ML13169A419

2013 Braidwood Station Initial License Examination Administered SRO Administrative JPMs

ML13169A419
Person / Time
Site:	Braidwood
Issue date:	04/15/2013
From:	Division of Reactor Safety III
To:	Exelon Generation Co
Shared Package
ML11354A330	List: ML13169A418 ML13169A419 ML13169A421 ML13169A422 ML13169A424 ML13169A426
References
Download: ML13169A419 (256)

Text

JOB PERFORMANCE MEASURE TASK CONDITIONS:

1. You are the Unit One Unit Supervisor.

2. Both units are at 100% power in a normal electrical lineup.

3. The State Estimator alarm is operable and indicates a potential degraded grid condition based on a Braidwood Unit Two trip.

4. The unit NSOs provide the following indication readings to you:

State Estimator predicted voltage is 343.8 KV for BOTH units Bus 143 1EI-AP055 indicates 4280 Volts Bus 143 1II-AP051 and 1II-AP194 indicate 700 amps Bus 144 1EI-AP087 indicates 4280 Volts Bus 144 1II-AP083 and 1II-AP198 indicate 700 amps Bus 243 2EI-AP055 indicates 4350 Volts Bus 243 2IIAP051 and 2II-AP194 indicate 650 amps Bus 244 2EI-AP087 indicates 4350 Volts Bus 244 2II-AP083 and 2II-AP198 indicate 650 amps INITIATING CUES:

Implement 0BwOA ELEC-1 and determine the operability status of BOTH unit offsite circuits.

S-107 Page 1 of 6

TASK TITLE: Determine Operability of Offsite Circuits per 0BwOA ELEC-1 for Abnormal Grid Conditions.

JPM No.: S-107 REV: 2013 NRC TPO No.: T.OA01A-03. K&A No.: 2.1.25 K&A IMP: 4.2 TASK No.: S-TS-006, Ensure compliance with all Tech Spec LCOs.

TRAINEE: SRO EVALUATOR: DATE:

The Trainee: PASSED this JPM. TIME STARTED:

FAILED TIME FINISHED:

JPM TIME: MINUTES CRITICAL ELEMENTS: (*) 3, 4, 5 COMPLETION TIME: 15 MINUTES CRITICAL TIME: N/A ALTERNATE PATH: YES EVALUATION METHOD: LOCATION:

X PERFORM IN PLANT SIMULATE X SIMULATOR

_ CONTROL ROOM GENERAL

REFERENCES:

1. 0BwOA ELEC-1 ABNORMAL GRID CONDITIONS rev. 8.

2. Technical Specifications and Bases.

MATERIALS:

1. 0BwOA ELEC-1 Rev. 8.

2. Calculator.

3. Technical Specifications and Bases.

TASK STANDARDS:

1. Determine operability status of both units offsite circuits.

TASK CONDITIONS:

1. You are are the Unit One Unit Supervisor.

2. Both units are at 100% power in a normal electrical lineup.

3. The State Estimator alarm is operable and indicates a potential degraded grid condition based on a Braidwood Unit Two trip.

4. The unit NSOs provide the following indication readings to you:

State Estimator predicted voltage is 343.8 KV for BOTH units Bus 143 1EI-AP055 indicates 4280 Volts Bus 143 1II-AP051 and 1II-AP194 indicate 700 amps Bus 144 1EI-AP087 indicates 4280 Volts Bus 144 1II-AP083 and 1II-AP198 indicate 700 amps Bus 243 2EI-AP055 indicates 4350 Volts Bus 243 2IIAP051 and 2II-AP194 indicate 650 amps Bus 244 2EI-AP087 indicates 4350 Volts Bus 244 2II-AP083 and 2II-AP198 indicate 650 amps INITIATING CUES:

1. Implement 0BwOA ELEC-1 and determine the operability status of BOTH unit offsite circuits.

S-107 Page 2 of 6

RECORD START TIME ____________

NOTE: Ensure examinee has access to a calculator and that the Technical Specifications and Bases are available.

PERFORMANCE STEP STANDARD Circle applicable

1. Obtain copy of 0BwOA ELEC-1 Obtain and review procedure: SAT UNSAT N/A Comments:

CUE: Give student procedure.

2. Determine Type of State Estimator Determine Type of State SAT UNSAT N/A Alarm Estimator Alarm: Comments:

• Alarm Operable (from task

• State Estimator -

conditions) OPERABLE

• Predicted grid voltage (from

• Record State Estimator task conditions) actual/predicted grid voltage:

• Unit 1: 343.8 KV

• Unit 2: 343.8 KV

• Abnormal grid: predicted (from

• Abnormal grid -

task conditions) PREDICTED CONDITION

• Predicted due to a Braidwood

• Abnormal grid predicted Unit trip (from task conditions) due to BRAIDWOOD UNIT TRIP NOTE: The examinee enters the information into the blanks provided in the procedure and performs the calculations per procedure.

• 3. Check 4KV Non-ESF Loading Check 4KV Non-ESF Loading SAT UNSAT N/A (goes to Attachment A) (goes to Attachment A): Comments:

• CALCULATE Unit 1 4 KV Non-ESF Bus Loading:

• Bus 143 loading: 0.00173 x 4280 V x 700 amps =

5183 + 1 Kva.

• Bus 144 loading: 0.00173 x 4280 V x 700 amps =

5183 + 1 Kva.

• CALCULATE Unit 2 4 KV Non-ESF Bus Loading

• Bus 243 loading: 0.00173 x 4350 V x 650 amps =

4892 + 1 Kva

• Bus 244 loading: 0.00173 x 4350 V x 650 amps =

4892 + 1 Kv S-107 Page 3 of 6

• 4. Determine Minimum Switchyard Determine Minimum SAT UNSAT N/A Voltage. Switchyard Voltage: Comments:

• Record Unit 1 minimum switchyard voltage (given that both units are in normal electrical lineup so dual SAT operation applies) per Figure 0BwOA ELEC-1-1: 344 KV (range of 343.9 to 344.1 KV acceptable)

• Record Unit 2 minimum switchyard voltage (given that both units are in normal electrical lineup so dual SAT operation applies) per Figure 0BwOA ELEC-1-1: 343.4 (range of 343.2 to 343.5 acceptable.

• Records same values on page 5 (step 2b) main body of procedure.

• 5. Determine if minimum required DETERMINE if minimum SAT UNSAT N/A switchyard voltage is greater required switchyard voltage is Comments:

than state estimator predicted greater than state estimator predicted::

NOTE: provide candidate with access to Technical

• Identifies that Unit 1 Specifications and Bases. minimum required switchyard voltage IS GREATER THAN STATE ESTIMATOR PREDICTED THEREFORE UNIT 1 OFFSITE CIRCUITS MUST BE DECLARED INOPERABLE.

• Identifies that Unit 2 minimum required switchyard voltage IS LESS THAN STATE ESTIMATOR PREDICTED THEREFORE UNIT 2 OFFSITE CIRCUITS ARE OPERABLE.

• IDENTIFIES THAT 1BwOL 3.8.1, LCOAR AC SOURCES OPERATING TECH SPEC 3.8.1 must be entered.

• IDENTIFIES THAT 2BwOL 3.8.1, LCOAR AC SOURCES OPERATING TECH SPEC 3.8.1 must be entered (for Unit 1 SATs inoperable as RESERVE for Unit 2).

CUE: THIS COMPLETES THIS JPM.

RECORD STOP TIME ____________

S-107 Page 4 of 6

COMMENTS:

S-107 Page 5 of 6

SIMULATOR SETUP INSTRUCTIONS JPM NO: SIM-408P REQUIRED SIMULATOR MODE (S): Any 100% power IC.

MALFUNCTION #S:

N/A Technical Data provided in Cue Sheet.

COMMENTS:

S-107 Page 6 of 6

TASK CONDITIONS:

INITIAL CONDITIONS:

1. Unit 1 is at 98.0% power, 1500 EFPH Cycle 17, 1040 ppm boron, with CB D at 200 steps.

2. Tave is 0.5°F greater than Tref.

3. The QNE has advised Control Bank D should be withdrawn 13 steps to the desired target for proper long term fuel burn up.

4. The RO has completed the following:

• Calculated the expected final Tave-Tref error that will result from the rod movement.

• Calculate reactivity change to match Tave to Tref following the manual rod withdrawal.

INITIATING CUES:

1. The RO has provided you with:

• The Reactivity Change Determination Form, Attachment 1 of OP-AP-300-1004 for the reactivity addition following the rod movement, and

• A copy of the procedure that will be used for the reactivity addition and asked you to approve the reactivity plan.

1 S-111A

TASK TITLE: Review/Approve Reactivity Change JPM No.: S-111A REV: 2013 NRC TPO No.: 4.C.CV-04 K&A No.: 2.1.43 TASK No.: R-CV-003, Perform boron dilution of the RC System K&A IMP: 4.1/4.3 EXAMINEE: RO SRO EVALUATOR: DATE:

The Examinee: PASSED this JPM. TIME STARTED:

FAILED TIME FINISHED:

JPM TIME: MINUTES CRITICAL ELEMENTS: (*) 3,4,5,6,7 APPROX COMPLETION TIME: 15 MINUTES CRITICAL TIME: N/A EVALUATION METHOD: LOCATION:

X PERFORM IN PLANT SIMULATE X_ SIMULATOR ___

GENERAL

REFERENCES:

1. OP-AP-300-1004, Rev.2, Pwr Boration and Dilution Requirements

2. BwCB-1 (Various), Braidwood Curve Book

3. Operator Aid (01-18) REMA Unit 1 Reactivity Parameters MATERIALS:

1. OP- AP-300-1004, Rev.2, Boration and Dilution Requirements (Note: have 2 copies of Att.1)

2. BwCB-1 (Various), Braidwood Curve Book

3. Operator Aid (01-18) REMA Unit 1 Reactivity Parameters

4. BwOP CV-5, Operation of the Reactor Makeup System in the Dilute Mode, Alternate Dilute Mode, Batch Dilution Method, rev. 25.

5. 1BwGP 100-8, Rev. 28, Generic Reactor Control Guidance, step F.10.

TASK STANDARDS:

1. Calculate the reactivity change required to match Tave to Tref.

2. Complete the Reactivity Change Determination Form.

TASK CONDITIONS:

1. Unit 1 is at 98.0% power, 1500 EFPH Cycle 17, 1040 ppm boron, with CB D at 200 steps.

2. Tave is currently 0.5°F greater than Tref.

3. The QNE has advised Control Bank D should be withdrawn 13 steps to the desired target for proper long term fuel burn up.

4. The RO has completed the following:

• Calculated the expected final Tave-Tref error that will result from the rod movement.

• Calculate reactivity change to match Tave to Tref following the manual rod withdrawal.

INITIATING CUES:

2 S-111A

1. The RO has provided you with:

• The Reactivity Change Determination Form, Attachment 1 of OP-AP-300-1004 for the reactivity addition following the rod movement, and

• A copy of the procedure that will be used for the reactivity addition and asked you to approve the reactivity plan.

3 S-111A

EVALUATOR NOTE: These steps may be performed in any order.

RECORD START TIME Note to evaluator: Provide the first completed copy of OP-AP-300-1004 Att. 1 with the procedure.

Later, when (if) examinee directs the RO to correct the calculation, provide the second copy of Att. 1.

PERFORMANCE STEP STANDARD Circle applicable

1. Refer to Reviews: SAT UNSAT N/A

• OP-AP-300-1004, Rev 2, Pwr

• OP-AP-300-1004, Rev 2, Comments:

Boration and Dilution Pwr Boration and Dilution Requirements Requirements

• Operator Aid, Unit 1 Reactivity

• Operator Aid, Unit 1 Parameters Reactivity Parameters NOTE: Provide the attached Operator Aid for Unit 1 Cycle 17 1000-2000 EFPH, OP-AP-300-1004, 1BwGP 100-8 step F.10 and BwOP CV-5. Inform the examinee that the Operator Aid is current for the purposes of this calculation.

2. Determine temperature change

• Determines that the ROs SAT UNSAT N/A calculated for the 13 step rod calculation for the change Comments:

withdrawal is correct. in Tave due to stepping rods out is correct.

• 3. Determine total temperature

• Determines Tave-Tref SAT UNSAT N/A error that must be compensated existing o

difference o

of Comments:

1.0 F plus 0.5 F after withdrawing rods 13o NOTE: IF examinee fails to steps for a total 1.5 F.

identify the temperature error, skip to JPM step 6.

NOTE: It is possible the examinee will identify the procedure error first (see step 6). If this occurs, instruct the examinee to make a pen/ink correction and to continue the review of the proposed reactivity change.

• 4. Determine amount of boron or

• From Operator aid: SAT UNSAT N/A dilution required to match boration o

amount for a Comments:

temperature 1.0 F temperature drop is 25 to 26 gallons boric acid. The total gallons boric acid required is 1.5 times (25-26) = 37.5 to 39 gallons boric acid.

4 S-111A

• 5. Directs the RO to correct the Directs the RO to correct the SAT UNSAT N/A calculation based on: calculation. Comments:

• Total Tave difference of o

• Determines corrected 1.5 F Attachment 1 calculation is acceptable.

• 6. Identifies that the procedure the

• Identifies that BwOP CV- SAT UNSAT N/A RO plans to use is incorrect. 5 would result in dilution Comments:

and directs the RO to NOTE: per step 4.4 of OP-AP- use BwOP CV-6.

300-1004 it is the US responsibility to ensure all planned MCR borations and dilutions are performed using the governing procedure.

Cue: If examinee identified the calculation error but NOT the procedure error, provide corrected Attachment 1 VERSION 1 for approval. If candidate approves VERSION 1, this is failure criteria.

If examinee correctly identified BOTH errors, provide corrected Attachment 1 VERSION 2 completed (boric acid calculation of 37.5-39 gallons).

• 7. Approves reactivity change

• Signs as SRO approval SAT UNSAT N/A (VERSION 2) on Attachment 1 after Comments:

BOTH the calculation error and procedure error are corrected.

CUE: THIS COMPLETES THIS JPM.

RECORD STOP TIME COMMENTS:

5 S-111A

SIMULATOR SETUP INSTRUCTIONS NOTE: Update JPM with current cycle reactivity numbers, or specify cycle and unit prior to use.

JPM NO: R-111A REQUIRED SIMULATOR MODE(S): N/A MALFUNCTION #S: N/A COMMENTS:

6 S-111A

PROCEDURE BwOP CV-5 UNIT NO. REVISION NO.

25 BRAIDWOOD STATION PROCEDURE TITLE:

OPERATION OF THE REACTOR MAKEUP SYSTEM IN THE DILUTE MODE/ALTERNATE DILUTE MODE/BATCH DILUTION METHOD Rev Summary IR# / EC# (if applicable) 25 Step reformat and clarification (F.4a-e). PCRA 1310727-02

BwOP CV-5 Revision 25 Continuous Use OPERATION OF THE REACTOR MAKEUP SYSTEM IN THE DILUTE MODE/ALTERNATE DILUTE MODE/BATCH DILUTION METHOD A. STATEMENT OF APPLICABILITY This procedure describes the method to be used to operate the Reactor Makeup System in the DILUTE MODE/ALTERNATE DILUTE MODE/BATCH DILUTION METHOD for Power Level Changes, Temperature Control, I Control and RCS dilution in MODES 1-5.

B. REFERENCES

1. Procedures:

a. BwOP CV-7, Operation of the Reactor Makeup System in the Auto Makeup or Manual MODE.

b. _BwGP 100-1A1, UNIT 1/2 Main Control Board Manual/Auto Controller Setpoints.

c. _BwOS NR-1, Power History Surveillance.

d. BwCB-1/2, Figure 5, Temperature Coefficient vs. Moderator Temperature.

e. BwCB-1/2, Figure 10, Differential Boron Worth at HFP ARO Equilibrium Xenon.

f. BwCB-1/2, Figure 12, Boron Dilution Rate Nomograph.

g. BwCB-1/2, Table 3-1, Braidwood Boration Dilution Tables.

h. BwCB-1/2, Table 4-1, Cycle Specific Physics Data.

i. OP-AP-300, Reactivity Management.

2. Station Drawing: M-64 (M-138), Diagram of Chemical & Volume Control and Boron Thermal Regeneration UNIT 1 and UNIT 2.

3. Tech Specs:

a. 3.1.1

b. 3.4.4 1

BwOP CV-5 Revision 25 Continuous Use B. 4. Technical Requirements Manual TLCOs:

a. 3.1.a f. 3.1.f

b. 3.1.b g. 3.1.g

c. 3.1.c h. 3.1.h

d. 3.1.d i. 3.1.i

e. 3.1.e j. 3.1.j

5. Station Commitment:

020-251-85-066, Step F.3.c. and the related CAUTION.

C. PREREQUISITES

1. The Primary Water System is available to the Boric Acid Blender.

2. Instrument Air and Electrical Power are available to the CV System.

3. At least 1 Reactor Coolant Pump must be operating with the corresponding loop stop valves open to provide coolant mixing when the Reactor Coolant Boron Concentration is being altered.

4. The UNIT is in MODES 1-5.

5. RMCS is aligned for Auto Makeup Mode per BwOP CV-7, Operation of the Reactor Makeup System in the Auto Makeup or Manual MODE.

D. PRECAUTIONS

1. During normal Reactor Operation, except during boration or dilution, the Reactor Coolant Make-up System should be operated in the AUTO MODE, with the boron concentration adjusted to equal the concentration of the Reactor Coolant System.

2. Dilution of the RCS may be performed only when the Reactor is substantially subcritical (The Total Dilution will not cause the Shutdown Margin to be exceeded), or with Control Rods above the Low Insertion Limit, when At Power.

2

BwOP CV-5 Revision 25 Continuous Use D. 3. The effects of dilution must be observed in terms of resulting Control Rod motion or changes in Coolant Tave or Source Range Counts. STOP the operation if the expected response does not occur, and take corrective action.

4. Operation of the Reactor Makeup System in the ALT DIL MODE should be limited to approximately 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, to prevent Hydrogen depletion in the RCS. The one hour limitation may be exceeded during PHYSICS TESTS. A longer Alternate Dilute may be desired to provide better reactivity control. This time should be limited as much as practical without impacting the testing.

5. The PW Predet Counter Window must be reclosed after setting the PW Flow Counter, to prevent continued flow.

6. Curves are validated within engineering tolerances for steady state conditions.

Some differences between the calculated values and the actual values required will vary depending on plant conditions.

7. CVCS was designed to operate with 75 gpm letdown. CVCS letdown flow rates greater than design may limit normal dilution flow rate due to back pressure from the VCT spray nozzles.

8. Improperly high or low primary water temperature could adversely affect RCP seals. Ensure the Primary Water Heat Exchanger is maintaining 100F - 110F if in operation when performing large amounts of VCT makeup. High makeup flowrate will compound the problem.

9. For RCS chemistry control it is desired to perform all steady state dilutions to the top of the VCT. Transient conditions, including ramping of the Unit may require faster responses and although Chemistry would prefer dilution to the top of the VCT, dilution to the bottom or alternate dilution is at the preference of the Reactor Operator.

10. If a dilution of greater than or equal to 2,000 gallons occurs, or is expected to occur within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, NOTIFY Chemistry to evaluate the effects of the dilution on RCS lithium and hydrogen concentrations and to make chemical action request(s), if needed.

11. When Letdown flow is diverted to the HUTS, locally monitor the AB feed filter DP as necessary. Contact the Operations Supervisor if the DP is above 20 psid.

When AB feed filter P reaches 25 psid, the filter should be changed.

12. If AB feed filter P reaches 40 psid while letdown flow is being diverted to the HUT, IMMEDIATELY STOP letdown flow to the HUT. The AB feed demineralizer and filter may then by bypassed at the direction of an Operations Supervisor and the activity continued.

3

BwOP CV-5 Revision 25 Continuous Use E. LIMITATIONS AND ACTIONS

1. Reactivity Management SOS Expectations:

a. When utilizing a second SRO as a Reactivity Manager (RM), the following expectations must be adhered to:

The Unit Supervisor must be aware of the reactivity plan.

The RM is not required to inform the Unit Supervisor of every manipulation that is within the plan. Any deviation or unexpected response MUST be communicated to the Unit Supervisor.

The RM provides the PEER check for reactivity manipulations.

The NSO and RM must verbalize the reactivity manipulation.

2. Upon VCT level decreasing to 5% (both _LT112 and _LT185), Charging Pump Suction will automatically transfer to the RWST.

3. Shutdown Margin SHALL be within the limits specified in the COLR in MODES 1-5.

4. PW Flow Deviation Alarm with PW Flow +/- 8 GPM from setpoint, after 30 seconds.

a. _CV110B, Boric Acid Blender to Chg Pps Vlv, Closes.

b. _CV111B, Boric Acid Blender to VCT Vlv, Closes.

4

BwOP CV-5 Revision 25 Continuous Use E. 5. VCT Pressure Guidelines and Setpoints:

a. VCT normal system pressure range is 15 psig to 65 psig.

b. Do not decrease VCT pressure below 15 psig with RCPs in operation, as this may adversely affect RCP seal operation.

c. Nominal VCT pressure should be maintained between 15 psig to 25 psig whenever a gas blanket is established.

d. Ideal VCT pressure for chemistry consideration should be maintained between 15 psig to 22 psig. This is for optimum hydrogen concentration when a hydrogen blanket has been established in order to minimize the effects of accelerated stress corrosion cracking of the RCS.

e. Over pressurizing the VCT can cause the VCT 75 psig relief to lift inducing a loss of inventory to the RHUT.

f. When establishing a nitrogen or hydrogen blanket or during degassing operations VCT pressure may be maintained at approximately 30 psig.

g. If no RCPs are in operation, then VCT pressure can be maintained between 5 psig and 10 psig. This is also desirable during degassing operations or VCT float operation.

h. Certain plant conditions may require RCS dissolved hydrogen concentration to be increased to no greater than 50 cc/Kg, to achieve an increase in RCS dissolved hydrogen, volume control tank pressure may be raised to approximately 30 psig.

5

BwOP CV-5 Revision 25 Continuous Use F. MAIN BODY

1. DETERMINE the desired amount of PW to be added by performing one of the following methods:

For MODES 1 and 2, Effects of previously performed dilutions.

For MODES 1 and 2, Braidwood Boration Dilution Tables (BwCB-1/2 Table 3-1):

1) Determine the desired RCS temperature change based on Auctioneered Hi Tavg/Tref error from: _TR-412, _TI-412, _TI-422,

_TI-432, _TI-442, T0499, T0496 or other appropriate indications.

2) Determine "Previous Cumulative EFPH" from _BwOS NR-1, Power History Surveillance step F.3.

3) Determine Isothermal Temperature Coefficient (ITC) from BwCB-1/2 Fig 5.

4) Determine the required reactivity change () in PCM by the following:

= ITC

• temperature change

5) Determine Differential Boron Worth (DBW) from BwCB-1/2 Fig 10.

6) Determine the required RCS Critical Boron (CB) concentration change in PPM by the following:

CB = / DBW

7) Determine the current RCS boron concentration from the most recent representative sample.

8) Determine the total amount of dilution required to accomplish the desired RCS temperature change from BwCB-1/2 Table 3-1 using the appropriate RCS temperature and boron concentration.

6

BwOP CV-5 Revision 25 Continuous Use F. 1. For Modes 3 through 5, Braidwood Boration Dilution Tables (BwCB-1/2 Table 3-1):

1) Determine the current RCS boron concentration from the most recent representative sample.

2) Determine the total amount of dilution required to accomplish the desired RCS boron concentration change from BwCB-1/2 Table 3-1 using the appropriate RCS temperature and boron concentration.

3) For expected changes in RCS Boron concentration of greater than 200 ppm, PERFORM the following:

a) Reduce the dilution to 80% of the total number of gallons calculated.

b) WAIT for a period of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for complete mixing to occur.

c) START the RCS sample purge and maintain for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

d) NOTIFY Chemistry Department to determine RCS Boron concentration.

e) RECALCULATE the remaining dilution required per step F.1.

Attachment 1, ReMA Form of procedure OP-AP-300-1003, PWR REACTIVITY MANEUVER.

_BwGP 100-4T2, LOAD SWING INSTRUCTION SHEET.

Operator Aid, OP-AA-115-101.

NOTE The Reactivity Change Determination Form is not required if a ReMA, Op Aid, Load Swing Instruction Sheet, or similar type of prepared reactivity plan is used per OP-AP-300-1004.

2. If required, COMPLETE Attachment 1, Reactivity Change Determination Form of procedure OP-AP-300-1004, PWR BORATION AND DILUTION REQUIREMENTS.

7

BwOP CV-5 Revision 25 Continuous Use

• CAUTION The PREDET Counter Window must be closed to prevent continued flow.

CAUTION Primary water flowrates are inaccurate if flowrate is 32 gpm. If the desired flowrate is less than 32 gpm, the BATCH dilution method should be utilized.

NOTE Steps F.3 dilutes using the AUTOMATIC functions. When performing a dilution of 300 gallons, the automatic functions should be used.

Step F.4. dilutes using the BATCH dilution method.

NOTE If Reactor Power or Tave makes an unexpected change, the Control Rods move in an unexpected direction, or the Rod Insertion Limit is reached, the dilution must be stopped IMMEDIATELY.

NOTE If letdown flow is directed to the VCT, normal dilution flow rate is limited by system back pressure. If the desired PW flow rate is >80 gpm, it may be necessary to direct a portion of letdown flow to the HUTs to prevent a PW Flow Deviation Alarm.

F. 3. DILUTE/ALT DILUTE in automatic by performing the following:

a. DETERMINE desired PW flow rate.

b. ADJUST the Setpoint on _FK-111, PW/Total Flow Cont Pot, to the value corresponding to the desired PW flow rate.

8

BwOP CV-5 Revision 25 Continuous Use

• F. 3. c. SET _FY-0111, Primary Water Control Predet Counter as follows:

1) DEPRESS and HOLD the RESET pushbutton WHILE opening the setpoint window.

2) SET the thumbwheels to the desired volume (right most digit is gallons).

3) WHILE holding the RESET pushbutton DEPRESSED, CLOSE the setpoint window.

d. PLACE the MAKEUP CONT Switch in the STOP position.

e. PLACE the MODE SELECT Switch in the DIL Position, for normal dilution or ALT DIL Position for alternate dilution.

f. PLACE the MAKEUP CONT Switch to the START position to commence the dilution.

g. VERIFY that the following occurs:

_CV111B, Boric Acid Blender to VCT Vlv, OPENS.

_CV111A, PW Boric Acid Blender Vlv, MODULATES OPEN.

_CV110B, Boric Acid Blender to Chg Pps Vlv, OPENS (in the ALT DIL MODE only).

0PW02PA/B, PW Makeup Pp 0A/B is in OPERATION.

Proper PW/Total Flow on _FR-110, Rx Makeup Flow recorder.

9

BwOP CV-5 Revision 25 Continuous Use F. 3. h. CONTROL Volume Control Tank level by one of the following methods:

VERIFY/ADJUST automatic control of M/A station _LK-112, VCT Lvl Cont _CV112A, setpoint by performing the following:

a) VERIFY/PLACE M/A station _LK-112, VCT Lvl Cont

_CV112A, in AUTO.

b) VERIFY/ADJUST the M/A station setpoint on _LK-112, VCT Lvl Cont _CV112A, to the desired value.

MANUALLY ADJUST _LK-112, VCT Lvl Cont _CV112A, by performing the following:

a) PLACE M/A station on _LK-112, VCT Lvl Cont _CV112A, in MANUAL.

b) DEPRESS the RAISE PUSHBUTTON on _LK-112, VCT Lvl Cont _CV112A, to the desired demand.

i. WHEN the desired amount of dilution has been achieved, PLACE the MAKE-UP CONT Switch to the STOP position.

j. VERIFY the following actions have occurred:

VERIFY/CLOSE, _CV111A, PW to Boric Acid Blender Vlv.

VERIFY/CLOSE, _CV111B, Boric Acid Blender to VCT Vlv.

VERIFY/CLOSE, _CV110B, Boric Acid Blender to Chg Pps Vlv.

VERIFY/STOP 0PW02PA/B, PW Makeup Pp 0A/B, if started during the performance of this procedure.

k. GO TO step F.5.

10

BwOP CV-5 Revision 25 Continuous Use F. 4. For BATCH DILUTION METHOD perform the following (otherwise N/A):

a. CONTROL Volume Control Tank level by one of the following methods:

VERIFY/ADJUST automatic control of M/A station _LK-112, VCT Lvl Cont _CV112A, setpoint by performing the following:

a) VERIFY/PLACE M/A station _LK-112, VCT Lvl Cont

_CV112A, in AUTO.

b) VERIFY/ADJUST the M/A station setpoint _LK-112, VCT Lvl Cont _CV112A, to the desired value and adjust as necessary throughout the evolution.

MANUALLY ADJUST _LK-112, VCT Lvl Cont _CV112A, by performing the following:

a) PLACE M/A station on _LK-112, VCT Lvl Cont _CV112A, in MANUAL.

b) DEPRESS the RAISE PUSHBUTTON on _LK-112, VCT Lvl Cont _CV112A, to the desired demand and adjust as necessary throughout the evolution.

b. IF desired, PERFORM the following to RESET PW Total Flow Totalizer to ZERO:

1) DEPRESS and HOLD the RESET pushbutton.

2) VERIFY PW Total Flow Totalizer resets to ZERO.

3) RELEASE the RESET pushbutton.

c. IF desired to dilute using the upper nozzle of the VCT, THEN OPEN

_CV111B, Boric Acid Blender to VCT.

d. IF desired to dilute using the outlet of the VCT, THEN OPEN _CV110B, Boric Acid Blender to Chg Pps Vlv.

e. OPEN _CV111A, PW to Boric Acid Blender Vlv.

f. WHEN the desired amount of Primary Water has been added, CLOSE

_CV111A, PW to Boric Acid Blender Vlv.

g. VERIFY/CLOSE _CV110B, Boric Acid Blender to Chg Pps Vlv.

h. VERIFY/CLOSE _CV111B, Boric Acid Blender to VCT.

11

BwOP CV-5 Revision 25 Continuous Use F. 4. i. VERIFY/PLACE the following valves in the AUTO position:

_CV111A, PW to Boric Acid Blender Vlv.

_CV111B, Boric Acid Blender to VCT Vlv.

_CV110B, Boric Acid Blender to Chg Pps Vlv.

5. If desired, VERIFY/RESTORE _LK-112 to AUTO by performing the following:

a. VERIFY/VCT level or pressure is at the desired value.

b. VERIFY/DEPRESS the LOWER PUSHBUTTON ON _LK-112, VCT Lvl Cont _CV112A, to 0 demand. (Only required if manual level control was selected.)

c. VERIFY/PLACE M/A station _LK-112, VCT Lvl Cont _CV112A, in AUTO.

d. VERIFY/ADJUST _LK-112, VCT Lvl Cont _CV112A to the desired corresponding level setpoint.

e. VERIFY/PLACE C/S for _CV112A in AUTO at _PM05J.

6. IF desired, PERFORM the following to RESET PW Total Flow Totalizer to ZERO:

a. DEPRESS and HOLD the RESET pushbutton.

b. VERIFY PW Total Flow Totalizer resets to ZERO.

c. RELEASE the RESET pushbutton.

7. MONITOR the following as appropriate.

Reactor Power Tave Control Rod position SR count rate 12

BwOP CV-5 Revision 25 Continuous Use F. 8. If desired, RETURN the Reactor Makeup System to AUTO as follows:

a. If necessary, DETERMINE the existing RCS Boron Concentration from the Chemistry Department.

NOTE When the MODE SELECT Switch is in AUTO, an internal Setpoint in the Process Racks is used to cause _FK-111 to control total makeup flow at 120 gpm. The potentiometer for _FK-111 is not used in this mode.

b. DETERMINE the desired Boric Acid Flow Rate from BwCB-1/2 Figure 16, Braidwood Blended Flow Table.

c. SET _FK-110, Boric Acid Flow to Blender, to the value corresponding to the desired flow rate and VERIFY that the controller is in AUTO.

d. VERIFY/PLACE the following valves in the AUTO position:

_CV111A, PW to Boric Acid Blender Vlv.

_CV111B, Boric Acid Blender to VCT Vlv.

_CV110A, VA to Blender Vlv.

_CV110B, Boric Acid Blender to Chg Pps Vlv.

e. VERIFY that _AB03P, Boric Acid Xfer Pp C/S is NOT in the PULL OUT position.

NOTE A Unit Makeup will Auto start the 0A PW Pump while a Unit 2 Makeup will Auto start the 0B PW Pump.

f. VERIFY that 0PW02PA/PB, PW Pump 0A/B Pp C/S for the affected unit is NOT in the PULL OUT position.

g. PLACE the MAKEUP CONT Switch in the STOP position.

h. PLACE the MODE SELECT Switch in the AUTO position.

i. PLACE the MAKEUP CONT Switch in the START position.

13

BwOP CV-5 Revision 25 Continuous Use F. 9. IF RCS Boron Concentration was changed by greater than 20 ppm, equalize Boron Concentration between the Pressurizer and the loops, OPEN the Pressurizer Spray Valves by either (otherwise N/A):

PLACE B/U Htr Grps A/B/D Contactor CONTROL Switch to the ON position, at _PM05J.

IF the RCS is water solid, OPEN _RY455B/C, Pressurizer Spray Valve, in manual.

10. IF RCS Boron Concentration was changed by greater than 20 ppm, perform the following (otherwise N/A):

a. NOTIFY the Chemistry Department to sample the following after approximately 1 hour:

The Reactor Coolant System The Pressurizer

b. When the RCS and Pressurizer Boron Concentrations are within 20 ppm of each other, PERFORM the following:

1) PLACE B/U Htrs Grp A/B/D Contactor CONTROL Switch to the desired position.

2) VERIFY that _RY455B/C, Pressurizer Spray Valve, is in the proper position.

(Final) 14

OP-AP-300-1004 Revision 1 2 Page 4 of 4 PWR BORATION AND DILUTION REQUIRMENTS Formatted: Bullets and Numbering 1.PURPOSE 1.1.The purpose of this T&RM is to define responsibilities and provide guidance for PWR boration and dilution evolutions.

2.TERMS AND DEFINITIONS 2.1. Approved (Governing) Procedure: as used in this document, refers to a procedure approved for use at the station, or to a document whose generation is described in and directed by a procedure approved for use at the station.

2.2.Licensed Operator: is synonymous with Reactor operator (RO), Senior Reactor Operator (SRO), or Nuclear Station Operator (NSO).

2.3.Steady-State: Reactivity Core Characteristics that are stable and behaving as expected per the core burn-up plot with stable Xenon conditions.

2.4.Non-Transient Conditions: Operations within normal station administrative parameters and guidance.

2.5.Deboration: Removal of Boric Acid from the letdown fluid by deborating demineralizers, the effluent of which is returned to the RCS. For the intent of this procedure is synonymous with Dilution.

3.RESPONSIBILITIES 3.1.Operations is responsible for all Boration and Dilutions of the Reactor Coolant System.

4.MAIN BODY 4.1.Operations shall PERFORM borations and dilutions in a deliberate, carefully controlled manner while constantly monitoring nuclear instrumentation and redundant indications of reactor power level, neutron flux, and coolant temperature (SOER 96-02).

4.2.The effects of boration or dilution must be observed in terms of resulting Control Rod motion, changes in Coolant Tave or Source Range Counts or change in Heatup/Cooldown Rate. STOP the operation if the expected response does not occur and take corrective action.

OP-AP-300-1004 Revision 1 2 Page 2 of 4 4.3.Operations shall PERFORM peer checking of all Main Control Room, MCR, non-transient boration and dilution evolutions. When utilizing a second SRO to support reactivity management functions related to the primary (Primary SRO), the following expectations must be adhered to:

• The Unit Supervisor must be aware of the reactivity plan.

• The Primary SRO is not required to inform the Unit Supervisor of every manipulation that is within the plan. Any deviation or unexpected response MUST be communicated to the Unit Supervisor.

• The US/Primary SRO may provide the PEER check for reactivity manipulations.

NOTE: Boration and/or dilution while shutdown, where adequate shutdown margin is assured, does not require the supervisor to be proximate to the reactor operator.

Formatted: Bullets and Numbering 4.4.The Unit Supervisor shall ENSURE all planned MCR borations and dilutions are performed by the Licensed Operator in accordance with the governing procedure or Operator Aid. In plant activities affecting reactivity equipment shall be directed by a licensed operator.

NOTE: If a ReMA was developed for a planned Reactivity Change, Attachment 1, Reactivity Change Determination Form is not required.

Formatted: Bullets and Numbering 4.5.Attachment 1, Reactivity Change Determination Form, shall be used:

• To ensure proper Technical Human Performance during reactivity maneuver planning.

• For reactivity changes that do not involve planned turbine load changes.

• To document each Reactivity manipulation OR, an entire shift of Reactivity manipulations during steady-state conditions as determined by the SRO.

• Alone or in conjunction with a ReMA per Shift Manager discretion.

4.5.1.Completed forms shall be forwarded to the Shift Manager.

4.6. All Reactivity manipulations shall be documented in the Unit Operator Logs.

Formatted: Bullets and Numbering 5.DOCUMENTATION - None 6.REFERENCES

OP-AP-300-1004 Revision 1 2 Page 3 of 4 6.1.INPO SOER 96-02, Design and Operating Considerations for Reactor Cores 7.ATTACHMENTS 7.1. Attachment 1 - Reactivity Change Determination FormATTACHMENT 1 REACTIVITY CHANGE DETERMINATION FORM Station: _Braidwood_ Unit: 1 2 Time: _Now___ Date: _Today__

Desired change:

(Parameter, Magnitude, and Direction: Reactor Power, Rod Position, RCS Temp, Delta I, etc.)

(Withdraw control bank D 13 steps per QNE for core burnup). Compensate for rod withdrawal to match Tave to Tref.

Reason for Change:

(Temperature control, flux control, fuel burn up)

Temperature Control What is the method and amount required for the reactivity change?

(Bleed Tank Volume, Gallons of Dilution/Boration/Blended Flow, Rod Insertion/Rod Withdrawal steps/percent) boration of 26 gallons per BwOP CV-5 Inputs:

(ReMA Thumbrules, ReMA maneuver guidance, Curve Book Figure/Table, Computer based trend plot, RCS Cb, EFPD - Preparer and Reviewer should use independent inputs when possible)

Approved operator aid for current cycle and EFPH Calculation of change:

(E.G. Bwd/Byr: ReMA Thumbrule identifies 20 gallons BA = 1.0°F RCS temp reduction.

Desired change = 0.5°F drop. Calculation of change: (20 gal/1.0°F)

• 0.5°F = 10 gal.,

previously used borations and dilutions)

(TMI: Procedure 1102-4 Power Operations Fig. 1, Volume of Deminerlized Water for 1% Rod Insertion)

(13 steps)(1oF/13 steps) = 1 oF Tave rise (26 gallons) x 1 oF = 26 gallons to match Tave to Tref 1 oF

___JN______ _____SB______ ______________

Preparer Reviewer Approver

OP-AP-300-1004 Revision 1 2 Page 4 of 4 (RO) (RO/SRO) (SRO)

Shift Manager Notified: Yes No

OP-AP-300-1004 Revision 1 2 Page 4 of 4 PWR BORATION AND DILUTION REQUIRMENTS Formatted: Bullets and Numbering 1.PURPOSE 1.1.The purpose of this T&RM is to define responsibilities and provide guidance for PWR boration and dilution evolutions.

2.TERMS AND DEFINITIONS 2.1. Approved (Governing) Procedure: as used in this document, refers to a procedure approved for use at the station, or to a document whose generation is described in and directed by a procedure approved for use at the station.

2.2.Licensed Operator: is synonymous with Reactor operator (RO), Senior Reactor Operator (SRO), or Nuclear Station Operator (NSO).

2.3.Steady-State: Reactivity Core Characteristics that are stable and behaving as expected per the core burn-up plot with stable Xenon conditions.

2.4.Non-Transient Conditions: Operations within normal station administrative parameters and guidance.

2.5.Deboration: Removal of Boric Acid from the letdown fluid by deborating demineralizers, the effluent of which is returned to the RCS. For the intent of this procedure is synonymous with Dilution.

3.RESPONSIBILITIES 3.1.Operations is responsible for all Boration and Dilutions of the Reactor Coolant System.

4.MAIN BODY 4.1.Operations shall PERFORM borations and dilutions in a deliberate, carefully controlled manner while constantly monitoring nuclear instrumentation and redundant indications of reactor power level, neutron flux, and coolant temperature (SOER 96-02).

4.2.The effects of boration or dilution must be observed in terms of resulting Control Rod motion, changes in Coolant Tave or Source Range Counts or change in Heatup/Cooldown Rate. STOP the operation if the expected response does not occur and take corrective action.

OP-AP-300-1004 Revision 1 2 Page 2 of 4 4.3.Operations shall PERFORM peer checking of all Main Control Room, MCR, non-transient boration and dilution evolutions. When utilizing a second SRO to support reactivity management functions related to the primary (Primary SRO), the following expectations must be adhered to:

• The Unit Supervisor must be aware of the reactivity plan.

• The Primary SRO is not required to inform the Unit Supervisor of every manipulation that is within the plan. Any deviation or unexpected response MUST be communicated to the Unit Supervisor.

• The US/Primary SRO may provide the PEER check for reactivity manipulations.

NOTE: Boration and/or dilution while shutdown, where adequate shutdown margin is assured, does not require the supervisor to be proximate to the reactor operator.

Formatted: Bullets and Numbering 4.4.The Unit Supervisor shall ENSURE all planned MCR borations and dilutions are performed by the Licensed Operator in accordance with the governing procedure or Operator Aid. In plant activities affecting reactivity equipment shall be directed by a licensed operator.

NOTE: If a ReMA was developed for a planned Reactivity Change, Attachment 1, Reactivity Change Determination Form is not required.

Formatted: Bullets and Numbering 4.5.Attachment 1, Reactivity Change Determination Form, shall be used:

• To ensure proper Technical Human Performance during reactivity maneuver planning.

• For reactivity changes that do not involve planned turbine load changes.

• To document each Reactivity manipulation OR, an entire shift of Reactivity manipulations during steady-state conditions as determined by the SRO.

• Alone or in conjunction with a ReMA per Shift Manager discretion.

4.5.1.Completed forms shall be forwarded to the Shift Manager.

4.6. All Reactivity manipulations shall be documented in the Unit Operator Logs.

Formatted: Bullets and Numbering 5.DOCUMENTATION - None 6.REFERENCES

OP-AP-300-1004 Revision 1 2 Page 3 of 4 6.1.INPO SOER 96-02, Design and Operating Considerations for Reactor Cores 7.ATTACHMENTS 7.1. Attachment 1 - Reactivity Change Determination FormATTACHMENT 1 REACTIVITY CHANGE DETERMINATION FORM Station: _Braidwood_ Unit: 1 2 Time: _Now___ Date: _Today__

Desired change:

(Parameter, Magnitude, and Direction: Reactor Power, Rod Position, RCS Temp, Delta I, etc.)

(Withdraw control bank D 13 steps per QNE for core burnup). Compensate for rod withdrawal to match Tave to Tref.

Reason for Change:

(Temperature control, flux control, fuel burn up)

Temperature Control What is the method and amount required for the reactivity change?

(Bleed Tank Volume, Gallons of Dilution/Boration/Blended Flow, Rod Insertion/Rod Withdrawal steps/percent) boration of 38 gallons per BwOP CV-5 Inputs:

(ReMA Thumbrules, ReMA maneuver guidance, Curve Book Figure/Table, Computer based trend plot, RCS Cb, EFPD - Preparer and Reviewer should use independent inputs when possible)

Approved operator aid for current cycle and EFPH Calculation of change:

(E.G. Bwd/Byr: ReMA Thumbrule identifies 20 gallons BA = 1.0°F RCS temp reduction.

Desired change = 0.5°F drop. Calculation of change: (20 gal/1.0°F)

• 0.5°F = 10 gal.,

previously used borations and dilutions)

(TMI: Procedure 1102-4 Power Operations Fig. 1, Volume of Deminerlized Water for 1% Rod Insertion)

(13 steps)(1oF/13 steps) = 1 oF Tave rise; Total error = 0.5 oF (current) + 1.0 oF = 1.5 oF (25 to 26 gallons) x 1.5 oF = 37.5 to 39 gallons to match Tave to Tref 1 oF

___JN______ _____ SB______ ______________

Preparer Reviewer Approver

OP-AP-300-1004 Revision 1 2 Page 4 of 4 (RO) (RO/SRO) (SRO)

Shift Manager Notified: Yes No

OP-AP-300-1004 Revision 1 2 Page 4 of 4 PWR BORATION AND DILUTION REQUIRMENTS Formatted: Bullets and Numbering 1.PURPOSE 1.1.The purpose of this T&RM is to define responsibilities and provide guidance for PWR boration and dilution evolutions.

2.TERMS AND DEFINITIONS 2.1. Approved (Governing) Procedure: as used in this document, refers to a procedure approved for use at the station, or to a document whose generation is described in and directed by a procedure approved for use at the station.

2.2.Licensed Operator: is synonymous with Reactor operator (RO), Senior Reactor Operator (SRO), or Nuclear Station Operator (NSO).

2.3.Steady-State: Reactivity Core Characteristics that are stable and behaving as expected per the core burn-up plot with stable Xenon conditions.

2.4.Non-Transient Conditions: Operations within normal station administrative parameters and guidance.

2.5.Deboration: Removal of Boric Acid from the letdown fluid by deborating demineralizers, the effluent of which is returned to the RCS. For the intent of this procedure is synonymous with Dilution.

3.RESPONSIBILITIES 3.1.Operations is responsible for all Boration and Dilutions of the Reactor Coolant System.

4.MAIN BODY 4.1.Operations shall PERFORM borations and dilutions in a deliberate, carefully controlled manner while constantly monitoring nuclear instrumentation and redundant indications of reactor power level, neutron flux, and coolant temperature (SOER 96-02).

4.2.The effects of boration or dilution must be observed in terms of resulting Control Rod motion, changes in Coolant Tave or Source Range Counts or change in Heatup/Cooldown Rate. STOP the operation if the expected response does not occur and take corrective action.

OP-AP-300-1004 Revision 1 2 Page 2 of 4 4.3.Operations shall PERFORM peer checking of all Main Control Room, MCR, non-transient boration and dilution evolutions. When utilizing a second SRO to support reactivity management functions related to the primary (Primary SRO), the following expectations must be adhered to:

• The Unit Supervisor must be aware of the reactivity plan.

• The Primary SRO is not required to inform the Unit Supervisor of every manipulation that is within the plan. Any deviation or unexpected response MUST be communicated to the Unit Supervisor.

• The US/Primary SRO may provide the PEER check for reactivity manipulations.

NOTE: Boration and/or dilution while shutdown, where adequate shutdown margin is assured, does not require the supervisor to be proximate to the reactor operator.

Formatted: Bullets and Numbering 4.4.The Unit Supervisor shall ENSURE all planned MCR borations and dilutions are performed by the Licensed Operator in accordance with the governing procedure or Operator Aid. In plant activities affecting reactivity equipment shall be directed by a licensed operator.

NOTE: If a ReMA was developed for a planned Reactivity Change, Attachment 1, Reactivity Change Determination Form is not required.

Formatted: Bullets and Numbering 4.5.Attachment 1, Reactivity Change Determination Form, shall be used:

• To ensure proper Technical Human Performance during reactivity maneuver planning.

• For reactivity changes that do not involve planned turbine load changes.

• To document each Reactivity manipulation OR, an entire shift of Reactivity manipulations during steady-state conditions as determined by the SRO.

• Alone or in conjunction with a ReMA per Shift Manager discretion.

4.5.1.Completed forms shall be forwarded to the Shift Manager.

4.6. All Reactivity manipulations shall be documented in the Unit Operator Logs.

Formatted: Bullets and Numbering 5.DOCUMENTATION - None 6.REFERENCES

OP-AP-300-1004 Revision 1 2 Page 3 of 4 6.1.INPO SOER 96-02, Design and Operating Considerations for Reactor Cores 7.ATTACHMENTS 7.1. Attachment 1 - Reactivity Change Determination FormATTACHMENT 1 REACTIVITY CHANGE DETERMINATION FORM Station: _Braidwood_ Unit: 1 2 Time: _Now___ Date: _Today__

Desired change:

(Parameter, Magnitude, and Direction: Reactor Power, Rod Position, RCS Temp, Delta I, etc.)

(Withdraw control bank D 13 steps per QNE for core burnup). Compensate for rod withdrawal to match Tave to Tref.

Reason for Change:

(Temperature control, flux control, fuel burn up)

Temperature Control What is the method and amount required for the reactivity change?

(Bleed Tank Volume, Gallons of Dilution/Boration/Blended Flow, Rod Insertion/Rod Withdrawal steps/percent) boration of 38 gallons per BwOP CV-6 Inputs:

(ReMA Thumbrules, ReMA maneuver guidance, Curve Book Figure/Table, Computer based trend plot, RCS Cb, EFPD - Preparer and Reviewer should use independent inputs when possible)

Approved operator aid for current cycle and EFPH Calculation of change:

(E.G. Bwd/Byr: ReMA Thumbrule identifies 20 gallons BA = 1.0°F RCS temp reduction.

Desired change = 0.5°F drop. Calculation of change: (20 gal/1.0°F)

• 0.5°F = 10 gal.,

previously used borations and dilutions)

(TMI: Procedure 1102-4 Power Operations Fig. 1, Volume of Deminerlized Water for 1% Rod Insertion)

(13 steps)(1oF/13 steps) = 1 oF Tave rise; Total error = 0.5 oF (current) + 1.0 oF = 1.5 oF (25 to 26 gallons) x 1.5 oF = 37.5 to 39 gallons to match Tave to Tref 1 oF

___JN______ _____ SB______ ______________

Preparer Reviewer Approver

OP-AP-300-1004 Revision 1 2 Page 4 of 4 (RO) (RO/SRO) (SRO)

Shift Manager Notified: Yes No

PROCEDURE 1BwGP 100-8 UNIT NO. REVISION NO.

1 28 BRAIDWOOD STATION PROCEDURE TITLE:

GENERIC REACTOR CONTROL GUIDANCE Rev Summary IR# / EC# (if applicable) 27 Add Rod Step and Ramping Hard Cards as PCRA 1134211-20 attachments 28 Add note and new step for limiting power to 100.0% PCRA 1230957-41 using LEFM

1BwGP 100-8 Revision 28 Reference Use GENERIC REACTOR CONTROL GUIDANCE A. STATEMENT OF APPLICABILITY This procedure establishes the guidance necessary for controlling the reactor. The guidance includes I Control, Temperature Control, Full Power Maintenance, Coastdown Operation, Positive MTC Operation, Rod Control Operation during normal conditions, and Minor Load Adjustments (< 2%).

B. REFERENCES

1. Westinghouse Generic Load Follow Strategy Report. - 5.0.300.

2. Westinghouse Operating Instruction 0-5, Reduced Temperature Return to Power.

3. Westinghouse Nuclear Fuel Division, Limitations and Conditions for Westinghouse Fuel Operation.

4. Braidwood Curve Book (BwCB-1).

5. Nuclear Fuel Services Special Report PWR Axial Xenon Oscillations, dated December 1988.

6. NFM Letter: NFM-MW: 01-0166, Validity of Loop Average Temperature, dated May 29, 2001.

7. NFS Letter PND/056/88, Naughton to Querio, dated 8-29-88.

8 NFS Letter PSS: 98-086, Policy for Operation at Hot Full Power, from D.R.

Redden to B. Wegner, dated June 25, 1998.

9. Technical Specifications:

a. LCO 3.1.3, Moderator Temperator Coefficient (MTC).

b. LCO 3.1.4, Rod Group Alignment Limits.

c. LCO 3.2.3, Axial Flux Difference (AFD).

d. LCO 3.2.4, Quadrant Power Tilt Ratio (QPTR).

10. Station Commitments:

a. 456-200-93-04301, Step D.3.

1

1BwGP 100-8 Revision 28 Reference Use C. PREREQUISITES None.

D. PRECAUTIONS

1. Core control and behavior must be fully understood at all times. In the event a situation arises that is not fully understood, it is the responsibility of every member of the Control Room team to question the indication. The Shift Manager SHALL be directly involved in the resolution of the concern.

2. Prior to raising power above 50%, reasonable I stability needs to exist. If I has been drifting away from target excessively, power should not be raised until I can be ensured to remain within BwCB-1, Figure 19 limits when the power rise is performed. Contact QNE for additional guidance.

• 3. I may be extremely positive at low power levels. I will be more positive the higher Control Bank D is maintained (above mid-plane). During reactor startup/power ascension (10-8 amps to 15% RTP) Controlling Bank (Bank C or D) must be maintained slightly above core mid-plane (115 steps) and withdrawn as power rises. Inserting/maintaining Controlling Bank (Bank C or D) below mid-plane will result in flux response converse to expected (i.e., rods out, I more negative).

4. If the Nuclear Instrumentation input to the process computer is interrupted, or the process computer is rebooted, the Iodine and Xenon programs should be considered suspect. Reactor Engineering should be consulted prior to using these points. AFD cals and Power Range ACOTS are examples of activities that can interrupt the input to the process computer.

E. LIMITATIONS AND ACTIONS

1. Maintain rod position within the limits for control bank insertion, sequence, and overlap per Tech Spec LCO 3.1.6.

2. Maintain rod position within the limits for control bank withdrawal per Tech Spec LCO 3.1.3 when applicable.

3. Operate within the limits and restrictions specified for I per Tech Spec LCO 3.2.3 when PDMS is inoperable.

2

1BwGP 100-8 Revision 28 Reference Use E. 4. The following guidelines are broken into sections covering parameters that should always be maintained during steady state operation. Steady State Operation is defined as:

I within 3% of Target.

Average Tave within 4ºF of Tref Generator online.

No load changes in progress.

5. I shall be maintained within the Admin limit specified in BwCB-1, Figure 19 by the operator during steady-state operations. If I deviates outside this limit or if a I oscillation occurs, immediate operator action is required to restore I to within its administrative limits. This administrative limit applies regardless of whether or not PDMS is OPERABLE, but is not applicable during coastdown operations.

6. During power operation, control rods should be used mainly for I control and boron concentration should be adjusted for maintaining Tave. Caution should be used when CBD is below 130 steps. I control is typically reduced as CBD is inserted below 130 steps until CBC reaches a bite position. If an unexpected flux profile occurs, contact Reactor Engineering.

If control rod withdrawal limits are implemented to maintain the Moderator Temperature Coefficient (MTC) within the COLR Limits, then the control strategy should be developed based on the limits imposed.

7. Perform Section 5.c, "Bang-Bang", under the direction of a Qualified Nuclear Engineer only.

8. Average Tave should be maintained within 3ºF of Tref during steady state and routine operation. If a Tave - Tref deviation of 4ºF occurs, take action to restore Average Tave. This administrative limit does not apply during coastdown if there was a cycle specific coastdown evaluation performed.

9. Coastdown occurs when the core burnup reaches a point where maximum power can no longer be maintained. To compensate for fuel depletion, load reductions or Average Tave drooping are required.

10. If the Process Computer Xenon Follow program has been suspended or interrupted for any reason within the past 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> do not use its output without approval from a Qualified Nuclear Engineer. The U1500 series computer points are all governed by this program. The PDMS Monitor Xe 24 Hour Trend Screen is also available.

3

1BwGP 100-8 Revision 28 Reference Use F. MAIN BODY

0. Procedure Overview

a. The steps of this procedure are independent of each other. Perform the applicable step(s).

b. The steps of the procedure perform the following:

Step F.1: I Control During Steady State Power Operation Step F.2: I Control During Power Ascension Following Startup Step F.3: I Control During Power Descension Step F.4: I Control During Xenon Oscillations Step F.5: I Control During Load Follow Operations Using the Spinning Reserve Strategy (SPINR)

Step F.6: RCS Temperature Control Step F.7: Full Power Maintenance Step F.8: Generic Coastdown Guidelines Step F.9: Core Control Considerations for Operation with a Positive Moderator Temperature Coefficient (PMTC)

Step F.10: Rod Control Operation Step F.11: Minor Load Adjustments 4

1BwGP 100-8 Revision 28 Reference Use NOTE Initiate boration/dilution operations early to allow sufficient time (ie.,

approximately 7 minutes) for the operation to take effect.

F. 1. I Control During Steady State Power Operation:

It is the NSOs responsibility to ensure that I is maintained near the Target Value. I should be maintained within 3% of the Target Value.

This applies to all power levels at steady state operation. Reactor Engineering guidance, however, may be implemented prior to a measurement of I for the purpose of generating new I Targets. Under these situations, I may be allowed to be "off" target, but within 3%, in order to position control banks at the appropriate bite position.

Maintaining I near target, regardless of whether or not PDMS is OPERABLE, maintains core power distribution and the associated peaking factors in a desired condition. It is highly unlikely any PDMS Limits will be exceeded if I is maintained within limits. Maintaining I near target at all times helps prevent divergent power distribution oscillations during steady state and undesirable power distributions following transient conditions. Furthermore, should PDMS become INOPERABLE at any time, I needs to be under control when the AFD LCO becomes applicable.

Several different factors influence power distribution and hence I. The most important of these factors are listed below and should be considered when controlling I.

a. Rod Position

1) In general, rod withdrawal alone causes I to become more positive. Rod withdrawal, coupled with boration to maintain Tave, will have an enhanced effect on I.

2) In general, rod insertion alone causes I to become more negative.

Rod insertion, coupled with dilution to maintain Tave, will have an enhanced effect on I.

3) Exceptions to these rules sometimes occur when a given control bank is inserted below midcore position. In this case, further rod insertion may have a reduced effect on I, and even result in I becoming more positive. This is usually seen when CBD is inserted below 130 steps down to about 90 steps or until CBC reaches a bite position. Once CBC reaches a bite position, further rod insertion should once again cause I to become more negative.

5

1BwGP 100-8 Revision 28 Reference Use F. 1. b. Turbine (or Steam Dump) Power

1) A rise in turbine power causes I to become more negative. A rise in turbine power coupled with rod withdrawal to maintain Tave, will have a reduced effect on I. In fact, the net effect may be a positive movement of I. A rise in turbine power, coupled with a dilution to maintain Tave, will have an enhanced effect on negative movement of I.

2) A reduction in turbine power causes I to become more positive. A reduction in turbine power coupled with rod insertion to maintain Tave, will have a reduced effect on I. In fact, the net effect may be a negative movement of I. A reduction in turbine power, coupled with a boration to maintain Tave, will have an enhanced effect on positive movement of I.

3) The reason for these effects is that the incremental change in density of water is greater at higher temperature. These effects are greater at end of core life because MTC is more negative.

c. Temperature (Boration and Dilution)

1) A Tave rise due to a dilution causes I to move negative. A dilution, coupled with rod insertion to maintain Tave, will have an enhanced effect on negative movement of I.

2) A Tave drop due to a boration causes I to move positive. A boration, coupled with rod withdrawal to maintain Tave, will have an enhanced effect on positive movement of I.

3) The reason for these effects is that the incremental change in density of water is greater at higher temperature. These effects are greater at end of core life because MTC is more negative.

6

1BwGP 100-8 Revision 28 Reference Use F. 1. d. Xenon Distribution

1) As I is caused to move positive (through any of the above means),

the neutron flux rises in the top of the core, causing a rise in Xenon burnout and a rise in Iodine production. Since the production of Xenon from Iodine is a delayed process, the initial result is a reduction of Xenon in the top of the core. This causes a further rise in power in the top of the core. At the same time, the bottom of the core is undergoing the exact opposite phenomena. The resulting effect of a rising I is an initial further rise in I.

As the raised Iodine concentration's production of Xenon in the top of the core catches up to the burnout and decay of Xenon, the Xenon concentration in the top of the core will begin rising again back toward its equilibrium value for the core conditions. The bottom of the core is again undergoing the exact opposite phenomena. The net result is an axial oscillation with a period of approximately 26 hours3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br />. This oscillation usually is convergent.

2) A negative movement in I (through any of the above means) will result in the opposite phenomena.

e. Burnup The beginning of life I is largely dependent on the axial burnup distribution of the fuel assemblies reloaded into the core. The I then usually drops early in cycle life since the Integral Fuel Burnable Absorber (IFBA) burns out heaviest in the bottom of the core. After the fuel depletion in the bottom of the core is matched by the IFBA burnup in the top of the core, I will reach its minimum value for the cycle and then move positive throughout most of the remainder of the fuel cycle.

Exceptions to this general rule occur when the fuel loaded into the core from the previous fuel cycle had experienced an abnormal axial burnup profile.

During coastdown, I continues to move positive until end of cycle. This is because power is incrementally reduced to maintain Tave while control rods are maintained nearly fully withdrawn.

The effects of the normal I control methods (rod motion, turbine load changes, and boron concentration changes) vary during core life. In general, the effects of all 3 methods rises over core life because the core power distribution shifts from the middle of the core to the extreme ends at end of life. This accentuates the temperature effects between the top and bottom of the cores and it raises the differential rod worth at the nearly fully withdrawn position.

7

1BwGP 100-8 Revision 28 Reference Use F. 1. f. Crud Induced Power Shift (CIPS)

The presence of boron-holding crud can affect the power of the afflicted assemblies and the core average I.

Axial Offset Anomaly (AOA) crud is now known as Crud Induced Power Shift (CIPS). During the first third of the fuel cycle, the crud formations have not attained the critical thickness to trap boron and lithium. However, once the critical thickness is reached and boron and lithium are trapped in the crud, the boron absorbs neutrons and suppresses the neutron flux and power in the crud region. A mild case of CIPS will shift the I more negative by up to 3%. Moderate to severe cases of CIPS can shift I more negative by ~ 4% to over 10%. Over time and burnup, this flux suppression results in less burnup in the upper regions of the affected fuel. Left unperturbed, the boron in the CIPS crud becomes depleted (B-10 depletion) and can have a lessened effect on core power shape over time.

Boron-depleted CIPS crud can undergo a significant change from physical, chemical, or thermal perturbations. The boron in the crud, or even the crud itself, can be displaced. These perturbations result from changes to power level, RCS Tave, pH or lithium concentrations, or by mechanical agitation (rod exercises or trips). If the crud structure remains intact, the return to normal full power conditions will result in fresh boron from the RCS, with little B-10 depletion, returning to the crud. This has a renewed, enhanced suppression effect on the CIPS fuel in upper core region.

If the crud structure is not preserved and the crud is physically removed from the CIPS fuel, the boron cannot quickly return and the upper portions of the CIPS fuel becomes more reactive. The net effect of the crud removal can result in a I shift in the positive direction. In summary, if CIPS crud is present, the core I can shift in either a more negative or more positive direction depending upon what happens to the crud.

As indicated above, the boron can be released from the CIPS crud at reduced powers. This can have a significant positive impact on the reactivity of the upper portions of the core after a power reduction. Under moderate CIPS and changing xenon conditions, the control rods may have insufficient worth to counteract the positive reactivity additions occurring in the upper regions of the fuel. In this case, I may rise regardless of the control rod movements.

The loss of CIPS crud after a shutdown can also have positive reactivity effects on the core. Both the SDM and ECC can be affected in a non-conservative manner. Existing margins and methodologies normally provide adequate compensation for the additional positive reactivity. However, Reactor Engineering can help quantify the effects of CIPS and provide guidance on how to treat these situations on a case-by-case basis.

8

1BwGP 100-8 Revision 28 Reference Use F. 2. I Control During Power Ascension Following Startup:

a. VERIFY/PLACE Control Bank D (by boration/dilution) well above the RIL but low enough to maintain I within the Tech Spec limits.

b. DETERMINE the change in boron concentration required to accomplish the desired power level change, accounting for Xenon, rod position, and Power defect (BwCB-1, Figures 2, 7, 8a, 8c, and 17a).

c. DETERMINE the number of gallons of Primary Water required to reach the new boron concentration (BwCB-1, Table 3-1).

NOTE The dilution rate or control rod position may need to be changed periodically to maintain I within the Tech Spec band about the Target/AFD Control Band.

d. INITIATE the dilution required to achieve the desired power change and yet maintain I within the Tech Spec limits.

e. Once the power level is reached, ADJUST the boron concentration to compensate for Xenon building/burnout and to maintain I at or near the Target/AFD Control Band Value.

9

1BwGP 100-8 Revision 28 Reference Use F. 3. I Control During Power Descension:

NOTE Proper control of the axial power distribution during reductions in power followed by a return to full power requires more than just maintaining I near the Target Value. The core average flux shape needs to maintained to prevent a I oscillation after the power reduction is complete. The core average flux shape can be monitored through Computer point PDMA02, which is in terms of Axial Offset. Axial Offset can be correlated to I by the following relationship:

Axial Offset = 100%

• I / Power (%)

Consequently, the Target Value for Axial Offset is a constant value and does not change with a change in power level as the I Target Value does.

The insertion of Control Bank D causes the top Power Range detectors to be shadowed and may result in a lower NIS axial offset as provided by PDMA02.

For this reason, during a downpower maneuver, it is generally advantageous to control I lower than the Target Value to be able to maintain the core average Axial Offset (Computer point PDMA02) at a nearly constant value. A general rule of thumb-rule would be to control I the same amount below the Target Value as computer point PDMA02 rises above its pre-ramp value. This strategy should be pursued unless I is about to exceed one of the limits specified in this procedure, at which time I should be controlled to within those limits.

NOTE Rapid power reductions or rejections may require immediate boration and Control Rod insertion in order to maintain I within RAOC Limits.

a. DETERMINE the change in boron concentration required to accomplish the desired power level change, accounting for Xenon, rod position, and Power Defect (BwCB-1, Figures 2, 7, 8a, 8c, and 17a).

10

1BwGP 100-8 Revision 28 Reference Use F. 3. b. DETERMINE the number of gallons of boric acid required to reach the new boron concentration (BwCB-1, Table 3-1).

NOTE The boration rate or Control Rod position may need to be changed periodically to maintain I within the admin band about the Target value.

c. DETERMINE and INITIATE the boration rate required to achieve the desired power change in the desired time interval and yet maintain I within the admin band about the Target value (BwCB-1, Figure 19).

d. ONCE the power level is reached, ADJUST the boron concentration as necessary to maintain I on the Target Value.

11

1BwGP 100-8 Revision 28 Reference Use F. 4. I Control During Xenon Oscillations:

CAUTION One key point associated with any of these methods is to initiate all control actions early to allow sufficient time for the required boration or dilution operations.

Furthermore, these methods are more tolerant of early control initiation rather than delayed action. Therefore, when in doubt, begin the control actions early. The resulting residual oscillations will usually be much less severe if you do.

a. Half - Cycle Dampening:

The half-cycle dampening method of I control is more of a maintenance strategy than a control strategy. This method is based on the maintenance of the Iodine and Xenon concentrations in their equilibrium condition. This is accomplished by maintaining I on or near target at all times. For those occasions when I is off target, this control strategy calls for action to restore I to target (See Figure 3). In general, this method can restore I to its equilibrium condition slightly faster than Hook 'n Drag, but this method is more costly in terms of boric acid and primary water use.

1) MONITOR actual and target I values on an hourly basis using PPC, process computer delta flux program, or some other method whenever a I oscillation is in progress.

NOTE Changing Tave several degrees can also supplement the suppression of the I oscillation. Reducing Tave will cause I to become more positive (less negative) and raising Tave will cause I to become more negative (less positive).

2) As I reaches the Target Value and continues to move in the positive direction, TAKE MANUAL control of the rods and STEP them inward in small increments at frequent intervals to maintain I on the Target Value. IF I is moving in the negative direction, STEP rods outward in small increments.

12

1BwGP 100-8 Revision 28 Reference Use CAUTION With Rods in Manual, Tave must be controlled with dilution/boration operations.

F. 4. a. 3) DILUTE/BORATE as necessary to maintain Tave equal to Tref.

4) ONCE Xenon has peaked (approximately 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />), MANUALLY ADJUST rods outward/inward in small increments at frequent intervals to maintain I on the Target Value.

5) DETERMINE whether the amplitude of the negative and positive I peaks are dampening. IF they are not dampening, CONTACT Reactor Engineering.

6) BORATE/DILUTE as necessary to maintain Tave equal to Tref.

NOTE As the Xenon oscillation is suppressed, the frequency and/or magnitude of rod motion needed to maintain I on the Target Value will drop.

7) PLACE rods in AUTO, or as determined by the Unit Supervisor, once the oscillation has been suppressed and I is on the Target Value (approximately 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> after initial rod movement).

13

1BwGP 100-8 Revision 28 Reference Use F. 4. b. Hook 'n Drag The Hook 'n Drag method of I control is based on the mechanics of harmonic oscillation. It is used to stress I back to its target after a I oscillation already exists. This is accomplished by decelerating I when I is already accelerating toward its target (See Figure 4). In general, this method restores I to its equilibrium conditions slower than Half Cycle Dampening, but this method is much less costly in terms of boric acid and primary water use.

1) MONITOR actual and target I values on an hourly basis using PPC, process computer delta flux program, or some other method whenever a I oscillation is in progress.

NOTE Changing Tave several degrees can also supplement the suppression of the I oscillation. Reducing Tave will cause I to become more positive (less negative) and raising Tave will cause I to become more negative (less positive).

2) AFTER I rounds the top peak of the oscillation and accelerates down toward the Target Value, TAKE MANUAL control of the rods and STEP them outward in small increments at frequent intervals to slow I's descent on the Target Value. IF I is moving in the positive direction, STEP rods inward in small increments.

CAUTION With rods in MANUAL, Tave must be controlled with dilution/boration operations.

3) DILUTE/BORATE as necessary to maintain Tave equal to Tref.

4) ONCE I has passed the target and shows signs of decelerating on its own (approximately 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />) CEASE rod motion. The use of rod motion just prior to a peak is limited to those times when I would otherwise exceed an established limit.

14

1BwGP 100-8 Revision 28 Reference Use NOTE As the Xenon oscillation is suppressed, the frequency and/or magnitude of rod motion needed to maintain I on the Target Value will reduce.

F. 4. b. 5) PLACE rods in AUTO, or as determined by the Unit Supervisor once the oscillation has been suppressed and I is on the Target Value (up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after initial rod movement).

CAUTION Perform the following section under the direction of a Qualified Nuclear Engineer.

NOTE The following steps suppress axial Xenon oscillations by utilizing the Bang-Bang method. This control procedure must be used judiciously, because timing is essential. Half Cycle Dampening is the preferred control method. The Bang-Bang method of control is based on the theory that during a Xenon oscillation, there are two relatively short periods of time during which a single rod control action results in simultaneous stressing of the Xenon and Iodine offsets. This behavior is predictable only during unforced oscillations.

NOTE The Bang-Bang method can be initiated at either a positive I peak or a negative I peak. Perform step F.4.c.1) if performing at a positive peak and step F.4.c.2) if performing at a negative peak.

c. Use of the Bang-Bang method to control an axial Xenon oscillation.

1) Bang-Bang at a positive I peak (I is above target value).

a) FOLLOW the free oscillation as I starts to approach its positive peak. By considering the rate of change of the I slope with time, ESTIMATE when I will be one hour before the peak.

15

1BwGP 100-8 Revision 28 Reference Use NOTE Pauses between rod motion increments should be limited to ensure the maximum effect of the dampening sequence.

NOTE Begin this control action 10 to 15 minutes early to account for delays in changing boron concentrations. It is much better to begin this step too early than too late. It is better to not start than to start too late.

NOTE Step F.4.c.1)c) may be skipped at the discretion of a Qualified Nuclear Engineer. It may be possible to maintain I on target without performing step F.4.c.1)c) depending on the magnitude of the oscillation.

F. 4. c. 1) b) WHEN I is approximately one hour before the peak, or as determined by a QNE, INSERT the control rods in 10 step increments WHILE monitoring reactor response for the desired/expected results until I is at its target value

(+0.25% AFD) or per the QNE. COMPENSATE for rod insertion by dilution.

c) MAINTAIN the control rod position and ALLOW I to drift in the negative direction. WHEN I has drifted below the target value by an amount approximately equal to the amount it was above target in step F.4 .c.1)b), ADJUST the boron concentration to WITHDRAW control rods to return I to its target value.

d) MAINTAIN I at its target value by movement of control rods WHILE maintaining temperature through boration or dilution as appropriate.

16

1BwGP 100-8 Revision 28 Reference Use F. 4. c. 2) Bang-Bang at a negative I peak (I is below target value).

a) FOLLOW the free oscillation as I starts to approach its negative peak. By considering the rate of change of the I slope with time, ESTIMATE when I will be one hour before the peak.

NOTE Pauses between rod motion increments should be limited to ensure the maximum effect of the dampening sequence.

NOTE Begin this control action 10 to 15 minutes early to account for delays in changing boron concentrations. It is much better to begin this step too early than too late. It is better to not start than to start too late.

NOTE Step F.4.c.2)c) may be skipped at the discretion of a Qualified Nuclear Engineer. It may be possible to maintain I on target without performing step F.4.c.2)c) depending on the magnitude of the oscillation.

b) WHEN I is approximately one hour before the peak, or as determined by a QNE, WITHDRAW the control rods until I is at its target value (+0.25% AFD) or per the QNE.

COMPENSATE for rod withdrawal by boration.

c) MAINTAIN the control rod position and ALLOW I to drift in the positive direction. WHEN I has drifted above the target value by an amount approximately equal to the amount it was below target in step F.4.c.2)b), ADJUST the boron concentration to as needed to INSERT control rods to return I to its target value.

d) MAINTAIN I at its target value by movement of control rods WHILE maintaining temperature through boration or dilution as necessary.

17

1BwGP 100-8 Revision 28 Reference Use F. 4. d. PDMS Xenon Mode:

The PDMS Xenon Mode method of I control is a combination of the Hook

'n Drag and Bang-Bang methods. The Xenon Mode control method provides a method by which the spatial xenon trends can be anticipated and therefore controlled efficiently. The use of this method is predicated on the availability of an operable PDMS Monitor display. If PDMS is unavailable in the Main Control Room, a Qualified Nuclear Engineer shall access the Xenon Mode display from another available workstation (See Figure 6).

NOTE The axes of the Xenon Mode display are reversed (negative values on the top and right sides and positive values on the bottom and left sides of the origin).

The Xenon Mode display will show the current d(Xe)/dt value as a function of Xe as a small square with a "tail" indicating the previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. With an undamped axial xenon oscillation occurring, the small square will move in a circle around the origin (central point) in the clockwise direction. The larger the oscillation, the larger the circle. Rod insertion has the effect of causing the current value to move vertically down and rod withdrawal has the effect of causing the current value to move vertically up on the display.

18

1BwGP 100-8 Revision 28 Reference Use NOTE Although rod motion can be initiated at any time within the yellow (upper right/bottom left) quadrants of the Xenon Mode display, optimal results are obtained when rod motion is initiated when the current value has left the green portion of the "Bow Tie" (the green and yellow interface).

NOTE The PDMS displays only update once per minute. Therefore, actions should be performed in a controlled manner, allowing for the display to register feedback prior to initiating subsequent action.

F. 4. d. 1) WHEN the current value, as indicated by the small square, leaves the green portion of the "Bow Tie", PERFORM the following:

a) IF the current value is at the top of the display (negative d(Xe)/dt), THEN INSERT the control rods until the current value is approximately moved half-way toward the origin.

Compensate for rod insertion by boron dilution.

b) IF the current value is at the bottom of the display (positive d(Xe)/dt), THEN WITHDRAW the control rods until the current value is approximately moved half-way toward the origin. Compensate for rod withdrawal by boration.

2) AFTER the small square traverses its arc 180 and reaches the opposite edge of the green portion of the "Bow Tie", PERFORM the following:

a) IF the current value is at the bottom of the display (positive d(Xe)/dt), THEN WITHDRAW the control rods until the current value is at approximately the origin. Compensate for rod withdrawal by boration.

b) IF the current value is at the top of the display (negative d(Xe)/dt), THEN INSERT the control rods until the current value is at approximately the origin. Compensate for rod insertion by boron dilution.

3) PLACE rods in AUTO, or as determined by the Unit Supervisor, once the oscillation has been suppressed and I is on the Target Value (up to 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> after initial rod movement).

19

1BwGP 100-8 Revision 28 Reference Use F. 5. I Control During Load Follow Operations Using the Spinning Reserve Strategy (SPINR):

NOTE This method minimizes boron concentration changes in order to promote rapid return to power. The following steps should be used when a rapid return to power is expected during the load follow.

Normal load follow operations can be done by using the applicable portions of F.2 and F.3.

NOTE Maintaining I more negative than the target following the power descension will provide additional reactivity from rods to facilitate a rapid return to power when desired.

a. For a power descension, ALLOW rods to insert as Turbine Power drops to force I more negative than the Target.

b. ONCE the desired power is reached, ADJUST the boron concentration as necessary to maintain I within BwCB-1, Figure 19 limits. USE the applicable portions of steps F.2 and F.3.

NOTE After the power ascension, maintaining I more positive than the Target will offset the preferential burnup in the bottom of the core as a result of the highly negative I from the reduced power level. This should be performed if SPINR is used frequently, otherwise control I within the operating band about Target value.

c. For a power ascension, ALLOW rods to step out to facilitate the power change and to force I more positive than the Target.

20

1BwGP 100-8 Revision 28 Reference Use NOTE A dilution may be required in addition to rod movement to accomplish the power change. Use applicable portions of steps F.2 and F.3 as necessary.

F. 5. d. MAINTAIN I more positive than the Target for as long a period as it was kept more negative.

e. ONCE the power level is reached, ADJUST the boron concentration as necessary to compensate for the changing Xenon concentrations.

f. RETURN I to the Target Value once the preferential burnup has been offset.

21

1BwGP 100-8 Revision 28 Reference Use F. 6. RCS Temperature Control:

NOTE According to Nuclear Fuel Management (NFM), RCS Tave is assumed to be maintained either by the Reactor Control system in automatic or with a similar strategy via manual control.

a. For steady-state and routine operation, MAINTAIN the following conditions:

The reactor is designed and expected to be operated with average Tave equal 1F to Design Average Temperature for the Cycle (as established in Fig. 35 of BwCB-1).

Auctioneered High Tave within dead band of automatic rod control.

Average Tave should not be allowed to exceed 588F.

b. Philosophy behind Tref bias:

The rod control system design for Braidwood uses High Auctioneered Temperature Average (HI Tave) being compared to Tref (as determined by turbine power) to move control rods in or out of the core depending on the polarity of the temperature mismatch error, Terr. Since each loop has a different full-power Tave, the average of all four loop Taves (AVG-Tave ) will always be less than the HI-Tave value. This results in the Unit running slightly less than the design full-power Tave when HI Tave and Tref are matched (i.e. 0 deg F Terr) thus producing less S/G pressure. By using a Tref bias (which accounts for the offset of loop Tave differences at full-power), the AVG-Tave will be closer to the design Tave of the core for a given cycle.

For Unit 1 and Unit 2 (when at full-power), matching HI-Tave to Tref, should result in AVG-Tave matching core design Tave.

Per the core design philosophy, while at full power, units are expected to be operated at their respective design core average temperatures - AVG Tave (587 F for Unit 1, 581 F for Unit 2). Based on current BWD configurations, this results in an approximate 0 deg F Terr for Unit 1 and Unit 2.

22

1BwGP 100-8 Revision 28 Reference Use F. 6. c. IF Average Tave is > 3F from Tref but within 4F of Tref, TAKE ACTION to return Average Tave to be within 3F of Tref as conditions allow (generally within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />).

d. IF Average Tave is > 4F from Tref, TAKE ACTION to restore Average Tave to be within 4F of Tref.

e. Under coastdown conditions or other special circumstances, specific neutronic and safety analyses may be performed to allow Average Tave to differ from Tref by more than 4F. These analyses and temporary Average Tave limitations will be identified on a cycle-specific basis, typically via a ReMa form.

This guidance reflects administrative controls for the Operations Department to support assumptions contained in the nuclear core design basis. These are not Tech Spec limits.

The 3F tolerance, however, does not apply to long term operation. Long term operation at a Average Tave different than assumed during the fuel cycle design can lead to fuel burnup that does not conform to the cycle specific safety analysis. Small variations from the set temperature, with plant operation following good industry standard, are allowed. It is acceptable if the difference between the nominal average temperature of the plant and nominal designed temperature is less than 1F, as long as the design temperature band of 575F to 588F, used in the safety analysis is maintained.

Although not usually a safety concern, Average Tave should be maintained within 4F of Tref. Should Average Tave deviate by more than 4F, action should be taken to restore Average Tave, although it should be understood that the severity of a mismatch of greater than 4F is less at reduced power.

23

1BwGP 100-8 Revision 28 Reference Use F. 6. f. The following methods of temperature control are at the disposal of the NSO:

1) To raise Tave:

DILUTE the RCS.

WITHDRAW control rods.

RAISE DEHC ramp rate when ramping down.

LOWER DEHC ramp rate when ramping up.

Momentarily HOLDING a ramp when ramping up.

REDUCE Turbine load.

2) To reduce Tave:

BORATE the RCS.

INSERT control rods.

RAISE DEHC ramp rate when ramping up.

REDUCE DEHC ramp rate when ramping down.

Momentarily HOLDING a ramp when ramping down.

RAISE Turbine load.

g. Although entirely optional, BwCB-1, Figure 35, can be used to estimate a bounding value for the amount of boration or dilution necessary to offset the changes in reactivity due to power defect when anticipating a power change.

24

1BwGP 100-8 Revision 28 Reference Use F. 7. Full Power Maintenance:

NOTE Thermal power for each unit shall be maintained < 100% RTP, normally indicated by the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> calorimetric. In order to maintain thermal power as close to 100% RTP without exceeding 100% RTP, the following guidance is provided.

a. Steam Generator Blowdown:

When Steam Generator Blowdown is raised from 0 gpm to 300 gpm total flow, the indications for calorimetric power will initially drop approximately 0.1% RTP. This effect is transitory in nature and lasts approximately 10 minutes. This effect is caused by the sluggishness of the Feed Reg system in maintaining Steam Generator level. After the initial drop in indicated power, steam generator levels will be restored and the secondary side of the plant will reach equilibrium, with the net effect of saturated water being taken from the Steam Generator and ultimately returned to the condenser. The long term net effect of initiating 300 gpm blowdown flow is a rise in thermal power of 0.5%. For this reason, thermal power should be confirmed to be less than 100% RTP by an appropriate amount prior to raising steam generator blowdown flow. The thermal power will change proportionally to changes to steam generator blowdown flow.

When Steam Generator Blowdown is isolated from an initial flow rate of 300 gpm total flow, the indications for calorimetric power will initially rise approximately 0.1% RTP. This effect is transitory in nature and lasts approximately 10 minutes. This effect is caused by the sluggishness of the Feed Reg system in maintaining Steam Generator level. After the initial rise in indicated power, steam generator levels will be restored and the secondary side of the plant will reach equilibrium. The long term net effect of isolating 300 gpm blowdown flow is a drop in thermal power of 0.5%. Should Steam Generator Blowdown be isolated for a significant period of time, consideration may be given to raising turbine load as applicable to maintain full power. The effects of re-initiating Steam Generator Blowdown, however, must be considered per the above paragraph. The thermal power will change proportionally to changes to steam generator blowdown flow.

25

1BwGP 100-8 Revision 28 Reference Use F. 7. b. Aux Feed:

When Aux Feed flow is initiated at 1320 gpm to the Steam Generators with the turbine on line, the initial indications from NIS will be a drop in power because of the drop in Tcold, although the post transient actual thermal power will rise approximately 3% RTP. More importantly, however, the Aux Feed flow to the Steam Generator amounts to unmeasured mass input into the heat balance and the calorimetric calculation will be non-conservative by that amount. For this reason, a derate of the unit is appropriate for any Aux Feed flow during power operation.

The opposite occurs when Aux Feed flow is terminated.

c. DEHC Programming While at Steady State Unless DEHC is being programmed for another operation, a 5 MW ramp down at 5 mw/min should be programmed into DEHC as a contingency for an unexpected fast moving reactivity event with the potential to overpower the reactor. This ramp is not intended to replace ramps directed by annunciator response or BwOAs for specific equipment malfunctions.

This contingency should be included as part of an early shift reactivity briefing by the Reactor Operators and the Unit Supervisor. This is a desired state whenever the unit is operating near a power limit or restriction.

d. LEFM Full Power Operation Limit calorimetric to 100.0% on LEFM and Venturi.

If the LEFM fails, maintain Venturi power at or below the Venturi power level just prior to the LEFM failure and less than 100.0%.

26

1BwGP 100-8 Revision 28 Reference Use F. 8. Generic Coastdown Guidelines:

Coastdown occurs when the core burnup reaches a level where maximum power cannot be maintained. During this period, Tave can be expected to drop approximately 1F every day. To compensate for fuel depletion, load reductions of about 1 to 2% per day may be required after Tave has dropped to 2F below Tref. If a cycle specific coastdown evaluation has been performed, Tave may be allowed to drop below Tref by whatever the nuclear design and safety analysis will support. This information will be provided on a cycle specific basis.

a. Boron concentration should be diluted as low as achievable (approximately 10 ppm or less).

NOTE Deviations may be required due to unexpected situations, at which point a Qualified Nuclear Engineer should be consulted. (QNE)

b. MAINTAIN the following AT ALL TIMES:

I within 2% of its positive limit or as directed by a QNE.

Tave within +/- 5F of Tref (based on computer points T0496, T0499, U0689 and main control board indications). A cycle specific Safety Analysis value for maximum deviation may replace this value.

The following computer points can be used for monitoring maximum deviation:

U9010 Tmin from Calorimetric Power (10 min)

U9011 Tmin from NIS Power (10 min)

U9012 Tave - Tmin (from 10 min Cal Power)

U9013 Tave - Tmin (from NIS Power)

Control Bank D should be maintained between 210 and 220 steps or as directed by a QNE.

Rod Control in Manual.

Boron concentration diluted as low as achievable depending on above parameters.

27

1BwGP 100-8 Revision 28 Reference Use F. 8. c. Steady-State Conditions

1) During coastdown rods will be maintained at approximately 215 steps withdrawn in manual control. This partial insertion will give the operators control over I during Xenon oscillations. RODS SHOULD NOT BE USED TO MAINTAIN I ON THE TARGET VALUE. Instead, operators should allow I to slowly drift positive while rods are held constant. Control rods may then be inserted to maintain I at least 2% from its positive limit or as directed by a QNE.

2) Operators should minimize control rod motion during coastdown as axial Xenon oscillations are easily induced. Operators should minimize control rod motion to a maximum of two steps per shift unless absolutely needed for the maintenance of I within its limits.

It is recommended the operators review the I trend during the past 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to rod motion to determine if rod motion will propel an existing oscillation. Remember, the differential worth of Control Bank D is much greater at end-of-cycle conditions than at any other time during the cycle. This is due to the axial flux profile being biased toward the top of the core (as indicated by a positive Target Axial Offset) and rod worth is proportional to the square of the flux.

This limitation on rod motion, however, does not preclude the performance of quarterly rod exercises.

3) Power should not be reduced by more than 1% per shift if possible.

This will minimize the change to I. Also, remember that Xenon reactivity will initially rise following a load reduction.

4) If possible, load reductions should be performed while I is either constant or lowering. This will tend to dampen any I swings.

5) Control Bank D should be maintained between 210 and 220 steps.

When the steady state rod position approaches 210 steps, Reactor Engineering will update the I Target values so that CBD may be further withdrawn. Control rods should be used for I maintenance only, control rods should not be moved for Temperature control.

6) MWe 'OUT' is the preferred choice of operation during steady-state operation at coastdown. However, the choice is entirely up to the NSO, Unit Supervisor, and Shift Manager as to which MODE they wish to operate at. MWe 'OUT' is preferred so that secondary perturbations will have a reduced effect on the reactor.

28

1BwGP 100-8 Revision 28 Reference Use F. 8. d. Non-Steady State Condition The reactor will become increasingly more of a challenge to control due to two factors:

1. 1. The inability to dilute out the soluble boron due to the very low boron concentration.

1. 2. The "double hump" shape of the reactor flux due to the center of the core being more highly burned.

Phenomena that will be experienced during coastdown will be a raised sensitivity to Xenon oscillations, sagging Tave, and a steadily rising AFD.

The guidelines presented below are intended to reduce Xenon induced AFD oscillations in light of the reduction of suppression capability and to maximize fuel economy.

1) Due to the inherent Xenon instability of the reactor in End of Life conditions, Control Rod motion will have a greater effect on AFD and may induce an AFD oscillation. For this reason, Control Rods should not be used to control Tave or to maintain AFD on target.

Control Rod motion should only be used to stabilize AFD oscillations.

2) Changes in turbine power should also be limited to small periodic increments since these changes will have an impact on AFD oscillations. Therefore, power changes should not normally exceed 8 MWe per shift.

3) Due to the double humped shape of the flux in the core, the top and bottom of the core becomes de-coupled, Control Bank D (CBD) differential worth becomes very high, and Tave changes have a much larger effect on AFD. For these reasons, AFD oscillations are capable of being initiated very easily. Therefore, Control Rod motion and substantial power changes should be avoided. During coastdown, AFD oscillations tend to become divergent; thus actions to dampen oscillations should be performed as early as practical.

29

1BwGP 100-8 Revision 28 Reference Use F. 8. d. 4) Control Bank D should be maintained at approximately 215 (210-220) steps in order to have sufficient differential rod worth to dampen an AFD oscillation but not add too much negative reactivity. The following parameters should be monitored: Reactor Power, Average Tave Mismatch, CBD Position and AFD, to identify a developing oscillation such that the least amount of Control Rod motion, or preferably, strategic power reductions can be used to minimize the oscillation. Generally, Control Rod usage should be limited to 2 steps per shift, if at all possible.

5) In the event and AFD oscillation is induced, use either the half-cycle dampening technique or the "Hook and Drag" technique described in Section 4 of this procedure to stress AFD to its last known steady state value. Power reductions may be used to stress AFD positive instead of CBD withdrawal when CBD is greater than 215 steps. A 1-to-3 MWe load reduction will cause AFD to rise 0.05 to 0.10%.

e. Summary of Recommendations:

The following table summarizes the recommendations contained in these guidelines:

Limit to 2 steps/shift and attempt to Control Rod Motion maintain at approximately 215 (210-220) steps withdrawn.

Reduce in 1 - 2 Mwe increments at 0.1 Turbine Load - 0.2 MWe/min when AFD is steady or lowering.

RCS Tave (U8062 for Avg Tave - Tref) or U9010 = Tmin (10 min cal) Allow to drop up to 3.5 - 4.0F (or as specified in the cycle specific NF safety U9011 = Tmin = (NIS) analysis) from Tref before initiating a turbine load reduction.

U9012 = Tave - Tmin (10 min Cal)

U9013 = Tave - Tmin (NIS)

Use CBD motion if AFD is near 2% of AFD the RAOC upper limit, or as determined by a QNE.

30

1BwGP 100-8 Revision 28 Reference Use F. 9. Core Control Considerations for Operation with a Positive Moderator Temperature Coefficient (PMTC):

Technical Specification LCO 3.1.3 allows a MTC of up to +7 pcm/F. A cycle specific value will be contained in the Core Operating Limits Report (COLR). The MTC will vary with reactor power and burnup, becoming less positive with rising power levels (see Figure 1). The expected maximum values to be seen will be

+3 to +5 pcm/F. Figures 1 and 2 were calculated using data from a +2.5 pcm/F design. These are considered representative of MTC behavior.

It is important to remember that reactor behavior is governed by Isothermal Temperature Coefficient (ITC), of which the MTC is one component. ITC is typically 1.5 to 2 pcm/F more negative/less positive than the MTC due to the Doppler contribution. Figure 2 demonstrates ITC behavior. It should be noted that ITC will likely be negative for power operation, with the exception of low power levels early in the cycle life.

Control of reactor power will likely be more difficult at low power levels when ITC is positive. The response to temperature changes will only feedback to change the temperature more, in the same direction. To help deal with the concerns, the following guidance is given. Additional guidance can be obtained from Reactor Engineering, as needed.

a. Only one method of positive reactivity addition should be used at a time, if possible.

b. Tave - Tref mismatch should be kept at a minimum. This will reduce the correction made by control rod motion, as temperature deviations will tend to build on themselves.

c. Make power changes slowly and deliberately. When making changes, pause between reactivity maneuvers to regain stability.

d. Steam demand will still drive reactor power, however with a +MTC, rising steam demand (causing a Tave drop) will reduce reactor power.

e. With the Steam Dumps in the Steam Pressure Mode, keeping some demand on the Steam Dumps, when making load changes, can help to keep RCS temperature more stable.

f. With the Steam Dumps in the Tave Mode, Turbine load can be adjusted to maintain Tave /Tref mismatch within limits.

g. Monitor the IR startup meters to anticipate the need for reactivity changes.

31

1BwGP 100-8 Revision 28 Reference Use F. 9. h. On the computer or PPC, trend the heatup/cooldown rate (U0800R) and an Intermediate Range NI Channel for current temperature and power trends.

i. Changes in feedwater flow should be communicated to the NSO controlling the reactor to anticipate the pending temperature change.

Communication between the Primary NSO and Secondary NSO is vital.

32

1BwGP 100-8 Revision 28 Reference Use NOTE The following step provides guidance for operation of the Rod Control System. The steps should only be used for normal operation and should not preclude the actions required to mitigate a transient.

F. 10 Rod Control Operation:

a. Automatic Rod Control:

1) VERIFY TURBINE LOW POWER INTLK C5 (1-BP-5.7) NOT ILLUMINATED.

2) VERIFY that the Rod Control direction lights are not ILLUMINATED:

RODS IN RODS OUT

3) VERIFY Tave within +/- 1F of Tref.

4) VERIFY/PLACE the Rod Bank Select switch in the AUTO position.

5) MONITOR rod control for proper response.

b. Manual Rod Control:

1) VERIFY automatic rod motion is not required.

2) PLACE Rod Bank Select switch to the MAN position.

3) Using the IN-HOLD-OUT switch, MOVE the control rods to the desired position.

4) MONITOR the following for the effects of the rod motion:

Tave Pressurizer Pressure Pressurizer Level Reactor Power

5) WHEN manual rod control is no longer required, RETURN Rod Control to AUTO per Step 10.a.

33

1BwGP 100-8 Revision 28 Reference Use F. 10. c. Steady State Manual Control Rod Operations:

1) The Reactor Operator at the controls shall exercise extreme caution when manually withdrawing control rods for steady state operations.

2) When manually withdrawing control rods in a critical reactor, the Reactor Operator at the controls SHALL stop rod withdrawal at least every three steps and check for expected response on nuclear instruments, rod position and reactor coolant temperature indication.

3) The Shift Manager/Unit Supervisor may suspend the three-step pull-and-wait when the reactivity computer is in service during the performance of physics testing or during a reactor start-up when reactor power is below the point of adding heat.

4) This sequence of actions SHALL be followed during 1BwOSR 3.1.4.2, Movable Control Assemblies Surveillance, verification of rod operability in the applicable Rod abnormal operating procedures and any troubleshooting activities at power.

5) All manual control rod manipulations shall be done in accordance with OP-AP-300-1001, PWR Control Rod Movement Requirements.

34

1BwGP 100-8 Revision 28 Reference Use NOTE The Load Swing Instruction Sheet, 1BwGP 100-4T2 is not required to be filled out when making minor (< 2%) load changes.

F. 11. Minor Load Adjustments:

DEHC in AUTO:

1) DETERMINE the required load change.

2) SELECT SETPOINT.

3) ENTER the desired Megawatt value into the REF DEMAND window.

4) SELECT left ENTER.

5) VERIFY the correct value appears in the REFERENCE DEMAND window on graphic 5501.

6) ENTER the desired MW/MIN rate into the RATE window.

7) SELECT right ENTER.

8) VERIFY the correct value appears in the RATE window on graphic 5501.

9) SELECT GO/HOLD.

10) SELECT GO.

11) VERIFY that load begins to rise or lower as desired.

12) MONITOR the following:

Reactor Power Tave Calorimetric Power

13) ADJUST RCS Boron Concentration per BwOP CV-5 or CV-6, as necessary, to maintain I within Limits of BwCB-1, Fig. 19.

35

1BwGP 100-8 Revision 28 Reference Use F. 11. DEHC in MANUAL:

1) DETERMINE the required load change.

2) Momentarily DEPRESS then RELEASE either of the following to manually adjust turbine load:

GOVERNOR V up arrow.

GOVERNOR V down arrow.

3) MONITOR the following:

Reactor Power Tave Calorimetric Power Governor Valve Position

4) ADJUST RCS Boron Concentration per BwOP CV-5 or CV-6, as necessary, to maintain I within Limits of BwCB-1, Fig. 19.

36

1BwGP 100-8 Revision 28 Reference Use FIGURE 1

• • MTC vs BURNUP AS A FUNCTION OF POWER BURNUP (GWD/MTU) 1 GWD/MTU = 24 EFPD

• • This graph should be used for guidance only. It is a generic graph, and does not represent the exact conditions and responses of Unit 1 core. Contact Reactor Engineering for further guidance.

37

1BwGP 100-8 Revision 28 Reference Use FIGURE 2

• • ITC vs. BURNUP AS A FUNCTION OF POWER BURNUP (GWD/MTU) 1 GWD/MTU = 24 EFPD

• • This graph should be used for guidance only. It is a generic graph, and does not represent the exact conditions and responses of Unit 1 Core. Contact Reactor Engineering for further guidance.

38

1BwGP 100-8 Revision 28 Reference Use FIGURE 3 Half-Cycle Dampening 39

1BwGP 100-8 Revision 28 Reference Use FIGURE 4 Hook 'n Drag 40

1BwGP 100-8 Revision 28 Reference Use FIGURE 5 Bang - Bang 41

1BwGP 100-8 Revision 28 Reference Use FIGURE 6 Xenon Mode Using PDMS 42

1BwGP 100-8 Revision 28 Reference Use ATTACHMENT A ROD CONTROL HARD CARD NOTE A review of the reactivity plan MUST be conducted and permission MUST be given by the UNIT SUPERVISOR prior to using this card for Manual Rod Control.

CAUTION Caution should be used when CBD is below 130 steps. I control is typically reduced as CBD is inserted below 130 steps until CBC reaches a bite position.

1. MANUAL ROD CONTROL:

a. VERIFY automatic rod motion is not required.

b. PLACE Rod Bank Select switch to the MAN position.

c. Using the IN-HOLD-OUT switch, MOVE the control rods to the desired position.

d. MONITOR the following for the effects of the rod motion:

Tave Pressurizer Pressure Pressurizer Level Reactor Power

e. If it is desired to return to Automatic Rod Control perform the following:

1) VERIFY TURBINE LOW POWER INTLK C5 (1-BP-5.7) NOT ILLUMINATED.

2) VERIFY that the Rod Control direction lights are not ILLUMINATED:

RODS IN RODS OUT

3) VERIFY Tave within +/- 1 F of Tref.

4) VERIFY/PLACE the Rod Bank Select switch in the AUTO position.

5) MONITOR rod control for proper response.

43

1BwGP 100-8 Revision 28 Reference Use ATTACHMENT B RAMPING HARD CARD NOTE This Hard card should only be used for emergent conditions with approval of the UNIT SUPERVISOR.

1. RECORD the desired MW LOAD ____________MW and desired RAMP RATE

__________MW/Min.

2. PROGRAM a new MW load on turbine, perform the following on graphic 5501:

a. SELECT SETPOINT.

b. ENTER desired MWs into the REF DEMAND window.

c. SELECT left ENTER.

d. VERIFY the correct value appears in the REFERENCE DEMAND window on graphic 5501.

e. ENTER desired rate into the RATE window.

f. SELECT right ENTER.

g. VERIFY the correct value appears in the RATE window on graphic 5501.

h. SELECT EXIT.

i. SELECT GO/HOLD.

j. VERIFY GO/HOLD illuminates orange.

k. VERIFY HOLD indicator illuminates red.

l. INFORM the crew of the pending ramp and rate with an UPDATE.

m. SELECT GO.

n. VERIFY GO indicator illuminates red while main turbine ramps.

(Final) 44

OP-AP-300-1004 Revision 2 Page 1 of 4 PWR BORATION AND DILUTION REQUIRMENTS

1. PURPOSE 1.1. The purpose of this T&RM is to define responsibilities and provide guidance for PWR boration and dilution evolutions.

2. TERMS AND DEFINITIONS 2.1. Approved (Governing) Procedure: as used in this document, refers to a procedure approved for use at the station, or to a document whose generation is described in and directed by a procedure approved for use at the station.

2.2. Licensed Operator: is synonymous with Reactor operator (RO), Senior Reactor Operator (SRO), or Nuclear Station Operator (NSO).

2.3. Steady-State

Reactivity Core Characteristics that are stable and behaving as expected per the core burn-up plot with stable Xenon conditions.

2.4. Non-Transient Conditions: Operations within normal station administrative parameters and guidance.

2.5. Deboration

Removal of Boric Acid from the letdown fluid by deborating demineralizers, the effluent of which is returned to the RCS. For the intent of this procedure is synonymous with Dilution.

3. RESPONSIBILITIES 3.1. Operations is responsible for all Boration and Dilutions of the Reactor Coolant System.

4. MAIN BODY 4.1. Operations shall PERFORM borations and dilutions in a deliberate, carefully controlled manner while constantly monitoring nuclear instrumentation and redundant indications of reactor power level, neutron flux, and coolant temperature (SOER 96-02).

4.2. The effects of boration or dilution must be observed in terms of resulting Control Rod motion, changes in Coolant Tave or Source Range Counts or change in Heatup/Cooldown Rate. STOP the operation if the expected response does not occur and take corrective action.

OP-AP-300-1004 Revision 2 Page 2 of 4 4.3. Operations shall PERFORM peer checking of all Main Control Room, MCR, non-transient boration and dilution evolutions. When utilizing a second SRO to support reactivity management functions related to the primary (Primary SRO), the following expectations must be adhered to:

• The Unit Supervisor must be aware of the reactivity plan.

• The Primary SRO is not required to inform the Unit Supervisor of every manipulation that is within the plan. Any deviation or unexpected response MUST be communicated to the Unit Supervisor.

• The US/Primary SRO may provide the PEER check for reactivity manipulations.

NOTE: Boration and/or dilution while shutdown, where adequate shutdown margin is assured, does not require the supervisor to be proximate to the reactor operator.

4.4. The Unit Supervisor shall ENSURE all planned MCR borations and dilutions are performed by the Licensed Operator in accordance with the governing procedure or Operator Aid. In plant activities affecting reactivity equipment shall be directed by a licensed operator.

NOTE: If a ReMA was developed for a planned Reactivity Change, Attachment 1, Reactivity Change Determination Form is not required.

4.5. Attachment 1, Reactivity Change Determination Form, shall be used:

• To ensure proper Technical Human Performance during reactivity maneuver planning.

• For reactivity changes that do not involve planned turbine load changes.

• To document each Reactivity manipulation OR, an entire shift of Reactivity manipulations during steady-state conditions as determined by the SRO.

• Alone or in conjunction with a ReMA per Shift Manager discretion.

4.5.1. Completed forms shall be forwarded to the Shift Manager.

4.6. All Reactivity manipulations shall be documented in the Unit Operator Logs.

5. DOCUMENTATION - None

6. REFERENCES

OP-AP-300-1004 Revision 2 Page 3 of 4 6.1. INPO SOER 96-02, Design and Operating Considerations for Reactor Cores

7. ATTACHMENTS 7.1. Attachment 1 - Reactivity Change Determination Form

OP-AP-300-1004 Revision 2 Page 4 of 4 ATTACHMENT 1 REACTIVITY CHANGE DETERMINATION FORM Station: _____________ Unit: 1 2 Time: _______ Date: ________

Desired change:

(Parameter, Magnitude, and Direction: Reactor Power, Rod Position, RCS Temp, Delta I, etc.)

Reason for Change:

(Temperature control, flux control, fuel burn up)

What is the method and amount required for the reactivity change?

(Bleed Tank Volume, Gallons of Dilution/Boration/Blended Flow, Rod Insertion/Rod Withdrawal steps/percent)

Inputs:

(ReMA Thumbrules, ReMA maneuver guidance, Curve Book Figure/Table, Computer based trend plot, RCS Cb, EFPD - Preparer and Reviewer should use independent inputs when possible)

Calculation of change:

(E.G. Bwd/Byr: ReMA Thumbrule identifies 20 gallons BA = 1.0°F RCS temp reduction.

Desired change = 0.5°F drop. Calculation of change: (20 gal/1.0°F)

• 0.5°F = 10 gal.,

previously used borations and dilutions)

(TMI: Procedure 1102-4 Power Operations Fig. 1, Volume of Deminerlized Water for 1% Rod Insertion)

Preparer Reviewer Approver (RO) (RO/SRO) (SRO)

Shift Manager Notified: Yes No

OP-AA-115-101 Revision 2 Page 1 of 6 Level 2 - Reference Use OPERATOR AID POSTINGS

1. PURPOSE 1.1. The purpose of this instruction is to describe the methodology for the authorization, documentation, and review of Operator Aids.

1.2. Existing Operator Aids approved under a previous revision or version of this procedure need not be re-issued upon approval of this procedure. However, any future update to an existing operator aid shall be performed in accordance with this procedure.

2. TERMS AND DEFINITIONS

2.1. Operator

An operator is broadly defined as anyone authorized to operate equipment associated with plant operation. In addition to Operations Department personnel, this definition includes Chemistry Technicians, Nuclear Engineers, System Engineers, Instrument Maintenance Technicians or other station personnel.

2.2. Operator Aids: Information including sketches, notes, graphs, lists, drawings and other documents used to assist operators in performing assigned duties associated with plant operation. Operator aids are NOT to be used in place of approved procedures or controlled drawings.

2.3. Unauthorized Operator Aid: Uncontrolled, unauthorized direction, instruction, or information needed for plant operation located in the plant. Examples could include dyno-tape providing equipment manipulation instruction, graffiti that provides fuse ID numbers, etc.

2.4. Station Work Aid: Photographs and associated drawings, which are placed within the plant for the purpose of assisting station personnel in locating plant equipment in the performance of their duties. This type of information is not considered an Operator Aid and therefore the requirements of this instruction do not apply.

3. RESPONSIBILITIES 3.1. Operations Management: Administers this procedure and approves new or revised Operator Aids.

3.2. Initiating Department: Ensures that the current revision of an Operator Aid is being utilized. Performs an annual review of Operator Aids being utilized and verifies during this annual review that copies of Operator Aids derived from procedures contain current information.

OP-AA-115-101 Revision 2 Page 2 of 6 3.3. WEC SRO: Administers an annual review of Operator Aids and informs the appropriate group or department of any Operator Aid removal and the reason for removal.

4. MAIN BODY 4.1. PREPARE the Operator Aid with consideration for the following:

Does the Operator Aid replicate information from a procedure?

Should the information be incorporated into a procedure?

Could the Operator Aid be eliminated with better labeling or a permanent placard?

Is the information clearly presented?

Are there any potential human error traps in the wording?

Is the information legible?

Do the words Operator Aid appear prominently?

Is color-coding appropriate for the conventions of the station?

Can the Operator Aid be positioned/mounted without interfering with other components?

Is the material used for the Operator Aid suitable for the environmental conditions?

4.2. ASSIGN each Operator Aid a Designated Number that shall be annotated on the Operator Aid.

4.3. COMPLETE Attachment 1 or electronic equivalent and submit it to the Department Head for review and approval.

4.4. SUBMIT the Operator Aid and other applicable documentation for approval to a manager in Operations.

4.5. LOG the Operator Aid in the Operator Aid Log, Attachment 2, or electronic equivalent.

4.6. Post the Operator Aid in the intended location(s).

4.7. PLACE the master copy of the Operator Aid along with its approval form in the Operator Aid Log.

4.8. IF the Operator Aid is posted in the control room, THEN Route a copy to the Simulator Fidelity Coordinator.

4.9. PERFORM the following when an Operator Aid is no longer needed as deemed by the applicable Department Head or Annual Review:

OP-AA-115-101 Revision 2 Page 3 of 6 4.9.1. LOG the removal of the Operator Aid on Attachment 2.

4.9.2. The WEC SRO shall REMOVE the master copy of the Operator Aid along with the Attachment 1 from the Operator Aid book and ENSURE copies are removed from all locations.

4.10. PERFORM an annual review of Operator Aids.

4.10.1. The Operator Aid Log in the WEC shall be reviewed to ensure only approved Operator Aids are in the book. This shall be done by comparing the Operator Aid Log to the Operator Aids in the WEC book.

4.10.2. Operations crew management will direct any department that has Operator Aids to review them. This review shall be returned to the Unit Supervisor in a timely manner.

4.10.3. The in-plant operators will conduct a field walkdown of accessible areas of the plant for authorized Operator Aids. This walkdown will check applicable items from 4.1.

4.11. Identification and removal of Unauthorized Operator Aids 4.11.1. All marker or other graffiti should be removed with appropriate cleaning solution, or paint/cover the affected area per the appropriate plant program.

4.11.2. Dyno-tape labels or other unauthorized information determined to be necessary to plant operation should be incorporated into the appropriate plant procedure(s) or replaced with an appropriate, approved labels or documents.

4.12. FORWARD copies of all added, revised, or removed Operator Aids to the Simulator Fidelity Coordinator if an electronic database version is not being maintained.

5. DOCUMENTATION - None

6. REFERENCES 6.1. INPO 01-002, "Guidelines for the Conduct of Operations at Nuclear Power Stations."

7. ATTACHMENTS 7.1. Attachment 1, Operator Aid Review and Approval 7.2. Attachment 2, Operator Aid Log

OP-AA-115-101 Revision 2 Page 4 of 6 ATTACHMENT 1 Operator Aid Review and Approval Page 1 of 1 Rev. No. 65 Op Aid # 01-018 Operator Aid

Title:

Unit 1 Reactivity Parameters Description/Use: Include primary Operator Aid Book, Effective 3/16/2013 - 6/1/2013 posting locations.

Permanent Sign/Label Required: Yes x No If Yes, Label Request Submittal Date:

3/1/2013 3/1/2013

OP-AA-115-101 Revision 2 Page 5 of 6

OP-AA-115-101 Revision 2 Page 6 of 6 ATTACHMENT 2 Operator Aid Log Page 1 of 1 OPERATOR TITLE/DESCRIPTION REASON FOR LOCATION ORIGINATOR POSTED BY REMOVED BY AID NUMBER POSTING NAME/DATE NAME/DATE NAME/DATE (sequential)

JOB PERFORMANCE MEASURE TASK CONDITIONS:

1. You are the Unit 1 Unit Supervisor.

2. Unit 1 is at 100% power.

3. The plant process computer has been inoperable for the last 30 minutes.

4. PDMS is inoperable.

INITIATING CUES:

1. The Unit 1 Assist NSO has completed 1BwOSR 3.2.4.1, UNIT ONE QUADRANT POWER TILT RATIO (QPTR) CALCULATION.

2. The Shift Manager has directed you to perform the supervisory review of 1BwOSR 3.2.4.1.

3. Inform the Shift Manager when you have completed the review of 1BwOSR 3.2.4.1.

S-205 Page 1 of 6

TASK TITLE: Review QPTR Calculation JPM No.: S-205 REV: 2013 NRC Task No.: S-AM-123 K&A No.: 2.2.42 Objective No.: 8E.AM-123 K&A IMP: 4.6 EXAMINEE: SRO EVALUATOR: DATE:

The Examinee: PASSED this JPM. TIME STARTED:

FAILED TIME FINISHED:

JPM TIME: MINUTES CRITICAL ELEMENTS: (*) 4, 5, 7, 8 APPROX COMPLETION TIME: 15 MINUTES CRITICAL TIME: NA EVALUATION METHOD: LOCATION:

X PERFORM IN PLANT SIMULATE X SIMULATOR GENERAL

REFERENCES:

1. 1BwOSR 3.2.4.1, UNIT ONE QUADRANT POWER TILT RATIO (QPTR) CALCULATION, Rev. 6

2. Operator Aid for 100% Power NIS Detector Currents

3. Technical Specifications MATERIALS:

1. 1BwOSR 3.2.4.1

2. Operator Aid for values used in QPTR Calculation.

3. Calculator

4. Technical Specifications and Bases TASK STANDARDS:

1. Determine QPTR for each NI detector.

2. Determine N42 upper detector QPTR is unacceptable.

TASK CONDITIONS:

1. You are the Unit 1 Unit Supervisor.

2. Unit 1 is at 100% power.

3. The plant process computer has been inoperable for the last 30 minutes.

4. PDMS is inoperable.

INITIATING CUES:

1. The Unit 1 Assist NSO has completed 1BwOSR 3.2.4.1, UNIT ONE QUADRANT POWER TILT RATIO (QPTR) CALCULATION.

CUE: Hand examinee completed copy of 1BwOSR 3.2.4.1. and Operator Aid 01-009

2. The Shift Manager has directed you to perform the supervisory review of 1BwOSR 3.2.4.1.

3. Inform the Shift Manager when you have completed the review of 1BwOSR 3.2.4.1.

S-205 Page 2 of 6

RECORD START TIME:

EVALUATOR NOTE: This JPM is performed by having the student review the Data Sheet D-3, Unit 1 QPTR calculation using NIS meters. The data sheet is complete but N42 upper detector QPTR was calculated in error. The examinee must locate the error, determine the QPTR for channel N-42 is outside the acceptance criteria, and provide the correct Tech Spec required action to the SM.

PERFORMANCE STEP STANDARD CIRCLE APPLICABLE

1. Refer to 1BwOSR 3.2.4.1, UNIT Refer to 1BwOSR 3.2.4.1. SAT UNSAT N/A ONE QUADRANT POWER TILT

• VERIFY all applicable Comments:

RATIO (QPTR) CALCULATION. Prerequisites, Precautions, and Limitations and CUE: All Prerequisites, Actions are satisfactorily Precautions, addressed.

Limitations and actions

• Review surveillance were met for the applicability (from performance of this statement of applicability) surveillance.

• NIS Power Range Tilts CUE: LCOAR 3.2.4 has NOT alarm is OPERABLE.

been entered.

• QPTR has been within PDMS is inoperable. limit.

Surveillance is

• Process computer is performed as a normal NOT available.

weekly.

2. Review completed data sheet D-3. Review data sheet D-3: SAT UNSAT N/A

• Being completed once per Comments:

CUE: LCOAR 3.2.4 has NOT 7 days (normal interval).

been entered.

• Date: Today.

• Time: 45 minutes ago.

• Channels indication reliable: Yes.

• Instrument Readings:

100%.

3. Review data sheet D-3 detector Review data sheet D-3: SAT UNSAT N/A currents.

• ALL present Upper and Comments:

Lower Detector Currents are recorded correctly from NIS drawer front indications

• ALL 100% detector Upper and Lower currents are recorded correctly from Operator Aid Book.

S-205 Page 3 of 6

EVALUATOR NOTE: JPM page 6 contains a key of correct QPTR calculations.

PERFORMANCE STEP STANDARD CIRCLE APPLICABLE

• 4. Review the calculations to Review the calculated SAT UNSAT N/A obtain the normalized detector Normalized Detector Currents Comments:

currents and compare them to for each detector by dividing the calculated values on the its present detector current data sheet. reading by the 100% detector current value.

Normalized detector current for N42 Upper Detector is in error.

• 5. Review the calculations to Calculate the Average SAT UNSAT N/A obtain the average normalized Normalized Current by Comments:

currents and compare them to summing the upper (lower) the values on the data sheet. normalized detector currents and dividing by 4.

The average normalized current in is error.

6. Review the calculations to obtain Calculate the QPTR for each SAT UNSAT N/A QPTR for each detector and detector by dividing each Comments:

compare them to the QPTR Normalized Detector Current values listed on the data sheet. by the Average Normalized Current Each of the QPTR calculations is in error.

• 7. Identify N42 Upper Detector Determine QPTR is SAT UNSAT N/A QPTR is unacceptable unacceptable: Comments:

(surveillance acceptance

• Identify N42 Upper criteria). Detector QPTR is >1.02 and is unacceptable.

CUE: As SM, acknowledge the

• Determine ALL other required initiation of channels QPTR is LCOAR 1BwOL 3.2.4. acceptable.

o Immediately notify the Shift Manager or Designee to initiate LCOAR (1BwOL 3.2.4)

• 8. Cue: As SM, direct the

• Determines power must SAT UNSAT N/A examinee to identify any be reduced to not greater Comments:

required actions to be than 91% within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> completed this shift as a result (from time of completion of the QPTR result. of the surveillance).

CUE: THIS COMPLETES THIS JPM.

RECORD STOP TIME:

COMMENTS:

S-205 Page 4 of 6

SIMULATOR SETUP INSTRUCTIONS

• Verify/perform TQ-BR-201-0113, BRAIDWOOD TRAINING DEPARTMENT SIMULATOR EXAMINATION SECURITY ACTIONS CHECKLIST. NOTE: This JPM may be performed in a classroom.

• Establish the conditions of IC 21, 100% power, steady state, equilibrium xenon.

• Complete items on Simulator Ready for Training Checklist.

• Place simulator in RUN.

COMMENTS

• Provide examinee copy of 1BwOSR 3.2.4.1, UNIT ONE QUADRANT POWER TILT RATIO (QPTR)

CALCULATION, Rev. 6

• Ensure copy of Operator Aid for current values to be used in QPTR Calculation available.

S-205 Page 5 of 6

KEY - DO NOT GIVE TO EXAMINEE QUADRANT POWER TILT RATIO CALCULATION NIS METERS Being performed once per:

7 Days (normal interval) Shiftly 12 Hours (with BwVSR 3.2.4.2.) Other:

Date: Today Time: 30 minutes ago Channel N41 N42 N43 N44 Is the channel operable? Y N Y N Y N Y N Instrument reading 100% 100% 100% 100%

UPPER DETECTORS (A)

Present upper detector current 192 187 190 185 100% upper detector current 194 181 192 186 Normalized detector current .990 1.033 .990 .995 Average normalized current 1.002 Upper power tilt ratio (¢1.02) ¢ .988 ¢ 1.031 ¢ .988 ¢ .993 LOWER DETECTORS (B)

Present lower detector current 170 150 165 165 100% lower detector current 170 153 165 168 Normalized detector current 1.00 .980 1.00 .982 Average normalized current .991 Lower power tilt ratio (¢1.02) ¢ 1.009 ¢ .989 ¢ 1.009 ¢ .991 Attach additional copies of this page as necessary.

KEY - DO NOT GIVE TO EXAMINEE S-205 Page 6 of 6

WC-AA-111 Revision 4 Page 25 of 61 ATTACHMENT 10 SURVEILLANCE WO DISPOSITION SHEET (APPLICABLE TO MID-WEST SITES ONLY)

Page 1 of 1 Unit: _1__ Procedure: 1BwOSR 3.2.4.1____

PMID/RQ: ______123456____ Work Order #: __ N/A____________

PMID/RQ

Title:

QPTR CALCULATION_________

PMID/RQ Due Date: ___ TODAY________ PMID/RQ Late Date: N/A Signature/Authorization Approval Review: Name Date Time Shift Authorization to Start Work: ___Joe Supervisor ______ Today 1 hr ago Work Started ___ John NSO __________ Today 1 hr ago Work Stopped: ___ John NSO _____________ Today 30 min. ago Supv Review of Work Completion: __________________________ ________ ________

ANI Review of work package: __________________________ ________ ________

Surveillance Found Within Acceptance Criteria YES NO Surveillance Left Within Acceptance Criteria YES NO (Work Started date (above shall be the credit date unless otherwise explained)

Complete one of the following:

Verify Credit Surveillance Credit Date per another WO# ______________

Below: If crediting per another WO, verify credit date is Work Started date of referenced WO.

_________ Complete Sat - Credit Surveillance Complete w/ Portions Unsat - Credit Surveillance No Work Performed - Credit Surveillance Failed - Do Not Credit (Surv Due/Late Dates will NOT advance)

No Work Performed - Do Not Credit (Surv Due/Late Dates will NOT advance)

Comments _____________________________________________

ADDITIONAL REVIEW OF RESULTS (IF REQUIRED)

Title Signature Date

WC-AA-111 Revision 4 Page 25 of 61

PROCEDURE 1BwOSR 3.2.4.1 UNIT NO. REVISION NO.

BRAIDWOOD STATION 1 8 PROCEDURE TITLE:

UNIT ONE QUADRANT POWER TILT RATIO (QPTR) CALCULATION Rev Summary IR# / EC# (if applicable) 8 Fix typo in first note on last page: Change DMV to PCRA 1230954-13 DVM. Add applicable step #s to Station Commitments wherever BwVSR 3.2.4.2 referenced, changed to NF-AP-545.

1BwOSR 3.2.4.1 Revision 8 Continuous Use UNIT ONE QUADRANT POWER TILT RATIO (QPTR) CALCULATION A. STATEMENT OF APPLICABILITY This procedure outlines the steps necessary to verify the QUADRANT POWER TILT RATIO is 1.02. It is applicable in MODE 1 above 50% RATED THERMAL POWER when the Power Distribution System (PDMS) is inoperable and shall be performed:

1. Once per 7 days.

• 2. Once per shift when the NIS Power Range Tilts alarm is INOPERABLE as directed by 1BwOL 3.2.4 and 1BwOSR 0.1-1,2,3.

3. Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when QUADRANT POWER TILT RATIO is not within limits as directed by LCOAR 1BwOL 3.2.4.

B. REFERENCES

1. Tech Spec LCO 3.2.4.

2. Tech Spec Surveillance Requirements:

a. 3.2.4.1.

b. 3.2.4.2.

3. TRM TLCO 3.3.h.

4. Station Procedures:

a. 1BwOSR 0.1-1,2,3, Unit One MODES 1, 2 & 3 Shiftly & Daily.

b. 1BwOL 3.2.4, LCOAR - Power Distribution Limits - QPTR.

c. 1BwOL TRM 3.3.h, Technical Requirements Manual (TRM) LCOAR -

Power Distribution Monitoring System (PDMS)

d. NF-AP-545, QPTR Checkout Using Incores.

5. Station Commitments:

a. 456-200-87-38101, limitation to check the operability of the QPTR Alarm anytime QPTR exceeds 1.02. Step E.3.

b. 456-130-98-3.2.4-0100 "Specific SAR Commitment" (Regarding shiftly surveillance interval when the power range tilts alarm is inoperable).

Steps A.2, E.3.

1

1BwOSR 3.2.4.1 Revision 8 Continuous Use C. PREREQUISITES

1. Receive permission to perform this surveillance from the Shift Manager or designee prior to performance by having the Data Package Cover Sheet signed and dated.

2. Reactor power should be constant while recording NIS data.

3. The latest 100% Power NIS Detector Currents are available (from Station Nuclear Engineer or Operator Aid).

D. PRECAUTIONS Static electricity may cause the needles on the NIS Meters to indicate abnormally. If the NIS Meters are being used to perform this surveillance, the meter faces should be wiped with a damp cloth or equivalent to remove the static charge prior to taking the reading.

E. LIMITATIONS AND ACTIONS

1. As stated in Tech Spec LCO 3.2.4.

2. In the event the Acceptance Criteria (¢) is not met during the performance of this surveillance, IMMEDIATELY notify the Shift Manager or designee to initiate LCOAR 1BwOL 3.2.4.

• 3. Anytime the calculated QPTR exceeds 1.02, the NIS Power Range Tilts alarm OPERABILITY should be reviewed. If the alarm is not illuminated the required frequency of this surveillance shall be increased from once per 7 days to once per shift in accordance with 1BwOL 3.2.4.

4. The process computer point calculation is the most accurate method of calculating QPTR and should normally be used. During the performance of AFD calibrations on the excore detectors the process computer point method will not be correct until ALL drawers are calibrated. During this calibration period QPTR MUST be calculated using the NIS meter method.

5. If the Power Range channel is inoperable but individual detector current indication is reliable, performance of NF-AP-545 is not required. Detector current indication can be considered reliable if detector degradation or failure is not indicated, the detector signal cable is attached to the 1PM07J drawer, and proper high voltage is applied to the detector. In this condition, the QPTR alarm may be inoperable but the neutron flux input to QPTR is available. QPTR can be calculated using the individual detector current meter indications.

2

1BwOSR 3.2.4.1 Revision 8 Continuous Use F. MAIN BODY NOTE All data taken/calculated will be recorded on the appropriate Data sheet.

1. VERIFY all applicable Prerequisites, Precautions, and Limitations and Actions are satisfactorily addressed.

2. INDICATE the applicability of this surveillance on the appropriate Data Sheet (REFER to Statement of Applicability):

a. Being performed once per 7 days.

b. Being performed once per shift.

c. Being performed once per 12 hrs with NF-AP-545.

d. Other (Specify).

3. RECORD the Date and Time.

4. RECORD the OPERABILITY status of the NIS drawer by checking the appropriate box on the Data Sheet.

NOTE With one Power Range Channel INOPERABLE and THERMAL POWER is > 50% but 75%, the QPTR may be calculated using the three OPERABLE channels. With one Power Range channel input to QPTR INOPERABLE with THERMAL POWER > 75%, the QPTR shall be calculated using the three OPERABLE channels taking data when directed by Reactor Engineering during performance of NF-AP-545.

5. RECORD the indicated Reactor Power from the operable NIS drawer front panel PERCENT FULL POWER meters on the appropriate Data Sheet. RECORD "N/A" for the INOPERABLE Power Range channel data.

3

1BwOSR 3.2.4.1 Revision 8 Continuous Use NOTE Step F.6 and F.7 are independent of each other. Perform the applicable step.

Step F.6 will use the process computer to determine the QPTR.

Step F.7 will use installed NIS Meters or DVMs to determine QPTR.

F. 6. DETERMINE the QPTR using process computer points as follows (N/A if determined with the NIS meters):

a. Perform the following for the Upper Detectors:

1) RECORD present computer point reading.

2) DIVIDE the sum of the computer points by the number of operable channels to obtain the average computer point reading.

Average Computer Sum of Computer Points

=

Point Reading Number of Operable NIS Channels

3) DIVIDE the Computer Point Reading by the Average Computer Point Reading to determine the Quadrant Power Tilt Ratio.

Computer Point Reading Power Tilt Ratio =

Average Computer Point Reading

b. Perform the following for the Lower Detectors:

1) RECORD present computer point reading.

2) DIVIDE the sum of the computer points by the number of operable channels to obtain the average computer point reading.

Average Computer Sum of Computer Points

=

Point Reading Number of Operable NIS Channels

3) DIVIDE the Computer Point Reading by the Average Computer Point Reading to determine the Quadrant Power Tilt Ratio.

Computer Point Reading Power Tilt Ratio =

Average Computer Point Reading 4

1BwOSR 3.2.4.1 Revision 8 Continuous Use F. 7. DETERMINE the QPTR using installed NIS Meters or DVMs NOTE Step 7.a will install DVMs, N/A step if using installed NIS Meters.

Step 7.b will determine the QPTR using installed NIS Meters or DVMs.

Step 7.c will remove DVMs, N/A step if using installed NIS Meters.

NOTE The following annunciator(s) may actuate during connection of the DVMs. This list is not all inclusive but if the annunciator(s) does not reset when the DVM is disconnected, investigate the cause before going to the next drawer.

10A04 PWR RNG UPPER DET FLUX DEV HIGH 10B04 PWR RNG LOWER DET FLUX DEV HIGH 10C04 PWR RNG CHANNEL DEV 10B05 PWR RNG FLUX HIGH ROD STOP CAUTION To minimize the effect of meter loading to the drawer, Fluke 8840A DVMs shall be used. If there are not enough 8840As available, Fluke 8505A and Fluke 8502 may be substituted. Other DVM may also be used with the consent of NIS System Engineer or backup. In addition, shielded test leads shall be used to avoid EMF induction to the reactor protection system circuitry.

CAUTION A Reactor Trip could occur if a 2 of 4 coincidence is made up due to a channel trip on the power range detector being measured. The DVM MUST be initially set to the millivolt range for detector current readings to prevent a channel trip.

If the current as seen on the face meter is low (at low powers), it is permissible to down range the detector meter current selector switch for better resolution.

5

1BwOSR 3.2.4.1 Revision 8 Continuous Use CAUTION Ensure that the DVM leads to be used have no flaws in their insulation. Also ensure that any contact points between the leads and the drawer are properly protected to ensure that chafing of the leads' insulation does not occur. If the DVM leads become shorted to ground after connection, the associated power range channel will be made inoperable.

CAUTION Power range cables can become snagged while opening the drawers. Open the rear cabinet doors to 1PM07J and station a person at the rear of the drawers to ensure that all cables are free while opening the drawer.

Minimize motion of the cables, since the cable may become disconnected from its connector if excessive motion occurs. This could make the drawer inoperable.

F. 7. a. NOTIFY IMD to perform the following for each Power Range "B" drawer:

1) CAREFULLY OPEN the Power Range Nuclear Instrumentation Channel "B drawer.

2) CONNECT a DVM between the red and black test jacks of the detector current meter for each of the eight Power Range detectors.

3) ROLL the Power Range "B" drawers carefully as far into the 1PM07J panel as possible. Avoid crimping or damaging the DVM leads. If possible, slightly engage the seismic screws on the front of the drawers.

4) SECURE the DVM leads to 1PM07J.

5) COMPLETE the appropriate sections of the DVM Calibration Table.

6

1BwOSR 3.2.4.1 Revision 8 Continuous Use F. 7. b. DETERMINE the QPTR using NIS meters or DVM as follows (N/A if determined with the computer points):

1) Perform the following for the Upper Detectors:

a) RECORD each present detector current.

b) RECORD the latest 100% Power NIS detector current (from Reactor Engineering or the Operator Aid).

c) DIVIDE the present detector current by the 100% detector current to obtain the normalized detector current.

Normalized Present Detector Current

=

Detector Current 100% Detector Current d) DIVIDE the sum of the normalized detector currents by the number of operable channels to obtain the average normalized current.

Average Sum of Normalized Detector Currents

=

Normalized Current Number of Operable NIS Channels e) DIVIDE the Normalized Detector Current by the Average Normalized Current to determine the Quadrant Power Tilt Ratio.

Normalized Detector Current Power Tilt Ratio =

Average Normalized Current 7

1BwOSR 3.2.4.1 Revision 8 Continuous Use F. 7. b. 2) Perform the following for the Lower Detectors:

a) RECORD each present detector current.

b) RECORD the latest 100% Power NIS detector current (from Reactor Engineering or the Operator Aid).

c) DIVIDE the present detector current by the 100% detector current to obtain the normalized detector current.

Normalized Present Detector Current

=

Detector Current 100% Detector Current d) DIVIDE the sum of the normalized detector currents by the number of operable channels to obtain the average normalized current.

Average Sum of Normalized Detector Currents

=

Normalized Current Number of Operable NIS Channels e) DIVIDE the Normalized Detector Current by the Average Normalized Current to determine the Quadrant Power Tilt Ratio.

Normalized Detector Current Power Tilt Ratio =

Average Normalized Current 8

1BwOSR 3.2.4.1 Revision 8 Continuous Use F. 7. c. PERFORM the following to RESTORE each Power Range B Drawers:

NOTE The following steps are applicable if DVMs are to be used to indicate detector current. Mark this section N/A if current meters installed in the drawers are to be used.

CAUTION Power Range cables can become snagged while opening the drawers. Open the rear cabinet doors to 1PM07J and station a person at the rear of the drawers to ensure that all cables are free while opening the drawer. Minimize motion of the cables, since the cable may become disconnected from its connector if excessive motion occurs. This could make the drawer inoperable.

1) CAREFULLY OPEN the Power Range B drawers.

2) REMOVE the DVM leads.

3) CAREFULLY CLOSE and SECURE the Power Range B drawers.

4) REMOVE all material installed to secure equipment.

5) COMPLETE the appropriate sections of the DVM Calibration Table.

G. ACCEPTANCE CRITERIA No Quadrant Power Tilt Ratio shall exceed 1.02.

(Final) 9

1BwOSR 3.2.4.1 Revision 8 Continuous Use UNIT ONE QUADRANT POWER TILT RATIO CALCULATION COMPUTER POINTS NOTE The process computer point calculation is the most accurate method of calculating QPTR and should normally be used. During the performance of AFD calibrations on the excore detectors the process computer point method will not be correct until ALL drawers are calibrated. During this calibration period QPTR MUST be calculated using the NIS meter method.

Being performed once per:

7 Days (normal interval) Shiftly 12 Hours (with NF-AP-545) Other: ___________________________________

Date: Time:

Channel N41 N42 N43 N44 Is the channel operable? Y N Y N Y N Y N Instrument reading  %  %  %  %

Upper Detectors (A)

Computer point N0041 N0043 N0045 N0047 Present computer point reading Average computer point reading Upper power tilt ratio (¢1.02) ¢ ¢ ¢ ¢ Lower Detectors (B)

Computer point N0042 N0044 N0046 N0048 Present computer point reading Average computer point reading Lower power tilt ratio (¢1.02) ¢ ¢ ¢ ¢ Date: Time:

Channel N41 N42 N43 N44 Is the channel operable? Y N Y N Y N Y N Instrument reading  %  %  %  %

Upper Detectors (A)

Computer point N0041 N0043 N0045 N0047 Present computer point reading Average computer point reading Upper power tilt ratio (¢1.02) ¢ ¢ ¢ ¢ Lower Detectors (B)

Computer point N0042 N0044 N0046 N0048 Present computer point reading Average computer point reading Lower power tilt ratio (¢1.02) ¢ ¢ ¢ ¢ ATTACH additional copies of this page as necessary.

D-2

1BwOSR 3.2.4.1 Revision 8 Continuous Use UNIT ONE QUADRANT POWER TILT RATIO CALCULATION NIS METERS Being performed once per:

X 7 Days (normal interval)

Shiftly 12 Hours (with NF-AP-545) Other: ___________________________________

Date: Today Time: 30 minutes ago Channel N41 N42 N43 N44 Is the channel indication reliable? Y N Y N Y N Y N Instrument reading 100% 100% 100% 100%

Upper Detectors (A)

Present upper detector current 192 187 190 185 100% upper detector current 194 181 192 186 Normalized detector current .990 .968 .988 .993 Average normalized current .985 Upper power tilt ratio (¢1.02) ¢ 1.005 ¢ .983 ¢ 1.003 ¢ 1.008 Lower Detectors (B)

Present lower detector current 170 150 165 165 100% lower detector current 170 153 165 168 Normalized detector current 1.00 .980 1.00 .982 Average normalized current .991 Lower power tilt ratio (¢1.02) ¢ 1.009 ¢ .989 ¢ 1.009 ¢ .991 Date: Time:

Channel N41 N42 N43 N44 Is the channel indication reliable? Y N Y N Y N Y N Instrument reading  %  %  %  %

Upper Detectors (A)

Present upper detector current 100% upper detector current Normalized detector current Average normalized current Upper power tilt ratio (¢1.02) ¢ ¢ ¢ ¢ Lower Detectors (B)

Present lower detector current 100% lower detector current Normalized detector current Average normalized current Lower power tilt ratio (¢1.02) ¢ ¢ ¢ ¢ ATTACH additional copies of this page as necessary.

D-3

1BwOSR 3.2.4.1 Revision 8 Continuous Use UNIT ONE DVM CALIBRATION TABLE DVM QA# Cal Date Due Date Initials IV Top N41 Bottom Top N42 Bottom Top N43 Bottom Top N44 Bottom Leads Installed IV Leads Removed IV DVM Name/Date Name/Date Name/Date Name/Date Top N41 Bottom Top N42 Bottom Top N43 Bottom Top N44 Bottom (Final)

D-4

Formatted: Bullets and Numbering 7.2.

OP-AA-115-101 Revision 21 Page 4 of 5 ATTACHMENT 1 Operator Aid Review and Approval Page 1 of 1 Rev. 73 Op Aid # 01-009 Unit 1 NIS Operator Aid Operator Aid

Title:

Operator Aid Book, Effective 3/22/2013-5/30/2013 Description/Use:

Permanent Sign/Label Required: Yes x No If Yes, Label Request Submittal Date: N/A Setpoint Detector N31 N32 High Flux at Shutdown (CPS) 60 51 60 51 Setpoint Reset Level Trip (CPS) 5 4 5 4 Setpoint Reset 1 x 10 5 x 10 1 x 10 5 x 10 N35 N36 High Flux at Shutdown

-5 -5 -5 -5 (CPS) 5.85 x 10 4.98 x 10 5.67 x 10 4.81 x 10 Setpoint Reset Level Trip (CPS) -5 -5 -5 -5 7.30 x 10 6.21 x 10 7.07 x 10 6.00 x 10 Setpoint Reset N41 N42 N43 N44 A B A B A B A B 100% Full Power 194 170 181 153 192 165 186 168

(µamps) Meters Overpower Trip Low Range 25% 25% 25% 25%

Overpower Trip High Range 109% 109% 109% 109%

Incore/Excore Offset K0554 K0552 K0551 K0553 Ratios 20.171 18.812 18.753 19.454 Matthew Loula 3/22/2013 Preparers Name:

Marri Marchionda-Palmer 3/22/2013 Department Head Approval:

Joe Klevorn 3/23/2013 Shift Manager Approval:

Review Items:

• Does this Operator Aid replicate information from a procedure? Yes X No

• Should this be incorporated into a procedure? Yes X No

• Could it be eliminated with better labeling or a placard? Yes X No

OP-AA-115-101 Revision 21 Page 4 of 5

OP-AA-115-101 Revision 21 Page 4 of 4

JOB PERFORMANCE MEASURE TASK CONDITIONS:

1. You are the Unit 1 Unit Supervisor.

2. Both Units are at full power.

3. The current time is 0700 today. Due to scheduled work on the liquid release line, release #L-13-002 must be COMMENCED by 0900 today using the low flow release path.

INITIATING CUES:

1. The Shift Manager has handed you a portion of a 0WX01T liquid release package, #L-13-002, completed through section G.6, and has directed you to complete Section H. All previous sections of the release package have been successfully completed.

2. Notify the Shift Manager when Section H of the release package is complete.

Page 1 of 7 S-302

TASK TITLE: Prepare/Perform a Liquid Radwaste Release JPM No.: S-302 REV: 2013 NRC TPO No.: 8C.HP-001 K&A No.: 2.3.6 TASK No.: S-HP-001, Authorize a liquid K&A IMP: 3.8 radwaste release EXAMINEE: SRO EVALUATOR: DATE:

The Examinee: PASSED this JPM. TIME STARTED:

FAILED TIME FINISHED:

JPM TIME: MINUTES CRITICAL ELEMENTS: (*) 3, 7 APPROX COMPLETION TIME: 30 MINUTES CRITICAL TIME: NA EVALUATION METHOD: LOCATION:

X PERFORM IN PLANT SIMULATE X SIMULATOR X CLASSROOM GENERAL

REFERENCES:

1. BwOP WX-501T1, Rev. 66, Liquid Release Tank 0WX01T Release Form

2. BwOP WX-501T2, Rev 6, Liquid Release Window Determination

3. BwOP WX-501T3, Rev 1, Authorization to Release Outside of Release Window MATERIALS:

1. BwOP WX-501T1, Rev. 66, Liquid Release Tank 0WX01T Release Form

2. BwOP WX-501T2, Rev 6, Liquid Release Window Determination

3. BwOP WX-501T3, Rev 1, Authorization to Release Outside of Release Window

4. Computer with network access.

TASK STANDARDS:

1. Complete Section G of a liquid release tank release form in accordance with BwOP WX-501T1.

2. Determine release start time is outside release start time window.

TASK CONDITIONS:

1. You are the Unit 1 Unit Supervisor.

2. Both Units are at full power.

3. The current time is 0700 today. Due to scheduled work on the liquid release line, release #L-13-002 must be COMMENCED by 0900 today using the low flow release path.

INITIATING CUES:

1. The Shift Manager has handed you a portion of a 0WX01T liquid release package, #L-13-002, completed through section G.6, and has directed you to complete Section H. All previous sections of the release package have been successfully completed.

2. Notify the Shift Manager when Section H of the release package is complete.

Page 2 of 7 S-302

RECORD START TIME Note: Provide the examinee with a copy of BwOP WX-501T1 completed through Step G.5.

PERFORMANCE STEP STANDARD Circle applicable

1. Obtain and record current Obtain and record current SAT UNSAT N/A Kankakee River flow data Kankakee River flow data by Comments:

NOTE: The USGS internet site performing the following:

can be accessed from

• Access the United States the computer desk top Geological Survey internet from workgroup apps site (usgs.gov).

menu or by using normal

• Access water watch-current internet access. stream flow conditions for NOTE: After examinee locates Illinois Kankakee river flow on

• Access USGS 05527500 usgs web site, indicator, Kankakee River near provide following cue: Wilmington Il flow CUE: Kankakee river stream

• Record discharge flow flow is 5680 cfs at 0700 on todays date AND the Kankakee River is currently NOT at flood stage.

NOTE: If examinee attempts to o Record Kankakee River access the Unit 1 US flow in Unit 1 US turnover turnover, provide the following cue:

CUE: Kankakee river flow has been logged in the Unit 1 US turnover.

2. Determine CW blowdown flow Determine CW blowdown flow SAT UNSAT N/A per BwOP WX-501T2 as Comments:

follows:

o Record liquid release #L-13-002 NOTE: After examinee locates

• Obtain and record current CW blowdown flow Kankakee River flow (5680 indicator, provide cfs) following cue:

• Record CW blowdown flow CUE: CW blowdown flow is 22,000 gpm. o F2400 o OUR-CW032 Page 3 of 7 S-302

PERFORMANCE STEP STANDARD Circle applicable

• 3 Determine the Liquid Release Determine the Liquid Release SAT UNSAT N/A Window per BwOP WX-501T2 Window per BwOP WX-501T2 Comments:

CUE: After examinee locates as follows:

correct procedure, provide copy.

NOTE: After examinee locates

• Access Liquid Release liquid release spread Window spread sheet sheet, inform student to (k:/shift/excel/liquid use spreadsheet on release) computer desktop.

o Enter arrival date at NOTE: A completed copy of the Wilmington (tomorrows liquid release spread date) sheet is located on page

7.

• Enter river flow rate (5680 cfs)

CUE: If examinee asks where release duration information is to be obtained from, inform the examinee the release duration is per BwOP WX-501T1.

CUE: As Shift Manager inform the examinee to use the

• Enter release duration release duration (638 mins from BwOP specified in BwOP WX- WX-501T1 step D.6.f.2) 501T1.

• Enter blowdown flow rate (22,000 gpm)

4. Maximum Release Rate Determine Maximum Release Rate (BwOP WX-501T1 H.1.e.2)):

• Records Chemistry release rate from step C.10.b (50 CUE: The RETDAS computer gpm) output values for

• Record Radioactive Radioactive Release rate Release rate (50 gpm) and most limiting are both 50 gpm.

• N/A step H.1.e.2)c)

• Record the most limiting value (50 gpm)

5. Record the Liquid Release

• Record the Liquid Release Window times Window times on BwOP WX-501T1 (step H.1.f)

• Target start time (1215)

• Start after time (1115)

• Start before time (1300)

• Start after time recorded in step D.3.h (N/A)

Page 4 of 7 S-302

6. Evaluate the expected time of Evaluate the expected time of SAT UNSAT N/A release release so that both biocide Comments:

treatment and the release can be accommodated by performing the following:

• Check if dechlorination CUE: Dechlorination skid is in skid in operation operation.

• Verify CW blowdown flow 8000 gpm (22,000 from previous cue)

PERFORMANCE STEP STANDARD Circle applicable

• 7. Identify release will not start Perform the following: SAT UNSAT N/A within desired time

• Determine release will be Comments:

performed outside of release start time window (from initiating cue, release must start at 0900)

• Determine BwOP WX-501T3 must be completed prior to authorizing release o Notify SM release will be performed outside of CUE: Acknowledge as SM release start time window notification of release OR performed outside start time window. Inform o Notify SM to delay release examinee another until work completed supervisor will perform OR BwOP WX-501T3.

o Notify SM to delay work until release completed within desired time window.

CUE: THIS COMPLETES THIS JPM.

RECORD STOP TIME COMMENTS:

Page 5 of 7 S-302

SIMULATOR/CLASSROOM SETUP GUIDE:

• Verify/copy Liquid Release Window spreadsheet to computer desktop prior to administering JPM.

Spreadsheet is located at k:/shift/excel/liquid release.

• Clear data from INPUTS field of Liquid Release Window spread sheet prior to administering JPM.

• Clear computer history of recently accessed documents, programs, and web sites visited prior to administering JPM by performing the following:

• Right mouse click on task bar

• Select properties

• Select advanced tab

• Select clear

• Delete Liquid Release Window spreadsheet from computer desktop after administering JPM to all candidates.

COMMENTS:

• BwOP WX-501T1, Rev. 66.

• BwOP WX-501T2, Rev 6.

• BwOP WX-501T3, Rev 1.

Page 6 of 7 S-302

KEY KEY INPUTS Arrival Date at Wilmington mm/dd/yyyy Tomorrow River Flow Rate CFS 5680 Release Duration Minutes 638 Blowdown Rate (F2400) GPM 22000 CALCULATED RESULTS Blowdown Time To River Minutes 120 River Time To Wilmington Intake Minutes 420 Blowdown Peak Time To Wilmington Intake Minutes 859 Margin Minutes 98 Start After Time Today 1115 Time #VALUE!

( = Peak Arrives at 10 PM)

Normal Start Time Today 1215

1. VALUE!

( = Center of Peak occurs at 2:30 AM)

Start BeforeTime Today 1300 Time #VALUE!

( = Peak Departs at 7 AM)

KEY KEY (Final)

Page 7 of 7 S-302

PROCEDURE NO.

BwOP WX-501T1 UNIT NO. REVISION NO.

66 BRAIDWOOD STATION PROCEDURE TITLE:

LIQUID RELEASE TANK 0WX01T RELEASE FORM Rev Summary IR# / EC# (if applicable) 63 Tank specific alarms created for individual Release EC 385919 Tanks 0WX01T & 0WX26T. BwAR 0PL01J-7-A9 PCRA 1230957-23 replaced by BwAR 0PL01J-7-B1 and BwAR 0PL01J-7-B2. References to alarm revised in BwOP WX-501T1/526T1. BwAR 0PL01J-7-A9 deleted.

64 Corrected nomenclature for 0PR052 PCRA 1306712-02 65 Add Administrative steps and Attachment to comply CA 1182804-33 with requirements of CC-AA-112 66 Updated attachment to comply with CC-AA-112. No PCRA 1306712-02, 1321744-02, Tech Eval required. Multiple editorial issues fixed. 1323031-02, 1314053-02, 1319267-02, CA 1312921-04

BwOP WX-501T1 Revision 66 Continuous Use LIQUID RELEASE TANK 0WX01T RELEASE FORM NOTE If performing partial procedure to fill Release Tank with WM GO TO Step H.27 or perform BwOP WX-174 to dilute/fill from PW.

Release Number L - __13____ - __002__

A. OPERATING DEPARTMENT RESPONSIBILITY RADWASTE OPERATOR NOTE Desired level is 85% to 90% for Release Package initiation.

A Release Package may be initiated anytime a release is deemed appropriate with Operations Supervision permission.

The mixer should not be run when level is < 70%.

Consideration should be given future water management needs when initiating a package with level < 85%.

NOTE If a liquid release is being performed per BwOP TR-21, Transferring the Clean Water Storage Tank to CW Blowdown, a liquid release from 0WX01T is not permitted.

JO __ 1. VERIFY 0WX01T is Recirculating per BwOP WX-171.

Tank Recirculation Started _ Today_/_14 hrs ago Date Time JO __ 2. RECORD 0WX01T Tank Level (0LR-WX028, Release Tank 0WX01T, Level Indication).

0WX01T Tank Level __58.5__%

JO __ 3. COMPLETE the entries in the Liquid Release Log in the RWCR.

1

BwOP WX-501T1 Revision 66 Continuous Use A JO _ 4. VERIFY/RECORD the Release Number from the Liquid Release Log in the space provided on page 1.

NOTE The minimum mixing time required for an accurate sample is 5 minutes, if recirculating with the mixer ON or 60 minutes, if recirculating with the mixer OFF. After meeting time requirements, Chemistry can be called for a sample.

JO __ 5. WHEN the minimum mixing time requirements have been satisfied, NOTIFY Chemistry that a Release Package in progress requires 0WX01T sampling.

NOTE If more than 25% of the volume in the Release Tank is water that was drained or processed out of one or more systems to support Refueling or Forced Outage activities, it is Outage Water.

JO __ 6. Is the water in this tank considered to be outage water?

YES NO JO __ 7. Is 0WX01T level greater than 80% (From Step A.2.)?

YES (GO TO STEP A.8.) NO (MARK STEP A.8. N/A.)

NOTE If more than 55 gallons of caustic has accumulated at the Release Tank Chemical Addition area (426 by 1A FW Pp), a caustic add should be performed unless directed otherwise by the Shift Supervisor based on release priority.

N/A __ 8. Is it desired to add caustic to 0WX01T?

YES NO JO __ 9. VERIFY/DELIVER this release package to the non-outage Unit Supervisor.

2

BwOP WX-501T1 Revision 66 Continuous Use B. OPERATING DEPARTMENT RESPONSIBILITY - UNIT SUPERVISOR NOTE A TSS analysis is required on ALL tanks released on the first day of the sampling week that releases are performed. The first release tank of the month requires Oil and Grease sampling. These sample analysis add 4-5 hours to the processing time. All chemistry analysis calculations require second verification (If there is only one Chem Tech Available, the verification occurs the following shift). A release package can process through Chemistry in as little as 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> if there are two Chem Techs, there are no higher priorities, no caustic add is required, and 0PR01J is operable.

NOTE Consideration should be given to scheduled activities that may impact operability/availability of 0PR01J and 0PR10J.

1. AAR 0BwOS RETS 2.1-1a in effect for:

JS ___ 0RE-PR001 YES NO VERIFICATION WS___

JS ___ 0RE-PR010 YES NO VERIFICATION WS___

3

BwOP WX-501T1 Revision 66 Continuous Use NOTE Two release path options are available. Generally, the Low Flow release would primarily be used when liquid radwaste inventory is high (i.e. outage). The Ultra Low Flow release rate is the preferred path and is correlated to the current river flow. This path would primarily be used when liquid radwaste inventory is normal. Contact Ops Supervisor for determination of which release flow path to use based on current liquid radwaste inventory, conditions, equipment availability, etc.

B. 2. SELECT which release path will be used for the release:

Low Flow Release Path Ultra Low Flow Release Path NOTE Prior to forwarding this Release Package to the Chemistry Department, Step F.1. and F.2. may be performed if operating conditions permit.

3. OPS Supervisor: I have reviewed Parts A and B and have verified them accurate and complete.

___ Joe Supervisor ____________/__ today_/__13 hrs ago OPS Supervisor Date Time JS ___ 4. NOTIFY the RADWASTE OPERATOR that his release package is ready for prompt delivery to Chemistry.

4

BwOP WX-501T1 Revision 66 Continuous Use C. CHEMISTRY DEPARTMENT RESPONSIBILITY NOTE 100% level for the 0WX01T release tank is 32,900 gallons.

NOTE If 0RE-PR001 is inoperable under AAR 0BwOS RETS 2.1-1a, analyses other than isotopics required in this package, i.e., Tritium, Boron, O & G (if required), and TSS (if required) must be run and the numbers reported on one of two samples that meet the 30%

acceptance criteria.

JT ___ 1. To verify a request has been made to add caustic to 0WX01T Release Tank, verify yes applies to all statements specified in step A.7 and A.8.

All statements are yes, a chemical addition has been requested, GO TO step C.2.

Not all statements apply. A chemical addition will not be performed, GO TO step C.3.

2. Caustic addition to 0WX01T.

a. Sample and analyze 0WX01T for boron concentration:

_____ Sampled by __________

_____ Time/Date ______/______

_____ Results __________ ppm (Record boron value in step C.9).

_____ b. Submit a chemical addition using BwCP 340-1T4 for caustic to 0WX01T based on the following chart.

PPM BORON GALLONS OF CAUSTIC 200 0 200 5

>200 400 10

>400 600 15

>600 800 20

>800 1000 25

>1000 1200 30

>1200 1400 35

>1400 1600 40

>1600 1800 45 5

BwOP WX-501T1 Revision 66 Continuous Use C. 2. c. PERFORM either of the following:

Chemical Addition:

_____ a) SUBMIT Chem Add to Operations for __________ gallons caustic. Submitted by:

__________________ Time/Date ______/______

_____ b) RECORD the Time and Date the caustic addition was completed:

__________________ Time/Date ______/______

_____ c) WHEN the notification has been received that the caustic addition is complete, GO TO step C.3.

OR

_____ OPS Supervisor notified that no caustic is to be added based on boron concentration. OPS Supervisor notified:

__________________ Time/Date ______/______ by Chem Tech

_______________________________________ GO TO Step C.3.

6

BwOP WX-501T1 Revision 66 Continuous Use C. 3. Sampling the Release Tank.

NOTE After obtaining a sample of the Release Tank, the analysis listed in Section C. (excluding sections C.1 and C.2) can be performed in any order necessary to perform the analysis in a safe and timely fashion.

It is not necessary to complete one analysis before starting another.

The sequence of performing the analysis is left to the discretion of individual performing the tasks.

1st set 2nd set (If Required) 1st Sample 2nd Sample 1st Sample 2nd Sample (If Required) (If Required)

Sampled by JT JT Date today today Sample Time 13 hrs ago 12.5 hrs ago JT ___ a. One liter in a poly bottle for isotopic analysis, tritium analysis, and boron analysis using appropriate Chemistry procedures and 250 ml for the monthly save (monthly composites).

C/M__ b. For the first release package of the month, ANALYZE sample for Oil and Grease as directed per BwCP 323-18.

NOTE Additional release packages sampled on the same day as those analyzed in Step C.3.c. will require TSS samples also.

C/M__ c. For the day of the first release package of the week, obtain a sample for Total Suspended Solids (TSS) analysis for ALL releases as directed per BwCP 323-18.

7

BwOP WX-501T1 Revision 66 Continuous Use C. 4. ISOTOPIC SAMPLING CHECK JT __ IF the Radwaste Effluent Process Monitor, 0RE-PR001 is operable per AAR 0BwOS RETS 2.1.-1a (see Step B.1.) then N/A Step C.5.

N/A __ IF Radwaste Effluent Process Monitor, ORE-PR001 is not operable per AAR 0BwOS RETS 2.1.-1a (see Step B.1.) then Perform Step C.5.

NOTE IF an Isotopic Verification is to be performed then an independent sample of sufficient volume for an Isotopic must be taken by an independent qualified individual.

5. ISOTOPIC VERIFICATION N/A __ a. VERIFY that Cobalt 60 (Co-60) activities are within 30% of each other by PERFORMING the following calculation:

A/B < 1.30 Where:

A = The Larger Co-60 activity, µCi/g = ____________________.

B = The Smaller Co-60 activity, µCi/g = ___________________.

_______________ ÷ _______________ = _______________ (1.30)

(A) (B) (A/B) 8

BwOP WX-501T1 Revision 66 Continuous Use C. 5. b. PERFORM either of the following:

N/A __ IF the activities are NOT within 30% of each other, GO TO step C.5.c.

N/A __ IF the activities are within 30% of each other, N/A Steps C.5.c.

through C.5.g. and GO TO Step C.6.

c. If the activities were not within 30% of each other, PERFORM the following:

N/A __ 1) DISCARD any results obtained for O & G, TSS, boron, and tritium on these samples.

N/A _ 2) INFORM OPS Supervision.

N/A __ 3) OBTAIN another set of INDEPENDENT samples.

N/A __ 4) PERFORM an isotopic analysis on each of the second set of samples.

N/A __ 5) VERIFY that Cobalt 60 (Co-60) activities are within 30% of each other by PERFORMING the following calculation:

A/B < 1.30 Where:

A = The Larger Co-60 activity, µCi/g = ____________________.

B = The Smaller Co-60 activity, µCi/g = ___________________.

_______________ ÷ _______________ = _______________

(A) (B) (A/B) (<1.30)

N/A __ d. A second INDEPENDENT set of samples has been obtained, analyzed and the Co-60 activities verified to be within 30% of each other. (Check one of the following.)

YES, GO TO Step C.6.

NO, INFORM Operations Supervision and Chemistry Supervision immediately. Save other analysis results, i.e., Tritium, boron, O & G (if required) and TSS (if required) obtained on the second set of samples.

__________________________________/_______

Signature Date 9

BwOP WX-501T1 Revision 66 Continuous Use NOTE Chemistry and OPS Supervision will attempt to resolve the activity mismatch. Further INDEPENDENT sampling and isotopic analyses may be necessary. Radiation Protection Supervision may need to be consulted to re-evaluate the 30% acceptance criteria.

C____ 5. e. Radiation Protection has waived 30% acceptance criteria.

________________________________________/______/______

Rad. Protection Supervisor Date Time

________________________________________/______/______

OPS Supervisor Date Time

f. If Radiation Protection waives the 30% acceptance criteria, report analysis results for Tritium, boron, O & G (if required) and TSS (if required) obtained on the second set of samples.

g. If Radiation Protection does not waive the 30% acceptance criteria, discard analysis results for Tritium, boron, O & G (if required) and TSS (if required) obtained on the second set of samples. Notify OPS Supervisor that this package is terminated and return to him. Chemistry Supervision will begin an investigation to determine the difference.

JT ___ 6. Radionuclide Analysis Performed (Isotopic report(s) attached).

JT ___ 7. PERFORM the following:

ANALYZE sample for tritium using appropriate Chemistry procedures.

RECORD the results from the completed BwCP 220-2T1 or applicable procedure.

PARAMETER FREQUENCY LIMIT RESULTS Tritium Each Batch None 0.3333_ µCi/g PLACE a copy of the completed Data Sheet that contains Tritium results in the Release Package for Radiation Protection.

JT ___ 8. Composite sample drawn, labeled with sample time, date and assigned release number and placed in designated sample storage area.

10

BwOP WX-501T1 Revision 66 Continuous Use C JT 9. ANALYZE sample for boron concentration, if not previously obtained in step C.2, using appropriate Chemistry procedure, and RECORD the results below.

POST DILUTION TANK PARAMETER FREQUENCY DISCHARGE LIMIT CONCENTRATION Boron Each Batch 1 ppm _______________ ppm JT ___ 10. Maximum Discharge Rate based on Water Quality Chemical Analysis.

a. PERFORM the following calculation for each analysis:

A x B = MAXIMUM DISCHARGE RATE (GPM)

C Where:

A = Kankakee River Flowrate = 91,392 gpm.

B = Parameter Limit = 1 ppm C = Tank Concentration (from Step C.9.)

(__91392_ (GPM) X ___1____ (PPM)) ÷ __1464.6_ (PPM) =

(A) (B) (C)

____62.4_________ GPM (Maximum Discharge Rate) 11

BwOP WX-501T1 Revision 66 Continuous Use NOTE When using the Low Flow release path, the MAXIMUM RELEASE RATE SHALL NOT exceed 50 gpm. When using the Ultra Low Flow release path, the MAXIMUM RELEASE RATE SHALL NOT exceed 20 gpm.

C. 10. b. REFER to step B.2. to determine which release path will be used for this release. Then complete one of the following:

The Low Flow release path will be used. RECORD the calculated Maximum Discharge Rate from step C.10.a. or 50 gpm, whichever is less.

____50___________ GPM ( 50 gpm)

The Ultra Low Flow release path will be used. RECORD the calculated Maximum Discharge Rate from step C.10.a. or 20 gpm, whichever is less.

______ N/A _______ GPM ( 20 gpm) 12

BwOP WX-501T1 Revision 66 Continuous Use NOTE All required NPDES LIMITS must be satisfied in the release tank prior to a release.

C N/A 11. ANALYZE sample as required by the NPDES Permit for Total Suspended Solids and Oil and Grease using appropriate Chemistry procedures. RECORD the results from the completed analyses below and on the NPDES Weekly Data Sheet. N/A this Step and C.12 if NPDES sampling has been satisfied.

1st set 2nd set (If Required) 2nd Sample(If 2nd Sample (If 1st Sample 1st Sample Required) Required)

Sampled by Date Sample Time PARAMETER FREQUENCY LIMIT RESULTS Total Suspended Solids Per Current NPDES Permit 30 ppm __________ ppm Oil and Grease Per Current NPDES Permit 20 ppm __________ ppm

12. Is the Release Tank within all specified NPDES limits as determined in Step C.11?

_____ YES The release tank is approved for Chemical Release. GO TO Step C.13.

_____ NO a. IMMEDIATELY NOTIFY the OPS Supervisor.

b. OPS Supervisor notified:

_________________________________/______/______

(Print Name) Date Time

c. RETURN this procedure to Operations for release cancellation.

13

BwOP WX-501T1 Revision 66 Continuous Use C. 13. Chemistry Department: I have reviewed Part C and have verified it is accurate and complete.

________________________________________/______/______

Chemistry Department Date Time

________________________________________/______/______

Verification Date Time JT ___ 14. PROMPTLY DELIVER this release package to Rad Protection for processing (ENSURE receipt is acknowledged).

14

BwOP WX-501T1 Revision 66 Continuous Use D. RAD PROTECTION DEPARTMENT RESPONSIBILITY RADIONUCLIDE ANALYSIS NOTE If 0RE-PR001 (Liquid Radwaste Release Monitor) is out-of-service, two release tank samples must be obtained and analyzed. For all release calculations the isotopic with the highest total activity SHALL be used. If an isotope appears on only one of the two analyses, then ensure that isotope is included in the calculations.

NOTE Verification is required if manual calculations are performed. If a computerized release program is used, attach the printout and N/A the appropriate verification spaces.

NOTE Rad Protection or Operations is to notify Chemistry when a release package is cancelled prior to release so that the NPDES data sheets can be updated as required.

RT __ 1. OBTAIN and REVIEW the Isotopic(s) for the tank to be released and ENCLOSE in this release form.

RT __ 2. PERFORM the following:

RT __ a. CALL the Unit Supervisor and VERIFY that there are no "Liquid Release in Progress" placards for the 0WX01T on panel 0PM01J.

___ Joe Supervisor _________/___ Today /_10 hrs ago _

Name of Verifier Date Time RT __ b. VERIFY that the status of the 0RE-PR001 and 0RE-PR010 monitors are the same as indicated in Step B.1.

Yes. The status for both monitors is the same as indicated in Step B.1. CONTINUE processing this package.

No. The status for one or both monitors is not the same as indicated in Step B.1. OBTAIN guidance from Operations on whether or not processing of this package should be continued.

15

BwOP WX-501T1 Revision 66 Continuous Use NOTE 0WX01T has capacity of 32,900 gallons. Tank level is recorded in Step A.2 D. 3. PERFORM the following to calculate the H-3 activity of this release:

RT __ a. __58.5%__ x 329 gal = _19246.5_ gallons (Step A.2) 1%

NOTE The units in step C.7, µCi/g, are equivalent to µCi/ml as seen in the following step.

RT __ b. 3.33E-1 µCi /ml X 3785 ml/gal x 19246.5gal x 1E-06 Ci/µCi = __24.3__ Ci (step C.7) (step D.3.a)

Performed by: __ RT _____/__ today __

Initials Date Verification  : ___ VT ____/_ today __

Initials Date

c. PERFORM one of the following:

RT __ If the H-3 activity is greater than or equal to 100 Ci, INFORM the Operations and Chemistry that the entire requested volume cannot be released in a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period and cancel this release package.

_______ N/A __________________/__________/____________

Supervisor Notified Date Time If H-3 activity is less than 100 Ci then continue to next step.

16

BwOP WX-501T1 Revision 66 Continuous Use D RT 3. d. RECORD the appropriate information in the Liquid Release Tritium Tracking log for this release package: Release Number, H-3 Concentration and Tank gallons. The Liquid Release Tritium Tracking Log is located at L:/Shared/8931/Liquid Release Information/Liquid Release Tritium Tracking Log.

NOTE Information required in Step D.3.e can be obtained from the Liquid Release Tritium Tracking Log or by contacting Radwaste Operations.

RT __ e. RECORD the following information for all liquid Rad Waste discharges completed in the last 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. (N/A this step if no releases in last 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.)

Release # ______ L-13-001_________

Date & Time release stopped __ yesterday @ 1700______

Actual Gallons Released _____9990___________

Tritium Activity (uCi/ml) ____13.6 Ci _____________

RT __ f. CALCULATE H-3 activity released in last 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. (N/A this step if no releases in the last 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.)

3.60E-1 µCi /ml X 3785 ml/gal x 9990 gal x 1E-06 Ci/µCi = ___13.6__ Ci Performed by: __ RT ___/___ today _

Initials Date Verification  : ___ VT ____/_ today ___

Initials Date 17

BwOP WX-501T1 Revision 66 Continuous Use D RT 3. g. PERFORM one of the following:

If there was a release in the last 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, CALCULATE the total Tritium activity using the following equation:

__24.3__ Ci H-3 + __13.6__ Ci H-3 = __37.9_ Ci H-3 (Step D.3.b.) (Step D.3.f.)

Performed by: __ RT ____/__ today __

Initials Date Verification  : __ VT ____/__ today __

Initials Date IF no release in the last 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, H-3 Activity = __________Ci H-3.

(Step D.3.b.)

RT __ h. PERFORM one of the following (and INITIAL appropriate bullet):

Results of D.3.g are LESS than 100 Ci - CONTINUE with discharge.

Results of D.3.g are GREATER than or EQUAL to 100 Ci

- INFORM Operations Field Supervisor that this release cannot start within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the completion of the last release.

________ N/A __________________________/________/________

Supervisor Notified Date Time RECORD release start time (24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> AFTER completion of last release.

__________ N/A ______________________

RT __ i. RECORD anticipated H-3 activity from Step D.3.b. and the sum of the anticipated H-3 activity plus the activity released in the last 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from Step D.3.g. in the Liquid Release Tritium Tracking Log.

18

BwOP WX-501T1 Revision 66 Continuous Use NOTE If 0RE-PR001 is inoperable and AAR 0BwOS RETS 2.1-1a has been initiated, Steps D.4.b-c., are not required and may be marked N/A.

D. 4. PERFORM the following:

RT __ a. CALL the Assist NSO (x2207 or x2208).

RT __ b. REQUEST and RECORD the 3 most recent 10 minute average readings from RM-11 for the 0RE-PR001 (0PS101).

1. 1 __2.02E-7_ µCi/ml

1. 2 __2.02E-7__ µCi/ml

1. 3 __2.02E-7_ µCi/ml RT __ c. RECORD the maximum background for 0RE-PR001 obtained from 3 average readings in Step D.4.b. above = 2.02E-7 µCi/ml RT __ d. OBTAIN the current 0RE-PR010 reading: ___8.12E-7 ______ µCi/ml RT __ e. RECORD the Time and Date the readings were obtained:

Time: _ Now ____ Date: _ today ___

______ Joe Operator _________________________________

Operator Contacted RT __ 5. INDICATE which release path will be used for this release (refer to step B.2):

Low Flow (Maximum Release Rate = 50 gpm)

Ultra Low Flow (Maximum Release Rate = 20 gpm) 19

BwOP WX-501T1 Revision 66 Continuous Use NOTE If the RETDAS computerized release program is available, you may attach the printout to this form and indicate see attached in the calculation spaces in D.6.a below. If no quantifiable peaks are found in the radionuclide analysis, write NQPF in the Table in Step D.6.a.

Actual release data will be completed in Section J.

D. 6. Radioactive Release Rate Determination:

RT __ a. To ensure compliance of the planned release with 10CFR20 limits, PERFORM one of the following:

RT __ IF using RETDAS computerized release program and the RETDAS data farmer link is operable, ENTER all data into the RETDAS software to complete the Liquid Pre-Release Permit Report. IF the data farmer link in the RETDAS computerized release program is operable, no verification of the Liquid Pre-Release Permit Report is needed. IF any isotopes were MANUALLY entered into RETDAS, have another qualified individual VERIFY all MANUALLY entered isotopes are correct.

Isotopic data entered by: ____ RT ___ Date / Time: today /_Now Isotopic data verified by: ___ N/A ___ Date / Time: _____/_____

REVIEW the Limits Analysis section of the Liquid Pre-Release Permit Report.

20

BwOP WX-501T1 Revision 66 Continuous Use D N/A 6. a. IF using RETDAS computerized release program and the RETDAS data farmer link is not operable, ENTER all data into the RETDAS software to complete the Liquid Pre-Release Permit Report and MANUALLY enter the isotopic information into RETDAS. Have another qualified individual VERIFY all MANUALLY entered isotopes are correct.

REVIEW the Limits Analysis section of the Liquid Pre-Release Permit Report.

Isotopic data entered by: __________ Date / Time: _____/_____

Isotopic data verified by: __________ Date / Time: _____/_____

N/A __ IF the RETDAS computerized release program is not operable, CONTACT Qualified R. P. Management individual to COMPLETE the following table. If an isotope is not present, you may leave the space blank.

NOTE DWC values are listed in 10CFR20, Appendix B Table 2, Column 2.

For ODCM Limit, take ten times the DWC value for each isotope listed for column 3. (i.e. the DWC value for Co-58 is 2E-5 µCi/ml.)

The ODCM Limit for noble gas isotopes is 2E-4 µCi/ml per CY-BR-170-301, ODCM Chapter 12, Radioactive Effluent Technical Standard step 12.3.1.a.

NOTE Columns 5 and 6 cannot be completed until the mathematical operations in Step D.6.g are performed. The appropriate values can then be entered into the table.

21

BwOP WX-501T1 Revision 66 Continuous Use

1. 1 #2 #3 #4 #5 #6 Isotope Undiluted ODCM Limit Column #2 Diluted Activity Unrestricted Area DWC Tank (µCi/ml) x 100% (µCi/ml) Fraction Activity Column #3

(µCi/ml)

Na-24 5.0 E-4 Cr-51 5.0 E-3 Mn-54 3.0 E-4 Co-57 6.0 E-4 Co-58 2.0 E-4 Fe-59 1.0 E-4 Co-60 3.0 E-5 Zn-65 5.0 E-5 Br-82 4.0 E-4 Kr-85 2.0 E-4 Sr-92 4.0 E-4 Nb-95 3.0 E-4 Zr-95 2.0 E-4 Zr-97 9.0 E-5 Ag-110m 6.0 E-5 Tc-99m 1.0 E-2 Sn-113 3.0 E-4 Sb-122 1.0 E-4 Sb-124 7.0 E-5 Sb-125 3.0 E-4 Sb-126 7.0 E-5 Cs-136 6.0 E-5 I-131 1.0 E-5 I-133 7.0 E-5 Xe-133 2.0 E-4 Xe-133m 2.0 E-4 Cs-134 9.0 E-6 Xe-135 2.0 E-4 Cs-137 1.0 E-5 Cs-138 4.0 E-3 Ba-140 8.0 E-5 La-140 9.0 E-5 Ce-144 3.0 E-5 H-3 1.0 E-2 Total Total (2) Sum of column #2 does NOT include Tritium (4) Sum of column #4 DOES include Tritium Completed by: _____________________________________________________ Date/Time: ______________

Print/Sign Data Calculations Verified by: _____________________________ Date/Time: ______________

Print/Sign 22

BwOP WX-501T1 Revision 66 Continuous Use NOTE If the RETDAS computerized release program is available, the total tank curies, excluding noble gas and tritium, are less than the administrative limit if no warning is displayed in the Limits Analysis section of the prerelease permit.

D. 6. b. PERFORM one of the following:

RT __ The total tank curies excluding noble gas and tritium are less than the administrative limit. MARK the remainder of Step D.6.b N/A and PROCEED to Step D.6.c.

N/A __ The total tank curies excluding noble gas and tritium are equal to or greater than the administrative limit. CONTACT the Ops Field Supervisor to receive permission to release the tank.

Will the tank be released? YES / NO (Circle one.)

_________ N/A _______________/__________/__________

Supervisor Contacted Date Time 23

BwOP WX-501T1 Revision 66 Continuous Use NOTE If the RETDAS computerized release program is available, you may mark Step D.6.c N/A.

NOTE The value to be used for Circulating Water Blowdown Rate in the following step is 8,000 GPM.

NOTE Release may be performed using the Low Flow release path or the Ultra Low Flow release path. When using the Ultra Low Flow release path, N/A step D.6.c-e. If the Ultra Low Flow release path is used, 20 GPM will be used as the value of the maximum release rate. Use this value as applicable in steps D.6.f-D.6.g.

D____ 6. c. When using the Low Flow release path, PERFORM the following calculation to DETERMINE the Radioactive Release Rate:

Circulating Water Blowdown Rate (8,000 gpm)

Radioactive Release Rate = / 0.02 Total of Column 4 (8000 GPM ÷ _______________) ÷ 0.02 = ________________ GPM (Total of Column 4) (Release Rate)

Performed by: __________/__________

Initials Date Verification: __________/__________

Initials Date 24

BwOP WX-501T1 Revision 66 Continuous Use NOTE If the RETDAS computerized release program is available, RECORD values for D.6.d. from the RETDAS permit.

D RT _ 6. d. Maximum Release Rate Determination:

1) RECORD the Chemistry Release Rate from step C.10.b. or RETDAS permit:

__50___ GPM

2) RECORD the Radioactive Release Rate from step D.6.c. or RETDAS permit:

__50___ GPM NOTE The maximum release rate SHALL NOT exceed 50 gpm. DO NOT record a value greater than 50 gpm in the following step.

RT __ e. RECORD the most limiting (smallest) value from step D.6.d. as the Maximum Release Rate below:

Maximum Release Rate = ___50____ GPM ( 50 gpm) 25

BwOP WX-501T1 Revision 66 Continuous Use NOTE If the RETDAS computerized release program is available, you may N/A steps D.6.f.1) and RECORD values for D.6.f.2) from the RETDAS permit.

D. 6. f. PERFORM the following:

N/A __ 1) Calculate the minimum release duration using formula below:

(___N/A ____ GAL - 3300 GAL) ÷ __ N/A ____ GPM = __ N/A _____MIN (Step D.3.a.) (Step D.6.e. or 20 GPM) (Min Release Duration)

Performed by: ___ N/A ___/__________

Initials Date Verification: ___ N/A ___/__________

Initials Date RT __ 2) RECORD the Minimum Release Duration (from Step D.6.f.1) or the RETDAS permit:

___638__________ MIN 26

BwOP WX-501T1 Revision 66 Continuous Use NOTE If the RETDAS Computerized Release Program is available, steps D.6.g.1) - 4) may be marked N/A.

D. 6. g. Calculation of DILUTED ACTIVITY and UNRESTRICTED AREA DWC FRACTION (Verification):

N/A __ 1) COMPLETE columns #5 and #6 of Step D.6.a. using the following equations on a radionuclide basis:

Analyzed Tank Activity (Ci/ml) ) (Column 2) x Max. Release Rate (gpm)

Diluted Activity =

Max. Release Rate (gpm) + Circ Wate r Blowdown Rate (8,000 gpm)

DWC Fraction = Diluted Activity (from above calculation) / Tech Spec Limit (Column 3)

N/A __ 2) RECORD the results of the previous step in the applicable rows of columns #5 and #6.

N/A __ 3) SUM the results of columns #5 and #6.

N/A __ 4) RECORD the values obtained on the appropriate TOTAL row of the table.

RT __ 5) PERFORM one of the following:

IF RETDAS is not used, VERIFY that the sum of column # 6 of D.6.a is less than 0.5. IF not, NOTIFY the Ops Supervisor and CANCEL this release package.

______ N/A ____________________/__________/__________

Ops Supervisor Date Time IF RETDAS is used, VERIFY that the sum of column # 6 labeled Percent of 10 x EC is less than 5.00 E + 1. IF not, NOTIFY the Ops Supervisor and CANCEL this release package.

_____ Joe Supervisor _________/____ today _/____now __

Ops Supervisor Date Time 27

BwOP WX-501T1 Revision 66 Continuous Use NOTE If 0RE-PR001 is inoperable and AAR 0BwOS RETS 2.1-1a has been initiated, Step D.7. is not required and may be N/Ad. Step D.7.a is not required if the RETDAS release software is operational and may be N/Ad. Ops Shift Management personnel may request performance of step D.7 to facilitate post maintenance testing.

D. 7. RADWASTE EFFLUENT MONITOR SETPOINT:

a. DETERMINE the Alert Alarm and High Alarm setpoints for the Liquid Radwaste Effluent Monitor (0RE-PR001) using the following equation:

N/A _ 1) RECORD the 0RE-PR001 maximum background from Step D.4.c.

_______________ µCi/ml N/A __ 2) PERFORM the following calculation:

(___________________µCi/ml x 1.5) + __________ µCi/ml =

(Step D.6.a Col 2 Total) (Step D.7.a.1)

__________ µCi/ml Calculated 0RE-PR001 Setpoint Performed by: __________/__________

Initials Date Verification: __________/__________

Initials Date N/A __ 3) RECORD the calculated 0RE-PR001 setpoint:

_______________ µCi/ml (Step D.7.a.2 results)

N/A __ 4) COMPARE the calculated 0RE-PR001 setpoint to each of the current 0RE-PR001 monitor setpoints. These setpoints are:

8.64E-05 µCi/ml for the HIGH setpoint 4.32E-05 µCi/ml for the ALERT setpoint 28

BwOP WX-501T1 Revision 66 Continuous Use D. 7. a. 5) PERFORM either of the following:

N/A __ If the calculated value is less than the current monitor HIGH setpoint, RECORD the current monitor setpoints as the Release setpoints.

N/A _ If the calculated value is greater than the current monitor HIGH setpoint, RECORD the calculated value as the Release HIGH setpoint, and 50% of the calculated HIGH setpoint as the ALERT setpoint.

b. RECORD 0RE-PR001 Monitor Liquid Release setpoints from RETDAS Permit or as calculated in D.7.a.5):

RT __ Chan Item 9 (HIGH Alarm Setpoint) ___1.31E-4_ µCi/ml RT __ Chan Item 10 (ALERT Alarm Setpoint) ___6.56E-5____ µCi/ml 29

BwOP WX-501T1 Revision 66 Continuous Use NOTE If 0RE-PR010 is inoperable and AAR 0BwOS RETS 2.1-1a has been initiated, Step D.8. is not required and may be N/Ad. Step D.8.a is not required if the RETDAS Release software is operational.

Mark the step(s) N/A as necessary. Ops Shift Management personnel may request performance of step D.8. to facilitate post maintenance testing.

D. 8. STATION BLOWDOWN MONITOR SETPOINT:

N/A _ a. DETERMINE the Alert Alarm and High Alarm setpoints for the Station Blowdown Monitor (0RE-PR010) using the following equation:

N/A __ 1) RECORD the current 0RE-PR010 reading from Step D.4.d.:

_______________ µCi/ml N/A __ 2) PERFORM the following calculation:

(1.25 x __________ x __________ GPM) ÷ (8,000 + __________)

(Total Col #2 Step D.6.a) (Step D.6.e or 20 GPM) (Step D.6.e. or 20GPM.)

= _________ µCi/ml 0RE-PR010 Calculated Setpoint Performed by: __________/__________

Initials Date Verification: __________/__________

Initials Date N/A __ 3) RECORD the Calculated 0RE-PR010 setpoint:

_______________ µCi/ml (Step D.8.a.2. results)

N/A __ 4) COMPARE the calculated 0RE-PR010 Setpoint to each of the current monitor setpoints. These setpoints are:

1.07E-06 µCi/ml for the HIGH setpoint 7.46E-07 µCi/ml for the ALERT setpoint 30

BwOP WX-501T1 Revision 66 Continuous Use D. 8. a. 5) PERFORM either of the following:

N/A __ IF the calculated value is less than the current monitor HIGH setpoint, RECORD the current monitor setpoints as the Release setpoints.

N/A _ IF the calculated value is greater than the current monitor HIGH setpoint, RECORD the calculated value as the Release HIGH setpoint, and 70% of the HIGH value for the ALERT setpoint.

b. RECORD 0RE-PR010 Monitor Liquid Release setpoints as determined in step D.8.a.5) or from the RETDAS release software:

RT __ Chan Item 9 (HIGH Alarm Setpoint) __8.19E-6 ____ µCi/ml RT __ Chan Item 10 (ALERT Alarm Setpoint) ___5.73E-6___ µCi/ml NOTE The following step is to ensure the permit number created for this release has been committed to the database.

9. PERFORM the following: (This step may be N/A if this package was not generated with RETDAS.)

RT __ a. CLOSE RETDAS.

RT __ b. REOPEN RETDAS and CLICK on release ID magnifying glass and select appropriate release tank. Then CLICK on permit number magnifying glass and VERIFY the permit number is in the database.

RT __ c. CLOSE RETDAS.

31

BwOP WX-501T1 Revision 66 Continuous Use NOTE If 0RE-PR001 is inoperable and AAR 0BwOS RETS 2.1-1a has been initiated, verification is required for Step D.10.

D. 10. APPROVAL FOR RADIOLOGICAL RELEASE:

RT __ Radiation Protection: I have reviewed Part D and have verified it is accurate and complete.

Performed by ___ Rhonda Technician ______/ today/_1 hr ago Radiation Protection Date Time Verified by: _____ Ralph Technician __/__ today/_1 hr ago Date Time RT __ 11. FORWARD to HPS/RPS for review.

RT __ 12. FORWARD Release Package to the OPS Supervisor or contact OPS Supervisor for instructions to forward this package.

32

BwOP WX-501T1 Revision 66 Continuous Use E. OPERATING/CHEMISTRY DEPARTMENT RESPONSIBILITY NOTE TSS is required for the first release of the week.

Oil and Grease is required for the first release of the month.

The week is defined as Monday thru Sunday.

1. Control Room Supervisor:

a. Is this the first release for the week/month?

YES GO TO Step E.1.b NO N/A steps E.1.b thru E.5 then GO TO Section F.

b. Are required analyses complete with results within the limits in step C.11?

YES N/A steps E.2 thru E.5 then GO TO Section F.

NO RETURN this release package to Chemistry to perform Step E.2 thru E.5.

N/A __ 2. ANALYZE sample as required by the NPDES Permit for Total Suspended Solids and Oil and Grease per appropriate procedures. RECORD the results from the completed analyses below and on the NPDES Weekly Data Sheet. N/A this step and E.3 if NPDES sampling has been satisfied.

1st set 2nd set (If Required) 2nd Sample(If 2nd Sample (If 1st Sample 1st Sample Required) Required)

Sampled by Date Sample Time PARAMETER FREQUENCY LIMIT RESULTS Total Suspended Solids Per Current NPDES Permit 30 ppm _________ ppm Oil and Grease Per Current NPDES Permit 20 ppm _________ ppm 33

BwOP WX-501T1 Revision 66 Continuous Use E N/A 3. Is the Release Tank within all specified NPDES limits as determined in steps C.11 and E.2?

N/A __ YES The release tank is approved for Chemical Release, perform Step E.4, N/A __ NO a. IMMEDIATELY NOTIFY the OPS Supervisor.

b. OPS Supervisor notified:

_________________________________/______/______

(Print Name) Date Time

c. RETURN this procedure to Operations for release cancellation.

4. Chemistry Department: I have reviewed Part E and have verified it is accurate and complete.

________________________________________/______/______

Chemistry Department Date Time

________________________________________/______/______

Verification Date Time

5. Promptly DELIVER this release package to the Control Room Supervisor for processing. (ENSURE receipt is acknowledged.)

34

BwOP WX-501T1 Revision 66 Continuous Use NOTE A Check Source Check is a verification of Detector Response. Even if Detector response is immediately evident when a "Hot" Release Tank is first lined up to 0PR01J, ODCM RETS 2.1.B-1 requires a Source Check. If a Check Source Test fails when High Activity is present, it is caused by the program function of 0PR01J. To pass the Check Source Test, the Activity has to stabilize or be missed, and repeated attempts may have to be performed until successful.

NOTE If 0RE-PR001 is inoperable and AAR 0BwOS RETS 2.1-1a has been initiated Step F.1. is not required.

F. OPERATING DEPARTMENT RESPONSIBILITY US __ 1. Perform 0BwOS RETS 2.1.B-1, "Unit Common Pre-Release Source Check of Liquid Effluent Monitor 0PR01J."

Time: 30 min ago Date: _ today _

2. Control Room Supervisor: I have verified that either the 0BwOS RETS 2.1.B-1 Acceptance Criteria has been met, or 0RE-PR001 is inoperable.

_____ Ulyses Supervisor _______________ today /_25 min ago Control Room Supervisor Date Time 35

BwOP WX-501T1 Revision 66 Continuous Use NOTE Two release path options are available. Generally, the Low Flow release would primarily be used when liquid radwaste inventory is high (i.e. outage). The Ultra Low Flow release rate is the preferred path and is correlated to the current river flow. This path would primarily be used when liquid radwaste inventory is normal. Contact Ops Supervisor for determination of which release flow path to use based on current liquid radwaste inventory, conditions, equipment availability, etc.

F JO 3. Before proceeding, VERIFY that no other liquid release packages are in progress which would interfere with this one (current releases, interlock checks, etc).

JO ___ 4. CONTACT OPS Supervisor for release flow rate path.

5. INDICATE which release flow rate path will be used (Ref. step B.2):

JO ___ Low Flow N/A __ Ultra Low Flow.

36

BwOP WX-501T1 Revision 66 Continuous Use NOTE If 0RE-PR010 is inoperable and AAR 0BwOS RETS 2.1-1a has been initiated, Step F.6. is not required.

F. 6. PERFORM the following from the RM-11 Console to OBTAIN 0RE-PR010 (0PS110) setpoints:

JO ___ a. DEPRESS Grid 1 key.

JO ___ b. KEY in 110.

JO ___ c. DEPRESS SEL key.

JO ___ d. VERIFY 0PR10J (0PS110) selected.

JO ___ e. DEPRESS CHAN ITEMS key.

JO __ f. RECORD the following CHAN ITEMS:

JO ___ Chan Item 9 (HIGH Alarm Setpoint) __8.19-6_____ µCi/ml JO ___ Chan Item 10 (ALERT Alarm Setpoint) __5.73-6_____ µCi/ml 37

BwOP WX-501T1 Revision 66 Continuous Use NOTE If 0RE-PR001 is inoperable and AAR 0BwOS RETS 2.1-1a has been initiated, Step F.7. is not required.

F. 7. PERFORM the following from the RM-11 Console to OBTAIN 0RE-PR001 (0PS101) setpoints:

JO ___ a. DEPRESS Grid 1 key.

JO ___ b. KEY in 101.

JO ___ c. DEPRESS SEL key JO ___ d. VERIFY 0PR01J (0PS101) selected.

JO ___ e. DEPRESS CHAN ITEMS key.

JO ___ f. RECORD the following CHAN ITEMS:

JO ___ Chan Item 9 (HIGH Alarm Setpoint) ____1.31E-4_____ µCi/ml JO ___ Chan Item 10 (ALERT Alarm Setpoint) ___6.56E-5_____ µCi/ml 38

BwOP WX-501T1 Revision 66 Continuous Use F. 8. PERFORM the following to prepare for release.

a. VERIFY 0BwOSR 0.1-0 daily channel check is complete on:

NOTE If 0RE-PR001 is inoperable and AAR 0BwOS RETS 2.1-1a has been initiated, the following step is not required.

JO ___ Rad Monitor 0RE-PR001: Liquid Radwaste Effluent.

NOTE If 0RE-PR010 is inoperable and AAR 0BwOS RETS 2.1-1a has been initiated, the following step is not required.

JO ___ Rad Monitor 0RE-PR010: Station Blowdown.

NOTE 0UR-CW032 is inoperable and AAR 0BwOS RETS 2.1-1a has been initiated, the following step is not required.

JO ___ Station Blowdown Line Monitor Loop 0UR-CW032.

JO ___ b. OPEN 0WX354, Release Tk Dsch to Process Rad Mon System (TB 401 J-18 between tanks).

VERIFICATION JB ___

39

BwOP WX-501T1 Revision 66 Continuous Use NOTE If 0RE-PR001 is inoperable and AAR 0BwOS RETS 2.1-1a has been initiated, Steps F.9. and F.10. are not required.

NOTE For a release through the low flow rate path COMPLETE Step F.9.

and mark Step F.10. N/A. If a Ultra Low Flow rate release, GO TO Step F.10. and mark Step F.9. N/A.

NOTE If the 0PR01J is in High Alarm at this point in the procedure due to high background, it will be necessary to reset the HIGH alarm setpoint to a value higher than the background. This will allow the 0AOV-WX896 to open to test the interlock function. Otherwise, Step F.9.f. is not required.

NOTE Upon receipt of a high radiation signal at 0PR01J, the Release Tank Discharge Valves, 0WX353 and 0WX896 will remain closed until the high radiation signal seal-in is reset at 0PL01J.

F. 9. VERIFY valve 0AOV-WX896, Release Tank Disch Isolation Valve, automatically closes on high radiation by PERFORMING the following Steps:

RO/JO a. VERIFY/RESET CIRC WTR BLOWDOWN FLOW LOW annuciator 0PL01J-7-B6.

RO/JO b. VERIFY/CLOSE 0AOV-WX897, Flow Control Radwaste Effluent Discharge Valve.

RO/JO c. VERIFY/CLOSE 0AOV-WX890, Release Tk Pp 0WX53P Dsch Isol.

RO/JO d. VERIFY/OPEN 0AOV-WX889, Release Tk Pp 0WX01P Dsch Isol.

RO/JO e. VERIFY/START 0WX01P, Release Tank Pump.

40

BwOP WX-501T1 Revision 66 Continuous Use CAUTION Some actions possible in the Supervisor Mode may have serious detrimental effects on system operation.

Therefore use caution when in this mode and do not leave the RM-11 console unattended when it is in this mode.

F. 9. f. IF the 0PR01J is in HIGH alarm, PERFORM the following CHANGE the HIGH alarm setpoint to a value higher than background. This will allow the RELEASE TANK 0WX01T DISCHARGE HEADER RADIATION HIGH alarm (Window 77B01 on 0PL01J) to be reset and, the 0AOV-WX896 valve to be opened after its seal-in has been reset. This can be accomplished as follows:

_____ 1) VERIFY/PLACE the RM-11 Console in SUPERVISOR MODE.

_____ 2) DEPRESS Grid 1 key.

_____ 3) KEY in 101.

_____ 4) DEPRESS SEL key.

_____ 5) VERIFY 0PR01J (0PS101) selected.

_____ 6) DEPRESS CHAN ITEM key.

_____ 7) KEY in 9.

_____ 8) DEPRESS SEL key (CHAN ITEM 9 should be displayed in reverse characters.)

_____ 9) KEY in a HIGH alarm setpoint USING the format XYZ +/- AB (i.e. a value of 3.76E-10 would be entered as 376-10).

_____ 10) DEPRESS the ENTER key. (The new value will be displayed after a short delay.)

RO/JO g. VERIFY/CLEAR RELEASE TANK 0WX01T DISCHARGE HEADER RADIATION HIGH Annunciator (Window 77B01 on 0PL01J).

41

BwOP WX-501T1 Revision 66 Continuous Use NOTE Upon receipt of a high radiation signal at 0PR01J, the Release Tank Discharge Valves, 0WX353 and 0WX896 will remain closed until the high radiation signal seal-in is reset at 0PL01J.

F JO 9. h. OPEN 0AOV-WX896, Release Tank Disch Isolation Valve.

i. PERFORM the following to AUTO CLOSE valve 0AOV-WX896, Release Tank Disch Isolation Valve, by LOWERING the Liquid Radwaste Effluent monitor 0RE-PR001 HIGH alarm setpoint to a value below the current activity as follows:

JO ___ 1) VERIFY/PLACE the RM-11 Console in SUPERVISOR MODE.

JO __ 2) DEPRESS Grid 1 key.

JO ___ 3) KEY in 101.

JO ___ 4) DEPRESS SEL key.

JO ___ 5) VERIFY 0PR01J (0PS101) selected.

JO ___ 6) DEPRESS CHAN ITEM key.

JO ___ 7) KEY in 9.

JO ___ 8) DEPRESS SEL key (CHAN ITEM 9 should be displayed in reverse characters.)

JO ___ 9) RECORD the current activity reading:

____8.12E-7______

JO ___ 10) KEY in a HIGH alarm setpoint USING the format XYZ +/- AB (i.e. a value of 3.76E-10 would be entered as 376-10), below the current activity value (from the upper right corner of the display) USING the format XYZ +/- AB for XYZ E +/- AB (i.e. a value of 3.76E-10 would be entered as 376-10).

JO ___ 11) RECORD the new HIGH alarm setpoint that was entered (channel item 9):

__1.31E-7______

JO ___ 12) DEPRESS the ENTER key.

JO ___ 13) ACKNOWLEDGE the alarm at the RM-11 console.

42

BwOP WX-501T1 Revision 66 Continuous Use F RO/JO 9. j. VERIFY 0AOV-WX896, Release Tank Disch Isolation Valve, Auto Closes.

RO/JO k. VERIFY RELEASE TANK 0WX01T DISCHARGE HEADER RADIATION HIGH alarm (Window 77B01 at 0PL01J) annunciates at 0PL01J and ACKNOWLEDGE.

RO/JO l. PLACE key locked switch for 0AOV-WX896, Release Tank Disch Isolation Valve, in CLOSE.

CAUTION Some actions possible in the Supervisor Mode may have serious detrimental effects on system operation.

Therefore use caution when in this mode and do not leave the RM-11 console unattended when it is in this mode.

JO ___ m. VERIFY/ADJUST the ALERT Alarm and HIGH Alarm setpoints for 0RE-PR001 (0PS101) to the values specified by Rad Protection in Step D.7.b. USING the instructions that follow.

JO ___ 1) VERIFY/PLACE the RM-11 Console in SUPERVISOR MODE.

JO ___ 2) DEPRESS Grid 1 key.

JO ___ 3) KEY in 101.

JO ___ 4) DEPRESS SEL key.

JO ___ 5) VERIFY 0PR01J (0PS101) selected.

JO ___ 6) DEPRESS CHAN ITEM key.

JO ___ 7) KEY in 10.

JO ___ 8) DEPRESS SEL key (CHAN ITEM 10 should be displayed in reverse characters.)

JO ___ 9) KEY in the new ALERT alarm setpoint USING the format XYZ +/- AB (i.e. a value of 3.76E-10 would be entered as 376-10)

JO ___ 10) DEPRESS the ENTER key. (The new value will be displayed after a short delay.)

43

BwOP WX-501T1 Revision 66 Continuous Use F JO 9. m. 11) VERIFY the new ALERT alarm setpoint is displayed.

VERIFICATION _ JH JO ___ 12) KEY in 9.

JO ___ 13) DEPRESS SEL key (CHAN ITEM 9 should be displayed in reverse characters.)

JO ___ 14) KEY in the new HIGH alarm setpoint USING the format XYZ +/- AB (i.e. a value of 3.76E-10 would be entered as 376-10).

JO __ 15) DEPRESS the ENTER key. (The new value will be displayed after a short delay.)

JO ___ 16) VERIFY the new HIGH alarm setpoint is displayed.

VERIFICATION _ JH JO ___ n. VERIFY/CLEAR RELEASE TANK 0WX01T DISCHARGE HEADER RADIATION HIGH annunciator (Window 77B01 at 0PL01J).

44

BwOP WX-501T1 Revision 66 Continuous Use NOTE If the 0PR01J is in High Alarm at this point in the procedure due to high background, it will be necessary to reset the HIGH alarm setpoint to a value higher than the background. This will allow the 0AOV-WX353 to open to test the interlock function. Otherwise, Step F.10.f. is not required.

F. 10. VERIFY valve 0AOV-WX353, Release Tank Disch Isolation Valve, automatically closes on high radiation by PERFORMING the following Steps for a release through the Ultra Low Flow rate path:

_____ a. VERIFY sufficient blowdown flow is established.

_____ b. VERIFY/CLOSE 0AOV-WX302, Flow Control Radwaste Effluent Discharge Valve.

_____ c. VERIFY/CLOSE 0AOV-WX890, Release Tk Pp 0WX53P Dsch Isol.

_____ d. VERIFY/OPEN 0AOV-WX889, Release Tk Pp 0WX01P Dsch Isol.

_____ e. VERIFY/START 0WX01P, Release Tank Pump.

45

BwOP WX-501T1 Revision 66 Continuous Use CAUTION Some actions possible in the Supervisor Mode may have serious detrimental effects on system operation.

Therefore use caution when in this mode and do not leave the RM-11 console unattended when it is in this mode.

F. 10. f. IF the 0PR01J is in HIGH alarm, CHANGE the HIGH alarm setpoint to a value higher than background. This will allow the RELEASE TANK 0WX01T DISCHARGE HEADER RADIATION HIGH alarm (Window 77B01 on 0PL01J) to be reset, and the 0AOV-WX353 valve to be opened after its seal-in has been reset. This can be accomplished as follows (N/A if 0PR01J is not in alarm):

_____ 1) VERIFY/PLACE the RM-11 Console in Supervisor Mode.

_____ 2) DEPRESS Grid 1 key.

_____ 3) KEY in 101.

_____ 4) DEPRESS SEL key.

_____ 5) VERIFY 0PR01J (0PS101) selected.

_____ 6) DEPRESS CHAN ITEM key.

_____ 7) KEY in 9.

_____ 8) DEPRESS SEL key (CHAN ITEM 9 should be displayed in reverse characters).

_____ 9) KEY in a new HIGH alarm setpoint USING the format XYZ +/- AB (i.e. a value of 3.76E-10 would be entered as 376-10).

_____ 10) DEPRESS the ENTER key (The new value will be displayed after a short delay).

46

BwOP WX-501T1 Revision 66 Continuous Use F ____ 10. g. VERIFY/CLEAR RELEASE TANK 0WX01T DISCHARGE HEADER RADIATION HIGH Annunciator (Window 77B01 on 0PL01J).

NOTE Upon receipt of a high radiation signal at 0PR01J, the Release Tank Discharge Valves, 0WX353 and 0WX896 will remain closed until the high radiation signal seal-in is reset at 0PL01J.

_____ h. OPEN 0AOV-WX353, Release Tank Disch Isolation Valve. (The key to operate the 0AOV-WX353 valve control switch must be obtained from the OPS Supervisor or Shift Manager.)

i. PERFORM the following to AUTO CLOSE valve 0AOV-WX353, Release Tank Disch Isolation Valve, by LOWERING the Liquid Radwaste Effluent monitor 0RE-PR001 HIGH alarm setpoint to a value below the current activity as follows:

_____ 1) VERIFY/PLACE the RM-11 Console in SUPERVISOR MODE.

_____ 2) DEPRESS the Grid 1 key.

_____ 3) KEY in 101.

_____ 4) DEPRESS SEL key.

_____ 5) VERIFY 0PR01J (0PS101) selected.

_____ 6) DEPRESS CHAN ITEM key.

_____ 7) KEY in 9.

_____ 8) DEPRESS SEL key CHAN ITEM 9 should be displayed in reverse characters.)

_____ 9) KEY in a new HIGH alarm setpoint below the current activity value (from the upper right corner of the display) USING the format XYZ

+/- AB for XYZ E +/- AB (i.e. a value of 3.76E-10 would be entered as 376-10).

_____ 10) RECORD the new HIGH alarm setpoint that was entered (channel item 9). ________________

_____ 11) DEPRESS the ENTER key.

_____ 12) ACKNOWLEDGE the alarm at the RM-11 console.

_____ j. VERIFY 0AOV-WX353, Release Tank Disch Isolation Valve, Auto Closes.

47

BwOP WX-501T1 Revision 66 Continuous Use F ____ 10. k. VERIFY RELEASE TANK 0WX01T DISCHARGE HEADER RADIATION HIGH alarm annunciates at 0PL01J and ACKNOWLEDGE.

(Window 77B01 on 0PL01J)

_____ l. PLACE key locked switch for 0AOV-WX353, Release Tank Disch Isolation Valve, in CLOSE.

CAUTION Some actions possible in the Supervisor Mode may have serious detrimental effects on system operation.

Therefore use caution when in this mode and do not leave the RM-11 console unattended when it is in this mode.

_____ m. VERIFY/ADJUST the ALERT Alarm and HIGH Alarm setpoints for 0RE-PR001 (0PS101) to the values specified by Rad Protection in Step D.7.b. USING the instructions that follow.

_____ 1) VERIFY/PLACE the RM-11 Console in SUPERVISOR MODE.

_____ 2) DEPRESS the Grid 1 Key.

_____ 3) KEY in 101.

_____ 4) DEPRESS SEL key.

_____ 5) VERIFY 0PR01J (0PS101) selected.

_____ 6) DEPRESS CHAN ITEMS.

_____ 7) KEY in 10.

_____ 8) DEPRESS SEL key (CHAN ITEM 10 should be displayed in reverse characters.)

_____ 9) KEY in the new ALERT alarm setpoint USING the format XYZ +/- AB (i.e. a value of 3.76E-10 would be entered as 376-10).

_____ 10) DEPRESS the ENTER key. The new value will be displayed after a short delay.

_____ 11) VERIFY the new ALERT alarm setpoint is displayed.

VERIFICATION _____

_____ 12) KEY in 9.

48

BwOP WX-501T1 Revision 66 Continuous Use F ____ 10. m. 13) DEPRESS SEL key (CHAN ITEM 9 should be displayed in reverse characters.)

_____ 14) KEY in the new HIGH alarm setpoint USING the format XYZ +/- AB (i.e. a value of 3.76E-10 would be entered as 376-10).

_____ 15) DEPRESS the ENTER key (The new value will be displayed after a short delay).

_____ 16) VERIFY the new HIGH alarm setpoint is displayed.

VERIFICATION _____

_____ n. VERIFY/CLEAR RELEASE TANK 0WX01T DISCHARGE HEADER RADIATION HIGH annunciator (Window 77B01 at 0PL01J).

49

BwOP WX-501T1 Revision 66 Continuous Use NOTE Step F.11. is not required if 0RE-PR010 is inoperable and AAR 0BwOS RETS 2.1-1a has been initiated or if ALERT ALARM AND HIGH ALARM setpoints have not changed from Step D.8.b.

F ____ 11. VERIFY/ADJUST the ALERT and HIGH setpoints for 0RE-PR010 to the values specified by Rad Protection in Step D.8.b. using the instructions that follow.

_____ a. VERIFY/PLACE the RM-11 Console in Supervisor Mode.

_____ b. DEPRESS the Grid 1 key.

_____ c. KEY in 110.

_____ d. DEPRESS SEL key.

_____ e. VERIFY 0PR10J (0PS110) selected.

_____ f. DEPRESS CHAN ITEM key.

_____ g. KEY in 10.

_____ h. DEPRESS SEL key (CHAN ITEM 10 should be displayed in reverse characters.)

_____ i. KEY in the new ALERT alarm setpoint USING the format XYZ +/- AB (i.e. a value of 3.76E-10 would be entered as 376-10).

_____ j. DEPRESS the ENTER key (The new value will be displayed after a short delay).

_____ k. VERIFY the new ALERT alarm setpoint is displayed.

VERIFICATION _____

_____ l. KEY in 9.

_____ m. DEPRESS SEL key (CHAN ITEM 9 should be displayed in reverse characters).

50

BwOP WX-501T1 Revision 66 Continuous Use F ____ 11. n. KEY in the new HIGH alarm setpoint USING the format XYZ +/- AB (i.e. a value of 3.76E-10 would be entered as 376-10).

_____ o. DEPRESS the ENTER key (The new value will be displayed after a short delay).

_____ p. VERIFY the new HIGH alarm setpoint is displayed.

JO __ 12. PLACE the RM-11 Console in the NORMAL MODE.

13. RECORD the following data in the space provided.

JO __ a. Circulating Water Blowdown Rate ___25400_____ gpm (0UR-CW032 at PNL 0PM01J, or computer Point F2400)

JO __ b. VERIFY CW BLOWDOWN RATE IS EQUAL TO OR GREATER THAN 8,000 gpm.

14. Control Room Supervisor: I have reviewed Part F and have verified it is accurate and complete.

______ Joe Supervisor __________________/ today/_15 min ago Control Room Supervisor Date Time 51

BwOP WX-501T1 Revision 66 Continuous Use G. SHIFT MANAGER OR SRO RESPONSIBILITY SM __ 1. VERIFY that Steps B.3., C.13., D.10., E.4 (if applicable), and F.14 are signed.

NOTE Biocide treatment of CW requires isolation of CW blowdown, if the dechlorination skid is not operational. The expected time of release and release duration must be considered so that both biocide treatment and the release can be accommodated.

2. VERIFY that the actual Circulating Water Blowdown Rate is equal to or greater than 8,000 gpm (0UR-CW032 at PNL 0PM01J, or Computer Point F2400).

__ Shift Manager __________________/_ today _

SHIFT MANAGER or SRO Date SM __ 3. Have an NSO PERFORM the following to ESTABLISH the required conditions for liquid release:

a. LOGIN to the alarm Agent website as follows: (N/A if already logged in.)

1) ACCESS the alarm Agent website at one of the following:

JO __ www.AlarmAgent.com

_____ BS0.ALARMAGENT.com JO __ 2) CLICK on User Login.

JO __ 3) ENTER one of the following combinations of User/Passwords to login:

USER: braidwoodops, Password: braidwoodops USER: braidwoodops2, Password: braidwoodops2 USER: braidwoodops3, Password: braidwoodops3 USER: braidwoodops4, Password: braidwoodops4 JO __ 4) CLICK Submit.

JO __ 5) VERIFY no active alarm in the Notification Groups for the Vacuum Breaker. (Verifies no vault level alarm.)

52

BwOP WX-501T1 Revision 66 Continuous Use NOTE Some Vacuum Breaker Vaults may have duplicate entries for the RTUs. These entries always show OFFLINE when checking RTU status. If a duplicate entry is displayed and there is an online RTU in the Vacuum Breaker Vault, these duplicate entries may be ignored.

Select Next RTU tab to continue with Vacuum Breaker Vault check.

G JO 3. a. 6) SELECT View RTU status.

JO __ 7) From Select RTU dropdown menu, SELECT Vacuum Bkr Vault 01.

JO __ 8) CLICK View Status.

b. CHECK the following for the CW Blowdown Vacuum Breaker vault monitoring status RTUs status:

1) Under Last Know RTU STATE:

JO __ Last Contact with RTU within previous 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> JO __ RTU online - Yes

2) Under Channel State:

JO __ Channel 1 - No water in vault, Normal (N/A for Interim Remediation Pump) or water detected in Vault, Alarm, Now Normal JO __ AC Power - Power On JO __ Battery - Battery OK

3) SELECT Next RTU to obtain the information for the next RTU.

JO __ c. When the CW Blowdown Vacuum Breaker vault RTUs have been VERIFIED acceptable, CONTINUE with the procedure.

53

BwOP WX-501T1 Revision 66 Continuous Use G SM 4. PLACE a placard stating "Liquid Release in Progress" at 0PM01J.

5. APPROVAL FOR RELEASE: ___ Shift Manager _____/_ today/5 min ago SHIFT MANAGER or SRO Date Time

6. COMMENTS ______ none__________________________________________

54

BwOP WX-501T1 Revision 66 Continuous Use H. OPERATING DEPARTMENT RESPONSIBILITY - Discharging Release Tank 0WX01T to Circulating Water Blowdown Line NOTE DO NOT release 0WX01T if Kankakee River Gage Height is 6.50 feet (flood stage).

NOTE If during the release, Circ Water Blowdown flow (Computer Point F2400) is reduced to <8,000 gpm, terminate the release. If during the release, Circ Water Blowdown flow is reduced to <7,000 gpm (low flow interlock setpoint), VERIFY the release is terminated. If Circ Water Blowdown flow can be re-established 8,000 gpm, the release may be restarted at step G.2 provided that the following conditions are met:

Shift Manager permission is obtained.

All applicable Steps are re-initialed/re-verified as necessary.

No additions have been made to the Release Tank.

Release totalizers have not been reset and the original totalizer readings are used to calculate the gallons released.

NOTE If Station Blowdown Line Flow Monitor (CW-032) is inoperable, effluent releases via this pathway may continue for up to 30 days provided the flow rate is estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases.

NOTE If this procedure is aborted before any effluent is released, VERIFY/PERFORM Steps H.24 through Step I. before exiting this procedure.

NOTE The purpose of the release window is to minimize the interaction with the City of Wilmington Water Department intake periods.

Release window is not applicable when using the Ultra Low Flow release path through the diffuser.

55

BwOP WX-501T1 Revision 66 Continuous Use NOTE Rad Protection or Operations is to notify Chemistry when a release package is cancelled prior to release so that the NPDES data sheets can be updated as required.

H. 1. Ops Supervisor performs the following:

NOTE Kankakee River Flow rate is normally obtained via the internet site for the U.S. Geological Survey (usgs.gov), WILMINGTON DATA (from the appropriate Unit Supervisor). If data is unavailable, RECORD most recent data from the Unit Supervisor turnover.

a. OBTAIN and RECORD current Kankakee River flow data:

USGS website;

_____ Stream Flow: __________ CFS

_____ At Date: _____/_____/_____

_____ At Time: __________

IF Kankakee River flow data is NOT available from the USGS website, CONTACT Chemistry/Environmental for concurrence to release using alternate river flow data provided by Chemistry/Environmental:

_____ a) River flow rate provided by Chemistry/Environmental

__________ CFS

_____ b) Chemistry/Environmental Personnel providing data:

Name: ___________________________________

Time: __________________

Date: __________________

_____ b. RECORD the Kankakee River flow rate and the source of the data obtained in step H.1.a. in the Unit Supervisor Turnover.

56

BwOP WX-501T1 Revision 66 Continuous Use NOTE Steps H.1.c and H.1.d can be marked N/A if the Ultra Low Flow Release Path is not being used.

H. 1. c. When using the Ultra Low flow path, CALCULATE Release flow Rate.

1) OBTAIN and RECORD the current lake blowdown flow from Plant Parameter Displays Trend ID BRW01V_F2400.

Lake Blowdown Flow: __________GPM

2) RECORD the release tank H-3 concentration from step C.7:

Release tank H-3 concentration: __________ uCi/ml

3) When using the Ultra Low Flow release path, PERFORM the following calculation to determine the maximum release rate.

Ultra Low Flow River Flow (cfs) x Lake Blowdown Flow (gpm) x 2.15E-08

=

Path Release Rate Release Tank H-3 Concentration (uCi/ml)

Ultra Low Flow

= _________ GPM Path Release Rate

d. VERIFY that the value calculated for the Ultra Low Flow Path Release Rate is less than 20 gpm. IF NOT, use 20 gpm as the maximum release rate.

57

BwOP WX-501T1 Revision 66 Continuous Use H. 1. e. DETERMINE the following:

_____ 1) Liquid Release Window per BwOP WX-501T2, Liquid Release Window Determination. (Can be N/A if using the Ultra Low Flow Flowpath through the diffuser.)

2) Maximum Release Rate:

_____ a) RECORD the Chemistry Release Rate from step C.10.b. or RETDAS permit:

__________ GPM NOTE N/A step H.1.e.2)b) if using the Ultra Low Flow path through the diffuser.

N/A step H.1.e.2)c) if using the Low Flow Path.

_____ b) RECORD the Radioactive Release Rate from step D.6.c or RETDAS permit if using the Low Flow path:

__________ GPM

_____ c) RECORD the Radioactive Release Rate from step H.1.c if using the Ultra Low Flow path:

__________ GPM NOTE The maximum release rate SHALL NOT exceed 50 gpm for the Low Flow path or 20 gpm for the Ultra Low Flow path.

_____ d) RECORD the most limiting (smallest) value from step H.1.e.2) a)-c) as the Maximum Release Rate below:

Maximum Release Rate = ________ GPM ( 50 gpm or 20 gpm) 58

BwOP WX-501T1 Revision 66 Continuous Use H. 1. f. RECORD the Liquid Release Window times (N/A if using the Ultra Low Flow path through the diffuser):

_____ Target Start Time: __________

_____ Start After __________

_____ Start Before __________

_____ Start after time recorded in Step D.3.h. (Applies to second bullet only if D.3.h. has a specified time, otherwise N/A.)

g. EVALUATE the expected time of release so that both biocide treatment and the release can be accommodated considering:

_____ CW Biocide treatment requires associated Unit CW blowdown isolated, if the dechlorination skid is not operational.

_____ At least 8000 GPM CW blowdown flow is required for the Liquid release.

NOTE Steps H.1.h and H.1.i can be marked N/A if the Ultra Low Flow Release Path through the diffuser is being used.

h. VERIFY release will start within release start time window recorded in step H.1.f. If release cannot start within times recorded in step H.1.f. this step is N/A. GO TO step H.1.i.

_________________________________/_____/_____

OPS Supervisor Date Time

i. To start release outside of release start time window recorded in step H.1.f. VERIFY Authorization to Release Outside of Release Window, BwOP WX-501T3, is completed and retained with this package.

_________________________________/_____/_____

OPS Supervisor Date Time 59

BwOP WX-501T1 Revision 66 Continuous Use CAUTION Changes in CW Blowdown flow will affect the backpressure in the blowdown line. Lowering pressure or flow may result in exceeding the liquid release rate limit.

H. 1. j. VERIFY the following:

BwOP CW-12 is NOT being performed.

CW Blowdown line backpressure has been established per BwOP CW-12. (Backpressure is not required if CW Blowdown Booster Pumps are not in operation.)

_________________________________/_____/_____

OPS Supervisor Date Time NOTE If this procedure must be exited prior to its completion, the following temporary alteration must be restored per Step H.26. prior to exit.

2. PERFORM the following if AAR 0BwOS RETS 2.1-1a is in effect for 0RE-PR001 (refer to Step B.1.):

NOTE To comply with CC-AA-112, Attachment A must be filled out during installation and removal of TCC.

a. OBTAIN Shift Manager or designee permission to perform the following Temporary Electrical Alteration.

_________________________________/_____/_____

Shift Manager/Designee Date Time SUPERVISOR VERIFICATION _____

_____ b. REMOVE Relay Block K1 at 0PR01J (inside the AC Power Panel) to allow opening of 0AOV-WX896/353, Release Tank Disch Isolation Valve.

Supervisor Verification _____

60

BwOP WX-501T1 Revision 66 Continuous Use H. 2 c. LOCALLY at 0PR01J place two placards stating "K1 RELAY REMOVED FOR LIQUID RELEASE":

_____ One on the AC Power Panel for 0PR01J

_____ One on the Rad Detector Cabinet for 0PR01J.

3. RECORD the following data in the space provided.

_____ a. Tank Level Start __________ %

(0LR-WX028, 0WX01T Level Indication at PNL 0PL01J)

_____ b. VERIFY level in Step H.3.a. is +/-5% OF LEVEL RECORDED IN STEP A.2, or receive Supervisor approval to continue.

c. RESET the Batch Totalizer reading to zero at PNL 0PL01J for the flowpath being used (This step may be marked N/A if Batch Totalizer is inoperable):

_____ 0FQI-WX001A, Ultra Low Flow

_____ 0FQI-WX630A, Low Flow

d. RESET the Cumulative Totalizer reading to zero at PNL 0PL01J for the flowpath being used (This step may be marked N/A if Cumulative Totalizer is inoperable):

_____ 0FQI-WX001B, Ultra Low Flow

_____ 0FQI-WX630B, Low Flow 61

BwOP WX-501T1 Revision 66 Continuous Use CAUTION Failure to record and use the correct maximum permissible release rate may result in violation of NPDES and/or 10CFR20 release criteria.

NOTE When using the Low Flow release path, the MAXIMUM RELEASE RATE SHALL not exceed 50 gpm. Do NOT record a value greater than 50 gpm in the following step when using the Low Flow release path. When using the Ultra Low Flow release path, the MAXIMUM RELASE RATE SHALL NOT exceed 20 gpm. Do NOT record a value greater than 20 gpm in the following step when using the Ultra Low Flow release path.

H____ 3. e. Maximum Release Rate from H.1.e.2)d)

__________ GPM SUPERVISOR VERIFICATION _____

_____ 4. STOP 0WX36M, Release Tank Mixer (if applicable).

62

BwOP WX-501T1 Revision 66 Continuous Use NOTE If 0RE-PR001 is inoperable and AAR 0BwOS RETS 2.1-1a has been initiated, Step F.1 is not required.

H____ 5. VERIFY Steps F.1. and F.2. have been completed within the previous 24 hrs (IF NOT, RE-PERFORM Steps F.1 and F.2.).

NOTE If 0RE-PR001 is inoperable and AAR 0BwOS RETS 2.1-1a has been initiated, verification is required in steps H.6. through H.13.

NOTE If any CW Blowdown vault alarms while a release is in progress, immediately STOP the release.

_____ 6. VERIFY/CLOSE 0AOV-WX834, Release Tank Inlet Isolation Valve for Release Tank 0WX01T.

SUPERVISOR VERIFICATION _____

_____ 7. VERIFY/CLOSE 0AOV-WX017, Release Tank Recycle Valve (Release Tank Discharge to Turbine Building Equipment Drain Tank Isolation Valve).

SUPERVISOR VERIFICATION _____

_____ 8. VERIFY/CLOSE 0AOV-WX910, Release Tank Pump Disch Valve (Release Tank Discharge to Regeneration Waste Drain Tank).

SUPERVISOR VERIFICATION _____

_____ 9. VERIFY/CLOSE 0AOV-WX302, Release Tank Discharge Control Valve/( Ultra Low Flow Path).

SUPERVISOR VERIFICATION _____

_____ 10. VERIFY/CLOSE, 0AOV-WX897, Release Tank Discharge Flow Control valve/(Low Flow Path).

SUPERVISOR VERIFICATION _____

63

BwOP WX-501T1 Revision 66 Continuous Use H____ 11. VERIFY/OPEN 0AOV-WX889, Release Tank Pump 0WX01P Discharge Isolation Valve.

SUPERVISOR VERIFICATION _____

NOTE The Release Tank Pump trips at approximately 15% tank level.

NOTE For releases through the low flow rate path, < 50 GPM or as specified by OPS Supervisor, COMPLETE step H.12 and mark Step H.13 "N/A". For releases through the Ultra Low Flow rate path, mark Step H.12 "N/A" and GO TO step H.13.

NOTE While releasing from the 0WX01T, high radiation from the 0PR90J will not cause the Release Tank Discharge Valves (0WX353 and 0WX896) to auto-close, because the 0PR90J is associated with the 0WX26T only.

CAUTION ALL Releases through the Low Flow flowpath SHALL be limited to <10,000 gallons. Secure the release prior to 10,000 gallons.

12. LOW FLOW RELEASE, PERFORM the following:

_____ a. VERIFY step F.9 has been completed. (N/A if 0RE-PR001 is inoperable and AAR 0BwOS RETS 2.1-1a has been initiated.)

_____ b. OBTAIN the key for 0AOV-WX896, Release Tank Outlet Valve.

64

BwOP WX-501T1 Revision 66 Continuous Use NOTE If Circ. Water Blowdown Flow Low and/or Release Tank Disch Header Radiation High alarms are lit, it may be necessary to reset the Rel. Tank Disch Header & Isolation Valves 0WX896 & 0WX353 by pressing their reset button prior to opening 0AOV-WX896.

NOTE Upon receipt of a high radiation signal at 0PR01J, the Release Tank Discharge Valves, 0WX353 and 0WX896 will remain closed until the high radiation signal seal-in is reset at 0PL01J.

NOTE NOTIFY the Shift Manager/Emergency Director to evaluate for Emergency Plan conditions if the maximum release rate is exceeded.

H____ 12. c. OPEN 0AOV-WX896, Release Tank Outlet Isolation Valve.

SUPERVISOR VERIFICATION _____

_____ d. VERIFY/CLOSE 0AOV-WX015, Release Tank 0WX01T Pump Recirc Valve.

SUPERVISOR VERIFICATION _____

65

BwOP WX-501T1 Revision 66 Continuous Use CAUTION The release rate shall NOT exceed 50 gpm.

H____ 12. e. THROTTLE OPEN 0AOV-WX897, Release Tank Discharge Flow Control Valve, with controller 0FK-WX630, TO OBTAIN a maximum discharge flowrate of less than the release rate specified in step H.3.e. ______ GPM by checking at least one of the following:

_____ Low Flow Totalizer accumulating (0FQ-WX-630A, 0FIQ-WX-630B).

_____ Low Flow Recorder rising (0FR-WX-630 Low Flow Indication).

_____ 0WX01T Level Recorder lowering (0LR-WX028, 0WX01T Level Indication).

_____ Computer Point (F0002) for release rate rising.

SUPERVISOR VERIFICATION _____

f. RECORD the following

_____ Release Start Time: ______:______

_____ Date: ______

SUPERVISOR VERIFICATION _____

_____ g. THROTTLE OPEN 0AOV-WX897, Release Tank Discharge Flow Control Valve, with controller 0FK-WX630, To OBTAIN a release rate NOT to exceed the maximum release rate specified in step H.3.e:

SUPERVISOR VERIFICATION _____

66

BwOP WX-501T1 Revision 66 Continuous Use NOTE While releasing from the 0WX01T, high radiation from the 0PR90J will not cause the Release Tank Discharge Valves (0WX353 and 0WX896) to auto-close, because the 0PR90J is associated with the 0WX26T only.

CAUTION Releases Not discharging via the Diffuser SHALL be limited to <10,000 gallons. If releasing via the alternate (old) discharge, secure prior to reaching 10,000 gallons.

Releases through the Ultra-Low Flow flowpath and the Diffuser do not have a total gallons release limit.

H. 13. ULTRA LOW FLOW RELEASE, PERFORM the following:

_____ a. VERIFY step F.10 has been completed. (N/A if 0RE-PR001 is inoperable and AAR 0BwOS RETS 2.1-1a has been initiated.)

_____ b. OBTAIN the key for 0AOV-WX353, Release Tank Outlet Valve.

67

BwOP WX-501T1 Revision 66 Continuous Use NOTE If Circ. Water Blowdown Flow Low and/or Release Tank Disch Header Radiation High alarms are lit, it may be necessary to reset the Rel. Tank Disch Header & Isolation Valves 0WX896 & 0WX353 by pressing their reset button prior to opening 0AOV-WX353.

NOTE Upon receipt of a high radiation signal at 0PR01J, the Release Tank Discharge Valves, 0WX353 and 0WX896 will remain closed until the high radiation signal seal-in is reset at 0PL01J.

NOTE NOTIFY the Shift Manager/Emergency Director to evaluate for Emergency Plan conditions if the maximum release rate is exceeded.

H____ 13. c. OPEN 0AOV-WX353, Release Tank Outlet Isolation Valve.

SUPERVISOR VERIFICATION _____

_____ d. VERIFY/CLOSE 0AOV-WX015, Release Tank 0WX01T Pump Recirc.

Valve.

SUPERVISOR VERIFICATION _____

68

BwOP WX-501T1 Revision 66 Continuous Use CAUTION The Ultra Low release rate shall NOT exceed 20 gpm.

H____ 13. e. THROTTLE OPEN 0AOV-WX302, Release Tank Discharge Flow Control Valve, with controller 0FK-WX001, TO OBTAIN a maximum discharge flowrate of less than the release rate specified in step H.3.e. ______ GPM by checking at least one of the following:

_____ Ultra Low Flow Totalizer accumulating (0FQI-WX001A, 0FQI-WX001B).

_____ Ultra Low Flow Recorder rising (0FR-WX630 Ultra Low Flow Indication).

_____ 0WX01T Level Recorder lowering (0LR-WX028, 0WX01T Level Indication).

_____ Computer Point (F0001) for release rate rising.

SUPERVISOR VERIFICATION _____

f. RECORD the following:

_____ Release Start Time: _____:_____

_____ Date: _____

SUPERVISOR VERIFICATION _____

_____ g. THROTTLE OPEN 0AOV-WX302, Release Tank Discharge Flow Control Valve, with controller 0FK-WX001, TO OBTAIN a release rate NOT to exceed the maximum release rate specified in step H.3.e.

SUPERVISOR VERIFICATION _____

69

BwOP WX-501T1 Revision 66 Continuous Use H____ 14. RECORD the Release Rate from the applicable recorder:

0FR-WX630, Ultra Low Flow Indication _____ Gal/Min ( 20 gpm) 0FR-WX630, Low Flow Indication _____ Gal/Min ( 50 gpm)

SUPERVISOR VERIFICATION _____

(LESS THAN MAXIMUM RATE DETERMINED IN STEP H.3.e.)

NOTE Consider using a timer to calculate the end time of the release based on the flow recorded in step H.14. and the time recorded in H.12.f. or H.13.f.

15. VERIFY the following:

NOTE If Batch and cumulative Totalizers are not operable, Step H.15.a. is not required. Gallons released shall be determined per note prior to Step H.19.e. if both Totalizers are not operable.

a. Batch Totalizer and/or Cumulative Totalizer readings accumulating. (It is acceptable, however, to observe no change in the readings at low release rates):

_____ 0FQI-WX001A, Batch Totalizer (Ultra Low Flow)

_____ 0FQI-WX001B, Cumulative Totalizer (Ultra Low Flow)

_____ 0FQI_WX630A, Batch Totalizer (Low Flow)

_____ 0FQI-WX630B, Cumulative Totalizer (Low Flow)

NOTE If 0FR-WX630 ULTRA LOW FLOW or 0FR-WX630 LOW FLOW, as applicable, is inoperable and AAR 0BwOS RETS 2.1-1a has been initiated, Step H.15.b is not required.

_____ b. PERFORM a Channel Check per 0BwOSR 0.1-0 for 0FR-WX630 ULTRA LOW FLOW or 0FR-WX630 LOW FLOW, as applicable, by OBSERVING indication at 0PL01J.

70

BwOP WX-501T1 Revision 66 Continuous Use NOTE If 0UR-CW032 is inoperable and AAR 0BwOS RETS 2.1-1a has been initiated Step H.15.c. is not required.

H____ 15. c. PERFORM a channel check per 0BwOSR 0.1-0 for the Station Blowdown Flow Monitor by observing 0UR-CW032, indicated on Panel 0PM01J, or computer point F2400.

d. RECORD Station Blowdown Flowrate during release:

_____ 0UR-CW032 __________ GPM

_____ Computer Point __________ GPM

_____ e. RECORD Station Blowdown Flowrate once per 24 Hr. on continuous release:

_____ 0UR-CW032 __________ GPM

_____ Computer Point __________ GPM NOTE If the first attempt to notify the Control Room or the Shift Manager is unsuccessful, proceed with Step H.16 and continue to notify the Control Room and Shift Manager that the release is in progress.

_____ f. NOTIFY Control Room of release in progress.

_____ g. NOTIFY Shift Manager of release in progress.

71

BwOP WX-501T1 Revision 66 Continuous Use H. 16. PERFORM the following rate checks. REFER to Liquid Release Rate Chart on next page.

a. For the Ultra Low Flow rate path check the flow rate by comparing a tank level (0LR-WX028, 0WX01T Level Indication) calculation over a 10 minute interval against computer point F0001 or Flow Recorder (0FR-WX-630 Ultra Low Flow Indication). PERFORM this check twice at the beginning of the release. Providing the flow rates are consistent and below the allowed release rate the release flow rate checks can be relaxed to once every 30 minutes. RECORD each flow rate obtained.

b. For the low flow rate release path check the flow rate by comparing a tank level (0LR-WX028, 0WX01T Level Indication) calculation over a 10 minute interval against computer point F0002 or Flow Recorder (0FR-WX630 Low Flow Indication). PERFORM this check twice at the beginning of the release. Providing the flow rates are consistent and below the allowed release rate the release flow rate checks can be relaxed to once every 30 minutes. RECORD each flow rate obtained.

Indicated Flow:

Computer Point F0001/F0002 or 0LR-WX028 329 X (l/t)

TIME Flow Recorder 0WX630 t l Operator*

Tank LEVEL (%) = gpm Ultra Low Flow/Low Flow (circle one)

Start Stop Start Stop Where: t = Stop Time - Start TIME l = Stop LEVEL - Start Level 329 = gallons per 1% tank level

• After each comparison of indicated flow vs. calculated flow, VERIFY the flowrate is less than the maximum release rate specified in step H.3.e., if not, IMMEDIATELY NOTIFY the OPS Supervisor.

72

BwOP WX-501T1 Revision 66 Continuous Use Liquid Release Rate Chart

%Level Time Change (Minutes)

Change 5.00 10.00 15.00 20.00 25.00 30.00 35.00 40.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.50 32.90 16.45 10.97 8.23 6.58 5.48 4.70 4.11 1.00 65.80 32.90 21.9. 16.45 13.16 10.97 9.40 8.23 1.50 98.70 49.35 32.90 24.68 19.74 16.45 14.10 12.34 2.00 131.60 65.80 43.87 32.90 26.32 21.93 18.80 16.45 2.50 164.50 82.25 54.83 41.13 32.90 27.42 23.50 20.56 3.00 197.40 98.70 65.80 49.35 39.48 32.90 28.20 24.68 3.50 230.30 115.15 76.77 57.58 46.06 38.38 32.90 28.79 4.00 263.20 131.60 87.73 65.80 52.64 43.87 37.60 32.90 4.50 296.10 148.05 98.70 74.03 59.22 49.35 42.30 37.01 5.00 329.00 164.50 109.67 82.25 65.80 54.83 47.00 41.13 5.50 361.90 180.95 120.63 90.48 72.38 60.32 51.70 45.24 6.00 394.80 197.40 131.60 98.70 78.96 65.80 56.40 49.35 6.50 427.70 213.85 142.57 106.93 85.54 71.28 61.10 53.46 7.00 460.60 230.30 153.53 115.15 92.12 76.77 65.80 57.58 7.50 493.50 246.75 164.50 123.38 98.70 82.25 70.50 61.69 8.00 526.40 263.20 175.47 131.60 105.28 87.73 75.20 65.80 8.50 559.30 279.65 186.43 139.83 111.86 93.22 79.90 69.91 9.00 592.20 296.10 197.40 148.05 118.44 98.70 84.60 74.03 9.50 625.10 312.55 208.37 156.28 125.02 104.18 89.30 78.14 10.00 658.00 329.00 219.33 164.50 131.60 109.67 94.00 82.25 10.50 690.90 345.45 230.30 172.73 138.18 115.15 98.70 86.36 11.00 723.80 361.90 241.27 180.95 144.76 120.63 103.40 90.48 11.50 756.70 378.35 252.23 189.18 151.34 126.12 108.10 94.59 12.00 789.60 394.80 263.20 197.40 157.92 131.60 112.80 98.70 12.50 822.50 411.25 274.17 205.63 164.50 137.08 117.50 102.81 13.00 855.40 427.70 285.13 213.85 171.08 142.57 122.20 106.93 13.50 888.30 444.15 296.10 222.08 177.66 148.05 126.90 111.04 14.00 921.20 460.60 307.07 230.30 184.24 153.53 131.60 115.15 14.50 954.10 477.05 318.03 238.53 190.82 159.02 136.30 119.26 15.00 987.00 493.50 329.00 246.75 197.40 164.50 141.00 123.38 15.50 1019.90 509.95 339.97 254.98 203.98 169.98 145.70 127.49 16.00 1052.80 526.40 350.93 263.20 210.56 175.47 150.40 131.60 16.50 1085.70 542.85 361.90 271.43 217.14 180.95 155.10 135.71 17.00 1118.60 559.30 372.87 279.65 223.72 186.43 159.80 139.83 17.50 1151.50 575.75 383.83 287.88 230.30 191.92 164.50 143.94 18.00 1184.40 592.20 394.80 296.10 236.88 197.40 169.20 148.05 18.50 1217.30 608.65 405.77 304.33 243.46 202.88 173.90 152.16 19.00 1250.20 625.10 416.73 312.55 250.04 208.37 178.60 156.28 19.50 1283.10 641.55 427.70 320.78 256.62 213.85 183.30 160.39 20.00 1316.00 658.00 438.67 329.00 263.20 219.33 188.00 164.50 20.50 1348.90 674.45 449.63 337.23 269.78 224.82 192.70 168.61 21.00 1381.80 690.90 460.60 345.45 276.36 230.30 197.40 172.73 21.50 1414.70 707.35 471.57 353.68 282.94 235.78 202.10 176.84 22.00 1447.60 723.80 482.53 361.90 289.52 241.27 206.80 180.95 22.50 1480.50 740.25 493.50 370.13 296.10 246.75 211.50 185.06 23.00 1513.40 756.70 504.47 378.35 302.68 252.23 216.20 189.18 24.00 1579.20 789.60 526.40 394.80 315.84 263.20 225.60 197.40 24.50 1612.10 806.05 537.37 403.03 322.42 268.68 230.30 201.51 25.00 1645.00 822.50 548.33 411.25 329.00 274.17 235.00 205.63 Enter % Enter 10.00 10.00 Flow Rate 329.00 Change Time 73

BwOP WX-501T1 Revision 66 Continuous Use NOTE Closing the 0AOV-WX889 will NOT isolate sample flow to the 0RE-PR001.

H. 17. IF the release MUST be interrupted to provide the operator a break when a relief is unavailable, THEN perform the following:

_____ a. Receive permission from the Shift Manager to secure the release for no more than 30 minutes.

_____ b. Make a log entry and an entry on the table in step H.16. denoting the time the release was stopped.

_____ c. OPEN 0AOV-WX015, Release Tank Pump 0WX01P Recirc Valve.

_____ d. NOTIFY Main Control Room of the following 0AOV-WX889 will be closed, suspending the release.

_____ e. CLOSE 0AOV-WX889, Release Tank Pump 0WX01P Discharge Isol Valve.

_____ f. VERIFY that the release has been stopped.

_____ g. MINIMIZE the pause in the release.

_____ h. NOTIFY Shift Manager that release will be started again.

_____ i. MAKE a log entry and an entry on the table in Step H.16. denoting the time which the release was restarted.

_____ j. OPEN 0AOV-WX889, Release Tank Pump 0WX01T Discharge Isol Valve.

74

BwOP WX-501T1 Revision 66 Continuous Use H____ 17. k. VERIFY/OPEN 0AOV-WX353/896, Release Tank Discharge Isolation Valve, for the flow path being used.

_____ l. CLOSE 0AOV-WX015, Release Tank 0WX01T Pump Recirc Valve.

NOTE Tripping the release tank pump and Closing the Release Tank Discharge Flow Control Valve will stop sample flow to the 0PR01J, thus causing it to interlock. Both actions should be performed with minimal delay to prevent reverse flow from the CW header through 0PR01J into the Release Tank.

_____ 18. WHEN the desired volume of water has been released from Release Tank 0WX01T, PERFORM the following:

a. NOTIFY the Main Control Room of the following:

_____ 1) The 0WX01T release will be complete.

_____ 2) 0PR01J will alarm due to loss of flow.

_____ b. TRIP Release Tank Pump 0WX01P.

NOTE If 0RE-PR001 is inoperable and AAR 0BwOS RETS 2.1-1a has been initiated, verification is required for step H.18.c.

_____ c. CLOSE 0AOV-WX302/897, Release Tank Discharge Flow Control Valve.

SUPERVISOR VERIFICATION _____

75

BwOP WX-501T1 Revision 66 Continuous Use H. 19. RECORD the following:

_____ a. Release Stop Time: ______:______

_____ b. Date: ______

_____ c. Tank Level Final _____________% (0LR-WX028, 0WX01T Level Indication)

NOTE If Batch and Cumulative Totalizers are inoperable, GO TO step H.19.e and mark H.19.d as N/A.

d. Determine the volume of liquid released from the totalizers by performing the following:

_____ 1) RECORD the appropriate Batch Totalizer final reading:

_____ 0FQI-WX630A (Low Flow) _______________ (if operable)

_____ 0FQI-WX001A (Ultra Low Flow) _______________ (if operable)

_____ MULTIPLY the Low Flow reading obtained by 10 (if applicable):

__________ x 10 = __________ Gallons Released (H.19.d.1)

_____ DIVIDE the Ultra Low Flow reading obtained by 10 (if applicable).

__________ ÷ 10 = __________ Gallons Released (H.19.d.1) 76

BwOP WX-501T1 Revision 66 Continuous Use H____ 19. d. 2) RECORD the appropriate CUMULATIVE TOTALIZER final reading:

_____ 0FQI-WX630B (Low Flow) _______________ (if operable)

_____ 0FQI-WX001B (Ultra Low Flow) _______________ (if operable)

_____ MULTIPLY the reading obtained by 10 (if applicable).

__________ x 10 = __________ Gallons Released (H.19.d.2)

_____ DIVIDE the Ultra Low Flow reading obtained by 10 (if applicable).

__________ ÷ 10 = __________ Gallons Released (H.19.d.2)

_____ 3) RECORD the Time and Date of the volume released calculation:

Time: __________

Date: __________

77

BwOP WX-501T1 Revision 66 Continuous Use NOTE The next step is only required if the Batch and Cumulative Totalizers are inoperable. (Otherwise, mark the next step N/A)

H. 19. e. Determine the volume of liquid released by performing a calculation based on the change in tank level by performing the following:

_____ 1) RECORD the value from step A.2: __________ Percent

_____ 2) RECORD the value from step H.19.c: __________ Percent

_____ 3) SUBTRACT step H.19.e.2) from H.19.e.1) and RECORD the Percent Level Change in the space below:

__________ Percent Level Change

_____ 4) MULTIPLY the Percent Change above by 329 to obtain the total number of gallons released and RECORD below:

__________ x 329 = __________ Gallons Released (H.19.e.3)

_____ 5) RECORD the Time and Date of the volume released calculation:

Time: __________

Date: __________

_____ f. NOTIFY the Shift Manager that the release is complete.

_____ g. NOTIFY the Control Room that the release is complete.

_____ h. LOG in Radwaste Operators Log the following:

Release #

Gallons released Date and Time release stopped 78

BwOP WX-501T1 Revision 66 Continuous Use NOTE If 0RE-PR001 is inoperable and AAR 0BwOS RETS 2.1-1a has been initiated, verification is required for steps H.20. and H.22.

H____ 20. VERIFY 0AOV-WX353, Release Tank Discharge Valve to Circ. Water Blowdown, LOCKED CLOSED.

SUPERVISOR VERIFICATION _____

_____ 21. RECORD time when key was removed from key lock switch for 0AOV-WX353, Release Tank Discharge Valve to Circ. Water Blowdown. ______:______

(N/A if the Ultra Low Flow Flowpath was not used.)

_____ 22. VERIFY the 0AOV-WX896, Release Tank Discharge Valve to Circ. Water Blowdown, LOCKED CLOSED.

SUPERVISOR VERIFICATION _____

_____ 23. RECORD time when key was removed from key lock switch for 0AOV-WX896, Release Tank Discharge Valve to Circ. Water Blowdown. ______:______

(N/A if the Low Flow flowpath was not used.)

_____ 24. CLOSE 0AOV-WX889 Release Tank Pp 0WX01P Discharge Isolation Valve.

_____ 25. CLOSE 0WX354, Release Tk Disch to Process Rad Mon System (TB 401 J-18 between tanks).

VERIFICATION _____

NOTE Complete Attachment A to ensure compliance with CC-AA-112.

26. IF Relay Block K1 at 0PR01J was removed in step H.2., then:

_____ a. NOTIFY Shift Manager that the temporary Electrical Alteration is being restored.

_____ b. REPLACE Relay Block K1 at 0PR01J, SUPERVISOR VERIFICATION _____

79

BwOP WX-501T1 Revision 66 Continuous Use H____ 26. c. REMOVE the two placards stating "K1 RELAY REMOVED FOR LIQUID RELEASE", that were placed in Step H.2.c.

_____ d. If the Electrical Alteration cannot be restored, process a Temporary Configuration Change.

NOTE If 0RE-PR001 is INOPERABLE and AAR BwOS RETS 2.1-1a has been initiated, steps H.27.a through H.27.q. may be omitted at Ops Supervisor discretion.

27. Backflush the 0PR01J radiation monitor as follows:

_____ a. VERIFY release tank 0WX01T is less than 96% (0LR-WX028, 0WX01T Level Indication).

_____ b. VERIFY/OPEN NO EPN, 0PR01J return to 0WX01T.

_____ c. VERIFY/CLOSE NO EPN, 0PR01J return to 0WX26T.

CAUTION Do not back flush the Radiation Monitor for a period of time such that the Release Tank level exceeds 97%

(0LR-WX028, 0WX01T Level Indication).

d. NOTIFY the Main Control Room of the following:

_____ 0PR01J will be flushed.

_____ 0PR01J will alarm on the RM-11.

_____ e. VERIFY/OPEN 0WM897, WM Header Isolation Valve.

_____ f. VERIFY/CLOSE 0WX354, Release Tank Discharge to Process Rad Monitor System. N/A if performed in step H.25.

VERIFICATION _____

_____ g. OPEN 0PR052, Rad Mon 0PR01J Bypass Valve.

_____ h. OPEN 0PR050, 0PR01J Backflush Isolation Valve.

_____ i. OPEN 0WM898, 0PR01J WM Supply Header Valve.

80

BwOP WX-501T1 Revision 66 Continuous Use H____ 27. j. WAIT 1 minute.

_____ k. CLOSE 0PR5004, Skid 0PR01J Flow Isolation Valve.

NOTE Expect Release Tank level to rise approximately 3% per hour.

_____ l. FLUSH 0PR01J, Radiation Monitor:

For 15 minutes after release.

Until the desired Release Tank level is obtained.

_____ m. CLOSE 0PR050, 0PR01J Backflush Isolation Valve.

_____ n. CLOSE 0WM898, 0PR01J WM Supply Header Valve.

_____ o. OPEN 0PR5004, Skid 0PR01J Flow Isolation Valve.

_____ p. CLOSE 0PR052, Rad Mon 0PR01J Bypass Valve.

_____ 28. OPS Supervisor: Update the Liquid Release Tritium Tracking Log columns for Date/Time Discharge complete, Actual Tritium Activity and Gallons Actual. (Log located at L:/Shared/8931/Liquid Release Information/Liquid release Tritium Tracking Log). IF the release was not performed, ENTER CANCELLED in the appropriate blanks.

NOTE Step H.29 is not applicable if performing an extended purge to fill the Release Tank.

29. OPS Supervisor: I have reviewed Part H and have verified it is accurate and complete.

________________________________________/______/______

OPS Supervisor Date Time 81

BwOP WX-501T1 Revision 66 Continuous Use I. OPERATING DEPARTMENT RESPONSIBILITY NOTE If the current activity level recorded in step I.1. is greater than 1.31E-4 µCi/ml, INITIATE a work request to decontaminate the 0RE-PR001 sample chamber. If 0PR01J is in RETS, step I.1 may be N/Ad at Supervisors discretion.

1. OBTAIN the current reading for 0RE-PR001 (0PS101) at the RM-11:

_____ a. VERIFY/SELECT Grid 1.

_____ b. KEY in 101.

_____ c. DEPRESS SEL key.

_____ d. DEPRESS CHAN ITEMS key.

_____ e. RECORD the current 0PR01J (0PS101) reading:

_______________ µCi/ml Date: ______

NOTE If 0RE-PR001 is inoperable and AAR 0BwOS RETS 2.1-1a has been initiated or if ALERT AND HIGH ALARM setpoints have not changed from Step D.7.a.4), Step I.2. is not required

2. SET the Rad Monitor 0RE-PR001 (0PS101) to the original setpoints as follows:

_____ a. VERIFY/PLACE the RM-11 Console in SUPERVISOR MODE.

_____ b. DEPRESS the Grid 1 Key.

_____ c. KEY in 101.

_____ d. DEPRESS SEL key.

_____ e. VERIFY 0PR01J (0PS101) selected.

_____ f. DEPRESS CHAN ITEMS.

_____ g. KEY in 10.

82

BwOP WX-501T1 Revision 66 Continuous Use I ____ 2. h. DEPRESS SEL key (CHAN ITEM 10 should be displayed in reverse characters).

_____ i. KEY in the new ALERT alarm setpoint of 4.32E-5 µCi/ml USING the format XYZ +/- AB (i.e. a value of 3.76E-10 would be entered as 376-10).

_____ j. DEPRESS the ENTER key. The new value will be displayed after a short delay.

_____ k. VERIFY the new ALERT alarm setpoint of 4.32E-05 µCi/ml is displayed.

VERIFICATION _____

_____ l. KEY in 9.

_____ m. DEPRESS SEL key (CHAN ITEM 9 should be displayed in reverse characters).

_____ n. KEY in the new HIGH alarm setpoint of 8.64E-5 µCi/ml USING the format XYZ +/- AB (i.e. a value of 3.76E-10 would be entered as 376-10).

_____ o. DEPRESS the ENTER key (The new value will be displayed after a short delay).

_____ p. VERIFY the new HIGH alarm setpoint of 8.64E-5 µCi/ml is displayed.

VERIFICATION _____

_____ q. PLACE the RM-11 Console in the NORMAL MODE.

NOTE If 0RE-PR010 is inoperable and AAR 0BwOS RETS 2.1-1a has been initiated or if ALERT AND HIGH ALARM setpoints have not changed from Step D.8.a.4), Step I.3. is not required

3. SET the Rad Monitor 0RE-PR010 (0PS110) to the original setpoints as follows:

_____ a. PLACE the RM-11 Console in SUPERVISOR MODE.

_____ b. DEPRESS the Grid 1 key.

_____ c. KEY in 110.

_____ d. DEPRESS SEL key.

83

BwOP WX-501T1 Revision 66 Continuous Use I ____ 3. e. VERIFY 0PR10J (0PS110) selected.

_____ f. DEPRESS CHAN ITEM key.

_____ g. KEY in 10.

_____ h. DEPRESS SEL key (CHAN ITEM 10 should be displayed in reverse characters).

_____ i. KEY in the new ALERT alarm setpoint of 7.46E-7 µCi/ml USING the format XYZ +/- AB (i.e. a value of 3.76E-10 would be entered as 376-10).

_____ j. DEPRESS the ENTER key (The new value will be displayed after a short delay).

_____ k. VERIFY the new ALERT alarm setpoint of 7.46E-7 µCi/ml is displayed.

VERIFICATION _____

_____ l. KEY in 9.

_____ m. DEPRESS SEL key (CHAN ITEM 9 should be displayed in reverse characters).

_____ n. KEY in the new HIGH alarm setpoint of 1.07E-6 µCi/ml USING the format XYZ +/- AB (i.e. a value of 3.76E-10 would be entered as 376-10).

_____ o. DEPRESS the ENTER key (The new value will be displayed after a short delay).

_____ p. VERIFY the new HIGH alarm setpoint of 1.07E-6 µCi/ml is displayed.

VERIFICATION _____

_____ q. PLACE the RM-11 Console in the NORMAL MODE.

84

BwOP WX-501T1 Revision 66 Continuous Use NOTE DO NOT isolate Circulating Water Blowdown until at least three and one-half (3.5) hours after the release stop time recorded in step H.19.a. to ensure the entire release tank effluent has passed through the Circulating Water Blowdown pipe to the Kankakee River.

Control of Circulating Water Blowdown Flow Limitations may be transferred to an Equipment Status Tag for the purpose of completing this package. The Equipment Status Tag must specify the time and date for completion of the 3.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> flush requirement.

This method is most applicable when performing multiple releases in one day. If control is transferred to an Equipment Status Tag, Step I.4. may be marked as Condition Met.

I. 4. 3.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> or more after the time recorded in Step H.19.a., PERFORM the following:

_____ a. REMOVE the placard stating "Liquid Release in Progress" at 0PM01J.

b. RECORD the following for "Liquid Release in Progress" placard is removal at 0PM01J:

_____ Time: ______:______

_____ Date: ______

_____ c. RESTORE CW Blowdown to desired flow.

_____ 5. FORWARD this form to Chemistry to complete Section J.

85

BwOP WX-501T1 Revision 66 Continuous Use J. CHEMISTRY DEPARTMENT RESPONSIBILITY NOTE If a computerized release program is available, you may attach the printout to this form and indicate "see attached" in the calculation spaces in step J.1. below.

_____ 1. COMPLETE the table below for each isotope identified in step D.6.a.:

Total Activity Total Activity Isotope Isotope Released (µCi)

• Released (µCi)

Sum of activities above = ___________________________

• OBTAIN by multiplying each number in column #2 of table in step D.6.a. by total volume released from step H.19.d. or H.19.e. (in ml)(ml=gal x 3785)

_____ Total ml released = _____________________ ml 86

BwOP WX-501T1 Revision 66 Continuous Use J. 2. VERIFY compliance with 10CFR50 dose limits, as specified in the ODCM:

_____ a. ENTER the final release into the RETDAS program to close the permit associated with this release.

_____ b. PRINT the closed permit for retention with this release package.

_____ c. REVIEW the closed permit to VERIFY compliance with 10CFR50 dose limits.

87

BwOP WX-501T1 Revision 66 Continuous Use ATTACHMENT A TCCP TRACKING LOG SHEET TCC

Description:

REMOVE Relay Block K1 at 0PR01J (inside the AC Power Panel) to allow opening of 0AOV-WX896/353, Release Tank Discharge Isolation Valve.

This TCC does not affect the Critical Control Room Drawings.

Installation/Removal functional test is not required.

This Procedurally Controlled TCC was implemented prior to 5/29/2001. Per the Fleets Change Management Decision, this procedure does not need a Technical Evaluation.

(only one TCC/EPN per tracking sheet)

TCC INSTALLATION TCC Expected Installation Date: ____________________

TCC Expected Removal Date: ____________________

Applicable Plant Mode Limitations: ____________________

Tech Eval Number: ___N/A______________

MR90 Applicable: NO Expiration date (one refueling cycle): ____________________

Extension Allowed (per CC-AA-112, Attach 2): ____________________

Shift Manager Approval __________________________________ ____________

Signature Date 88

BwOP WX-501T1 Revision 66 Continuous Use ATTACHMENT A (Cont.)

TCCP TRACKING LOG SHEET TCC Installed by: _______________________________ ______/______

Print Name Initial Date Independent Verification by: _______________________________ ______/______

Print Name Initial Date Placards Installed per step H.2.c: _______________________________ ______/______

Print Name Initial Date Logged in TCCP Log: _______________________________ ______/______

Print Name Initial Date LCO/RETS Entered if applicable: _______________________________ ______/______

Print Name Initial Date TCC REMOVAL Shift Manager Approval __________________________________ ____________

Signature Date TCC Removed by: _______________________________ ______/______

Print Name Initial Date Independent Verification by: _______________________________ ______/______

Print Name Initial Date Placards Removed per step H.26.c:___________________________ ______/______

Print Name Initial Date Logged out of TCCP Log: _______________________________ ______/______

Print Name Initial Date LCO/RETS Exited if applicable: _______________________________ ______/______

Print Name Initial Date TCC TRANSFER OF ACCOUNTABILITY to CC-AA-112 (if not removed by governing procedure)

Method used for accountability (EST, Clearance Order, etc.)

Shift Manager Approval __________________________________ ____________

Signature Date (Final) 89

BwOP WX-501T2 Revision 6 Continuous Use LIQUID RELEASE WINDOW DETERMINATION NOTE Kankakee River Flow rate is normally obtained via the internet site for the U.S. Geological Survey (usgs.gov), WILMINGTON DATA (from the appropriate Unit Supervisor). If data is unavailable, RECORD most recent data from the Unit Supervisor turnover.

1. RECORD Liquid Release Number from BwOP WX-501T1:

L - __________ - __________

2. OBTAIN and RECORD current (within last 24 hrs.) Kankakee River flow data:

_______________ CFS at Date: ______/_____/_____ at Time: _____

3. RECORD CW blowdown flow F2400 _______________ GPM OUR-CW032 _______________ GPM

4. PERFORM either of the following to determine the liquid release window:

IF the Liquid Release Window Spreadsheet is available, GO TO Step 5.

IF a manual Liquid Release Window calculation is to be performed, GO TO Step 6.

1

BwOP WX-501T2 Revision 6 Continuous Use

5. PERFORM the following to determine the Liquid Release Window using the Liquid Release Window Spreadsheet:

a. ACCESS the Liquid Release Window spreadsheet at k:/shift/excel/liquid release.

b. ENTER the following data in the appropriate sections of the spreadsheet:

Arrive Wilmington (This is normally the day AFTER the release will occur but may be on the second day after the release will occur if Blowdown Peak time to Wilmington intake exceeds 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.)

River Flow rate recorded in Step 2.

Release duration:

From BwOP WX-501T1.

As directed by the Shift Manager.

CW Blowdown flow recorded in Step 3.

c. GO TO Step 7.

6. PERFORM the following to manually calculate the Liquid Release Window:

a. DETERMINE the length of time for CW blowdown to traverse the CW Blowdown piping:

2,640,329 GALS (Volume of CW B/D Piping) ÷___________GPM =_______ MIN (Step 3 CW B/D flow)

b. DETERMINE the time for the liquid release to travel from the outfall structure to the Wilmington Intake:

40523 x (_________________) -0.5286 = _______________ MINUTES (Step 2 cfs)

c. RECORD the release duration in minutes:

From BwOP WX-501T1.

As directed by the Shift Manager.

_______________ MINUTES 2

BwOP WX-501T2 Revision 6 Continuous Use

6. d. DETERMINE the travel time from source to mid peak at Wilmington:

_______________ + _______________ + (______________ ÷ 2) =

(Step 6.a) (Step 6.b) (Step 6.c)

_______________ MINUTES NOTE If the liquid release duration is within the range of 480 - 600 minutes, set the margin at 60 minutes. Always record the margin as a positive value.

e. DETERMINE the margin for start of the release:

540 min - _______________ = ____________MINUTES (Step 6.c)

f. DETERMINE the target start time of the liquid release (results in the mid peak of the release reaching Wilmington at about 02:30 AM):

02:30 AM - _______________________ = _______ : _______

(Step 6.d) (round to nearest 1/4 hour)

g. DETERMINE the Start After Time:

_______ : _______ - [______________ ÷ 2] = _______ : _______

(Step 6.f) (Step 6.e) (round to nearest 1/4 hour)

h. DETERMINE the Start Before Time:

_______ : _______ + [______________ ÷ 2] = _______ : _______

(Step 6.f) (Step 6.e) (round to nearest 1/4 hour)

7. RECORD the following in BwOP WX-501T1 as applicable:

Target start time.

Start After Time.

Start Before Time.

(Final) 3

BwOP WX-501T3 Revision 1 Reference Use AUTHORIZATION TO RELEASE OUTSIDE OF RELEASE WINDOW Time/Date _____/_____

Release Number: ____________________

Process Tank Levels:

Release Tanks 0WX01T __________% 0WX26T __________%

HUTs 0A __________% 0B __________%

AB Monitor Tanks 1AB02T __________% 2AB02T __________%

WX Monitor Tanks 0A __________% 0B __________%

WF Tanks 0A __________% 0B __________%

WE Tanks 0A __________% 0B __________%

Chem Drain Tank 0WZ01T __________%

Chem/Regen Waste Drain Tank 0WX08T __________%

Regen Waste Drain Tank 0WX25T __________%

Describe conditions/evolutions in progress or expected (give time frame) that prevent releasing this tank within appropriate release time window:

Operations Supervisor: ___________________________ Time/Date: _________/________

Shift Manager: _________________________________ Time/Date: _________/________

Station Duty Officer: _____________________________ Time/Date: _________/________

Include this form with liquid release package. Forward copy of this form to RW Coordinator for trending purposes.

(Final) 1

JOB PERFORMANCE MEASURE TASK CONDITIONS:

1. You are the Shift Emergency Director.

2. A RCS LOCA has occurred.

3. The TSC and OSC are NOT yet staffed.

4. An EO has received a life threatening injury and is incapacitated in the Unit 2 364 Curved Wall Area.

5. A rescue attempt must be made to rescue the injured person.

6. The estimated dose to an individual attempting the rescue is 50 Rem.

7. Joe Radworker, age 28, Employee ID Number 123456, has volunteered to rescue the injured person. Joe Radworkers current annual exposure is 24 mRem.

INITIATING CUES:

1. Authorize rescue of the injured person.

2. Notify the examiner when you have completed authorization of emergency exposure for rescue of the injured person.

S-409 Page 1 of 6

TASK TITLE: Emergency Dose Authorization JPM No.: S-409 REV: 2013 NRC Task No.: S-ZP-010 K/A No.: 2.4.38 Objective No.: 7F.ZP-010-A K/A IMP: 4.4 EXAMINEE: SRO EVALUATOR: DATE:

The Examinee: PASSED this JPM. TIME STARTED:

FAILED TIME FINISHED:

JPM TIME: MINUTES CRITICAL ELEMENTS: (*) 2, 4, 5 APPROX COMPLETION TIME: 15 MINUTES CRITICAL TIME: N/A EVALUATION METHOD: LOCATION:

X PERFORM X IN PLANT SIMULATE X SIMULATOR GENERAL

REFERENCES:

1. EP-AA-113, PERSONNEL PROTECTIVE ACTIONS, REV 11.

2. EP-AA-113-F-02, AUTHORIZATION FOR EMERGENCY EXPOSURE, REV B.

MATERIALS:

1. EP-AA-113, PERSONNEL PROTECTIVE ACTIONS, REV 11.

2. EP-AA-113-F-02, AUTHORIZATION FOR EMERGENCY EXPOSURE, REV B.

TASK STANDARDS:

1. Determine emergency exposure is required to rescue injured worker.

2. Brief affected personnel of possible health effects of emergency exposure.

3. Authorize personnel exposure in excess of 10CFR20 limits.

TASK CONDITIONS:

1. You are the Shift Emergency Director.

2. A RCS LOCA has occurred.

3. The TSC and OSC are NOT yet staffed.

4. An EO has received a life threatening injury and is incapacitated in the Unit 2 364 Curved Wall Area.

5. A rescue attempt must be made to rescue the injured person.

6. The estimated dose to an individual attempting the rescue is 50 Rem.

7. Joe Radworker, age 28, Employee ID Number 123456, has volunteered to rescue the injured person. Joe Radworkers current annual exposure is 24 mRem.

INITIATING CUES:

1. Authorize rescue of the injured person.

2. Notify the examiner when you have completed authorization of emergency exposure for rescue of the injured person.

S-409 Page 2 of 6

RECORD START TIME:

PERFORMANCE STEP STANDARD CIRCLE APPLICABLE

1. Refer to EP-AA-113, Refer to EP-AA-113: SAT UNSAT N/A PERSONNEL PROTECTIVE

• Determines section 4.3 Comments:

ACTIONS. needs to be performed.

CUE: Provide examinee copy of EP-AA-113.

• 2. Determine emergency exposure Determines emergency SAT UNSAT N/A is required. exposure is required per EP- Comments:

AA-113, step 4.3.2:

• From initiating cue, estimated dose during rescue is 50 Rem.

• Determines 50 Rem is above 5 Rem limit.

EVALUATOR NOTE: Page 6 contains a key of a correctly completed EP-AA-113-F-02 form.

3. Complete EP-AA-113-F-02, Authorizes radiation exposure SAT UNSAT N/A AUTHORIZATION FOR greater than 10CFR20 limits: Comments:

EMERGENCY EXPOSURE:

• Complete EP-AA-113-F-02, AUTHORIZATION FOR CUE: Provide examinee copy EMERGENCY EXPOSURE:

of EP-AA-113-F-02.

• Name: Joe Radworker

• Date/Time:

CUE: If asked, Joe Radworker Today/Current Time has NOT had a previous

• Social Security Number:

emergency exposure. 123-45-6789

• Current Annual Exposure: 24 mRem

• Reason for request:

Rescue of injured worker.

• Requesting authorization to exceed:

25 Rem TEDE box checked.

• Emergency worker signature.

• Rad Protection Management Review complete.

S-409 Page 3 of 6

PERFORMANCE STEP STANDARD CIRCLE APPLICABLE

• 4. Inform emergency personnel Informs emergency personnel SAT UNSAT N/A before the fact of possible before the fact of possible Comments:

health effects of anticipated health effects of anticipated exposure. exposure.

• Determines emergency exposure risks per EP-AA-113, Attachment 1:

• Determines health affects associated with whole body absorbed doses received within a few house per EP-AA-113:

• 2% of populations affected by prodromal effects.

• Determines risk of premature death based on workers age: (28 years old from initiating cue)

• 9.1 deaths/1000 persons

• Determines average years of life lost if premature death occurs based on workers age: (28 years old from initiating cue)

• 24 years CUE: Joe Radworker has

• Briefs personnel on understood healh risks emergency exposure.

and has signed EP-AA-113-F-02.

• Ensures emergency worker acknowledges risks and CUE: If asked, the Rad signs EP-AA-113-F-02.

Protection Manager is not available.

• 5 Authorize exposure in excess of Authorizes exposure in excess SAT UNSAT N/A 10CFR20 limits. of 10CFR20 limits: Comments:

• Sign and date/time Station Emergency Director block on EP-AA-113-F-02.

CUE: THIS COMPLETES THIS JPM.

RECORD STOP TIME:

COMMENTS:

S-409 Page 4 of 6

SIMULATOR SETUP INSTRUCTIONS

• Verify/perform TQ-BR-201-0113, BRAIDWOOD TRAINING DEPARTMENT SIMULATOR EXAMINATION SECURITY ACTIONS CHECKLIST.

• Complete items on Simulator Ready for Training Checklist.

COMMENTS

• Provide copy of EP-AA-113, PERSONNEL PROTECTIVE ACTIONS, REV 11.

• Provide copy of EP-AA-113-F-02, AUTHORIZATION FOR EMERGENCY EXPOSURE, REV B.

S-409 Page 5 of 6

KEY - DO NOT GIVE TO EXAMINEE EP-AA-113-F-02 Revision A Page 1 of 1 AUTHORIZATION FOR EMERGENCY EXPOSURE Name: Joe Radworker____________________ Date / Time: Today _Current Time Employee ID Number: 123456 Current Annual Exposure: _24_______ mRem Reason For Request:

Rescue of injured worker REQUESTING AUTHORIZATION TO EXCEED:

5 Rem TEDE (Authorized to receive greater than 5 Rem TEDE but less than 10 Rem TEDE) 10 Rem TEDE (Authorized to receive greater than 10 Rem TEDE but less than 25 Rem TEDE) 25 Rem TEDE (Authorized to receive greater than 25 Rem TEDE)

_Joe Radworker_________________________________ __Today/Now___

• Emergency Worker Signature Date / Time

• Emergency Worker Exposure Limits and Associated Risks (EP-AA-113 Attachment 1) have been reviewed and the potential health affects are understood.

Rad. Protection Management (Review) Date / Time

____Examinee________________________________________ _ Today/Now___

1. Station Emergency Director (Authorization) Date / Time

1. The Shift Manager (Shift Emergency Director) may approve prior to transferring Command and Control to the Station Emergency Director.

KEY - DO NOT GIVE TO EXAMINEE S-409 Page 6 of 6

EP-AA-113 Revision 11 Page 1 of 15 Level 2 - Reference Use PERSONNEL PROTECTIVE ACTIONS

1. PURPOSE 1.1. This procedure provides the necessary guidance used in determining onsite personnel protective actions during an event.

Assembly, Accountability and Evacuation REFER to Section 4.1 Habitability REFER to Section 4.2 Emergency Exposure Limits REFER to Section 4.3 KI Assessment REFER to Section 4.4

2. TERMS AND DEFINITIONS 2.1. Accountability - Accountability is the process of verifying the location of personnel who are inside the Protected Area. That is, any personnel within the Protected Area who have not carded into the card reader will be identified as missing (unaccounted for). Accountability is required to be completed within 30 minutes of its initiation (the names of any missing persons identified by security and the number of missing provided to the Station Emergency Director).

Accountability must be conducted at a Site Area or General Emergency, if not previously initiated. Accountability may be conducted at the Alert level following TSC activation, at the discretion of the Station Emergency Director.

2.2. Assembly - Assembly occurs at a Site Area Emergency (or at the discretion of the Station Emergency Director). On-duty and ERO personnel assemble in the emergency response facilities. All other non-essential personnel, contractors and visitors report to their designated Assembly Area. The Assembly Area is used to coordinate the need for any immediate additional resources and to establish an ERO shift relief roster and schedule.

EP-AA-113 Revision 11 Page 2 of 15 2.3. Evacuation - A site evacuation is required at the Site Area Emergency classification level immediately following completion of Accountability actions.

Site evacuation may be called for at any lower classification; however, conditions that require a site evacuation are inherently defined as Site Area Emergency events and should be classified as such.

Evacuation can involve the movement of large numbers of personnel outside of the Protected Area by keying out of the turnstiles. Evacuation may warrant station egress control by Security. Security will provide specific instructions to personnel leaving the Protected Area. Evacuees may be directed to a Relocation Center (offsite assembly areas) for monitoring and decontamination, or sent home. Other situations that involve the evacuation of personnel from occupied localized onsite areas are controlled on a case-by-case basis.

2.4. OCA - Owner Controlled Area. Company owned property on which a nuclear station is located and may include Exelon Nuclear leased-lands adjacent to that nuclear station.

2.5. Protected Area - Area controlled by Security and surrounded by a double fence. Access is normally gained through the Main Access Facility (or Gatehouse).

2.6. Release - A Release in Progress is defined as ANY radioactive release that is a result of, or associated with, the emergency event.

2.7. Thyroid Blocking Agent - an agent which when properly administered to an individual will result in sufficient accumulation of stable iodine in the thyroid to prevent significant uptake of radioiodine. Potassium Iodide (KI) is such an agent.

3. RESPONSIBILITIES 3.1. The Shift Manager (Shift Emergency Director) will perform the responsibilities of the Station Emergency Director until relieved.

3.2. The Station Emergency Director is responsible for the following protective actions:

Authorization of emergency exposure greater than 5 Rem (per EPA-400 lower limits).

Authorization for issuance of KI to Exelon Nuclear emergency workers and/or onsite personnel.

Direction of Assembly, Accountability and Evacuation of personnel.

EP-AA-113 Revision 11 Page 3 of 15 3.3. The respective Radiation Protection Manager (TSC or EOF) is responsible for approval of emergency exposures below 5 Rem (EPA-400 lower limits) for Exelon personnel associated with response actions under their facilitys direction.

3.4. The Security Shift Supervisor (or Security Coordinator when the TSC is activated) is responsible for performing Accountability, controlling site access, and coordinating Site and OCA Evacuations.

3.5. The Security Coordinator in the TSC is responsible for coordinating activities between the TSC and the Security force.

3.6. The Maintenance Manager is responsible for coordinating Search and Rescue Teams and Assembly Area rosters.

4. MAIN BODY NOTE: Protective Actions for the onsite workers shall be based on preventing or minimizing radiological exposures to the emergency workers onsite.

4.1. Assembly, Accountability and Evacuation 4.1.1. Protective Measure Guidelines

1. Accountability is required to be conducted at a Site Area or General Emergency, if not previously initiated and maintained. Accountability may be conducted at the Alert level at the discretion of the Station Emergency Director, or Shift Manager (Shift Emergency Director) prior to TSC activation.

A. Accountability and evacuation of non-essential site personnel should also be considered when a security-related Unusual Event or Alert has been declared.

B. Accountability shall be initiated expeditiously, but only after evaluating the need for offsite assembly and appropriate evacuation route based on radiological release and meteorological conditions.

C. Once initiated, accountability is required to be completed (i.e.,

the names of any missing persons identified by security and the number of missing provided to the Station Emergency Director) within 30 minutes of initial PA announcement for site evacuation.

EP-AA-113 Revision 11 Page 4 of 15

2. A Site Evacuation may be delayed if the health and safety of the plant personnel may be in jeopardy, such as severe weather or due to a security-related Unusual Event or Alert.

3. Non-essential personnel evacuating the site, contractors and visitors, shall report to a Remote (Off-Site) Assembly Area, if designated, for radiological monitoring and decontamination as warranted.

4. Protected Area access is halted during personnel accountability, except for the following:

ERO responders requiring access to staff the Operations Support Center (OSC) and/or Technical Support Center (TSC).

Direct approval from the TSC Security Coordinator or Shift Manager for others.

5. Accountability, once achieved, will be maintained by restricting Protected Area access and controlling/tracking the movement of on-shift personnel or ERO personnel on site in or out of their respective emergency response facility.

4.1.2. Determination of Actions NOTE: Site Evacuation of non-essential personnel shall be conducted immediately after a Site Area or General Emergency has been declared. An exception may be made for events that could require the pre-planned evacuation to be rerouted or delayed such as:

Severe weather, radiological or other hazardous conditions threaten safe movement of personnel.

A security threat is occurring which could have an adverse impact on security response or personnel while leaving the site.

1. IF a Site Area Emergency has been declared THEN immediately perform protective measure steps per the appropriate Checklist:

A. Mid-Atlantic Stations shall use EP-AA-113-F-04, Mid Atlantic Site Assembly, Accountability and Evacuation Checklist.

B. Mid-West Stations shall use EP-AA-113-F-07, Mid West Site Assembly, Accountability and Evacuation Checklist.

EP-AA-113 Revision 11 Page 5 of 15 NOTE: Site Assembly and/or Site Evacuation of non-essential personnel should be considered when a security related Unusual Event or Alert has been declared.

2. IF a Site Area Emergency has not been declared, THEN evaluate the need for and ability to conduct a Site Assembly and/or Site Evacuation.

A. CONDUCT a Site Assembly whenever it has been determined that:

1. Excess dose or other dangers exist to the onsite personnel.

2. Positive control of location and movement of all onsite personnel is necessary for support of response efforts.

B. CONDUCT a Site Evacuation whenever it has been determined that:

1. Hazardous conditions exist that necessitate the removal of all non-essential personnel from the site.

2. Positive control of location and movement of essential personnel is necessary for support of response efforts.

4.2. Habitability 4.2.1. DETERMINE if radiological controls are required to protect onsite personnel.

The need for radioactive controls shall be based on monitored radioactive releases, exposure levels, and plant status information. Standard Radiation Protection policies and procedures shall form the basis of the decision-making for the administration of radiological controls.

NOTE: The decision to utilize radiological controls that differ from standard Radiation Protection practices shall be documented in position logs.

4.2.2. Radiological controls for continuously occupied areas for emergency workers are to be evaluated using EP-AA-113-F-01, On-Site Habitability Checklist.

4.2.3. Onsite radiological controls shall be used to the extent practical based on the emergency condition. They include but are not limited to the following:

1. Radiological Access Control for Rad/High Rad Areas - Access Control is used to limit the personnel who may be exposed to the radiological condition.

EP-AA-113 Revision 11 Page 6 of 15

2. Use of Radiological Protective Clothing - Protective clothing shall be used to limit the spread of radiological contamination and to protect the emergency worker from becoming radiologically contaminated.

3. Use of Radiological Respiratory Protective Equipment - Respiratory protective equipment shall be used to limit the inhalation and ingestion of radioactive materials during the course of the emergency event. The need for respirators shall be based on air samples, plant monitoring systems, and plant conditions.

4. Use of Contamination Control Techniques - Contamination control techniques such as Step-off Pads, Posting, Contamination surveys, and whole body frisking shall be used to the extent practical based on the emergency condition.

4.3. Emergency Exposure Limits NOTE: This section implements the requirements of RP-AA-203 and should not be revised without first reviewing the requirements of the current revision of the procedure.

Emergency Exposure Determination REFER to Section 4.3.1 Briefing Personnel (greater than 5 Rem TEDE) REFER to Section 4.3.2 Authorization (greater than 5 Rem TEDE) REFER to Section 4.3.3 Tracking and Recording of Exposures REFER to Section 4.3.4 4.3.1. Emergency Exposure Determination NOTE: In certain onsite emergency situations, extremely high dose rates may be encountered (more than 500 Rem/hr).

Before a rescue team is committed to life-saving emergency dose limits, weigh the probability of success against the probable cost of the commitment. Specifically there must be reasonable assurance that the victim is in the area and that they are alive or likely to survive.

1. ASSURE that the emergency exposure is for a bona fide emergency involving risk of life or limb, or the destruction of valuable property.

A. PLAN emergency operations prior to entry.

B. WEAR respiratory protection and protective clothing to reduce contamination where possible.

EP-AA-113 Revision 11 Page 7 of 15

2. DETERMINE if emergency exposure limits in excess of 5 Rem TEDE (EPA-400 lower limits) are required for Exelon emergency workers.

3. If emergency exposure is less than 5 Rem TEDE (EPA-400 lower limits), then OBTAIN approval as appropriate:

TSC Radiation Protection Manager for onsite Exelon personnel EOF Radiation Protection Manager for Exelon field team personnel 4.3.2. Briefing Personnel (greater than 5 Rem TEDE)

1. For exposures at or above 5 Rem TEDE (EPA-400 lower limits),

COMPLETE an Authorization for Emergency Exposure (EP-AA-113-F-02).

2. INFORM emergency personnel (volunteers) before the fact of possible health effects at the anticipated exposure level using Attachment 1, Emergency Worker Exposure Limits and Associated Risks.

3. OBTAIN emergency workers acknowledge that they have volunteered and understand the associated risks. Acknowledgement should be in writing on Authorization for Emergency Exposure Form if possible OR verbally for teams in the field,

4. FORWARD to the completed form to the Station Emergency Director for approval.

4.3.3. Authorization greater than 5 Rem TEDE (EPA-400 lower limits):

CAUTION Emergency exposure limits greater than 5 Rem TEDE may be applicable for stopping a release, life saving actions, and protection of major equipment and large populations. Emergency exposure greater than 5 Rem TEDE should be voluntary.

All emergency exposures in excess of 25 Rem TEDE shall be voluntary and shall be limited to once in a lifetime. Persons who may receive exposures greater than 25 Rem TEDE shall be fully aware of the risks involved.

1. OBTAIN and DOCUMENT Station Emergency Director approval, by signature, for the use of the emergency dose limits above 5 Rem TEDE (EPA-400 lower limits) on the Authorization for Emergency Exposure form.

EP-AA-113 Revision 11 Page 8 of 15 NOTE: The decision to authorize personnel exposure per EPA-400 limits is the responsibility of the Station Emergency Director and may not be delegated.

2. NOTIFY Occupational Health (Medical) Services Department promptly if any EPA-400 dose limit is exceeded.

4.3.4. Tracking and Recording

1. ESTIMATE and RECORD personnel dose equivalents resulting from any emergency situation.

2. REPORT final emergency exposures greater than 5 Rem TEDE (EPA-400 lower limits) to the NRC.

4.4. KI Assessment Determination REFER to Section 4.4.1 Authorization and Issuing KI REFER to Section 4.4.2 Briefing Personnel REFER to Section 4.4.3 4.4.1. Determination

1. ASSESS the potential of high thyroid exposure to emergency workers in, or projected to be sent into, areas where the possibility exists of exposure to radioactive iodine as follows:

A. For Field Monitoring Teams or other Exelon emergency workers working offsite, determine if EITHER of the following conditions exist:

Condition 1 There is an Offsite Release in Progress.

And There has been a loss or potential loss of the Fuel Clad Barrier.

OR

EP-AA-113 Revision 11 Page 9 of 15 Condition 2 Dose Assessments project iodine thyroid exposure for emergency workers will be 50 Rem Committed Dose Equivalent (CDE).

B. For OSC Emergency Teams and other onsite workers, determine if EITHER of the following conditions exist:

Condition 1 Workers will be entering an unknown radiological atmosphere that is suspected to have a high iodine concentration. Loss of the Fuel Clad barrier is a good indication of possible high iodine concentrations.

OR Condition 2 The calculated iodine thyroid exposure (actual or projected) for emergency workers, base on station Radiation Protection procedures or use of the dose assessment program, will be 50 Rem Committed Dose Equivalent (CDE).

2. If the condition A and/or B listed above are met then, RECOMMEND the issuance of one (1) 130 mg KI tablet to each emergency worker affected per day for 10 consecutive days 4.4.2. Authorization NOTE: The Radiation Protection Manager and OSC Director should avoid the use of individuals known to have possible adverse reactions to KI for tasks where exposure to iodine may occur. A list of individuals who indicated possible allergies is available.

1. DOCUMENT the decision to issue KI using Thyroid Blocking Agent Authorization Form (EP-AA-113-F-03).

The Station Emergency Director must authorize issuance of KI to Exelon emergency workers.

2. NOTIFY Occupational Health (Medical) Services Department promptly if KI is to be issued to Exelon Nuclear personnel or contractors.

EP-AA-113 Revision 11 Page 10 of 15 4.4.3. Briefing Personnel and Issuing KI NOTE: The effectiveness of potassium iodide as a thyroid blocking agent decreases as a function of time. The effectiveness of potassium iodide is as follows:

90% effective if taken immediately prior to or concurrent with exposure to radioactive iodine.

50% effective if taken within 3 to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> following exposure.

Ineffective if taken more than 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> following exposure.

NOTE: The FDA KI Package insert provided with the KI product identifies the side effects and risks involved with KI usage. It is general use guidance intended for members of the public. It states approval from state and public health authorities is needed prior to use, this applies to members of the public. Exelon has the authority and responsibility to direct use of KI by Exelon Emergency Workers.

NOTE: Persons with a known allergy to iodine should not be considered for work requiring the use of potassium iodide blocking agents.

CAUTION KI dosage in excess of that recommended by this procedure could lead to possible effects including: rash, swelling of salivary glands, soreness in the teeth and gums, upset stomach and diarrhea.

1. REVIEW Thyroid Blocking Agent Authorization Form (EP-AA-113-F-

03) to ensure all individuals being issued KI are listed and form is complete.

2. READ, or instruct the Emergency Worker(s) to read, Information on use of Thyroid Blocking Agent on authorization form or the FDA KI package insert prior to taking or administering KI.

EP-AA-113 Revision 11 Page 11 of 15 NOTE: Potassium Iodide (KI) has a limited effective shelf life, which may be extended by the manufacturer. Potassium iodide must be stored in sealed containers that are protected from light and are in areas that meet all manufacturers limitations on temperature variances.

3. VERIFY the expiration date of the KI to ensure it is within its acceptable shelf life period prior to being used.

4. ISSUE of one (1) 130 mg KI tablet to each emergency worker affected per day for 10 consecutive days.

4.5. The following forms will be used by various members of the ERO to perform their duties related to personnel protective actions outlined in this procedure:

EP-AA-113-F-01, On-Site Habitability Checklist EP-AA-113-F-02, Authorization of Emergency Exposure EP-AA-113-F-03, Thyroid Blocking Agent Authorization Form EP-AA-113-F-04, MA Emergency Director - Site Assembly, Accountability and Evacuation Checklist EP-AA-113-F-05, Vehicle and Evacuee Control Group Leader Checklist EP-AA-113-F-06, Vehicle and Evacuee Control Group Member Checklist EP-AA-113-F-07, MW Emergency Director - Site Assembly, Accountability and Evacuation Checklist EP-AA-113-F-08, PBAPS Assembly, Accountability and Evacuation Guidelines EP-AA-113-F-09, LGS Assembly, Accountability and Evacuation Guidelines EP-AA-113-F-10, TMI Assembly, Accountability and Evacuation Guidelines EP-AA-113-F-11, Remote Assembly Area Muster List EP-AA-113-F-12, Vehicle Survey and Decontamination Report EP-AA-113-F-13, Facility Accountability List (Within Protected Area)

EP-AA-113-F-14, Rock River Division Headquarters Vehicle Traffic Flowpath EP-AA-113-F-15, Rock River Division Headquarters Frisking Area and Personnel Flowpath EP-AA-113-F-17, Braidwood Assembly, Accountability and Evacuation Guidelines

EP-AA-113 Revision 11 Page 12 of 15 EP-AA-113-F-18, Byron Assembly, Accountability and Evacuation Guidelines EP-AA-113-F-19, Dresden Assembly, Accountability and Evacuation Guidelines EP-AA-113-F-20, LaSalle Assembly, Accountability and Evacuation Guidelines EP-AA-113-F-21, Quad Cities Assembly, Accountability and Evacuation Guidelines EP-AA-113-F-22, Clinton Assembly, Accountability and Evacuation Guidelines EP-AA-113-F-23, Assembly Area Roster EP-AA-113-F-24, Relocation Center Operations Checklist EP-AA-113-F-25, Relocation Center Accountability Log EP-AA-113-F-26, Relocation Center Monitoring Log EP-AA-113-F-27, Midwest ERO Off-Site Staging Area Checklist EP-AA-113-F-28, MA ERO Off-Site Staging Area Checklist EP-AA-113-F-29, Oyster Creek Assembly, Accountability and Evacuation Guidelines

5. DOCUMENTATION 5.1. The following forms, when completed during a declared event document implementation of this procedure:

EP-AA-113-F-01, On-Site Habitability Checklist EP-AA-113-F-02, Authorization of Emergency Exposure EP-AA-113-F-03, Thyroid Blocking Agent Authorization Form EP-AA-113-F-04, MA Emergency Director - Site Assembly, Accountability and Evacuation Checklist EP-AA-113-F-05, Vehicle and Evacuee Control Group Leader Checklist EP-AA-113-F-06, Vehicle and Evacuee Control Group Member Checklist EP-AA-113-F-07, MW Emergency Director - Site Assembly, Accountability and Evacuation Checklist EP-AA-113-F-08, PBAPS Assembly, Accountability and Evacuation Guidelines

EP-AA-113 Revision 11 Page 13 of 15 EP-AA-113-F-09, LGS Assembly, Accountability and Evacuation Guidelines EP-AA-113-F-10, TMI Assembly, Accountability and Evacuation Guidelines EP-AA-113-F-11, Remote Assembly Area Muster List EP-AA-113-F-12, Vehicle Survey and Decontamination Report EP-AA-113-F-13, Facility Accountability List (Within Protected Area)

EP-AA-113-F-14, Rock River Division Headquarters Vehicle Traffic Flowpath EP-AA-113-F-15, Rock River Division Headquarters Frisking Area and Personnel Flowpath EP-AA-113-F-16, River Bend Middle School Vehicle Traffic and Relocation Center Layout EP-AA-113-F-17, Braidwood Assembly, Accountability and Evacuation Guidelines EP-AA-113-F-18, Byron Assembly, Accountability and Evacuation Guidelines EP-AA-113-F-19, Dresden Assembly, Accountability and Evacuation Guidelines EP-AA-113-F-20, LaSalle Assembly, Accountability and Evacuation Guidelines EP-AA-113-F-21, Quad Cities Assembly, Accountability and Evacuation Guidelines EP-AA-113-F-22, Clinton Assembly, Accountability and Evacuation Guidelines EP-AA-113-F-23, Assembly Area Roster EP-AA-113-F-24, Relocation Center Operations Checklist EP-AA-113-F-25, Relocation Center Accountability Log EP-AA-113-F-26, Relocation Center Monitoring Log EP-AA-113-F-27, Midwest ERO Off-Site Staging Area Checklist EP-AA-113-F-28, MA ERO Off-Site Staging Area Checklist EP-AA-113-F-29, Oyster Creek Assembly, Accountability and Evacuation Guidelines 5.2. The Standard Records Retention ID for the above documents per the Standards Records Retention Schedule is 5B.100.

EP-AA-113 Revision 11 Page 14 of 15

6. REFERENCES 6.1. Development References 6.1.1. Nuclear Operations Directive NOD-RP.14, "ALARA, Exposure Management, Work Controls and Radiological Monitoring," current revision.

6.1.2. EPA 400-R-92-001, "Manual of Protective Action Guides and Protective Actions for Nuclear Incidents," October 1991.

6.1.3. "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion, "Federal Guidance Report No. 11, Office of Radiation Programs, U.S. EPA, EPA-520/1-88-020, September 1988.

6.1.4. "Potassium Iodide as a Thyroid Blocking Agent in Radiation Emergency: Final Recommendations on use," Federal Register, Vol. 47, No. 125, June 29, 1982.

6.1.5. "Protection of Thyroid Gland in the Event of Releases of Radioiodine," NCRP Report No. 55, 1977.

6.1.6. Commonwealth Edison Quality Verification Audit Finding, Audit No. CE 04, CAR# CE-92-029 (Nov. 18, 1992) 6.1.7. Commonwealth Edison Medical Dept. Procedure and Practice Guideline, "Exposure Evaluation: Ionizing Radiation" (10/5/93).

6.1.8. RP-AA-203, Exposure Control and Authorization 6.2. User References None

7. ATTACHMENTS 7.1. Attachment 1 - Emergency Worker Exposure Limits and Associated Risks

EP-AA-113 Revision 11 Page 15 of 15 ATTACHMENT 1 EMERGENCY WORKER EXPOSURE LIMITS AND ASSOCIATED RISKS Page 1 of 1 EMERGENCY WORKER EXPOSURE LIMITS The dose-limiting recommendations for emergency situations are as follows:

Dose Limit Activity Condition (Rem TEDE)*

5 All Personnel should be kept within normal 10CFR20 limits during emergencies, except as authorized for activities as indicated below 10 Protecting Valuable Property When a lower dose is not practical 25 Life Saving or Protection of Large When a lower dose is not practical Populations

>25 Life Saving or Protection of Large Only on a voluntary basis to persons fully aware Population of the risks involved

• Dose Equivalent Limit (TEDE in Rem). Workers performing services during emergencies should limit dose to the lens of the eye (LDE) to three times each listed value and doses to any other organ (including skin and body extremities) to ten times each listed value.

EMERGENCY EXPOSURE RISKS Health effects associated with whole body absorbed doses received within a few hoursa Percent of population b

affected by prodromal effects (e.g. reddening of c

Dose in rad skin, loss of appetite, nausea, Dose in rad Early fatalities

( Rem DDE) fatigue, diarrhea) ( Rem DDE) (percent affected) 50 rad 2% 140 rad 5%

100 rad 15 % 200 rad 15 %

150 rad 50 % 300 rad 50 %

200 rad 85 % 400 rad 85 %

250 rad 98 % 460 rad 95 %

Approximate cancer risk to average individuals from 25 Rem TEDE received promptly Age at exposure Risk of premature death Average years of life lost (years) (deaths per 1000 persons if premature death occurs exposed) (years) 20 to 30 9.1 24 30 to 40 7.2 19 40 to 50 5.3 15 50 to 60 3.5 11 a

Risks will be lower for extended exposure periods.

b Forewarning symptoms of more serious health effects associated with large doses of radiation.

c Supportive medical treatment may increase the dose at which these frequencies occur by approximately 50 percent.

EP-AA-113-F-02 Revision B Page 1 of 1 AUTHORIZATION FOR EMERGENCY EXPOSURE Name: ___________________________ Date / Time: ____/____/____ ____:____

Employee ID Number: ________________ Current Annual Exposure: __________ mRem Reason For Request:

REQUESTING AUTHORIZATION TO EXCEED:

5 Rem TEDE (Authorized to receive greater than 5 Rem TEDE but less than 10 Rem TEDE) 10 Rem TEDE (Authorized to receive greater than 10 Rem TEDE but less than 25 Rem TEDE) 25 Rem TEDE (Authorized to receive greater than 25 Rem TEDE)

• Emergency Worker Signature Date / Time

• Emergency Worker Exposure Limits and Associated Risks (EP-AA-113 Attachment 1) have been reviewed and the potential health affects are understood.

Rad. Protection Management (Review) Date / Time

1. Station Emergency Director (Authorization) Date / Time

1. The Shift Manager (Shift Emergency Director) may approve prior to transferring Command and Control to the Station Emergency Director.

Document Retention SRRS ID - 5B.100