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2013 Braidwood Station Initial License Examination Proposed JPMs
	ML13148A101
Person / Time
Site:	Braidwood
Issue date:	04/15/2013
From:	; NRC/RGN-III
To:	; Exelon Generation Co
	Zoia, C.
Shared Package
ML11354A333	List: ML13148A096; ML13148A098; ML13148A101; ML13148A105;
References
	Download: ML13148A101 (852)
	v • d • e

JOB PERFORMANCE MEASURE TASK CONDITIONS:

1. You are an extra NSO.

2. Both units are at power.

INITIATING CUES:

Channel Checks of the Unit 1 RCS Subcooling Margin Monitors and Containment Water level indications need to be performed to close out work packages. The Unit Supervisor has directed you to perform the applicable step(s) of 1BwOSR 3.3.3.1, Unit One Accident Monitoring Instrumentation Channel Checks.

R-120 Page 1 of 6

TASK TITLE: Perform Channel Checks of the RCS Subcooling Margin Monitor and Containment Water Level.

JPM No.: R-120 REV: 2013 NRC TPO No.: 4C.AM-01 K&A No.: 2.1.18 TASK No.: R-AM-018, Perform Mode 1-3 shiftly and K&A IMP: 3.6/3.8 daily operating surveillance.

TRAINEE: RO SRO (Circle One)

EVALUATOR: DATE:

The Trainee: PASSED this JPM. TIME STARTED:

FAILED TIME FINISHED:

JPM TIME: MINUTES CRITICAL ELEMENTS: (*) 2, 3, 4, 5 COMPLETION TIME: 10 MINUTES CRITICAL TIME: N/A ALTERNATE PATH: YES EVALUATION METHOD: LOCATION:

X PERFORM IN PLANT SIMULATE X SIMULATOR

_ CONTROL ROOM GENERAL

REFERENCES:

1. 1BwOSR 3.3.3.1, Rev. 14, Unit One Accident Monitoring Instrumentation Channel Checks.

MATERIALS:

1. 1BwOSR 3.3.3.1, Rev. 14.

TASK STANDARDS:

1. Perform the channel checks of the RCS Subcooling Margin Monitor and Containment floor water level.

TASK CONDITIONS:

1. You are an extra NSO.

2. Both units are at power INITIATING CUES:

1. Channel Checks of the Unit 1 RCS Subcooling Margin Monitors and Containment Water level indications need to be performed to close out work packages. The Unit Supervisor has directed you to perform the applicable step(s) of 1BwOSR 3.3.3.1, Unit One Accident Monitoring Instrumentation Channel Checks.

R-120 Page 2 of 6

RECORD START TIME ____________

PERFORMANCE STEP STANDARD Circle applicable

1. Obtain copy of 1BwOSR 3.3.3.1 Obtain and review procedure: SAT UNSAT N/A Comments:

CUE: Give student

1BwOSR 3.3.3.1 surveillance.

Check Precautions, As each precaution etc Prerequisites, and is inquired about, Limitations and Actions are provide cue that it is met met

Determine steps F.2.a-e and F.5.a-f are applicable Note: The Channel Check of the Subcooling Margin Monitor consists of comparing of the two trains with a Maximum Allowed Deviation of < 10 degrees F. Each consists of an average of the 10 highest Incore Thermocouples and a W/R RCS Pressure channel.

Note: The procedure does not specifically require that the SMM channel check be performed prior to the Containment Water level channel checks or vice versa. If examinee starts with the Containment Floor water level checks, go to step 4 of the JPM then return to step 2.

2. Record the instrument readings At 1PM05J/6J,RECORD: SAT UNSAT N/A for each train of SMM Comments:

Acceptable values:

o 1TI-IT001: 595 F o

1TI-IT001 (CETC) 1TI-IT002: As read F

1TI-IT002 (CETC)

The values recorded for 1PI-

1PI-403A (1A RC Loop 403A and 1PI-405 should match WR pressure) the indications on the meters,

1PI-405 (1C RC Loop WR which may range from 2225 to pressure) 2300 psig.

R-120 Page 3 of 6

3. Determine SMM Channel Check DETERMINE SMM Channel SAT UNSAT N/A Status Check Status as follows: Comments:

Examinee will determine

CALCULATE and that the CETC RECORD the "Actual temperatures are >10 F Maximum Deviation" apart from each other and between OPERABLE notifies US to enter LCO. readings

COMPARE to the stated "Allowed Maximum Deviation" CUE: (When examinee gives

DETERMINE that the information that CETCs Actual Deviation is NOT are not within channel within the Allowed check allowance) CUE: Deviation and circles the The SRO has evaluated recorded reading for 1TI-A train CETC channel IT001 as suspect and calls reading as inoperable, but to SRO attention.

the B train is operable o Determine that the RC based on the individual LOOP W/R Pressure CETC readings. meters (1PI-403A and 1PI-405) DO MEET the allowed maximum deviation.

INDICATE the CUE: SRO directs you to acceptability of the complete channel check of Channel Check of each subcooling margin instrument by checking the monitor. 'Y/N' boxes (checks N for 1TI-IT001 checks Y for 1TI-IT002 in CHANNEL CHECK OK column);

checks Y for 1PI-403A and 1PI-405.

VERIFY the total number of OPERABLE Channels >

Required Channels Operable (NOT met) o Verify Reg guide 1.97 designation (black dot) on labels by checking Y for each.

4. Record the instrument readings At 1PM06J, RECORD: SAT UNSAT N/A for each Containment Water Comments:

level instrument.

Acceptable range:

1LI-PC006 (0 inches) 1LI-PC006 0-1 inches

1LI-PC007 (10 inches) 1LI-PC007 9-11 inches R-120 Page 4 of 6

5. Determine Containment Water DETERMINE Containment SAT UNSAT N/A Level Channel Check Status Water Level Channel Check Comments:

Status as follows:

Examinee will determine that the Containment Water level

CALCULATE and channels differ by more than RECORD the "Actual 7.2% and notify the US to enter Maximum Deviation" LCO. CUE: The SRO has between OPERABLE evaluated 1LI-PC007 reading as readings inoperable, 1LI-PC006 is

COMPARE to the stated operable based on RF sump and "Allowed Maximum other parameters. Deviation"

DETERMINE that the Actual Deviation is NOT within the Allowed Deviation Checks Y box for 1LI-PC006 in

INDICATE the CHANNEL CHK OK? column. acceptability of the Checks N box for 1LI-PC007 Channel Check of each in CHANNEL CHK OK? instrument by checking the column. 'Y/N' boxes

VERIFY the total number of OPERABLE Channels >

Required Channels CUE: The SRO acknowledges Operable (not met) the notification. o Inform US of status CUE: THIS COMPLETES THIS JPM.

RECORD STOP TIME ____________

COMMENTS:

R-120 Page 5 of 6

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

MALFUNCTION #S:

Override CETC train A and B to indicate >10 degrees apart from each other by placing RF OR02 in OVER and forcing a value with RF OR02A to 595 degrees F.

Override 1LI-PC007 to 10% using IOR ZAO1LIPC007 10.

COMMENTS:

R-120 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 3.3.3.1____

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

PMID/RQ

Title:

UNIT 1 ACCIDENT MONITORING INSTRUMENTATION CHANNEL CHECKS PMID/RQ Due Date: ___ N/A________ PMID/RQ Late Date: N/A Signature/Authorization Approval Review: Name Date Time Shift Authorization to Start Work: ___Joe Supervisor ______ Today 5 min ago Work Started __________________________ ________ ________

Work Stopped: __________________________ ________ ________

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 Perform the applicable step(s) for the Unit 1 RCS Subcooling Margin Monitors and Containment Water level instruments, needs to be performed to close out work packages _

ADDITIONAL REVIEW OF RESULTS (IF REQUIRED)

Title Signature Date

WC-AA-111 Revision 4 Page 25 of 61

PROCEDURE 1BwOSR 3.3.3.1 UNIT NO. REVISION NO.

1 14 BRAIDWOOD STATION PROCEDURE TITLE:

UNIT ONE ACCIDENT MONITORING INSTRUMENTATION CHANNEL CHECKS Rev Summary IR# / EC# (if applicable) 14 Clarification concerning performance of WRGM steps PCRA 1208019-02 at 1PM10J or 2PM10J.

1BwOSR 3.3.3.1 Revision 14 Continuous Use UNIT ONE ACCIDENT MONITORING INSTRUMENTATION CHANNEL CHECKS A. STATEMENT OF APPLICABILITY This procedure outlines the steps necessary to verify the OPERABILITY of the Accident Monitoring Instrumentation by performing a CHANNEL CHECK of the required instruments and indications and verifying the required number of channels are OPERABLE. This procedure is applicable in MODES 1, 2 & 3.

B. REFERENCES

1. Technical Specifications:

a. LCO 3.3.3

b. SR 3.3.3.1

c. Table 3.3.3-1

2. TRMs:

a. TLCO 3.3.i

b. TLCO 3.3.j

c. TSR 3.3.i.1

d. TSR 3.3.j.2

e. Table T3.3.i-1

3. Station Procedures:

a. 1BwOL 3.3.3 LCOAR - Post Accident Monitoring (PAM) Instrumentation.

b. 1BwOL TRM 3.3.i, LCOAR - Post Accident Monitoring (PAM)

Instrumentation.

c. 1BwOL TRM 3.3.j, LCOAR - Hydrogen Monitor.

4. Tech Spec Definition: Section 1.1 "CHANNEL CHECK".

5. Operability Determination 99-003.

1

1BwOSR 3.3.3.1 Revision 14 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. This procedure may be performed in MODES 1, 2, 3, or 4.

D. PRECAUTIONS The Unit Operator should VERIFY that a qualified relief is monitoring the Unit panels prior to checking any Control Room back panels.

E. LIMITATIONS AND ACTIONS

1. As stated in Tech Spec LCO 3.3.3.

2. The parameters do not have to be surveilled in sequence.

3. Any inoperable parameter(s) that reduce the number of OPERABLE Channels to less than the total number specified requires a LCOAR be entered or already in effect to VERIFY the "Required Channels" OPERABLE requirements of Tech Spec Table 3.3.3-1, TRM Table T3.3.i-1 and TRM 3.3.j are satisfied. The "Required Channels" columns of the Data sheets provides guidance.

4. System instrumentation used in this procedure must be in current calibration.

5. 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 3.3.3, 1BwOL TRM 3.3.i or 1BwOL TRM 3.3.j for the affected parameter(s) if in MODES 1, 2 or 3, as applicable.

6. Instrument readings that exceed the "MAXIMUM ALLOWABLE DEVIATION" guidelines shall be referred to an SRO for further evaluation. The SRO shall evaluate the readings against all other available indications and parameters that may assist in determining channel OPERABILITY and RECORD the evaluation of the results in the comments section of each data sheet.

7. A partial surveillance may be performed at the discretion of the Shift Manager or designee to demonstrate operability of individual instruments in the data tables provided all Prerequisites, Precautions, and Limitations and Actions are observed. The Shift Manager or designee shall determine the steps to be performed. The Data Package Cover Sheet must indicate that a partial surveillance was performed and the reason why listed in the Comments section.

2

1BwOSR 3.3.3.1 Revision 14 Continuous Use E. 8. A CHANNEL CHECK shall be the qualitative assessment, by observation of channel behavior during operation. This determination shall include where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channel measuring the same parameter.

9. If only one hydrogen monitor is available, then the channel check shall consist of the qualitative assessment of channel behavior during operation (i.e. indicating as expected for current plant operation and is typically less than 1%).

3

1BwOSR 3.3.3.1 Revision 14 Continuous Use F. MAIN BODY NOTE Steps F.1 through F.5 may be performed in any order.

NOTE Although TRM TLCO 3.3.j only requires ONE hydrogen monitor to be OPERABLE, a Channel Check should be performed on both monitors, if available.

1. PERFORM the CHANNEL CHECK of the Hydrogen Monitor(s) on the appropriate data sheet as follows:

a. VERIFY/OPEN the following valves to ALIGN the hydrogen monitor(s) being checked:

Hydrogen Monitor 1HSU-PS345:

1PS228A 1PS229A 1PS230A Hydrogen Monitor 1HSU-PS346:

1PS228B 1PS229B 1PS230B

b. PLACE the ON-OFF Selector switch(es) to the ON position at the Hydrogen Monitor Panels at 1PM12J for the hydrogen monitors being checked:

1HSU-PS345 1HSU-PS346

c. RECORD the status of the GREEN light on the Data Sheet.

4

1BwOSR 3.3.3.1 Revision 14 Continuous Use F. 1. d. PERFORM the following for the Hydrogen Monitor(s) being checked:

1) WAIT at least 4 minutes.

2) VERIFY the following lights are OFF:

H2 SYSTEM STATUS

3) RECORD the light status on the Data Sheet.

e. WAIT at least 30 minutes to allow an adequate purge of the sample lines, THEN PERFORM the following:

1) RECORD the containment hydrogen concentration on the Data Sheet from one of the following:

Meter (The meter is the preferred choice):

1AI-PS344 1AI-PS343 Computer point:

Y2001 Y2002

2) VERIFY the value(s) obtained in the previous step indicate as expected for current plant status.

3) VERIFY Reg Guide 1.97 designation (black dot) on the labels for each of the following:

1AI-PS344 1AI-PS343

f. INDICATE the acceptability of the CHANNEL CHECK of each Hydrogen Monitor(s) being surveilled by checking "Y" or "N" in the space provided.

¢ g. VERIFY at least one Hydrogen Monitor OPERABLE.

5

1BwOSR 3.3.3.1 Revision 14 Continuous Use F. 1. h. VERIFY/PLACE the ON-OFF Selector switches to the OFF position at the Hydrogen Monitor Panels.

1HSU-PS345 1HSU-PS346 NOTE 1PS228A/B and 1PS229A/B are normally maintained open.

i. CLOSE the following valves:

1PS230A, POST LOCA H2 MON A outside Disch Valve.

1PS230B, POST LOCA H2 MON B outside Disch Valve.

2. PERFORM the CHANNEL CHECKS of the Reactor Coolant Subcooling Margin Monitor on the Data Sheet as follows:

NOTE The CHANNEL CHECK of the Subcooling Margin Monitor consists of comparing of the two trains with a Maximum Allowed Deviation of 10°F. Each consists of an average of the 10 highest Incore Thermocouples and a W/R RCS Pressure channel.

a. RECORD the instrument readings for each train.

b. CALCULATE and RECORD the "Actual Maximum Deviation" between OPERABLE readings, and COMPARE to the stated "Allowed Maximum Deviation".

c. IF the "Actual Maximum Deviation" exceeds the stated "Allowed Maximum Deviation", CIRCLE the readings that are suspect and REFER the deviation to an SRO for evaluation of the channel OPERABILITY status.

d. INDICATE the acceptability of the CHANNEL CHECK of each instrument by checking "Y" or "N" in the space provided (channels that were circled as suspect are to be marked "Y" or "N" based on the SRO evaluation).

¢ e. VERIFY the number of OPERABLE channels is the "Required Channels Operable".

6

1BwOSR 3.3.3.1 Revision 14 Continuous Use F. 3. PERFORM the CHANNEL CHECKS of the Radiation Monitoring Instrumentation as follows:

NOTE The Aux Building Vent Stack WRGM low, medium and high range channels inputs are not in continuous use. Only one green "AVAIL" light will be ILLUMINATED for the channel range in use.

NOTE If it is desired, some or all of the CHANNEL CHECKS may be accomplished from the RM-23 as indicated on the data sheets. If the RM-23 is used, the checks need not be performed using the RM-11 if a parameter is NOT surveilled using the RM-23, it MUST be surveilled using the RM-11.

a. Perform the following for each Radiation Monitoring Instrument channel using the RM-23 at 1PM10J: (2PM10J for 2RIU-PR030):

Containment High Range Area Radiation Monitors a) RECORD the green AVAIL light status on the data sheet D-8.

b) VERIFY Reg Guide 1.97 designation (black dot) on the labels for each of the following:

1RIU-AR020 1RIU-AR021 Main Steam Line Radiation Monitors a) RECORD the green AVAIL light status on the data sheet D-8.

b) VERIFY Reg Guide 1.97 designation (black dot) on the labels for each of the following:

1RIU-AR022 1RIU-AR023 7

1BwOSR 3.3.3.1 Revision 14 Continuous Use F. 3. a. Aux Building Vent Stack WRGM a) RECORD the green AVAIL light for the three (Low, Med, or High) Channels on data sheet D-9.

b) RECORD the green AVAIL light for the effluent Channel on data sheet D-9.

c) VERIFY Reg Guide 1.97 designation (black dot) on the labels for each of the following:

1RIU-PR030 2RIU-PR030

b. OBTAIN the INSTRUMENT VALUE and CHANNEL CHECK from the RM-23 by performing the following:

1) DEPRESS the channel DISPLAY/CONTROL key pushbutton and VERIFY it ILLUMINATES.

2) VERIFY the following lights/pushbuttons are NOT ILLUMINATED:

a) ITEM.

b) MON.

c) ERROR.

d) SUPV MODE.

e) KYBD LOCK OUT.

3) RECORD the Rad level from the LED digital readout.

4) INDICATE the acceptability of the CHANNEL CHECK of each instrument by checking "Y" or "N" in the space provided (channels that were circled as suspect are to be marked "Y" or "N" based on the SRO evaluation).

¢ 5) VERIFY the number of OPERABLE channels is the "Required Channels Operable".

8

1BwOSR 3.3.3.1 Revision 14 Continuous Use F. 3. c. To perform the CHANNEL CHECKS of the Rad Monitoring Instrumentation using the RM-11 console, the following steps apply:

1) SELECT the grid indicated on the data sheet using the appropriate pushbutton.

2) ENTER the channel number from the data sheet.

3) DEPRESS the SEL pushbutton and VERIFY the channel is outlined.

4) DEPRESS the STATUS pushbutton.

5) VERIFY the Monitor status using the status cursor and RECORD the highest cursor color.

6) RECORD the Rad level.

7) INDICATE the acceptability of the CHANNEL CHECK of each instrument by checking "Y" or "N" in the space provided (channels that were circled as suspect are to be marked "Y" or "N" based on the SRO evaluation).

¢ 8) VERIFY the number of OPERABLE channels is the "Required Channels Operable".

9

1BwOSR 3.3.3.1 Revision 14 Continuous Use F. 4. PERFORM the CHANNEL CHECKS of the Incore Thermocouples on the appropriate Data Sheet from 1TI-IT001 and 1TI-IT002 as follows:

NOTE The Incore Thermocouple CHANNEL CHECKS are in two groups:

those with 1/8 core symmetry (Max Allowed Deviation of 20°F) and those without any symmetry (Max Allowed Deviation of 60°F).

a. RECORD the instrument reading for each Incore Thermocouple that is not known inoperable (RECORD "INOP" for any that are known inoperable).

b. CALCULATE and RECORD the "Actual Maximum Deviation" between OPERABLE readings and COMPARE to the stated "Allowed Maximum Deviation".

c. IF the "Actual Maximum Deviation" exceeds the stated "Allowed Maximum Deviation", CIRCLE the readings that are suspect and REFER the deviation to an SRO for evaluation of the channel OPERABILITY status.

¢ d. RECORD the total number of OPERABLE Incore Thermocouples per quadrant and VERIFY the total is 4.

e. VERIFY Reg Guide 1.97 designation (black dot) on the labels for each of the following:

1TI-IT001 1TI-IT002 10

1BwOSR 3.3.3.1 Revision 14 Continuous Use F. 5. PERFORM all remaining CHANNEL CHECKS of the instrumentation on the appropriate Data Sheets as follows:

a. RECORD the instrument readings for all instruments (RECORD "INOP" for any that are known inoperable).

b. CALCULATE and RECORD the "Actual Maximum Deviation" between OPERABLE readings, and COMPARE to the stated "Allowed Maximum Deviation".

c. IF the "Actual Maximum Deviation" exceeds the stated "Allowed Maximum Deviation", CIRCLE the readings that are suspect and REFER the deviation to an SRO for evaluation of the channel OPERABILITY status.

d. INDICATE the acceptability of the CHANNEL CHECK of each instrument by checking "Y" or "N" in the space provided (channels that were circled as suspect are to be marked "Y" or "N" based on the SRO evaluation).

¢ e. VERIFY the total number of OPERABLE channels is the "Required Channels Operable".

f. PERFORM the following for each of the instruments listed on the Data Sheets:

1) VERIFY Reg Guide 1.97 designation (black dot) on the labels.

2) CHECK Y or N as appropriate in the designated area.

11

1BwOSR 3.3.3.1 Revision 14 Continuous Use G. ACCEPTANCE CRITERIA

1. When performing this surveillance as a complete, routinely scheduled surveillance, the following criteria apply:

a. The required number of channels are OPERABLE for each instrument or indication listed on the data sheets.

b. A CHANNEL CHECK was SATISFACTORILY performed for each OPERABLE instrument or indication listed on the data sheets.

2. When performing this surveillance as a partial to meet the retest criteria to exit a LCOAR, this surveillance shall be considered SATISFACTORILY COMPLETED if the following criteria are met:

a. A CHANNEL CHECK was SATISFACTORILY performed for the parameter(s) being restored.

b. The Data Package Cover Sheet indicates that a partial surveillance was performed and the reason why listed in the Comments section.

(Final) 12

1BwOSR 3.3.3.1 Revision 14 Continuous Use UNIT ONE ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE DATA SHEET PARAMETER INSTRUMENT STATUS ACCEPTANCE CRITERIA VERIFY the green "ON" light is ILLUMINATED for each Instrument 1HSU-PS345 ON OFF GREEN LIGHT ON Channel being checked. 1HSU-PS346 ON OFF VERIFY the H2 and SYSTEM STATUS light is OFF after 4 minutes 1HSU-PS345 ON OFF H2 AND SYSTEM STATUS for each Instrument Channel being checked. 1HSU-PS346 ON OFF LIGHTS OFF NOTE The Hydrogen Monitor must be operating for 30 minutes prior to taking data. To perform the CHANNEL CHECK, CNMT ISOL Valves 1PS228A/B, 1PS229A/B & 1PS230A/B must be OPEN. (The meter is the preferred choice).

CHANNEL CHECK RG 1.97 PARAMETER INSTRUMENT VALUE ACCEPTANCE CRITERIA SAT? DOT 1AI-PS343 or

% Y N Y N HYDROGEN MONITORS AT LEAST 1 OPERABLE Y2001 TRM 3.3.j CHANNEL WITH CHAN CHK CNMT H2 1AI-PS344 SAT CONCENTRATION or

% Y N Y N Y2002 D-2

1BwOSR 3.3.3.1 Revision 14 Continuous Use UNIT ONE ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE DATA SHEET INSTR MAXIMUM DEVIATION CHANNEL RG 1.97 REQUIRED PARAMETER INSTRUMENT UNITS ACCEPTANCE CRITERIA VALUE ACTUAL ALLOWED CHK OK? DOT CHANNELS CONTAINMENT 1PI-PC004 Y N Y N 2 2 OPERABLE CHANNELS PRESSURE 4.8 PSIG 1PI-PC005 Y N Y N T.S. 3.3.3.7 WITH CHAN CHKS SAT NOTE For the S/G Aux Feed Flow instruments that are not in use, the reading may range from slightly above to slightly below zero but should not be pegged low on scale (contact IMD for assistance as necessary).

S/G 1A AUX PP 1A 1FI-AF011A Y N Y N 2 2 OPERABLE CHANNELS N/A GPM WITH CHAN CHKS SAT FEED FLOW PP 1B 1FI-AF012A Y N Y N TRM 3.3.i.1 S/G 1B AUX PP 1A 1FI-AF013A Y N Y N 2 2 OPERABLE CHANNELS N/A GPM WITH CHAN CHKS SAT FEED FLOW PP 1B 1FI-AF014A Y N Y N TRM 3.3.i.1 S/G 1C AUX PP 1A 1FI-AF015A Y N Y N 2 2 OPERABLE CHANNELS N/A GPM WITH CHAN CHKS SAT FEED FLOW PP 1B 1FI-AF016A Y N Y N TRM 3.3.i.1 S/G 1D AUX PP 1A 1FI-AF017A Y N Y N 2 2 OPERABLE CHANNELS N/A GPM WITH CHAN CHKS SAT FEED FLOW PP 1B 1FI-AF018A Y N Y N TRM 3.3.i.1 CONTAINMENT WATER 1LI-PC006 Y N Y N 2 2 OPERABLE CHANNELS 7.2 IN WITH CHAN CHKS SAT LEVEL 1LI-PC007 Y N Y N T.S. 3.3.3.10 CNMT FLOOR DRN SUMP 1LI-PC002 Y N Y N 2 2 OPERABLE CHANNELS WATER LEVEL 9.9 IN WITH CHAN CHKS SAT 1LI-PC003 Y N Y N TRM 3.3.i.5 NOTE Both the CETCs and the associated Wide range pressure channels must be operable to ensure that subcooling margin operability is met.

1TI-IT001 Y N Y N 2 2 OPERABLE CHANNELS CETCs 10 °F 1TI-IT002 Y N Y N TRM 3.3.i.7 WITH CHAN CHKS SAT RC LOOP W/R 1A 1PI-403A Y N Y N 2 2 OPERABLE CHANNELS 210 PSIG PRESSURE 1C 1PI-405 Y N Y N T.S. 3.3.3.1 WITH CHAN CHKS SAT D-3

1BwOSR 3.3.3.1 Revision 14 Continuous Use UNIT ONE ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE DATA SHEET PARAMETER INSTR MAXIMUM DEVIATION CHANNEL RG 1.97 REQUIRED INSTRUMENT UNITS ACCEPTANCE CRITERIA VALUE ACTUAL ALLOWED CHK OK? DOT CHANNELS 1LI-930 Y N Y N RWST LEVEL 1LI-931 Y N Y N 2 2 OPERABLE CHANNELS 7 %

1LI-932 Y N Y N T.S. 3.3.3.9 WITH CHAN CHKS SAT 1LI-933 Y N Y N 1A 1TI-413A Y N Y N REACTOR COOLANT HOT 1B 1TI-423A Y N Y N 2 2 OPERABLE CHANNELS 49 °F LEG WIDE RANGE 1C 1TI-433A Y N Y N T.S. 3.3.3.2 WITH CHAN CHKS SAT TEMPERATURE 1D 1TI-443A Y N Y N 1A 1TI-413B Y N Y N REACTOR COOLANT COLD 1B 1TI-423B Y N Y N 2 2 OPERABLE CHANNELS 49 °F LEG WIDE RANGE 1C 1TI-433B Y N Y N T.S. 3.3.3.3 WITH CHAN CHKS SAT TEMPERATURE 1D 1TI-443B Y N Y N NOTE A Reactor Vessel Water Level instrument channel is considered OPERABLE if one of the two (1/2) sensors in the HEAD region and three of the six (3/6) sensors in the PLENUM region are OPERABLE. The operability of a sensor may be determined by reviewing the ERROR messages on the control board indicator.

BwOP RC-12 provides the ERROR message code meanings.

REACTOR VESSEL 1LI-RC019 Y N Y N 2 2 OPERABLE CHANNELS N/A N/A %

WATER LEVEL 1LI-RC020 Y N Y N T.S. 3.3.3.14 WITH CHAN CHKS SAT 1LI-459A Y N Y N PRESSURIZER 2 2 OPERABLE CHANNELS 1LI-460A 7 % Y N Y N WATER LEVEL T.S. 3.3.3.6 WITH CHAN CHKS SAT 1LI-461 Y N Y N Comments:

D-4

1BwOSR 3.3.3.1 Revision 14 Continuous Use UNIT ONE ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE DATA SHEET PARAMETER INSTR MAXIMUM DEVIATION CHANNEL RG 1.97 REQUIRED ACCEPTANCE INSTRUMENT UNITS VALUE ACTUAL ALLOWED CHECK OK? DOT CHANNELS CRITERIA NOTE

1. PORV VPI IS NOT APPLICABLE for valve(s) with the associated block valve in the closed position. Record the indicated valve position in the "INSTR VALUE" column.

PZR PORV VALVE 1RY-455A Y N 1 PER VALVE 1 OPERABLE N/A N/A AVAIL N/A POSITION IND 1RY-456 Y N TRM 3.3.i.2 INDICATION PER VALVE NOTE

- BLOCK VALVE VPI IS NOT APPLICABLE IF valve is verified closed AND power is removed (INDICATE status in comments section below). IF power is available to the valve, then VPI is required. Record the indicated valve position in the "INSTR VALUE" column.

PZR PORV ISOLATION 1RY-8000A Y N 1 PER VALVE 1 OPERABLE N/A N/A AVAIL N/A VALVE POS IND 1RY-8000B Y N TRM 3.3.i.3 INDICATION PER VALVE 1RY-8010A PZR SAFETY 1 PER VALVE 1 OPERABLE 1RY-8010B N/A N/A AVAIL N/A Y N VALVE POS IND TRM 3.3.i.4 INDICATION PER VALVE 1RY-8010C 1PI-514A Y N Y N S/G 1A 2 OPERABLE CHAN 1PI-515A 91 PSIG Y N Y N 2 T.S. 3.3.3.8 PRESSURE WITH CHAN CHKS SAT 1PI-516A Y N Y N 1PI-524A Y N Y N S/G 1B 2 OPERABLE CHAN 1PI-525A 91 PSIG Y N Y N 2 T.S. 3.3.3.8 PRESSURE WITH CHAN CHKS SAT 1PI-526A Y N Y N 1PI-534A Y N Y N S/G 1C 2 OPERABLE CHAN 1PI-535A 91 PSIG Y N Y N 2 T.S. 3.3.3.8 PRESSURE WITH CHAN CHKS SAT 1PI-536A Y N Y N 1PI-544A Y N Y N S/G 1D Y N 2 OPERABLE CHAN 1PI-545A 91 Y N 2 T.S. 3.3.3.8 PRESSURE PSIG WITH CHAN CHKS SAT 1PI-546A Y N Y N Comments:

D-5

1BwOSR 3.3.3.1 Revision 14 Continuous Use UNIT ONE ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE DATA SHEET PARAMETER INSTR MAXIMUM DEVIATION CHANNEL RG 1.97 REQUIRED ACCEPTANCE INSTRUMENT UNITS VALUE ACTUAL ALLOWED CHECK OK? DOT CHANNELS CRITERIA S/G 1A 1LI-517 YN YN NARROW RNG 1 1 OPERABLE CHAN 1LI-518 7 % YN YN WATER T.S. 3.3.3.5 WITH CHAN CHKS SAT LEVEL 1LI-519 YN YN S/G 1B 1LI-527 YN YN NARROW RNG 1 1 OPERABLE CHAN 1LI-528 7 % YN YN WATER T.S. 3.3.3.5 WITH CHAN CHKS SAT LEVEL 1LI-529 YN YN S/G 1C 1LI-537 YN YN NARROW RNG 1 1 OPERABLE CHAN 1LI-538 7 % YN YN WATER T.S. 3.3.3.5 WITH CHAN CHKS SAT LEVEL 1LI-539 YN YN S/G 1D 1LI-547 YN YN NARROW RNG 1 1 OPERABLE CHAN 1LI-548 7 % YN YN WATER T.S. 3.3.3.5 WITH CHAN CHKS SAT LEVEL 1LI-549 YN YN S/G 1A 1LI-501A N/A N/A YN YN W/R 1B 1LI-502A N/A N/A YN YN 1 PER S/G 4 OPERABLE CHAN WATER 1C 1LI-503A N/A N/A YN YN T.S. 3.3.3.4 WITH CHAN CHKS SAT LEVEL 1D 1LI-504A N/A N/A YN YN Comments:

D-6

1BwOSR 3.3.3.1 Revision 14 Continuous Use UNIT ONE ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE DATA SHEET PARAMETER INSTR MAXIMUM DEVIATION CHANNEL RG 1.97 REQUIRED INSTRUMENT UNITS ACCEPTANCE CRITERIA VALUE ACTUAL ALLOWED CHK OK? DOT CHANNELS NOTE The Post Accident Neutron Monitor Wide Range channel checks are performed by comparing the meter indication to the calorimetric power if in Mode 1 or between the channels if in Modes 2,3, or 4. The Narrow Range Channel Checks are performed by comparing the meter indications between the channels.

POST ACCIDENT 1NI-NR005A 1/2 Y N Y N N/A*

NEUTRON MONITOR Decade N/A WIDE RANGE 1NI-NR006A % Y N Y N N/A*

10 MINUTE Plant (See Note N/A N/A N/A CALORIMETRIC POWER Computer below) 1/2 1NI-NR006B Y N Y N N/A*

POST ACCIDENT Decade NEUTRON MONITOR Cps N/A Narrow Range 1NI-NR005B (See Note Y N Y N N/A*

below)

Comments:

If a Post Accident Neutron Monitor is inoperable, ENTER 1BwOS NR2-1a.

NOTE: The following is the agreed upon method of determining the half decade acceptance criteria.

log(meter 1) - log(meter 2) = x As long as x is 0.5, then we meet the 1/2 decade acceptance criteria.

Example 1: 1NI-NR006B reads 2x104 CPS and 1NI-NR005B reads 8x103 CPS To determine if they meet the 1/2 decade acceptance criteria:

Log (2x104) - Log (8x103) = 0.398 (Acceptable)

Example 2: 1NI-NR005A reads 77%, 1NI-NR006A reads 67% and the calorimetric reads 23%

Log 77 - Log 23 = 0.524 Unacceptable Log 67 - Log 23 = 0.464 Acceptable D-7

1BwOSR 3.3.3.1 Revision 14 Continuous Use UNIT ONE ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE DATA SHEET The Rad Monitoring CHANNEL CHECKS on this page are performed using the RM-23 (IF desired).

PARAMETER AVAIL INSTR CH CHK CHANNEL RG 1.97 REQUIRED INSTRUMENT UNITS ACCEPTANCE CRITERIA LIGHT VALUE ACCEPT

CHK OK? DOT CHANNELS 1RIU-AR020 ON GREEN Y N CONTAINMENT HIGH (R/HR Key) OFF CHANNEL 1 1 OPERABLE CHANNEL MR/HR Y N RANGE AREA RAD 1RIU-AR021 ON AVAIL Light T.S. 3.3.3.11 WITH CHAN CHKS SAT Y N (R/HR Key) OFF ON 1RIU-AR022A ON GREEN Y N MAIN STEAM LINE (MR/HR Key) OFF CHANNEL 1 1 OPERABLE CHANNEL MR/HR Y N 1A RADIATION 1RIU-AR023A ON AVAIL Light T.S. 3.3.3.12 WITH CHAN CHKS SAT Y N (MR/HR Key) OFF ON 1RIU-AR022B ON GREEN Y N MAIN STEAM LINE (MR/HR Key) OFF CHANNEL 1 1 OPERABLE CHANNEL MR/HR 1B RADIATION 1RIU-AR023B ON AVAIL Light T.S. 3.3.3.12 WITH CHAN CHKS SAT Y N (MR/HR Key) OFF ON 1RIU-AR022C ON GREEN Y N MAIN STEAM LINE (MR/HR Key) OFF CHANNEL 1 1 OPERABLE CHANNEL MR/HR 1C RADIATION 1RIU-AR023C ON AVAIL Light T.S. 3.3.3.12 WITH CHAN CHKS SAT Y N (MR/HR Key) OFF ON 1RIU-AR022D ON GREEN Y N MAIN STEAM LINE (MR/HR Key) OFF CHANNEL 1 1 OPERABLE CHANNEL MR/HR 1D RADIATION 1RIU-AR023D ON AVAIL Light T.S. 3.3.3.12 WITH CHAN CHKS SAT Y N (MR/HR Key) OFF ON

Limitation and Action E.8 met.

Comments:

D-8

1BwOSR 3.3.3.1 Revision 14 Continuous Use UNIT ONE ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE DATA SHEET The Rad Monitoring CHANNEL CHECKS on this page are performed using the RM-23 (IF desired):

AVAIL INSTR CH CHK CHANNEL REQUIRED ACCEPTANCE PARAMETER INSTRUMENT UNITS RG 1.97 DOT LIGHT VALUE ACCEPT

CHK OK? CHANNELS CRITERIA UNIT ONE GAS 1RIU-PR030 ON AUX BLDG LOW (LOW Key) OFF One of three VENT STACK 1RIU-PRO30 GREEN 1RIU-PR030 IS GAS ON 1 WRGM (MED Key) CHANNEL µc/ml Y N OPERABLE WITH MED OFF TRM 3.3.i.6 AVAIL Light Y N CHAN CHKS SAT GAS 1RIU-PR030 ON ON HIGH (HIGH Key) OFF 1RIU-PR030 ON AVAIL Light EFFL µc/sec Y N N/A N/A (EFFL Key) OFF ON GAS 2RIU-PR030 ON One of three LOW (LOW Key) OFF GREEN 2RIU-PR030 IS UNIT TWO GAS 2RIU-PR030 ON 1 CHANNEL µc/ml Y N OPERABLE WITH AUX BLDG MED (MED Key) OFF TRM 3.3.i.6 AVAIL Light Y N CHAN CHKS SAT VENT STACK GAS 2RIU-PR030 ON ON WRGM HIGH (HIGH Key) OFF 2RIU-PR030 ON AVAIL EFFL µc/sec Y N N/A N/A (EFFL Key) OFF Light ON

Limitation and Action E.8 met.

Comments:

D-9

1BwOSR 3.3.3.1 Revision 14 Continuous Use UNIT ONE ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE DATA SHEET The Rad Monitoring CHANNEL CHECKS on this page are performed using the RM-11 (IF the RM-23 is not used). Cursor color may be indicated as follows:

G=Green, W=White, Y=Yellow, M=Magenta, DB=Dark Blue, LB=Light Blue, R=Red, C=Cyan.

CURSOR INSTR CH CHK CHANNEL REQUIRED PARAMETER INSTRUMENT UNITS ACCEPTANCE CRITERIA COLOR VALUE ACCEPT

CHK OK? CHANNELS CONTAINMENT HIGH 1RE-AR020 Cursor is Y N RANGE AREA RAD (G4 4AS120) NOT White 1 1 OPERABLE CHANNEL R/HR 1RE-AR021 Dark Blue or T.S. 3.3.3.11 WITH CHAN CHKS SAT Y N (G4 4AS121) Magenta 1RE-AR022A Cursor is Y N MAIN STEAM LINE (G1 4AA122) NOT White 1 1 OPERABLE CHANNEL MR/HR 1A RADIATION 1RE-AR023A Dark Blue or T.S. 3.3.3.12 WITH CHAN CHKS SAT Y N (G1 4AA123) Magenta 1RE-AR022B Cursor is Y N MAIN STEAM LINE (G1 4AB222) NOT White 1 1 OPERABLE CHANNEL MR/HR 1B RADIATION 1RE-AR023B Dark Blue or T.S. 3.3.3.12 WITH CHAN CHKS SAT Y N (G1 4AB223) Magenta 1RE-AR022C Cursor is Y N MAIN STEAM LINE (G1 4AC322) NOT White 1 1 OPERABLE CHANNEL MR/HR 1C RADIATION 1RE-AR023C Dark Blue or T.S. 3.3.3.12 WITH CHAN CHKS SAT Y N (G1 4AC323) Magenta 1RE-AR022D Cursor is Y N MAIN STEAM LINE (G1 4AD422) NOT White 1 1 OPERABLE CHANNEL MR/HR 1D RADIATION 1RE-AR023D Dark Blue or Y N T.S. 3.3.3.12 WITH CHAN CHKS SAT (G1 4AD423) Magenta

Limitation and Action E.8 met.

Comments:

D-10

1BwOSR 3.3.3.1 Revision 14 Continuous Use UNIT ONE ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE DATA SHEET The Rad Monitoring CHANNEL CHECKS on this page are performed using the RM-11 (IF the RM-23 is not used). Cursor color may be indicated as follows:

G=Green, W=White, Y=Yellow, M=Magenta, DB=Dark Blue, LB=Light Blue, R=Red, C=Cyan.

CURSOR INSTR CH CHK CHANNEL REQUIRED PARAMETER INSTRUMENT UNITS ACCEPTANCE CRITERIA COLOR VALUE ACCEPT

CHK OK? CHANNELS UNIT ONE GAS 1RE-PR030 Cursor is AUX BLDG LOW (G2 1PA130) NOT White VENT STACK GAS @ 1RE-PR030 Dark Blue or 1 1RE-PR030 IS OPERABLE

µc/ml Y N WRGM MED (G2 1PB230) Magenta TRM 3.3.i.6 CHAN CHKS SAT GAS @ 1RE-PR030 For Effluent HIGH (G2 1PC330) Channel and at least one of 1RE-PR030 the Gas EFFL µc/sec Y N N/A N/A (G2 1PF430)

Channels GAS 2RE-PR030 Cursor is LOW (G2 2PA130) NOT White GAS @ 2RE-PR030 Dark Blue or 1 2RE-PR030 IS OPERABLE UNIT TWO µc/ml Y N MED (G2 2PB230) Magenta TRM 3.3.i.6 CHAN CHKS SAT AUX BLDG GAS @ 2RE-PR030 For Effluent VENT STACK HIGH (G2 2PC330) Channel and WRGM at least one of 2RE-PR030 EFFL the Gas µc/sec Y N N/A N/A (G2 2PF430)

Channels

Limitation and Action E.8 met.

Comments:

@ Gas Medium and Gas High Channels are normally NOT on line and are dark blue.

D-11

1BwOSR 3.3.3.1 Revision 14 Continuous Use UNIT ONE ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE DATA SHEET The following Incore Thermocouple groups are symmetrically associated (one group per line). Maximum Deviation between thermocouples in each group is 20°F. If the channel is inoperable, record "INOP". (Required channels: 4 per quadrant. T.S. 3.3.3.13)

IN NO QUADRANT QUADRANT 1 QUADRANT 2 QUADRANT 3 QUADRANT 4 DEVIATION 1 39 49 °F 2 30 °F 4 14 63 °F 5 ** 55 ** 6 56 26 42 °F 7 43 65 ** °F 8 32 °F 9 25 °F 10 62 °F 34 12 11 64 °F 27 13 °F 38 15 °F 52 35 31 16 °F 18 33 44 ** °F 36 19 46 °F 53 57 20 °F 21 51 ** 54 28 48 47 61 °F 22 ** 41 °F 23 58 °F 37 59 24 45 °F The following Incore Thermocouples are NOT symmetrically associated. Maximum Deviation between all 6 is 60 °F 40 3 50 17 29 **

60 °F RECORD total OPERABLE Incore

¢ _____ (4) ¢ _____ (4) ¢____ (4) ¢____ (4)

Thermocouples for each quadrant VERIFY 4 per quadrant (init)

Comments: ** Incore Thermocouple disconnected. Value not required.

(Final)

D-12

JOB PERFORMANCE MEASURE TASK CONDITIONS:

1. You are an extra NSO.

2. Unit 1 is at full power (8,000 EFPH per 1BwOS NR-1) with all control systems in automatic except rod control, which is in manual.

3. Boron concentration was 825 ppm 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ago.

4. Control Bank D is at 220 steps.

5. RCS Tave is 587 °F.

6. At hrs (30 minutes ago) it was determined rods M-4 and M-12 are inoperable and immovable due to failure to move during the Movable Control Assembly Surveillance. The QNE is informed.

INITIATING CUES:

1. The US has directed you to perform 1BwOSR 3.1.1.1-2, Unit One Shutdown Margin Surveillance During Operation, per LCOAR 1BwOL 3.1.4, Condition A, Required Action A.1.1.

and inform the US of the results.

2. This is a time critical JPM.

Page 1 of 6 R-104

TASK TITLE: Determine Shutdown Margin is Inadequate JPM No.: R-104 REV: NRC 2011 TPO No.: 4.C.GP-03 K&A No.: 2.1.25 TASK No.: R-RK-005, Perform SDM Calculation K&A IMP: 3.9/4.2 EXAMINEE: RO SRO (Circle One)

EVALUATOR: DATE:

The Examinee: PASSED this JPM. TIME STARTED:

FAILED TIME FINISHED:

JPM TIME: MINUTES CRITICAL ELEMENTS: (*) 3-7 APPROX COMPLETION TIME: 23 MINUTES CRITICAL TIME: 30 minutes EVALUATION METHOD: LOCATION:

X PERFORM IN PLANT SIMULATE X SIMULATOR X CLASSROOM GENERAL

REFERENCES:

1. 1BwOSR 3.1.1.1-2, Rev. 3, Unit One Shutdown Margin Surveillance During Operation

2. BwCB-1 (Various), Cycle 17 Braidwood Curve Book

3. 1BwOL 3.1.4, Rev. 4, LCOAR - Rod Group Alignment Limits Tech Spec LCO 3.1.4

4. Braidwood TRM and Unit 1 COLR MATERIALS:

1. 1BwOSR 3.1.1.1-2

2. BwCB-1 (Various), Cycle 17 Braidwood Curve Book

3. Braidwood Technical Requirements Manual (TRM)

4. Calculator TASK STANDARDS:

1. Perform the required actions of 1BwOSR 3.1.1.1-2, Unit 1 Shutdown Margin Surveillance During Operation (within 30 minutes).

2. Determine Shutdown Margin unacceptable for current plant conditions.

TASK CONDITIONS:

1. You are an extra NSO.

2. Unit 1 is at full power (8,000 EFPH per 1BwOS NR-1) with all control systems in automatic except rod control, which is in manual.

3. Boron concentration was 825 ppm 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ago.

4. Control Bank D is at 220 steps.

5. RCS Tave is 587 °F.

6. At hrs (30 minutes ago) it was determined rods M-4 and M-12 are inoperable and immovable due to failure to move during the Movable Control Assembly Surveillance. The QNE is informed.

INITIATING CUES:

1. The US has directed you to perform 1BwOSR 3.1.1.1-2, Unit One Shutdown Margin Surveillance During Operation, per LCOAR 1BwOL 3.1.4, Condition A, Required Action A.1.1. and inform the US of the results.

2. This is a time critical JPM.

Page 2 of 6 R-104

Provide CUES ONLY if actual plant/ simulator conditions are not available.

RECORD START TIME PERFORMANCE STEP STANDARD Circle applicable

1. Refer to 1BwOSR 3.1.1.1-2. Open 1BwOSR 3.1.1.1-2. SAT UNSAT N/A Comments:

CUE: Provide a copy of the procedure.

All Prerequisites, Precautions, Limitations and Actions have been met.

2. Document the Present Determine and record the SAT UNSAT N/A Conditions following: Comments:

Date and Time (step F.1.a).

CUE: Core Average Burnup is

Core Average Burnup from 8,000 EFPH). 1BwOS NR-1 (step F.1.b).

Tave is 587 °F.

Core Average Temperature (step F.1.c).

Reactor Power level is

Power Level (step F.1.d).

100%.

RCS Boron is 825 ppm 1

Present Boron hr ago, no changes have Concentration (step F.1.e).

been made.

3. Determine total worth due to Determine total worth due to SAT UNSAT N/A rods. rods and record the following: Comments:

Control Bank position (step Control Bank D=220 steps. F.2.a).

Remaining worth of the 10 pcm (0 to 25 pcm) Control Banks from BwCB-Student Value: ____ 1 figure 2 based on recorded position in step F.2.a. (step F.2.b) and current EFPH.

SUBTRACT the Control 3304.9 pcm - 10 pcm Bank remaining worth from

= 3294.9 pcm (3269.9 to 3304.9 the Control Bank total pcm) worth to obtain the total Student Value: ____ available worth due to Control Bank position.

(step F.2.c).

ADD the Shutdown Bank worth (from BwCB-1, Table 4-1) plus the total available 3431.9 pcm + 3294.9 pcm Control Bank worth (F.2.c.)

= 6726.8 pcm (6701.8 to 6736.8 and record the total worth pcm). due to rods (step F.2.d).

Student Value:____

Page 3 of 6 R-104

PERFORMANCE STEP STANDARD Circle applicable

4. Determine actual reactivity Determine and record actual SAT UNSAT N/A available due to rods. reactivity due to rods as Comments:

follows:

CUE: QNE has been notified

Number of immovable or that continued untrippable control rods operations is desired. (step F.3.a).

Highest stuck rod worth 2 untrippable rods from BwCB-1 Table 4-1 (step F.3.b).

MULTIPLY the number of 947.4 pcm immovable or untrippable control rods (step F.3.a) by 2000pcm (step F.3.c).

Total rod worth (F.2.d) 2 x 2000 = 4000 pcm minus worth of immovable or untrippable rods (F.3.c.)

minus highest stuck rod worth (F.3.b) = actual reactivity available due to 6726.8 -4000 - 947.4 rods (step F.3.d).

= 1779.4 pcm (1754.4 to 1789.4 pcm)

Student Value:____

5. Determine current Power Defect Determine and record the SAT UNSAT N/A current power defect for this Comments:

Boron Concentration and Power Level from either:

1885 pcm + 15 (Fig. 17a) o Figure 17A

- OR -

1885 pcm (1898 to 1873) (Table o Table 2-1 2-1) o Checks appropriate box for the method used.

Page 4 of 6 R-104

PERFORMANCE STEP STANDARD Circle applicable

6. Perform Shutdown Margin VERIFY Shutdown Margin as SAT UNSAT N/A Verification follows: Comments:

1779.4 pcm + (-)1885 pcm

ADD total corrected rod

= -105.6 pcm (-311.5 to -367.5 worth (F.3.d) to the power pcm) defect (F.4) (Step F.5.a)

Record the Shutdown 1.3 x 1000 = 1300 pcm. Margin Limit for Modes 1 and 2 from the COLR (step F.5.b)

-336.5 pcm (-143.6 to -83.6 pcm

VERIFY the available

> 1300 pcm (NO) shutdown reactivity Student Value:______ recorded in step F.5.a is greater than or equal to the minimum required Shutdown Margin Limit recorded in step F.5.b.

(Step F.5.c)

CUE: As US acknowledge o Inform US that Shutdown inadequate SDM and you Margin is NOT met and will take the appropriate LCOAR 1BwOL TRM 3.1.h actions. needs to be initiated Note: Record the time

(________) that the SDM is determined to be unacceptable.

7. Verify total elapsed time to

Determine inadequate SAT UNSAT N/A determine SDM unacceptable is SDM within 60 minutes of Comments:

< 30 minutes. time given in Task Conditions.

CUE: THIS COMPLETES THIS JPM.

RECORD STOP TIME COMMENTS:

Page 5 of 6 R-104

SIMULATOR SETUP INSTRUCTIONS JPM NO: R-104 REQUIRED SIMULATOR MODE(S): If performed in simulator, 100% power steady state, Rods in Manual or can be performed in Classroom MALFUNCTION #S: N/A COMMENTS:

Perform surveillance beforehand to obtain correct numbers for grading purposes. Update JPM cues with latest numbers from current curve book data.

Page 6 of 6 R-104

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 3.1.1.1-2____

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

PMID/RQ

Title:

U-1 SHUTDOWN MARGIN SURV. DURING OPERATION_________

PMID/RQ Due Date: ___ N/A________ PMID/RQ Late Date: N/A Signature/Authorization Approval Review: Name Date Time Shift Authorization to Start Work: ___Joe Supervisor ______ Today 5 min ago Work Started __________________________ ________ ________

Work Stopped: __________________________ ________ ________

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

1BwOSR 3.1.1.1-2 Revision 3 Continuous Use UNIT ONE SHUTDOWN MARGIN SURVEILLANCE DURING OPERATION A. STATEMENT OF APPLICABILITY This procedure outlines the steps necessary to verify Shutdown Margin in MODE 1 and MODE 2 when the Reactor is critical.

This Procedure SHALL be performed:

1. Within one hour after detection of one or more inoperable shutdown or control rods in MODE 1; and MODE 2 with the reactor critical as directed by LCOAR 1BwOL 3.1.4.

2. Within one hour after detection of one control or shutdown rod not within alignment limits and once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter as directed by LCOAR 1BwOL 3.1.4.

3. Within one hour after detection of more than one shutdown or control rod not within alignment limits as directed by LCOAR 1BwOL 3.1.4.

4. Within one hour after detection of one or more shutdown banks not within the insertion limits specified in the COLR as directed by LCOAR 1BwOL 3.1.5.

5. Within one hour after detection of one or more control banks not within the insertion, sequence and overlap limits specified in the COLR in MODE 1; and MODE 2 with the reactor critical as directed by LCOAR 1BwOL 3.1.6.

B. REFERENCES

1. Tech Spec LCO:

a. 3.1.4.

b. 3.1.5.

c. 3.1.6.

2. Technical Requirements Manual TLCO: 3.1.h.

3. Technical Requirements Manual Surveillance Requirements: 3.1.h.1.

1

1BwOSR 3.1.1.1-2 Revision 3 Continuous Use B. 4. Station Commitments:

a. 456-130-98-3.1.1.1-0200, "Specific SAR Commitment" (Regarding factors used in SDM calculation).

b. 456-130-98-3.1.1.2-0200, "Specific SAR Commitment" (Regarding factors used in SDM calculation).

5. Station Procedures:

a. BwCB-1, Braidwood Curve Book - Unit One.

b. 1BwOS NR-1, Power History Hourly Surveillance.

c. 1BwOL 3.1.4, LCOAR - Reactivity Control Systems - Rod Group Alignment Limits.

d. 1BwOL 3.1.5, LCOAR - Reactivity Control Systems - Shutdown Bank Insertion Limits.

e. 1BwOL 3.1.6, LCOAR - Reactivity Control Systems - Control Bank Insertion Limits.

f. 1BwOL TRM 3.1.h, LCOAR - Reactivity Control Systems - Shutdown Margin (SDM).

g. BwVS TRM 3.1.h.1, Core Reload Sequence and Verification.

6. Braidwood Station Core Operating Limits Report, (COLR).

C. PREREQUISITES 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.

D. PRECAUTIONS BwCB Figures are core life dependent. Ensure Figures and Tables used are correct for current core burnup.

2

1BwOSR 3.1.1.1-2 Revision 3 Continuous Use E. LIMITATIONS AND ACTIONS

1. As stated in Tech Spec LCO 3.1.4, 3.1.5, 3.1.6, and TRM TLCO 3.1.h.

2. In the event the Acceptance Criteria is not met during the performance of this surveillance, IMMEDIATELY notify the Shift Manager to initiate LCOAR procedure 1BwOL TRM 3.1.h.

3. The following factors should be considered in calculating SDM:

a. Reactor Coolant System boron concentration.

b. Control rod position.

c. Reactor Coolant System average temperature.

d. Fuel burnup based on gross thermal energy generation.

e. Xenon concentration.

f. Samarium concentration.

3

1BwOSR 3.1.1.1-2 Revision 3 Continuous Use F. MAIN BODY

1. Present Conditions:

a. RECORD the Date/Time of this calculation:

Date: ___________ Time: ___________

b. RECORD the Core EFPH (Burnup) from 1BwOS NR-1 for the date and time recorded above:

___________ EFPH

c. RECORD the Core Average Temperature:

___________ °F

d. RECORD the Power Level:

e. RECORD the present Boron Concentration:

___________ ppm 4

1BwOSR 3.1.1.1-2 Revision 3 Continuous Use NOTE The Shutdown banks must be fully withdrawn when operating with the Reactor critical, therefore, the Shutdown Bank worth is taken from BwCB-1, Table 4-1, Shutdown Bank total Worth (pcm) for the appropriate time in cycle life.

F. 2. Total Worth Due To Rods:

a. RECORD the Control Bank position:

Bank: _________ Step: _________

NOTE Select the appropriate graph from either BwCB-1 Figure 2 or Figure 2a based on power level and core burnup.

b. RECORD the inserted worth of the Control Banks from BwCB-1 Figure 2 or Figure 2a using Control Bank position from step F.2.a:

___________ pcm

c. SUBTRACT the Control Bank inserted worth (F.2.b) from the Control Bank total worth (from BwCB-1, Table 4-1) to obtain the total available worth due to the Control Bank position:

pcm - pcm = pcm (BwCB-1, Table 4-1, (F.2.b)

Total CB Worth)

d. ADD the Shutdown Bank worth (from BwCB-1, Table 4-1) plus the total available Control Bank worth (F.2.c) and RECORD the total worth due to rods:

pcm + pcm = pcm (BwCB-1, Table 4-1, (F.2.c)

Total Shutdown Bank Worth) 5

1BwOSR 3.1.1.1-2 Revision 3 Continuous Use F. 3. Actual Reactivity Available Due To Rods NOTE If any inoperable Control Rod(s) is (are) determined to be immovable or untrippable, INFORM a Qualified Nuclear Engineer if continued operations is desired.

NOTE The following step addresses several off normal shutdown and control bank conditions. If there are no known stuck/untrippable rods, enter 0 in step F.3.a and F.3.c.

a. RECORD the number of immovable and/or untrippable Control Rods:

_________ Rod(s)

b. RECORD the highest stuck rod worth from BwCB-1, Table 4-1:

_________ pcm

c. MULTIPLY the number of immovable and/or untrippable Control Rods (F.3.a) by 2000 pcm:

x 2000 pcm = pcm (F.3.a)

d. PERFORM the following calculation:

Total rod worth (F.2.d) minus worth of immovable/untrippable rod(s)

(F.3.c) minus the highest stuck rod worth (F.3.b) = actual reactivity available due to rods:

________ pcm - ________ pcm - ________ pcm = ________ pcm (F.2.d) (F.3.c) (F.3.b) 6

1BwOSR 3.1.1.1-2 Revision 3 Continuous Use F. 4. Power defect for present Power Level:

NOTE The pcm value for Power Defect as used in this procedure will always be a negative number.

a. RECORD Power Defect from BwCB-1 Figure 17A (or proper chart in Table 2-1 for the core age) using Boron Concentration (F.1.e) and Power Level (F.1.d):

(-) ___________ pcm INDICATE Method used: Figure 17A Table 2-1

¢ 5. Shutdown Margin Verification:

a. ADD the total corrected rod worth (F.3.d) to the Power Defect (F.4):

_________ pcm + (-)_________ pcm = ¢_________ pcm (F.3.d) (F.4.a)

b. RECORD the Shutdown Margin Limit for MODES 1 and 2 from the COLR:

_________ % k/k x 1000 ___pcm____ = _________ pcm SDM Limit % k/k

c. VERIFY that the available shutdown reactivity recorded in step (F.5.a) is greater than or equal to the minimum required Shutdown Margin Limit recorded in step (F.5.b)

_________ pcm _________ pcm (F.5.a) (F.5.b)

G. ACCEPTANCE CRITERIA The available Shutdown Margin must be within the limits specified in the COLR.

(Final) 7

JOB PERFORMANCE MEASURE TASK CONDITIONS:

1. You are the Unit 2 Assist NSO.

2. The U-0 Hogging vacuum pump is being removed from service for the FIN team to make a packing adjustment.

3. A standard worker tagout for 0OG01P has been printed.

INITIATING CUES:

1. The Unit 2 Unit Supervisor directs you to review the first hang for Worker Tagout #P13-100, to isolate and drain 0OG01P. The final clear will be prepared at a later date.

2. Inform the Unit Supervisor when you have completed your review of the WTO and, either approve the WTO form or feedback (mark up) all necessary changes.

R-203 Page 1 of 5

TASK TITLE: Verify Worker Tagout Checklist.

JPM No.: R-203 REV: 2013 NRC Task No.: 4E.AM-06 K&A No.: 2.2.13 Objective No.: R-AM-010 K&A IMP: 4.1/4.3 EXAMINEE: RO EVALUATOR: DATE:

The Examinee: PASSED this JPM. TIME STARTED:

FAILED TIME FINISHED:

JPM TIME: MINUTES CRITICAL ELEMENTS: (*) 5, 6, 7 APPROX COMPLETION TIME: 30 MINUTES CRITICAL TIME: N/A EVALUATION METHOD: LOCATION:

X PERFORM X IN PLANT SIMULATE X SIMULATOR GENERAL

REFERENCES:

1. OP-AA-109-101, CLEARANCE AND TAGGING, REV 9.

2. M-47, sheet 1A, DIAGRAM OF OFF-GAS SYSTEM UNIT 1.

3. M-150, sheet 1, DIAGRAM OF OFF-GAS SYSTEM UNIT 2.

4. 20E-0-4030-OG01, SCHEMATIC DIAGRAM HOGGING VACUUM PUMP 0 - 0OG01P.

5. 20E-0-4030-OG05, SCHEMATIC DIAGRAM VACUUM PUMP 0 INLET VALVE - 0OG009.

MATERIALS:

1. OP-AA-109-101, CLEARANCE AND TAGGING, REV 9.

2. OP-BR-109-101-1001, BRAIDWOOD SYSTEM SPECIFIC TAGGING GUIDES, REV 8.

3. M-47, sheet 1A, DIAGRAM OF OFF-GAS SYSTEM UNIT 1.

4. 20E-0-4030-OG01, SCHEMATIC DIAGRAM HOGGING VACUUM PUMP 0 - 0OG01P.

5. 20E-0-4030-OG05, SCHEMATIC DIAGRAM VACUUM PUMP 0 INLET VALVE - 0OG009.

TASK STANDARDS:

1. Determine 0OG047 valve has incorrect unit designator.

2. Determine 0OG01P suction line not properly isolated.

3. Determine the sequence of isolation points for 0OG01P C/S and breaker is incorrect.

TASK CONDITIONS:

1. You are the Unit 2 Assist NSO.

2. The U-0 Hogging vacuum pump is being removed from service for the FIN team to make a packing adjustment.

3. A standard worker tagout for 0OG01P has been printed.

INITIATING CUES:

1. The Unit 2 Unit Supervisor directs you to review the first hang for Worker Tagout #P13-100, to isolate and drain 0OG01P. the final clear will be prepared at a later date.

CUE: Hand examinee partially completed Worker Tagout.

2. Inform the Unit Supervisor when you have completed your review of the WTO and either approve the WTO form or feedback (mark up) all necessary changes.

R-203 Page 2 of 5

RECORD START TIME:

NOTE TO EVALUATOR: DO NOT PROVIDE DRAWING M-150 UNTIL THE EXAMINEE REQUESTS IT LATER IN THE JPM. THE OTHER DRAWINGS AS HIGHLIGHTED ARE PART OF THE PACKAGE AND MAY BE PROVIDED ALL TOGETHER TO THE EXAMINEE.

PERFORMANCE STEP STANDARD CIRCLE APPLICABLE

1. Refer to OP-AA-109-101, Refer to OP-AA-109-101. SAT UNSAT N/A CLEARANCE AND TAGGING. Comments:

CUE: Provide copy of OP-AA-109-101.

2. Refer to Drawing: Refer to M-47, sheet 1A. SAT UNSAT N/A

M-47, sheet 1A, DIAGRAM OF Comments:

OFF-GAS SYSTEM UNIT 1 CUE: Provide copy of M-47, sheet 1A.

3. Refer to Drawing: Refer to 20E-0-4030-OG01. SAT UNSAT N/A

20E-0-4030-OG01, Comments:

SCHEMATIC DIAGRAM HOGGING VACUUM PUMP 0

- 0OG01P CUE: Provide copy of 20E 4030-OG01.

4. Refer to Drawing: Refer to 20E-0-4030-OG05. SAT UNSAT N/A

20E-0-4030-OG05, Comments:

SCHEMATIC DIAGRAM HOGGING VACUUM PUMP 0 INLET VALVE - 0OG009 CUE: Provide copy of 20E 4030-OG05.

Evaluators Note: The performer should review the WTO checklist for proper isolation points, sequencing, tag types and OOS positions.

The critical steps of identifying each error in the WTO can be performed in any order. All (3) three errors must be identified to the evaluator for successful JPM performance.

Any additional comments made by the performer should be acknowledged by the evaluator in the same manner as the identification of the WTO errors.

5. Determine the clearance Determines clearance SAT UNSAT N/A sequence for the U0 Hogging sequence is incorrect: Comments:

Vacuum Pump breaker and C/S are swapped.

0OG01P U0 Hogging Pump C/S should be sequenced prior CUE: Acknowledge as Unit to the Brkr.

Supervisor and inform examinee that C/O will be corrected per their mark o Notifies US of sequencing up. error.

R-203 Page 3 of 5

PERFORMANCE STEP STANDARD CIRCLE APPLICABLE

6. Determine the U0 Hogging Determines clearance isolation SAT UNSAT N/A Vacuum Pump suction isolation is incorrect: Comments:

is not adequate.

Suction isolation point of 0OG009 is inadequate and further action is needed for CUE: Acknowledge as Unit proper isolation as follows:

Supervisor and inform examinee that C/O will be o Gag closed the 0OG009 corrected per their mark valve up. OR o Identify and use upstream CUE: If asked, provide drawing isolation points (1OG043 M-150 sheet 1. and 2OG043, both air op valves that fail closed are acceptable upstream isolation points) o Notifies US of isolation error.

7. Determine a wrong unit Determines a wrong unit SAT UNSAT N/A designator is used. designator is used. Comments:

Valve 0OG011 is misidentified CUE: Acknowledge as Unit as 1OG011 Supervisor and inform o Notifies US of component examinee that C/O will be EPN error.

corrected per their mark up.

8. Determine the WTO Tag types are Determines the WTO Tag SAT UNSAT N/A correct. types are correct. Comments:

9. Determine the WTO Hang Determines the WTO Hang SAT UNSAT N/A Positions are correct. Positions are correct. Comments:

CUE: THIS COMPLETES THIS JPM.

RECORD STOP TIME:

COMMENTS:

R-203 Page 4 of 5

SIMULATOR SETUP INSTRUCTIONS

N/A COMMENTS

Provide copy of OP-AA-109-101, CLEARANCE AND TAGGING, REV 5.

Provide copy of M-47, sheet 1A, DIAGRAM OF OFF-GAS SYSTEM UNIT 1.

Provide copy of 20E-0-4030-OG01, SCHEMATIC DIAGRAM HOGGING VACUUM PUMP 0 - 0OG01P.

Provide copy of 20E-0-4030-OG05, SCHEMATIC DIAGRAM VACUUM PUMP 0 INLET VALVE -

0OG009.

R-203 Page 5 of 5

OP-AA-109-101 Revision 9 Page 78 of 86 ATTACHMENT 14 PART 1 WTO Form Hang/Lift Section Page 1 of 1 Exceptional C/O: Mode Dependent: Condition Dependent:

Production Risk: Environmental Risk: Atmospheric Risk: Reactivity Risk:

WORKER TAGOUT# P13-100 JOB DESCRIPTION: U-0 HOGGING VACUUM PUMP PACKING ADGUSTMENT WORKING DEPARTMENT: MMD W/O OR W/R: 12345 EQUIP. TAG# 0OG01P COMPONENT DESCRIPTION: U-0 HOGGING VACUUM PUMP FIRST APPROVAL: __Jim NSO_________________________ DATE/TIME: Today/One hour ago SECOND APPROVAL: _____________ ___________________ DATE/TIME: Today/45 minutes ago WTO AUTHORIZATION: ____________ __________________ DATE/TIME Today/30 minutes ago SPECIAL INSTRUCTIONS: YES: NO: (IF YES SEE ATTACHMENT 14 PART 2)

EQUIP. TAG/EQUIPMENT SEQ TAG POSITION HUNG VERIF. SFTY. RTS RTS RTS VERIF.

NAME TYPE BY BY VERIF. SEQ POSITION BY BY Bus 134Y Cub 5B (1AP17EQ) 1 RD R/O 0OG01P U0 Hogging Pump Brk 0OG01P U0 Hogging Pump C/S 2 CI PTL 0HS-OG011 (0PM01J) 0OG009 L/C/S Hog Vac pp Inlet 2 CD CLOSED Vlv 0HS-OG030 (0OG01J) 0OG009 FU-5X Fuse Hog Vac Pp 3 RD RMVD Inlet Vlv C/P (0OG01J) 0OG044A U0 Hog Vac Pp Suct 4 RD CLOSED Isol From U1 Wtr Box Priming Hdr 0OG044B U0 Hog Vac Pp Suct 4 RD CLOSED Isol From U2 Wtr Box Priming Hdr 0OG023 Hog Vac Pp Demin Wtr 4 RD CLOSED Supply 0OG047 Air Sep Tk 0 Outlet To U- 4 RD CLOSED 2 Vent Stack 1OG011 Air Sep Tk 0 Outlet To U- 4 RD CLOSED 1 Vent Stack 0OG046 Air Sep Tk 0 Drn 5 RI INFO 0OG045 Hog Vac Pp 0 Seal Drn 5 RI INFO Vlv WTO PLACED: ___________________________________________________________ DATE/TIME: _______________

WTL COMPLETED WORK START: ___________________________________________ DATE/TIME: _______________

WTO FINAL CLEAR: WORK CREWMEMBER RELEASE: _________________________ DATE/TIME: _______________

WTO CLEARED: ____________________________________________________________ DATE/TIME: ____________________

(COPIES MAY BE MADE OF THIS FORM FOR ADDITIONAL ISOLATION POINTS)

OP-AA-109-101 Revision 9 Page 79 of 86 ATTACHMENT 14 PART 2 WTO Form Special Instructions Section Page 1 of 1 WTO # P13-100 EXEPTIONAL CO Motor htr. not OOS.

WS not isolated to hogging cooler. Reference BwOP OG-1 & BwOP OG-2 as necessary Info card instruction: 0OG045 and 0OG046 open for drain.

- - - - RTS NOTES ******************************************************************************

Review BwOP OG-2 For S/D Line up

OP-AA-109-101 Revision 9 Page 66 of 86 ATTACHMENT 5 Clearance Preparation/Approval Checklist Page 1 of 4 CLEARANCE # ______ P13-100____________

EQUIPMENT ___0OG01P_______________________________________________

Exceptional C/O: Mode Dependent: Condition Dependent:

Production Risk: Environmental Risk: Atmospheric Risk: Reactivity Risk:

Preparation Brief:

Pre-Job Brief may be Required IF: HU-AA-1212 may be required IF:

(Initial following brief, or N/A) (Initial, or N/A)

Writer/Preparer Approver First time for writing this type of Complex C/O which C/O? integrates several systems?

Unfamiliar with system or N/A N/A prints? Boundary involves Daisy N/A Chains?

Confusing nomenclature?

Boundary impacts PLC or Black box logic?

Emergent request? Pre-Job Brief required Pre-Job Brief Discussion Items:

(, or N/A) (Initial, or N/A)

Is there any in-house or What human performance tools external OE? will be utilized (e.g. C/O N/A Preparer Checklist, HU-AA series procedures)?

Applicable Clearance Order preparation considerations.

Writer/Preparer Approver Actions to be performed for all checklist types:

() - N/A () - N/A Preparation Brief requirements reviewed Special Instructions reviewed / entered Exceptional criteria evaluated Containment integrity considered N/A C/O hang (lift) risk considered (See Page 4 of 4)

C/O Production/Reactivity/Environmental/Atmospheric (Breathing or Explosive)

Risk impact evaluated and critical steps identified

OP-AA-109-101 Revision 9 Page 67 of 86 ATTACHMENT 5 Clearance Preparation/Approval Checklist Page 2 of 4 Specific actions to be performed for hang checklists: CHK # _________ Writer/Preparer Approver

() - N/A () - N/A C/O positions and Sequence correct All attached work scope understood Drain and vent requirements identified Tech Spec applicability assessed Fire Protection concerns noted / addressed C/O step types and tag types correct Requestor notified if work not isolated as requested Specific actions to be performed for lift checklists: CHK # _________ Writer/Preparer Approver

() - N/A () - N/A Lift positions / sequence appropriate for plant status N/A Non-tagged items included in checklist as needed N/A Fill and vent issues addressed N/A Instrumentation backfill requirements identified N/A Configuration control actions properly addressed? N/A Specific actions for Work Addition to an approved C/O: List W/Os* Writer/Preparer Approver

() - N/A () - N/A New work scope reviewed and understood N/A Isolation point positions and tag types verified as adequate N/A Exceptional C/O criteria evaluated N/A Containment integrity considered N/A Drain and vent requirements identified N/A Special Instructions reviewed / entered N/A Requestor notified if work not isolated as requested N/A

IF C/O is placed, THEN complete ALL approvals before attaching the additional work

OP-AA-109-101 Revision 9 Page 68 of 86 ATTACHMENT 5 Clearance Preparation/Approval Checklist Page 3 of 4 Clearance Order preparation considerations Determine the scope of work:

Review and approve the Clearance Request.

Review the Work Order instructions and applicable procedures.

Identify C/O and temp lift requirements, placement of jumpers, or introductions of any energy sources.

Review any TMODs or design changes that are in progress against the system or equipment.

Review the applicable Unit Turnovers for any abnormalities or unusual conditions.

Consult with the Work Planner or SME (Fire Marshal, Engineer) if doubt exists on the scope of work and/or return the C/R if needed for further information.

Establish the Zone of Protection:

Identify electrical and mechanical drawings as needed. Refer to Passport T210 or T215 panels to identify pending document changes.

Request DCP or Mod packages as needed Prepare a sketch or outline of the protection needed including grounds.

Review equipment procedures for special needs in startup, shutdown, or changeover.

Walkdown the equipment looking for interfaces with other equipment/systems not identified or incorrect on drawings.

Submit label requests and drawing change requests as needed.

Review any historical/model C/Os for the same work scope. Compare zone of protection, Special Instructions, etc.

Verify positions correct, sequencing appropriate, tag types correct.

Identify concerns in the Special Instructions:

Equipment draining requirements. Note any process lines that cant be drained, any siphon paths, hoses needed, etc.

Daisy chained neutrals.

Safety hazards (confined space, fall hazard, etc.)

Tech Spec / TRM / ODCM requirements.

Document any Subject Matter Expert review (Fire Marshal, System Engineer, Component Engineer, etc.)

Any switching orders required, other departments needed to assist in hanging/clearing the C/O (Rad Pro, Maintenance, etc.). The Operations Planning person(s) should be notified to appropriately schedule these resources.

Include a note of any grounds that need to be installed / removed, by which department, and manipulations that may be required.

Exceptional C/O criteria evaluated.

Containment integrity considered.

Environmental concerns such as special sampling equipment affected, compensatory measures required, draining of hazardous materials, or systems containing tritium.

OP-AA-109-101 Revision 9 Page 69 of 86 ATTACHMENT 5 Clearance Preparation/Approval Checklist Page 4 of 4 C/O Hang/Lift risk consideration Hang risk actions Lift risk actions Possible effects Fuse or circuit board Fuse or circuit board Auto-starts removal installation Equipment trips Draining / venting Filling / Venting Reactor Protection Logic signals Isolating instruments Valving in instruments Control Room indication changes Jumper installation Jumper removal Control Room annunciators Breaking daisy chains Restoring daisy chains Opposite Unit / Train effects Isolating control air Valving in control air Turbine Supervisory Logic De-energizing control Energizing control power Radioactive release power Loss of Main condenser vacuum Lifting of leads Landing of leads Installing grounds Removing grounds The 5 Key Questions What are the Critical Steps in the task?

What is the Worst Thing that can go wrong?

What are the Error Likely Situations?

What Defenses are we relying upon?

What actions will assure proper configuration control?

Note: When assembling the C/O package include pages 1-4 of this attachment.

Writer/Preparer ___________Jim NSO_________________________/_Today___

Name Date Approver _______________________________________________/_________

Name Date C/O Challenge ________________________________________/_________

Name Date

OP-AA-109-101 Revision 9 Page 1 of 86 Level 3 - Information Use CLEARANCE AND TAGGING

1. PURPOSE 1.1. Description 1.1.1. To establish a process to protect personnel while performing work activities on mechanical and electrical systems or components.

1.1.2. The Clearance and Tagging (C&T) Process may be used to perform the following when other tools are not used.

Protect equipment while maintenance is being performed.

Prevent inadvertent operation when equipment is in a degraded condition.

Establish administrative controls when deemed necessary by Operations.

1.1.3. The following sections are contained in this procedure:

1. Purpose ........................................................................................................... 1

2. Administrative Requirements........................................................................... 3

3. Terms and Definitions...................................................................................... 4

4. Responsibilities................................................................................................ 7

5. Clearance Tag Standards................................................................................ 8

6. Clearance Request Standards....................................................................... 12

7. Clearance Development Standards............................................................... 14

8. Clearance Development ................................................................................ 29

9. Clearance Work Addition/Work Scope Modification ...................................... 32

10. Authorizing and Performing Clearance Manipulations................................... 34

11. Performing Work Under Clearance Protection .............................................. 40

12. Temp Lifts and Partial Clears ........................................................................ 49

13. Worker Tagout (WTO) Process ..................................................................... 50

14. Equipment Tagout Program Problem Response ........................................... 55

15. Documentation .............................................................................................. 59

16. References .................................................................................................... 60

17. Attachments .................................................................................................. 61

OP-AA-109-101 Revision 9 Page 2 of 86 1.2. Scope 1.2.1. The requirements of this procedure apply to all site personnel working within the Exelon Nuclear C&T process. The process applies to personnel who physically enter or break the plane of the area where energy normally exists in the system, or placement of part or all of their body in the zone of protection of a C/O.

1.2.2. Checklists included in this procedure are intended to be used by ALL disciplines working within the C&T process as directed in this procedure.

1.2.3. When switchyard and other transmission distribution related equipment is under the operational control of an outside organization (e.g. power distribution company),

then the outside organizations tagout procedure may be used in lieu of the requirements of this procedure

1. If transmission and/or distribution equipment under the operational control of ComEd and/or PECO is to be worked using this procedure (OP-AA-109-101),

then refer to step 4.6.7 of OP-AA-108-107-1002, INTERFACE PROCEDURE BETWEEN COMED / PECO AND EXELON GENERATION (NUCLEAR /

POWER) FOR TRANSMISSION OPERATIONS, for additional guidance.

1.2.4. Use of other C&T procedures is allowed at individual sites to support specific needs (i.e., Vendor Tagging Programs, Outside Protected Area Tagging). These C&T procedures shall be reviewed and approved by the Corporate C&T Process Owner, Site Clearance Coordinator and Site Industrial Safety Representative prior to use.

These procedures shall be certified in writing by the submitting organization to meet all applicable OSHA Standards.

1.2.5. The requirements of this procedure shall be met to protect against potential hazards to personnel safety from plant systems during physical work on a system. Hazards to be considered include, but are not limited to:

1. Electricity

2. Fluids, Gases, and Vapors

3. Chemicals (refer to MSDS for hazard information)

4. Physical hazards

5. Radioactivity

6. Stored energy 1.2.6. To determine if a Clearance Order (C/O) is required, refer to Attachment 1, Activities That Do Not Require a C/O.

1.2.7. This process shall not be used as the sole controlling process for troubleshooting or design changes to the plant, but may be used to provide isolation for such activities

OP-AA-109-101 Revision 9 Page 3 of 86 under the control of an approved process that meets the applicable requirements (e.g. design change requirements including 50.59 screenings).

1.2.8. Any C/O prepared prior to the implementation of this procedure revision, or a previous revision of this procedure, may be processed without additional restrictions.

Any C/O in place at the time of implementing this procedure need not be retrofitted to meet the requirements listed here, including Tags Plus.

2. ADMINISTRATIVE REQUIREMENTS 2.1. Any changes to this procedure or support T&RMs shall be approved by the Corporate C&T process owner prior to implementation.

2.2. Process Assessment 2.2.1. Annual inspections (performed during the month of May) required by OSHA to ensure employee compliance with personnel safety related work practices will be implemented at each site and tracked in the action tracking database.

1. OSHA REQUIRES regular inspections to occur on an ANNUAL basis as a minimum, to ensure each employee is complying with safety-related work practices. Personnel observations as a representative sampling of employees to assess and monitor generic performance, and group meetings to review the responsibilities of employees with respect to Clearance & Tagging will be used to satisfy these inspections. Document the group meetings on an annual frequency in the action tracking item or equivalent for retrievability purposes.

Personnel observation details on clearance order activity shall be recorded in the Fundamental Management System (FMS) or equivalent.

2.2.2. At least once per calendar year, a qualified assessment group will perform an Assessment of the C&T process, procedure, and practices at each site for areas in potential need of improvement.

2.2.3. Audits of C/Os with placed Tags will be performed by qualified personnel to ensure their integrity using OP-AA-109-101-1002 Clearance and Tagging Quarterly Audit.

1. On a quarterly interval, the documentation of all C/Os with placed Tags shall be verified.

2. On a quarterly interval, a sampling of 25% or at least five currently placed C/O Tags shall be field verified.

3. On a quarterly interval, C/Os that have Tags in place for greater than two months will be assessed for closeout, verified scheduled for repair, evaluated for 50.59 applicability, or identified for abandonment.

2.2.4. On an annual basis, an independent review will be conducted of this procedure to verify compliance with OSHA regulations. This review will be performed by the Corporate C&T Process Owner, which satisfies the OSHA requirement to have a person not directly involved with the C&T process perform this review.

OP-AA-109-101 Revision 9 Page 4 of 86

3. TERMS AND DEFINITIONS

3.1. Accept

The act of placing an electronic hold on a C/O preventing manipulations without notification and release. This term is synonymous with sign-on when discussing electronic sign-on.

3.2. Active

C/O status indicating ALL Tags hung and C/O ready for Acceptance.

3.3. AWT/CLOS: C/O status indicating all steps hung by the current C/O have been lifted and checklists completed. C/O in AWT/CLOS may be set to CLOSED or a New First Hang Checklist may be processed to re-hang the C/O if needed.

3.4. Backgrounding a Clearance: The process of electronically copying a previously prepared C/O.

3.5. Boundary Breach: The opening of the process, cooling or lubrication boundary such that the system is exposed. Instrumentation and lubrication lines that can be isolated by valves or other mechanical devices are not considered breaching of boundaries.

3.6. Boundary Report: A list of isolation points to be walked down by qualified personnel to verify the zone of protection is established.

3.7. C/O Challenge: An oversight review of a C/O which has been prepared and approved by the C/O writers. The challenge is intended to be an overview of the C/O product to ensure the required process steps have been completed, the C/O meets the intent of the C/R, and a high level review of the C/O technical aspects.

The C/O Challenge is not to be an Approval of the C/O.

3.8. Clearance Status: Indication of which stage a C/O is in as it progresses through the C/O life cycle.

3.9. Comment (CMT): Procedure steps listed in C/O Checklist that does not involve boundary equipment.

3.10. Condition Dependent Clearance (CD): A C/O that takes credit for administrative control of a given plant condition to control the hazards for the planned work.

3.11. Danger Tag: A tag used to identify and control clearance points that isolate equipment from energy sources.

3.12. Distributed: C/O and Checklist status indicating that a Checklist has advanced in status past Approved. Checklist is ready to be executed.

3.13. Dual Function (DF): A process used to hang and lift isolation points in a zone of protection on the same Checklist.

3.14. Electronic Sign-On (ESO): An electronic process to provide documentation of individual employee accountability. The sign-on provides for a record of all employees assigned to a particular job relying on C/O protection. This is the electronic equivalent of a Worker Tracking List.

OP-AA-109-101 Revision 9 Page 5 of 86 3.15. Emergent C/O: A C/O that has been requested for preparation within a timeframe after work week daily schedule freeze and request is 3 days prior to execution of the work (does not apply to outage C/Os and FIN Team C/Os).

3.16. Exceptional Clearance: A C/O that does not provide complete conventional isolation (i.e., valves closed, breakers off, etc.). An Exceptional C/O will be designated as such in the C/O Special Instructions along with explanation of the condition. Refer to Attachment 2, Examples of Exceptional Clearances for examples.

3.17. External Energy Injection (EEI): Applying energy into a zone of protection from an external energy source, such as hydro-testing, temporary air supply, or Meggering.

3.18. Facilities Maintenance: (FM) Work that takes place on non-plant/non-power block equipment that may be facilitated by use of the Worker Tagout process.

3.19. Facilities Maintenance Technician: An Exelon employee that performs work on non-plant/non-power block equipment. This person may write, approve, apply, and remove FM Worker Tagouts, with proper qualification and authorization. This generic term represents all MW Sites Facilities Maintenance personnel (L15 or L51).

3.20. General Worker: Exelon or non-Exelon employees who are not ESO qualified but have received NGET that includes C&T General Awareness Training. These employees use a WTL instead of Passport to sign on to a C/O.

3.21. Grounding Device: Device that is designed to provide a metallic connection from ground to the terminals of the equipment that is being worked, and has adequate capacity to carry fault current at the grounding point. The purpose of a grounding device is to protect the worker should the equipment become inadvertently energized. These devices will be controlled under the C/O process.

3.22. Ground Test Device: A device designed for installation in a breaker compartment that allows for testing to be performed and provides a connection between the de-energized equipment and the station grounding system.

3.23. Holder: Any individual who is qualified to accept and release a C/O. This person may be a cognizant team member or supervisor.

3.24. Holder Acceptance Lock: Option used to prevent Holders from accepting a C/O due to current conditions with that C/O.

3.25. Information Tags: Tags used in conjunction with a Clearance to provide indication that the associated equipment is tagged out or other pertinent information.

3.26. Lead Worker: Trained and qualified work group personnel who have the ability to sign on and off C/Os electronically. These may be craft employees or administrators depending on employer. This term defines a role and qualification status used in the clearance and tagging process and is not intended to define any role in relation to the bargaining unit contract at any location.

OP-AA-109-101 Revision 9 Page 6 of 86 3.27. Model Clearances: A C/O developed in advance for repeated C/O use that can be backgrounded into a new C/O to perform work. The goal of Model C/O is to minimize C/O preparation by providing consistent and proven equipment isolation plans to reuse.

3.28. Mode Dependent Clearance (MD): A C/O that takes credit for administrative control of the plant mode and associated hazards.

3.29. Mousing / Test Leads: Leads or wires configured for the purpose of providing an electrical drain path, as the result of static or induced voltage build up or for conducting various electrical tests. Normally utilized during maintenance and testing activities when the equipment has been electrically disconnected or removed from the C/O Boundary. These leads would be controlled by the maintenance or testing activity WO alteration log.

3.30. Partial Clear (PC): A process used to return only a portion of the zone of protection to service.

3.31. Personnel Escort: Any individual badged for unescorted access that is responsible for the continuous observation, safety and procedural compliance of visitors under their escort. For Clearance and Tagging activities, the Personnel Escort must be Lead Worker or Holder qualified if the escorted visitor is entering the clearance order zone of protection.

3.32. Principle Equipment: The equipment within the C/O boundary that maintenance will be performed on, normally listed on a Work Order Task attached to the C/O.

3.33. Release: The act of removing an electronic hold on a C/O allowing manipulations without notification.

3.34. Released: C/O status indicating ALL holders have signed off the C/O.

3.35. Safety Verification: The process of ensuring that it is safe to perform work within a zone of protection. This includes a walk down of the required isolation points by the Working Group using the C/O Boundary Report.

3.36. Suspend: C/O status indicating C/O coverage is suspended, no active work requiring protection of the C/O can proceed (C/O Tags may still be hanging).

3.37. Tags Plus: A philosophy of providing additional measures such that no single inadvertent action could by itself un-isolate the Danger Tagged component acting as a C/O isolation point.

3.38. Tags Plus Methodologies: Any device or technique used by Operations to prevent unwanted component repositioning. These can include valve lockouts, releasable cable ties that prevent valve movement or breaker operation, non-conductive fuse clip inserts, dual valve isolation, robust area barriers, breaker removal, or ball valves with modified handles. (This list is not intended to be all inclusive) 3.39. Temp Lift (TL): A process used to temporarily restore equipment to service for testing or any other purpose deemed necessary by Shift Management.

OP-AA-109-101 Revision 9 Page 7 of 86 3.40. Temporary: This term in relation to employee electronic or WTL sign on means lasting for a limited time. This can be associated with assigned to another job or leaving at the end of the day.

3.41. Visitor: An individual or individuals that are under the control of a Personal Escort.

3.42. Worker Tracking List: A manually produced hardcopy listing of employees assigned to a particular job associated with a C/O(s). The list is used to track individual employees relying on the protection of the associated C/O(s) and prevent Lifting of the C/O(s) until sign-off by ALL associated employees. It satisfies OSHAs requirement for individual accountability.

3.43. Worker Safety Lock/Worker Safety Tag Program: A program which allows personnel working under a C/O to apply Worker Safety Lock(s) or Worker Safety Tag(s) on C/O tagged components(s) closest to their work.

3.44. Worker Tagout: A process that provides personnel protection that is used in place of the electronic tagging process. This is also the backup to the electronic process in the event the computer goes down.

3.45. Working: C/O status indicating at least 1 Holder has accepted a C/O.

3.46. WTO Tracking List Tag: A Tag used by employees as a physical indication to others that they are relying on the tagged component as their main isolation point. It is only used for WTOs because ESO cannot be used.

3.47. Zone of Protection (ZOP): The boundary in which an employee is safe to perform work established by isolating, de-energizing and tagging potential sources of stored energy that could create a hazard for the employee.

4. RESPONSIBILITIES 4.1. The responsibilities and actions required by each position using the C&T process are listed in the body of this procedure.

4.2. All Personnel are responsible to ensure their own safety while working with C/Os by following the requirements of this procedure.

OP-AA-109-101 Revision 9 Page 8 of 86

5. CLEARANCE TAG STANDARDS 5.1. General Standards 5.1.1. No device or equipment shall be operated while C/O or WTO Tags are attached with the following exceptions:

1. Qualified Operations personnel (or qualified FM Technician for WTO being used by FM) performing position verification while placing C/Os or WTOs.

2. Qualified Operations personnel to improve isolation. Prior to this manipulation, permission must be obtained from Shift Management and all Holders who have accepted the C/O or may be affected by the evolution. If the component is Danger Tagged, then the component shall only be moved in the direction of the as applied position.

3. Qualified FM Technician to improve isolation of a FM WTO. Prior to this manipulation, permission must be obtained from the FM Supervisor. If the component is Danger Tagged, then the component shall only be moved in the direction of the as applied position.

4. Qualified personnel manipulating Information Tagged equipment.

5.1.2. All C/O Tags shall contain the following information as a minimum:

1. Component ID Number or noun name when component ID number is not available.

2. Component Description.

3. Position or status of component.

5.1.3. Clearance Tags should be placed on or as close to the component being controlled as possible to avoid confusion as to what point the Tag is controlling. Temporary attachment devices can be used or with proper Engineering approvals permanent attachment devices or holes can be employed.

5.1.4. For touch screen controls designation of a common location for tag placement is suggested to aid in human performance tool use. This location should be as close to the screen as possible to allow screen users to be aware tags are hanging that could affect their work.

OP-AA-109-101 Revision 9 Page 9 of 86 5.1.5. C/O Tags that are found to be either unattached or missing shall be reported immediately to Shift Management who will take the following actions:

1. DETERMINE affected C/O(s) and status.

2. STOP affected work if necessary for safety.

3. EVALUATE the need to Suspend or apply Holders Acceptance Lock to prevent Holders from accepting the affected C/O.

4. If the C/O Tag is still required, then HAVE the Tag reattached and re-verified as applicable.

5. If the C/O Tag is not required, then DISPOSE of the Tag.

6. UPDATE C&T program and documentation as required.

5.1.6. Because Exelon uses Danger Tags instead of locks, Tags Plus Devices and Methodologies will be used so that no single inadvertent action could by itself unisolate the component. Some references call these methodologies Additional Measures. The following criteria apply to Tags Plus.

1. Only one measure need be applied to each isolation point.

2. Energy release paths (vents, drains, Grounds), Not Tagged Steps, and Information Tagged items do not require Tags Plus methodologies.

3. Tags Plus devices do not require separate tracking via the C/O or WTO.

4. Tags Plus Methodologies such as dual valve isolation or racking out a breaker after turning it off, versus turning it off and leaving it racked in the cubicle are also acceptable methods of implementing this requirement.

5. Implementation of Tags Plus is to be discussed at the PJB for placing and removing the C/O and is considered a skill of the craft activity.

6. Tags plus devices shall be installed and removed only by Operations personnel or FM Technicians using FM WTOs.

7. See Job Aid posted in Tags Plus Folder on C&T Website located on the Exelon Nuclear home page for examples and available devices.

8. If Tags Plus devices or methodologies cannot be employed then designate the C/O as exceptional.

5.1.7. When work on equipment that is tagged will not affect the isolation capability of the equipment and Shift Management concurs, then work may be performed on that equipment.

OP-AA-109-101 Revision 9 Page 10 of 86 EXAMPLES OF WORK ON TAGGED EQUIPMENT:

A vent valve tagged closed may have the outlet weld repaired.

An MOV with the hand wheel tagged closed may have electrical work performed that will not cause the valve stem to be moved.

A blocked or gagged device may be worked on if the work will not affect the isolation ability of the block or valve.

Valve stem lubrications.

5.1.8. Untagged component manipulation within the C/O boundary is permitted provided the manipulation is controlled by and documented in an approved procedure or process. The documentation shall include the as-found and as-left position (as-left should match as-found unless otherwise tracked) including verifications as required.

EXAMPLES OF APPROVED PROCESSES Work Order Instructions Station Surveillance Tests MA-AA-716-100, Maintenance Alterations Process 5.1.9. C/O Tags shall not be placed or removed from components tagged with a Safety Lock/Tag. If a component is tagged with a Safety Lock/Tag, then CONTACT Shift Management for resolution.

5.2. Danger Tags 5.2.1. A Danger Tag will override all other Tag types in use at the facility.

5.2.2. A component with a Danger Tag attached to it shall not be physically removed from the system.

5.2.3. Danger Tags shall not be physically removed and/or equipment manipulated until the administrative requirements of this procedure have been met.

5.2.4. A Danger Tag can be applied to a component bearing another Danger Tag, or an Information Tag provided the component positions do not conflict. The Danger Tag shall not be obstructed by the Information Tag.

5.2.5. A Danger Tag shall not be applied to a component bearing a local leak rate test (LLRT) Tag, integrated leak rate test (ILRT) Tag, or Hydro Tag if the required component positions conflict.

5.2.6. A Danger Tag shall not be used to tag a breaker in the energized state.

5.2.7. A Danger Tag should not be used to tag a valve open to maintain a pressurized state, unless the pressure is being used to maintain isolation (e.g., air supply to a line stop bladder).

OP-AA-109-101 Revision 9 Page 11 of 86 5.3. Information Tags and Not Tagged Steps:

5.3.1. Since Information Tags may not be used to hold a boundary point in a zone of protection, but merely identify a component that is associated with a C/O, then components with Information Tags may be operated, removed, or have maintenance performed on the component with Shift Managements permission.

5.3.2. Information Tags and Not Tagged Steps are used in the Clearance and Tagging process for configuration management as appropriate. They are not C/O isolation points. Some examples of their uses are as follows:

1. An Information Tag may be applied to control stations extension controls and indicators to inform Operations personnel how equipment is affected by the C/O.

2. An Information Tag or Not Tagged Step may be used on components that are to be worked on or replaced under the C/O to aid in system restoration.

3. An Information Tag or Not Tagged Step may be used on manual valves within the C/O boundary, which may be manipulated, to aid in system restoration.

4. Information Tags or Not Tagged Steps may be applied to vents and drains and other points associated with a C/O that are not isolation points.

5. An information tag may be used on instrument air supplies to air operated valves unless the AOV is being used as a clearance boundary, in which case the air supply has to be Danger Tagged.

5.4. WTO Tracking List Tags 5.4.1. WTO Tracking List Tags are to be used by employees protected by WTOs, where ESO is not used. The Tag is intended to be a physical indication to others that employees are relying on the tagged component as the main isolation point for the work. A Worker Safety Locking and Tagging Program may be utilized in lieu of the WTO Tracking List Tag.

5.4.2. The Tags will be blue and white and will contain the following: A header stating WTO Tracking List Tag (all workers on WTL sign here), WTO#, date hung, department, and signatures of employees using the tag. Attachment 14 Part 6 is a sample of what the tag should look like. Similar likeness and nomenclature is acceptable if all required information is present.

5.4.3. A designated crewmember should coordinate other employees on the job signing the Tag during the process of completing the WTL.

5.4.4. A designated crewmember should hang one tag on an isolation point, as agreed to by the work crew. Use additional tags if more lines are needed for more employees.

Suggested placement is on the main isolation point protecting the employees. If no main isolation point, placement should be on the first isolation point expected to be cleared.

5.4.5. For components with dual power feeds a tag may be placed on both feeds if the breaker is the point chosen for tagging. This is annotated on Attachment 14 Part 4 as DUAL.

5.4.6. The Tag shall be removed prior to submitting the WTO to Operations for removal or daily at the end of the employees shift, whichever occurs first.

OP-AA-109-101 Revision 9 Page 12 of 86

6. CLEARANCE REQUEST STANDARDS 6.1. A Clearance Requester shall 6.1.1. CONSIDER whether the work can be done without a C/O. Refer to Attachment 1, Activities That Do Not Require a Clearance. If not applicable, CONTINUE at step 6.1.2.

6.1.2. SUBMIT a Clearance Request (C/R) providing as much detailed information regarding scope of work and reference material as possible (reference Attachment 3, Clearance Requestor Checklist, for guidance), including the following information:

1. Equipment Tag, or name description if the Equipment Tag is not in the database. If an equipment number does not exist for a piece of equipment and the site determines a number is required, SUBMIT an Issue Report (IR) or Engineering Change Request (ECR) and RECORD the IR/ECR number in the C/R.

2. W/O and task number, if applicable, must be provided (multiple W/O tasks requiring the same isolations can be bundled under a single C/R).

3. IDENTIFICATION of grounds or ground test devices that will be required to support the work or testing. INCLUDE specific location information and identify the manipulations required to support the work or testing.

4. Suggested isolation points if known.

5. IDENTIFY any Temp Lifts or Partial Clears of the C/O that will be required to support the work or testing, if known.

6. Total work scope including procedure/surveillance numbers and steps if applicable. If partial procedures will be performed, IDENTIFY those steps in the C/R.

6.1.3. SUPPLY approved drawings or required information (i.e., modifications) if current approved drawings are insufficient for determining isolation points.

6.1.4. ENSURE a Work Order task has been created to facilitate Instrument Maintenance Department backfill or venting of instrumentation upon returning a system to service following work that may have drained the instruments.

6.1.5. PROVIDE detail regarding any non-standard isolation methodologies that will be utilized such as line stop or freeze seal.

6.1.6. EVALUATE the work being performed and REQUEST isolation/control of fire protection systems if needed (i.e., CO2 and Halon).

OP-AA-109-101 Revision 9 Page 13 of 86 6.1.7. INCLUDE requirement to use checklists for Supervision, Lead Worker, and Worker (Attachments 11, 12, and 13) in the Work Order package for Work Orders that require C/O protection. Copies provided in shop areas can be used to facilitate ease of access and use by the protected employees.

6.1.8. The Clearance Requester should INCLUDE any additional abnormal or unusual details that will assist the Writer/Preparer and Approver in developing the C/O when known, such as:

1. Drawing references

2. System Configuration A. Systems required to be isolated (i.e., one or both sides of a heat exchanger).

B. Venting C. Draining D. Instrument air Isolated E. Control/Logic/Annunciator Power de-energized

3. Related Fire Protection System Impairment Information.

6.1.9. INCLUDE additional details on configuration of sub-components or subsystems and required C/O manipulations related to the work.

EXAMPLES:

For Emergency Diesel Generator work:

Fuel oil tank drained below sight glass taps Engine coolant drained Oil pumps tagged but draining not required Maintenance Requires Control power energized Temp Lift required for oil pump testing 6.1.10. The C/R Approver shall:

1. REVIEW the C/R to ensure adequate information is available for planning the C/O.

2. NOTIFY the Clearance Requester and RETURN the C/R if the scope is not properly identified.

3. APPROVE the C/R (may use Expedite Approval option).

4. PLAN the C/O, ASSIGN the C/R to a C/O Writer/Preparer to plan, or ASSIGN the C/R to a Clearance Assembly (C/A) for C/O preparation.

OP-AA-109-101 Revision 9 Page 14 of 86

7. CLEARANCE DEVELOPMENT STANDARDS 7.1. Clearance Development General Requirements 7.1.1. The Clearance Coordinator or Operations Management designee will EVALUATE the level of pre-job brief and HU-AA-1212 review using Attachment 5, Clearance Preparation/Approval Checklist.

7.1.2. C/Os will provide a safe zone of protection for all physical work to be performed under the C/O or for required equipment protection. This is accomplished by identifying, isolating, and tagging all required isolation points. If all required isolation points cannot be isolated, then the C/O will be designated as Exceptional. SEE Attachment 2, Examples of Exceptional Clearances.

7.1.3. C/Os written for one unit that affect systems common to the other unit must be carefully evaluated to assure that conditions on both units allow the equipment/system to be removed from service.

7.1.4. C/O impacts must be evaluated to ensure that affects on systems and components outside of the C/O boundary are identified and are acceptable, or properly dispositioned (i.e., evaluate affect of work on fire systems such as CO2/Halon injection or deluge systems).

7.1.5. During C/O development, the Writer/Preparers and Approvers will ASSESS Operational/Atmospheric (breathing and explosive)/Environmental/Reactivity risk impact. IDENTIFY any critical steps on the C/O which have the potential to result in a

> 20 MWe unplanned load reduction, impact breathing air in a space causing it to become uninhabitable, creation of explosive atmospheres when ventilation systems are removed from service, or affect reactivity. WC-AA-104 Integrated Risk Management has information regarding this topic. DISCUSS risks identified with Supervisor and take necessary actions, which may include notifying Cycle or Work Week Mgr, initiation of a Corrective Action Program document, or providing special instructions to address the risk.

7.1.6. C/O written on systems that remain in service or are only partially removed from service by the C/O must ensure that there are no adverse affects on the whole system as a result of the C/O.

7.1.7. Baseline Equipment Tagout has the feature of multiple open Checklists in approved status for a single C/O. Because of this tool, when changes are made to existing Checklists or additional Checklists are added, the Writer/Preparer and Approver as part of the process of development and approval of the Checklist being altered or created must ASSESS the impact on all other approved Checklists. ADDRESS all steps Tagged and Not Tagged in this review. Those Checklists impacted will be reset to PLAN status or canceled.

OP-AA-109-101 Revision 9 Page 15 of 86 7.1.8. If a C/O leaves uncertainty to the affects on Plant SSCs (Structures, Systems and Components), then REFER to LS-AA-104 Exelon 50.59 Review Process, LS-AA-104-1000 Exelon 50.59 Resource Manual, and CC-AA-112 Temporary Configuration Changes.

1. C/Os used to remove equipment from service to perform maintenance do not require a 10 CFR 50.59 review as long as the C/O strictly applies to the equipment being worked on (i.e., isolating a pump or removing the power feed from a motor operated valve).

2. C/Os that involve a temporary configuration change in support of maintenance fall into the 90-day clock category.

3. C/Os that involve a temporary configuration change for a degraded or nonconforming condition which are not in support of maintenance but allow for continued operation of the degraded or nonconforming equipment until maintenance can be performed, are required to have a 10 CFR 50.59 review performed prior to installation of the C/O.

7.1.9. C/O development shall consider ALARA principles.

1. CONSIDER changes to area dose rates when radioactive system draining will be performed.

2. CONSIDER alternate methods of isolation of C/O boundaries to minimize entries into high radiation areas to minimize personnel exposure.

7.1.10. Controlled drawings (including ECR Issue drawings) and references shall be used in the preparation of C/Os when available.

1. If controlled drawings are not available, then a C/O walk down shall be performed.

2. If a C/O walk down cannot be performed or cannot confirm isolation points, then a knowledgeable person (System Engineer, Subject Matter Expert, Vendor Representative, etc.) shall be consulted.

3. If isolation cannot be confirmed by other methods, then a Field Check of System conditions must be performed prior to releasing the C/O for work to start. If energy is detected during these checks, CONTINUE research until a safe zone of protection can be established.

7.1.11. The impact of a C/O on a Temporary Configuration Change Package (TCCP) shall be CONSIDERED and should be DOCUMENTED in the Special Instructions section of the C/O.

OP-AA-109-101 Revision 9 Page 16 of 86 7.1.12. All components manipulated during C/O activities shall be TRACKED to ensure configuration control by one of the following methods:

1. Tagged with a C/O Tag

2. Listed as a Not Tagged step

3. Tracked by a procedure that governs the manipulation 7.1.13. When C/O Tags are required to be placed on control panels or distribution panels that have closely spaced control switches, indications, breakers or controls where Regular Sized Tags may obscure these controls or indications, then Control Switch or Sticker size C/O Tags shall be used.

7.1.14. When a procedure exists to secure or restore equipment to service, then the procedure should be used to perform the task. The C/O may be performed in conjunction with the activity as appropriate.

7.1.15. Not Tagged C/O steps used for configuration control are required to be final cleared.

7.1.16. Procedures used as part of C/O performance should be listed in the Special Instructions, Checklist Notes, or as Comment (CMT) Steps and properly sequenced with the C/O steps.

7.1.17. If the C/O is determined to be an Exceptional C/O (refer to Attachment 2, Examples of Exceptional Clearances), then an explanation as to the reason shall be clearly stated in the Special Instructions of the C/O.

7.1.18. Special Instructions should contain the following items as a minimum, as determined by the C/O writer and approver, when applicable (list is not all inclusive or in order).

1. Work Group Cautions/Hazards including exceptional criteria

2. If the Clearance is Mode or Condition Dependent describe why

3. Operations Hang Info

4. Operations Cautions/Hazards

5. RTS info including fill and vent information

6. Procedures required to support Clearance execution

7. Work Scope if warranted by complexity

8. Administrative Requirements (Tech Specs, Fire Impairments, Plant Barrier Impairments, OLR or SDR)

OP-AA-109-101 Revision 9 Page 17 of 86 7.2. Preparation and Approval Requirements 7.2.1. If the C/O affects Technical Specification (Tech Spec) or Safety Related equipment, then the C/O approval must be performed by a licensed or previously licensed individual.

7.2.2. All C/O Writer/Preparers and Approvers are accountable for the items on the applicable Clearance Preparation/Approval Checklist. Copies of each completed attachment shall be routed with the C/O paperwork.

7.2.3. The C/O Challenge is required for all Clearances and WTOs prior to being placed and whenever work is added to a placed C/O. The C/O Challenge is not required for subsequent TL, RH, PC, FC Checklists, or FM WTOs.

7.2.4. When an On-Line Emergent C/O is prepared, then measures shall be used to ensure an independent review is performed. This will be accomplished by independently marking two sets of prints to identify isolation points.

7.2.5. When a change is made to an APPROVED C/O, then the review requirements are limited to those aspects of the C/O that are affected by the change. An entry should be made on the C/O route list notes or Special Instructions to document the change and level of review performed.

7.2.6. When the affects of C/O are not understood by the C/O Writer/Preparer or Approver, then Engineering or a Subject Matter Expert shall be contacted to provide technical expertise detailing the affects of the C/O including the affects on equipment that must remain operable.

7.2.7. If the affects of a C/O still cannot be determined, ADD Not Tagged steps to the C/O to take field readings to verify the zone of protection is safe prior to releasing the C/O to the work group.

7.2.8. When a Condition Dependent C/O is used, then the following information shall be included in the C/O Special Instructions:

1. Designate C/O as exceptional

2. Basis for using this type of C/O

3. Dependent condition to be maintained or procedure governing the condition 7.2.9. For Condition Dependent C/Os, the condition being administratively controlled shall be clearly identified with a C/O Information Tag or other indicating device to alert those responsible for monitoring and maintaining the condition within its required status or range. If the condition is being controlled under the direction of a governing procedure (e.g. Reactor Head Disassembly/Reassembly), then the indicating device is not required to be identified with a Tag.

OP-AA-109-101 Revision 9 Page 18 of 86 7.3. Clearance Isolation Standards 7.3.1. Sequencing of C/O step performance

1. C/O isolation points may be arranged to reduce unnecessary travel as long as personnel safety and equipment reliability is not compromised.

2. When a procedure is used to secure or realign equipment, then the equipment shall be manipulated by the sequence dictated by the procedure.

3. C/O Application sequencing should use the following techniques as applicable:

A. Control switches prior to power supplies B. Control switches prior to gagging/blocking devices C. Control switches prior to hydraulic/pneumatic control isolation D. Power supplies prior to components E. High energy systems prior to low energy systems if covered by the same C/O F. Driving equipment prior to driven equipment G. Discharge valves prior to suction valves H. Vents prior to drains (hard piped drains should be opened first to depressurize an isolated boundary)

4. Restoration sequencing should use the following techniques as applicable:

A. Vents and drains B. Suction valves prior to discharge valves C. Low energy systems prior to high-energy systems if covered by the same C/O.

D. Driven equipment prior to driving equipment E. Components prior to power supplies F. Control switches after hydraulic/pneumatic control isolation G. Power supplies prior to control switches H. Gagging/blocking devices prior to control switches

OP-AA-109-101 Revision 9 Page 19 of 86 7.3.2. Mechanical Isolation General Standards

1. Manual valves will normally have the Tag applied to the hand wheel.

However, if the valve is deemed inaccessible and verified by other means in the required position, a Tag may be hung in highly visible location such that access cannot be gained to the valve without having to address the Tag, i.e.,

door handle on the door to the room or area where the valve is located.

2. If a C/O is placed where rotation of the equipment would cause a safety hazard to employees or damage to the equipment, then CONSIDER isolation of flow paths that could cause rotation.

3. Dual valve isolation should be provided when isolating from an energy source of greater than 200 Fahrenheit or pressures greater than 500 psig. If dual valve isolation is not provided, then the C/O shall be deemed an Exceptional C/O.

4. Throttled valves should not normally be used as isolation points. When a throttle valve is used as a C/O isolation point, then sufficient administrative control shall be put in place in order to properly position the valve on return to service.

5. Check valves that cannot be physically restrained in the isolated position by a hand wheel or gag should not be used as boundary isolation points unless no other isolation is practical. If a check valve without restraint capability is used as a primary or secondary boundary, then an explanation shall be listed in the Special Instructions and the C/O shall be designated as an Exceptional C/O.

6. Hydraulically operated valves used as isolation points shall have hydraulic pressure removed or blocked in the isolated position and C/O Tag attached.

If these conditions cannot be met, then this C/O shall be an Exceptional C/O.

7. Using a valve backseat for isolation (i.e., to isolate packing leakage for repair/replacement):

A. VERIFY the valve is designed with a backseat for use as isolation.

B. The valve will be OPENED and TORQUED on the backseat, as applicable. Reference OP-AA-103-105, Limitorque Motor-Operated Valve Operations.

C. CONTACT the System Engineer as applicable if proper guidance cannot be found in OP-AA-103-105.

D. The hand wheel will be Danger Tagged in the backseated position.

8. A valve may be considered inaccessible due to location requiring a ladder/scaffolding to access and Tag or entry into a High Radiation Area is required only to Tag the valve (i.e., no work or general access is allowed in the area. An example would be a BWR MOV located in the Drywell).

9. Locking devices can be utilized when a valve is identified as having a high potential for inadvertent contact. A valve identified as always needing a locking device to prevent inadvertent opening while tagging out can be identified as such on the Passport Equipment Notes. Locking devices are to be placed and removed within the timeframe of the C/O and can be designated on the C/O Checklist as Not Tagged steps. Installation shall be reviewed on a case-by-case basis for fire loading and seismic affect.

OP-AA-109-101 Revision 9 Page 20 of 86 7.3.3. Gagging and Blocking Device Standards

1. Gagging and blocking of C/O isolation points shall be done using C/O steps, work packages, or approved procedures that include any pre-approved engineering solutions. These C/Os shall be designated Exceptional.

2. No work may be performed on blocked or gagged equipment that may affect the block/gags ability to maintain isolation capabilities of the component.

3. When a gagging or blocking device is used to maintain a C/O boundary, then a C/O Tag shall be applied to the gagging or blocking device.

4. If pneumatic operated or motor operated valves are used as an isolation boundary, then an appropriate gagging device may be used to maintain the isolation boundary with the operator removed.

5. If a device fails to a position different from the required C/O position on a loss of control power or air supply, then it shall be held in its tagged position by a gagging/blocking device. When the gagging/blocking device has been installed, then the motive force of that valve shall be removed to ensure that the gagging/blocking device is performing its intended function. Once tested, the motive force may be restored.

6. If a component is physically restrained in a required position using an approved gagging/blocking device to establish a zone of protection, then the gags/blocks shall be used as isolation points and a C/O Tag shall be attached to the gag/block.

7.3.4. Plug, Line Stop, and Freeze Seal Standards

1. The use of plugs/line stops shall require that the C/O be an Exceptional C/O.

Tagging of plugs that are underwater is not required.

2. Plugs may be used as isolation boundaries when they are determined to be seated, and at least one of the following is true:

A. The plug is provided with a constant gas/water supply to remain inflated.

B. A Physical gagging/blocking device is installed and the device is tagged with a C/O Tag.

OP-AA-109-101 Revision 9 Page 21 of 86

3. When a freeze seal is used as an isolation point to perform work, then the following are required:

A. Freeze seals shall be performed by approved procedures and controlled by work instructions in a Work Order Task.

B. A C/O shall be placed to control the other isolation boundaries associated with the freeze seal.

C. The associated C/O shall be classified as Exceptional with the details of the freeze seal entered into the C/O Special Instructions.

D. Any drains or vents opened with the placement of the C/O shall be tagged with Information Tags or listed as Not Tagged steps and re-closed after draining, or an Operator will be assigned to monitor for leakage past the freeze seal and close the valves if needed.

E. Any additional draining or system breach performed by Maintenance during the freeze seal work shall be tracked by the work crew in the W/O instructions and restored prior to removing the freeze seal and prior to the Holder releasing the C/O.

F. Coordination with the maintenance group responsible for maintaining the freeze seal will be established to ensure that the seal is established and removed in the proper sequence.

G. CONSIDER inserting a Not Tagged step for the freeze seal on the isolation boundary C/O to ensure proper sequencing the restoration of the boundaries.

7.3.5. Air Operated Valves and Dampers (AOVs) Standards

1. A fail open AOV may be used as a closed isolation point if the following conditions are met:

A. The valve control station(s) shall be tagged closed.

B. The valve shall be forcibly held closed with an installed gagging or blocking device. The integrity of the gagging or blocking device installation shall be verified by:

1. CLOSE and VENT the air supply to ensure AOV remains as positioned.

2. RESTORE the air supply.

C. The air supply valve to a gagged AOV shall be Information Tagged to aid in establishing the component in a safe condition prior to gagging device removal.

OP-AA-109-101 Revision 9 Page 22 of 86

2. A fail-as-is AOV may be used as an isolation point if all of the following conditions are met:

A. The valve control station(s) shall be tagged.

B. The valve should be visually checked closed.

C. The valve shall be tagged and forcibly held closed with an installed gagging or blocking device unless the valve mechanically locks in position without pneumatic supply.

D. The air supply valve shall be tagged closed.

E. If the above requirements cannot be met, then the AOV may still be used as an isolation point under proper approval and the C/O classified as exceptional.

3. If an air operated valve is used as an isolation point, and it fails in the closed position, then air shall be isolated, bled down and tagged or the solenoid deactivated and tagged to ensure the valve cannot be operated.

4. If an air operated valve is to be worked on such that the air supply must be isolated to prevent the valve from stroking or for air operator work, then the air supply stop at the AOV should be tagged with an INFO tag allowing the working crew to manipulate the air supply as needed for maintenance and testing.

7.3.6. Motor Operated Valve (MOV) Standards

1. A motor operated valve may be used as a C/O isolation point provided all the following conditions are met:

A. The valve control station(s) shall be tagged.

B. The electrical energy source shall de-energized and tagged.

NOTE: The hand wheel may be considered inaccessible due to location requiring a ladder/scaffolding to operate and Tag or entry into a High Radiation Area is required only to Tag the valve (i.e. no work or general access allowed in the area. An example would be a BWR MOV located in the Drywell).

C. The valves hand wheel should be tagged if personnel protection is being provided unless the hand wheel is inaccessible, in which case the C/O shall be an Exceptional C/O.

OP-AA-109-101 Revision 9 Page 23 of 86 7.3.7. Venting and Draining Standards

1. When a system containing hazardous fluids/gases is drained or vented for removal from service, then methods for capturing the substance shall be noted in the C/O Special Instructions. Re-closure of vents and drains may be necessary to contain residuals.

2. When a pressure boundary is tagged for internal work, and an energy potential exists that would create a concern for the employee, then the zone of protection must be depressurized and drained by the use of vents and drains that are included on the C/O. If these conditions cannot be met, then the C/O shall be an Exceptional C/O.

3. If no valves are available to drain/depressurize an isolated system, then the working department must be informed that other measures (i.e., breaking flanges/fittings or loosening connections) are required to drain/depressurize the system after the C/O is placed. These activities will be controlled by a work package. Such C/Os shall be designated as an Exceptional C/O.

4. If venting or draining is required to compensate for excessive leak-by of an isolation point, then the vent drain valves shall be tagged open unless they will be removed for maintenance.

5. NOTIFY cognizant Radwaste personnel prior to draining significant amounts of fluids from systems that could affect waste processing.

7.3.8. Electrical Isolation General Standards

1. Isolation for personnel protection should not consist of tagging a control switch only, unless no other means to isolate are practical, in which case the C/O will be designated as Exceptional.

2. If Main Control Board switches or Remote Shutdown Panel controls are tagged to indicate C/O conditions, then they should normally be tagged with Information Tags.

3. When gang operated components (i.e., four valves operated by one control switch) are to be tagged individually, then detailed instructions shall be included on the C/O Checklist to assure the components that are not being removed from service remain in the desired state. Such instructions are not required if the entire group of components is tagged simultaneously.

4. It is preferred to use breakers as isolation points rather than pulling fuses under load, which may cause damage to fuse holders.

5. Remote or alternate shutdown panel controls are not required to be tagged unless they are in use as the controlling station.

6. When a lead will be lifted where multiple leads are landed on the same terminal point, then the affects of lifting all leads shall be evaluated.

OP-AA-109-101 Revision 9 Page 24 of 86

7. When leads must be lifted to isolate work from an electrical hazard, then C/O Tags shall be used on the leads lifted unless covered by the criteria in Attachment 1, Activities That Do Not Require a C/O.

8. A C/O Tag placed on a breaker handle or compartment door does not prevent opening the cubicle door for inspection by qualified individuals.

9. If an annunciator that is related to a system that remains operable or in operation is made inoperable because of a C/O, then consideration should be given to placing an Information Tag on the annunciator window to explain the conditions.

10. When a C/O is placed to support bus inspections where all components are not completely de-energized or the potential for backfeed exists, then the live components and backfeeds will be listed in the C/O Special Instructions and the C/O will be considered Exceptional.

7.3.9. Breaker Standards

1. When an MCC type or distribution panel breaker is tagged as an isolation point, then:

A. The C/O Tag shall be placed on the breaker handle/switch in the OFF position, unless the Clearance Request identifies that the scope of work will require the Tag to be placed on the cubicle door to facilitate work such as bucket or breaker removal.

B. If using an MCC Breaker as an isolation point, and that model breaker has been proven unreliable to open, then contact open checks should be performed by qualified personnel. These should be done prior to installing the Tag on the locking mechanism, or the qualified individual performing the check may not be able to open the breaker door to physically perform the check. (This will require work group coordination with Operations when hanging the C/O if checks done by other than Operations.)

CAUTION Depending on the breaker configuration lifting leads at other than the breaker operating handle mechanism may not isolate breaker control power - resulting in no longer having the same isolation as opening up the breaker. If not lifting leads at the breaker operating handle mechanism, VERIFY the leads being lifted provide the same electrical isolation as opening the breaker.

C. If a tagged breaker is tagged on the handle/switch and work will require moving the Tag to the cubicle door, then the Operations Department may transfer the C/O Tag to the cubicle door or lifted leads without the Holder(s) releasing the C/O.

OP-AA-109-101 Revision 9 Page 25 of 86 NOTE: During the following activity, work tied to the C/O may not continue because the zone of protection is being altered. This is required to ensure no one is working on the equipment powered from the breaker during installation of the breaker /lead landing activity.

D. When installing a breaker that has been removed from an MCC or relanding leads that were previously lifted from a breaker, the responsible Work Group for the activity shall perform the following actions:

1. COORDINATE with Operations to have the Holders Acceptance Lock applied to all C/Os using that breaker as an isolation point.

2. COORDINATE with the Supervisors and Workers signed on to the affected C/Os to release for TL or FC.

3. VERIFY all Holders have released from the affected C/Os and Holder Acceptance Locks have been applied.

4. VERIFY all phases OPEN or OFF prior to breaker installation.

5. PERFORM breaker installation/lead termination.

6. Following breaker installation, COORDINATE with Operations to transfer the Clearance Tag to the breaker operating mechanism (unless more cubicle work will be performed) and have the Holders Acceptance Lock removed from the affected C/Os not being Final Cleared.

2. For rackable breaker C/O positions, racked out (R/O) allows all breaker positions except racked in and racked to test.

3. For non-rackable breaker positions, OFF allows all breaker positions except ON.

4. When a rackable breaker is tagged as an isolation point in the racked out position, then the C/O Tag shall be placed on the cubicle door or racking device.

5. When distribution panel breakers are tagged as an isolation point, then the C/O Tag shall be attached to the breaker switch using a station approved method that will securely attach the C/O Tag to the switch. Adhesives such as tape and adhesive backed tabs can be used to attach C/O Tags, or Sticker Tags may be used on distribution panel breakers when the environment and physical conditions are not likely to cause the Tag to become detached inadvertently.

OP-AA-109-101 Revision 9 Page 26 of 86 7.3.10. Grounding Standards WARNING THE EFFECTS OF ENERGIZING GROUNDED EQUIPMENT CAN BE CATASTROPHIC! ALL GROUNDS SHALL BE VERIFIED REMOVED PRIOR TO RE-ENERGIZING EQUIPMENT.

1. All grounding devices providing personnel protection shall be INCLUDED as an isolation point on a C/O or WTO and will be tagged with a Danger Tag that is hung on the grounding strap, the cubicle door, or on the GTD in an appropriate location (such as the racking screw or front panel).

2. If additional grounds are identified after the start of work as being required, then Operations must be contacted to Danger Tag the additional grounds.

3. The following are exempt of the requirements of C/O Danger Tags:

A. Grounding scaffolding B. Grounding vehicles / lifting devices C. Mousing / test leads D. Other ground devices not in the electrical circuit bounded by the Zone Of Protection for attached work orders

4. Grounding devices installed for testing shall be IDENTIFIED as such with an Information Tag or as a Not Tagged item on a C/O or WTO.

5. When a bus or power source is to be grounded, then all electrical feeds and potential backfeeds to that bus or power source shall be tagged out prior to grounding. If there are multiple electrical feeds to the bus or power source, if installing ground straps/clusters, or if closing a grounding disconnect, the step to tag the ground(s) must be included on a Clearance or WTO that also tags all electrical feeds and potential backfeeds to that bus or power source.

6. Employees installing or removing grounds straps on installed devices or Ground Test Devices shall be PROTECTED by a C/O or use Attachment 1 criteria prior to commencing the installation. An example of Attachment 1 criteria would be if the equipment has single or multiple feeds and the feed is in the sole control of the worker. If multiple feeds exist, and sole control is not possible, then C/O acceptance is required.

7. Ground Test Device and ground strap installation should be performed in accordance with an approved station procedure or work instructions.

8. Plant Operations and the work group shall EVALUATE grounds that are lengthy to determine if both ends require tagging. Normally only one tag per ground cluster is required.

OP-AA-109-101 Revision 9 Page 27 of 86 7.3.11. Fuse Standards

1. When a fuse is removed to provide C/O isolation, then the fuse shall be replaced with a non-conductive clip or other Tags Plus device that prevents insertion of a fuse when C/O is hanging.

2. ATTACH the tag to the fuse clip or place it as close to the clip as possible. If a non-conductive fuse block out device is not used, then the fuse shall be identified and stored for restoration when the C/O is removed, and a Tag will be placed such that another fuse cannot be accidentally installed.

3. EXERCISE care to insure that the size and rating of fuse removed during C/O activities is the same as the fuse that gets reinstalled during restoration.

4. Breaker control power fuses should only be tagged when they are included as part of the zone of protection.

5. When tagging a fuse block to provide C/O isolation, then the fuse block shall be controlled in one of the following manners.

A. Place the fuse block (and fuses) in a bag identified with a copy of the Danger Tag or information traceable back to the C/O, store in a safe location, and place the actual Danger Tag on a wire terminated at the base of the stationary portion of the fuse block, covering the fuse block to prevent other fuses from being installed.

B. Turn the removable portion of the fuse block 180 degrees to the OFF position and reinsert into the stationary portion of the fuse block, with the Danger Tag placed on handle of the fuse block.

7.3.12. Logic Circuits and Instrumentation Standards WARNING EXTRA CARE SHALL BE TAKEN WHEN WORKING WITH THE REACTOR PROTECTION SYSTEM, PRIMARY CONTAINMENT ISOLATION SYSTEM, ECCS LOGIC SYSTEM, AND TURBINE SUPERVISORY SYSTEM TO PREVENT INDUCING INADVERTENT ACTUATION SIGNALS DURING C/O MANIPULATIONS.

1. The C/O Preparer and Approver must fully understand C/O impacts on logic circuits and instrumentation. If there is any question regarding response, then assistance must be requested from subject matter experts.

2. When instrument components normally manipulated by IM personnel are part of a C/O, then IM personnel should perform the manipulations.

3. In every case that instrumentation component manipulation is required for a C/O, all plant effects of the manipulation shall be known and compensated for prior to the manipulation.

4. The affects of any lost or inaccurate inputs into plant processes (e.g., heat balance inputs, etc.), resulting from the C/O application, shall be evaluated.

OP-AA-109-101 Revision 9 Page 28 of 86 7.3.13. External Energy Injection (EEI) Standards

1. When External Energy Injection will be performed on equipment within a Clearance boundary (e.g., hydro-testing, high pot testing, back filling of piping, Baker testing, temporary air supply, Meggering), then the activity shall be performed under the requirements of the governing approved procedure or work instructions to ensure the proper safety precautions are taken. The work group performing the energy injection is responsible for ensuring energy being introduced will not jeopardize any employees safety. The following will be addressed:

A. Guarding of test areas.

B. Requesting supporting ground test devices.

C. Test observers.

D. Safety checks.

E. Worker Notification

2. The Supervision performing the EEI activity shall perform the following:

A. CONTACT and COORDINATE with all Supervision for associated C/Os to discuss the impact of the EEI on all work in progress.

B. USE the Holder Acceptance Lock to support the EEI activity for all affected Clearances.

C. VERIFY C/O Holders and protected employees for associated C/Os are notified and agree to the EEI by completing Attachment 16, External Energy Injection (EEI) Notification. If all workers sign off the Clearance before the EEI commences then Attachment 16 is not required. The Holders Lock shall still be applied.

D. WHEN EEI is complete REMOVE Holders Lock and workers can resume work.

3. C&T EEI Standards are not required if the component is removed from the Zone of Protection of the Clearance, either by physical removal or separation.

EEI safety practices still need to be employed as listed in section 7.3.13.1 above. Examples of when Attachment 16 is not required:

A. Transformer work with disconnects or bus work physically removed within line of sight of the transformer.

B. Meggering of bolts on a pump with insulated flange connections.

C. AOV maintenance and testing with an external air supply or INFO or Not Tagged air supply valve.

D. Equipment not installed in the ZOP like a motor or pump in the shop, a breaker removed from its cubicle, or equipment electrically disconnected.

OP-AA-109-101 Revision 9 Page 29 of 86

8. CLEARANCE DEVELOPMENT 8.1. Processing Requests for Clearance 8.1.1. The Clearance Group or Qualified Operations personnel shall perform the following:

1. REVIEW and APPROVE C/Rs per Section 6.

2. For situations that require multiple C/Os to support the W/O task, GENERATE additional C/Rs for each additional C/O that is required.

3. BUNDLE related C/Rs/CAs for efficiency.

4. IDENTIFY any Temp Lift, Partial Clear, or Final Clear Checklists of the C/O that can be prepared in advance during the planning process.

8.2. Clearance Development and Approval 8.2.1. The C/O Writer/Preparer shall perform the following in accordance with the requirements of this procedure using a copy of Attachment 5, Clearance Preparation/Approval Checklist.

1. CONTACT the Clearance Requestor(s) if there is any doubt of the scope of work, isolation requirements or special conditions/instructions. If the Clearance Request is inadequate, then RETURN it to the work planner for additional information.

2. COPY/BACKGROUND a Model or Historical C/O or CREATE a new C/O as appropriate.

A. REVIEW the work to be performed. IDENTIFY an Authorized Model or historical C/O for same or similar work scope to be performed.

NOTE: Passport enhancements are in place to highlight documents that have pending revisions. REFER to the T210 or T215 panels.

B. VERIFY that the references, including drawings and procedures, listed on the Model have not undergone revision or the revisions verified not to impact proper isolation.

C. BACKGROUND the Model/Historical C/O or CREATE a new C/O.

D. ATTACH the appropriate C/Rs.

OP-AA-109-101 Revision 9 Page 30 of 86

3. DEVELOP a boundary isolation list to establish, modify or lift a zone of protection as applicable.

A. USE equipment records as they appear in the database.

B. ENTER the Equipment Tag and name in the description field if the proper record cannot be located in the database and INFORM a Data Steward of the problem if a new record is required. If it is not desired to create an equipment record in Passport, ENTER the required information in the Equipment/Description field to identify the component.

C. ENTER the appropriate tag type for the application.

D. UTILIZE the most detailed reference material available to ensure the actual configuration of the system is understood.

4. ENTER procedures to be used in conjunction with the C/O as comment (CMT) steps or Special Instructions.

5. REQUEST assistance from Engineering or Subject Matter Expert if necessary and INCORPORATE the information provided into C/O.

6. EVALUATE the work being performed for the need to isolate/control automatic initiation of fire protections systems (i.e., CO2 and Halon).

7. ENTER hang or lift positions to establish, modify or lift the zone of protection as applicable.

8. SEQUENCE all C/O steps.

9. ENSURE drain precautions or fill requirements are specified as applicable.

10. SPECIFY Boundary Verification Requirements.

11. DESIGNATE the C/O as Exceptional and ENTER the appropriate information in the Special Instructions if required.

12. ENSURE that any C/O related TCCP that may affect the C/O zone of protection or affected equipment is properly configured prior to, or in correct sequence with, C/O boundary manipulations.

13. EVALUATE the risk potentials using Attachment 5, Clearance Preparation/Approval Checklist. ENTER comments in the C/O Special Instructions as appropriate.

14. ENSURE that all information provided by the Clearance Requester(s) is addressed by the C/O.

15. INCLUDE in the Document panel all drawings and procedures used in preparation of the C/O.

OP-AA-109-101 Revision 9 Page 31 of 86

16. NOTIFY the Clearance Requestor if equipment is not isolated as requested in the C/R to ensure that any special conditions/instructions are met, or assumptions made during the work planning (including risk evaluation) are not compromised.

17. NOTIFY the Cycle Manager/Unit Coordinator if the activity is determined to be a Reactivity/Atmospheric (Breathing and Explosive)/

Operational/Environmental risk activity outside E-4 or Work Week Manager if inside E-4.

18. APPROVE the C/O Outline (may use Expedite Approval option).

19. PREPARE a C/O Checklist.

20. IDENTIFY Reactivity/Atmospheric (Breathing and Explosive)/

Operational/Environmental Risk critical steps on the C/O Checklist by entering a step note or in the Special Instructions.

21. ROUTE the checklist for approval.

8.2.2. The C/O Approver(s) shall perform the following in accordance with all requirements of this procedure using a copy of Attachment 5, Clearance Preparation/Approval Checklist.

1. VERIFY that the C/O activity was properly prepared as required by this procedure.

2. RETURN for revision or REVISE the C/O Checklist if discrepancies are identified.

3. APPROVE the C/O Checklist.

8.2.3. The C/O Challenge MUST be performed prior to C/O Checklist distribution and before work is added to an ACTIVE C/O. REFERENCE Attachment 7, C/O Challenge Guidelines as required, and DOCUMENT completion of review on Attachment 5, Clearance Preparation and Approval Checklist.

OP-AA-109-101 Revision 9 Page 32 of 86 8.2.4. REQUEST a walk down of the C/O to be performed using Attachment 6, Clearance Walkdown Sheet, for the following types of C/Os:

1. Refuel outage C/Os as determined by the Clearance Coordinator/Outage Planner.

2. C/Os involving work that places the plant in a shutdown condition of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or less.

3. C/Os where the work is scheduled to extend beyond the WC-AA-101, On-line Work Control Access, allowable LCO duration.

4. C/Os that result in Online Risk changing to Orange or Red.

5. Other C/O types as requested by the Clearance Coordinator or Operations Management.

8.3. Development and Approval of Subsequent Checklist 8.3.1. The C/O Writer/Preparer shall approve the subsequent Checklists using Attachment 5, Clearance Preparation/Approval Checklist as a guide.

8.3.2. The C/O Approver shall approve the subsequent Checklists using Attachment 5, Clearance Preparation/Approval Checklist as a guide.

9. CLEARANCE WORK ADDITION/WORK SCOPE MODIFICATION NOTE: Work Addition and approval must be performed to the same level of review as the original C/O.

9.1. Adding a Work Order (W/O) Task or a C/R to an Existing C/O 9.1.1. The Clearance Group or qualified Operations personnel shall perform the following:

1. REVIEW the work to be performed and IDENTIFY an existing C/O that is adequate for the work scope.

NOTE: For ACTIVE C/Os (i.e., tags are hanging) the C/O Challenge and both approvals must be performed before the Approver initiates the scope change in Passport. This will prevent anyone from starting work before the C/O Approval and Challenge are completed.

2. INITIATE scope change.

3. ADD the C/R and W/O Tasks to C/O.

OP-AA-109-101 Revision 9 Page 33 of 86

4. PERFORM reviews and approvals.

A. Writer/Preparer reviews and approves scope change in Passport and documents approval on Attachment 5, Clearance Preparation/Approval Checklist.

B. Approver reviews and approves scope change and documents approval on Attachment 5, Clearance Preparation/Approval Checklist.

C. PERFORM a C/O Challenge using Attachment 7, C/O Challenge as a guide and document completion on Attachment 5, Clearance Preparation/Approval Checklist.

9.2. Removing a Work Order (W/O) Task or a C/R from an Existing C/O 9.2.1. The Clearance Group or qualified Operations personnel shall perform the following:

1. The Work Week Manager, Outage Coordinators, or Work Group Lead should CONTACT the Clearance Coordinator or Operations Supervisor to have the W/O task removed from the C/O.

2. VERIFY the W/O Task status is set to Suspend. If W/O task status is working, HAVE cognizant Work Group set to Suspend.

3. INITIATE a Scope Change.

4. DELETE W/O Tasks/Clearance Requests from the existing C/O and APPROVE the Scope Change. DOCUMENT removal reason on Route List Notes.

5. RESTORE W/O task status to the as found status.

9.3. Modifying Work Instructions/Scope of a W/O attached to an active C/O 9.3.1. The Clearance Group or qualified Operations personnel shall perform the following:

1. The Work Planner or Work Supervisor will contact the Clearance Coordinator or Operations Supervisor. Nature of the revision will be discussed in detail to determine:

A. If revision of the C/O will be necessary or if other work attached to the C/O will be affected, then the Cognizant Operations Supervisor will ensure:

1. The C/O is modified as needed.

2. The C/O is placed in SUSPEND status or Holder Acceptance Lock is applied if needed to prevent continued or new work as appropriate.

OP-AA-109-101 Revision 9 Page 34 of 86

10. AUTHORIZING AND PERFORMING CLEARANCE MANIPULATIONS 10.1. Clearance Placement Standards 10.1.1. Any changes to a C/O should be documented electronically to maintain configuration control.

10.1.2. Return to service position changes require review by two qualified individuals (RO or SRO).

10.1.3. Exceptions are allowed for the following, which may be pen/ink changes reviewed and initialed by Shift Management prior to executing change.

1. Sequence changes.

2. Minor description/location changes.

3. Information items that do not affect the zone of protection.

10.1.4. If a C/O cannot be completed as written, then the equipment shall be placed in a safe condition and Shift Management notified.

10.1.5. C/O Tags will be securely fastened to all points of isolation when possible with a non-reusable nylon cable tie with a minimum unlocking strength of 50 pounds for regular size Tags.

1. ATTACH the Tag directly to the component if possible. Tape, string, or other suitable methods of attachment may be used when a cable tie is not practical.

2. When attachment is not possible, then the Tag will be attached in a highly visible location near the equipment to alert all personnel of tagout conditions.

10.1.6. If C/O Tags will remain inside of Containment (Primary Containment) after Containment closeout or during power Operation, then they may be replaced by stainless steel C/O Tags attached with stainless steel straps, unless evaluated and approved by Engineering.

10.1.7. If the isolation component has been designed to accept a locking device, then the C/O Tag will be attached at the locking point in the same manner that a locking device would be attached if accessible.

OP-AA-109-101 Revision 9 Page 35 of 86 10.1.8. Normally qualified Operations personnel operate plant systems or equipment for C/O manipulations. The following are examples of exceptions to this practice:

EXAMPLES OF NON-OPERATIONS C/O MANIPULATIONS:

Instrument Mechanic installing and removing a pneumatic jumper Electrician lifting/landing an electrical lead or installing grounds Mechanic installing and removing a block or gag FM personnel manipulating non-plant/non power block equipment for their WTOs When non-Operations personnel assist with equipment manipulations for C/O activities, the sign offs on the Clearance will record the operators who placed the tags.

10.1.9. When systems or components are tagged that require draining, then the C/O shall not be electronically released for work until after the draining is verified complete or adequate for the work to be performed. If boundary has not been drained, then DOCUMENT details in the C/O Special Instructions and screen C/O for exceptional status.

10.1.10. If the equipment information on a C/O Tag does not match the equipment label such that there is reasonable doubt of the identity of the equipment, then Shift Management shall be contacted to make a final determination if the C/O Tag should be placed or not.

1. Data revision should be initiated.

2. If a labeling discrepancy is identified, then INITIATE a labeling change request.

10.1.11. For Mode or Condition Dependant C/Os, the Operations Clearance Prejob Brief will discuss the following as listed in the C/O Special Instructions.

1. Basis for using this type of C/O.

2. Dependent condition to be maintained or procedure governing the condition.

10.1.12. A Condition Dependent C/O shall not be taken to the ACTIVE status until the applicable condition has been verified and is being maintained and must be released prior to allowing the condition to leave the established status or range specified in the C/O. If the condition is being controlled under the direction of a governing procedure (e.g., Reactor Head Disassembly/Reassembly), then these status and Holder accept/release activities are not required.

10.1.13. A Mode Dependent C/O shall not be taken to the ACTIVE status until the applicable plant mode has been verified. Plant procedures shall not allow the plant mode to change to an undesirable mode until all applicable mode dependent C/Os have been verified cleared or acceptable.

OP-AA-109-101 Revision 9 Page 36 of 86 10.1.14. Before placing a Mode Dependent or Condition Dependent C/O, the Operations Clearance Prejob Brief will discuss the following as listed in the C/O Special Instructions. If the condition is being controlled under the direction of a governing procedure (e.g., Reactor Head Disassembly/Reassembly), then the briefings are not required to be repeated for each condition change.

1. Basis for using this type of C/O.

2. Dependent condition to be maintained or procedure governing the condition.

10.1.15. When modifying a Distributed checklist, steps for tags that have been placed should be completed in Passport prior to modifying the checklist.

10.1.16. When resetting the status of multiple Distributed checklists to change the C/O that owns the HANG Action(s), all C/Os sharing steps must be Returned/Modified, and then reset to Distributed in the correct order. This should be performed in a timely manner, especially when tags have been placed.

10.2. Restoration Standards 10.2.1. If a lift position is determined to be different from the normal lineup position for the present plant condition and not tracked by another C/O or procedure, then Shift Management shall be notified and equipment tracking initiated.

10.2.2. If there is reason to believe that uncontrolled manipulations of equipment within the C/O boundary may have occurred, or if deemed necessary by Shift Management, then a system lineup checklist or equivalent shall be performed on systems or components with the zone of protection being returned to service.

10.2.3. Consideration should be given to initiate tracking of equipment that is to be returned to service and not considered operable due to testing requirements.

10.2.4. Prior to physically removing C/O Tags a visual inspection of the principal equipment should be performed. The inspection should include:

1. System Integrity

2. Proper Lubrication

3. Valve/breaker alignment

4. Removal of Grounds

5. Equipment Cleanliness 10.2.5. For return to service purposes, Information Tagged and applicable Not Tagged Items shall be handled as tagged items (i.e., sequencing, return to service positions, and appropriate signoffs).

OP-AA-109-101 Revision 9 Page 37 of 86 10.3. Clearance Authorization 10.3.1. The Authorizer shall perform the following using Attachment 8, Clearance Authorization Checklist.

1. REVIEW the comments/Special Instructions for applicable information.

2. REVIEW the C/O for plant/conditions impact prior to authorizing execution of the C/O.

3. REVIEW THE C/O for redundant train or other unit operability concerns/impact.

4. VERIFY any required testing is completed, prior to performing the clearance activity in order to comply with requirements, e.g., Tech Spec requirements.

5. VERIFY applicable procedure prerequisites are satisfied.

6. VERIFY Tech Spec Limiting Conditions for Operation (LCO) and any administrative requirements are declared or closed out and properly documented as applicable.

7. CHECK that the risk potentials and Reactivity/Operational/Atmospheric/

Environmental Risk critical steps are correctly identified and required mitigating actions performed appropriately.

8. VERIFY On-line Risk, Shutdown Risk and any applicable databases are updated as required.

9. DETERMINE if the risk associated with the equipment manipulations required by the C/O require application of the HLA process and INITIATE THE HLA process if required.

10. VERIFY Fire Protection and Barrier Breach required actions initiated/secured.

11. TAKE the C/O Checklists to Distributed status and assemble Checklist paper copy and tags. The C/O Checklist shall be either the Master or a Duplicate, not a Review.

12. DESIGNATE on the C/O Checklist what type of verification shall be used (CV or IV) per the verification procedure if applicable.

13. INITIAL or SIGN the Checklist to record authorization of the C/O Checklist execution.

14. ASSIGN the C/O to be performed.

OP-AA-109-101 Revision 9 Page 38 of 86

15. For lift activities, in addition to the steps above, PERFORM the following:

A. VERIFY that all attached work is at the proper status for the lift activity.

If attached W/O are < status 48 (working), then the holder providing final release SHALL enter the reason why the clearance protection is no longer required on the Holder Notes Panel in Passport.

B. SPECIFY the principle equipment positioning and lift inspection requirements on the C/O work order task page for each work order task.

C. VERIFY that the applicable Post Maintenance Test (PMTs) are coordinated with Partial and Final Clear Checklists if desired.

D. INCLUDE any applicable valve and equipment lineup checklists with the lift activity.

E. VERIFY no WTLs in use by reviewing Contacts Panel.

F. VERIFY all Supervisors and Lead Workers have released the C/O.

10.4. Executing Clearance Checklists 10.4.1. The following shall be performed using the C/O Checklist and a copy of the Attachment 10, Clearance Manipulation Prejob Brief Checklist.

1. C/O Placement Activities:

NOTE: Tag plus devices to be used will be identified by the dispatching Supervisor during C/O placement Pre-job brief.

A. PARTICIPATE in the C/O prejob brief where all questions and issues will be resolved or addressed.

B. NOTIFY Radwaste prior to draining significant amounts of fluids from systems that could affect waste processing.

C. Prior to performing any equipment manipulations, INFORM the affected Reactor Operator or dispatching Facility of the planned C/O.

D. EXECUTE the C/O Checklist actions with Checklist in hand:

1. FOLLOW all actions as instructed during the C/O prejob brief.

2. FOLLOW the proper sequence specified.

3. PLACE equipment in the positions/conditions specified.

4. PLACE C/O Tags as required.

5. INSTALL Tags Plus Devices or implement the methodology to be used as discussed in the prejob brief.

OP-AA-109-101 Revision 9 Page 39 of 86 E. REVIEW/UPDATE Tag placement status after all steps are performed.

F. NOTIFY the Shift Management placement steps are complete and any difficulties encountered.

G. STATUS C/O ready for work electronically.

H. FILE the C/O documents appropriately.

2. C/O Removal Activities:

A. VERIFY no active WTLs by reviewing the C/O Contacts Panel.

B. VERIFY the C/O is released electronically and attached W/Os are complete. For W/Os that are open, INVESTIGATE reason and DETERMINE if it is acceptable to remove the C/O with the work at the current status. This information can be found on the T214 Holders Panel Notes or the T313 Holders History Panel in the notes.

C. PARTICIPATE in the C/O prejob brief where all questions and issues will be resolved or addressed.

D. INFORM the affected Reactor Operator or dispatching Facility of the planned C/O manipulation prior to performing any equipment manipulations.

E. EXECUTE the C/O Checklist actions:

1. FOLLOW all actions as instructed during the C/O prejob brief.

2. PEFORM the pre-lift visual inspection of the equipment that was worked on for proper housekeeping and equipment condition (OP-AA-108-106 Equipment Return to Service).

3. FOLLOW the proper sequence specified on the C/O checklist.

4. LIFT C/O Tags as required and remove Tags Plus devices that were installed.

5. PLACE equipment in the positions/conditions specified on the C/O Checklist.

6. ACCOUNT for removed Tags.

F. REVIEW/UPDATE Tag removal status after applicable steps are performed.

G. NOTIFY the Shift Management removal steps are complete and any difficulties encountered.

H. COMPLETE the C/O electronically.

I. If C/O Tags have been hung or rehung, then SET C/O to ACTIVE status.

OP-AA-109-101 Revision 9 Page 40 of 86 10.4.2. PERFORM any post C/O manipulation activities required per Attachment 8, Clearance Authorization Checklist.

1. ENSURE/DIRECT the performance of any required Boundary Verification.

2. FOLLOW UP on any issues identified during the C/O manipulation.

3. NOTIFY working group or testing group as appropriate.

4. COMPLETE any Tech Spec related actions or compensatory actions as required.

5. ENSURE that the C/O activity is logged appropriately.

6. ENSURE that any handwritten notes found on the original C/O hardcopy are entered in the database as appropriate.

7. STATUS C/O appropriately and FILE the C/O documents as required.

11. PERFORMING WORK UNDER CLEARANCE PROTECTION NOTE: Attachment 11, Supervision Clearance Acceptance/Release Checklist, Attachment 12, Lead Worker Clearance Checklist, and Attachment 13, Worker Clearance Checklist (only if a General Worker is on the job), are required to be completed during C/O accept and release activities but are not required to be retained as quality records after work is complete. COMPLETE only one of each applicable type for each crew. Not required for WTO activities.

11.1. Clearance Accepting and Releasing Standards 11.1.1. All appropriately qualified Exelon employees and specifically designated non-Exelon employees will electronically ACCEPT (sign-on) and RELEASE (sign-off) required C/Os daily. The exception to this is Supervision who may remain signed on to the C/O for the duration of the work to ensure boundary changes have not occurred without their knowledge.

1. Workers using ESO should always enter a release reason of FC, regardless of the type of checklist.

2. Supervision should enter either TL, PC, or FC for the release reason, as required.

11.1.2. Visitors performing work under the protection of a Clearance Order must attend the pre-job brief for the work, sign on to the WTL, and be supervised by a qualified CO Holder or Lead Worker while in the Zone of Protection.

OP-AA-109-101 Revision 9 Page 41 of 86 11.1.3. During a Temp Lift or Partial Clear work on WOs tied to the C/O may not continue, since the zone of protection is removed. Testing facilitated by the TL may occur per work instructions, with a WO task, or testing procedure. Work attached to the C/O may continue after the Temp Lift is rehung, or the zone of protection is verified for the work that remains tied electronically after the Partial Clear is complete.

11.1.4. Exelon personnel and Supplemental Workers performing work observations, inspections, or measurements who break the plane of a clearance boundary will sign-on a hardcopy WTL per this section if they are not ESO qualified, but have received NGET which contains C&T General Awareness Training. These personnel are classified as General Workers for the purposes of this procedure.

11.1.5. If the computer program is not available, then a hardcopy WTL should be utilized for all qualified employees. An Operations Supervisor shall control these with the master copy of the C/O until the computer is restored.

11.1.6. Contract employees normally will sign on and off required C/Os via a WTL (Attachment 9) unless qualified to use ESO.

11.1.7. When a WTL is used by General Workers, the following must be performed:

1. Two unique Holders, one of which may be a qualified Lead Worker must electronically sign on to the C/O whenever a WTL is used. These individuals cannot release the C/O for each other.

2. A responsible Holder must electronically ACCEPT each C/O required for protection.

3. An individual (qualified as C&T Lead Worker) must electronically ACCEPT each C/O required for protection. This acceptance may be one time or once for each specific W/O task if desired by the Work Group.

4. It is recommended a screen print be made of the Holders panel at this point to demonstrate to the employees electronic sign-on did occur by their Holder.

5. The C&T Lead Worker will enter their own name on the Contacts Panel of each C/O and indicate that they are signed on for WTL Control (these actions are only required once per C/O for multiple WTLs).

6. The Lead Worker must CONTROL WTLs for their designated work group at an appropriate location (preferably in a binder, notebook, or file with a specific section or tab for each C/O).

7. All Employees not electronically signing on must sign their name on a WTL (Attachment 9) for each C/O required for their work. The C/O number and associated W/O number(s) will be listed on the WTL for tracking purposes.

OP-AA-109-101 Revision 9 Page 42 of 86

8. If WTLs are temporarily removed from the designated location to collect signatures, then PLACE an out card to indicate who removed the WTL and PREVENT the C/O from being released. The WTL can only be removed by someone signed on to it, to ensure safety is not compromised.

9. When all WTLs are completed and the C/O is no longer required for employee protection, the Lead Worker signed on for WTL control shall delete only their entry on the Contacts Panel in Passport and electronically sign off the C/O.

10. The expectation is to sign off WTLs prior to leaving the facility each day unless otherwise directed. The Supervisor and Lead Worker signing on electronically for WTL control should remain signed on for the duration of the work.

11. For work groups that do not have electronic sign on qualified personnel, cognizant Exelon Supervision and C&T Lead Workers can fulfill these functions.

11.1.8. A W/O task/activity requiring C/O protection must be tied to ALL necessary C/Os.

11.1.9. If a W/O is tied to a C/O or C/Os, then acceptance and releasing standards are to be applied to ALL associated C/Os.

11.1.10. No work that is directly under the protection of a C/O will start until all required C/Os have been accepted. Activities associated with the W/Os such as staging, set-up, and in-shop work that do not require protection from the C/O may be performed without the C/O being hung and without performing C/O acceptance.

11.1.11. Until the C/O has been accepted, Operations retains control of the equipment and the associated C/O.

11.1.12. Only qualified Operations personnel are permitted to manipulate components to verify position. However, non-Operations personnel may assist in establishing or improving isolation under Operations direction.

11.1.13. The on-duty Shift Manager may release for all departments under the requirements of this procedure, if there is a plant emergency.

11.1.14. No work may be performed on blocked or gagged equipment that may affect the block/gags ability to maintain isolation capabilities of the component.

11.1.15. When a C/O has been hung to control a hazard associated with entry into a work area (e.g., Traversing Incore Probes for Drywell entry, Movable Incore Detectors for Containment entry, etc.) as directed by an approved procedure that establishes and maintains safe environmental conditions in the area (e.g. Drywell Entry Procedure, Containment entry Procedure, etc.), work will not be tied to the C/O, and acceptance and releasing standards do not apply.

OP-AA-109-101 Revision 9 Page 43 of 86 NOTE: With proper Authorization, the Safety Verification walk down may be performed by the work group at the same time the C/O or Worker Tagout is being hung. Acceptance and verification of this walk down against what Tags are physically placed must still be performed prior to work start.

11.1.16. The Supervision is responsible to ENSURE a safety verification walk down of the required isolation points occurs.

11.1.17. If a walk down is not possible, alternate means may also be utilized to determine proper system isolation. These could include control power lights extinguished, drains no longer flowing fluid, piping for hot systems cold, observation via remote means such as an ALARA camera, pressure gauges reading zero (examples provided in this list are not all inclusive, and all items on list do not have to be checked).

11.1.18. Before starting work on equipment that has been tagged out, the Holder shall verify isolation and/or deenergizing of the equipment has been accomplished. If normally energized parts will be exposed to contact by an employee while the equipment is deenergized, a test shall be performed to ensure that these parts are deenergized (Test Before Touch).

11.1.19. If the Employee (Lead Worker or General Worker) is not on site and the C/O must be released, then the Supervision releasing the C/O shall perform the following:

1. Try to contact the employee by phone or other means. If the employee cannot be contacted, STOP here and continue with step 2. If the employee is contacted successfully, perform the following 2 steps.

A. DOCUMENT the employees permission to release them from the electronic sign-on using the holders panel in Passport or if applicable on the paper WTL.

B. INITIATE an Issue Report documenting the circumstances as to why the employee did not release themselves from the C/O..

2. VERIFY that the employee is not at the facility. If working outside of the Protected Area, then they must be contacted by phone or in person, or verified not in the work area prior to releasing the C/O. COMPLETE the actions listed in Attachment 15, Documentation for Release of Another Employees C/O Protection.

3. RECORD the absence of the employee on the C/O Holders Panel in the notes or on the paper WTL. INITIATE an Issue Report documenting the circumstances as to why the employee did not release themselves from the C/O.

4. If applicable, REMOVE the employees name from the WTO Tracking List Tag by single line out, initial, date.

5. ENSURE that the employee is notified of electronic release before they resume work at the facility. FORWARD the completed Attachment 15 to the site Clearance Coordinator in Operations for trending.

OP-AA-109-101 Revision 9 Page 44 of 86 11.1.20. If an employee is on site they are required to sign off the C/O or WTO themselves.

Extenuating circumstances such as an injury requiring medical attention or radiological issues may require a Supervisor to follow the same process to sign the worker off, as if they are offsite. This allowance is not intended for schedule convenience and should be used sparingly with Operations approval. Document the circumstances in an IR for each occurrence to allow trending as a Level 4 C&T IR.

11.1.21. Supervisors not actually performing work under protection of a C/O may be released by other Supervisors when work is completed to facilitate system restoration or test runs. This should be discussed at turnover between the cognizant supervisors.

11.1.22. When W/O tasks attached to a C/O are rescheduled such that they will not be worked under the C/O, then the Working Group Supervisor shall ensure that the work is to a point that the C/O may be cleared and the W/O Tasks are properly statused.

11.1.23. W/O Tasks may be attached to multiple C/Os that are not all required to be in the ACTIVE status to start work. This will occur when contingency C/Os are preplanned or when C/Os are written to facilitate different stages of tasks with broad scopes of work.

11.1.24. If there are uncertainties over which C/Os must be accepted, then Operations must be consulted for direction.

11.1.25. Steps listed on the boundary report that are not part of the zone of protection are not required to be verified and may be N/Ad. (Example: control switches that do not provide isolation).

11.1.26. If an individual is unable to release the C/O, then it is the responsibility of Supervision from the same department with knowledge of the work to release the C/O per the requirements of this procedure.

11.1.27. Prior to releasing a C/O to support a Partial Clear or Dual Function Checklist, all Holders must understand how the boundaries will change and any system dynamics such as valving in a section of piping that was previously drained. It is the responsibility of the Supervision requesting the release to explain the boundary change and obtain concurrence.

11.1.28. Before work is started under a Mode Dependent or Condition Dependent C/O, the Maintenance Prejob Brief will discuss the following as listed in the C/O Special Instructions. If the condition is being controlled under the direction of a governing procedure (e.g., Reactor Head Disassembly/Reassembly), then the briefings are not required to be repeated for each condition change.

1. Basis for using this type of C/O.

2. Dependent condition to be maintained or procedure governing the condition.

OP-AA-109-101 Revision 9 Page 45 of 86 11.2. Supervision Clearance Activities 11.2.1. For crews performing physical work under the protection of a C/O, the supervision directly in charge of the personnel performing the work shall be signed on as a Holder.

For contract work crews, the Holder shall be the Supervisor in charge of the work crew or the contract area supervisor. Exelon Supervision may fulfill this function.

11.2.2. When Exelon Supervision is the Holder, and that person becomes the employee doing work (example Operational Analysis personnel), no additional Holders are required to sign on to fulfill the requirements of this procedure.

11.2.3. To direct work under C/O protection, the Supervision shall perform the following (Attachment 11, Supervisor Clearance Acceptance/Release Checklist shall be used):

1. IDENTIFY all proper C/Os (may be multiple) to provide protection for the work.

2. VERIFY that the applicable work order tasks are attached to the proper C/Os.

3. ADD their own USERID to Holder panel FOR ALL NECESSARY C/Os, if not already listed.

4. ACCEPT the C/O to prevent the removal of C/O Tags during performance of the Safety Verification.

NOTE: The work group may perform the Safety Verification at the same time the Clearance/Worker Tagout is being placed. A copy of the FH checklist or WTO can be substituted for the Boundary Report. The Boundary Report must still be verified against the FH checklist used to perform the verification and signed off after the C/O has been placed.

11.2.4. PREPARE or ENSURE that a Clearance Order Boundary Report is properly prepared.

11.2.5. ENSURE that the following are performed:

1. A proper prejob brief is performed including a discussion of work hazards, a discussion of Special Instructions including Exceptional details. (This can be a reverse style brief with the crew.)

2. All employees ACCEPT the C/O or sign-on the WTL as applicable.

3. Boundary report is used to walk down required isolations by a representative of the work group prior to starting work.

OP-AA-109-101 Revision 9 Page 46 of 86 11.2.6. The Supervision releasing a C/O for Temp Lift, Final Clear or Partial Clear shall perform the following (reference Attachment 11, Supervisor Clearance Acceptance/Release Checklist):

1. ENSURE that the equipment, as pertains to their scope of work is:

A. In a condition that can support the requested testing prior to release.

B. Cleared of personnel C. Cleared of obstructions D. Cleared of grounding devices if applicable

2. When releasing for Final Clear, then Supervision shall ENSURE that their specific work is complete and correctly statused for the applicable condition of the work.

A. If attached Work Orders are < status 48 (working), then the Holder providing final release SHALL enter the WO number, task, and reason why the clearance protection is no longer required on the Holder Notes Panel in Passport or Holders History Panel if the Holder Notes Panel is no longer open for editing, in Passport.

B. If the Holder had previously released with a release reason other than FC and all tags are lifted, then the Holder providing final release SHALL document the release on the Holders History Panel in Passport.

3. VERIFY all employees electronically released or signed off WTLs and associated WTL entries on Contacts Panel are deleted.

4. RELEASE the C/O.

11.2.7. Executing/Releasing Holder Acceptance Lock

1. The Supervisor applying the Holder Acceptance Lock will:

A. APPLY holder acceptance lock.

B. VERIFY that ALL required Supervisors and Employees have electronically released the C/O.

C. MODIFY C/O as required.

D. PERFORM required work steps and testing.

2. If a Temp Lift or other boundary manipulation was performed, then VERIFY with an Operations Supervisor the COMPLETION of necessary Checklist to establish a safe working boundary.

3. REMOVE THE Holders Acceptance Lock. If the Supervisor that imposed the Holder Acceptance Lock is not on site and the C/O must be released, then the Supervisor releasing the Lock shall determine that all required isolation points have been rehung to establish the necessary zone of protection for all attached work prior to releasing.

OP-AA-109-101 Revision 9 Page 47 of 86 11.3. Lead Worker Clearance Activities (ESO Qualified) 11.3.1. To start work under C/O protection, each crew shall perform the following (Attachment 12, Lead Worker Clearance Checklist, shall be used). In the case of contractors, the designated Lead Worker should perform these actions:

1. VERIFY Supervision sign-on as holder (Passport, screen prints). This prevents C/O modification.

2. PARTICIPATE in, or ENSURE a designee conducts the prejob brief as directed by Supervision where a discussion of hazards and protection provided by the C/O will take place.

3. PERFORM, have a designee perform, or VERIFY a Safety Verification has been performed by another crew or crewmember for the applicable C/O boundaries. (Each crew or crewmember does not have to perform a safety verification if another crew already performed one.)

4. VERIFY applicable work order tasks are electronically attached to the proper C/Os. This can be done by using screen prints or direct viewing at a computer.

5. ACCEPT the C/O electronically or sign on to a WTL.

6. If accepting as the individual responsible for a WTL, VERIFY the required actions are performed per step 11.1.7.

7. PERFORM work.

8. At least one crewmember DOCUMENT the as-found position (and another crewmember provides independent verification that the component was restored to the as-found position) of manipulations of untagged components within the C/O boundary in an approved procedure or process.

NOTE: For purposes of the following step, 'stop work' is meant to apply only to situations when there are no immediate plans for an individual to return to a specific task under the C/O.

9. When employees stop work under C/O protection, the Lead Worker shall PERFORM the following:

A. At least one crewmember, NOTIFY Supervision work has stopped.

B. RELEASE C/O or sign off WTL.

OP-AA-109-101 Revision 9 Page 48 of 86 11.3.2. To restart work that was stopped under C/O protection, each crew shall perform the following (Attachment 12, Lead Worker Clearance Checklist, shall be used). The designated Lead Worker should perform these actions:

1. VERIFY each new day of work that the Supervisions Electronic acceptance remains in place since the last time work was performed and that no boundary changes were made. (This can be verified by viewing the C/O, discussing the status with the cognizant Supervision, or using screen prints of the applicable screens).

2. ACCEPT C/O or sign on WTL.

3. PERFORM, or have a designee PERFORM, or VERIFY another crew or crewmember performed a Safety Verification if any required boundaries changed. (Each crew or crewmember does not have to perform a Safety Verification if another crew already performed one.)

4. VERIFY work order tasks remain attached to the C/O.

5. ENSURE new crewmembers receive a Brief.

6. RESTART work.

11.4. General Worker Clearance Activities (Not ESO Qualified) 11.4.1. To start work under C/O protection, General Workers, who can be Exelon or non-Exelon employees who are not ESO qualified, shall perform the following (Attachment 13, General Workers Clearance Checklist, at least one per crew, shall be used):

1. PARTICIPATE in prejob brief, which should provide information in regards to Work Group holder signed-on to C/O, and Safety Verification walk down status.

2. SIGN ON to a WTL and VERIFY with Supervision requirements of 11.1.6 have been satisfied.

3. PERFORM work.

4. When done with work for the day, SIGN OFF the WTL.

5. To restart work each new day, PERFORM Steps 11.4.1.1 through 11.4.1.3.

OP-AA-109-101 Revision 9 Page 49 of 86

12. TEMP LIFTS AND PARTIAL CLEARS 12.1. Requesting Temp Lifts and Partial Clears 12.1.1. The requesting Supervision or Operations personnel shall perform the following:

1. CONTACT and COORDINATE with all affected Supervision on this C/O and affected C/Os to discuss the impact on all work attached to the C/O. During a Temp Lift or Partial Clear, work on WOs tied to the C/O may not continue, as the zone of protection may be removed.

NOTE: Supervision should not release for TL or PC until the checklist is approved if they wish to verify that only the steps allowed to be lifted are listed on the checklist.

2. NOTIFY all Holders to release (sign-off) for TL, PC, or FC. In addition, NOTIFY personnel listed on the Contacts Panel to have WTL tracked employees sign-off, release for FC, and remove their information from the contacts panel.

3. CREATE the required Checklist providing the following information (C/O tags can be hung and lifted at the same time on a PC Checklist).

A. LIST the equipment to be lifted/hung and PROVIDE the following information on the checklist notes panel:

B. Reason for the Hang/Lift C. When the Hang/Lift is required D. Who to contact when the Hang/Lift is complete E. Expected duration if a TL F. Any special instructions or conditions needed

4. INFORM the Clearance Coordinator or Operating Shift Management of the need for Hang/Lift.

5. Operations should review the checklist submitted and make required modifications in accordance with Clearance Checklist development and approval standards, prior to approving the submission.

OP-AA-109-101 Revision 9 Page 50 of 86 12.2. Executing Temp Lifts and Partial Clears 12.2.1. Operations personnel will perform the following:

1. VERIFY that ALL Supervision and employees have electronically released the C/O.

2. If performing a Temp Lift, APPLY the Holders Acceptance Lock or SET the status of the C/O to SUSPEND to prevent released or new Supervision from resuming work until the required tags have been rehung.

A. If all tags are lifted and the status of the C/O goes to AWT/CLOS, then applying the Holders Lock or setting the status of the C/O to SUSPEND is not required.

3. EXECUTE Checklists per Section 10.4, Executing Clearance Checklists.

4. If a Temp Lift was performed, COMPLETE a Rehang Checklist to establish a safe working boundary, and SET the status of the C/O to ACTIVE, or REMOVE the Holders Acceptance Lock. NOTIFY working group(s) as applicable.

5. If a Rehang is not required for the remaining work, then SET the status of the C/O to ACTIVE, or REMOVE the Holders Acceptance Lock. NOTIFY working group(s) as applicable.

6. If components are left in an abnormal position after a Temp Lift Checklist, then CONSIDER ADDING Not Tagged steps to a FC Checklist to ensure proper system alignment during Final Clear.

7. Additional TL or PC checklists may be performed with authorization from Holders that originally released for TL or PC.

13. WORKER TAGOUT (WTO) PROCESS 13.1. Purpose 13.1.1. To establish a process that provides personnel protection that may be used in place of electronic tagging processes.

13.1.2. Also establishes a process that is available for use when the electronic process is not available (i.e., Network outage) and tagging is required to maintain safety for personnel and or plant equipment.

13.1.3. The same standards apply for technical rigor in development, reviews, authorization and field application that apply to the electronic process.

13.2. Scope 13.2.1. The process is designed to support work activities that are of limited scope and duration with a limited number of isolation points.

13.2.2. The WTO process may be used at request of Working Group with Operations approval.

OP-AA-109-101 Revision 9 Page 51 of 86 13.3. Administrative Requirements 13.3.1. Placed WTOs may remain in place for the duration of the work.

13.3.2. MAINTAIN a log of WTO transactions. An electronic database may be used versus hard copy Log (Attachment 14 Part 5, Worker Tagout Log).

13.3.3. The WTO process uses the same Danger and Information Tags as the Clearance and Tagging process.

13.3.4. The requester or Operations shall complete Attachment 14, Worker Tagout Form, Parts 1 through 6, as applicable. Operations shall review and approve the WTO using Attachment 5, Clearance Preparation/Approval Checklist and document approval in the WTO checklist signature blocks.

13.3.5. Worker Tagout tags shall contain the following information:

1. Equipment Tag number and name

2. Required Component position/condition

3. Worker Tagout number 13.3.6. WTO Tracking List Tags (shown in Attachment 14 Part 6) shall contain the following information.

1. A header stating WTO Tracking List Tag (all workers on WTL sign here)

2. WTO #

3. Date hung

4. Department

5. Signature of ALL workers under the protection of the WTO.

13.3.7. If the Shift Manager determines that the WTO must be removed to support operational needs, then the Shift Manager may order the removal of any WTO under the requirements of this procedure.

13.3.8. The original copy of the WTO once Placed, will normally be in the possession of the Work Group designee when actively performing work protected by the WTO. This will assure the zone of protection remains in place during the work.

13.3.9. When Work is stopped (other than routine breaks) and at the end of each shift, the WTO will be returned to Operations Shift Management.

13.3.10. A copy of the WTO should be maintained in a WTO Log Book unless an electronic log/database is being maintained. The purpose of this copy is as a back-up in the event the Master Copy is lost, contaminated, or destroyed. Therefore, the Copy or electronic database will be updated to remain current. This will allow use of the copy in the event the original is lost, contaminated, or destroyed.

OP-AA-109-101 Revision 9 Page 52 of 86 13.4. Performing a Worker Tagout NOTE: Attachments 11, 12, and 13 of this procedure are not intended for use with WTOs. They are for use with Passport C/Os.

1. PERFORM the WTO Checklist steps and verifications as required.

2. RECORD time and date placed in the WTO Log.

3. The assigned Employee shall:

A. PARTICIPATE IN or LEAD the prejob brief where a discussion of hazards and protection provided by the WTO will take place.

B. VERIFY that their W/O tasks are attached to the WTO.

C. SIGN ON the WTO by completing Attachment 14 Part 4, WTO Worker Tracking List. COMPLETE only one copy (usually the WTL provided in the WTO package).

D. VERIFY crewmembers have signed on to Attachment 14 Part 4, WTO Worker Tracking List.

E. PERFORM the Safety Verification or VERIFY that a Safety Verification has been performed for the applicable WTO boundaries.

4. The Designated Crewmember shall:

A. HANG a completed WTO Tracking List Tag on the applicable main isolation point for the WTO B. DOCUMENT tag placed for each worker on Attachment 14, Part 4, WTO Worker Tracking List. A second tag may be used for dual feed components if desired.

C. SIGN for WTL Completed Work Start on Attachment 14, Part 1.

5. PERFORM work.

6. If all work is complete or prior to leaving for the day, then the Designated Crewmember shall :

A. VERIFY all crewmembers have signed off of Attachment 14 Part 4, WTO Worker Tracking List.

B. SIGN the bottom of Attachment 14, Part 4.

C. REMOVE the WTO Tracking List Tag(s).

D. DOCUMENT tag removal on Attachment 14, Part 4, for each worker.

E. If all attached Work on WTO is complete, then RELEASE WTO for Final Clear on Attachment 14 Part 1.

7. If work is to continue or new work is to be performed by a different crew, then the oncoming crew shall PERFORM all applicable actions of section 13.4.

OP-AA-109-101 Revision 9 Page 53 of 86 13.5. Performing WTO Manipulations 13.5.1. Shift Management will REVIEW, then APPROVE or DENY the manipulation requests.

13.5.2. Designated work crewmembers will sign off Attachment 14 Part 4, releasing the WTO for the manipulation after WTO Tracking List Tag has been removed.

13.5.3. VERIFY Attachment 14 Part 4, WTO Worker Tracking List (WTL), has been signed off releasing the WTO for the manipulation. A new WTO Worker Tracking List may be started, as needed.

13.5.4. Qualified personnel will PERFORM manipulations as necessary and within the requirements specified on Attachment 14 Part 3.

13.5.5. If additional work is required, the Working Group will REQUEST rehang of the WTO and ensure the employees are briefed if the conditions changed as a result of the manipulations performed.

13.5.6. PERFORM all applicable actions of section 13.4.

13.6. Clearing the WTO 13.6.1. VERIFY all WTO Tracking List Tags are documented as removed on Attachment 14, Part 4 and all crewmembers have signed off, releasing the WTO to be cleared..

13.6.2. VERIFY the Designated Crewmember has signed off Attachment 14, Parts 1 and 4 releasing the WTO for final clear.

13.6.3. PERFORM the WTO clear.

13.6.4. COMPLETE the WTO Log.

13.6.5. DISCARD the WTO tags.

13.6.6. FILE and RETAIN the completed WTO for six months.

OP-AA-109-101 Revision 9 Page 54 of 86 13.7. Facilities Maintenance (FM) Worker Tagout Process 13.7.1. This section describes a process in which Exelon FM personnel that are properly trained and qualified may prepare, review, approve, apply, manipulate, and remove their own Worker Tagouts.

13.7.2. The same standards apply for technical rigor in development, authorization, and field application that apply to the C&T process. Zones of protection must be safe and documentation accurate. Due to the limited scope and simple nature of the equipment, a WTO challenge is not required.

13.7.3. Preparation, Review, and Approval of FM WTOs will be documented via Attachment 4.

13.7.4. The same standards apply for tagging practices such as tags used, attachment methodology, and self-check practices. It is acceptable to create stickers that are placed on Exelon Danger tags, or the tags may be legibly handwritten with indelible black ink.

13.7.5. FM Worker Tagout tags shall contain the following information:

1. Equipment Tag number and name or Identifying Noun Name if not numbered

2. Required Component position/condition

3. FM Worker Tagout number 13.7.6. The application of WTOs for FM activities is normally limited to non-plant related equipment. Refer to Sites Matrix or listing for specific non-plant related equipment identification included in the FM program.

13.7.7. FM WTOs shall not be applied to Tech Spec, ODCM, or Power Block systems.

13.7.8. For FM WTOs the preparation and independent review is performed by FM technicians at that site using Attachment 4, FM WTO Preparation/Approval Checklist. The FM Supervisor authorizes the WTO for placement. If there is any question regarding appropriateness of isolation points or authorization for placement contact the on shift operating crew for assistance.

13.7.9. CONSIDER whether the work can be done without a WTO. Refer to Attachment 1, Activities That Do Not Require a Clearance.

13.7.10. When it is determined an FM WTO is required utilize the forms and tags shown in Attachment 14 to document isolation points, work details, sign on and off, special instructions, equipment manipulations for testing, and FM WTO log entries.

13.7.11. When Work is stopped (other than routine breaks) and at the end of each shift, the WTO will be returned to FM Supervisor.

OP-AA-109-101 Revision 9 Page 55 of 86 13.7.12. FM shall CREATE and MAINTAIN an up to date log for FM Worker Tagouts at each site. The WTOs shall be numbered in the following manner; FM-YYYY-ZZZZ, with YYYY being the year, and ZZZZ being a sequential number starting at 0001 each new year.

13.7.13. The scope of work shall be clearly IDENTIFIED and REFERENCED on the WTO.

13.7.14. To go to work each day the FM Technician does the following:

1. ATTEND a PJB with supervisor to discuss scope of work, WTO protection, and any required manipulations for testing.

2. OBTAIN approved FM WTO and proceed to field, hang WTO, and PERFORM work.

3. When work is complete, if authorized and required, PERFORM manipulations to conduct post maintenance test. Either rehang WTO for additional work or final clear if work is complete.

4. Return documentation to FM Supervisor.

14. EQUIPMENT TAGOUT PROGRAM PROBLEM RESPONSE NOTE: The Equipment Tagout Program Desk Top Instructions are an excellent source of program usage information. They are located in the Passport web page under Functional Area Documents.

14.1. When a problem is identified in the Equipment Tagout Program, then FOLLOW these steps:

14.1.1. CONTACT the Clearance Coordinator or other Site individual knowledgeable in the program for assistance.

14.1.2. WORK to determine the source of the problem.

1. REVIEW the history of the C/O with the problem to determine if a previous manipulation is causing the problem.

2. REVIEW the list of known bugs and work-arounds.

3. REVIEW the desktop instructions.

4. REVIEW the training materials.

14.1.3. If necessary, then CONTACT the site IT individual responsible for Passport support for assistance.

OP-AA-109-101 Revision 9 Page 56 of 86 14.2. If the problem cannot be resolved with resources identified above, then CLASSIFY and RESPOND to the problem as listed below.

14.2.1. Non-urgent problems

1. The Clearance Coordinator will REPORT non-urgent problems to the Passport support organization using the Test Director process.

14.2.2. Urgent problems

1. An urgent problem is one that prevents the performance of physical work at the site or that backs up the work preparation process to the point that scheduled work activities or major plant evolutions will be affected due to the problem.

2. There are usually no work-arounds for urgent problems or the work-arounds cannot be completed without significant delays in the sites work flow or scheduled activities.

3. REPORT urgent problems using the Help Desk reporting process.

A. STRESS the importance of the problem when calling it in to the Help Desk and ASK for immediate attention if required.

B. The Help Desk will Hot Page the program experts to investigate the problem if required.

4. CONTACT the Clearance Coordinators at the other Sites and Corporate Nuclear Duty Officer for all urgent program issues via email and or phone calls to make them aware of possible impacts on work at multiple sites.

14.2.3. New software bugs

1. The Clearance Coordinator will REVIEW the latest bug list to verify that the problem is not already identified and CONFIRM that a real bug exists by trying to repeat it the non-Production regions of Passport.

2. Then REPORT verified program bugs to the Passport support organization using the Test Director process.

OP-AA-109-101 Revision 9 Page 57 of 86 NOTE: It is not possible to cover all possible scenarios resulting in the inability to complete a Checklist. Therefore, the following is generic guidance only. ALL steps may not be required to resolve the problem or additional steps may be required that are not covered here. It is ultimately the responsibility of the Shift Management to determine the Scope of the problem and the recovery plan.

14.3. Hang Checklist Cannot be Completed 14.3.1. The Shift Management shall DETERMINE the scope of the problem and a recovery plan for the checklist.

1. If the problem is identified prior to electronically signing off steps in the Equipment Tagout program and no placed Tags will be removed, then the Checklist may be modified to correct the steps, and then taken back to Distributed.

2. UPDATE the original Checklist or TRANSFER hard copy Checklist signoffs from the original Checklist to the new Checklist for correct actions already taken.

3. ATTACH the original Checklist to the new Checklist as a record if necessary.

4. If the problem is on a First Hang Checklist and is identified after some electronic signoffs have been entered, but the problem includes only steps that have not been signed off in the Equipment Tagout Program and no placed Tags will be removed, then the Checklist may be modified to correct the steps not yet signed off.

A. ATTACH the original Checklist to the new Checklist as a record, or UPDATE the original Checklist.

WARNING NEVER REMOVE A C/O TAG FROM THE FIELD AFTER A STEP HAS BEEN PERFORMED AND ELECTRONICALLY SIGNED OFF.

5. If the problem is on a hang Checklist that includes steps that have been signed off in the Equipment Tagout program that must be changed, or it has been determined that the Checklist will not be performed, then the steps may be handled with the undo steps option in the Equipment Tagout Program.

The C/O Tags can then be removed from the field and the Checklist set to the MODIFY status to be corrected after checking the associated panel first and performing UNDO STEPS if required.

OP-AA-109-101 Revision 9 Page 58 of 86 14.4. Lift Checklist Cannot be Completed 14.4.1. Operations Shift Management shall DETERMINE the scope of the problem and a recovery plan for the Checklist.

WARNING IF A CHECKLIST NEEDS TO BE MODIFIED FOR CORRECTIONS, VERIFY ALL STEPS LIFTED IN THE FIELD ARE DOCUMENTED ELECTRONICALLY.

THIS WILL PREVENT ADDITIONAL C/OS FROM TAKING VIRTUAL CREDIT FOR TAGS NOT CURRENTLY PLACED.

1. If the problem is identified prior to electronically signing off steps in the Equipment Tagout program, then the Checklist can be set to MODIFY, required changes made, and then taken back to DISTRIBUTED.

A. UPDATE the original Checklist or TRANSFER hard copy Checklist signoffs from the original Checklist to the new Checklist for correct actions already taken.

B. ATTACH the original Checklist to the new Checklist as a record if required.

2. If the problem is on a lift Checklist that includes steps that have been signed off in the Equipment Tagout program that must be changed, or it has been determined that the Checklist will not be performed, then the following must be performed:

A. REHANG tags and document on lift Checklist.

B. UNDO steps electronically in the Equipment Tagout program.

C. RETURN the lift Checklist to the MODIFY status for correction.

D. ATTACH all revisions of the Checklist.

E. ENSURE a C/O pre-job brief is performed prior to the performance of the modified Checklist.

OP-AA-109-101 Revision 9 Page 59 of 86 14.5. Unavailability of the Electronic C/O Program (Equipment Tagout) 14.5.1. If the Equipment Tagout program is unavailable, then no lifting of C/O Tags placed and under control of the Equipment Tagout program is allowed except under the following conditions:

1. Tags are required to be lifted to meet Technical Specification action statements, or;

2. Tags are required to be lifted to prevent a unit shutdown or de-rate, or;

3. Tags are required to be lifted to ensure health and safety of the public and personnel safety, or;

4. Tags are required to be lifted for critical path work.

14.5.2. Prior to lifting any Equipment Tagout Program controlled C/O Tags when the Equipment Tagout program is unavailable:

1. The Shift Manager must determine that one of the above criteria is satisfied.

2. Operations must review all work in progress to verify it will not be impacted by the lift activity.

3. Any work that would be affected must be stopped until adequate protection is restored.

4. Any additional work started must also be reviewed for impact by the lift activity.

14.5.3. Shift Management shall process a manual lift checklist, documenting actions on hardcopy, per the requirements of this procedure and lift the required Tags. The Equipment Tagout program shall be updated when the system becomes available.

14.5.4. When the Equipment Tagout program is unavailable and new work is required to be performed, then the WTO process shall be used.

15. DOCUMENTATION - None

OP-AA-109-101 Revision 9 Page 60 of 86

16. REFERENCES 16.1. Commitments - None 16.2. User References - None 16.3. Writer References 16.3.1. ComEd Company Directive No. 68 Hazardous Energy Control Program 16.3.2. HU-AA-101, Human Performance Tools and Verification Practices 16.3.3. HU-AA-1211, Briefings - Pre-job, Heightened Level of Awareness, Infrequent Plant Activity and Post-Job Briefings 16.3.4. HU-AA-1212, Technical Task Risk/Rigor Assessment, Pre-job Brief, Independent Third Party Review, and Post-job Brief 16.3.5. CC-AA-112, Temporary Configuration Changes 16.3.6. OP-AA-108-106 Equipment Return to Service 16.3.7. LS-AA-104, Exelon 50.59 review Process 16.3.8. LS-AA-104-1000, Exelon 50.59 Resource Manual 16.3.9. WC-AA-104 Integrated Risk Management 16.3.10. CC-AA-206 Fuse Controls 16.3.11. OSHA Regulations 29 CFR 1910.145, Specifications for Accident Prevention Signs and Tags 16.3.12. OSHA Regulations 29 CFR 1910.147, The Control of Hazardous Energy (Lockout/Tagout) 16.3.13. OSHA Regulations 29 CFR 1910.269, Electric Power Generation, Transmission, and Distribution 16.3.14. OSHA Regulations 29 CFR 1910.333, Selection and Use of Work Practices 16.3.15. INPO 87-002 Good Practice OP-203, Tagging Procedures for Protection of Personnel, Components, and Systems 16.3.16. INPO 96-008, Guidelines for the Conduct of Operations at Nuclear Power Stations 16.3.17. WC-AA-101-1002 On-line Scheduling Process 16.3.18. TQ-AA-174, Industrial Safety Training Program 16.3.19. Electric Power Research Institute (EPRI) Clearance and Tagging Guidelines for Nuclear Electric Generating Stations Report 1015082, Final Report, December 2007.

16.3.20. EN-AA-103 Environmental Review

OP-AA-109-101 Revision 9 Page 61 of 86 16.3.21. OP-AA-108-107-1002, INTERFACE PROCEDURE BETWEEN COMED / PECO AND EXELON GENERATION (NUCLEAR / POWER) FOR TRANSMISSION OPERATIONS

17. ATTACHMENTS 17.1. Attachment 1, Activities That Do Not Require A Clearance 17.2. Attachment 2, Examples of Exceptional Clearances 17.3. Attachment 3, Clearance Requester Checklist 17.4. Attachment 4, FM WTO Preparation/Approval Checklist 17.5. Attachment 5, Clearance Preparation/Approval Checklist 17.6. Attachment 6, Clearance Walk Down Sheet 17.7. Attachment 7, C/O Challenge Guidelines 17.8. Attachment 8, Clearance Authorization Checklist 17.9. Attachment 9, Worker Tracking List 17.10. Attachment 10, Clearance Manipulation Prejob Brief Checklist 17.11. Attachment 11, Supervision Clearance Acceptance/Release Checklist 17.12. Attachment 12, Lead Worker Clearance Checklist 17.13. Attachment 13, General Worker Clearance Checklist 17.14. Attachment 14, Part 1 Worker Tagout Form Hang/Lift Section 17.15. Attachment 14, Part 2 Worker Tagout Form Special Instructions Section 17.16. Attachment 14, Part 3 Worker Tagout Form Testing/Manipulation Section 17.17. Attachment 14, Part 4 Worker Tagout Worker Tracking List (WTL) Section 17.18. Attachment 14, Part 5 Worker Tagout Log 17.19. Attachment 14, Part 6 WTO Tracking List Tag 17.20. Attachment 15, Documentation for Release of Another Employees C/O Protection 17.21 Attachment 16, External Energy Injection (EEI) Notification

OP-AA-109-101 Revision 9 Page 62 of 86 ATTACHMENT 1 Activities That Do Not Require a Clearance Page 1 of 1 NOTE: If these activities extended beyond the employees shift, then Operations will be notified. A WTO or C/O will be placed to control the required isolations for the activity.

This Attachment provides guidance to allow specific activities to be performed without a Clearance providing the work supervisor, the employee associated with the activity, and Operations agree that adequate safety will be maintained. For FM work the FM Supv and Technician are authorized to make the determination for non-plant/non power block equip.

1. Minor changes and adjustments and other minor servicing activities, which take place during normal production operations, do not require a clearance if they are routine, repetitive, and integral to the use of the equipment for production, the activity is controlled by approved plant procedures or work order that include direction to manipulate and restore components, and the isolation point disconnection is accessible, visible to, and under the sole control of the employee performing the activity.

EXAMPLES:

Instrument Maintenance work that requires isolation of instruments Lifting of electrical leads, when the work group agrees that work can be performed safely while energized Filter changes Charging accumulators with cover gas Nitrogen or other gas bottle change-outs Service Air and Instrument Air hose connections, pipe cap and fitting connections Flange and pipe cap removal and installation for general plant support activities.

Hose connections for general plant activities (breathing air, fire protection, demineralized water, etc.)

2. Work on cord and plug connected electric equipment for which exposure to the hazards of unexpected energization or start-up of the equipment is controlled by the unplugging of the equipment from the energy source and by the plug being under the exclusive control of the employee performing the servicing or maintenance.

3. If work is being performed that involves the de-energization of transmission and distribution lines, the work may be performed without a Clearance providing the following two conditions exist:

Only one crew will be working on the lines or equipment The means of disconnection is accessible and visible to and under the sole control of the employee in charge of the clearance.

OP-AA-109-101 Revision 9 Page 63 of 86 ATTACHMENT 2 Examples of Exceptional Clearances Page 1 of 1

1. All required isolation points cannot be isolated.

2. Use of an MOV as a boundary isolation point when the hand wheel is inaccessible to hang a C/O Tag.

3. Use of a control switch as the sole electrical isolation point for personnel or equipment protection.

4. Use of inaccessible valve hand wheels that cannot be physically verified closed or Tag cannot be attached.

5. Lack of dual valve isolation when isolating >500 psig or >200F.

6. When a pressure boundary is tagged for internal work, or a segment within the boundary has energy potential that would create a concern for the employee, and the boundary and segment within the boundary is not depressurized and drained.

7. All stored energy cannot be relieved from within an isolation boundary or component to be worked on.

8. Use of an AOV as an isolation point when pressure cannot be removed or valve cannot be blocked in the isolate position.

9. Use of pipe plugs, line stops, or freeze seals.

10. Use of gagging/blocking devices.

11. Use of a hydraulically operated valve as an isolation point when pressure cannot be removed or valve cannot be blocked in the isolate position.

12. Use of check valves not physically restrained to provide isolation as a primary or secondary boundary.

13. Use of a Condition Dependent Clearance.

14. Use of a Mode Dependent Clearance.

15. Work in electrical components that may not be de-energized as requested due to backfeed voltages or live circuits in areas that were requested to be de-energized.

16. Tags Plus devices or methodologies cannot be employed.

OP-AA-109-101 Revision 9 Page 64 of 86 ATTACHMENT 3 Clearance Requester Checklist Page 1 of 1

() - N/A Equipment to be worked on properly identified Equipment number(s) listed Equipment name(s) listed ECR/IR submitted if equipment number assignment required Correct Unit, train, or division specified Work Order properly identified?

Work Order/Task number(s) listed Isolation requirements identified?

Mechanical Isolation required Electrical Isolation required Both mechanical and electrical Evaluate the need to install grounding devices at locations to be determined by the work group Supervision. Include required manipulations Freeze seal used?

Total Scope of work identified?

What work will be done On which components will it be done Will boundary be breached (process, cooling, or lubrication)

What procedures/surveillances and applicable steps will be performed Review clearance requests on similar work on one or both units (where applicable)

Supplemental drawings or information provided if needed?

Modification related work Other reference materials provided List any environmental risks or hazards (tritium, permit compliance equipment, hazardous material)

Issue Report submitted to Instrument Maint. To backfill drained instruments if required?

Drawing reference numbers provided?

Suggested isolation points (if known) or system configuration (i.e., venting, draining, instrument air, etc.)?

Fire Protection System Impairment information provided?

Interactions identified (If known)?

Limit Switches Interlocks Logic C/O manipulations Temp Lifts required Partial Clears required Testing activities

OP-AA-109-101 Revision 9 Page 65 of 86 ATTACHMENT 4 FM WTO Preparation/Approval Checklist Page 1 of 1 WTO # FM-____________________

EQUIPMENT _____________________________________________________________

Exceptional WTO: Environmental Risk: Atmospheric Risk:

Writer/Preparer Approver Actions to be performed: () - N/A () - N/A Preparation Brief requirements reviewed Special Instructions reviewed / entered Exceptional criteria evaluated Is an Environmental Risk created such as special sampling equipment affected, compensatory measures required, draining of hazardous materials, or systems containing refrigerant, oils, or fuels? If yes, take actions to mitigate.

Is an Atmospheric Risk created (either Breathing or Explosive)? If yes, take actions to mitigate.

WTO positions and Sequence correct Review equipment procedures for special needs in startup, shutdown, or changeover. (check vendor manuals if available)

Drain and vent requirements identified. Equipment draining requirements. Note any process lines that cant be drained, any siphon paths, hoses needed, etc.

Safety hazards (confined space, fall hazard, components not deenergized, etc.)

Walk down the equipment looking for interfaces with other equipment, components not identified (labeling missing), or incorrect on drawings.

The 5 Key Questions What are the Critical Steps in the task?

What is the Worst Thing that can go wrong?

What are the Error Likely Situations?

What Defenses are we relying upon?

What actions will assure proper configuration control?

FM Technician Writer/Preparer____________________________________/________

Name Date FM Technician Approver ________________________________________/________

Name Date FM Supervisor Authorization_____________________________________/________

Name Date

OP-AA-109-101 Revision 9 Page 66 of 86 ATTACHMENT 5 Clearance Preparation/Approval Checklist Page 1 of 4 CLEARANCE # __________________

EQUIPMENT _____________________________________________________________

Exceptional C/O: Mode Dependent: Condition Dependent:

Operational Risk: Environmental Risk: Atmospheric Risk: Reactivity Risk:

Preparation Brief:

Pre-Job Brief may be Required IF: HU-AA-1212 may be required IF:

(Initial, or N/A) (Initial, or N/A)

Writer/Preparer Approver First time for writing this type of Complex C/O which C/O? integrates several systems?

Unfamiliar with system or prints? Boundary involves Daisy Chains?

Confusing nomenclature?

Boundary impacts PLC or Black box logic?

Emergent request? Pre-Job Brief required Pre-Job Brief Discussion Items:

(, or N/A) (, or N/A)

Is there any in-house or What human performance tools external OE? will be utilized (e.g. C/O Preparer Checklist, HU-AA series procedures)?

Applicable Clearance Order preparation considerations.

Writer/Preparer Approver Actions to be performed for all checklist types:

() - N/A () - N/A Preparation Brief requirements reviewed Special Instructions reviewed / entered Exceptional criteria evaluated Containment integrity considered C/O hang (lift) risk considered (See Page 4 of 4)

C/O Operational/Reactivity/Environmental/Atmospheric (Breathing or Explosive)

Risk impact assessed and critical steps identified

OP-AA-109-101 Revision 9 Page 67 of 86 ATTACHMENT 5 Clearance Preparation/Approval Checklist Page 2 of 4 Specific actions to be performed for hang checklists: CHK # _________ Writer/Preparer Approver

() - N/A () - N/A C/O positions and Sequence correct All attached work scope understood Drain and vent requirements identified Tech Spec applicability assessed Fire Protection concerns noted / addressed C/O step types and tag types correct Requestor notified if work not isolated as requested Specific actions to be performed for lift checklists: CHK # _________ Writer/Preparer Approver

() - N/A () - N/A Lift positions / sequence appropriate for plant status Non-tagged items included in checklist as needed Fill and vent issues addressed Instrumentation backfill requirements identified Configuration control actions properly addressed?

Specific actions for Work Addition to an approved C/O: List W/Os* Writer/Preparer Approver

() - N/A () - N/A New work scope reviewed and understood Isolation point positions and tag types verified as adequate Exceptional C/O criteria evaluated Containment integrity considered Drain and vent requirements identified Special Instructions reviewed / entered Requestor notified if work not isolated as requested

IF C/O is placed, THEN complete ALL approvals before attaching the additional work

OP-AA-109-101 Revision 9 Page 68 of 86 ATTACHMENT 5 Clearance Preparation/Approval Checklist Page 3 of 4 Clearance Order preparation considerations Determine the scope of work:

Review and approve the Clearance Request.

Review the Work Order instructions and applicable procedures.

Identify C/O and temp lift requirements, placement of jumpers, or introductions of any energy sources.

Review any TMODs or design changes that are in progress against the system or equipment.

Review the applicable Unit Turnovers for any abnormalities or unusual conditions.

Consult with the Work Planner or SME (Fire Marshal, Engineer) if doubt exists on the scope of work and/or return the C/R if needed for further information.

Establish the Zone of Protection:

Identify electrical and mechanical drawings as needed. Refer to Passport T210 or T215 panels to identify pending document changes.

Request DCP or Mod packages as needed Prepare a sketch or outline of the protection needed including grounds.

Review equipment procedures for special needs in startup, shutdown, or changeover.

Walkdown the equipment looking for interfaces with other equipment/systems not identified or incorrect on drawings.

Submit label requests and drawing change requests as needed.

Review any historical/model C/Os for the same work scope. Compare zone of protection, Special Instructions, etc.

Verify positions correct, sequencing appropriate, tag types correct.

Identify concerns in the Special Instructions:

Equipment draining requirements. Note any process lines that cant be drained, any siphon paths, hoses needed, etc.

Daisy chained neutrals.

Safety hazards (confined space, fall hazard, etc.)

Tech Spec / TRM / ODCM requirements.

Document any Subject Matter Expert review (Fire Marshal, System Engineer, Component Engineer, etc.)

Any switching orders required, other departments needed to assist in hanging/clearing the C/O (Rad Pro, Maintenance, etc.). The Operations Planning person(s) should be notified to appropriately schedule these resources.

Include a note of any grounds that need to be installed / removed, by which department, and manipulations that may be required.

Exceptional C/O criteria evaluated.

Containment integrity considered.

Environmental concerns such as special sampling equipment affected, compensatory measures required, draining of hazardous materials, or systems containing tritium.

OP-AA-109-101 Revision 9 Page 69 of 86 ATTACHMENT 5 Clearance Preparation/Approval Checklist Page 4 of 4 C/O Hang/Lift risk consideration Hang risk actions Lift risk actions Possible effects Fuse or circuit board Fuse or circuit board Auto-starts removal installation Equipment trips Draining / venting Filling / Venting Reactor Protection Logic signals Isolating instruments Valving in instruments Control Room indication changes Jumper installation Jumper removal Control Room annunciators Breaking daisy chains Restoring daisy chains Opposite Unit / Train effects Isolating control air Valving in control air Turbine Supervisory Logic De-energizing control Energizing control power Radioactive release power Loss of Main condenser vacuum Lifting of leads Landing of leads Installing grounds Removing grounds The 5 Key Questions What are the Critical Steps in the task?

What is the Worst Thing that can go wrong?

What are the Error Likely Situations?

What Defenses are we relying upon?

What actions will assure proper configuration control?

Note: When assembling the C/O package include pages 1-4 of this attachment.

Writer/Preparer _____________________________________/________

Name Date Approver _____________________________________/________

Name Date C/O Challenge _______________________________/________

Name Date

OP-AA-109-101 Revision 9 Page 70 of 86 ATTACHMENT 6 Clearance Walk Down Sheet Page 1 of 1 C/O Number: ______________________________

Safety/Rad Comments RWP Required Y N __________________________________________________________

Safety Person Required Y N __________________________________________________________

Confined Space Entry Y N __________________________________________________________

Other Safety Concerns Y N __________________________________________________________

(i.e., SA-AA-116-2124)

Job Hazard Analysis)

Dose received during Walk Down __________________________________________________________

Miscellaneous Other Discipline Support Y N __________________________________________________________

Required (i.e., lead lifting, etc.)

Equipment Purge Reqd Y N __________________________________________________________

(H2, Offgas, etc)

Locked Valve Manipulation Y N __________________________________________________________

Application Duration Time Estimate (including Draining) __________________________________________________________

Configuration Control Challenge Y N ________________________________________________________________

due to work area or component style Removal Duration __________________________________________________________

Time Estimate Ability to install Tags Plus Device Y N ________________________________________________________________________

Component Locations Y N __________________________________________________________

Accurate Component Labeled Y N __________________________________________________________

(C/O Tag & Label Match)

Draining Equipment Needed (hoses, tubing, drums, pumps, etc).

Component Access Requirements Ladder Y N __________________________________________________________

Scaffold Y N __________________________________________________________

Other Y N __________________________________________________________

Required Equipment Staged Y N (Location)__________________________________________________

Additional Issues/Comments: _________________________________________________________________________

Walk Down Performed by: _____________________________________ Date: ___________________________

Comments/Issues Resolved by: _________________________________ Date: ___________________________

OP-AA-109-101 Revision 9 Page 71 of 86 ATTACHMENT 7 C/O Challenge Guidelines Page 1 of 1 NOTE: The C/O Challenge will be conducted by a knowledgeable Management Individual (i.e. SRO, SRO Certified, previously licensed SRO or individual possessing specific technical knowledge).

CLEARANCE #___________________ CHECKLIST#_______________

1. The C/O package will include the following as applicable:

()

______ Prints with highlighted isolation boundaries

______ Clearance Request (C/R), including revisions based on scope change

______ Preparation Checklist

______ Review the final approved copy of the C/O

______ Procedures, as applicable

______ Any other materials needed or used in the preparation of the C/O

______ Notes, e-mail, etc, to identify communications/corrective actions taken against any discrepancies found during preparation.

2. The individual performing the challenge will review the C/R to identify:

______ Principle Equipment (PE)

______ Scope of Work

______ Recommended isolation points

3. The individual performing the challenge will review C/O Package and consider the following Technical Aspects:

______ Proposed drain/vent path, if applicable

______ Proper use of C/O Tags for those isolation points necessary for Personnel Protection

______ Proper steps sequencing

______ Special Instructions are clear and include appropriate procedural references.

______ Plant conditions, expected system and alarm response

OP-AA-109-101 Revision 9 Page 72 of 86 ATTACHMENT 8 Clearance Authorization Checklist Page 1 of 1 C/O #__________________________

C/O APPLICATION SUPERVISORY AUTHORIZATION ( - N/A)

C/O is in the Approved Status and C/O challenge complete Special Instructions reviewed Plant conditions acceptable Review existing TCC/TMODs for emergent changes Redundant train operability assessed including any confidence runs and shared support equipment.

Pre-clearance activity testing required/performed Tech Spec & Admin requirements met/initiated Applicable procedure prerequisites satisfied C/O Risk Potentials reviewed/acceptable (Attachment 5)

C/O Reactivity/Operational/Environmental/ Atmospheric (Breathing or Explosive) Risks considered/addressed PRA, Online & Shutdown Risk acceptable/updated HLA criteria evaluated and initiated if required Fire Protection actions/paperwork initiated Barrier Breach actions/paperwork initiated Verification type properly designated (IV, CV, or none)

C/Os taken to Distributed status with tags printed and Checklist is Master or Duplicate (not Review)

Mode/Condition Dependent actions initiated/Performed C/O application authorized (SRO signature)

C/O application pre-job brief initiated/performed For RH Checklist, Remove Holders Acceptance Lock after tags rehung.

C/O REMOVAL SUPERVISORY AUTHORIZATION W/O statused correctly for release reason with notes as applicable Method of restoration Acceptable C/O Risk Potentials reviewed/acceptable (Attachment 5, Page 4 of 4)

C/O Reactivity/Operational/Environmental/Atmospheric (Breathing or Explosive) Risks considered/addressed HLA criteria evaluated and initiated if required Verification type properly designated (IV, CV, or none)

C/O restoration authorized (SRO signature)

C/O restoration pre-job brief initiated/performed PMTs are being coordinated with C/O removal C/O checklist is Master or Duplicate (not Review) and Special Instructions reviewed All C/O Supervision and employees have released the C/O No names listed on Contacts Panel for WTL Control For Temp Lift has Holder Acceptance Lock been applied or C/O placed in Suspended status?

C/O CLOSEOUT ACTIVITIES Tech Spec actions updated, as required Fire Protection issues updated, as required All Tags removed/accounted for and any tags missing have been reconciled with final clear checklist.

Barrier Breach issues updated, as required Ensure C/O activity logged, as required Working/Testing Department notified

OP-AA-109-101 Revision 9 Page 73 of 86 ATTACHMENT 9 Worker Tracking List Page 1 of 1 Use additional sheets as needed: Sheet ____ of _____

WO(s)#

C/O # PJB Performed by (Print): Attachment 13 by: (Print):

Phone Extension/Pager #:

Worker Sign ON Worker Sign OFF Print AND Sign Name Date Time Sign Name Date Time Verify Worker Sign OFF column completed for all employees, then sign (WTL Cognizant sign and date) ________________________________/__________________

OP-AA-109-101 Revision 9 Page 74 of 86 ATTACHMENT 10 Clearance Manipulation Prejob Brief Checklist Page 1 of 1 C/O # ____________________________ CHK# ______________________

Operational/Reactivity/Environmental/Atmospheric Risk activities must include each of the following:

Perform a C/O prejob Brief and HLA Brief as appropriate for the activity Mark or highlight Critical Step(s) in the activity that relate to Risk Obtain authorization from the Unit or Control Room Supervisor directly prior to performing a critical step or critical steps related to the Risk Monitor/Validate performance of each critical step related to the Risk by direct oversight in the field, by work group supervision unless alternate methods are specifically determined at the prejob brief/HLA.

BRIEFING ITEMS FOR DISCUSSION & COMMENTS

( - N/A) ( - N/A)

Job purpose/scope Previous history and lessons learned Roles and responsibilities Other departments involved Clearance Step Verification Requirements Checklist Type Specific Concerns (i.e., Dual annotated (CV, IV, or none) Function)

Safety concerns/potential hazards Procedure coordination issues ALARA concerns Special Instructions and C/O notes reviewed Special Tooling or access (man-lift, keys, Defenses against errors and Human valve bar, gags, etc) Performance Tools discussed (flagging, 2-minute drill, peer checks)

Radwaste concerns (drain locations) Virtual tags use discussed Reactivity Management concerns MCR/Radwaste/other persons notified C/O identified as Operational/Reactivity/ Effect on other systems/equipment (fail safe Environmental/Atmospheric Risk. If yes, position of valves) perform HLA as required per HU-AA-1211 Operational/Reactivity/Environmental/ Abort criteria and Contingencies Atmospheric Risk Critical Step performance and monitoring established with key participants Critical Steps identified on C/O checklist Main Control Room interface, alarms, change in indication (first check)

Key Questions? Tag Plus devices/methods that will be used.

What are the Critical Steps in the task? Identify any C/O Tags in advance that cannot be returned during C/O removal. If additional tags are identified during removal activities inform dispatching Supervisor.

What is the Worst Thing that can go wrong? C/O Checklist Master or Duplicate, not Review What are the Error Likely Situations? Assign inspection prior to RTS using OP-AA-108-106 for Housekeeping and Condition What Defenses are we relying upon? Notes/Discussion Items What actions will assure proper configuration control?

OP-AA-109-101 Revision 9 Page 75 of 86 ATTACHMENT 11 Supervision Clearance Acceptance/Release Checklist Page 1 of 1 NOTE: Perform applicable Section as required (Acceptance or Release).

CLEARANCE #_______________________

ACCEPTANCE TASKS Prior to Work Start/Work Restart ( - N/A) Safety Verification Requirements ( - N/A)

All C/O(s) instructions reviewed Required isolation identified by Supervision W/O(s) tied to all required C/O(s) verified Drain and/or vent paths used (listed on C/O, flow observed at drains?)

C/O(s) Accepted by Holder (recheck daily) C/O exceptional (discuss why)

Boundary report properly prepared to facilitate Electrical grounds used, any manipulations Safety Verification required Prejob Brief performed Walkdown assigned to employee Ensure Worker Sign-on Occurs (ESO or WTL)

RELEASE TASKS Releasing for Restoration ( - N/A) Processing/Releasing a Temp Lift/Partial ( - N/A)

Clear Verify equipment is cleared of personnel, Contact/Coordinate with affected Supervisor and cleared of obstructions, grounding devices Operations removed Verify Proper completion of Worker Tracking Affected Holders and employees notified and List(s). C/O Electronic Sign Off(s) complete. understand PC/TL impact as applicable to their Contacts panel entries for your crew are zone of protection removed Work is completed and statused properly in Request information submitted to Operations (lift computer. If not complete, add notes to isolations, when needed, duration of lift, reason, Holders Panel who to contact, Special Instructions, and proposed checklist)

C/O released by Supervisor Notify Supervisors to release after Approval and prior to Authorization Checklists released, as required (Supervision TL, PC, FC and all other holders FC)

Work Stop ( - N/A)

Supervisors/Employee agree and release WTL or C/O Electronic Sign OFF, as required This attachment can be reused.

OP-AA-109-101 Revision 9 Page 76 of 86 ATTACHMENT 12 Lead Worker Clearance Checklist Page 1 of 1 NOTE: Perform applicable Section as required (Work Start, Work Stop).

LEAD WORKER TASKS CLEARANCE #__________________________________

Lead Worker Tasks - Work Start ( - N/A) Lead Worker Tasks - Work Stop ( - N/A)

Verify Supervision sign-on as holder (Passport, At least one crewmember notify supervisor of screen prints). This prevents C/O modification. workers that cannot be located if applicable.

Participate in/lead/verify designee performs PJB Sign off WTL or perform Electronic Sign Off (C/O hazards, Special Instructions, controls, ZOP)

Perform or verify a Safety Verification was At least one crewmember notifies the performed by another crew or crewmember. Supervision of work stop.

Review isolations identified as required on the Boundary Report.

Verify hazards are isolated Lead Worker Tasks - Work Re-start ( - N/A)

Verify systems are depressurized and drained. Each new day of work:

Verify work area is not exposed to unexpected Verify that no boundary changes were made electrical hazards. (use C/O status panel in Passport, discuss with work group supervisor).

Place completed Boundary Report in work Perform or verify a Safety Verification was package or in a designated location performed by another crew or crewmember, if required due to changes of Boundary.

Verify W/O tasks are attached to proper Verify Acceptance/Re-accept of the C/O clearances (view in Passport or on screen prints)

After walk down re-brief as needed if conditions Verify required work order tasks remain were not as expected or new information available attached to the clearance Electronically Sign On or sign WTL. Brief any new crewmembers not ESO qualified, and have them sign the WTL.

Confirm crewmembers electronically accepted or a WTL has been signed by them.

Perform work.

The Worker Tracking List shall be maintained in an appropriate location and shall be controlled by the individual Electronically signed-on for WTL Control.

For contract personnel, this responsibility will be performed by the Exelon Nuclear site contact designated by the project or contract area supervisor.

Only one of these Attachment 12s is needed per crew as a minimum, and can be reused.

OP-AA-109-101 Revision 9 Page 77 of 86 ATTACHMENT 13 General Worker Clearance Checklist Page 1 of 1 NOTE: Perform applicable Section as required (Work Start, Work Stop, Work Restart).

CLEARANCE #___________________________

General Worker Tasks - Work Start ( - N/A) General Worker Tasks - Work Re-start ( - N/A)

Participate in Prejob Brief. Always ask: Each new day of work:

Is this C/O exceptional? Why?

(Attachment 2)

Will there be any boundary changes?

Is there anything unusual about this C/O?

Verify your Supervision AND a second individual Verify that no boundary changes were made who is at least Lead Worker qualified are both (use C/O status panel in Passport or discuss signed onto your C/Os. (The Lead Worker with Lead Worker or Supervisor) qualified individual must also be listed on the Contacts Panel)

Verify with Lead Worker or Supervision that a Discuss Safety Verification of Boundary Safety Verification has been done Changes if required with Lead Worker or Supervisor Verify work order tasks are attached to C/O Verify Acceptance/Re-accept of the C/O (Passport, screen prints), ask Lead Worker or (Passport or screen prints), ask Lead Worker or Supervision Supervision Sign the Worker Tracking List for required C/Os Verify W/O tasks remain attached to the C/O for your work and verify WTL is controlled by the (Passport or screen prints), ask Lead Worker or Lead Worker qualified individual. Supervision Perform work Sign the Worker Tracking List for required C/Os for your work and verify WTL is controlled by Lead Worker qualified individual who must also be signed on to the C/O for WTL control General Worker Tasks - Work Stop Notify the Lead Worker or Supervision of work stop Sign off WTL daily, before end of your shift REMINDER - NEVER:

OPERATE A DEVICE THAT HAS A DANGER TAG ON IT REMOVE A DANGER TAG COMPONENT FROM A SYSTEM REMOVE A DANGER TAG The Worker Tracking List shall be maintained in a pre-designated location and shall be controlled by the individual Electronically signed-on for WTL Control.

For contract personnel, this responsibility will be performed by the Lead Worker qualified site contact designated by the project or contract area supervisor.

Only one of these Attachment 13s is needed per crew as a minimum, and can be reused.

OP-AA-109-101 Revision 9 Page 78 of 86 ATTACHMENT 14 PART 1 WTO Form Hang/Lift Section Page 1 of 1 Exceptional C/O: Mode Dependent: Condition Dependent:

Operational Risk: Environmental Risk: Atmospheric Risk: Reactivity Risk:

WORKER TAGOUT# __________________________ JOB DESCRIPTION: ________________________________________

WORKING DEPARTMENT: __________________ W/O OR W/R: ____________________ EQUIP. TAG# _____________________

COMPONENT DESCRIPTION: ________________________________________________________

FIRST APPROVAL: ____________________________________ DATE: _________________

SECOND APPROVAL: _________________________________ DATE: _________________

WTO AUTHORIZATION: _______________________________ DATE/TIME __________________

SPECIAL INSTRUCTIONS: YES: NO: (IF YES SEE ATTACHMENT 14 PART 2)

EQUIP. TAG/EQUIPMENT NAME SEQ TAG POSITION HUNG VERIF. SFTY. RTS RTS RTS VERIF.

TYPE BY BY VERIF. SEQ POSITION BY BY WTO PLACED: ______________________________________________________________ DATE/TIME: ___________________

WTL COMPLETED WORK START: _____________________________________________ DATE/TIME: ___________________

WTO FINAL CLEAR: WORK CREWMEMBER RELEASE: ____________________________ DATE/TIME: ___________________

WTO CLEARED: ____________________________________________________________ DATE/TIME: ____________________

(COPIES MAY BE MADE OF THIS FORM FOR ADDITIONAL ISOLATION POINTS)

OP-AA-109-101 Revision 9 Page 79 of 86 ATTACHMENT 14 PART 2 WTO Form Special Instructions Section Page 1 of 1 WTO #

OP-AA-109-101 Revision 9 Page 80 of 86 ATTACHMENT 14 PART 3 WTO Form Testing/Manipulation Section Page 1 of 1 WTO # __________________________________________

RECORD ALL MANIPULATIONS (HANG AND LIFT) ASSOCIATED WITH THIS WTO (ADDITIONAL COPIES MAY BE USED AS NEEDED) Page ____ of _____

EQUIP. TAG/ EQUIP. NAME SEQ AS FOUND MANIP. POSIT. VERIF. RH RH RH VERIF. SFTY.

POSITION POSITION BY BY SEQ POSITION BY BY VERIF.

OP-AA-109-101 Revision 9 Page 81 of 86 ATTACHMENT 14 PART 4 WTO Worker Tracking List (WTL)

Page 1 of 1 Use additional sheets as needed. Sheet _____ of ______

W/O # WTO # Supervisor (Print): Designated Crew member (Print):

Worker Sign ON Worker Sign OFF**

Print and Sign Name Date Time WTO* Sign Name Date Time WTO*

Tracking Tracking List Tag List Tag Placed Removed (Yes/Dual) (Yes/Dual)

Indicate Yes if done and use Dual if 2 tags used for dual feed components. Required for individuals that hung the tag.

Verify Worker Sign Off column completed for all employees, then sign (Designated Work Crewmember sign and date) ______________________________________/ ____________________

OP-AA-109-101 Revision 9 Page 82 of 86 ATTACHMENT 14 PART 5 Worker Tagout Log Page 1 of 1 WTO # EQUIP. SYSTEM JOB DESCRIPTION WO/IR/ WORK GROUP DATE/TIME DATE/TIME TAG ID WR NUMBER SUPERVISOR HUNG CLEARED (or Dept.)

OP-AA-109-101 Revision 9 Page 83 of 86 ATTACHMENT 14 PART 6 WTO Tracking List Tag Page 1 of 1 WTO TRACKING LIST TAG WTO Tracking List Tag (all workers on WTL sign here)

WORK IN PROGRESS WTO #_______________________________________

DO NOT OPERATE Date Hung:____________________ Dept.:_________

FRONT BACK

OP-AA-109-101 Revision 9 Page 84 of 86 ATTACHMENT 15 Documentation for Release of Another Employees C/O Protection Page 1 of 1 WARNING USE OF THIS ATTACHMENT REQUIRES 100% VERBATIM PROCEDURE COMPLIANCE, AS YOU ARE RELEASING ANOTHER EMPLOYEES ZONE OF PROTECTION. DEATH OR INJURY COULD RESULT IF PERFORMED INCORRECTLY.

C/O or WTO Number:_________________________________ Date: _____/____/______

Name of employee:_________________________________________________________________

Work Group or Department of employee:________________________________________________

Supervisor completing release: printed name/signature____________________/___________________

Sign off all Steps:

1. CONTACT Security and VERIFY employee is not in the Protected Area ________

2. TAKE additional actions to notify employees if job assignment is outside the Protected Area ________

3. REQUEST Security set the status of employees badge to Zero and notify Operations when worker returns to the site ________

4. RECORD employee absence on the Worker Tracking List (if used) or in Passport on holders panel ________

5. VERIFY WTL or electronic sign-off complete ________

6. KEEP this attachment on file until notified that the employee has returned to site ________

7. When employee returns to site, NOTIFY them that the C/O or WTO was released ________

Employee Acknowledgement of Notification:

Name_____________________________________ Signature/Date:_________________

8. RESET employees badge status to original status ________

9. RECORD IR number written by work group ________

10. ATTACH WTL (if used) to this attachment ________

11. SUBMIT completed Attachment 15 to the Site Clearance Coordinator ________

NOTE: The Clearance Coordinator is responsible to trend the incident and retain the completed attachment on file for 6 months.

OP-AA-109-101 Revision 9 Page 85 of 86 ATTACHMENT 16 External Energy Injection (EEI) Notification Page 1 of 2 Clearance #: ___________________________

Description of the EEI:

Requestor (print name): _______________________________ Phone #: _____________________

Holder Lock Applied by (print name and date): _______________________________

Employee Approvals:

All Holders, Lead Workers, and General Workers have been notified and understand the EEI that will occur. Work has been stopped as necessary. All holders and workers have signed off the clearance or their approval of the EEI has been obtained by their signing of the External Energy Injection (EEI)

Notification list in this attachment.

Check boxes as applicable (both may be applicable):

Work Stoppage Required (if yes exit this form and sign off ESO or WTL)

Work Stoppage NOT Required (proceed to Attachment 16 page 2 and collect worker signatures)

Note:

Working Group to maintain Attachment 16 with work package until EEI activity is complete and work package is completed. After work package completion Attachment 16 retention is not required.

OP-AA-109-101 Revision 9 Page 86 of 86 ATTACHMENT 16 External Energy Injection (EEI) Notification Page 2 of 2 Clearance #: ___________________________

WO Activity Worker Name (Print) Worker Signature Date/Time Notified Note: This attachment is not required if all workers sign off the Clearance/WTL before the EEI.

Clearance Worker Notification completed prior to Energy Injection: _________________ ____/_____

Holder Signature Date/Time Holder Lock Removed following Energy Injection by (print name and date): _____________________

NOTE TO EXAMINER:

ONLY PROVIDE THE ENCLOSED DRAWING (M-150 SHEET 1) IF THE EXAMINEE SPECIFICALLY REQUESTS THAT DRAWING.

DO NOT PROVIDE THIS DRAWING AS PART OF THE INITIAL CLEARANCE ORDER PACKAGE AT START OF THE JPM.

JOB PERFORMANCE MEASURE TASK CONDITIONS:

1. You are the Unit 2 Assist NSO.

2. A reactor trip has occurred on Unit 1.

3. An Alert was declared forty minutes ago. The initial NARS notification was transmitted in accordance with required procedures. Two minutes ago a change in plant condition resulted in an upgrade to the emergency action level to a Site Area Emergency FS1.

4. EP-MW-114-100-F-01, NUCLEAR ACCIDENT REPORTING SYSTEM (NARS) FORM has been filled out and approved.

5. This is a Time Critical JPM.

INITIATING CUES:

1. The Shift Manager directs you to transmit the NARS form for the upgraded EAL status of Unit 1 per EP-MW-114-100, MW Region Offsite Notifications.

2. Another NSO will monitor the remainder of the Main Control Board panels and address alarms as necessary.

3. Inform the Shift Manager when the NARS form has been transmitted.

R-402 Page 1 of 7

TASK TITLE: Perform NARS Update Transmittal JPM No.: R-402 REV: CERT 2013 TPO No.: 4F.ZP-02 K&A No.: 2.4.39 TASK No.: R-ZP-004 Transmit NARS Form K&A IMP: 3.9/3.8 EXAMINEE: RO EVALUATOR: DATE:

The Examinee: PASSED this JPM. TIME STARTED:

FAILED TIME FINISHED:

JPM TIME: MINUTES CRITICAL ELEMENTS: (*) 3, 4 APPROX COMPLETION TIME: 10 MINUTES CRITICAL TIME: 13 minutes EVALUATION METHOD: LOCATION:

X PERFORM IN PLANT SIMULATE X SIMULATOR GENERAL

REFERENCES:

1. EP-MW-114-100, MW REGION OFFSITE NOTIFICATIONS, Rev. 12.

2. EP-MW-114-100-F-01, NUCLEAR ACCIDENT REPORTING SYSTEM (NARS) FORM, Rev. G.

MATERIALS:

1. EP-MW-114-100, Rev. 12, MW REGION OFFSITE NOTIFICATIONS.

2. EP-MW-114-100-F-01, Rev. G, NUCLEAR ACCIDENT REPORTING SYSTEM (NARS) FORM.

TASK STANDARDS:

1. Determine correct NARS phone code or phone number.

2. Complete NARS initial roll call within 15 minutes of the initiating cue.

3. Transmit NARS data to offsite agencies.

TASK CONDITIONS:

1. You are the Unit 2 Assist NSO.

2. A reactor trip has occurred on Unit 1.

3. An Alert was declared forty minutes ago. The initial NARS notification was transmitted in accordance with required procedures. Two minutes ago a change in plant condition resulted in an upgrade to the emergency action level to a Site Area Emergency FS1.

4. EP-MW-114-100-F-01, NUCLEAR ACCIDENT REPORTING SYSTEM (NARS) FORM has been filled out and approved.

5. This is a Time Critical JPM.

INITIATING CUES:

1. The Shift Manager directs you to transmit the NARS form for the upgraded EAL status of Unit 1 per EP-MW-114-100, MW Region Offsite Notifications.

2. Another NSO will monitor the remainder of the Main Control Board panels and address alarms as necessary.

3. Inform the Shift Manager when the NARS form has been transmitted.

R-402 Page 2 of 7

RECORD START TIME:

EVALUATOR NOTE: Provide examinee the completed NARs form and copy of EP-MW-114-100-F-01.

EVALUATOR NOTE: JPM critical time (13 minutes) starts when the initiating cue has been read to the examinee and stops after the initial roll call is made and the NARS information starts to be transmitted.

PERFORMANCE STEP STANDARD CIRCLE APPLICABLE

1. Refer to EP-MW-114-100, MW Refer to EP-MW-114-100: SAT UNSAT N/A REGION OFFSITE

Determine step 4.2 needs Comments:

NOTIFICATIONS. to be performed.

2 Refer to EP-MW-114-100-F-01, Refer to EP-MW-114-100-F-NUCLEAR ACCIDENT 01:

REPORTING SYSTEM (NARS)

Determine NARS Code 20 FORM. to be used to transmit NARS form.

R-402 Page 3 of 7

3. Establish communications: Establish communications as SAT UNSAT N/A follows: Comments:

Note: After examinee dials Code 20, provide the

Pick up NARS phone.

following cue:

CUE: After a short pause, a

DIAL code 20. (hears busy signal is heard. busy signal)

CUE: After a short pause, a

DIAL code 50 to enter the dial tone is heard. (if bridge. (hears pause and candidate tries code 20 then dial tone) or 50 again, repeat the same cues).

CUE: After dialing 1-217-782-

Determines that it will be 7860, you announce that necessary to call via the you are Steve from IEMA commercial exchange on the line. number for IEMA found on page 2 of the NARS form.

Dials 1-217-782-7860.

Note: After examinee reads

Read the following messages, provide the message: This is Exelon following cue: Nuclear Braidwood Station CUE: IEMA online. Control Room. Please standby for a NARS message.

o Read the following message: This is the Exelon Nuclear Braidwood Station Control room.

Please standby to receive a NARS message and respond as the roll is called.

TAKE Initial Roll Call

Mark Initial Box for IEMA

Record time and date initial roll call complete.

EVALUATOR NOTE: Critical time TIME STOPS when examinee completes initial roll call.

Determine critical time:

_________________________ - ________________________ = ________________________

(Time initial roll call complete) (JPM start time) < 13 minutes R-402 Page 4 of 7

PERFORMANCE STEP STANDARD CIRCLE APPLICABLE

4. Verbally transmit the NARS Verbally transmit the NARS SAT UNSAT N/A Form. Form: Comments:

Utility Message No: 2_

State Message No: N/A

Status - [B] Drill/Exercise

Station - [A] Braidwood

Onsite Condition - [C] Site Area Emergency

Accident Classified:

Time: Two minutes ago.

Date: Today.

EAL # : FS1

Accident Terminated Date and Time: N/A

Release Status: [A] None

Type of Release: [A] Not Applicable

Wind Dir: 270

Wind Speed:

o [A] is N/A

[B] 4.5 Miles/Hr

Recommended Actions:

Utility Recommendation:

[A] None

Additional Information:

None Verified With: U. Supervisor Approved By: S. Manager

5. Complete the NARS form. Fill in the following information SAT UNSAT N/A on the NARS Form after Comments:

transmitting info in blocks 1-10:

Mark 11A, EXELON CUE: IF examinee asks for a

Examinee Name phone number to use, provide: outside line is

Outside line number 815-458-7882.

Current Time

Current Date

Name of person from CUE: Steve Smith, IEMA. IEMA receiving message

Organization (IEMA)

Current time

Todays date R-402 Page 5 of 7

PERFORMANCE STEP STANDARD CIRCLE APPLICABLE

6. Perform Final Roll Call PERFORM Final Roll Call and SAT UNSAT N/A Note: As examinee performs marks boxes for: Comments:

final roll call provide the

IEMA following cues:

Ask if there are any CUE: IEMA (Steve) questions about the CUE: No questions from either information provided.

IEMA

7. STATE NARS communication is STATE NARS communication SAT UNSAT N/A complete. is complete. Comments:

CUE: THIS COMPLETES THIS JPM.

RECORD STOP TIME:

COMMENTS:

R-402 Page 6 of 7

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-MW-114-100, MW REGION OFFSITE NOTIFICATIONS, Rev. 12.

Provide copy of EP-MW-114-100-F-01, NUCLEAR ACCIDENT REPORTING SYSTEM (NARS) FORM, Rev. G, with the following information completed:

Utility Message No - 2 State Message No - N/A Status - [B] Drill/Exercise Station - [A] Braidwood Onsite Condition - [C] Site Area Emergency Accident Classified:

Time - Two minutes ago.

Date - Today.

EAL # - FS1 Accident Terminated Date and Time are N/A.

Release Status - [A] None Type of Release - [A] Not Applicable Wind Dir - 270 Wind Speed - [B] 4.5 Miles/Hr ([A] is N/A)

Recommendations - [A] None Additional Information - None Verified With - U. Supervisor Approved By - S. Manager (Final)

R-402 Page 7 of 7

EP-MW-114-100 Revision 12 Page 1 of 13 Level 2 - Reference Use MIDWEST REGION OFFSITE NOTIFICATIONS

1. PURPOSE 1.1. Provide prompt and accurate notification of nuclear station emergencies to local, state and federal agencies.

State and Local Notification Requirement REFER to section 4.1 Completing the NARS Form REFER to section 4.2 NARS Call Transmittal REFER to section 4.3 Receiving a NARS Message REFER to section 4.4 Follow-Up Notifications REFER to section 4.5

2. TERMS AND DEFINITIONS 2.1. Nuclear Accident Reporting System (NARS) is a telecommunication network used to transmit information to appropriate State and local agencies.

2.2. NARS Form(s): NARS hardcopy form in procedure EP-MW-114-100-F-01 and NARS electronic equivalent.

3. RESPONSIBILITIES 3.1. The Emergency Director in the Emergency Response Facility (ERF) with Command and Control shall ensure that all required notifications are initiated as follows:

1. Within 15 minutes of:

a. Declaring an emergency

b. Emergency Classification escalation

c. Issuing or changing Protective Action Recommendations (PARs)

d. A radioactive release OR a change in radioactive release conditions

2. Within one hour of Termination or entry into Recovery.

3.2. Operations personnel on shift are responsible for transmitting the State/Local notification over the NARS when the Shift Emergency Director is in Command and Control.

3.3. The State/Local Communicator in the TSC is responsible for transmitting the State/Local notification over the NARS when the Station Emergency Director is in Command and Control.

EP-MW-114-100 Revision 12 Page 2 of 13 3.4. The State/Local Communicator in the EOF is responsible for transmitting the State/Local notification over the NARS when the Corporate Emergency Director is in Command and Control.

4. MAIN BODY 4.1. STATE AND LOCAL NOTIFICATION REQUIREMENT 4.1.1. INITIATE offsite notification within 15 minutes of the following:

1. The declaration of an emergency

2. Classification of an emergency

3. A change in Protective Action Recommendations (PARs)

4. A change in the radioactive release conditions

5. A change in wind direction that affects a different combination of Subareas/Sectors when a release is occurring.

4.1.2. INITIATE offsite notification as soon as possible, but within one hour of Termination or entry into Recovery.

NOTE: The electronic NARS form equivalent is the preferred method when available.

4.2. COMPLETING THE NARS FORM 4.2.1. Utility Message Number

1. ENTER a Utility Message Number sequentially, starting with 1, for the event described.

2. ENTER "N/A" on the hard copy form if this is a State NARS Message or

3. If using the electronic form, CLICK inside the State Message No. box and VERIFY that the NA auto-populated.

4.2.2. State Message Number

1. ENTER the State Message Number when receiving a NARS Message from the State.

2. ENTER "N/A" if this is a Utility NARS Message.

EP-MW-114-100 Revision 12 Page 3 of 13 4.2.3. Block 1, Status

1. [A] ACTUAL - MARK this box to indicate a notification is being performed based on actual plant conditions.

2. [B] Drill/Exercise - MARK this box to indicate a notification is being performed during exercises, drills, training sessions, or communications tests.

4.2.4. Block 2, Station

1. [A] Through [G] - MARK the appropriate box for the affected station.

4.2.5. Block 3, Onsite Condition

1. When classifying events, USE the highest classification level for the site (all units).

2. [A] Through [F] - MARK the box corresponding to the highest classification or condition level for the site (all units).

4.2.6. Block 4, Accident Classified NOTE: The time and date are specific to the current emergency classification and the date will auto-populate when using the electronic NARS form.

1. If issuing the form for a change other than a new classification, THEN ENTER the date, time, and EAL# for the current classification in effect.

2. If one of the four emergency event levels is being communicated as the Block #3 Onsite Condition, THEN ENTER the TIME & DATE that the event was declared and the corresponding EAL #.

3. If entry into Recovery is being communicated as the onsite condition, THEN:

ENTER the TIME & DATE that Recovery was entered and N/A the EAL # if using the hard copy form or VERIFY that the electronic NARS form auto-populates.

4. When using the hard copy form, ENTER N/A next to TIME & DATE under ACCIDENT TERMINATED.

EP-MW-114-100 Revision 12 Page 4 of 13 4.2.7. Block 4, Accident Terminated

1. When using the hard copy form, ENTER the TIME & DATE that the accident condition was terminated or when using electronic NARS:

A. ENTER the TIME and B. VERIFY the DATE auto-populated.

2. ENTER N/A next to TIME & DATE and EAL # under ACCIDENT CLASSIFIED or when using electronic NARS:

A. VERIFY TIME & DATE auto-populated under ACCIDENT CLASSIFIED B. VERIFY block 3, ONSITE CONDITION, TERMINATED is checked.

4.2.8. Block 5, Release Status

1. USE EP-AA-114-F-01(02), PWR (BWR) Release in Progress, as needed, to identify a release in progress.

2. [A] NONE - MARK this box to indicate that no release is occurring.

3. [B] "OCCURRING" - MARK this box to indicate that there is a release in progress.

4. [C] TERMINATED - MARK this box to indicate when a radioactive release of gasses or liquids associated with the emergency event are no longer being released based on sampling or direct measurement.

4.2.9. Block 6, Type Of Release

1. If [A] NONE, was selected in Block 5, THEN MARK [A] NOT APPLICABLE or VERIFY NOT APPLICABLE is checked when using electronic NARS.

2. If [B] OCCURRING, was selected in Block 5, THEN MARK the following as appropriate:

MARK [B] GASEOUS MARK [C] LIQUID

3. If [C] TERMINATED was selected in Block 5, THEN MARK the following as appropriate:

MARK [B] GASEOUS MARK [C] LIQUID

EP-MW-114-100 Revision 12 Page 5 of 13 4.2.10. Block 7 Wind Direction & Block 8, Wind Speed

1. REFER to EP-MW-110-1001, Data Point Tables, as needed, for a listing of PPDS meteorological data points.

NOTE: Meteorological data is taken from the appropriate level of the tower to match the expected release height.

STATION RELEASE POINT LEVEL No Release Elevated Chimney Elevated Dresden and Quad Reactor Bldg. Vent Ground Isolation Condenser Dresden (Only) Ground Hole in Wall/Other Ground No Release Elevated Station Vent Stack Elevated LaSalle Standby Gas Treatment Stack Elevated Hole in Wall/Other Ground Braidwood, Byron & Clinton All Ground

2. OBTAIN meteorological data from the following sources in the order listed below:

- PPDS data

- Control Room Meteorological Instruments

- Contracted Weather Service - Murray and Trettel - The phone numbers for the contracted weather service are located in the Emergency Response Facilities Telephone Directory.

- National Weather Service (NWS) -The phone numbers for the weather services are located in the Emergency Response Facilities Telephone Directory. Additionally, the information may be obtained from the NWS Web Site.

- Direct Observation Estimate- Estimation of the wind direction by direct observation of outside conditions.

3. Block 7 - ENTER the wind direction (from) in degrees.

4. Block 8 - MARK the box and enter the wind speed for either or both as follows:

[A] METERS/SEC

[B] MILES/HR

EP-MW-114-100 Revision 12 Page 6 of 13 Quad Cities

5. Block 8 - MARK [A] and [B] and FILL IN both "METERS/SEC" and "MILES/HR".

4.2.11. Block 9, Recommended Actions WARNING: Do not delete subareas that have been previously identified in Block 9.

Recommended subareas may be added, but not deleted by the utility.

1. If [D] General Emergency, was not selected in Block 3, THEN MARK

[A] NONE or A. VERIFY [A] NONE auto-populated if using electronic NARS.

2. If [D] General Emergency, was selected in Block 3, THEN:

A. When Shelter has been determined to be the appropriate PAR, MARK boxes [B] and/or [C] for the affected state(s).

ENTER the Subareas to be sheltered on the appropriate state line per EP-AA-111, Emergency Classifications and Protective Action Recommendations.

If Subareas were previously identified in Block 9, DO NOT delete.

B. When Evacuate has been determined to be the appropriate PAR, MARK boxes [D] and/or [E] for the affected state(s).

ENTER the Subareas to be evacuated on the appropriate state line per EP-AA-111, Emergency Classifications and Protective Action Recommendations.

If Subareas were previously identified in Block 9, DO NOT delete.

3. Boxes [F] through [K] are for State Use. They are completed only when Exelon personnel are receiving a notification transmission from the State.

EP-MW-114-100 Revision 12 Page 7 of 13 4.2.12. Block 10, Additional Information

1. If a situation arises where both units are affected by unrelated event EALs, THEN NOTE the other EAL and the applicable unit number in the Additional Information section and proceed to step 4.2.12.4.

2. If this is the first NARS issued for the event, THEN ENTER None.

3. If a subsequent NARS form is being issued because of a change in the classification level, THEN ENTER None.

4. If a subsequent NARS form is being issued because of a change in one of the conditions listed below but the classification level of the event remains the same, THEN briefly EXPLAIN the changed condition.

Change in Release Status Change in PARs Change in affected Subareas Corrections are being made to a previously issued NARS 4.2.13. PRINTING ELECTRONIC NARS

1. SAVE the electronic form by:

A. SCROLLING to the top of the record and B. SELECTING save.

2. CLOSE the blank input form by X-ing out at the top right hand corner of the blank form.

3. From the Boards Display Panel, DOUBLE CLICK the MW NARS Form.

4. SELECT the desired NARS form by CLICKING the View Entire Form button for the NARS form to be printed.

5. CLICK on the green Print button for the board to be printed.

6. SELECT the desired printer and CLICK print.

EP-MW-114-100 Revision 12 Page 8 of 13 4.2.14. APPROVAL BLOCK

1. COMPLETE the Verified with section when using a peer check for accuracy (e.g. TSC or EOF Directors completing the NARS form for the Emergency Director), otherwise mark as N/A.

2. OBTAIN approval from the Emergency Director in Command & Control prior to transmission of the NARS form.

Control Room Shift Manager TSC Station Emergency Director EOF Corporate Emergency Director 4.2.15. Blocks 11 and 12

1. These blocks record name, organization, date and time of message transmission/receipt.

2. These Blocks are not completed during the preparation of the NARS form. Completion of Blocks 11[A] and 12 is performed by the Communicator when reading the message over the NARS telephone system.

3. Blocks 11[B] and [C] are completed by the Communicator when receiving a notification transmission from the State.

4.3. NARS CALL TRANSMITTAL NOTE: Dialing the NARS phone code activates a conference bridge. A brief pause will occur prior to connection once the desired code has been entered. A beep will indicate when a party joins the bridge.

CAUTION:

Wait several seconds (approx. 5 sec) after hanging up the NARS phone prior to initiating another call or the conference bridge circuit will be blocked with a busy signal.

EP-MW-114-100 Revision 12 Page 9 of 13 4.3.1. Using the Roll Call Box for the affected station on Page 2 of the NARS Form, DIAL the appropriate code on the NARS telephone.

1. If the NARS call is successful, THEN go to step 4.3.2.

2. If a busy signal is received after dialing the code, DIAL 50 to enter the bridge. ANNOUNCE who you are and the reason for your call.

3. If the NARS network fails, THEN:

NOTE: Commercial telephone numbers for the State are listed on Page 2 of the NARS Form. Other contacted agencies are listed in Section (Tab) 10 of the ERF Telephone Directory.

A. CONTACT the agencies that are noted as "Required to be Notified within 15 minutes". This is denoted next to the roll call listing for each NARS Code on the back of the NARS Form.

B. CALL all other agencies that are part of the roll call listing for the NARS call.

C. INFORM the Emergency Director of all non-contacts.

4.3.2. Following a short pause and a beep indicating you are connected to the bridge, READ the following message:

"This is the Exelon Nuclear [Station and Facility originating the call]. Please standby for a NARS message."

4.3.3. As the agencies respond to the call, READ the following message:

"This is the Exelon Nuclear [Station and Facility originating the call]. Please standby to receive a NARS message and respond as the roll is called."

4.3.4. WAIT a short period of time to allow the appropriate agencies to join the bridge.

NOTE: Radiological Emergency Assessment Center (REAC) is NOT staffed 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months a day. REAC is NOT a required agency to consider the call complete.

4.3.5. CONDUCT an initial roll call for the agencies listed under the NARS code used on the back of the NARS form. CHECK them OFF as they respond to the roll call.

EP-MW-114-100 Revision 12 Page 10 of 13

1. If any required agencies do not answer the roll can, THEN CONTACT each agency separately after the completion of the NARS call.

4.3.6. FILL IN the box in the center section of Page 2 of the NARS Form under the heading INITIAL ROLL CALL COMPLETE.

The Time and Date entered in this box corresponds to the completion of the initial roll call for required agencies and the 15-minute clock for the NARS notification.

4.3.7. READ the NARS message.

1. READ the NARS message # _____.

2. Read the blocks 1-10 one at a time; stating the number, the title, the letter (if appropriate) and the description.

4.3.8. COMPLETE Sections 11 and 12 on the NARS form as you get to them.

Communicate the information you put into these blocks to the personnel on the NARS call.

1. Section 11, MARK [A] Exelon. ENTER your name and an outside phone number that the state agencies can use to call back if necessary.

2. Section 12, ASK for the name of the IEMA representative that received the NARS message, THEN ENTER this information on the NARS form.

4.3.9. REPEAT the roll call for each agency listed under the NARS code used and:

1. ASK if there are any questions about the information provided.

2. CLARIFY NARS message data questions at this time.

4.3.10. STATE NARS communication is complete.

4.3.11. If any agency that was present for the initial roll-call does not answer the final roll-call, THEN CONTACT that agency via commercial telephone line.

1. USE the ERF Telephone Directory to find the commercial telephone numbers needed.

2. CALL any agency listed as REQUIRED TO BE NOTIFIED immediately.

3. INFORM the Emergency Director of all non-contacts on the NARS network.

4.3.12. STANDBY to receive NARS verification call backs from the affected state agencies.

4.3.13. STANDBY to receive State NARS call, initiated by IEMA (Instructions for receiving a NARS Message are found in section 4.4).

EP-MW-114-100 Revision 12 Page 11 of 13 4.4. RECEIVING A NARS MESSAGE NOTE: The State of Iowa receives the Utility NARS message but does not use this system to communicate back to their Local Counties and agencies.

4.4.1. Following the issuance of a Utility NARS message, the State of Illinois has two possible return calls they make back that could involve the affected site.

Confirmation Call - IEMA may call back to the Utility to confirm the authenticity of the Utility NARS message prior to their taking action on the message. This call should come into the number listed as the "Outside Phone Number" in Block 11 of the NARS form. When receiving this call, answer IEMA's questions pertaining to the call.

State NARS Message - Following the issuance of a Utility NARS Message, the State of Illinois will use the NARS, as necessary, to communicate the information provided by the Utility and their recommendations to the Local and County organizations in the affected area.

NOTE: If the NARS line is not answered within 45 seconds for an incoming call, it will stop ringing. Dialing 50 will allow entry to the bridge.

4.4.2. ANSWER the NARS phone when it rings.

1. If a busy signal is received, THEN DIAL 50 to enter the bridge.

2. ANNOUNCE who you are following the connect beep.

4.4.3. RESPOND to the Roll Call as read by the state communicator.

4.4.4. DOCUMENT the information provided on the NARS form. Do not ask questions as the information is being provided, an opportunity to ask questions will be provided at the end of the call.

4.4.5. RESPOND to IEMA's query for an Exelon Nuclear representative in Block 12 of the NARS form.

4.4.6. ASK questions of the state communicator when they indicate the opportunity to do so. Clarify information provided as needed and specifically any information that differed from the information that was provided by the Utility.

4.4.7. DISTRIBUTE the completed State NARS Message.

EP-MW-114-100 Revision 12 Page 12 of 13 4.5. FOLLOW-UP NOTIFICATIONS NOTE: Follow-up notifications are the responsibility of the EOF. State updates are required at the top of the hour, plus or minus ten minutes, starting in the second hour following a classification of Alert or higher.

The facility in Command and Control is ultimately responsible for ensuring that the State updates are completed in a timely manner.

Commercial telephone numbers for the State and all other contacted agencies are listed in Section (Tab) 10 of the ERF Telephone Directory.

4.5.1. OBTAIN update data as required for:

1. Form EP-MW-114-100-F-02, "Management State Update Information (PWR)"

2. Form EP-MW-114-100-F-03, "Management State Update Information (BWR)"

3. Form EP-MW-114-100-F-04, "Radiological State Update Information" 4.5.2. CONTACT State agency personnel (by the State Decision-Makers Hotline or from the numbers provided in the ERF Telephone Directory) and DISCUSS the event.

1. For BW, BY, CL, DR or LS, use the IL State Decision-Makers Hotline (EOF) or commercial line to contact the REAC Manager.

2. For QC, use the QC State Decision-Makers Hotline or commercial line to contact the REAC Manager and the Iowa Emergency Operations Center simultaneously.

4.5.3. DIRECT the State Environmental Coordinator to contact the applicable state counterparts and discuss the information on form EP-MW-114-100-F-04, Radiological State Update Information.

1. For BW, BY, CL, DR or LS, contact the REAC Environmental Analyst (call the number listed for REAC and ask for the Environmental Analyst).

2. For QC, contact separately both the REAC Environmental Analyst and the IEMD Health Physics Hotline.

EP-MW-114-100 Revision 12 Page 13 of 13

5. DOCUMENTATION 5.1. The following forms when completed during a declared event document implementation of this procedure.

EP-AA-111-F-02, Braidwood Plant Based PAR Flowchart EP-AA-111-F-03, Byron Plant Based PAR Flowchart EP-AA-111-F-04, Dresden Based PAR Flowchart EP-AA-111-F-05, LaSalle Based PAR Flowchart EP-AA-111-F-06, Quad Based PAR Flowchart EP-AA-111-F-07, Clinton Based PAR Flowchart EP-MW-114-100-F-01, Nuclear Accident Reporting System (NARS) Form EP-MW-114-100-F-02, Management State Update Information (PWR)

EP-MW-114-100-F-03, Management State Update Information (BWR)

EP-MW-114-100-F-04, Radiological State Update Information 5.2. The Standard Records Retention ID for the above documents per the Standards Records Retention Schedule is 5B.100.

6. REFERENCES

- EP-MW-110-1001, Data Point Tables

- EP-AA-114-F-01, PWR Release in Progress Determination Guidance

- EP-AA-114-F-02, "BWR Release In Progress Determination Guidance"

7. ATTACHMENTS None

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.

INITIATING CUES:

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

2. 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.

3. 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: CERT 2013 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.

INITIATING CUES:

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

2. The RO has completed the following:

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

Calculated a reactivity change to match Tave to Tref following the manual rod withdrawal.

2 S-111A

3. 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 steps for a total 1.5 F.

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 NOTE: IF examinee fails to boric acid required is 1.5 identify the temperature error, times (25-26) = 37.5 to 39 skip to JPM step 6. gallons boric acid.

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 is acceptable.

Cue: Provide corrected Attachment 1 completed (boric acid calculation of 37.5-39 gallons).

4 S-111A

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.

7. Approves reactivity change

Signs as SRO approval SAT UNSAT N/A on Attachment 1 Comments:

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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , 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 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , 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 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for complete mixing to occur.

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

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 2 Page 4 of 4 ATTACHMENT 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 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______ ______________ ______________

Preparer Reviewer Approver (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 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 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 0.00722 hours 4.298942e-5 weeks 9.893e-6 months . 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 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months ), 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 0.00389 hours 2.314815e-5 weeks 5.327e-6 months 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 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months ) 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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . 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 0.00389 hours 2.314815e-5 weeks 5.327e-6 months 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ).

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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 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 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 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. The inability to dilute out the soluble boron due to the very low boron concentration.

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)

OP-AP-300-1004 Revision 2 Page 4 of 4 ATTACHMENT 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 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______ ______________ ______________

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

Shift Manager Notified: Yes No

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 5

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: (*) 2, 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.

MATERIALS:

1. 0BwOA ELEC-1 Rev. 8.

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 5

RECORD START TIME ____________

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 Determine Type of State SAT UNSAT N/A Estimator 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

Abnormal grid -

(from task conditions) PREDICTED CONDITION

Predicted due to a

Abnormal grid predicted Braidwood Unit trip (from due to BRAIDWOOD task conditions) 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 Kva.

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

5183 Kva.

CALCULATE Unit 2 4 KV Non-ESF Bus Loading

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

4892 Kva

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

4892 Kv S-107 Page 3 of 5

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::

Identifies that Unit 1 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.

CUE: THIS COMPLETES THIS JPM.

RECORD STOP TIME ____________

COMMENTS:

S-107 Page 4 of 5

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 5 of 5

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:

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 current values used in QPTR Calculation.

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.

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:

CUE: All present and 100% Lower Detector Currents values of Upper and are recorded correctly from Lower Detector currents NIS drawer front are accurate. 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 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

completed this shift as a result of the QPTR result.

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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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: ___________________________________

{PRIVATE }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) ¢ ¢ ¢ ¢

{PRIVATE }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: ___________________________________

{PRIVATE }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

{PRIVATE }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

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 that the

Enter release duration BwOP WX-501T1 release (638 mins from BwOP duration is 638 minutes. WX-501T1 step D.6.f.2)

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

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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . (N/A this step if no releases in last 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .)

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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . (N/A this step if no releases in the last 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .)

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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of the completion of the last release.

________ N/A __________________________/________/________

Supervisor Notified Date Time RECORD release start time (24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 __2.02E-7_ µCi/ml

2 __2.02E-7__ µCi/ml

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 #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 If 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 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 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 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 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .)

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 Station 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 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 Station 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 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: Rad Protection Manager signs EP-AA-113-F-02.

has reviewed and signed EP-AA-113-F-02.

Ensures Rad Protection Management signs EP-AA-113-F-02.

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_Manager_____________________________ __Today/Now___

Rad. Protection Management (Review) Date / Time

____Examinee________________________________________ _ Today/Now __

Station Emergency Director (Authorization) Date / Time

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-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

Station Emergency Director (Authorization) Date / Time

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

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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months following exposure.

Ineffective if taken more than 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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.

JOB PERFORMANCE MEASURE TASK CONDITIONS:

1. You are the Unit 1 NSO.

2. Unit 1 is at 100% power.

3. Maintenance was performed last shift to repair shutdown bank C rod control.

INITIATING CUES:

1. The Unit 1 Unit Supervisor has directed you to perform 1BwOSR 3.1.4.2, Unit One Movable Control Assemblies Surveillance, for shutdown bank C rods.

2. All Prerequisites Precautions, Limitations & Actions of 1BwOSR 3.1.4.2 have been met.

3. Another NSO will monitor the remainder of the Main Control Board panels and address alarms as necessary.

4. Inform the Unit 1 Unit Supervisor when you have completed 1BwOSR 3.1.4.2 for shutdown bank C rods.

SIM-102 Page 1 of 6

TASK TITLE: Perform Movable Control Assemblies Surveillance JPM No.: SIM-102 Rev: 2013 NRC Task No.: R-RD-004 K&A No.: 00100A4.03 Objective: 4.C.GP-04 K&A IMP: 4.0/3.7 EXAMINEE: RO SRO (Circle One)

EVALUATOR: DATE:

The Examinee: PASSED this JPM. TIME STARTED:

FAILED TIME FINISHED:

JPM TIME: MINUTES CRITICAL ELEMENTS: (*) 3, 5, 6, 7, 8 APPROX COMPLETION TIME: 30 MINUTES CRITICAL TIME: NA EVALUATION METHOD: LOCATION:

X PERFORM IN PLANT SIMULATE X SIMULATOR GENERAL

REFERENCES:

1. 1BwOSR 3.1.4.2, UNIT ONE MOVABLE CONTROL ASSEMBLIES QUARTERLY SURVEILLANCE, Rev 23.

MATERIALS:

1. 1BwOSR 3.1.4.2, UNIT ONE MOVABLE CONTROL ASSEMBLIES QUARTERLY SURVEILLANCE, Rev 23.

TASK STANDARDS:

1. Perform rod movement verification of shutdown bank C rods.

TASK CONDITIONS:

1. You are the Unit 1 NSO.

2. Unit 1 is at 100% power.

3. Maintenance was performed last shift to repair shutdown bank C rod control.

INITIATING CUES:

1. The Unit 1 Unit Supervisor has directed you to perform 1BwOSR 3.1.4.2, Unit One Movable Control Assemblies Surveillance, for shutdown bank C rods.

CUE: Hand examinee copy of 1BwOSR 3.1.4.2.

2. All Prerequisites, Precautions, Limitations & Actions of 1BwOSR 3.1.4.2 have been met.

3. Another NSO will monitor the remainder of the Main Control Board panels and address alarms as necessary.

4. Inform the Unit 1 Unit Supervisor when you have completed 1BwOSR 3.1.4.2 for shutdown bank C rods.

SIM-102 Page 2 of 6

RECORD START TIME:

NOTE: As examiner, role play peer check and concur with any recommendations from the examinee.

PERFORMANCE STEP STANDARD CIRCLE APPLICABLE

1. Refer to 1BwOSR 3.1.4.2. Refer to 1BwOSR 3.1.4.2. SAT UNSAT N/A

VERIFY all applicable

VERIFY all applicable Comments:

Prerequisites, Precautions, Prerequisites, Precautions, and Limitations and Actions and Limitations and are satisfactorily addressed Actions are satisfactorily (step F.2.1). addressed.

CUE: All Prerequisites, Precautions, Limitations and Actions have been met.

2. Transfer Rod Control to Manual Perform the following at SAT UNSAT N/A and Verify Tave is matched to Tref 1PM05J: Comments:

(step F.2.2).

Place the Rod Bank Select switch to the MAN position.

Verify Tave matched to Tref.

3. Select Shutdown Bank C with SAT UNSAT N/A Rod Bank Select Switch.

Place rod bank select Comments:

switch in SBC.

4. Record initial rod data. Record initial group step SAT UNSAT N/A counter readings (ARO park Comments:

228) and DRPI readings (228) for SBC on Table 1 (Page D-2).

5. Insert SBC one step Place rod motion control SAT UNSAT N/A CUE: As Unit Supervisor, switch to in and insert SBC to Comments:

acknowledge reports of (ARO park 228 -1 = 227) annunciators due to rod motion steps on group step counter.

as they occur.

(Failure: if examinee moves any other bank)

6. Withdraw SBC to step 231

Place rod motion control SAT UNSAT N/A switch to out and withdraw Comments:

SBC to 231 steps on group step counter.

o Verify DRPI indicates

>222.

SIM-102 Page 3 of 6

PERFORMANCE STEP STANDARD CIRCLE APPLICABLE

7 Insert SBC 10-15 steps

Place rod motion control SAT UNSAT N/A switch to in and insert SBC Comments:

10-15 steps as indicated (Failure criteria: DRPI 210 light lit) on the group step counter (far enough to cause a DRPI change of > 10 steps).

o Record the group step counter reading and the DRPI readings for SBC on Table 1 (Page D-2).

o Verify each rod in SBC indicates movement > 10 steps and record by checking the appropriate box.

8 Withdraw SBC to original

Place rod motion control SAT UNSAT N/A position switch to out and withdraw Comments:

SBC to ARO park 228 steps on group step counter.

o Record the final group step counter reading (ARO park 228) and DRPI readings (228) for SBC on Table 1 (Page D-2).

o Verify SBC DRPI > 222 steps.

o Verify that all rods of SBC are at the initial position recorded on Table 1 (Page D-2).

o Verify the SBC is within the limits specified in the COLR.

o Complete Table 1 for the SBC within the insertion limits of the COLR by checking the appropriate box.

SIM-102 Page 4 of 6

PERFORMANCE STEP STANDARD CIRCLE APPLICABLE

9. Rod Control Restoration. (step Restore Rod Control as SAT UNSAT N/A F.4). follows: Comments:

CUE: If asked, the Bank Overlap Counter has not

Verify controlling Control changed since Bank is in its original commencing this position.

surveillance.

Place the Rod Bank Select NOTE: If asked to perform Switch to MANUAL.

independent verifications in the

Verify Low Power Interlock following steps, provide C-5 NOT LIT.

the following cue as

Obtain Independent asked: Verification of C-5 NOT CUE: Verification has been LIT.

provided.

Verify Tave/Tref deviation NOTE: If asked for desired < 1 °F.

alignment of rod control

Verify the following systems, provide the Annunciators are clear:

following cue:

1-10-A6, ROD BANK CUE: Unit Supervisor desires LO-2 INSERTION automatic rod control. LIMIT.

1-10-A7, ROD DEV POWER RNG TILT.

1-10-B6, ROD BANK LOW INSERTION LIMIT.

Obtain Independent Verification that the above annunciators are clear.

Place the Rod Bank Select Switch to AUTO.

Obtain Independent Verification of Rod Bank Select Switch in AUTO.

CUE: All ductwork has been

Verify all required RD reinstalled. cabinet ductwork has been reinstalled.

10. Acknowledge completion of Inform the Unit 1 Unit surveillance, and terminate the Supervisor that you have JPM. completed 1BwOSR 3.1.4.2 for shutdown bank C rods CUE: THIS COMPLETES THIS JPM.

RECORD STOP TIME:

COMMENTS:

SIM-102 Page 5 of 6

SIMULATOR SETUP INSTRUCTIONS

Verify/perform TQ-BR-201-0113, BRAIDWOOD TRAINING DEPARTMENT SIMULATOR EXAMINATION SECURITY ACTIONS CHECKLIST.

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

Complete items on Simulator Ready for Training Checklist.

Place simulator in RUN.

Verify CBD at 220 steps.

Record ARO park position in body JPM where ARO park ___ designated (see JPM steps 4, 5, 8) IF NOT ALREADY FILLED IN FOR THE JPM.

COMMENTS

Provide examinee copy of 1BwOSR 3.1.4.2, UNIT ONE MOVABLE CONTROL ASSEMBLIES SURVEILLANCE.

(Final)

SIM-102 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 3.1.4.2____

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

PMID/RQ

Title:

MOVABLE CONTROL ASSEMBLY SURVIELLANCE ________

PMID/RQ Due Date: ___ N/A________ PMID/RQ Late Date: N/A Signature/Authorization Approval Review: Name Date Time Shift Authorization to Start Work: ___Joe Supervisor ______ Today 5 min ago Work Started __________________________ ________ ________

Work Stopped: __________________________ ________ ________

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 (partial surveillance) PMT for Shutdown Bank C ADDITIONAL REVIEW OF RESULTS (IF REQUIRED)

Title Signature Date

WC-AA-111 Revision 4 Page 25 of 61

PROCEDURE NO.

1BwOSR 3.1.4.2 UNIT NO. REVISION NO.

1 23 BRAIDWOOD STATION PROCEDURE TITLE:

UNIT ONE MOVABLE CONTROL ASSEMBLIES SURVEILLANCE Rev Summary IR# / EC# (if applicable) 23 Remove EC 368959 requirements from procedure (EC PCRA 1230957-30 was closed but procedure revisions never reflected the removal of the EC.)

1BwOSR 3.1.4.2 Revision 23 Continuous Use UNIT ONE MOVABLE CONTROL ASSEMBLIES SURVEILLANCE A. STATEMENT OF APPLICABILITY This procedure outlines the steps necessary to verify the OPERABILITY of each Movable Control Assembly by movement of at least 10 steps in any one direction and is applicable in MODES 1 and 2. This procedure SHALL be performed either:

1. As scheduled,

2. Non-routinely in conjunction with a Reactor Startup or Rod Malfunction or,

3. To align the rods to a new ARO park position as determined by Reactor Engineering.

B. REFERENCES

1. Tech Spec LCOs:

a. 3.1.4.

b. 3.1.5.

c. 3.1.6.

2. Tech Spec Surveillance Requirement: 3.1.4.2.

3. Station Procedures:

a. 1BwGP 100-2, Reactor Startup

b. 1BwGP 100-8, Generic Reactor Control Guidance

c. 1BwOL 3.1.4, LCOAR - Reactivity Control Systems - Movable Control Assemblies - Group Height 1

1BwOSR 3.1.4.2 Revision 23 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.

NOTE The following Prerequisite may require MMD support to remove and re-install interfering ductwork at the RD Power Supply Cabinets.

2. A visual inspection inside of all 5 RD power cabinets has been performed ensuring no blown fuse indicators tripped (reference Attachment D for blown fuse illustration).

3. The Reactor is operating in steady state conditions, if this surveillance is being performed with the Unit in Mode 1.

4. BwCB-1 Table 4-1 has been revised to indicate the ARO park position, if necessary.

5. A visual inspection outside of all 5 RD power cabinets indicates that one GROUP SELECT light is LIT per cabinet.

6. Prior to initiating rod motion, refer to the Rod Control Operation section of 1BwGP 100-8.

2

1BwOSR 3.1.4.2 Revision 23 Continuous Use D. PRECAUTIONS NOTE All of the following precautions are only applicable for performance of Subsection 2.0.

1. Prior to transferring Rod Control to the automatic MODE, VERIFY:

a. Permissive C-5 is extinguished.

b. VERIFY Tave/Tref deviation 1°F.

2. Avoid variations in plant load, Reactor Coolant temperature, and Boron concentration.

3. DO NOT allow Tave changes of greater than -4°F or +1°F. Compensate by intermittent rod movement to match Tave/Tref.

4. If any control rod group (except Control Bank D) is withdrawn past 231 steps, STOP the surveillance. PERFORM Attachment A, Rod Bank Realignment to return the affected bank to the ARO position and resume testing of the remaining rods as required. If Control Bank D is withdrawn past 231, STOP the surveillance. PERFORM Attachment A, Rod Bank Realignment, to return Control Bank D to initial position.

3

1BwOSR 3.1.4.2 Revision 23 Continuous Use E. LIMITATIONS AND ACTIONS

1. As stated in Tech Spec LCOs 3.1.4, 3.1.5 and 3.1.6.

2. If the Acceptance Criteria (¢) is not met during the performance of this surveillance, IMMEDIATELY notify the Shift Manager or designee to initiate LCOAR 1BwOL 3.1.4 if in MODES 1 or 2.

3. Each Rod Bank tested must be returned to the rod insertion limits specified in the COLR (for Shutdown Rods) and to its original or new ARO park position (for Control Rods) to ensure the limits of Tech Spec 3.1.5 and 3.1.6 are not exceeded prior to proceeding to the next Rod Bank (N/A if performing Subsection 1.0).

4. Annunciators 1-10-A6, "ROD BANK LO-2 INSERTION LIMIT", 1-10-B6, "ROD BANK LOW INSERTION LIMIT", and 1-12-C1, PZR PRESS CONT DEV LOW HTRS ON, may alarm during movement of the Control Banks.

5. Annunciator 1-10-A7, "ROD DEV POWER RNG TILT" may alarm during movement of the Shutdown Banks or Control Banks.

6. It is permissible to place DRPI in Half Accuracy MODE, as required, if data failures prohibit performing this surveillance. Prior to placing DRPI in Half Accuracy, an evaluation shall be performed to verify loss of both A & B Channels to individual rods will not occur. (Sections 1.0 and 2.0 only)

7. Annunciator 1-10-A7, SER point 2153, should be considered inoperable during the performance of Section 3.0. If this section can not be completed, the computer points reset and the alarm cleared within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , then 1BwOS RD-2 should be completed within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months of the alarm condition.

8. Westinghouse has suggested that performing an insertion step, as opposed to a withdraw step, as the first step may minimize the probability of a dropped rod during rod movement.

4

1BwOSR 3.1.4.2 Revision 23 Continuous Use F. MAIN BODY NOTE Initial each step in the space provided adjacent to the procedure step number AFTER the step has been successfully completed.

Person(s) performing VERIFICATIONS SHALL initial in the space provided following the step.

0.0 SURVEILLANCE OVERVIEW 0.1 Parallel Subsections 1.0, 2.0, and 3.0 are independent of one another so that either Subsection may be performed.

0.2 Performance of either Subsection 1.0, or 2.0 fully satisfies the surveillance requirement.

0.3 Performance of the steps in either Subsections 1.0 or 2.0 for less than all Movable Control Assemblies is acceptable if a partial surveillance is required.

The Shift Manager or designee SHALL determine the steps to be performed.

The Data Package Cover Sheet must indicate that a partial surveillance was performed, which rod(s) were exercised, and the reason(s) why stated in the comments section.

0.4 Subsection 3.0 will establish a new ARO park position. This subsection may be performed after the rods have been exercised in Subsection 2.0 or independently to establish a new ARO park position. Performance of this Subsection is optional.

5

1BwOSR 3.1.4.2 Revision 23 Continuous Use F. 0.5 The Subsections perform the following:

F.1.0 Takes credit for the movement of the Shutdown and Control Banks during a Reactor Startup.

F.2.0 Actually moves the Shutdown and Control Banks when the UNIT is at power and restores the rods to their original position.

F.3.0 Established a new ARO park position.

F.4.0 Restores rod control and must always be performed after Subsections F.2.0 or F.3.0.

START Rod Movement Verification During 1.0 Startup Rod Movement Establishes a new ARO Verification 2.0 3.0 Park Position During Operation 4.0 Restoration END 6

1BwOSR 3.1.4.2 Revision 23 Continuous Use F. 1.0 ROD MOVEMENT VERIFICATION DURING STARTUP

_____ 1.1 VERIFY all applicable PREREQUISITES, PRECAUTIONS, and LIMITATIONS AND ACTIONS are satisfactorily addressed.

¢ ____ 1.2 During the withdrawal of the Shutdown Banks as directed in 1BwGP 100-2, VERIFY each rod moved at least 10 steps.

¢ ____ 1.3 During the withdrawal of the Control Banks as directed in 1BwGP 100-2, VERIFY each rod moved at least 10 steps.

NOTE The following step may be marked N/A at the discretion of the SM/Designee if the RD cabinet ductwork is required to remain removed for additional surveillances of other RD work.

_____ 1.4 VERIFY all required RD cabinet ductwork has been re-installed.

7

1BwOSR 3.1.4.2 Revision 23 Continuous Use F. 2.0 ROD MOVEMENT VERIFICATION DURING OPERATION

_____ 2.1 VERIFY all applicable PREREQUISITES, PRECAUTIONS, and LIMITATIONS AND ACTIONS are satisfactorily addressed.

2.2 VERIFY/TRANSFER rod control to MANUAL and ESTABLISH Tave/Tref match:

_____ a. VERIFY/PLACE the Rod Bank Select switch to the MAN position.

_____ b. MAINTAIN Tave matched with Tref.

NOTE As long as the Shutdown Bank is above 224 steps, as indicated by the bank demand step counters and verified by DRPI, indicating 222 steps, the rod insertion limits are met as specified in the COLR.

Westinghouse has suggested that performing an insertion step, as opposed to a withdraw step, as the first step may minimize the probability of a dropped rod during rod movement.

2.3 PERFORM the rod movement verification for the Shutdown Rods as follows:

NOTE The Bank order of the Shutdown Rod movement verifications may be done in any order. The preferred order is Shutdown Bank E, D, C, B, A.

Shutdown Bank E

1) SELECT Shutdown Bank E on the Rod Bank Select.

2) RECORD the initial Group Step Counter reading and the DRPI readings for Shutdown Bank E on TABLE 1.

3) INSERT Shutdown Bank E one step from the initial Group Step Counter reading recorded on TABLE 1 Shutdown Bank E. (This step N/A if Group Step Counter already at 231 steps).

NOTE Annunciator 1-10-A7, "ROD DEV POWER RNG TILT", may alarm in the following step.

4) VERIFY/WITHDRAW Shutdown Bank E to 231 steps on the Group Step Counter.

8

1BwOSR 3.1.4.2 Revision 23 Continuous Use F. 2.3 5) RECORD the withdrawn to 231 Group Step Counter reading and the DRPI readings for the Shutdown Bank E on Table 1.

6) VERIFY DRPI indicates 222 steps withdrawn.

7) INSERT Shutdown Bank E 10 to 15 steps as indicated on the associated Group Step Counter (ensure the insertion is sufficient to result in a DRPI change of greater than or equal to 10 steps indicated).

8) RECORD the Group Step Counter reading and the DRPI readings for Shutdown Bank E on TABLE 1.

¢ 9) VERIFY/RECORD (by checking the appropriate box), that each rod in Shutdown Bank E indicates movement greater than or equal to 10 steps.

10) WITHDRAW Shutdown Bank E to the initial Group Step Counter reading.

11) RECORD the final Group Step Counter reading and the DRPI readings for Shutdown Bank E on TABLE 1.

12) VERIFY Shutdown Bank E DRPI reading 222 steps.

NOTE DRPI indication may vary by one position from the initial reading if the control rod is between coils. This is acceptable if the deviation is off by only one position.

13) VERIFY that all rods in the Shutdown Bank E are at the initial position recorded TABLE 1.

14) VERIFY Shutdown Bank E is within the insertion limits specified in the COLR.

15) VERIFY/COMPLETE TABLE 1 for Shutdown Bank E.

9

1BwOSR 3.1.4.2 Revision 23 Continuous Use F. 2.3 Shutdown Bank D

1) SELECT Shutdown Bank D on the Rod Bank Select switch.

2) RECORD the initial Group Step Counter reading and the DRPI readings for Shutdown Bank D on TABLE 1.

3) INSERT Shutdown Bank D one step from the initial Group Step Counter reading recorded on TABLE 1 for Shutdown Bank D. (This step N/A if Group Step Counter already at 231 steps).

NOTE Annunciator 1-10-A7, "ROD DEV POWER RNG TILT", may alarm in the following step.

4) VERIFY/WITHDRAW Shutdown Bank D to 231 steps on the Group Step Counter.

5) RECORD the withdrawn to 231 Group Step Counter reading and the DRPI readings for the Shutdown Bank D on Table 1.

6) VERIFY DRPI indicates 222 steps withdrawn.

7) INSERT Shutdown Bank D 10 to 15 steps as indicated on the associated Group Step Counter (ensure the insertion is sufficient to result in a DRPI change of greater than or equal to 10 steps indicated).

8) RECORD the Group Step Counter reading and the DRPI readings for Shutdown Bank D on TABLE 1.

¢ 9) VERIFY/RECORD (by checking the appropriate box), that each rod in Shutdown Bank D indicates movement greater than or equal to 10 steps.

10) WITHDRAW Shutdown Bank D to the initial Group Step Counter reading.

11) RECORD the final Group Step Counter reading and the DRPI readings for Shutdown Bank D on TABLE 1.

12) VERIFY Shutdown Bank D DRPI reading 222 steps.

10

1BwOSR 3.1.4.2 Revision 23 Continuous Use NOTE DRPI indication may vary by one position from the initial reading if the control rod is between coils. This is acceptable if the deviation is off by only one position.

F. 2.3 13) VERIFY that all rods in the Shutdown Bank D are at the initial position recorded TABLE 1.

14) VERIFY Shutdown Bank D is within the insertion limits specified in the COLR.

15) VERIFY/COMPLETE TABLE 1 for Shutdown Bank D.

11

1BwOSR 3.1.4.2 Revision 23 Continuous Use F. 2.3 Shutdown Bank C

1) SELECT Shutdown Bank C on the Rod Bank Select switch.

2) RECORD the initial Group Step Counter reading(s) and the DRPI readings for Shutdown Bank C on TABLE 1.

3) INSERT Shutdown Bank C one step from the initial Group Step Counter reading recorded on TABLE 1 for Shutdown Bank C. (This step N/A if Group Step Counter already at 231 steps).

NOTE Annunciator 1-10-A7, "ROD DEV POWER RNG TILT", may alarm in the following step.

4) VERIFY/WITHDRAW Shutdown Bank C to 231 steps on the Group Step Counter.

5) RECORD the withdrawn to 231 Group Step Counter reading and the DRPI readings for the Shutdown Bank C on Table 1.

6) VERIFY DRPI indicates 222 steps withdrawn.

7) INSERT Shutdown Bank C 10 to 15 steps as indicated on the associated Group Step Counter (ensure the insertion is sufficient to result in a DRPI change of greater than or equal to 10 steps indicated).

8) RECORD the Group Step Counter reading and the DRPI readings for Shutdown Bank C on TABLE 1.

¢ 9) VERIFY/RECORD (by checking the appropriate box), that each rod in Shutdown Bank C indicates movement greater than or equal to 10 steps.

10) WITHDRAW Shutdown Bank C to the initial Group Step Counter reading.

11) RECORD the final Group Step Counter reading and the DRPI readings for Shutdown Bank C on TABLE 1.

12) VERIFY Shutdown Bank C DRPI reading 222 steps.

12

1BwOSR 3.1.4.2 Revision 23 Continuous Use NOTE DRPI indication may vary by one position from the initial reading if the control rod is between coils. This is acceptable if the deviation is off by only one position.

F. 2.3 13) VERIFY that all rods in the Shutdown Bank C are at the initial position recorded TABLE 1.

14) VERIFY Shutdown Bank C is within the insertion limits specified in the COLR.

15) VERIFY/COMPLETE TABLE 1 for Shutdown Bank C.

13

1BwOSR 3.1.4.2 Revision 23 Continuous Use F. 2.3 Shutdown Bank B

1) SELECT Shutdown Bank B on the Rod Bank Select switch.

2) RECORD the initial Group Step Counter reading(s) and the DRPI readings for Shutdown Bank B on TABLE 1.

3) INSERT Shutdown Bank B one step from the initial Group Step Counter reading recorded on TABLE 1 for Shutdown Bank B. (This step N/A if Group Step Counter already at 231 steps).

NOTE Annunciator 1-10-A7, "ROD DEV POWER RNG TILT", may alarm in the following step.

4) VERIFY/WITHDRAW Shutdown Bank B to 231 steps on the Group Step Counters.

5) RECORD the withdrawn to 231 Group Step Counter readings and the DRPI readings for the Shutdown Bank B on Table 1.

6) VERIFY DRPI indicates 222 steps withdrawn.

7) INSERT Shutdown Bank B 10 to 15 steps as indicated on the associated Group Step Counter(s) (ensure the insertion is sufficient to result in a DRPI change of greater than or equal to 10 steps indicated).

8) RECORD the Group Step Counter reading(s) and the DRPI readings for Shutdown Bank B on TABLE 1.

¢ 9) VERIFY/RECORD (by checking the appropriate box), that each rod in Shutdown Bank B indicates movement greater than or equal to 10 steps.

10) WITHDRAW Shutdown Bank B to the initial Group Step Counter reading.

11) RECORD the final Group Step Counter reading(s) and the DRPI readings for Shutdown Bank B on TABLE 1.

12) VERIFY Shutdown Bank B DRPI reading 222 steps.

14

1BwOSR 3.1.4.2 Revision 23 Continuous Use NOTE DRPI indication may vary by one position from the initial reading if the control rod is between coils. This is acceptable if the deviation is off by only one position.

F. 2.3 13) VERIFY that all rods in the Shutdown Bank B are at the initial position recorded TABLE 1.

14) VERIFY Shutdown Bank B is within the insertion limits specified in the COLR.

15) VERIFY/COMPLETE TABLE 1 for Shutdown Bank B.

15

1BwOSR 3.1.4.2 Revision 23 Continuous Use F. 2.3 Shutdown Bank A

1) SELECT Shutdown Bank A on the Rod Bank Select switch.

2) RECORD the initial Group Step Counter reading(s) and the DRPI readings for Shutdown Bank A on TABLE 1.

3) INSERT Shutdown Bank A one step from the initial Group Step Counter reading recorded on TABLE 1 for Shutdown Bank A. (This step N/A if Group Step Counter already at 231 steps).

NOTE Annunciator 1-10-A7, "ROD DEV POWER RNG TILT", may alarm in the following step.

4) VERIFY/WITHDRAW Shutdown Bank A to 231 steps on the Group Step Counters.

5) RECORD the withdrawn to 231 Group Step Counter readings and the DRPI readings for the Shutdown Bank A on Table 1.

6) VERIFY DRPI indicates 222 steps withdrawn.

7) INSERT Shutdown Bank A 10 to 15 steps as indicated on the associated Group Step Counter(s) (ensure the insertion is sufficient to result in a DRPI change of greater than or equal to 10 steps indicated).

8) RECORD the Group Step Counter reading(s) and the DRPI readings for Shutdown Bank A on TABLE 1.

¢ 9) VERIFY/RECORD (by checking the appropriate box), that each rod in Shutdown Bank A indicates movement greater than or equal to 10 steps.

10) WITHDRAW Shutdown Bank A to the initial Group Step Counter reading.

11) RECORD the final Group Step Counter reading(s) and the DRPI readings for Shutdown Bank A on TABLE 1.

12) VERIFY Shutdown Bank A DRPI reading 222 steps.

16

1BwOSR 3.1.4.2 Revision 23 Continuous Use NOTE DRPI indication may vary by one position from the initial reading if the control rod is between coils. This is acceptable if the deviation is off by only one position.

F. 2.3 13) VERIFY that all rods in the Shutdown Bank A are at the initial position recorded TABLE 1.

14) VERIFY Shutdown Bank A is within the insertion limits specified in the COLR.

15) VERIFY/COMPLETE TABLE 1 for Shutdown Bank A.

17

1BwOSR 3.1.4.2 Revision 23 Continuous Use F. 2.4 PERFORM the rod movement verification for the Control Rods as follows:

NOTE The Control Banks may be moved in or out at the discretion of the Shift Manager or Designee to meet the requirements of this surveillance. Monitor Tave and Rx Power closely and correct as needed to minimize plant transients.

NOTE If a Control Bank is fully inserted, RECORD only the Group 1 & 2 Initial Step Counter readings and MARK any other columns on the Data Table for the fully inserted Control Bank "N/A". DO NOT perform the rod exercise for that Bank. The surveillance is still considered "Complete" as Tech Specs require testing only those rods NOT fully inserted in the core.

NOTE The Bank order of the Control Rod movement verifications may be done in any order. The preferred order is Control Bank A, B, C, D to facilitate final Tave adjustment.

NOTE Based on the RIL figure in the COLR the sequence, overlap, and rod insertion limits are satisfied as long as the Control Bank is above 224 steps as indicated by the bank demand step counters and verified by DRPI. Westinghouse has suggested that performing an insertion step, as opposed to a withdraw step, as the first step may minimize the probability of a dropped rod during rod movement.

Control Bank A

1) SELECT Control Bank A on the Rod Bank Select switch.

2) RECORD the Initial Group Step Counter readings and the DRPI readings for Control Bank A on TABLE 2.

18

1BwOSR 3.1.4.2 Revision 23 Continuous Use NOTE Annunciators 1-10-A6, "ROD BANK LO-2 INSERTION LIMIT", and 1-10-B6, "ROD BANK LOW INSERTION LIMIT", may alarm in the following steps.

NOTE If failures associated with DRPI do not allow verification of 10 steps indicated movement, insertion up to 21 steps is allowed, provided DRPI vs. demanded position remains within +/- 12 steps.

F. 2.4 3) INSERT Control Bank A one step from the initial Group Step Counter reading recorded on TABLE 2 for Control Bank A. (This step N/A if Group Step Counter already at 231 steps.)

4) VERIFY/WITHDRAW Control Bank A to 231 steps on the Group Step Counters.

5) RECORD the withdrawn to 231 Group Step Counter readings and the DRPI readings for the selected Control Bank on TABLE 2.

6) VERIFY DRPI indicates 222 steps withdrawn.

19

1BwOSR 3.1.4.2 Revision 23 Continuous Use F. 2.4 7) INSERT Control Bank A 10 to 15 steps as indicated on the associated Group Step Counter(s) (ensure the insertion is sufficient to result in a DRPI change of greater than or equal to 10 steps indicated).

8) RECORD the Inserted Group Step Counter reading(s) and the DRPI readings for Control Bank A on TABLE 2.

¢ 9) VERIFY/RECORD (by checking the appropriate box), that each rod in Control Bank A indicates movement greater than or equal to 10 steps.

10) WITHDRAW Control Bank A to the Initial Group Step Counter reading.

11) RECORD the Final Group Step Counter reading(s) and the DRPI readings for Control Bank A on TABLE 2.

12) VERIFY Control Bank A DRPI reading 222 steps.

NOTE DRPI indication may vary by one position from the initial reading if the control rod is between coils. This is acceptable if the deviation is off by only one position.

13) VERIFY that all rods in Control Bank A are at the initial position recorded on TABLE 2.

20

1BwOSR 3.1.4.2 Revision 23 Continuous Use F. 2.4 14) PERFORM the following:

a) VERIFY/RECORD that the following annunciators are CLEAR:

1-10-A6, "ROD BANK LO-2 INSERTION LIMIT" 1-10-A7, "ROD DEV POWER RNG TILT" 1-10-B6, "ROD BANK LOW INSERTION LIMIT" b) IF one or more of the annunciators listed above have not cleared, PERFORM the following corrective actions, (otherwise N/A):

(1) With Reactor Engineering concurrence, WITHDRAW rods a maximum of 2 additional steps, not to exceed 231 steps, in an attempt to clear the alarm(s).

(2) RESTORE rods to the Initial Group Step Counter reading.

15) VERIFY/COMPLETE TABLE 2 for Control Bank A.

21

1BwOSR 3.1.4.2 Revision 23 Continuous Use F. 2.4 Control Bank B

1) SELECT Control Bank B on the Rod Bank Select switch.

2) RECORD the Initial Group Step Counter readings and the DRPI readings for Control Bank B on TABLE 2.

NOTE Annunciators 1-10-A6, "ROD BANK LO-2 INSERTION LIMIT", and 1-10-B6, "ROD BANK LOW INSERTION LIMIT", may alarm in the following steps.

NOTE If failures associated with DRPI do not allow verification of 10 steps indicated movement, insertion up to 21 steps is allowed, provided DRPI vs. demanded position remains within +/- 12 steps.

3) INSERT Control Bank B one step from the initial Group Step Counter reading recorded on TABLE 2 for Control Bank B. (This step N/A if Group Step Counter already at 231 steps.)

4) VERIFY/WITHDRAW Control Bank B to 231 steps on the Group Step Counters.

5) RECORD the withdrawn to 231 Group Step Counter readings and the DRPI readings for the selected Control Bank on TABLE 2.

6) VERIFY DRPI indicates 222 steps withdrawn.

7) INSERT Control Bank B 10 to 15 steps as indicated on the associated Group Step Counter(s) (ensure the insertion is sufficient to result in a DRPI change of greater than or equal to 10 steps indicated).

8) RECORD the Inserted Group Step Counter reading(s) and the DRPI readings for Control Bank B on TABLE 2.

¢ 9) VERIFY/RECORD (by checking the appropriate box), that each rod in Control Bank B indicates movement greater than or equal to 10 steps.

22

1BwOSR 3.1.4.2 Revision 23 Continuous Use F. 2.4 10) WITHDRAW Control Bank B to the Initial Group Step Counter reading.

11) RECORD the Final Group Step Counter reading(s) and the DRPI readings for Control Bank B on TABLE 2.

12) VERIFY Control Bank B DRPI reading 222 steps.

NOTE DRPI indication may vary by one position from the initial reading if the control rod is between coils. This is acceptable if the deviation is off by only one position.

13) VERIFY that all rods in Control Bank B are at the initial position recorded on TABLE 2.

14) PERFORM the following:

a) VERIFY/RECORD that the following annunciators are CLEAR:

1-10-A6, "ROD BANK LO-2 INSERTION LIMIT" 1-10-A7, "ROD DEV POWER RNG TILT" 1-10-B6, "ROD BANK LOW INSERTION LIMIT" b) IF one or more of the annunciators listed above have not cleared, PERFORM the following corrective actions, (otherwise N/A):

(1) With Reactor Engineering concurrence, WITHDRAW rods a maximum of 2 additional steps, not to exceed 231 steps, in an attempt to clear the alarm(s).

(2) RESTORE rods to the Initial Group Step Counter reading.

15) VERIFY/COMPLETE TABLE 2 for Control Bank B.

23

1BwOSR 3.1.4.2 Revision 23 Continuous Use F. 2.4 Control Bank C

1) SELECT Control Bank C on the Rod Bank Select switch.

2) RECORD the Initial Group Step Counter readings and the DRPI readings for Control Bank C on TABLE 2.

NOTE Annunciators 1-10-A6, "ROD BANK LO-2 INSERTION LIMIT", and 1-10-B6, "ROD BANK LOW INSERTION LIMIT", may alarm in the following steps.

NOTE If failures associated with DRPI do not allow verification of 10 steps indicated movement, insertion up to 21 steps is allowed, provided DRPI vs. demanded position remains within +/- 12 steps.

3) INSERT Control Bank C one step from the initial Group Step Counter reading recorded on TABLE 2 for Control Bank C. (This step N/A if Group Step Counter already at 231 steps.)

4) VERIFY/WITHDRAW Control Bank C to 231 steps on the Group Step Counters.

5) RECORD the withdrawn to 231 Group Step Counter readings and the DRPI readings for the selected Control Bank on TABLE 2.

6) VERIFY DRPI indicates 222 steps withdrawn.

7) INSERT Control Bank C 10 to 15 steps as indicated on the associated Group Step Counter(s) (ensure the insertion is sufficient to result in a DRPI change of greater than or equal to 10 steps indicated).

8) RECORD the Inserted Group Step Counter reading(s) and the DRPI readings for Control Bank C on TABLE 2.

¢ 9) VERIFY/RECORD (by checking the appropriate box), that each rod in Control Bank C indicates movement greater than or equal to 10 steps.

24

1BwOSR 3.1.4.2 Revision 23 Continuous Use F. 2.4 10) WITHDRAW Control Bank C to the Initial Group Step Counter reading.

11) RECORD the Final Group Step Counter reading(s) and the DRPI readings for Control Bank C on TABLE 2.

12) VERIFY Control Bank C DRPI reading 222 steps.

NOTE DRPI indication may vary by one position from the initial reading if the control rod is between coils. This is acceptable if the deviation is off by only one position.

13) VERIFY that all rods in Control Bank C are at the initial position recorded on TABLE 2.

14) PERFORM the following:

a) VERIFY/RECORD that the following annunciators are CLEAR:

1-10-A6, "ROD BANK LO-2 INSERTION LIMIT" 1-10-A7, "ROD DEV POWER RNG TILT" 1-10-B6, "ROD BANK LOW INSERTION LIMIT" b) IF one or more of the annunciators listed above have not cleared, PERFORM the following corrective actions, (otherwise N/A):

(1) With Reactor Engineering concurrence, WITHDRAW rods a maximum of 2 additional steps, not to exceed 231 steps, in an attempt to clear the alarm(s).

(2) RESTORE rods to the Initial Group Step Counter reading.

15) VERIFY/COMPLETE TABLE 2 for Control Bank C.

25

1BwOSR 3.1.4.2 Revision 23 Continuous Use F. 2.4 Control Bank D

1) SELECT Control Bank D on the Rod Bank Select switch.

2) RECORD the Initial Group Step Counter readings and the DRPI readings for Control Bank D on TABLE 2.

NOTE Annunciators 1-10-A6, "ROD BANK LO-2 INSERTION LIMIT", and 1-10-B6, "ROD BANK LOW INSERTION LIMIT", may alarm in the following steps.

NOTE If failures associated with DRPI do not allow verification of 10 steps indicated movement, insertion up to 21 steps is allowed, provided DRPI vs. demanded position remains within +/- 12 steps.

3) INSERT Control Bank D one step from the initial Group Step Counter reading recorded on TABLE 2 for Control Bank D. (This step N/A if Group Step Counter already at 231 steps.)

NOTE Control Bank D should NOT be withdrawn past 231 steps. It is desired to withdraw Control Bank D 10 to 15 steps, if possible.

4) VERIFY/WITHDRAW Control Bank D 10 to 15 steps, not to exceed 231 steps on the Group Step Counters.

a) RECORD the target CBD position _________ for withdrawal.

b) WITHDRAW Control Bank D to the target value.

5) RECORD the withdrawn Group Step Counter readings and the DRPI readings for the selected Control Bank on TABLE 2.

6) INSERT Control Bank D 10 to 15 steps as indicated on the associated Group Step Counter(s) (ensure the insertion is sufficient to result in a DRPI change of greater than or equal to 10 steps indicated).

7) RECORD the Inserted Group Step Counter reading(s) and the DRPI readings for Control Bank D on TABLE 2.

26

1BwOSR 3.1.4.2 Revision 23 Continuous Use

¢ F. 2.4 8) VERIFY/RECORD (by checking the appropriate box), that each rod in Control Bank D indicates movement greater than or equal to 10 steps.

9) WITHDRAW Control Bank D to the Initial Group Step Counter reading.

10) RECORD the Final Group Step Counter reading(s) and the DRPI readings for Control Bank D on TABLE 2.

NOTE DRPI indication may vary by one position from the initial reading if the control rod is between coils. This is acceptable if the deviation is off by only one position.

11) VERIFY that all rods in Control Bank D are at the initial position recorded on TABLE 2.

12) PERFORM the following:

a) VERIFY/RECORD that the following annunciators are CLEAR:

1-10-A6, "ROD BANK LO-2 INSERTION LIMIT" 1-10-A7, "ROD DEV POWER RNG TILT" 1-10-B6, "ROD BANK LOW INSERTION LIMIT" b) IF one or more of the annunciators listed above have not cleared, PERFORM the following corrective actions, (otherwise N/A):

(1) With Reactor Engineering concurrence, WITHDRAW rods a maximum of 2 additional steps, not to exceed 231 steps, in an attempt to clear the alarm(s).

(2) RESTORE rods to the Initial Group Step Counter reading.

13) VERIFY/COMPLETE TABLE 2 for Control Bank D.

27

1BwOSR 3.1.4.2 Revision 23 Continuous Use F. 3.0 ESTABLISHING NEW ARO PARK POSITION

_____ 3.1 VERIFY all applicable PREREQUISITES, PRECAUTIONS, and LIMITATIONS AND ACTIONS are satisfactorily addressed.

3.2 VERIFY/TRANSFER rod control to MANUAL and ESTABLISH Average Tave/Tref within +/- 1°F:

_____ a. VERIFY/PLACE the Rod Bank Select switch to the MAN position.

_____ b. ESTABLISH Tave within +/- 1°F of Tref using control rods, as needed.

_____ c. RECORD the new ARO park position from BwCB-1, Table 4-1 or Reactor Engineering _______________ steps.

3.3 PERFORM the following to establish the ARO park position for the Shutdown Rods:

NOTE Annunciator 1-10-A7, ROD DEV POWER RNG TILT, may alarm in the following steps.

NOTE The Bank order of the Shutdown Rod movement verifications may be done in any order. The preferred order is Shutdown Bank E, D, C, B, A.

Shutdown Bank E:

1) SELECT Shutdown Bank E on the Rod Bank Select switch.

2) RECORD the Initial Group Step Counter reading and the DRPI readings for Shutdown Bank E on TABLE 3.

3) If the new ARO park position is above the current ARO park position, INSERT Shutdown Bank E one step from the Initial Group Step Counter reading recorded on TABLE 3 for Shutdown Bank E.

28

1BwOSR 3.1.4.2 Revision 23 Continuous Use F. 3.3 4) MOVE Shutdown Bank E to the ARO park position listed in BwCB-1, Table 4-1 on the Group Step Counter.

5) VERIFY DRPI indicated 222 steps withdrawn.

6) RECORD the Final Group Step Counter reading(s) and the DRPI readings for Shutdown Bank E on TABLE 3.

7) VERIFY using Group Step Counter or DRPI, that all rods in Shutdown Bank E are at the ARO position recorded on TABLE 3.

8) VERIFY/COMPLETE TABLE 3 for Shutdown Bank E.

Shutdown Bank D:

1) SELECT Shutdown Bank D on the Rod Bank Select switch.

2) RECORD the Initial Group Step Counter reading and the DRPI readings for Shutdown Bank D on TABLE 3.

3) If the new ARO park position is above the current ARO park position, INSERT Shutdown Bank D one step from the Initial Group Step Counter reading recorded per TABLE 3.

4) MOVE Shutdown Bank D to the ARO park position listed in BwCB-1, Table 4-1 on the Group Step Counter.

5) VERIFY DRPI indicated 222 steps withdrawn.

6) RECORD the Final Group Step Counter reading and the DRPI readings for Shutdown Bank D on TABLE 3.

7) VERIFY using Group Step Counter or DRPI, that all rods in Shutdown Bank D are at the ARO position recorded on TABLE 3.

8) VERIFY/COMPLETE TABLE 3 for Shutdown Bank D.

29

1BwOSR 3.1.4.2 Revision 23 Continuous Use F. 3.3 Shutdown Bank C:

1) SELECT Shutdown Bank C on the Rod Bank Select switch.

2) RECORD the Initial Group Step Counter reading and the DRPI readings for Shutdown Bank C on TABLE 3.

3) If the new ARO park position is above the current ARO park position, INSERT Shutdown Bank C one step from the Initial Group Step Counter reading recorded on TABLE 3.

4) MOVE Shutdown Bank C to the ARO park position listed in BwCB-1, Table 4-1 on the Group Step Counter.

5) VERIFY DRPI indicated 222 steps withdrawn.

6) RECORD the Final Group Step Counter reading and the DRPI readings for Shutdown Bank C on TABLE 3.

7) VERIFY using Group Step Counter or DRPI, that all rods in Shutdown Bank C are at the ARO position recorded on TABLE 3.

8) VERIFY/COMPLETE TABLE 3 for Shutdown Bank C.

Shutdown Bank B:

1) SELECT Shutdown Bank B on the Rod Bank Select switch.

2) RECORD the Initial Group Step Counter reading and the DRPI readings for Shutdown Bank B on TABLE 3.

3) If the new ARO park position is above the current ARO park position, INSERT Shutdown Bank B one step from the Initial Group Step Counter reading recorded on TABLE 3.

4) MOVE Shutdown Bank B to the ARO park position listed in BwCB-1, Table 4-1 on the Group Step Counters.

5) VERIFY DRPI indicated 222 steps withdrawn.

6) RECORD the Final Group Step Counter reading and the DRPI readings for Shutdown Bank B on TABLE 3.

7) VERIFY using Group Step Counter or DRPI, that all rods in Shutdown Bank B are at the ARO position recorded on TABLE 3.

8) VERIFY/COMPLETE TABLE 3 for Shutdown Bank B.

30

1BwOSR 3.1.4.2 Revision 23 Continuous Use F. 3.3 Shutdown Bank A:

1) SELECT Shutdown Bank A on the Rod Bank Select switch.

2) RECORD the Initial Group Step Counter reading(s) and the DRPI readings for Shutdown Bank A on TABLE 3.

3) If the new ARO park position is above the current ARO park position, INSERT Shutdown Bank A one step from the Initial Group Step Counter reading recorded on TABLE 3.

4) MOVE Shutdown Bank A to the ARO park position listed in BwCB-1, Table 4-1 on the Group Step Counters.

5) VERIFY DRPI indicated 222 steps withdrawn.

6) RECORD the Final Group Step Counter reading(s) and the DRPI readings for Shutdown Bank A on TABLE 3.

7) VERIFY using Group Step Counter or DRPI, that all rods in Shutdown Bank A are at the ARO position recorded on TABLE 3.

8) VERIFY/COMPLETE TABLE 3 for Shutdown Bank A.

31

1BwOSR 3.1.4.2 Revision 23 Continuous Use F. 3.4 PERFORM the following to establish the new ARO park position for the Control Rods:

NOTE The Bank order to establish the ARO park position should be Control Bank A, B, and then C (if at the ARO position).

Control Bank A

1) SELECT Control Bank A on the Rod Bank Select switch.

2) RECORD the Initial Group Step Counter readings and the DRPI readings for Control Bank A on TABLE 4.

3) If the new ARO park position is above the current ARO park position, INSERT Control Bank A one step from the Initial Group Step Counter reading recorded on TABLE 4.

4) MOVE Control Bank A to the ARO park position listed in BwCB-1, Table 4-1.

5) RECORD the Final Group Step Counter reading(s) and the DRPI readings for Control Bank A on TABLE 4.

6) VERIFY DRPI indicated 222 steps withdrawn.

7) VERIFY using Group Step Counter or DRPI, that all rods in Control Bank A are at the ARO position.

8) VERIFY/COMPLETE TABLE 4 for Control Bank A.

32

1BwOSR 3.1.4.2 Revision 23 Continuous Use F. 3.4 Control Bank B

1) SELECT Control Bank B on the Rod Bank Select switch.

2) RECORD the Initial Group Step Counter readings and the DRPI readings for Control Bank B on TABLE 4.

3) If the new ARO park position is above the current ARO park position, INSERT Control Bank B one step from the Initial Group Step Counter reading recorded on TABLE 4.

4) MOVE Control Bank B to the ARO park position listed in BwCB-1, Table 4-1.

5) RECORD the Final Group Step Counter reading(s) and the DRPI readings for Control Bank B on TABLE 4.

6) VERIFY DRPI indicated 222 steps withdrawn.

7) VERIFY using Group Step Counter or DRPI, that all rods in Control Bank B are at the ARO position.

8) VERIFY/COMPLETE TABLE 4 for Control Bank B.

33

1BwOSR 3.1.4.2 Revision 23 Continuous Use F. 3.4 Control Bank C

1) SELECT Control Bank C on the Rod Bank Select switch.

2) RECORD the Initial Group Step Counter readings and the DRPI readings for Control Bank C on TABLE 4.

3) If the new ARO park position is above the current ARO park position, INSERT Control Bank C one step from the Initial Group Step Counter reading recorded on TABLE 4.

4) MOVE Control Bank C to the ARO park position listed in BwCB-1, Table 4-1.

5) RECORD the Final Group Step Counter reading(s) and the DRPI readings for Control Bank C on TABLE 4.

6) VERIFY DRPI indicated 222 steps withdrawn.

7) VERIFY using Group Step Counter or DRPI, that all rods in Control Bank C are at the ARO position.

8) VERIFY/COMPLETE TABLE 4 for Control Bank C.

_____ 3.5 VERIFY/PLACE the Rod Bank Select switch in MANUAL.

_____ 3.6 PERFORM Attachment B, Thumbwheel Switch Setting and Checkout for the new ARO park position:

_____ 3.7 NOTIFY Site IT to ADJUST the computer points as required for the new ARO position.

34

1BwOSR 3.1.4.2 Revision 23 Continuous Use F. 4.0 ROD CONTROL RESTORATION NOTE The following step is performed to ensure that the Bank Overlap Unit reflects the proper control bank position. If the controlling bank cannot be restored to its original position due to plant conditions, then RESET the Bank Overlap Unit to match the present controlling bank position prior to continuing with step 4.1

_____ 4.1 VERIFY the controlling Control Bank has been returned to its original position, using any of the following methods (N/A if rods cannot be restored due to plant conditions):

Tave within +/- 1°F of Tref , no adjustment required.

Boration.

Dilution.

Turbine load changes.

_____ 4.2 VERIFY/PLACE Rod Bank Select switch to the MANUAL position.

_____ 4.3 VERIFY Low Power Interlock C-5 NOT LIT.

VERIFICATION _____

_____ 4.4. VERIFY Tave/Tref deviation 1°F, if returning Rod Bank Select switch to AUTO.

4.5 VERIFY the following annunciators are CLEAR:

_____ a. 1-10-A6, "ROD BANK LO-2 INSERTION LIMIT".

VERIFICATION _____

_____ b. 1-10-A7, "ROD DEV POWER RNG TILT".

VERIFICATION _____

_____ c. 1-10-B6, "ROD BANK LOW INSERTION LIMIT".

VERIFICATION _____

35

1BwOSR 3.1.4.2 Revision 23 Continuous Use F ____ 4.6 VERIFY/PLACE the Rod Bank Select switch to the AUTO or MANUAL position as directed by Shift Manager or designee based on plant conditions.

AUTO/MANUAL VERIFICATION _____

NOTE The following step may be marked N/A at the discretion of the SM/Designee if the RD cabinet ductwork is required to remain removed for additional surveillances of other RD work.

_____ 4.7 VERIFY all required RD cabinet ductwork has been reinstalled.

G. ACCEPTANCE CRITERIA

1. For a complete surveillance, all Rods required to be tested have been determined OPERABLE by movement of at least 10 steps in any one direction.

2. For a partial surveillance, each Rod tested has been determined OPERABLE by movement of at least 10 steps in any one direction.

36

1BwOSR 3.1.4.2 Revision 23 Continuous Use ATTACHMENT A ROD BANK REALIGNMENT NOTE The following steps are to be used in the event a group of control rods is withdrawn past 231 steps. If the affected rod is in Shutdown Banks C, D, or E, GO TO Step 10.

1. RECORD the following information:

Affected Bank: ________________________

Group 1 step counter reading: ________________________

Group 2 step counter reading: ________________________

2. RECORD the As Found condition of the Master Cycler (Card A 105 1RD07J):

DS1 light status: ON/OFF (circle status)

DS2 light status: ON/OFF (circle status)

DS3 light status: ON/OFF (circle status) 37

1BwOSR 3.1.4.2 Revision 23 Continuous Use ATTACHMENT A (cont.)

ROD BANK REALIGNMENT NOTE DS 1 and DS 2 light status is irrelevant in the following step. DS 3 light lit is sufficient to VERIFY Master Cycler Status.

3. PERFORM either of the following:

VERIFY the Master Cycler is set for Group 2 to move inward next.

DS 3 light LIT on Card A 105 at 1RD07J ADJUST the Master Cycler using the MC+1 pushbutton so that Group 2 will move inward next.

DS 3 light LIT on Card A 105 at 1RD07J

4. RECORD the As Left condition of the Master Cycler:

DS1 light status: ON/OFF (circle status)

DS2 light status: ON/OFF (circle status)

DS3 light status: ON/OFF (circle status)

5. SET both group step counters for the affected Bank to 231 steps.

6. RECORD the following information:

Affected Bank: ______________________

Group 1 step counter reading: ______________________ steps Group 2 step counter reading: ______________________ steps 38

1BwOSR 3.1.4.2 Revision 23 Continuous Use ATTACHMENT A (cont.)

ROD BANK REALIGNMENT

7. VERIFY/ADJUST the affected bank computer point to match the affected bank step counters:

Step Counter on Rod Bank Computer Point 1PM05J Grp 1 ______________

CONT A U0049 _______________

Grp 2 ______________

Grp 1 ______________

CONT B U0050 _______________

Grp 2 ______________

Grp 1 ______________

CONT C U0051 _______________

Grp 2 ______________

Grp 1 ______________

CONT D U0052 _______________

Grp 2 ______________

Grp 1 ______________

SHUTDOWN A U0053 _______________

Grp 2 ______________

Grp 1 ______________

SHUTDOWN B U0054 _______________

Grp 2 ______________

39

1BwOSR 3.1.4.2 Revision 23 Continuous Use ATTACHMENT A (cont.)

ROD BANK REALIGNMENT

8. PERFORM the following:

a. MANUALLY insert the affected bank to 228 steps.

b. VERIFY Group 2 of the affected bank inserts before Group 1.

c. MAUALLY INSERT/WITHDRAW the affected bank to the ARO position (BwCB-1 Table 4-1)

9. IF the affected group was in a control bank, PERFORM the following at 1RD08J:

a. PLACE the P/A Display switch to the affected bank position.

b. IF required, ADJUST the setting for the affected bank to actual rod position:

1) HOLD the MANUAL/AUTO switch in the MANUAL position.

2) MOMENTARILY DEPRESS the UP/DOWN pushbutton to match the actual position of the affected bank.

3) RELEASE the MANUAL/AUTO switch.

4) RETURN to Main Body step in effect.

40

1BwOSR 3.1.4.2 Revision 23 Continuous Use ATTACHMENT A (cont.)

ROD BANK REALIGNMENT NOTE The following steps are used to align Shutdown Banks C, D, or E only.

10. RECORD the following As Found information:

Affected Bank: ______________________

Step counter reading: ______________________ steps

11. VERIFY the affected bank step counter greater than 231 steps.

12. SET the step counter to 231 steps for the affected bank.

13. MANUALLY insert the affected bank to 228 steps.

14. VERIFY proper operation of the affected bank.

15. MANUALLY INSERT/WITHDRAW the affected bank to the ARO position (BwCB-1 Table 4-1).

16. RECORD the following As Left information:

Affected Bank: ______________________

Step counter reading: ______________________ steps

17. RETURN to Main Body step in effect.

41

1BwOSR 3.1.4.2 Revision 23 Continuous Use ATTACHMENT B THUMBWHEEL SWITCH SETTING AND CHECKOUT This section sets the thumbwheel switches to the desired full out axial park position.

This section also verifies the correct setting of these switches by simulation Bank Overlap.

1. The REM or designee will RECORD the desired full out axial park position of the control rods and the desired As Left thumbwheel switch settings below. See Attachment C as a guide for required switch settings.

Full out axial park position: _________ steps.

S1- _______ S2- _______ S3- _______ S4- _______ S5- _______ S6- _______

________/________

Initial Date

2. RECORD the As Found thumbwheel switch settings for the Bank Overlap in 1RD07J.

S1- _______ S2- _______ S3- _______ S4- _______ S5- _______ S6- _______

________/________

Initial Date

3. SELECT/ENSURE the Bank Selector Switch is in MANUAL (to allow Bank Overlap to function).

________/________

Initial Date CAUTION The thumbwheel switches are designed for best operation by rotating the switches down.

4 CYCLE the thumbwheel switches S1 through S6 through complete rotation.

This should include the units, tens, and hundreds positions for all switches.

________/________

Initial Date 42

1BwOSR 3.1.4.2 Revision 23 Continuous Use ATTACHMENT B (cont.)

THUMBWHEEL SWITCH SETTING AND CHECKOUT

5. SET the thumbwheel switches S1 through S6 to the positions listed in step 1.

________/________

Initial Date

6. RECORD the As Found value of Bank Overlap step counter in Logic Cabinet.

AS FOUND ______________

________/________

Initial Date

7. RESET the Step Counter in the Logic Cabinet by DEPRESSING the reset button on the Bank Overlap Panel.

________/________

Initial Date

a. OBSERVE the step position indication resets to '000'.

________/________

Initial Date NOTE Steps 8 and 9 are performed simultaneously.

8. Using the "+1 Step" pushbutton in the Logic Cabinet, SIMULATE the rods being stepped out by DEPRESSING the "+1 Step" pushbutton as needed.

________/________

Initial Date 43

1BwOSR 3.1.4.2 Revision 23 Continuous Use ATTACHMENT B (cont.)

THUMBWHEEL SWITCH SETTING AND CHECKOUT

9. OBSERVE the indications of proper bank start and step positions. This may be done by observing DS1, DS2, DS3, and DS4 indicators on the Bank Overlap Decoder card A206 in the Logic Cabinet

a. The control bank select lights on the Bank Overlap Display (BOD) card (A206 in 1RD07J show proper selection.

0 BOU < S1 DS1 only S1 BOU < S2 DS1 and DS2 S2 BOU < S3 DS2 only S3 BOU < S4 DS2 and DS3 S4 BOU < S5 DS3 only S5 BOU < S6 DS3 and DS4 S6 BOU DS4 only

________/________

Initial Date

10. RETURN the step counter in the Logic Cabinet to its As Found value from step 6 using the +1 step push button.

AS FOUND ___________ AS LEFT ___________

________/________

Initial Date 44

1BwOSR 3.1.4.2 Revision 23 Continuous Use ATTACHMENT C ROD WITHDRAWAL/INSERTION BANK OVERLAP SEQUENCE 225 Step Full Out Axial Park Position S1 - 115 S2 - 225 S3 - 230 S4 - 340 S5 - 345 S6 - 455 (Bank Overlap - 110 steps Bank Separation - 115 steps) 226 Step Full Out Axial Park Position S1 - 115 S2 - 226 S3 - 230 S4 - 341 S5 - 345 S6 - 456 (Bank Overlap - 111 steps Bank Separation - 115 steps) 227 Step Full Out Axial Park Position S1 - 115 S2 - 227 S3 - 230 S4 - 342 S5 - 345 S6 - 457 (Bank Overlap - 112 steps Bank Separation - 115 steps) 228 Step Full Out Axial Park Position S1 - 115 S2 - 228 S3 - 230 S4 - 343 S5 - 345 S6 - 458 (Bank Overlap - 113 steps Bank Separation - 115 steps) 229 Step Full Out Axial Park Position S1 - 115 S2 - 229 S3 - 230 S4 - 344 S5 - 345 S6 - 459 (Bank Overlap - 114 steps Bank Separation - 115 steps) 45

1BwOSR 3.1.4.2 Revision 23 Continuous Use ATTACHMENT C (cont.)

ROD WITHDRAWAL/INSERTION BANK OVERLAP SEQUENCE Directions and Formulas for calculating Bank Overlap unit Switch Settings:

1. Obtain the desired Bank Separation and Bank Overlap values from Reactivity/Nuclear Engineering, as supported in the applicable COLR.

2. Bank Separation must be at least one greater than Bank Overlap; these values may never be equal.

3. Bank Separation must be at least (Full out axial park position)/2+1).

4. S1 (CBB start) = Bank Separation value.

5. S2 (CBA stop) = S1 + Bank Overlap value = Full out axial park position.

6. S3 (CBC start) = 2(S1).

7. S4 (CBB stop) = S1 + S2.

8. S5 (CBD start) = 3(S1)

9. S6 (CBC stop) = S1 + S4 46

1BwOSR 3.1.4.2 Revision 23 Continuous Use ATTACHMENT C (cont.)

ROD WITHDRAWAL/INSERTION BANK OVERLAP SEQUENCE 231 Step Full Out Axial Park Position S1 - 116 S2 - 231 S3 - 232 S4 - 347 S5 - 348 S6 - 463 (Bank Overlap - 115 steps Bank Separation - 116 steps)

Thumbwheel Switch Setting/Function CBA CBB CBC CBD

-- - 000 Start CBA Out 0 0 0 0 S1 - 116 Start CBB Out 116 0 0 0 S2 - 231 Stop CBA Out 231 115 0 0 S3 - 232 Start CBC Out 231 116 0 0 WITHDRAW S4 - 347 Stop CBB Out 231 231 115 0 S5 - 348 Start CBD Out 231 231 116 0 S6 - 463 Stop CBC Out 231 231 231 115

-- - 464 Moving CBD 116 steps 231 231 231 116 S6 - 463 Start CBC In 231 231 231 115 S5 - 348 Stop CBD In 231 231 116 0 S4 - 347 Start CBB In 231 231 115 0 S3 - 232 Stop CBC In 231 116 0 0 INSERT S2 - 231 Start CBA In 231 115 0 0 S1 - 116 Stop CBB In 116 0 0 0

-- - 000 Stop CBA at 0 steps 0 0 0 0 47

1BwOSR 3.1.4.2 Revision 23 Continuous Use ATTACHMENT D Blown Fuse Illustration Blown Fuse Indicator pictured on the left provides an indication of a blown fuse (indicator is extended).

Blown Fuse Indicator pictured on the right provides a normal view (indicator is not extended, fuse is not blown).

(Final) 48

1BwOSR 3.1.4.2 Revision 23 Continuous Use TABLE 1 - SHUTDOWN ROD BANKS ROD Inserted DRPI > 10 Initial Position Withdrawn to 231 Steps Final Position BANK Steps ROD NO. GROUP GROUP GROUP GROUP STEP DRPI STEP DRPI STEP DRPI STEP DRPI COUNTER COUNTER COUNTER COUNTER H4 D8 ________ ________ ________ ________

S/D H12 E-1 E-1 E-1 E-1 E M8 EACH ROD MOVED AT LEAST 10 STEPS? ¢Y N Shutdown Bank within insertion limits of COLR? ## ## Y N Inserted DRPI > 10 Initial Position Withdrawn to 231 Steps Final Position Steps ROD ROD NO. GROUP GROUP GROUP GROUP BANK STEP DRPI STEP DRPI STEP DRPI STEP DRPI COUNTER COUNTER COUNTER COUNTER C5 E13 _____ _____ _____ _____

S/D N11 D-1 D-1 D-1 D-1 D L3 EACH ROD MOVED AT LEAST 10 STEPS? ¢Y N Shutdown Bank within insertion limits of COLR? ## ## Y N Inserted DRPI > 10 Initial Position Withdrawn to 231 Steps Final Position Steps ROD ROD NO. GROUP GROUP GROUP GROUP BANK STEP DRPI STEP DRPI STEP DRPI STEP DRPI COUNTER COUNTER COUNTER COUNTER E3 C11 _____ _____ _____ _____

S/D L13 C-1 C-1 C-1 C-1 C N5 EACH ROD MOVED AT LEAST 10 STEPS? ¢Y N Shutdown Bank within insertion limits of COLR? ## ## Y N ROD Inserted DRPI > 10 Initial Position Withdrawn to 231 Steps Final Position BANK Steps ROD NO. GROUP GROUP GROUP GROUP STEP DRPI STEP DRPI STEP DRPI STEP DRPI COUNTER COUNTER COUNTER COUNTER G3 C9 _____ _____ _____ _____

J13 B-1 B-1 B-1 B-1 N7 S/D C7 B G13 _____ _____ _____ _____

N9 B-2 B-2 B-2 B-2 J3 EACH ROD MOVED AT LEAST 10 STEPS? ¢Y N Shutdown Bank within insertion limits of COLR? ## ## Y N

1. "YES" REQUIRED prior to continuing to another Shutdown Rod Bank or completing this surveillance. DRPI indication may vary by one position from the initial reading if the control rod is between coils. This is acceptable if the deviation is off by only one position.

Corrective action to ensure the limits of Tech Spec 3.1.5 are satisfied is required for any "NO" response.

D-2

1BwOSR 3.1.4.2 Revision 23 Continuous Use TABLE 1 - SHUTDOWN ROD BANKS (Cont.)

ROD Inserted DRPI > 10 Initial Position Withdrawn to 231 Steps Final Position BANK Steps ROD NO. GROUP GROUP GROUP GROUP STEP DRPI STEP DRPI STEP DRPI STEP DRPI COUNTER COUNTER COUNTER COUNTER D2 B12 _____ _____ ______ _____

M14 A-1 A-1 A-1 A-1 P4 S/D B4 A D14 _____ _____ _____ _____

P12 A-2 A-2 A-2 A-2 M2 EACH ROD MOVED AT LEAST 10 STEPS? ¢Y N Shutdown Bank within insertion limits of COLR? ## ## Y N

1. "YES" REQUIRED prior to continuing to another Shutdown Rod Bank or completing this surveillance. DRPI indication may vary by one position from the initial reading if the control rod is between coils. This is acceptable if the deviation is off by only one position.

Corrective action to ensure the limits of Tech Spec 3.1.5 are satisfied is required for any "NO" response.

D-3

1BwOSR 3.1.4.2 Revision 23 Continuous Use TABLE 2 - CONTROL ROD BANKS Inserted DRPI > 10 Initial Position Withdrawn to 231 Steps Final Position Steps ROD ROD NO. GROUP GROUP GROUP GROUP BANK STEP DRPI STEP DRPI STEP DRPI STEP DRPI COUNTER COUNTER COUNTER COUNTER H6 ________ ________ ________ ________

H10 A-1 A-1 A-1 A-1 F8 ________ ________ ________ ________

K8 A-2 A-2 A-2 A-2 CONT A EACH ROD MOVED AT LEAST 10 STEPS? ¢Y N RODS RETURNED TO ORIGINAL POSITION? ** ## Y N ANNUNCIATORS 1-10-A6, 1-10-A7 and 1-10-B6 ARE CLEAR? Y N Or corrective action taken? N/A Y N Inserted DRPI > 10 Initial Position Withdrawn to 231 Steps Final Position Steps ROD ROD NO. GROUP GROUP GROUP GROUP BANK STEP DRPI STEP DRPI STEP DRPI STEP DRPI COUNTER COUNTER COUNTER COUNTER F2 B10 _____ _____ _____ _____

K14 B-1 B-1 B-1 B-1 P6 B6 F14 _____ _____ _____ _____

CONT B P10 B-2 B-2 B-2 B-2 K2 EACH ROD MOVED AT LEAST 10 STEPS? ¢Y N RODS RETURNED TO ORIGINAL POSITION? ** ## Y N ANNUNCIATORS 1-10-A6, 1-10-A7 and 1-10-B6 ARE CLEAR? Y N Or corrective action taken? N/A Y N Inserted DRPI > 10 Initial Position Withdrawn to 231 Steps Final Position Steps ROD ROD NO. GROUP GROUP GROUP GROUP BANK STEP DRPI STEP DRPI STEP DRPI STEP DRPI COUNTER COUNTER COUNTER COUNTER H2 B8 _____ _____ ______ _____

H14 C-1 C-1 C-1 C-1 P8 F6 F10 _____ _____ _____ _____

CONT C K10 C-2 C-2 C-2 C-2 K6 EACH ROD MOVED AT LEAST 10 STEPS? ¢Y N RODS RETURNED TO ORIGINAL POSITION? ** ## Y N ANNUNCIATORS 1-10-A6, 1-10-A7 and 1-10-B6 ARE CLEAR? Y N Or corrective action taken? N/A Y N

1. "YES" REQUIRED prior to continuing to another Control Rod Bank or completing this surveillance. DRPI indication may vary by one position from the initial reading if the control rod is between coils. This is acceptable if the deviation is off by only one position. Corrective action to ensure the limits of Tech Spec 3.1.6 are satisfied is required for any "NO" response.

- Not Required if this is the controlling Control Rod Bank. Ensure the Rod insertion limits of Tech Spec 3.1.6 are satisfied.

D-4

1BwOSR 3.1.4.2 Revision 23 Continuous Use TABLE 2 - CONTROL ROD BANKS (Cont.)

Inserted DRPI > 10 Initial Position Withdrawn to 231 Steps Final Position Steps ROD ROD NO. GROUP GROUP GROUP GROUP BANK STEP DRPI STEP DRPI STEP DRPI STEP DRPI COUNTER COUNTER COUNTER COUNTER D4 M12 D-1 D-1 D-1 D-1 D12 M4 _____ _____ _____ _____

CONT D H8 D-2 D-2 D-2 D-2 EACH ROD MOVED AT LEAST 10 STEPS? ¢Y N RODS RETURNED TO ORIGINAL POSITION? ## Y N ANNUNCIATORS 1-10-A6, 1-10-A7 and 1-10-B6 ARE CLEAR? Y N Or corrective action taken? N/A Y N

1. "YES" REQUIRED prior to continuing to another Control Rod Bank or completing this surveillance. DRPI indication may vary by one position from the initial reading if the control rod is between coils. This is acceptable if the deviation is off by only one position. Corrective action to ensure the limits of Tech Spec 3.1.6 are satisfied is required for any "NO" response.

- Not Required if this is the controlling Control Rod Bank. Ensure the Rod insertion limits of Tech Spec 3.1.6 are satisfied.

COMMENTS:

D-5

1BwOSR 3.1.4.2 Revision 23 Continuous Use TABLE 3 - SHUTDOWN ROD BANKS INITIAL POSITION FINAL POSITION ROD BANK ROD NO.

GROUP DEMAND DRPI GROUP DEMAND DRPI H4 D8 _____ _____

Shutdown H12 E-1 E-1 E M8 EACH ROD MOVED TO ARO PARK POSITION per BwCB-1, Table 4-1? ¢ Y N Shutdown Bank within insertion limits of COLR? ## ** ## Y N C5 E13 _____ _____

Shutdown N11 D-1 D-1 D L3 EACH ROD MOVED TO ARO PARK POSITION per BwCB-1, Table 4-1? ¢ Y N Shutdown Bank within insertion limits of COLR? ## ** ## Y N E3 C11 _____ _____

Shutdown L13 C-1 C-1 C N5 EACH ROD MOVED TO ARO PARK POSITION per BwCB-1, Table 4-1? ¢ Y N Shutdown Bank within insertion limits of COLR? ## ** ## Y N G3 C9 _____ _____

J13 B-1 B-1 N7 Shutdown C7 B

G13 _____ _____

N9 B-2 B-2 J3 EACH ROD MOVED TO ARO PARK POSITION per BwCB-1, Table 4-1? ¢ Y N Shutdown Bank within insertion limits of COLR? ## ** ## Y N D2 B12 _____ _____

M14 A-1 A-1 P4 Shutdown B4 A

D14 _____ _____

P12 A-2 A-2 M2 EACH ROD MOVED TO ARO PARK POSITION per BwCB-1, Table 4-1? ¢ Y N Shutdown Bank within insertion limits of COLR? ## ** ## Y N

1. YES REQUIRED prior to continuing to another Shutdown Rod Bank or completing this surveillance.

DRPI indication may vary by one position from the initial reading if the control rod is between coils.

This is acceptable if the deviation is off by only one position.

Corrective action to ensure the limits of Tech Spec 3.1.5 are satisfied is required for any NO response.

COMMENTS:

D-6

1BwOSR 3.1.4.2 Revision 23 Continuous Use TABLE 4 - CONTROL ROD BANKS INITIAL POSITION FINAL POSITION ROD BANK ROD NO.

GROUP DEMAND DRPI GROUP DEMAND DRPI H6 _____ _____

H10 A-1 A-1 F8 _____ _____

CONT A K8 A-2 A-2 EACH ROD MOVED TO ARO PARK POSITION per BwCB-1 Table 4-1? ## Y N F2 B10 B-1 B-1 K14 P6 B6 CONT B F14 _____ _____

P10 B-2 B-2 K2 EACH ROD MOVED TO ARO PARK POSITION per BwCB-1 Table 4-1? ** ## Y N H2 B8 _____ _____

H14 C-1 C-1 P8 F6 CONT C F10 _____ _____

K10 C-2 C-2 K6 EACH ROD MOVED TO ARO PARK POSITION per BwCB-1 Table 4-1? ** ## Y N (N/A if a controlling bank.)

1. "YES" REQUIRED prior to continuing to another Control Rod Bank or completing this surveillance.

DRPI indication may vary by one position from the initial reading if the control rod is between coils.

This is acceptable if the deviation is off by only one position. Corrective action to ensure the limits of Tech Spec 3.1.6 are satisfied is required for any "NO" response.

- Not Required if this is the controlling Control Rod Bank. Ensure the Rod insertion limits of Tech Spec 3.1.6 are satisfied.

COMMENTS:

(Final)

D-7

TASK CONDITIONS:

1. You are an Assist NSO.

2. Unit 1 is in Mode 4.

3. Maintenance has recently completed packing adjustment of 1SI8806, SI PPs Suc from RWST Isol Vlv.

4. 1BwOSR 5.5.8.SI-5 is required to be performed to verify operability of 1SI8806.

INITIATING CUES:

1. The Unit 1 US has directed you to perform 1BwOSR 5.5.8.SI-5, SVAG Valve Stroke Surveillance for 1SI8806, steps F.1 and F.3.

2. Inform the Unit 1 US when you have completed the surveillance.

3. Applicable LCOs have been entered. BwOP SI-100 has been completed.

1 SIM-223

TASK TITLE: 1SI8806 SVAG Valve Stroke Surveillance JPM No.: SIM-223 REV: 2013 NRC TPO No.: 4E.AM-23 K&A No.: 006000A4.07 TASK No.: R-AM-068 K&A IMP: 4.4/4.4 EXAMINEE: RO SRO (Circle One)

EVALUATOR: DATE:

The Examinee: PASSED this JPM. TIME STARTED:

FAILED TIME FINISHED:

CRITICAL ELEMENTS: (*) 3, 4, 5 JPM TIME: ___ MINUTES CRITICAL TIME: NA APPROX COMPLETION TIME: 15 MINUTES ALTERNATE PATH: YES EVALUATION METHOD: LOCATION:

X PERFORM IN PLANT SIMULATE X SIMULATOR GENERAL

REFERENCES:

1. 1BwOSR 5.5.8.SI-5, Rev. 5 MATERIALS:

1. Marked up copy of 1BwOSR 5.5.8.SI-5, Rev 5.

2. Digital stopwatch.

TASK STANDARDS:

1. 1SI8806 stroke tested per surveillance.

TASK CONDITIONS:

1. You are an Assist NSO.

2. Unit 1 is in Mode 4.

3. Maintenance has recently completed packing adjustment of 1SI8806, SI PPs Suc from RWST Isol Vlv.

4. 1BwOSR 5.5.8.SI-5 is required to be performed to verify operability of 1SI8806.

INITIATING CUES:

1. The Unit 1 US has directed you to perform 1BwOSR 5.5.8.SI-5, SVAG Valve Stroke Surveillance for 1SI8806, steps F.1 and F.3. (Cue: Hand examinee copy of surveillance).

2. Inform the Unit 1 US when you have completed the surveillance.

3. Applicable LCOs have been entered. BwOP SI-100 has been completed.

2 SIM-223

RECORD START TIME_____________

Note: Stroke times are determined using the dual valve indications on the MCB.

PERFORMANCE STEP STANDARD Circle applicable

1. Verify initial conditions

Review Prerequisites SAT UNSAT N/A (steps F.1.1 through F.1.3) Precautions Limitations Comments:

and Actions.

CUE: If asked, it is not desired to perform 1BwOSR 5.5.8.SI-6

Verify IST coordinator listed on cover sheet

Obtain digital stopwatch.

2. Record as found position of 1SI8806

Determines and records SAT UNSAT N/A (step F.3.1) 1SI8806 as Open Comments:

3. Perform CLOSED stroke of Perform the following: SAT UNSAT N/A 1SI8806 (in accordance with steps o Verify open 1SI8806 Comments:

outlined in Attachment B).

Simultaneously start the stopwatch and close Note: Close stroke time for 1SI8806 1SI8806.

during this JPM should be within the

Stop the stopwatch alert and operable limits, (i.e. 6.9- when 1SI8806 indicates 11.5 sec.). If the examinee closed.

determines a stroke time outside this band then give the following cue.

Record the Stroke Closed Test Time.

o Record 1SI8806 MLB status light indication.

Cue: Display stopwatch cue #1, o Verify 1SI8806 JPM stopwatch at 00:10.00 (10.00 indicates closed on seconds). 1PM06J.

Cue: If asked, the Unit Supervisor directs you to perform the Open Stroke Timing Step when opening 1SI8806.

3 SIM-223

4. Perform OPEN stroke of 1SI8806 Perform the following: SAT UNSAT N/A (in accordance with steps outlined o Verify close 1SI8806 Comments:

in Attachment A).

Simultaneously start the stopwatch and open 1SI8806.

Note: First open stroke time for

Stop the stopwatch 1SI8806 during this JPM should be when 1SI8806 indicates between the alert and operable open.

limits, (i.e. 11.8-14.1 sec.). If the

Record the Stroke Open examinee determines a stroke time Test Time.

outside this band then give the following cue. o Record 1SI8806 MLB status light indication.

o Verify 1SI8806 indicates open on 1PM06J.

Cue: Display stopwatch cue #2,

Determine the open test JPM stopwatch at 00:13.00 (13.00 time is within the seconds). OPERABLE Limits.

Cue: When informed as US, o Check the YES block in acknowledge valve stroke time the VER OPER section exceeds alert limit (when to indicate that 1SI8806 informed) has been verified operable.

Note: Alternate path begins here

5. Determine 1SI8806 open stroke Perform the following: SAT UNSAT N/A time is NOT within alert limit and

Determine the opening Comments:

perform valve stroke retest. test time is within the operability limits, but not Cue: When informed as US, within ALERT for min acknowledge valve stroke time time limit exceeds alert limit (when o May inform US of informed) problem at this point.

Re-CLOSES valve.

Note: Second open stroke time for

Simultaneously starts 1SI8806 during this JPM should be the stopwatch and within the alert and operable limits, opens 1SI8806.

(i.e. 6.9-11.5 sec.). If the examinee

Stop the stopwatch determines a stroke time outside this when 1SI8806 indicates band then give the following cue. open.

Record the stroke open Cue: Display stopwatch cue #3, retest time.

JPM stopwatch at 00:10.00 (10.00

Determine the open seconds). retest time is within the alert and operability Cue : As US acknowledge need (OPER) Limits.

for generating IR and ER-AA-321 o Inform US that an IR to document first open stoke test needs to be generated time. to the IST coordinator documenting the initial open test results.

6. Acknowledge completion of Inform the Unit 1 US when SAT UNSAT N/A surveillance. you have completed the Comments:

surveillance.

4 SIM-223

(CUE:) THIS COMPLETES THIS JPM.

RECORD STOP TIME ___ _____________

5 SIM-200

SIMULATOR SETUP GUIDE:

Verify/perform TQ-BR-201-0113, BRAIDWOOD TRAINING DEPARTMENT SIMULATOR EXAMINATION SECURITY ACTIONS CHECKLIST.

Establish the conditions of IC 26, mode 4.

Close SVAG valve MCC Feed Breakers Copy file sim223.cae to s:\opensim\monitor\examadmin (this must be done since the cae file will not run properly from a pen drive)

Run sim223setup.cae from disk Complete items on Simulator Ready for Training Checklist Place simulator in RUN.

COMMENTS:

Provide copy of 1BwOSR 5.5.8.SI-5 Ensure stop watch is available (Final) 6 SIM-223

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 5.5.8.SI-5____

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

PMID/RQ

Title:

UNIT ONE SAFETY INJECTION SYSTEM SVAG VALVE STROKE SURV____

PMID/RQ Due Date: ___ N/A________ PMID/RQ Late Date: N/A Signature/Authorization Approval Review: Name Date Time Shift Authorization to Start Work: ___Joe Supervisor ______ Today 5 min ago Work Started __________________________ ________ ________

Work Stopped: __________________________ ________ ________

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 (partial surveillance) PMT 1SI8806 ADDITIONAL REVIEW OF RESULTS (IF REQUIRED)

__ IST Coordinator __ ____________________________________ ________

Title Signature Date

WC-AA-111 Revision 4 Page 25 of 61

1BwOSR 5.5.8.SI-5 Revision 5 Continuous Use COMMON TRAIN UNIT ONE SAFETY INJECTION SYSTEM SVAG VALVE STROKE SURVEILLANCE A. STATEMENT OF APPLICABILITY The purpose of this procedure is to verify that the Safety Injection System (SVAG) valves stroke within their specified time when tested pursuant to Tech Spec 5.5.8.

Testing will be performed after any maintenance affecting valve operability and is applicable for MODES 1, 2, 3 and 4.

B. REFERENCES

1. Tech Spec LCOs:

a. 3.4.6 d. 3.4.3

b. 3.4.7 e. 3.5.2

c. 3.4.8 f. 3.5.3

2. Tech Spec Surveillance Requirement: 5.5.8

3. Station Procedures:

a. BwOP RH-6, Placing the RH System in Shutdown Cooling.

b. ER-AA-321, Administrative Requirements for Inservice Testing.

c. 1BwOSR 5.5.8.SI-3A, Unit One SI System SVAG Valve Stroke Surveillance.

d. 1BwOSR 5.5.8.SI-6, Common Train SI System Isolation Valve Indication Surveillance.

e. BwOP SI-100, Energizing and De-Energizing SVAG Valve MCCs and SI Accumulator Outlet Valves in Modes One Through Four

4. Station Drawings: M-61

5. In Service Testing Program Plan for Valves (IST Program).

6. EC350458, LCOAR Entry During Testing of 1SI8804B and 1CV8804A during surveillance testing.

1

1BwOSR 5.5.8.SI-5 Revision 5 Continuous Use B. 7. AT 562197-03, Regulatory Commitment (Regarding the implementation of administrative controls to ensure that one complete ECCS train can be actuated automatically must be maintained when a logic train is INOPERABLE.)

C. PREREQUISITES

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

2. This surveillance must be performed in MODE 5, 6 or defueled. A partial surveillance may be performed in any MODE per the discretion of the Shift Manager or designee.

3. A digital stopwatch will be necessary to perform this surveillance.

4. The applicable Safety Injection Pump must not be operating.

5. Execution of this procedure in Modes 1-4 may require the use of BwOP SI-100.

SVAG valve MCCs will be energized/de-energized per BwOP SI-100.

6. If the Unit is in Mode 4, the 1CV8804A cannot be stroked.

7. If the Unit is in Modes 1-3, both trains of ECCS pumps (SI, CV, and RH) must be operable prior to testing the 1CV8804A.

8. If the Unit is in Modes 1-4, THEN the OPPOSITE train of SSPS and Reactor Trip Breaker (RTB) train must be OPERABLE prior to performing any actions that renders an ECCS train INOPERABLE in order to ensure the regulatory commitments of License Amendment No. 148 are maintained.

D. PRECAUTIONS

1. VERIFY that all requirements of the applicable RWP have been met.

2. Monitor for potential leak/sneak paths prior to stroking valves.

3. If the Unit is in Modes 1-3, OPENING 1CV8804A renders both trains of ECCS inoperable due to the potential impact on RH pump ECCS flow.

E. LIMITATIONS AND ACTIONS

1. As stated in Tech Spec LCOs 3.4.6, 3.4.7, 3.4.8, 3.4.3, 3.5.2, and 3.5.3.

2. In the event a valve fails to change position, or the stroke time exceeds the Operability (Oper) Limit during surveillance performance, IMMEDIATELY NOTIFY the Shift Manager or designee to declare the valve inoperable and initiate corrective actions.

2

1BwOSR 5.5.8.SI-5 Revision 5 Continuous Use E. 3. In the event a valve stroke time exceeds the Alert Limit, but is less than the Operability (Oper) Limit, the following should be performed:

a. The Shift Manager or designee must be notified

b. The valve should be stroked a second time.

c. INITIATE an IR for the IST Coordinator to analyze and document the initial stroke and the cause of the deviation (per ER-AA-321).

d. If the second stroke time exceeds the Alert Limit, but is less than the Operability (Oper) Limit, then INITIATE an IR for the IST Coordinator to perform a valve evaluation with a 96 hour0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months time clock per ER-AA-321. N/A if second stroke is within Alert Limits. The valve is considered operable until the evaluation is complete. The Dequip program is an acceptable tracking method.

4. For any valve declared inoperable demonstrate acceptable operation after required corrective action has been taken but before returning the valve to service.

5. IF ALARA concerns permit, THEN local stroke timing and local examination of the valve should be performed if Operability Acceptance Criteria (Oper Limit) is not met.

6. Per the requirements of the IST Program, Tech Spec 5.5.8, valve stroke time limits SHALL be set up which accurately reflect the way the valve strokes. These times, in some instances, may be more limiting than other Tech Spec values.

Per the IST Program requirements, Tech Spec 5.5.8, these stroke times SHALL be the basis on which the valve is declared inoperable.

7. If possible, PERFORM 1BwOSR 5.5.8.SI-6 (when required) concurrently with this procedure to obtain both valve stroke timing data and indication check documentation.

8. EM Department assistance will be required to install jumpers during performance of this surveillance. (Section F.2)

9. EC 350458 has determined that 1SI8804B should not be opened if the Unit is in Mode 4 due to the potential impact on the RH train that is operable for LCO 3.5.3. Therefore, the 1SI8804B SHALL not be tested when the Unit is in Mode 4.

3

1BwOSR 5.5.8.SI-5 Revision 5 Continuous Use F. MAIN BODY 0.0 SURVEILLANCE OVERVIEW 0.1 The parallel subsection strings are independent of one another so that they may be performed in any order or individually if performance of a partial surveillance is required.

0.2 Parallel subsections SHALL NOT be performed simultaneously without the permission of the Shift Manager or designee.

0.3 Steps for timing the valve strokes (Attachments A and B) are repeated for each valve being stroked. Record data from the valve strokes in the appropriate blocks of the table.

0.4 The timing valve strokes may be performed in any order to minimize the number of needless valve strokes.

0.5 The subsections of this surveillance perform the following.

F.1.0 Establish Initial Conditions F.2.0 Stroke test of 1CV8804A, RH Hx 1A PPs Isol Vlv.

F.3.0 Stroke test of 1SI8806, SI PPs Suc from RWST Isol Vlv.

F.4.0 Stroke test of 1SI8813, SI PPs Miniflow Isol Vlv.

F.5.0 Stroke test of 1SI8835, SI PP to Cold Lets Isol Vlv.

F.6.0 Stroke test of 1SI8840, RH to Hot Legs Isol Vlv.

START 1.0 2.0 3.0 4.0 5.0 6.0 END 4

1BwOSR 5.5.8.SI-5 Revision 5 Continuous Use F. 1.0 INITIAL CONDITIONS NOTE Initial each step in the space provided adjacent to the procedure step number AFTER the step has been SUCCESSFULLY completed. Person(s) performing VERIFICATIONS SHALL initial in the space provided following the step.

NOTE "Valve stroke time" is defined as the time duration from the instant of handswitch (or manual relay) actuation until the instant of indication of the valve's intended final position.

_____ 1.1 VERIFY all applicable PREREQUISITES, PRECAUTIONS, and LIMITATIONS AND ACTIONS are satisfactorily addressed.

_____ 1.2 VERIFY the IST Coordinator is listed on the Data Package Cover Sheet to review the results.

_____ 1.3 OBTAIN a digital stopwatch.

5

1BwOSR 5.5.8.SI-5 Revision 5 Continuous Use F. 2.0 STROKE TEST OF 1CV8804A, RH HX 1A TO CV PPS ISOL VLV.

NOTE VERIFY the 1A RH Pump discharge pressure is below 220 psig to prevent lifting the CV pump suction relief while stroking 1CV8804A.

2.1 RECORD the "AS FOUND" position of the following equipment (CIRCLE as appropriate):

_____ 1CV8804A, RH HX 1A to CV PPs Isol Vlv.

OPEN/CLOSED

_____ 1SI8811A, Cnmt Sump Isol Vlv.

OPEN/CLOSED

_____ 1RH8701A, 1A RHR PP Loop Suction Vlv.

OPEN/CLOSED

_____ 1RH8701B, 1A RHR PP Loop Suction Vlv.

OPEN/CLOSED

_____ 1SI8809A, RH to Cold Legs A & D Isol Vlv, at 1PM06J.

OPEN/CLOSED

_____ 1RH8716A, RH Discharge Hdr X-Tie Isol Vlv, at 1PM06J.

OPEN/CLOSED

_____ 1RH01PA, 1A RHR Pump NAC/NAT/PTL NOTE Verify the 1A RH Pump discharge pressure is below 200 psig to prevent lifting the CV pump suction relief while stroking 1CV8804A.

_____ 2.2 VERIFY/PLACE the Train B Residual Heat Removal System in operation to fulfill the shutdown cooling function as requested by the Shift Manager (N/A if shutdown cooling is not required).

_____ 2.3 VERIFY/STOP 1RH01PA, 1A Residual Heat Removal Pump.

2.4 IF the Unit is in Modes 5, 6, or DEFUELED, perform the following:

_____ a. VERIFY the 1A RH Train is NOT REQUIRED to be OPERABLE.

_____ b. PLACE 1RH01PA C/S in PTL.

6

1BwOSR 5.5.8.SI-5 Revision 5 Continuous Use NOTE Closing 1RH8701A or 1RH8701B will isolate the "A" Train RH suction relief valve. PRIOR to performing this action in Modes 4, 5, and 6, with the reactor head installed, verify the requirements of Tech Spec 3.4.9.3 are met F. 2.5 VERIFY/CLOSE the following:

_____ 1SI8811A, Cnmt Sump Isol Vlv.

One of the following: (Mark "N/A" for valve not manipulated)

_____ 1RH8701A, 1A RHR PP Loop Suction Vlv.

_____ 1RH8701B, 1A RHR PP Loop Suction Vlv.

_____ 1CV8804A, RH Hx 1A to CV PPs Isol Vlv.

NOTE The jumper PLACED in the next step will simulate the 1SI8811A OPEN and 1SI8813 CLOSED.

_____ 2.6 IF the Unit is in Modes 1, 2, or 3, ENTER LCO 3.5.2 Condition A.

_____ 2.7 NOTIFY EMD to PLACE a Jumper between Terminal 3 in the FRONT compartment of MCC 131X1 cub J5 and Terminal 28 in the REAR of compartment of MCC 131X1 cub J5.

INSTALLED BY ___________________ DATE/TIME _______/_______

VERIFICATION _____ DATE/TIME _______/_______

7

1BwOSR 5.5.8.SI-5 Revision 5 Continuous Use CAUTION Immediately CLOSE 1CV8804A in the event a safety injection actuates during the stroke test.

CAUTION Prior to opening 1CV8804A, verify there are no flow paths created to allow gravity fill of the RWST or VCT to the cavity. (i.e.; RH Discharge Lines)

F ____ 2.8 IF the Unit is in Modes 1, 2, or 3, ENTER LCO 3.5.2 Condition B.

NOTE 1SI8809A is REQUIRED to remain OPEN and DEENERGIZED in MODES 1-4.

NOTE Mark Step 2.9 N/A if BOTH RH Trains are REQUIRED to be OPERABLE and it is desired to stroke 1CV8804A with 1SI8809A and 1RH8716A open.

2.9 IF the Unit is in Modes 5, 6, or DEFUELED, perform the following:

_____ a. VERIFY BwOP RH-6, Attachment A or Attachment B is NOT in progress.

_____ b. CLOSE 1RH8716A, RH Discharge Hdr X-Tie Isol Vlv, at 1PM06J.

_____ c. CLOSE 1SI8809A, RH to Cold Legs A and D Isol Vlv, at 1PM06J.

_____ 2.10 PERFORM an OPEN Valve Stroke Test of 1CV8804A at 1PM05J. (PERFORM in accordance with steps outlined in Attachment A, and RECORD in Data Table).

Valve: 1CV8804A Panel: 1PM05J Stroke @ Oper @ Alert Status @ Test @ Retest Ver Oper Init Limits ¢ Limits ¢ Lights Time ¢ Time ¢ OPEN Max 10.0 Min 7.0 LIT YES Max N/A DARK NO

@ All limits and times are in seconds.

8

1BwOSR 5.5.8.SI-5 Revision 5 Continuous Use F. 2.11 RESTORE the following to the "AS FOUND" position or as directed by the Shift Manager or designee (Circle as appropriate):

_____ 1CV8804A, RH HX 1A to CV PPs Isol Vlv.

OPEN/CLOSED VERIFICATION _____

_____ 1SI8809A, RH to Cold Legs A & D Isol Vlv, at 1PM06J.

OPEN/CLOSED VERIFICATION _____

_____ 1RH8716A, RH Discharge Hdr X-Tie Isol Vlv, at 1PM06J.

OPEN/CLOSED VERIFICATION _____

_____ 1SI8811A, Cnmt Sump Isol Vlv.

OPEN/CLOSED VERIFICATION _____

_____ 1RH8701A, 1A RHR PP Loop Suction Vlv.

OPEN/CLOSED VERIFICATION _____

_____ 1RH8701B, 1A RHR PP Loop Suction Vlv.

OPEN/CLOSED VERIFICATION _____

_____ 1RH01PA, 1A RHR Pump NAC/NAT/PTL VERIFICATION _____

_____ 2.12 EXIT LCO 3.5.2 Condition B, if entered due to the performance of this procedure.

_____ 2.13 NOTIFY EMD to REMOVE the Jumper that was installed between Terminal 3 in the FRONT compartment of MCC 131X1 cub J5 and Terminal 28 in the REAR of compartment of MCC 131X1 cub J5.

REMOVED BY ___________________ DATE/TIME _______/_______

VERIFICATION _____ DATE/TIME _______/_______

_____ 2.14 EXIT LCO 3.5.2 Condition A, if entered due to the performance of this procedure.

_____ 2.15 RETURN the Residual Heat Removal System to operation as requested by the Shift Manager.

9

1BwOSR 5.5.8.SI-5 Revision 5 Continuous Use F. 3.0 STROKE TEST OF 1SI8806, SI PPS SUC FROM RWST ISOL VLV.

Valve: 1SI8806 Panel: 1PM06J Stroke @ Oper @ Alert Status @ Test @ Retest Ver Oper Init Limits ¢ Limits ¢ Lights Time ¢ Time ¢ OPEN Max 14.1 Min 7.1 LIT YES Max 11.8 DARK NO CLOSE Max 13.8 Min 6.9 LIT YES Max 11.5 DARK NO

_____ 3.1 RECORD the "AS FOUND" position of 1SI8806, SI PPs Suc from RWST Isol Vlv, at 1PM06J, (Circle as appropriate):

OPEN/CLOSED

_____ 3.2 PERFORM an OPEN and CLOSED Valve Stroke Test of 1SI8806 at 1PM06J.

(PERFORM in accordance with steps outlined in Attachments A and B and RECORD in the Data Table).

_____ 3.3 RESTORE 1SI8806, SI PPs Suc from RWST Isol Vlv, at 1PM06J, to the "AS FOUND" position or as directed by the Shift Manager or designee (Circle as appropriate).

OPEN/CLOSED VERIFICATION _____

4.0 STROKE TEST OF 1SI8813, SI PPS MINIFLOW ISOL VLV.

Valve: 1SI8813 Panel: 1PM06J Stroke @ Oper @ Alert Status @ Test @ Retest Ver Oper Init Limits ¢ Limits ¢ Lights Time ¢ Time ¢ CLOSE Max 10.0 Min 6.4 LIT YES Max N/A DARK NO

_____ 4.1 RECORD the "AS FOUND" position of 1SI8813, SI PPs Miniflow Isol Vlv, at 1PM06J, (Circle as appropriate):

OPEN/CLOSED

_____ 4.2 VERIFY/OPEN 1SI8813 (verify OPEN light indication).

_____ 4.3 PERFORM a CLOSED Valve Stroke Test of 1SI8813 at 1PM06J. (PERFORM in accordance with steps outlined in Attachment B and RECORD in the Data Table).

_____ 4.4 RESTORE 1SI8813, SI PPs Miniflow Isol Vlv, at 1PM06J, to the "AS FOUND" position or as directed by the Shift Manager or designee (Circle as appropriate).

OPEN/CLOSED VERIFICATION _____

@ All limits and times are in seconds.

10

1BwOSR 5.5.8.SI-5 Revision 5 Continuous Use F. 5.0 STROKE TEST OF 1SI8835, SI PP TO COLD LEGS ISOL VLV.

Valve: 1SI8835 Panel: 1PM06J Stroke @ Oper @ Alert Status @ Test @ Retest Ver Oper Init Limits ¢ Limits ¢ Lights Time ¢ Time ¢ OPEN Max 9.9 Min 5.0 LIT YES Max 8.3 DARK NO CLOSE Max 9.5 Min 4.7 LIT YES Max 7.9 DARK NO

_____ 5.1 RECORD the "AS FOUND" position of 1SI8835, SI PP to Cold Legs Isol Vlv, at 1PM06J, (Circle as appropriate):

OPEN/CLOSED

_____ 5.2 PERFORM an OPEN and CLOSED Valve Stroke Test of 1SI8835 at 1PM06J.

(PERFORM in accordance with steps outlined in Attachments A and B and RECORD in the Data Table).

_____ 5.3 RESTORE 1SI8835, SI PP to Cold Legs Isol Vlv, at 1PM06J, to the "AS FOUND" position or as directed by the Shift Manager or designee (Circle as appropriate).

OPEN/CLOSED VERIFICATION _____

6.0 STROKE TEST OF 1SI8840, RH TO HOT LEGS ISOL VLV.

Valve: 1SI8840 Panel: 1PM06J Stroke @ Oper @ Alert Status @ Test @ Retest Ver Oper Init Limits ¢ Limits ¢ Lights Time ¢ Time ¢ OPEN Max 15.0 Min 10.5 LIT YES Max 14.3 DARK NO CLOSE Max 14.2 Min 9.6 LIT YES Max 13.0 DARK NO

_____ 6.1 RECORD the "AS FOUND" position of 1SI8840, RH to Hot Legs Isol Vlv, at 1PM06J, (Circle as appropriate):

OPEN/CLOSED

_____ 6.2 PERFORM an OPEN and CLOSED Valve Stroke Test of 1SI8840 at 1PM06J.

(PERFORM in accordance with steps outlined in Attachments A and B and RECORD in the Data Table).

_____ 6.3 RESTORE 1SI8840, RH to Hot Legs Isol Vlv, at 1PM06J, to the "AS FOUND" position or as directed by the Shift Manager or designee (Circle as appropriate).

OPEN/CLOSED VERIFICATION _____

@ All limits and times are in seconds.

11

1BwOSR 5.5.8.SI-5 Revision 5 Continuous Use G. ACCEPTANCE CRITERIA

1. Each valve must have been verified to stroke within the Operability (OPER)

Limits.

2. Each valve must have been verified in accordance with one of the following:

a. The valve stroke time was within the Alert Limits.

b. The valve stroke time exceeded the Alert Limits, but was within the Operability (Oper) Limits and the following criteria have been met:

1) The valve was stroked a second time.

2) The IST Coordinator has been NOTIFIED to PERFORM an evaluation to document valve operability per ER-AA-321 and attach it to this surveillance.

3) The second valve stroke time exceeded the Alert Limits, but was within the Operability (Oper) Limits and the valve is being tracked with a 96 hour0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months clock to complete the ER-AA-321 evaluation. (Valve is considered operable until evaluation is complete.) (The Dequip program is an acceptable tracking method.)

12

1BwOSR 5.5.8.SI-5 Revision 5 Continuous Use ATTACHMENT A TIMING VALVES IN THE OPEN DIRECTION

1. VERIFY/CLOSE the valve.

2. SIMULTANEOUSLY START the stopwatch and OPEN the valve with its handswitch.

3. STOP the stopwatch when the valve indicates OPEN.

¢ 4. RECORD the stroke OPEN TEST TIME.

5. RECORD the MLB status light indication associated with the valve.

6. VERIFY the valve indicates OPEN on the control panel.

¢ 7. VERIFY the OPEN TEST TIME is within the OPERABILITY (OPER) LIMITS. (If not, DECLARE the valve INOPERABLE and initiate appropriate actions.)

8. If the valve is within the OPERABILITY (OPER) LIMITS, but is not within ALERT LIMITS, PERFORM the following (otherwise N/A):

a. VERIFY/CLOSE the valve (May be performed in conjunction with a close stroke timing step).

b. SIMULTANEOUSLY START the stopwatch and OPEN the valve with its handswitch.

c. STOP the stopwatch when the valve indicates OPEN.

¢ d. RECORD the stroke OPEN RETEST TIME.

¢ e. VERIFY the OPEN RETEST TIME is within the OPERABILITY (OPER)

LIMITS. (If not, DECLARE the valve INOPERABLE and initiate appropriate actions.)

f. Attach ER-AA-321 to this surveillance for the IST Coordinator to evaluate.

g. If the second stroke time exceeds the Alert Limit, but is less than the Operability (Oper) Limit, then TRACK the valve with a 96 hour0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months clock to complete the ER-AA-321 evaluation. (Valve is considered operable until evaluation is complete.)

9. RETURN the valve to the "AS FOUND" position or as designated by the Shift Manager or designee (May be performed in conjunction with a close stroke timing step).

13

1BwOSR 5.5.8.SI-5 Revision 5 Continuous Use ATTACHMENT B TIMING VALVES IN THE CLOSE DIRECTION

1. VERIFY/OPEN the valve.

2. SIMULTANEOUSLY START the stopwatch and CLOSE the valve with its handswitch.

3. STOP the stopwatch when the valve indicates CLOSED.

¢ 4. RECORD the stroke CLOSED TEST TIME.

5. RECORD the MLB status light indication associated with the valve.

6. VERIFY the valve indicates CLOSED on the control panel.

¢ 7. VERIFY the CLOSED TEST TIME is within the OPERABILITY (OPER) LIMITS.

(If not, DECLARE the valve INOPERABLE and initiate appropriate actions.)

8. If the valve is within the OPERABILITY (OPER) LIMITS, but is not within ALERT LIMITS, PERFORM the following (otherwise N/A):

a. VERIFY/OPEN the valve (May be performed in conjunction with an open stroke timing step).

b. SIMULTANEOUSLY START the stopwatch and CLOSE the valve with its handswitch.

c. STOP the stopwatch when the valve indicates CLOSED.

¢ d. RECORD the CLOSED RETEST TIME.

¢ e. VERIFY the CLOSED RETEST TIME is within the OPERABILITY (OPER)

LIMITS. (If not, DECLARE the valve INOPERABLE and initiate appropriate actions.)

f. Attach ER-AA-321 to this surveillance for the IST Coordinator to evaluate.

g. If the second stroke time exceeds the Alert Limit, but is less than the Operability (Oper) Limit, then TRACK the valve with a 96 hour0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months clock to complete the ER-AA-321 evaluation. (Valve is considered operable until evaluation is complete.)

9. RETURN the valve to the "AS FOUND" position or as designated by the Shift Manager or designee (May be performed in conjunction with an open stroke timing step).

(Final) 14

TASK CONDITIONS:

1. You are the Unit 1 NSO.

2. Unit 1 has recently returned to full power following power ascension.

3. PRZ B/U HTR GRP A was placed in ON to facilitate proper chemical mixing in the pressurizer during the unit ramp.

INITIATING CUES:

1. The US has directed you to place the PRZ B/U HTR GRP A to AUTO per BwOP RY-11.

2. Inform the US when the evolution is complete.

SIM-305A 1

TASK TITLE: Place PZR B/U Heater Group from ON to AUTO JPM No.: SIM 305A REV: 2013 NRC TPO No.: 4E.AM-18 K&A No.: 010000A4.02 TASK No.: R-AM-022, Use Operating Department Procedures K&A IMP: 3.6/3.4 EXAMINEE: RO SRO (Circle One)

ALTERNATE PATH: YES EVALUATOR: DATE:

The Examinee: PASSED this JPM. TIME STARTED:

FAILED TIME FINISHED:

CRITICAL ELEMENTS: (*) 4, 5, 6 JPM TIME: MINUTES CRITICAL TIME: NA APPROX COMPLETION TIME: 20 MINUTES EVALUATION METHOD: LOCATION:

X PERFORM IN PLANT SIMULATE X SIMULATOR GENERAL

REFERENCES:

1. BwOP RY-11, Rev. 2, PRESSURIZER HEATER OPERATION .

MATERIALS:

1. BwOP RY-11 TASK STANDARDS:

1. Place PRZ B/U heater group in auto per BwOP RY-11.

2. Recognize inability of variable heaters to maintain pressurizer pressure

3. Re-energize B/U heater group.

TASK CONDITIONS:

SIM-305A 2

1. You are the Unit 1 NSO.

2. Unit 1 has recently returned to full power following power ascension.

3. PRZ B/U HTR GRP A was placed in ON to facilitate proper chemical mixing in the pressurizer during the unit ramp.

INITIATING CUES:

1. The US has directed you to place the PRZ B/U HTR GRP A to AUTO per BwOP RY-11.

2. Inform the US when the evolution is complete.

SIM-305A 3

RECORD START TIME PERFORMANCE STEP STANDARD Circle applicable

1. Refer to BwOP RY-11.

Refer to BwOP RY-11. SAT UNSAT N/A Comments:

CUE: Prerequisites, precautions,

Verify all applicable limitations and actions are prerequisites, met. precautions limitations and actions are addressed.

CUE: Another NSO will monitor the

Verify Pressurizer computer points in step 2. Pressure is Pressurizer Pressure is 2235 approximately 2235 psig on lowest computer point. psig from the lowest computer point indication P0480, CUE: If asked, the SM and System P0481, P0482, P0483.

Engineer have concurred with performance of this evolution.

(see caution prior to step 3)

2. At 1PM05J, places 1PK-455A in

Depresses Manual SAT UNSAT N/A Manual pushbutton on 1PK-455A.

Comments:

3. Raise PZR pressure to approx. 2250

Perform the following: SAT UNSAT N/A psig.

Lower 1PK-455A demand until pressurizer pressure is Comments:

approx. 2250 psig.

(2245-2260)

4. Place B/U HTR GRP A to AUTO

Perform the following: SAT UNSAT N/A

Place control switch for B/U HTR GRP A CONTACTOR in Comments:

AUTO

ALTERNATE PATH BEGINS*

SIM-305A 4

PERFORMANCE STEP STANDARD Circle applicable

5. Maintain RY pressure in desired

Perform the following: SAT UNSAT N/A band by manually controlling PZR pressure controller.

Adjust 1PK-455A o Monitor pressurizer Comments:

pressure.

o Maintains pressure between 2235 and 2250 psig by adjusting the master PZR CUE: (provide cue after examinee pressure controller in has stabilized PZR pressure to manual.

his/her satisfaction and is

STABILIZE PZR waiting for 10 minutes to pressure at elapse) 10 minutes has approximately 2235 elapsed. psig (2230-2240 psig).

o IF PZR spray valve demand > 0, or variable heater load <

100 amps, THEN take other backup heaters to the AUTO position, by repeating step 3.

NOTE: The auto portion of the master pressurizer pressure controller failed when the controller was placed in manual. The controller output will cause sprays to open and lower PZR pressure.

Additionally, lowering controller demand at this point will activate alarm 1-12-C1, PZR PRESS CONT DEV LOW HTRS ON. Critical step successful completion requires stabilizing RCS pressure without allowing pressure to drop below 2209 psig.

SIM-305A 5

6. Determines PZR Master Pressure Place the PZR Master SAT UNSAT N/A Controller does not function in Pressure Controller in AUTO AUTO and maintains manual PZR as follows:

pressure control. Comments:

o VERIFY/SET the PZR Master Pressure Controller, 1PK-455A, potentiometer to maintain 2235 psig.

VERIFY/PLACE the PZR Master Pressure Controller, 1PK-455A, in AUTO.

VERIFY that the PZR Master Pressure Controller, 1PK-455A, is controlling PZR pressure at approximately 2235 psig in Auto.

Examinee notes that the controller is causing reduced PZR Pressure and places the controller back in manual and stabilizes PZR pressure at 2235 psig (2230-2240 psig).

(CUE:) THIS COMPLETES THIS JPM.

RECORD STOP TIME __________

COMMENTS:

SIM-305A 6

SIMULATOR SETUP INSTRUCTIONS JPM NO: SIM-305 REQUIRED SIMULATOR MODE(S): 100% power steady state.

Place B/U HTRS GRP A CONTACTOR to ON Insert malfunction below Allow pressurizer pressure to stabilize in auto.

MALFUNCTION #S:

Activate CAE sim305A and verify the following:

trgset 1 "ZLO1PK455A(2)==1" IMF RX15 (1 0) 2270 to trigger Malfunction RX15 to 2270 psig when the controller is placed in manual. This fails the auto portion of the controller to a higher output value.

COMMENTS:

SIM-305A 7

BwOP RY-11 Revision 2 Continuous Use PRESSURIZER HEATER OPERATION A. STATEMENT OF APPLICABILITY The purpose of this procedure is to provide direction for operating with the least amount of PZR heaters required to maintain pressure and provide adequate mixing of the Pressurizer in MODES 1, 2, and 3.

B. REFERENCES

1. Tech Spec LCO 3.4.9 and 3.4.1.

2. Tech Spec Surveillance Requirement: SR 3.4.9.2

3. Station Procedure: BwOL 3.4.9, LCOAR, Reactor Coolant System -Pressurizer.

4. UFSAR 15.0.1.1 Condition 1 Normal Operation and Operational Transients, and 4.4.2.2.1 Departure from Nucleate Boiling Technology C. PREREQUISITES

1. Receive permission from the Shift Manager or designee prior to performing this procedure.

2. Perform a pre-job briefing with all personnel involved covering the performance of this procedure and expected results.

3. The Unit is stable at Normal Operating Pressure and Normal Operating Temperature.

D. PRECAUTIONS

1. At least 2 groups of Pressurizer heaters shall be operable, each with a capacity of at least 150 KW, in Modes 1-3.

2. If PZR pressure starts to drop below 2229 psig on the lowest reading channel/computer point with both PZR spray valves indicating ZERO demand, IMMEDIATELY turn on Back-up Heaters as necessary to avoid PZR pressure decreasing below 2209 psig.

1

BwOP RY-11 Revision 2 Continuous Use E. LIMITATIONS AND ACTIONS

1. As stated in Tech Spec LCO 3.4.9

2. Do NOT exceed Pressurizer Pressure of 2260 PSIG.

3. Do NOT allow Pressurizer Pressure to drop below 2209 PSIG. If Pressurizer Pressure decreases below 2209 PSIG, then LCOAR _BwOL 3.4.1 must be entered.

4. If any primary or secondary manipulations need to be performed, do NOT proceed with this procedure until all Unit conditions are stable. Do NOT perform any primary or secondary manipulations while this procedure is in progress.

2

BwOP RY-11 Revision 2 Continuous Use CAUTION If any primary or secondary manipulations need to be performed, do NOT proceed with this procedure until all unit conditions are stable. Do NOT perform any primary or secondary manipulations while this procedure is in progress.

F. MAIN BODY

1. VERIFY Pressurizer pressure is at approximately 2235 psig from the lowest computer point indication P0480, P0481, P0482, P0483.

2. VERIFY the following computer points can be monitored:

PZR Pressure P0480 PZR Pressure P0481 PZR Pressure P0482 PZR Pressure P0483 PZR Spray Water A Inlet Temp T0483 PZR Spray Water B Inlet Temp T0484 PZR Spray Cont 1 F0483 PZR Spray Cont 2 F0484 PZR Steam Temp T0481 3

BwOP RY-11 Revision 2 Continuous Use CAUTION If PZR spray demand is zero, and the variable heaters are drawing current less than 100 amps, cautiously perform the next step with the concurrence of the Shift Manager and System Engineer. If PZR spray demand is zero and the variable heaters are drawing current greater than 100 amps, then Step 3 is N/A.

NOTE Perform the following step while monitoring PZR pressure. The NSO may make any adjustments to the PZR and/or unit to stabilize parameters.

F. 3. To place a B/U HTRS GRP_ CONTACTOR in the AUTO position from the ON position, PERFORM the following:

a. VERIFY/PLACE in MANUAL Master PZR Pressure Controller, _PK-455A.

b. SLOWLY DECREASE the Master PZR Pressure Controller, _PK 455A, demand until PZR pressure increases to approximately 2250 psig.

CAUTION If PZR pressure starts to drop below 2229 psig on the lowest reading channel/computer point with both PZR spray valves indicating zero demand, immediately turn on back-up heaters as necessary to avoid PZR pressure decreasing below 2209 psig.

c. PLACE the desired B/U HTRS GRP_ CONTACTOR C/S into AUTO.

d. MAINTAIN pressure between 2235 and 2250 psig by adjusting master PZR pressure controller _PK-455A as required until variable heaters energize and/or spray valves are closed.

4

BwOP RY-11 Revision 2 Continuous Use CAUTION When a B/U heater is deenergized, it will take some time to dissipate its latent heat. PZR pressure should be monitored at least 10 minutes before the pressure is considered stable.

F. 3. e. STABILIZE PZR pressure at approximately 2235 psig.

f. IF PZR spray valve demand is greater than zero, or variable heater load is less than 100 amps, THEN CONTINUE to take other backup heaters to the AUTO position as directed by Unit Supervisor, by repeating Step 3 for the other desired B/U HTRS GRP_ CONTACTORS (Otherwise proceed to next Step).

4. VERIFY/SET the PZR Master Pressure Controller, _PK-455A, potentiometer to maintain 2235 psig.

5. VERIFY/PLACE the PZR Master Pressure Controller, _PK-455A , in AUTO.

6. VERIFY that the PZR Master Pressure Controller, _PK-455A, is controlling PZR pressure at approximately 2235 psig in Auto.

(Final) 5

TASK CONDITIONS:

1. You are the Unit 1 Assist NSO.

2. Both Units are in Mode 4.

3. Yesterday, a fire in the MCR required implementation of 1/2BwOA PRI-5, CONTROL ROOM INACCESSIBLITY.

4. The fire is now extinguished. Individual systems and components are being evaluated by Engineering and then released to Operations to transfer control to the MCR from the RSDP.

Engineering has just released the 1B SX pump for transfer of control back to the MCR.

INITIATING CUES:

1. The Unit 1 Unit Supervisor has directed you to coordinate with the NSO at the RSDP for Unit 1 to restore remote control of the 1B SX pump from the MCR per 1BwOA PRI-5 Attachment D, RESTORING OPERATIONS FROM MAIN CONTROL ROOM step 5.

2. NO switches were repositioned at the Fire Hazards Panel for the event.

Page 1 of 5 SIM-410S

TASK TITLE: Restore Remote Control of 1B SX Pump from MCR JPM No.: SIM-410S REV: NRC 13-1 TPO No.: 4C.SX-03 K&A No.: 076000A4.01 TASK No.: R-SX-002/003, Startup/shutdown an Essential K&A IMP: 2.9/2.9 Service Water pump TRAINEE: RO SRO (Circle One)

EVALUATOR: DATE:

The Trainee: PASSED this JPM. TIME STARTED:

FAILED TIME FINISHED:

JPM TIME: MINUTES CRITICAL ELEMENTS: (*)4, 6 COMPLETION TIME: 22 MINUTES CRITICAL TIME: N/A ALTERNATE PATH: YES EVALUATION METHOD: LOCATION:

X PERFORM IN PLANT SIMULATE X SIMULATOR CONTROL ROOM GENERAL

REFERENCES:

1. 1BwOA PRI-5, CONTROL ROOM INACCESIBILITY, Rev. 106.

MATERIALS:

1. 1BwOA PRI-5, CONTROL ROOM INACCESIBILITY, Rev. 106 Attachment D, RESTORING OPERATIONS FROM MAIN CONTROL ROOM.

2. 1BwOA PRI-5, CONTROL ROOM INACCESIBILITY, Rev. 106 Attachment A, REMOTE SHUTDOWN PANEL LINEUP.

3. BwAR 1-2-A1 SX PUMP TRIP, Rev. 7.

TASK STANDARDS:

1. Restore control of 1B SX pump to MCR.

2. Respond to 1B SX pump trip and start 1A SX pump.

TASK CONDITIONS:

1. You are the Assist NSO.

2. Both Units are in Mode 4.

3. Yesterday, a fire in the MCR required implementation of 1/2BwOA PRI-5, CONTROL ROOM INACCESSIBLITY.

4. The fire is now extinguished. Individual systems and components are being evaluated by Engineering and then released to Operations to transfer control to the MCR from the RSDP.

Engineering has just released the 1B SX pump for transfer of control back to the MCR.

INITIATING CUES:

1. The Unit 1 Unit Supervisor has directed you to coordinate with the NSO at the RSDP for Unit 1 to restore remote control of the 1B SX pump from the MCR per 1BwOA PRI-5 Attachment D, RESTORING OPERATIONS FROM MAIN CONTROL ROOM step 5.

2. NO switches were repositioned at the Fire Hazards Panel for the event.

(Examiner hand trainee copy of Attachments A and D of 1BwOA PRI-5)

Page 2 of 5 SIM-410S

RECORD START TIME:

PERFORMANCE STEP STANDARD Circle applicable

1. Refer to 1BwOA PRI-5, Refer to 1BwOA PRI-5, SAT UNSAT N/A CONTROL ROOM CONTROL ROOM Comments:

INACCESIBILITY, Attachment D, INACCESIBILITY, Attachment RESTORING OPERATIONS D, RESTORING FROM MAIN CONTROL ROOM. OPERATIONS FROM MAIN CONTROL ROOM.

Copy of 1BwOA PRI-5 Attachments A and D provided with initiating cue.

2. Review logs for all local actions Review logs for all local SAT UNSAT N/A taken. actions taken. Comments:

CUE: Logs were previously reviewed and there are no issues related to the pump control transfer.

3. Restore indications to MCR by Restore indications to MCR by SAT UNSAT N/A placing Fire Hazards Panel placing Fire Hazards Panel Comments:

switches to - NORMAL. switches to - NORMAL.

INITIATING CUE: No

Switches are in normal.

switches were repositioned at the Fire Hazards Panel.

4. Transfer controls listed in Transfer controls listed in SAT UNSAT N/A Attachment A back to the MCR Attachment A back to the Comments:

one at a time. MCR one at a time.

CUE: When asked, report 1B SX pump control switch position at RSP is after-start.

At 1PM06J places C/S for CUE: Acknowledge as the 1SX01PB in normal after-NSO at the remote close.

shutdown panel to place

Place LOCAL/REMOTE the LOCAL/REMOTE switch at RSP in remote.

switch for 1B SX pump to remote.

NOTE: Cue the Simulator operator to initiate the pre-established commands to model placing the LOCAL/REMOTE switch in remote. Shortly after restoring control to the MCR, the 1B SX pump will trip.

Page 3 of 5 SIM-410S

- ALTERNATE PATH START**

5. Respond to 1B SX pump Trip Respond to 1B SX pump trip SAT UNSAT N/A using BwAR 1-2-A1 Comments:

At 1PM06J pulls BwAR

6. Verify/Align SX flowpath to meet Perform the following at SAT UNSAT N/A 1A SX pump start interlocks and 1PM06J: Comments:

Start 1A SX Pump o Verify/OPEN 1SX001A (is OPEN).

o Verify/OPEN 1SX016A (is open)

Verify/OPEN 1SX027A (currently closed) (must be performed, valve is CLOSED, examinee must OPEN the valve)

Places C/S for 1A SX pump to START and starts pump (initially in standby, RUNNING at completion of action).

7. Verify voltage on ALL 3 phases of Verify voltage on ALL 3 SAT UNSAT N/A 4KV bus > 3990 volts. phases of 4KV bus (141) > Comments:

CUE: ALL 3 phases are > 3990 3990 volts.

Volts.

CUE: THIS COMPLETES THIS JPM.

RECORD STOP TIME COMMENTS:

Page 4 of 5 SIM-410S

SIMULATOR SETUP INSTRUCTIONS JPM NO: SIM-410S REQUIRED SIMULATOR MODE (S): Any mode with SX available.

MALFUNCTION #S:

1. Verify/place the 1B SX pump in service and secure the 1A SX pump.

2. Secure the 1A and 1C RCFCs completely.

3. CLOSE 1SX027A.

Perform Items 4-6 or run CAE SIM-410S SETUP then continue with item 7.

4. Override Annunciator 1-2-E1 SX PUMP LOCAL CONT IMF PB2271 ON.

5. Override the 1B SX pump control switch to Normal After-close IOR ZDI1SX01PB NAC.

6. Override the lights for the 1B SX Pump off using the following:

a. IOR ZLO1SX01PB1 OFF (overrides STOP light to off)

b. IOR ZLO1SX01PB3 OFF (overrides RUN light off)

7. Place the physical control switch for 1B SX pump in PTL.

The simulator is now ready for the start of the JPM. You (Simulator Operator) will be required to monitor the progress of the JPM, and when cued by the examiner to perform the NSO action at the RSDP to place the LOCAL/REMOTE switch for the 1B SX pump in REMOTE, perform the following:

Perform the following (set on a trigger or run CAE SIM-410S RSDP switch to REMOTE):

8. DMF PB2271 (clears Annunciator 1-2-E1)

9. DOR ZDI1SX01PB (restores control of 1B SX C/S to the physical switch)

10. DOR ZLO1SX01PB1 (restores STOP light indication)

11. DOR ZLO1SX01PB3 (restores RUN light indication)

12. IMF SW01B 3 (trips 1B SX pump with 3 second delay)

COMMENTS:

1. This JPM requires that the Simulator Operator be available to perform action as the NSO at the Unit 1 RSDP in restoring control of the 1B SX pump to the MCR.

Page 5 of 5 SIM-410S

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 A. PURPOSE This procedure provides actions required to take the plant to Cold Shutdown in the event that the Main Control Room must be evacuated.

B. SYMPTOMS OR ENTRY CONDITIONS This procedure is entered from 0BwOA PRI-5, CONTROL ROOM INACCESSIBILITY when the MCR must be evacuated.

Page 1 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED (PG 1 OF 1)

TABLE OF CONTENTS 1 SECTION SECTION:: TITLE:

MAIN BODY ATTACHMENT A (Page 49) REMOTE SHUTDOWN PANEL LINEUP ATTACHMENT B (Page 53) LOCAL OPERATOR ACTIONS ATTACHMENT C (Page 57) INSTALLATION OF RH SYSTEM PNEUMATIC JUMPERS ATTACHMENT D (Page 58) RESTORING OPERATIONS FROM MCR ATTACHMENT E (Page 61) ESF MANUAL BLOCK OR RESET ATTACHMENT F (Page 78) SI TERMINATION ATTACHMENT G (Page 86) *MAINTAINING HOT STANDBY WITH AN SI

-END-Page 2 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 1 VERIFY REACTOR TRIP TRIP::

a. Trip Reactor

b. Check reactor trip and bypass b. Locally trip the breakers.

breakers - OPEN OPEN::

RTA and BYA RTB and BYB

c. Check rod bottom lights - LIT c. IF TWO OR more rods are NOT fully inserted, THEN initiate boration:

1) Start the Boric Acid transfer pump.

2) Open the emergency boration valve, 1CV8104.

d. Check Neutron Flux - DROPPPING 2 CHECK IF IMMEDIATE MCR EVACUATION REQUIRED REQUIRED::

a. Fire in the MCR requires - a. GO TO Step 3.

IMMEDIATE EVACUATION

b. GO TO Step 7 (Page 5) 3 VERIFY TURBINE TRIPPED TRIPPED:: Manually trip the turbine.

All Turbine throttle valves - IF any throttle AND any CLOSED governor valve are open, THEN locally trip the turbine All Turbine governor valves - at the pedestal.

CLOSED 4 VERIFY POWER TO 4KV ESF BUSES BUSES:

Locally restore at least ONE 4KV ESF bus per:

ESF buses - BOTH ENERGIZED ENERGIZED:

1BwOA ELEC-3, LOSS OF 4KV Bus 141 ESF BUS:

Bus 142 o ATTACHMENT B (1A DG) o ATTACHMENT D (1B DG)

Page 3 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 5 VERIFY FEEDWATER ISOLATION :

ISOLATION:

a. Feedwater isolation monitor a. Manually close the lights - LIT valve(s).

IF any feedwater reg valve will NOT close, THEN close the associated 1FW006 valve.

b. Trip Feedwater pumps: b. Locally trip the pumps.

FW pump 1A FW pump 1B FW pump 1C Startup Feedwater pump

c. Trip HD pumps: c. Locally trip the pumps.

HD pump 1A HD pump 1B HD pump 1C Page 4 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6 PREPARE FOR RSP OPERATIONS :

OPERATIONS:

a. Verify letdown divert valve in - AUTO AUTO::

1CV112A

b. Establish - 45 GPM LETDOWN

c. Place PZR PRESSURE CONTROL CHANNEL SELECTOR to - 457/458

d. Place PZR LEVEL CONTROL CHANNEL SELECTOR to - 461/460

e. Pick up radio

f. Open RCS loop sample containment isolation valves:

1PS9356A (1PM11J) 1PS9356B (1PM11J)

g. Open PZR liquid sample containment isolation valves:

1PS9355A (1PM11J) 1PS9355B (1PM11J)

h. Open PZR steam sample containment isolation valves:

1PS9354A (1PM11J) 1PS9354B (1PM11J) 7 DISPATCH OPERATOR TO PERFORM ATTACHMENT B (Page 53)

Page 5 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

>>¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥ CAUTION Taking ANY control switch on the Fire Hazards Panel to the FIRE position:

Removes ALL indications from the RSP and MCR.

Feeds a low signal to the affected loop.

May cause ESF actuations if another channel is already tripped OR in test.

¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥º 8 ACTIVATE RSP RSP:

a. Unit Supervisor and NSO go to RSP

b. Align RSP per ATTACHMENT A (Page 49)

c. Check following indications - c. Dispatch an operator to AVAILABLE AVAILABLE:: the Fire Hazards Panel (426' S12 CWA) to align Source Range NI needed instrumentation.

Intermediate Range NI SG pressures SG wide range levels PZR pressure PZR level RCS hot leg temperatures RCS cold leg temperatures

d. Maintain log of:

All jumpers installed All local actions taken Page 6 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 9 MCR EVACUATED DUE TO FIRE FIRE:: GO TO STEP 10.

a. Open the following breakers:

MCC 131X1 M3 (1SI8811A)

MCC 132X4 H1 (1SI8811B)

b. Locally check CNMT sump b. Perform the following:

isolation valves - CLOSED CLOSED::

1) Open the following 1SI8811A (364' U13 CWA) breaker(s):

1SI8811B (364' X13 CWA) o MCC 131X1A Q1 (1SI8812A) o MCC 132X4A M2 (1SI8812B)

2) Locally close RH pump suction from RWST isolation valve(s):

o 1SI8812A (1A CS Pump Rm) o 1SI8812B (1B RH Pump Rm) 10 CHECK STEAM GENERATOR LEVELS LEVELS::

a. AF pumps - AT LEAST ONE RUNNING a. Start an AF pump per:

o BwOP AF-5, MOTOR DRIVEN AUXILIARY FEEDWATER PUMP

_A STARTUP ON RECIRC o BwOP AF-7, AUXILIARY FEEDWATER PUMP _B (DIESEL) STARTUP ON RECIRC

b. Control AF flow to maintain ALL b. Locally fail air and SG wide range levels - BETWEEN throttle the 1AF005 flow 65% AND 70% control valves.

(364' P10 HANDWHEEL)

Page 7 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 11 CHECK SI STATUS STATUS::

a. Following equipment - NOT AUTO a. Dispatch an operator to STARTED STARTED:: verify SI actuation by checking status of BOTH SI CV Pumps - ONLY ONE RUNNING pump breakers.

SX Pumps - ONLY ONE RUNNING IF EITHER SI pump breaker is CLOSED, CC Pumps - ONLY ONE RUNNING THEN GO TO ATTACHMENT F (Page 78).

Diesel Generators - NONE RUNNING 12 CHECK MODE MODE::

a. Unit in - MODE 3 a. IF the unit is in Mode 4, THEN GO TO Step 31 (Page 36).

IF the unit is in Mode 5 or 6, THEN GO TO Step 38b (Page 45).

b. RCS cooldown - NOT PREVIOUSLY b. GO TO Step 14 (Page 10).

IN PROGRESS Page 8 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 13 CHECK RCS AVERAGE TEMPERATURE TEMPERATURE: :

a. Determine Tave using EITHER of a. Calculate Tave using the the following: following:

o Process computer points: o Saturation temperature for SG pressure in place o T0400 RCL1 1 TAVG of cold leg wide range o T0420 RCL2 1 TAVG temperature.

o T0440 RCL3 1 TAVG o T0460 RCL4 1 TAVG o RCS hot leg and cold leg temperatures from the

-OR- Fire Hazards Panel.

o Calculate using hot leg and cold leg wide range temperatures

b. RCS Tave - LESS THAN 561 561F b. Reduce Tave to 561 F:

561 o Manually open SG PORV(s).

-OR-o Locally open SG PORV(s) per BwOP MS-6, LOCAL OPERATION OF THE SG PORVs.

GO TO Step 14 (Next Page).

c. RCS Tave - STABLE c. IF RCS Tave drops less than 557 557F, THEN perform the following:

1) Close ALL MSIVs.

2) IF cooldown continues, THEN control AF flow.

Maintain flow greater than 500 GPM until wide range level is greater than 59% in at least ONE SG.

Page 9 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

NOTE *

The jumpers installed in Step 14a *

RNO also defeat the PZR heater level *

interlocks.

14 MONITOR PZR PRESSURE PRESSURE:

a. PZR pressure - GREATER THAN a. Perform the following:

2220 PSIG

1) IF PZR pressure is dropping, THEN trip RCP(s) as required to stop PZR pressure drop:

RCP 1D RCP 1C RCP 1B RCP 1A

2) IF PZR pressure is still dropping, THEN perform the following:

a) Place the LOCAL/REMOTE switch at the breaker in LOCAL:

1RY8000A (1RY455A)

MCC 131X2B A5 1RY8000B (1RY456)

MCC 132X2 C4 b) Locally close PORV block valves:

1RY8000A (1RY455A) 1RY8000B (1RY456)

Step continued on next page Page 10 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED Step 14 (continued)

3) IF any PORV block valve can NOT be closed, THEN locally remove the PORV control power fuses to fail its associated PORV closed:

o 1RY455A (at 1DC10J):

FU-11 FU-12 o 1RY456 (at 1DC11J):

FU-46 FU-47

4) IF a controlled depressurization was in progress, THEN GO TO Step 15 (Page 14).

5) Verify PZR backup heaters are ON:

Group A Group B Step continued on next page Page 11 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED Step 14 (continued)

IF ANY backup heater can NOT be energized AND PZR level is greater than 17%

17%,,

THEN jumper the control contactor to energize the heater:

o Group A contactor:

Install jumper in 1PL06J from Terminal Board 1, point 104, to Terminal Board 1, point 99.

o Group B contactor:

Install jumper in 1PL06J from Terminal Board 3, point 113, to Terminal Board 3, point 107.

b. PZR pressure - LESS THAN b. Perform the following:

2260 PSIG

1) Verify PZR heaters are OFF:

Group A Group B

2) Control pressure with the PZR aux spray valve:

1CV8145 Step continued on next page Page 12 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED Step 14 (continued)

c. PZR pressure - STABLE AT OR c. Manually control PZR TRENDING TO 2235 PSIG pressure with PZR heaters and the PZR aux spray valve.

IF manual pressure control is NOT available, THEN perform the following while continuing with this procedure:

1) Fill the PZR solid.

2) Control charging flow to control PZR pressure.

Page 13 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 15 VERIFY RCP SEAL COOLING COOLING: :

a. Check following computer a. Perform the following:

points - AVAILABLE AVAILABLE::

1) Locally monitor RCP seal Seal water outlet injection flow:

temperature:

1FIT-0145 (1A RCP)

T0181 (RCP 1A) (383' V17)

T0182 (RCP 1B) 1FIT-0142 (1D RCP)

T0183 (RCP 1C) (383' V17)

T0184 (RCP 1D) 1FIT-0144 (1B RCP)

(364' U17)

Lower bearing temperature: 1FIT-0143 (1C RCP)

(364' U17)

T0417 (RCP 1A)

T0437 (RCP 1B) 2) IF seal injection flow T0457 (RCP 1C) is indicated on all RCPs, T0477 (RCP 1D) THEN GO TO Step 15d (Page 17).

3) IF any RCP with no indicated seal injection flow also has no indication of seal leakoff OR lower radial bearing temperature, THEN perform the following:

a) Trip affected RCP(s).

b) Close associated RCP seal injection manual flow control valve:

o 1CV8369A (391' CWA P-33) o 1CV8369B (387' CWA P-53) o 1CV8369C (387' CWA P-53) o 1CV8369D (391' CWA P-33)

Step continued on next page Page 14 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED Step 15 (continued)

4) Check CC flow to RCP thermal barriers between 150 GPM and 231 GPM GPM:

1FIS-685A (383' U18)

5) IF no CC flow is indicated to the RCP thermal barriers, THEN locally close CC from RCPs thermal barrier isolation valve:

1CC685 (395' CWA P-24)

6) IF no CC flow is indicated AND a fire has occurred in the plant, THEN locally close the following valve to provide double isolation of CC from the thermal barrier:

1CC9438 (395' R7)

7) GO TO Step 15c (Next Page).

Step continued on next page Page 15 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED Step 15 (continued)

b. Check RCP temperatures - LESS b. Perform the following:

THAN LIMITS LIMITS::

1) Trip affected RCP(s).

Seal water outlet temperatures - LESS THAN 2) Close associated RCP 235 235F seal injection manual flow control valve:

Lower bearing temperatures -

LESS THAN 225 F 225 o 1CV8369A (391' CWA P-33) o 1CV8369B (387' CWA P-53) o 1CV8369C (387' CWA P-53) o 1CV8369D (391' CWA P-33)

3) Locally close CC from RCPs thermal barrier isolation valve:

1CC685 (395' CWA P-24)

4) IF a fire has occured in the plant, THEN locally close the following valve to provide double isolation of CC from the RCP thermal barriers:

1CC9438 (395' R7)

c. Check CENT CHG pumps - AT LEAST c. WHEN CENT CHG pump suction ONE RUNNING has been aligned to the RWST, THEN start one CENT CHG pump.

Step continued on next page Page 16 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED Step 15 (continued)

d. Throttle 1CV121 to maintain seal injection flow - BETWEEN 10 GPM AND 15 GPM PER PUMP (UNLESS PREVIOUSLY ISOLATED)

ISOLATED)::

1FIT-0145 (1A RCP) (383' V17) 1FIT-0142 (1D RCP) (383' V17) 1FIT-0144 (1B RCP) (364' U17) 1FIT-0143 (1C RCP) (364' U17)

e. Monitor RCP seal status:

o Computer points o Local seal injection flow Page 17 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 16 CHECK PZR LEVEL :

LEVEL:

a. Check charging flow - INDICATED INDICATED:: a. Establish charging flow using 1CV121.

o 1FI-121B (1PL06J)

IF manual control of o F0128 Charg Pump Disch Hdr 1CV121 is NOT available, Flow THEN locally bypass 1CV121:

1) Open the charging header flow control bypass valve for the running CV pump:

o 1CV8387A (364' U15 1A CV pump room) o 1CV8387B (364' Y14 1B CV pump room)

2) Close at least ONE charging header flow control valve manual isolation:

o 1CV8483A (364' +10' U13 CWA) o 1CV8483B (364' +8' U13 CWA)

3) Throttle the charging header flow control bypass valve to maintain PZR level.

Step continued on next page Page 18 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED Step 16 (continued)

4) IF charging flow can NOT be established with 1CV121, THEN perform the following:

a) Locally throttle open one CENT CHG pump to cold leg isolation valve:

o 1SI8801A (395' CWA P-26) o 1SI8801B (395' CWA P-26) b) IF the PZR is NOT being maintained water solid, THEN maintain PZR level between 25% and 31%

31%..

c) GO TO Step 17 (Page 23).

b. Dispatch an operator to bypass 1CV182:

1) Throttle open charging header flow control bypass valve:

1CV8403 (364' V13 CWA P-71)

2) Close charging header flow control manual isolation valves:

1CV8402A (364' V13 CWA P-71) 1CV8402B (364' V13 CWA P-71)

Step continued on next page Page 19 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED Step 16 (continued)

c. Check PZR level - GREATER THAN c. Perform the following:

17%

1) Verify letdown isolation valves closed:

1CV459 1CV460 1CV8149A 1CV8149B 1CV8149C

2) Verify group A and B PZR heaters are OFF.

3) Raise charging flow to restore PZR level to greater than 17%

17%.

4) Continue with Step 17 (Page 23),

WHEN PZR level is greater than 17%

17%,

THEN restore letdown per Step 16d RNO.

Step continued on next page Page 20 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED Step 16 (continued)

d. Check letdown - IN SERVICE SERVICE:: d. IF normal charging is in service, o Letdown orifice isolation THEN perform the following valves - ANY OPEN OPEN:: to restore letdown:

o 1CV8149A 1) Manually open the o 1CV8149B letdown isolation o 1CV8149C valves:

-OR- 1CV459 1CV460 o F0134 Ltdn Hx Ltdn Outlet Flow 2) Manually open the letdown orifice isolation valve(s) to establish 45 GPM GPM:

o 1CV8149A o 1CV8149B o 1CV8149C IF letdown can NOT be restored, THEN perform the following:

1) Verify CC flow to RCP thermal barriers between 150 GPM and 231 GPM (unless previously isolated):

1FIS-685A (383' U18)

2) Locally close charging header flow control bypass valve:

1CV8403 (364' V13 CWA P-71)

Step continued on next page Page 21 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED Step 16 (continued)

3) Throttle 1CV121 to maintain seal injection flow between 6 GPM and 8 GPM per pump to minimize PZR level rise (unless PZR is being maintained water solid):

F0131 RCP 1 Seal Injection Wtr Flow F0129 RCP 2 Seal Injection Wtr Flow F0127 RCP 3 Seal Injection Wtr Flow F0125 RCP 4 Seal Injection Wtr Flow

4) GO TO Step 16f.

e. Check letdown orifice isolation e. Establish at least 45 GPM valves aligned to establish - letdown.

45 GPM LETDOWN LETDOWN::

o 1CV8149A o 1CV8149B o 1CV8149C

f. Check PZR bubble - BEING f. IF pressure is being MAINTAINED FOR PRESSURE CONTROL controlled with a solid PZR, THEN maintain the PZR solid.

GO TO Step 17 (Next Page).

g. Adjust 1CV121 to maintain PZR level - BETWEEN 25% AND 31%

Page 22 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 17 CHECK RCP STATUS STATUS::

a. RCPs - AT LEAST ONE RUNNING a. Verify natural circulation:

RCS subcooling acceptable per:

o Computer point X0190, Degrees of Subcooling

-OR-o Iconic Display

-OR-o FIGURE 1BwOA PRI-5-1 (Page 48) using:

PZR pressure RCS temperature from RCS hot leg temperature indication SG pressure stable OR dropping.

RCS hot leg temperature stable OR dropping.

Average of ten highest core exit TCs stable OR dropping per:

o Computer point X0113, Core Exit T Avg 10 Hottest

-OR-o Iconic Display RCS cold leg temperature at saturation for SG pressure.

IF natural circulation can NOT be verified, THEN dump more steam from SGs.

Page 23 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 18 CHECK IF SOURCE RANGE DETECTORS SHOULD BE ENERGIZED ENERGIZED::

a. IR current - LESS THAN a. Continue with Step 19 10-10 AMPS AMPS:: (Next Page),

WHEN IR current is less 1NI-NR003 (N35) than 10-10 AMPS AMPS,,

1NI-NR004 (N36) THEN do Step 18b.

b. SR detectors - ENERGIZED ENERGIZED:: b. Verify P10 AND P6 reset by checking the following 1NI-NR001 (N31) computer points indicate 1NI-NR002 (N32) RESET:

ND0011 Nucl Pwr 1 RE TR P10 Part Perm ND0012 Nucl Pwr 2 RE TR P10 Part Perm ND0013 Nucl Pwr 3 RE TR P10 Part Perm ND0014 Nucl Pwr 4 RE TR P10 Part Perm ND0032 Interm Rng 1 RE TR P6 Part Block ND0033 Interm Rng 2 RE TR P6 Part Block IF P10 OR P6 are NOT RESET, THEN reset per ATTACHMENT E (Page 61).

Page 24 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 19 MAINTAIN STABLE PLANT CONDITIONS CONDITIONS::

a. Check controlled cooldown and a. GO TO Step 19c.

depressurization - NOT PREVIOUSLY IN PROGRESS

b. Maintain RCS Tave - BETWEEN 550 550F AND 561 561F

c. Check PZR bubble - BEING c. IF pressure is being MAINTAINED FOR PRESSURE CONTROL controlled with a solid PZR, THEN throttle 1CV121 to control PZR pressure.

GO TO Step 19f.

d. Maintain PZR pressure - BETWEEN 2220 PSIG AND 2260 PSIG

e. Maintain PZR level - BETWEEN 25% AND 31%

f. Maintain SG wide range levels -

BETWEEN 65% AND 70%

g. Check VCT level - LESS THAN 95% g. Perform the following:

1) Verify primary water pump 0A and boric acid transfer pump are OFF.

2) Contact UNIT 2 to verify primary water pump 0B is OFF.

h. Check current RCS boron h. Borate until shutdown sample - GREATER THAN SHUTDOWN margin requirements are MARGIN REQUIREMENT per: met.

1BwOSR 3.1.1.1-1, SHUTDOWN MARGIN VERIFICATION DURING SHUTDOWN

i. Complete applicable actions of 1BwGP 100-5, PLANT SHUTDOWN AND COOLDOWN Step continued on next page Page 25 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED Step 19 (continued)

j. Dispatch operators to complete shutdown procedures for tripped FW pumps and HD pumps

k. Dispatch an operator to prop open room door for running CENT CHG pump - IF NECESSARY TO MAINTAIN ROOM TEMPERATURE NORMAL

l. STA implement Status Tree monitoring for both units 20 CHECK RCFC STATUS STATUS:

a. RCFCs - AT LEAST ONE RUNNING IN a. Manually start ONE RCFC.

HI SPEED IF NO RCFCs can be manually started, THEN locally start at least ONE RCFC:

1) Verify ALL RCFC LO speed breakers are OPEN OPEN:

Bus 131X 4C (1A RCFC)

Bus 131X 2C (1C RCFC)

Bus 132X 4C (1B RCFC)

Bus 132X 2C (1D RCFC)

2) Close the HI speed breaker for at least ONE RCFC:

Bus 131X 5C (1A RCFC)

Bus 131X 3C (1C RCFC)

Bus 132X 5C (1B RCFC)

Bus 132X 3C (1D RCFC) 21 CHECK CRDM EXHAUST FANS FANS:

a. Exhaust fans - RUNNING RUNNING:

a. Manually start the fans.

1VP03CA 1VP03CB 1VP03CC 1VP03CD Page 26 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 22 CHECK CST LEVEL INDICATION INDICATION::

a. Check CST level indication - a. Perform the following:

AVAILABLE AVAILABLE::

1) Crosstie U-1 CST to U-2 o 0PL01J RADWASTE ROOM CST per BwOP CD-2, o 0PL11J MUDS RAISING CST LEVEL WITH MAKEUP OR BY CROSSTYING

2) Monitor U-1 CST level on U-2 CST level indication:

2LI-CD051B (0PL01J) 2LI-CD051C (0PL11J) 23 DETERMINE LONG TERM PLANT STATUS STATUS::

a. Shift Manager determines: a. RETURN TO Step 13 (Page 9).

o Hot Shutdown - DESIRED o Cold Shutdown - DESIRED Page 27 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

>>¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥ CAUTION PZR pressure may drop rapidly during cooldown if the RCS is water solid.

¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥º

NOTE *

SG wide range level is cold *

calibrated. As SG temperature *

drops, wide range indicated level *

must be raised to maintain actual *

level constant.

24 INITIATE RCS COOLDOWN TO 350 F:

350

a. Check Shutdown Margin - a. Borate until Shutdown ADEQUATE FOR HOT SHUTDOWN per: Margin requirements are met.

1BwOSR 3.1.1.1-1, SHUTDOWN WHEN shutdown margin MARGIN DAILY VERIFICATION requirements are met, DURING SHUTDOWN. THEN continue with Step 24b.

b. Stop all but one RCP

c. Maintain cooldown rate in RCS cold legs - LESS THAN OR EQUAL TO 50 50F IN ANY 1 HR PERIOD

d. Maintain RCS temperature and pressure per 1BwOSR 3.4.3.1, RCS PRESSURE/TEMPERATURE LIMIT SURVEILLANCE

e. Dump steam using SG PORVs e. Locally open SG PORVs per BwOP MS-6, LOCAL OPERATION OF THE SG PORVs.

f. Control AF flow to maintain ALL f. Locally fail air and SG wide range levels - BETWEEN throttle the 1AF005 flow 65% AND 70% control valves.

(364' P10 HANDWHEELS)

Page 28 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 25 DEPRESSURIZE RCS TO 1880 PSIG :

PSIG:

a. Turn Group A and B PZR a. Locally open 480 volt feed heaters - OFF breaker(s):

o Group A:

Bus 1RY01EA Cub B2 (414' S12 CWA) o Group B:

Bus 1RY01EB Cub B2 (426' S12 CWA)

b. Locally open 480 volt feed breakers to PZR heater groups C and D:

Group C:

Bus 1RY01EC Cub B2 (426' S12 CWA)

Group D:

Bus 1RY01ED Cub B2 (414' S12 CWA)

c. Check PZR bubble - BEING c. Perform the following:

MAINTAINED FOR PRESSURE CONTROL

1) Depressurize by reducing charging flow.

2) GO TO Step 25f.

d. Monitor PZR spray water temperature differential per 1BwOS TRM 3.4.c.1, PRESSURIZER TEMPERATURE LIMIT SURVEILLANCE Step continued on next page Page 29 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED Step 25 (continued)

e. Depressurize RCS using PZR aux e. IF PZR aux spray can NOT spray: be used, THEN depressurize using a

1) Check letdown - IN SERVICE PZR PORV:

2) Check PZR spray water 1) Contact Electrical differential - LESS THAN Maintenance to repair a 320 320F: PZR PORV per MA-BR-726-633, T0126 Regen HX Charg Out T INSTALLATION OF T0481 PZR Steam T POST-FIRE COLD SHUTDOWN EMERGENCY CABLE.

3) Open PZR aux spray valve:

2) Depressurize using the 1CV8145 repaired PZR PORV:

o 1RY455A o 1RY456

f. Check RCS pressure - LESS THAN f. RETURN TO Step 25c 1880 PSIG (Previous Page).

g. Stop depressurization:

o Close PZR aux spray valve o Close PZR PORV

h. Maintain 1880 PSIG using:

o PZR heaters o PZR aux spray o Charging flow o PZR PORV Page 30 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 26 BLOCK SI ACTUATIONS :

ACTUATIONS: RETURN TO Step 22 (Page 27).

a. Block following SI signals per ATTACHMENT E (Page 61):

PZR LOW PRESS SI STEAMLINE LOW PRESS SI

b. Verify SI signals blocked:

Computer points indicate -

SET SET::

PD0495 PZR LO P SI TRN A Block PD0496 PZR LO P SI TRN B Block PD0570 SG LO STM LINE P SI TRN 1 BLOK PD0571 SG LO STM LINE P SI TRN 2 BLOK Page 31 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 27 CONTINUE RCS COOLDOWN AND DEPRESSURIZATION DEPRESSURIZATION: :

a. Determine RCS wide range a. Locally align pressure pressure from process computer indicator 1PI-PS298 (HRSS points: panel 1PS25J) to EITHER of the following:

o P0491 RCS Wide Rng Ch IV o P0492 RCS Wide Rng Ch II o PZR steam sample line:

o P0493 RCS Wide Rng Ch I o P0494 RCS Wide Rng Ch III a) Open PZR steam inlet isolation valve:

1PS9350A (HRSS panel 1PS27J) b) Open valve 1.1 (HRSS Panel 1PS25J)

-OR-o PZR liquid sample line:

a) Open PZR liquid inlet isolation valve:

1PS9350B (HRSS panel 1PS27J) b) Open valve 1.2 (HRSS Panel 1PS25J)

IF NO RCS pressure indication is available, THEN contact Electrical Maintenance to repair a wide range RCS pressure transmitter:

o 1PI-403 o 1PI-405

b. Maintain RCS cooldown rate -

LESS THAN 50 50F IN ANY 1 HR PERIOD

c. Verify ALL PZR heaters - OFF Step continued on next page Page 32 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED Step 27 (continued)

d. Continue depressurization:

o Open PZR aux spray valve:

1CV8145 o Open repaired PZR PORV

e. Check PZR bubble - BEING e. IF pressure is being MAINTAINED FOR PRESSURE CONTROL controlled with a solid PZR, THEN maintain the PZR solid.

GO TO Step 27g.

f. Maintain PZR level - BETWEEN 25% AND 31%

g. Complete applicable actions of 1BwGP 100-5, PLANT SHUTDOWN AND COOLDOWN Page 33 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

>>¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥ CAUTION SI accumulators should be isolated when RCS pressure is between 1000 PSIG and 800 PSIG PSIG.

¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥º 28 CHECK IF SI ACCUMULATORS SHOULD BE ISOLATED ISOLATED::

a. RCS pressure - LESS THAN a. Continue with Step 29 1000 PSIG (Next Page),

WHEN RCS pressure is less than 1000 PSIG PSIG,,

THEN do Steps 28b thru 28c.

b. Close SI accumulator discharge valves:

Train A (1SI8808A and D):

a) Energize SVAG VALVE MCC per 1BwOA ELEC-5, LOCAL EMERGENCY CONTROL OF SAFE SHUTDOWN EQUIPMENT b) Locally close SI b) Close SI accumulator accumulator discharge discharge valve(s):

valves per 1BwOA ELEC-5, LOCAL EMERGENCY CONTROL OF o 1SI8808A (412' R15 SAFE SHUTDOWN EQUIPMENT OMB) o 1SI8808D (412' R9 MCC 131X2A A3 (1SI8808A) OMB)

(414' S12 CWA)

MCC 131X2A A2 (1SI8808D)

(414' S12 CWA)

Train B (1SI8808B and C):

a) Energize SVAG VALVE MCC per 1BwOA ELEC-5, LOCAL EMERGENCY CONTROL OF SAFE SHUTDOWN EQUIPMENT b) Locally close SI b) Close SI accumulator accumulator discharge discharge valve(s):

valves per 1BwOA ELEC-5, LOCAL EMERGENCY CONTROL OF o 1SI8808B (412' R18 SAFE SHUTDOWN EQUIPMENT OMB) o 1SI8808C (412' R5 MCC 132X2A A3 (1SI8808B) OMB)

(426' S12 CWA)

MCC 132X2A A2 (1SI8808C)

(426' S12 CWA)

Page 34 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 29 CHECK IF COLD OVERPRESSURE PROTECTION CAN BE PLACED IN SERVICE SERVICE: :

a. RCS temperature - LESS THAN a. Continue to cooldown, 380 380F WHEN RCS temperature is less than 380 F, 380 THEN do Step 29b.

b. Place Cold Overpressure b. Refer to Tech Spec 3.4.12.

Protection in service per ATTACHMENT E (Page 61) 30 CHECK IF ECCS PUMPS SHOULD BE LOCKED OUT OUT:

a. RCS temperature - LESS THAN a. RETURN TO Step 27 350 350F (Page 32).

b. Locally rack out breakers for the following ECCS equipment:

BOTH SI pumps:

Bus 141 Cub 3 (SI Pump 1A)

Bus 142 Cub 3 (SI Pump 1B)

Non-running CV pump:

o Bus 141 Cub 11 (CV pump 1A) o Bus 142 Cub 10 (CV pump 1B)

Page 35 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 31 MAINTAIN STABLE PLANT CONDITIONS CONDITIONS::

a. RCS average temperature - LESS THAN 350 F 350

b. RCS pressure - BETWEEN 330 PSIG AND 360 PSIG

c. Check PZR bubble - BEING c. IF pressure is being MAINTAINED FOR PRESSURE CONTROL controlled with a solid PZR, THEN throttle 1CV121 to control PZR pressure.

GO TO Step 31e.

d. PZR level - BETWEEN 25% AND 31%

e. SG wide range levels - BETWEEN 65% AND 70%

f. Check VCT level - LESS THAN 95% f. Perform the following:

1) Verify primary water pump 0A and boric acid transfer pump are OFF.

2) Contact UNIT 2 to verify primary water pump 0B is OFF.

g. Complete applicable actions of 1BwGP 100-5, PLANT SHUTDOWN AND COOLDOWN 32 DETERMINE LONG TERM PLANT STATUS STATUS::

a. Shift Manager determines - COLD a. RETURN TO Step 31.

SHUTDOWN DESIRED Page 36 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

NOTE *

Cooldown on SGs is preferable to RH *

cooldown due to lack of RH controls *

and indications at the RSP.

33 CONTINUE RCS COOLDOWN TO 200 200F:

a. Check Shutdown Margin - a. Borate until Shutdown ADEQUATE FOR COLD SHUTDOWN per per:

Margin requirements are met.

1BwOSR 3.1.1.1-1, SHUTDOWN WHEN shutdown margin MARGIN VERIFICATION DURING requirements are met, SHUTDOWN THEN continue with Step 33b.

b. Maintain RCS pressure - BETWEEN 330 PSIG AND 360 PSIG

c. Continue to cool down with SG PORVs

d. Check RCS temperature - d. Align SG blowdown to DROPPING control RCS temperature.

IF sufficient cooldown can NOT be obtained with SG PORVs AND SG blowdown, THEN GO TO Step 34 (Next Page).

e. RETURN TO Step 32 (Previous Page)

Page 37 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 34 ALIGN RH SYSTEM FOR SAMPLING :

SAMPLING:

a. RH pumps - NONE RUNNING IN a. GO TO Step 38b (Page 45).

SHUTDOWN COOLING MODE

b. Refer to BwOP RH-5, RH SYSTEM STARTUP FOR RECIRC, for applicable actions

c. Verify RH hot leg suctions c. Locally verify RH pump hot isolated from RCS by checking leg suction valves are RH suction pressure - AT LEAST CLOSED CLOSED::

50 PSIG LESS THAN RCS WIDE RANGE PRESSURE PRESSURE:: 1RH8701A (377' R7 OMB P-68)

RH suction pressure: 1RH8702A (377' R4 OMB P-75) o Computer points: 1RH8701B (377' R11 IMB near "D" loop against Rx P0601 RH Pump 1A Suct cavity wall)

Press 1RH8702B (377' R3 IMB P0602 RH Pump 1B Suct near "C" loop against Rx Press cavity wall) o Local gauge pressure:

1PI-0601 (RH Pump 1A)

(346' V16) 1PI-0602 (RH Pump 1B)

(346' W15)

-AND-RCS wide range pressure:

o Computer points:

o P0491 RCS Wide Rng Ch IV o P0492 RCS Wide RnG Ch II o Local gauge pressure:

o 1PI-402 (at Panel 1PL66J) (377' R1) o 1PI-404 (at Panel 1PL54J) (377' R11)

Step continued on next page Page 38 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED Step 34 (continued)

d. Locally check RH pump miniflow d. Locally open any closed valves - OPEN :

OPEN: valve using 1BwOA ELEC-5, LOCAL EMERGENCY CONTROL OF 1RH610 (357' S16 in NW corner SAFE SHUTDOWN EQUIPMENT:

of 1A RH HX Room) 1RH611 (357' V16 in NW corner o MCC 131X1 F2 (1RH610) of 1B RH HX Room) o MCC 132X1 C4 (1RH611)

e. Locally check containment e. Locally close any open recirc sump valves - CLOSED CLOSED:: valve using 1BwOA ELEC-5, LOCAL EMERGENCY CONTROL OF 1SI8811A (364' U13 CWA) SAFE SHUTDOWN EQUIPMENT:

1SI8811B (364' X13 CWA) o MCC 131X1 M3 (1SI8811A) o MCC 132X4 H1 (1SI8811B)

f. Locally check RH HX to CV and f. Locally close any open SI pumps isolation valves - valve using 1BwOA ELEC-5, CLOSED CLOSED:

LOCAL EMERGENCY CONTROL OF SAFE SHUTDOWN EQUIPMENT:

1CV8804A (364' S13 CWA) 1SI8804B (364' Y13 above 1B o MCC 131X1 J5 (1CV8804A)

SI pump) o MCC 132X4 E1 (1SI8804B)

g. Locally check CS sump suction g. Locally close any open valves - CLOSED CLOSED:

valve using 1BwOA ELEC-5, LOCAL EMERGENCY CONTROL OF 1CS009A (1A CS pump room) SAFE SHUTDOWN EQUIPMENT:

1CS009B (1B CS pump room) o MCC 131X1 C1 (1CS009A) o MCC 132X1 G1 (1CS009B)

h. Locally check RWST to RH pump h. Locally open any closed outlet isolation valves - OPEN OPEN:

valve using 1BwOA ELEC-5, LOCAL EMERGENCY CONTROL OF 1SI8812A (1A CS Pump Rm) SAFE SHUTDOWN EQUIPMENT:

1SI8812B (1B RH Pump Rm) o MCC 131X1A Q1 (1SI8812A) o MCC 132X4A M2 (1SI8812B)

Step continued on next page Page 39 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED Step 34 (continued)

i. Install pneumatic i. RETURN TO Step 32 jumper/regulator to bypass (Page 36).

signal converters for selected RH flow control valves per ATTACHMENT C (Page 57):

o RH Pump 1A:

1RH606 1RH618 o RH Pump 1B:

1RH607 1RH619

j. Locally close selected RH train j. RETURN TO Step 32 HX flow control valve using (Page 36).

pneumatic jumper/regulator:

o 1RH606 o 1RH607

k. Locally verify selected RH k. Close valve using train HX bypass flow control pneumatic valve - CLOSED CLOSED:: jumper/regulator.

o 1RH618 (357' +10' S16 1A RH HX Room) o 1RH619 (357' +10' V16 1B RH HX Room)

l. Separate RH trains:

Locally close RH discharge Open the breaker and header crosstie valve using separate RH trains by 1BwOA ELEC-5, LOCAL EMERGENCY locally closing using CONTROL OF SAFE SHUTDOWN the handwheel:

EQUIPMENT, for train NOT being recirced: o 1RH8716A (364' +11' S14 CWA) o MCC 131X1 F3 (1RH8716A) o 1RH8716B o MCC 132X4 A4 (1RH8716B) (364' +11' U14 CWA)

Page 40 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 35 LOCALLY PLACE RH SYSTEM IN OPERATION FOR SAMPLING SAMPLING: :

a. Start the selected RH pump a. Continue cooldown on SG using 1BwOA ELEC-5, LOCAL PORVs, EMERGENCY CONTROL OF SAFE RETURN TO Step 33 SHUTDOWN EQUIPMENT (Page 37).

b. Shift Manager determines recirc flowpath:

o Miniflow:

Maintain RH flow - GREATER THAN 500 GPM GPM:

o F0601 RHR Pump 1A Minflow o F0602 RHR Pump 1B Minflow

-OR-o Back to RWST:

a) Obtain key for 1RH8735 b) Unlock and open 1RH8735 (364' +11' S13) c) Adjust RH bypass flow control valve to obtain -

3300 GPM GPM::

o 1RH618:

F0626 RHX 1 Coolant Disch F o 1RH619:

F0627 RHX 2 Coolant Disch F

c. Contact Chemistry for boron samples:

RCS Operating RH train

d. Locally stop running RH pump per 1BwOA ELEC-5, LOCAL EMERGENCY CONTROL OF SAFE SHUTDOWN EQUIPMENT Page 41 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 36 ALIGN CC SYSTEM FOR SHUTDOWN COOLING COOLING::

a. Align CC for shutdown cooling per BwOP CC-8, ISOLATION OF CC BETWEEN UNITS 1 AND 2

b. Locally open RH HX CC return b. Open the breaker and valve for selected RH train per locally open the valve 1BwOA ELEC-5, LOCAL EMERGENCY using the handwheel:

CONTROL OF SAFE SHUTDOWN EQUIPMENT: o 1CC9412A (364' +10' S17) o 1CC9412B (364' +12' V18) o 1MCC 131X1 K3 (1CC9412A) o 1MCC 132X1 D4 (1CC9412B)

Page 42 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 37 ALIGN SELECTED RH TRAIN FOR SHUTDOWN COOLING COOLING:

a. Refer to BwOP RH-6, PLACING THE RH SYSTEM IN SHUTDOWN COOLING, for applicable actions

b. Check RCS pressure - LESS THAN b. Depressurize RCS to 360 PSIG PSIG:

less than 360 PSIG PSIG..

o Computer points:

o P0498 RCL System WR LP 3 P o P0499 RCL System WR LP 1 P o Local gauge pressure:

o 1PI-402 (at Panel 1PL66J)

(377' R1) o 1PI-404 (at Panel 1PL54J)

(377' R11)

c. Close RH pump suction from RWST:

1) Energize SVAG VALVE MCC per 1BwOA ELEC-5, LOCAL EMERGENCY CONTROL OF SAFE SHUTDOWN EQUIPMENT

2) Locally close RH pump suction 2) Open the breaker and from RWST valve using 1BwOA locally close the valve ELEC-5, LOCAL EMERGENCY using the handwheel:

CONTROL OF SAFE SHUTDOWN EQUIPMENT: o 1SI8812A (1A CS Pump Rm) o MCC 131X1A Q1 (1SI8812A) o 1SI8812B (1B RH Pump o MCC 132X4A M2 (1SI8812B) Rm)

Step continued on next page Page 43 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED Step 37 (continued)

d. Locally open RCS hot leg to RH d. Open the breaker and pump suction valves using 1BwOA locally open the valves ELEC-5, LOCAL EMERGENCY CONTROL using the handwheels:

OF SAFE SHUTDOWN EQUIPMENT:

o RH Pump 1A: o RH Pump 1A:

MCC 131X2 B1 (1RH8701A) 1RH8701A MCC 132X2 B3 (1RH8701B) (377' R7 OMB P-68) 1RH8701B (377' R11 IMB near "D" loop against Rx cavity wall) o RH Pump 1B: o RH Pump 1B:

MCC 131X2 B4 (1RH8702A) 1RH8702A MCC 132X2 B1 (1RH8702B) (377' R4 OMB P-75) 1RH8702B (377' R3 IMB near "C" loop against Rx cavity wall)

e. Locally verify RH pump miniflow e. Locally open the valve valve - OPEN OPEN:: using 1BwOA ELEC-5, LOCAL EMERGENCY CONTROL OF SAFE o 1RH610 (357' S16 in NW corner SHUTDOWN EQUIPMENT:

of 1A RH HX Room) o 1RH611 (357' V16 in NW corner o MCC 131X1 F2 (1RH610) of 1B RH HX Room) o MCC 132X1 C4 (1RH611)

f. Locally verify RH HX flow f. Close the valve using control valve - CLOSED CLOSED:: pneumatic jumper/regulator.

o 1RH606 (357' +10' S16 1A RH HX Room) o 1RH607 (357' +10' V16 1B RH HX Room)

g. Locally verify RH HX bypass g. Close the valve using flow control valve - CLOSED CLOSED:: pneumatic jumper/regulator.

o 1RH618 (357' +10' S16 1A RH HX Room) o 1RH619 (357' +10' V16 1B RH HX Room)

Page 44 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 38 PLACE SELECTED RH TRAIN IN OPERATION FOR COOLDOWN COOLDOWN:

a. Locally start RH pump using a. Continue cooldown using 1BwOA ELEC-5, LOCAL EMERGENCY SG PORVs, CONTROL OF SAFE SHUTDOWN RETURN TO Step 33 EQUIPMENT (Page 37).

b. Locally establish cooldown:

Throttle RH HX bypass flow control valve using temporary regulator to maintain RH flow - GREATER THAN 3300 GPM GPM:

o 1RH618:

F0626 RHX 1 Coolant Disch F o 1RH619:

F0627 RHX 2 Coolant Disch F Throttle RH HX flow control valve using temporary regulator to maintain RCS cooldown rate - LESS THAN 50 50F IN ANY 1 HR PERIOD PERIOD:

o 1RH606 o 1RH607 Page 45 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 39 ESTABLISH RH LETDOWN AT DISCRETION OF SHIFT MANAGER MANAGER:

a. Refer to BwOP CV-17, ESTABLISHING AND SECURING NORMAL AND RH LETDOWN FLOW, for applicable actions

b. Check letdown isolation b. Manually open the valves - OPEN OPEN:

valve(s).

1CV459 1CV460

c. Check letdown orifice isolation c. Manually open the valves - OPEN OPEN:

valve(s).

1CV8149A 1CV8149B 1CV8149C

d. Obtain key from RSP and locally open RH HX outlet to CV letdown HX isolation valve for selected train:

o 1RH8734A (364' S14 CWA 25' West of door) o 1RH8734B (364' V14 CWA 6' East of door)

e. Locally open RH to CV letdown valve using a pneumatic jumper:

1CV128 (383' U15 1B letdown HX valve room)

Step continued on next page Page 46 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED Step 39 (continued)

f. Locally adjust letdown to maintain PZR level:

1) Monitor charging and letdown flow on computer points:

o F0134 Letdown Hx Letdown Outlet F o F0128 Charg Pmp Disch Hdr F

2) Adjust 1CV131 manual bypass as necessary when establishing letdown:

1CV8409 (364' +29' S13 CWA)

3) Locally isolate 1CV131 by closing its manual isolation valves:

o 1CV8408A (364' +29' S13 CWA) o 1CV8408B (364' +29' S13 CWA)

g. Locally close letdown line containment isolation valve:

Fail air to 1CV8152 (364'

+27' X13 CWA P-41) 40 PROCEED TO COLD SHUTDOWN CONDITION PER PER::

1BwGP 100-5, PLANT SHUTDOWN AND COOLDOWN

-END-Page 47 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 RCS Pressure (PSIG) 2600 2400 2200 ACCEPTABLE 2000 1800 1600 1400 1200 NOT 1000 ACCEPTABLE 800 Containment 600 Conditions:

400 Normal---

---Saturation 200 0

200 250 300 350 400 450 500 550 600 650 700 RCS Temperature (°F)

FIGURE 1BwOA PRI-5-1 RCS SUBCOOLING MARGIN Page 48 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT A (PG 1 OF 4)

REMOTE SHUTDOWN PANEL LINEUP

>>¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥ CAUTION Switching control to LOCAL may result in unwanted OR unexpected equipment operation if RSP control switch positions do NOT match current equipment conditions.

¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥º 1 PLACE B TRAIN VC LOCAL/REMOTE SWITCHES IN LOCAL LOCAL:

a. Dispatch an NSO with the key to 1PL05JA (364' M23) to place the following switches in - LOCAL LOCAL:

EPN EQUIPMENT 0VC01CB MCR SUPPLY FAN 0B

- 0VC02CB 0VC02CB MCR RETURN FAN 0B 0VC02Y, 3Y, 4Y MCR EXH, RETURN OUTSIDE AIR DAMPERS

- 0VC05Y, 0VC05Y, 6Y, 44Y RECIRC CHAR ABSORB INLT, OUTLT, BYP DAMPERS

- Check control switch position matches current component position prior to placing Local/Remote switch in the Local position.

Page 49 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT A (PG 2 OF 4)

REMOTE SHUTDOWN PANEL LINEUP 2 PLACE REMOTE/LOCAL SWITCHES IN LOCAL AT 1PL04J 1PL04J:

EPN EQUIPMENT 0VC01CA MCR SUPPLY FAN 0A

- 0VC02CA 0VC02CA MCR RETURN FAN 0A 0VC18Y, 19Y, 20Y MCR EXH, RETURN, OUTSIDE AIR DAMPERS

- 0VC21Y, 0VC21Y, 22Y, 43Y RECIRC CHAR ABSORB INLT, OUTLT, BYP DAMPERS

- 1MS001A 1MS001A & 1MS001D MSIV 1A & 1D CONTROL

- 1AF005A 1AF005A SG 1A FLOW CONT VLV 1AF013A SG 1A ISOL VLV 1AF01PA AF PUMP 1A

- 1AF005B 1AF005B SG 1B FLOW CONT VLV 1AF013B SG 1B ISOL VLV 1CV01PA CENT CHG PUMP 1A

- 1AF005C 1AF005C SG 1C FLOW CONT VLV 1AF013C SG 1C ISOL VLV 1VP01CA RCFC 1A HIGH SPEED

- 1AF005D 1AF005D SG 1D FLOW CONT VLV 1AF013D SG 1D ISOL VLV 1VP01CC RCFC 1C HIGH SPEED

- 1MS018A 1MS018A SG 1A PORV 1CC01PA CC PUMP 1A

- 1MS018D 1MS018D SG 1D PORV 0CC01P CC PUMP 0 1SX01PA SX PUMP 1A

- Check control switch position matches current component position prior to placing Local/Remote switch in the Local position.

Page 50 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT A (PG 3 OF 4)

REMOTE SHUTDOWN PANEL LINEUP 3 PLACE REMOTE/LOCAL SWITCHES IN LOCAL AT 1PL05J 1PL05J::

EPN EQUIPMENT

- 1MS001B 1MS001B & 1MS001C MSIV 1B & 1C CONTROL

- 1AF005E 1AF005E SG 1A FLOW CONT VLV 1AF013E SG 1A ISOL VLV 1AF01PB AF PUMP 1B

- 1AF005F 1AF005F SG 1B FLOW CONT VLV 1AF013F SG 1B ISOL VLV 1CV01PB CENT CHG PUMP 1B

- 1AF005G 1AF005G SG 1C FLOW CONT VLV 1AF013G SG 1C ISOL VLV 1VP01CB RCFC 1B HIGH SPEED

- 1AF005H 1AF005H SG 1D FLOW CONT VLV 1AF013H SG 1D ISOL VLV 1VP01CD RCFC 1D HIGH SPEED

- 1MS018B 1MS018B SG 1B PORV 1CC01PB CC PUMP 1B

- 1MS018C 1MS018C SG 1C PORV 0CC01P CC PUMP 0 1SX01PB SX PUMP 1B 1CV8104 EMER BORATION VALVE

- Check control switch position matches current component position prior to placing Local/Remote switch in the Local position.

Page 51 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT A (PG 4 OF 4)

REMOTE SHUTDOWN PANEL LINEUP 4 PLACE REMOTE/LOCAL SWITCHES IN LOCAL AT 1PL06J 1PL06J::

EPN EQUIPMENT

- 1VP03CA 1VP03CA CRDM EXHAUST FAN 1A

- 1VP03CB 1VP03CB CRDM EXHAUST FAN 1B

- 1VP03CC 1VP03CC CRDM EXHAUST FAN 1C

- 1VP03CD 1VP03CD CRDM EXHAUST FAN 1D

- 1CV8149A 1CV8149A 45 GPM LETDOWN ORIFICE

- 1CV460 1CV460 LETDOWN LINE ISOL 0PW02PA PW MAKEUP PUMP 0A

- 1CV8149B 1CV8149B 75 GPM LETDOWN ORIFICE

- 1CV459 1CV459 LETDOWN LINE ISOL

- 1AB03P 1AB03P AB XFER PUMP 1

- 1CV8149C 1CV8149C 75 GPM LETDOWN ORIFICE PZR B/U HEATER GRP A CONTACTOR PZR B/U HEATER GRP A BREAKER

- 1CV8145 1CV8145 PZR AUX SPRAY VALVE PZR B/U HEATER GRP B CONTACTOR PZR B/U HEATER GRP B BREAKER

- Check control switch position matches current component position prior to placing Local/Remote switch in the Local position.

NOTE *

When in "LOCAL" the charging flow *

controller provides a direct air *

signal to the 1CV121 valve *

controller.

5 CONTROL CHARGING FLOW FLOW:

a. Place charging flow control in - LOCAL LOCAL:

1FHC-121 6 RETURN TO MAIN BODY, Step 8c (Page 6)

-END-Page 52 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT B (PG 1 OF 4)

LOCAL OPERATOR ACTIONS

NOTE *

Vital area keys will be available at *

the Remote Shutdown Panel for entry *

through doors with disabled card *

readers.

1 LOCALLY DEENERGIZE REACTOR HEAD VENT VALVES VALVES:

Open circuit breaker 9 on DC Bus 113, Cub ER1:

1RC014A 1RC014C Open circuit breaker 10 on DC Bus 114, Cub ER1:

1RC014B 1RC014D 2 LOCALLY VERIFY BOTH RX TRIP Open the breakers.

BREAKERS OPEN 3 LOCALLY VERIFY ALL TURBINE VALVES CLOSED CLOSED::

Governor valves Throttle valves Reheat stop valves Intercept valves 4 VERIFY PUMPS TRIPPED TRIPPED:: Locally open breaker(s).

HD Pump 1B (Bus 156 Cub 3)

FW Pump 1A (Bus 156 Cub 4)

HD Pump 1A (Bus 157 Cub 3)

HD Pump 1C (Bus 157 Cub 5)

Startup FW Pump (Bus 159 Cub 4)

Page 53 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT B (PG 2 OF 4)

LOCAL OPERATOR ACTIONS 5 VERIFY MAIN GENERATOR TRIPPED TRIPPED:

a. Locally check PMG output a. Open the breaker.

breaker - OPEN OPEN:

41 breaker (426' J4 at 1MP09E) 6 VERIFY POWER TO 4KV ESF BUSES BUSES:

Locally restore at least ONE 4KV ESF bus per:

ESF buses - BOTH ENERGIZED ENERGIZED:

1BwOA ELEC-3, LOSS OF 4KV Bus 141 ESF BUS:

Bus 142 o ATTACHMENT B (1A DG) o ATTACHMENT D (1B DG)

Page 54 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT B (PG 3 OF 4)

LOCAL OPERATOR ACTIONS

NOTE *

Bus status report should include *

breaker positions, control power *

status, and any dropped relays.

7 DETERMINE STATUS OF BUS 141 EQUIPMENT EQUIPMENT::

a. Disable auto start of CS pump 1A:

1) Pull control power fuses:

Bus 141 Cub 9 (CS pump 1A)

2) Check CS pump breaker - OPEN OPEN:

2) Open breakers with a reach rod.

Bus 141 Cub 9 (CS pump 1A)

b. Report status of SI pump breakers and CS pump breakers to RSP:

Bus 141 Cub 3 (SI Pump 1A)

Bus 141 Cub 9 (CS pump 1A)

c. Report status of Train A 4KV busses and breakers to RSP:

Bus 141 Bus 143 Page 55 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT B (PG 4 OF 4)

LOCAL OPERATOR ACTIONS 8 DETERMINE STATUS OF BUS 142 EQUIPMENT EQUIPMENT::

a. Disable auto start of CS pump 1B:

1) Pull control power fuses:

Bus 142 Cub 8 (CS pump 1B)

2) Check CS pump breaker - OPEN OPEN:

2) Open breakers with a reach rod.

Bus 142 Cub 8 (CS pump 1B)

b. Report status of SI pump breakers and CS pump breakers to RSP:

Bus 142 Cub 3 (SI Pump 1B)

Bus 142 Cub 8 (CS pump 1B)

c. Report status of Train B 4KV busses and breakers to RSP:

Bus 142 Bus 144 9 VERIFY FW PUMPS TRIPPED TRIPPED:: Locally trip pump(s).

FW Pump 1B FW Pump 1C 10 LOCALLY VERIFY CLOSED ANY FW VALVES NOT PREVIOUSLY VERIFIED CLOSED FROM THE MCR 11 REPORT STATUS OF DIESEL GENERATORS TO RSP RSP:

1A DG 1B DG

-END-Page 56 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT C (PG 1 OF 1)

INSTALLATION OF RH SYSTEM PNEUMATIC JUMPERS 1 INSTALLATION OF PNEUMATIC JUMPERS JUMPERS::

a. Obtain the selected pneumatic jumper and regulator from the RSP cabinet.

b. Back regulator out to zero.

c. Isolate the instrument air supply to the installed regulator and I/P converter.

d. Connect temporary pneumatic jumper and regulator as shown in the drawing below.

e. Unisolate instrument air supply and throttle valves as directed

-END-Page 57 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT D (PG 1 OF 3)

RESTORING OPERATIONS FROM MAIN CONTROL ROOM 1 VERIFY MCR HABITABLE HABITABLE:

RETURN TO procedure and step in effect.

Contact brigade leader to verify - INITIATING CONDITION HAS CLEARED Contact Rad Protection to verify - SAMPLES INDICATE MCR ATMOSPHERE SAFE FOR HABITATION 2 ESTABLISH NORMAL MCR MANNING MANNING:

a. Phone security shift supervisor at X-2829 to perform the following:

1) Enable card readers into MCR:

Door 505 Door 507 Door 511 Door 512

2) Establish Main Security Control Room manning

b. Establish normal MCR manning using additional operators while maintaining current remote control station manning 3 ESTABLISH COMMUNICATIONS BETWEEN MCR AND RSP 4 EVALUATE MCR DAMAGE AND LOST CONTROLS CONTROLS::

a. Determine capability of MCR for plant control

b. Check MCR indications and b. IF ANY controls are controls - ALL AVAILABLE damaged, THEN maintain remote operation of that control.

Page 58 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT D (PG 2 OF 3)

RESTORING OPERATIONS FROM MAIN CONTROL ROOM 5 TRANSFER CONTROL TO MCRMCR::

a. Review logs for all local actions taken

b. Restore indications to MCR by placing Fire Hazards Panel switches to - NORMAL

c. Transfer controls listed in ATTACHMENT A (Page 49) back to MCR - ONE AT A TIME TIME::

1) Verify MCR switch position -

MATCHES RSP SWITCH POSITION

2) Place LOCAL/REMOTE switch at RSP in - REMOTE

d. Place charging flow controller in - REMOTE REMOTE::

1FHC-121 6 CHECK JUMPER STATUS STATUS:

a. All jumpers - REMOVED a. Initiate Temp Configuration Change paperwork for jumpers remaining installed.

7 LOCALLY REENERGIZE REACTOR HEAD VENT VALVES VALVES:

Close circuit breaker 9 on DC Bus 113, Cub ER1:

1RC014A 1RC014C Close circuit breaker 10 on DC Bus 114, Cub ER1:

1RC014B 1RC014D Page 59 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT D (PG 3 OF 3)

RESTORING OPERATIONS FROM MAIN CONTROL ROOM 8 VERIFY APPLICABLE STEPS OF BwGPs COMPLETED COMPLETED::

o 1BwGP 100-4, POWER DESCENSION o 1BwGP 100-5, PLANT SHUTDOWN AND COOLDOWN

-END-Page 60 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT E (PG 1 OF 17)

ESF MANUAL BLOCK OR RESET

NOTE *

Some jumpers will be left installed, *

while other jumpers are only *

momentarily installed. Temporary *

Configuration Change paperwork *

should be initiated for any jumpers *

left installed.

1 DETERMINE IF AEER ACCESSIBLE ACCESSIBLE:

a. Obtain status report:

o Fire Brigade Leader o Rad Protection

b. AEER determined to be - b. Contact the Shift Manager ACCESSIBLE for recovery options.

RETURN TO procedure and step effect.

2 OBTAIN NECESSARY EQUIPMENT EQUIPMENT::

Obtain keys to ESF cabinets:

1PA09J Train A 1PA10J Train B 1PA27J Train A 1PA28J Train B Obtain jumpers from cabinet at Remote Shutdown Panel or MCR:

Determine from functions in Step 3 (Next Page) the number of jumpers required Obtain necessary safety equipment:

o SCBAs o Lights o Turnout Gear Page 61 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT E (PG 2 OF 17)

ESF MANUAL BLOCK OR RESET 3 PERFORM BLOCK/RESET FUNCTION(S)

FUNCTION(S):

o To reset SI, GO TO Step 4 (Page 64) o To block PZR LOW PRESSURE SI, GO TO Step 5 (Page 65) o To block STEAMLINE LOW PRESS SI, GO TO Step 6 (Page 66) o To reset CONTAINMENT ISOLATION PHASE A, GO TO Step 7 (Page 67) o To reset CONTAINMENT ISOLATION PHASE B, GO TO Step 8 (Page 68) o To reset CONTAINMENT SPRAY actuation, GO TO Step 9 (Page 69) o To reset CONTAINMENT VENT ISOLATION, GO TO Step 10 (Page 70) o To reset NUCLEAR AT POWER PERMISSIVE P10, GO TO Step 11 (Page 71) o To reset SOURCE RANGE PERMISSIVE P6, GO TO Step 12 (Page 72)

Step continued on next page Page 62 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT E (PG 3 OF 17)

ESF MANUAL BLOCK OR RESET Step 3 (continued) o To place COLD OVERPRESSURE PROTECTION in service, GO TO Step 13 (Page 73) o To reset SI RECIRC SUMPS, GO TO Step 14 (Page 74) o To reset CV MINIFLOW ISOLATIONS, GO TO Step 15 (Page 75)

Page 63 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT E (PG 4 OF 17)

ESF MANUAL BLOCK OR RESET 4 RESET SI SI::

a. Verify Reactor Trip Breakers -

OPEN (P4 actuated)

b. Install jumpers across terminal points listed below for Trains A and/or B:

Install TWO jumpers per train to - RESET RESET::

>>¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥ TRAIN A Rear of Logic Cabinet - 1PA09J Terminal Board TB505 points 7 and 8 (Resets SI Signal, blocks Auto SI)

Rear of Output Cabinet - 1PA09J Terminal Board TB644 points 9 and 10 (Unlatches slave relays)

¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥ TRAIN B Rear of Logic Cabinet - 1PA10J Terminal Board TB505 points 7 and 8 (Resets SI Signal, blocks Auto SI)

Rear of Output Cabinet - 1PA10J Terminal Board TB644 points 9 and 10 (Unlatches slave relays)

¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥º

c. Check relays on affected c. Perform the following:

train(s) - DEENERGIZED DEENERGIZED:

1) Remove jumper from K602 TB644.

K603 K604 2) Contact Maintenance to K608 manually reset any K609 energized relays per K610 Step 16 (Page 76).

K611 K630 3) Remove jumper from TB505.

4) GO TO Step 4e.

d. Remove jumpers

e. Check if other ESF manual e. RETURN TO procedure and blocks or resets - REQUIRED step in effect.

f. RETURN TO Step 3 (Page 62)

Page 64 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT E (PG 5 OF 17)

ESF MANUAL BLOCK OR RESET 5 BLOCK PZR LOW PRESSURE SI SI:

a. Verify RCS pressure - LESS THAN 1930 PSIG

b. Install jumper(s) across terminal points listed below for Trains A and/or B:

Install ONE jumper per train to - BLOCK BLOCK::

>>¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥ TRAIN A Rear of Logic Cabinet - 1PA09J Terminal Board TB509 points 1 and 2

¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥ TRAIN B Rear of Logic Cabinet - 1PA10J Terminal Board TB509 points 1 and 2

¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥º

c. Check K628 relay(s) - ENERGIZED ENERGIZED:

c. Notify Maintenance to jumper slave relay K628-6 o Train A (1PA09J) to cabinet ground.

o Train B (1PA10J)

d. Leave jumper(s) - INSTALLED

e. Check if other ESF manual e. RETURN TO procedure and blocks or resets - REQUIRED step in effect.

f. RETURN TO Step 3 (Page 62)

Page 65 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT E (PG 6 OF 17)

ESF MANUAL BLOCK OR RESET 6 BLOCK STEAMLINE LOW PRESSURE SI SI:

a. Verify RCS pressure - LESS THAN 1930 PSIG

b. Install jumper(s) across terminal points listed below for Trains A and/or B:

Install ONE jumper per train to - BLOCK BLOCK::

>>¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥ TRAIN A Rear of Logic Cabinet - 1PA09J Terminal Board TB509 points 7 and 8

¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥ TRAIN B Rear of Logic Cabinet - 1PA10J Terminal Board TB509 points 7 and 8

¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥º

c. Check K628 relay(s) - ENERGIZED ENERGIZED:

c. Notify Maintenance to jumper slave relay K628-6 o Train A (1PA09J) to cabinet ground.

o Train B (1PA10J)

d. Leave jumper(s) - INSTALLED

e. Check if other ESF manual e. RETURN TO procedure and blocks or resets - REQUIRED step in effect.

f. RETURN TO Step 3 (Page 62)

Page 66 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT E (PG 7 OF 17)

ESF MANUAL BLOCK OR RESET 7 RESET CONTAINMENT ISOLATION PHASE A A::

a. Install jumpers across terminal points listed below for Trains A and/or B:

Install TWO jumpers per train to - RESET RESET::

>>¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥ TRAIN A Rear of Logic Cabinet - 1PA09J Terminal Board TB504 points 7 and 8 (Resets Cnmt Phase A signal)

Rear of Output Cabinet - 1PA09J Terminal Board TB644 points 3 and 4 (Unlatches slave relay)

¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥ TRAIN B Rear of Logic Cabinet - 1PA10J Terminal Board TB504 points 7 and 8 (Resets Cnmt Phase A signal)

Rear of Output Cabinet - 1PA10J Terminal Board TB644 points 3 and 4 (Unlatches slave relay)

¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥º

b. Check relays on affected b. Perform the following:

train(s) - DEENERGIZED :

DEENERGIZED:

1) Remove jumper from K605 TB644.

K606 K607 2) Contact Maintenance to K612 manually reset any K613 energized relays per K614 Step 16 (Page 76).

3) Remove jumper from TB504.

4) GO TO Step 7d.

c. Remove jumpers

d. Check if other ESF manual d. RETURN TO procedure and blocks or resets - REQUIRED step in effect.

e. RETURN TO Step 3 (Page 62)

Page 67 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT E (PG 8 OF 17)

ESF MANUAL BLOCK OR RESET 8 RESET CONTAINMENT ISOLATION PHASE B B::

a. Install jumpers across terminal points listed below for Trains A and/or B:

Install TWO jumpers per train to - RESET RESET::

>>¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥ TRAIN A Rear of Logic Cabinet - 1PA09J Terminal Board TB505 points 1 and 2 (Resets Cnmt Phase B signal)

Rear of Output Cabinet - 1PA09J Terminal Board TB644 points 7 and 8 (Unlatches slave relay)

¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥ TRAIN B Rear of Logic Cabinet - 1PA10J Terminal Board TB505 points 1 and 2 (Resets Cnmt Phase B signal)

Rear of Output Cabinet - 1PA10J Terminal Board TB644 points 7 and 8 (Unlatches slave relay)

¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥º

b. Check relays on affected b. Perform the following:

train(s) - DEENERGIZED :

DEENERGIZED:

1) Remove jumper from K618 TB644.

K626

2) Contact Maintenance to manually reset any energized relays per Step 16 (Page 76).

3) Remove jumper from TB505.

4) GO TO Step 8d.

c. Remove jumpers

d. Check if other ESF manual d. RETURN TO procedure and blocks or resets - REQUIRED step in effect.

e. RETURN TO Step 3 (Page 62)

Page 68 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT E (PG 9 OF 17)

ESF MANUAL BLOCK OR RESET 9 RESET CONTAINMENT SPRAY ACTUATION ACTUATION::

a. Install jumpers across terminal points listed below for Trains A and/or B:

Install TWO jumpers per train to - RESET RESET:

>>¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥ TRAIN A Rear of Logic Cabinet - 1PA09J Terminal Board TB504 points 4 and 5 (Resets Cnmt spray signal)

Rear of Output Cabinet - 1PA09J Terminal Board TB644 points 1 and 2 (Unlatches slave relay)

¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥ TRAIN B Rear of Logic Cabinet - 1PA10J Terminal Board TB504 points 4 and 5 (Resets Cnmt spray signal)

Rear of Output Cabinet - 1PA10J Terminal Board TB644 points 1 and 2 (Unlatches slave relay)

¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥º

b. Check relays on affected b. Perform the following:

train(s) - DEENERGIZED :

DEENERGIZED:

1) Remove jumper from K643 TB644.

K644

2) Contact Maintenance to manually reset any energized relays per Step 16 (Page 76).

3) Remove jumper from TB504.

4) GO TO Step 9d.

c. Remove jumpers

d. Check if other ESF manual d. RETURN TO procedure and blocks or resets - REQUIRED step in effect.

e. RETURN TO Step 3 (Page 62)

Page 69 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT E (PG 10 OF 17)

ESF MANUAL BLOCK OR RESET 10 RESET CONTAINMENT VENT ISOLATION ISOLATION::

a. Install jumpers across terminal points listed below for Trains A and/or B:

Install TWO jumpers per train to - RESET RESET:

>>¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥ TRAIN A Rear of Logic Cabinet - 1PA09J Terminal Board TB504 points 10 and 11 (Resets Cnmt Vent signal)

Rear of Output Cabinet - 1PA09J Terminal Board TB644 points 5 and 6 (Unlatches slave relay)

¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥ TRAIN B Rear of Logic Cabinet - 1PA10J Terminal Board TB504 points 10 and 11 (Resets Cnmt Vent signal)

Rear of Output Cabinet - 1PA10J Terminal Board TB644 points 5 and 6 (Unlatches slave relay)

¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥º

b. Check relays on affected b. Perform the following:

train(s) - DEENERGIZED :

DEENERGIZED:

1) Remove jumper from K615 TB644.

K622

2) Contact Maintenance to manually reset any energized relays per Step 16 (Page 76).

3) Remove jumper from TB504.

4) GO TO Step 10d.

c. Remove jumpers

d. Check if other ESF manual d. RETURN TO procedure and blocks or resets - REQUIRED step in effect.

e. RETURN TO Step 3 (Page 62)

Page 70 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT E (PG 11 OF 17)

ESF MANUAL BLOCK OR RESET 11 RESET NUCLEAR AT POWER PERMISSIVE P10 P10:

a. Install jumpers across terminal points listed below for Trains A and/or B:

Install SIX jumpers per train to - RESET RESET::

>>¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥ TRAIN A Front of Input Bay - 1PA09J Terminal Board TB101 point 5 to TB111 point 3 Terminal Board TB101 point 6 to TB111 point 9 Terminal Board TB201 point 5 to TB211 point 3 Terminal Board TB201 point 6 to TB211 point 9 Terminal Board TB301 point 3 to TB311 point 3 Terminal Board TB301 point 4 to TB311 point 9 (Simulates three PR channels less than 10%)

¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥ TRAIN B Front of Input Bay - 1PA10J Terminal Board TB101 point 5 to TB111 point 3 Terminal Board TB101 point 6 to TB111 point 9 Terminal Board TB201 point 5 to TB211 point 3 Terminal Board TB201 point 6 to TB211 point 9 Terminal Board TB301 point 3 to TB311 point 3 Terminal Board TB301 point 4 to TB311 point 9 (Simulates three PR channels less than 10%)

¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥º

b. Check K629 relay(s) - b. Notify Maintenance to lift DEENERGIZED DEENERGIZED:: and tape slave relay K629-6.

o Train A (1PA09J) o Train B (1PA10J)

c. Leave jumpers - INSTALLED

d. Check if other ESF manual d. RETURN TO procedure and blocks or resets - REQUIRED step in effect.

e. RETURN TO Step 3 (Page 62)

Page 71 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT E (PG 12 OF 17)

ESF MANUAL BLOCK OR RESET 12 RESET SOURCE RANGE PERMISSIVE P6 P6::

a. Check P10 - RESET RESET:

a. Reset P10 per Step 11 (Previous Page).

Check relay K629 -

DEENERGIZED

b. Lift TWO leads per train to -

RESET RESET::

>>¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥ TRAIN A Front of Input Bay - 1PA09J Terminal Board TB101 point 1 Terminal Board TB201 point 1 (Simulates N35 less than 5x10-11 AMPS)

¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥ TRAIN B Front of Input Bay - 1PA10J Terminal Board TB101 point 1 Terminal Board TB201 point 1 (Simulates N36 less than 5x10-11 AMPS)

¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥º

c. Re-land leads

d. Check if other ESF manual d. RETURN TO procedure and blocks or resets - REQUIRED step in effect.

e. RETURN TO Step 3 (Page 62)

Page 72 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT E (PG 13 OF 17)

ESF MANUAL BLOCK OR RESET 13 PLACE COLD OVERPRESSURE PROTECTION IN SERVICE SERVICE:

a. Install jumper(s) across terminal points listed below for Trains A and/or B:

Install ONE jumper per train to - PLACE IN SERVICE SERVICE::

>>¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥ TRAIN A Rear of Cabinet - 1PA27J Terminal Board TB917 point 11 to Terminal Board TB916 point 11

¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥ TRAIN B Rear of Cabinet - 1PA28J Terminal Board TB917 point 11 to Terminal Board TB916 point 11

¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥º

b. Leave jumper(s) - INSTALLED

c. Check if other ESF manual c. RETURN TO procedure and blocks or resets - REQUIRED step in effect.

d. RETURN TO Step 3 (Page 62)

Page 73 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT E (PG 14 OF 17)

ESF MANUAL BLOCK OR RESET 14 RESET SI RECIRC SUMPS ISOLATION VALVES VALVES::

a. Check SI signal - RESET RESET:

a. Reset SI per Step 4 (Page 64).

K602 relay - UNLATCHED

b. Install jumper(s) across terminal points listed below for Trains A and/or B:

Install ONE jumper per train to - RESET RESET::

>>¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥ TRAIN A Rear of Output Cabinet - 1PA09J Terminal Board TB656 points 11 and 12 (1SI8811A will not Auto Open)

(1CV8110 will not Auto Close)

(Allows breaker 1411 closure)

¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥ TRAIN B Rear of Output Cabinet - 1PA10J Terminal Board TB656 points 11 and 12 (1SI8811B will not Auto Open)

(1CV8111 will not Auto Close)

(Allows breaker 1421 closure)

¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥º

c. Check K647 relay(s) - c. Perform the following:

DEENERGIZED DEENERGIZED::

1) Remove jumper from o Train A (1PA09J) TB656.

o Train B (1PA10J)

2) Contact Maintenance to manually reset any energized relays per Step 16 (Page 76).

3) GO TO Step 14e.

d. Remove jumper(s)

e. Check if other ESF manual e. RETURN TO procedure and blocks or resets - REQUIRED step in effect.

f. RETURN TO Step 3 (Page 62)

Page 74 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT E (PG 15 OF 17)

ESF MANUAL BLOCK OR RESET 15 RESET CV MINIFLOW ISOLATION VALVES VALVES::

a. Check SI signal- RESET: a. Reset SI per Step 4 (Page 64).

K602 relay - UNLATCHED

b. Install ONE jumper per train to - RESET RESET:

>>¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥ TRAIN A Rear of Output Cabinet - 1PA09J Terminal Board TB645 points 7 and 8 (1CV8114 will not Auto Close)

¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥ TRAIN B Rear of Output Cabinet - 1PA10J Terminal Board TB645 points 7 and 8 (1CV8116 will not Auto Close)

¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥º

c. Check K646 relay(s) - c. Perform the following:

DEENERGIZED DEENERGIZED: :

1) Remove jumper from o Train A (1PA09J) TB645.

o Train B (1PA10J)

2) Contact Maintenance to manually reset any energized relays per Step 16 (Next Page).

3) GO TO Step 15e.

d. Remove jumper(s)

e. Check if other ESF manual e. RETURN TO procedure and blocks or resets - REQUIRED step in effect.

f. RETURN TO Step 3 (Page 62)

Page 75 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT E (PG 16 OF 17)

ESF MANUAL BLOCK OR RESET

>>¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥ CAUTION An insulated screwdriver and low voltage gloves are required to perform this step.

¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥º

NOTE *

It is acceptable to remove daisy *

chained wires in this step.

16 PERFORM THE FOLLOWING TO MANUALLY RESET SSPS SLAVE RELAYS RELAYS::

o Reset a Westinghouse AR style (box shaped) relay as follows:

1) Tag/Remove wires from two terminals (one will be energized) on latch (topmost) assembly

2) Remove two screws that fasten latch assembly to relay

3) Separate latch assembly from relay

4) Manually reset latch finger to recessed position

5) Reinstall latch assembly

6) Verify latch indicator button is 'Out' (not latched)

7) Restore wiring

8) RETURN TO procedure and step in effect.

Step continued on next page Page 76 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT E (PG 17 OF 17)

ESF MANUAL BLOCK OR RESET Step 16 (continued) o Reset a Potter & Brumfield MDR (cylindrical shaped) relay as follows:

1) Locate armature screw in center of front face of relay

2) Check screwdriver slot - 2) Rotate armature screw ALIGNED WITH EMBOSSED MARKS approximately 30 DEGREES ON RELAY (relay already until armature 'snaps' deenergized) into position with slot aligned to embossed marks.

3) RETURN TO procedure and step in effect.

o Reset a Cutler-Hammer relay as follows:

1) Locate the release lever on the relay

2) Manually move the release lever towards the front of the relay

3) Verify the relay plunger moved in

4) RETURN TO procedure and step in effect.

-END-Page 77 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT F (PG 1 OF 8)

SI TERMINATION 1 CHECK FOR LOW PZR PRESSURE SI SI:

a. PZR pressure - LESS THAN a. GO TO Step 2 (Next Page).

1829 PSIG

b. PZR pressure - DROPPING b. GO TO Step 2 (Next Page).

c. Trip RCP(s) as required to stop PZR pressure drop:

o RCP 1D o RCP 1C o RCP 1B o RCP 1A

d. Check if PZR pressure - STILL d. GO TO Step 2 (Next Page).

DROPPING

e. Locally isolate PORV 1RY455A at e. Locally remove the control MCC 131X2B A5 (414' S12 CWA): power fuses at 1DC10J to fail PORV 1RY455A closed:

1) Place 1RY8000A LOCAL/REMOTE switch in - LOCAL FU-11 FU-12

2) Close 1RY8000A

f. Check if PZR pressure - STILL f. GO TO Step 2 (Next Page).

DROPPING

g. Locally isolate PORV 1RY456 at g. Locally remove the control MCC 132X2 C4 (426' S12 CWA): power fuses at 1DC11J to fail PORV 1RY456 closed:

1) Place 1RY8000B LOCAL/REMOTE switch in - LOCAL FU-46 FU-47

2) Close 1RY8000B

h. Locally restore PORV 1RY455A:

1) Place 1RY8000A LOCAL/REMOTE switch at MCC 131X2B A5 in -

LOCAL

2) Open 1RY8000A Page 78 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT F (PG 2 OF 8)

SI TERMINATION 2 OBTAIN WIDE RANGE PRESSURE PRESSURE::

a. Determine RCS wide range a. Locally align pressure pressure from process computer indicator 1PI-PS298 (HRSS points: panel 1PS25J) to EITHER of the following:

o P0491 RCS Wide Rng Ch IV o P0492 RCS Wide Rng Ch II o PZR steam sample line:

o P0493 RCS Wide Rng Ch I o P0494 RCS Wide Rng Ch III a) Open PZR sample containment isolation valves using pneumatic jumpers:

1PS9354A (377' +6' R6 OMB P-70) 1PS9354B (364' +13' V13 P-70 CWA) b) Open PZR steam inlet isolation valve:

1PS9350A (HRSS panel 1PS27J) c) Open valve 1.1 (HRSS Panel 1PS25J)

-OR-o PZR liquid sample line:

a) Open PZR sample containment isolation valves using pneumatic jumpers:

1PS9355A (377' +6' R6 OMB P-70) 1PS9355B (364' +13' V13 P-70 CWA) b) Open PZR liquid inlet isolation valve:

1PS9350B (HRSS panel 1PS27J) c) Open valve 1.2 (HRSS Panel 1PS25J)

Page 79 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT F (PG 3 OF 8)

SI TERMINATION 3 CHECK IF ECCS FLOW SHOULD BE WHEN SI termination criteria TERMINATED TERMINATED:: are met, THEN terminate SI per Steps 4 RCS subcooling - ACCEPTABLE ACCEPTABLE:

thru 17.

o ICONIC DISPLAY

-OR-o Computer point (greater than 30 30F):

X0190 Degrees of Subcooling

-OR-o FIGURE 1BwOA PRI-5-1 (Page 48) using:

RCS pressure from Step 2 (Previous Page)

RCS temperature from RCS hot leg temperature indication RCS Pressure - STABLE OR RISING PZR level - GREATER THAN 4%

4 CHECK SG LEVELS LEVELS:

a. Wide range level - GREATER THAN a. Maintain total feed flow 59% IN ANY SG greater than 500 GPM until wide range level is greater than 59% in at least ONE SG.

b. Maintain wide range level -

BETWEEN 65% AND 70%

Page 80 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT F (PG 4 OF 8)

SI TERMINATION 5 RESET ACTUATIONS ACTUATIONS::

a. Check fire not occurring in a. GO TO ATTACHMENT G either of the following: (Page 86).

o MCR o AEER

b. Check AEER - ACCESSIBLE b. GO TO ATTACHMENT G (Page 86).

c. Reset functions per ATTACHMENT E (Page 61):

SI Containment isolation Phase A CV Miniflows SI Recirc Sumps

d. Check automatic SI relay on d. GO TO ATTACHMENT G affected train(s) - UNLATCHED UNLATCHED:: (Page 86).

K602 (1PA09J/10J) 6 RESTORE INSTRUMENT AIR TO CONTAINMENT CONTAINMENT::

a. Dispatch operators to locally open Instrument Air containment isolation valves using pneumatic jumpers:

1IA065 (391' CWA P-39) 1IA066 (377' +12' R5 OMB P-39) 7 REALIGN CV SYSTEM PUMPS PUMPS:

a. Stop all but ONE CV pump and place in standby Page 81 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT F (PG 5 OF 8)

SI TERMINATION 8 ESTABLISH CV PUMP MINIFLOW MINIFLOW: :

a. Locally check CV pump a. Perform the following:

miniflow - GREATER THAN 60 GPM GPM:

o Open motor operated 1FI-CV048 (346' Q12) miniflow valves per 1BwOA ELEC-5, LOCAL EMERGENCY CONTROL OF SAFE SHUTDOWN EQUIPMENT:

o MCC 131X1 M1 (1CV8110):

1CV8110 (364' S13 CWA) o MCC 132X4 C4 (1CV8111):

1CV8111 (364' S13 CWA) o Open the solenoid valves by pulling fuses:

o Fuses 61 and 62 at 1PA27J (1CV8114) o Fuses 61 and 62 at 1PA28J (1CV8116) 9 ESTABLISH NORMAL CHARGING CHARGING::

a. Throttle 1CV121 to - 5% OPEN

b. Locally open charging line b. Open the breaker(s) and containment isolation valves locally open valve(s) per 1BwOA ELEC-5, LOCAL using the handwheel:

EMERGENCY CONTROL OF SAFE SHUTDOWN EQUIPMENT: o 1CV8105 (379' CWA P-71) o 1CV8106 (379' CWA P-71) 1CV8105 (MCC 132X4 C3) 1CV8106 (MCC 131X1 K1)

Page 82 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT F (PG 6 OF 8)

SI TERMINATION 10 ISOLATE COLD LEG INJECTION INJECTION:

a. Locally close charging pumps to a. Open the breaker and cold leg injection isolation locally close the valve(s) valves using 1BwOA ELEC-5, using the handwheel:

LOCAL EMERGENCY CONTROL OF SAFE SHUTDOWN EQUIPMENT: o 1SI8801A (395' CWA P-26) o 1SI8801B (395' CWA P-26) 1SI8801A (MCC 131X1 F4) 1SI8801B (MCC 132X5 A4) 11 CONTROL CHARGING FLOW TO MAINTAIN IF 1CV121 can NOT be PZR LEVEL LEVEL:

controlled, THEN perform the following:

Throttle 1CV121 to maintain PZR level - BETWEEN 25% and 31% a. Locally throttle open one CENT CHG pump to cold leg isolation valve to maintain PZR level:

o 1SI8801A (395' CWA P-26) o 1SI8801B (395' CWA P-26)

b. Cycle PZR heater groups A and B to maintain pressure stable.

c. GO TO Step 14 (Page 85).

12 CONTROL PZR PRESSURE :

PRESSURE:

Cycle PZR heater groups A and B to maintain pressure - STABLE Page 83 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT F (PG 7 OF 8)

SI TERMINATION 13 CHECK IF LETDOWN CAN BE ESTABLISHED ESTABLISHED::

a. PZR level - GREATER THAN 17% a. Continue with Step 14 (Next Page),

WHEN PZR level is greater than 17%

17%,

THEN do Step 13b.

b. Establish letdown: b. IF letdown can NOT be restored,

1) Open letdown isolation THEN perform the valves: following:

1CV459 1) Verify CC flow to RCP 1CV460 thermal barriers between 150 GPM and 231 GPM GPM:

2) Locally open letdown line containment isolation valves 1FIS-685A (383' U18) using pneumatic jumpers:

2) Close at least ONE 1CV8152 (364' +27' X13 CWA charging line P-41) containment isolation 1CV8160 (377' +15' R5 OMB valve using 1BwOA P-41) ELEC-5, LOCAL EMERGENCY CONTROL OF SAFE SHUTDOWN

3) Open letdown orifice EQUIPMENT:

isolation valves - NOT TO EXCEED 120 GPM GPM:

o MCC 132X4 C3 (1CV8105):

o 1CV8149A o 1CV8149B 1CV8105 (379' CWA o 1CV8149C P-71) o MCC 131X1 K1 (1CV8106):

1CV8106 (379' CWA P-71)

3) Throttle 1CV121 to control injection flow while maintaining PZR level less than 90% :

90%:

F0131 RCP 1A Seal Inj Flow F0129 RCP 1B Seal Inj Flow F0127 RCP 1C Seal Inj Flow F0125 RCP 1D Seal Inj Flow Page 84 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT F (PG 8 OF 8)

SI TERMINATION 14 DISPATCH OPERATOR TO LOCALLY STOP ECCS PUMPS PUMPS:

a. Stop ECCS pumps using 1BwOA ELEC-5, LOCAL EMERGENCY CONTROL OF SAFE SHUTDOWN EQUIPMENT:

o SI Pump 1A (Bus 141 Cub 3) o RH Pump 1A (Bus 141 Cub 4) o SI Pump 1B (Bus 142 Cub 3) o RH Pump 1B (Bus 142 Cub 4) 15 RESTORE SEAL RETURN RETURN:

a. Locally open seal water return a. Open the breaker and containment isolation valves locally open the valve(s) using 1BwOA ELEC-5, LOCAL using the handwheel:

EMERGENCY CONTROL OF SAFE SHUTDOWN EQUIPMENT: o 1CV8100 (395' CWA P-28) o 1CV8112 (395' R5 OMB MCC 131X4 A5 (1CV8100) P-28)

MCC 132X2 B4 (1CV8112) 16 CHECK IF DIESEL GENERATORS SHOULD BE STOPPED STOPPED::

a. Verify 4KV ESF buses - a. Try to restore offsite ENERGIZED BY OFFSITE POWER POWER: : power to ESF buses.

ACB 1412 - CLOSED IF offsite power can NOT ACB 1422 - CLOSED be restored, THEN notify Transmission System Operator to initiate an emergency AC restoration program.

GO TO Step 17.

b. Dispatch operators to stop any unloaded DG and place in standby per BwOP DG-12, DIESEL GENERATOR SHUTDOWN 17 RETURN TO MAIN BODY, Step 12 (Page 8)

-END-Page 85 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT G (PG 1 OF 3)

MAINTAINING HOT STANDBY WITH AN SI 1 STOP ALL BUT ONE CV PUMP PUMP:

Stop selected pump using 1BwOA ELEC-5, LOCAL EMERGENCY CONTROL OF SAFE SHUTDOWN EQUIPMENT 2 CHECK RCP STATUS STATUS::

a. RCPs - ANY RUNNING a. GO TO Step 3.

b. Stop all but one RCP 3 ESTABLISH CV PUMP MINIFLOW MINIFLOW::

a. Locally check CV pump a. Perform the following:

miniflow - GREATER THAN 60 GPM GPM:

o Open motor operated 1FI-CV048 (346' Q12) miniflow valves per 1BwOA ELEC-5, LOCAL EMERGENCY CONTROL OF SAFE SHUTDOWN EQUIPMENT:

o MCC 131X1 M1 (1CV8110):

1CV8110 (364' S13 CWA) o MCC 132X4 C4 (1CV8111):

1CV8111 (364' S13 CWA) o Open the solenoid valves by pulling fuses:

o Fuses 61 and 62 at 1PA27J (1CV8114) o Fuses 61 and 62 at 1PA28J (1CV8116)

Page 86 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT G (PG 2 OF 3)

MAINTAINING HOT STANDBY WITH AN SI 4 ISOLATE COLD LEG INJECTION INJECTION:

a. Check CC flow to RCP thermal a. Locally establish CC flow barriers - BETWEEN 150 GPM AND to RCP thermal barriers:

231 GPM GPM::

1) Open the breaker for 1FIS-685A (383' U18) 1CC685:

MCC 132X4 D4

2) SLOWLY throttle open CC from RCPs thermal barrier isolation valve:

1CC685 (395' CWA P-24)

3) Maintain CC flow from RCP thermal barriers between 150 GPM and 231 GPM GPM::

1FIS-685A (383' U18)

b. Deenergize charging pump(s) to RCS cold leg injection isolation valves:

1SI8801A (MCC 131X1 F4) 1SI8801B (MCC 132X5 A4)

c. Locally close charging pump(s) to RCS cold leg injection isolation valves using the handwheel:

1SI8801A (395' CWA P-26) 1SI8801B (395' CWA P-26)

Page 87 of 88

REV. 106 CONTROL ROOM INACCESSIBILITY 1BwOA UNIT 1 PRI-5 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT G (PG 3 OF 3)

MAINTAINING HOT STANDBY WITH AN SI 5 MAINTAIN PZR LEVEL LEVEL:

a. Locally bypass 1CV121:

1) Open charging header flow control bypass valve for running CV pump:

o 1CV8387A (364' U15 1A CV pump room) o 1CV8387B (364' Y14 1B CV pump room)

2) Close at least ONE charging header flow control valve manual isolation:

o 1CV8483A (364' +10' U13 CWA) o 1CV8483B (364' +8' U13 CWA)

b. Control charging header flow b. IF charging flow can NOT control bypass valve to be reduced with the 1CV121, maintain - STABLE STABLE:: THEN reduce charging through the RCP seals to PZR level 3 GPM PER PUMP using the RCP seal injection manual PZR pressure flow control valves:

1CV8369A (391' CWA P-33)

F0131 RCP 1 Seal Injection Wtr Flow 1CV8369D (391' CWA P-33)

F0125 RCP 4 Seal Injection Wtr Flow 1CV8369B (387' CWA P-53)

F0129 RCP 2 Seal Injection Wtr Flow 1CV8369C (387' CWA P-53)

F0127 RCP 3 Seal Injection Wtr Flow 6 RETURN TO ATTACHMENT F, Step 14 (Page 85)

-END-Page 88 of 88

REV. 106 OPERATOR ACTION

SUMMARY

1BwOA PRI-F:5 FOR 1BwOA PRI-5 IF SI ACTUATES AFTER STEP 9 9:

AF PUMP DAY TANK LEVEL <50%

<50%::

GO TO ATTACHMENT F, SI Refill the day tank TERMINATION (Page 78)

IF MCR BECOMES HABITABLE HABITABLE::

GO TO ATTACHMENT D, RESTORING OPERATIONS FROM MCR (Page 58)

USE INDICATIONS AT FIRE HAZARDS PANEL IF NOT AVAILABLE AT REMOTE SHUTDOWN PANEL PANEL:

Source Range NI Intermediate Range NI SG pressures SG wide range levels PZR pressure PZR level RCS Hot Leg temperatures RCS Cold Leg temperatures PERFORM MAIN BODY STEP 15b RNO IF IF:

o RCP seal outlet temperature rises to greater than or equal to 235 235F

-OR-o RCP lower radial bearing temperature rises to greater than or equal to 225 F 225

-OR OR-o No seal injection flow is indicated to RCPs having no seal or radial bearing temperature indication IF FLOW IS LOST/ISOLATED TO ANY SG AND NR SG LESS THAN OR EQUAL TO 45%

FOR GREATER THAN 75 MINUTES, THEN:

Feed affected SG(s) between 60 GPM and 80 GPM for 10 MINUTES prior to restoring desired feedwater flow.

(Final)

JOB PERFORMANCE MEASURE TASK CONDITIONS:

1. You are the Unit 1 Assist NSO.

2. Unit 1 had an automatic Safety Injection Actuation. The 1B and 1D RCFCs are out of service.

INITIATING CUES:

1. The Unit Supervisor directs you to perform 1BwEP-0, Step 7 to Verify RCFCs are running in Accident Mode.

SIM-508 Page 1 of 5

TASK TITLE: Start RCFCs in Accident Mode.

JPM No.: SIM-508 REV: 2013 NRC TPO No: 4C.VP-06 K/A No.: 022000A4.01 TASK No.: R-VP-007 Start-up a RCFC K/A IMP: 3.6/3.6 EXAMINEE: RO SRO (Circle One)

ALTERNATE PATH: YES EVALUATOR: DATE:

The Examinee: PASSED this JPM. TIME STARTED:

FAILED TIME FINISHED:

JPM TIME: MINUTES CRITICAL ELEMENTS: (*) 3, 4, 5, 8 APPROX COMPLETION TIME: 10 MINUTES CRITICAL TIME: NA EVALUATION METHOD: LOCATION:

X PERFORM _ IN PLANT

_ SIMULATE X SIMULATOR GENERAL

REFERENCES:

1. 1BwEP-0, Rev. 204, REACTOR TRIP OR SI MATERIALS:

1. 1BwEP-0, Step 7 TASK STANDARDS:

1. Start RCFC fans in low speed following SI with failure of SX valves to automatically align.

TASK CONDITIONS:

1. You are the Unit 1 Assist NSO.

2. Unit 1 had an automatic Safety Injection Actuation. The 1B and 1D RCFCs are out of service.

INITIATING CUES:

1. The Unit Supervisor directs you to perform 1BwEP-0, Step 7 to Verify RCFCs are running in Accident Mode.

SIM-508 Page 2 of 5

RECORD START TIME:

PERFORMANCE STEP STANDARD CIRCLE APPLICABLE

1. Refer to 1BwEP-0, Reactor

LOCATE and refer to SAT UNSAT N/A Trip or Safety Injection. 1BwEP-0, Reactor Trip or Comments:

Safety Injection

2. Check Group 2 RCFC Accident

Group 2 RCFC Accident SAT UNSAT N/A Mode Status Lights. Mode Status Lights are NOT lit Comments:

- ALTERNATE PATH START**

3. Stop any RCFC running in High

Stop all RCFCs running SAT UNSAT N/A Speed. in High Speed (the two running must be stopped) Comments:

1VP01CA

1VP01CC

4. Close CNMT chiller inlet and

Close 1SX112A & SAT UNSAT N/A outlet valves. 1SX114A Comments:

5. Open CNMT chiller bypass

Open 1SX147A. SAT UNSAT N/A valves.

Comments:

6. Verify/Open RCFC inlet valves.

1SX016A is OPEN. SAT UNSAT N/A Comments:

7. Verify RCFC outlet valves are

1SX027A is OPEN. SAT UNSAT N/A OPEN.

Comments:

8. Start all RCFCs in Low Speed.

Start all RCFCs in Low SAT UNSAT N/A Speed (for each, after a 20 second delay). Comments:

1VP01CA

1VP01CC SIM-508 Page 3 of 5

CUE: THIS COMPLETES THIS JPM.

RECORD STOP TIME: ________

COMMENTS:

SIM-508 Page 4 of 5

SIMULATOR SETUP INSTRUCTIONS

Verify/perform TQ-BR-201-0113, BRAIDWOOD TRAINING DEPARTMENT SIMULATOR EXAMINATION SECURITY ACTIONS CHECKLIST.

Reset to IC-21

Shut down the operating containment chiller (to prevent nuisance trip during JPM)

Place high and low switches for 1B and 1D RCFCs in PTL and place clearance order cards on them.

COMMENTS:

SIM-508 Page 5 of 5

REV. 204 REACTOR TRIP OR SAFETY INJECTION 1BwEP-0 WOG 2 UNIT 1 A. PURPOSE This procedure provides actions to verify proper response of the automatic protection systems following manual or automatic actuation of a Reactor Trip or Safety Injection, to assess plant conditions, and to identify the appropriate recovery procedure.

B. SYMPTOMS OR ENTRY CONDITIONS

1) The following are symptoms that may require a Reactor Trip, if one has not occurred:

o Source range high level ³ 105 CPS o Intermediate range high level ³ 25% power o Power range lo-level ³ 25% power o Power range hi-level ³ 109% power o Power range positive rate ³ +5% power change in 2 seconds o Overtemperature Delta T ³ 132.5% +/- penalties o Overpower Delta T ³ 107.2% - penalties o High PZR pressure ³ 2385 PSIG o Low PZR pressure £ 1885 PSIG o High PZR level ³ 92%

o Single loop loss of flow £ 90% loop flow o Two loop loss of flow £ 90% loop flow in 2/4 loops o RCP breakers OPEN o RCP bus low frequency £ 57.0 HZ o RCP bus undervoltage £ 5268 VOLTS o Turbine trip emergency trip header £ 1000 PSIG oil pressure or Turbine throttle valves shut o SI manual actuation o CNMT high pressure SI ³ 3.4 PSIG o Low PZR pressure SI £ 1829 PSIG o Low steamline pressure SI £ 640 PSIG (rate sensitive) o Steam Generator water level low-low £ 18% of narrow range span

2) The following are symptoms of a reactor trip:

o Any Reactor Trip first out annunciator lit.

o Rapid drop in neutron level indicated by nuclear instrumentation.

o All shutdown and control rods fully inserted and rod bottom lights lit.

o Rapid drop in Unit load to zero power.

Page 1 of 42

REV. 204 REACTOR TRIP OR SAFETY INJECTION 1BwEP-0 WOG 2 UNIT 1 Step 2 (continued)

3) The following may be symptoms that require a Reactor Trip and Safety Injection, if one has not occurred:

o Low PZR pressure £ 1829 PSIG PSIG..

o Low steamline pressure £ 640 PSIG (rate sensitive).

o CNMT high pressure ³ 3.4 PSIG PSIG. .

4) The following may be symptoms of a Reactor Trip and Safety Injection:

o Any SI first out annunciator lit.

o All Group 2 cold leg injection monitor lights lit.

o ESF equipment actuated.

o SI actuated BYPASS-PERMISSIVE light lit.

5) This procedure may also be entered:

o Anytime a manual reactor trip or safety injection is actuated.

o Anytime an SI is actuated or required while in Mode 3.

Page 2 of 42

REV. 204 REACTOR TRIP OR SAFETY INJECTION 1BwEP-0 WOG 2 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

NOTE *

With this procedure in effect, the *

Emergency Director shall evaluate *

for Emergency Plan conditions. *

NOTE *

"ADVERSE CNMT" is defined as: *

o CNMT pressure GREATER THAN 5 PSIG *

-OR- *

o CNMT radiation level GREATER THAN *

105 R/HR R/HR:: *

o 1RT-AR020 Grid 4 4AS120 *

o 1RT-AR021 Grid 4 4AS121

1 VERIFY REACTOR TRIP TRIP:: Manually trip the Reactor:

Rod bottom lights - ALL LIT

1PM05J

1PM06J

Reactor trip and bypass breakers - OPEN IF PR channels are greater than 5%

Neutron flux - DROPPING OR IR SUR is positive, THEN GO TO 1BwFR-S.1, RESPONSE TO NUCLEAR POWER GENERATION/ATWS, Step 1.

Page 3 of 42

REV. 204 REACTOR TRIP OR SAFETY INJECTION 1BwEP-0 WOG 2 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2 VERIFY TURBINE TRIP TRIP:: Manually trip the turbine:

All Turbine throttle valves - o Trip pushbutton CLOSED o OWS graphic 5512

All Turbine governor valves -

CLOSED IF any throttle AND any governor valve are open, THEN isolate the steam supply:

o Manually run back the turbine at maximum rate at OWS graphic 5501:

1) Select turbine MANUAL.

2) Select RAPID.

3) Select and HOLD GV lower arrow.

o Manually actuate Main Steamline Isolation AND verify MSIV bypass valves are CLOSED.

3 VERIFY POWER TO 4KV ESF BUSSES BUSSES:

a. ESF busses - AT LEAST ONE a. GO TO 1BwCA-0.0, LOSS OF ENERGIZED ENERGIZED:: ALL AC POWER, Step 1.

o Bus 141 o Bus 142

b. ESF busses - BOTH ENERGIZED ENERGIZED:

b. WHEN time permits, THEN try to restore power

Bus 141 to deenergized ESF bus per

Bus 142 1BwOA ELEC-3, LOSS OF 4KV ESF BUS.

Page 4 of 42

REV. 204 REACTOR TRIP OR SAFETY INJECTION 1BwEP-0 WOG 2 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 4 CHECK SI STATUS STATUS: :

a. Check if SI - ACTUATED ACTUATED:

a. Check if SI is required:

o Any SI first out o PZR pressure less than annunciator - LIT or equal to 1829 PSIG PSIG.

-OR- o Steamline pressure less than or equal to o SI ACTUATED permissive 640 PSIG PSIG.

light - LIT o CNMT pressure greater

-OR- than or equal to 3.4 PSIG PSIG.

o SI equipment - AUTOMATICALLY ACTUATED ACTUATED:: IF SI is required, THEN manually actuate SI.

o Either SI pump - RUNNING IF SI is NOT required, o Either CENT CHG pump to THEN GO TO 1BwEP ES-0.1, cold leg injection isol REACTOR TRIP RESPONSE, valve - OPEN OPEN:

Step 1.

o 1SI8801A o 1SI8801B

b.

Manually actuate SI:

1PM05J

1PM06J 5 DIRECT AN NSO TO PERFORM ATTACHMENT B (Page 32) WHILE CONTINUING WITH THIS PROCEDURE 6 VERIFY ECCS PUMPS RUNNING RUNNING:

Manually start pump(s).

CENT CHG pumps - BOTH RUNNING

RH pumps - BOTH RUNNING

SI pumps - BOTH RUNNING Page 5 of 42

REV. 204 REACTOR TRIP OR SAFETY INJECTION 1BwEP-0 WOG 2 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 7 VERIFY RCFCs RUNNING IN ACCIDENT MODE MODE::

a. Group 2 RCFC Accident Mode a. Manually align RCFCs in status lights - LIT accident mode as necessary:

1) Stop any RCFC running in high speed.

2) Close CNMT chiller inlet and outlet valves:

o 1SX112A o 1SX114A o 1SX112B o 1SX114B

3) Open CNMT chiller bypass valves:

o 1SX147A o 1SX147B

4) Open RCFC inlet and outlet valves:

o 1SX016A o 1SX016B o 1SX027A o 1SX027B

5) Start all RCFCs in low speed.

Page 6 of 42

REV. 204 REACTOR TRIP OR SAFETY INJECTION 1BwEP-0 WOG 2 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 8 VERIFY CNMT ISOLATION PHASE AA:

a. Group 3 CNMT Isol monitor a. Manually actuate CNMT lights - LIT Isolation Phase A.

IF any Phase A valve will NOT close, THEN manually close valve(s).

IF any valve(s) located outside of CNMT can NOT be closed manually, THEN locally close the valve(s) while continuing with Step 9.

9 VERIFY CNMT VENTILATION ISOLATION ISOLATION::

a. Group 6 CNMT Vent Isol monitor a. Perform the following:

lights - LIT

1) Stop any running VQ fans.

2) Manually close VQ isol valve(s) as necessary.

Page 7 of 42

REV. 204 REACTOR TRIP OR SAFETY INJECTION 1BwEP-0 WOG 2 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 10 VERIFY AF SYSTEM SYSTEM::

a. AF pumps - BOTH RUNNING a. Manually start pump(s).

b. AF isol valves - OPEN OPEN:: b. Manually open valve(s) as necessary.

1AF013A

1AF013B

1AF013C

1AF013D

1AF013E

1AF013F

1AF013G

1AF013H

c. AF flow control valves - c. Manually throttle valve(s)

THROTTLED THROTTLED:: open as necessary.

1AF005A

1AF005B

1AF005C

1AF005D

1AF005E

1AF005F

1AF005G

1AF005H 11 VERIFY CC PUMPS RUNNING RUNNING:

a. CC pumps - BOTH RUNNING a. Manually start pump(s).

12 VERIFY SX PUMPS RUNNING RUNNING:

a. SX pumps - BOTH RUNNING a. Manually start pump(s).

Page 8 of 42

REV. 204 REACTOR TRIP OR SAFETY INJECTION 1BwEP-0 WOG 2 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 13 CHECK IF MAIN STEAMLINES SHOULD BE ISOLATED ISOLATED::

a. Check for either of the a. GO TO Step 14 (Next following: Page).

o Any SG pressure - LESS THAN 640 PSIG

-OR-o CNMT pressure (1PR-937 or 1PI-CS934 thru 1PI-CS937) -

GREATER THAN 8.2 PSIG

b. Verify the following: b. Perform the following:

MSIVs - CLOSED 1) Manually actuate Main Steamline Isolation.

MSIV bypass valves - CLOSED

2) Verify MSIV and MSIV bypass valves are closed.

IF any valve will NOT close, THEN manually close valve(s).

Page 9 of 42

REV. 204 REACTOR TRIP OR SAFETY INJECTION 1BwEP-0 WOG 2 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 14 CHECK IF CS IS REQUIRED REQUIRED:

a. CNMT pressure (1PR-937 or a. Continue with Step 15 1PI-CS934 thru 1PI-CS937) - HAS (Page 12).

RISEN TO GREATER THAN 20 PSIG IF CNMT pressure rises to greater than 20 PSIG PSIG,,

THEN do Steps 14b thru 14f.

b. Group 6 CS monitor lights - LIT b. Manually actuate CS and Phase B Isolation.

IF Group 6 CS monitor lights are NOT LIT LIT,,

THEN GO TO ATTACHMENT C, Step 1 (Page 41).

c. Group 6 Phase B Isolation c. Manually actuate CS and monitor lights - LIT Phase B Isolation.

IF Group 6 Phase B isolation monitor lights are NOT LIT LIT, THEN manually close Phase B isolation valves.

d. Stop all RCPs

e. Check CS eductor suction flow e. Dispatch an operator with on running pump(s) - GREATER keys to verify valve(s)

THAN 15 GPM GPM:: are OPEN:

o 1FI-CS013 o 1CS035A (1A CS Pump Rm) o 1FI-CS014 o 1CS035B (1B CS Pump Rm)

Step continued on next page Page 10 of 42

REV. 204 REACTOR TRIP OR SAFETY INJECTION 1BwEP-0 WOG 2 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED Step 14 (continued)

f. Check CS eductor additive flow f. Dispatch operator(s) with on running pump(s) - GREATER keys to verify valves are THAN 5 GPM GPM:: OPEN:

o 1FI-CS015 o Train A:

o 1FI-CS016

1CS017A (364' U13)

1CS018A (364' U13)

1CS040A (364' U13)

1CS021A (1A CS Pump Rm) [Throttled]

1CS046A (1A CS Pump Rm) o Train B:

1CS017B (364' U13)

1CS018B (364' U13)

1CS040B (364' U13)

1CS021B (1B CS Pump Rm) [Throttled]

1CS046B (1B CS Pump Rm)

Page 11 of 42

REV. 204 REACTOR TRIP OR SAFETY INJECTION 1BwEP-0 WOG 2 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 15 VERIFY TOTAL AF FLOW FLOW::

a. AF flow - GREATER THAN 500 GPM a. IF SG narrow range level is greater than 10% ((31%

31%

ADVERSE CNMT) in any SG, THEN control feed flow to maintain narrow range level.

IF SG narrow range level is less than 10% ((31%

31%

ADVERSE CNMT) in all SGs, THEN perform the following:

a) Manually start pump(s) and align valve(s) as necessary.

b) IF feed flow greater than 500 GPM can NOT be established, THEN GO TO 1BwFR-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, Step 1.

b. Check SG narrow range levels - b. IF ruptured SG is NOT RISING IN AN UNCONTROLLED identified AND affected SG MANNER narrow range level is greater than 10% ((31%

31%

ADVERSE CNMT),

THEN manually close its AF isol valves:

o SG 1A:

1AF013A

1AF013E o SG 1B:

1AF013B

1AF013F o SG 1C:

1AF013C

1AF013G o SG 1D:

1AF013D

1AF013H Page 12 of 42

REV. 204 REACTOR TRIP OR SAFETY INJECTION 1BwEP-0 WOG 2 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 16 VERIFY ECCS VALVE ALIGNMENT ALIGNMENT:

a. Group 2 Cold Leg Injection a. Manually align valve(s) as monitor lights required for necessary.

ECCS valve alignment - LIT 17 VERIFY ECCS FLOW FLOW::

a. High head SI flow (1FI-917) - a. Manually start CENT CHG GREATER THAN 100 GPM pumps and align valves as necessary.

b. RCS pressure (1PI-403A/405) - b. GO TO Step 18 (Next LESS THAN 1700 PSIG Page).

c. SI pump discharge flow c. Manually start SI pumps (1FI-918/922) - GREATER THAN and align valves as 200 GPM necessary.

d. RCS pressure - LESS THAN d. GO TO Step 18 (Next 325 PSIG Page).

e. RH pump discharge flow e. Manually start RH pumps (1FI-618/619) - GREATER THAN and align valves as 1000 GPM necessary.

f. Check two CENT CHG pumps - f. IF only one CENT CHG pump RUNNING is running, THEN perform the following:

1) Verify head SI flow (1FI-917) greater than 100 GPM or SI pump discharge flow greater than 200 GPM GPM.

2) Trip all RCPs.

3) WHEN the RCS is depressurized, THEN manually close RCP seal injection isolation valves:

1CV8355A

1CV8355B

1CV8355C

1CV8355D Page 13 of 42

REV. 204 REACTOR TRIP OR SAFETY INJECTION 1BwEP-0 WOG 2 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 18 CHECK PZR PORVS AND SPRAY VALVES VALVES::

a. PORVs - CLOSED CLOSED:: a. IF PZR pressure is less than 2315 PSIG PSIG,

1RY455A THEN manually close PORVs.

1RY456 IF any PORV can NOT be closed, THEN manually or locally close its isol valve:

o 1RY8000A (1RY455A)

MCC 131X2B A5 (414' S12 CWA) o 1RY8000B (1RY456)

MCC 132X2 C4 (426' S12 CWA)

IF PORV isol valve can NOT be closed, THEN GO TO 1BwEP-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1.

b.

PORV isol valves - AT LEAST b. GO TO Step 18d.

ONE ENERGIZED

c.

PORV relief path - AT LEAST c. Perform the following to ONE AVAILABLE AVAILABLE:

establish a PORV relief path for any PORV NOT

PORV in - AUTO failed open:

Associated isol valve - OPEN 1) Place the PORV in AUTO.

2) Open the associated PORV isol valve.

d. Normal PZR spray valves - d. IF PZR pressure is less CLOSED CLOSED: : than 2260 PSIG PSIG, THEN manually close spray

1RY455B valve(s).

1RY455C IF any spray valve(s) can not be closed, THEN stop RCP(s) as necessary to stop spray flow:

o RCP 1D o RCP 1C o RCP 1B o RCP 1A Page 14 of 42

REV. 204 REACTOR TRIP OR SAFETY INJECTION 1BwEP-0 WOG 2 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 19 CHECK RCS TEMPERATURES TEMPERATURES: : IF temperature is less than 557°F and dropping, o RCPs - ANY RUNNING RUNNING:: THEN perform the following:

RCS average temperature - a. Stop dumping steam.

STABLE AT OR TRENDING TO 557°F b. IF cooldown continues, THEN control total feed

-OR- flow:

o RCPs - NONE RUNNING RUNNING: :

Maintain total feed flow greater than 500 GPM

RCS cold leg temperature - until SG narrow range STABLE AT OR TRENDING TO level is greater than 557°F 10% (

(31%

31% ADVERSE CNMT) in at least one SG.

c. IF cooldown continues, THEN close MSIV and MSIV bypass valves.

IF temperature is greater than 557°F and rising, THEN perform the following:

o IF the C-9 permissive light is NOT LIT AND the MSIV(s) or MSIV bypass valve(s) are open, THEN dump steam to condenser:

1) Place MS header pressure controller in MANUAL and reduce demand signal to zero.

2) Place steam dump mode selector switch in STM PRESS mode.

3) Adjust MS header pressure controller in manual or auto.

-OR-o Dump steam using SG PORVs.

Page 15 of 42

REV. 204 REACTOR TRIP OR SAFETY INJECTION 1BwEP-0 WOG 2 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

NOTE *

Seal injection flow should be *

maintained to all RCPs to prevent *

seal damage due to overheating.

20 CHECK IF RCPS SHOULD BE STOPPED STOPPED:

a. RCPs - ANY RUNNING a. GO TO Step 21.

b. ECCS flow: b. GO TO Step 21.

o High head SI flow (1FI-917) -

GREATER THAN 100 GPM

-OR-o SI pump discharge flow (1FI-918/922) - GREATER THAN 200 GPM

c. RCS pressure - LESS THAN c. GO TO Step 21.

1425 PSIG

d. Stop all RCPs 21 CHECK IF SGs SECONDARY PRESSURE BOUNDARIES ARE INTACT INTACT:

a. Check pressure in all SGs: a. GO TO 1BwEP-2, FAULTED STEAM GENERATOR

NO SG PRESSURE DROPPING IN AN ISOLATION, Step 1.

UNCONTROLLED MANNER

NO SG COMPLETELY DEPRESSURIZED Page 16 of 42

REV. 204 REACTOR TRIP OR SAFETY INJECTION 1BwEP-0 WOG 2 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 22 CHECK IF SG TUBES ARE INTACT INTACT:: GO TO 1BwEP-3, STEAM GENERATOR TUBE RUPTURE,

SJAE/Gland Steam Exhaust Gas Step 1.

radiation - HAS REMAINED LESS THAN ALERT ALARM SETPOINT SETPOINT::

1PR27J Grid 1 1PS127

SG Blowdown Liquid radiation -

HAS REMAINED LESS THAN ALERT ALARM SETPOINT SETPOINT::

1PR08J Grid 1 1PS108

Main Steamline radiation - HAS REMAINED LESS THAN ALERT ALARM SETPOINT SETPOINT::

Main Steamline 1A, MSIV Rm:

1RT-AR022 Grid 1 4AA122

1RT-AR023 Grid 1 4AA123

Main Steamline 1B, MSIV Rm:

1RT-AR022 Grid 1 4AB222

1RT-AR023 Grid 1 4AB223

Main Steamline 1C, MSIV Rm:

1RT-AR022 Grid 1 4AC322

1RT-AR023 Grid 1 4AC323

Main Steamline 1D, MSIV Rm:

1RT-AR022 Grid 1 4AD422

1RT-AR023 Grid 1 4AD423 Page 17 of 42

REV. 204 REACTOR TRIP OR SAFETY INJECTION 1BwEP-0 WOG 2 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 23 CHECK IF RCS IS INTACT INTACT:: GO TO 1BwEP-1, LOSS OF REACTOR OR SECONDARY COOLANT,

CNMT area radiation monitors - Step 1.

HAVE REMAINED LESS THAN ALERT ALARM SETPOINTS SETPOINTS::

1RT-AR014 Grid 4 4AS101

1RT-AR014 Grid 4 4AS202

1RT-AR014 Grid 4 4AS303

1RT-AR011 Grid 4 4AS111

1RT-AR012 Grid 4 4AS112

1RT-AR020 Grid 4 4AS120

1RT-AR021 Grid 4 4AS121

CNMT pressure - LESS THAN 3.4 PSIG

CNMT floor drain sump level -

LESS THAN 46 INCHES INCHES::

1LI-PC002

1LI-PC003 Page 18 of 42

REV. 204 REACTOR TRIP OR SAFETY INJECTION 1BwEP-0 WOG 2 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 24 CHECK IF ECCS FLOW SHOULD BE REDUCED REDUCED::

a. RCS subcooling - ACCEPTABLE ACCEPTABLE:

a. GO TO Step 25.

o ICONIC DISPLAY

-OR-o ATTACHMENT A (Page 31)

b. Secondary heat sink: b. IF neither condition is satisfied, o Total feed flow to SGs - THEN GO TO Step 25.

GREATER THAN 500 GPM

-OR-o Narrow range level in at least one SG - GREATER THAN 10%

c. RCS pressure - STABLE OR RISING c. GO TO Step 25.

d. PZR level - GREATER THAN 14% d. Perform the following:

1) IF normal PZR spray is available, THEN try to stabilize RCS pressure.

2) RETURN TO Step 24a.

e. GO TO 1BwEP ES-1.1, SI TERMINATION, Step 1 25 INITIATE MONITORING OF CRITICAL SAFETY FUNCTION STATUS TREES Page 19 of 42

REV. 204 REACTOR TRIP OR SAFETY INJECTION 1BwEP-0 WOG 2 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 26 CHECK SG LEVELS LEVELS:

a. Narrow range levels - GREATER a. Maintain total feed flow THAN 10% greater than 500 GPM until narrow range level is greater than 10% in at least one SG.

b. Control feed flow to maintain b. IF narrow range level in narrow range levels - BETWEEN any SG continues to rise 10% AND 50% in an uncontrolled manner, THEN GO TO 1BwEP-3, STEAM GENERATOR TUBE RUPTURE, Step 1.

Ú¿

³ CAUTION ³

³ If offsite power is lost after SI ³

³ reset, manual action may be required ³

³ to restart RH and SI pumps. ³ 27 RESET SI SI:: IF bypass permissive panel is energized and SI has NOT

a. Depress both SI reset reset, pushbuttons THEN reset SI per 1BwOA PRI-5, CONTROL ROOM

b. Verify SI ACTUATED permissive INACCESSIBILITY, ATTACHMENT light - NOT LIT E.

c. Verify AUTO SI BLOCKED permissive light - LIT 28 RESET CONTAINMENT ISOLATION ISOLATION:

Reset per 1BwOA PRI-5, CONTROL ROOM INACCESSIBILITY,

Phase A ATTACHMENT E.

Phase B if necessary Page 20 of 42

REV. 204 REACTOR TRIP OR SAFETY INJECTION 1BwEP-0 WOG 2 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 29 ESTABLISH INSTRUMENT AIR TO CONTAINMENT CONTAINMENT::

a. Check SACs - ANY RUNNING a. Dispatch an operator to start one SAC per BwOP SA-1, STARTUP AND OPERATION OF A STATION AIR COMPRESSOR.

Continue with Step 30 (Next Page). OBSERVE CAUTION PRIOR TO STEP 30.

WHEN a SAC is running, THEN do Step 29b.

b. Open instrument air CNMT isol valves:

1) 1IA065 1) Locally open the valve using a pneumatic jumper (391' CWA P-39).

Continue with Step 30 (Next Page). OBSERVE CAUTION PRIOR TO STEP 30.

WHEN 1IA065 is open, THEN open 1IA066.

2) 1IA066 Page 21 of 42

REV. 204 REACTOR TRIP OR SAFETY INJECTION 1BwEP-0 WOG 2 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

Ú¿

³ CAUTION ³

³ RCS pressure should be monitored. ³

³ If RCS pressure drops in an ³

³ uncontrolled manner to less than ³

³ 325 PSIG PSIG,

, the RH pumps must be ³

³ manually restarted to supply water ³

³ to the RCS. ³ 30 CHECK IF RH PUMPS SHOULD BE STOPPED STOPPED::

a. Check RCS pressure:

1) Pressure - GREATER THAN 1) GO TO 1BwEP-1, LOSS OF 325 PSIG REACTOR OR SECONDARY COOLANT, Step 1.

2) Pressure - STABLE OR RISING 2) GO TO Step 31 (Next Page).

b. Stop RH pumps and place in standby Page 22 of 42

REV. 204 REACTOR TRIP OR SAFETY INJECTION 1BwEP-0 WOG 2 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 31 CHECK SECONDARY RADIATION NORMAL NORMAL::

a. Sample all SGs for activity:

1) Open SG Blowdown Sample Isol valves:

1SD005A (SG 1A)

1SD005C (SG 1B)

1SD005D (SG 1C)

1SD005B (SG 1D)

2) Request Chem Dept to sample all SGs for activity

b. Check secondary radiation b. GO TO 1BwEP-3, trends (PPC or RM-11) - NORMAL STEAM GENERATOR TUBE FOR PLANT CONDITIONS CONDITIONS:

RUPTURE, Step 1.

SJAE/Gland Steam Exhaust Gas radiation:

1PR27J Grid 1 1PS127

SG Blowdown Liquid radiation:

1PR08J Grid 1 1PS108

Main Steamline radiation:

Main Steamline 1A, MSIV Rm:

1RT-AR022 Grid 1 4AA122

1RT-AR023 Grid 1 4AA123

Main Steamline 1B, MSIV Rm:

1RT-AR022 Grid 1 4AB222

1RT-AR023 Grid 1 4AB223

Main Steamline 1C, MSIV Rm:

1RT-AR022 Grid 1 4AC322

1RT-AR023 Grid 1 4AC323

Main Steamline 1D, MSIV Rm:

1RT-AR022 Grid 1 4AD422

1RT-AR023 Grid 1 4AD423

c. Secondary activity samples - c. GO TO 1BwEP-3, NORMAL (WHEN AVAILABLE) STEAM GENERATOR TUBE RUPTURE, Step 1.

Page 23 of 42

REV. 204 REACTOR TRIP OR SAFETY INJECTION 1BwEP-0 WOG 2 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 32 CHECK AUXILIARY BUILDING RADIATION RADIATION::

a. Check Aux Bldg radiation trends a. Evaluate cause of abnormal (PPC or RM-11) - NORMAL FOR conditions.

PLANT CONDITIONS CONDITIONS:

IF cause is loss of RCS

Unit 1 Aux Bldg vent stack inventory outside CNMT, effluent (1PR28J): THEN GO TO 1BwCA-1.2, LOCA OUTSIDE CONTAINMENT,

Grid 2 Beta 1PA228 Step 1.

Grid 2 Gas Low 1PB128

Grid 2 Iodine 1PC328

Grid 2 Gas High 1PD428

Unit 1 Aux Bldg vent stack effluent (1PR30J):

Grid 2 Gas Low 1PA130

Grid 2 Gas Med 1PB230

Grid 2 Gas High 1PC330

Grid 2 Effluent 1PF430

Unit 2 Aux Bldg vent stack effluent (2PR28J):

Grid 2 Beta 2PA228

Grid 2 Gas Low 2PB128

Grid 2 Iodine 2PC328

Grid 2 Gas High 2PD428

Unit 2 Aux Bldg vent stack effluent (2PR30J):

Grid 2 Gas Low 2PA130

Grid 2 Gas Med 2PB230

Grid 2 Gas High 2PC330

Grid 2 Effluent 2PF430 Step continued on next page Page 24 of 42

REV. 204 REACTOR TRIP OR SAFETY INJECTION 1BwEP-0 WOG 2 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED Step 32a (continued)

ECCS cubicles:

RH/CS pump 1A Cubicle (1PR13J):

Grid 2 Beta 1PA213

Grid 2 Gas 1PB113

RH/CS pump 1B Cubicle (1PR14J):

Grid 2 Beta 1PA214

Grid 2 Gas 1PB114

RH HX 1A Cubicle (1PR15J):

Grid 2 Beta 1PA215

Grid 2 Gas 1PB115

RH HX 1B Cubicle (1PR16J):

Grid 2 Beta 1PA216

Grid 2 Gas 1PB116

CENT CHG pump 1A Cubicle (1PR17J):

Grid 2 Beta 1PA217

Grid 2 Gas 1PB117

CENT CHG pump 1B Cubicle (1PR18J):

Grid 2 Beta 1PA218

Grid 2 Gas 1PB118

Grid 4 Aux Bldg area radiation 33 CHECK PRT CONDITIONS NORMAL NORMAL:: Evaluate cause of abnormal conditions.

PRT Pressure - LESS THAN 6 PSIG

PRT Level - LESS THAN 88%

PRT Temperature - LESS THAN 125°F Page 25 of 42

REV. 204 REACTOR TRIP OR SAFETY INJECTION 1BwEP-0 WOG 2 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 34 CHECK IF DGs SHOULD BE STOPPED STOPPED:

a. 4KV busses - ENERGIZED BY a. Try to restore offsite OFFSITE POWER POWER:: power to 4KV busses:

Bus 141 1) Consult TSO for status

Bus 142 of offsite power restoration.

Bus 143

Bus 144 IF offsite power is available, THEN perform the following:

1) Restore offsite power to 4KV ESF busses per BwOP AP-32, SYNCHRONIZING A SAT TO A BUS BEING FED BY A DG.

2) Sync and close associated 4KV NON-ESF SAT feed breakers:

ACB 1432

ACB 1442 Step continued on next page Page 26 of 42

REV. 204 REACTOR TRIP OR SAFETY INJECTION 1BwEP-0 WOG 2 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED Step 34 (continued)

IF offsite power can NOT be restored to 4KV NON-ESF bus(es),

THEN crosstie the NON-ESF bus(es) to the ESF bus(es) as follows:

1) Dispatch an operator to place the following switch in PULL OUT (Panel 0VS03J, 3rd floor HVAC room):

Service Bldg chiller 0A (Bus 144 only)

2) Place feeder breakers for affected 4KV NON-ESF bus(es) in PULL OUT:

o Bus 143:

ACB 1431

ACB 1432 o Bus 144:

ACB 1441

ACB 1442

3) Open all 480 volt transformer HIGH side and LOW side breakers for affected bus(es).

4) Open all 480 volt PZR heater transformer LOW side breakers at 1PM05J for affected bus(es).

5) Reset SI recirc sump isol valves if necessary:

1SI8811A

1SI8811B Step continued on next page Page 27 of 42

REV. 204 REACTOR TRIP OR SAFETY INJECTION 1BwEP-0 WOG 2 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED Step 34 (continued)

6) Place non-running equipment in PULL OUT on affected bus(es):

Cnmt chillers

WS pumps

SACs

7) Close affected bus(es)

NON-ESF to ESF crosstie breaker:

o ACB 1411 o ACB 1421 Load equipment as necessary while continuing with Step 34b (Page 29):

1) Restore PZR heaters:

a) Close 4KV PZR heater transformer HIGH side breakers.

b) Close 480 volt PZR heater transformer LOW side breakers at 1PM05J.

2) Energize Unit 1 480 volt busses.

3) Start a WS pump per BwOP WS-1, STARTUP AND OPERATION OF WS SYSTEM, if necessary.

Step continued on next page Page 28 of 42

REV. 204 REACTOR TRIP OR SAFETY INJECTION 1BwEP-0 WOG 2 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED Step 34 (continued)

4) Restore air, if necessary:

a) Start a SAC per BwOP SA-1, STARTUP AND OPERATION OF A STATION AIR COMPRESSOR.

b) Restore IA to CNMT:

1) Open 1IA065.

2) Open 1IA066.

5) Start other NON-ESF loads as necessary:

o Boric acid transfer pump o SFP cooling pump o Air side seal oil pump o Hydrogen side seal oil pump IF any 4KV ESF bus is NOT energized, THEN perform 1BwOA ELEC-3, LOSS OF 4KV ESF BUS as time permits.

b. Stop any unloaded DG and place in standby per BwOP DG-12, DIESEL GENERATOR SHUTDOWN 35 RETURN TO STEP 18 (Page 14)

-END-Page 29 of 42

REV. 204 REACTOR TRIP OR SAFETY INJECTION 1BwEP-0 WOG 2 UNIT 1 (NORMAL)

RCS Pressure (PSIG) 2600 2400 2200 ACCEPTABLE 2000 1800 1600 1400 1200 NOT 1000 ACCEPTABLE 800 Containment 600 Conditions:

Adverse---

400 Normal---

---Saturation 200 0

200 250 300 350 400 450 500 550 600 650 700 RCS Temperature ( °F)

FIGURE 1BwEP 0-1 RCS SUBCOOLING MARGIN Page 30 of 42

REV. 204 REACTOR TRIP OR SAFETY INJECTION 1BwEP-0 WOG 2 UNIT 1 ATTACHMENT A A. Determination of Post-Accident RCS Subcooling Subcooling:

1) Check CNMT for ADVERSE conditions:

o CNMT pressure greater than 5 PSIG PSIG.

-OR-o CNMT radiation greater than 105 R/HR R/HR:

o 1RT-AR020 Grid 4 4AS120 o 1RT-AR021 Grid 4 4AS121

2) Check RCS pressure on wide range pressure instruments (1PI-403A/405).

3) Determine temperature for RCS pressure using NORMAL or ADVERSE CNMT curves per FIGURE 1BwEP 0-1 (Previous Page).

4) Check average of ten highest core exit TCs from ICONIC DISPLAY OR MCB indicators (1TI-IT001/IT002).

5) If average of ten highest core exit TCs is less than temperature for RCS pressure, then acceptable subcooling exists.

Page 31 of 42

REV. 204 REACTOR TRIP OR SAFETY INJECTION 1BwEP-0 WOG 2 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT B (PG 1 OF 9)

BALANCE OF PLANT VERIFICATION 1 VERIFY FW ISOLATION ISOLATION:: Manually trip pump(s) and close valve(s) as necessary.

FW pumps - TRIPPED IF any FW reg valve can NOT

FW isolation monitor lights - be closed, LIT THEN manually close its associated FW shutoff valve:

FW pumps discharge valves -

CLOSED CLOSED:: o 1FW006A (1FW510) o 1FW006B (1FW520)

1FW002A o 1FW006C (1FW530)

1FW002B o 1FW006D (1FW540)

1FW002C 2 VERIFY DGs RUNNING RUNNING:

a. DGs - BOTH RUNNING a. Manually start DG(s).

b. DGs SX valve - OPEN OPEN: : b. Manually open valve(s).

1SX169A

1SX169B

c. Dispatch operator to check DGs operation 3 VERIFY GENERATOR TRIP TRIP::

a. Unit 1 Main Transformer output a. Manually open breaker(s).

breakers - OPEN OPEN:

OCB 1-8

OCB 7-8

b. PMG output breaker - OPEN b. Manually open PMG output breaker.

Page 32 of 42

REV. 204 REACTOR TRIP OR SAFETY INJECTION 1BwEP-0 WOG 2 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT B (PG 2 OF 9)

BALANCE OF PLANT VERIFICATION 4 VERIFY CONTROL ROOM VENTILATION ALIGNED FOR EMERGENCY OPERATION OPERATION::

a. Control Room outside air intake a. Locally verify the radiation - LESS THAN HIGH following fans are ALARM SETPOINT SETPOINT:: TRIPPED:

Control Room Outside Air 1) Control Room offices Intake 0A: HVAC Panel 0VV01J (451' K24):

0PR31J Grid 2 0PA231

0PR31J Grid 2 0PB131

0VV01CA, Supply Fan

0PR31J Grid 2 0PC331 OA

0PR32J Grid 2 0PA232

0VV01CB, Supply Fan

0PR32J Grid 2 0PB132 OB

0PR32J Grid 2 0PC332

2) Laboratory HVAC Panel

Control Room Outside Air 0VL01J (426' M10):

Intake 0B:

0VL02CA, Fume Hood

0PR33J Grid 2 0PA233 Exhaust Fan OA

0PR33J Grid 2 0PB133

0VL02CB, Fume Hood

0PR33J Grid 2 0PC333 Exhaust Fan OB

0PR34J Grid 2 0PA234

0PR34J Grid 2 0PB134 3) Radwaste Building HVAC

0PR34J Grid 2 0PC334 Panel 0VW01J (433' J45 SB):

0VW03CA, Exhaust Fan OA

0VW03CB, Exhaust Fan OB Step continued on next page Page 33 of 42

REV. 204 REACTOR TRIP OR SAFETY INJECTION 1BwEP-0 WOG 2 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT B (PG 3 OF 9)

BALANCE OF PLANT VERIFICATION Step 4 (continued)

b. Operating VC train equipment - b. Manually start equipment RUNNING RUNNING: : for VC train in operation.

o Train A: IF equipment can NOT be started,

Supply fan 0A THEN perform the following unless attempts have

Return fan 0A already failed to start both trains:

M/U fan 0A a) Reset Control Room Vent

Chilled water pump 0A Isolation.

MCR chiller 0A b) Stop inoperable VC train equipment.

o Train B:

c) Start opposite VC train

Supply fan 0B equipment.

Return fan 0B d) RETURN TO Step 4b.

M/U fan 0B

Chilled water pump 0B

MCR chiller 0B

c. Operating VC train dampers - c. Perform the following ALIGNED ALIGNED: : unless attempts have already failed to start

M/U fan outlet damper - NOT and align both trains:

FULLY CLOSED CLOSED:

1) Reset Control Room Vent o 0VC24Y (Train A) Isolation.

o 0VC08Y (Train B)

2) Stop inoperable VC train

VC train M/U filter light - equipment.

LIT

3) Start opposite VC train equipment.

4) RETURN TO Step 4b.

Step continued on next page Page 34 of 42

REV. 204 REACTOR TRIP OR SAFETY INJECTION 1BwEP-0 WOG 2 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT B (PG 4 OF 9)

BALANCE OF PLANT VERIFICATION Step 4 (continued)

d. Operating VC train M/U filter d. Place M/U Fltr Inlet aligned to - NORMAL TBTB:

Select switch to NORMAL TB position.

o Train A:

0VC25Y - OPEN

0VC312Y - CLOSED o Train B:

0VC09Y - OPEN

0VC313Y - CLOSED

e.

Operating VC train Charcoal e. Place RECIRC Charcoal Absorber - ALIGNED ALIGNED:

Absorber selector switch to the ABSORB position.

o Train A:

IF Charcoal Absorber is

0VC43Y bypass damper - still NOT aligned, CLOSED THEN perform the following unless attempts have

0VC21Y inlet damper - OPEN already failed to start and align both trains:

0VC22Y outlet damper -

OPEN 1) Reset Control Room Vent Isolation.

-OR-

2) Stop inoperable VC train o Train B: equipment.

0VC044Y bypass damper - 3) Start opposite VC train CLOSED equipment.

0VC05Y inlet damper - OPEN 4) RETURN TO Step 4b (Previous Page).

0VC06Y outlet damper -

OPEN

f. Control Room pressure f. Restore MCR pressure per (MCR/TB DP, OPDI-VC038) - BwOP VC-14, MAIN CONTROL GREATER THAN +0.125" H 2 O ROOM PRESSURE LOW, while continuing with this procedure.

Page 35 of 42

REV. 204 REACTOR TRIP OR SAFETY INJECTION 1BwEP-0 WOG 2 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT B (PG 5 OF 9)

BALANCE OF PLANT VERIFICATION 5 VERIFY AUX BLDG VENTILATION ALIGNED FOR EMERGENCY OPERATION OPERATION: :

a.

Inaccessible Filter Plenums - a. Align plenums and start TWO PLENUMS ALIGNED WITH fans as necessary per CHARCOAL ABSORBERS ON-LINE ON-LINE:

BwOP VA-5, AUX BLDG CHARCOAL BOOSTER FAN o Plenum A: OPERATION.

o Fan 0VA03CA - RUNNING RUNNING::

0VA022Y Flow Cont damper - NOT FULLY CLOSED

0VA020Y Byp Isol damper - CLOSED

-OR-o Fan 0VA03CB - RUNNING RUNNING::

0VA023Y Flow Cont damper - NOT FULLY CLOSED

0VA436Y Byp Isol damper - CLOSED Step continued on next page Page 36 of 42

REV. 204 REACTOR TRIP OR SAFETY INJECTION 1BwEP-0 WOG 2 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT B (PG 6 OF 9)

BALANCE OF PLANT VERIFICATION Step 5a (continued) o Plenum B:

o Fan 0VA03CC - RUNNING RUNNING:

0VA024Y Flow Cont damper - NOT FULLY CLOSED

0VA021Y Byp Isol damper - CLOSED

-OR-o Fan 0VA03CD - RUNNING RUNNING:

0VA025Y Flow Cont damper - NOT FULLY CLOSED

0VA437Y Byp Isol damper - CLOSED o Plenum C:

o Fan 0VA03CE - RUNNING RUNNING:

0VA067Y Flow Cont damper - NOT FULLY CLOSED

0VA052Y Byp Isol damper - CLOSED

-OR-o Fan 0VA03CF - RUNNING RUNNING:

0VA072Y Flow Cont damper - NOT FULLY CLOSED

0VA438Y Byp Isol damper - CLOSED Page 37 of 42

REV. 204 REACTOR TRIP OR SAFETY INJECTION 1BwEP-0 WOG 2 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT B (PG 7 OF 9)

BALANCE OF PLANT VERIFICATION 6 VERIFY FHB VENTILATION ALIGNED FOR EMERGENCY OPERATION OPERATION:

a. FHB Charcoal Absorbers - ONE a. Align one train per TRAIN ALIGNED ALIGNED:: BwOP VA-6, FUEL HANDLING BLDG CHARCOAL BOOSTER FAN o Train A: OPERATION.

Fan 0VA04CA - RUNNING

0VA060Y Charcoal Absorber Inlet Isol damper - OPEN

0VA057Y Filter Flow Control damper - NOT FULLY CLOSED

0VA051Y Charcoal Absorber Bypass Isolation damper -

CLOSED

-OR-o Train B:

Fan 0VA04CB - RUNNING

0VA055Y Charcoal Absorber Inlet Isolation damper -

OPEN

0VA062Y Filter Flow Control damper - NOT FULLY CLOSED

0VA435Y Charcoal Absorber Bypass Isolation damper -

CLOSED Page 38 of 42

REV. 204 REACTOR TRIP OR SAFETY INJECTION 1BwEP-0 WOG 2 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT B (PG 8 OF 9)

BALANCE OF PLANT VERIFICATION 7 SHUTDOWN UNNECESSARY PLANT EQUIPMENT EQUIPMENT::

Trip all running HD pumps

Shutdown FW pumps as necessary per:

³ o BwOP FW-2, SHUTDOWN OF A

³ TURBINE DRIVEN MAIN FEEDWATER

³ PUMP

³ o BwOP FW-8, SHUTDOWN OF A

³ MOTOR DRIVEN MAIN FEEDWATER

³ PUMP

Shutdown all unnecessary CD/CB pumps per BwOP CD/CB-2, CONDENSATE/CONDENSATE BOOSTER SYSTEM SHUTDOWN

Shutdown all unnecessary CW pumps per BwOP CW-2, CIRCULATING WATER PUMP/SYSTEM SHUTDOWN Page 39 of 42

REV. 204 REACTOR TRIP OR SAFETY INJECTION 1BwEP-0 WOG 2 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT B (PG 9 OF 9)

BALANCE OF PLANT VERIFICATION

³ 8 INITIATE PERIODIC CHECKING OF

³ SPENT FUEL COOLING COOLING:

³ a. Locally verify SFP level is a. IF SFP level drops to the ³

³ greater than 420' ELEV (20 FT 420' ELEV, ³

³ above top of fuel) THEN makeup to the SFP per ³

³ o BwOP FC-11, SPENT FUEL ³ POOL LEVEL ADJUSTMENT ³ o 1BwOA REFUEL-2, REACTOR ³ CAVITY OR SPENT FUEL ³ POOL UNCONTROLLED LEVEL ³ LOSS ³

³ b. Locally verify SFP b. IF SFP temperature is ³

³ temperature - STABLE rising, ³ THEN restore cooling: ³

0BwOA REFUEL-3, LOSS OF ³ SPENT FUEL COOLING ³

³ c. NOTIFY the STA of SFP cooling

³ Status 9 NOTIFY UNIT SUPERVISOR OF THE FOLLOWING FOLLOWING::

Manual actions taken

Failed Equipment status

ATTACHMENT B completed

-END-Page 40 of 42

REV. 204 REACTOR TRIP OR SAFETY INJECTION 1BwEP-0 WOG 2 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT C (PG 1 OF 2)

MANUAL CS ACTUATION 1 CHECK CS VALVE ALIGNMENT ALIGNMENT::

a. CS pump RWST suction valves - a. Manually open valve(s).

OPEN OPEN::

1CS001A

1CS001B

b. CS pump header isol valves - b. IF associated CS pump is OPEN OPEN:: NOT running, THEN manually open the

1CS007A valve(s).

1CS007B IF associated CS pump is running, THEN perform the following to open the affected valve(s):

1) Place CS pump(s) in PULL OUT.

2) Verify CS pump(s) test switch is in NORMAL.

3) Manually open the valve(s) after the 30 SECOND time delay.

4) Restart CS pump(s).

c. CS eductor spray additive c. Perform the following for valves - OPEN OPEN:: the affected train(s):

1CS019A 1) Place CS pump(s) test

1CS019B switch in TEST.

2) Manually open the valve(s).

3) Place CS pump(s) test switch in NORMAL.

d. CS eductor inlet flow control d. Manually open the valves - OPEN OPEN:: valve(s).

1CS010A

1CS010B Page 41 of 42

REV. 204 REACTOR TRIP OR SAFETY INJECTION 1BwEP-0 WOG 2 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT C (PG 2 OF 2)

MANUAL CS ACTUATION 2 CHECK CS PUMPS RUNNING

a. CS pumps - AT LEAST ONE RUNNING a. Locally start ONE CS pump per 1BwOA ELEC-5, LOCAL EMERGENCY CONTROL OF SAFE SHUTDOWN EQUIPMENT, while continuing with this procedure.

3 RETURN TO MAIN BODY, Step 14c (Page 10)

-END-Page 42 of 42

REV. 204 OPERATOR ACTION

SUMMARY

1BwEP-F:0 WOG 2 FOR 1BwEP-0 TRIP RCPs WHEN : GO TO 1BwEP ES-1.3 IF :

o CC water to RCP lost

RWST level <46%

(affected pumps only)

-OR- AF PUMP SUCTION PRESSURE LOW o CNMT Phase B actuated ALARM (1-3-A7) LIT :

-OR-o BOTH of the following conditions o Crosstie unit CSTs per exist: BwOP CD-2, RAISING CST LEVEL WITH MAKEUP OR BY

RCS pressure <1425 PSIG CROSSTYING

-AND- o Reduce cooldown rate

High head SI flow indicator (1FI-917) >100 GPM or SI AF PUMP SX SUCTION VLVS ARMED pump discharge flow >200 GPM ALARM (1-3-E7) LIT :

CLOSE ASSOCIATED 1AF013 VALVES

Verify operating AF pumps AFTER STEP 15 COMPLETION IF A SX suction valves open:

SG TUBE RUPTURE IS IDENTIFIED o 1AF006A and 1AF017A AND o 1AF006B and 1AF017B AFFECTED SG NARROW RANGE LEVEL

>10% (31% ADVERSE CNMT) :

AF PUMP DAY TANK LEVEL <50%

o Level rising in an

Refill the day tank uncontrolled manner

-OR- IF FLOW IS LOST/ISOLATED TO ANY o Abnormal secondary radiation SG AND NR SG LEVEL LESS THAN OR EQUAL TO 45% FOR GREATER THAN 75 MINUTES, THEN :

Feed affected SG(s) between 60 GPM and 80 GPM for 10 MINUTES prior to restoring desired feedwater flow

REV. 204 CONTINUOUS ACTION

SUMMARY

1BwEP-C:0 WOG 2 FOR 1BwEP-0 14 CHECK IF CS IS REQUIRED (while in this procedure) :

IF CNMT pressure (1PR-937 or 1PI-CS934 thru 1PI-CS937)

HAS RISEN TO GREATER THAN 20 PSIG PSIG,

, THEN:

1) Stop all RCPs

2) Verify Group 6 CS monitor lights - LIT

3) Verify Group 6 Phase B isolation monitor lights - LIT

4) Verify CS eductor suction flow on running pump(s) -

GREATER THAN 15 GPM GPM::

5) Verify CS eductor additive flow on running pump(s) -

GREATER THAN 5 GPM GPM:

19 CHECK RCS TEMPERATURES (while in this procedure) :

o Any RCP running - RCS AVERAGE TEMPERATURE STABLE AT OR TRENDING TO 557°F

-OR-o NO RCPs running - RCS COLD LEG TEMPERATURES STABLE AT OR TRENDING TO 557°F 26 CHECK SG LEVELS :

Maintain total feed flow greater than 500 GPM until narrow range level is greater than 10% in at least one SG.

Control feed flow to maintain narrow range levels -

BETWEEN 10% AND 50%

IF narrow range level in any SG continues to rise in an uncontrolled manner, THEN GO TO 1BwEP-3.

30 CHECK IF RH PUMPS SHOULD BE STOPPED :

IF RCS pressure is less than 325 PSIG PSIG, THEN GO TO 1BwEP-1.

Stop RH pumps and place in standby if:

1) RCS pressure - GREATER THAN 325 PSIG AND

2) RCS pressure - STABLE OR RISING

JOB PERFORMANCE MEASURE TASK CONDITIONS:

1. You are an assist NSO.

2. Unit 1 is in Mode 1.

3. The 1B D/G was manually started, and is currently supplying bus 142 (DG is only source currently feeding bus 142) for a special engineering test. The test is now complete.

4. Breaker 1424 is closed to prevent equipment sequencing onto bus 142 INITIATING CUES:

1. The US has directed you to synchronize SAT 142-2 back to the 1B D/G per BwOP AP-32.

2. Do NOT place the 1B EDG in the Manual Emergency Mode.

Page 1 of 5 SIM-601

TASK TITLE: Synchronize a SAT to a Bus Being Fed by an Emergency Diesel Generator JPM No.: SIM-601 REV: 2013 NRC TPO No.: 4D.AP-03 K&A No.: 062000A4.07 TASK No.: R-AP-013, Sync. SAT to bus fed by D/G K&A IMP: 3.1/3.1 EXAMINEE: RO SRO (Circle One)

EVALUATOR: DATE:

The Examinee: PASSED this JPM. TIME STARTED:

FAILED TIME FINISHED:

JPM TIME: MINUTES CRITICAL ELEMENTS: (*) 5, 6 APPROX COMPLETION TIME: 19 MINUTES CRITICAL TIME: NA EVALUATION METHOD: LOCATION:

X PERFORM IN PLANT SIMULATE X SIMULATOR GENERAL

REFERENCES:

1. BwOP AP-32, Rev. 5, Synchronizing a SAT to a Bus Being Fed by a DG.

MATERIALS:

1. BwOP AP-32, Rev. 5.

TASK STANDARDS:

1. Correctly synchronize SAT 142-2 to a bus being fed by the 1B D/G.

TASK CONDITIONS:

1. You are an assist NSO.

2. Unit 1 is in Mode 1.

3. The 1B D/G was manually started, and is currently supplying bus 142 (DG is only source currently feeding bus 142) for a special engineering test. The test is now complete.

4. Breaker 1424 is closed to prevent equipment sequencing onto bus 142 INITIATING CUES:

1. The US has directed you to synchronize SAT 142-2 back to the 1B D/G per BwOP AP-32.

2. Do NOT place the 1B EDG in the Manual Emergency Mode.

Page 2 of 5 SIM-601

RECORD START TIME Note: Provide a copy of BwOP AP-32 to the examinee.

PERFORMANCE STEP STANDARD Circle applicable

1. Refer to BwOP AP-32. Open BwOP AP-32. SAT UNSAT N/A Comments:

CUE: All Prerequisites, Precautions, Limitations and Actions have been met.

2. Place the 1B D/G in the Manual VERIFY/PLACE the 1B D/G in the SAT UNSAT N/A Emergency Mode. Manual Emergency Mode as Comments:

follows:

Note: This step is optional per o PLACE the Emergency Mode the note prior to step 1 of Control Switch to the MAN the procedure. EMERG position.

3. Verify the 1B D/G is in the Droop VERIFY/PLACE 1B D/G in the SAT UNSAT N/A mode of operation. Droop Mode of operation as Comments:

follows:

VERIFY ACB 2424 Control switch is in PULL to LOCK position.

CUE: When asked, breaker 2424 o TURN the ACB 1424 C/S is in the PULL TO Synchroscope Switch to ON.

LOCK position. o CLOSE ACB 1424 to place the 1B D/G in the Droop Mode.

o TURN the ACB 1424 Synchroscope Switch to OFF.

4. Verify 1B D/G is operating properly. VERIFY 1B D/G is operating SAT UNSAT N/A properly as follows: Comments:

1B D/G frequency is approximately 60 hz.

1B D/G voltage is approximately 4160 volts.

Page 3 of 5 SIM-601

5. Prepare 1B D/G for parallel Prepare 1B D/G for parallel SAT UNSAT N/A operation with SAT 142-2. operations as follows: Comments:

TURN ACB 1422 Synchroscope Switch ON.

USING the 1B D/G voltage adjust control, adjust the RUNNING voltage slightly HIGHER than the INCOMING voltage (0-4 volts).

o VERIFY the same voltage on AB, BC, and CA with the 1B D/G Voltmeter selector switch.

USING the 1B D/G governor adjust control, ADJUST generator speed such that the synchroscope is rotating slowly in the SLOW direction.

6. Parallel the 1B D/G to SAT 142-2. Parallel the 1B D/G to SAT 142-2 SAT UNSAT N/A as follows: Comments:

When the synchroscope is slightly before the 12 oclock position, CLOSE ACB 1422.

o VERIFY the synchroscope has LOCKED IN at the 12 oclock position.

o TURN the synchroscope switch for ACB 1422 to OFF.

7. Restore breaker positions. Restore breaker positions as SAT UNSAT N/A follows: Comments:

OPEN ACB 1424 CUE: When asked, ACB 2424 is

PLACE ACB 2424 in AFTER in after trip. TRIP.

8. Unload 1B D/G per BwOP DG-12. Refer to BwOP DG-12 to unload SAT UNSAT N/A 1B D/G. Comments:

CUE: The US will direct another NSO to unload the 1B D/G.

CUE: THIS COMPLETES THIS JPM.

RECORD STOP TIME COMMENTS:

Page 4 of 5 SIM-601

SIMULATOR SETUP INSTRUCTIONS JPM NO: SIM-601 REQUIRED SIMULATOR MODE(S): Any At Power IC.

MALFUNCTION #S: N/A COMMENTS:

1. Swap to 1B SX pump to put load on Bus 142.

2. Place 1B D/G auto recluse circuit arm switch in SURV TEST.

3. Start 1B D/G and sync to grid.

4. Load 1B D/G until SAT feed amps = 0.

5. Close 1424.

6. Open 1422.

7. Turn on 1422 synchroscope and adjust 1B D/G speed until the synchroscope is rotating in the FAST direction.

8. Adjust 1B D/G voltage so running voltage is LOWER than incoming voltage.

9. Turn off 1422 synchroscope. Leave Synchroscope Key Switch in 1423 but OFF.

10. Ensure the Governor Adjuster and the Voltage Adjuster are not set at values that happen to be exactly what the examinee needs (i.e. the intent is to force the examinee to manipulate the controls).

Page 5 of 5 SIM-601

BwOP AP-32 Revision 5 Continuous Use SYNCHRONIZING A SAT TO A BUS BEING FED BY A DG A. STATEMENT OF APPLICABILITY This procedure outlines the steps necessary to parallel a SAT to a BUS being fed by a Diesel Generator.

B. REFERENCES

1. Station Procedures:

a. BwOP DG-12, Diesel Generator Shutdown.

b. BwOP DG-13, Trouble Shooting Diesel Generators.

2. Station Drawings:

a. 20E-0-4001

b. 20E-0-4000B

3. Station Commitment: 456-103-84-0690051 Step D.5.

C. PREREQUISITES

1. The diesel generator is running and feeding its respective bus.

2. Diesel generator control MODE switch in REMOTE.

3. Notify Security one hour prior to energizing/de-energizing overhead lines that intersect the PA boundary.

1

BwOP AP-32 Revision 5 Continuous Use D. PRECAUTIONS

1. Continuous rating of generator is 5500 Kw.

2. Short term maximum (2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ) rating of generator is 6050 Kw.

3. Minimum continuous steady-state loading on the diesel generator is 3000 Kw.

4. When a Diesel Generator is in the Emergency MODE and paralleled to the grid DO NOT return the Emergency MODE Speed Voltage C/S to Auto if it is currently in the Manual Emergency position. This will prevent Isochronous operation while in parallel.

5. Operate only ONE Emergency Diesel Generator in parallel with offsite power at any one time. This will prevent damage to more than one Diesel Generator if a fault condition develops on the grid.

E. LIMITATIONS AND ACTIONS

1. Adhere to the following Generator load limits when DG is in parallel with offsite power:

a. Continuous rating - 5500 KW and 1000 KVAR.

b. 2000 Hour Rating - 5935 KW and 1000 KVAR.

c. Two Hour Rating - 6050 KW and 1000 KVAR.

2. Refer to BwOP DG-13 if diesel generator trip/trouble occurs.

2

BwOP AP-32 Revision 5 Continuous Use F. MAIN BODY CAUTION if the Diesel Generator started due to a loss of off site power, the Diesel Generator Output Breaker may trip if the Mode Control Switch is placed in "MANUAL TEST MODE".

NOTE If the diesel generator was started manually, Step 1 is not necessary. The MODE control switch may be left in auto.

NOTE Do not close in SAT Feed Breaker if a Degraded Voltage Condition

(<3990 VAC) exists on the off site power source (switchyard).

1. VERIFY/PLACE the Diesel Generator in "Manual Emerg MODE" to enable speed and voltage control.

2. If synchronizing the SAT to the UNIT 1 ESF Bus, perform the following:

a. VERIFY/PLACE ACB 2414/2424 CONTROL Switch in the PULL TO LOCK position.

b. TURN the ACB 1414/1424 Synchroscope Switch to ON.

NOTE The following step will cause the DG to shift to DROOP mode. The engine may run slower as noted by a drop in RPM and Frequency.

c. CLOSE ACB 1414/1424 to place the Diesel Generator in the DROOP MODE.

d. TURN the ACB 1414/1424 Synchroscope Switch to OFF.

3

BwOP AP-32 Revision 5 Continuous Use F. 3. If synchronizing the SAT to the UNIT 2 ESF Bus perform the following:

a. VERIFY/PLACE ACB 1414/1424 CONTROL Switch in the PULL TO LOCK position.

b. TURN the ACB 2414/2424 Synchroscope Switch to ON.

NOTE The following step will cause the DG to shift to DROOP mode. The engine may run slower as noted by a drop in RPM and Frequency.

c. CLOSE ACB 2414/2424 to place the Diesel Generator in the DROOP MODE.

d. TURN the ACB 2414/2424 Synchroscope Switch to OFF.

4. VERIFY/ADJUST the diesel generator frequency to approximately 60 hz and voltage to approximately 4160 volts.

5. TURN the SAT Feed Bkr Synchroscope Switch to "ON".

6. USING the diesel generator voltage adjust control, adjust the "RUNNING" voltage slightly HIGHER than the "INCOMING" voltage (0-4 volts).

7. VERIFY the same voltage on "AB", "BC", and "CA" with Diesel Gen Voltmeter selector switch.

8. USING the diesel generator governor adjust control, ADJUST generator speed such that the synchroscope is rotating slowly in the SLOW direction.

9. When the synchroscope is slightly before the "12 o'clock" position, CLOSE the SAT Feed Breaker.

10. VERIFY the synchroscope has LOCKED IN at the "12 o'clock" position.

11. TURN the SAT Feed Breaker Synchroscope Switch to "OFF".

12. OPEN the ACB that was closed in step F.2.c./3.c.

13. VERIFY/PLACE ACB CONTROL Switches for all breakers in steps F.2.a. and F.3.a. to the AFTER TRIP position.

14. UNLOAD the diesel generator per BwOP DG-12.

(Final) 4

JOB PERFORMANCE MEASURE TASK CONDITIONS:

1. You are an extra NSO.

2. Both units are at full power with all systems normal for current plant conditions.

3. System Engineering is preparing to perform the incore detector operability surveillance, and needs the Incore Seal Table Rad Monitor audible alarm disabled.

INITIATING CUES:

The US has directed you to disable the audible alarm of the Incore Seal Table Rad Monitor for Unit 1 per BwOP IC-9, step F.1.a.

Page 1 of 4 SIM-707

TASK TITLE: Operate a Rad Monitor (Disable Incore Seal Table Monitor Audible Alarm)

JPM No.: SIM-707 REV: 2013 NRC TPO No.: 4C.AR-03 K&A No.: 073000A4.02 TASK No.: R-AR-001, Operate the RM-11 Rad K&A IMP: 3.7/3.7 Monitoring System EXAMINEE: RO SRO (Circle One)

EVALUATOR: DATE:

The Examinee: PASSED this JPM. TIME STARTED:

FAILED TIME FINISHED:

JPM TIME: MINUTES CRITICAL ELEMENTS: (*) 2, 3 APPROX COMPLETION TIME: 9 MINUTES CRITICAL TIME: NA EVALUATION METHOD: LOCATION:

X PERFORM IN PLANT SIMULATE X SIMULATOR GENERAL

REFERENCES:

1. BwOP IC-9, Rev. 21, Movable Incore Detector Operation

2. TRM 3.3.a. Movable Incore Detectors MATERIALS:

1. BwOP IC-9, Rev. 21 TASK STANDARDS:

1. Disable the audible alarm of the Incore Seal Table Radiation Monitor.

TASK CONDITIONS:

1. You are an extra NSO.

2. Both units are at full power with all systems normal for current plant conditions.

3. System Engineering is preparing to perform the incore detector operability surveillance and needs the Incore Seal Table Rad Monitor audible alarm disabled.

INITIATING CUES:

1. The US has directed you to disable the audible alarm of the Incore Seal Table Rad Monitor for Unit 1 per BwOP IC-9, step F.1.a.

Page 2 of 4 SIM-707

RECORD START TIME PERFORMANCE STEP STANDARD Circle applicable

1. Refer to BwOP IC-9 Locate and open the following: SAT UNSAT N/A Comments:

CUE: After the student locates

BwOP IC-9, Step F.1.a correct procedure, provide a copy.

All Prerequisites, Precautions, Limitations and Actions have been met.

2. Select 1AR014J skid on RM-11. Select 1AR014J skid at the RM- SAT UNSAT N/A 11 keyboard as follows: Comments:

PLACE the RM-11 in Supervisor mode.

Channel 4303 is entered.

SELECT grid 4 on the RM-1AR014J has white cursor 11.

surrounding it.

DEPRESS, in order, 4, 3, 0, 3.

DEPRESS SEL.

3. Disable the audible alarm for the Disable the audible alarm for SAT UNSAT N/A Incore Seal Table Rad Monitor. the Incore Seal Table Rad Comments:

Monitor as follows:

Channel Item button

Push the CHANNEL ITEM pushed. button.

16 inserted, Select

On the keypad, TYPE 16 pushbutton pushed. and push the SELECT pushbutton.

CUE: As US and Unit NSOs, o Notify US and both Unit NSOs acknowledge notification of of expected alarm on the RM-expected RM-11 alarm. 11 due to next step.

0 inserted, Enter button

On the keypad, TYPE 0 and pushed. PUSH the ENTER pushbutton.

RM-11 in Normal mode. o PLACE the RM-11 to NORMAL mode.

CUE: As US/NSO acknowledge o Inform US/NSO audible Alarm report of audible alarm for Incore Seal Table Rad disabled. Monitor is disabled.

CUE: THIS COMPLETES THIS JPM.

RECORD STOP TIME COMMENTS:

Page 3 of 4 SIM-707

SIMULATOR SETUP INSTRUCTIONS JPM NO: SIM-707 REQUIRED SIMULATOR MODE (S): At power with RM-11 operating.

MALFUNCTION #S: N/A COMMENTS:

1. Ensure Seal Table Rad Monitor (Grid 4, 4303), is enabled by selecting Channel Item 16 and entering a 1.

2. Place RM-11 on Grid 1.

3. Ensure RM-11 NOT in supervisory mode.

Page 4 of 4 SIM-707

PROCEDURE BwOP IC-9 UNIT NO. REVISION NO.

BRAIDWOOD STATION 21 PROCEDURE TITLE:

MOVABLE INCORE DETECTOR OPERATION Rev Summary IR# / EC# (if applicable) 18 This procedure is being revised to reflect the EC 375574 installation of the Replacement Plant Process ATI 1172997-11 Computer on Unit 1.

19 Inserted table on page 11 that was inadvertently PCRA 1364041-01 removed in previous revision.

20 Add defeat/restoration steps for Loose Parts PCRA 1371608-02 1VE-LM003 and 1VE-LM004 Alarms for Flux Maps. PCRA 1408795-02 Added step to Attachment A step G to return the DRIVE SELECTOR switch back to the ALL position, if desired.

Reformat Attachment B to clarify actions to clear a blocked thimble.

21 Changes steps F.3.g, F.3.i and Figure 1 per PCRA 1435306-03 EC 391242 due to thimble blockage at core positions EC 391242 L10 and R11.

BwOP IC-9 Revision 21 Continuous Use MOVABLE INCORE DETECTOR OPERATION A. STATEMENT OF APPLICABILITY The purpose of this procedure is to perform an operability check of the Incore Detector (IC) System pursuant to TRM 3.3.a. Also, this procedure describes the steps necessary to move the incore detectors to map the core and place back in storage.

Testing will be performed at the interval of at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , applicable when the IC System is used for recalibration of the excore neutron flux detector system, monitoring the Quadrant Power Tilt Ratio (in accordance with Tech Spec SR 3.2.4.2), or measurement of FNH, FCQ (Z), W(Z), FWQ (Z), and calibration of the Power Distribution System (PDMS).

B. REFERENCES

1. Tech Specs:

a. TRM 3.3.a, Movable Incore Detectors.

b. 3.2.4, Quadrant Power Tilt Ratio.

c. TRM 3.3.h, Power Distribution Monitoring System.

2. Station Drawings (Specification 2702, S.O. 360):

a. 6062D83, Sheet 4.

b. 43118, Sheets 2, 3 and 5, Unit 1.

c. 43119, Sheets 2, 3 and 5, Unit 2.

d. 27650, Sheets 3 and 5.

e. 27641, Sheet 9.

f. 43118, Sheet 1-6.

3. Vendor Manual: Technical Manual for Incore Instrumentation Byron/Braidwood Units 1 & 2 (2702-360) Book 1 & 2.

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BwOP IC-9 Revision 21 Continuous Use B. 4. Station Procedures:

a. BwOP IC-E1/E2, Electrical Lineup.

b. BwOP IC-M1/M2, Mechanical Lineup.

c. NF-AP-576, Determination of Rod Position Using Movable Incore Detector System (MIDS).

C. PREREQUISITES

1. Notify the Shift Manager that this surveillance involves movements of the incore movable detectors and as a result, no personnel should be allowed in containment until this procedure is complete unless there is an incore operability concern.

2. The main power circuit breakers should be closed and power turned on to each detector readout panel for at least 30 minutes before using the flux mapping system. Move the detectors to the bottom of the core to warm up, if the core is to be flux mapped. (Data taken.)

3. BwOP IC-E1/E2 applicable portions completed.

4. BwOP IC-M1/M2 completed.

5. There are sufficient movable detectors, detector drives and strip chart recorders, or disc space (paperless recorder) to collect the required data via the process computer.

6. Compact Flash Cards 2-4Gb or larger will be required for data storage from each of the recorders that will be used. (Only required if actually taking data.)

2

BwOP IC-9 Revision 21 Continuous Use D. PRECAUTIONS

1. Personnel may be allowed in containment while the detectors are in a fully withdrawn position to address an operability problem or concern that exists with an Incore Detector(s). (Refer to BwAP 1450 -1 Access to Containment requirements with incore capable of moving.)

2. Irradiated detectors, in the withdrawn or parked position, may pose a radiation hazard. Personnel required to be working around the Incore Detector System should follow the specific requirements of the applicable RWP and Radiation Protection Dept.

3. Reactor Coolant System controlling parameters (i.e. temperature, xenon distribution, and boron concentration) as well as power level should be constant during the core map or as directed by a Qualified Nuclear Engineer (QNE) or designee.

4. Obtain the permission of the Shift Manager or designee prior to operating the IC system.

5. Care must be taken not to drive the detectors into the top of the core, withdraw the detectors past the safety limit switch or change the position of the Operation Selector Switch while the detector is inserted beyond the withdrawal limit switch.

6. Watch for slippage of the detector drive clutch. This can be observed by detector position lights stopping while the detector drive is still in operation.

7. Operation SELECTOR and PATH SELECTOR switch positions are not to be changed unless the detector is at its withdrawal limit. If the withdrawn limit switch is disabled for an inoperable detector, the PATH SELECTOR switch may be changed for emergency passes.

8. Inoperable detector drives may be maintained in the OFF position. Steps associated with operation of inoperable drives may be marked N/A.

9. Inoperable detector path may be placed in the OFF position during the particular pass. Steps associated with operation of inoperable paths may be marked N/A.

10. Do NOT attempt to unblock a path that was previously identified as being blocked without Operations Management approval. Attempting to unblock a path can lead to the loss of detector function or other system capabilities due to unavailable 10-paths. Authorized attempts should consider what affect losing a detector and associated equipment have on the system, as well as required equipment per TLCO 3.3.a. A list of previously identified blocked paths can be found in the Incore Limits Operator Aid.

3

BwOP IC-9 Revision 21 Continuous Use D. 11. When the START pushbutton on the electronic recorders is pushed, the recorder will begin recording at low speed (10 hour1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months s/division). Once the trace is triggered by the external contact to the recorder, it will shift to high speed (25 millisecond/division). The recorder will continue recording, generating a new file every 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months . The recorder may be stopped at any time by pressing the STOP pushbutton. Stopping the recorder will transfer the data file to the recorders internal memory and the inserted compact flash card (if applicable).

E. LIMITATIONS AND ACTIONS

1. Definitions of terms for the Incore movable detectors:

Stored: Shielded storage location in the wall of the Incore Seal Table Room, or the bottom of the Reactor Vessel.

Withdrawn: Located at the withdrawal limit switch at the Incore Detector Drive(s).

Parked: Located in a stationary position anywhere between the Incore Detector Drive motors and the Reactor Core.

2. Manual operation of the detector drives may be utilized provided that the detectors are not withdrawn past the drive respective zero as indicated on the associated DETECTOR POSITION indications.

3. Flux mapping operations should only be performed while reactor is at a nearly constant power level. Neutron flux variations should be kept to less than 5% per hour/or as directed by a QNE.

4. A work group may be in containment provided all Containment Access Procedure steps for MIDS operation are adhered to/enforced.

5. Steps of this procedure may be repeated as necessary.

4

BwOP IC-9 Revision 21 Continuous Use F. MAIN BODY NOTE F.1. will align the radiation monitor, set the detectors to bottom of core for heatup, plant computer and recorders.

F.2. will perform Incore Detector Operability.

F.3. will perform a Full Core Flux Map.

F.4. will restore the system.

Attachment A directs normal incore operation.

Attachment B directs incore troubleshooting.

Attachment C directs emergency/common passes.

Attachment D removes/restores a 5-path from rotating.

NOTE For troubleshooting the IC system, use any applicable steps and data sheets as directed by the Unit Supervisor or Reactor Engineering.

NOTE Steps may be N/A by the Unit Supervisor or Reactor Engineer as conditions warrant.

NOTE Disabling the Audible Alarm Capability of the General Atomics RM-11 in the Control Room may be necessary to reduce the possibility of the RM-11 overloading the Radiation Monitor System Computer during flux mapping. This is due to frequent alarms from

_RE-AR003, Incore Seal Table Room.

NOTE If a zero is inserted into channel item 16, the channel will be inoperable. If a one is inserted into channel item 16, the channel will be operable.

5

BwOP IC-9 Revision 21 Continuous Use F. 1. ALIGN the rad monitor, plant computer, loose parts, and recorders per the following steps:

a. Defeat Alarms

1) VERIFY/ PERFORM the following to remove the audible alarm capability of the detector 4AS303/5AS303 (U1/U2 incore seal table detector) on the General Atomics RM-11 in the main control room.

a) PLACE the RM-11 in SUPERVISOR Mode.

b) SELECT grid four on the RM-11.

c) On the keypad, TYPE 4303/5303 and PUSH the SELECT pushbutton (this will cue up the U1/U2 incore seal table detector).

d) PUSH the CHANNEL ITEM pushbutton on the RM-11.

e) On the keypad, TYPE 16 and PUSH the SELECT pushbutton.

f) NOTIFY Unit NSO, the opposite Unit NSO, and Unit Supervisor of expected alarm on the RM-11 due to the next step.

g) On the keypad, TYPE 0 and PUSH the ENTER pushbutton.

h) PLACE the RM-11 to NORMAL mode.

NOTE Ensure proper coverage per TRM 3.3.d prior to defeating alarms in the following step.

2) VERIFY/PERFORM the following to disable Loose Parts Alarms:

a) ENTER TRM LCO 3.3.d for the 1VE-LM003 and 1VE-LM004.

b) At 1PA44J, PLACE the ALM ENABLE/DEFEAT Switch to ALM DEFEAT for:

1VE-LM003 1VE-LM004 6

BwOP IC-9 Revision 21 Continuous Use NOTE Attachment A provides guidance on how to operate the Incore Drive System. Refer to these steps to perform desired movement of the Incore Drive System.

NOTE If a problem occurs during Incore operations that require troubleshooting, refer to Attachment B of this procedure.

NOTE If an individual Drive Selector Switch is in the OFF position, that drive will not operate.

NOTE If a detector cannot be withdrawn from storage, use ATTACHMENT D to allow access to the appropriate Drive's 10 path.

F. 1. b. VERIFY/WITHDRAW the operable incore detectors per Attachment A to allow for warm-up of detector.

c. PERFORM ATTACHMENT D for any operable detectors that cannot be withdrawn (N/A if all withdrew).

7

BwOP IC-9 Revision 21 Continuous Use F. 1. d. VERIFY/ESTABLISH the following switch configurations on the DETECTOR CONTROL panels for each operable detector. (This step may be N/A if Flux map data is not required.)

1) PLACE the OPERATION SELECTOR switches in NORMAL for all known operable detectors.

2) PLACE the OPERATION SELECTOR switches in OFF for all known inoperable detectors.

3) PLACE PATH SELECTOR switch to locations of highest relative power (Desired Paths). If the thimble listed is not available, a different thimble that is as close to the center of the core as possible may be used (Make note in table below).

PATH SELECTOR SWITCHES Alternative Path Detector Desired Path (N/A if not used)

A Path 5 B Path 5 C Path 1 D Path 1 E Path 8 F Path 1

e. INSERT all operable detectors to the bottom of the core per Attachment A to start the 30 minute warm-up. (This step may be N/A if flux map data is not required.)

Warm-Up Start Time 8

BwOP IC-9 Revision 21 Continuous Use F. 1. f. INITIALIZE the Flux Map Storage on the process computer, zeroing out all the previous passes, by performing the following: (This step may be N/A if flux map data is not required.)

1) On the PPC Main Menu screen SELECT Operator Demandable.

2) On the Operator Demandable screen SELECT Moveable Detectors (Flux Mapping).

3) On the Flux Mapping Traverse screen SELECT Create New Map.

4) ENTER the following data on the Flux Mapping new Map Data window (Data may be obtained from Reactor Engineering):

Description Map number Reactor Power (%)

Burnup (MWD/MTU)

5) SELECT Create.

NOTE Subsections of this step may be re-performed as necessary to properly setup the paperless recorders.

g. IF required by Reactor Engineering, PERFORM the following to VERIFY the paperless recorders are setup to record flux map data: (Parts of this step may be N/A if flux map data is not required.)

1) VERIFY that a 2-4Gb Compact Flash Card is in the recorders being used.

2) PRESS the green START button on the recorder to begin basic recording. (This starts the recording in slow speed at a rate of 10 hour1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months s/division.)

3) VERIFY light located on the electronic recorders control panel is green.

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BwOP IC-9 Revision 21 Continuous Use F. 2. PERFORM Incore Detector Operability.

NOTE Attachment A provides guidance on how to operate the Incore Drive System. Refer to these steps to perform desired movement of the Incore Drive System.

NOTE If a problem occurs during Incore operations that require troubleshooting, refer to Attachment B of this procedure.

NOTE If section F.2 has been performed within the past 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and the plant has remained stable, F.2.a. through F.2.e may be marked N/A.

a. VERIFY/ESTABLISH the following switch configurations on the COMMON CONTROLS panel.

1) COMPUTER switch in OFF.

2) MAIN POWER switch in ON.

3) AUTO-MANUAL switch in AUTO.

4) SPEED switch in LOW.

5) DRIVE SELECTOR switch in ALL.

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BwOP IC-9 Revision 21 Continuous Use F. 2. b. VERIFY/ESTABLISH the following configurations on the DETECTOR READOUT panels for each operable detector. (This step may be N/A if flux map data is not required).

1) PLACE EXTERNAL RECORD switch in REC.

2) VERIFY/ADJUST RECORDER POTENTIOMETER Readings to values as listed below or as directed by the System Engineer.

Unit 1 A - 2.01 B - 2.01 C - 1.75 D - 1.99 E - 1.98 F - 1.45 Unit 2 A - 2.02 B - 1.51 C - 1.98 D - 2.00 E - 2.02 F - 2.02

3) RECORD RECORDER POTENTIOMETER settings in the table below if they differ from the above. (N/A if above settings are used)

A- B- C- D- E- F-

c. VERIFY 30 minute warm up complete.

(Warm up time complete) 30 minutes + time from Step F.1.e.

(This step may be N/A if Flux map data is not required.)

d. PERFORM a Detector Operating Voltage Determination/Check with the following steps: (This step may be N/A if Flux map data is not required.)

1) DEPRESS the SCAN pushbutton on the Common Controls Panel to scan all operable detectors to the top of the core.

2) OBSERVE/DETERMINE the location of the highest Relative Neutron Flux.

3) PLACE AUTO-MANUAL switch on the COMMON CONTROLS panel to MANUAL.

4) PLACE recorders in service.

a) INSERT Compact Flash Card and VERIFY boot program is complete for the paperless recorders (N/A if not used or previously performed per step F.1.g.).

b) VERIFY light located on the electronic recorders panel is green.

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BwOP IC-9 Revision 21 Continuous Use F. 2. d. 5) PLACE the INSERT-OFF-WITHDRAW switch on the COMMON CONTROLS panel to WITHDRAW to drive the operable detectors into the core until the detectors reach their approximate maximum flux value.

6) ADJUST the RANGE switch as necessary to ensure the strip chart recorders remain on scale.

7) RECORD the As Found voltage setting for each operable detector.

As Found Voltages Detector A V Detector D V Detector B V Detector E V Detector C V Detector F V

8) SET each operable detector's voltage to approximately 0 volts to determine the recorders pen moves.

9) ADJUST each operable voltage to 80 volts.

10) RECORD % full scale of recorders on Table 1.

11) INCREASE each operable detector's voltage by approximately 10 volts.

12) RECORD % full scale of recorders on Table 1.

13) REPEAT previous two steps until each operable detector's voltage is approximately 150 volts. FILL in the data on Table 1 for each 10-volt increment.

Table 1 Moveable Incore Detectors Operability Check A % Full B % Full C % Full D % Full E % Full F % Full Detector Scale of Scale of Scale of Scale of Scale of Scale of Voltage Recorder Recorder Recorder Recorder Recorder Recorder 80 90 100 110 120 130 140 150 12

BwOP IC-9 Revision 21 Continuous Use F. 2. d. 14) From the data recorded in step above, SELECT a range of approximately 20 volts where the detector output varies the least.

Detector A _________ V to _________ V Detector B _________ V to _________ V Detector C _________ V to _________ V Detector D _________ V to _________ V Detector E _________ V to _________ V Detector F _________ V to _________ V

15) RECORD the midpoint of this range and have an Independent Verification of the results.

Detector Midpoint IV A __________ V B __________ V C __________ V D __________ V E __________ V F __________ V

16) ADJUST Operating Voltages for each operable detector to the midpoint value specified in the previous step.

Detector Adjusted Midpoint Initial/Date A __________ V ___________/_______

B __________ V ___________/_______

C __________ V ___________/_______

D __________ V ___________/_______

E __________ V ___________/_______

F __________ V ___________/_______

17) RECORD the time and date the Detector Operating Voltage Determination/Check was completed.

Time: ___________ Date: ___________

e. On each individual control ROTATE the current selector switch through each current position. (This step may be N/A if Flux map data is not required.)

13

BwOP IC-9 Revision 21 Continuous Use NOTE Step F.3. will perform a full core flux map. If it is desired to perform a partial, quarter or a QPTR flux map then transition to the applicable T-sheet at step F.3.d. of this procedure.

BwOP IC-9T3 directs a partial flux map.

BwOP IC-9T4 directs a quarter flux map.

BwOP IC-9T5 directs a QPTR flux map.

F. 3. PERFORM a FULL CORE Flux Map by performing the following:

a. VERIFY/PERFORM the following at the COMMON CONTROLS panel:

1) AUTO-MANUAL switch in AUTO.

2) PUSH WITHDRAW pushbutton to withdraw all operable detectors to the withdrawn position.

3) COMPUTER Switch in ON.

4) VERIFY light located on the electronic recorders panel is green.

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BwOP IC-9 Revision 21 Continuous Use NOTE BwOP IC-9 Attachment A is a reference step on how to operate the Incore Drive System under normal conditions. Refer to the appropriate substeps to perform desired movement of the Incore Drive System.

F. 3. b. RECORD the following information prior to the Flux Map:

(This step may be N/A if Flux map data is not required.)

SBA ______ SBB ______ SBC ______ SBD ______ SBE ______

CBA ______ CBB ______ CBC ______ CBD ______

Unit: Cycle:

Time: Date:

Power: % Flux map ID #:

c. Reason for taking map or using the system:

Monthly Surveillance.

Incore/Excore Calibration.

PDMS Calibration.

System Checkout.

Troubleshooting.

Other, specify:

d. VERIFY no personnel in Containment, if applicable

e. If performing a full core flux map continue with the next step, otherwise transition to the applicable T-sheet:

BwOP IC-9T3 directs a partial flux map.

BwOP IC-9T4 directs a quarter flux map.

BwOP IC-9T5 directs a QPTR flux map.

15

BwOP IC-9 Revision 21 Continuous Use F. 3. f. PLACE a check () when complete for Pass 1.

ALIGN Operations Selector Switch and Path Detector Switch Positions as follows:

A B C D E F Calibrate Normal Normal Normal Normal Normal

--(J-10) 1 (D-10) 1 (G-9) 1 (J-7) 1 (K-12) 1 (D-8)

PATH Switch Position Aligned per above.

VERIFY Operations Selector Switch in position required above.

VERIFY no personnel in Containment. (This step may be N/A if a Work Group is in Containment.)

DEPRESS INSERT Pushbutton.

DEPRESS SCAN Pushbutton.

VERIFY all Strip Chart Recorders remained on Scale.

DEPRESS RECORD Pushbutton.

VERIFY all Strip Chart Recorders remained on scale.

VERIFY the data was received by the process computer.

(Pass number increments by 1. Mapped core locations turn green.)

(N/A if flux map data not required.)

ENTER the time of the pass in the adjacent box.

DEPRESS WITHDRAW Pushbutton.

COMPLETE NIS Power Range Channel Data Table if reactor power 5% or COMPLETE NIS Intermediate Range Data Table if reactor power <5% (N/A if not applicable).

16

BwOP IC-9 Revision 21 Continuous Use F. 3 f. RECORD NIS POWER RANGE CHANNEL DATA (N/A if < 5%

power or deemed not necessary by RE):

Detector Currents (Ma) and Percent Power Pass Channel 41 Channel 42 Channel 43 Channel 44

//////// Top Bot Q Top Bot Q Top Bot Q Top Bot Q 1

Delta Flux (%) (MCB Meters and Computer) 10 Minute Pass Calorimetric

_NI-41C _NI-42C _NI-43C _NI-44C

Power (%)

1

//////// CH 41 CH 42 CH 43 CH 44 ///////////////////

1 ///////////////////

RECORD NIS INTERMEDIATE RANGE DATA TABLE (N/A if > 5%

power):

Detector Currents (Amps)

Reactivity Computer Pico Pass # Channel 35 Channel 36 Ammeter Reading (If applicable) 1 17

BwOP IC-9 Revision 21 Continuous Use F. 3. g. PLACE a check () when complete for Pass 2.

ALIGN Operations Selector Switch and Path Detector Switch Positions as follows:

A B C D E F Normal Calibrate Normal Normal Normal Normal 2 (R-11) 1 (H-15) --(J-10) 2 (R-8) 2 (F-14) 2 (H-2)

OFF * (U2)

Capped per EC 391242 (A2R16)

PATH Switch Position Aligned per above.

VERIFY Operations Selector Switch in position required above.

VERIFY no personnel in Containment. (This step may be N/A if a Work Group is in Containment.)

DEPRESS INSERT Pushbutton.

DEPRESS SCAN Pushbutton.

VERIFY all Strip Chart Recorders remained on Scale.

DEPRESS RECORD Pushbutton.

VERIFY all Strip Chart Recorders remained on scale.

VERIFY the data was received by the process computer.

(Pass number increments by 1. Mapped core locations turn green.)

(N/A if flux map data not required.)

ENTER the time of the pass in the adjacent box.

DEPRESS WITHDRAW Pushbutton.

COMPLETE NIS Intermediate Range Data Table if reactor power

<5% (N/A if not applicable).

RECORD NIS INTERMEDIATE RANGE DATA TABLE (N/A if > 5%

power):

Detector Currents (Amps)

Reactivity Computer Pico Pass # Channel 35 Channel 36 Ammeter Reading (If applicable) 2 18

BwOP IC-9 Revision 21 Continuous Use F. 3. h. PLACE a check () when complete for Pass 3.

ALIGN Operations Selector Switch and Path Detector Switch Positions as follows:

A B C D E F Normal Normal Calibrate Normal Normal Normal 2 (K-2) 2 (A-11) --(J-10) 3 (B-8) 3 (H-4) 3 (B-3)

PATH Switch Position Aligned per above.

VERIFY Operations Selector Switch in position required above.

VERIFY no personnel in Containment. (This step may be N/A if a Work Group is in Containment.)

DEPRESS INSERT Pushbutton.

DEPRESS SCAN Pushbutton.

VERIFY all Strip Chart Recorders remained on Scale.

DEPRESS RECORD Pushbutton.

VERIFY all Strip Chart Recorders remained on scale.

VERIFY the data was received by the process computer.

(Pass number increments by 1. Mapped core locations turn green.)

(N/A if flux map data not required.)

ENTER the time of the pass in the adjacent box.

DEPRESS WITHDRAW Pushbutton.

COMPLETE NIS Intermediate Range Data Table if reactor power <5%

(N/A if not applicable).

RECORD NIS INTERMEDIATE RANGE DATA TABLE (N/A if > 5%

power):

Detector Currents (Amps)

Reactivity Computer Pico Pass # Channel 35 Channel 36 Ammeter Reading (If applicable) 3 19

BwOP IC-9 Revision 21 Continuous Use F. 3. i. PLACE a check () when complete for Pass 4.

ALIGN Operations Selector Switch and Path Detector Switch Positions as follows:

A B C D E F Normal Normal Normal Calibrate Normal Normal 3 (L-10) (U1) 3 (K-6) 3 (C-5) --(J-10) 4 (M-7) 4 (L-15)

OFF * (U2)

Capped per EC 391242 (A2R16)

PATH Switch Position Aligned per above.

VERIFY Operations Selector Switch in position required above.

VERIFY no personnel in Containment. (This step may be N/A if a Work Group is in Containment.)

DEPRESS INSERT Pushbutton.

DEPRESS SCAN Pushbutton.

VERIFY all Strip Chart Recorders remained on Scale.

DEPRESS RECORD Pushbutton.

VERIFY all Strip Chart Recorders remained on scale.

VERIFY the data was received by the process computer.

(Pass number increments by 1. Mapped core locations turn green.)

(N/A if flux map data not required.)

ENTER the time of the pass in the adjacent box.

DEPRESS WITHDRAW Pushbutton.

COMPLETE NIS Intermediate Range Data Table if reactor power <5%

(N/A if not applicable).

RECORD NIS INTERMEDIATE RANGE DATA TABLE (N/A if > 5%

power):

Detector Currents (Amps)

Reactivity Computer Pico Pass # Channel 35 Channel 36 Ammeter Reading (If applicable) 4 20

BwOP IC-9 Revision 21 Continuous Use F. 3. j. PLACE a check () when complete for Pass 5.

ALIGN Operations Selector Switch and Path Detector Switch Positions as follows:

A B C D E F Normal Normal Normal Normal Calibrate Normal 4 (P-4) 4 (F-1) 4 (B-13) 4 (L-13) --(J-10) 5 (N-6)

PATH Switch Position Aligned per above.

VERIFY Operations Selector Switch in position required above.

VERIFY no personnel in Containment. (This step may be N/A if a Work Group is in Containment.)

DEPRESS INSERT Pushbutton.

DEPRESS SCAN Pushbutton.

VERIFY all Strip Chart Recorders remained on Scale.

DEPRESS RECORD Pushbutton.

VERIFY all Strip Chart Recorders remained on scale.

VERIFY the data was received by the process computer.

(Pass number increments by 1. Mapped core locations turn green.)

(N/A if flux map data not required.)

ENTER the time of the pass in the adjacent box.

DEPRESS WITHDRAW Pushbutton.

COMPLETE NIS Intermediate Range Data Table if reactor power <5%

(N/A if not applicable).

RECORD NIS INTERMEDIATE RANGE DATA TABLE (N/A if > 5%

power):

Detector Currents (Amps)

Reactivity Computer Pico Pass # Channel 35 Channel 36 Ammeter Reading (If applicable) 5 21

BwOP IC-9 Revision 21 Continuous Use F. 3. k. PLACE a check () when complete for Pass 6.

ALIGN Operations Selector Switch and Path Detector Switch Positions as follows:

A B C D E F Normal Normal Normal Normal Normal Calibrate 5 (H-6) 5 (F-7) 5 (H-11) 5 (N-4) 5 (N-13) -- (J-10)

PATH Switch Position Aligned per above.

VERIFY Operations Selector Switch in position required above.

VERIFY no personnel in Containment. (This step may be N/A if a Work Group is in Containment.)

DEPRESS INSERT Pushbutton.

DEPRESS SCAN Pushbutton.

VERIFY all Strip Chart Recorders remained on Scale.

DEPRESS RECORD Pushbutton.

VERIFY all Strip Chart Recorders remained on scale.

VERIFY the data was received by the process computer.

(Pass number increments by 1. Mapped core locations turn green.)

(N/A if flux map data not required.)

ENTER the time of the pass in the adjacent box.

DEPRESS WITHDRAW Pushbutton.

COMPLETE NIS Power Range Channel Data Table if reactor power 5% or COMPLETE NIS Intermediate Range Data Table if reactor power <5%. (N/A if not applicable.)

22

BwOP IC-9 Revision 21 Continuous Use F. 3. k. RECORD NIS POWER RANGE CHANNEL DATA (N/A if < 5%

power or deemed not necessary by RE):

Detector Currents (Ma) and Percent Power Pass Channel 41 Channel 42 Channel 43 Channel 44

//////// Top Bot Q Top Bot Q Top Bot Q Top Bot Q 6

Delta Flux (%) (MCB Meters and Computer) 10 Minute Pass Calorimetric

_NI-41C _NI-42C _NI-43C _NI-44C

Power (%)

6

//////// CH 41 CH 42 CH 43 CH 44 ///////////////////

6 ///////////////////

RECORD NIS INTERMEDIATE RANGE DATA TABLE (N/A if > 5%

power):

Detector Currents (Amps)

Reactivity Computer Pico Pass # Channel 35 Channel 36 Ammeter Reading (If applicable) 6 23

BwOP IC-9 Revision 21 Continuous Use F. 3. l. PLACE a check () when complete for Pass 7.

ALIGN Operations Selector Switch and Path Detector Switch Positions as follows:

A B C D E F Calibrate Normal Normal Normal Normal Normal

--(J-10) 6 (R-6) 6 (J-14) 6 (D-14) 6 (J-8) 6 (G-12)

PATH Switch Position Aligned per above.

VERIFY Operations Selector Switch in position required above.

VERIFY no personnel in Containment. (This step may be N/A if a Work Group is in Containment.)

DEPRESS INSERT Pushbutton.

DEPRESS SCAN Pushbutton.

VERIFY all Strip Chart Recorders remained on Scale.

DEPRESS RECORD Pushbutton.

VERIFY all Strip Chart Recorders remained on scale.

VERIFY the data was received by the process computer.

(Pass number increments by 1. Mapped core locations turn green.)

(N/A if flux map data not required.)

ENTER the time of the pass in the adjacent box.

DEPRESS WITHDRAW Pushbutton.

COMPLETE NIS Intermediate Range Data Table if reactor power <5%

(N/A if not applicable).

RECORD NIS INTERMEDIATE RANGE DATA TABLE (N/A if > 5%

power):

Detector Currents (Amps)

Reactivity Computer Pico Pass # Channel 35 Channel 36 Ammeter Reading (If applicable) 7 24

BwOP IC-9 Revision 21 Continuous Use F. 3. m. PLACE a check () when complete for Pass 8.

ALIGN Operations Selector Switch and Path Detector Switch Positions as follows:

A B C D E F Normal Calibrate Normal Normal Normal Normal 6 (D-12) --(J-10) 7 (J-1) 7 (G-5) 7 (C-7) 7 (A-9)

PATH Switch Position Aligned per above.

VERIFY Operations Selector Switch in position required above.

VERIFY no personnel in Containment. (This step may be N/A if a Work Group is in Containment.)

DEPRESS INSERT Pushbutton.

DEPRESS SCAN Pushbutton.

VERIFY all Strip Chart Recorders remained on Scale.

DEPRESS RECORD Pushbutton.

VERIFY all Strip Chart Recorders remained on scale.

VERIFY the data was received by the process computer.

(Pass number increments by 1. Mapped core locations turn green.)

(N/A if flux map data not required.)

ENTER the time of the pass in the adjacent box.

DEPRESS WITHDRAW Pushbutton.

COMPLETE NIS Intermediate Range Data Table if reactor power <5%

(N/A if not applicable).

RECORD NIS INTERMEDIATE RANGE DATA TABLE (N/A if > 5%

power):

Detector Currents (Amps)

Reactivity Computer Pico Pass # Channel 35 Channel 36 Ammeter Reading (If applicable) 8 25

BwOP IC-9 Revision 21 Continuous Use F. 3. n. PLACE a check () when complete for Pass 9.

ALIGN Operations Selector Switch and Path Detector Switch Positions as follows:

A B C D E F Normal Normal Calibrate Normal Normal Normal 7 (B-6) 7 (N-14) --(J-10) 8 (D-3) 8 (F-8) 8 (P-9)

PATH Switch Position Aligned per above.

VERIFY Operations Selector Switch in position required above.

VERIFY no personnel in Containment. (This step may be N/A if a Work Group is in Containment.)

DEPRESS INSERT Pushbutton.

DEPRESS SCAN Pushbutton.

VERIFY all Strip Chart Recorders remained on Scale.

DEPRESS RECORD Pushbutton.

VERIFY all Strip Chart Recorders remained on scale.

VERIFY the data was received by the process computer.

(Pass number increments by 1. Mapped core locations turn green.)

(N/A if flux map data not required.)

ENTER the time of the pass in the adjacent box.

DEPRESS WITHDRAW Pushbutton.

COMPLETE NIS Intermediate Range Data Table if reactor power <5%

(N/A if not applicable).

RECORD NIS INTERMEDIATE RANGE DATA TABLE (N/A if > 5%

power):

Detector Currents (Amps)

Reactivity Computer Pico Pass # Channel 35 Channel 36 Ammeter Reading (If applicable) 9 26

BwOP IC-9 Revision 21 Continuous Use F. 3. o. PLACE a check () when complete for Pass 10.

ALIGN Operations Selector Switch and Path Detector Switch Positions as follows:

A B C D E F Normal Normal Normal Calibrate Normal Normal 8 (E-9) 8 (N-2) 8 (L-8) --(J-10) 9 (C-8) 9 (N-8)

PATH Switch Position Aligned per above.

VERIFY Operations Selector Switch in position required above.

VERIFY no personnel in Containment. (This step may be N/A if a Work Group is in Containment.)

DEPRESS INSERT Pushbutton.

DEPRESS SCAN Pushbutton.

VERIFY all Strip Chart Recorders remained on Scale.

DEPRESS RECORD Pushbutton.

VERIFY all Strip Chart Recorders remained on scale.

VERIFY the data was received by the process computer.

(Pass number increments by 1. Mapped core locations turn green.)

(N/A if flux map data not required.)

ENTER the time of the pass in the adjacent box.

DEPRESS WITHDRAW Pushbutton.

COMPLETE NIS Intermediate Range Data Table if reactor power <5%

(N/A if not applicable).

RECORD NIS INTERMEDIATE RANGE DATA TABLE (N/A if > 5%

power):

Detector Currents (Amps)

Reactivity Computer Pico Pass # Channel 35 Channel 36 Ammeter Reading (If applicable) 10 27

BwOP IC-9 Revision 21 Continuous Use F. 3. p. PLACE a check () when complete for Pass 11.

ALIGN Operations Selector Switch and Path Detector Switch Positions as follows:

A B C D E F Normal Normal Normal Normal Calibrate Normal 9 (H-3) 9 (H-13) 9 (F-3) 10 (L-11) --(J-10) 1 (D-8)

PATH Switch Position Aligned per above.

VERIFY Operations Selector Switch in position required above.

VERIFY no personnel in Containment. (This step may be N/A if a Work Group is in Containment.)

DEPRESS INSERT Pushbutton.

DEPRESS SCAN Pushbutton.

VERIFY all Strip Chart Recorders remained on Scale.

DEPRESS RECORD Pushbutton.

VERIFY all Strip Chart Recorders remained on scale.

VERIFY the data was received by the process computer.

(Pass number increments by 1. Mapped core locations turn green.)

(N/A if flux map data not required.)

ENTER the time of the pass in the adjacent box.

DEPRESS WITHDRAW Pushbutton.

COMPLETE NIS Intermediate Range Data Table if reactor power <5%

(N/A if not applicable).

RECORD NIS INTERMEDIATE RANGE DATA TABLE (N/A if > 5%

power):

Detector Currents (Amps)

Reactivity Computer Pico Pass # Channel 35 Channel 36 Ammeter Reading (If applicable) 11 28

BwOP IC-9 Revision 21 Continuous Use F. 3. q. PLACE a check () when complete for Pass 12.

ALIGN Operations Selector Switch and Path Detector Switch Positions as follows:

A B C D E F Normal Normal Normal Normal Normal Calibrate 10 (L-5) 10 (E-11) 10 (E-5) 1 (J-7) 1 (K-12) --(J-10)

PATH Switch Position Aligned per above.

VERIFY Operations Selector Switch in position required above.

VERIFY no personnel in Containment. (This step may be N/A if a Work Group is in Containment.)

DEPRESS INSERT Pushbutton.

DEPRESS SCAN Pushbutton.

VERIFY all Strip Chart Recorders remained on Scale.

DEPRESS RECORD Pushbutton.

VERIFY all Strip Chart Recorders remained on scale.

VERIFY the data was received by the process computer.

(Pass number increments by 1. Mapped core locations turn green.)

(N/A if flux map data not required.)

ENTER the time of the pass in the adjacent box.

DEPRESS WITHDRAW Pushbutton.

COMPLETE NIS Power Range Channel Data Table if reactor power 5% or COMPLETE NIS Intermediate Range Data Table if reactor power <5%. (N/A if not applicable.)

29

BwOP IC-9 Revision 21 Continuous Use F. 3. q. RECORD NIS POWER RANGE CHANNEL DATA (N/A if < 5%

power or deemed not necessary by RE):

Detector Currents (Ma) and Percent Power Pass Channel 41 Channel 42 Channel 43 Channel 44

//////// Top Bot Q Top Bot Q Top Bot Q Top Bot Q 12 Delta Flux (%) (MCB Meters and Computer) 10 Minute Pass Calorimetric

_NI-41C _NI-42C _NI-43C _NI-44C

Power (%)

12

//////// CH 41 CH 42 CH 43 CH 44 ///////////////////

12 ///////////////////

RECORD NIS INTERMEDIATE RANGE DATA TABLE (N/A if > 5%

power):

Detector Currents (Amps)

Reactivity Computer Pico Pass # Channel 35 Channel 36 Ammeter Reading (If applicable) 12

r. PERFORM any required Emergency/Common passes per Attachment C.

s. CIRCLE all locations that could not be mapped on FIGURE 1 of this procedure.

t. VERIFY/PLACE the Computer Switch to the OFF position.

u. COMPLETE ATTACHMENT D for all drives that could not be withdrawn from storage.

v. POSITION Incore detectors per the applicable sections of Attachment A as required:

VERIFY/INSERT all operable detectors to the bottom of the core.

VERIFY/PLACE all operable Detectors into storage.

PLACE in location as directed by Shift Manager or designee.

30

BwOP IC-9 Revision 21 Continuous Use F. 4. System Restoration:

a. VERIFY/ PERFORM the following to restore the audible alarm capability of the detector 4AS303/5AS303 (U1/U2 incore seal table detector) on the General Atomics RM-11 in the main control room.

1) PLACE the RM-11 in SUPERVISOR Mode.

2) SELECT grid four on the RM-11.

3) On the keypad, TYPE 4303/5303 and PUSH the SELECT pushbutton (this will cue up the U1/U2 incore seal table detector).

4) PUSH the CHANNEL ITEM pushbutton on the RM-11.

5) On the keypad, TYPE 16 and PUSH the SELECT pushbutton.

6) On the keypad, TYPE 1 and PUSH the ENTER pushbutton.

7) PLACE the RM-11 to NORMAL mode.

b. VERIFY/PERFORM the following to restore Loose Parts Alarms:

1) At 1PA44J, PLACE the ALARM ENABLE/DEFEAT switch to ALM ENABLE for:

1VE-LM003 1VE-LM004

2) EXIT TRM LCO 3.3.d for restored channels.

c. REMOVE the Compact Flash Card(s) from the recorder(s) if directed by Reactor Engineering.

d. ALIGN the IC panel per the Shift Manager or designee.

e. ATTACH completed BwOP IC-9T3, 9T4, or 9T5 sheets (as applicable).

f. FORWARD copies of any BwOP IC-9, 9T3, 9T4, 9T5, which were used to Reactor Engineering.

31

BwOP IC-9 Revision 21 Continuous Use MOVABLE INCORE DETECTORS CORE LOCATIONS FIGURE 1 R P N M L K J H G F E D C B A 1 C7 B4 2 B8 A2 F2 3 A9 C9 D8 F3 4 A4 D5 E3 5 A1 D7 C10 C3 6 B6 F5 B3 A5 A7 7 E4 D1 B5 E7 8 C2 F9 C8 E6 E8 F1 E9 D3 9 F8 C1 A8 F7 10 A3* CP B1 11 D2* D1 C5 B10 B2 12 E1 F6 A6 13 E5 D4 B9 C4 14 B7 C6 E2 D6 15 F4 A1 NORMAL MODE FLUX THIMBLE LOCATIONS In this case, there is one to one thimble to detector correspondence (i.e., thimble letter equals detector letter and number corresponds to detector path selector numbers).

CP - Calibration Path

Unit 2 only, L10 and R11 Capped for Cycle 17 per EC 391242 (A2R16) 32

BwOP IC-9 Revision 21 Continuous Use ATTACHMENT A NORMAL INCORE OPERATIONS Perform the applicable step to operate the Incore System as directed in BwOP IC-9.

NOTE Step A will WITHDRAW Detectors from Storage.

Step B INSERT Detectors to the bottom of the core Step C will SCAN detectors from the bottom of the core to the top of the core Step D will RECORD and move detectors from the top the core to the bottom of the core Step E will WITHDRAW the Detectors from the bottom of the core to the fully withdrawn position Step F will place Detectors in STORAGE.

Step G will manually operate a detector or detectors.

A. To WITHDRAW Detectors from Storage, PERFORM the following:

1) DRIVE SELECTOR positioning at the Common Controls Panel.

VERIFY/PLACE the DRIVE SELECTOR Switch in the ALL position, if all of the Detectors are to be placed in the WITHDRAW position.

VERIFY/PLACE the DRIVE SELECTOR Switch in the A/B/C/D/E/F POSITION, if less than the entire group of Detectors is to be placed in the WITHDRAW position.

2) VERIFY that there are NO PERSONNEL in Containment, if applicable.

3) DEPRESS the WITHDRAW Pushbutton at the Common Control Panel.

4) VERIFY that the Detector(s) fully withdrawn.

5) REPEAT previous steps as necessary to fully withdraw all selected Detectors from Storage (N/A if all detectors were withdrawn).

33

BwOP IC-9 Revision 21 Continuous Use ATTACHMENT A (Contd)

B. To INSERT Detectors to the bottom of the core, PERFORM the following:

1) VERIFY that the Detectors to be inserted are in the FULLY WITHDRAWN position.

2) For each Detector to be inserted, PERFORM the following at each Detector Control Panel:

a) SET the OPERATION SELECTOR Switch to the desired position.

b) SET the PATH SELECTOR Switch to the desired position.

3) DRIVE SELECTOR positioning at the Common Controls Panel.

VERIFY/PLACE the DRIVE SELECTOR Switch in the ALL position, if all of the Detectors are to be inserted to the bottom of the core.

VERIFY/PLACE the DRIVE SELECTOR Switch in the A/B/C/D/E/F POSITION, if less than the entire group of Detectors is to be inserted to the bottom of the core.

4) IF an emergency or common pass is required, VERIFY/UPDATE the EMERGENCY/COMMON/STORAGE limits for the associated drive per the Incore System Operator Aid.

5) VERIFY that there are NO PERSONNEL in Containment, if applicable.

6) DEPRESS the INSERT Pushbutton on the Common Control Panel.

7) VERIFY that the Detector(s) is(are) in the bottom of core position.

8) REPEAT previous steps as necessary to place all selected Detectors in the bottom of the core (N/A if all detectors were inserted).

34

BwOP IC-9 Revision 21 Continuous Use ATTACHMENT A (Contd)

C. To SCAN detectors from the bottom of the core to the top of the core, PERFORM the following:

1) VERIFY that the Detectors to be scanned are at the bottom of the core position.

2) DRIVE SELECTOR positioning at the Common Controls Panel.

VERIFY/PLACE the DRIVE SELECTOR Switch in the ALL position, if all of the Detectors are to be scanned to the top of the core.

VERIFY/PLACE the DRIVE SELECTOR Switch in the A/B/C/D/E/F POSITION, if less than the entire group of Detectors is to be scanned to the top of the core.

3) VERIFY that there are NO PERSONNEL in Containment.

4) DEPRESS the SCAN Pushbutton on the Common Control Panel.

5) VERIFY/ADJUST detector range to keep sensor output onscale of recorder (N/A if recorder not used).

6) VERIFY that the Detector(s) is(are) at the top of core position.

7) REPEAT the previous steps as necessary to place all selected Detectors in the top of the core (N/A if all detectors were scanned).

35

BwOP IC-9 Revision 21 Continuous Use ATTACHMENT A (Contd)

D. To RECORD and move detectors from the top of the core to the bottom of the core, PERFORM the following:

1) VERIFY that the Detectors to be recorded are at the top of the core position.

2) DRIVE SELECTOR positioning at the Common Controls Panel.

VERIFY/PLACE the DRIVE SELECTOR Switch in the ALL position, if all of the Detectors are to record and move to the bottom of the core.

VERIFY/PLACE the DRIVE SELECTOR Switch in the A/B/C/D/E/F POSITION, if less than the entire group of Detectors is to record and move to the bottom of the core.

3) VERIFY that there are NO PERSONNEL in Containment.

4) DEPRESS the RECORD Pushbutton on the Common Control Panel.

a) VERIFY that the Detector(s) is(are) at the bottom of core position.

b) REPEAT previous steps as necessary to place all selected Detectors in the bottom of the core (N/A if all detectors were recorded).

E. To WITHDRAW the Detectors from the bottom of the core to the FULLY WITHDRAWN position, PERFORM the following:

1) DRIVE SELECTOR positioning at the Common Controls Panel.

VERIFY/PLACE the DRIVE SELECTOR Switch in the ALL position, if all of the Detectors are to be fully withdrawn.

VERIFY/PLACE the DRIVE SELECTOR Switch in the A/B/C/D/E/F POSITION, if less than the entire group of Detectors is to be fully withdrawn.

2) VERIFY that there are NO PERSONNEL in Containment.

3) DEPRESS the WITHDRAW Pushbutton, at the Common Controls Panel.

4) VERIFY that the Detector(s) is(are) fully withdrawn.

5) REPEAT previous steps as necessary to withdraw individual Detectors (N/A if all detectors were withdrawn).

36

BwOP IC-9 Revision 21 Continuous Use ATTACHMENT A (Contd)

NOTE The Incore Detectors may be considered fully inserted into storage when the Encoder position is within 12 inches of the higher value of the two storage limits.

F. To place Detectors in Storage, PERFORM the following:

1) For each Detector to be placed in Storage, PERFORM the following at the Associated Detector Control Panel:

a) VERIFY that the Detector is fully withdrawn.

b) PLACE the OPERATION SELECTOR Switch to the STORAGE Position

2) DRIVE SELECTOR positioning at the Common Controls Panel.

VERIFY/PLACE the DRIVE SELECTOR Switch in the ALL position, if all of the Detectors are to be placed in storage.

VERIFY/PLACE the DRIVE SELECTOR Switch in the A/B/C/D/E/F POSITION, if less than the entire group of Detectors is to be placed in storage.

3) IF the EMERGENCY/COMMON/STORAGE limits have been changed for execution of common or emergency passes, THEN VERIFY/UPDATE the limits for storage using the Incore System Operator Aid.

4) VERIFY that there are NO PERSONNEL in Containment.

5) DEPRESS the INSERT Pushbutton at the Common Controls Panel.

6) VERIFY that the Detector(s) STOP at the Storage Lower Limit.

7) DEPRESS the SCAN Pushbutton at the Common Controls Panel.

8) VERIFY that each Detector STOPS at the Storage Upper Limit.

9) REPEAT previous steps as necessary to place all selected Detectors into Storage (N/A if all detectors were placed into storage).

37

BwOP IC-9 Revision 21 Continuous Use ATTACHMENT A (Contd)

NOTE Manual operation of the detector may be utilized provided that the detectors are not withdrawn past 0.0 inches as indicated on the associated DETECTOR POSITION indications.

G. To manually operate a detector or detectors, PERFORM the following:

1) DRIVE SELECTOR positioning.

VERIFY/PLACE the DRIVE SELECTOR Switch in the ALL position, if all of the Detectors are to be manually operated.

VERIFY/PLACE the DRIVE SELECTOR Switch in the A/B/C/D/E/F POSITION, if less than the entire group of Detectors is to be manually operated.

2) VERIFY that there are NO PERSONNEL in Containment.

3) VERIFY/PLACE the AUTO/MANUAL Switch in the MANUAL position.

4) INSERT OR WITHDRAW the detector(s) as necessary using the INSERT-OFF-WITHDRAW Switch.

5) VERIFY/PLACE the AUTO/MANUAL Switch in the AUTO position.

6) VERIFY/PLACE the DRIVE SELECTOR Switch in the ALL position, if desired (otherwise N/A this step).

38

BwOP IC-9 Revision 21 Continuous Use ATTACHMENT B INCORE TROUBLESHOOTING The following is a list of potential problems that, although unlikely, may occur. This is not intended to be an all-inclusive list.

NOTE If any problems occur that are outside of those listed, please contact a member of the Reactor Engineering Department.

NOTE If during Insert, Scan, or Record, the appropriate button does not extinguish and the detector(s) has ceased movement, the detector(s) may not have reached its limit due to blockage in the thimble tube.

NOTE Do NOT attempt to unblock a path that was previously identified as being blocked without Operations Management approval.

Attempting to unblock a path can lead to the loss of detector function or other system capabilities due to unavailable 10-paths. Authorized attempts should consider what affect losing a detector and associated equipment have on the system, as well as required equipment per TLCO 3.3.a. A list of previously identified blocked paths can be found in the Incore Limits Operator Aid.

39

BwOP IC-9 Revision 21 Continuous Use ATTACHMENT B (Contd)

PROBLEM SOLUTION RNO Blocked thimble. Try to clear blockage per Step 1. Refer to step 1.i.

Path light does not Follow actions of Step 2. Contact an RE.

illuminate.

5 or 10 path does not Wait for rotation to continue to Contact RE if excessive rotation stop on selected path. selected position. occurs (>5 rotations).

Contact RE if withdrawn light is lit 5 or 10 path does not Verify detector withdrawn light is and excessive time has elapsed rotate. lit. Wait for rotation.

(>5 min).

VERIFY more than 1 drive is not STOP light Check all drive selectors are selected to the same location.

illuminates. selected to the proper position.

Contact RE.

Fluxmap data not Contact NIS.

being received.

Go to manual and individual drive Withdraw light not and Insert/Withdraw in Low Contact an RE.

illuminated Speed

1. To attempt to clear blockage in the thimble tube, PERFORM the following:

a. DEPRESS the stop button, and DETERMINE which detector has not reached its limit.

b. SELECT the detector, which has not reached its limit, on the Common Controls Panel.

c. PLACE the AUTO/MANUAL switch to MANUAL.

d. SELECT the SPEED switch to HIGH.

e. PLACE the INSERT/OFF/WITHDRAW Switch in WITHDRAW for the detector and WITHDRAW the detector about 20 inches.

f. PLACE the INSERT/OFF/WITHDRAW Switch in INSERT for the detector and INSERT the detector until the limit is reached, the detector stops, or the detector passes the point of blockage.

g. Repeat steps 1.e & f for a maximum of 3 times

h. TAKE the AUTO/MANUAL switch back to AUTO.

40

BwOP IC-9 Revision 21 Continuous Use ATTACHMENT B (Contd)

1. i. PERFORM one of the following:

If the blockage has NOT been cleared, THEN PERFORM the following:

1) DEPRESS Withdraw on the common control panel.

2) ONCE the detector is withdrawn, PLACE the PATH SELECTOR for that drive to OFF.

3) PLACE the DRIVE SELECTOR Switch in the ALL position. If one of the drives is off, the path selector light for that drive will be extinguished.

4) SELECT the speed switch to LOW.

5) Return to step in effect.

IF the blockage has been cleared, THEN PERFORM the following:

1) PLACE the DRIVER SELECTOR Switch in the ALL position.

2) SELECT the speed switch to LOW.

3) PUSH the INSERT or SCAN pushbutton to reinsert or rescan with the detector.

4) Return to step in effect.

2. IF the correct number of path lights does not illuminate on the common panel, there may be a problem with the indication microswitch.

a. VERIFY that all detectors being inserted have a flux indication on scan.

b. IF there is no flux indication after about 50 inches of scan, STOP the trace and CONTACT a Reactor Engineer.

41

BwOP IC-9 Revision 21 Continuous Use ATTACHMENT C EMERGENCY/COMMON PASS NOTE BwOP IC-9 Attachment A is a reference step on how to operate the Incore Drive System. Refer to the appropriate substeps to perform desired movement of the Incore Drive System.

NOTE Copy additional forms of this attachment as needed for each Emergency/Common pass.

1. RECORD As Found Emergency/Common/Storage and Calibrate limits for the detector(s) being used (N/A for detectors not used):

Emergency/Common/Storage "As Found" Limits Detector A B C D E F Top Bottom Calibrate "As Found" Limits Detector A B C D E F Top Bottom

2. VERIFY/UPDATE Emergency/Common/Storage and Calibrate limits for the drive utilizing the Incore Operator Aid, if applicable.

3. RECORD the Emergency pass positions required by the Reactor Engineering Group in Step 4.

42

BwOP IC-9 Revision 21 Continuous Use ATTACHMENT C (Contd)

4. PLACE a check () when complete for the Emergency/Common Pass.

RECORD Operations Selector Switch and Path Detector Switch Positions as determined by Reactor Engineering as follows:

A B C D E F PATH Switch Position Aligned per above.

VERIFY Operations Selector Switch in position required above.

VERIFY no personnel in Containment, if applicable.

DEPRESS INSERT Pushbutton.

DEPRESS SCAN Pushbutton.

VERIFY all Strip Chart Recorders remained on Scale.

DEPRESS RECORD Pushbutton.

VERIFY all Strip Chart Recorders remained on scale.

VERIFY the data was received by the process computer.

(Pass number increments by 1. Mapped core locations turn green.)

RECORD required data (Pass # , Detector and ten path position, on the paperless recorder between traces per BwOP IC-9, Attachment B or enter the time of the pass in the adjacent box).

DEPRESS WITHDRAW Pushbutton.

Emergency/Common/Storage and Calibrate limits changed? (Yes/No).

PERFORM next step if limits were changed, otherwise N/A next step.

5. IF the map is complete, RESTORE Emergency/Common/Storage and Calibrate limits, to the "As Found" limits or per the Incore Operator Aid. N/A if more emergency passes are to be completed.

a. RETURN to BwOP IC-9 procedure and step in effect.

43

BwOP IC-9 Revision 21 Continuous Use ATTACHMENT D REMOVING/RESTORING A 5-PATH FROM ROTATING NOTE The following section is to be used to allow access to the ten paths of drives, which have detectors that cannot be withdrawn. This section can be marked "N/A" if no leads are to be lifted.

NOTE Removal of the 5-path transfer relay per the steps below will ensure that the 5-path will not rotate.

NOTE Copy this Appendix for each Drive that CANNOT be withdrawn from storage.

NOTE Steps 1 through 5 will disable a 5-Path from turning to support mapping. Steps 6 through 12 will return the system to the as found configuration.

1. REMOVE a 5-PATH from operation for all Drives that cannot be withdrawn from storage by lifting leads in the following steps:

a. LIST the Drive(s) for which a lead is being lifted.

b. NOTIFY the Shift Manager that the lead(s), and relay(s) for the Drive(s) listed in 1.a. will be lifted.

44

BwOP IC-9 Revision 21 Continuous Use ATTACHMENT D (Contd)

1. c. CIRCLE the lead(s), and relay(s) to be lifted from the list below:

Lead Relay Drive A TB3-11 K90A Drive B TB7-11 K91A Drive C TB19-11 K92A Drive D TB23-11 K93A Drive E TB26-14 K94A Drive F TB29-14 K95A

2. VERIFY/ESTABLISH the Operation Selector switch for each applicable drive to the STORAGE position at its Detector Control panel.

3. REMOVE the 5-path transfer motor relay(s) circled in Step 1.c from the rear of the

_PM08J panel (Access Key 69).

VERIFICATION _____

4. VERIFY/ESTABLISH the Operation Selector switch for each applicable drive to the OFF position at its Detector Control panel. The Storage lamp will extinguish.

CAUTION The lead(s) to be lifted are energized with 120V AC.

5. LIFT the lead(s) circled in Step 1.c, located in the rear of the _PM08J panel.

VERIFICATION _____

45

BwOP IC-9 Revision 21 Continuous Use ATTACHMENT D (Contd)

NOTE Steps 6 through 12 are to be used to reconnect any leads lifted in step 5.

6. RESTORE a 5-PATH to operation for all Drives that cannot be withdrawn from storage by lifting leads in the following steps:

7. LIST the Drive(s) for which a lead is being landed.

8. RECONNECT all leads that were lifted in step 5 of this attachment as specified below:

Lead Drive A TB3-11 Drive B TB7-11 Drive C TB19-11 Drive D TB23-11 Drive E TB26-14 Drive F TB29-14 VERIFICATION _____

9. VERIFY/SELECT STORAGE on the Operation Selector switch for the applicable drive at its Detector Control Panel.

10. VERIFY Storage lamp is ILLUMINATED.

11. REPLACE all motor relay(s) that were removed in step 5 as specified below:

Relay Drive A K90A Drive B K91A Drive C K92A Drive D K93A Drive E K94A Drive F K95A VERIFICATION _____

12. VERIFY/ESTABLISH the Operation Selector switch as desired by the Shift Manager or designee. System interlocks should not allow operation of the 5-path transfer motor with the detector inserted.

(Final) 46

JOB PERFORMANCE MEASURE TASK CONDITIONS:

1. You are an extra NSO.

2. Unit 1 is in Mode 5.

3. 1PR01J is currently operable, but is scheduled to be taken OOS for maintenance next shift.

4. A Unit 1 containment release is scheduled in anticipation of the 1PR01J outage.

INITIATING CUES:

1. The Unit Supervisor has handed you a Containment release package G-13-001, completed through section D, and has directed you to perform Section E using the containment mini-purge exhaust fan and BwOP VQ-6 to reduce Containment pressure to between 0.0 and 0.1 psig. All previous sections of the release package have been successfully completed.

2. An Equipment Operator is standing by to obtain the 1FI-VQ009 flowrate Page 1 of 5 SIM-805

TASK TITLE: Perform a Containment Mini-Purge Release JPM No.: SIM-805 REV: 2013 NRC TPO No.: 4C.VQ-02 K&A No.: 029000 A2.03 TASK No.: R-VQ-006, Start the containment mini-purge sys. K&A IMP: 2.7/3.1 EXAMINEE: RO SRO (Circle One)

EVALUATOR: DATE:

The Examinee: PASSED this JPM. TIME STARTED:

FAILED TIME FINISHED:

JPM TIME: MINUTES CRITICAL ELEMENTS: (*) 6, 8 APPROX COMPLETION TIME: 15 MINUTES CRITICAL TIME: NA EVALUATION METHOD: LOCATION:

X PERFORM IN PLANT SIMULATE X SIMULATOR GENERAL

REFERENCES:

1. BwOP VQ-6 Rev. 21, Containment Mini Purge System Operation

2. RP-BR-980, Rev 12, Containment Vent And Mini Purge Gaseous Effluents MATERIALS:

1. BwOP VQ-6 Containment Mini Purge System Operation

2. RP-BR-980, Rev 12, Containment Vent And Mini Purge Gaseous Effluents TASK STANDARDS:

1. Complete Section E.2. a-f of Containment Release Form in accordance with RP-BR-980.

2. Correctly align and start containment mini purge system.

TASK CONDITIONS:

1. You are an extra NSO.

2. Unit 1 is in Mode 1.

3. 1PR01J is currently operable, but is scheduled to be taken OOS for maintenance next shift.

4. A Unit 1 containment release is scheduled in anticipation of the 1PR01J outage.

INITIATING CUES:

1. The Unit Supervisor has handed you a Containment release package G-13-001, completed through section D, and has directed you to perform Section E using the containment mini purge exhaust fan and BwOP VQ-6 to reduce Containment pressure to between 0.0 and 0.1 psig. All previous sections of the release package have been successfully completed.

2. An Equipment Operator is standing by to obtain the 1FI-VQ009 flowrate Page 2 of 5 SIM-805

RECORD START TIME Note: Provide the examinee with a copy of RP-BR-980 through Step D and BwOP VQ-6.

When requested by the examinee, Independent Verification has been completed.

PERFORMANCE STEP STANDARD Circle applicable

1. Refer to partially completed RP-

Open RP-BR-980 SAT UNSAT N/A BR-980, Section E.2 Comments:

REVIEW the applicable CUE: Prerequisites, Prerequisites, Precautions, Precautions, Limitations and Limitations and and Actions are met. Actions.

2. RECORD the affected

Record 1 in the affected SAT UNSAT N/A containment number. containment blank. Comments:

Initial and date operator blank.

CUE: US has initialed and dated the SRO blank.

Request SRO initial and date SRO blank.

3. RECORD the affected

Record affected SAT UNSAT N/A containment pressure. containment pressure in Comments:

blank.

Initial and date operator NOTE: If examinee indicates blank.

they would use containment pressure meter on 1PM06J, inform the examinee that the meter on 1PM06J is inoperable and that the equivalent meter at 0PM02J is available (1PDI-VP231).

4. Ensure HVAC requirements are

Verify 0VA02CA or CB is SAT UNSAT N/A still in effect. running. Comments:

Initial and date the operator blank

5. Refer to BwOP VQ-6

Open BwOP VQ-6. SAT UNSAT N/A Comments:

REVIEW the applicable Prerequisites, Precautions, CUE: Prerequisites, and Limitations and Precautions, Limitations Actions.

and Actions are met.

Determine step 8 is applicable.

Page 3 of 5 SIM-805

6*. Open mini purge containment

At 0PM02J: SAT UNSAT N/A isolation valves. Comments:

Open 1VQ005A

Open 1VQ005B

Open 1VQ005C

7. Record the time the valves were

Record the current time. SAT UNSAT N/A open on RP-BR-980 step E.2.d. Comments:

Initial and date the operator blank 8*. Start Mini Purge Exhaust Fan.

At 0PM02J, start 1VQ05C SAT UNSAT N/A Comments:

9. Record the time the fan was

Record the current time. SAT UNSAT N/A started on RP-BR-980 step E.2.e. Comments:

Initial and date the operator blank CUE: THIS COMPLETES THIS JPM.

RECORD STOP TIME COMMENTS:

Page 4 of 5 SIM-805

SIMULATOR SETUP INSTRUCTIONS JPM NO: SIM-805 REQUIRED SIMULATOR MODE (S): ANY MALFUNCTION #S: N/A COMMENTS:

1. RP-BR-980 needs to be filled out through section D.

2. Verify 0VA02CA or CB is running.

3. Raise containment pressure to > 0.3 psig with main containment purge supply system.

4. Place Release in Progress placard on 0PM02J Page 5 of 5 SIM-805

PROCEDURE BwOP VQ-6 UNIT NO. REVISION NO.

21 BRAIDWOOD STATION PROCEDURE TITLE:

CONTAINMENT MINI-PURGE SYSTEM OPERATION Rev Summary IR# / EC# (if applicable) 21 Reinstate Step F.1 clarification that was inadvertently PCRA 1292723-02 dropped from Rev 19.

BwOP VQ-6 Revision 21 Continuous Use CONTAINMENT MINI-PURGE SYSTEM OPERATION A. STATEMENT OF APPLICABILITY This procedure describes the steps required to startup and shutdown the Containment Mini-Purge System.

B. REFERENCES

1. Station Procedures:

a. BwOP VQ-M1/M2, Mechanical Lineup.

b. BwOP VQ-E1/E2, Electrical Lineup.

c. RP-BR-980, Containment Vent and Mini Purge Gaseous Effluents.

d. RP-BR-932, Containment Vent and Mini Purge Gaseous Effluents with 1(2)PR01J Inoperable.

e. _BwOSR 3.6.3.2, Cnmt Ventilation 8" Purge Sup/Exh Isol Weekly Surv.

2. Station Drawing: M-105, Containment Purge System.

3. Tech Specs:

a. 3.6.4.

b. 3.6.5.

c. 3.6.3.

d. 3.9.4.

4. UFSAR Sections:

a. 9.4.9.

b. 11.5.2.

5. Westinghouse PLS.

6. Station Commitment: 456-402-91-00100, Precaution on Spent Fuel Pool Impact.

1

BwOP VQ-6 Revision 21 Continuous Use C. PREREQUISITES

1. The system is lined up in accordance with BwOP VQ-M1/M2.

2. The system is lined up in accordance with BwOP VQ-E1/E2.

3. NOTIFY the Radiation Protection Department that this procedure is being performed and the purpose of the performance and verify that the filter will not be changed in _PR01J during release.

4. Either of the following may be used to perform the Containment Release:

RP-BR-980, Containment Vent and Mini Purge Gaseous Effluents

(_PR01J OPERABLE).

RP-BR-932, Containment Vent and Mini Purge Gaseous Effluents with 1(2)PR01J INOPERABLE.

5. _PR28J must be OPERABLE if the containment release is being performed using RP-BR-932 with _PR01J INOPERABLE.

D. PRECAUTIONS

Startup and Shutdown of the Containment Mini-Purge System may impact Spent Fuel Pool Level if the Spent Fuel Pool is connected to the Refueling Cavity via the Transfer Canal. If the "Spent Fuel Pit Level High Low" annunciator is not operable, direct communications between the Control Room and the Spent Fuel Pool MUST be maintained until conditions stabilize.

2

BwOP VQ-6 Revision 21 Continuous Use E. LIMITATIONS AND ACTIONS

1. When any system valves of Containment Mini-Purge lines are open in MODE 1, 2, 3 and 4, in accordance with Tech Spec 3.6.3, or are open during core alterations or movement of irradiated fuel within the containment in accordance with Tech Spec 3.9.4:

a. The valves must be capable of closing under accident conditions.

b. The instrumentation for causing isolation of the valves must be functioning.

c. The effluent release must be monitored and must be within regulatory limits.

2. Containment internal pressure shall be maintained between -0.1 and +1.0 psig in MODES 1, 2, 3 and 4, in accordance with Tech Spec 3.6.4.

3. Containment maximum temperature shall not exceed 120°F in MODES 1, 2, 3, and 4 per Tech Spec 3.6.5.

4. IF Containment temperature is less than 70°F with the SI Accumulators pressurized, VERIFY _BwOS SI-1a is entered.

5. Refer to Attachment A of this procedure if _PR01J alarms during a containment release. (N/A if release initiated with RP-BR-932.)

6. The following Containment Mini-Purge valves will close upon a Containment Ventilation Isolation Signal:

a. _VQ003, Mini-Flow to Post LOCA Purge Isol Vlv.

b. _VQ005A, Mini-Flow Prg Exh Inside Isol Vlv.

c. _VQ005B, Mini-Flow Prg Exh Outside Isol Vlv.

d. _VQ005C, Mini-Flow Prg Exh Outside Isol Vlv.

e. _VQ004A, Mini-Flow Prg Sup Inside Isol Vlv.

f. _VQ004B, Mini-Flow Prg Sup Outside Isol Vlv.

7. All references to _BwOSR 3.6.3.2 are not applicable in Modes 5 or 6, and recording data is not required in these modes.

8. Containment pressure should be less than 0.3 psig prior to starting the _VQ04C, Mini-Purge Supply Fan to allow forward flow.

3

BwOP VQ-6 Revision 21 Continuous Use F. MAIN BODY CAUTION If _PR01J becomes inoperable during the release, IMMEDIATELY suspend the release. The release may still be performed if initiated with RP-BR-932.

NOTE Steps 4, 5, 6, 7, 8, 9, and 10 can be performed independent of each other.

Steps 4 and 5: Purge the Containment with No Mini-Purge Fans.

Steps 6 and 7: Operate Containment Mini-Purge Supply Fans.

Steps 8 and 9: Operate Containment Mini-Purge Exhaust Fans.

Step 10: Performs an Extended Purge of Containment (feed and bleed).

1. VERIFY either of the following is approved by the Shift Manager or designee:

(N/A if only supply fans are to be run):

RP-BR-980 (_PR01J OPERABLE)

RP-BR-932 (_PR01J INOPERABLE)

NOTE If taking credit for VA Charcoal Booster and FHB Charcoal Booster Fans, then the opposite units VA Exhaust Fan should be shutdown to prevent a loss of flow up the applicable vent stack.

2. VERIFY when starting Unit 1 Containment Mini-Purge System at least one of the following is in operation. (N/A if only supply fans are to be run).

Unit One Aux Building Exhaust Fan 0VA02CA/B.

One Lab HVAC Fume Hood Exhaust Fan, 0VL02CA/B.

Two VA Charcoal Booster Fans (0VA03CA/B/C/D/E/F) and one FHB Charcoal Booster Fan (0VA04CA/B).

4

BwOP VQ-6 Revision 21 Continuous Use NOTE If taking credit for VA Charcoal Booster and FHB Charcoal Booster Fans, then the opposite units VA Exhaust Fan should be shutdown to prevent a loss of flow up the applicable vent stack.

F. 3. VERIFY when starting Unit 2 Containment Mini-Purge System at least one of the following is in operation. (N/A if only supply fans are to be run).

Unit Two Aux Building Exhaust Fan 0VA02CC/D.

One Radwaste Building Exhaust Fan 0VW03CA/B.

Two VA Charcoal Booster Fans (0VA03CA/B/C/D/E/F) and one FHB Charcoal Booster Fan (0VA04CA/B).

5

BwOP VQ-6 Revision 21 Continuous Use NOTE The Mini-Purge containment isolation valves will not maintain their open position unless the limit switch interlock is complete. Limit switch interlock is complete when valve indication no longer shows dual indication (only the open light is lit).

NOTE If _PR01J alarms during a containment release, PERFORM Attachment A of this procedure for _PR01J alarm response. (N/A if release was initiated with RP-BR-932.)

F. 4. To PURGE Containment with no Mini-Purge Fans, perform the following at 0PM02J:

a. RECORD Containment initial pressure on RP-BR-980, Containment Vent and Mini Purge Gaseous Effluents or RP-BR-932, Containment Vent and Mini Purge Gaseous Effluents with 1(2)PR01J Inoperable.

b. OPEN _VQ005A, Mini-Flow Prg Exh Inside Isol Vlv.

c. OPEN _VQ005B, Mini-Flow Prg Exh Outside Isol Vlv.

d. OPEN _VQ005C, Mini-Flow Prg Exh Outside Isol Vlv.

e. RECORD the time when valves were opened and release began on the following:

RP-BR-980 (_PR01J OPERABLE)

RP-BR-932 (_PR01J INOPERABLE) 6

BwOP VQ-6 Revision 21 Continuous Use F. 5. To SECURE/SUSPEND PURGING Containment with no Mini-Purge Fans, perform the following at 0PM02J.

a. CLOSE _VQ005A, Mini-Flow Prg Exh Inside Isol Vlv.

b. CLOSE _VQ005B, Mini-Flow Prg Exh Outside Isol Vlv.

c. CLOSE _VQ005C, Mini-Flow Prg Exh Outside Isol Vlv.

d. RECORD the time when valves were closed and Release was secured/suspended on the following:

RP-BR-980 (_PR01J OPERABLE)

RP-BR-932 (_PR01J INOPERABLE)

e. RECORD Containment final pressure on the following:

RP-BR-980 (_PR01J OPERABLE)

RP-BR-932 (_PR01J INOPERABLE) 7

BwOP VQ-6 Revision 21 Continuous Use CAUTION When any system valves of Containment Mini-Purge lines are open in Mode 1, 2, 3 and 4, in accordance with Tech Spec 3.6.3 then:

1. The valves must be capable of closing under accident conditions.

2. The instrumentation for causing isolation of the valves must be functioning.

3. The effluent release must be monitored and must be within regulatory limits.

NOTE When starting _VQ04C, Cnmt Mini-Flow Prg Supply Fan, the Control Switch must be held in the start position until the fan suction damper

_VQ01Y is in the open position. The fan will not start until that interlock is satisfied.

NOTE Notify Radiation Protection to address any radiological concerns when starting Cnmt Mini-Purge Supply when Containment Integrity is set.

NOTE Before proceeding with the next step, Containment Pressure should be less than 0.3 psig to allow forward flow.

NOTE The Mini-Purge containment isolation valves will not maintain their open position unless the limit switch interlock is complete. Limit switch interlock is complete when valve indication no longer shows dual indication (only the open light is lit).

8

BwOP VQ-6 Revision 21 Continuous Use NOTE If _PR01J alarms during a containment release, PERFORM Attachment A of this procedure for _PR01J alarm response. (N/A if release initiated with RP-BR-932.)

F. 6. To startup Cnmt Mini-Purge Supply Fan, perform the following at 0PM02J:

a. OPEN _VQ004A, Mini-Flow Prg Sup Inside Isol Vlv.

b. OPEN _VQ004B, Mini-Flow Prg Sup Outside Isol Vlv.

c. START _VQ04C, Cnmt Mini Flow Prg Supply Fan.

d. MONITOR Containment pressure.

7. To SECURE/SUSPEND Cnmt Mini-Purge Supply Fan, perform the following at 0PM02J:

a. STOP _VQ04C, Cnmt Mini-Flow Prg Supply Fan.

b. CLOSE _VQ004A, Mini-Flow Prg Sup Inside Isol Vlv.

c. CLOSE _VQ004B, Mini-Flow Prg Sup Outside Isol Vlv.

9

BwOP VQ-6 Revision 21 Continuous Use CAUTION When any system valves of Containment Mini-Purge lines are open in Mode 1, 2, 3 and 4, in accordance with Tech Spec 3.6.3 then:

1. The valves must be capable of closing under accident conditions.

2. The instrumentation for causing isolation of the valves must be functioning.

3. The effluent release must be monitored and must be within regulatory limits.

NOTE The Mini-Purge containment isolation valves will not maintain their open position unless the limit switch interlock is complete. Limit switch interlock is complete when valve indication no longer shows dual indication (only the open light is lit).

NOTE If _PR01J alarms during a containment release, PERFORM Attachment A of this procedure for _PR01J alarm response. (N/A if release initiated with RP-BR-932.)

F. 8. To Startup Cnmt Mini-Purge Exhaust Fan, perform the following at 0PM02J:

a. OPEN _VQ005A, Mini-Flow Prg Exh Inside Isol Vlv.

b. OPEN _VQ005B, Mini-Flow Prg Exh Outside Isol Vlv.

c. OPEN _VQ005C, Mini-Flow Prg Exh Outside Isol Vlv.

d. RECORD time valves were opened on the following:

RP-BR-980 (_PR01J OPERABLE)

RP-BR-932 (_PR01J INOPERABLE)

e. START _VQ05C, Cnmt Mini-Flow Prg Exh Fan.

10

BwOP VQ-6 Revision 21 Continuous Use F. 8. f. RECORD start time of fan on the following:

RP-BR-980 (_PR01J OPERABLE)

RP-BR-932 (_PR01J INOPERABLE)

g. OPERATE Containment Mini-Purge Exhaust Fan as directed by the Unit Supervisor while MONITORING the Containment pressure.

11

BwOP VQ-6 Revision 21 Continuous Use F. 9. To SECURE/SUSPEND Cnmt Mini-Purge Exhaust Fan, perform the following at 0PM02J:

a. STOP _VQ05C, Cnmt Mini-Flow Prg Exh Fan.

b. RECORD fan stop time on the following:

RP-BR-980 (_PR01J OPERABLE)

RP-BR-932 (_PR01J INOPERABLE)

c. CLOSE _VQ005A, Mini-Flow Prg Exh Inside Isol Vlv.

d. CLOSE _VQ005B, Mini-Flow Prg Exh Outside Isol Vlv.

e. CLOSE _VQ005C, Mini-Flow Prg Exh Outside Isol Vlv.

f. RECORD valve closure time on the following:

RP-BR-980 (_PR01J OPERABLE)

RP-BR-932 (_PR01J INOPERABLE)

g. RECORD Containment final pressure on the following:

RP-BR-980 (_PR01J OPERABLE)

RP-BR-932 (_PR01J INOPERABLE) 12

BwOP VQ-6 Revision 21 Continuous Use F. 10. To perform an Extended Purge (feed and bleed) of Unit _ Containment, perform the following:

CAUTION Containment pressure SHALL be maintained between

- 0.1 and 1.0 psig in Modes 1, 2, 3, and 4.

a. VERIFY/START the Cnmt Mini-Purge Exhaust Fan per Step F.8.

NOTE Before proceeding with the next step, Containment Pressure should be less than 0.3 psig to allow forward flow.

b. START the Cnmt Mini-Purge Supply Fan per Step F.6.

c. WHEN Containment Pressure reaches the desired value, STOP _VQ05C, Cnmt Mini-Flow Prg Exh Fan.

d. OPERATE Cnmt Mini-Purge Supply and Exhaust Fans as directed by the Unit Supervisor while monitoring Containment Pressure.

e. SECURE/SUSPEND the Release per Steps F.7 and F.9 when necessary.

13

BwOP VQ-6 Revision 21 Continuous Use ATTACHMENT A

_PR01J ALARM RESPONSE DURING CONTAINMENT RELEASES NOTE This attachment should only be used if the release was initiated using RP-BR-980 (_PR01J OPERABLE).

If _PR01J alarms during a containment release, PERFORM the following as applicable:

If a HIGH Alarm is received on any Channel, PERFORM the following:

1. SECURE the release by performing the applicable steps of this procedure.

2. TERMINATE the release package.

3. NOTIFY Rad Protection that the release has been terminated.

If an ALERT Alarm is received on any Channel, continue to CLOSELY MONITOR the containment release. (The ALERT Alarm is normally set close to the HIGH setpoint to warn the operator that prompt manual action may be required).

If a Communications, Operate, or Equipment Failure has occurred, PERFORM the following:

1. SUSPEND the release by performing the applicable steps of this procedure.

2. Determine the cause of the monitor failure per BwOP AR/PR-11, using the RM-11 Alarm Response Guidelines.

3. If the alarm condition can be cleared and the monitor restored to normal while the unit is in Mode 5, 6 or defueled, then the release may be RESTARTED with Shift Supervisor permission.

4. If the alarm condition CANNOT be cleared, TERMINATE the release package.

(Final) 14

RETDAS v3.6.3 <BRA> VSSI GASEOUS PRE-RELEASE PERMIT REPORT Permit Number: 2006100 Release Point: Unit 1 Containment Purge Release Mode : 2 Batch Permit Status : Pre-Release Comments:

RELEASE DATA ================================================

Release Number .......................................... G-13-001 1(2) PB101 High Alarm Setpoint (uCi/cc)................... 6.06E-04 Alert Alarm Setpoint (uCi/cc)................... 6.06E-05

MONITOR DATA ================================================

1(2) PB101 Monitor Background(uCi/cc)...................... 1.82E-06 Calculated Setpoint (uCi/cc).............................. 7.23E-06

RELEASE RATE DATA ===========================================

Procedure: BwRP 6110-13T1 Section: A.5.b.1........... YES This package is acceptable for release using the Main Purge, Mini-Purge, Vent Path or Post-LOCA flowpaths.

Discharge flowrate (cfm)................................... 4.39E+04 Discharge flowrate (cc/sec)................................ 2.07E+07 NG Release Rate (uCi/sec).................................. 7.48E+01 Percent of Release Rate Limit (%).......................... 7.48E-02 H-3 Release Rate (uCi/sec)................................. 8.50E+01 Percent of Release Rate Limit (%).......................... 8.50E-02

LIMITS ANALYSIS =============================================

Performed by:_____R. P. Tech____________________ Date: _Today_____

RETDAS v3.6.3 <BRA> VSSI GASEOUS PRE-RELEASE PERMIT REPORT Permit Number: 2006100

=== NUCLIDE DATA

===========================================

Undiluted Rel Rate Nuclide uCi/cc uCi/sec XE-133 4.89E-05 7.48E+03 F&AG 5.09E-05 7.48+03 H-3 1.82E-06 8.50E+01 H-3 1.82E-06 8.50E+01 Total 5.27E-05 1.60E+02

RP-BR-911 Revision 6 Page 14 of 14 ATTACHMENT 8 1/2RE-PR011J ATMOSPHERIC TRITIUM CALCULATION FORM Page 1 of 1 A. Sample Information Sample Location:_____1PR11J________ RT:________WH____________

Date On: _____today__________ Date Off: _______ today __________

Time On: _______0100________ Time Off: ________0215__________

B. Tritium Concentration Calculation

___4.10E-4____Ci/ml (150 ml)

( 200cc/min) ( 75_ min)

Tritium Concentration = ___4.1E-6_____Ci/cc C. Derived Air Concentration Calculation Tritium Concentration 2 E-5 Ci/cc/DAC DAC Fraction = ___2.05E-1______

Reviewed By: _____Rad Pro Sup________/___today___

Radiation Protection/Chemistry Date

RP-BR-980 Revision 12 Page 1 of 25 Level 1 - Continuous Use CONTAINMENT VENT AND MINI PURGE GASEOUS EFFLUENTS

1. PURPOSE 1.1. This procedure outlines the method to be used to verify that the principal gamma emitting noble gas isotopes, iodine and tritium activities in the Containment Building atmosphere are identified and quantified and dose rates established as required by Technical Specifications.

2. MATERIAL AND SPECIAL EQUIPMENT - NONE

3. PRECAUTIONS, LIMITATIONS, AND PREREQUISITES 3.1. Precautions 3.1.1. If an out-of-spec condition exists (such as exceeding activity limits in step A.5.b.2.,

monitoring equipment failure, etc.) immediately notify the Shift Manager.

3.2. Limitations 3.2.1. Contact Operations to determine if 1(2)PR01J is operable. If 1(2)PR001J is inoperable, then refer to RP-BR-932 for release from containment with 1(2)PR001J inoperable 3.2.2. The limiting condition for operation is met when the principle gamma emitting noble gases, iodine and tritium activities are identified and quantified and the dose rates released in gaseous effluents from the site to areas at or beyond the site boundary are limited to the following (exceeding activity concentrations in A.5.b.2. may indicate these dose limits need to be evaluated by chemistry):

1. Whole body - less than or equal to 500 mrem/yr.

2. Skin - less than or equal to 3000 mrem/yr.

3.2.3. Dose rate calculations for this surveillance shall be performed in accordance with the methodology and parameters in the Offsite Dose Calculation Manual.

3.2.4. This procedure is applicable at all times and in all modes of reactor operation.

3.2.5. The Shift Manager must be notified immediately whenever the limiting condition for operation cannot be met.

3.2.6. In the event an out-of-specification condition exists, immediately notify the Shift Manager to implement the applicable LCOAR procedure.

3.2.7. Use of N/A is allowed when procedure/attachment step is not required.

RP-BR-980 Revision 12 Page 2 of 25 3.3. Prerequisites 3.3.1. Attachment 1, Containment Release Form, has been approved by Radiation Protection and the Shift Manager or SRO prior to commencing a containment release.

4. MAIN BODY 4.1. OBTAIN Attachment 1, Containment Release Form. Radiation Protection SHALL assign a Release Number from Attachment 2, Containment Release Log.

4.2. Radiation Protection SHALL OBTAIN all necessary sample results and COMPLETE Section A. The form should be HAND DELIVERED to Chemistry to COMPLETE Section B, unless Section B is not applicable and Chemistry ODCM evaluation is not required. The form should be HAND DELIVERED to Operating to COMPLETE Sections C, D, E and F.

4.3. Following the completion of the release, Attachment 1 will be delivered to Chemistry for completion of Section G. Attachment 1 will be FILED by the Chemistry Department.

5. RETURN TO NORMAL 5.1. This procedure is considered complete and no further action is required when Attachment 1 is properly completed for each release and the dose limits have been met.

6. REFERENCES 6.1. Commitments 6.1.1. Offsite Dose Calculation Manual (ODCM).

6.1.2. Technical Specification Section 3.6.3, "Containment Isolation Valves".

6.1.3. Technical Specification Section 5.5.4, "Radioactive Effluent Controls Program".

7. ATTACHMENTS 7.1. Attachment 1 - Containment Release Form 7.2. Attachment 2 - Containment Release Log

RP-BR-980 Revision 12 Page 3 of 25 ATTACHMENT 1 Containment Release Form Page 1 of 22 1(2) PR 01J Operable ___ X___Yes ________No (refer to RP-BR-932)

Release Number __ G-13-001___

Initiate Purge by Time/Date ___0700/tomorrow _

A. Radiation Protection/Chemistry Responsibility

1. INDICATE the Containment to be released by CHECKING the applicable Unit.

Unit One Containment X Unit Two Containment N/A Release Type Notes Initial Date Routine Release 1,2,3,6,7 RR today First Post-Shutdown Release 1,2,3,6,7 N/A N/A Second Post Shutdown Release 1,2,3,6,7 N/A N/A Third Post Shutdown Release 1,2,3,6,7 N/A N/A Additional Non-Continuous Post Shutdown Release 1,2,3,6,7 N/A N/A Continuous Post Shutdown Release 3,4,5,6,7 N/A N/A NOTE 1: Only one containment release can be performed with each containment noble gas, iodine and tritium analysis, unless otherwise approved by RP/Chemistry Supervision. A release is defined as the exhaust isolation valves being open for greater than one minute.

Leave blank if no approval needed.

SRRS 2C.111

RP-BR-980 Revision 12 Page 4 of 25 ATTACHMENT 1 Containment Release Form Page 2 of 22 NOTE 2: Routine non-outage analyzed samples are valid for a period of 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months from the time the sample is pulled. As long as the purge is initiated in the 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months window, the package is valid until the purge is terminated. Under conditions of continuous feed and bleed in modes 1-4, a new sample must be obtained every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and a new release package must be prepared and used within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months from the time each sample is pulled.

NOTE 3: Following a startup, shutdown, or thermal power change of 15% within one hour, new containment samples must be obtained and analyzed prior to a containment purge or vent.

NOTE 4: During refueling or extended outages when containment integrity is broken and the containment purge system is in continuous use, the following special practices will be implemented:

A new containment release form should be completed every 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months , not to exceed 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months during the first three days of the outage until the noble gas and tritium activity in containment has stabilized at or near LLD.

Once the noble gas and tritium concentrations are verified stabilized by trending for a period of 3 days, the purge can be run continuously without generating a new package.

To initiate a containment release package, with no expiration date, complete steps A.1. through A.6., and mark continuous release in the Initiate Purge by blank on Page 1 If significant increases in daily noble gas or tritium concentrations are noted or the purge is terminated a new containment release package must be initiated.

NOTE 5: In Modes 5, 6 and defueled only, interruptions of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or less shall not be considered a termination of release.

RP-BR-980 Revision 12 Page 5 of 25 ATTACHMENT 1 Containment Release Form Page 3 of 22 NOTE 6: It is permissible to simultaneously release from multiple sources (i.e., U-1 Containment and Gas Decay Tank) provided that each release path meets its respective release rate limits as documented on the applicable release form.

NOTE 7: All times should be recorded in a 2400 hour0.0278 days 0.667 hours 0.00397 weeks 9.132e-4 months time format.

A. 2. OBTAIN the following and ATTACH to this release form:

a. Containment noble gas activity

b. Containment tritium activity (RP-BR-911 or RP-BR-949)

c. Containment Iodine activity

__ RR _/__ today Initial Date

3. VERIFY that the noble gas activity from 1(2)PB111 has not changed significantly since sampling. (NA this step if 1(2)PB111 is not in service). The 1(2) PB111 trend can be obtained from the 1(2) RM11, or Plant Parameter Displays Trend ID BRW01V_RP0076 (Unit 1) or BRW02V_RP0114 (Unit 2).

__ RR _/_ today Initial Date CAUTION If 0VA02CC/D is in operation without 0VA02CA/B in operation, VA will not provide any flow up the unit 1 stack even with the charcoal booster fans in operation. In this case, a Laboratory Fume Hood exhaust fan (0VL02CA/B) must be in operation to provide air flow.

RP-BR-980 Revision 12 Page 6 of 25 ATTACHMENT 1 Containment Release Form Page 4 of 22

4. a. For a Unit one release VERIFY at least one of the following conditions exists. (Check box next to operating component, NA this step if performing a Unit two release)

Unit one Aux Building Exhaust Fan (0VA02CA or 0VA02CB) running One Lab HVAC Fume Hood Exhaust (0VL02CA or 0VL02CB) running Two VA Charcoal Booster Fans (0VA03CA-F) and one FHB Charcoal Booster Fan running (0VA04CA or 0VA04CB) with NO main VA fans running (0VA02CA-D).

__ RR __/_ today Initial Date CAUTION If 0VA02CA/B is in operation without 0VA02CC/D in operation, VA will not provide any flow up the unit 2 stack even with the charcoal booster fans in operation. In this case, a Radwaste Exhaust Fan (0VW03CA/B) must be in operation to provide air flow.

A. 4. b. For a Unit two release VERIFY at least one of the following conditions exists. (Check box next to operating component, NA this step if performing a Unit one release)

Unit two Aux Building Exhaust Fan (0VA02CC or 0VA02CD) running One Radwaste Building Exhaust Fan (0VW03CA or 0VW03CB) running Two VA Charcoal Booster Fans (0VA03CA-F) and one FHB Charcoal Booster Fan runnning (0VA04CA or 0VA04CB) with no main VA fans running (0VA02CA-D).

_______/_______

Initial Date

RP-BR-980 Revision 12 Page 7 of 25 ATTACHMENT 1 Containment Release Form Page 5 of 22 NOTE: If no quantifiable noble gas peaks and no tritium are found in the containment radionuclide analysis, or if all identified noble gases and tritium are less than their respective LLD's, enter "<LLD" in steps A.5.a.1 and A.5.a.2 NOTE: If a computerized release program is available, attach the printout to this form. N/A may be used for steps that perform same function as computer when computer is used.

5. Release Rate and Monitor Setpoint Determination

a. VERIFY that the release does not exceed the 10CFR20 release limits by COMPARING the calculated total µCi/cc values to their stated µCi/cc limits in Step A.5.b.

RP-BR-980 Revision 12 Page 8 of 25 ATTACHMENT 1 Containment Release Form Page 6 of 22 A. 5. a. 1) RECORD the total noble gas activity from the applicable isotopic below.

Noble Gas Activity = ______4.44E-4______ uCi/cc

__ RR __/__ today Initial Date

2) RECORD the tritium activity from Section B of RP-BR-911 or RP-BR-949.

Tritium Activity = _______4.1E-6_______ uCi/cc

__ RR __/__ today Initial Date b) 1) Is the NOBLE GAS activity (step A.5.a.1) less than or equal to 5.29E-2 µCi/cc AND the TRITIUM activity (step A.5.a.2) less than or equal to 5.29E-2 µCi/cc?

[ ] YES This package is acceptable for release using the Mini-Purge or Post-Loca flowpaths. (N/A all of step A.5.b.2).

[ ] NO Then answer the following question:

2) Is the NOBLE GAS activity (step A.5.a.1) less than or equal to 5.29E-1 µCi/cc AND the TRITIUM activity (step A.5.a.2) less than or equal to 5.29E-1 µCi/cc?

[ ] YES This package is acceptable for release using the Post-Loca Flowpath only. N/A all of step E.1 now.

[ ] NO THIS PACKAGE MAY BE UNACCEPTABLE FOR RELEASE. Notify Unit Supervisor. Notify Chemistry ODCM/RETS owner for further guidance.

__ RR __/_ today _

Initial Date

RP-BR-980 Revision 12 Page 9 of 25 ATTACHMENT 1 Containment Release Form Page 7 of 22 NOTE: The following guidance only applies to the RETDAS computer program:

The release rate calculation should initially be performed assuming a containment purge rate of 4000 cfm (1.89E6 cc/sec). This release rate is associated with the mini purge system.

If a recalculation is required (Step A.5.b.2 is answered yes) the containment purge rate used should be 400 cfm (1.89E5 cc/sec). This release rate is associated with the post-LOCA purge system.

In either case, the total noble gas or tritium release rate must be <=1E5

µCi/sec.

NOTE: If the noble gas activity recorded in Step A.5.a.1. is <LLD, a value of zero should be used for the total containment activity in Step A.5.c.

NOTE: Independent verification of steps A.5.c and A.5.d is required if manual calculations are performed. If a computerized release program is used, attach the printout and "NA" Steps A.5.c. and A.5.ed.

c. The alarm setpoints will be set at a value of 50% above the containment total analyzed noble gas activity plus the current containment purge monitor gas detector [1(2)PB101] background. The current 1(2)PB101 background value can be OBTAINED from the 1(2)RM-11, or Plant Parameter Displays Trend ID BRW01V_RP0066 (Unit 1) or BRW02V_RP0104 (Unit 2).

(Total Containment activity x 1.5) + [1(2)PB101] background =

(________________ µCi/cc x 1.5) + _________________ µCi/cc =

(Step A.5.a.1)

_________________ µCi/cc Indep Verf

__ _____/_ ____ _ _____/______

Initial Date Initial Date

RP-BR-980 Revision 12 Page 10 of 25 ATTACHMENT 1 Containment Release Form Page 8 of 22

d. EVALUATE the calculated monitor setpoint as follows:

1) COMPARE the calculated monitor setpoint from Step A.5.c. to the baseline monitor HIGH alarm setpoint of 6.06E-4 µCi/cc. If the calculated value is less than the baseline monitor setpoint, RECORD the baseline monitor HIGH alarm setpoint as the release setpoint. If the calculated value is greater than the baseline monitor HIGH alarm setpoint, RECORD the calculated value as the release setpoint.

1(2)PB101 HIGH Alarm Setpoint __________ µCi/cc

2) COMPARE the calculated monitor setpoint from Step A.5.c. to the baseline monitor ALERT alarm setpoint of 6.06E-5 µCi/cc. If the calculated value is less than the baseline monitor setpoint, RECORD the baseline monitor ALERT alarm setpoint as the release setpoint. If the calculated value is greater than the baseline monitor ALERT alarm setpoint, RECORD the calculated value as the release setpoint.

1(2)PB101 ALERT Alarm Setpoint _________ __ µCi/cc

e. RECORD Release Setpoints:

1(2)PB101 HIGH Alarm Setpoint __6.06E-4___ µCi/cc ALERT Alarm Setpoint __6.06E-5 ____ µCi/cc Indep Verf

__ RR __/ today __ N/A_/______

Initial Date Initial Date NOTE: If any single isotope of iodine is present in the attached isotopic report(s) at greater than 1.0E-8 µCi/cc, then Chemistry ODCM evaluation is required prior to performing this containment release. If Section B of this procedure is N/A, then forward this release package to Operations (as required by Step 4.2 in this procedure) after approval for release at Step A.7.

RP-BR-980 Revision 12 Page 11 of 25 ATTACHMENT 1 Containment Release Form Page 9 of 22 A. 6. REVIEW the attached iodine isotopic report(s) and SELECT one of the following:

o Any single isotope of iodine is present at greater than 1.0 E-8 µCi/cc, Section B must be completed by Chemistry.

_______/______

Initial Date o No single isotope of iodine is present at greater than 1.0E-8 µCi/cc, mark Section B N/A.

_______/______

Initial Date

7. APPROVAL FOR RELEASE Radiation Protection _____ Rad Supervisor________

RP-BR-980 Revision 12 Page 12 of 25 ATTACHMENT 1 Containment Release Form Page 10 of 22 B. Chemistry Department Responsibility NOTE: If detectable levels of Iodine are present in the attached isotopic report(s), then Chemistry ODCM evaluation is required for Quarterly and Annual Effluent dose limits prior to performing this containment release.

1. The Chemistry ODCM evaluation is complete.

_______/______

Initial Date The following release path is required:

Post-Loca flowpath Release path as outlined in step A.5.b.

Approval for release:

Chemistry ________________________________

_______/______

Initial Date C. Operating Department Responsibility NOTE: If any of the below instruments are inoperable, then refer to RETS 12.2.2.A and Table 12.2-3 for appropriate action.

1. PERFORM the appropriate instrumentation operability checks and required Tech Spec surveillances on applicable monitors.

a. PERFORM _1BwOS RETS 2.2.B-1, Unit 1_Pre-Release Source and Channel Check of Containment Purge Effluent Monitor 1PR01J (1RE-PR001A/B/C).

___ JN _/_ Today Initial Date

RP-BR-980 Revision 12 Page 13 of 25 ATTACHMENT 1 Containment Release Form Page 11 of 22

b. RECORD original Setpoint of __RE-PR001 Gas Channel RM-11 Monitor GRID ADDRESS CNMT 2 _1PB101 HIGH ALARM SETPOINT 6.06E-4__µCi/cc PURGE EFF ALERT ALARM SETPOINT _6.06E-5_µCi/cc

__ JN __/_ Today Initial Date NOTE: Steps c-f should be completed only if the setpoints recommended by RP in Step A.5.e. are different than the current setpoints of _RE-PR001 Gas Channel.

NOTE: When the RM-11 is in SUPERVISOR MODE, some actions may have serious detrimental effects on system operation.

Use CAUTION and DO NOT leave the RM-11 console unattended when it is in the SUPERVISOR MODE. If any unusual conditions occur then contact the system STE.

c. PLACE the RM-11 console in SUPERVISOR MODE.

_______/_______

Initial Date

RP-BR-980 Revision 12 Page 14 of 25 ATTACHMENT 1 Containment Release Form Page 12 of 22

d. DEPRESS the CHANNEL ITEM Key. Then SELECT the High Alarm Setpoint Channel Item by KEYING in "09" and then DEPRESSING the SEL key.

Grid 2 ____PB101

_______/______

Initial Date

e. ENTER the High Alarm Setpoint for _PB101 suggested by Radiation Protection/Chemistry in section A.5.e. using the format XYZ + AB. (i.e. A value of 5.36E-12 would be entered as 536-12).

High Alarm Release Setpoint Indep Verf

___PB101 ______________ _______/______ _______/______

Initial Date Initial Date

f. ENTER the Alert Alarm Setpoint suggested by Radiation Protection/Chemistry in Section A.5.e. using the method described in steps d and e. In order to select the Alert Alarm Channel Item in step d, a "10" must be KEYED in.

High Alarm Release Setpoint Indep Verf

___PB101 ______________ _______/______ _______/______

Initial Date Initial Date

RP-BR-980 Revision 12 Page 15 of 25 ATTACHMENT 1 Containment Release Form Page 13 of 22 D. SHIFT ENGINEER OR SRO RESPONSIBILITY

1. PLACE the placard "Gaseous Release in Progress" somewhere on 0PM02J where the placard will be visible. This is to ensure that for a unit 1 release an Aux. Bldg. Exhaust Fan (unit 1 side) or a Lab HVAC exhaust fan is in operation, OR for a unit 2 release an Aux. Bldg. Exhaust Fan (unit 2 side) or a Radwaste Bldg. Exhaust Fan is in operation, or for either unit , to have (2) Charcoal Booster Fans (0VA03CA-F) and (1) FHB Charcoal Booster Fan (0VA04CA or 0VA04CB) in operation.

_ US___/_ today Initial Date NOTE: Routine non-outage analyzed samples are valid for a period of 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months . As long as the purge is initiated in the 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months window, the package is valid until the purge is terminated NOTE: Following a startup, shutdown, or thermal power change of 15% within one hour, new containment samples must be obtained and analyzed prior to a containment purge or vent.

2. ENSURE sections A.7. and B.1 are signed or labeled not applicable by a member of Radiation Protection and/or Chemistry approving the release.

ENSURE the sample analyses have not expired from page 1.

__ US__/_ today Initial Date

RP-BR-980 Revision 12 Page 16 of 25 ATTACHMENT 1 Containment Release Form Page 14 of 22

3. If the release is from Containment through the Mini Purge System, then INSTRUCT the operator to start the Mini Purge System per BwOP VQ-6 Containment Mini-Purge Operation (The fan start section), following SE or SRO approval in Step D.2. above. ENSURE the purge is acceptable per HP calculations in Step A.5.b. for Mini-Purge flowpath, and per Chemistry approval in Step B.1 (if required).

If the release is from Containment through the Mini Purge System for the purpose of equalizing Containment pressure with atmospheric pressure (no fans required), then INSTRUCT the Operator to perform procedure BwOP VQ-6, Containment Mini-Purge Operation (The venting containment section), following SE or SRO approval in Step D.2. above. ENSURE the purge is acceptable per HP calculations in Step A.5.b. for mini purge flowpath, and per Chemistry approval in Step B.1 (if required).

If the release is from Containment through the Post-LOCA Purge System, INSTRUCT the operator to PERFORM procedure BwOP VQ-7 following SE or SRO approval in step D.2. above. ENSURE the purge is acceptable per HP calculations in step A.5.b. for Post-LOCA flowpath, or per Chemistry direction in Step B.1.

D. 4. REVIEW information and ENSURE the form is filled out properly.

Approval for Release _______ US ________/__ today SE OR SRO Date

RP-BR-980 Revision 12 Page 17 of 25 ATTACHMENT 1 Containment Release Form Page 15 of 22 E. Operator Responsibility

1. If the release is through the Containment Mini Purge System, then COMPLETE the following:

OPERATOR SRO

a. Affected Containment ____ ______/______ ______/______

b. RECORD affected containment pressure ____psig ______/______

c. ENSURE that the HVAC requirements of step A.4.a, or A.4.b as applicable, are still in effect.

______/______

d. Start time of purge ____ ______/______

Exhaust isolation dampers open per BwOP VQ-6 OR Time of transfer from Release # _________________________

e. Start time of fan ____ ______/______

f. Purge flowrate _FI-VQ009 ____cfm ______/______

(or estimate if flow gauge is inoperable)

g. Stop time of fan ____ ______/______

h. Stop time of purge ____ ______/______

Exhaust isolation dampers closed per BwOP VQ-6 or Time of transfer to Release #___________________________

i. Final affected containment pressure ____psig ______/______

NOTE: In Modes 5, 6 and defueled only, momentary interruptions of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or less shall not be considered a termination of release.

RP-BR-980 Revision 12 Page 18 of 25 ATTACHMENT 1 Containment Release Form Page 16 of 22 E. 1. j. Purge interruptions of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or less Stop time Start time

____ ____ ______/______

E. 2. If the release is through the Containment Mini Purge System as a VENT PATH (without a fan in operation), then COMPLETE the following:

OPERATOR SRO

a. Affected Containment ____ ______/______ ______/______

Unit.

b. RECORD affected Containment ____psig ______/______

Positive Pressure

c. ENSURE that the HVAC requirements of step A.4.a, or A.4.b as applicable, are still in affect.

______/______

d. Start time of release (Exhaust isolation valves open per BwOP VQ-6) ____ ______/______

e. Stop time of release (Exhaust Isolation valves closed per BwOP VQ-6) ____ ______/______

f. Final affected Containment Pressure ____psig ______/______

RP-BR-980 Revision 12 Page 19 of 25 ATTACHMENT 1 Containment Release Form Page 17 of 22 E. 3. If the release is through the CNMT Post LOCA Purge System, then COMPLETE the following:

OPERATOR SRO

a. Affected Containment ____ ______/______ ______/______

b. RECORD affected containment pressure ____psig ______/______

c. ENSURE that the HVAC requirements of step A.4.a, or A.4.b as applicable, are still in affect.

______/______

d. Start time of purge ____ ______/______

Exhaust isolation dampers open per BwOP VQ-7 or Time of transfer from Release # _________________________

e. Start time of fan ____ ______/______

f. Purge flowrate _FI-VQ093 ____cfm ______/______

(or estimate if flow gauge is inoperable)

g. Stop time of fan ____ ______/______

h. Stop time of purge ____ ______/______

Exhaust isolation dampers closed per BwOP VQ-7 or Time of transfer to Release #___________________________

i. Final affected containment pressure ____psig ______/______

j. Purge interruptions of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or less Stop time Start time

____ ____ ______/______

RP-BR-980 Revision 12 Page 20 of 25 ATTACHMENT 1 Containment Release Form Page 18 of 22 NOTE: If this release will be continued on another release package (unit is in a continuous release mode) step E.4 and E.5 can be skipped.

E. 4. RETURN Rad Monitors for the affected release path to their baseline setpoints (This Step is NOT APPLICABLE if setpoints were not changed in step C.1.)

a. Containment Release ( RE-PR001)

1) RETURN the HIGH ALARM Setpoint for PB101 to the baseline setpoint in Section A.5.e. (USE the method described in Section C.1.)

High Alarm Baseline Setpoint Indep Verf

___PB101 ______________ _______/________ _______/________

Initial Date Initial Date

2) RETURN the Alert Alarm Setpoint for PB101 to the baseline Setpoint in section A.5.e. (USE the method described in Section C.1.).

Alert Alarm Baseline Setpoint Indep Verf

___PB101 ______________ _______/________ _______/________

Initial Date Initial Date

5. REMOVE the placard "Gaseous Release in Progress" from 0PM02J.

6 RETURN this release form to the SE or SRO.

RP-BR-980 Revision 12 Page 21 of 25 ATTACHMENT 1 Containment Release Form Page 19 of 22 F. SE or SRO Responsibility NOTE: Notify Radiation Protection/Chemistry that the release has been terminated if containment purge will be discontinued for more than 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months AND containment integrity is broken.

1. REVIEW the discharge data and ENSURE that the form is filled out properly.

Discharge complete; reviewed by _________/______/_____

SE or SRO Date Time

2. FORWARD this form to Chemistry Supervision.

RP-BR-980 Revision 12 Page 22 of 25 ATTACHMENT 1 Containment Release Form Page 20 of 22 G. Chemistry Responsibility

1. Actual Gaseous and TRITIUM Activity Released NOTE: If a computerized release program is available, attach the printout to this form and indicate "see attached" in the calculation spaces below. If manual calculations are performed, independent verification is required.

NOTE: More than one method may be used to quantify a release if the time the isolation dampers were opened differs from the time the fans were turned on or separate calculations of the same method may be performed. For example two different release paths were used with different flow rates.

a. Differential Pressure Method - to be used when containment integrity is not broken.

1) Volume of containment released Pi Pf 7.82 E + 10 (cc in containment ) x =

cc Pi + 14.7 Where:

P i = pressure before release _____psig P f = pressure after release _____psig

RP-BR-980 Revision 12 Page 23 of 25 ATTACHMENT 1 Containment Release Form Page 21 of 22 G. 1. a. 2) DOCUMENT in the table below the total µCi released of each noble gas isotope and tritium.

NOTE: µCi released = Analyzed noble gas or tritium activity

(µCi/cc) x volume of containment released (cc).

Noble Gas and Tritium Isotope µCi Released Indep Verf

_______/______ _______/______

Initial Date Initial Date

b. Activity x Flowrate x Time method - to be used when containment integrity is broken (i.e. outages) and no difference in pressure can be noted.

Fill in the chart MULTIPLYING the first 4 columns to OBTAIN activity released in µCi. DIVIDE the activity by the duration of release (seconds) to OBTAIN µCi/sec.

NUCLIDE CONTAINMENT FAN FLOW CONSTANT TIME ACTIVITY RATE

(µCi/cc) (cfm) (cc/cf) (min) (µCi) (µCi/s)

H-3 2.83E+004 Ar-41 2.83E+004 Kr-85 2.83E+004 Kr-85M 2.83E+004 Kr-87 2.83E+004 Kr-88 2.83E+004 Xe-131M 2.83E+004 Xe-133 2.83E+004 Xe-133M 2.83E+004 Xe-135 2.83E+004 TOTALS Indep Verf

_______/______ _______/______

Initial Date Initial Date

RP-BR-980 Revision 12 Page 24 of 25 ATTACHMENT 1 Containment Release Form Page 22 of 22 G. 1. c. Concentration Curve Fit Method - if a high fan flow or high concentration was used during the release and sufficient containment atmosphere samples are available the rate change of concentration in containment may be used for a more accurate determination of released activity.

REFER to policy Memo EFF-06 and ATTACH pertinent calculations to this form.

2. VERIFY compliance with 10CFR50 dose limits by ENTERING release data into the 10CFR50 ODCM gaseous release program per CY-AA-170-200, Radioactive Effluent Controls Program.

RP-BR-980 Revision 12 Page 25 of 25 ATTACHMENT 2 Containment Release Log Page 1 of 1 Date Release Release Date Release Release Pkg. Made Number Source Pkg. Made Number Source Records Retention: SRRS 2C.111

TASK CONDITIONS:

1. You are an EO.

2. The Control Room has been evacuated.

3. 1BwOA PRI-5, Control Room Inaccessibility, is in progress.

4. 1CV112D is stuck closed and 1CV112E will not open locally due to the handwheel not engaging.

INITIATING CUES:

1. You have been directed to open 1CV112E at MCC 132X4 Cubicle C2 per 1BwOA ELEC-5. You have already obtained the jumper from the Remote Shutdown Panel.

1 IP-204

TASK TITLE: Open RWST to CV Pump Suction Valve (1CV112E) from the MCC JPM No.: IP-204 REV: 2013 NRC TPO No.: 4.D.OA-35 K&A No.: 006000 2.4.35 TASK No.: R-OA-099, Establish Emergency Control of K&A IMP: 3.8/4.0 Safe Shutdown equipment EXAMINEE: RO SRO (Circle One)

EVALUATOR: DATE:

The Examinee: PASSED this JPM. TIME STARTED:

FAILED TIME FINISHED:

JPM TIME: MINUTES CRITICAL ELEMENTS: (*) 3-6 APPROX COMPLETION TIME: 31 MINUTES CRITICAL TIME: NA EVALUATION METHOD: LOCATION:

PERFORM X IN PLANT X SIMULATE SIMULATOR GENERAL

REFERENCES:

1. 1BwOA ELEC-5, Attachment C, Rev. 105 MATERIALS:

1. 1BwOA ELEC-5, Attachment C, Rev. 105

2. PPE for electrical work TASK STANDARDS:

1. Open 1CV112E from the MCC.

TASK CONDITIONS:

1. You are an EO.

2. The Control Room has been evacuated.

3. 1BwOA PRI-5, Control Room Inaccessibility, is in progress.

4. 1CV112D is stuck closed and 1CV112E will not open locally due to the handwheel not engaging.

INITIATING CUES:

1. You have been directed to open 1CV112E at MCC 132X4 Cubicle C2 per 1BwOA ELEC-5. You have already obtained the jumper from the Remote Shutdown Panel.

2 IP-204

RECORD START TIME NOTE: The student must obtain/locate high voltage protective gear (face shield, apron or approved switching coverall, gloves, hardhat, eye protection) to perform this JPM. It is NOT necessary to don the gear for the simulation.

NOTE: DO NOT ALLOW EXAMINEE TO ACTUALLY OPEN THE MCC CUBICLE DOOR. It is the intent of this JPM for the examinee to locate the MCC cubicle that the jumper will be installed in and explain how the MCC door can be opened. The evaluator should then show the examinee the attached photo of an open MCC and the remainder of the JPM will consist of the examinee explaining their actions to the evaluator using the photo.

PERFORMANCE STEP STANDARD Circle applicable

1. Refer to 1BwOA ELEC-5, Attachment Locate and open 1BwOA ELEC-5, SAT UNSAT N/A C, step 1. Attachment C, step 1. Comments:

CUE: After examinee locates procedure, provide a copy

2. Locate proper MCC and cubicle. Locate MCC 132X4, Cub C2. SAT UNSAT N/A Comments:

3. De-energize valve. Turn Breaker OFF and OPEN SAT UNSAT N/A cubicle door for valve to be Comments:

CUE: Brkr is OFF and Cubicle opened.

door is OPEN.

NOTE: At this point provide examinee with attached photo of 480V MCC valve breaker cubicle.

4. Install jumper. Remove terminal cover, then SAT UNSAT N/A install jumper between points 2 Comments:

and 3 on terminal board at front of CUE: Jumper is installed the cubicle. (Point out to evaluator between points 2 and 3. on photo where jumper will be installed) 3 IP-204

5. Override interlock and then turn Override breaker/door interlock, SAT UNSAT N/A breaker on. then turn breaker ON. (Point out Comments:

NOTE: The door interlock for to evaluator on photo how breaker closing the breaker with the door closing interlock will be over open, is defeated by pushing the ridden) steel bar (that protrudes through a slot in the top of the cubicle bucket above the breaker handle) toward the rear of the cubicle.

NOTE: The interlock screw above the breaker handle is NOT the correct interlock for this JPM. The screw is used to defeat the interlock that prevents opening the door while the breaker is closed. If the examinee tries to use that interlock to close the breaker with the door open, CUE the examinee that the breaker will not close.

CUE: Interlock is overridden, breaker is ON, O contactor energizes.

6. Restore breaker. When O contactor drops out: SAT UNSAT N/A Comments:

CUE: O contactor has dropped out.

Immediately turn breaker Breaker is Off. OFF.

Remove the jumper.

Jumper is removed. o Install terminal cover.

Terminal cover is installed.

Close the cubicle door.

Cubicle door is closed.

7. Verify valve position Verify valve position locally by SAT UNSAT N/A visual inspection. Comments:

CUE: Another EO at 1CV112E reports that 1CV112E is open.

CUE: THIS COMPLETES THIS JPM.

RECORD STOP TIME COMMENTS:

4 IP-204

SIMULATOR SETUP INSTRUCTIONS JPM NO: IP-204 REQUIRED SIMULATOR MODE (S): N/A, IN PLANT MALFUNCTION #S: N/A COMMENTS:

(Final) 5 IP-204

LOCAL EMERGENCY CONTROL OF SAFE REV. 105 1BwOA SHUTDOWN EQUIPMENT ELEC-5 UNIT 1 A. PURPOSE This procedure provides the actions required for local emergency control of loads necessary for safe shutdown operation of the plant.

B. SYMPTOMS OR ENTRY CONDITIONS

1) The following conditions may cause entry into this procedure:

o Any event causing a loss of normal controls for safe shutdown equipment when operation of that equipment is necessary for safe plant control.

o A loss of normal control of a 480V, 4KV or 6.9KV breaker.

o A loss of normal control of a motor operated valve where local operation is NOT prudent.

Page 1 of 27

LOCAL EMERGENCY CONTROL OF SAFE REV. 105 1BwOA SHUTDOWN EQUIPMENT ELEC-5 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

>>¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥ CAUTION Operators shall wear high voltage protective gear when operating any circuit breaker locally.

¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥º

>>¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥ CAUTION Local closure of a breaker will start equipment with its starting interlocks disabled.

¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥º

NOTE *

ALL ESF equipment operated in the *

local emergency mode should be *

powered from ONE ESF Bus. *

Non-emergency mode equipment should *

be powered from the other ESF bus. *

NOTE *

With this procedure in effect, the *

Emergency Director shall evaluate *

for Emergency Plan conditions.

1 IMPLEMENT APPROPRIATE ATTACHMENT ATTACHMENT::

o 4KV or 6.9KV Breaker Local Operation:

o Closing Breaker -

ATTACHMENT A, Step 1 (Page 4) o Opening Breaker -

ATTACHMENT A, Step 3 (Page 7)

Step continued on next page Page 2 of 27

LOCAL EMERGENCY CONTROL OF SAFE REV. 105 1BwOA SHUTDOWN EQUIPMENT ELEC-5 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED Step 1 (continued) o 480V Rackable Breaker Local Operation:

o Closing Breaker -

ATTACHMENT B, Step 1 (Page 8) o Opening Breaker -

ATTACHMENT B, Step 2 (Page 9) o Motor Operated Valve (MOV)

Local Operation:

o Open MOV -

ATTACHMENT C, Step 1 (Page 10) o Close MOV -

ATTACHMENT C, Step 2 (Page 13) o Component Cooling Pump Local Start -

ATTACHMENT D (Page 17) o SVAG VALVE MCC energization -

ATTACHMENT E (Page 22)

-END-Page 3 of 27

LOCAL EMERGENCY CONTROL OF SAFE REV. 105 1BwOA SHUTDOWN EQUIPMENT ELEC-5 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT A (PG 1 OF 4) 4KV OR 6.9KV BREAKER LOCAL OPERATION

>>¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥ CAUTION EITHER of the following will disable protective trips on 4KV or 6.9KV equipment:

o Loss of DC control power o Control power fuses removed

¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥º 1 LOCAL CLOSING OF 4KV OR 6.9KV BREAKERS BREAKERS::

a. Check breaker - RACKED IN a. Perform the following:

1) Pull the trip and close circuit fuse(s).

2) Rack the breaker in.

3) Verify floor trip mechanism reset.

b. Check relay targets - NOT UP b. IF redundant equipment is available, THEN RETURN TO Step 1a.

IF NO equipment is available, THEN RETURN TO procedure and step in effect.

c. Check trip and close circuit c. Install the fuses.

fuses - INSTALLED

d. Check closing spring - CHARGED d. Charge spring with the charging lever.

e. Verify MCR control switch in -

AFTER TRIP

f. Close breaker with close reach rod Step continued on next page Page 4 of 27

LOCAL EMERGENCY CONTROL OF SAFE REV. 105 1BwOA SHUTDOWN EQUIPMENT ELEC-5 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT A (PG 2 OF 4) 4KV OR 6.9KV BREAKER LOCAL OPERATION Step 1 (continued)

g. Verify equipment - RUNNING RUNNING:

g. IF redundant equipment is available, o Breaker indicates - CLOSED THEN RETURN TO Step 1a.

o Ammeter at MCB indicates - IF ALL available equipment RUN CURRENT fails to start, THEN GO TO Step 2 (Next o Local Observation Page).

h. Verify associated ESF pump h. Establish alternate means cubicle cooler(s) - RUNNING of cooling for ESF pump cubicle(s).

i. RETURN TO procedure and step in effect.

Page 5 of 27

LOCAL EMERGENCY CONTROL OF SAFE REV. 105 1BwOA SHUTDOWN EQUIPMENT ELEC-5 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT A (PG 3 OF 4) 4KV OR 6.9KV BREAKER LOCAL OPERATION

>>¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥ CAUTION Do NOT attempt to close a breaker without control power if its power cable is damaged.

¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥º 2 START OF EQUIPMENT WITHOUT CONTROL POWER POWER::

a. Select equipment for start without control power

b. Check relay targets - NOT UP b. IF redundant equipment is available, THEN RETURN TO Step 2a.

IF NO equipment is available, THEN RETURN TO procedure and step in effect.

c. Pull trip and close circuit fuses

d. Check closing spring - CHARGED d. Charge spring with the charging lever.

e. Close breaker with close reach rod

f. Verify equipment - RUNNING :

RUNNING: f. IF redundant equipment is available, o Breaker indicates - CLOSED THEN RETURN TO Step 2a.

o Ammeter at MCB indicates - IF ALL available equipment RUN CURRENT fails to start, THEN RETURN TO procedure o Local observation and step in effect.

g. Verify associated ESF pump g. Establish alternate means cubicle cooler(s) - RUNNING of cooling for ESF pump cubicle(s).

h. RETURN TO procedure and step in effect.

Page 6 of 27

LOCAL EMERGENCY CONTROL OF SAFE REV. 105 1BwOA SHUTDOWN EQUIPMENT ELEC-5 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT A (PG 4 OF 4) 4KV OR 6.9KV BREAKER LOCAL OPERATION 3 LOCAL OPENING OF 4KV OR 6.9KV BREAKERS BREAKERS::

a. Pull trip and close circuit fuses

b. Open breaker using open reach rod

c. RETURN TO procedure and step in effect.

-END-Page 7 of 27

LOCAL EMERGENCY CONTROL OF SAFE REV. 105 1BwOA SHUTDOWN EQUIPMENT ELEC-5 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT B (PG 1 OF 2) 480V RACKABLE BREAKER LOCAL OPERATION

NOTE *

480 Volt breakers protective trips *

do NOT require control power to *

function. *

NOTE *

When shifting RCFC's from high to *

low speed a 20 second time delay *

must be observed to prevent *

equipment damage. *

1 LOCAL CLOSING OF 480V BREAKERS BREAKERS:

a. Check breaker - RACKED IN a. Perform the following:

1) Pull the trip and close circuit fuse.

2) Rack the breaker in.

b. Check trip and close circuit b. Install the fuse.

fuse - INSTALLED

c. Check closing spring - CHARGED c. Charge the closing spring.

d. Verify MCR control switch in -

AFTER TRIP

e. Depress CLOSE pushbutton on front of breaker Step continued on next page Page 8 of 27

LOCAL EMERGENCY CONTROL OF SAFE REV. 105 1BwOA SHUTDOWN EQUIPMENT ELEC-5 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT B (PG 2 OF 2) 480V RACKABLE BREAKER LOCAL OPERATION Step 1 (continued)

f. Check equipment - RUNNING RUNNING:

f. IF redundant equipment is available, o Breaker indicates - CLOSED THEN RETURN TO Step 1a (Previous Page).

o Ammeter at MCB indicates -

RUN CURRENT IF ALL available equipment fails to start, o Local Observation THEN perform the following:

1) Select equipment to start without control power.

2) Pull the trip and close circuit fuse for the selected equipment.

3) RETURN TO Step 1c (Previous Page).

g. RETURN TO procedure and step in effect 2 LOCAL OPENING OF 480V BREAKERS BREAKERS::

a. Pull trip and close circuit fuse

b. Depress TRIP pushbutton on front of breaker

c. RETURN TO procedure and step in effect

-END-Page 9 of 27

LOCAL EMERGENCY CONTROL OF SAFE REV. 105 1BwOA SHUTDOWN EQUIPMENT ELEC-5 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT C (PG 1 OF 7)

MOTOR OPERATED VALVE (MOV) LOCAL OPERATION

NOTE *

If a seal-in signal is present the *

MOV will reclose after the "O" *

contactor drops out, unless the MOV *

is IMMEDIATELY deenergized. *

NOTE *

Valves 1SI8811A or B can not be *

jumpered OPEN without first lifting *

the lead to defeat the shorting *

circuit.

1 TO OPEN ANY MOV (480 VOLT MCC)

MCC):

a. Turn breaker OFF

b. Open cubicle door for valve to be opened Step continued on next page Page 10 of 27

LOCAL EMERGENCY CONTROL OF SAFE REV. 105 1BwOA SHUTDOWN EQUIPMENT ELEC-5 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT C (PG 2 OF 7)

MOTOR OPERATED VALVE (MOV) LOCAL OPERATION Step 1 (continued)

c. Check valve - NOT LISTED BELOW BELOW:

c. Locally open valve(s):

1SI8811A o Open electrically from 1SI8811B breaker:

a) Lift lead from Point 10 on terminal strip at front of cubicle to defeat shorting circuit:

o 1SI8811A MCC 131X1 M3 (364' S12) o 1SI8811B MCC 132X4 H1 (426' S12) b) Tape end of lead.

c) Notify the control room to log lifted lead in TCC Log.

d) GO TO Step 1d o Open manually at valve:

a) Locally open valve using the handwheel.

b) RETURN TO procedure and step in effect.

d. Install jumper between points 2 and 3 on terminal board at front of cubicle

e. Override breaker and door interlock

f. Turn breaker ON Step continued on next page Page 11 of 27

LOCAL EMERGENCY CONTROL OF SAFE REV. 105 1BwOA SHUTDOWN EQUIPMENT ELEC-5 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT C (PG 3 OF 7)

MOTOR OPERATED VALVE (MOV) LOCAL OPERATION Step 1 (continued)

g. WHEN "O" contactor drops out, THEN immediately turn breaker OFF

h. Remove jumper

i. Close cubicle door

j. Check valve position by local j. Locally open valve at inspection if possible Shift Manager's discretion.

k. RETURN TO procedure and step in effect Page 12 of 27

LOCAL EMERGENCY CONTROL OF SAFE REV. 105 1BwOA SHUTDOWN EQUIPMENT ELEC-5 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT C (PG 4 OF 7)

MOTOR OPERATED VALVE (MOV) LOCAL OPERATION

NOTE *

If a seal-in signal is present the *

MOV will reopen after the "C" *

contactor drops out, unless the MOV *

is IMMEDIATELY deenergized. *

NOTE *

The valves listed in step 2c (Next *

Page) can not be jumpered Closed *

without first lifting a lead to *

defeat the shorting circuit. *

NOTE *

Valves 1AF013C, D, G and H require *

placing the RSDP Transfer Control *

Switch in LOCAL to defeat the *

shorting circuit. Transfer switch *

must be maintained in LOCAL after *

use.

2 TO CLOSE ANY MOV (480 VOLT MCC)

MCC):

a. Turn breaker OFF

b. Open cubicle door for valve to be closed Step continued on next page Page 13 of 27

LOCAL EMERGENCY CONTROL OF SAFE REV. 105 1BwOA SHUTDOWN EQUIPMENT ELEC-5 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT C (PG 5 OF 7)

MOTOR OPERATED VALVE (MOV) LOCAL OPERATION Step 2 (continued)

c. Check valve - NOT LISTED BELOW BELOW:

c. Locally close valve:

1CV112B o Close electrically from 1CV112C breaker:

1CV8110 1CV8111 a) Lift lead to defeat 1SX004 shorting ciruit:

1SX010 1SX011 o 1CV112B MCC 131X5 1SX033 A5 (426' Q16) 1SX034 (Point 13) 1SX136 o 1CV112C MCC 132X4 G1 (426' S12 CWA)

(Point-13) o 1CV8110 MCC 131X1 M1 (364' S12)

(Point 14) o 1CV8111 MCC 132X4 C4 (426' S12)

(Point 14) o 1SX004 MCC 131X1 A2 (364' S12)

(Point-13) o 1SX010 MCC 132X1 H4 (364' P18)

(Point-13) o 1SX011 MCC 132X1 B2 (364' P18)

(Point-13) o 1SX033 MCC 131X1 A4 (364' S12)

(Point-13) o 1SX034 MCC 132X1 B4 (364' P18)

(Point-13) o 1SX136 MCC 132X1 H5 (364' P18)

(Point-13) b) Tape end of lead.

Step continued on next page Page 14 of 27

LOCAL EMERGENCY CONTROL OF SAFE REV. 105 1BwOA SHUTDOWN EQUIPMENT ELEC-5 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT C (PG 6 OF 7)

MOTOR OPERATED VALVE (MOV) LOCAL OPERATION Step 2 (continued) c) Notify the control room to log lifted lead in TCC Log.

d) GO TO Step 2e.

o Locally close valve using the hand wheel.

d. Check valve - NOT LISTED BELOW BELOW:

d. Close electrically from breaker:

1AF013C 1AF013D 1) Defeat shorting circuit:

1AF013G 1AF013H a) Place RSDP Local/Remote Transfer C/S in LOCAL.

b) Install a jumper between points 21 and 5 on terminal board in front of cubicle.

2) Notify the control room to log jumper in TCC Log.

3) Notify the control room to log switch position using an Abnormal Component Position Sheet.

4) GO TO Step 2f (Next Page).

e. Install jumper between points 4 and 5 on terminal board at front of cubicle Step continued on next page Page 15 of 27

LOCAL EMERGENCY CONTROL OF SAFE REV. 105 1BwOA SHUTDOWN EQUIPMENT ELEC-5 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT C (PG 7 OF 7)

MOTOR OPERATED VALVE (MOV) LOCAL OPERATION Step 2 (continued)

f. Override breaker and door interlock

g. Turn breaker ON

h. WHEN "C" contactor drops out, THEN immediately turn breaker OFF

i. Remove jumper

j. Close cubicle door

k. Check valve position by local k. IF unable to electrically inspection if possible close valve, THEN locally close at Shift Manager's discretion.

l. RETURN TO procedure and step in effect

-END-Page 16 of 27

LOCAL EMERGENCY CONTROL OF SAFE REV. 105 1BwOA SHUTDOWN EQUIPMENT ELEC-5 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT D (PG 1 OF 5)

COMPONENT COOLING PUMP LOCAL START

>>¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥ CAUTION EITHER of the following will disable the protective trips on the CC pumps:

o Loss of DC control power o Control power fuses removed

¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥º

>>¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥ CAUTION For the U-0 CC pump to trip on low surge tank level, the control power fuses must be installed in EITHER the 1A CC pump breaker if the U-0 pump is racked into Bus 141 OR in the 1B CC pump breaker if the U-0 pump is racked into Bus 142.

¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥º

NOTE *

The U-0 CC pump has a bus breaker *

and a local breaker in series. The *

local breaker is interlocked to *

close when the bus breaker closes.

1 CC PUMP LOCAL EMERGENCY START :

START:

a. Check selected pump a. Perform the following:

breaker(s) - RACKED ININ:

1) Pull the trip and close o CC pump 1A (Bus 141 Cub 12) circuit fuses.

o CC pump 1B (Bus 142 Cub 9) 2) Rack the breaker(s) in.

o CC pump 0: 3) Verify floor trip mechanism reset.

Bus 141 Cub 18

-AND-Local Breaker for Bus 141 (383' N-17)

Step continued on next page Page 17 of 27

LOCAL EMERGENCY CONTROL OF SAFE REV. 105 1BwOA SHUTDOWN EQUIPMENT ELEC-5 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT D (PG 2 OF 5)

COMPONENT COOLING PUMP LOCAL START Step 1a (continued) o CC pump 0:

Bus 142 Cub 12

-AND-Local Breaker for Bus 142 (383' N-17)

b. Check relay targets - NOT UP b. IF redundant equipment is available, THEN RETURN TO Step 1a (Previous Page).

IF NO CC pumps are available, THEN RETURN TO procedure and step in effect.

c. Verify the following for EACH breaker to be closed:

1) Trip and close circuit 1) Install the fuses.

fuses - INSTALLED

2) Closing spring - CHARGED 2) Charge spring with the charging lever.

d. Verify MCR control switch in -

AFTER TRIP

e. Close breaker with close reach rod:

o CC pump 1A (Bus 141 Cub 12) o CC pump 1B (Bus 142 Cub 9) o CC pump 0 (Bus 141 Cub 18) o CC pump 0 (Bus 142 Cub 12)

Step continued on next page Page 18 of 27

LOCAL EMERGENCY CONTROL OF SAFE REV. 105 1BwOA SHUTDOWN EQUIPMENT ELEC-5 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT D (PG 3 OF 5)

COMPONENT COOLING PUMP LOCAL START Step 1 (continued)

f. Verify pump - RUNNING RUNNING:

f. IF the CC pump 0 did NOT start, o Breaker(s) indicate - CLOSED THEN close its associated breaker (383' N-17) with o Ammeter at MCB indicates - the close reach rod.

RUN CURRENT IF the selected pump did o Local observation NOT start, THEN RETURN TO Step 1a (Page 17) to start an alternate pump.

IF ALL available CC pumps fail to start, THEN GO TO Step 2 (Next Page).

g. RETURN TO procedure and step in effect.

Page 19 of 27

LOCAL EMERGENCY CONTROL OF SAFE REV. 105 1BwOA SHUTDOWN EQUIPMENT ELEC-5 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT D (PG 4 OF 5)

COMPONENT COOLING PUMP LOCAL START 2 START OF A CC PUMP WITHOUT CONTROL POWER POWER:

a. Select a CC pump for start without control power

b. Check relay targets - NOT UP b. IF redundant equipment is available, THEN RETURN TO Step 2a.

IF NO CC pumps are available, THEN RETURN TO procedure and step in effect.

c. Pull trip and close circuit fuses

d. Check closing spring - CHARGED d. Charge spring with the charging lever.

Step continued on next page Page 20 of 27

LOCAL EMERGENCY CONTROL OF SAFE REV. 105 1BwOA SHUTDOWN EQUIPMENT ELEC-5 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT D (PG 5 OF 5)

COMPONENT COOLING PUMP LOCAL START Step 2 (continued)

e. Close breaker(s) with close reach rod:

o CC pump 1A (Bus 141 Cub 12) o CC pump 1B (Bus 142 Cub 9) o CC pump 0:

Bus 141 Cub 18

-AND-Local Breaker for Bus 141 (383' N-17) o CC pump 0:

Bus 142 Cub 12

-AND-Local Breaker for Bus 142 (383' N-17)

f. Verify pump - RUNNING RUNNING:: f. IF redundant equipment is available, o Breaker(s) indicate - CLOSED THEN RETURN TO Step 2a (Previous Page).

o Ammeter at MCB indicates -

RUN CURRENT IF NO CC pumps are available, o Local observation THEN RETURN TO procedure and step in effect.

g. RETURN TO procedure and step in effect.

-END-Page 21 of 27

LOCAL EMERGENCY CONTROL OF SAFE REV. 105 1BwOA SHUTDOWN EQUIPMENT ELEC-5 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT E (PG 1 OF 6)

SVAG VALVE MCC ENERGIZATION 1 ENERGIZE DESIRED MCC(S)

MCC(S):

o Train A SI accumulator discharge valves (MCC 131X2A) -

GO TO STEP 2 (Next Page) o Train B SI accumulator discharge valves (MCC 132X2A) -

GO TO STEP 3 (Page 24) o Train A SVAG VALVES (MCC 131X1A) -

GO TO STEP 4 (Page 25) o Train B SVAG VALVES (MCC 132X4A) -

GO TO STEP 5 (Page 26)

Page 22 of 27

LOCAL EMERGENCY CONTROL OF SAFE REV. 105 1BwOA SHUTDOWN EQUIPMENT ELEC-5 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT E (PG 2 OF 6)

SVAG VALVE MCC ENERGIZATION 2 TRAIN A (1SI8808A AND D)

D):

a. Locally energize MCC 131X2A (414' S12 CWA):

1) Turn MCC 131X2 B2 - OFF

2) Open cubicle door

3) Install jumper between point 1 and 3A on terminal board at front of cubicle

4) Override breaker and door interlock

5) Turn breaker MCC 131X2 B2 -

ON

6) Check MCC 131X2A - ENERGIZED

b. Locally close SI accumulator b. Locally close valve(s):

discharge valves per 1BwOA ELEC-5, LOCAL EMERGENCY CONTROL o 1SI8808A (412' R15 OMB)

OF SAFE SHUTDOWN EQUIPMENT o 1SI8808D (412' R9 OMB)

MCC 131X2A A3 (1SI8808A)

(414' S12 CWA)

MCC 131X2A A2 (1SI8808D)

(414' S12 CWA)

c. Locally de-energize MCC 131X2A (414' S12 CWA):

1) Turn MCC 131X2 B2 - OFF

2) Remove jumper

3) Close cubicle door

4) Turn MCC 131X2 B2 - ON Page 23 of 27

LOCAL EMERGENCY CONTROL OF SAFE REV. 105 1BwOA SHUTDOWN EQUIPMENT ELEC-5 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT E (PG 3 OF 6)

SVAG VALVE MCC ENERGIZATION 3 TRAIN B (1SI8808B AND C)

C):

a. Locally energize MCC 132X2A (426' S12 CWA):

1) Turn MCC 132X2 B2 - OFF

2) Open cubicle door

3) Install jumper between point 1 and 3A on terminal board at front of cubicle

4) Override breaker and door interlock

5) Turn breaker MCC 132X2 B2 -

ON

6) Check MCC 132X2A - ENERGIZED

b. Locally close SI accumulator b. Locally close valve(s):

discharge valves per 1BwOA ELEC-5, LOCAL EMERGENCY CONTROL o 1SI8808B (412' R18 OMB)

OF SAFE SHUTDOWN EQUIPMENT o 1SI8808C (412' R5 OMB)

MCC 132X2A A3 (1SI8808B)

(426' S12 CWA)

MCC 132X2A A2 (1SI8808C)

(426' S12 CWA)

c. Locally de-energize MCC 132X2A (426' S12 CWA):

1) Turn MCC 132X2 B2 - OFF

2) Remove jumper

3) Close cubicle door

4) Turn MCC 132X2 B2 - ON Page 24 of 27

LOCAL EMERGENCY CONTROL OF SAFE REV. 105 1BwOA SHUTDOWN EQUIPMENT ELEC-5 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT E (PG 4 OF 6)

SVAG VALVE MCC ENERGIZATION 4 TRAIN A SVAG VALVES VALVES:

a. Locally energize MCC 131X1A (364' S12 CWA):

1) Turn MCC 131X1 M2 - OFF

2) Open cubicle door

3) Lift lead from Point 14 on terminal strip at front of cubicle to defeat shorting circuit

4) Tape end of lead.

5) Notify the control room to log lifted lead in TCC log

6) Install jumper between points 1 and 3 on control relay in front of cubicle

7) Override breaker and door interlock

8) Turn breaker MCC 131X1 M2 -

ON

9) Check MCC 131X1A - ENERGIZED

b. Align valve(s) as required:

o Control switch o 1BwOA ELEC-5, LOCAL EMERGENCY CONTROL OF SAFE SHUTDOWN EQUIPMENT

c. Locally de-energize MCC 131X1A (364' S12 CWA):

1) Turn MCC 131X1 M2 - OFF

2) Remove jumper

3) Untape and land lead from Point 14 on terminal strip at front of cubicle

4) Notify control room that lead was landed

5) Close cubicle door

6) Turn MCC 131X1 M2 - ON Page 25 of 27

LOCAL EMERGENCY CONTROL OF SAFE REV. 105 1BwOA SHUTDOWN EQUIPMENT ELEC-5 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT E (PG 5 OF 6)

SVAG VALVE MCC ENERGIZATION 5 TRAIN B SVAG VALVES VALVES:

a. Locally energize MCC 132X4A (426' S12 CWA):

1) Turn MCC 132X4 K2 - OFF

2) Open cubicle door

3) Lift lead from Point 14 on terminal strip at front of cubicle to defeat shorting circuit

4) Tape end of lead.

5) Notify the control room to log lifted lead in TCC log

6) Install jumper between points 1 and 3 on control relay in front of cubicle

7) Override breaker and door interlock

8) Turn breaker MCC 132X4 K2 -

ON

9) Check MCC 132X4A - ENERGIZED

b. Align valve(s) as required:

o Control switch o 1BwOA ELEC-5, LOCAL EMERGENCY CONTROL OF SAFE SHUTDOWN EQUIPMENT Step continued on next page Page 26 of 27

LOCAL EMERGENCY CONTROL OF SAFE REV. 105 1BwOA SHUTDOWN EQUIPMENT ELEC-5 UNIT 1 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT E (PG 6 OF 6)

SVAG VALVE MCC ENERGIZATION Step 5 (continued)

c. Locally de-energize MCC 132X4A (426' S12 CWA):

1) Turn MCC 132X4 K2 - OFF

2) Remove jumper

3) Untape and land lead from Point 14 on terminal strip at front of cubicle

4) Notify control room that lead was landed

5) Close cubicle door

6) Turn MCC 132X4 K2 - ON

-END-Page 27 of 27

JOB PERFORMANCE MEASURE TASK CONDITIONS:

1. You are an extra NSO.

2. A loss of Essential Service Water is in progress on Unit 2.

3. 2A CV pump is not running.

INITIATING CUES:

1. The Unit Supervisor has directed you to align Fire Protection Cooling ONLY to the 2A Centrifugal Charging Pump per 2BwOA PRI-8, ESSENTIAL SERVICE WATER MALFUNCTION, Attachment C.

2. 2A CV pump will remain in standby.

3. Inform the Unit Supervisor when you have aligned Fire Protection Cooling to the 2A Centrifugal Charging Pump.

IP-406S Page 1 of 4

TASK TITLE: Align Fire Protection Cooling to the 2A Centrifugal Charging Pump JPM No.: IP-406S REV: 2013 NRC Task No.: R-CV-23 K&A No.: K2.1.30 Objective No.: 4.D.OA-69 K&A IMP: 4.4/4.0 EXAMINEE: RO SRO (Circle One)

EVALUATOR: DATE:

The Examinee: PASSED this JPM. TIME STARTED:

FAILED TIME FINISHED:

JPM TIME: MINUTES CRITICAL ELEMENTS: (*) 2, 3 APPROX COMPLETION TIME: 15 MINUTES CRITICAL TIME: NA EVALUATION METHOD: LOCATION:

PERFORM X IN PLANT X SIMULATE SIMULATOR GENERAL

REFERENCES:

1. 2BwOA PRI-8, ESSENTIAL SERVICE WATER MALFUNCTION, Rev 105.

MATERIALS:

2. 2BwOA PRI-8, ESSENTIAL SERVICE WATER MALFUNCTION, Rev 105.

TASK STANDARDS:

1. Connect FP hose between FP system and SX system.

2. Align FR system to 2A CV pump oil cooler.

TASK CONDITIONS:

1. You are an extra NSO.

2. A loss of Essential Service Water is in progress on Unit 2.

3. 2A CV pump is not running.

INITIATING CUES:

1. The Unit 2 Unit Supervisor has directed you to align Fire Protection Cooling ONLY to the 2A Centrifugal Charging Pump per 2BwOA PRI-8, ESSENTIAL SERVICE WATER MALFUNCTION, Attachment C.

2. 2A CV pump will remain in standby.

3. Inform the Unit 2 Unit Supervisor when you have aligned Fire Protection Cooling to the 2A Centrifugal Charging Pump.

IP-406S Page 2 of 4

RECORD START TIME:

PERFORMANCE STEP STANDARD CIRCLE APPLICABLE

1. Refer to 2BwOA PRI-8, Locate and open 2BwOA PRI- SAT UNSAT N/A ESSENTIAL SERVICE WATER 8, ESSENTIAL SERVICE Comments:

MALFUNCTION. WATER MALFUNCTION, CUE: After examinee locates Attachment C.

procedure, provide copy

Determine 2A CV pump of 2BwOA PRI-8, selected for FP alignment Attachment C. (from initial cue).

2. Connect and align fire hose. Connect and align fire hose SAT UNSAT N/A

Locate fire hose in 2A CV Comments:

pump room.

Connect one end of fire hose to CV pump 2A lube oil cooler.

CUE: FP Supply Hose

Connect opposite end of Connected fire hose to FP connection outside 2A CV Pump room (364 V18).

Determine FP hose NOT required to be connected to 1A CV pump (from initiating cue, only 2A CV pump to be aligned to FP cooling).

CUE: 0FP840 is rotated

Open 0FP840, 1A/2A CV counter clockwise until pump oil cooler alternate the valve handwheel cooling water supply tie stops. valve (364 V18)

CUE: Hose is not pinched by

Verify fire hose charged room door. No kinks in hose

Hose not pinched by room door.

No kinks in hose.

IP-406S Page 3 of 4

PERFORMANCE STEP STANDARD CIRCLE APPLICABLE

3. Align FP cooling to oil cooler Align FP to CHG PUMP Lube SAT UNSAT N/A CUE: 2SX259A is rotated Oil Cooler: Comments:

counter clockwise until

Open 2SX259A, 2A CV the valve handwheel pump FP supply to oil stops. cooler isolation valve (364 CUE: 2SX258A is rotated U20 in 2A CV ump room).

clockwise until the valve

Close 2SX258A, 2A CV handwheel stops. pump gear and oil cooler isolation valve (364 U20 in 2A CV ump room).

4. Check Centrifugal Charging Pump Check Centrifugal Charging SAT UNSAT N/A 2A Operation: Pump 2A Operation: Comments:

CUE: 2A CV Pump is not

2A CV pump is not running running. (from initiating cue)

Determine 2A CV pump is being aligned for standby operation (from initiating cue)

5. Check if FP alignment required for Check if FP alignment 2B CV pump: required for 2B CV pump:

Determine 2A CV pump selected for FP alignment (from initial cue).

Return to procedure and CUE: As Unit Supervisor, step in effect.

acknowledge report.

Inform US FP aligned to 2A CV pump.

NOTE: The alignment does render the 2A CV pump inoperable, even though the pump will function.

CUE: THIS COMPLETES THIS JPM.

RECORD STOP TIME:

COMMENTS:

(Final)

IP-406S Page 4 of 4

REV. 105 ESSENTIAL SERVICE WATER MALFUNCTION 2BwOA UNIT 2 PRI-8 A. PURPOSE This procedure provides actions required in the event of a malfunction of the Essential Service Water system.

B. SYMPTOMS OR ENTRY CONDITIONS

1) The following annunciators may cause entry into this procedure:

o CNMT DRAIN LEAK DETECT FLOW HIGH (2-1-A2) o SX PUMP TRIP (2-2-A1) o SX PUMP DSCH HDR PRESS LOW (2-2-A2) o SX PUMP DSCH HDR TEMP HIGH/LOW (2-2-B2) o SX PUMP SUCT PRESS LOW (2-2-C1) o SX STRN DP HIGH (2-2-C2) o SX PUMP SUCT VLV PIT LEVEL HIGH (2-2-D2)

Page 1 of 29

REV. 105 ESSENTIAL SERVICE WATER MALFUNCTION 2BwOA UNIT 2 PRI-8 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

NOTE *

With this procedure in effect, the *

Emergency Director shall evaluate *

for Emergency Plan conditions.

1 CHECK FOR EXCESSIVE LEAKAGE IN GO TO ATTACHMENT A, Step 1 AUX BUILDING BUILDING:

(Page 15).

Contact Radwaste to monitor aux building sumps:

Aux Bldg sumps - NORMAL SX PUMP SUCT VLV PIT LEVEL HIGH (2-2-D2) - NOT LIT 2 CHECK STATUS OF SX PUMPS PUMPS:

a. SX pumps - AT LEAST ONE RUNNING a. Perform the following for the SX train to be started:

1) Verify the following valves open:

o Train A 2SX001A 2SX016A 2SX027A

-OR-o Train B 2SX001B 2SX016B 2SX027B

2) Start the selected SX pump.

IF NO UNIT 2 SX pump(s) can be started, THEN GO TO

ATTACHMENT B (Page 18).

Page 2 of 29

REV. 105 ESSENTIAL SERVICE WATER MALFUNCTION 2BwOA UNIT 2 PRI-8 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 3 CHECK STATUS OF SX SYSTEM SYSTEM::

a. SX PUMP SUCT PRESSURE LOW a. Perform the following:

(2-2-C1) - NOT LIT

1) Verify SX pump(s) suction valves are open:

2SX001A 2SX001B

2) Dispatch an operator to verify traveling screens clear of icing/debris.

b. SX STRN DP HIGH (2-2-C2) - NOT b. Locally backwash LIT strainer(s) per BwOP SX-6, ESSENTIAL SERVICE WATER STRAINER MANUAL OPERATION

c. SX PUMP DSCH HDR PRESS LOW c. Perform the following:

(2-2-A2) - NOT LIT o Start an additional SX pump.

o Locally verify the SX pump discharge strainers are NOT backwashing.

Step continued on next page Page 3 of 29

REV. 105 ESSENTIAL SERVICE WATER MALFUNCTION 2BwOA UNIT 2 PRI-8 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED Step 3 (continued) o Locally adjust SX outlet from CC heat exchanger valve(s) while maintaining outlet temperature(s) less than 105 105F:

o 2SX007 (346' M20):

1) Close 2SX007E, Local Disc Sw.

2) Throttle 2SX007 as required.

3) WHEN adjustments are complete, THEN open 2SX007E, Local Disc Sw.

o 0SX007 (346' M16):

1) Close 0SX007E, Local Disc Sw.

2) Throttle 0SX007 as required.

3) WHEN adjustments are complete, THEN open 0SX007E Local Disc Sw.

Step continued on next page Page 4 of 29

REV. 105 ESSENTIAL SERVICE WATER MALFUNCTION 2BwOA UNIT 2 PRI-8 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED Step 3 (continued)

IF SX pump discharge header pressure can NOT be restored, THEN perform the following:

a) Monitor temperatures of equipment cooled by SX.

b) Shutdown ANY unnecessary equipment:

o DG(s) o MCR chiller(s) o SI pump(s) o RCFC(s) o Containment chiller(s) c) Close the SX outlet valve for ANY shutdown RCFC train(s):

o 2SX027A o 2SX027B d) IF CENT CHG pump temperatures are approaching the limits of TABLE A (Page 29),

THEN align FP to a CENT CHG pump lube oil cooler per ATTACHMENT C (Page 23) while continuing with this procedure:

o CENT CHG pump 2A o CENT CHG pump 2B e) Shutdown ANY vital equipment exceeding the limits of TABLE A (Page 29).

Step continued on next page Page 5 of 29

REV. 105 ESSENTIAL SERVICE WATER MALFUNCTION 2BwOA UNIT 2 PRI-8 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED Step 3 (continued) f) At Shift Manager discretion align UNIT 1 SX to cool Unit 2 CC loads via the Unit 0 CC heat exchanger:

1) Open CC HX 0 SX inlet valve:

1SX005

2) Open the CC HX 0 SX outlet valve(s):

o 0SX146 o 0SX147

3) Align the UNIT 0 CC heat exchanger to Unit 2 per BwOP CC-8, ISOLATION OF CC BETWEEN UNITS 1 AND 2.

Step continued on next page Page 6 of 29

REV. 105 ESSENTIAL SERVICE WATER MALFUNCTION 2BwOA UNIT 2 PRI-8 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED Step 3 (continued)

d. SX PUMP DSCH HDR TEMP HIGH LOW d. Perform the following:

(2-2-B2) - NOT LIT

1) Start an additional SX pump at Shift Manager discretion.

2) Monitor temperatures of running equipment cooled by SX.

3) Shutdown ANY unnecessary equipment:

o DG(s) o MCR chiller(s) o SI pump(s) o RCFC(s) o Containment chiller(s)

4) Close the SX outlet valve for ANY shutdown RCFC train(s):

o 2SX027A o 2SX027B

5) IF CENT CHG pump temperatures are approaching the limits of TABLE A (Page 29),

THEN align FP to a CENT CHG pump lube oil cooler per ATTACHMENT C (Page 23) while continuing with this procedure:

o CENT CHG pump 2A o CENT CHG pump 2B

6) Shutdown ANY vital equipment exceeding the limits of TABLE A (Page 29).

Step continued on next page Page 7 of 29

REV. 105 ESSENTIAL SERVICE WATER MALFUNCTION 2BwOA UNIT 2 PRI-8 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED Step 3 (continued)

7) At Shift Manager discretion align UNIT 1 SX to cool Unit 2 CC loads via the Unit 0 CC heat exchanger:

a) Open the CC HX 0 SX inlet valve:

1SX005 b) Open CC HX 0 SX outlet valve(s):

o 0SX146 o 0SX147 c) Align the UNIT 0 CC heat exchanger to Unit 2 per BwOP CC-8, ISOLATION OF CC BETWEEN UNITS 1 AND 2.

e. Locally check tripped SX e. Perform the following:

pump(s) - NOT ROTATING

1) Dispatch an operator to energize the affected pump's suction valve:

o 2SX001A at MCC 231X3 E4 (401' M20) o 2SX001B at MCC 232X1 C1 (383' M23)

2) Close affected pump's suction valve:

o 2SX001A o 2SX001B Page 8 of 29

REV. 105 ESSENTIAL SERVICE WATER MALFUNCTION 2BwOA UNIT 2 PRI-8 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 4 CHECK FOR SX LEAKAGE INTO Perform the following:

CONTAINMENT CONTAINMENT::

a. Verify only ONE SX pump CNMT DRAIN LEAK DETECT FLOW running.

HIGH (2-1-A2) - NOT LIT

b. Shutdown RCFC train for non-running SX pump:

1) Stop associated RCFCs:

o SX pump 2A:

RCFC 2A RCFC 2C o SX pump 2B:

RCFC 2B RCFC 2D

2) Close associated RCFC SX inlet valve:

o 2SX016A (SX pump 2A) o 2SX016B (SX pump 2B)

3) Close associated RCFC SX outlet valve:

o 2SX027A (SX pump 2A) o 2SX027B (SX pump 2B)

Step continued on next page Page 9 of 29

REV. 105 ESSENTIAL SERVICE WATER MALFUNCTION 2BwOA UNIT 2 PRI-8 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED Step 4 (continued)

c. Determine if leakage stopped:

o Monitor SX pump parameters:

Pump discharge pressure Pump amps o Monitor containment water level:

Floor drain sump level:

2LI-PC002 2LI-PC003 Floor water level:

2LI-PC006 2LI-PC007

d. IF leakage is stopped, THEN perform the following:

1) Verify the RCFC SX outlet rad monitor is online:

o 2PR02J o 2PR03J

2) GO TO Step 5 (Page 12).

Step continued on next page Page 10 of 29

REV. 105 ESSENTIAL SERVICE WATER MALFUNCTION 2BwOA UNIT 2 PRI-8 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED Step 4 (continued)

e. IF leakage still exists, THEN perform the following to swap running RCFC trains:

1) Open RCFC SX inlet valve for non-running SX pump:

o 2SX016A (SX pump 2A) o 2SX016B (SX pump 2B)

2) Open RCFC SX outlet valve for non-running SX pump:

o 2SX027A (SX pump 2A) o 2SX027B (SX pump 2B)

3) Swap running SX pumps.

4) Start non-running RCFCs.

5) RETURN TO Substep 4b RNO above.

Page 11 of 29

REV. 105 ESSENTIAL SERVICE WATER MALFUNCTION 2BwOA UNIT 2 PRI-8 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 5 CHECK CC OUTLET TEMPERATURE :

TEMPERATURE:

a. CC heat exchanger outlet a. Perform the following:

temperature(s) - LESS THAN 105 105F: 1) Locally throttle SX outlet from CC heat (2TI-674) exchanger valve(s) to (2TI-675) maintain CC temperature(s) less than 105 105F:

o 2SX007 (346' M20):

1) Close 2SX007E, Local Disc Sw.

2) Throttle 2SX007 as required.

3) WHEN adjustments are complete, THEN open 2SX007E, Local Disc Sw.

o 0SX007 (346' M16):

1) Close 0SX007E, Local Disc Sw.

2) Throttle 0SX007 as required.

3) WHEN adjustments are complete, THEN open 0SX007E Local Disc Sw.

2) IF RCP THERMAL BARR CC WTR TEMP HIGH (2-7-E3) is LIT, THEN maintain seal injection flow between 8 GPM and 13 GPM per pump.

Page 12 of 29

REV. 105 ESSENTIAL SERVICE WATER MALFUNCTION 2BwOA UNIT 2 PRI-8 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 6 CHECK RCP COOLING :

COOLING:

a. Check the following alarms - a. Monitor RCP temperatures.

NOT LIT LIT::

IF motor bearing RCP THERM BARR CC WTR TEMP temperature exceeds 195 F 195 HIGH (2-7-E3) OR lower radial bearing temperature exceeds 225 F 225 RCP BRNG CC WTR TEMP HIGH OR seal outlet temperature (2-7-E5) exceeds 235 235F, THEN perform the following:

a) Trip the reactor.

b) Trip the affected RCP(s).

c) Perform 2BwEP-0, REACTOR TRIP OR SAFETY INJECTION while continuing with this procedure.

7 NOTIFY THE SHIFT MANAGER TO PERFORM THE FOLLOWING FOLLOWING:

Risk Evaluation Initiate an IR Notify the following personnel as appropriate:

o Station Duty Manager o Station Duty Officer o Nuclear Duty Officer o Work Week Manager 8 REFER TO TECH SPECS SPECS:

3.6.6 3.7.8 3.7.9 Perform a risk assessment Page 13 of 29

REV. 105 ESSENTIAL SERVICE WATER MALFUNCTION 2BwOA UNIT 2 PRI-8 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 9 RETURN TO PROCEDURE AND STEP IN EFFECT

-END-Page 14 of 29

REV. 105 ESSENTIAL SERVICE WATER MALFUNCTION 2BwOA UNIT 2 PRI-8 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT A (PG 1 OF 3)

AUX BUILDING PIPING RUPTURE 1 PERFORM 0BWOA PRI-8, AUXILIARY BUILDING FLOODING, WHILE CONTINUING WITH THIS PROCEDURE 2 MONITOR TEMPERATURES ON RUNNING EQUIPMENT COOLED BY SX SX::

PPC Trend Page TR104 (BwOA PRI-8, SX MALFUNCTION)

CC heat exchanger outlet temperature 3 ALIGN FIRE PROTECTION TO CENT CHG PUMP LUBE OIL COOLERS COOLERS:

a. Dispatch an operator to align FP to CENT CHG pump(s) lube oil cooler per ATTACHMENT C (Page 23) while continuing with this procedure:

o CENT CHG pump 2A o CENT CHG pump 2B 4 PROTECT IMPORTANT EQUIPMENT EQUIPMENT:

a. Shutdown ANY unnecessary equipment:

o DG(s) o MCR chiller(s) o SI pump(s) o Containment chiller(s)

b. Place in PULL OUT ANY vital equipment - EXCEEDING THE LIMITS OF TABLE A (Page 29)

c. Dispatch an operator to prepare Startup FW pump for start per BwOP FW-5, OPERATION OF A STARTUP FW PUMP Page 15 of 29

REV. 105 ESSENTIAL SERVICE WATER MALFUNCTION 2BwOA UNIT 2 PRI-8 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT A (PG 2 OF 3)

AUX BUILDING PIPING RUPTURE 5 CHECK IF REACTOR SHUTDOWN REQUIRED REQUIRED::

a. Field reports indicate flooding a. Continue with Step 6 (Next of vital equipment (SX pumps in Page).

both rooms, RH pumps, etc.) - IF reports indicate IMMINENT flooding of vital equipment is imminent, THEN do Steps 5b thru 5j.

b. Trip the reactor

c. Perform 2BwEP-0, REACTOR TRIP OR SAFETY INJECTION while continuing with this procedure

d. Check WS pumps - ANY RUNNING d. Perform the following:

1) Place motor driven AF pump in - PULL OUT OUT::

AF pump 2A

2) Shutdown the following SX cooled equipment:

DG(s)

MCR chiller(s)

SI pump(s)

Containment chiller(s)

3) Control feed flow from the diesel driven AF pump to maintain narrow range levels - BETWEEN 42% AND 50%

4) GO TO Step 6 (Next Page).

e. Align normal feedwater per 2BwEP ES-0.1, REACTOR TRIP RESPONSE, ATTACHMENT C Step continued on next page Page 16 of 29

REV. 105 ESSENTIAL SERVICE WATER MALFUNCTION 2BwOA UNIT 2 PRI-8 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT A (PG 3 OF 3)

AUX BUILDING PIPING RUPTURE Step 5 (continued)

f. Control feed flow to maintain narrow range levels - BETWEEN 42% AND 50%

g. Place motor driven AF pump in -

PULL OUT OUT::

AF pump 2A

h. Shutdown the following SX cooled equipment:

DG(s)

MCR chiller(s)

SI pump(s)

Containment chiller(s)

i. Check all SG levels - GREATER i. Continue with Step 6.

THAN 42% WHEN all SG levels are greater than 42%

42%,,

THEN do Step 5j.

j. Place diesel driven AF pump in - AFTER TRIP TRIP:

AF pump 2B 6 CHECK STATUS OF PIPE LEAK :

LEAK:

a. Aux building flooding - STOPPED a. RETURN TO Step 2 (Page 15).

b. SX pumps - NONE RUNNING ON b. IF an SX pump is running EITHER UNIT on Unit 2, THEN RETURN TO MAIN BODY, Step 3 (Page 3).

c. GO TO 0BwOA PRI-8, AUXILIARY BUILDING FLOODING, Step 10

-END-Page 17 of 29

REV. 105 ESSENTIAL SERVICE WATER MALFUNCTION 2BwOA UNIT 2 PRI-8 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

ATTACHMENT B (PG 1 OF 5)

ESSENTIAL SERVICE WATER SYSTEM CROSSTIE 1 START AN ADDITIONAL UNIT 1 SX PUMP PUMP::

a. Check the following valves for a. Manually open valve(s).

UNIT 1 SX train to be started - OPEN OPEN:: IF an SX001 valve is deenergized closed, o Train A: THEN dispatch an operator to energize the affected 1SX001A pump's suction valve:

1SX016A 1SX027A o 1SX001A at MCC 131X3 E4 (383' M15)

-OR- o 1SX001B at MCC 132X1 C1 (364' P18 o Train B:

1SX001B 1SX016B 1SX027B

b. Start standby UNIT 1 SX pump b. Perform the following:

1) Shutdown ONE RCFC train on EACH unit:

o 2A and 2C RCFC o 2B and 2D RCFC o 1A and 1C RCFC o 1B and 1D RCFC

2) Close the SX outlet valve for the shutdown RCFC trains:

o 2SX027A o 2SX027B o 1SX027A o 1SX027B

3) Monitor containment temperature and pressure on BOTH units.

Page 18 of 29

REV. 105 ESSENTIAL SERVICE WATER MALFUNCTION 2BwOA UNIT 2 PRI-8 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

ATTACHMENT B (PG 2 OF 5)

ESSENTIAL SERVICE WATER SYSTEM CROSSTIE 2 CROSSTIE SX SYSTEM SYSTEM:

a. Open Unit 0 CC HX SX inlet a. Locally open valves:

valves:

o 1SX005 (330' Q19) 1SX005 o 2SX005 (330' Q20) 2SX005

b. Check SX pump crosstie valves - b. Manually or locally open OPEN OPEN:: valves:

1SX033 o 1SX033 (330' Q17) 1SX034 o 1SX034 (330' Q19) 2SX033 o 2SX033 (330' Q17) 2SX034 o 2SX034 (330' Q20)

Page 19 of 29

REV. 105 ESSENTIAL SERVICE WATER MALFUNCTION 2BwOA UNIT 2 PRI-8 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

ATTACHMENT B (PG 3 OF 5)

ESSENTIAL SERVICE WATER SYSTEM CROSSTIE 3 MONITOR UNIT 1 SX SYSTEM SYSTEM:

a. Check the following: a. Perform the following:

UNIT 1 SX pump motor amps - o IF CENT CHG pump LESS THAN 180 AMPS temperatures are approaching the limits UNIT 1 SX pump discharge of TABLE A (Page 29),

pressure - GREATER THAN THEN align FP to a CENT 90 PSIG PSIG:: CHG pump lube oil cooler per ATTACHMENT C o 1PI-SX007 (1A SX pump) (Page 23) while o 1PI-SX008 (1B SX pump) continuing with this procedure:

CC heat exchanger outlet temperature - LESS THAN 105 F:

105 o CENT CHG pump 2A o CENT CHG pump 2B 1TI-674 2TI-674 o Isolate SX to UNIT 2 0TI-675 RCFC train(s):

a) Shutdown RCFC train(s):

o 2A and 2C RCFC o 2B and 2D RCFC b) Close RCFC SX outlet valves:

o 2SX027A o 2SX027B c) Monitor containment temperature and pressure.

Step continued on next page Page 20 of 29

REV. 105 ESSENTIAL SERVICE WATER MALFUNCTION 2BwOA UNIT 2 PRI-8 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

ATTACHMENT B (PG 4 OF 5)

ESSENTIAL SERVICE WATER SYSTEM CROSSTIE Step 3 (continued) o Locally adjust SX outlet from CC heat exchanger valve(s):

o 2SX007 (346' M20):

1) Close 2SX007E, Local Disc Sw.

2) Throttle 2SX007 as required.

3) WHEN adjustments are complete, THEN open 2SX007E, Local Disc Sw.

o 1SX007 (346' M16)

1) Close 1SX007E, Local Disc Sw.

2) Throttle 1SX007 as required.

3) When adjustments are complete, THEN open 1SX007E, Local Disc Sw.

o 0SX007 (346' M16):

1) Close 0SX007E, Local Disc Sw.

2) Throttle 0SX007 as required.

3) WHEN adjustments are complete, THEN open 0SX007E Local Disc Sw.

o Shutdown ANY unnecessary diesel generators.

Page 21 of 29

REV. 105 ESSENTIAL SERVICE WATER MALFUNCTION 2BwOA UNIT 2 PRI-8 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

ATTACHMENT B (PG 5 OF 5)

ESSENTIAL SERVICE WATER SYSTEM CROSSTIE 4 CHECK CHILLER OPERATION OPERATION::

a. MCR chillers - AT LEAST ONE a. Place ONE chiller in RUNNING operation per BwOP VC-10, STARTUP OF THE CONTROL ROOM CHILLED WATER SYSTEM.

b. Restart containment chillers as necessary 5 RETURN TO MAIN BODY, Step 3 (Page 3)

-END-Page 22 of 29

REV. 105 ESSENTIAL SERVICE WATER MALFUNCTION 2BwOA UNIT 2 PRI-8 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT C (PG 1 OF 4)

ALIGNMENT OF FP TO CENT CHG PUMP LUBE OIL COOLER 1 LOCALLY ALIGN FP TO CENT CHG PUMP 2A LUBE OIL COOLER COOLER::

a. Check CENT CHG pump 2A - a. GO TO Step 3 (Page 25) to SELECTED FOR FP ALIGNMENT align CENT CHG pump 2B.

b. Connect fire hose (located in 2A CV pump room) to CENT CHG pump 2A lube oil cooler AND FP connection outside 2A CV pump room (364' V18)

c. Check FP hose - CONNECTED TO c. IF only CENT CHG pump 2A CENT CHG PUMPS ON BOTH UNITS UNITS:

is being aligned to FP, THEN GO TO Step 1d.

CENT CHG pump 2A IF CENT CHG pump 1A is CENT CHG pump 1A also being aligned, THEN do NOT continue until hose connections are complete to BOTH CENT CHG pumps.

d. Open FP hose supply isolation valve:

0FP840 (364' V18)

e. Verify fire hose - CHARGED :

CHARGED:

Hose NOT pinched by room door No kinks in hose

f. Open CENT CHG pump oil cooler FP supply isolation valve:

2SX259A (364' U20 2A CENT CHG pump room)

g. Close CENT CHG pump oil cooler SX supply isolation valve:

2SX258A (364' U20 2A CENT CHG pump room)

Page 23 of 29

REV. 105 ESSENTIAL SERVICE WATER MALFUNCTION 2BwOA UNIT 2 PRI-8 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT C (PG 2 OF 4)

ALIGNMENT OF FP TO CENT CHG PUMP LUBE OIL COOLER 2 CHECK CENT CHG PUMP 2A OPERATION OPERATION::

a. CENT CHG pump 2A - RUNNING a. IF CENT CHG pump 2A is being aligned for standby operation, THEN GO TO Step 3 (Next Page).

IF CENT CHG pump 2A is desired to be running, THEN Start CENT CHG pump 2A per either of the following:

o BwOP CV-19, SWITCHING CHARGING PUMPS

-OR-o BwOP CV-1, CV SYSTEM STARTUP

b. Monitor temperatures listed in TABLE A (Page 29) for CENT CHG pump 2A

c. Place a portable fan in door opening as necessary to maintain CENT CHG pump 2A room temperature - NORMAL Page 24 of 29

REV. 105 ESSENTIAL SERVICE WATER MALFUNCTION 2BwOA UNIT 2 PRI-8 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT C (PG 3 OF 4)

ALIGNMENT OF FP TO CENT CHG PUMP LUBE OIL COOLER 3 LOCALLY ALIGN FP TO CENT CHG PUMP 2B LUBE OIL COOLER COOLER::

a. Check CENT CHG pump 2B - a. RETURN TO procedure and SELECTED FOR FP ALIGNMENT step in effect

b. Connect fire hose (located in 2B CV pump room) to CENT CHG pump 2B lube oil cooler AND FP connection outside 2B CV pump room (364' Y21)

c. Open FP hose supply isolation valve:

2FP384 (364' Y21)

d. Verify fire hose - CHARGED CHARGED:

Hose NOT pinched by room door No kinks in hose

e. Open CENT CHG pump oil cooler FP supply isolation valve:

2SX259B (364' Y22 2B CENT CHG pump room)

f. Close CENT CHG pump oil cooler SX supply isolation valve:

2SX258B (364' Y22 2B CENT CHG pump room)

Page 25 of 29

REV. 105 ESSENTIAL SERVICE WATER MALFUNCTION 2BwOA UNIT 2 PRI-8 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT C (PG 4 OF 4)

ALIGNMENT OF FP TO CENT CHG PUMP LUBE OIL COOLER 4 CHECK CENT CHG PUMP 2B OPERATION OPERATION::

a. CENT CHG pump 2B - RUNNING a. IF CENT CHG pump 2B is being aligned for standby operation, THEN RETURN TO procedure and step in effect.

IF CENT CHG pump 2B is desired to be running, THEN Start CENT CHG pump 2B per either of the following:

o BwOP CV-19, SWITCHING CHARGING PUMPS

-OR-o BwOP CV-1, CV SYSTEM STARTUP

b. Monitor temperatures listed in TABLE A (Page 29) for CENT CHG pump 2B

c. Place a portable fan in door opening as necessary to maintain CENT CHG pump 2B room temperature - NORMAL

d. RETURN TO procedure and step in effect

-END-Page 26 of 29

REV. 105 ESSENTIAL SERVICE WATER MALFUNCTION 2BwOA UNIT 2 PRI-8 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT D (PG 1 OF 2)

RESTORATION OF SX TO CENT CHG PUMP LUBE OIL COOLER

NOTE *

If either the FP cooling or the *

portable fan will remain in place, *

Temporary Configuration Change *

Paperwork should be initiated per *

CC-AA-112.

1 LOCALLY ALIGN SX TO CENT CHG PUMP 2A LUBE OIL COOLER COOLER::

a. Check CENT CHG pump 2A - a. GO TO Step 2 (Next Page)

ALIGNED FOR FP COOLING to align CENT CHG pump 2B.

b. Open CENT CHG pump oil cooler SX supply isolation valve:

2SX258A (364' U20 2A CENT CHG pump room)

c. Close CENT CHG pump oil cooler FP supply isolation valve:

2SX259A (364' U20 2A CENT CHG pump room)

d. Check CENT CHG pump 1A lube oil d. Do NOT continue until SX cooler - NOT ALIGNED TO FP cooling is restored to the COOLING CENT CHG pump 1A lube oil cooler.

e. Close FP hose supply isolation valve:

0FP840 (364' V18)

f. Disconnect fire hose

g. Remove portable fan Page 27 of 29

REV. 105 ESSENTIAL SERVICE WATER MALFUNCTION 2BwOA UNIT 2 PRI-8 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED ATTACHMENT D (PG 2 OF 2)

RESTORATION OF SX TO CENT CHG PUMP LUBE OIL COOLER 2 LOCALLY ALIGN SX TO CENT CHG PUMP 2B LUBE OIL COOLER COOLER:

a. Check CENT CHG pump 2B - a. RETURN TO procedure and ALIGNED FOR FP COOLING step in effect.

b. Open CENT CHG pump oil cooler SX supply isolation valve:

2SX258B (364' Y22 2B CENT CHG pump room)

c. Close CENT CHG pump oil cooler FP supply isolation valve:

2SX259B (364' Y22 2B CENT CHG pump room)

d. Close FP hose supply isolation valve:

2FP384 (364' Y21)

e. Disconnect fire hose

f. Remove portable fan

g. RETURN TO procedure and step in effect

-END-Page 28 of 29

REV. 105 ESSENTIAL SERVICE WATER MALFUNCTION 2BwOA UNIT 2 PRI-8 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED TABLE A (PG 1 OF 1)

VITAL EQUIPMENT TEMPERATURE LIMITS 1 TEMPERATURE LIMITS LIMITS::

>>¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥ EQUIPMENT COMPUTER TREND/POINT LIMIT

¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥ CENT CHG PUMP 2A TR048

¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥ INBD BRNG T0112 205 205F OUTBD BRNG T0113 205 205F THRUST BRNG T0114 205 205F GEAR DRIVE OIL (Local gauge at pump) 175 175F

¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥ CENT CHG PUMP 2B TR049

¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥ INBD BRNG T0117 205 205F OUTBD BRNG T0118 205 205F THRUST BRNG T0119 205 205F GEAR DRIVE OIL (Local gauge at pump) 175 175F

¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥ SX PUMP 2A TR037

¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥ INBD BRNG T0643 175 175F OUTBD BRNG T0644 175 175F

¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥ SX PUMP 2B TR038

¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥ INBD BRNG T0648 175 175F OUTBD BRNG T0649 175 175F

¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥ AF PUMP 2A TR042

¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥ THRUST BRNG T2372 165 165F INBD BRNG T2373 165 165F OUTBD BRNG T2374 165 165F

¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥ AF PUMP 2B TR043

¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥ THRUST BRNG T2377 165 165F INBD BRNG T2378 165 165F OUTBD BRNG T2379 165 165F

¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥¥º

-END-Page 29 of 29

REV. 105 OPERATOR ACTION

SUMMARY

2BwOA PRI-F:8 FOR 2BwOA PRI-8 GO TO ATTACHMENT A STEP 5b IF FLOODING OF VITAL EQUIPMENT IS IMMINENT

JOB PERFORMANCE MEASURE TASK CONDITIONS:

1. You are an extra NSO.

2. Both Units are at 100% power.

3. A fire is occurring in the 2B Aux Feedwater Pump Room.

4. The automatic CO2 actuating circuits have failed to operate.

INITIATING CUES:

1. The Unit 2 Unit Supervisor has instructed you to manually initiate CO2 to the 2B Aux Feedwater Pump Room.

2. Inform the Unit 2 Unit Supervisor when CO2 has been initiated to the 2B Aux Feedwater Pump Room.

IP-804 Page 1 of 6

TASK TITLE: Manual Actuation of the CO2 Fire Suppression System JPM No.: IP-804 REV: 2013 NRC Task No.: R-FP-002 K&A No.: 08600A2.04 Objective No.: 4C.FP-02 K&A IMP: 3.3/3.9 EXAMINEE: RO SRO (Circle One)

EVALUATOR: DATE:

The Examinee: PASSED this JPM. TIME STARTED:

FAILED TIME FINISHED:

JPM TIME: MINUTES CRITICAL ELEMENTS: (*) 5, 6 APPROX COMPLETION TIME: 25 MINUTES CRITICAL TIME: NA ALTERNATE PATH: YES EVALUATION METHOD: LOCATION:

PERFORM X IN PLANT X SIMULATE SIMULATOR GENERAL

REFERENCES:

1. BwOP CO-5, MANUAL ACTUATION OF THE CARBON DIOXIDE FIRE SUPPRESSION SYSTEMS, Rev 6.

2. BwOP CO-5T2, MANUAL ACTUATION OF THE UNIT 2 CARBON DIOXIDE FIRE SUPPRESSION SYSTEMS TABLE 2, Rev. 4.

MATERIALS:

1. BwOP CO-5, MANUAL ACTUATION OF THE CARBON DIOXIDE FIRE SUPPRESSION SYSTEMS, Rev 6.

2. BwOP CO-5T2, MANUAL ACTUATION OF THE UNIT 2 CARBON DIOXIDE FIRE SUPPRESSION SYSTEMS TABLE 2, Rev. 4.

TASK STANDARDS:

1. Determine Carbon Dioxide system manual alignment required to actuate system.

2. Manually initiate the Carbon Dioxide suppression system to the 2B Aux Feedwater Pump Room.

TASK CONDITIONS:

5. You are an extra NSO.

6. Both Units are at 100% power.

7. A fire is occurring in the 2B Aux Feedwater Pump Room.

8. The automatic CO2 actuating circuits have failed to operate.

INITIATING CUES:

3. The Unit 2 Unit Supervisor has instructed you to manually initiate CO2 to the 2B Aux Feedwater Pump Room.

4. Inform the Unit 2 Unit Supervisor when CO2 has been initiated to the 2B Aux Feedwater Pump Room.

IP-804 Page 2 of 6

RECORD START TIME:

PERFORMANCE STEP STANDARD CIRCLE APPLICABLE

1. Refer to BwOP CO-5 and BwOP Refer to BwOP CO-5 and SAT UNSAT N/A CO-5T2. BwOP CO-5T2: Comments:

CUE: After examinee locates

Verify all applicable procedures, provide Prerequisites, Precautions, copies of BwOP CO-5 & and Limitations and BwOP CO-5T2. Actions are satisfactorily CUE: All applicable addressed.

prerequisites, precautions, limitations and actions have been met.

2. Determine and locate the Determine and locate SAT UNSAT N/A appropriate Pushbutton Station for pushbutton stations for 2B AF Comments:

the 2B AF Pump Room. pump room from page 2 of Note: 2HS-CO032 is located on BwOP CO-5T2 as follows:

the wall to the right of o Pushbutton #1 (2HS-2B AF pump room door, CO032) is at Aux Bldg 383 383 M-19. M-19.

Note: 2HS-CO033 is located on o Pushbutton #2 (2HS-the wall to the left of 2B CO033) is at Aux Bldg 383 AF pump room door, M-19.

383 M-19.

The Procedure does not specify to try one PB prior to the other.

IP-804 Page 3 of 6

Examiners note: The examinee may attempt to actuate CO2 from both pushbuttons in the following step. Depressing both pushbuttons is NOT required since they are redundant functions.

PERFORMANCE STEP STANDARD CIRCLE APPLICABLE

3. Actuate CO2 system from local Perform the following at one of SAT UNSAT N/A pushbuttons. the pushbutton locations to Comments:

attempt to actuate CO2 system from local pushbuttons: (Step may be performed twice, once at 2HS-CO032 and once at 2HS-CO033):

CUE: Pushbutton Station

Pull down the cover on the Cover is pulled down. pushbutton station.

CUE: Pushbutton has been

Depress the pushbutton depressed. for 3-5 seconds.

NOTE: Wait 3-5 seconds and provide the following cue:

CUE: 3-5 seconds have elapsed.

CUE: Pushbutton has been

Verify the pre-discharge released. alarm sounds. (NO CUE: For FIRST Pushbutton ALARM sounded) attempted: Pre-

Realizes the first discharge alarm did NOT pushbutton did not sound. No sound of CO2 function.

flowing and discharge piping is NOT frosted.

CUE: For SECOND Pushbutton attempted (if

Attempt to actuate CO2 used): Pre-discharge using alternate pushbutton alarm has sounded. (following first attempt).

CUE: Pre-discharge alarm is stopped.

Verify the pre-discharge alarm sounds. (ALARM Note: Provide the following sounded) cue after the examinee

After pre-discharge alarm has checked for CO2 stops, verify CO2 flow. discharge by sound and CUE: No sound of CO2 frosting of piping above flowing. 2CO14JB. (No sound of flow or frosting)

CUE: CO2 discharge piping is NOT frosted.

Determines CO2 system did not actuate.

Proceed to step F.2 (following second attempt).

IP-804 Page 4 of 6

EVALUATOR NOTE: Alternate path begins here

4. Determine and locate the 2B AF Determine and locate the 2B SAT UNSAT N/A Pump Room Damper Control AF Pump Room Damper Comments:

Cabinet and determine power is Control Cabinet from BwOP available. CO-5T2 page 2 as follows:

Note: 2CO18J is located on the

Damper Control Cabinet wall to the left of 2B AF (2CO18J) for 2B AF Pump pump room door, 383 Room is at Aux Bldg 383 M-20. M-20.

Note: When correct cabinet is

VERIFY power at the located, and power light Damper Control Cabinet.

is checked, provide the

Power available light lit.

following cue:

CUE: The RED (power available) light is lit.

IP-804 Page 5 of 6

PERFORMANCE STEP STANDARD Circle applicable

5. Actuate CO2 from Selector Perform the following to SAT UNSAT N/A EMPC valve actuate CO2 system from the Comments:

Note: 2CO14JB is located on Selector EMPC valve:

the wall to the right of 2B

Determine and locate the AF pump room door, 383 selector EMPC (2CO14JB)

M-19. at Aux Bldg 383 M-19.

Break the selector EMPC CUE: Selector EMPC glass is cabinet glass.

broken.

Place selector EMPC CUE: Selector EMPC is rotated actuator lever in the open 90° to open position. position.

CUE: Sound of CO2 flowing is

Verify CO2 discharge by heard and frosting of sound and frosting of piping is evident. piping.

6. Secure CO2 using the Selector Perform the following to SAT UNSAT N/A EMPC valve. secure CO2 system from the Comments:

Selector EMPC valve CUE: After 79 seconds have elapsed, ask the

Maintain selector EMPC in examinee when the next open position for >79 step may be performed. seconds.

IF the examinee closes

Place the Selector EMPC the EMPC actuator lever actuator lever in the closed prior to 79 seconds has position.

elapsed, then failure criteria is met.

CUE: Selector EMPC is in close position.

Note: After examinee closes the selector EMPC valve provide the following cue:

CUE: No sound of CO2 flowing.

CUE: Unit supervisor informs you another operator will complete BwOP CO-5.

CUE: THIS COMPLETES THIS JPM.

RECORD STOP TIME:

COMMENTS:

(Final)

IP-804 Page 6 of 6

PROCEDURE NO.

BwOP CO-5 UNIT NO. REVISION NO.

6 BRAIDWOOD STATION PROCEDURE TITLE:

MANUAL ACTUATION OF THE CARBON DIOXIDE FIRE SUPPRESSION SYSTEMS Rev Summary IR# / EC# (if applicable) 6 UCSR CO2 Abandonment withdrawn per EC 383002 EC 383002 PCRA 1118751-11

BwOP CO-5 Revision 6 Continuous Use MANUAL ACTUATION OF THE CARBON DIOXIDE FIRE SUPPRESSION SYSTEMS A. STATEMENT OF APPLICABILITY This procedure provides the method to be used to manually actuate any of the carbon dioxide fire suppression systems, with, or without power.

B. REFERENCES

1. Station Procedures:

a. BwAP 1110-1, Fire Protection Program System Requirements.

b. BwOP CO-5T1, Manual Actuation of the Unit 1 Carbon Dioxide Fire Suppression Systems, Table 1.

c. BwOP CO-5T2, Manual Actuation of the Unit 2 Carbon Dioxide Fire Suppression Systems, Table 2.

d. BwOP CO-6, Carbon Dioxide Fire Suppression Systems Reset.

2. Station Drawing: M-58, Diagrams of CO2 and H2 System, sheets 1, 2, and 4.

3. Vendor Manual: Chemetron Fire Systems Operation and Service Manual.

4. Exelon Radiation Protection Standards.

C. PREREQUISITES

1. A fire has been determined to exist in an area protected by carbon dioxide and automatic actuation of the area's fire suppression system has failed.

2. Obtain permission from the Shift Manager, or designee, prior to performing this procedure.

3. The system being actuated must be in service and lined up in accordance with the appropriate Mechanical Lineup for a successful actuation.

4. Verify personnel have been evacuated from the fire area.

1

BwOP CO-5 Revision 6 Continuous Use D. PRECAUTIONS

1. Actuation of a system utilizing the EMPCs WILL NOT GENERATE A PRE-DISCHARGE WARNING. Personnel must be notified to evacuate the area prior to an EMPC actuation.

2. If there is no power to the associated fire damper control cabinet, the dampers for the zone to be actuated will not close. An actuation under these conditions will result in carbon dioxide extending beyond the area of the fire and may place plant personnel in a hazardous situation. Prior to actuating a system under these conditions, an evaluation must be made, giving consideration to the following:

a. What is the extent and intensity of the fire?

b. Do other feasible means exist to suppress the fire?

c. To what extent is the fire threatening the safety of the public, plant personnel, and plant equipment?

d. A discharge under these conditions may not extinguish the fire.

e. All personnel anywhere near the area must be evacuated and the discharge will probably have to exceed required discharge duration.

3. Carbon dioxide in the systems is scented with a wintergreen odorizer. If a wintergreen scent is detected, appropriate safety measures should be taken immediately.

4. Carbon dioxide will displace oxygen in confined/enclosed spaces and will seek the lowest level and accumulate.

5. Breathing carbon dioxide vapors may cause dizziness, faintness, headache, loss of consciousness, suffocation due to lack of oxygen.

6. Contact with liquid carbon dioxide may cause frostbite.

2

BwOP CO-5 Revision 6 Continuous Use E. LIMITATIONS AND ACTIONS

1. The Fire Brigade shall be activated in situations requiring actuation of a carbon dioxide fire suppression system.

2. Self contained breathing apparatus, protective clothing, and fire suppression equipment shall be used when making any entry into an area that has had a carbon dioxide system actuation.

3. Once the fire has been extinguished, an investigation into the cause and origin must take place. In order to assure the safety of personnel and to protect any existing evidence, access to the area must be restricted until it has been declared to be CLEAR by the Shift Manager, Station Fire Marshal and Radiation Protection. CLEAR status shall be declared when the initiating condition has been corrected, the atmosphere contains a minimum of 19.5% oxygen, all required investigative information has been obtained, and the area is safe for personnel to enter.

4. Actuation of the Carbon Dioxide Fire Suppression System to any of the Diesel Generator Rooms will also actuate the system protecting the corresponding Diesel Generator Day Tank Room.

5. Actuation of any Carbon Dioxide Fire Suppression System utilizing the EMPCs will result in IMMEDIATE discharge of carbon dioxide WITHOUT A PRE-DISCHARGE WARNING.

6. The system Master Valves are designed to fail OPEN on loss of power. This will charge system piping with carbon dioxide up to the Selector Valves.

7. Carbon dioxide will continue to discharge for as long as the Selector EMPC is maintained in the OPEN position. Placing the Selector EMPC in the CLOSED position will terminate the discharge.

8. Loss of power to a damper control panel will result in the failure of associated dampers to close. An evaluation of the effect of a carbon dioxide discharge under these conditions must be made prior to actuating a carbon dioxide system.

9. The Upper Cable Spreading Rooms Carbon Dioxide Fire Suppression System is a manual system to be used as back-up in the event that the Automatic Halon Fire Suppression System fails.

3

BwOP CO-5 Revision 6 Continuous Use F. MAIN BODY

1. Manual actuation of carbon dioxide with electrical power:

NOTE Refer to BwOP CO-5T1 for Unit 1 system information. Refer to BwOP CO-5T2 for Unit 2 system information.

a. DETERMINE the appropriate Pushbutton Station and location, for the zone to be actuated.

b. PULL DOWN the cover on the Pushbutton Station.

c. DEPRESS the Pushbutton for 3-5 seconds.

d. VERIFY the pre-discharge alarm sounds.

e. Upon termination of pre-discharge alarm, VERIFY carbon dioxide discharge by sound and frosting of supply piping.

f. IF the Carbon Dioxide Fire Suppression System fails to actuate, THEN PERFORM step F.2.

g. IF the zone being actuated is in the Upper Cable Spreading rooms, THEN PERFORM the following:

1) Wait 10 minutes.

2) RE-PERFORM steps F.1.a thru F.1.e NOTE During the 20 minute soak time, adjacent areas should be checked to verify no fire extension, carbon dioxide leakage, or other danger to personnel and equipment.

h. ALLOW a minimum of 20 minutes soak time prior to entering the area.

4

BwOP CO-5 Revision 6 Continuous Use NOTE Once the fire has been extinguished, an investigation into the cause and origin must take place. In order to assure the safety of personnel and to protect any existing evidence, access to the area must be restricted until it has been declared to be CLEAR by the Shift Manager, Station Fire Marshal, and Radiation Protection.

CLEAR status shall be declared when the initiating condition has been corrected, the atmosphere contains a minimum of 19.5%

oxygen, all required investigative information has been obtained, and the area is safe for personnel to enter.

F. 1. i. Once the fire has been extinguished, SECURE the area, with Fire Watch, Security Guards, or otherwise, until the area has been returned to CLEAR status.

j. IMPLEMENT the appropriate measures/actions as required by BwAP 1110-1, section E.4.

k. WHEN appropriate, RESET the system utilizing BwOP CO-6.

5

BwOP CO-5 Revision 6 Continuous Use F. 2. Manual actuation of carbon dioxide without electrical power:

NOTE Refer to BwOP CO-5T1 for Unit 1 system information.

Refer to BwOP CO-5T2 for Unit 2 system information.

a. DETERMINE the Damper Control Cabinet, and its location for the zone to be actuated.

CAUTION If there is no power to the associated Damper Control Cabinet, the fire dampers for the zone to be actuated will not close. This will result in carbon dioxide extending beyond the fire zone area and may place plant personnel in a hazardous situation. A decision must be made, taking into account the extent and intensity of the fire, the ability to suppress the fire utilizing other means, and the extent to which the fire is threatening the safety of the general public, plant personnel, and the plant itself.

All these aspects must be evaluated before discharging carbon dioxide.

b. VERIFY power at the Damper Control Cabinet.

c. DETERMINE the Selector EMPC and location for the zone to be actuated.

d. BREAK the Selector EMPC Cabinet glass.

e. PLACE the Selector EMPC in the OPEN position.

f. VERIFY carbon dioxide discharge, by sound and frosting of supply piping.

6

BwOP CO-5 Revision 6 Continuous Use F. 2. g. IF the Carbon Dioxide Fire Suppression System fails to actuate, THEN PERFORM the following for the appropriate zone(s):

1) For Diesel Generator, D/G Day Tank or Cable Tunnel Zones:

a) CLOSE the SELECTOR EMPC.

b) IDENTIFY the MASTER EMPC for the affected zone.

c) VERIFY/OPEN the MASTER EMPC.

d) PLACE the SELECTOR EMPC in the OPEN position.

e) VERIFY carbon dioxide discharge by sound and frosting of supply piping.

2) For AFW Pump and AFW Day Tank Zones:

a) CLOSE the SELECTOR EMPC.

b) IDENTIFY the MASTER EMPC and the REDUNDANT MASTER EMPC for the affected zone.

c) VERIFY/OPEN the MASTER EMPC.

d) VERIFY/OPEN the REDUNDANT MASTER EMPC.

e) PLACE the SELECTOR EMPC in the OPEN position.

f) VERIFY carbon dioxide discharge by sound and frosting of supply piping.

3) For LCSR Zones:

a) CLOSE the SELECTOR EMPC.

b) IDENTIFY the MASTER EMPC and the REDUNDANT MASTER EMPC for the affected zone.

c) VERIFY/OPEN the MASTER EMPC.

d) VERIFY/OPEN the REDUNDANT MASTER EMPC.

e) PLACE the SELECTOR EMPC in the OPEN position.

f) VERIFY carbon dioxide discharge by sound and frosting of supply piping.

7

BwOP CO-5 Revision 6 Continuous Use F. 2. g. 4) For UCSR Zones:

a) CLOSE the SELECTOR EMPC.

b) IDENTIFY the MASTER EMPC and the REDUNDANT MASTER EMPC for the affected zone.

c) VERIFY/OPEN the MASTER EMPC.

d) VERIFY/OPEN the REDUNDANT MASTER EMPC.

e) PLACE the SELECTOR EMPC in the OPEN position.

f) VERIFY Carbon Dioxide discharge by sound and frosting of supply piping

h. MAINTAIN the SELECTOR EMPC and/or REDUNDANT SELECTOR EMPC in the OPEN position for the time specified in the Required Discharge Duration column of the applicable Table.

i. WHEN the Required Discharge Duration has been completed, CLOSE the SELECTOR EMPC and/or REDUNDANT SELECTOR EMPC.

j. IF the zone being actuated is in the Upper Cable Spreading Rooms, THEN PERFORM the following:

1) WAIT 10 minutes.

2) REOPEN the Selector EMPC for the Initial Discharge Duration again.

3) CLOSE the Selector EMPC when the second Initial Discharge Duration has been completed.

8

BwOP CO-5 Revision 6 Continuous Use NOTE During the 20 minute soak time, adjacent areas should be checked to verify no fire extension, carbon dioxide leakage, or other danger to personnel and equipment.

k. ALLOW a minimum of 20 minutes soak time prior to entering the area.

l. Once the fire has been extinguished, SECURE the area, with Fire Watch, Security Guards, or otherwise, until the area has been returned to CLEAR status.

m. IMPLEMENT the appropriate measures/actions as required by BwAP 1110-1, section E.4.

n. WHEN appropriate, RESET the system utilizing BwOP CO-6.

(Final) 9

PROCEDURE NO.

BwOP CO-5T2 UNIT NO. REVISION NO.

TWO 4 BRAIDWOOD STATION PROCEDURE TITLE:

MANUAL ACTUATION OF THE UNIT 2 CARBON DIOXIDE FIRE SUPPRESSION SYSTEMS TABLE UNIT 2 DIESEL GENERATOR AND DAY TANK ROOMS Rev Summary IR# / EC# (if applicable) 4 UCSR CO2 Abandonment withdrawn per EC 383002 EC 383002 PCRA 1118751-11

BwOP CO-5T2 Revision 4 Continuous Use MANUAL ACTUATION OF THE UNIT 2 CARBON DIOXIDE FIRE SUPPRESSION SYSTEMS TABLE 2 UNIT 2 DIESEL GENERATOR AND DAY TANK ROOMS SUPPRESSION 2S-37 2S-38 2S-39 2S-40 ZONE #

ZONE 2B D/G RM 2A D/G RM 2B D/G 2A D/G DESCRIPTION DAY TANK RM DAY TANK RM PUSHBUTTON #1 2HS-CO002 2HS-CO012 2HS-C0022 2HS-CO027 LOCATION TURB BLDG TURB BLDG 2B D/G RM 2A D/G RM 401' L-28 401' L-28 401' P-28 401' P-28 PUSHBUTTON #2 2HS-CO003 2HS-CO013 NONE NONE LOCATION TURB BLDG TURB BLDG 401' L-29 401' L-24 DAMPER CONTROL 2CO17JB 2CO17JA 2CO17JB 2CO17JA CABINET LOCATION TURB BLDG TURB BLDG TURB BLDG TURB BLDG 401' L-29 401' L-25 401' L-29 401' L-25 SELECTOR EMPC 2CO03JB 2CO01JB 2CO04JB 2CO02JB LOCATION TURB BLDG TURB BLDG TURB BLDG TURB BLDG 401' L-29 401' L-25 401' L-28 401' L-25 REQUIRED 95 SECONDS 92 SECONDS 493 SECONDS 492 SECONDS DISCHARGE (1 minute, (1 minute, (8 minutes, (8 minutes, DURATION 35 seconds) 32 seconds) 13 seconds) 12 seconds)

DAMPER CONTROL MCC 234V3 MCC 233X3 MCC 234V3 MCC 233X3 POWER SUPPLY COMPT. C2, COMPT. C2 COMPT. C2 COMPT. C2 CKT. 5 CKT. 12 CKT. 5 CKT. 12 MASTER EMPC 0CO09J 0CO09J 0CO07J 0CO07J LOCATION TURB BLDG TURB BLDG TURB BLDG TURB BLDG 401' L-17 401' L-17 401' L-17 401' L-17 1

BwOP CO-5T2 Revision 4 Continuous Use MANUAL ACTUATION OF THE UNIT 2 CARBON DIOXIDE FIRE SUPPRESSION SYSTEMS TABLE 2 UNIT 2 AUX FW PP AND DAY TANK ROOMS SUPPRESSION 2S-41 2S-42 ZONE #

ZONE 2B AUX FW 2B AUX FW PP DESCRIPTION PP RM DAY TANK RM PUSHBUTTON #1 2HS-CO032 2HS-CO038 LOCATION AUX BLDG AUX BLDG 383' M-19 383' M-20 PUSHBUTTON #2 2HS-CO033 NONE LOCATION AUX BLDG 383' M-19 DAMPER CONTROL 2CO18J 2CO18J CABINET LOCATION AUX BLDG AUX BLDG 383' M-20 383' M-20 SELECTOR EMPC 2CO14JB 2CO15JB LOCATION AUX BLDG AUX BLDG 383' M-19 383' M-19 REQUIRED 79 SECONDS 167 SECONDS DISCHARGE (1 minute, (2 minutes, DURATION 19 seconds) 47 seconds)

DAMPER CONTROL MCC 234V3 MCC 234V3 POWER SUPPLY COMPT. C2, COMPT. C2, CKT. 7 CKT. 7 MASTER EMPC 1CO16J 1CO16J LOCATION TURB BLDG TURB BLDG 401' L-17 401' L-17 REDUNDANT 1CO23J 1CO23J MASTER EMPC TURB BLDG TURB BLDG LOCATION 401' L-17 401' L-17 2

BwOP CO-5T2 Revision 4 Continuous Use MANUAL ACTUATION OF THE UNIT 2 CARBON DIOXIDE FIRE SUPPRESSION SYSTEMS TABLE 2 UNIT 2 LOWER CABLE SPREADING ROOMS SUPPRESSION 2S-43 2S-44 2S-45 2S-46 ZONE #

ZONE LCSR LCSR LCSR LCSR DESCRIPTION AREA 2Z1 AREA 2Z2 AREA 2Z3 AREA 2Z4 PUSHBUTTON #1 2HS-CO043 2HS-CO047 2HS-C0051 2HS-CO055 LOCATION AUX BLDG AUX BLDG AUX BLDG AUX BLDG 463 Q-19 463 Q-19 463 Q-19 463 Q-19 PUSHBUTTON #2 2HS-CO044 2HS-CO048 2HS-CO052 2HS-CO056 LOCATION AUX BLDG AUX BLDG AUX BLDG AUX BLDG 439' P-26 439' P-23 439' P-20 439' P-19 AREA 2Z2 FROM AREA 2Z4 FROM AREA 2Z4 FROM UPPER VLV TURB BLDG TURB BLDG TURB BLDG OPERATING AREA U2 FROM TURB BLDG DAMPER CONTROL 2CO19JA 2CO19JB 2CO19JB 2CO19JB CABINET LOCATION TURB BLDG AUX BLDG AUX BLDG AUX BLDG 401' L-26 463' Q-20 463' Q-20 463' Q-20 SELECTOR EMPC 2CO05JB 2CO06JB 2CO07JB 2CO08JB LOCATION AUX BLDG AUX BLDG AUX BLDG AUX BLDG 439' Q-19 439' Q-20 463 Q-20 463 Q-20 REQUIRED 1223 SECONDS 1168 SECONDS 1200 SECONDS 1204 SECONDS DISCHARGE (20 minutes, (19 minutes, (20 minutes, (20 minutes, DURATION 23 seconds) 28 seconds) 00 seconds) 04 seconds)

DAMPER CONTROL MCC 234V3 MCC 234V3 MCC 234V3 MCC 234V3 POWER SUPPLY COMPT. C2, COMPT. C2 COMPT. C2 COMPT. C2 CKT. 9 CKT. 11 CKT. 11 CKT. 11 REDUNDANT 2CO05JC 2CO06JC 2CO07JC 2CO08JC SELECTOR EMPC AUX BLDG AUX BLDG AUX BLDG TURB BLDG LOCATION 439' P.5-19 439' P.5-19 439' P.5-19 439' P.5-19 MASTER EMPC 1CO16J 1CO16J 1CO16J 1CO16J LOCATION TURB BLDG TURB BLDG TURB BLDG TURB BLDG 401' L-17 401' L-17 401' L-17 401' L-17 REDUNDANT 1CO23J 1CO23J 1CO23J 1CO23J MASTER EMPC TURB BLDG TURB BLDG TURB BLDG TURB BLDG LOCATION 401' L-17 401' L-17 401' L-17 401' L-17 3

BwOP CO-5T2 Revision 4 Continuous Use MANUAL ACTUATION OF THE UNIT 2 CARBON DIOXIDE FIRE SUPPRESSION SYSTEMS TABLE 2 UNIT 2 ELECTRICAL CABLE TUNNEL SUPPRESSION 2S-47 ZONE #

ZONE U-2 ELECTRICAL DESCRIPTION CABLE TUNNEL PUSHBUTTON #1 2HS-CO059 LOCATION TURB BLDG 401' L-28 PUSHBUTTON #2 2HS-CO060 LOCATION TURB BLDG 401' K.5-27 DAMPER CONTROL 2CO19JA CABINET TURB BLDG LOCATION 401' L-26 SELECTOR EMPC 2CO13JB LOCATION TURB BLDG 401' K-5-26 REQUIRED 187 SECONDS DISCHARGE (3 minutes, DURATION 07 seconds)

DAMPER CONTROL MCC 234V3 POWER SUPPLY COMPT. C2 CKT. 9 MASTER EMPC 0CO09J LOCATION TURB BLDG 401' L-17 4

BwOP CO-5T2 Revision 4 Continuous Use MANUAL ACTUATION OF THE UNIT 2 CARBON DIOXIDE FIRE SUPPRESSION SYSTEMS TABLE 2 UNIT 2 UPPER CABLE SPREADING ROOMS SUPPRESSION 2S-48 2S-49 2S-50 2S-51 ZONE #

ZONE UCSR UCSR UCSR UCSR DESCRIPTION AREA 2EE1 AREA 2EE2 AREA 2EE3 AREA 2EE4 PUSHBUTTON #1 2HS-CO063 2HS-CO067 2HS-C0071 2HS-CO075 LOCATION AUX BLDG AUX BLDG AUX BLDG AUX BLDG 426' P-22 426' P-22 426' P-21 426' P-21 PUSHBUTTON #2 2HS-CO064 2HS-CO068 2HS-CO072 2HS-CO076 LOCATION AUX BLDG AUX BLDG AUX BLDG AUX BLDG 463' L-25 463' M-23 463' P-20 463' Q-18 0B VC HVAC FROM TURB FROM TURB ROOM FROM BLDG BLDG TURB BLDG DAMPER CONTROL 2CO20J 2CO20J 2CO20J 2CO20J CABINET LOCATION AUX BLDG AUX BLDG AUX BLDG AUX BLDG 426' P-20 426' P-20 426' P-20 426' P-20 SELECTOR EMPC 2CO09JB 2CO10JB 2CO11JB 2CO12JB LOCATION AUX BLDG AUX BLDG AUX BLDG AUX BLDG 426' P-22 426' P-20 426' P-21 426' P-21 REQUIRED 152 SECONDS 254 SECONDS 244 SECONDS 200 SECONDS DISCHARGE (2 minutes, (4 minutes, (4 minutes, (3 minutes, DURATION 32 seconds) 14 seconds) 04 seconds) 20 seconds)

DAMPER CONTROL MCC 233V2 MCC 233V2 MCC 233V2 MCC 233V2 POWER SUPPLY COMPT. B2, COMPT. B2 COMPT. B2 COMPT. B2 CKT. 13 CKT. 13 CKT. 13 CKT. 13 MASTER EMPC 1CO16J 1CO16J 1CO16J 1CO16J LOCATION TURB BLDG TURB BLDG TURB BLDG TURB BLDG 401' L-17 401' L-17 401' L-17 401' L-17 REDUNDANT 1CO23J 1CO23J 1CO23J 1CO23J MASTER EMPC TURB BLDG TURB BLDG TURB BLDG TURB BLDG LOCATION 401' L-17 401' L-17 401' L-17 401' L-17 (Final) 5

ML13148A101: Difference between revisions

Latest revision as of 02:09, 10 March 2020

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3.1. Accept

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RELEASE DATA ================================================

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