the states.
* Complete the release rate information if it has already been calculated using EDCM or ODCM calculations.
It is not necessary to perform calculations just to complete this form.
* From the ODCM calculations request that ChemistrylEnvironmental staff calculate the % of TS. This can be accomplished using the ARDA ODCM page. Divide the "Previous Hour" total iodine and noble gas values by the NOUE limits listed on the page.
* The HOO guide is information that the Headquarters Operations Officer (HOO) would use. It is not for FNPuse.
* Complete the RADIATION MONITOR READINGS for those monitors that are in alarm that would cause the ARDA to actuate. Refer to EIP-9.l.
* Complete the ALARM SETPOINTS for any radiation monitor reading that is entered. Refer to EIP-9.l.
* TS limits for rad monitors in alarm are not applicable.
: 17. ReS OR SG TUBE LEAKS Fill in the appropriate data if there is a leak or rupture in progress that exceeds technical specification limits. Page 5 of 5 Version 59.0 09/01/08 15:32:53 FNP-0-EIP-9.0 FIGURE 6 EMERGENCY NOTIFICATION FORM l. __ Complete page two (or a similar form)of this form as a follow-up notification.
* All initial and upgrade emergency classifications should be performed using the initial verbal notification form in the back of Guidelines 1 through 4.
* Follow-up messages are required to be sent at least once per hour or whenever plant conditions change that could affect the emergency condition.
* Instructions for completing this form are included starting on page 4 of this figure, if required.
* Number each verbal initial and follow-up messages sequentially starting at 001 for the first verbal message.
* Determine the stability class from either dose assessment program, from the EP _WEATHER program if available or from the table below. ilT (200' elev. temp, OF -35' elev. temp, OF) Stability Class <-1.74 A -1.74 to <-1.56 B -1.56 to <-1.38 C -1.38 to <-0.46 D -0.46 to < 1.38 E 1.38 to 3.60 F >3.60 G 2. __ Fill in line 2 Notification time/date and line 17 notified by (person doing the faxing) 3. __ Fax page two to state, local and company agencies using the speed dial button determined in page 3. 4. __ Verify that the following agencies received the fax using the ENN in the group mode or numbers listed below. 4.1._Verify the Southern LINC ENN Radio being used is turned on 4.2._If the Southern LINC display does not show "WIDE AREA, FEP ENN" when group is pressed perfrm the following:
4.2.1. __ Press the button with the square until the top line is indicated, then press the arrow buttons until "WIDE AREA" is displayed, then press the button under OK. Press the button with the square until the second line is indicated then press the arrow buttons until "FEP ENN" is displayed, then press the button under OK. 4.3 __ Press group pushbutton, verify display shows WIDE AREA, FEP ENN. Correct per 3.2.1 if necessary.
Figure 6 Request each agency individually Person Contacted DatelTime
________ .Alabama Radiation Control at Montgomery EOC ENN (1305), OPX (6628), phone (334-206-5391)
AL Radiation Control at Alabama FEOClHouston Co --------ENN(1307), OPX (6621), (334-794-9720, 793-9655, 334-677-4807,4808)
________ GEMA at Atlanta EOC ENN (1304), OPX (6629), (404-635-7200)
________ GEMA at Georgia FEOClEarly County ENN(1308)
OPX (6622)(229-723-3577, 3578,4826)
_______ -----'AEMA at Clanton EOC ENN (1306) _______ -----'FDEM at Tallahassee (Not on the ENN) (800-320-0519)
(850-413-9911) ________ TSCIEOF page 1 of 6 Version 59.0 
( 09/01108 15:32:53 FNP-0-EIP-9.0 Southern Nuclear Emergency Notification Form FIGURE 6 1. DRILL AACTUAL EVENT MESSAGE # __ _ 2. INITIAL WOLLOW-UP NOTIFICATION:
TIME _____ DATE_....I.I_
..... Ie-_AUTHENTICATION
# N/A (334) 814-4662.
814-4663 3. SITE: FARLEY NUCLEAR PLANT Confirmation Phone # 334 794-0800 899-5156 4. EMERGENCY CLASSIFICATION: UNUSUAL EVENT I&sect; ALERT 19 SITE AREA EMERGENCY IQI GENERAL EMERGENCY BASED ON EAL # ____ _ EAL DESCRIPTION:
__________________
_ 5. PROTECTIVE ACTION RECOMMENDATIONS: NONE
&sect;SHELTER ________________________________________________
__ IQI Advise Remainder of EPZ to Monitor Local RadiolTV Stationsl TARs for Additional Information and CONSIDER THE USE OF KI (POTASSIUM IODIDE) IN ACCORDANCE WITH STATE PLANS AND POLICY.
: 6. EMERGENCY RELEASE: 7. RELEASE SIGNIFICANCE:
: 8. EVENT PROGNOSIS:
: 9. METEOROLOGICAL DATA: 35 foot elevation preferred I&sect; Is Occurring Not applicable I&sect; Within normal operating limits Improving Stable Wind Direction from _____ degrees Precipitation
____ _ 19 Has Occurred 19 Above normal operating limits &sect; Degrading Wind Speed mph IQI Under evaluation Stability Class I&sect; 19 IQI I&sect; lEI IQ] 10. DECLARATION I&sect;TERMINATION Time _____________
Date ____ 1 __ 1 ____ _ 11. AFFECTED UNIT(S): [] I[] 12. UNIT STATUS: (Unaffected Unites) Status Not Required for U1 ____ % Power Shutdown at Time _______ Date _1 ____ 1 __ I&sect; U2 ____ % Power Shutdown at Time Date _1 ____ 1 __ Initial Notifications) 3 13.REMARKS:
________________________________________________________________________
___ FOLLOW-UP INFORMATION (Lines 14 through 16 Not Required for Initial Notifications)
EMERGENCY RELEASE DATA. NOT REQUIRED IF LINE 6 A IS SELECTED.
: 14. RELEASE CHARACTERIZATION:
TYPE: Elevated I&sect; Mixed 19 Ground UNITS: Ci I&sect; Ci/sec 19 J,lCi/sec MAGNITUDE:
Noble Gases: ________ lodines: _________
Particulates:
________ Other: _____ _ FORM: Airborne Start Time ________ Date _1 ____ I __ Stop Time _______ Date _1 ____ 1 __ I&sect; Liquid Start Time ________ Date _1 ____ I __ Stop Time _______ Date _1 ____ 1 __ 15. PROJECTION PARAMETERS:
Projection period: ___ Hours Estimated Release Duration ____ Hours Projection performed:
Time _____ Date _1 ____ 1__ Accident Type: ________ _ 16. PROJECTED DOSE: DISTANCE TEDE (mrem) Adult Thyroid CDE (mrem) 17. APPROVED BY: NOTIFIED Site boundary 2 Miles 5 Miles 10 Miles RECEIVED Title D Emergency Director D EOF Manager BY: __________
__ BY: __________________
__ Figure 6 page 2 of6 Time ___ Date_'_' ___ Time Date_I_I __ Version 59.0 
( 09/01/08 15:32:53 FNP-0-EIP-9.0 TELECOPY GROUP DIAL NUMBERS Telecopy (fax) the follow-up Emergency Notification Form (Fig. 6 page 2) to all of the locations using the dial numbers listed on the below flow chart. When the activity report is received retransmit the form to clny location that did not receive the form using the individual speed dial numbers listed below. Verify that the form has been received at all locations using page 1 of this figure. START NO NO NO Use rou dial number 25 on both the AI. and Ga. fax AL. FAX MACHINE GA. FAX MACHINE group dial number 25 ARC at Montgomery EOC ARC at AI. FEOC AEMA at Clanton EOC EOF group dial number 25 GEMA at Atlanta EOC GEMA at GA FEOC FDEM at Tallahassee DO NOT USE TELECOPY Read the message over the ENN or commercial telephone Use group dial number 28 on the operable fax machine ARC at Montgomery EOC ARC at Alabama FEOC GEMA at Atlanta EOC GEMA at Georgia FEOC AEMA at Clanton EOC FDEM at Tallahassee EOF FAX ENN IND PHONE Refer to FNP-O-EIP-8.1 or FIG. 6 for OPX/commercial numbers. SPEED LOCATION DIAL NUMBER Alabama Office of Radiation Control At Montgomery EOC 1 11 Alabama Office of Radiation Control At Alabama Forward EOC 3 13 Alabama Emergency Management Agency at Clanton EOC 7 51 FNP EOF (from opposite location) 5 63 Georgia Emergency Management Agency at Atlanta EOC 2 21 Georgia Emergency Management Agency at Georgia Forward EOC 4 22 Florida Department of Emergency Management at Tallahassee 8 none Figure 6 page 3 of6 Version 59.0 
( 09/01108 15:32:53 FNP-0-EIP-9.0 EMERGENCY NOTIFICATION FORM GUIDANCE Emergency Notification Form (ENF) Guidance is provided below. The guidance is provided for filling out the ENF (FIGURE 6, page 2). This attachment can be used as guidance when filling out the form or for training.
Line 1
* Mark A or B. Except for actual emergencies A should be checked in training and for drills/exercises.
* Number each verbal initial and follow-up messages sequentially starting at 001 for the first verbal message. Line 2
* B 1 Follow-Up is already marked. All initial notifications should be made using the pages in the guidelines.
* Notification time and date should be completed by the individual doing the faxing when the form is faxed. Line 3
* No action required.
Extensions 4662 and 4663 ring at the unit 2 SS desk and in the TSC at the EDITSC Manager's desk. Line 4
* Check A, B, C or D (only one) as appropriate.
Check no boxes if this is a termination.
* Enter the EAL number as listed in the guidelines.
Example RG 1, SA2 etc.
* Enter the description of the EAL as listed in Initiating Condition of EIP-9.2 of the Hot or Cold Matrix. Line 5
* Refer to Step L of the appropriate FNP-0-EIP-9.0 Guideline and NMP-EP-109 to determine appropriate Protective Action Recommendations (PARs).
* If there are no protective action recommendations, mark box A and proceed to step 6.
* For a General Emergency boxes B or C should always be marked and the appropriate zones for evacuation or sheltering should be filled in.
* For a General Emergency boxesD should always be marked
* Mark and complete box E only if there are additional PARs such as PAR 4 from NMP-EP-109 Line 6
* An emergency release is occurring if an effluent monitor has increased by a factor of 10 over and above normal operating levels OR is in alarm. The effluent monitors are R-18, R-23B, R-15, R-14, R-22 R-60 (A,B,C,D)and R-29B(NG)
* Mark box A if no emergency release is in progress or has occurred
* Mark box B if an emergency release is in progress
* Mark box C if an emergency release has occurred, but is currently stopped Line 7
* Release Significance.
Mark box A, B, C or D. Normal limits are being exceeded if an effluent monitor listed in line 6 above is in alarm
* Mark box A if 6A is marked j Mark box B if 6B or 6C is marked and NO effluent monitor is or has been in alarm.
* Mark box C if 6B or 6C is marked and ANY effluent monitor is or has been in alarm.
* Mark box D if 6B or 6C is marked and it can not be determined if an effluent monitor is or has been in alarm. Figure 6 page 4 of6 Version 59.0 09101108 15:32:53 FNP-0-EIP-9.0 Line 8
* Check A, B or C.
* A should be checked if mitigation efforts appear successful, progressing toward termination/recovery.
B should be checked if escalation to a higher classification is unlikely based on current conditions.
* C should be checked if escalation to a higher emergency classification or PAR change is likely. Line 9
* Fill in the meteorological data required (35 foot elevation preferred).
Note that line 9 meteorological data must be the same data that was used in performing the dose assessment calculation information provided on lines 14, 15 and 16.
* When possible use 15 minute average data, available from the NR ERDS MIDAS page or the EP _WEATHER program
* If stability class is not available it can be calculated from delta temperature from the below table Line 10 dT (200' elev. temp, OF -35' elev. temp, OF) <-1.74 -1.74 to <-1.56 -1.56 to <-1.38 -1.38 to <-0.46 -0.46 to < 1.38 1.38 t 0 3.60 >3.60 Stability Class A B C D E F G
* Check A or B. Time is for the declaration checked in line 4 or the time of termination..
Termination should only be done per FNP-0-EIP-28.0.
If this is a termination, go to line 17. Line 11
* Mark the unit that is involved with the emergency declaration, or all if both units are affected.
Line 12
* Fill in the per cent power or the time of shutdown for both units even if one is not involved with the event Line 13
* Provide a brief, concise summary of plant conditions that requires the classification and other pertinent information.
Avoid the use of acronyms and jargon.
* If additional information that will not fit in the space provided continue the information on Figure 7 and fax with Figure 6 sheet 2 Line 14 -Not required if 6A (Emergency Release NONE) is marked.
* TYPE -Box C is pre marked. Our dose assessment models always assume a ground release.
* UNITS -Box C is premarked.
The ARDA and MIDAS programs provide release rate in f.,lCuries/Sec.
* MAGNITUDE
-fill in the values using the output from MIDAS or ARDA
* FORM -Mark A or B as appropriate and fill in the times for start and stop of release as appropriate.
Line 15 -Not required if 6A (Emergency Release NONE) is marked.
* Fill in 4 hours for the Projection time and the Estimated Release Duration.
If a better time is known for the release duration it should be used but only if it is used in the dose assessment as well.
* Fill in the time that the dose projection was performed from the MIDAS or the ARDA printout.
* Complete the Accident Type from the MIDAS printout if Midas is being used for dose assessment Figure 6 page 5 of6 Version 59.0 09/01108 15:32:53 Line 16 -Not required if 6A (Emergency Release NONE) is marked.
* Fill in the values using the output from MIDAS or ARDA Line 17
* The Emergency Director or EOF Manager must sign the form with time and date.
* The time and date are the time that the EDIEOF Manager actually signs the form. Figure 6 page 6 of6 FNP-0-EIP-9.0 Version 59.0 
( 09/01108 15:32:53 EMERGENCY NOTIFICATION CONTINUATION SHEET 13. (Continued)
Additional Comments:
FNP-0-EIP-9.0 Message Number _____ _ Figure 7 Version 59.0 Southern Nuclear Operating Company SOUTHERN A Emergency NMP-EP-109 COMPANY Implementing Protective Action Recommendations Version 2.0 Elurgy ttl Sn-Pe :tD"r w.u Procedure Page 1 of 18 Procedure Owner: __
..wH!.:" .
__ (Print: Name / Title / Site) Approved By: _____
___ __ (Peer Team Champion/Procedure Owner's Signature
/ Date) Effective Dates: 05/0212008 Corporate 05/0212008 FNP 05/02/2008 HNP 05/0212008 VEGP The individuals listed below are the members of the Peer Team responsible for writing and maintaining this procedure.
Corporate Plant Farley Plant Hatch Plant Vogtle Charles K. Brown Chris E. Boone Clint S. Hartfield Robert J. Vanderbye Rachelle G. Reddick Lawrence E. Mayo PROCEDURE USAGE REQUIREMENTS Procedure must be open and readily available Continuous at the work location.
Follow procedure step by Use: step unless otherwise directed by the procedure.
Procedure or applicable section(s) available at Reference Use: the work location for ready reference by person performing steps. Information Available on site for reference as needed. Use: Printed: 9/112008 SECTIONS ALL 
( Southern Nuclear Operating Company SOUTHERN A.. Emergency NMP-EP-109 COMPANY Implementing Protective Action Recommendations Version 2.0 EfI.{!1'gy to S""t Procedure Page 2 of 18 Revision Description Version Number 1.0 2.0 Printed: 9/1/2008 Revision Descri tion Implements a common fleet procedure for developing offsite Protective Action Recommendations (PARs). The procedure incorporates the revised guidance from RIS 2004-13, RIS 2004-13, Supplement 1 and RIS 2005-08. This procedure change adds separate definitions for "uncontrolled release" and "controlled release", incorporates procedural recommendations for completing the emergency notification forms, and adds human factorin to the PAR Worksheet 1, based on user feedback.
Southern Nuclear Operating Company SOUTHERN A Emergency NMP-EP-109 Implementing Protective Action Recommendations Version 2.0 COMPANY Procedure Page 3 of 18 Ennn lh'r WfJ,.&#xa3;r 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: 9/112008 Southern Nuclear Operating Company SOUTHERN A Emergency NMP-EP-109 Implementing Protective Action Recommendations Version 2.0 COMPANY Procedure Page 4 of 18 Ene-rnID&rw Y.,..,.WO,.Lr 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 (PAD) 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 site-specific and 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 Licensee's Range of Protective Action Recommendations", August 2, 2004 3.8 NRC RIS 2004-13, Supplement 1, "Consideration of Sheltering in Licensee's Range of Protective Action Recommendations, Dated Aug. 2004", March 1 0, 2005 3.9 NRC RIS 2005-08, Endorsement of NEI Guidance "Range of Protective Actions for Nuclear Power Plant Incidents", June 6, 2005 Printed: 9/112008 Southern Nuclear Operating Company SOUTHERN A Emergency NMP-EP-109 Implementing Protective Action Recommendations Version 2.0 COMPANY Procedure Page 5 of 18 Eturn If) $4rfle 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. (VCMT# 1985304906) 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: 9/112008 Southern Nuclear Operating Company SOUTHERN A Emergency NMP-EP-109 Implementing Protective Action Recommendations Version 2.0 COMPANY Procedure Page 6 of 18 &wntD $fflIe lWt"Wf,r.t.r 5.0 RESPONSIBILITIES 5.1 The Emergency Director (ED) has the non-delegable responsibility for approving PARs (VCMT#1985304893).
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 Control Room, TSC or EOF staffs as directed by the ED. 6.0 PRECAUTIONS AND LlMITIATIONS 6.1 Evacuation and Shelter Recommendations Printed: 9/112008 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.
Southern Nuclear Operating Company SOUTHERN A Emergency NMP-EP-109 Implementing Protective Action Recommendations Version 2.0 COMPANY Procedure Page 7 of 18 E.urrt .. _ Yow,""'""," 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 Printed: 911/2008 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.
Southern Nuclear Operating Company SOUTHERN A Emergency NMP-EP-109 Implementing Protective Action Recommendations Version 2.0 COMPANY Procedure Page 8 of 18 Efte,-,ytoS."rIe Y .. rWfwllr 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 MUTUAL Y 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. (VCMT# 1986309134) 6.5.4 When available, actual sample data from monitored or unmonitored release pOints should be utilized in conjunction with other dose assessment and projection methods to validate calculated PARs and to determine whether the plant based protective actions are adequate.
6.5.5 VEGP and FNP off-site dose rates may be significantly higher (up to 10 times) due to volatilization of iodine if a steam generator (SG) water level falls below the break point during a SG tube rupture 7.0 PROCESS DESCRIPTION Guidance is provided in the form of attachments.
Attachment 1, Action Checklist for Off-Site PAR Development", Attachment 2, "Farley Site Specific Data Sheets", Attachment 3, "Hatch Site Specific Data Sheets", Attachment 4 "Vogtle Site Specific Data Sheets", and Attachment 5 "PAR Worksheet" direct the initial and supplemental actions. 8.0 RECORDS Records generated during actual emergencies will be maintained as QA records in accordance with applicable administrative procedure.
9.0 COMMITMENTS Farley -None Hatch -1989301429, 1990303261, 1990303410 Vogtle -1985304693, 1985304906, 1986309134 Printed: 9/1/2008 
( Southern Nuclear Operating Company SOUTHERN A Emergency NMP-EP-109 Implementing Protective Action Recommendations Version 2.0 COMPANY Procedure Page 9 of 18 Enern to
}Qllr w.,,/d.
* Continuing Activity Attachment 1 (Page 1 of 3) Action Checkl ist for PAR Development NOTE: ONLY THE MUTUAL Y 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 CONSERVATIVE.
IN SUCH EVENTS, THE ED SHOULD USE JUDGMENT AS APPROPRIATE.
A. INITIAL ACTIONS Please Check 1.
* 2.
* 3. 4. 5. 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. Determine General Emergency PARs using the Attachment 1 Flowchart.
* PAR 1 -Shelter to 2 miles and 5 mile downwind zones
* PAR 2 -Evacuate to 2 miles and 5 mile downwind zones
* PAR 3 -Evacuate to 5 miles and 10 mile downwind zones
* PAR 4 -Guidance for PARs Beyond the 10 Mile EPZ CAUTION -PAR Revisions must include previous PARs D D For PAR 1, 2, and 3, determine the affected zones using Site specific Table 1. D 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 chan e in conditions.
Communicate developed PARs to the ED for review and approval.
NOTE: Once PARs are developed they should be communicated to appropriate agencies as soon as possible. (The expectation for communication is 15 minutes after development, as directed by position s ecific instructions.
Communicate ED approved PARs to offsite agencies using appropriate procedural guidance.
On the ENN Form ensure that the following PAR information is selected:
* Select block 5.B and record the "Evacuate" zones OR select block 5.C and record the "Shelter" zones
* Select block 5.D * !.E PAR 4 selected THEN additionally select block 5.E "Other" and provide "Affected Sectors" and "To Miles". D D Printed: 9/112008 
( Southern Nuclear Operating Company SOUTHERN A Emergency NMP-EP-109 Implementing Protective Action Recommendations Version 2.0 COMPANY Procedure Page 10 of 18 En.e,," to Strtle Ynr
* Continuing Activity Attachment 1 (Page 2 of 3) B. 1.
* 2.
* 3.
* 4.
* Action Checklist for PAR Development (Cont) SUPPLEMENTAL ACTIONS Please Check Continue assessment actions applying applicable Precautions
& limitations.
IF a release is in progress THEN it is appropriate to dispatch Field Monitoring Teams (FMT) to downwind and adjacent areas as soon as possible.
FMT data should be used to validate calculated exposure rates by comparison with actual field exposure rates to ensure issued PARs remain conservative.
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 anddose assessment calculations indicate a possible need to issue PARs beyond 10 miles, THEN it is appropriate to perform dose assessment calculations to verify calculation assumptions and accuracy prior to issuing PARs beyond 10 miles.
* Use any available FMT readings, I F 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. D D D IF conditions requiring PAR 1 entry are eliminated or dose projections D 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 D 6. 7. assessment results should be used to refine (but not reduce) protective action recommendations after adequate data becomes available.
Utilize real time meteorological and effluent radiation monitor readings in D 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. Dose projections are NOT required to support the decision process in development of the plant condition based PARs utilizing the PAR flowchart if no D 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: 911/2008 SOUTHERN A COMPANY &I toSt.rfle y .. ,.WiI'i4r NO
* CONTINUE ASSESSMENT Return to START PAR 2 EVACUATE o -2 mile radius And downwind to 5 miles Advise Remainder of EPZ to Monitor Local RadioffV Stations!
TARs for Additional Information Consider the use of KI in accordance with State plans and policy Refer to site specific Table 1 or computer program for affected zones CONTINUE ASSESSMENT Return to START Printed: 9/112008 NO-"NO-Protective Action Recommendations NO NO YES PAR 4 Evaluate the Need for PARs Beyond 1 0 Miles -Refer to Table 2 YES. YES. . YES .. YES" NMp*EP-109 Version 2.0 Pa e 11 of 18 Attachment 1, Flowchart (Page 3 of 3) PARt SHELTER o -2 mile radius And downwind to 5 miles Advise Remainder of EPZ to Monitor Local RadiotrV Stations!
TARs for Additional Information Consider the use of KI in accordance with State plans and policy Refer to site specific Table 1 or computer program for affected zones CONTINUE ASSESSMENT Return to START PAR 3 EVACUATE o -5 mile radius And downwind to 10 miles Advise Remainder of EPZ to Monitor Local RadioffV Stations!
TARs for Additional Information Consider the use of KI in accordance with State plans and policy Refer to site specific Table 1 or computer program for affected zones *PAGs
* 1 REMTEDEor
* 5 REM Thyroid CDE Southern Nuclear Operating Company SOUTHERN A Emergency Implementing Protective Action Recommendations COMPANY Procedure E'MT'rI ,.$,tw HrUI'W#1'/J.'" PLANT FARLEY NMP-EP-109 Version 2.0 Page 12 of 18 Attachment 2 Table 1 AFFECTED ZONES FOR PROTECTIVE ACTION RECOMMENDATIONS WIND DIRECTION FROM (ttAfU_.lit\
NE >34-56 ENE >56-79 E >79-101 Printed: 9/112008 PAR 1 and 2 AFFECTED ZONES PAR 3 Southern Nuclear Operating Company SOUTHERN A. Emergency Implementing Protective Action Recommendations COMPANY Procedure Emt'V1l/o lOur PLANT FARLEY GUIDANCE FOR PARS BEYOND THE 10 MILE EPZ NMP-EP-109 Version 2.0 Page 13 of 18 Attachment 2 Table 2 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) _____________
Affected
.. ,s 3. Recommend Evacuation from 10 miles to the Evacuation Distance Affected Sectors (determined in step 2). 4. Check Line 5, Item E -Other on the Emergency I\ln,tifi"",tin sectors and distance range in miles for Evacuation.
p Printed: 91112008 1) for the Southern Nuclear Operating SOUTHERN A Emergency Implementing Protective Action Recommendations COMPANY Procedure PLANT HATCH NMP-EP-109 Version 2.0 Pace 14 of 18 Attachment 3 Table 1 AFFECTED ZONES FOR PROTECTIVE ACTION RECOMMENDATIONS PAR 1 and 2 PAR 3 N >349-11 >11 -34 N >34-56 ENE >56-79 K10 L10 NNW >326 -349 Printed: 9/112008 Southern Nuclear Operating Company SOUTHERN A Emergency Implementing Protective Action Recommendations COMPANY Procedure E7m'F1Ile$ern YONrWilr/tr PLANT HATCH GUIDANCE FOR PARS BEYOND THE 10 MILE EPZ NMP-EP-109 Version 2.0 Page 15 of 18 Attachment 3 Table 2 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
: 2. Determine the affected sectors for the current 15 minute average (From) 3. Recommend Evacuation from 10 miles to the Evacuation Affected Sectors (determined in step 2). 4. Check Line 5, Item E -Other on the Emergency Nn'tifir'gt.i.diiilIlIIIIi sectors and distance range in miles for Evacuation.
p Printed: 91112008 
( Southern Nuclear ODerating Company SOUTHERN A Emergency Implementing Protective Action Recommendations COMPANY Procedure
&#xa3;mrrf t.Strw Y."W-t'Itr PLANT VOGTLE NMP-EP-109 Version 2.0 Paae 16 of 18 Attachment 4 Table 1 AFFECTED ZONES FOR PROTECTIVE ACTION RECOMMENDATIONS
>349-11 SRSt02 Miles NNE >11-34 SRS to 2 Miles N >34-56 ENE >56-79 >79-101 SRS to 5 Miles SRS t02 Miles Printed: 9/112008 
( " Southern Nuclear Operating Company SOUTHERN A Emergency Implementing Protective Action Recommendations COMPANY Procedure E1UrnI.tJS,N/tIYoul'W4JrIJ" PLANT VOGTLE GUIDANCE FOR PARS BEYOND THE 10 MILE EPZ NMP-EP-109 Version 2.0 Page 17 of 18 Attachment 4 Table 2 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
: 2. Determine the affected sectors for the current 15 minute average (From) 3. Recommend Evacuation from 1 0 miles to the Evacuation Distance (calcu Affected Sectors (determined in step 2). 4. Check Line 5, Item E -Other on the Emergency
"-."1titi,.",ti,,,., sectors and distance range in miles for Evacuation
.. p Printed: 9/1/2008 Southern Nuclear Operating Company SOUTHERN A Emergency Implementing COMPANY Procedure EmrnllfJSerwYONI'Wiwh/'" INSTRUCTIONS:
Protective Action Recommendations PAR WORKSHEET NMP-EP-109 Version 2.0 Page 18 of 18 Attachment 5 Figure 1 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) (SWR) OR ground level release (PWR). 3. Use the applicable "Site Specific" PAR table (Table 1 or 2) to determine the affected zones. CAUTION: PAR Revisions must include previous PARs. On the ENN Form for the selected PAR:
* Select block 5.B and record the "Evacuate" zones QB select block 5.C and record the "Shelter" zones"
* Select block 5.0
* IF PAR 4 is selected, THEN additionally select block 5.E "Other" and provide "Affected Sectors" and ''To Miles" Wind direction from D ENN Line 5 [C] Shelter Zones Advise remainder of EPZ to Monitor Local RadiofTV Stations PAR 1 ENN Line 5 [0] rrone Alert Radios. Consider the use of KI (Potassium Iodide) in accordance with State Plans and Policy Wind direction from D ENN Line 5 [8] Evacuate Zones Advise remainder of EPZ to Monitor Local RadiofTV Stations PAR 2 ENN Line 5 [0] rrone Alert Radios. Consider the use of KI (Potassium Iodide) in accordance with State Plans and Policy Wind direction from D ENN Line 5 [8] Evacuate Zones PAR 3 Advise remainder of EPZ to Monitor Local RadiofTV Stations ENN Line 5 [0] rrone Alert Radios. Consider the use of KI (Potassium Iodide) in accordance with State Plans and Policy Wind direction from D ENN Line 5 [8] Evacuate Zones Advise remainder of EPZ to Monitor Local RadiofTV Stations!
ENN Line 5 [0] Tone Alert Radios. Consider the use of KI (Potassium Iodide) in PAR 4 accordance with State Plans and ENN Line 5 [E] Evacuate Affected Sectors to OTHER miles Approval:
____ -J'I ___ _ Emergency Director DatelTime Printed: 9/1/2008 
( 09/06/0716:18:23 FNP-O-EIP-9.2 DATA SHEET 1 CLASSIFICATION DETERMINATION 1.LHave the On Shift Dose Analyst (Shift Radio Chemist) commence performing the calculations for dose assessment per EIP-9.0 step 4.2.
the affected Unit is in Modes 1,2,3, or 4, go to step 4. 3.M/A IF the affected Unit is in Modes 5, 6, or Defueled, go to step 6.
the status of the fission product barriers using Figure 1 or the "Fission Product Barrier Matrix" linked document.
: a. J Fuel Cladding Integrity 0 LOSS LOSS 0 INTACT (See Figure 1 or "Fission Product Barrier Matrix" linked document.)
Coolant System MOSS 0 POTENTIAL LOSS 0 INTACT Integrity (See Figure 1 or "Fission Product Barrier Matrix" linked document.)
: c. Containment Integrity 0 LOSS 0 POTENTIAL LOSS UlANTACT (See Figure 1 or "Fission Product Barrier Matrix" linked document.)
: 5. Use Figure 2 or the "Emergency Classification Hot Matrix" linked document .to evaluate and determine the Hot Initiating Condition based on events which are in progress, considering past events, and their impact on current plant conditions.
When using Figure 2 refer to the Threshold Value page associated with the Initiating Condition chosen to ensure that the Threshold is met. When using the "Emergency Classification Hot Matrix" linked document refer to the Threshold Value page for the IC if desired to evaluate the basis. Proceed to step 7. 6. MIA Use Figure 3 or the "Emergency Classification Cold Matrix" linked document to evaluate and determine the Cold Initiating Condition based on events which are in progress, considering past events, and their impact on current plant conditions.
When using Figure 3 refer to the Threshold Value page associated with the Initiating Condition chosen to ensure that the Threshold is met. When using the "Emergency Classification Cold Matrix" linked document refer to the Threshold Value page for the IC if desired to evaluate the basis. 7. Check 0 One: General Emergency (EIP-9.0 Guideline
: 1) I!!!r Site Area Emergency (EIP-9.0 Guideline
: 2) o Alert (EIP-9.0 Guideline
: 3) o Notification Of Unusual Event (EIP-9.0 Guideline
: 4) Comments:
...... _________________
_ 8. Assume the position of Emergency Director, sign this form and indicate the date and time of classification Signature:
Date: To Ida I Y Time: Emergency Director to the FNP-O-EIP-9.0 Guideline indicated in step 7 to perform appropriate actions for the declared emergency.
Classification time is the time indicated in step 8. Version 7 09106107 16:19:26 FNP-0-EIP-9.0 GUIDELINE 2 --GUIDELINE 2 SITE AREA EMERGENCY I. Purpose of Classification The classification of Site Area Emergency applies to those events which are in progress or have occurred involving actual or likely major failures of plant functions needed for protection of the public from radiation or contamination or HOSTILE ACTION that results in intentional damage or malicious acts; (1) toward site personnel or equipment that could lead to the likely failure of or; (2) that prevent effective access to equipment needed for the protection of the public. The potential for release of radioactive material for the Site Area Emergency classification is up to 1000 Ci of 1-131 equivalent, or 10 4 to 10 6 Ci of Xe-13 3 equivalent.
The purpose of the declaration of a Site Area Emergency is to: (a) Assure that response centers are manned, (b) Assure that monitoring teams are dispatched, (c) Assure that personnel involved in an evacuation effort of near site areas are at their duty stations if the situation worsens, and, (d) Provide current information for and consultation with offsite authorities and the public. ( e) A Site Area Emergency would be declared for plant conditions that warrant activation of emergency centers and monitoring teams. A Site Area Emergency would be declared Based on FNP-O-EIP-9.2 II. Emergency Director Actions NOTE: THE SHIFT MANAGER SHALL PERFORM THE DUTIES OF THE EMERGENCY DIRECTOR UNTIL IDS ARRIVAL AND ASSUMPTION OF DUTIES. Initials A .IrS 2. Notify personnel on site If the plant emergency alarm has not already been activated, then announce over the public address system, "All plant personnel report to designated assembly areas", activate the PEA for 30 seconds, then repeat announcement.
Announce the condition, request setup of the TSC and OSC, and give needed evacuation instructions over plant public address system. Page 1 of8 Version 59.0}}

Latest revision as of 11:38, 14 January 2025

Initial Exam 2008-301 Draft Administrative JPMs
ML091480123
Person / Time
Site: Farley  Southern Nuclear icon.png
Issue date: 05/28/2009
From:
NRC/RGN-II
To:
Southern Nuclear Operating Co
References
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