ML101230057
| ML101230057 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 05/03/2010 |
| From: | NRC/RGN-II |
| To: | Tennessee Valley Authority |
| References | |
| 50-327/10-301, 50-328/10-301 | |
| Download: ML101230057 (353) | |
Text
JPM A.1.1 JPMA.1.1 Page 11 of?
Page ot7 Rev.
Rev. 00 SEQUOYAH NUCLEAR NUCLEAR PLANT PLANT JOB PERFORMANCE PERFORMANCE MEASURE MEASURE JPMA.1 .1 JPMA.1.1 Determine Maintenance Determine Maintenance of Active License License Status PREPARED PREPARED!!
REVISED BY:
BY: Datel Date!
VALIDATE VALIDATEDD BY:
BY:
- Datel Date!
APPROVED APPROVED BY:
BY: Datel Date!
(Operations (Operations Training Training Manager)
Manager)
CONCURRE CONCURRED:D: **
- Datel Date!
(Operations (Operations Representativ Representative)e)
- Validation not required Validation not for minor required for minor enhancement enhancements, s, procedure procedure Rev Rev changes changes thatthat do do not not affect the JPM, affect the JPM, oror individual individual step step changes changes that that do do not not affect affect the the flow flow of of the the JPM.
JPM.
revision).
JPM A.1.1 JPMA.1.1 Page22of7 Page of 7 Rev.
Rev. 00 NUCLEAR TRAINING NUCLEAR TRAINING REVISIONIUSAGE LOG REVISION/USAGE LOG REVISION REVISION DESCRIPTION OF DESCRIPTION OF VV DATE DATE PAGES PAGES PREPARED/
PREPARED!
NUMBER NUMBER REVISION REVISION AFFECTED AFFECTED REVISED REVISED BY: BY:
00 Initial Issue, Initial Issue, Adapted Adapted fromfrom watts watts Bar Bar A.1-1 Al-i YY 1/18/2010 1/18/2010 All All M.
M. Hankins Hankins 2009 NRC 2009 NRC exam exam Vv -Specify Specify ifif the the JPM JPM change change will will require require another another Validation Validation (Y (Y or or N).
N).
See cover sheet for criteria.
See cover sheet for criteria.
JPM A.1.1 JPMA.1.1
- Page Page30f7 3 of 7 Rev.
Rev. 00 SEQUOYAH SEQUOY NUCLEAR PLANT AH NUCLEAR PLANT ROISRO ROISRO JOB PERFORMANCE JOB PERFORMANCE MEASUREMEASURE Task Determine Task Determine License License Status Status Activellnactive Active/Inactive JAITAtask JAITA task ##
Knowledge of Knowledge of Conduct Conduct of of Operations Operations requirements requirements K/A Ratings:
KIA Ratings:
2.1.1 3.8/4.2 2.1.1 3.8/4.2 Task Standard:
Task Standard:
Evaluation Method:
Evaluation Method: Simulator _ _ __
Simulator In-Plant - - - - Classroom In-Plant Classroom ~
X
========================================================================
Performer:
Performer:
NAME Start Start time time _ __
Performance Rating:
Performance Rating: SAT UNSAT Performance Time time _ __
Finish time Evaluator:
Evaluator: I/ _ _ _---c _ _
SIGNATURE SIGNATURE DATE
========================================================================
COMMENT COMMENTS S
JPMA.1.1 JPMA.1.1 Page 4 of?
-Page4of7 Rev. 0 Rev. 0 SPECIAL INSTRUCTIONS SPECIAL INSTRUCTIONS TO TO EVALUATOR:
EVALUATOR:
1.
- 1. AA Critical Critical step step isis identified identified bold bold type type inin the the SAT/UNSAT SAT/UNSAT column.column.
2.
- 2. Any UNSAT Any UNSAT requires requires comments.
comments.
3.
- 3. This JPM This JPM will will be performed inin aa classroom be performed classroom Validation Time:
Validation Time: CR CR _ __ Local Local _ _ _ __
ToolslEquipmentlProcedures Needed:
Tools/Equipment/Procedures Needed:
OPDP-1O OPDP-10
REFERENCES:
REFERENCES:
Reference Reference Title Title Rev Rev No.
No.
OPDP-10 OPDP-10 License Status License Status Maintenance, Maintenance, reactivation reactivation and and 1 Proficiency for Non-Licensed Proficiency Non-Licensed Positions Positions
[jk Task Number Task Title ContTRN Cont TRN Maintain Active NRC License
=================================================================
READ TO OPERATOR Directions to Trainee:
II will explain the initial conditions, and state the task to be performed. II will provide initiating cues. Ensure you indicate to me when you understand your assigned assigned task. To indicate that you have have completed your assigned task return the handout handout sheet II provided you.
INITIAL INITIAL CONDITION CONDITIONS: S:
Four Four Senior Senior Reactor Reactor Operators Operators have have thethe following following history:
history:
1.
- 1. All four All four SROs SRO's have have off-shift off-shift assignments assignments at at the the plant, plant, are current are current in in License License Operator Operator Requalificati Requalification Training, on Training, and and have have hadhad aa medical medical examination examination in in the the last last year.
year.
2.
- 2. None None of the 44 SROs of the SRO's have have worked worked any any shift shift since since 12/01/09.
12/01/09.
3.
- 3. Active/Inacti Activellnactive ve status status and and time time on on shift shift since since October October 1, 1,2009 2009 areare listed listed on the following on the following pagepage for for each each of of the the Senior Senior Reactor Reactor Operators.
Operators.
JPMA.1.1 JPMA.1.1 Page 5 of7 Page5ofT Rev.
Rev. 00 INITIATING CUES:
INITIATING CUES:
- 1. You
- 1. You are are to determine ifif each to determine each of of the the Senior Senior Reactor Reactor Operators Operators License License Status Status is is Active Active to to work the Unit work the Unit 1I SRO SRO position position on on the 0700 - 1900 the 0700 - 1900 shift shift on on January January 31, 31, 2010.
2010. Include Include reasons reasons for for determining determining active active or or inactive inactive status.
status.
License was active on October 1, 2009.
10/02/09 Worked 0700-1900 shift as Unit 1 SRO.
10/03/09 Worked 0700-1 900 shift as Unit I SRO.
10/04/09 Worked 0700-1900 shift in the Tagging Office.
10/05/09 Worked 0700-1 900 shift as Unit 2 SRO.
10/06/09 Worked 0700-1 900 shift as Unit 2 SRO. SRO performed an observation at the Training Center for ILT in the simulator for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.
11/14/09 Worked 1900-0700 shift as Unit 1 SRO.
License was active on October 1, 2009.
10/07/09 Worked 0700-1 900 shift as Unit 1 SRO.
10/08/09 Worked 0700-1900 shift as Unit 1 SRO. Absent from the Control Room for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> while conducting a plant tour with another Senior Reactor Operator who is reactivating their license.
10/09/09 Worked 0700-1 900 shift as Unit 1 SRO.
10/10/09 Worked 0700-1 900 shift as Unit 2 SRO.
10/11/09 Worked 0700-1 900 shift as Unit 2 SRO.
License was active on October 1, 2009.
10/01/09 Worked 0700-1 900 shift as Unit 1 SRO.
10/02/09 Worked 0700-1 900 shift in the Tagging Office.
10/03/09 Worked 0700-1 900 shift as Unit 1 CR0.
10/05/09 Worked 0700-1 900 shift as Unit 2 SRO.
10/14/09 Worked 1900-0700 shift as Unit 2 SRO.
11/02/09 Worked 0700-1900 shift in the WCC.
License was inactive on October 1, 2009.
10/5/09 thru 10/09/09 worked 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> under the direction of the Unit 1 SRO and completed all requirements for license reactivation.
11/12/09 Worked 0700-1900 shift as Unit 1 SRO.
11/1 3/09 Worked 0700-1900 shift as Unit 1 SRO.
11/15/09 Worked 0700-1 900 shift as Unit 2 SRO.
11/21/09 Worked 1900-0700 shift as Unit I SRO.
JPMA.1.1 JPMA.1.1 Page 6 of?
Page6of7 Rev.
Rev. 00 Job Performance Checklist:
Job Performance Checklist:
STEPISTANDARD STEP/STANDARD SAT/UNSAT SATIUNSAT STEP 1.:
STEP 1.: Determine the Determine the Active Active 1I Inactive Inactive status status ofof Operator Operator AA license.
license. - SAT SAT
- UNSAT UNSAT STANDARD:
STANDARD: Applicant determines Applicant determines the licensee is the licensee is Inactive Inactive because the operator did because the operator did not not work the the required required qualified qualified CRITICAL CRITICAL twelve hour 55 twelve hour shifts shifts in in aa license license position position during during the the previous previous STEP STEP quarter. The shift on 10/06/09 quarter. The shift on 10106/09 DOES DOES NOT NOT count count due due to to the the 33 hour3.819444e-4 days <br />0.00917 hours <br />5.456349e-5 weeks <br />1.25565e-5 months <br /> hour absence. OPDP-10, OPDP-1 0, Section 3.2.4.B states Absences from the Control Room for extended periods "Absences Start Time Start (i.e., Fitness-for-Duty (Le., Fitness-for-Duty testing) will not not count towards shift functions.
functions."
- SAT STEP 2.:
STEP Determine the Active 1I Inactive status of Operator B license - UNSAT STANDARD:
STANDARD: Applicant determines the licensee is Active because the operator worked 5 twelve hour shifts in a license position CRITICAL during the previous quarter. The 1 STEP 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> time during which the plant tour was conducted does count as actively "actively performing the functions of an operator. operator."
STEP 3.: Determine the Active!Active 1 Inactive status of Operator C license. _SAT
- SAT
- UNSAT UNSAT STANDARD STANDARD:: Applicant determines determines the license is InactiveInactive because the operator did did not not work the required 55 twelve hour shifts in hour shifts in aa license license position position during during the the previous previous quarter.
quarter. CRITICAL CRITICAL The shifts worked in The in the tagging office and tagging office and the WCC are are not not STEP STEP qualified qualified positions.
positions.
JPMA.1.1 JPMA.1 .1 Pagel PageYof7of 7 Rev.
Rev. 00 Job Performance Job PerformanceChecklist:
Checklist:
STEPISTANDARD STEP/STANDARD SAT/UNSAT SATIUNSAT SAT SAT STEP 4.:
STEP 4.: Determine the Determine Active /I Inactive the Active Inactive status status ofof Operator Operator DD license.
license.
UNSAT UNSAT STANDARD: Applicant STANDARD: Applicant determines determines the the license license isis Active Active because because the the license was license was reactivated reactivated inin the previous quarter, the previous quarter, including including CRITICAL CRITICAL working 40 working 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> hours under under thethe direction direction ofof the the Unit Unit 1I SRO.
SRO. STEP STEP Stop Stop Time Time End OfJPM End Of JPM
READ TO OPERATOR Directions to Trainee:
II will explain the initial conditions, and state the task to be performed. II will provide initiating cues. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet II provided you.
INITIAL CONDITIONS:
Four Senior Reactor Operators have the following history:
- 1. All four SRO's SROs have off-shift assignments at the plant, are current in License Operator Requalification Training, and have had a medical examination in the last year.
- 3. 1, 2009 are Active/Inactive status and time on shift since October 1,2009 listed on the following page for each of the Senior Reactor Operators.
INITIATING CUES:
INITIATING CUES:
- 1. You
- 1. You areare to to determine determine ifif each each ofof the the Senior Senior Reactor Reactor Operators License Status Operators License Active to Status isis Active to work the work the Unit Unit 11 SRO SRO position position onon the the 0700 - 1900 shift 0700 - 1900 shift on January 31, 2010.
on January 31, 2010. IncludeInclude reasons for reasons for determining determining active active or or inactive inactive status.
status.
Operator A License was active on October 1, 2009.
10/02/09 Worked 0700-1 900 shift as Unit 1 SRO.
10/03/09 Worked 0700-1900 shift as Unit 1 SRO.
, 10/04/09 Worked 0700-1 900 shift in the Tagging Office.
. 10/05/09 Worked 0700-1 900 shift as Unit 2 SRO.
- . 10/06/09 Worked 0700-1900 shift as Unit 2 SRO. SRO performed an observation at the Training center for ILT in the simulator for 3hours.
- 11/14/09 Worked 1900-0700 shift as Unit 1 SRO.
Operator B License was active on October 1, 2009.
10/07/09 Worked 0700-1 900 shift as Unit 1 SRO.
. 10/08/09 Worked 0700-1 900 shift as Unit 1 SRO. Absent from the control Room for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> while conducting a plant tour with another Senior Reactor Operator who is reactivating their license.
10/09/09 Worked 0700-1 900 shift as Unit 1 SRO.
- , .- 10/10/09 Worked 0700-1 900 shift as Unit 2 SRO.
10/11/09 Worked 0700-1 900 shift as Unit 2 SRO.
License was active on October 1, 2009.
Operator C 10/01/09 Worked 0700-1 900 shift as Unit I SRO.
10/02/09 Worked 0700-1 900 shift in the Tagging Office.
10/03/09 Worked 0700-1 900 shift as Unit I CR0.
10/05/09 Worked 0700-1 900 shift as Unit 2 SRO.
10/14/09 Worked 1900-0700 shift as Unit 2 SRO.
11/02/09 Worked 0700-1 900 shift in the WC.
erD - License was inactive on October 1, 2009.
10/5/09 thru 10/09/09 worked 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> under the direction of the Unit 1 SRO and completed all requirements for license reactivation.
11/12/09 I Worked 0700-1900 shift as Unit 1 SRO.
11/13/09 Worked 0700-1 900 shift as Unit I SRO.
1 1/15/09 Worked 0700-1900 shift as Unit 2 SRO.
11/21/09 Worked 1900-0700 shift as Unit 1 SRO.
JPM123 JPMI23 Page Page 11 of of 55 Rev.
Rev.22 SEQUOYAH NUCLEAR SEQUOYAH NUCLEAR PLANT PLANT JOB PERFORMANCE JOB PERFORMANCE MEASURE MEASURE JPMI23 JPM123 CONTAINMENT FORMALDEHYDE CONTAINMEN'T FORMALDEHYDE STAY TIME CALCULATION CALCULATION PREPARED!
PREPARED/
REVISED BY: Date/
Date!
VALIDATED VALIDATED
- BY:
- Date/
Date!
APPROVED Date/
Date!
BY:
(Operations Training Manager)
CONCURRE D:
CONCURRED: **
Date/
Date!
(Operations Representativ Representative)e)
- Validation Validation not not required for minor enhancement enhancements,s, procedure procedure Rev Rev changes changes that that do not affect the JPM do not affect the JPM or or individual individual step step changes changes that that do do not not affect affect the the flow ofof the the JPM.
JPM.
- Operations Concurrence required
- Operations Concurrence required for new new JPMs JPMs and and changes changes that that affect affect the the flow of ofthe the JPM JPM (if (ifnot not driven by aa procedure driven by procedure revision).
revision).
JPM123 JPM123 Page Page 22 of of 55 Rev.
Rev. 22 NUCLEAR TRAINING NUCLEAR TRAINING REVISIONIUSAGE LOG REVISION/USAGE LOG REVISION REVISION DESCRIPTION OF DESCRIPTION OF VV DATE DATE PAGES PAGES PREPARED/
PREPARED!
NUMBER NUMBER REVISION REVISION AFFECTED AFFECTED REVISED BY:
REVISED BY:
00 New JPM NewJPM YY 12/5/08 12/5/08 All All T.
T. Wooley Wooley 11 Revised due Revised due inaccuracies inaccuracies regarding regarding NN 12/9/08 12/9/08 2,6 2, 6 M.
M. Chambers Chambers respiratory requirement respiratory requirement not not applicable.
applicabe.
22 Updated KA Updated Task, revised KA Task, revised initial initial YY 1/06/10 1/06/10 All All M M Hankins Hankins conditions conditions Vv -Specify Specify ifif the the JPM JPM change change will will require require another another Validation Validation (Y (Y or or N).
N).
See cover See cover sheet for criteria.
sheet for criteria.
JPM123 JPM123 Page Page 33of5 of 5 Rev.
Rev. 22 SEQUOYAH SEQUOYAH NUCLEAR NUCLEAR PLANi PLANT ROISRO RO/SRO JOB JOB PERFORMANCE PERFORMANCE MEASURE MEASURE Task:
Task:
Calculation Containment Calculation Containment Formaldehyde Formaldehyde stay time and stay time and Determine Determine respiratory respiratory protection protection requirements.
requirements.
JA/TA JAITA task:
task:
KIA Ratings:
KIA Ratings:
2.1.26 (3.4 2.1.26 (3.4!/ 3.6) Knowledge of 3.6) Knowledge of Industrial Industrial Safety Safety Procedures Procedures Task Task Standard:
Standard:
Calculate containment containment formaldehyde formaldehyde stay time and determine respiratory protection protection requirements in accordance with O-TI-OPS-OOO-001.0.
O-Tl-OPS-000-O01 .0.
Evaluation Method: Simulator _ _ __ In-Plant _ __ Classroom _-,-X...!..-_
X
=======================================================================
Performer:
NAME Start Time _ _ __
Performance Rating: SAT UNSAT Performance Time Finish Time _ __
( Evaluator:
Evaluator: I SIGNATUR SIGNATURE E DATE
=======================================================================
COMMENT COMMENTS S
JPM123 JPM123 Page Page 44 of of55 Rev. 2 Rev. 2 SPECIAL INSTRUCTIONS SPECIAL INSTRUCTIONS TO EVALUATOR:
TO EVALUATOR:
(*)*
1.1. Critical steps Critical steps identified identified by by anan asterisk asterisk (*).
2.
- 2. Sequenced steps Sequenced steps identified by identified an "s".
by an s.
3.3. Any UNSAT Any UNSAT requires requires comments.
comments.
4.
- 4. Ensure Operator Ensure Operator performsperforms the the following following required required actions actions forfor SELF*CHECKING; SELF-CHECKING;
- a. Identifies the
- a. Identifies the correct correct unit, unit, train, train, component, component, etc. etc.
- b. Reviews the
- b. Reviews intended action the intended action andand expected expected response.
response.
- c. Compares C. Compares the the actual actual response response to to the the expected expected response.
response.
Validation Time:
Validation Time: CR. CR._ __ Local Local _ _ _ __
ToolslEquipmentlProcedures Needed:
Tools/Equipment/Procedures Needed:
0-Tl-OPS-000-00 1.0, Containment 0-TI-OPS-000-001.0, Containment Formaldehyde Formaldehyde Stay Stay Time Time Calculation Calculation Calculator Calculator
References:
Reference Reference Title Title Rev Rev No.
No.
- 1. 0-Tl-OPS-000-001 .0 0-TI-OPS-000-001.0 Containment Formaldehyde Containment Formaldehyde Stay Time Calculation Calculation 5
=================================================================
READ TO OPERATOR Directions to Directions to Trainee:
II will explain explain the initial conditions, and state the task to be performed. This JPM will be performed in the classroom. II will provide initiating cues. When you complete the task successfully, the objective for this classroom.
job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet II provided provided you.
INITIAL INITIAL CONDITION CONDITIONS: S:
- Unit Unit 11 is is in in Mode I1 at 100% 100% power.
power.
- A Level Level Switch inside inside lower lower containment containment needs needs repair.
- 0-Sl-OPS-00 0-SI-OPS-000.011.0, 0.01 1 .0, Containment Access Control Control during during Modes Modes 11 - 4, 4, has has been initiated initiated in in preparation preparation for for aa containment containment entry entry to to investigate investigate the the alarm alarm condition.
condition.
- The The containment entry entry requires at at least least 120 120 minutes.
minutes.
- AA Chemistry Chemistry sample sample takentaken today today at at 0900 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br /> hours yielded lower containment yielded aa lower containment formaldehyd formaldehyde e concentration concentration of of 1.32 1.32 ppm.
ppm.
- Section Section 4.0,4.0, Prerequisite Prerequisite Actions, Actions, of of 0-Tl-OPS-00 0-001 .0 isis complete.
0-TI-OPS-000-001.0 complete.
INITIATING INITIATING CUES: CUES:
You have You have been been directed directed by by thethe USUS to:
to:
a) Calculate a) Calculate the the allowable allowable containment containment stay stay time for the time for given formaldehyd the given formaldehyde concentration e concentration inin accordance with 0-Tl-OPS-00 accordance with 0-TI-OPS-000-001.0 0-001 .0 AND AND b)b) Identify Identify all all required required actions actions to to complete complete the the level level switch switch repair repair inin accordance accordance with with 0-Tl-OPS-00 0-TI-OPS-000-001.0, 0-001 .0, Containment Containment Formaldehyd Formaldehyde e Stay Time Calculation.
Stay Time Calculation.
JPM123 JPM123 Page Page 55 of of 55 Rev.
Rev. 22 -
STEP *1.:
STEP *1.: Unit 11 Lower Unit Lower Containment Containment Entry Entry CALCULATE Unit CALCULATE Unit 11 Lower Lower containment containment stay time USING stay time USING thethe following following SAT SAT equation:
equation:
_UNSATUNSAT 0.3 ppm 0.3 ppm XX 480 minutes 480 minutes = _ _ _ minutesminutes sample recorded sample recorded in in Step Step 5.1 5.1[1] (1.32)
[1] (1.32) Start Start Time Time__
.3X480
_ --=..:.3::....:X-'-'-48=0"--_ == 144 144 == 109.1 109.1 1.32 1.32 1.32 1.32 Critical Critical Step Step STANDARD: Operator STANDARD: Operator calculates calculates aa containment containment staystay time time of of 109.1 109.1 (+/-
(+/- 1)
- 1) minutes minutes using using equation found equation found in in applicable applicable section section (5.1)
(5.1) of of O-TI-OPS-000-001.0.
0-TI-OPS-000-001 .0.
STEP 2.:
STEP 2.: Identify all Identify all required required actionsactions toto complete complete level level switch switch repair repair nn accordance with step 7 of TI:
SAT Operator determines Job duration exceeds Stay Operator Stay time
_UNSATUNSAT
[7] IF any required task CANNOT be performed within allowed stay time, THEN PERFORM the following ...
[7.1]Contact Industrial Safety for additional guidance Critical Step
[7.2] Evaluate or notify supervisor to evaluate the need for lower Containment Purge in accordance with O-SO-30-3. 0-S0-30-3.
[7.3] DO NOT CONTINUE task UNTIL one of the following conditions are met:
Job Safety Analysis has been performed OR Stop Time __
Stay Time is Acceptable EXAMINER NOTE: If applicant states that the level switch repairs cannot be performed unless aa respirator is worn, this is not correct.
STANDARD:
STANDARD: Operator Operator determines determines Job Job duration exceeds exceeds Calculated Calculated Stay Stay Time.
Operator Operator determines that the level level switch switch repair cannot be be performed performed until until the following following criteria are are completed:
completed:
1- A Job 1- Safety Analysis has Job Safety has been performed performed 2-2- Industrial Industrial Safety Safety is is contacted contacted 3- An 3- An evaluation evaluation of the need of the need for for Lower Lower Containment Containment Purge Purge COMMENTS:
COMMENTS:
End End of JPM ofJPM
READ TO READ OPERATOR TO OPERATOR Directions to Directions to Trainee:
Trainee:
II will will explain explain the initial conditions, the initial conditions, and and state state the the task task to to be be performed.
performed. ThisThis JPM JPM will will be be performed in performed in the classroom.
classroom. II will provide provide initiating initiating cues.
cues. When you complete the task successfully, the successfully, the objective objective for for this this job performance performance measure measure will will be be satisfied.
satisfied. Ensure Ensure indicate to me you indicate me when you you understand understand your your assigned assigned task.
task. To To indicate indicate that that you you have have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
CONDITIONS:
- Unit 11 is in Mode 1I at 100% power.
- A Level Switch inside lower containment needs repair.
- 0-Sl-OPS-000.01 1.0, Containment Access Control during Modes 1I - 4, has been 0-SI-OPS-000.011.0, initiated in preparation for a containment entry to investigate the alarm condition.
- The containment entry requires at least 120 minutes.
- A Chemistry sample taken today at 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br /> yielded a lower containment formaldehyde concentration of 1.32 ppm.
formaldehyde
- Section 4.0, Prerequisite Actions, of 0-TlOPS-000 0-TI-OPS-000-001.0
-001 .0 is complete.
INITIATING CUES:
You have been directed by the US to:
a) Calculate the allowable containment stay time for the given formaldehyd formaldehyde e concentration in accordance accordance with 0-TI-OPS-00 0-001 .0, 0-TI-OPS-000-001.0, AND b) Identify b) Identify all required actions actions to complete the level switch switch repair inin accordance with 0-TI-OPS-00 0-001 .0, Containment with 0-TI-OPS-000-001.0, Containment Formaldehyd Formaldehyde Stay Time e Stay Time Calculation.
Calculation.
OPERATOR READ TO OPERATOR Directions to Trainee:
II will explain the initial conditions, and state the task to be performed. This JPM will be performed in the classroom. II will provide initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet II provided you.
INITIAL CONDITIONS:
- Unit 1 I at 100% power.
1 is in Mode 1
- A Level Switch inside lower containment needs repair.
- 0-SI-OPS-000.01 1.0, Containment Access Control during Modes 1 0-SI-OPS-000.011.0, 1 - 4, has been initiated in preparation for a containment entry to investigate the alarm condition.
e* The containment entry requires at least 120 minutes.
CD A Chemistry sample taken today at 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br /> yielded a lower containment formaldehyde concentration of 1.32 ppm.
- Section 4.0, Prerequisite Actions, of 0-TI-OPS-000-001.0 0-Tl-OPS-000-0O1 .0 is complete.
INITIATING CUES:
You have been directed by the US to:
a) Calculate the allowable containment stay time for the given formaldehyde 0-Tl-OPS-000-001 .0, section 5.1 step 3.
concentration in accordance with 0-TI-OPS-000-001.0, AND b) Identify all required actions to complete the level switch repair in accordance with 0-TI-OPS-000-001.0, 0-TI-OPS-000-001 .0, Containment Formaldehyde Stay Time Calculation, Section 5.1, Step 7.
JPM41 0-1 JPM410-1 Page 11 of Page of 77 Rev. 0 Rev.Q SEQUOYAH NUCLEAR NUCLEAR PLANT PLANT PERFORMANCE MEASURE JOB PERFORMANCE JPM 410-1 SROA2 Review Surveillance for Approval PREPARED!
PREPAREDI REVISED BY: Date!
VALIDATED BY:
- Date!
APPROVED BY: Date!
(Operations Training Manager)
CONCURRED: ** Date!
(Operations Representative)
- Validation not required required for minor minor enhancements, enhancements, procedure procedure Rev Rev changes that do not affect the JPM, JPM, or individual step changes that that do not affect affect the flow of the JPM.
JPM.
revision).
JPM410-1 JPM41 0-1 Page 22 of Page of 77
- Rev Rev. 00 NUCLEAR TRAINING NUCLEAR TRAINING REVISIONIUSAGE LOG REVISION/USAGE LOG Revision Revision Description Description Pages Pages Prepared/
Preparedl Number Number Of Revision Of Revision V V Date Date Affected Affected Revised By:
Revised By:
00 Initial issue- adapted Initial issue- adapted from from SRO SRO JPMJPM A2 A2 on on Y Y 1/08/10 1/08/10 All All MM Hankins Hankins 3-07 AUDIT 3-07 AUDIT Exam, Exam, revised revised initial initial cues cues and and data recorded in data recorded in SI SI to improve JPM to improve JPM flow flow and and evaluation criteria evaluation criteria j
Vv -Specify
- Specify ififthe JPM change the JPM will require change will require another another validation validation (Y (Y or or N).
N).
See cover See cover sheet sheet for for criteria.
criteria.
JPM410-1 JPM4I 0-1 Page Page 33 of of 77 Rev. 0 Rev.0 SEQUOYAH NUCLEAR SEQUOYAH NUCLEAR PLANT PLANT ROISRO ROISRO JOB PERFORMANCE JOB PERFORMANCE MEASUREMEASURE Task:
Task:
Review aa surveillance Review surveillance for for approval approval JAITA task JA/TA task ##:: 004 099 099 0201 Adjust Adjust seal injection injection supply supply controlled controlled leakage leakage K/A Ratings:
KIA Ratings: 2.2.12 (3.0)
(3.0)
Task Standard:
Determine that seal injection flow is not within the acceptable area for the listed RCS pressure and determine that needle valves require adjustment Evaluation Method: Simulator -....:.-!..--
X In-Plant _ __ Classroom X
========================================================================
Performer:
NAME Start Time _ _ __
Performance Rating: SAT UNSAT Performance Time Finish Time _ __
Evaluator:
~~~=-==-----/_-=~~ I SIGNATURE DATE
========================================================================
COMMENTS
JPM410-1 JPM41 0-1 Page Page 44 of of 77 Rev. 0 Rev.0 SPECIAL INSTRUCTIONS SPECIAL INSTRUCTIONS TO TO EVALU-ATOR:
EVALUATOR:
This JPM 1.1. This JPM will will be be performed performed inin aa classroom classroom setting.
setting.
- 2. Any
- 2. Any unsat unsat requires requires comments.
comments.
Validation Time:
Validation Time: CR.CR. 20 minutes 20 minutes Local _ _ _ __
Local Tools/EquipmentlProcedures Needed:
Tools/Equipment/Procedures Needed:
Ruler Ruler Calculator Calculator
References:
References' Reference Reference Title Title Rev Rev No.No.
1.
- 1. 0-Sl-SXX-068-1 37.3 0-SI-SXX-068-137.3 Measurement of Measurement of Reactor Reactor Coolant Coolant Pump Pump Seal Seal Injection Injection Flow Flow for for 66 Units 11 and Units and 22 22 SPP-3.5 SPP-3.S Regulatory Requirements Regulatory Requirements 21 21 3.
- 3. TS TS Technical Specifications Technical Specifications Latest Latest 4.
- 4. TR TR Technical Requirements Technical Requirements Latest Latest
===========================================================================
READ TO OPERATOR DIRECTIONS TO TRAINEE:
DIRECTIONS II will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. II will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet II provided you.
INITIAL CONDITION CONDITIONS: S:
- You are the Unit I1 Unit Unit Supervisor.
- RCS RCS Pressure Pressure 2240 2240 psig psig (P1-68-334)
(PI-68-334)
- 0-Sl-SXX-06 0-SI-SXX-068-137.3,8-1 37.3, Measuremen Measurementt of of Reactor Reactor Coolant Pump Pump Seal Seal Injection Injection Flow Flow for Units Units 11 and and 2,2, has has just been completed.
just been completed.
INITIATING INITIATING CUES: CUES:
1.
- 1. Perform Perform the the Unit Unit Supervisor Supervisor review review of the completed of the completed surveillance.
surveillance.
2.
- 2. Identify Identify anyany actions actions required.
required.
3.
- 3. Identify Identify allall required required notifications notifications thatthat the Shift Manager the Shift Manager must must make.
make.
JPM410-1 JPM41 0-1 Page 55 of Page of77 Rev.
Rev00 STEP 1.:
STEP 1.: Reviews sections Reviews sections 4.0,4.0, 4.1, 4.1, 4.2, 4.2, 4.3 4.3 and and 4.4 4.4 of of surveillance surveillance SAT SAT
- UNSAT UNSAT STANDARD:
STANDARD: Determines all Determines all required required initials initials and signatures are and signatures are present, present, steps steps performed performed have required have required place place keeping.
keeping.
Start Start COMMENTS:
COMMENTS: Time Time______
The following The following steps steps are from Section are from Section 6.0.6.0.
STEP 2.:
STEP 2.: [6.1 .1] ENSURE
[6.1.1] ENSURE RCS RCS pressure pressure reading reading is is 2235 2235 +/-+1- 20 20 psig psig
- SAT SAT STANDARD: SRO STANDARD: SRO reviews reviews stepstep and and ensure ensure RCS RCS pressure pressure is is within within 2235 2235 psig psig +/-
+1- 20 20 psig.
psig.
- UNSAT UNSAT COMMENTS:
COMMENTS:
STEP 3.:
STEP 3.: [6.1.2] ENSURE CCP A-A is operating .....
- SAT STANDARD: SRO reviews step and ensures CCP AA is in service STANDARD:
- UNSAT COMMENTS:
COMMENTS:
STEP STEP 4.: [6.1.3] RECORD pressure reading in MCR MCR. ....
- SAT SAT
[6.1.3.a] P1-68-334 PI-68-334 psig
- UNSAT UNSAT STANDARD:
STANDARD: SRO SRO reviews step step and and ensures ensures RCS RCS pressure pressure recorded is is within within 2235 2235 ÷1-+/- 20 psig. Initial 20 psig. Initial conditions conditions RCS RCS pressure pressure 2240 2240 psig psig on on P1-68-334.
PI-68-334.
COMMENTS:
COMMENTS:
STEP STEP 5.:
5.: [6.1.3]
[6.1.3] RECORD RECORD pressure reading in pressure reading in MCR.
MCR. ...
. ..(Continued)
(Continued) - SAT SAT
[6.1 .3.b] PI-62-92A
[6.1.3.b] PI-62-92A psig psig - UNSAT UNSAT STANDARD:
STANDARD: SRO SRO reviews reviews step and ensures step and ensures CCP CCP discharge discharge pressure pressure recorded recorded isis 2400. Initial conditions 2400. Initial conditions IA-A CCP discharge 1A-A CCP discharge pressure pressure isis 2400 2400 psig psig
JPM410-1 JPM41 0-1 Page Page 66 of of77 Rev.
Rev. 00 STEP 6.:
STEP 6.: [6.1.4] PERFORM calculation
[6.1.41 PERFORM calculation to determine differential to determine differential pressure pressure...... SAT SAT STANDARD:
STANDARD: SRO reviews SRO reviews calculation calculation for for differential differential pressure pressure andand determines determines that that UNSAT UNSAT
2240 psig.
- Differential Differential pressure pressure isis actually actually 160 160 psid psid rather rather than than 170 170 psid psid as as Critical Critical Step Step recorded.
recorded.
SRO initiates SRO initiates aa SR SR (PER)
(PER) onon the Human Performance the Human Initiation of Error. Initiation Performance Error. of SR SR isis Not Not aa Critical Critical Step)
Step)
COMMENTS:
COMMENTS:
STEP 7.::
STEP [6.1.5] IF
[6.1.5] IF pressure drop is less than 100 100 psig ...... SAT
- UNSAT UNSAT STANDARD:
STANDARD: SRO determines step 6.1 6.1[5]
[5] is N/A since pressure drop is greater than 100 psig.
COMMENTS:
COMMENTS: Critical Step Step STEP 8.:
STEP [6.1.6] RECORD the seal injection flow rate to each of the four RCP's RCPs ....... SAT
- UNSAT STANDARD:
STANDARD: SRO determines flow rates are recorded for each RCP loop and that the total Injection flow rate was calculated correctly.
Step Critical Step 9.4+9.6+9.3+
9.4 + 9.6 + 9.3 + 9.7 =
9.738gpm 38 gpm COMMENT S:
COMMENTS:
JPM410-1 JPM41 0-1 Page Page 77 of of 77 Rev.
Rev. 00 STEP 9.:
STEP 9.: [6.1 .7] FIND
[6.1.7] the point FIND the point on on the the figure figure inin Appendix Appendix AA corresponding corresponding to to DP DP....... . SAT SAT UNSAT UNSAT STANDARD: Determines STANDARD: Determines that that with with the the correct correct DP,DP, Acceptance Criteria isis not Acceptance Criteria not met met for for the the current seal current injection flows.
seal injection flows.
Critical Critical Step Step The following The following actions actions or or notifications notifications may may bebe performed performed inin this this step step or or in JPM step in JPM step 9.
9.
SRO determines SRO determines the following actions the following actions must must be performed:
be performed:
- Enter Enter LCO LCO 3.5.6, 3.5.6, 44 hours5.092593e-4 days <br />0.0122 hours <br />7.275132e-5 weeks <br />1.6742e-5 months <br /> hours to to adjust adjust valves valves or or be be in Hot Standby in Hot Standby inin the the next 6 next 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />shours
- Make Make notifications, notifications, in in accordance accordance with with SPP-3.5 SPP-3.5 to Duty Plant to Duty Plant Manager, Manager, Plant Manager, Plant Manager, Site Site VP andand Corporate Corporate DutyDuty officer officer (Unplanned (Unplanned entryentry into aa LCO into LCO with time duration duration 72 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> hours or or less.
less.
- SRO is is initiate initiate a SR (PER) on on the Human Human Performance Performance Error. Error. (Not (Not aa critical step) critical step)
COMMENTS:
COMMENTS:
STEP 10.: [6.1.8] IF the plotted point for differential pressure versus seal injection flow falls SAT outside the "acceptable acceptable region" region ....... .
UNSAT STANDARD:
STANDARD: SRO determines that the plotted point is not in the acceptable region and actions/notifications are required:
therefore the following actions/notifications
- Perform SI Section 6.3, Throttle Adjustment of Seal Injection Needle Valves Critical Step
- Enter LCO 3.5.6, 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to adjust valves or be in Hot Standby in the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Stop Time_____
Time_ _
- Make notifications, in accordance with SPP-3.5, SPP-3.5, Appendix D D-Site Event Notification Matrix, due due to an Unplanned Unplanned entry into aa LCO with time duration duration 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> hours or less:
less:
o Duty Plant Plant Manager Manager o Plant Plant Manager Manager o Site Site VP oo Corporate Corporate Duty Duty Officer Officer 0o (NOTE:
(NOTE: These notifications notifications may may bebe accomplished accomplished by by the SM notifying the SM notifying Operations Operations Management Management and and the the Duty Plant manager.
Duty Plant manager. The Duty Duty Plant Plant Manager is is responsible responsible for the remaining for the internal management remaining internal management notifications notifications as as noted noted in in the the matrix.
matrix. SeeSee note note above above thethe matrix matrix inin Appendix Appendix D) OJ
- Initiate Initiate aa SRSR (PER)
(PER) (initiation (initiation ofof SR not aa critical SR isis not critical step) step)
COMMENTS:
COMMENTS:
End End ofof JPM JPM
DIRECTIONS TO TRAINEE:
II will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. II will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet II provided you.
INITIAL CONDITIONS:
- o You are the Unit 1 1 Unit Supervisor.
- 1 IA-A (Pl-62-92A) uS, discharge pressure 2400 psig (PI-62-92A)
A-A CCP is I/S,
- RCS Pressure 2240 psig (PI-68-334) (P1-68-334) 0-SI-SXX-068-1 37.3, Measurement of Reactor Coolant Pump Seal
- 0-SI-SXX-068-137.3, Injection Flow for Units 11 and 2, has just been completed.
INITIATING CUES:
- 1. Perform the Unit Supervisor review of the completed surveillance.
- 2. Identify any actions required.
- 3. Identify all required notifications that the Shift Manager must make.
SurveHlance Task Surveillance Task Sheet Sheet (STS)
(STS) wk Order:
Irk Order: SI Key: Procedure: O-SI-SXX-068-137.3 Procedure: O-Sl-SXX-068-1 37.3 Train/Loop:
Train/Loop: Unique Unique Data:
Data:
M-j, j]ie: Measurement of ritle: Measurement of RCP RCP Seal Seal Injection Injection Flow Flow for for Unit Unit 11 & & 22 Pert Sect:
Perf Sect: OPS OPS Test Reason Test Reason Quarterly Quarterly Unit: 00 Unit:
Jrb
/uthorization to Begin: SRO
/L(uthorization to Begin: SRO Date Date To Time
-U Time
- 70v{c-(.~' .7- II
',- '/rJ04i 'J- C.
Data Sheet:
Data Sheet: One One Complete Complete copy copy Data Start Datd Start Time Time Completion Completion Date Date Time Time Issued:
Issued: Extension:
Extension:
FreQuency:
Frequenc~: NONE NONE FO: N FO: N TS: YY TS: ASME XI:
ASME XI: NN Mode:
Mode:
sx SX Applicable Modes:
Applicable Modes: 1,2,3,4,5,6 1,2,3,4,5,6 Perfor Modes:
Perfor Modes: 1,2,3,4,5,6 1,2,3,4,5,6 jranquirej:
Clearance Required: Sched. Rec.#:
Sched. Rec.#: Dry Cask Dry Cask Storaqe:
Storage:
SubseQuent Reviews:
Subsequent Reviews: Initial Initial Date Date Was this Was this aa Complete Complete or or Partial Partial Performance?
Performance?
Particial in (Explain Particial in "Remarks" Remarks below) below)
Cognizant Engr Cognizant Cem Admin Engr Admin Reviewer Reviewer Comolete I rvi Partial Partialtr Cem Were all Tech Spec/Tech Req/ISFSI Req/ISFSI CoC/ODCM/Fire CoC/ODCM/Fire Prot Prot Req/AMSAC acceptance criteria satisified?
Yesr Yes[vl*.1
/
Nor No[ N/A[r 11 N/A Were all other acceptance criteria satisfied?
If all Tech Spec Tech ReqllSFSI Req/ISFSI CoC/ODCM/Fire
,4 No[
Yes 1
Yes[
CoC/ODCM/Fire Prot LA/
1I N/A N/A((
Req/AMSAC were not satisfied, was an LCO/TR/ODCMLCOITRJODCM Action required ((Explain in "Remarks")
Remarks)
Yes Yes(( ]j No[ ]I N/A ((V
&IUJ&~O~)C £'--ciua~1L ~
rint Name
)rint Test Performer's Performers Signature Initial Section i?_
k,*c;o.J-d.,O,.1N",h.-'i 1i . J, h ( 1.1. 1... v V Pn/
3f7/ [5 Dj15 /fL)O ToM
- 7) )
- 47z
- hr ;
Rr)O of.crCh?.:hrv (!(//kA C In dt" \/ ?4 PL.."...j. 25s Of'S Test Diredor Direc(or Lead Perfor#Jer Lead Perlorither Date kA,~hM'(17 5P;1",. KA.I7J(
2 2 d I
j lL ,....
{i f.d ~';n tiil<'r!.J.... ,iQJ i_&,Lv f
r./OJi J erSn/S Acceptance Criteria Review:SRO Date Time (ASME Xl XI Sls Sis require review within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br />)
Independent Reviewer
\
PERMANEN PERMANENT T COMMENT COMMENTS: S: REMARKS:
REMARKS:
TENNESSEE TENN ESSEE VALLEY VALLEY AUTHORIT AUTHORITYY SEQUOYAH NUCLEAR SEQUOYAH NUCLEAR PLANT PLANT SURVEILLANCE SURVEILLA NCE INSTRUCTI INSTRUCTION ON O-SI-SXX-068-137.3 O-SI-SXX-0 68-1 37.3 MEASUREMENT MEASUREM ENT OFOF REACTOR REACTOR COOLANT COOLANT PUMP PUMP SEAL INJECTION FLOW SEAL INJECTION FLOW FOR UNITS FOR UNITS I1 AND AND 22 Revision 66 QUALITY RELATED RELATED PREPARED BY:
PREPARED MS Leenerts
--~~~~-------------------
RESPONSIBLE ORGANIZATION:
RESPONSiBLE ORGANIZA TION: _S;:::.!E:::../:....:..NS;::..:S:::.;.:S==---______
SE/NSSS _
BY: MR Cooper ___________________
APPROVEDBY:~M~R~C~o~o~pe~r APPROVED EFFECTIVE DATE: 03/21/2001 LEVEL LEVEL OF OF USE: CONTINUOUS CONTINUOUS USE
SQN SQN MEASUREMENT MEASUREM ENT OF REACTOR COOLANT OF REACTOR COOLANT O-SI-SXX-0 68-1 37.3 0-SI-SXX-068-137.3 PUMP SEAL PUMP SEAL INJECTION FLOW FOR INJECTION FLOW UNITS I1 FOR UNITS Rev Rev 66 11,2 2 Page2o Page 2 of f2l 21 AND2 AND2 REVISION REVISION DESCRIPTION DESCRIPTI ON Revised to Revised seal injection clarify seal to clarify flow calculation.
injection flow calculation.
Revised to Revised incorporate the to incorporate impacts of the impacts of TS TS change change 00-05 (TS 4.1 00-05 (TS 4.1.2.1.c and TS
.2.1 .c and TS 4.1 4.1.2.2.c changed to
.2.2.c changed to TRM 4.1.2.1 TRM and TRM
.c and 4.1.2.1.c 4.1 .2.2.c). Non TRM 4.1.2.2.c). Non Intent Intent change change
SQN SQN MEASUREMENT MEASUREM ENT OF REACTORCOOLANT OF REACTOR COOLANT O-SI-SXX-0 O-SI-SXX-068-137.3 68-1 37.3 PUMP SEAL PUMP SEALINJECTIONINJECTION FLOW FLOWFOR FORUNITS UNITS I1 Rev Rev 6 6 11,2 2 Page3o Page 3 of f2l21 AND2 AND2 TABLE OF TABLE OF CONTENTS CONTENTS PAGE 11OF PAGE OF I1 Section Title Section Title Page Page TABLE OF TABLE OF CONTENTS CONTENTS 33 1.0
1.0 INTRODUCTION
INTRODUC TION 44 1.1 1.1 Purpose ..... .......... ..... ........ ...... .... ...................... ......... ........... ... ............... ........... ...... ...
Purpose 44 1.2 Scope .........................................................................................................................
Scope 44 1.2 1.2.1 1.2.1 Test to Test to be be Performed Performed .................................................................................................. 44 1.2.2 1.2.2 Requirements Requirement Fulfilled ................................................................................................
s Fulfilled 55 1.2.3 1.2.3 Modes.... .... .... .... .... ..... ....... ...... ..... ................................... ... ...... ..... ... .......... ... .......... ...
Modes 55 11.3
.3 Test Frequency/C Test Frequency/Conditionsonditions ......................................................................................... 55 2.0
2.0 REFERENCES
REFERENC ES ........................................................................................................... 55 2.1 2.1 Performance References............................................................................................
Performance References 55 References ..... ........ ............................. ............. ............ ...... ..... ... ...... 6 6
22.22 Developmental Developmental References.
3.0 3.0 PRECAUTIONS PRECAUTIONS AND LIMITATIONS LIMITATIONS .......................................................................... 66 4.0 4.0 PREREQUISITE PREREQUISITE ACTIONS.........................................................................................
ACTIONS 77 4.1 4.1 Preliminary Preliminary Actions.
Actions ... .... ...... ... .................. ......... ................ ...... ..... ....... ......... ........ ...... 77 4.2 4.2 Measuring Measuring andand TestTest Equipment, Equipment, Parts, Parts, and and Supplies ................................................. 77 4.3 4.3 Field Field Preparations.......
Preparations ....... ........ ............... ...... ........................ ................... ... .............. 88 4.4 4.4 Approvals Approvals andand Notifications........................................................................................
Notifications 88 5.0 5.0 ACCEPTANCE ACCEPTANCE CRITE'RIA..........................................................................................
CRITERIA 99 6.0 6.0 PERFORMANCE PERFORMANCE ........................................................................................................ 99 6.1 6.1 Centrifugal Centrifugal Charging Charging Pump Pump A-A....A-A ........ ... ........ ..... .... ............ ............. ......................... 99 6.2 6.2 Centrifugal Centrifugal Charging Charging Pump Pump B-B..................................................................................
B-B 13 13 6.3 6.3 Throttle Throttle Adjustment Adjustment of of Seal Seal Injection Injection Needle Needle Valves Valves .................................................. 17 17 7.0 7.0 POST POST SURVEILLANCE SURVEILLANCE ACTIVITIES ACTIVITIES ......................................................................... 19 19 7.1 7.1 Restoration.................................................................................................................
Restoration 19 19 7.2 7.2 Results......................................
Results .................................................................................. 19 19 8.0 8.0 RECORDS RECORDS....................................................................................................................... 20 20 APPENDIX APPENDIXAA ................................................................................................................. 21 21
SON SQN 11,2 2
MEASUREMENT MEASUREM PUMP SEAL PUMP ENT OF SEAL INJECTION REACTOR COOLANT OF REACTOR INJECTION FLOW FLOW FOR COOLANT UNITS I1 FOR UNITS r 0-SI-SXX-06 Rev Rev 66 8-137.3 0-SI-SXX-068-137.3 AND2 AND2 Page4of2l Page 4 of 21 UNIT______
UNIT_---=-_ __
1.0
1.0 INTRODUCTION
INTRODUC TION 1.1 1.1 Purpose Purpose This Surveillance This Surveillance Instruction Instruction (SI)
(SI) provides steps to detailed steps provides detailed total injection measure total to measure injection flow to flow to the the reactor reactor coolant coolant pump pump seals for Units seals for and 2.
Units I1 and The purpose of this SI
- 2. The purpose of this SI is is to to ensure ensure adequate adequate resistance exists exists in in the the seal seal injection injection lines lines so so that that in in the the event event of of of Coolant Accident (LOCA) the safety injection flow will not Loss of Loss less than be less not be assumed in assumed in the the accident analysis. desired, this analysis. IfIf desired, SI can be this SI be used improve system to improve used to system positions meet the Acceptance Criteria.
balance and used to verify final valve positions 1.2 1.2 Scope 1.2.1 1.2.1 Test to be Performed Measurements of seal injection flow shall be performed while in Mode 1, 2 or 3 with Measurements the RCS pressure at 2235.::!:.
2235 20 psig.
A. This SI will verify during this test that the total injection flow to the RCP seals Specifications for seal injection flow limits.
meets the requirements of Technical Specifications
- 1. If Acceptance Criteria are not met, the seal injection line needle valves will be adjusted to provide required system resistance.
- 2. Needle valves will be sealed in position after adjustment.
B.
B. Instruction shall verify that these valves are sealed in position This Instruction position after the adjustment.
adjustment. (Reference (Reference TRM 4.1.2.1.c &
TRM 4.1.2.1.c 4.1.2.2.c.)
& 4.1.2.2.c.)
SQN SQN MEASUREMENT MEASUREM ENT OF REACTOR COOLANT OF REACTOR COOLANT O-Sl-SXX-0 68-1 37.3 O-SI-SXX-06S-137.3 PUMP SEAL INJECTION PUMP SEAL INJECTION FLOW FLOW FOR FOR UNITS I1 UNITS Rev Rev 66 11,22 Page5of2l Page 5 of 21 AND2 AND2 UNIT______ ____
UNIT_ _.:......-_ _
1.2.2 1.2.2 Requirements Requirement Fulfilled s Fulfilled Performance of Performance of this this Instruction meets the Instruction meets of TS requirements of the requirements and partially 4.5.6 and TS 4.5.6 partially fulfills fulfills the the requirements requirements of of TRM TRM 4.1.2.1.c 4.1.2.1.c and and 4.1.2.2.c.
4.1.2.2.c.
1.2.3 1.2.3 Modes Modes Plant operating modes Plant modes for for which which the the requirements by this covered by requirements covered Instruction shall this Instruction shall be be satisfied (applicable modes) and during which (applicable modes) test can be which the test performed (performing be performed (performing modes) are:
modes)
A. Modes 1, Applicable Modes 1, 2, and 3.
B. Performance Mode 1, 2, or 3.
1.3 1.3 Test Frequency/Conditions Frequency/Conditions This Instruction shall be performed at least once per 31 days and after any seal work on RCPs. This Instruction is not required to be performed until RCS pressure has stabilized at 2215 to 2255 psig. When the 31 day limit has been exceeded or seal work has been performed, this instruction must be performed within4 within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after stabilization within these limits.
2.0
2.0 REFERENCES
REFERENCES 2.1 2.1 Performance Performance References References A.
A. SPP-3.1, SPP-3.1, Corrective Corrective Action Action Program.
Program.
B.
B. SPP-S.1, SPP-8.1, Conduct Conduct ofof Testing.
Testing.
C.
C. 1-S0-62-1, 1-SO-62-1, 2-S0-62-1, 2-SO-62-1, Chemical Volume Control Chemical && Volume System.
Control System.
SQN SQN MEASUREMENT MEASUREM ENT OF REACTOR COOLANT OF REACTOR COOLANT 0-Sl-SXX-06 8-137.3 0-SI-SXX-068-137.3 PUMP SEAL PUMP SEAL INJECTION INJECTION FLOW FLOW FOR UNITS 11 FOR UNITS Rev Rev 66 11,22 Page6of2l AND2 AND2 Page 6 of 21 UNIT UNIT II 2.2 2.2 Developmental Developmen References tal References A.
A. Writer's Guide.
Writers Guide.
B.
B. Technical Specification Technical Specifications Requirement 4.5.6 s Surveillance Requirement and Technical 4.5.6 and Technical Requirements Requirement Manual 4.1.2.1.c s Manual and 4.1.2.2.c.
4.1.2.1.c and 4.1.2.2.c.
C. Specification Figure 3.5.6-1, Technical Specification Injection Flow Limits.
3.5.6-1, Seal Injection D. Westinghouse Westinghous e letter TVA-86-671 from L. L. Williams to John A. Raulston, dated June 27, 1986 (RIMS No. B45 860707 607).
27,1986 E. Westinghouse Westinghous e letter TVA-84-057 from R. S. Howard to John A. Raulston, dated March 16, 1984 (RIMS No. LOO 840322161).
16, 1984 F. SQRO-50-327!86044, Inadequate Verification of ECCS Flow Due to LER SQRO-50-327/86044, Procedural Inadequacy.
G. Design Criteria, SQN-DC-V-27.3, SQN-DC-V-27.3, Safety Injection System H. Technical Specification Change 98-10.
I. Technical Specification Change 00-05.
3.0 PRECAUTIONS LIMITATIONS PRECAUTIONS AND LIMITATIONS
(;tj RCS pressure must be maintained at at 2235 ..:!:÷ 20 psig throughout performance
~ of this surveillance.
of this surveillance.
(;f Failure Failure to to meet meet Acceptance Acceptance Criteria Criteria may may result in entering result in Limiting Condition entering Limiting for Condition for I7 Operation Operation (LCO) needle (LCO) 3.5.6, valves to 3.5.6, which give a needle valves to give a flow which may flow within within result in may result limits limits in adjusting in in 44 hours.
hours.
manual seal adjusting manual injection seal injection
SQN SQN MEASUREMENT MEASUREM ENT OF REACTOR COOLANT OF REACTOR COOLANT O-Sl-SXX-0 68-137.3 O-SI-SXX-068-137.3 PUMP SEAL PUMP SEAL INJECTION INJECTION FLOW FLOW FOR UNITS I1 FOR UNITS Rev 6 Rev 6 11,22 Page7of2l Page 7 of 21 AND2 AND2 Unit'_ _- 4_
Unit_______ ____
__ Date /Z)DAY' Date_______ __
4.0 4.0 PREREQUISITE PREREQUIS ACTIONS ITE ACTIONS
~E I 1 Throughout this Throughout statement, the this Instruction, Instruction, during the step step should should be an IF-THEN during an IF-THEN N/A when marked N/A be marked when statement, stated stated IF IF condition condition does does not not occur.
occur.
JOTE 2 The Surveillance The Surveillance Task may be Sheet may Task Sheet be completed completed as as information becomes available.
available.
4.1 4.1 Preliminary Actions Preliminary Pii11 f7]) ENSURE Instruction to be used is aa copy of the effective version, and RECORD applicable Pretest Data on Surveillance Task Sheet.
ni als
- tv ENSURE NO clearances or system off normal configurations configurations exist which would prevent completion of testing. /7
&fi:
IniIals
(~IF
! ] IF configurations configurations or clearances prevent performance of this
~nstruction, NOTIFY Unit NOTIFY THEN Instruction, THEN Unit SRO SRO andand responsible responsible Supervisor.
Supervisor.
Initi Is 4.2 4.2 Measuring Measuring andand Test Test Equipment, Equipment, Parts, Parts, and Supplies and Supplies None.
None.
SQN SQN MEASUREMENT MEASUREM ENT OF REACTOR COOLANT OF REACTOR COOLANT O-Sl-SXX-0 68-1 37.3 O-SI-SXX-008-137.3 PUMP PUMP SEAL SEAL INJECTION INJECTION FLOW FLOW FOR FOR UNITS UNITS I1 Rev 66 Rev 11,2 2 Page8of2l AND2 AND2 Page 8 of 21 Unit~-----
Unit_______ f ___ Date 'TO {J A__
Date_______ (
4.3 4.3 Fiel~reparations Field reparations
~TE TE Steps within Steps within Section Section 4.3 (Field Preparations) 4.3 (Field Preparations) may be may be performed performed in any order.
in any order.
~VERIFY the following personnel personnel are available to support CfY the test test as required:
r!! Assistant Unit Operator (AUO).
((5 Radiological Control (RADCON). V nitials Initials A?f f1 VERIFY Radiation Work Permits are available for test
,IVERIFY P performance, performance, OR OBTAIN RWPs as required.
Initia
, plant is in Mode 1, VERIFY planl 1, 2, or 3.
4.4 4.4 Approvals and Notifications
perform this Instruction.
rT kLL~' (/7/ / /M / ?t
/ToDJi,/ / i\Je1'J
~'~~U~n~it~SR~O~------~D~a-te~~T~im~e~
Unit SRO Date Time
SQN SQN MEASUREMENT MEASUREM ENT OF REACTOR COOLANT OF REACTOR COOLANT O-S I-SXX~068-137.3 0-SI-SXX-06 8-1 37.3 PUMP SEAL PUMP INJECTION FLOW SEAL INJECTION FLOW FOR UNITS I1 FOR UNITS Rev Rev 66 11,22 Page9of2l AND2 AND2 Page 9 of 21 Unit- - - - - ' ' - -__
Unit_______ --
Date Date 'ToOA f TODAy 5.0 5.0 ACCEPTANCE ACCEPTAN CRITERIA CE CRITERIA
?rX
/
Total flow Total flow rate rate to to the the RCP RCP seals must be seals must within the be within "acceptable region the acceptable shown in region" shown in the figure the figure in in Appendix Appendix A A with pressure at RCS pressure with RCS at 2235 2235.:t
+/- 20 20 psig.
psig.
6.0 6.0 PEREORMANCE PERORMAN CE
~
pITE I1 Component's prefix is Components omitted throughout is omitted procedure; it shall be 11 or 22 as procedure; as per unit tested.
~22 t.óTE This instruction is written such that either section 6.1 or section 6.2 can be performed to take advantage of the pump in operation.
(dTE 3 Section 6.3 may be performed to balance seal injection flows when desired.
6.1 Centrifugal Charging Pump A-A
'~E 1I All steps in this section may be marked N/A if CCP B-B is in service.
~E2 (j/OTE 2 Indicator/Computer Point not used in N/A the Indicator/Computer Steps [3] and [6]
~E3 j,.P(OTE 3 IfIf instrument reading does not meet Acceptance Criteria of 2235 .:t +/- 20 psig, then acceptable pressure pressure will have have to be be established or wait for required required pressure pressure andand then [1].
repeat Step 6.1 [1].
then repeat M
p(r/
LJ ENSURE reactor ENSURE
+/-+/- 20 20 psig reactor coolant psig at at oneone of coolant pressure of the pressure reading the following: (Check (Check one 2235 is 2235 reading is used.)
one used.)
<E) at [P1-68-3341 Main at [PI-68-3341 Control Room Main Control (MCR) or Room (MCR) or B.
B. P0481A P0481A (corresponding Point),
Computer Point),
(corresponding Computer OR OR C.
C. at [P1-68-3231 MCR at [PI-68-3231 MCR or or D.
D. P0482A (corresponding Computer P0482A (corresponding Point)
Computer Point)
SQN SQN MEASUREMENT OF MEASUREMENT REACTOR COOLANT OF REACTOR COOLANT O-SI-SXX-068-1 0-SI-SXX-068-137.3 37.3 PUMP SEAL PUMP SEAL INJECTION INJECTION FLOW FLOW FOR UNITS I1 FOR UNITS Rev Rev 66 11,22 AND2 AND2 PagelOof2l Page 10 of 21 Unit Unit I Date -ro D,Af 7747 6.1 Centrifugal Charging Centrifugal Charging Pump A-A (Continued) tf"'XNSURE Centrifugal Charging pump (COP)
ØNSURE (CCP) A-A is operating and supplying normal charging and seal flow in Woperating accordance with 11,2-SO-62-1. ,2-S0-62-1.
ircitiais
~RECORDRECORD pressure readings r~adingS in MCR MeR for the following following:
/Jf [PI-68-334]
[P1-68-334] cD ;J,,? tfo psig or r/ [P0481Al
[P0481A] AJ AJM psig, OR o..;:..[P.. .:. I--=6=8.. ;:-3=2=3..1._ - I/-_ _ _ psig or rPI-68-323]
[P0482A1 Li
[L.:;.P...;;O;...;.4..;;.;82;:;:.;A..;:.J],_---4\.,t--_ _ psig.
I 7
[PI-62-92A]
[Pl-62-92A] ().
[P0142A]
1P0142A1 c2 L/
i\Ji4
(\j 4log
/.4 00 psig or psig.
IriaIs PERFORM calculation to determine differential pressure (between PT-62-92 and pressurizer):
' Step 6.1 [3] B d100 - (minus) Step 6.1 [3] A
- ;/).
7? 3t) =
= / 7) 17i) psig psig psid Ints Cher
SQN SQN MEASUREMENT MEASUREM ENT OF REACTOR COOLANT OFREACTOR COOlANT . O-SI-SXX-0 68-137.3 O-SI-SXX-068-137.3-PUMP SEAL PUMP INJECTION FLOW SEAL INJECTION FLOW FOR UNITS I1 FOR UNITS Rev Rev 66 11,2 2
AND2 AND2 Page 11 Page 11 of2l of 21 I __
Unit._ _.....:.-_
Unit Date Date 775 £47
'TO DAy
/
6.1 Centrifugal Charging Charging PumpPump A-AA-A (Continued)
(Continued) a 6.1 Centrifugal
/
(3 IF pressure drop IF pressure drop isis less ADJUST FFCV-62-89 ADJUST [FCV-62-891 less than than 100 CLOSED to
] CLOSED psig, THEN 100 psig, THEN increase header to increase header pressure, and pressure, and Steps 6.1 REPEAT Steps REPEAT 6.1 [3]
[3] and 6.1 [4].
and 6.1 [4].
NJA-Initials Initials
~E Failure to meet Acceptance Criteria results in entering Limiting Condition for Operation (LCO) 3.5.6 for seal injection flow. The flow rate must be reduced to meet Acceptance Criteria within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by adjustment of seal injection needle valves.
I~ RECORD the seal injection flow rate to each of the four reactor coolant pumps (RCPs), and CALCULATE total flow rates below by adding seal CALCULATE injection injection flow rates in each RCP loop.
q,t-j4 P RCP Loop 11 [FI-62-1A]
RCP Loop [Fl-62-IA]
F0704A F0704A )JJi)-
Nil}:
gpm or gpm gpm gpm or
~!is
[if RCP RCP Loop Loop 22 [FI-62-14A]
[Fl-62-14A1 F0703A F0703A q~
- vIii IJ/4 gpm gpm gpm or gpm or
£a
SQN SQN MEASUREMENT MEASUREM ENT OF REACTOR COOLANT OF REACTOR COOLANT O-SI-SXX-0 68--137.3 O-SI-SXX-068-137.3 PUMP PUMP SEAL SEAL INJECTION.
INJECTION . FLOW FLOW FOR FOR UNITS I1 UNITS Rev 66 Rev 11,2 2 Page 12of2l Pagel2 of21 AND2 AND2 Unit- -_____
Unit__ '---
Date Date *tv D.4 i 6.1 61 Centrifugal Centri Charging fugal Chargi Pump A-A ng Pump A-A (Continued)
(Continued) q.3 fI RCP Loop RCP Loop 33 IEJ-62-27A1
[FI-62-27 A]
F0702A F0702A
. 3 ij4-J'JL I}-
gpm or gpm gpm gpm or Initials (if RCP Loop RCP Loop 44 rFI-62-4oAl
[FI-62-40A] or.} gpm or gpm or F0701A FO7OIA Nl.4- gpm Initials Injection Flow Rate Total Seal Injection Total =A ++ BB ++ CC ++ D.
D.
V
== 37 gpm gpm /J7L Initials Initials
~/
Checker M FIND the point on the figure in Appendix A corresponding corresponding to the DP from from y Step 6.16.1[4J[4] and Seal Injection Flow from Step 6.16.1[6jE. [6]E. tZe 14/
/<JE checker
.~tance cceptance Criteria Criteria Plotted Plotted point injection point for for differential differential pressure acceptable region" the "acceptable seal versus seal pressure versus the of the region of injection flow flow falls falls within within the figure'in Appendix A.
figure in Appendix A.
IF IF the the plotted plotted point point for for differential pressure versus differential pressure seal versus seal injection injection flow flow falls falls outside outside thethe "acceptable acceptable region" of the region of the figure inin Appendix figure Appendix A, A, THEN THEN
' NOTIFY NOTIFY Unit Unit SRO SRO thatthat LCO LCO 3.5.6 should be 3.5.6 should be entered AND entered AND PERFORM PERFORM Section Section 6.3.6.3. f\J'A:
~itials lfitials
SQN SQN MEASUREMENT MEASUREM ENT OF REACTOR COOLANT OF REACTOR COOLANT 0-SI-SXX-06 8-137.3 0-SI-SXX-068-137.3 PUMP SEAL INJECTION PUMP SEAL INJECTION FLOW FLOW FOR FOR UNITS I1 UNITS Rev Rev 66 11,2 2 Pagel5of2l Page 15 of 21 AND2 AND2 Unit._ _---I\__
Unit_______ ___ Date 6.2 6.2 Centrifugal Charging Centrifugal Charging Pump Pump B-B (Continued) 8-8 (Continued)
[5] IF
[5] IF pressure pressure drop drop isis less less than than 100 psig, THEN 100 psig, THEN ADJUST [FCV-62-89]
ADJUST [FCV-62-89] CLOSEDCLOSED to increase header to increase header pressure, pressure, and and REPEAT Steps REPEAT Steps 6.2 6.2 [3][3] and 6.2 [4].
and 6.2 [4].
Initials NOTE NOTE Criteria results in meet Acceptance Criteria Failure to meet in entering Limiting Condition for Operation (LCO) 3.5.6. The leakage leakage rate must be reduced to meet Acceptance Criteria within 44 hours5.092593e-4 days <br />0.0122 hours <br />7.275132e-5 weeks <br />1.6742e-5 months <br /> by adjustment of seal injection needle valves.
[6] RECORD the seal injection flow rate to each of the four reactor coolant pumps (RCPs), and CALCULATE CALCULATE total flow rates below by adding seal lnjection Thjection flow rates in each RCP loop.
A. RCP Loop 1I [FI-62-1A]
[Fl-62-IA] gpm or F0704A gpm Initials!
B.
B. RCP RCP Loop Loop 22 [FI-62-14A]
IFI-62-14A1 gpm or gpm or F0703A F0703A gpm Initi S C.
C. RCP RCP Loop Loop 33 [FI-62-27
[FI-62-27A]A] gpm or gpm or F0702A F0702A gpm InliaIs D.
D. RCP RCP Loop Loop 44 [FI-62-40A]
[FI-62-40A1 gpm or gpm or F0701A FO7OIA gpm nitials E.
E. Total Total Seal Seal Injection Injection Flow Rate =
Flow Rate =A D.
A ++ BB ++ CC ++ D.
= _ _ _ _ _ gpm gpm Initials Initials Checker Checker
SQN SQN MEASUREMENT MEASUREM ENT OF REACTOR COOLANT OF REACTOR COOLANT O-SI-SXXO6 8-137.3 O-S I-SXX-068-13 7.3 PUMP SEAL PUMP SEAL INJECTION INJECTION FLOW FLOW FOR UNITS I1 FOR UNITS Rev 66 Rev 11,22 Pagel6of2l AND2 AND2 Page 16 of 21 Unit Unit_______ ___ Date 1U nAy Date_______ _
6.2 6.2 Charging Pump Centrifugal Charging Centrifugal Pump B-B B*B *(Continued)
(Continued)
[7] FIND
[7] FIND the the point point on on the figure in the figure Appendix A in Appendix A correspondin corresponding g to the to the DP DP from from Step Step 6.2[41 6.2[4] and and Seal Flow from Injection Flow Seal Injection from Step 6.2[6]E.
Step 6.2[6]E.
IaIs Checker Checker Acceptance Criteria paint for differential pressure versus seal injection Plotted point region" of the figure in "acceptable region flow falls within the acceptable Appendix A.
[8] IF the plotted point for differential pressure versus seal injection flow falls outside the "acceptable region of the acceptable region" figure in Appendix A, THEN NOTIFY Unit SRO that LCO 3.5.6 should be entered and PERFORM Section 6.3.
Initials Initials
SQN SQN MEASUREMENT MEASUREM ENT OF REACTOR COOLANT OF REACTOR COOLANT 0-SI-SXX-06 8-137.3 0-St-SXX-068-137.3 PUMP SEAL INJECTION PUMP SEAL INJECTION FLOW FLOW FOR FOR UNITS I1 UNITS Rev Rev 66 11,22 Pagel7of2l AND2 AND2 Page 17 of 21 Unit- - - - '\ -____
Unit_______ ---
Date Date 171h4 1D S) rt1I 6.3 6.3 THROTTLE ADJUSTME THROTTLE ADJUSTMENT NT OFOF SEAL INJECTION NEEDLE SEAL INJECTION NEEDLE VALVES VALVES NOTE I1 NOTE Section 6.3 Section 6.3 can can bebe done done with [FCV-62-93] in with [FCV-62-931 in automatic or automatic or manual.
manual.
NOTE 22 NOTE The goal The goal is is to to have have equal flow to seal flow equal seal each RCP to each RCP and positioning and positioning of [FCV-62-89] and of [FCV-62-891 [FCV-62-93]
and [FCV-62-93]
to provide to optimized control for provide optimized normal plant for normal plant operation operation and and transients. An example example is is
[FCV-62-89] throttled approximatel
[FCV-62-89] approximately y 60-70 60-70 percent Open, percent Open, [FCV-62-93] throttled approximately approximatel y 30-40 Open, and percent Open, 30-40 percent Charging to RCS pressure between 130 130 to 160 160 psig. Other conditions may also provide acceptable results.
NOTE 3 Opening throttle valves,62-556 through 559, will result in opening of [FCV-62-89] to maintain seal flow with a decrease in charging header pressure. Closing throttle valves,62-556 rFCV-62-891 to through 559, will result in closing [FCV-62-89]
maintain seal flow with an increase in charging header pressure.
CAUTION CAUTiON Do not not allow seal injection injection flow to drop below below 66 gpm during the following step to prevent seal damage. Maintain pressurizer level level within within normal normal operating operating band.band.
NOTE NOTE 44 Steps Steps [1][1} and and [2]
[21 can can be done together.
be done together.
[1]
[1] ADJUST ADJUST RCPRCP seal seal injection injection needle valves to needle valves achieve to achieve approximately approximately the the same same flow flow rate rate at gpm (6 at 88 gpm (6 to gpm 10 gpm to 10 tolerance) on each RCP tolerance) on each RCP loop. loop.
Initials
, Initials
SQN MEASUREMENT MEASUREM ENT OF REACTOR COOLANT OF REACTOR COOLANT O-SI-SXX-0 68-1 37.3 O-SI-SXX-068-137.3 PUMP SEAL PUMP SEAL JNJECTION INJECTION FLOWFLOW FOR UNITS I1 FOR UNITS Rev Rev 66 1,2 AND2 AND2 Page 18 Page of 21 18 of 21 Unit"_ _ _-;\_ _
Unit Date_____
Date '({) bit :f 6.3 6.3 THROTTLE ADJUSTME THROTTLE ADJUSTMENT NT OFOF SEAL SEAL INJECTION VALVES (Continued)
NEEDLE VALVES INJECTION NEEDLE (Continued)
[2] MAINTAIN
[2] MAINTAIN Pressurizer Pressurizer level level and seal injection and seal flow rates injection flow rates at normal at normal operating operating conditions conditions by adjusting [FCV-62-93]
by adjusting [FCV-62-93]
and [FCV-62-89]
and [FCV-62-89] as as necessary.
necessary.
Initls Initials RECORD adjustments
[3] RECORD adjustments to the seal seal injection needle valves.
injection needle RCP-SEAL ADJUSTME ADJUSTMENT NT (LOOP NO) VALVE 1 62-556 turns OPEN 2 62-557 turns OPEN 3 62-559 turns ./
4 62-558 turns OPEN* ./
1 lvtrr Initials
[4] PERFORM section 6.1 or section 6.2 to verify Acceptance Criteria after seal injection needle valve adjustments have been made.
lntaIs Initials
SQN MEASUREMENT MEASUREM ENT OF REACTOR COOLANT OF REACTOR COOLANT O-SI-SXX-0 68-1 37.3 O-SI-SXX-068-137.3 PUMP SEAL PUMP SEAL INJECTiON INJECTION FLOW FLOW FOR UNITS I1 FOR UNITS Rev 6 Rev 6 1,2 AND2 AND2 I Pagel9of2l Page 19 of 21 Unit._ _---I._ __
Unit Date "12 \)
Date_______ fij_
ILLANCE ACTIVITIES ACTIVITIES IfIf difficulty difficulty is encountered in is encountered in automatic automatic pressurizer level pressurizer control after level control adequate seal after adequate seal flow is flow is obtained obtained System Engineering should System Engineering should be notified be notified to evaluate cause.
to evaluate cause.
7.1 7.1 Restoration Restoration
~
F F valves were adjusted, THEN ENSURE that lead seals are installed on the seal injection line needle valves listed below:
RCP-SEAL (LOOP NO) VALVE IST/IV 1ST/IV A. 11 62-556 fJl!h B. 2 62-557 /I C. 3 62-559 /
D. 4 62-558 62-558 .t7/
7I
\
[2]
[2] ENSURE ENSURE [HIC-62-93Al
[HIC-62-93A] MCR MCR isis in AUTO.
in AUTO.
Initials
.Iv 7.2 e
~
7.2 Re Its Its
)) ENSURE ENSURE any any LCOs LCOs areare exited exited and and testing recorded on testing isis recorded on Surveillance Surveillance Task Task Sheet.
Sheet.
Initials
[2] ENSURE ENSURE SRO SRO and and UOUO are aware of are aware completion of of completion testing of testing and and test test results.
results.
SQN MEASUREMENT MEASUREM ENT OF REACTOR COOLANT OF REACTOR COOLANT O-SI-SXX-0 68-1 37.3 0-SI-SXX-068-137.3 PUMP SEAL INJECTION PUMP SEAL INJECTION FLOW FLOW FOR FOR UNITS I1 UNITS Rev 66 Rev 1,2 AND2 AND2 Page2Oof2l Page 20 of 21 Unit,_ _---:~__
Unit Date To3A Date <TOO AY 8.0 8.0 RECORDS RECORDS
~ Signature and Signature and spaces Surveillance Task Surveillance Task Sheet provided on are provided spaces are on for review/appro Sheet for val of review/approval of test Additional sheets results. Additional test results. may be added sheets may be added as necessary.
as necessary.
~
~1]
1] )COMPLETE applicable sections of Surveillance Task Sheet.
Sheet.
37*3 SQN MEASUREMENT OF MEASUREMENT OF REACTOR REACTOR COOLANT COOLANT O-SI-SXX-068-1 O-SI-SXX-068-137.3 PUMP SEAL PUMP SEAL INJECTION INJECTION FLOW FLOW FOR UNITS I1 FOR UNITS Rev Rev 66 1,2 AND2 AND 2 21 of2l Page 21 Page of 21 APPENDIX A APPENDIX A Page 11 of Page of I1 Seal Injection Seal Injection Flow Flow Limits Limits 250 /
V "C'
OJ a,
NN ACCEPTABLE
"§ REGION II) a, II) a, a,:::
0 "0
0.
ffi 200 a,
/
Co /
/
I 0
a, a,
a,
.0 V
~
a, C1) a, a,
0 a,
~
~
a, a,
50 25 30 35 40 45 50 Seal Injection Flow (gpm)
Injection Flow
JPMA.3 JPMA.3 SROSRO Page 11 of Page of 55 REV.
REV. I1 SEQUOYAH NUCLEAR PLANT JOB PERFORMA PERFORMANCE NCE MEASURE ADMIN SRO A.3 SROA.3 JPM Approval of a Waste Gas Tank Release PREPARED/
PREPARED!
REVISED BY: Date!
Date/
VALIDATED VALIDATED BY: ** Date!
Date/
~=-----------
APPROVED BY: Date!
Date/
(Operations Training Manager)
CONCURRED:
CONCURRED: **
Date!
Date/
(Operations Representative)
(Operations Representative)
JPM.
Operations Operations Concurrence Concurrence required for new required for JPMs and new JPMs changes that and changes the affect the that affect flow of the JPM (if not flow of the JPM (if not driven driven by a by a procedure procedwe revision).
revision).
JPMA.3 SRO JPMA.3 SRO Page Page 22 of of 55 REV.
REV. 1I I
NUCLEAR TRAINING NUCLEAR TRAINING REVISION/USAGE LOG REVISION/USAGE LOG REVISION REVISION DESCRIPTION OF DESCRIPTION OF V V DATE DATE PAGS PAGI=S PREPARED/
PREPARED!
NUMBER NUMBER REVISION REVISION AFFECTED AFFECTED REVISED REVISED BY: BY:
00 New New Y Y All All 11 Revised to Revised change the to change the initiating initiating cues, and cues, and Y Y 1/11/10 1/11/10 All All M M Hankins Hankins steps for procedure steps for procedure review review in the JPM in the JPM
/
v - Specify if the JPM V - JPM change wifl will require another validation (Y or N).
N).
See cover sheet for criteria.
JPMA.3 JPMA.3 SRO SRO Page 3 of 5 Page3of5 REV.
REV. 11 SEQUOYAHNUCLEAR
-SEQUOYAH NUCLEAR PLANT PLANT ROISRO RO/SRO JOB PERFORMANCE JOB PERFORMANCE MEASUREMEASURE Task:
Task:
Approval of Approval of aa Waste Waste Gas Gas Tank Tank Release Release JA/TA task:
JAfTA task:
5030010102 (SRO) 5030010102 (SRO) 0690150102 (SRO) 0690150102 (SRO)
KIA Ratings:
KIA Ratings:
2.3.6 (2'.0/3.8) 2.3.6 (2.013.8) 2.3.11 Ability 2.3.11 Ability to Approve Release to Approve Release Permits.
Permits. (CFR:
(CFR: 41.13/45.4 41 .13 / 45.4 1I 45.10) 45.10) 2.0 2.0 1/ 3.8 3.8 Task Standard:
Task Standard:
Candidate identifies ...
(1) Determine the required actions (1) actions for RM-90-118 RM-90-1 18 being inoperable.
(2) Review Release Release package, package, 0-SI-CEM-077-410.4 0-Sl-CEM-077-410.4 for approval.
Valuafion Method:
Valuation X Simulator _~X~_ In-Plant - - -
=======================================================================
Performer:
Performer:
NAME Start Start Time Time _ __
Performance Rating: SAT Performance UNSAT Performance Time Finish Time Time ____
Evaluator:
Evaluator: __________________1 I _ __
SIGNATUR SIGNATURE E DATE
=======================================================================
COMMENT COMMENTS S
JPMA.3 JPMA.3 SRO SRO Page 4 of 5 Page4of5 REV.
REV. 11 SPECIAL INSTRUCTIONS SPECIAL INSTRUCTIONS TO TO EVALUATOR; EVALUATOR;
- 1. Any
- 1. Any UNSAT UNSAT requires requires comments comments
- 2. This
(. This task task can can be performed inin aa classroom be performed classroom setting.
setting.
Validation Time:
Validation Time: CR.
CR. 2020 min mm Local _ _ _ __
. Local Tools/Equipment/Procedures Needed:
Tools/Equipment/Procedures Needed:
OPDP-1, Conduct OPDP-1, Conduct ofof Operations Operations
References:
References:
Reference Reference Title Title Rev Rev No.
No.
1.
- 2. 0-Sl-CEM-077-41 0.4 0-SI-CEM-077-410.4 Waste Gas Waste Decay Tank Gas Decay Tank Release Release 15 15
=================================================================
READ TO READ TO OPERATOR OPERATOR Directions to Trainee:
II will explain the initial conditions, and state the task to be performed. This JPM will be performed in a classroom. II will provide the initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet II provided you.
INITIAL CONDITIONS:
- The operating crew is preparing to release the Waste Gas Decay Tank 'c' C at 1900 today.
- Release can not be rescheduled.
- 0-RM-90-1 18A, Waste Gas Radiation Monitor, is inoperable.
0-RM-90-118A,
- Release path is Unit 2 Shield Building Vent
- The monthly projected offsite dose limits have not been exceeded.
- 0-Sl-CEM-077-410.4 0-SI-CEM-077-410.4 has been complete through Section 6.2 Pre-Release -Pre-Release Instructions- Chemistry, for release of Waste Gas Decay Tank C.
INITIATING CUES:
You are the UnitUnit 11 US US and are to:
1.
TRM, and/or for 0-RM-90-1 0-RM-90-118 18 being inoperable inoperable during during aa Waste Gas Decay Tank Release.
Gas Decay Release.
2.
- 2. Review Review release package, 0-Sl-CEM-077-410.4, release package, O-SI-CEM-077-410.4, and and complete all all applicable steps steps in in Section 6.3 for Section 6.3 for approval approval ofof WGDT WGDT C C release.
JPMA.3 JPMA.3 SROSRO Page 5 of 5 Page5of5 REV. 11 REV.
Job Performance Job Performance Checklist Checklist STEPISTANDARD STEP/STANDARD SAT/UNSAT SATIUNSAT STEP 1.:
STEP 1.: Operator reviews TS, Operator reviews TS, TRM TRM andand ODCM ODCM for for requirements requirements for for making making aa Start Start Time Time_ _
Waste Gas Waste Gas Tank Tank Release Release with with 0-RM-90-118 0-RM-90-1 18 inoperable.
STANDARD: SRO STANDARD: addresses requirements SRO addresses requirements forfor release of WGDT release of WGDT with with RM-90-118 RM-90-1 18 inoperable.
ODCM 1.1.2 ODCM 1.1.2 Action Action 40 40 SAT SAT Release with Release with the number of the number channels OPERABLE of channels OPERABLE less less than than required by required by the Minimum Channels the Minimum Channels OPERABLE OPERABLE requirement, requirement, the the _UNSATUNSAT contents of the tank(s) tank(s) may be released to to the environment initiating the release:
provided that prior to initiating release:
a.
- a. At least two independent least two independent samples samples of of the the tank's tanks contents contents Critical obtained by obtained two technically by two technic&ly qualified qualified members members of of the the Step facility staff are analyzed, and
- b. At least two technically qualified members of the Facility Staff independently verify the release rate calculations and:
- c. At least two technically qualified members of the Facility Staff independently verify the discharge valve lineup.
Otherwise, suspend release of radioactive effluents via this pathway.
STEP 2.: US/SRO reviews release package for approval:
SAT STANDARD: US reviews release package for WGDT C and identifies two conditions that prevent the package from being approved: UNSAT 1- US Identifies that chemistry did not complete the Section 6.2, Step [2]
1- Critical to meet the ODCM requirements for chemistry to obtain two Step independent samples and independently analyze these samples.
- 2. US identified that data data recorded in in Section Section 6.2, step [11] for Total Body Dose Rate (mremlyr)
(mrem/yr) did not meet the acceptance criteria.
Stop Time ENDOFJPM END OF JPM
READ TO OPERATOR Directions to Trainee:
II will explain the initial conditions, and state the task to be performed. This JPM will be performed in aa classroom. II will provide the initiating cues. When you complete the task successfully, the objective for this job performance measure will be satisfied.
Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet II provided you.
INITIAL CONDITIONS:
- The operating crew is preparing to release the Waste Gas Decay Tank C "C' at 1900 today.
- Release can not be rescheduled.
- 0-RM-90-1 1 8A, Waste Gas Radiation Monitor, is inoperable.
0-RM-90-118A,
- Release path is Unit 22 Shield Building Vent
- The monthly projected offsite dose limits have not been exceeded.
- Pre-Release 0-SI-CEM-077-410.4 has been complete through Section 6.2 -Pre-Release Instructions- Chemistry, for release of Waste Gas Decay Tank C.
INITIATING CUES:
You are the Unit 1 I US and are to:
- 1. Determine any required actions (TS, TRM, and/or ODCM) for 0-RM-90-118 0-RM-90-1 18 being inoperable during a Waste Gas Decay Tank Release.
- 2. Review release package, j3ackage, 0-SI-CEM-077-41 0-Sl-CEM-077-41 0.4, and complete all applicable steps in Section 6.3 for approval of WGDT C release.
NPG Standard NPG Standard Conductof Conduct ofTesting Testing SPP8.1 SPP;.8.1 Programs and Programs and Rev. 0006 Rev. 0006 Processes Processes Pa~e 13 Page of14 13 of 14 Attachment 22 Attachment (Page 11 ofl)
(Page of 1)
SPP-S.1 Chronologica SPP-8.1-2 - Chronological l Test Log (CTL)
Test Log (CTL)
CHRONOLOGICAL CHRONOLO GICAL TEST TEST LOG LOG (CTL)
(CTL)
Data Package Page Data Package Page of of I
Procedure No.
Procedure No. O-~/-Cf*l!J O-S/ (/ -O~Q -
-l../IO,l Rev.
Rev. /,L f2 Date(3)/Time(1)
Time Date
/
3 Narrative Narrative Initials Initials DA y Nc).)
!ovAl' J 1~~---_~.~c/V"L11.4'ILL{' Iy
/ if 0 _S~.J_ e-i!)1*1 ~() ,-/1 c:: y t tG L ~.e: . <l-4__<--
tL)("7trr J(ff1C c Ci4 Log Log entries entries havehave been been reviewed reviewed and and items items are are appropriately addressed.
appropriately addressed.
j Test Test Director(2 Director Date Date (1)Use kjse 24 1 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> hour clock clock for for each each entry.
entry.
(2)Test Test Director t2 Director signature signature only only required required on on last last sheet sheet of ofCTL.
CTL. TheThe other blanks can review blanks other review be marked can be N/A.
marked N/A.
(3) The TheDate Date column column needs needs toto bebe filled filled inin for for the the first first entry entry on on the the CTL and for CTL and the first forthe after each entry after frst entry date each date change.
change.
TVA TVA40681 40681 [1100-2008]
.. 2008J Page11 ofof1I Page SPP-8.I-2[10-17-2008J SPP-8.1-2 [10-17-20081
Sequoyah Nuclear Sequoyah Nuclear Plant Plant Unit 00 Unit Surveillance Instruction Surveillance Instruction 77-41 0.4 0-SI-CEM-077-410.4 0-SI-CEM-0 Waste Gas Waste Gas Decay Tank Release Decay Tank Release Revision 0015 Revision 0015 Quality Related Related Use: Reference Use Level of Use:
Effective Effective Date:
Date: 09-03-2009 09-03-2009 Responsible Responsible Organization:
Organization: CEM, Chemistry CEM, Chemistry Prepared By:
Prepared By: W.
W. Kenneth Kimsey Kenneth Kimsey Approved By:
Approved By: Diedre Diedre B.
B. Nida Nida
SQN SQN Waste Gas Waste Decay Tank Gas Decay Tank Release Release 0-SI-CEM-0 0-SI-CEM-077 77-410A
-410.4 Unit 00 Unit Rev. 0015 Rev. 0015 Page 22 of Page of 42 42 Revision Log Revision Log Revision Revision Affected Affected or Change or Change Effective Effective Page Page Number Number Date Date Numbers Numbers Description of Description of Revision/Ch ange Revision/Change 0014 0014 12/19/2007 12/19/2007 pages 14, pages 14, Added tracking mechanism Added tracking tracking setpoint for tracking mechanism for setpoint 19,42 19, 42 changes. PER changes. PER 134683.
134683.
0015 0015 09/03/2009 09/03/2009 pages 66 pages Updated sampling reference.
Updated sampling reference.
10.
and 10.
- SQN SQN Waste Gas Waste Gas Decay Decay Tank Tank Release Release 0-Si-CEM-07 0-SI-CEM-077 7-410.4
-410.4 Unit 0 UnitO Rev. 0015 Rev. 0015 Page3of42 Page 3 of 42 Table of Table of Contents Contents 1.0
1.0 INTRODUCTION
INTRODUC TION ..........................................................................................................55 1.1 1.1 Purpose ........................................................................................................................ 55 Purpose 1.2 1.2 Scope ............................................................................................................................ 55 Scope 1.2.1 1.2.1 Tests to Tests to be Performed .................................................................................... 55 be Performed 11.2.2
.2.2 Requirements Requirement Fulfilled .................................................................................... 55 s Fulfilled 1.3 1.3 Frequency and Frequencyan Conditions ............................................................................................ 66 d Conditions 2.0
2.0 REFERENCES
REFERENC ES ............................................................................................................. 66 2.1 Performance References .............................................................................................. 66 2.2 2.2 Developmental Developmen tal References ........................................................................................... 66 3.0 3.0 PRECAUTIONS PRECAUTIO LIMITATIONS NS AND LIMITATIO NS ........................................................................... 66 4.0 PREREQUISITE PREREQUiSITE ACTIONS .......................................................................................... 7 4.1 Preliminary Actions ....................................................................................................... 77 4.2 Approvals and Notifications .......................................................................................... 7 5.0 ACCEPTANCE ACCEPTANCE CRITERIA CRiTERIA ........................................................................................... 7 6.0 6.0 PERFORMANCE .......................................................................................................... 8 PERFORMANCE 6.1 6.1 Pre-Release Instructions - Operations .......................................................................... 8 8
6.2 6.2 Instructions - Chemistry ................................................... '" ................... 10 Pre-Release Instructions -
10 6.3 6.3 Release Instructions - Operations ............................................................................... 15 7.0 7.0 POST POST PERFORMANCE ACTIVITY-CHEMISTRY ..................................................... 18 PERFORMANCE ACTIVITY-CHEMISTRY 18 8.0 8.0 RECORDS .................................................................................................................. 19 RECORDS 19 Appendix Appendix A:A: Correction Correction Curve Curve ...................................................................................... 20 20 Appendix Appendix B:B: Release Release Data Data ............................................................................................. 21 21 Appendix Appendix C:C: Sample Sample Requirements Requirements .............................................................................. 22 22 Appendix D:
Appendix D: Gaseous Gaseous Release Release PermitPermit Processing Processing...................................................... 23 23 Appendix Appendix E:E: Opening Opening Permits Permits ....................................................................................... 28 28 Appendix 35 Appendix F:F: Closing Closing PermitsPermits ........................................................................................ 35 Appendix Screen........................................ 39 39 Appendix G:G: Editing Editing Sample Sample Entry/Concentrations EntrylConcentrations Screen
SQN SQN Waste Gas Waste Gas Decay Tank Release DecayTank Release O-Sl-CEM-0 0-SI-CEM-077 77-410.4
-410.4 UnitO0 Unit Rev. 0015 Rev. 0015 Page 44 of Page of4242 Table of Table Contents (continued) of Contents (continued)
Appendix H:
Appendix H: Updating the Updating the CDAS CDAS Setpoint Screen ......................................................42 Setpoint Screen 42
SON SQN Waste Gas Waste Gas Decay Tank Release DecayTank Release 0-SI-CEM-0 77-410.4 0-SI-CEM-077-41 0.4 Unit 00 Unit Rev. 0015 Rev. 0015 Page of42 Page 55of 42 1.0
1.0 INTRODUCTION
INTRODUC TION 1.1 1.1 Purpose Purpose This Instruction This Instruction provides provides detailed detailed steps document the to document steps to radiochemicall analyses the radiochemica analyses required by required by the the Sequoyah Sequoyah Offsite Offsite Dose (ODCM) for Manual (ODCM)
Calculation Manual Dose Calculation release of for release of Waste Gas Waste Gas Decay Decay Tanks Tanks (WGDTs)
(WGDTs) contents.
contents. WGDTs WGDTs are are common common equipment.
equipment.
1.2 1.2 Scope Scope 1.2.1 1.2.1 Tests to Tests to be be Performed Performed The following activities The activities are in connection with performed in are performed the release of with the Waste Gas of Waste Gas Decay Tank Decay Tank contents.
A. Verification of the noble gas dose rate from the Shield Building exhaust due to WGDT releases.
B. Determination Determinatio n of the radiation monitor response prior to each release.
C. Verification that the effluent flow rate measuring device is operable during the release of waste gas.
D. Verification of radioactive gaseous effluent monitoring.
1.2.2 1.2.2 Requirements Requirements Fulfilled Instruction partially fulfills Offsite Dose Calculation Manual Performance of this Instruction (ODCM)
(ODCM) SUNeiliance Surveillance Requirements Requirements (SR's)
(SRs)..
- ~*~'X,"'c~;"S~,,;eillanceR~quirements Surveillance Requirements Applicable Applicable Modes Modes . . Performance Modes Performance Modes ODCM ODCM p. p. 2.2.2.1.1, 2.2.2.1.1, Table Table 2.2-2, 2.2-2, Item Item AA All All All All ODCM ODCM p. p. 2.1.2.1.a, 2.1 .2.1 .a, Table Table 1.1-2, 1.1-2, Item Item 1.a l.a All All All All ODCM p.
ODCM p. 2.1.2.1.b, 2.l.2.l.b, Table Table 1.1-2, 1.1-2, Item Item 1.b 1.b All All All All ODCM ODCM p.p. 2.2.2.2.
2.2.2.2. All All All All ODCM ODCM p.p. 2.2.2.4.
2.2.2.4. All All All All ODCM ODCM p.p. Control Control 1.1.2, 1.1.2, Table Table 1.1-2, 1.1-2, All All All All Action Action 40 40
SQN SQN Waste Gas Waste DecaY'Tank Release Gas DecayTank Release 0-Sl-CEM-07 0*SI*CEM*077 7-410.4
- 410.4 Unit 0 UnitO Rev. 0015 Rev. 0015 Page 66 of Page of 42 42 1.3 1.3 Frequency and Frequency and Conditions Conditions This Instruction This Instruction is is performed performed in in any any mode when aa release mode when from the required from release isis required the WGDT. Verification WGDT. Verification of of the the flow flow rate monitor (0-FE-77-230 rate monitor (0-FE-77-230) ) isis required per four once per required once four (4) hours when waste (4) hours when waste gas gas is is being being released.
released.
2.0
2.0 REFERENCES
REFERENC ES 2.1 2.1 References Performance References A. 0-SO-77-15, 0-SO-77-1 5, Waste Gas Decay Tank Gas Decay Tank Release B. Conduct of Testing.
SPP-8.1, Conduct C. 0-Tl-CEM-2 60-01 1.21, Chemical Analytical Methods - Gas Analysis 0-TI-CEM-260-011.21, -
D. 0-Tl-CEM-0 00-016.40, Primary Sampling - Waste Gas 0-TI-CEM-000-016.40, -
E. 0-TI-CEM-0 30-030.0, Manual Calculation of Plant Gas, Iodine and Particulate 0-TI-CEM-030-030.O, Release Rates for Offsite Dose Calculation Manual (ODCM) Compliance 2.2 Developmental Developmental References A. TI-18, Tl-18, Radiation Monitoring B. Sequoyah Nuclear Plant Offsite Dose Calculation Manual (ODCM)
C. Preoperational Test of FE-77-230 PT-476 (2-18-80), Preoperational D. TVA Drawing 47W560-16 E. PER SQP890667 and 930807 3.0 PRECAUTIONS PRECAUTIONS AND LIMITATIONS LIMITATIONS
( t;>(' IfIf the the monthly monthly projected projected offsite offsite dose limits have dose limits exceeded, the been exceeded, have been release the release
,'X/ cannot cannot be be made made unless unless thethe waste waste gasgas decay tank has decay tank held aa minimum been held has been minimum ofof 60 60 daysdays for for radioactive radioactive decay.
decay. The The Cognizant should be Chemist should Cognizant Chemist contacted be contacted for any monthly projected any monthly projected offsite offsite dose dose limits.
limits.
ci c7 The The setpoint changed setpoint for changed without for the the shield shield building without aa change change to building radiation to the radiation monitors ODCM.
the ODCM.
(RM-90-400) can monitors (RM-90-400) NOT be can NOT be
SQN SQN Waste Gas Waste Gas Decay Decay TankTank Release Release 0-Sl-CEM-07 0-SI-CEM-077 7-410.4
-410.4 UnitO0 Unit Rev. 0015 Rev. 0015 Page7of42 Page 7 of 42 4.0 4.0 PREREQUISITE PREREQUIS ACTIONS ITE ACTiONS NOTE NOTE During the During the performance performance of of this Instruction, any this Instruction, any IF-THEN statement may IF-THEN statement may be marked N/A be marked N/A when the corresponding stated condition does when the corresponding stated condition does NOT NOT occur.
occur.
4.1 4.1 Preliminary Actions NOTE Sampling of the Waste Gas Decay Tanks can be performed prior to Radiation Monitor checks as long as a second independent sample is collected and analyzed if O-RM-90-1 O-RM-90-118 18 is inoperable.
~ EN~UREENSURE Instruction to be used is a copy of the effective V ,verSion.
/version.
d Sheet.
fl!Y
)C _
RECORD the start date and time on the Surveillance Task RECORD the start date and time on the Surveillance Task Sheet.
d COMPLETE the Test Performers Performers block on the Surveillance P / Task Sheet. ,
Chronological Test INITIATE SPP-8.1 Chronological
/INITIATE Test Log. V TRANSMIT the release release package package to the main room for control room main control A radiation monitor checks.
checks.
4.2 4.2 Approvals Approvals andand Notifications Notifications None None 5.0 5.0 ACCEPTANCE ACCEPTANCE CRITERIACRITERIA Acceptance Acceptance criteria criteria are are based based on administrative limits on administrative related to limits related the site to the limit release limit site release and and the the design design flow flow rate rate of of each each release pathway. Regulatory release pathway. will NOT limits will NOT be Regulatory limits be exceeded exceeded until until a a site site evaluation evaluation is is complete.
complete. Acceptance Acceptance criteria criteria are noted are where noted where comparison comparison with with test data isis made.
test data made.
SQN SQN Waste Gas Waste Tank Release Decay Tank Gas Decay Release 0-Sl-CEM-07 7-410.4 0-SI-CEM-077-41 0.4 Unit 00 Unit Rev. 0015 Rev. 0015 Page of 42 Page 88 of 42 6.0 6.0 /ERFORMANCE
,,/PERFORM ANCE
~
/ NOTE NOTE U'S/SRO is 1Y/SRO is defined defined as as aa Unit Unit Supervisor who is Supervisor who also Senior is also Operator qualified.
Reactor Operator Senior Reactor qualified.
~
r4 6 Instructions - Operations Pre-Release Instructions Pre-Release -
[1]
[1] RECORD Waste Gas Decay Tank (WGDT) being released.
Tank (WGDT)
WGDT
[2] OBTAIN approval of the US/SRO for radiation monitor checks.
/
~ US/SRO I *17JDA t Date r00~
IIJoJ Time
SQN SQN Waste Gas Waste Gas Decay Tank Release Decay Tank Release 0-Sl-CEM-07 0-SI-CEM-077 7-410.4
-410.4 Unit 00 Unit Rev.
Rev. 00150015 Page 99 of Page of 42 42 6.1 6.1 Pre-Release Instructions Pre-Release Instructions - Operations
- Operations (continued)
(continued)
)1 IF 10-RM-90-1 IF [O-RM-90-118J operable, THEN 181 isis operable, THEN PERFORM source PERFORM source check response, and check response, and COMPLETE the COMPLETE following table.
the following table.
- ",Initials Background Source Background Source Check Check Monitor Monitor Operable Operable? Initials
Response
Response ' Response Response Setpoint Setpoint Yes/No Yes/No (cpm) ,
(cpm) (cpm)
NJA N 1;'+
tJIA Iv1/A. 'WD £N
! I
~ePtance ptance Criteria: Source Check Response> Background.
I V
/ NOTE '
is
/or thethe purposes of this Instruction, if the flow instrumentationinstrumentation for the shield building is INOPERABLE, INOPERABLE, then the monitor is considered NOT OPERABLE, OPERABLE , and a background of 0 "0"
is is used for permitting the release.
(jfJ IF IF [RE-90-4001 IRE-90-4001 is is operable operable forfor unit receive flow, THEN will receive that will unit that THEN COMPLETE COMPLETE the the following table:
following table:
' Initials';
Unit Unit Background Background Monitor Setpoint MonitorSetpoint Initials (IlCi/sec)
(pCilsec) (iCi/sec)
(IlCi/sec)
,..- ~ :>-
(~ / t:-g fS*/ 23,400 23,400
/0v
[5]
[5] TRANSMIT TRANSMIT releaserelease permit permit to to Chemistry Laboratory.
Chemistry Laboratory.
SQN SQN Waste Gas Waste Tank Release Decay Tank Gas Decay Release 0-Sl-CEM-07 0-SI-CEM-077 7-410.4
-410.4 Unit 00 Unit Rev. 0015 Rev. 0015 PagelOof42 Page 10 of 42 6.2 6.2 Pre-Release Instructions Pre-Release Instructions - Chemistry
- Chemistry ENSURE that ENSURE that radwaste radwaste operator has aligned operator has the applicable aligned the applicable WGDT to WGDT to the the waste waste gas gas analyzer.
analyzer.
NOTES NOTES Vsecond sample signoff econd signoff in the following step should be marked N/A if 0-RM-90-1 0-RM-90-118 18 is OPERABLE.. IfIf 0-RM-90-1 OPERABLE 0-RM-90-118 18 is is NOT OPERABLE , a second sample NOT OPERABLE, a second sample must be must be
~ependently collected and analyzed.
pdependently 2VAII noble gas samples must be analyzed within one hour of sample collection.
2,/AlI Otherwise, another sample must be collected.
p;;;r-7/ SAMPLE applicable WGDT in accordance with 0-TI-CEM-000-016.40 0-Tl-CEM-000-01 6.40 and COMPLETE the following table.
': ,,' ,,', :'~>', >
Sample Sample Time Time Analysis Time' Analyst First lt5DA f I.)IS'
/.)lI I{)D.A',/ 1230 1Z3 C£zI I Second \ WIA /'
r SQN SQN Unit00 Unit Waste Gas Waste Gas Decay DecayTank Tank Release Release 0-Sl-CEM-07 0-SI-CEM-077-41 Rev. 0015 Rev. 0015 7-410.4 0.4 L Page 11of42 Pagell of 42 6.2 6.2 Pre-Release Instructions Pre-Release Chemistry (continued)
Instructions - Chemistry (continued)
!jJf IF Waste IF Waste Gas Analyzer isis OPERABLE Gas Analyzer OPERABLE, , THEN THEN RECORD oxygen RECORD oxygen and hydrogen concentration and hydrogen concentrations from Waste s from Waste Gas Analyzer Gas Analyzer in in the table below the table Step 6.2[4]
below Step N/A grab and NIA 6.2[4] and grab sample analyses sample analyses data data blanks.
blanks.
r;f5 IF Waste IF Waste Gas Analyzer is Gas Analyzer OPERABLE,, THEN NOT OPERABLE is NOT THEN RECORD Grab RECORD Grab Sample Sample analysis analysis data below, and table below, in table data in and N/A-N/A Waste NIA Waste Gas Analyzer data Gas Analyzer data blanks.
blanks.
Item Waste Gas Grab Sample Sample Initials Analyzer Data Analyzer Analyses Data Data
(%) (%)
Oxygen 7)
Concentration Concentration o. S-73 0, ~ NIA ~
~
4 Concentration Concentration 0.0\ 0 ely RECORD tank pressure of WGDT to be released in the following table, table, and and N/A NIA all all remaining remaining blanks.
blanks.
. '. . '. .,(,'
'WGDT WGDT Indicator Indicator Pressure Pressure WGDT WGDT Indicator Indicator Pressure Pressure Number Number Number Number (psig)
(psig) Number Number Number Number (psig)
, (psig)
AA O-PIS-77-115 O-PIS-77-115 rJ\3 II A- FF O-PIS-77-102 0-PIS-77-102 N((\-
BB 0-PIS-77-114 O-PIS-77-114 {; GG O-PIS-77-145 0-PIS-77-145 (C) f)
1 0-PIS-77-113 O-PIS-77-113 G(, ~-1f HH O-PIS-77-146 0-PIS-77-146
~-
O-PIS-77-147
.y 0D 0-PIS-77-100 O-PIS-77-100 tJ fAA JJ 0-PIS-77-147 EE 0-PIS-77-101 O-PIS-77-1O1 .-0
SQN SQN Waste Gas Waste Decay Tank Gas Decay Tank Release Release O-SI-CEM-0 77-410.4 0-SI-CEM-077-41 0.4 Unit 0 UnitO Rev. 0015 Rev. 0015 Page 12 Page of 42 12 of 42 6.2 6.2 Pre-Release Instructions Pre-Release - Chemistry (continued)
Instructions - Chemistry (continued)
(jff IF hydrogen IF concentration is hydrogen concentration is greater percent, OR 40 percent, than 40 greater than OR IF oxygen IF oxygen concentration concentration is greater than is greater percent, THEN than 55 percent, THEN PERFORM either PERFORM Step 6.2[6.1]
either Step 6.2[6.1] or 6.2[6.2] as or 6.2[6.2J as appropriate.
appropriate.
~ REQUEST Operations to dilute tank prior prior to release, and WHEN notified of completion of tank dilution, dilution, THEN GO TO Step 6.2[1]6.2[1], OR OBTAIN support for release rate calculations from System Engineering and/or Cognizant Chemist, and RECORD the support provided in the Remarks "Remarks" section of Surveillance Task Sheet.
(f,1) INFORM Operations of completion of sampling so they can realign the appropriate WGDT.
. NOTES 10f 1 two wer~
o samples were required, the analysis results associated with the higher noble gas concentration should be used for further release permit processing.
2)~e ratesetpoint calculations for 11,2-RM-90-4 2)e EMS release rate$etpoint ,2-RM-90-400 tCi/s 00 are labeled as IlCi/s rather rather than cpm.
ANALYZE ANALYZE the the sample(s) collected above, sample(s) collected one hour, within one above, within in hour, in accordance accordance with with Appendix Appendix CC for for principal principal gamma gamma emitters emitters (noble (noble gas).
gas).
PROCESS PROCESS release release permit permit in accordance with in accordance Appendix E, with Appendix and E, and ENSURE ENSURE the the expected expected release release rate (RM-90-400 from rate (RM-90-400 Page 11 from Page of of the the special report) isis less special report) 23,400 IlpCi/s.
than 23,400 less than Ci/s.
j SQN SQN WasteGas Waste DecayTank Gas Decay TankReleas Release e 0-S1-C 0-Sf-CEM-077 EM-0774104 10,4 Unit 00 Unit Rev. 0015 Rev. 0015 L Page 13of42 Pagel3 of 42 6.2 6.2 Pre-Release Pre-Re lease InstrucInstructions tions -Chemi
- Chemistry stry (contin (continued) ued) the total IF the IF total body body dose dose rate determined inin the rate determined last step the last step isis 7 greaterthan greater than 47.8 47.8 mrem/yr mrem/yr or orthe noble gas the noble release rate gas release rate isis
>23,400 jiCils,
>23,400 ~Ci/s, THEN THEN REPROCESS REPROCES release at S release at aa lower release rate lower release rate by Step 6.2[9}
by Step 6.2[9]
above (applicable above (applicable sectionsection of of Appendix E release Appendix E release processing). processing).
~VcOMPLETE
,,(oMPLETE the the following following tables using results tables using from analysis results from analysis
~ performed ~erformed above. above.
Dose Rates Dose Rates Data Data Accep Acceptance tance Initials Initials
- Criteri Criteria a
[ft :::; 4.78E+01 Total body dose rate (mrem/yr): 1 qIq, qt.j - c!fv-t..j, s-q b
£- L/ :::; 2.87E+02
~
Skin dose rate (mrem!yr):
Skin (mrem/yr): U Parameter Parameter Data Acceptance Acceptance Initials Initials Criteria Criteria 0-RM-90-118 0-RM-90-1 18 setpoint (cpm) Nft
/J / 13.88E+03
- 1.88E+03(3) g4 leLl et; /
I
~/£/
1,2 I ,2 RE-90-400 RE-90-400 Expected Expected Response Response 2.34E÷04
- 2.34E+04(2) 2
(~Ci/sec)
(Ci/sec) 0,0 /70/7 I 7/ 7 Maximum Maximum allowable allowable release elease rate rate from from 57(1)
- 57(1) /
Appendix 0 analysis Appendix D analysis (CFM) (CFM) j ()
C4/~
Ij(j (1)
(1) Maximum Maximum release release flow flow rate rate that that flow instrumentation can flow instrumentation measure.
can measure.
(2)
(2) This This value value isis based based onon ODCM ODCM Rev.Rev. 45 45 which 9.55% of which isis 9.55% ofthe release rate the release limit for rate limit Xe-i 33 for Xe-133 at at 500 500 mRem/y mRem/y and and can can NOT NOT be be changed changed without change to without aa change to the the ODCMODCM (this value isis (this value equivalent equivalentto to -1.73E-03 1 .73E-03 I-lCilcc).
pCi/cc).
(3)
(3) This This isis aa default defaultsetpoint setpoint defined defined inin the the ODCM.
ODCM. Temporary changes can Temporary changes can be made up be made up toto
~ 32,526 CPM (the ODCM 32,526 CPM (the ODCM Limit). Limit).
SON Waste Gas Decay Tank Release O-SI-GEM-077 -410.4 Unit 0 Rev. 0015 Page 14 of 42 6.2 6.2 Pre-Release Pre-Re Instructions lease Instruc tions -Chemi
- Chemistrystry (contin ued)
(continued)
IFIFthe thesetpoin setpoint for0-RM-t for 0-RM-90-118 step 6.2[1 90-1 18 inin step 6.2[11] greaterthan 1] isisgreater than step 6.1 [3],
step 6.1[3J, THEN THEN UPDATE UPDA TE thethe CDAS CDAS CHEM CHEM5 5 setpoin setpoint screen inin accord t screen ance accordance with Appen with Appendix dix H. H. JrJ/4-NNOTV OT-. .
Appendix Appen dix AA isis based based on on the the setpoin setpoint of PCV-7 t of PCV-77-117 psig) and (2.0 psig) 7-1 17 (2.0 and aa temper temperature of 80°F.
ature of 80°F.
DETERMINE DETE RMINE the the expect expected ed pressu pressure re drop across flow drop across flow orifice orifice
[0-FE-77 FO-FE-77-23 -230]
01 using using Appendix Appen dix A, A, the the maxim maximum um allowa ble allowable release rate release rate from from Step Step 6.2[1 6.2[11] above and 1] above and hydrog hydrogen en concentration concen tration from Steps 6.2[3] or Steps 6.2[3j or 6.2{4].
6.2[4].
I/
inches of H 0 2
H2 0 Perform Performerer RECORD RECORD release number number and the allowable pressure drop allowable pressure across flow orifice [0-FE-77 across rO-FE-77-23 -2301 smaller of Step 6.2[13]
01 as the smaller 6.2[13]
or or the the administrative administrative limit of ::;;14 14 inches of water on Appendix Appen dix B.
~ IF [O-RE-90-1181 is IF [O-RE-90-118] INOPERABLE, THEN is INOPERABLE, OBTAIN OBTAIN independent verification of independent verification of Steps 6.2{13} and Steps 6.2[13] 6.2[14]
and 6.2[14]
above.
above. '
Sf'-l /I u~ /I "fj[),4t /I Now V~fier
<fLy inches inches of of HH 0
220 Ind. Vfier Ind. Date Date Time Time
SQN SQN Waste Gas Waste Gas Decay Tank Release Decay Tank Release 0-Sl-CEM-077-410.4 0-SI-CEM-077 -410.4 Unit 00 Unit Rev. 0015 Rev. 0015 PaQe 15 Page 15 of of 4242 6.2 Pre-Release Instructions - Chemistry (continued)
Pre-Release Instructions (continued) p SIGNOFF for item SIGNOFF item A and item B and either item or item B or item C C and CIRCLE&or C CIRCLE(or indicate which one to indicate C to one was satisfied.
satisfied.
A. Approval of pre-release data generated by this Instruction.
CLL perf~mer Perfthmer If on7 DA i-Date
/f Time eJ r\J C)() cd g;
7 erification cation that monthly projected offsite dose limits (ODCM SR 2.2.2.4) have NOT been exceeded, based on ts C.
most recent performance of Sl-422.1, SI-422.1, OR Verification, with Operations support, that selected ----" WGDT has been held a minimum of 60 days and all applicable requirements have been met.
fi /lDA-i I f/ NoJ Perfomer Date Time
~ TRANSMIT release package to Operations with authorization P to release. '
6.3 6.3 Release Release Instructions Instructions - Operations
[1] REVIEW Steps Steps 6.1 [3] and 6.1 6.1[3] 6.2[11j monitor
[4] and Steps 6.2[11]
6.1[4]
data.
[2]
[2] IF IF radiation radiation monitor 0-RM-90-1 18 setpoint monitor 0-RM-90-118 change is setpoint change required, is required, (when (when setpoint setpoint inin Step 6.2[1 1] is Step 6.2[11] than the greater than is greater setpoint in the setpoint in Steps 6.1 [3]), THEN Steps 6.1[3]), THEN REQUEST change.
setpoint change.
REQUEST aa setpoint
SQN SQN Waste Gas Waste Gas Decay Tank Release Decay Tank Release 0-SI-CEM-0 0-SI-CEM-077 77-410.4
-410.4 Unit 00 Unit Rev. 0015 Rev. 0015 Page 16 Page 16 of of 42 42 6.3 6.3 Release Instructions Release Instructions - Operations
- Operations (continued)
(continued)
[3]
[3] IF aa release IF release isis to be made to be outside of made outside release hours normal release of normal hours (0900 -
(0900 1600),
- 1600), THEN THEN OBTAIN US/SRO OBTAIN justification and US/SRO justification in remarks initials in and initials section of remarks section of Surveillance Task Surveillance Task Sheet.
Sheet.
[4]
[4] OBTAIN US/SRO OBTAIN approval of US/SRO approval pre-release data of pre-release generated by data generated by this Instruction this Instruction and and approval approval for for this this release.
release.
I/ /
US/SRO Date
- -Time
[5] INITIATE release of selected WGDT contents in accordance 0-SO-77-1 5 at or below the flow rate (i.e., pressure drop) with 0-SO-77-15 recorded on Appendix B, and RECORD release start time and information requested in the table in Appendix B for release initiation and at one-half hour intervals.
NOTE OPERABLE OPERABLE status status of 0-FE-77-230 can be be determined by indicator.
noting deflection of indicator.
by noting
[6]
[6] IF IF [0-FE-77-230J
[0-FE-77-2301 is INOPERABLE at is INOPERABLE initiation of at initiation release, of release, THEN THEN GO GO TO TO Step Step 6.3[8].
6.3[8].
[7]
[7] IF IF [0-FE-77-230]
[0-FE-77-2301 becomes INOPERABLE during becomes INOPERABLE release, during release, THEN THEN PERFORM PERFORM the the following substeps:
following substeps:
[7.1]
[7.1] STOP STOP release.
release.
[7.2]
[7.2] NOTIFY NOTIFY US/SRO.
US/SRO.
SQN Waste Gas Decay Tank Release 0-Sl-CEM-077-410.4 0-SI-CEM-077 -410.4 Unit 00 Unit Rev. 0015 17 of 42 Page 17 6.3 Release Instructions - Operations (continued)
[8] [0-FE-77-2301 INOPERABLE, IF release is to continue with [0-FE-77-230JINOPERABLE, THEN PERFORM the following substeps.
[8.1]
[8.11 ENSURE that a test gauge (0 - 20 inches of H
- 0 2
H20 suggested) is installed across [0-FE-77-2301.
[8.2] ENSURE serial number, range and calibration due date Mechanics of test gauge along with installing Instrument Mechanic's initials are recorded in remarks section of Appendix B.
[8.3] ENSURE pressure readings from test gauge are recorded in place of [O-FE-77-230J
[0-FE-77-2301 readings on Appendix B.
[9] IF 10-RM-90-1181 fRM-90-400J alarms, THEN fO-RM-90-118J or [RM-90-4001 NOTIFY On-shift Chemistry Personnel who will contact the Cognizant Chemist/System Engg. for further guidance in processing tank contents.
[10] WHEN release is complete or stopped, THEN RECORD the following on Appendix B.
[10.1] Release stop time o D
[10.2]
[10.2J WGDT psig o
[10.3] Initials Initials' oD
[11] IF radiation monitor setpoint changes were made (Step 6.3[2]), THEN RETURN the radiation monitors to their initial setpoints.
[12] NOTIFY the US/SRO and On-shift Chemistry Personnel that this release is complete.
[13] REVIEW 0-SO-77-15.
[14] ATTACH 0-SO-77-15 ATIACH 0-S0-77-15 to this release package.
[15] TRANSMIT the release package to the Chemistry Laboratory for post release evaluation.
SQN Waste Gas Decay Tank Release 0-SI-CEM-077-410.4 0-SI-CEM-077-41 0.4 UnitO0 Unit Rev.0015 Rev. 0015 Page 18 of 42 7.0 POST PERFORMANCE ACTIVITY-CHEMISTRY
[1] CLOSE the permit, and DETERMINE the release total body and skin dose rates during the WGDT release according to Appendix F. 0
[2] COMPLETE the following table. oC Dose Rate (mrem/yr) Data Acceptance Criteria Initials Total Body Dose Rate E+O1
< 4.78 E+01 Skin Dose Rate E÷02
< 2.87 E+02
[3] IF any Acceptance Criteria were NOT met, THEN PERFORM the following actions. 0C
[3.1] REVERIFY and REANALREANALYZE YZE sample. 0C
[3.2] RESAMPLE and REANAL REANALYZE.
YZE. 0C
[3.3] REVIEW of Operations logs, System Operating Instructions, etc. 0C
[3.4] EVALUATE all release pathways to determine if a violation of offsite dose criteria has occurred. 0C
[4] IF the investigation above does NOT resolve the failure to meet the Acceptance Criteria, THEN INITIATE an evaluation in accordance with O-Tl-CEM-030-030.O, and O-TI-CEM-030-030.0, NOTIFY the SM immediately of the results of the above evaluation. 0C
[5] COMPLETE the SPP-8.1 Chronological Test Log. 0C
[6] ENSURE all records, evaluations, analyses, calculations, and the SPP-8.1 Chronological Test Logs are attached to this data package. 0
SQN Waste Gas Decay Tank Release 0-Sl-CEM-077-41 0-SI-CEM-077 0.4
-410.4 Unit 0 Rev. 0015 Page Paael919 of 42 7M 7.0 POST PERFORMANCE ACTIVITY-CHEMISTRY (continued)
[7] RECORD the completion date and time on the Surveillance Task Sheet. 0
[8] COMPLETE the Test Performers block on the Surveillance Task Sheet, if not already done. 0Li
[9] IF the CDAS CHEM5 screen was changed in Step 6.2[12],
THEN RETURN it to initial setpoint in accordance with Appendix H. 0Li 8.0 RECORDS The completed SI package is a QA document controlled in accordance with SPP-2.4.
SQN SQN Waste Gas Waste Gas Decay Decay Tank Tank Release Release 0-SI-CEM-077-410.4 0-SI-CEM-077 -410.4 Unit 00 Unit Rev.
Rev. 0015 0015 Page 20 Page of 42 20 of 42 Appendix A Appendix A (Page 11 of (Page of 1) 1)
Correction Curve Correction Curve Expected Pressure Expected Pressure Drop Drop Across Q-FE-77-230 1 Across OFE77230 1
Hydrogen:
Hydrogen: As indicated As indicated by by curves curves Oxygen:
Oxygen: 0-5% (By 05% (By Volume)
Volume)
Balance:
Balance: Nitrogen Nitrogen Hydrogen: As indicated by curves 60 40%
40%
55 Hydrogen Hydrogen 25%
25%
50 15%
15%
10%
10%
5%
5%
0%
0%
45 40 35 E
()
30 00
..J
-J u..
U- 25 20 15 10 5
o 5 10 15 20 INCHES INCHES IN WATER IN WATER Based Based on on 2.0 2.0 psig psig and and 80°F.
80°F.
SQN SQR Wa$teGas Waste GasDecay DecayTank TankReleas Release e ro-sl-c EM-o7741o.4 0-SI-CEM-077-410.4 Unit00 Unit Rev. 0015 Rev. 0015 Page2121 of42 Page of 42 Appendix Appen dix BB (Page1 1of (Page of1)1)
Release Releas e Data Data IReleas Release Number:
e Numb er: I;<%o/J,.o.?},
j/o, IUn1t:
oo/,GIUnit:
oi I ..9. IDate:
Date: I '/oIJAY Release Releas e Release Releas e Tank Tank Start Time: Stop StopTime: Time: ID:
10:
StartTime:
Pressure Pressu re dropdrop limit limit across across 0-FE-7 0-FE-77-2307-230 Admin Admin. . pressu pressure drop limit.
re drop limit.
'5:1 L/ inches inches of H20of H2O of H inches of 14.0 inches
< 14.0 0 2H2O Parameter Param eter Data Data Time:
Time:
Countr ate for Countrate for 0-RM-0-RM-90-118, 90-1 18, (cpm):(cpm):
RM-90-400 RM-90 response,
-400 respon se,
()lCi/sec or or t2)lCi/cC)(2) c)
(liCi/sec iCi/c Shield Buildi Shield Building exhaustt flow ng exhaus flow rate, rate, 1 (cfm)(1)
(cfm
> )
Pressure Pressu drop across re drop across 0-FE-70-FE-77-2307-230 or IMs 1M's test gauge, (inches test gauge, (inches of H of H 0) 2 2 O)
Waste Gas Decay Tank pressure, Waste Gas Decay Tank pressure, (psig)
Operator Operator in in charge charge of of release, release, (initials)
(initials)
Remarks:
Remarks:
(1) Actual Actual flowflow rate rate for forapplicable applicable Shield Shield Building vent Building vent (Computer (Computerpoint point 1,1 2Y2210A 2Y2210Afor applicable Unit).
forapplicable flow Unit). IfIfflow measuring instrumentation measuring instrumentation is NOT is NOT ABLE OPERABLE, OPER , total total design design flow flowrate fans inin operation rate ofoffans operation isis used used (for example, (forexample,
'ABGTS ABGTS design design flow flow rate rate is is 9000 9000 cfm).
cfm).
(2)
(2) IfIfflow flowindicator indicatorisisNOTNOTOPERABLE, OPERABLE, record pCi/ccvs record\-lCi/cc vs
\-lCi/sec.
pCi/sec.
SQN SQN Waste Gas Waste Decay Tank Gas Decay Tank Release Release 0-Sl-CEM-07 7-410.4 0-SI-CEM-077-41 0.4 UnitO0 Unit Rev0015 Rev. 0015 Page 22 of Page 22 of 42 42 Appendix CC Appendix (Page 11 ofl)
(Page of 1)
Sample Requirement Sample Requirements s 1.0 1.0 SAMPLE REQUIREM SAMPLE REQUIREMENTS ENTS
~
Noble I
Noble gas gas samples samples must must bebe counted counted within NOTE NOTE 60 minutes within 60 sample collection from sample minutes from collection 2000 seconds in for 2000 in order order to LLDs. If>
to meet 60 minutes If> 60 elapsed from has elapsed minutes has collection time, collection time, collect collect another another sample.
sample.
1.1 1.1 COUNTING ANALYSIS
[1] COUNT the sample by following the CAS SAMPLE PROCESSING PROCESSING MENU.
J
/ NME NOTE REFER TO Appendix D of this instruction for Gaseous Release Permit Processing.
REFER
[2]
[2] PERFORM Appendix E.
PERFORM E.
SQN SQN Waste Gas Waste Gas Decay Decay Tank Tank Release Release 0-SI-CEM-0 0-SI-CEM-077 77-4104
-410.4 UnitO0 Unit Rev 0015 Rev. 0015 Page Page 23 of 42 23 of 42 Appendix 0D Appendix (Page 11 of (Page of 5) 5)
Gaseous Release Gaseous Release Permit Permit Processing Processing 1.0 1.0 DEFINITIONS DEFINITION S 1.1 1.1 Effluent Management Effluent Management System System (EMS) - Introduction to (EMS) - Introduction to Gaseous Gaseous Permits Permits The gaseous The gaseous effluent effluent permit definition form permit definition form is is used used to input defining to input data for defining data for aa new new data for aa permit already in edit data permit and to edit database. To in the database. move around in the To move screen, use screen, use the the following keys:
keys:
TAB key: Moves the cursor forward through the screen. No Moves data is No data is changed when changed_wh en_using_TA using TAB. B.
CTRL P: The CRTL key is held down and the "P" key is pressed to move lip, the cursor backward through the screen. No data is changed.
RETURN key: Terminates an input. This key will blank, or zero, a data field.
PF1 key: Moves the cursor to the command line at the bottom* bottom of the screen. Repeated pressing of this key at the command line will expose any other commands, if available. This key is also used to call data onto the screen from some menus.
PF3 key: Used to return to the previous screen, or to a previous sub-section. Also known as the END key.
PF4 key: Exits from the EMS software. Also known as the QUIT key.
In In addition addition to to the the above above keys, keys, all function keys all function listed on keys listed command line on the command line at the at the bottom bottom of the screen have have a code in in parentheses parentheses that corresponds to the key key with that that label.
label. To To perform perform thethe stated stated command, command, press press the enclosed in parentheses.
key enclosed in parentheses.
the key The The function function can can also also be be performed performed by by typing command name the command typing the with the name with cursor the cursor located on the command located on the command line.
line. Commands Commands associated associated with with the the gaseous gaseous effluent effluent permit permit definition definition screen screen include:
include:
HELP:
HELP: Provides Provides assistance assistance or or additional information.
additional information.
PERMITS:
PERMITS: Provides Provides aa list list ofof existing permit entry existing permit numbers.
entry numbers.
SAMPLES SAMPLES Displays Displays aa listlist of samples inin the of samples database.
the database.
FILL:
FILL: Allows Allows thethe computer computer to calculate blank data to calculate blank fields.
data fields.
SAVE:
SAVE: Inscribes Inscribes datadata inin the database. Use the database. entering or after entering Use after altering or altering data data onon the the Permit Form and Definition Form Permit Definition using before using the and before the PROCESS PROCESS command. command.
PROCESS:
PROCESS: Sends Sends data entered on data entered on the Permit Definition the Permit Form to Definition Form system the system to the for for calculation calculation of setpoints and of setpoints doses.
and doses.
SQN Waste Gas Decay Tank Release O-Sl-CEM-077-410.4 0-SI-CEM-077 -410.4 Unit 0 UnitO Rev.0015 Rev. 0015 Page 24 of 42 Appendix D D (Page2of5)
(Page 2 of 5)
Gaseous Release Permit Processing 1.1 Effluent Management System (EMS) - Introduction to Gaseous Permits (continued)
The concentrations table is used to review nuclides and concentrations in aa given sample, or to edit the nuclides and concentrations in aa given sample. Commands associated with the concentration table include:
HELP: Provides assistance or additional information.
COMPOSITES: Reads in current monthly/quarterly composite nuclide data for a specific release point.
VMS-GSP: Reads in gamma nuclide data from a specific release sample.
SAVE: Used after editing nuclide and concentration data.
DELETE: Used to delete sample nuclide data.
systems calculations of dose The results form displays the values resulting from the system's rates and doses, and indicates whether these values have exceeded the applicable limits. This form also displays the set-points for radiation monitors. Commands associated with the results form include:
HELP: Provides assistance or additional information.
OPEN: open status so pre-release reports Places the permit in an "open" can be generated.
CLOSE: Ends the permit processing after the release is complete and the_permit_is_updated_with_real_release_data.
the permit is updated with real release data.
DELETE: Deletes dose and activity data for a release permit from the database.
REPORT: Provides printouts of pre-release and post-release data.
SQN SQN Waste Gas Waste Gas Decay Tank Release Decay Tank Release 0-Sl-CEM-07 0-SI-CEM-077 7-410.4
-410.4 Unit 00 Unit Rev.
Rev. 0015 0015 Page 25 Page of 42 25 of 42 Appendix D Appendix D (Page 3 of 5)
(Page3of5)
Gaseous Release Gaseous Permit Processing Release Permit Processing 1.2 1.2 Gaseous Release Gaseous Release Permit Permit Numbers Numbers Gaseous release permit Gaseous permit numbers numbers are assigned for are assigned release and each release for each are formatted and are as follows:
as follows:
YYYYSSS.RRR.sss.T YYYYSSS.R RR.sss.T where: YYYY YYYY =
= current year the current SSS = the sequential number of releases from the plant RRR = the release point number sss = the sequential number of releases from release point number T = A character, either "L" G, indicating L or "0",
that the release is either a gas or liquid release IEXAMPLE EXAMPLE 2000001.027.001.G 2000001.027.001 .G
\
In the example example above, the release liquid release of 2000 both from the release is the first liquid plant and from Release Release Point Number Number 27.
Release Release Permit Permit Numbers Numbers are are assigned automatically by assigned automatically the Effluent by the Management Effluent Management System System (EMS)
(EMS) when aa permit permit is defined.
is defined.
cc,) oz 0
ci
-I om 0 0 SQN Waste Gas Decay Tank Release C)
CD ci)
(I) CD C.) ci) ci) CD CD ci) 0CD 0*SI*CEM*077*410.4 I -.4 Unit 0 Rev. 0015 Page 26 of 42 CD o 0
Appendix D 0.
CDCD -4 (Page 4 of 5)
G)
Gaseous Release Permit Processing 0
CD 0 C C) CD CD ci)
C)
CD CD 1 3 0
-I C.)
CD 0
0 CD 1.2 G) CD 0 0 CD CD 0 CD Gaseous Release Permit Numbers (continued) 0 -D CD -I 3 z C 3 CD 1 0 0 0 z z C CD 0.
0 m CDrn z NOTE H:3- :3-The short form of the SI number appears in EMS.
CD CD 0 0 CD CD :3 ac3- CD -,
V V
CD ci) 1 C,)
0
-n I 0 z 0 CD I-FOLLOWING IS A LISTING OF GASEOUS RELEASE POINT NUMBERS:
I Cl) H z 0 0 -n 0 > CD m 0 C CD m I m :1: CD m -o 0 z H
z C m CD Cl,
(/)>CC>CCCCGCECCCCCCCccCcCCczccccc
?mmcPOOm 9
000030 j
z 0
z m
3Jr\3r.JJ cBccmccbbbbbbbbbbbbbbbbzzClcl) m OX6cL)O2rnmmmCl Zrnrnmmmmmmmmmmmmmmmm<<C 23 MISCELLANEOUS UNDEFINED GAS zz mr Cy1C71 24 U1 CVE 119(99) NG (0-SI-CEM-030-415.0) ccoo H --c 25 U2 CVE 119(99) NG (0-SI-CEM-030-415.0) 0 O?<mmG)oc COD 26 U1 INCORE INST RM PG 0-SI-CEM-030-41 0.3
)occ,c-27 U1 CONTAINMENT VENT 0-SI-CEM-030-41 0.1 28 U1 CONTAINMENT PURGE 0-SI-CEM-030-41 0.2 29 U2 CONTAINMENT PURGE 0-SI-CEM-030-41 0.2 30 U2 INCORE INST RM PG 0-SI-CEM-030-41 0.3 HHHHHHHHHHHHHHHHHH 31 U2 CONTAINMENT VENT 0-SI-CEM-030-41 0.1 32 U1 WGDT A (0-SI-CEM-077-410A) 33 U2 WGDT A (0-SI-CEM-077-410A) 34 U1 WGDT B (0-SI-CEM-077-410A) 1 cn 35 U2 WGDT B (0-SI-CEM-077-410A) -
36 U1 WGDT C (0-SI-CEM-077-410A) 37 U2 WGDT C (0-SI-CEM-077-410A) mc--
38 ,U1 WGDT D (0-SI-CEM-077-410A) 9mmoooo>>mmcocoz 39 U2 WGDT D (0-SI-CEM-077-410A) -
40 U1 WGDT E (0-SI-CEM-077-410A) 41 U2 WGDT E (O-SI-CEM-077-410A)
QG)G)C)G)G)G)OOQG)OC)OOOc)<<m m.mmI--H 42 U1 WGDT F (0-SI-CEM-077-410A) 43 U2 WGDT F (0-SI-CEM-077-410A) 44 U1 WGDT G (0-SI-CEM-077-410A) 45 U2 WGDT G (0-SI-CEM-077-410A) m 46 U1 WGDT H (0-SI-CEM-077-410A) 47 U2 WGDT H (0-SI-CEM-077-410A) 48 U1 WGDT J (0-SI-CEM-077-410A) 49 U2 WGDT J (0-SI-CEM-077-410A) 50 ABGTS U 1 DISCHARGE (O-SI-CEM-030-415.0) C 01 S 51 U1 EGTS (0-SI-CEM-030-415.0) e 52 U2 EGTS (0-SI-CEM-030-415.0)
B ()° 3 m4 ob 53 AUX. BLDG. EXH. NG (0-SI-CEM-030-415.0)
Z . - e Cii 54 SERVICE BLDG EXHAUST NG (0-SI-CEM-030-415.0)
SQN Waste Gas Decay Tank Release 0-SI-CEM-077 -410.4 4I.
oC) om -.
-.1
-9 Cl, P.
CD C.) Cl, CD C) -( z CD CD Cfl CD Unit 0 F. 0 Rev. 0015 -
)CD Page 27 of 42 CD o oi -h . r3 Appendix D 0-*
(Page 5 of 5)cv CDCD -h Gaseous Release Permit Processing C) Cl, CD 0C Cl, CD CD Cl, CD
-o CD - 3 P.
-D 1
0 C)
CD Cl)
Cl) z 1.2 F) Gaseous Release Permit Numbers (continued)
Cl, CD 0
C C,)
CD CD Cl, CD -o CD 3 z C 3 0 CD ci) C) 0 P. C CD 55 ABGTS U2 DISCHARGE (O-SI-CEM-030-415-0.)
C-1HcC°m QQcIcDO p
mmwD C)C mmmm 03 T
aZZ8 C) 4 C)CC>CCC)CC>CCCC>
0 DD IIQ<<ITUJZI<<
- 5 0 Q1CJICII QWDAJ mmm>mmm>O]
56 U1 CVE 119(99) P/I (0-SI-CEM-030-407.2) 57 U2 CVE 119(99) P/I (0-SI-CEM-030-407.2)
ZZ 58 U1 SHIELD BLDG VENT NG (0-SI-CEM-030-415.0)
C44 99 (71 59 U2 SHIELD BLDG VENT NG (0-SI-CEM-030-415.0) (71 c.c.m 62 AUX BLDG EXHAUST P/I (0-SI-CEM-030-407.2)
-.1 J C mCDCmDC--
63 U1 SHLD BLDG EXH P/I (0-SI-CEM-030-407.2)
DDCX(0JC 64 U2 SHLD BLDG EXH P/I (0-SI-CEM-030-407.21 mcmc--
65 SERVICE BLDG EXHAUST P/I (0-SI-CEM-030-407.2) mmm° 66 U1 CVE 119(99) H-3 (0-SI-CEM-030-415.0) 67 U2 CVE 119(99) H-3 (0-SI-CEM-030-415.01 oI a8a-o I
rncDcD 68 AUX BLDG EXHAUST H-3 (0-SI-CEM-030-415.0)
P9; bCC.
xxxc c5b j34i 69 U1 SHLD BLDG EXH H-3 (O-SI-CEM-030-415.0) -.
xxx -.- C 70 U2 SHLD BLDG EXH H-3 (0-SI-CEM-030-415.0) --
71 SERVICE BLDG EXH H-3 (0-SI-CEM-030-415.0) -
SQN SQN Waste Gas Waste Gas Decay Tank Release Decay Tank Release 0-SI-CEM-0 0-SI-CEM-077 77-410.4
-410.4 UnitO0 Unit Rev. 0015 Rev. 0015 Page 28 Page of 42 28 of 42 Appendix EE Appendix (Page 11 of (Page of 7) 7)
Opening Permits Opening Permits 1.0 1.0 PROCESSING PROCESSIN WASTE GAS G WASTE GAS DECAY DECAY TANKTANK FOR FOR RELEASE RELEASE
~ REVIEW the REVIEW the gamma isotopic analysis gamma isotopic for correctness.
results for analysis results correctness. ~.
~ CORRECT CORRECT any any errors to processing.
prior to errors prior processing. /
W WHEN all all of of the the data data has has been verified, THEN been verified, LOG ON LOG ON aa CAS computer terminal (if CAS computer NOT already (if NOT logged on).
already logged on).
f~
/F-y
/tM::; SELECT the item on the Main item on associated with Menu associated Main Menu with Effluent "Effluent P
)& Management",
Management , and PRESS Return.
PRESS "Return".
i~~SELECT Process "Process Gaseous Permit Permit" option from the Effluent e;,Y Management Menu, and PRESS "Return".
Return.
/ ~
J NOTE In n the the following step, if a "?" ? is entered at the "Enter Number: prompt, aa list Enter Release Point Number:" list of of gaseous release point numbers will appear.
6 ENTER ENTER the the appropriate appropriate release release point number at point number prompt at the prompt "Enter Release Enter Release Point Point Number:",
Number:, and and PRESS PRESS "Return" Return..
.~TE NTE The The terminal terminal willwill indicate indicate that that three three samples samples may be required; may be however only required; however required one isis required only one for aa WGDT for WGDT release.
release.
PRESS PRESS thethe Return Return keykey three times.
three times.
SQN SQN Waste Gas Tank Release Decay Tank Gas Decay Release 0-Sl-CEM-077-410.4 0-SI-CEM-077-410.4 Unit 0 UnitO Rev. 0015 Rev. 0015 Page 29 Page of 42 29 of 42 Appendix EE (Page 22 of 7)
Opening Permits rTER 1.0 1.0 PROCESSING WASTE GAS PROCESSING GAS DECAY DECAY TANK FOR FOR RELEASE RELEASE (continued)
V4TER the noble gas sample number, and ESS Return.
~
)fESS "Return".
([9 SELECT the "Define Permit" option Define and Open aa New Gaseous Permit
/C from the menu.
SQN Waste Gas Decay Tank Release 0-SI-CEM-077-410.4 0-SI-CEM-077 -410.4 UnitO0 Unit Rev. 0015 Page 30 of 42 Appendix E E 3of7)
(Page 3 of 7)
Opening Permits 1.0 PROCESSING WASTE GAS DECAY TANK FOR RELEASE (continued)
V V NOTE information on the last permit for this release point will be displayed, and the system will Information ask if you want to define and open a permit.
~E E "Y" 2
j for Yes, and Y lor Return.
PRESS "Return".
rWfE NOfE In the following step, the estimated start time can be obtained from Operations, past experience, etc. Examples: 23-May-99 13:00, 5/23/99 13:00.
Release Start" ENTER the estimated start time at the "Release Start field, and I~S J3ESS "Return".
Return.
~~~~hrOUgh Release End" through the "Release field.
End field.
~NTER TAB ENTER the estimated release flow rate (routinely 50 CFM),
(Z: nand W d Return.
PRESS "Return".
$'[ ] PRESS "Return" field.
Release Volume Return at the "Release Volume" field to zero the
SQN Waste Gas Decay Tank Release 0-Sl-CEM-077-410A 0-SI-CEM-077 -410.4 Unit 0 Rev. 0015 Page 31 of 42 Appendix E (Page4of7)
(Page 4 of 7)
Opening Permits tO 1.0 PROCESSING WASTE GAS DECAY TANK FOR RELEASE (continued)
NOTE ~
/
The following pressure may change prior to release; however, it is only being used to estimate pre-release offsite dose.
~2 OBTAIN the initial pressure information from Operations, and P Initial Pressure" ENTER the value in the "Initial Pressure field.
,/,IPRESS p Return.
R E S S "Return".
NOTE . Z /
Based on the design of the Waste Gas Analysis System the following final pressure value should never be zero; however, this value is being used to estimate the maximum activity released and maximum offsite dose.
~ESS "Ret~rn" to zero the "Final
.RESS Return Pressure field.
Final Pressure"
~ ENTER the appropriate initials in the "Collected Collected By" By field, and Return.
RESS "Return".
PRESS V
~RESS Fill command to update the screen.
RESS the "Fill"
~/VERIFY YERIFY all data is correct.
~MAKE any required changes.
~~ESS Save command key.
SS the "Save" Y Process (Do)"
PRESS the "Process (Do) command.
SQN SQN Waste Gas Waste Gas Decay Decay Tank Release Tank Release 0-SI-CEM-077-410.4 0-SI-CEM-077 -410.4 Unit 00 Unit 0015 Rev. 0015 Rev.
Page 32 of Page 32 of 42 42 Appendix EE (Page5of7)
(Page 5 of 7)
Opening Permits Opening Permits 1.0 1.0 PROCESSING WASTE GAS PROCESSING GAS DECAY DECAY TANK TANK FOR RELEASE FOR RELEASE (continued)
/'
NOTE /
Sample Entry/Concentrations" The "Sample Entry/Concentrations screen will appear. After the following step, a message will appear that says the particulate and iodine sample configurations could NOT be opened. This message can be ignored.
~RESS
~~
2 PRESS the "VMS-GSP"
~'n
)iormation rmation VMS-GSP command to read the spectral data from the sample counted for this release. .~
<., VERIFY all nuclides and concentration values against the /
5& printed gamma spec summary report(s). o D
NOTEZ NOTE/
If the radiation monitor is NOT OPERABLE and the permit is being opened using the sample with the highest Noble Gas Concentration, the file may still need to be edited. The pre-release file should reflect all identified isotopes, excluding natural products, and the highest concentration between the two samples.
~he he radiation monitor [0-RM-90-118]
THEN is NOT OPERABLE,
[O-RM-90-118) is COMPARE all non-natural nuclides and concentration values against the printed gamma spec summary report printed gamma report and/or and/or corrected results for both both samples and and
.., EDIT EDIT in in accordance with Appendix G.
accordance with G.
~ natural occurring nuclides are present, THEN ji natural occurring nuclides are present, THEN EDIT EDIT in in accordance with Appendix accordance with Appendix G.
G.
SQN SQN Waste Gas Waste Gas Decay Decay Tank Tank Release Release 0-SI-CEM-077 -410.4 0-Sl-CEM-077-410.4 UnitO Unit 0 Rev 0015 Rev. 0015 Page Page 33 of 42 33 of 42 Appendix EE Appendix (Page6of7)
(Page 6 of 7)
Opening Permits Opening Permits /
1.0 1.0 PROCESSING WASTE GAS PROCESSING GAS DECAY DECAY TANK TANK FORFOR RELEASE RELEASE (contipued) conti ued)
F: /
.~
dEDIT 7 IF the concentration concentration for a nuclide removed or edited, THEN removed nuclide or a nuclide EDIT in accordance with Appendix G.
nuclide is to be be added,
~ ./ SELECT the "Process Process (Do)".
(Do).
~ ENTER the [0-RM-90-118] monitor's monitors background as V
determined by Operations, and Return.
PRESS "Return".
~ PRESS the "Process Process (Do)"
(Do) key.
~ç3ENTERENTER the background for [RM-90-400] as determined by
.V k/ Operations, and PRESS Return.
"Return".
~ PRESS SS the "Process Process (Do)"
(Do) key.
~REVIEW REVIEW all data on the results screen, and ENSURE no limits are exceeded.
[~ no limits are
[94 a~e exceeded, THEN PRESS the Process "Process (Do)
(Do)" key to open the permit.
/
/
/ NOTE IfIf limits are exceeded, the release will have to be be reprocessed utilizing aa lower flow rate.
~its are limits are exceeded exceeded and all input and all input data data is correct, THEN is correct, THEN CONTACT CONTACT the the Cognizant Chemist or Cognizant Chemist Designee before or Designee before proceeding.
proceeding. rJjA
SQN Waste Gas Decay Tank Release 0-Sl-CEM-077-410.4 0-SI-CEM-077-41 0.4 UnitO Unit 0 Rev.0015 Rev. 0015 Page 34 of 42 Appendix E (Page7of7)
(Page 7 of 7)
Opening Permits 1.0 PROCESSING WASTE GAS DECAY TANK FOR RELEASE n ued)
(con 'nued)
A/AFFIRM FFIRM that a permit is to be opened.
Report command.
PRESS the "Report" Return to obtain a default number of copies, OR PRESS "Return" IF needed, THEN INPUT more copies, and Return.
PRESS "Return".
~AIT AIT for reports to print out, THEN 4
PRESS the PF4 key to exit EMS.
,.~EVIEW 4fEVIEW the pre-release report.
~ IF the data is correct, THEN 7
( ATTACH , and LOG applicable data in the SI package.
SIGN, ATTACH, .~
SQN Waste Gas Decay Tank Release 0-Sl-CEM-077-410.4 0-SI-CEM-077 -410.4 Unit 0 Rev. 0015 Page 35 of 42 Appendix F (Page 1 1 of 4)
Closing Permits 1.0 POST- ANALYSIS POST-ANAL YSIS
[1))
[1 0-Sl-CEM-077-410.4 is complete on VERIFY the information in 0-SI-CEM-077-410A the returned release package. D
[2] LOG ON the CAS computer (if NOT already logged on). D
[3] Effluent Management",
SELECT the item associated with "Effluent Management, and Return.
PRESS "Return". D
[4] Process Gaseous Permit",
SELECT "Process Permit, and Return.
PRESS "Return". D
[5] ENTER the Release Point Number, and Return.
PRESS "Return". D
[6] Return four times to move out of the sample number PRESS "Return" section. D
[7] SELECT "Close Close A Gaseous Permit".
Permit. D I:
[8] TAB to move to the "Permit Permit Number" Number field. D C
[9] IF the Permit Number is correct, THEN Process (Do)"
PRESS "Process (Do) key. D
[10] ENTER the actual start time at the Release "Release Start Start" time field, and Return.
PRESS "Return". D C
NOTE The Stop Time may have to be adjusted if there were any interruptions during the release.
SQN Waste Gas Decay Tank Release 0-Sl-CEM-077-410.4 0-SI-CEM-077-41 0.4 UnitO Unit 0 Rev. 0015 Page 36 of 42 Appendix FF (Page 2 of 4)
Closing Permits 1.0 POST- ANALYSIS (continued)
[II]
[11 ] ENTER the actual stop time in the Release End time field, "Release End" and PRESS "Return".
Return. C 0
[12] Return at the "Release PRESS "Return" Rate field to zero the Release Flow Rate" field. C 0
[13] Return at the "Release PRESS "Return" Volume" field to zero the Release Volume field. 0
[14] ENTER the correct initial pressure value in the "Initial Initial Pressure" Pressure field, and Return.
PRESS "Return". C 0
[15] Pressure Final Pressure" ENTER the correct final pressure value in the "Final field, and Return.
PRESS "Return". C 0
[16] Fill key to update the screen.
PRESS the "Fill" C 0
[17] REVIEW the screen and VERIFY all data is correct. 0
[18] IF correct, THEN Save key.
PRESS the "Save" C 0
[19] (Do) key.
Process (Do)"
PRESS the "Process C 0
NOTE The "Sample Entry/Concentrations screen will appear.
Sample Entry/Concentrations"
[20] VERIFY all nuclides and concentration values are correct. o
SQN SON Waste GasGas Decay Decay Tank Release Release 0-SI-CEM-077-410.4 0-SI-CEM-077 -410.4 UnitO Unit 0 Rev. 0015 Rev. 0015 Page 37 of Page of 42 Appendix F (Page 3 of 4)
Closing Permits 1.0 POST- ANALYSIS (continued)
NOTES
- 1) Editing data in the following step requires a password which is available from Chemistry Supervision.
- 2) In the following step, the SAVE command is only required if the data has been edited.
[21] IF the concentration for a nuclide or a nuclide is to be added, removed, or edited, THEN EDIT in accordance with Appendix G. a 0
[221
[22] Process (Do)".
SELECT the "Process (Do). a 0
[23] IF all information is correct and no limits are exceeded THEN PRESS the "Process Process (Do)"
(Do) key to close the permit. 0 D
[24] ENTER "Y",Y, and PRESS Return, "Return". a0
[25] PRESS the Report "Report" command. a0
[26] PRESS Return "Return" to obtain aa default number of copies, OR IF needed, THEN INPUT more copies. a0
[27] REVIEW the printout, printout, and VERIFY the data is correct.
[28] PRESS the PF4 key to exit, PRESS exit. a0
SQN Waste Gas Decay Tank Release 0-SI-CEM-077-410.4 0-SI-CEM-077 -410.4 UnitO Unit 0 0015 Rev. 0015 Page 38 of 42 Page Appendix F (Page4of4)
(Page 4 of 4)
Closing Permits 1.0 POST- ANALYSIS (continued)
POST-ANALYSIS
[29] SIGN and ATTACH the printout to the SI,Si, and Si.
LOG applicable data in the 81. o
SQN Waste Gas Decay Tank Release O-SI-CEM-077-410.4 0-SI-CEM-077 -410.4 Unit 0 Rev. 0015 Page 39 of 42 Appendix G G (Page 1 1 of 3)
Editing Sample Entry/Concentrations Screen NOTES
- 1) The system will read in the gamma spectral data from the sample counted for this release. Editing of the concentration table may be required. Movement within the table is accomplished by using the arrow keys and the "Tab" Tab key.
- 2) If the radiation monitor is NOT operable and the permit is opened with the highest Eel ECL concentration editing may still be required. The pre-release file should have all identified isotopes included as well as the highest activity of each isotope identified included.
- 3) Return before saving.
Editing data requires a "Return"
- 4) When editing data, use applicable password EMS or SEMS.
1.0 ADDITION OF A NUCLIDE AND CONCENTRATION
[1]J
[1 IF a Nuclide and concentration is to be added, THEN PERFORM the following:
[1.1))
[1.1 PLACE the cursor below the last nuclide, and ADD the nuclide to the list. 0D
[1.2]
[1.2J PRESS T TAB, AS, and ENTER the concentration, and Return.
PRESS "Return". 0D
[2]
[2J IF other nuclides need to be added, THEN 1.O[1.2].
1.O[1.l] and 1.0[1.2J.
REPEAT sub-steps 1.0[1.1J 0
[3]
[3J PRESS "Save" (FlO).
Save command key (F10). 0D
[4]
[4J ENTER "Y"Y at the prompt "Has (YIN).
Has this been authorized? (YIN)". 0D
SQN SQN Waste Gas Waste Gas Decay Tank Release Decay Tank Release 0-Sl-CEM-077-410.4 0-SI-CEM-077-41 0.4 Unit 00 Unit Rev. 0015 Rev 0015 Page 40 Page 40 of of 42 42 Appendix G Appendix G (Page2of3)
(Page 2 of 3)
Editing Sample EntrylConce Editing Sample ntrations Screen Entry/Concentrations Screen 1.0 1.0 ADDITION OF ADDITION OF AA NUCLIDE NUCLIDE AND CONCENTRATION (continued)
AND CONCENTRATION (continued)
[5]
[5] ENTER the ENTER the appropriate password when appropriate password prompted, and when prompted, and PRESS Return.
PRESS "Return". D0 2.0 2.0 EDITING A NUCLIDE EDITING NUCLIDE AND CONCENTRATION CONCENTRATION
[1 ]
[1] IF a concentration for a nuclide is to be edited, THEN PERFORM the following:
PERFORM
[1.1 ]
[1.11 PLACE the cursor on the nuclide to be edited. D0
[1.2] PRESS TAB, TAS, and ENTER the concentration, and PRESS "Return".
Return. EJ 0
[2] IF other nuclides nucHdes need to be edited, THEN REPEAT sub-steps 2.0[1.1] 2.O[1.2].
2.O[1.1j and 2.0[1.2]. 0D
[3] PRESS "Save" Save command key (F10).(FlO). 0D
[4] ENTER "Y" (YIN).
Has this been authorized? (YIN)".
Y at the prompt "Has 01J
[5] ENTER the appropriate password when prompted, and PRESS PRESS "Return".
Return. 0D 3.0 3.0 REMOVAL REMOVAL OF OF A NUCLIDE CONCENTRATION NUCLIDE AND CONCENTRATION
[1
[11] IF IF aa nuclide nuclide and and concentration concentration is be removed, to be is to THEN removed, THEN PERFORM PERFORM the the following:
following:
[1.1
[1.1)) PLACE PLACE thethe cursor cursor on on the to be nuclide to the nuclide removed.
be removed. 0D
[1.2]
[1.2] PRESS PRESS thethe Remove Remove Key Delete Key or Delete Key or on the Key on keyboard.
the keyboard. 0C
SQN Waste Gas Decay Tank Release 0-SI-CEM-077-410.4 0-SI-CEM-077 -410.4 UnitO0 Unit Rev. 0015 Page 41 of 42 Appendix G (Page 3 of 3)
EntrylConcentrations Screen Editing Sample Entry/Concentrations 3.0 REMOVAL OF A NUCLIDE AND CONCENTRATION (continued)
[1.3] ENTER "Y" Y at the prompt "Has Has this been authorized?
(YIN).
(YIN)". D
[1.4] Return.
PRESS "Return". D
[1.5] SEMS when prompted for ENTER "SEMS" for the password, and Return.
PRESS "Return". D
[1.6] TYPE "R"R and PRESS "Return" Return When prompted by sample or row. D
[2] IF other nuclides need to be removed, THEN REPEATStep3.O[1].
REPEAT Step 3.0[1]. D
SQN SQN Waste Gas Waste Gas Decay Tank Release Decay Tank Release 0-SI-CEM-0 0-SI-CEM-07777-410.4
-410.4 Unit 00 Unit Rev. 0015 Rev. 0015 Page 42 Page of 42 42 of 42 Appendix HH Appendix (Page of 1)
(Page 11 of 1)
Updating the Updating Setpoint Screen CDAS Setpoint the CDAS Screen 1.0 1.0 UPDATING THE UPDATING THE CDAS SETPOINT SCREEN CDAS SETPOINT SCREEN NOTE NOTE The common rad monitors The monitors are are on UiU1 screen.
[1 ]
[1] SELECT the Rad Mon button from U1!U2 U1/U2 CDAS CHEMISTR CHEMISTRY Y MAIN VIEW. D
[2] CHANGE Security Level to level 7, and USE CHEMSET as the User name and password. D
[3] SELECT GASEOUS RAD MON SETPOINTS (CHEM 5) button. D
[4]
[4J SELECT the rad monitor button of the monitor to be changed. D
[5] SELECT the F2 key to zero the field. 1J D
[6] SET the cursor to the left of the decimal, and TYPE in the new setpoint. 1J D
NOTE Under Under the Date Date Modified Modified Field Field the the message NOT momentarily be displayed NOT SAVED will momentarily then the date will appear.
[7]
[7] SELECT SELECT thethe F3 F3 key key to to save the new save the setpoint.
new setpoint. D
[8]
[8] SELECT SELECT thethe F1 Fl Key.
Key. DC
[9]
[9] VERIFY VERIFY the the as as left setpoint.
left setpoint. DC
[10]
[101 SELECT SELECT thethe Chemistry Chemistry Rad Rad Mon button.
Menu button.
Mon Menu DC
[11
[11)) SELECT SELECT thethe Chemistry Chemistry MainMain View button (Chem_D1)
View button button.
(Chem_Di) button. D
._SSEE VALLEYVALLEY AUTHORIT AUTHORITY Y . 2010012.037 .O01.G 2010012.037.001.G
,_QUOYAH NUCLEAR PLANT PLANT -
Unit Unit #- 11 -
212 APP. B.9 BATCH GASEOUS BATCH GASEOUS EFFLUENT EFFLUENT PERMIT PERMIT Allocation l00.
Allocation 100.%
- ========================;=======================~~=== =======================
KEQUEST:
REQUEST:
XX NORMAL NORMAL RELEASE POINT RELEASE POINT ESTIMATED START:
ESTIMATED START:
UNPLANNED UNPLANNED U2 U2 WGDTC WGDTC (SI-410.4)
(SI-410.4) Today Tod~y 19:00:00 19:00:00 RELEASE VOLUME RELEASE VOLUME (EST.)
(EST.) DISCHARGE DISCHARG POINT E POINT ESTIMATED STOP; ESTIMATED STOP; 2.6122E+03 2.6122E÷03 CF CF U2 SHIELD U2 SHIELD BUILDING BUILDING EXHAUST EXHAUST Tod?y 19:52:15 Today 19:52:15
=====~=z~============================~========== =========~==========
II. SAMPLE II. SAMPLE IDENTIFICA IDENTIFICATION:
TION:
NUMBER NUMBER -
COLLECTION COLLECTIO DATE/TIME N DATE/TIME ANALYSIS DATE/TIME ANALYSIS DATE/TIME 9888 988 Tod_ay 00:03:00 Today 00: 03: 00 Today 00:18:46 Today 00:18:46 Noble Gas Noble Gas File File Name Name : CASSAM:S0 CAS SAM;S090211001.cnf 90211001.cnf Particulate File Name; Particulate File Name; N/A N/A-Radioiodine File Radioiodine File Name:
Name: N/AN/A
===========~==================================== =========;==========
III. RADIOANA III. RADIOANALYSIS LYSIS - GASEOUS:
GASEOUS: -
CUMULATIVE CUMULATI DOSES VE DOSES PROJ. BETA PROJ. BETA DOSE(31-DA DOSE (31-DAY)Y) DOSE (31-DAY)
PROJ. GAMMA DOSE(3l-DA Y) PROJ. ORGAN PROJ. O~GAN DOSE(31-DA DOSE(31-DAY) Y) 1.S7E-04 mrad 1.57E-04 mrad << 0.40 0.40 3.62E-0~ mrad <<
3.62E04 0.20 0.20 3.27E-04 mrem 3.27E-04 mrem < 0.30 < 0.30 AIR DOSE-BETA AIR DOSE-BETA(Q) (Q) DOSE-GAM~~(Q)
AIR DOSE-GAM AIR MA(Q) ORG.2\.N DOSE(Q)
ORGAN DOSE (Q) 1.06E-04 l.06E-04 mrad mrad < 10.00 10.00 2.45E-04 inrad mrad << 5.00 2.22E-04 mrem mrem << 7.50 7.50 AIR DOSE-BETA AIR DOSE-BETA(A) (A) DOSE-GAMVA(A)
AIR DOSE-GAM MA(A) O~GAN DOSE ORGAN (A)
DOSE(A)
- 06E-04 OEE-04 mradmrad << 20.00 20.00 2.45E-04 mrad < 10.00 2.22E-04 mrem 15,00 mrem << 15.00 YEPRLY YEARLY DOSE RATES LOC T-BODY
~LOC T-BODY DOSE DOSE RATE RATE ALLOC SKIN DOSE ~.TERATE 9.71E-04 9.71E-04 mrem/yr mrem/yr << 500.
500. 3000.
rnrem/yr << 3000.
2.29E-03 mrem/yr ALLOC ORGA...~
ORGAN DOSE RATE P_~TE Setpoint Sebpoint Option:
Option: Dose Dose Rates 0.OOE+00 mrem/yr << 1500.
O.OOE+OO 1500.
~============================~============================================~=
IV.
IV. RADIATION RADIATION MONITOR(S)
MONITOR(S)::
NUMBER NUMBER SETPOINT EXPECTED RESPONSE 0-RM-90-118 0-RN-90-118 (NG)
(NG) 1880.0 1880.0 CPM CPM 35.132 35.132 CPM 2-RH-90-400 2-RN-90-400 (NG)
(NG) 0.19997 0.19997 uCi/s uCi/s 0.17617 0.17617 uCi/s uCi/s
====================================================================
V.
V. AUTHORIZlI.TION:
AUTHORIZATION:
ivlAX.
MAX. VOLUME VOLUME MAX.
MAX. EFFLUENT EFFLUENT FLOWFLOW RATE RATE 2.6122E+03 2.6122E+03 CF CF 5.0000E+Ol 5.0000E+0l CFM CFM The and is is in compliance with in compliance with The above-named above-named source source hashas been been sampled sampled andand analyzed analyzed and the for the volume the volume and and the Offsite Offsite Dose Dose Calculation Calculation Manual.
Manual. Release Release is is authorized authorized for flow flow rates rates specified.
specified.
F-NESSEE VALLEY AUTHORITY
~ESSEE VALLEY AUTHORITY page page 11 of of 99
.OOYAI-I UOYAH NUCLEAR PLANT NUCLEAR PLANT 1'I-12 APP. B.9 TI-l2 APP. B.9 Gaseous Radioactive Gaseous Radioactive Waste Waste Release Release Permit Permit 2009012.037.001.
2009012.037.001.G G Pre-Release Supplementary Pre-Release Supplementary Data Data PART I:
PART I: PRE-RELEASE PRE-RELEASE DATA DATA RELEASE POINT RELEASE POINT C 37): U2 37); U2 WGDT WGDT CC (SI-4l0.4)
(SI-410.4)
DISCHARGE POINT DISCHARGE POINT C 8): U2 8): U2 SI4IELD SHIELD BUILDING BUILDING EXHAUST EXHAUST Permit Issued:
Permit Issued: 21-jan-2009 21-jan-2009 10:42:08 10:42:08 Release Type:
Release Type: Batch Batch Rad Monitor:
Rad Monitor: (C.4 0-RM-90-118 (C.4 )) 0-RM-90--1l8 Rad Monitor Rad Monitor Bckgrnd:
Bckgrnd: 3.5000E+01 CPM 3.5000E÷01 CPM Estim. Waste Estim. waste Flow:
Flow: 5.0000E+01 CFM CFM Estim.
Estim. Waste Waste Volume:
Volume: 2.6122E+03 2.6l22E+03 CF CF Estim. Release Estim. Release Start:
Start: 21-jan--2009 21-jan-2009 12:00:00 12:00:00 Estim. Release Estim. Release End:
End: 12:52:15 21-jan-2009 12:52:15 Initial Pressure 4000E+Ol 6.4000E+01 6.
Estim. Duration:
Estim. Duration: 52.2449 MIN 52.2449 Final Pressure 0000E+00 O.OOOOE+OO 0.
PART II:
PART II: PRE-RELEASE CALCULATIONS Sample Entry Sample Entry ## :: 9888 ble le Gas Gas File Name Name : CAS SAM:S090211001.cnf CASSAM:S090211001.cnf
- ticulate
- ticulate File Name: N/A File Name: N/A-
~ddioiodine adioiodine File Name: Name: N/A N/A Gas Gas sample sample time: 21-jan-2009 00:03:00 Sampled by: WDT Gas Gas Monitor Monitor Response: 3.51E+01 3.S1E+0l CPM Setpoint Setpoint Option: Dose Rates Allocated Allocated Total Body Dose Rate: 9.71E-04 mrem/yr %- Limit = 0. 0 0.0%
Allocated Allocated Skin Dose Rate: 2.29E-03 mrem/yr %- Limit
%- =
= 0. 0%-
O.O%"
Allocated Allocated Max Max Organ Organ Dose Rate: O.OOE+OO 0.OOE-i-00 mrem/yr % Limit
% =
= 0.0%-
0.0%
Max Max Monitor Monitor Setpoints: O-RM-90-118 0- RN 118 2-RM-90-400 2-RN 90 -400 Noble Gas 1. 88E+03 CPM l.88E+03 2.00E-01 2.OOE-Ol uCi/s Particulate O.OOE+OO A A A A A A
- 0. OOE+00 AAAAAA O.OOE+OO 0.OOE÷00 A .... AAAA Radioiodine O.OOE+OO 0.OOE+00 AAAAAA O.OOE+OO o.ooE÷oo "AAAAA Flag:
Flag:
Flags:
Flags; A-Release Curies>Curies > Local Local Limit N-Noble Gas Dose Rate > Limit Limit S-Release S-Release Curies Curies > > Site Site Limit Limit a-Organ 0-Organ Dose Rate > Limit Rate > Limit Analysis Analysis DateDate Measured Measured Coneen.
Concen. Est. Curies Est. Curies Noble Noble Gases Gases 21-jan-2009 2l-jan-2009 00:18:46 00;l8:46 4.03E-06 4.03E-06 uCi/cc uCi/cc 2.98E-04 2.98E-04 Particulates Particulates 21-jan-2009 21-jan-2009 00:18:46 00:18:46 O.OOE+OO 0.OOE÷00 uCi/cc uCi/cc 0.OOE+00 O.OOE+OO Radioiodines Radioiodines 21-jan-2009 21-jan-2009 00:18:46 00:18:46 O.OOE+OO 0.OOE÷00 uCi/ce uCi/cc 0.OOE+00 O.OOE+OO
- ~;~~;~~:~~~:::F !:tlj~:::::::::::::::: ~~:: ~~:: ~ ~::::::::::::
Date
VALLEY AUTHORITY
~ESSEE VALLEY NESSEE AUTHORITY page page 22 of of 99
~UOYAH NUCLEAR PLANT JJOYAH NIJCLEAR PLANT
-12 APP.
T1-12 APP. B.9B.9 Gaseous Radioactive Gaseous Radioactive Waste Waste Release Release Permit Permit .OOl.G 2009012.037.001.G 2009012.037 Pre-Release Supplementa Pre-Release Supplementary Data ry Data ISOTOPIC IDENTIFICATION ISOTOPIC IDENTIFICATION - Unit
- Unit 11 Pre-Disp. : Post-Disp.:
Pre-Disp. Post-Disp.: Release Release : Estimated Estimated
- Measured Measured
- Rate Rate : Curies Curies Isotope : uCi/cc Isotope uCi/cc uCi/cc uCi/cc uCi/sec uCi/sec Released Released XE-133 N:
XE-133 N: 4.03E-06;:
4.03E-O6 6.61E-13::
6.61E-13 9.52E-02::
9.52E-02 2.98E-04 2.98E-04 Totals::
Totals 4.03E-06:
4.03E-06 6.61E-13;:
6.61E-13 9.S2E-02;:
9.52E-02 2.98E-04:
2.98E-04
'lliESSEE VALLEY TNESSEE VALLEY AUTHORIT AUTHORITYY page page 33 of of 99
- UOYAH NUCLEAR PLANT UOYAH NUCLEAR PLANT APP. B.9
'.I..L-12 APP.
2 ii-l B. 9 Gaseous Radioactive Gaseous Radioactive Waste Waste Release Release Permit Permit 2009012.037 ,001.0 2009012.037.001.0 Pre-Release Supplementary Pre-Release Supplementa ry Data Data Calculated Gamma Calculated Gamma && Beta Beta : Calculated Calculated Doses Doses at at Site Site Boundary.
Boundary.
Air Doses Air Doses @@ Site Site Boundary:
Boundary: Gamma Gamma and and Beta Beta Air Air Doses, Doses, Tot-body and Skin Tot-body and Skin Doses and Doses and Dose Dose Rates.
Rates.
Type of Type of Activity Activity Noble Gases
- Noble Gases Controlling Sector Controlling Sector N Unit number Unit number 11
- Site
- Site : Tot-body
- Tot-boy :Skin Dose
- Skin Dose :Garnma
- Gamma Air Air :Beta Air
- Beta Air :Unalloc.
- Unalloc. :Unalloc.
- Unalloc.
- Boundary
- Boundary :Dose
- Dose :mrem
- mrem :mrad
- mrad :mrad
- mrad : Tot-body
- TOt-body :Skin
- Skin (km)
- Dist (km)
- Dist :mrem
- mrem : : :Dose Rate
- DQSe
- Dose Rate
- Dose Rate
- mrem/year
- rnrem/year :mrem/year
- mrem/year N
N :: 9.50E-01 9.50E-Ol : 1.93E-08 1.93E-08 : 4.56E-08 2.32E-08 :: 6.89E-08 4.56E-OS : 2.32E-08 1.94E-04 : 4.59E04 6.89E-08 :: 1.94E-04 4.S9E-04
VALLEY AUTHORIT
~ESSEE VALLEY AUTHORITY Y page page 44 of of 99 NESSEE UOYAH (YOYAH NUCLEAR NUCLEAR PLANT PLANT
-12 APP.
L.L-l2 APP. B.9 B.9 Gaseous Radioactive s Radioa waste Releas ctive Waste Release Permit e Permit 20090 12.037.OO1.G 2009012.037.001.G Gaseou Pre-Release Pre-Re Supplementary lease Supple Data mentary Data Report Catego Report Categoryry Calculated Calcul Dose Rate ated Dose Rate to Man (mrem to Man (mrem/year) from this
/year) from this Release Releas at Site e at Site Bound Boundary.
ary.
Type of Type of Activi Activity ty Radioiodines Radioi odiries andand Partiul Particulates ates Age Group Age Group & & Pathway(s)
Pathw ay(s)
Controlling Contro lling Sector Sector Unit numbe Unit number r : 11
- Bone : Liver :Tot-body
- Tot-b oy : Thyroid
- TIyro id : Kidney Kidney ;Lung
- Lung ;GI-LL
- GI-LLI I
- Bone Liver NN : O.OOE÷OO O.OOE+OO : Q.OOE--OO O.OOE+OO :: O.OOE÷OO O.OOE+OO : O.OOE÷OO O.OOE+OO :: O.OOE÷OO O.OOE+OO : O.OOE+OO O.OOE+OO : O.OOE÷OO O.OOE+OO NN ; O.OOE÷OO O.OOE+OO :: O.OOE÷OO O.OOE+OO : O.OOE÷OO O.OOE+OO : O.OOR+OO O.OOE+OO : O.OOE÷OO O.OOE+OO : O,00E÷OO O.OOE+OO : O.OOE÷OO O.OOE+OO NN :: O.OOE÷OO O.OOE+OO :: O.OOE÷OO O.OOE+OO :: O.OOE-t-OO O.OOE+OO ; O.OOE÷OO O.OOE+OO :: O.OOE+OO O.OOE+OO : O,00E+OO O.OOE+OO :: O.OOE+OO O.OOE+OO N
N : O.OOE÷OO O.OOE+OO : O.OOE÷OO O.OOE+OO ! O.OOE+OO O.OOE+OO : O.OOE--OO O.OOE+OO : O.OOE-t-OO O.OOE+OO : O.OOE÷OO O.OOE+OO ; O.OOE÷OO O.OOE+OO
'J'ESSEE VALLEYVALLEY AUTHORIT AUTHORITY Y page page 55 of of 99 ESSEE JOYAH JOYAH NUCLEARNUCLEAR PLANT PLANT TI-12 APP.
TI-12 APP. B.9 B.9 Gaseous Gaseou Radioactive s Radioa Waste Releas ctive Waste Release Permit e Permit 20090 12.037.001. G 2009012.037.001.G Pre-Release Pre-Re lease Supple Supplementary mentary Data Data Report Catego Report Category ry : Cumulative Cumul Dose at ative Dose at Site Site Boundary Boundary Type of Type of ActiviActivity ty : Noble Noble Gases Gases Location Locati on : NN at at 0.950 km.
0.950 km.
Unit number Unit number : 11
- Tot-body
- Tot-b ody :Skin
- Skin :Gamma Air
- Gamma Air :eta;Beta Air Air
- mrem
- mrem :mrem
- mrem :mrad
- mrad :mrad
- mrad This This : :
Release Releas e :: l.93E-0 1.93E-08 8 :: 4.56E-4.56E-OS08 :: 2.32E-2.32E-08 08 :: 6.89E-OS 6.89E-OS :
31D Prior:
31D Prior: : :
To ReI To Rel : 2.32E~04
- 2.32E- 04 : 3.46E-04 3.46E- 04 : : 2.45E-2.4SE-0404 :; l.06E-0 1.06E-04 4 :
31D After:
31D After: :
Release Releas e ; 2.32E-2.32E-0404 :; 3.46E-3.46E-0404 :: 2.45E-2.45E-0404 :: l.0E-04 1.06E-04 :
31 Day 3lDay : : :
Limit Limit :: O.OOE+DO 0.OOE+00 :: O.OOE+OO 0.OOE+00 :: 2.OOE-0l 2.00E-Ol ;: 4.OOE-01 4.00E-01 ;
- 'n 3lDay:Day: : : :
.tit ait : 0.00%:
0.00%; 0.00%: 0.12%: 0.03%:
0.03%:
~-----------------------------------------------------
Qtr Qtr Prior:
Prior: : : :
To To ReI Rel ;: 2.32E-04 2.32E-04 :: 3.46E-04 3.46E-04 : 2.4SE-04 2.45E-04 : 1.06E-04
],.06E-04 :
Qtr Qtr After; After: : : :
Release Release ; 2.32E-04
- 2.32E- 04 :: 3.46E-04 3.46E- 04 : 2.4SE-04 2.45E- 04 : 1.06E-04 1.06E-04 :
Quarterly:
Quarterly Limit Limit : O.OOE+OO 0.OOE÷00 :: O.OOE+OO 0.OOE÷00 :: S.OOE+OO 5.OOE+00 :: 1.00E+01 1.DOE+0l :
% Quarter:
Quarter:
Limit Limit : 0.00%:
0.00%: 0.00%:
0.00%; 0.00%:
0.00%: 0.00%:
0.00%:
Ann AnnPr Prior:
ior: :
To ReI To Rel : : 2.32E-04 2.32E- 04 :: 3.46E-04 3.46E-04 :: 2.4SE-04 2.45E-04 :: 1.06E-04 1.06E-04 :
Ann Ann After:
After: :
Release Release :: 2.32E-04 2.32E-04 :: 3.46E-04 3.46E-04 :: 2.45E-04 2.45E-04 :: 1.06E-04 1.06E-04 :
Annual Annual : :
Limit Limit : O.OOE+OO 0.OOE÷O0 :: O.OOE+OO 0.OOE÷00 :: 1.00E+01 1.OOE+01 :: 2.00E+01 2.OOE-i-O1 :
% Annual
%Ann ual :: :
Limit Limit : 0.00%:
0.00%: 0.00%:
0.00%: 0.00%:
0.00%: 0.00%:
0.00%:
~ESSEE VALLEY VALLEY AUTHORIT AUTHORITY Y page.
page 66 of of 99 NESSEE JOYAH NUCLEAR JOYAI-I NUCLEAR PLANT PLANT TI-12 APP.
TI-12 APP. B.9 B.9 Gaseous Radioactive Waste Releas Release Permit e Permit 20090 12.037.OOl.G 2009012.037.001.G Gaseous Radioactive Waste Pre-Release Supplementary Pre-Release Supplementary Data Data Report Catego Report Category ry : Projected Projec Dose at ted Dose Site Bound at Site ary Boundary Type Type of of Activity Activi ty : Noble Gases Noble Gases Location Locati on NN at at 0.950 km.
0.950 km.
Unit numbe Unit number r : 11
- Tot-body
- Tot-b ody :Skin
- 5km :Gamma Air
- Gamma Air :Beta
- Beta Air Air
- mrem
- trirem :mrem
- mrem :mrad
- mrad :mrad
- mrad This This :
Release Release :: 1.93E08 1.93E-08 :: 4.56E-4.56E-0808 ; 2.32E-2.32E-0808 :: 6.89E-6.89E-0808 :
31D Prior:
31D Prior: :
To Rel To ReI :: 3.43E-3.43E-0404 :: 5.11E-5.11E-04 04 :; 3.62E-3.62E-0404 :: 1.57E-1.57E-0404 :
31D After:
31D After: :
Release Release : 3.43E-04
- 3.43E- 04 :: 5.llE-0 5.11E-04 4 :: 3.62E-3.62E-04 04 :: 1.57E-1.57E-0404 :
31 Day 31 Day :
Limit Limit :: 0.OOE÷O0 O.OOE+OO :: 0.OOE+00 O.OOE+OO :: 2.OOE 2.00E-01-0l :: 4.OOE 4.00E-01-0l :
31 Day 31 Day :: :
nit nit : 0.00%:
0.00%: 0.00%:
0.00%: 0.18%:
0.18%: 0.04%:
0.04%:
Qtr Qtr prior:
Prior: :
To ReI To Rel : : 1.02E-03 l.02E-0 3 :: 1.52E-03 1.52E-03 : 1.07E-03 l.07E-03 :: 4.65E-04 4.65E-04 :
Qtr Qtr After:
After: :
Release Release :: 1.02E-03 l.02E-03 :: 1.52E-03 1.52E-03 : 1.07E-03 4.65E-04 :
l.07E-03 ; 4.65E-04 Quarterly:
Quarterly: :
Limit Limit ;: O.OOE+OO 0.OOE+0O : O.OOE+OO 0.OOE+00 :: 5.00E+00 1.OOE+0l :
5.OOE+00 :: 1.00E+01
% Quarter:
%Quar ter: :
Limit Limit : 0.00%:
0.00%: 0.00%:
0.00%: 0.02%:
0.02%: 0.00%:
0.00%:
Ann AnnPr Prior:
ior; : :
To ReI To Re]. :: 4.04E-03 4.04E-03 :: 6.01E-03 6.O1E-03 :: 4.26E-03 l.84E-03 :
4.26E-03 :: 1.84E-03 Ann Ann After:
After: : :
Release Release : : 4.04E-03 4.04E- 03 : : 6.01E-03 6.O1E -03 :: 4.26E-03 l.84E-03 :
4.26E-03 :: 1.84E-03 Annual Annual : : :
Limit Limit :: O.OOE+OO O.OOE+00 ;: O.OOE+OO 0.OOE+00 :: 1.00E+01 2.OOE÷0l :
l.OOE+0]. :: 2.00E+01
%"Annual
%Anriual : : :
Limit Limit : 0.00%:
0.00%: 0.00%:
0.00%: 0.04%
0.04%:: 0.01%:
0.01%:
~ESSEE VALLEY AUTHORITY page page 77 of of 99 TESSE E VALL EY AUTH ORITY
~UOYAH
[JOYAH NUCL 4 NUCLEAR EAR PLANT PLAN T TI-12 APP.
T1-12 APP. B.9 B.9 Gaseous Radioactive Waste Releas Release Permit e Permit 20090 12.037.O0l.G 2009012.037.001.G Gaseou s Radioa ctive Waste Pre-Release Supplementary Pre-Release Supplementary Data Data Report Catego Category : Cumulative Cumul Maximum ative Maxim Individual um Indiv Dose (mrem idual Dose (mrem)) for for Report ry Controlling Con trolling Age Group at Age Group at Con troll ing Locati Controlling Location on Type of of Acti Activity vity Radioiodines Radioi odines and and Parti culat Particulates es Type Age Group && Pathw Age Group Pathway(s) ay(s)
Location Location : at at 0.000 km.
0.000 km.
Unit numbe Unit number r : 11
- Bone : Liver :Tot-body
- Tot-b :Thyroid ody :Thyro id :Kidne
- Kidney y :Lung
- Lung ;GI-LL I
- GI-LLI*
- Bone :Liver This This : : :
Release :: 0.OOE O.OOE+OO: O.OOE+OO: O.OOE+OO:
+00: 0.ODE +00: 0.00E+
O.OOE+OO: 00: 0.OOE O.OOE+OO: +0O: 0,00E+
O.OOE+OO: 00 O.OOE+OO Release +00: 0.OOE +00: 0.OOE 31D Prio 3l]D Prior:
r: : :
To P.el ReI 04: 2.22E 04: 2.22E- 04: 2.22E- 04 To :: 2,22E-2.22E-04: 2.22E-04:
04: 2.22E- 2.22E-04:
04: 2.22E- 04: 2.22E-2.22E-04: 2.22E-04: 2.22E-04: 2.22E-04 31D Afte 31D After:
r: : ; :
Release : 2.22E-04: 2.22E-04: 2.22E-04:
2.22E- 04: 04: 2.22E-2.22E-04:
2.22E- 2.22E-04:04 2.22E- 04; 2.22E-2.22E-04: 04 2.22E-04 Release : 2.22E-04: 2.22E- 04; 31 Day 3lDa y : : :
T.imit -Ol: 3.OOE -0l: 3.OOE -0l: 3.OOE Ol T,irnjt :: 3.OOE3.00E-01:
-Ol: 3.00E-01:
3.OOE 3.00E-01:
-0l: 3.OOE -0l: 3.OOE3.00E-01: 3.00E-01: 3.00E-01: 3.00E-01 31 Day :
Limit 0.07%: 0.07%: 0.07%:
0.07%: 0.07%:
0.07%: 0.07%:
0.07%: 0.07%:
0.07%: 0.07%
0.07%
Limit : 0.07%: 0.07%:
Qtr QtrP Prior:
rior: : :
To ReI : 2.22E-04: 2.22E-04:
04: 2.22E-04:
2.22E- 04: 2.22E-04:
2.22E-04: 2.22E-04: 2.22-04 2.22E-04: 2.22E-04 2.22E04: 2.22E-04:
ToRel : 2.22E- 04: 2.22E-Qtr Qtr After:
After: : : :
Release : 2.22E-04: 2.22E-04:04; 2.22E-04:
2.22E- 04: 2.22E-04:
2.22E-04: 2.22E-04: 2.22E-04 2.22E-04; 2.22E-04 2.22E-04: 2.22E-04:
Releas e : 2.22E- 04: 2.22E-Quarterly:
Quarterly: :
Limit : 7.50E+00: 7.50E+00:00: 7.50E+00:
7.50E+ 00; 7.50E+00~
7.50E+00: 7.50E+00: 7.SOE+00 7.SOE+00: 7.50E+00 7.SOE+00: 7.50E+00:
Limit : 7.SOE+/-00: 7.50E+
%% Quarter:
Quarter; : ;
Limit 0.00%: 0.00%:
0.00%: 0.00%:
0.00%: 0.00%:
0.00%: 0.00%:
0.00%: 0.00%:
0.00%: 0.00%
O.OO%"
Limit : 0.00%:
Ann AnnPrior:
Prior: : : :
To ReI : 2.22E-04: 2.22E-04: 2.22E-04: 04 2.22E-04:
2.22E- 04: 2.22E-04: 2.22E-04 2.22E-04; 2.22E-04 2.22E-04: 2.22E-04:
To Rel : 2.22E-04; 2.22E-04: 2.22E-Ann AnnAfter:
After: : : ; :
Release : 2.22E-04: 2.22E-04: 2.22E-04:
2.22E- 04: 2.22E-04:
2.22E- 04: 2.22E-04: 2.22E-04 2.22E-04: 2.22E-04 2.22E-04: 2.22E-04:
Release 2.22E- 04: 2.22E- 04:
------------------------~
Annual Annual : : ; :
Limit : : 1.S0E+01: 1.SOE+Ol: 1.50E+01: l.50E+0l l.50E+01: 1.50E+01 Limit l.50E+01: 1.50E+01:
1.50E+0l; 1.50E+01:
l.50E+01: 1.50E+01:
l.SOE+01: 1.50E+01:
%%Ann Annual :
ual : : : : :
0.00%
0.00%:
0.00%; 0.00%:
0.00%: 0.00%:
0.00%: 0.00%:
0.00%: 0.00%;
0.00%: 0.00%;
0.00%: 0.00%
imit :
.il'ESSEE VALLEY VALLEY AUTHORIT AUTHORITY Y page page 88 of of 99 ESSEE
~~~UOYAH
..UOY AH NUCLEAR PLANT NUCLEAR PLANT TI-12 APP.
TI-12 APP. B.9 B.9 Gaseous Radioactive Waste Releas Release Permit e Permit 20090 12.037.001. G 2009012.037.001.G Gaseous Radioactive Waste Pre-Release Pre-Release Supple Supplementary mentar y Data Data Report Catego Report Category ry : Projected Projec Maximum Individ ted Maximum Individual (mrem) for Dose (mrem) ual Dose for Controlling Contro lling Age Age Group Group at at Controlling Locati Contro lling Locationon Type of Type of Activi Activity ty Radioiodines
- Radioi odines and and Particu Particulates lates Age Group Age Group & Pathw<< Pathway(s) ay(s)
Location Locati on : at at. 0.000 km.
0.000 km.
Unit numbe Unit number r : 11
- Bone : Liver .
- Liver :Tot-body
- Tot-b :Thyroid ody :Thyro id :Kidfle
- Kidney y :Lung
- Lung :GI-LL
- GI-LLI I
- Bone
----------------------~~
This This : : : : ..
Release +00: 0.OOE +00: 0.OOE +00 Releas e :: 0.OOE D.OOE+OO:
+00: 0.OOEO.OOE+OO: O.OOE+OO:
+00: 0.OOE +00: 0.OOE O.OOE+OO: O.OOE+OO:
+00: 0.OOE O.OOE+OO: O.OOE+OO 31D Prior:
3lDPri or: : :
To ReI : 3.27E-04: 3.27E-04:
3.27E- 04: 3.27E-04:
3.27E- 04: 3.27E-3.27E-04: 04: 3.27E-3.27E-04:
04: 3.27E- 04: 3.27E-3.27E-04: 3.27E-04 04 To Rel : 3.27E- 04:
31D After:
31D After: ; : :
Release : 3.27E-04:
04: 3.27E-04:
3.27E- 04: 3.27E-04:
3.27E- 04: 3.27E-04:
3,27E- 04: 3.27E- 04: 3.27E-3.27E-04: 04: 3.27E-3.27E-04: 3.27E-04 04 Releas e : 3.27E-31 Day 3lDay ; : : : ;
/""i.mit : 3.00E-01: 3.00E-01:
-01: 3.00E-01:
3.OOE -0l: 3.00E-01:
3.OOE -01: -0l: 3.OOE
3.0 0E-01
3.OOE -0l; 3.OOE
3.0 0E-01
3.00E-01-01 3.OOE-0l: 3.OOE
((" ----------------------------------------------------------------------------~
31 Day :: :: :; :: : : :
3lDay Limit 0.11%: 0.11%:
0.11%-: 0.11%":
0.11%-: 0.11%:
0.11%: 0.11%:
0.11%: 0.11%:
0.11%: 0.11%
0.11%
Limit 0.11%:
Qtr QtrPriPrior:or: ; :
To ReI :: 9.71E-04: 9.71E04 9.71E-04: 9.71E-04 9.71E-04: 9.71E-04:
To Rel 9.71E04; 9.71E-04:
9.71E-04: 9.71E-04:
9.71E-04: 9.71E-04: 9.71E-04: 9.71E-04:
Qtr Qtr After:
After; : : :
Release : 9.71E-04: 9.71E-04:
9.71E- 04: 9.71E-04:
9.71E- 04: 9.71E-04:
9.71E04: 9.71E-04; 9.71E-04 9.71E-04: 9.71E-04 9.71E-04: 9.71E-04:
Release : 9.71E-04:
Quarterly: : : : : .
Quarterly:
Limit :: 7.50E+OO: 7.SOE +00: 7.50+00 7.50E+00: 7.508+00 Limit 7,50E+OO: 7.50E+00; 7.50E+0Q; 7.50E+00:
7.50E-f-00: 7.S0E+00:
7.50E+ 00: 7.50E+00: 7.50E+00:
-----------------------~-
%% Quarter:
Quarter: : : : :
. Limit 0.01%: 0.01%:
0.01%: 0.01%:
0.01%: 0.01%:
0.01%: 0.01%:
0.01%: 0.01%:
0.01%: 0.01%
0.01%
Limit : 0.01%:
Ann AnnPrPrior:ior: : : :
To ReI : 3.85E-03:03: 3.85E-03:
3.85E- 03: 3.85E-03:
3.8SE- 03: 3.8SE-03:
3.85E- 03: 3.85E-03; 3.85E-03:
3.85E-03: 3.85E03 3.85E-03: 3.85E-03 To Rel 3.85E-Ann Ann After:
After: :; :
Release 3.85E-03: 3.85E-03: 3.85E-03 3.8SE-03: 3.85E-03 Release :: 3.8SE-03: 3.85E-03: 3.85E-03:
3.85E-03: 3.85E-03:
3.85E-03: 3.8SE-03: 3.85E-03: 3.8SE-03:
Annual : : : : :
Annual :
- : 1.50E+01: l.SOE+01: 1.S0E+01: 1.50E+01 1.SOE+01: 1.S0E+01 Limit Limit 1.SOE+01: 1.50E+01:
1,50E+01; 1.50E+01:
1.50E+01: 1.S0E+01: *1.SOE+01: 1.S0E+01:
% Annual ual : : : : ; :
%Ann
-,imit 0.03%: 0.03%:
0.03%: 0.03%:
0.03%: 0.03%:
0.03%-: 0,03%
0.03%; : 0.03%;
0.03%: 0.03%
0.03%
imit : 0.03%:
VALLEY AUTHORIT
~ESSEE VALLEY AUTHORITY Y page page 99 of of 99 JESSEE
~UOYAH
,CJOYAH NUCLEAR NUCLEAR PLANT PLANT TI-12 APP.
TI-12 APP. B.3 B.9 Gaseous Radioactive Waste Releas ctive Waste Release Permit e Permit 20090 12.037.00l.G 2009012.037.001.G Gaseou s Radioa Pre-Release Pre-Re lease SuppleSupplementary mentary DataData Report Catego Report Category ry : Fuel Cycle Fuel Cycle Dose Dose Type of Activity Type of Activi ty : Noble Gases Noble Gases Location Locati on : NN at at 0.950 km.
0.950 km.
Unit numbe Unit number r 1
- Tot-body
- Tot-b ody :Skin
- Skin
- mrem
- mrem :mrem
- mrem This This :
Release Release :: 1.35E-1.3SE-0808 :: 3.19E-3.19E-OB 08 ;
Projected:
Projec ted:
Prior ReI: 2.83E-Prior Rel: 2.B3E-0303 :: 4.21E-4.21E-03 03 :
Projected:
Projec ted:
After Rel: 2.83E-After Rel: 2.B3E-0303 :: 4.21E-4.21E-03 03 :
Annuall Annua :
Limit Limit :: 2.50E÷ 2.50E+0101 :: 2.50E-2.50E+Oli-0l :
mnual nnua1 ::
( .mit mit 0.00%':
0.00%: 0.00%':
0.00%:
Cumulativ:
Cumulativ:
Prior Prior Rel:
Rel: 1.63E-04 l.63E-04 :: 2.42E-04 2.42E-04 :
Cumulativ:
Cumulativ; :
After After Rel:
Rel: 1.63E-04 1.63E-04 :: 2.42E-04 2.42E-04 :
Annual Annual Limit Limit :: 2.50E+Ol 2.50E+01 :: 2.S0E+Ol 2.SOE+01 :
% Annuall :
Annua :
Limit Limit : 0.00%:
0.00%: 0.00%:
0.00%:
JPM19AP3 JPM19AP3 Page 11 of Page of 77 Rev. 00 Rev.
SEQUOYAH NUCLEAR PLANT PERFORMANCE MEASURE JOB PERFORMANCE JPMI9AP3 JPM19AP3 Classify the Event per the REP (LOCA with Significant Fuel Failure)
PREPARED!
PREPARED/
REVISED BY: Date/
Date!
VALIDATED BY:
- Date/
Date!
~~----------
APPROVED BY: Date/
Date!
(Operations Training Manager)
CONCURRED: **
- Date/
Date!
(Operations Representative)
- Validation not required for minor enhancements, procedure Rev changes that do not affect the JPM, or individual step changes that do not affect the flow of the the JPM.
JPM.
JPM19AP3 JPM1 9AP3 Page 2 of 7 Page2of7 Rev.
Rev. 00 I NUCLEAR TRAINING NUCLEAR TRAINING REVISIONIUSAGE LOG REVISION/USAGE LOG REVISION REVISION DESCRIPTION OF DESCRIPTION OF V V DATE DATE PAGES PAGES PREPARED/
PREPARED/
NUMBER NUMBER REVISION REVISION AFFECTED AFFECTED REVISED REVISED BY:BY:
00 New JPM, New JPM, adapted adapted from from JPM JPM 19AP2 19AP2 Y Y 1/11/10 1/11/10 All All M M Hankins Hankins v - Specify ifif the JPM change will require another validation (Y or N).
V -
N).
See See cover cover sheet for criteria.
JPM19AP3 JPM19AP3 Page Page 33 of of 77 Rev.
Rev. 00 SEQUOYAH NUCLEAR
-SEQUOYAH NUCLEAR PLANT PLANT SRO SRO JOB PERFORMANCE JOB PERFORMANCE MEASURE MEASURE Task:
Task:
Classify the Classify Event per the Event per the REP (LOCA the REP (LOCA with with Significant Significant Fuel Fuel Failure)
Failure)
JAITA task JAITA task #:
- 3440030302 3440030302 (SRO)
(SRO) 3440190302 3440190302 (SRO)
(SRO)
KIA Ratings:
KIA Ratings:
2.4.29 (2.6/4.0) 2.4.29 (2.6/4.0) 2.4.38 (2.2/4.0) 2.4.38 (2.2/4.0) 2.4.44 2.4.44 (2.1/4.0)
(2.1/4.0) 2.4.30 (2.2/3.6) 2.4.30 (2.2/3.6) 2.4.40 (2.3/4.0) 2.4.40 (2.3/4.0) 2.4.37 (2.0/3.5) 2.4.37 (2.0/3.5) 2.4.41 (2.3/4.1) 2.4.41 (2.3/4.1)
Evaluation Method: Simulator _ __ In-Plant _ __
In-Plant Classroom - - ' -X' ' - - -
========================================================================
Performer:
NAME Start Time _ __
Performance Rating: SAT UNSAT Performance Time Finish Time _ __
Evaluator: /
SIGNATURE DATE
========================================================================
COMMENTS
JPM19AP3 JPMI9AP3 Page Page 44 of of 77 Rev. a0 Rev.
SPECIAL INSTRUCTIONS SPECIAL INSTRUCTIONS TO TO EVALUATOR:
EVALUATOR:
- 1. Any UNSAT requires
- 1. Any UNSAT requires comments.comments.
- 2. Ensure
- 2. Ensure operator operator performs performs the the following following required required actions actions for for SELF-CHECKING; SELF-CHECKING;
- a. Identifies the
- a. Identifies the correct correct unit, unit, train, train, component, component, etc. etc.
- b. Reviews
- b. Reviews the intended action the intended action and and expected expected response.
response.
- c. Compares
- c. Compares the the actual actual response response to to the the expected expected response.
response.
- 3. Clock
- 3. Clock must must be be available available in in classroom classroom and and visible visible to examiner and to examiner and examinees.
examinees.
Caution:
Caution: DO NOT DO NOT LETLET THE THE EXAMINEE EXAMINEE FAX FAX THE THE NOTIFICATION NOTIFICATION FORM FORM OFFSITE!
OFFSITE!
Validation Time:
Validation Time: CR.CR. 15 mins 15 mins Local _ _ _ __
Local Tools/Equipment/Procedures Needed:
Tools/Equipment/Procedures EPIP-1 thru 5, for each student in classroom FR Procedures Steam Tables, for each student in classroom Clock must be available in classroom that all examinees and evaluator can see.
References:
References:
Reference Title Rev No.
- 1. EPIP-1 Emergency Plan Initiating Conditions Matrix 42 42
- 2. EPIP-4 Site Area Emergency 30 30
JPM19AP3 JPM19AP3 Page of 7 Page 55of7 Rev.
Rev. 00 READ TO READ TO OPERATOR OPERATOR Directions to Directions to Trainee:
Trainee:
II will will explain explain the the initial initial conditions, conditions, and and state state the task to the task to be be performed.
performed. All All steps steps ofof this this JPM shall JPM shall be be performed performed in in aa classroom classroom or or in in the simulator (simulator the simulator (simulator will will not not be be set set up up to match to match the scenario).
the scenario).
The evaluator The evaluator will provide initiating will provide initiating cues.
cues. Time Time begins begins when when directed directed byby evaluator.
evaluator.
When the When the declaration declaration has has been been made, made, raise raise your your hand, hand, the the evaluator evaluator will will record record the the time, and and then continue continue the procedure.
procedure.
Raise your Raise hand again your hand again when when you you have have completed completed the the TVA TVA Initial Initial Notification Notification Form, Form, to to the point of notifying point of notifying the ODS.
the ODS.
INITIAL CONDITIONS:
CONDITIONS:
- 1. Unit 2 is at 100% RTP and stable.
- 2. Unit 1I experienced an AUTO SI from a small RCS leak which quickly escalated to a LOCA and a high containment pressure.
- 3. RCS pressure has stabilized at 600 psig.
- 4. Subcooling is 10°F.
- 5. Crew is entering FR-C.2 Core Cooling, Orange Path.
RVLIS lower range is indicating 40%.
- 6. RVLlS
- 8. Containment Spray pumps are running.
- 9. Maximum containment pressure was 55 psig.
- 10. Containment radiation level are as follows:
-1 .8E+02 Rem/hr on RM-90-273A and RM-90-274.
-1.8E+02
-1 .7E+02 Rem/hr on RM-90-271A and RM-90-272.
-1.7E+02
11.
12.All radiological releases are within Tech Spec limits.
12.AII 13.
- 13. There are no indications of an Onsite Security Event.
INITIATING CUES:
You are the Unit Unit I1 USUS and have have assumed the SED position, until until the TSC is staffed.
You are to perform each each of the following:
- 1. Classify
- 1. this event Classify this event perper EPIP EPIP 1, 1, and and 2.
- 2. Fill TVA Initial out TVA Fill out Initial Notification Notification FormForm and make Protective and make Protective Action Action Recommend Recommendations, ations, ifif any.
any.
THIS IS IS A A TIME TIME CRITICAL JPM JPM Time begins begins when directed directed by by evaluator.
JPM19AP3 JPMI9AP3 Page Page 66 of of 77 Rev.
Rev. 00 Job Performance Checklist Job Performance Checklist STEP/STAN STEP/ST DARD ANDARD SAT/U SATIUNSATNSAT I STEP STEP 1.:
1.: Refers to Refers EPIP-1 to to EPIP-1 to determine determine levellevel of event.
of event. SAT SAT STANDARD: Operator STANDARD: Operator refers refers to EPIP-1, Section to EPIP-1, Section 1, 1, Fission Fission Product Product Barrier Barrier Matrix.
Matrix. UNSAT UNSAT Operator determines Operator determines thatthat they they have have metmet the the conditions conditions of:
of:
1 .1.5 Loss, 1.1.5 Loss, "Containment Containment High High Radiation" Radiation AND AND Critical Critical Step Step 1 .2.2 Loss 1.2.2 Loss "RCS RCS leak leak results results in in subcooling subcooling <40°F"
<40°F and and II or or 1.2.4 Loss RVLIS <42%
1.2.4 Loss RVLlS <42% with with no no RCP's RCPs running running
- (1 .1.1 Potential,
- (1.1.1 Potential, "Core Core Cooling Cooling Orange" Orange maymay also also be be selected selected but but not not required) required) Task Task Start Start Time Time Declaration of event must Declaration must be be made made in in 15 15 minutes minutes from the time the task was accepted.
Record Time of Record of Declaration:
Declaration:____________
Time from Task Acceptance to Declaration: Declaration:____________
Emergency Class Criteria",
Utilizing "Emergency Criteria, operator determines the need to declare a SITE AREA EMERGENCY EMERGENCY based on Loss of two barriers.
Time of Declaration is recorded when the operator raises his hand.
The following steps implement EPIP-4:
STEP 2.: Implements EPIP-4 SITE AREA EMERGENCY, EMERGENCY, Section 3.1 SAT
[1))
[1 operational...
If TSC is operational ...
- UNSAT STANDARD STANDARD:: Operator N/As N/A's this step, per initiating cues the TSC is not staffed.
STEP 3. [3] ACTIVATE Emergency Paging System (EPS) as follows: SAT
- UNSAT STANDARD STANDARD:: Operator recalls from initial conditions, that EPS has is not available from thethe control room room and and continues goes goes toto Step Step [4].
[4].
JPM19AP3 JPM1 9AP3 Page Page 77of7 of 7 Rev.
Rev.O0
~-Job Performance Checklist:
Job Performance Checklist:
STEPISTANDARD STEP/STANDARD SAT/UNSAT SATIUNSAT I SAT SAT
- 4. -
STEP 4.
STEP [4] Complete
[4] Complete Appendix Appendix BB (TVA INITIAL NOTIFICATION (TVA INITIAL NOTIFICATION FOR FOR SITE SITE AREA AREA EMERGENCY).
EMERGENCY). UNSAT UNSAT Critical Critical Step Step STANDARD: Operator STANDARD: Operator fills fills out out Appendix Appendix BB through through step step 7, 7, prior prior to to Notifying Notifying the the ODS.
ODS.
- 1. This
- 1. This isis aa DRILL DRILL
- 2. This
- 2. This isis [Their
[Their name, name, Shift Shift Manager Manager at at SQN SQN Plant]
Plant] Sequoyah Sequoyah has has declared aa SITE declared SITE AREA AREA EMERGENCY EMERGENCY affecting affecting [Unit
[Unit 1]
1]
- 3. EAL
- 3. EAL Designator(s):
Designator(s):
1.2.2 LOSS; 1.2.2 LOSS; and/or andlor 1.2.4 1.2.4 LOSS; LOSS; AND AND 1.1.5 LOSS 1.1.5 LOSS (1.1.1 (1.1.1 POTENTIAL POTENTIAL may may also also be be listed listed but but not not required) required) 4.. Brief description 4 .. Brief description of incident:
incident: [Core
[Core Cooling Cooling Orange Orange Path Path AND Containment High High Radiation Radiation AND RCS RCS leakleak results results in in subcooling <40°F]
subcooling <40°F]
55.... Radiological Conditions [Minor releases within federally approved limits.]
- 6. Event Declared: [Time and Date]
Recommendation: [None].
- 7. Protective Action Recommendation:
- 8. Please repeat back the information you have received to ensure accuracy.
- 9. When completed, FAX this information to the ODS.
STEP 5. [5] NOTIFY ODS. -
SAT Initial Time
- UNSAT NOTE: Evaluator Enter time call is made to the ODS ODS_________________
Time from Declaration (step 1) 1) to ODS Notification:____________ Critical Step STANDARD: Operator raises hand as signal that they have completed TVA Initial Stop Time:
Notification Notification form and are ready to Notify the ODS.
0D5 ODS should be notified within 10 10 minutes minutes after declaration declaration of the event.
End End of JPM ofJPM
READ TO READ OPERATOR TO OPERATOR Directions to Directions to Trainee:
Trainee:
will explain II will explain the initial conditions, the initial conditions, and and state the task state the task to to be be performed.
performed. All All steps steps of of this this JPM shall JPM shall be performed in be performed in aa classroom classroom or in the or in the simulator simulator (simulator (simulator will will not not be be set set up up to match to match the scenario).
the scenario).
The evaluator The evaluator willwill provide provide initiating initiating cues.
cues. Time Time begins begins when when directed directed by by evaluator.
evaluator.
When the declaration has been When the declaration has been made, raise your made, raise your hand, hand, the the evaluator evaluator will will record record thethe time, and time, and then then continue continue the the procedure.
procedure.
Raise your Raise your hand hand again again when when you you have have completed completed the the TVA TVA Initial Initial Notification Notification Form, Form, to the pOintpoint of notifying notifying the ODS. ODS.
INITIAL CONDITIONS:
INITIAL CONDITIONS:
- 1. Unit 2 is at 100% 100% RTP and stable.
- 2. Unit 1I experienced an AUTO SI from a small RCS leak which quickly escalated to a LOCA and a high containment pressure.
- 3. RCS pressure has stabilized at 600 psig.
- 4. Subcooling is 10°F.
- 5. Crew is entering FR-C.2 Core Cooling, Orange Path.
RVLIS lower range is indicating 40%.
- 6. RVLlS
- 8. Containment Spray pumps are running.
- 9. Maximum containment pressure was 5 psig.
- 10. Containment radiation levels are as follows:
--1 .8E+02 Rem/hr on RM-90-273A and RM-90-274.
-1.8E+02 1 .7E+02 Rem/hr on RM-90-271A and RM-90-272.
-1.7E+02
12.AII 12.AII radiological releases are within Tech Spec limits.
- 13. There are no indications of an Onsite Security Event.
13.
INITIATING INITIATING CUES:
You are the Unit Unit I1 US and have assumed the SED position, position, until the TSC is is staffed.
staffed.
You are to perform perform each of the following:
- 1. Classify
- 1. Classify this event event per EPIPEPIP 1, 1, and and
- 2. Fill
- 2. out TVA Fill out TVA Initial Initial Notification Notification Form Form and and make make Protective Protective Action Action Recommend Recommendations, ations, ifif any.
any.
THIS IS IS A A TIME CRITICAL CRITICAL JPM JPM Time begins begins when directed directed by by evaluator.
evaluator.
SITEAREA AREAEMER EMERGENCY GENCY ISEQUOYAH
[SEQU OYAH SFE EPIP EPIP-4 -4 APPENDIX APPEN DIX BB TVA INITIAL WA INITIAL NOTIFICAT NOTIFICATION ION FOR FOR SITEAREA SITE AREAEMER EMERGENCYGENCY TVAINITIAL WA INITIALNOTIFICAT NOTIFICATION ION FOR FORSITESITEAREAAREAEMERGENC EMERGENCY Y 1.1. ~
This This isisaa Drill Drill Elo This Thisisisan anActual Actual Event - Repeat -This Event -Repeat -
This isis an Actual Event anActual Event
- 2. This is SED ~ NO,",<- If
, Sequo Sequoyah yah has declared aa SITE has declared SITE AREA AREA EMER GENCY EMERGENCY
- 2. This is SED affecting: EE1 affecting: ~UnitUnit 11 o El Unit22 Unit 0 Both El Unit 11and Both Unit Unit22 and Unit 3.3. EAL-Desigri EAl: Designator(s):
ator(s): Li. i,'. 5L5 L eJ <1.~d 2.2 ~,l* 2 LL */o 'f-/ot I. J.*LjLJ LL
- 4. Brief
- 4. Brief Description Description of of the the Event:
Event: L<Dt--<!. G,()L~j Oc Ji OIC'\A\y~. c4L PCl-tl tOI\"tC"'~1I\
n c vi e vv\ev\.\ (*\-."*\A R L RVod oJ Res IS C <S L Lc.\.~ k. <;-<-6 C()e: It:",c <~f)~ 0 F ci V I ..
ci0 (N4: 1.1.1 P l.LI; /./,,-/ f' I.i , i. 1 .1. P j.2P k (iS+e t(;
I
- 5. Radiological
- 5. Radiological ConditConditions:
ions: (Check one box under each Airborne AND Liquid column.) column.)
Airborne Releases Airborne Releases Offsite Liquid Releases Offsite
@Minor Minor releases releases within within federally federally approved limits limits 1
B Mino Minor limits approved limits r releases within federally approved 1 oEl Releases Releases above above federally federally approved approved limits limits 1
o El Releases above federally approvedapproved limits 1 limits oEl Release Release information information not not known known oEl Release Release information not not known l Tech
((Tech Specs)
Specs) ((Tech 1Tech Specs)
Specs) 6.
- 6. Event Event Declared:
Declared: Time: (tiM ed) Date:
Date: I ck c-'cy1 Ted 7.
- 7. Provide Provide Protective Protective ActionAction Recommendation:
Recommendation: ~None None 8.8. Please Please repeat repeat back back thethe information information you you have have received received to to ensure ensure accuracy.
accuracy. 0El 9.9. When When completed, completed, FAX FAX this this information information to to the the ODS.
ODS. 0 FORWARD PAGE14 PAGE 14ofof15 15 REVISION30 REVISION 30 FORWARDCOMPLETED COMPLETEDPROCEDURE PROCEDURETO TO EMERGENCY EMERGENCY PREPAREDNESSMANAGER PREPAREDNESS MANAGER
TO OPERATOR READ TOOPERAT READ OR Directions to Directions to Trainee:
Trainee:
II will explain explain the initial initial conditions, conditions, and state the task and state task to be steps of performed. All steps be performed. of this JPM JPM shall be performed in in a a classroom or in the simulator (simulator (simulator will not not be be set up up to match the scenario).
The evaluator will provide initiating cues. Time begins when directed by evaluator.
declaration has When the declaration has been made, evaluator will record the hand, the evaluator made, raise your hand, time, and then continue the procedure.
Raise your hand again when you have completed the TVA Initial Notification Form, to the point of notifying the ODS.
CONDITIONS:
INITIAL CONDITION S:
1.
- 1. Unit 2 is at 100%
100% RTP and stable.
- 2. Unit 1 1 experienced an AUTO SI from a small RCS leak which quickly escalated to a LOCA and a high containment pressure.
- 3. RCS pressure has stabilized at 600 psig.
- 4. Subcooling is 10°F.
- 5. Crew is entering FR-C.2 Core Cooling, Orange Path.
- 6. RVLlS RVLIS lower range is indicating 40%.
S.
- 8. Containment Spray pumps are running.
- 9. Maximum containment pressure was 5 psig.
- 10. Containment radiation levels are as follows:
-1.SE+02 1 .8E+02 Rem/hr on RM-90-273A and RM-90-274.
-1.7E+02 1 .7E+02 Rem/hr on RM-90-271 RM-90-271A A and RM-90-272.
12.AII 12.AlI radiological releases are within Tech Spec limits.
- 13. There are no indications of an Onsite Security Event.
INITIATING CUES:
You are the Unit 11 US and have assumed the SED position, until the TSC is staffed.
You are to perform each of the following:
1.
- 1. Classify Classify this event per per EPIP 1, and
- 2. FillFill out TVA Initial Initial Notification Notification Form and make Recommendations, make Protective Action Recommendations, if any.
THIS IS A TIME CRITICAL JPM Time begins when directed by evaluator.
JPM JPM 190 190 of88 Page 11of Page Rev.
Rev. 22 SEQUOYAH SEQU OYAH NUCL NUCLEAR EAR PLAN PLANT T JOB PERFO JOB PERFORMANCE RMANCE MEAS MEASURE URE JPM 190 JPM 190 Reactivity Reacti Balance vity Baanc e Calcul Calculationation PREPARED!
PREPARED!
REVISED BY: Date!
VALIDATED VALIDATED BY: ** Date!
~==------------
APPROVED BY:
BY: Date!
Date!
(Operations (Operations Training Manager)
Training Manager)
CONCURRED:
CONCURRED: **
Date!
Date!
(Operations Representative)
(Operations Representative)
- Validation Validation not not required required for minor enhancements, for minor changes that Rev changes procedure Rev enhancements, procedure that do do not not affect affect the the JPM JPM or or individual step changes individual step do not that do changes that affect the not affect flow of the flow the of the JPM.
JPM.
Operations Operations Concurrence Concurrence required for new required for JPMs and new JPMs changes that and changes the affect the that affect flow flow of of the the JPM JPM (if(if not not driven driven by by aa procedure revision).
procedure revision).
JPM JPM190 190 Page2of8 Page 2 of 8
~ Rev.2 Rev. 2 NUCLEAR NUCLEARTRAINING TRAINING REVISION/USAGELOG REVISIONIUSAGE LOG REVISION REVISION DESCRIPTION OF DESCRIPTION OF VV DATE DATE PAGES PAGES PREPARED!
PREPARED/
NUMBER NUMBER REVISION REVISION AFFECTED AFFECTED REVISED BY:
REVISED BY:
00 Initial Issue Initial Issue YY 3/17/04 3/17/04 ALL ALL G.S. Poteet G.S. Poteet Penlink Pen/ink Made corrections Made corrections resulting resulting fromfrom validation validation NN 5/12/04 5/12/04 2,2,4-7 4-7 G.S. Poteet G.S. Poteet 11 Developed for Developed 6/7-14/04 NRC for 6/7-14/04 NRC Exam.
Exam. NN 6/15/04 6/15/04 All All J.J. Kearney Kearney Transferred to JPM Transferred to JPM Bank. Bank.
22 Revised to Revised to update update to to the the latest latest procedure procedure YY 1/11)10 1/11/10 All All MM Hankins Hankins revision, enhanced revision, enhanced initial initial conditions.
conditions.
vV- Specify
- Specifyififthe theJPM changewill JPMchange willrequire requireanother anotherValidation Validation(Y N).
(YororN).
See Seecover coversheet sheetfor forcriteria.
criteria.
JPM 190 JPM 190 Page3of8 Page 3 of 8 Rev.2 Rev. 2 SEQUOYAH NUCLEAR SEQUOYAH NUCLEAR PLANT PLANT AUO/RO/SRO AUOIROISRO JOB PERFORMANCE JOB PERFORMANCE MEASURE MEASURE Task:
Task: Perform aa Reactivity Perform Reactivity Balance Balance Calculation Calculation per per 0-SO-62-7, 0-SO-62-7, Appendix EE JAITA TASK #: 0040070101 JAITATASK#: 0040070101 (RO)(RO)
KIA Ratings:
2.1.25 2.1 .25 (3.9/4.2)
(3.9/4.2) K5.20 (3.6/3.7) 004 K5.20 004 A4.04 (3.2/3.6) 004 Task Standard:
Operator performs 0-SO-62-7 Appendix E, Reactivity Balance Calculation Evaluation Method: Simulator _~X"---_
X In-Plant In-Plant - - - -
=======================================================================
Performer:
NAME Start Time _ __
Performance Rating: SAT UNSAT Performance Time Finish Time _ __
Evaluator: /
SIGNATURE DATE
=======================================================================
COMMENTS
JPM JPM 190 190 Page 44 of 88 Rev,2 Revs 2 SPECIAL INSTRUCTIONS TO SPECIAL TO EVALUATOR:
- 1. Critical steps identified.
1.
- 2. Any UNSAT
- 2. UNSAT requires comments
- 3. Ensure operator performs the following required actions for SELF-CHECKING; SELF-CHECKING;
- a. Identifies the correct unit, train, component, etc.
- b. Reviews the intended action and expected response.
- c. Compares the actual response to the expected response.
Validation Time: CR. min 35 mm Local Tools/Equipment/Procedures Needed ToolslEquipmentlProcedures
- 1. Cycle Nuclear Design Report (NDR)
- 1. (NOR)
- 2. 0-SO-62-7 Boron Concentration Control
- 3. Highlighter and ruler
References:
Reference Title Rev No.
A. 0-SO-62-7 Boron Concentration Control 56 B. TI-44 Boron Tables 12
=================================================================
READ TO OPERATOR Directions to Trainee:
II will explain the initial conditions, and state the task to be performed. All steps shall be performed for this JPM. II will provide initiating cues and indicate any steps to be discussed.
When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet II provided you.
INITIAL CONDITIONS:
- 1. Unit 11 is currently stable at 20 %.
- 2. Control rod Bank 0D is at 160 steps.
- 4. 11U0981 U0981 Core burnup is 600 MWD/MTU.
- 5. Reactor Engineering has provided following Xenon data:
11 =
XE XE = -2430 pcm 22 =
XE XE = -2250 pcm INITIATING CUES:
Perform 0-SO-62-7, Appendix E, Reactivity Balance calculation, in preparation for a change in reactor power from 20% with Control Rods at 160 steps on 0D Bank, to 70% with Control Bank 0D at 228 steps, using a 3%/hour power increase rate.
JPM 190 Page 5 of 8 Rev. :22 Job Performance Checklist:
STEPISTANDARD STEP/ST ANDARD SATIUNSAT SAT/UNSAT I.:
STEP 1.: Obtain a copy of the procedure. - SAT
- UNSAT STANDARD: Operator obtains a copy of 0-SO-62-7 Boron Concentration Control, Appendix E Reactivity Balance Calculation. Start Time __
Time__
STEP 2.: /
[1] ENTER the following Data: - SAT
- UNSAT Current RCS Boron NOTE Per initial conditions ReS RCS boron concentration is 1400 ppm STANDARD Operator enters 1400 ppm from INITIAL CONDITIONS STEP 3.: Core Burnup - SAT NOTE Per initial conditions computer point 1U0981 indicates -
UNSAT MWD/MTU 600 MWDIMTU STANDARD Operator uses 11 U0981 data from initial conditions, and enters 600 MWD/MTU on Appendix E.
STEP 4.: Current Reactor Power - SAT
- UNSAT NOTE Per initial conditions, current reactor power is 20%.
STANDARD: Operator enters 20% per Initial Conditions STEP 5.: Final Reactor Power -
- UNSAT NOTE Per initial conditions, final reactor power is 70%.
STANDARD: Operator enters 70% per Initial Conditions STEP 6.: Total Reactor Power Change -
- UNSAT STANDARD: Operator determines power change to be 50%.
Critical Step
\
JPM JPM 190 190 Page Page 66 of of 88 Rev.
EW.t.22 Job Performance Job Performance Checklist:
Checklist:
STEP/STANDARD STEP/ST ANDARD SAT/UNSAT SATIUNSAT STEP 7.:
STEP 7.: Rate of Rate of Reactor Reactor Power Power change change SAT SAT STANDARD:
STANDARD: Operator enters 3%/hr3%/hr per per initial initial conditions. -
UNSAT UNSAT STEP *8.:
STEP *8.: Number of hours Number hours to change power
- SAT SAT UNSAT UNSAT STANDARD: Operator calculates number STAt\DARD: number of hours to change power; of hours power; 50% I1 3%/hour and enters results:
16 2/3 16 213 hours0.00247 days <br />0.0592 hours <br />3.521825e-4 weeks <br />8.10465e-5 months <br /> hours (or 16.67 16.67 hours7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br />, or 1616 hours0.0187 days <br />0.449 hours <br />0.00267 weeks <br />6.14888e-4 months <br /> and 40 minutes).
minutes).
STEP *9*9.: Current Rod Position -
SAT UNSAT STANDARD: Operator enters 160 160 steps on Bank D D per Initial Conditions STEP *j*10.:
0.: Final Rod Position -
- UNSAT STANDARD: Operator enters 228 steps per Initial Conditions STEP *11.: [2] CALCULATE change in boron concentration by performing the following:
[a] Llp p POWER DEFECT
- SAT Llp IP POWER DEFECT = = pcm PD 11 -
PD - pcm PD 22= __ pcm PD UNSAT NOTE: Use "eye-ball" eye-ball interpolation between closest parameter lines. Band accuracy Y2 % increment presented on figure. Critical Step STANDARD: Operator uses proper curve, Figure 1, U1 Cl 7 Power Defect BOL, Ui C17 1400 ppm line (long dash line) to enter data.
For 20% operator should enter 350 pcm.
For 70%, operator should enter 1100 pcm.
Llp POWER POWER DEFECT = 350 pcm PD DEFECT = 11 - 1100 pcm =
PD - = -750 pcm STEP *12.: [b] Llp -
SAT P XENON XENON 180 pcm UNSAT UNSAT Llp XENON = -2250 pcm XE p XENON 22 - (-2430 pcm) XE XE - 11 == 180 XE -
STANDARD: Operator enters Xenon values (provided in the initial conditions) and reactivity due to Xenon.
calculates the change in reactivity Critical Step
JPM 190 JPM 190 Page7of8 Page 7 of 8 Rev.2 Rev. 2 Job Performance Job Performance Checklist:
Checklist:
STEPISTANDARD STEP/STANDARD SATIUNSAT SAT/UNSAT STEP *13.:
STEP *13.: [cj
[c] tip b:.p RODS RODS tip RODS = ___ pcm b:.p RODS pcm Rods Rods 2 2 - ___
- Rods 1 == __pcm pcm Rods pcm 1 pcm SAT SAT UNSAT UNSAT NOTE:
NOTE: Use eye-ball Use interpolation between "eye-ball" interpolation closest parameter between closest lines. Band parameter lines. Band accuracy 4 1h increment presented on figure.
Critical Step STANDARD: Operator uses STANDARD: uses proper curve Figure 4, 25% line 4,25% 160 steps operator line for 160 operator should enter should enter -480-480 (-450
(-450 to -525 pcm).
to -525 pcm). For 228 steps, For 228 operator should steps, operator should enter 0.
enter O.
b:.p RODS tip RODS = Rods 2 - -480 (Acceptable Range -450 to -525) pcm Rods
(0) pcm Rods 2 - 1 Rods 1 =
480 (Acceptable Range 450 to 525 pcm) 14.:
STEP 14.: [d] Change in reactivity due to Power Defect, Xenon and Rods
[dl SAT
[a] + + [b]+[c]
[b]+[c =__ pcm UNSAT STANDARD: Operator calculates Change in reactivity due to power defect, Xenon and rods:
-750 pcm + + 180 pcm + + 480 (450 to 525) pcm = = -90 pcm Critical Step (Acceptable Range -120 pcm to -45 pcm)
STEP 15.: [e] Change in Boron Reactivity SAT Substep [d] [dj X (-1) =
= 90 pcm UNSAT (Acceptable Range 120 pcm to 45 pcm)
Critical Step STANDARD: Operator calculates the change in Boron Reactivity, by multiplying substep [d] [dl by -1.
STEP 16.:16.: [f]
[f] Change Change in in Boron Boron Concentration Concentration SAT Substep [e] [e] /I Boron Boron Worth UNSAT UNSAT STANDARD:
STANDARD: OperatorOperator Records Records change change in boron reactivity in boron and determines reactivity and the determines the Critical Step Critical Step Boron Boron Worth Worth pcm/ppm pcmlppm from Figure 7.
Figure 7.
Substep Substep [e] [e] /I -6.25
-6.25 pcm/ppm Boron worth =
pcmlppm Boron 14.4
= 14.4 (Acceptable (Acceptable Range Range 19.2 19.2- 7.2 pcm) 7.2 pcm)
JPM JPM 190 190 Page8of8 Page 8 of 8 Rev-2 Re\42 Job Performance Checklist:
Job Performance Checklist:
STEPISTANDARD STEP/ST ANDARD SATIUNSAT SAT/UNSAT STEP 117.:
STEP 7.: [3] Ensure
[3] independently verified Ensure independently SRO in by SRO verified by accordance with in accordance with SAT SAT Appendix J.
J.
UNSAT STANDARD: Operator notifies the US STANDARD: US anan independent verification is independent verification is required in accordance with Appendix J.
in accordance J.
End Time End Time End End of JPMJPM
CONC N CON TRA ENTR CEN TION CON ATION CONT TRO ROLL 0-SO--62-7 0-SO 62-7 SQN SQN BORO BOR ON Rev. 56 1,2 1,2 Page 14 164 of 201
/---- ----
( t<C Y Ir( P I~-\~
APP APPE ENDNDIX E IX E
/
-""~!~~/
)
Page 1 1 of 18 TIVITY REACTIVIT REAC BALANC Y BALA NCE E CAL CALC CUL ATIO ULAT ION N approxim required ation of require imation d Boron change Eyeballll change.. Eyeba NOTE 1 tion calculatio One calcula change.. Calculation is an approx n is required for each major change I .
graphs is expect interpolation of graphs ed.
expected.
change from Pl power change value for power 1 % to PP P power in time period T with rods 22 % power NOTE 2 Dilution or Boration value Dilution currentt point, 2 = target point)
R 1 to R R (Subscrip
.2. (Subsc 2 conventio riptt conven n: 11 =
tion: = curren = target moving from step position Rl moving
[1]
[1] ENTE ENTER R the follow ing data:
following DATA WhereTo Where To Get DATA REQUREQUIR IRED ED
(( 00 i40D ppm Chem Lab or Estima Estimatete using Appendi using Appen dixx 00 Curre nt RCS Boron Current Boron o
9 C
GOD MWD/MTU MWO/ MTU ICS U0981 lOS U0981 Core Burnu Burnup p
,:2 00 %
% NIS or ICS NIS lOS Curre nt React Current Reactor or power power Final React Final Reactor or power power 70 7o %% required As requir for plant ed for ionss condition plant condit S1) 3D A% Current L\A Curre nt and Reactor final React and final power or power Power chang or Power changee L\%
Total React Total Reactor
,1. %/hr
%/hr As required As requir ed for plant condit for plant ionss condition Rate of Rate of React Reactor change power chang or power e 2J )(. ;i 'IVld 1(.,,}1 f;i for plant ionss condition plant condit
{0.?-/3 required As require d for Numb Number er of hours to of hours to chang change power e power ) /3 hr(s) hr(s) )Jp',t-1 As lOS or ICS or MCR Board MCR Board n I (iD
({po steps steps Curre Current Rod Positio nt Rod Position Estimate Estima number te numb of rod er of required steps requir rod steps ed toto
),)~ steps steps controll L\I contro and rod Al and withdraw rod withdr awal requirem al requir ementsents Rod Positio Final Rod Final n Position for power for ge.
chan e.
power chang --
CONCENTR N CONC ENTRATION ATION CONT CONTROL ROL 0-SO-6 2-7 0 62-7 SQN SQN BORON BORO Rev. 56 Rev. 56 1,2 1,2 Page 1?5 of Page 165 of 201201 APPEN APPE NDIX DIX EE /! /(;1" Te,/) \ ~ \q~
/
/
I Page 22 of Page of 18 18 . ',."P 2/S tly. (See (See Examp Exam ple le PowPowe err Incre Increa se and ase and Pow Powe err decr decre ease ase.) .) .~.~~
CAUTION ION Follow sign Follow sign conv conve entio ntions ns explici explic itly.
E chan gee in boron concen in boron trationn by conce ntratio by perform perfor minging the followiing:
the follow ng:
CALCULAT
[2] CALC
[2] ULATE chang Calc Calcu ulati on lation Value Para Param mete r eter Where To Where To GetGet (negati (negativ vee Attached Power Defect Curves::
Defect Curves 3:50 1 - 110D PD pcm PD 1 pcm - ( I O pcm 22 == --75D pcm forpow PD pcm PD for power er
[a] p t.p POWERDEF POWER DEFECT ECT Unit 1:
Unit or 3 1, 2, or3 Figure 1,2, 1: Figure (current) t.>.P POWER DEFECT POWER DEFECT increas increase e))
(current)
Unit 2:
Unit Figure 8, 2: Figure or 10.
g, or 8, 9, 10.
(negati (negativ vee Xenon1: From 1
Xenon From ics*ICS* or ~~~CT or REAC TFF (either currentt INOTE (e.ither curren NOTE:: Xenon reactiviity Xenon reactiv must be ty must be negativee for rise inin conditio condit ions or project ns or ionn to projectio conditio Initial condit to initial n).
ion). Xenon Xenon From ICS*
n: From ICS* or REACREACT TFF 1= = (00 pcm
[b] t.p XENON XENON Xeno 2
Xenon2 - ))-SD pcmX pcm 2 XE E2 -- '-24~cpc 3 pcmmXE1 XE conc)
(projecti
( project on ion over over time period period T).
t) L'-.P XENON XENON (curren (current)
- (ICS
e sign).
Attached Rod Worth Curves::
Worth Curves [) pcmR 2 odss2 - -
Rod L
-/S O pcmR =
odss1 =
Rod 1 4 (),'L-:-. pcm (negativvee (negati for rod
[c] t.p
[C] RODS RODS Unit 1:
Unit 1: Figure 4,5, or 6 4, 5, or6 (curren t) IP n~n.
L'-." RODS inserti on))
insertion Lj S C ,~'tl S.J.5 .r(,~~SJ.L{5L~ ~ 5~~_)
. (current)
Unit 2:
Unit Figure 11, 2: Figure 13.
12, or 13.
11, 12, iKbN~z..
DEFEC R DEFE CT,T, XENO XENON u
N,, AND RODS RODS)) - co (i'o pcm (CHANGE GE IN REACT IN REAC IVY DUE TIVY DUE TO POWE POWER
[d] AfD t.p POWER DEFECT POWERDEF ECT+XENO + RODS
+ XENONN.RODS
=
= ACc~p*k~)!e. F11./YlSC
[aJ
[al POWER pcm L'-.p POWE pcmAp DEFEC R DEFE T +
CT + [b]
b1 6p XENON pcm pXEN ON + + [cJ Ed pcm Ap6p RODS
- ()c (J- 0 Dc m .i-, -r6 - g<
- 74 C;A' m f
tia 0 pcm
[e] p t.p (CHANGE IN BORO BORON REACT N REAC IVITY)
TIVIT Y)
= L'-.p BORO N C({(Zc
- 2. 0. 'm q:;)
(c BORON =
ii
[c.i] pcm t.p pcmAp POWER DEFECT P0WERDEF
+ RODS)
+ XENONN+RODS)
ECT+XENO X (-1)
X (1) BORON (negativvee (negati
[t] Appm t.ppm (CHANGE IN BORO BORON CONCE N CONC NTRAT ENTR ION))
ATION for dilutio dilution,n,
[f] BORON BORON G.)
I s,-- pcm/pp m Boron Worth) = - 1 4. t-/ ppm
- 1) ppm positi~ee for positiv for
(( [e]
fel pcm Ap BORON)) -:- (
L'-.p BORON (from Fig.,-.v,. -
. pcm/ppm (U-1) or Fig. 14 (U-2) 7 (U-i) j.
, J
"'i LJ._,j-Q..;z.2.
L boratio boratJon
,PfJr'n )
2 ppi n))
ndentlyy verified by SRO 8RO in acco accord rdan ancece with Appendix dix J.
[3] ENSU RE independentl (N/A if perform perfor med ed by an SRO to verify data provid ed by Rx. Eng)
SQN SQN BORON CONCENTRATION CONTROL BORON CONCENTRATION CONTROL 0-SO-62-7 0-80-62-7 I1,2
,2 Rev. 56 Rev. 56 Page Page 168 168 of of 201201 APPENDIX EE Page 55 of 18 Page 18 Figure 11 UICI7 U1 C17 Power Defect BOL NOTE NOTE Use eye-ball "eye-ball" interpolation between closest parameter lines.
UNIT 1 I CYCLE 17 17 POWER DEFECT - BOL (150-4000 MWD/MTU) 1800 1800 I corn 1300a ppm 1700 i / JDQ I /
1600 E+/-E+/-EEE I I
/
/
I .CC 14 oem 00 ppm 1500 i I
/ L" I "
1400 1/ 1,/
E ZTE /I /' 13CC lB corn 00 ppm 1300 V I /
/ 1//
1200 1100 _..
t EEEEEEEEE E E EEEE4E
/
/
,/-7
/:1
/'
I
) .
/ /j .' I EEC) /
F I
S a 1000 -
v'
/
- I tl
~ / v,- I
<Il 900 900 0 /
7/I / iI L.,
<Il 800 800 v V I 30 0..
/ / !
700
,/ I V v i
/ r/-/" I 600 600
- zz /./
/ V',
- i I
500
/,9 I 400 z:_:_ -
/V*
/~
..". I I
300 300
__7 'i/.>' . i
~¥
- I 200 200 if" I j I 100 7' I EEEEZETTEH 100
/ I 00.
[/ I o0 10 10 20 20 30 30 40 40 50 50 60 60 70 70 8080 90 90 100 100 Power Power Level (%)
Level (%)
Reference:
Reference:
NOR NDR TableTable 6-23 6-23 toto 6-27 6-27
SQN BORON CONCENTRATION CONTROL BORON CONCENTRATION CONTROL 0-SO-62-7 0-SO-62-7 1,2 1,2 Rev. 56 Page 171 171 of 201
~ ". .-,--.
APPENDIX E APPENDIX E freTPf1) f Page 88 of 18 18 Figure 44 UICI7 Insert ed Rod Worth BOL U1C17 Inserted
- NOTE NOTE Use eye-ball interpolation between "eye-ball" interpolation between closest closest parameter lines.
parameter UNIT1 CYCLE 17 UNITI 17 INSERTED BOL INSERT ED ROD WORTH (150-4000 MWD/MTU)
(150-4000 MWDIMTU) 0 T 1 T I H--t-HI-t++++ --t-HH -H--H-
-100 -H--H- 1 I-- ++-H-H -+-H-t+ I -H-++- +--+-+ -.:f7l A'. ;;t-'~-+-+--+-:+-t-I
-100 i V,"
b b -f-b -W-I---t--+--J--+-h
-+fr,H /.+:,+-+-I---t-t---1r.t-h
-200 -H-+--t -Hi-t-H --H-++ -+-t-+- H-t+++ +-++--t -HH-H -+++++ //.
-200 /~r~4
-t-H-H --t-H- H-t+-H -+++++ ++--t- H-H~~H /~
H--H--H-+++- L4 -/
-300
-300 A.
rr.":r
(,+-+I+-+-+- t--!-+-t- -l-l
. 1 / .: i-
+ --I--- -f+/- - - + -
V l .44
- r-'HV ,', 'I I
-400 -H-+--t -HH-H- t++++-- t-HH-H -+++++ -+-H-+- f---1:,.<
-400
/1,J 1, -1 I I
-500
.-L I 1/
-600 ,r- Vl
,t
-700
.iJ I -
E0
§~ -800 -H-+++- -t-H-H-- t-H-H--- +++--t;> 4-A-+:- 'I' v C. v~
~ -900+T-
-900 t !-++--+--+-~+-+~-!-+--+--J~~,r'"j/~~++-!-++--+--t
'1.1 -H-+-+++-!-+~--t-H-+-+~~
~
0
-1000 ++-+-t--+--J-t-t--t--t-+++-+-tAL-!-:-f-,+-++-+--+-t-+-t--H--t-H--+-++-+--+-t--'--l--t-H--+-+++-t-+
-1000 J~[~~hV+ ++-t--+- t-H-+-H- -+-++-+- -H-t--l- +-H-t+++ -!-+--+- -JrH
~o
- 0 H-+-+++++-!-+-I---t--+--v/1'
!"-t---i-t-t--t-++++-H+--+--t-H-t+-t-+-!-++--+-+-~+-+~-H 0 "
-1100 -t-+++-+-t--t-H-+-+-t--b'i'I/--r-n 0:: -1100
~
OJ
-H ai~U, -1200 ++-H---t--!-+-H--+--h'+"'-Ii-:-'-jH--t-t--t -+++-+- t-H--t-H -t--t-+-+ ---t-t-l-- -t--t---t- +-+++-! -+---t--!
-1200
~I'
£C ,)
-1300
-1300 V .' '+,'-H-t--l --t-H-+ +++++ -+-t-HH -H-+++ +-+-+i -HH-H -++-H- H
-4--i - - - - - - - -
-1400 -t---t--!--t-rhl!~'+.I'+-+--H--H--t-t-t--t-+++~---t--!--t-H-+-+++++---t--!I--t-H- +-+-t-+-! -++--+
- -I- /4.- - - - - ,- - - - - - -
-1400+--t -
,ii" I
I rrt-+t- +Tn:
-1500 +++-+- HI*7H-+ -++++- +-HH-H -+++++ -+-+-t- Hi-t-+- ++++-+ -+-H--t-H --H--H --H
-1500 v I I
t-H-t+ +++--t -H--t-H-t+TT~~
-1600-H-~~Ln
-1600
- A 1,1
-H-t++ ++--t-rw.Si*+-+-HH-H-H-+++++++-t-H-++
-1700 H~V.;t.Lt-+-H-+-++++-+-t--l-
-1700 HH-H-- H-+++- -t-H--
-+-+-t-+-t-t--l-HH-++++-+
++++-+-t--HH-H
-H-H-++~II+++++--t-H--HH
-+--t-H-H--++--H-t-i
-1800 iww ij
-1900 ++-+-+-tH-H-+-++++-+-HH-+-++++++-+-t--lH-H-t++++
-1900+
-2000 0~JJ~-L~LL~~~~LL~JJ~~--t-LLL+~J4
-200 o0 20 40 60 80 100 120 140 160
--t1-+1--HH-H--++~-t-i I~-L~~~~---j 180 180 200 220 240 Bank Steps Withdra DBank D Withdrawn wn (steps) 1-- 100%
100 Power -
% Power
- Power- , , , 50% Power -
75% Power* . .
, -25%
. 25% Power - .. 0%
- Powe1 0%Powe ence: NOR
Reference:
Refer NDR Table 6-34.
SQN BORON CONCENTRATION CONTROL 0-SO-62-7 1,2 Rev. 56 Page 174 of 201
-q><
0) rn APPENDIX E (0
Page 11 of 18 CD C
CD
-.1 0 Figure 7 U1C17 Differential Boron Worth CD 1CD 0) w 0 -I 0 0
-I-0 z NOTE 0 rn I Use "eye-ball" interpolation between closest CD
- 0) CD 0 CD C) (I) U)
CD CD
-C
-D 0
- 0) CD CD 0 parameter lines. CD< - =
D CD z-<
UNIT 1 CYCLE 17 0- C)
C 0 1
m m
z 00 DIFFERENTIAL BORON WORTH (pcm/ppm) 0 -g 3 -o 3
-6.1
-6.2 01 BOL C-
-6.3 C.)
I I
-6.4
-6.5
-6.6 0)
E Boron Worth (pcm!ppm)
Q.
Q.
-6.7 Eu
.e:
.c -6.8 I t
~
c -6.9 c!3 0
0 en
-7.0
-7.1 -
-7.2 C.)
I. :-=-r:- EOL
-7.3 C.)
-7.4
-7.5 01 1J r-- .
C) 0 0) 0 200 r)01 0 400 c.0 600 0) 0 0 800 03 0
0 01 1000 0
0 1200 0 0 1400 0 1600 0
0 Boron Concentration (ppm) o 0 C) CD D DC 0 -o D.C C.)
F) 0)
0
- 0) 0
- - BOL (0-4000) - - MOL (4000-16000) 0 9 . . . . . EOL (16000-21223) 0 0
03 C 0
0 0 0 0 0 to CD
Reference:
NOR Table 6-7 CD CD CD D
C)
CD z -1 0 CD 0)
READ TO READ TO OPERATOR OPERATOR Directions to Directions to Trainee:
Trainee:
I will will explain explain the the initial initial conditions, conditions, and and state state the the task task to to be performed. All be performed. All steps shall be steps shall be performed performed for for this this JPM.
JPM. I I will will provide provide initiating initiating cues cues and and indicate indicate any any steps steps to to be be discussed.
discussed.
When you When you complete complete the the task task successfully, successfully, thethe objective for this objective for this job measure will performance measure job performance will be be satisfied. Ensure satisfied. Ensure youyou indicate indicate to to me me when when youyou understand your assigned understand your task. To assigned task. indicate that To indicate that you have you have completed completed your your assigned assigned tasktask return the handout return the handout sheet provided you.
sheet II provided you.
INITIAL CONDITIONS:
INITIAL CONDITIONS:
1.
- 1. Unit us Unit 1 is currently stable at 20 20 %.%.
- 2. Control rod Bank D D is at 160 160 steps.
steps.
- 4. 1U0981 Core burnup is 600 MWD/MTU.
1U0981 MWD/MTU.
- 5. Reactor Engineering has provided following Xenon data:
XE 1 ==-2430 pcm 1
XE XE 2 =-2250 pcm 2
XE INITIATING CUES:
Perform 0-SO-62-7, Appendix E, Reactivity Balance calculation, in preparation for a change in reactor power from 20% with Control Rods at 160 steps on D Bank, to 70% with Control Bank D D at 228 steps, using a 3%/hour power increase rate.
TENNESSEE VALLEY TENNESSEE VALLEY AUTHORIT Y AUTHORITY SEQUOYAH NUCLEAR SEQUOYAH NUCLEAR PLANT PLANT SYSTEM OPERATING SYSTEM OPERATING INSTRUCTI ONS INSTRUCTIONS 0-50-62-7 O-SO-62-7 BORON CONCENTR CONCENTRATION ATION CONTROL Revision 56 QUALITY RELATED PREPARED BY: _ _ _--=O..:..:..iv!..!.:ia~Ta::::::..yL.!.:lo:::..!.r Olivia Taylor_ _ _ _ __
RESPONSIBLE RESPONSIBLE ORGANIZATION:
ORGANIZATION: OPERATIONS OPERATIONS APPROVED BY: _ _ _~J~ J.. .!K. . .!oK=-,W~IL:!...!Kc=.E.:::..S WILKES _ _ _ __
EFFECTIVE DATE: 07/06/09 LEVEL OF USE: CONTINUOUS CONTINUOUS USE REVISION DESCRIPTION:
DESCRIPTION: Minor editorial change made to correct UNID issue in Section 8.15 (09001012)
PERFORMANCE PERFORMANCE OF OF THIS THIS PROCEDURE PROCEDURE MAY MAY IMPACT REACTIVITY IMPACT REACTIVITY
SQN SQN - 027 0-SO-62-7 1,2 BORON CONCENTR BORON CONCENTRATION ATION CONTROLCONTROL Rev. 56 Page 2 of 201 Page2of 201 TABLE OF TABLE OF CONTENTS CONTENTS Page 11 of Page of 33 Section Title Section Title Page Page 1.0
1.0 INTRODUCTION
INTRODUC TION .............................................................................................. 55 1.1 1.1 Purpose ........................................................................................................... .
Purpose 55 1.2 1.2 Scope ................................................................................................................
Scope 55
2.0 REFERENCES
REFERENC ES .................................................................................................. 55 2.1 2.1 Performance References ................................................................................ .. 55 2.2 Developmental Developmen tal References .............................................................................. . 6 3.0 PRECAUTIONS PRECAUTIO LIMITATIONS NS AND LIMITATIO NS ................................................................ 7 4.0 PREREQUISITE PREREQUIS ITE ACTIONS .............................................................................. 9 5.0 STARTUP/STANDBY STARTUP/S TANDBY READINESS ................................................................ . 13 5.1 Automatic Makeup ............................................................................................ 13 6.0 NORMAL OPERATION .................................................................................... 17 6.1 At Power Routine Dilution ................................................................................. 17 6.2 Dilute ................................................................................................................. 19 6.3 Alternate Dilute ................................................................................................. 25 6.4 Borate ............................................................................................................... 29 6.5 Manual Makeup Control (preferred method for VCT makeup in Modes 11 and 2) 33 7.0 SHUTDOWN.....................................................................................................
SHUTDOWN \
39 8.0 INFREQUENT INFREQUENT OPERATION ............................................................................ 40 8.1 8.1 Blending to Spent Fuel Pit Using Blender via Using Blender SFP SFP Cooling Cooling Pump Pump Suction Suction Pressure Indicators ..............................................
Pressure Indicators 40 40 8.2 8.2 Blending Blending to to Spent Spent Fuel Fuel PitPit Using Blender via Using Blender via Bull Hose directly to Bull Hose directly to Spent Spent Fuel Fuel Pit..................................................................
Pit 50 50 8.3 8.3 Makeup Makeup to to RWST RWST ............................................................................................. 58 58 8.3.1 8.3.1 Blending Blending to to Refueling Refueling Water Water Storage Storage lank (RWST) Using Tank (RWST) Using Boric Blender Acid Blender Boric Acid 58 58 8.3.2 8.3.2 High High Boron Boron Concentration Concentration Makeup Makeup to RWST ...................................................
to RWST 63 63 8.4 8.4 Makeup Makeup to to the the Reactor Reactor Coolant System from Coolant System from the RWST in the RWST in Modes Modes 1-41-4 when when Automatic/Manual Automatic/Manual Makeup unavailable Makeup isis unavailable............................. 69 69
SQN SQN 0-SO-62-7 0-SO-62-7 ATION CONTROL BORON CONCENTR CONCENTRATION CONTROL 1,2 1,2 BORON Rev. 56 Rev. 56 I Page 33 of Page of 201 201 TABLE OF TABLE OF CONTENTS CONTENTS Page 22 of Page of 33 Section Title Section Title Page Page 8.5 8.5 Manual Makeup Manual Makeup to to the the Reactor Reactor Coolant Coolant System System from the from the RWST RWST in in Modes Modes 55 or or 66 ........................................................................... 72 72 8.6 8.6 Blending to Blending to Transfer Transfer Canal Canal Using Using Boric Boric Acid Acid Blender Blender... .... ... ...... ........... ............ ... 75 75 8.7 8.7 Blending to Blending to the the Holdup Holdup Tank Tank (HUT)
(HUT) Using Using Boric Boric AcidAcid Blender Blender............................. 83 83 8.8 8.8 Flushing Unit Flushing Unit I1 Blender/Pipi Blender/Piping Using Primary Water (Maintenanc ng Using (Maintenance e Activities)
Activities).... 93 93 8.9 8.9 Unit 22 Blender/Pipi Flushing Unit Blender/Pipingng Using Primary Water (Maintenanc (Maintenance e Activities)
Activities).... 99 99 8.10 Rapid Boration using Emergency Borate Valve Valve.................................................... 106 106 8.11 Manual Blending to RCS During Refill Operations Operations in Mode 55 or 66....................... 109 109 8.12 Blending to B "B" Holdup Tank (HUT) Using Unit 11 Boric Acid Blender ... ........ ... .... 116 116 8.13 Blending to Refueling Water Storage Tank (RWST) Using aa Boric Acid Blender Blender. 125 125 8.13.1 Blending to Unit 2 Refueling Water Storage Tank (RWST)
Using Unit 1 1 Boric Acid Blender...........
Blender .......... .... .... ..... ..... ....... ... ...... .... ......... .... 125 8.13.2 Blending to Unit 1 I Refueling Water Storage Tank (RWST)
Using Unit 2 Boric Acid Blender......
Blender .......... ... ..... .......... .... ...... .......... ............. ..... 138 8.14 Unit 11 Alternate divert path using RCL sampling system......................................
system 150 8.15 Conditions At Power Boration to Maintain Steady State Power Conditions............................ 155 9.0 9.0 RECORDS ........................................................................................................ 157 157 APPENDIXES APPENDIXES APPENDIX A: HOSE HdSE CONNECTION CONNECTION UTILIZING UTILIZING MAINTENANCEMAINTENANCE SUPPORT 158 APPENDIX B: BORIC ACID FLOW FLOW RATE CALCULATIONS RATE CALCULATIONS........................ 159 159 APPENDIX C: CALCULATION OF BORIC ACID AND PRIMARY WATER CALCULATION INTEGRATOR INTEGRATOR SETTING SETTING FOR FOR MANUALMANUAL MAKEUP MAKEUP TO TO VCT (RCS) 161 (RCS) 161 APPENDIX D: D: CALCULATION CALCULATION FOR FOR AMOUNT OF BORIC ACID OR OF BORIC PRIMARY OR PRIMARY WATER (TI-44)
WATER (Tl-44) ...................................................................... 163 163 APPENDIX APPENDIX E: E: REACTIVITY REACTIVITY BALANCE BALANCE CALCULATIONCALCULATION .............................. 164 164 APPENDIX F:
APPENDIX F: CALCULATION CALCULATION OF BORIC ACID OF BORIC ACID AND AND PRIMARYPRIMARY WATER WATER INTEGRATOR INTEGRATOR SETTING SETTING FOR FOR MANUALMANUAL MAKEUP MAKEUP TO TO RWSTRWST OR OR HOLDUP HOLDUP TANK............................................
TANK ................... 182 182 APPENDIX G:
APPENDIX G: CALCULATION CALCULATION OF INTEGRATOR SETTINGS OF INTEGRATOR SETTINGS FOR FOR MANUALMANUAL BLEND DURING RCS BLEND DURING RCS FILL FILL ................................................... 185 185
SQN SQN 0-SO-62-7 0-SO-62-7 BORON CONCENTR BORON CONCENTRATION ATION CONTROL CONTROL 1,2 1,2 I Rev. 56 Rev. 56 Page 4 of 201 Page4of 201 TABLE OF TABLE OF CONTENTS CONTENTS Page 33 of Page of 33 Section Title Section Title Page Page APPENDIXES APPENDIXE S H:
APPENDIX H:
APPENDIX INDEPENDENT INDEPENDE VERIFICATION NT VERIFICAT ION OF OF CALCULAT CALCULATION ION OF OF BORIC ACID BORIC ACID AND PRIMARY WATER AND PRIMARY WATER INTEGRATO INTEGRATOR R SETTING SETTING FOR FOR MANUAL MANUAL MAKEUP MAKEUP TO TO VCT VCT (RCS)
(RCS)............................... 188 188 APPENDIX I:I:
APPENDIX INDEPENDENT INDEPENDE VERIFICATION NT VERIFICAT ION OF OF CALCULAT CALCULATION ION FOR FOR AMOUNT OF OF BORICBORIC ACID ACID OR PRIMARY WATER OR PRIMARY WATER (TI-44)..(TI-44).. 190 190 APPENDIX J:
APPENDIX J: INDEPENDENT INDEPENDE NT VERIFICAT VERIFICATION ION OF OF REACTIVIT REACTIVITY Y BALANCE BALANCE CALCULATION......................................................................
CALCULAT ION 191 191 APPENDIX K: INDEPENDENT INDEPENDE VERIFICATION NT VERIFICAT ION OF CALCULAT CALCULATION ION OF BORIC ACID AND PRIMARY WATER INTEGRATO INTEGRATOR R SETTING FOR MANUAL MAKEUP TO RWST OR HOLDUP TANK ..... 193 APPENDIX L: INDEPENDENT INDEPENDENT VERIFICAT VERIFICATION ION OF CALCULAT CALCULATION ION OF INTEGRATOR SETTINGS FOR MANUAL BLEND DURING INTEGRATOR RCS FILL ............................................................................... 196 APPENDIX M: CALCULATION OF BORIC ACID CONTROLLER CALCULATION CONTROLLER SETTING FOR AUTO MAKEUP.............................................................
MAKEUP 198 APPENDIX N: INDEPENDENT INDEPENDENT VERIFICATION VERIFICATION FOR CALCULATION CALCULATION OF CONTROLLER SETTING FOR BORIC ACID CONTROLLER AUTO MAKEUP ...... ..... ..... ...... ...... .... ........... ... ........ ... ........ .... 199 199 APPENDIX 0: ESTIMATION OF CURRENT RCS BORON ESTIMATION CONCENTRATION................................................................
CONCENTRATION 200
\
SOURCE SOURCE NOTES NOTES " .. ,"" ........ ,.. ,........ ,.... " ...... ,........ ,' ........ ,'" .............. ,............ , 201 ATTACHMENTS ATTACHMENTS ATTACHMENT ATTACHMENT 1: 1: POWER POWER CHECKLIST CHECKLIST 1-62-7.01 1-62-7.01 ATTACHMENT ATTACHMENT 2: 2: POWER POWER CHECKLIST CHECKLIST 2-62-7.02 2-62-7.02 ATTACHMENT ATTACHMENT 3: 3: VALVE VALVE CHECKLIST CHECKLIST 1-62-7.03 1-62-7.03 ATTACHMENT ATTACHMENT 4: 4: VALVE VALVE CHECKLIST CHECKLIST 2-62-7.04 2-62-7.04
~
SQN SQN O-SO-62-7 0-SO-62-7 1,2 BORON CONCENTR BORON CONCENTRATIONATION CONTROL CONTROL Rev. 56 Rev. 56 1,2 Page5of2Ol Page 5 of 201 1.0
1.0 INTRODUCTION
INTRODUC TION 1.1 1.1 Purpose Purpose To provide To provide instructions instructions for for operation operation of the Boron of the Control System.
Boron Control System.
1.2 1.2 Scope Scope This instruction This instruction provides provides detailed detailed steps steps for the following modes for the of operation:
modes of Makeup Automatic Makeup At Power At Power Routine Routine Dilution Dilute and Alternate Dilute Borate Manual Makeup Control (preferred method for VCT makeup in Modes 1 1 and 2)
Blending to Spent Fuel Pit Using Boric Acid Blender via SFP Cooling Pump Suction Pressure Indicators Blending to Spent Fuel Pit Using Boric Acid Blender via Bull Hose Directly to Spent Fuel Pit Blending to RWST Using Boric Acid Blender Makeup to the Reactor Coolant System from the RWST in modes 1-4 when the Automatic/Manual Automatic/Manual Makeup is unavailable.
Manual Makeup to the Reactor Coolant System from the RWST in modes 5 or 6 Blending Blending to Transfer Canal Using Boric Acid Blender Blender Blending Blending toto the the Holdup Holdup Tank Tank using using Boric Blender Boric Acid Blender Flushing Flushing Unit Unit 11 Blender/Piping Blender/Piping Using Using Primary (Maintenance Activities)
Primary Water (Maintenance Flushing Flushing Unit Unit 22 Blender/Piping Blender/Piping Using Using Primary Water (Maintenance Primary Water Activities)
(Maintenance Activities)
UNIT UNIT 22 Alternate Alternate divert divert path path using using RCLRCL sampling system sampling system 2.0
2.0 REFERENCES
REFERENCES 2.1 2.1 Performance Performance References References A.
A. Procedures Procedures 1.
- 1. 0-SO-62-10, O-SO-62-1O, Boric Boric Acid Acid Batch, Batch, Transfer, and Storage Transfer, and System Storage System
( 2.
- 2. 0-SO-78-1, O-SO-78-1, Spent Spent Fuel Fuel Pit Pit Cooling System Cooling System B.
B. Technical Technical Instructions Tl-44, Boron Instructions - TI-44,
- Tables Boron Tables
SQN SQN O-SO-62-7 0-SO-62-7 1,2 BORON CONCENTR BORON ATION CONTROL CONCENTRATION CONTROL Rev.
Rev. 56 56 1,2 Page6of2Ol Page 6 of 201 2.2 2.2 Developmental Developmen References tal References A.
A. Procedures Procedures 1.
- 2. 0-Pl-OPS-00
- 2. 0-PI-OPS-000-633.0, 0-633.O, Aux. Rm. Switch Cont. Rm.
Aux. Cont. Alignment Verification Switch Alignment Verification
- 3. Westinghous
- 3. Westinghouse e Vendor Manual SQN-VM 4990 Manual SQN-VM 4990 B.
B. Technical Specification Technical s Specifications 1.
- 1. 3.1.1.1 3.1.1.1
- 2. 3.1.1.2
- 3. 3.9.1
- 4. 3.10.1
- 5. Bases 3/4.1.3 Requirements C. Technical Requirement s Manual 1.3.1.2.1
- 1. 3.1.2.1
- 2. 3.1.2.2
- 3. 3.1.2.3
- 4. 3.1.2.4
- 5. 3.1.2.5
- 6. 3.1.2.6
- 7. Bases 3/4.1.2 D. FSAR
- 1. 9.3.4.2.5
- 2. 9.3.4.2.2
- 3. 9.3.4.2.6 4.
- 4. 15.2.4 15.2.4 5.
- 5. 15.2.14.1 15.2.14.1 6.
- 6. 15.4.6.1 15.4.6.1 E.
E. TV TVAA Drawings Drawings 1.
- 1. 47W809-1 47W809-1 2.
- 2. 47W809-2 47W809-2 3.
- 3. 47W809-5 47W8095
SQN SQN I 0-SO-62-7 0-SO-62-7 ATION CONTROL 1,2 1,2 BORON CONCENTR BORON CONCENTRATION CONTROL Rev. 56 Rev. 56 I Page 77 of Page of 201 201 3.0 3.0 PRECAUTIONS PRECAUTIO AND LIMITATIO NS AND LIMITATIONS NS A.
A. The mode The mode selector should be switch should selector switch returned to be returned the AUTO to the AUTO makeup makeup mode mode after after any dilution any dilution oror boration operation. The boration operation. control switch The control must be turned switch must be turned to START to START in order in order for for the the auto makeup to auto makeup to function.
function.
B.
B. least one Reactor Coolant Pump At least Pump or one RHR or one RHR Pump must be in Pump must in operation operation during during dilution dilution operations.
operations. [C.6]
[C.6]
C. Maintain Pressurizer boron concentration within 50 ppm of reactor coolant loop concentration.. This can be accomplished by turning boron concentration boron turning pressurizer heaters heaters on on and allowing sprays to maintain maintain RCS pressure Normal Spray is program. IfIf Normal pressure within program. is NOT available, then Auxiliary Spray should be used (1, 2-SO-62-1) 2-S0-62-1) in conjunction with pressurizer backup heaters.
D. Axial flux difference should be maintained within limits by using the control bank concentration..
of rods while changing boron concentration E. Prior to making aa positive reactivity change, Tech Specs and TRM should be referenced to ensure the unit is not in aa LCO action that prohibits aa positive reactivity change. [C.1]
F. A boron sample should be obtained whenever reactor makeup water is added to the VCT, unless the unit is at power and results of the makeup are as expected.
G. When making an RCS dilution of 2:: 3000 gallons, it should be done in batches with an RCS boron concentration verification at the halfway point (e.g., 1500 gallons). Allow at least 15 minutes between batches. [C.S] [C.7]
[C.5] [C.?]
H. Simultaneous Simultaneous makeup to the RWST and the RCS should be avoided to prevent the possibility of injecting unborated (or under borated) water into the core. [C.4] [C.4]
[C.6] [C.?]
[C.7]
I. Reactivity balance calculations are required for any power changes more than
%, except when immediate 11%, boration is immediate boration required to maintain rods is required rods above the insertion insertion limit limit or as as required during an required during Shutdown or Rapid Shutdown an Rapid Reduction Load Reduction or Load (AOP-C.03) or dropped/misaligned dropped/misaligned rod recovery (AOP-C.01). (AOP-C.01). Although stated in stated in the the procedure procedure that that only only one calculation is one calculation required is required for a major change a major change in Reactorin Reactor Power, Power, calculations calculations should should be be current and take current and account the into account take into dependency time dependency the time of of parameters parameters used used in in the the calculation.
calculation. [e.g. calculation to one calculation
[e.g. one decrease RX to decrease RX power to 70% power to remove a MFP power to 70% power to remove a MFP is is acceptable].
acceptable]. In In the the event event of of a a large large power power manipulation manipulation (GO (GO startup startup oror shutdown) calculations will several calculations shutdown) several be will be required.
required. AA calculation calculation should should be performed for be performed increase to the increase for the Reactor 30% Reactor to 30%
power, power, another another forfor an increase to an increase and so on. These calculations 50%, and so on. These calculations may to 50%, may bebe correlated correlated to to GO GO plateaus.
plateaus.
SQN SQN 0-SO-62-7 0-SO-62-7 1,2 BORON CONCENTR BORON CONCENTRATION ATION CONTROL CONTROL Rev. 56 Rev. 56 1,2 Page 8 of 201 Page8of 201 3.0 3.0 PRECAUTIONS PRECAUTIO NS ANDAND LIMITATIO LIMITATIONS NS (CONTINUE (CONTINUED) D)
Boric Acid J.J. Boric Acid Controller adjustment is Controller adjustment required for is required depletion for B-10 depletion for B-ID for automatic automatic andand manual makeup manual makeup to to improve accuracy of the accuracy improve the of the the blend. The B-l0 depletion blend. The B-10 depletion value value for each for each unit unit can can be from the obtained from be obtained Rx Eng the Rx Information file Eng Information located on file located the site on the site intranet. Reactor intranet. Reactor Eng Information ICON Eng Information ICON cancan be found on be found on the room PCs.
control room the control PC's.
K. An K. An unanticipated unanticipated power change greater power change MWT, rod than 55 MVVT, greater than greater than motion greater rod motion than I1 step step (in (in or or out),
out), or or TAVG greater than TAVG greater PER and 0.5°F, require aa PER than 0.5°F, should be and should be SPP-10A, Reactivity management event per SPP-10.4, evaluated as aa potential reactivity management Program.
Management Program.
measurementt inaccuracies and integrator calibration L. Boron concentration measuremen tolerance may result in aa small difference between RCS boron concentration and concentration.. This may result in aa small change in Tavg (-l/4°F) blend boron concentration (-1/4°F) and thermal power (by aa few megawatts) after makeup.
M. Manual Makeup (Section 6.5) of approximatel approximately y 200 gallons or less is preferred over allowing the system to automatically make up in Modes 1 I and 2. Performing manual makeup and limiting the volume of makeup is preferred to reduce the impact on reactivity, RCP seal performance (due to reduced pressure/temperaturepressure/temperature tranSients) transients) and RCS chemistry (due to reduced VCT pressure changes). During transient conditions, emergencies, or during plant cooldown, automatic makeup may be used as necessary.
N. The potential exists that the blender piping contains primary water. This will result in a dilution and a small reactivity addition.
O.
- 0. Completely emptying the BAT's BATs for all valve work is not required to establish a safe work boundary. The valves on the lower portions the tanks require an empty tank to establish safe conditions. The tank drain, level instrument isolation and pump pump suction lineline are all at or near bottom of the tank. These are listed in the near the bottom table below:
below:
BAT BATA A BATC BATC BATB BATB 1-VLV-62-1049 I -VLV-62-1 049 0-VLV-62-1 049 0-VLV-62-1049 2-VLV-62-1 2-VLV-62-1049049 1-VLV-62-1058 1 -VLV-62-1 058 0-VLV-62-1 058 0-VLV-62-1058 2-VLV-62-1 058 2-VLV-62-1058 1-VLV-62-1088 1-VLV-62-1088 0-VLV-62-1088 0-VLV-62-1088 2-VLV-62-1088 2-VLV-62-1088 The The other other valves valves associated associated with the Boric with the Acid Transfer Boric Acid Pumps can Transfer Pumps worked be worked can be with with some some level remaining in level remaining in the tanks. As the tanks. margin of As aa margin maximum of safety, aa maximum of safety, of 85%
85%
should should bebe used used toto establish safe working establish safe conditions.
working conditions.
SQN 0-SO-62-7 0-SO-62-7 BORON CONCENTR CONCENTRATION ATION CONTROL CONTROL 1,2 1,2 BORON Rev.
Rev. 56 56 I Page 9 of 201 Page9of 201
/
unit*_-t-i_ _ __
Unit Date Date 'ID b.A 'I 4.0 4.0 PREREQUISITE PREREQUIS ACTIONS ITE ACTIONS vIoTE VTE Throughout this Throughout exists, the exists, the this Instruction step step should should be be where an Instruction where N/A N/A if if an IFITHEN IFITHEN statement condition condition does does statement not exist.
not exist.
- Gj) ENSURE the the instruction to to be used is be used copy of is aa copy of the the () .
( effective version. ~
haso~
r6jl Precautions and Limitations, Section 3.0, ENSURE Precautions ENSURE been reviewed.
3.0, has
~
rtOO REVIEW the following Status Files for any off-normal performance::
alignments that may impact performance Status File V
./
Unit Unit_11 ~
Unit Unit22 GV lv.
Radwaste cv/
LJ/
{J r ENSURE Chemical and Volume Control System is in operation.
1iI: IF in modes 1,1,2,2, oror3,3, THEN P ENSURE requirements of TRM L.C.O. 3.1.2.6 are met, OR COMPLY with applicable actions.
&{ IFIF inin modes modes 4, 5, or 4,5, THEN 6, THEN or6, r ENSURE requirements ENSURE OR OR requirements of of TRM TRM L.C.O. 3.1.2.5 are L.C.O. 3.1.2.5 met, are met, COMPLY with COMPLY with applicable actions.
applicable actions. AJ/4-
/Ii,1) IF Primary Water required for the evolution to be IF Primary Water required for the evolution to be P
)- performed, THEN performed, THEN ENSURE Primary ENSURE Primary Makeup Makeup Water system in Water system service.
in service. tJ//J.
SQN 0-SO-62-7 0-SO-62-7 1,2 BORON CONCENTR BORON CONCENTRATION ATION CONTROL CONTROL Rev. 56 Rev. 56 1,2 Page 10of201 Page 10 of 201 Unit._ _ _-4-_ __
Unit 4.0 PREREQUIS 4.0 PREREQUISITE ACTIONS (Continued)
ITE ACTIONS (Continued)
Date Date Ii? JJ 4)1 4!
~OTE L4OTE The following step The following step is performed at is performed the discretion at the discretion of the of the RORO and/or and/or SRO.
SRO.
fo!iJ WHEN jJ) performing aa dilution WHEN performing boration, THEN or boration, dilution or THEN
[a]
[a] Normal pressurizer spray IF Normal IF spray is available, THEN is available, THEN heaters so pressurizer heaters ENERGIZE pressurizer sprays can so sprays can between the concentration between equalize the boron concentration pressurizer and the RCS /J//r
[b] Normal pressurizer spray is IF Normal IF NOT available, is NOT THEN PLACE Auxiliary Spray in in service 2-S0-62-1) in conjunction with pressurizer (1, 2-SO-62-1) backup heaters. (N/A if not applicable) NJA--
f\JjA
(ó) ENSURE appropriate Valve Checklist has been completed r (N/A if not applicable).
VALVE CHECKLIST INITIALS 1-62-7.03 1 7.03 Ytoy 2-62-7.04 NI I-t
~ ENSURE appropriate Power Checklist had been completed l' NSURE P
)C-
. r (N/A if not appllca bl)
(NIA if not applicable). e.
POWER CHECKLIST INITIALS 1-62-7.01 1-62-7.01 ~
\\
2-62-7.02 rJ/ty-
<QY IFIF Boric Boric Acid Acid Tank is borated water source, THEN the borated is the THEN ENSURE Boric ENSURE Boric acid pump aligned acid pump properly in aligned properly accordance in accordance tJ l jL:
with 0-SO-62-10.
,.Kwith 0-SO-62-10. __ ~
~IF r_
7 7(])IF using N~
N9E EN~
using the the RWST RWST for for the LCV-62-1 35 and/or EN!.RE LCV-62-135 Step Step [13]
[13] may may be borated water the borated OPERABLE.
LCV-62-1 36 OPERABLE.
and/or LCV-62-136 be marked marked N/A THEN source, THEN water source, must be boration must N/A ifif boration immediately be immediately
(\a lit
~
) Ar initiated initiated to to maintain margin OR shutdown margin maintain shutdown OR if performing aa rapid if performing rapid boration boration using using FCV-62-138 FCV-62-138 in preparation for in preparation for RCS cooldown.
RCS cooldown.
~F reactorreactor isis subcritical subcritical AND AND an boration or RCS boration an RCS dilution isis or dilution y ~equired, PERFORM THEN required, THEN PERFORM Appendix Appendix D. D.
\l k fL
'--+\J.!.-/T.!--__
SQN SQN BORON CONCENTR BORON CONCENTRATION ATION CONTROL CONTROL 0-SO-62-7 0-SO-62-7 I 1,2 1,2 Rev. 56 Rev. 56 Page 11 Page of 201 11 of 201 Unit Unit Date _ _ _ _ __
Date 4.0 4.0 PREREQUISITE PREREQUIS (Continued)
ACTIONS (Continued)
ITE ACTIONS Step [14]
Step may be
[14] may be marked marked N/AN/A for any of for any the following of the following conditions:
conditions:
- Minor power Minor Section 3.0) changes (Reference Section power changes 3.0)
- must be immediately IfIf boration must initiated to maintain control immediately initiated control rods above insertion limit above the insertion limit
- During an emergency shutdown During shutdown (AOP-C.03)
(AOP-C.03)
- Recovery of aa dropped or misaligned rod (AOP-C.01).
- If initiating aa rapid boration using FCV-62-138 immediately prior to reactor shutdown in preparation for RCS cooldown.
- During low power physics testing per 0-RT-NUC-0 00-003.0 if 0-RT-NUC-000-003.0 tion values have been boration/dilution boration/dilu provided and verified by Reactor Engineering.
N Appendix D D and E E may be used to verify data provided by Reactor Engineering. IV is not required if Appendices are performed by an SRO to verify Rx. Engineering data.
I ~
~:ill (6IF reactor is critical AND RCS boration or dilution C- will be performed, THEN PERFORM the following:
ffAPpendi~
Appendi< E Reactivity balance calculation. P-tf
'~ Appendix DD Calculation for amount of boric acid or r; primary water (TI-44).
(Tl-44). Nlffy 1
jJ(
~~~EN
<<perfOrming IF performing aa Spent Spent Fuel Fuel Pit Pit boration, boration, THEN ENSURE RCL ENSURE RCL has has provided provided supporting data.
supporting data. ~Ik
SQN SQN O-SO-62-7 0-SO-62-7 1,2 BORON CONCENTRATION CONTROL BORON CONCENTRATION CONTROL Rev.
Rev. 56 56 1,2 Pagel2of2Ol Page 12 of 201 Unit Unit___________ Date TO \)A Date__________ f 4.0 PREREQUISITE ACTIONS (Continued) ra REVIEW OJ REVIEW Unit and Radwaste Status Files for any off normal
~Iignments that may impact performance. .
alignments g documents their name ENSURE each performer and verifier documents JENSURE rp L// and initials:
Print Name Jnitials Anitials Qft4t
~INDICATE jjINDICATE below which performance section of this
~ instruction will be used and the reason for this performance:
oEl 5.0 STARTUP/STANDBY READINESS oEl 6.0 NORMAL OPERATION oLI 7.0 SHUTDOWN oEl 8.0 ~BlliENT 8.0 OPERA~~N
).NFREQUENTOPERAT,JN ,, ,
REAS~N:~~
REASQN:
~~~~~~U G: ~( ~
End of Section 4.0
SQN SQN BORON CONCENTR BORON CONCENTRATION ATION CONTROL CONTROL 0-SO-62-7 0-SO-62-7 1,2 1,2 Rev. 56 Rev. 56 Page 164 Page of 201 164 of 201 APPENDIX EE APPENDIX Page 1 of 18 Page10f18 REACTIVIT REACTIVITY Y BALANCE CALCULAT CALCULATION ION NOTE I1 One calculation is required for each major change. Calculation is an approximatio approximation n of required Boron change. Eyeball interpolation of graphs is expected.
NOTE NOTE 22 Dilution or Boration value for power change from P1 P 22 % power in time period T with rods 1 % to P P
moving from step position R 1 R2. (Subscript convention: 1I =current point, 22 ==target point)
R1 to R 2
[1] ENTER the following data:
DATA REQUIRED DATA Where To Get Current RCS Boron ppm Chem Lab or Estimate using Appendix 00 Chern Core Burnup MWD/MTU MWO/MTU ICS U0981 Current Reactor power % NIS or ICS Final Reactor power % As required for plant conditions Total Reactor Power Power change .6.% .6. Reactor power A Current and final Reactor Rate of Reactor power change %/hr As required for plant conditions Number Number ofof hours hours to to change change power power hr(s) hr(s) As required plant conditions required for plant lOS or ICS or MCR Board MCR Board Current Current Rod Rod Position Position steps steps number of Esti&iate number Estimate of rod steps required rod steps to required to Final Final Rod Rod Position Position steps steps Al and control .6.1 control and rod requirements withdrawal requirements rod withdrawal for power for change..
SQN SQN BORON CONCENTR BORON CONCENTRATION ATION CONTROL CONTROL 0-SO-62-7 0-80-62-7 1,2 1,2 Rev. 56 Rev. 56 Page 165 Page 165 ofof201 201 APPENDIX EE APPENDIX Page 22 of Page of 1818 CAUTION CAUTION Follow sign Follow sign conventions conventions explicitly. explicitly. (See (See Example Example Power Power Increase Increase and and Power Power decrease.)
decrease.)
[2] CALCULAT
[2] CALCULATE change inin boron E change boron concentration concentration by by performing performing the the following:
following:
Parameter Parameter Where To Where To GetGet Calculation Calculation Value Value Attached Power Attached Power Defect Defect Curves:
Curves: (negative (negative
~p POWER pcm PD pcm PD 1 1 pcm PD 2PD2 = pcm pcm
((a]
a] Ap POWERDEFECT DEFECT Unit 1:1: Figure Unit Figure 1,1, 2,2, or or 3 Ap L'lp POWER for for power power increase)
(current)
(current) POWERDEFECT DEFECT increase)
Unit 2:2: Figure Unit Figure 8,8, 9,9, or or 10.
10.
1Xenon1: From Xenon From ICS*
ICS* or or REACTF REACTF (either (either current current NOTE: Xenon NOTE: Xenon reactivity must be reactivity must be neciative negative (negative (negative conditions or conditions projection to or projection to initial initial condition).
condition). for rise inin for rise
[b] Ap
[b] ~p XENON XENON :
2Xenon2: From Xenon From ICS*ICS* or or REACTF REACTF pcm pcm Xenon Xenon (projection over period T).
time period over time T). pcm XE pcm 2XE2 - pcm XE 1XE 1 = conc) conc)
(projection -
add negative sign). (current)
[c] xp
[c] ~p RODS Attached Rod Attached Rod Worth Worth Curves:
Curves: pcm Rods 1 =
= (negative (negative RODS pcm Rods pcm 2 Rods 2 - Rods 1 pcm pcm for rod for Unit 1:1: Figure Unit Figure 4,4, 5, 5, oror 66 rod (current)
(current)
Ap insertion) insertion)
Unit 2: Figure 11, 12, 12, or 13.
or 13. L'lp RODS RODS Unit 2: Figure 11,
[d] Ap
[d] ~p POWER POWER DEFECT DEFECT +XENON XENON +RODS
+ (CHANGE IN RODS (CHANGE REACTIW DUE IN REACT1VY DUE TO TO POWER POWER DEFECT,DEFECT, XENON, XENON, AND AND RODS)
RODS) pcm pcm
+
[a]
lal pcm Ap pcm POWER DEFECT L'lp POWER DEFECT + + Fbi
[b] pcm tXp pcm ~p XENON XENON + + fcl
[c] pcm Ap pcm ~p RODS RODS = =
[e] ~p
[e] Ap BORON (CHANGE IN (CHANGE IN BORON BORON REACTIVITY)
REACTIVITY) pcm pcm BORON
. d1
[d] ~p pcm Lp POWER >>) XX (1)
(1)
Ai BORON
-- L'lp BORON
=
~
<- pcm XENON ++ RODS)
DEFECT ++ XENON POWER DEFECT RODS
[f] ~ppm BORON
[f] Appm BORON (CHANGE (CHANGE IN IN BORON BORON CONCENTRATION)
CONCENTRATION) (negative (negative for for dilution, dilution, positive for positive
(( [e]
Fel pcm Ap pcm L'lp BORON)
BORON) ÷ -;- (from
(
from Fig. (U-1) or Fig. 77 (U-i) pcm/ppm Boron pcm/ppm Fig. 14 or Fig. 14 (U-2)
(U-2)
Boron Worth)
Worth) = = ppm ppm boration) boration) for
[3]
[3] ENSURE independentl ENSURE independently verified by y verified by SRO8RO in accordance with in accordance Appendix J.
with Appendix J.
(N/A ifif performed (N/A performed by by an an SRO 8RO to to verify datadata provided provided by by Rx.
Rx. Eng)
Eng)
SQN SQN CONCENTRATION CONTROL BORON CONCENTRATION BORON CONTROL O-SO-62-7 0-SO-62-7 1,2 1,2 Rev. 56 Rev. 56 Page 166 of Page 166 of 201 201 APPENDIX EE APPENDIX Page of 18 Page 33 of 18 Example Power Increase Example Power Increase NOTE NOTE Typical values Typical displayed in values displayed example are this example in this are not not Unit and Unit specific, however, Cycle specific, and Cycle the following however, the example indicates proper example proper sign convention.
Current RCS boron Current boron 1000 ppm 1000 ppm burnup Coreburnup Core 3000 MWD/MTU Current reactor power 70%
Final reactor power 100%
100%
Total reactor power change 30%
Rate of reactor power change 5%/hr Number of hours to change power 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Current rod position 180 steps Final Rod Position 220 steps Reactivity Balance:
[a] !:lp Power Defect PPowerDefect == 1210 pcm PD1 -1720 1720 pcm PD2 510 pcm
= -510
[b] !:lp zp Xenon xenon == -2262 2262 pcm XE2 -(-2436) XEI (2436) pcm XE1 =
= +174 pcm
\
[c] !:lp
/xp Rods Rods == -10 10 pcm Rods2 - (-275)
Rodsi (275) pcm Rods1 ÷265 pcm
= +265
[d] Ap POWER OEFECT+XENON÷RODS 510 pcm ++ 174pcm
[d] L).PPOWERDEFECT+XENON+RODS=-510pcm 265 pcm == -71 174 pcm ++ 265pcm pcm 71 pcm
[e]
[e] L).p Ap BORON BORON = = -7171 pcm pcm x (-1)
(1) == ++ 71 pcm 71 pcm Change Change in in Boron Boron PPM: PPM:
[f]
[f] (+71)
(+71) pcm pcm Boron Boron -7÷ (-6.35)
(6.35) pcm/ppm pcm/ppm Boron worth == -11 Boron worth (dilution) ppm (dilution) 11 ppm
('
SQN SQN BORON CONCENTR BORON CONCENTRATION ATION CONTROL CONTROL 0-SO-62-7 0-SO-62-7 1,2 1,2 Rev. 56 Rev. 56 Page 167 of Page 167 of 201 201 APPENDIX EE APPENDIX Page of 18 Page 44 of 18 Example Power Decrease Example Power Decrease NOTE NOTE displayed in values displayed Typical values example are this example in this are not not Unit and Unit Cycle specific, and Cycle however, the specific, however, the following example indicates proper sign convention.
Current RCS boron boron 500 ppm 500 Core burnup 18000 MWD/MTU 18000 Current reactor power 100%
100%
Final reactor power 80%
Total reactor power change -20%
Rate of reactor power change -5%/hr
( Number of hours to change power 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Current rod position 220 steps Final Rod Position 200 steps Reactivity Balance:
[a] Ap Power Defect LPPowerDefect =
= 2630 pcm PD1 -2100 2100 pcm PD2 = +530 pcm
[b] APXenon PXenon =
= -;-3030 303 pcm XE2 -(-2884)
T
° (2884) pcm XE1 XEI = 146 pcm
= -146
[c]
[c] Ap.P Rods Rods == -220 220 pcm Rods2 - (-20) pcm Rods2 Rods 1 pcm Rods1 (20) pcm = -200 pcm 200 pcm Ed] ~p
[d] Ap POWER POWER DEFECT + XENON + RODS =+530 DEFECT+XENON.RQDS pcm +
+530 pcm pcm) +
(146 pcm)
+ (-146 + (-200 pcm) =
(200 pcm) = +184 pcm
+184 pcm
[e] ~p
[e] tp BORON BoRoN =+184
+184 pcm (1) pcm xx (-1) == -184 pcm 184 pcm Change Change in in Boron Boron -PPM:
PPM:
[f]
[t] (-184)
(184) pcmpcm Boron Boron -:- (-7.47) pcm/ppm Boron (7.47) pcm/ppm worth Boron worth == +25
+25 ppm (boration) ppm (boration)
SQN SQN BORON CONCENTR BORON CONCENTRATION ATION CONTROL CONTROL 0-SO-62-7 0-80-62-7 1,2 1,2 Rev.
Rev. 56 56 Page 168 Page 168 of of 201 201 APPENDIX EE APPENDIX Page 55 of Page of 18 18 Figure 11 UICI7 Figure U1C17 Power Power Defect Defect BOL BOl NOTE NOTE Use eye-ball Use interpolation between "eye-ball" interpolation between closestclosest parameter lines.
parameter lines.
UNIT I1 CYCLE 17 17 DEFECT - BOL POWER DEFECT-POWER SOL (150-4000 MWD/MTU MWD/MTU))
1800 1800 moo ppm 1000 ppm 1700 /
1700 -------
/
1600 1600 /
/
1400 ppm OO ppm 1500 1500
/ /
1400 1400 L/ 1//
ppm
/ L iSOC ppm lBOO 1300 1300
/
L /
/
1200 1200
/
1100 1100 L k v /
EE
.e 1000 0
0.
/
v L
<:5 1/
.21 900 900
/
<Il 0 / /
/ V
~
0 800 800
\ / /
CL
/ /
700 700
//
600 600
/ /
/4" 500 500
/ /,
/
400 400 /4"
/V, 300 300 :z /
/, ::
[:'
200 200 ~'
100 100 7'
)'
00 1/
o0 10 10 20 20 30 30 40 40 50 50 60 60 70 70 80 80 90 90 100 100 Power PtwerLevelLevel(%)
(%)
Reference:
Reference:
NOR NDR TableTable 6-23 6-23 to 6-27 to 6-27
SQN SQN BORON CONCENTR BORON CONCENTRATION ATION CONTROLCONTROL 0-SO-62-7 0-SO-62-7 1,2 1,2 Rev.
Rev. 56 56 Page 169 Page 169 of of 201 201 APPENDIX EE APPENDIX Page 66 of Page of 18 18 Figure 22 UICI7 Figure U1C17 Power Power Defect Defect MOL MOL NOTE NOTE Use eye-ball Use interpolation between "eye-ball" interpolation between closest closest parameter lines.
parameter lines.
UNIT I1 CYCLE UNIT CYCLE 17 17 DEFECT - MOL POWER DEFECT-POWER MWD/MTU))
(4000-16000 MWD/MTU MOL (4000-16000 2200 2200 400 ppm 400 ZZ7 ppm 2100 2100 /
v 2000 2000
/
/
1900 900 ppm 900 1900 EEZZ / /
ppm 1800 1800
/ /
1700 1700 / 1/
(
/ ppm 1400 ppm 1400 1/
1600 1600 /
.~/
1500 / /
1500 1400 1400 ZZEZ / ZZ
/
E 1300 ZZ2E / ZZ
/
u0 -
.e,
-S 1200 /
1200 "00
~ 1100 1100 /
CIl / /
0 1000 / ~
~0 1000
/ V a.. 900 900
/
/
800 800
/
700 / /
700 V
600 600
/ /
V 500 500 / /, '
7
/~.'
400 //'
400 ~,
300 300 4-
/:'
200 200 ZE.l- EZZZZ 100 100 f
o0 Y o0 10 10 20 20 30 30 40 40 50 50 60 60 70 70 80 80 90 90 100 100 FwerLevel Power (%)
Level (%)
Reference:
Reference:
NOR NDR TableTable 6-23 6-27.
to 6-27.
6-23 to
SQN SQN BORON CONCENTR BORON CONCENTRATION ATION CONTROL CONTROL 0-SO-62-7 0-80-62-7 1,2 1,2 Rev. 56 Rev. 56 Page 170 Page 170 of of 201 201 APPENDIXE APPENDIX E Page 77 of Page of 18 18 Figure 33 UICI7 Figure U1C17 Power Power Defect Defect EOL EOL NOTE NOTE Use eye-ball Use "eye-ball" interpolation between closest interpolation between closest parameter lines.
parameter lines.
UNIT CYCLE 17 UNIT I1 CYCLE 17 POWER DEFECT-POWER DEFECT - EOL EOL (16000-2122 (16000-21223 MWD/MTU))
3 MWD/MTU 3000 3000 ooppm ppm 2900 /
2900 2800 2800 2700 2700 /
500 ppm 500 ppm 2600 2600 /
2500 2500 IL 1000 ppm 1000 ppm 2400 2400 1. lL 1/
2300 2300 /
L 2200 /
2200 2100 2100 L 2000 2000 L 1900 1900 /
~ 1800 /
5 0.
1700 1700 -
/
/
=-0 1600 1600 /
.m<ll 1500 1500 0 1400 /
L.. 1400
<ll 3= 1300 1300 0 ~
0..
1200 1200
/
1100 1100 1000 1000 /.£.
900 900 /
800 /
800
/
700 700 / .
600 600 500 500 ty, 400 I' 400
~
300 300 //
200 /f' 200
~
100 100 00 00 10 10 20 20 30 30 40 40 50 50 60 60 70 70 80 80 90 90 100 100 Power Pbwer Level (%)
Level (%)
Reference:
NOR
Reference:
NDR Table Table 6-236-23 to 6-27 to 6-27
SQN SQN BORON CONCENTR BORON CONCENTRATION ATION CONTROL 0-SO-62-7 0-80-62-7 1,2 1,2 Rev. 56 Rev. 56 Page 171 Page 171 of of 201 201 APPENDIX EE Page 88 of 18 Page 18 Figure 44 UICI7 U1C17 Inserted Rod Worth BOL BOL NOTE "eye-ball" interpolation between closest Use eye-ball parameter lines.
UNIT1 CYCLE 17 UNITI 17 BOl INSERTED ROD WORTH (150-4000 MWDIMTU BOL INSERTED MWD/MTU))
00
~
.~
-100 v -
vr/ *17
-200
.r,;
-300 v -i7
-400 1/ .
-500 V.
/
-600 V vl/
/
1/
-700 E(.) -800
/
.2: 1/
.j
.c -900 1:: V
~ -1000
'I*
"C 0
0:: -1100
-1100 rk "C
Q) 0 1::
Q) -1200
-1200
//1'
=
.E 0
-1300
-1400
-1400 II '1.
1/ .i/' .
-1500
-1500 ril'
-1600 1/
-1600 t'/ .
-1700 l/'*i~*
-1700
-1800
-1800
-1900
-1900
-2000
-2000 o0 20 20 40 40 60 60 80 80 100 100 120 120 140 140 160 160 180 180 200 200 220 220 240 240 D Bank Steps DBank Steps Withdrawn (steps)
Withdrawn (steps)
--100% 100% Power Fw er -
75%
75% Fbwer" Power " " " 50%
- - - - Pow er -
50% Fbwer " -25%
- Pow er -
25% Fbwer
" " 0% POw e
Reference:
Reference:
NOR NDR Table 6-34.
Table 6-34.
SQN SQN BORON CONCENTRATION CONTROL BORON CONCENTRATION CONTROL 0-SO-62-7 0-80-62-7 1,2 1,2 Rev.
Rev. 56 56 Page Page 172 172 of of 201 201 APPENDIX EE APPENDIX Page 9of18 Page 9 of 18 Figure 55 UICI7 Figure Inserted Rod U1C17 Inserted Rod WorthWorth MOL MOL NOTE NOTE Use eye-ball Use interpolation between "eye-ball" interpolation between closest closest parameter lines.
parameter lines.
UNIT CYCLE 17 UNIT I1 CYCLE 17 MOL INSERTED MOL INSERTED ROD ROD WORTH (4000-16000 MWDIMTU)
WORTH (4000-16000 MWD/MTU) 00
-100
-100 EE EE E EE E E H E W 1 1/.
0[f
.~
-200
-300 f
[I
-400 k' L
-soo
-500
-600 v v
-700 v'
-800 V ,
/
EE
<.) k'
-900
.e:
.c -1000
~
'1/
~ -1100 "t:J 0
a:: -1200 "t:J Q)
~ -1300
.5 Q)
G)
I/)
0
.E -1400
-1400 I ..
I . II .
-1S00
-1500
-1600
-1600
-+
[I
[I' .
-1700
-1700
.1/
-1800
-1800 /1* .
-1900
-1900
/1/
-2000
-2000
-2100 u [U [ t[U I t[U [1 JU0 T iuHb
[qL I-I ~L I ~U T
[I')U 2
,~I~l Lb
~'FU 2U 1£' o
-2100
-2200
-2200 oDBank Bank Steps Steps Withdrawn Withdrawn (steps)
(steps)
--100% 100% Power-Fwer -
7S%Power**
75% Fwer- - - SO%Power-*
- - - 50% Ftwer -2S%Power-**
- 25% RDwer . - 0% ADwerl O%Powe
Reference:
Reference:
NOR Table 6-34.
NDR Table 6-34.
SQN SQN BORON CONCENTRATION BORON CONCENTRATION CONTROL CONTROL 0-SO-62-7 0-SO-62-7 1,2 1,2 Rev.
Rev, 56 56 Page 173 Page 173 of of 201 201 APPENDIX EE APPENDIX Page 10 Page 10 of of 18 18 Figure 66 UICI7 Figure U1C17 Inserted Inserted Rod Rod WorthWorth EOL EOl NOTE NOTE Use eye-bail Use interpolation between "eye-ball" interpolation between closest closest parameter lines.
parameter lines, UNIT I1 CYCLE UNIT CYCLE 17 17 EOl INSERTED EOL INSERTED ROD ROD WORTH (16000-21223 MWDIMTU)
WORTH (16000-21223 MWD/MTU)
-100
-200
-300
-400 v'
r fl.',
'J';
/,I,
["
-500 4, 1/
.. 00 1/
V 'II
-700 V
-BOO
!/ V
-1000 V ,
v
-1100
,'I I-v
-1300 j t/J:
-1400
-1400 /
I :;
I - -
-1500
-0500 -- - - - 'f -
iI Iii ' / it'
-1600
-1600
-1700
-1700
- - VI/-+
I I
-1800
-1800 - -
-1900 /11
/ ,
1900
-:1_ _--
-20ao
-2000 --.
-2100
-2100 I. 1-.
- H 2 0 2 2 210
'I
-2200 1
-2300 D0 Bank S to5. W B nk Steps N itbdrawn (tp.)
it6W (steps)
--100% 100% PowerPower - - 75% Power - - . 50%
75% Power* - - -- Power -
50% Power - -25%
Power -
25% Power - - 0%
- - 0% Power Power
Reference:
Reference:
NOR NDR Table Table 6-34,6-34.
Cl)
SQN 1,2 OJ 0 0 c ~
1:: Eu E Z Boron Worth (pcmlppm) .e: CI.
0
--1 i I I 4 I ) ) ) ) 0) ) ) cLI) ) I
-7.5 -7.4
-7.3 -7.2 -7.1 -7.0 -6.9
.c -6.8
- a. -6.7
- C 0 C -4
-6.6
- 0) -6.5
( .
-6.4 -6.3 C.) -6.2 -6.1 NOTE ni 0
1 0*
200 w cn 0 o i- (D 0
- - BOL (0-4000) 400 o
- i:j m
3 (D
CD<
.i 0
Z 2 0 o I m c Z
- Z CD (_)
I C)
- WO) m o 0 600 D I ° (p ii> Z Use "eye-ball" interpolation between closest CD D UJ4 -
I 0 APPENDIX E z CD *1 ci 800 0
80 -I Z Z H
(p I IIIIIIIIILIIILIIHIIIIIIIHIHIIII CD Page 11 of 18 0
° I 11111 Ii I Ii WH 0 tv10L (4000-16000) 9 I I II I ii Iii I I I i II I I II I III I II II ii iii I I
Boron Concentration (ppm) UNIT 1 CYCLE 17 i 8 ii I 1000 It H I H 111111111111111111 Ii Li 11111 l::::: CD
° I II liii H (p 0 I I LIII II I I I IllIlIlIlli II Ii I liii 11111 D
Reference:
NOR Table 6-7 HI ci 0 11111 BORON CONCENTRATION CONTROL DIFFERENTIAL BORON WORTH (pcm/ppm) 1200 CD 0 i i C,)
parameter lines.
I I III Hi I I I I I ii I I I N I I II Figure 7 U1C17 Differential Boron Worth I I Ii 11111 o I I i I
II I II I I I111111111 I111I1 I I I I II II I I I I I I I II I II I II I II I1111 II *IlIlllII IIjIiIIIiIIIiIIiIIiII IltI 91 II,Il III II 1400 Olillil IlIIIi IIIII1II1IIIIII IHIHI I °tHIi I huh lii uihuiiiuii Ili, ci) CD )...
- - - - - EOL (16000-21223)
I <V) 0-80-62-7 II vO I iIHIIi li-Ililihl iiuuhitiIiIiiiiHIiHIIhHIHM I C-O) 1600 8 Rev. 56
-I, N) 0 Page 174 of 201
SQN SQN CONCENTRATION CONTROL BORON CONCENTRATION BORON CONTROL 0-SO-62-7 0-80-62-7 1,2 1,2 Rev.
Rev. 56 56 Page 175 Page 175 of of 201 201 APPENDIX EE APPENDIX Page Page 12 12 of 18 of 18 Figure 88 U2C16 Figure U2C16 Power Power DefectDefect BOL BOL NOTE NOTE Use "eye-ball" interpolation between closest parameter lines.
Use eye-ball lines.
UNIT 22 CYCLE 16 UNIT 16 DEFECT - BOL POWER DEFECT- SOL (0-4000 (0-4000 MWD/MTU)
MWD/MTU) 1900 1800 1800 O0ppm lOOO ppm L
1700 1700
/
1400 1400 ppm ppm 1600 1600 /
/
/
1500 1500 7
1/
000ppm lBOO ppm 1400 1400 / /
V /
1300 1200 7ZZ
/ v
/
1200 1/ /
/ V E2 1100 V/ /
-e
()
0 0.
///
u0 1000 V/
<I)
/// /
ci) 00 900 1/ v7
~
00 L /
c.. 800 - -
V ,,
700 / i/
600 z /
/
\ //
500 /
/ /,'
// '
400 400
~,
300 V/'
300
.!'iI'
~'
200 200
//
~
100 100
/'
o0 1/
o0 10 10 20 20 30 30 40 40 50 50 60 60 70 70 80 80 90 90 100 100 Power Level Power (%)
Level (%)
Reference:
Reference:
NOR NDR TableTable 6-23 6-23 to 6-27, Total to 6-27, Power Defect Total Power Defect
SQN SQN BORON BORON CONCENTRATION CONCENTRATION CONTROL CONTROL 0-SO-62-7 0-SO-62-7 1,2 1,2 Rev.
Rev. 56 56 Page 176 Page 176 of of 201 201 APPENDIX EE APPENDIX Page 13 Page 13 ofof 18 18 Figure Figure 99 U2C16 U2C16 Power Power Defect Defect MOL MOL NOTE NOTE "eye-ball" interpolation between closest parameter lines.
Use eye-ball Use UNIT 22 CYCLE 16 16 POWER DEFECT-DEFECT - MOLMOL (4000-16000 MWD/MTU)MWD/M1U) 2200 2200 2100 2100 400 ppm 400 ppm
/
2000 L
1900 IL Z/ 900 ppm 900 1800 1800 /7_ /
/
1700 / /
ppm 1400 ppm 1600 L /
.L 1500 / /
V 1400 / 1/
V L E 1300 1/
1/
S 1200 /
/
/
0
~ 1100 0
Q) 1/ /
1000
~
0
/ /
a.. 900 /
/
/
800
/V 700 //
/
600
/
-/ '
500
// '
400 /'
300
//
200 200
- z:z:z:
/~
11' 100 100 00 / 7FEEE
/
o0 10 10 20 20 30 30 40 40 50 50 60 60 70 70 80 80 90 90 100 100 Power Power Level (%)
Lev& (%)
Reference:
Reference:
NDR NDR Table 6-23 to Table 6-23 to 6-27, Power Defect Total Power 6-27, Total Defect
SQN BORON CONCENTRATION CONTROL 0-SO-62-7 0-80-62-7 1,2 Rev. 56 Page 177 of 201 APPENDIX E E Page 14 of 18 Figure 10 U2C16 Power Defect EOl EOL NOTE Use "eye-ball" eye-ball interpolation between closest parameter lines.
UNIT 2 CYCLE 16 POWER DEFECT DEFECT-- EOl EOL (16000-21355 (16000-21 355 MWD/MTU) 3000~~~--~~~~~~~~~~--~~~~--~~~~~
3000 oCppm ppm 2900 E Z Z Z Z 2900t=~=t==~t=~=t~~t=~=t~==t=~=t~==t=i==t=+~
2800+--r-+--~+--r-+~~+--r-+~--+-~-+~--r-~-+-fr~
2800 2700 +--r-+--~+--r-+~~+--+--+~--+-~-+~--r-~-t7/'--t-----715OOppm 500 ppm 2600+=~=+~==~+=~=+~==~+=~=+=+==~+=~=t;4~~
2600 2500 2500 +--j--+--f---1--j--+---1f--+--I--+_I--+--I--j-_I--+--,f--j-:--'-t~1DOO ppm oooppm 2400t=~=+~==~+=~=+=+==~+=~=+=+==~+=~=t~~~
2400 2300+--j--+--f---1--j--+---1f--+--I--+_I--+--I--j-_I~/rr~*~~"+-~
2300 2200 2200+--j--+--f--+--j--+---1f--+--I--+_I--+--I--+-/~-b~~~+-+-~
2100+--r-+--~+--r-+~~+--+--+~--+-~-b/~~/r--T--+-+~
2100 _4_7_;-___
2000+--j--+--f--+--I--+---1f--+--I--+_I--+-"/~~~'~_I_-+_+~
2000 1900t=~=+==~+=~=+~~+=~=+~==~/4=;t~~t=i==t=+~
1900 -
1800+--r-+~~+--r-+~~+--+--+~--~~-+~--r-~-+-+~
1800 o 1700+--j--+---1f---1--I--+---1f--+--I--+_I/~/7~~~+_-I--+-+--+-+-~
5E 1700
~ 1600 1600t=~=t~~t=~=t~t=t=~=t=/A=/~~==t=~=t=+==t=+=~
~ 1500+_-j--+---1f--+--I--+---1f--+_-I-~1/~~"+--I--+-I--+-_I_-+_+~
1500 , -
1400t=~=+~t=+=~=+~==+=~L~~==+=i==t=4==t=i==t=+~
1400 j
o 1300+--j--+---1--+__j_-+---1--~~/~/~-I--+--I--j--I--+--I--j-_+~
ZEZZZZE7EEZZZ___
1200+_-I--+---1--+--I--+---1-,~/~~_-~+--I--j--+--+--I--r-+--+-+-~
1100+=~=+====t=~=+==~/~~==+=i==+=4==t=i==t=i==t=+=~
1100 1000+--j--+~--+__j_-+/~/~~_-j--I--+--I--j--I--+--I--j--+--+-+-~
1000 900t=+=~~=+=+~t=~t=+=~~=t=+=4==~~+=~~~
900 ---- -
800+--j--+~--+_~/~~~--+-_j__+-I--+_-I--j-_I--+-_I_-r_+~
800 700 741 700+--I--+---1--+7~~-+---1--+_-I--+-I--+-_I_-+-I--r_+--r_+~
600t=~i=~~:+/-t~==~t=t=i=~=t=+=i==~~+=+=~~
600 500 500 t-=--i-=----t+--...,.g-lrh~/.!..-_.:.+f--_-l+-_--t_-_-l+-_--t_-_-l+-_--t_-_-l+--_--t_-_-l-;-_--t_-_-l+--_-_t----l-;-~_t---+t_--=1 40°t=4=~ft=4==~t=4=~=t=+~==t=+=~~=+=4==~~
300+-_j_~~--+__j__+~--+__j__+-I--+__I_-+_I--r__I_-r_+~
-1/1 200 o
010 10 20 30 40 50 6060 70 80 90 100 Power Level (%) (%)
Reference:
NOR NDR Table 6-23 to 6-27, Total Power Defect
SQN BORON CONCENTRATION CONTROL 0-SO-62-7 1,2 1,2 Rev. 56 Page 178 of 201 APPENDIX E E Page 15 of 18 18 Figure 11 U2C16 Inserted Rod Worth BOL NOTE "eye-ball" interpolation between closest parameter lines.
Use eye-ball UNIT 22 CYCLE 16 16 BOL INSERTED ROD WORTH (0-4000 MWD/MTU) MWDIMTU) 0
\?
-100 11 rh
'/ :
-200 v "'~
7':
-300 - - -
vI' or:
1/
-400 - - - - - -
vi, 4 - - - -
-500
-500 - - - -
// - _
-600 - - - - - - - -
//1'
/
-700 -- - - - - -
E E -
u 0
- 'L Co -SOO
-800 - - - - -
..c :Ii' t
-900 900 'v
~ I, "C
0 -1000 /"
- 1,
- -1000 - -- - - - -
0::: - - -- - -- - -
"C ',1/
Q) -1100 t
Q)
II) , ,
.E -1200
.E-1200 "
d
-1300 ~i,
~:ij'
-1400 I~';
-1500
!~
~
-1600 f
!Y
-1700
-1800
-1S00
-1900 o0 20 40 60 SO 80 100 120 140 160 180 1S0 200 220 240 oD Bank Steps Withdrawn (steps)
--100% 100% Fbwer Power -
- 75% FbwerPower - - - - 50% Fbwer
- - - - Power - 25% Power -
- -25%
- - - 0% Fbwe
- - Powe
Reference:
NOR NDR Table 6-34, HFP Integral Rod Worth as a function of Steps withdrawn and burnup for Banks CD, CC, CB in overlap.
SQN BORON CONCENTRATION CONTROL 0-SO-62-7 1,2 Rev. 56 Page 179 of 201 APPENDIX E Page 16 of 18 Figure 12 U2C16 Inserted Rod Worth MOL NOTE eye-ball interpolation between closest parameter lines.
Use "eye-ball" UNIT 2 CYCLE 16 MOL INSERTED ROD WORTH (4000-16000 MWD/MTU) 0
- 1j:I: E~
dJ
-100 - - - - - - - - - - - - - -
~'
- - - - - - - - - - j- /.
-200 -- - -- -- - -
j- v. n--
.'1 - --
-300
-300 t*.
v
/
-400
-400 - -- - ----*
-[/
/
-500
-500 - -- - --- -
-600
-600 - -
- -; I*
/ ... --- --
-700 -
E-800-C..l -SOO -- -
.e: .'1/.
.c -900 'l'4' 1: I//'
0
?: -1000 - - . - - - - -
.1 i,1 "0::0o I. /:
-1100 -1100 - -- - 1/ . -- -- -- -
"1:
0 (I)
(I) -1200 - -
Vitj .
U, 1/1 - - -- - --
.E
-1300 -1300 - -- 1:/.' - -- - --
- -- I* I, -- -- -
/._ -
-1400 ~
~
-1500 / ,
/".
-1600 -
I~**I
-1700 d
',f
-1S00
-1900
-2000 o0 20 40 60 SO 80 100 120 140 160 1S0 180 200 220 240 D Bank Steps Withdrawn (steps)
D
--100% 1w er - 75% Power-100% Power- Fw er -- -25%
Rw er - -- -- -- 50% Power- Pw er -- -- 0% Powe 25% Power- Pow e
Reference:
NOR NDR Table 6-34, HFP Integral Rod Worth as a function of Steps withdrawn and burnup for Banks CD, CC, CB in overlap.
SQN SQN BORON CONCENTRATION BORON CONCENTRATION CONTROL CONTROL 0-SO-62-7 0-SO-62-7 1,2 1,2 Rev.
Rev. 56 56 Page Page 180 180 of of 201 201 APPENDIX E E Page 17 Page 17 of 18 18 Figure 13 Figure 13 U2C16 Inserted Inserted Rod Rod Worth EOl EOL NOTE NOTE Use "eye-ball" Use eye-ball interpolation interpolation between between closest closest parameter parameter lines.
UMT 22 CYCLE UNIT CYCLE 16 16 EOL INSERTED EOL INSERTED ROD WORTH (16000-21355 ROD WORTH MWD/MTU)
(16000-21355 MWD/MTU) 0 L
If.;
-100
/If
-200 1/ 1, I/,Y
-300
-400
-500
/
-600 I
V
-700 V
-800 E E -I u
0 -900
.::: /;-
-=t -1000 I
~ !
I-c 0::
-c t
4>
4>
.E 0
en
-1100
-1200
-1300
-1400 \ I I ~
11/
hJ'
-1500
,'I.
I,
-1600 I
-1700 Ir
-1800 rI'
, II
-1900 7}(
-2000 r;]/
-2100 00 20 20 4040 60 60 80 80 100 100 120 120 140 140 160 160 180 180 200 200 220 220 240 240 D Bank Steps DBank Steps Withdrawn Withdrawn (steps)
(steps)
--100% R:>wer -
100% Power -
75% R:>wer - - - - 50%
75% Power - - - - R:>wer -
50% Power -- - 25%
- R:>wer -
25% Power -- - 0%
- R:lwer 0% Power
Reference:
NOR Table
Reference:
NDR Table 6-34,6-34, . HFP
. Integral Rod HFP Integral Rod Worth Worth as as aa function of Steps withdrawn of Steps withdrawn and and burnup for Banks burnup for Banks CD, CD, CC, CC, CB CB in in overlap.
overlap.
di 0 CNCDO SQN Q2 0 0 z BORON CONCENTRATION CONTROL C) 0 z Ui 0 z I H 0 z C) 0 z I 0 -J 0-SO-62-7 1,2 Rev. 56
> C)
Q) ( (0LO- 0 Page 181 of 201 APPENDIX E Page 18 of 18 CO cD Figure 14 U2C16 Differential Boron Worth I- CD C) ci) CU OC z 0 UI D LG)
- G) O/) -C NOTEH Use "eye-ball" interpolation between closest parameter lines.
Cl) ci)
L 0 C 0 °G) (_) 0 E a) ci) 00
>-z -JO UNIT 2 CYCLE 16 - CD IJJ U
U wz DIFFERENllAL BORON WORTH (pcm/ppm) 0 C1 I a E 0
a E
-6.1 C
-6.2 C)
C N
C)
-6.3 C
-6.4 CD F
MOL
-6.5 CD C
-6.6 CD C
-6.7 C-(0 CD
-6.B (wddjw3d) 11J uojog E
0.
CD
~
u -6.9 0)
CD S
~ -7.0 c:
e0 ell
-7.1
-7.2
-7.3 C- C F El I
-7.4 EOl
-7.5 C. CC)
-7.6 CD 1FF C
C-
-7.7 C
C.
-7.B U) 0 BOO o 0 1200 8 1400 1600 8
CD 1000 8
0 0 200 0
0 C) 400 600 0 0 CD C
0 0
CD 8 Boron Concentration (ppm)
U)
C)
C CU C a.
C) CD
- - BOl (0-4000) - - rvDl (4000-16000) - - - - EOL (16000-21355) 0 0 0 8 0 0 0 0 0
0 U, CD CD 11
Reference:
NOR Table 6-7, HFP Differential Boron Worth ci) ci)
C)
C z U H CO (0
ci) 0 U U C ci) 4-, cci CoC 0
L.
0 0t -c
Surveillance Task Sheet (STS) c Order: SI Key: 0-SI-OPS-068-1 37.0 Procedure: O-SI-OPS-068-137.0 Train/Loop:
Train/Loon: Unique Data:
we:
I Hie: Reactor Coolant system Water Inventory .--
- I io4y
/6b4'L AJoj NOi-:..J Perf Sect: OPS Test Reason Daily Unit: 0 /Authorization to Begin: SRO
/Authorization Date Time LO04i o4 / tJo~
j\J Data Sheet: One Complete copy Start Date Time Completion Date Time Issued: Extension:
Frequency: NONE FO: NN TS: Y ASMEXI: N N Mode:
sx 1,2,3,4,5,6 Applicable Modes: 1,2,3,4,5,6 Perfor Modes: 1,2,3,4,5,6 Reauired:
Clearance Required: Sched. Rec.#: Drv Dry Cask Storaqe:
Storaae:
Subsequent Reviews: Initial Date Was this a a Complete or Partial Performance?
Remarks below)
(Explain Particial in "Remarks" Cognizant Engr Comrlete rF 1 Complete 1 Partial rF Cem Admin Reviewer Req/ISFSI CoC/ODCM/Fire Prot Were all Tech Spec/Tech ReqllSFSI Req/AMSAC acceptance criteria satisified?
Yes[r 1 Yes No[r 1 No N/A[r 1 N/A 1
Were all other acceptance criteria satisfied?
Yes r 1 Yes[ No((
j No 1 N/A[r
] N/A Req/ISFSI CoC/ODCM/Fire Prot If all Tech Spec Tech ReqllSFSI LCOITRJODCM Req/AMSAC were not satisfied, was an LCO/TRlODCM
((Explain in "Remarks")
Action required <<Explain Remarks)
I(
\ "
Yes(( 1 Yes No((
] No 1j N/A((
N/A Print Print Name Performers Siqnature Test Performer's Signature Initial Lnitial Section terO rfg)( J1j), (j7 k4 /),4 .!2t.
cC)i (zdt,-- Q0.-Jn 'j nfJ6h1 ZLdC-I 2 Director Test Direct6r Lead Performer D8tT Datd I I I '
.4 Acceptance Criteria Review:SRO Date Time (ASME Xl Sls require review within 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br />)
XI Sis Independent Reviewer PERMANENT COMMENTS: REMARKS:
JPM43-2 JPM43-2 Manual Manual Page Page 11 of of 99 Rev.
Rev. 00 SEQUOYAH NUCLEAR NUCLEAR PLANT PLANT PERFORMANCE MEASURE JOB PERFORMANCE MEASURE JPM 43-2 Manual ROA2 PERFORM REACTOR COOLANT SYSTEM INVENTORY (137.0)
WATER INVENTORY (1 37=0)
PREPARED!
PREPARED!
REVISED BY: Datel Date!
VALIDATE VALIDATEDD BY:
- Datel Date!
APPROVED BY: Datel Date!
(Operations Training Manager)
CONCURRE CONCURRED:D: ** Datel Date!
(Operations Representativ Representative) e)
- Validation not required for minor enhancement enhancements,s, procedure Rev changes that do not affect the JPM, or individual step changes that do not affect the flow of the JPM.
JPM.
JPM43-2 JPM43-2 Manual Manual Page 22 of9 Page of 9 Rev. 0 Rev.O NUCLEAR TRAINING NUCLEAR TRAINING REVISION!USAGE LOG REVISION/USAGE LOG Revision Revision Description Description Pages Pages Prepared/
Preparedl Number Number Of Revision Of Revision VV Date Date Affected Affected Revised By:
Revised By:
00 New JPM New JPM toto perform perform manual manual calculation calculation ofof ReS RCS YY 1/29/10 1/29/10 All All M.
M. Hankins Hankins water inventory, water inventory, and and toto be be performed performed inin aa classroom.
classroom.
Vv -Specify Specify ifif the the JPM JPM change will require change will require another another validation validation (Y (Y or or N).
N).
See cover sheet for criteria.
See cover sheet for criteria.
JPM43-2 JPM43-2 Manual Manual Page Page 30f9 3 of 9 Rev.
Rev. 00 SEQUOYAH SEQUOY NUCLEAR PLANT AH NUCLEAR PLANT ROISRO ROISRO JOB PERFORMANCE JOB PERFORMANCE MEASURE MEASURE Task: Perform Task: Perform RCS RCS Leakage Leakage Calculation Calculation (0-SI-OPS-068-137.0)
(0-Sl-OPS-068-1 37.0)
JAITAtask#:
JA/T 0020010201 A task # : 0020010201 (RO)
(RO)
KIA Ratings:
KIA Ratings: 2.2.12 2.2.12 (3.7/4.1))
(3.7/4.1 002A4.01 002A4.01 (3.5/3.8)
(3.5/3.8) 002K405 002K405 (3.8/4.2)
(3.8/4.2) 002K504 002K504 (3.1/3.4)
(3.1/3.4)
Task Standard:
Task Standard:
Upon completion Upon completion of this task, of this task, the the operator operator will will have have correctly correctly determined determined RCS RCS leakage leakage per per O-SI-OPS-0-SI-OPS-068-137.0 and notify 068-137.0 and notify the SRO SRO of of Tech Tech Spec Spec and and EPIP EPIP requirements.
requirements.
Evaluation Method:
Evaluation Method: Simulator _..:...X-'----_
Simulator X In-Plant In-Plant _ __
=======================================================================
Performer:
Performer:
NAME Start Time Time _ __
Performance Rating: SAT UNSAT Performance Time Time _ __
Finish Time Evaluator:
Evaluator:
~~--------/~-==
SIGNATURE SIGNATURE I
DATE
======================================================================
COMMENT COMMENTS S
JPM43-2 JPM43-2 Manual Manual Page Page 44 of of 99 Rev.
Rev. 00 SPECIAL INSTRUCTIONS SPECIAL INSTRUCTIONS TO TO EVALUATOR:
EVALUATOR:
- 1. Any UNSAT
- 1. Any UNSAT requires requires comments.
comments.
- 2. Ensure calculator
- 2. Ensure calculator isis available available for for operators operators use.
use.
- 3. A
- 3. A copy copy of of 0-SI-OPS-068-137.0 O-Sl-OPS-068-1 37.0 and previously performed and previously performed procedural procedural steps steps must must be be provided provided to to the the operator for operator for task task performance.
performance.
Validation Time:
Validation Time: CR.
CR. 20 minS' 20 mins Local Local _ _ _ __
ToolslEquipmentlProcedures Needed:
Tools/Equipment/Procedures Needed:
O-SI-OPS-068-1 37.0 0-SI-OPS-068-137.0
References:
References:
Reference Title Rev Rev No.
1.
- 1. 0-Sl-OPS-068-1 37.0 0-SI-OPS-068-137.0 Reactor Coolant System Water Inventory 22 2 TS Specifications Technical Specifications Latest
==========================================================================
JPM43-2 JPM43-2 Manual Manual Page 50f9 Page 5 of 9 Rev.
Rev. 00 READ TO READ TO OPERATOR OPERATOR DIRECTIONS TO DIRECTIONS TO TRAINEE:
TRAINEE:
II will will explain explain the initial conditions, the initial conditions, and and state state the the task task to to be performed. II will be performed. will provide provide initiating initiating cues.
cues. When When you you complete the task successfully, the complete the task successfully, the objective objective for for this this job job performance performance measure measure will will be be satisfied.
satisfied. Ensure Ensure you you indicate to indicate to meme when when you understand your you understand your assigned assigned task. task. To To indicate indicate that that you you have have completed completed youryour assigned assigned task return task return the handout sheet the handout sheet II provided provided you.
you.
INITIAL CONDITIONS:
INITIAL CONDITIONS:
- 1. Unit-1
- 1. Unit-i is is inin MODE MODEl. 1.
- 2. The
- 2. The RCSRCS leakage leakage surveillance surveillance required required by by T.S.
T.S. 4.4.6.2.1 4.4.6.2.1 is is due due this this shift shift and and the ICS the ICS com computer puter is not available is not available The off going
- 3. The going crew initiated initiated performance performance of of 0-SI-OPS-068-137.0, 0-Sl-OPS-068-1 37.0, Section 6.1 and AppendixAppendix C C are complete.
Appendix 0D is complete through is complete through section section 1.4 1.4
- 4. SG leakages SG#1 SG#2 SG#3 SG#4 3.2 gpd 2.2 gpd 2.3 gpd 4.8 gpd S1-50 and SI-137.5
- 5. SI-50 SI-i 37.5 were completed last nigth at 2300.
- 6. Chemistry supervisor reported no additions or samples taken from the RCS during the selected performance period.
- 7. CLA Levels initial and final are as follows:
CLA LI INITIAL FINAL 11 63-1 63-129 29 7692 7692 7692 22 63-1 63-109 09 7677 7677 33 63-89 63-89 7672 7672 7672 7672 44 63-89 63-89 7680 7680 7680 7680
- 8. CCPIT/HUT
- 8. CCPIT/HUT leakage leakage and and other "other" leakage leakage is is 00 gpm gpm 9.
- 9. DoDo allall calculations calculations to to three three decimal decimal places, places, or or to to 1/1 000.
1/1000.
10.
- 10. Data Data collected collected for for performance performance of of this this leak rate isis documented leak rate documented in in Appendix Appendix C C and and was was collected collected over over 124 124 minutes minutes INITIATING INITIATING CUES: CUES:
You You are are the the Unit-I Unit-1 CR0CRO and and have have been been directed directed to to complete complete the the performance performance of of 0-SI-OPS-06 0-SI-OPS-068-137.0 8-1 37.0 Appendix Appendix D "0" andand Section Section 6.1 .1 through 6.1.1 step 8.
through step 8.
JPM43-2 JPM43-2 Manual Manual Page 66 of9 Page of 9 Rev.
Rev. 00 e,-E r 1.: _SAT SAT STEP Operator begins .
i i.: Operator begins with
. with Appendix
. Appendix D, D, Step Step 1.51.5 Total Total RCSRCS Leakage:
Leakage:
_UNSAT UNSAT STANDARD: Operator STANDARD: Operator continues continues at at step step 1.5 1.5 ofof Appendix Appendix DD and and Critical Critical Step Step totals leakage totals leakage from from steps steps 1.1 1.1 (VCT)
(VCT),, 1.3[3]
1 .3[3] (PZR)and (PZR)and 1.4 1 .4 RCS RCS TempTemp Corr Corr (1.46 ++ 0.031 (1.46 0.031 ++ -0.066
-0.066 == 1.425 1.425 GPM)
GPM)
Start Start Time Time STEP 2.:
STEP 2.: 2.1 Pressurizer 2.1 Pressurizer ReliefRelief Tank Tank _SAT SAT PRT Leakage =
PRT Leakage Final Volume
= Final Volume - Initial Initial Volume Volume Delta Time Delta Time
_UNSAT UNSAT STANDARD: Operator STANDARD: Operator obtains obtains volumes volumes thatthat were calculated calculated in Appendix "C" in Appendix C Section Section 6.0 6.0 and determines and determines the the PRT PRT leakage leakage to to be be Critical Critical Step Step 0.242 GPM = (8622 --8592)! 124.
8592) / 124.
STEP 3.:
STEP 2.2 Reactor Coolant Drain Tank _SAT SAT RCDT Leakage = = Final Volume - Initial Volume delta time
_UNSAT UNSAT STANDARD: Operator obtains volumes that were calculated in Appendix "C" STANDARD: C Section 7.0 and determines the RCDT leakage to be Critical Step Step 0.033 = / 124.)
= (85.4 - 81.3) /124.)
STEP STEP 4.: 2.3 Steam Generator _SATSAT STANDARD STANDARD:: Operator utilizes information provided in in the initial conditions or contacts Chemistry Chemistry _UNSAT UNSAT NOTE NOTE 1: 1: SIG SIG leakages leakages from from initial initial conditions conditions are are as as follows:
[a] SG 13.2 GPO Critical Step Critical Step
[a] SG 1=3.2 GPO
[b]
[b] SG SG 2=2.2 2=2.2 GPDGPO
[c] SG 3=2.3
[c] SG 3=2.3 GPD GPO
[d] SG 4=4.8
[d] SG 4=4.8 GPO GPO NOTE NOTE 2:2: Per Per initial initial conditions, conditions, Sl-50 and SI 51-50 and 137.5 were 51137.5 were completed completed yesterday yesterday at at 2300.
2300.
STANDARD STANDARD: : Operator Operator obtains obtains SG SG leakages leakages from from initial initial conditions:
conditions:
Performs Performs calculation calculation and and determines determines Total Total SG leakage ==.3.2 SG leakage .3.2 ++ 2.2 2.2 ++ 2.3 4.8 = 12.5 2.3 ++ 4.8 GPD =0.009 12.5 GPD 0.009 1440 mm/day 1440 min/day Records Records performance performance times times for for Sl-50 SI-50 andand SI-I 37.5, from SI-137.5, from initial initial conditions conditions
JPM43-2 JPM43-2 Manual Manual Page Page 7of9 7 of 9 Rev.
Rev. 00
~--"-
STEP 5.:
STEP 5.: 2A Cold 2.4 Cold LegLeg Accumulators Accumulators - SAT SAT NOTE:
NOTE: Operator should Operator should use note and use note and determine determine CLA CLA leakage leakage can can be be marked marked - UNSAT UNSAT N/A. IfIf calculation N/A. calculation is is performed, performed, result result should should be be 00 GPM GPM since since the the start start and end and end levels levels of of all all accumulators accumulators remained remained constant.
constant.
STANDARD: Operator STANDARD: Operator determines determines CLA CLA leakage leakage isis either either not not applicable applicable andand N/A's N/As the the step step or records or records zero.
zero.
STEP 6.: 2.5 Other 2.5 Other identified identified leakage leakage - SAT SAT NOTE:
NOTE: Operator should Operator should use use note note and and determine determine other other leakage leakage can can bebe marked marked N/A or utilize N/A utilize initial initial condition condition that states no no other other leakage.
leakage. - UNSAT UNSAT STANDARD: Operator STANDARD: Operator determines determines "other" other leakage leakage is is either either not not applicable applicable andand N/A's N/As the the step or records zero.
STEP 7.: 2.6 Total Identified Leakage -
SAT NOTE:
NOTE: Operator should use initial conditions to determine that the CCPIT/HUT CCPITIHUT -
UNSAT leakage is zero.
Critical Step Total Identified Leakage =PRT + RCDT + SG ÷+ CLA +
Total Identified + CCPIT/HUT + + OTHER TIL == 0.242 + 0.033 + 0.009+ 0 + + 0 +0 = = 0.284 STANDARD: Operator totals the individual contributions to total leakage and determines identified leakage to be 0.284 0284 GPM.
STEP 8.: 3.0 3.0 Unidentified leakage -
SAT SAT Unidentified leakage ==Total Leakage -Identified Unidentified Identified leakage leakage UNSAT UNSAT UL =1.425 - 0.284 UL1.4250 =1.141 gpm
.284=1.141 gpm Critical Step Critical Step STANDARD:
STANDARD: Operator Operator should should subtract subtract identified identified leakage leakage from from step 2.6 from step 2.6 total leakage from total leakage determined determined in step 1.5 in step 1.5 and and find find unidentified unidentified leakage leakage to be == 1.141 to be 1.141 GPM.
GPM.
JPM43-2 JPM43-2 Manual Manual Page Page 88 of9 of 9 Rev.
Rev. 00 Operator Operator continues continues with with section 6.1.1 section 6.1.1 -
STEP 9.:
STEP 9.: 6.1.1 [1[IICALCULA 6.1.1 ]CALCULATE total RCS TE total RCS leakage, leakage, identified dentified leakage leakage...... -
SAT SAT Total RCS Total RCS Leakage =
Leakage = 1.425 1.425 gpm gpm Identified Leakage Identified Leakage = 0.242 gpm 0.242 gpm - UNSAT UNSAT Unidentified Leakage Unidentified =
Leakage = 11.141 gpm
.141 gpm STANDARD: Operator STANDARD: Operator records records leakage leakage values values determined determined fromfrom Appendix Appendix D. D.
10.:
STEP 10.:
STEP 6.1.1 [2]
6.1.1 [2] Iff identified identified leakage leakage isis less less than than zero zero...
SAT SAT STANDARD: The STANDARD: The operator operator should mark mark this step step N/A since the leakageleakage is is greater greater than -
UNSAT UNSAT zero.
STEP 11.: 6.1.1 [3] If identified leakage is more negative negative...... -
SAT STANDARD: The operator should mark this step N/A since the leakage is greater than STANDARD: -
UNSAT zero.
STEP 12.: 6.1.1 [4] If an identified leakage more positive...positive ... -
SAT SAT STANDARD STANDARD:: The operator should mark this step N/A since the leakage is greater than -
UNSAT zero.
zero.
STEP 13.:
STEP 13.: 6.1.1 6.1.1 [5]
[5] Record Record maximum maximum leak leak rate from an rate from an individual individual steam steam generator...
generator ... -
SAT SAT STANDARD STANDARD: The operator
- The operator should should reference reference Appendix Appendix D or the "D" or the initiating initiating cue cue to to determine determine -
UNSAT UNSAT the the maximum maximum steam steam generator generator leakage 4.8 GPD leakage isis 4.8 GPD from S/G #4 from S/G # 4 and and the the total total leakage leakage is is 0.009 0.009 GPM GPM
JPM43-2 JPM43-2 Manual Manual Page Page 99 of of 99 Rev.
Rev. 00 STEP 14.:
STEP 14.: 6.1.1 [6]
6.1.1 [6] Check Check appropriate appropriate box box to to indicate indicate whether whether acceptance acceptance criteria criteria were were - SAT SAT met ....
met..
Technical Sgecifications:
Technical Specifications:
Max individual SG Max individual leakage SG leakage check Yes check Yes - UNSAT UNSAT Total Identified Total Identified check Yes check Yes Total unidentified Total unidentified check NO check NO Critical Critical Step Step Administrative Accegtance Administrative Acceptance SG leakage ~ 75 SG leakage 75 GPD GPD check Yes check Yes STANDARD: The STANDARD: The operator operator should should check check "Yes" Yes for for acceptance acceptance criteria criteria met for S/G met for S/G leakage leakage and total and total identified identified leakage leakage BUT BUT "No" No for for unidentified unidentified leakage leakage less less than than 1.0.
1.0.
1 5.:
STEP 15.: 6.1.1 [7]
6.1.1 [7] IfIf any any Technical Technical Specification Specification acceptance acceptance criteria criteria NOT NOT satisfied satisfied ...... - SAT SAT Notify SM NotifySM Refer to REP Refer Refer to AOP- R01 R.01 or orAOP-R.05 AOP-R05 - UNSAT UNSAT NOTE to Evaluator:
NOTE Follow up question to determine procedure transition may be required.
STANDARD: The operator should address each SUb-step.
STANDARD: sub-step. *Critical Step The SM is notified that TS acceptance criteria were not met based on unidentified leakage greater than 1I gpm.
- SM/US is notified
- identification*
AOP-R.05, RCS Leak and Leak Source identification*
Refer AOP-R05, (SI also references AOP-R.01,AOP-R01, Steam Generator Tube Leak in this step, but RO should recognize that AOP-R01 AOP-R.01 is not applicable)
STEP 16.: 6.1.1 [8] If leakage is within Tech Spec limits but exceeds... exceeds ... -
SAT STANDARD STANDARD:: The operator should should mark mark this step N/A since S/G leakage leakage is is within all -
UNSAT acceptance criteria.
Stop Time Stop END END OF OF JPM JPM
READ TO READ TO OPERATOR OPERATOR DIRECTIONS TO DIRECTIONS TRAINEE:
TO TRAINEE:
will explain I will explain the initial conditions, the initial conditions, and and state state the the task task to be performed.
to be performed. II will will provide provide initiating initiating cues.
cues. When When you you complete the complete the task successfully, the task successfully, the objective objective for for this this job performance measure job performance measure will will be be satisfied.
satisfied. Ensure Ensure you you indicate to indicate to meme when when youyou understand understand your your assigned assigned task. To indicate task. To indicate that that you you have have completed completed your your assigned assigned task return task return thethe handout handout sheet sheet II provided provided you.
you.
INITIAL CONDITIONS:
INITIAL
- 1. Unit-1
- 1. Uhit-i is in MODEMODE 1. 1.
- 2. The RCS
- 2. RCS leakage leakage surveillance surveillance required required by by T.S. 4.4.6.2.1 is is due due this shift shift and and the ICS computer is not available
- 3. The off going crew initiated initiated performance of 0-SI-OPS-068-137.0, O-Sl-OPS-068--1 37.0, Section 6.1 and Appendix C are complete.
Appendix 0D is complete through section 1.4 1.4
- 4. SG leakages SG#1 SG#2 SG#3 SG#4 3.2 gpd 2.2 gpd 2.3 gpd 4.8 gpd Sl-50 and SI-137.5
- 5. SI-50 SI-i 37.5 were completed last nigth at 2300.
- 6. Chemistry supervisor reported no additions or samples taken from the RCS during the selected performance period.
- 7. CLA Levels initial and final are as follows:
CLA LI INITIAL FINAL 11 63-1 63-129 29 7692 7692 2 63-1 09 63-109 7677 7677 33 63-89 7672 7672 4 63-89 7680 7680
- 8. CCPIT/HUT leakage and other "other" leakage is 00 gpm
- 9. Do all calculations to three decimal places, or to 1/1 000.
1/1000.
10.
- 10. Data collected for performance of this leak leak rate is documented in Appendix C C and was collected over 124 minutes 124 minutes INITIATING CUES:
You are the Unit-iUnit-1 CR0CRO and performance of have been directed to complete the performance and have of 0-Sl-OPS-068-1 0-SI-OPS-068-137.0 37.0 Appendix D "0" andand Section Section 6.1 .1 through step 6.1.1 step 8.8.
TENNESSEE VALLEY TENNESSEE VALLEY AUTHORIT AUTHORITY Y SEQUOYAH NUCLEAR SEQUOYAH NUCLEAR PLANT PLANT SURVEILLANCE SURVEILLA NCE INSTRUCTI INSTRUCTION ON 0-SI-OPS-068-137.0 0SIOPS -.-0681 37.0 COOLANT SYSTEM REACTOR COOLANT SYSTEM WATER WATER INVENTOR INVENTORY Y Revision 22 22 QUALITY RELATED PREPARED/PROOFREAD PREPARED /PROOFREAD BY: _ _--'OOLIVIA
- .;L=IV...
- ....:..:...IA:...:.H-'
HEAD -'E=A....:.::D=--_ _ __
RESPONSIBLE RESPONSIB ORGANIZATION:
LE ORGANIZA TION: _ _ _OPERATION O:;. . ;P'-'E=R.. ;:. A. .;. .:T. . :. .;IO=.. S
- N. .;. ;S"'--_ _
APPROVED BY: _ _ _ _ _ _-=J.~K~.~W...:...:I=LK~E=S~
J. K. WILKES _ _ ____
EFFECTIVE DATE: 04/24/08 LEVEL OF USE: CONTINUOUS CONTINUOUS USE REVISION REVISION DESCRIPTION:
DESCRIPTION: Revised Revised to change the manual manual calculation formulas for temperature correction correction and and PZR PZR leakage leakage rates rates per guidelines. A engineering guidelines.
per engineering normalized normalized equation equation will will be be used used with with the specific gravity the specific gravity of at water at of water 70 70 degrees degrees (07001541).
(07001541). Made Made conservative conservative administrative administrative changes to changes to Post Performance Activity Post Performance Activity section section based based on on management management directive.
directive.
SQN SQN REACTOR COOLANT REACTOR COOLANT 0-SI-OPS-068-1 0-SI-OPS-068-137.0 37.0 SYSTEM WATER SYSTEM WATER INVENTORY INVENTORY Rev: 22 Rev: 22 1& 2 1&2 Page2of6l Page 2 of 61 TABLE OF TABLE OF CONTENTS CONTENTS Page 11 of Page of 22 Section Section Title Page 1.0
1.0 INTRODUCTION
........................................................................................................ 4 1.1 1.1 Purpose................................................................................................................
Purpose 44 1.2 1.2 Scope...................................................................................................................
Scope 44 1.2.1 1.2.1 Surveillance Test to be Performed ............................................................ 4 1.2.2 1.2.2 Requirements Fulfilled ......................;..... .................................................. 4 Modes... ...... ...... ... .... ... ........ ... ............... ......... .............. ........ ........ .......... ...
1.2.3 Modes 44 1.3 Frequency and Conditions.
Conditions .... ... .... ...... .... .... ... ................. ........ ..... .......... ..... .......... 4
2.0 REFERENCES
..................................... ................... ................................................... 55 2.1 Performance References .......... ......... .......... ... ...... ... ..... ...... .... ..... .............. ... ....... 5 5
2.2 Developmental References ... ............. ......... ............. .................. ............... ...... ..... 5 3.0 PRECAUTIONS AND LIMITATIONS ............................. ........... .................................. 6 6
3.1 Manual Calculations...
Calculations ........ ...... ....... ........ ............ .......... ....... ............ ..... .... ..... ...... 8 3.2 Plant Computer ..... ........ .... ....... .... ...... ... .... ... ......... ......... ... ......... ... ... .... .......... ...... 9 4.0 PREREQUISITE ACTION*S ACTIONS ........................................................................................ 11 4.1 Preliminary Actions...............................................................................................
Actions 11 4.2 Measuring and Test Equipment, Parts, and Supplies...........................................
Supplies 12 4.3 Field Preparations .. :............................................................................................. 13 4.4 Approvals and Notifications..
Notifications ..... .......... ......... .................. .................. .... ..... ........... 13 5.0 ACCEPTANCE CRITERIA ......................................................................................... 14 14 6.0 6.0 PERFORMANCE...........................................
PERFORMANCE ........................ ............................... ...... 15 15 6.1 6.1 Data Data Collection Collection forfor MANUAL MANUAL calculation calculation method. method ............ ... ... ...... ... ..... ... ....... ...... 16 16 6.1.1 6.1.1 Calculation Calculation of RCS RCS Leakage Leakage using using the MANUAL method MANUAL method......................... 21 6.1.2 6.1.2 Restoration Restoration using using the MANUALMANUAL method. method ........... ... ...... ..... ...... .... ............... 26 6.2 6.2 RCS RCS Leakage Leakage Using Using the the Plant Plant Computer Computer ........ ......... .... ..... ........... ......... ... ...... ...... 2828
SQN SQN REACTOR COOLANT REACTOR COOLANT 0-SI-OPS-068-1 0-SI-OPS-068-137.0 37.0 SYSTEM WATER SYSTEM WATER INVENTORY INVENTORY Rev: 22 Rev: 22 1&2 1&2 Page3of6l Page 3 of 61 TABLE OF TABLE OF CONTENTS CONTENTS Page 22 of Page of 22 Section Section Title Page Page 7.0 7.0 POST PERFORMANCE ACTIVITY POST PERFORMANCE ACTiViTy ............................................................................ 39 APPENDIX A:
APPENDIX IDENTIFICATION OF tDENTIFICATION OF RCS LEAKAGE .......................................... 41 RCS LEAKAGE 41 APPENDIX B: REACTOR COOLANT DRAIN TANK LEAKAGE ............................................................... 42 APPENDIX C: INITIAL/FINAL DATA DATA..................................................................... 45 APPENDIX D: RCS LEAKAGE CALCULATIONS ................................................. 50 APPENDIX E: PRESSURIZER RELIEF TANK (PRT)
LEVEL VS. VOLUME ....... ..... ..... ......................... ....... ................... 59 Notes............................................................................................................. 61 Source Notes
SQN SQN REACTOR COOLANT REACTOR COOLANT 0-SI-OPS-06 8-1 37.0 0-SI-OPS-068-137.0 SYSTEM WATER INVENTOR SYSTEM WATER INVENTORY Y Rev: 22 Rev: 22 1&2 1&2 Page4of6l Page 4 of 61 1.0 INTRODUC
1.0 INTRODUCTION
TION 1.1 Purpose 1.1 Purpose This Instruction This Instruction provides detailed steps provides detailed performing aa water for performing steps for inventory balance water inventory balance onon the the Reactor Coolant Coolant System System (RCS).
1.2 Scope 1.2 Scope 1.2.1 Surveillance Test 1.2.1 Test to be Performed Performed This SISI performs aa detailed water inventory balance on on the RCS to determine the and unidentified RCS leakage.
total identified and These values are then compared to applicable sections of Technical Specification (TS) Limiting Condition for Operation (LCO) 3.4.6.2 and to the administrativ administrative S/G leakage and unidentified e limits on SIG leakage.
1.2.2 Requirement Requirements s Fulfilled A. Performance of this instruction completely fulfills TS 3.4.6.2 surveillance requirement (SR) 4.4.6.2.1 & & 4.4.6.2.2.
B. Performance of this instruction may be utilized to fulfill TS LCO 3.4.6.1 action a.
or 3.4.6.1 action b. on a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> frequency, however is not required until 12 establishment of steady state operation.
hours after establishment 1.2.3 Modes Plant operating modes for which the surveillance requirements covered by this Instruction must be satisfied (applicable modes) and during which the test can be performed (performance modes) are:
A. Applicable M~des:
Modes: 1, 1, 2, 3, and 4 B. Performance B. Performance Modes:Modes: 1I through 5 1.3 1.3 Frequency Frequency and Conditions A.
A. This This SI SI must must be be performed performed at at least least once every 72 once every however is hours, however 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, is not required not required to to be be performed performed until until 12 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> hours after establishment of after establishment of steady plant state plant steady state conditions.
conditions.
B.
B. This This SI SI may may be be performed performed at at least least once every 24 once every hours to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> satisfy LCO to satisfy 3.4.6.1 LCO 3.4.6.1 action action a.
a.
C.
C. This This SI SI may may be be performed performed at at least least once every 24 once every hours to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> satisfy LCO to satisfy 3.4.6.1 LCO 3.4.6.1 action action b.
- b. in in lieu lieu of of performance performance of Lower Containment Gaseous SI-i 83, Lower Containment Gaseous and of SI-183, and Particulate Particulate Radioactivity Radioactivity Monitoring During Periods Monitoring During ofRadiation Periods of Monitor Radiation Monitor In operability.
Inoperability.
SQN SQN REACTOR COOLANT REACTOR COOLANT 0-SI-OPS-06 8-1 37.0 0-SI-OPS-068-137.0 SYSTEM WATER INVENTOR SYSTEM WATER INVENTORY Y Rev: 22 Rev: 22 1&2 1&2 Page5of6l Page 5 of 61 2.0 REFERENC
2.0 REFERENCES
ES 2.1 Performance 2.1 Performance References References A. 0SICEM000050.0, A. 0-SI-CEM-000-050.0, 72Hour Chemistry Requirement 72-Hour Chemistry Requirements.s.
B. I, B. 1, 2SlCEM0681 2-SI-CEM-068-137.5, 37.5, PrimanjTo Prim ary- To-Secondary Leakage Via Secondary Leakage Generators Steam Generators 2.2 Developmen 2.2 Developmental tal References A. SQNSON Unit 11 & 22 Technical Specification Specifications.s.
37.1, Reactor Coolant System Unidentified Leakage Measuremen SI-137.1, B. SIi Measurement. t.
C. SQNSON Final Safety Analysis Report (FSAR), Chapter 5.2.7 and 5.1-1.
Table 5.1i.
D. Westinghous Westinghouse PDC7623, Pressurizer Level Channel Cross e Calculation No. PDC-76-23, Reference, G. Richard, November 15, 1976. (Information Sheet from Westinghouse, Westinghouse, S. O. 0. No. TVA 320).
TVA88533, Steam Generator Secondary Water Volume, Westinghouse Letter TVA-88-533, E. Westinghouse T. A. Lordi to J. B. Hosmer, February 11, ii, 1988.
F. TVA Drawings 47W801-2; 47W8091,2; 47W813-1; 47W8012; 47W809-1,2; 47W8301.
47W8131; and 47W830-1.
1099J9i.
Westinghouse Drawing 1099J91.
G. Westinghouse Tl41 .68, Scaling and Setpoint Document Reactor Coolant System.
H. TI-41.68, I. ONP-STD-4.~.7, ONPSTD4.4.7, Attachment 1, Technical Documents.
Writers Guide for Technical 1, Writer's J. Safety Safety Evaluation, Evaluation, Reg Guide 1.121 Reg Guide SQN 1I S/G Circumferential Eva! of SON 1.121 Eval Defect.
Circumferential Defect.
K.
K. STA Log.
L. SPP8. 1, Conduct L. SPP-8.1, Conduct of Testing.
of Testing.
M.
M. Westinghouse Westinghouse Safety Safety Evaluation, Circumferential Oriented SECL91431, Circumferential Evaluation, SECL-91--431, Oriented Primary Primary Water Water Stress Stress Corrosion Cracking WEXTEX Corrosion Cracking - WEXTEX Region.Region.
N.
N. Integrated Integrated Computer Computer System, System, NSSS Critical Design NSSS Critical Chapter 9, Review, Chapter Design Review, Leakage RCS Leakage 9, RCS Rate.
Rate.
O.
- 0. TSC TSC 05-09.
05-09.
P. WCAP-16423-NP, Pressurized P. WCAP-16423-NP, Water Owners Pressurized Water Standard Process Group Standard Owners Group and Process and Methods Methods forfor Calculating Calculating RCS Rate for Leak Rate RCS Leak Pressurized Water for Pressurized Reactors.
Water Reactors.
SQN SQN REACTOR COOLANT REACTOR COOLANT 0-SI-OPS-06 8-1 37.0 0-SI-OPS-068-137.0 SYSTEM SYSTEM WATER INVENTORY INVENTOR Y Rev:
Rev: 22 22 1&2 1&2 Page6of6l Page 6 of 61 3.0 PRECAUTIO 3.0 PRECAUTIONS LIMITATIONS NS AND LIMITATIO NS ri(J Stability Stability of the RCS during performance of this test is of utmost importance.
is of importance. ItIt is is t/ o essential that the end end points temperature and pressure be as close as pOints for RCS temperature possible to the RCS temperature and pressure values used at the beginning of as the test.
(F£. Two hours is the minimum test duration. Use of aa longer test duration (3, 4 or 66 Y hours) is preferred, but not required.
/r£". The administrative r secondary leakage to an individual SG is primary-to-secondary administrative limit for primaryto GPO. This reduced limit is due to the circumferent 75 GPD. ial cracking of SG tubes at circumferential the tube sheet caused by primary water stress corrosion cracking. The limit is Primary-To-Secondary Leak Guidelines.
obtained from EPRI PWR Primary-To-Secondary
(;£.
r identity RCS leakage in accordance with Appendix A must be All attempts to identify completed before proceeding past section 6.1. This is not meant to delay the completion of this test; test: rather, to identify as many sources of RCS leakage as possible while performing section 6.1.
vr-U. The Reactor Coolant Drain Tank (RCDT) level data may be marked N/A if conditions do not permit obtaining RCDT level. The leakage into the RCDT in this case will be accounted for as unidentified leakage.
(£ During the performance of this Instruction, it is expected that the unidentified v:; leakage will occasionally be determined to be less than zero (Le., (i.e., negative leakage). If negative leakage is calculated to be more negative than -0.10 0.10 gpm, then the following sequence of actions are taken: [C.2]
1A'l A minimum of one hour of additional data is collected and all' all calculations Yare are re-performed reperformed (at the discretion of the Test Director, any twohour block two-hour PRECAUTIONS AND or longer of data may be used provided all PRECAUTIONS LIMITATIONS are LIMITATIONS [C.2]
satisfied). [C.2]
are satisfied).
(g) leakage calculated using the additional data is equal to or IfIf the unidentified leakage r more more positive positive than -0.10 acceptable acceptable result.
0.10 GPM,
[C.2]
result. [C.2]
GPM, this value may recorded as an be recorded may be an
SQN SQN REACTOR COOLANT REACTOR 0-SI-OPS-068-1 37.0 0-SI-OPS-068-137.0 SYSTEM WATER INVENTORY SYSTEM WATER INVENTORY Rev:
Rev: 22 22 1&2 1&2 Page7of6l Page 7 of 61 3.0 PRECAUTIONS AND LIMITATIONS LIMITATIONS (Continued)
/~ re-calculated unidentified leakage calculated using the additional data IfIf the recalculated data V is more negative than 0.10 must be
-0.10 GPM, the test must continued until:
until: [C.2]
I 6 The calculated value of unidentified leakage is equal to or more positive than 0.10
-0.10 GPM, or fØThe 1.0 gpm, or The total RCS leakage is less than or equal to 1.0
~A condition occurs which causes the test to be aborted (e.g., makeup to YA the VCT).
If an unidentified leakage equal to or more positive 0.10 GPM can nQ.t positive than -0.10 not be obtained but the total RCS leakage is less than or equal to 1.0 GPM, the calculated value of unidentified leakage may be recorded as an acceptable result provided an investigation is initiated by Systems Engineering and Operations to determine the source of the negative calculation. If the total RCS leakage is greater than 1.0 GPM (coincident with an unidentified leakage more negative than -0.1 nonRCS inleakage may be 0.1 GPM), then non-RCS masking the true RCS leakage and the validity of the test is questionable.
Under these conditions, the test must be continued until the above described criteria are satisfied or a condition occurs which causes the test to be aborted. [C.2]
~: If four consecutive tests result in negative values for unidentified leakage, inleakage must be initiated an investigation into the source of the in-leakage regardless of whether or not the above described criteria are satisfied.
[C.2]
SQN SQN REACTOR COOLANT REACTOR COOLANT 0-SI-OPS-06 0-SI-OPS-068-137.08-1 37.0 SYSTEM WATER SYSTEM WATER INVENTOR INVENTORY Y Rev: 22 Rev: 22 1&2 1&2 Page8of6l Page 8 of 61 3.0 PRECAUTIO 3.0 PRECAUTIONS AND LIMITATIO NS AND LIMITATIONS NS (Continued)
(Continued) 3.1 Manual 3.1 Manual Calculations Calculations fA The final The final RCS temperature must RCS temperature be within must be 1°F of within +/-+/- 1°F the initial of the RCS temperature initial RCS temperature If or the final data or the is VOID data is VOID andand must must bebe retaken.
retaken.
(flj The The final core core power power level must be level must within +/-+/- 2.0 be within % of 2.0 % the initial of the power level core power initial core level
'f/ must be retaken.
is VOID and must data is or the final data rrl:J. pumps, coolers, valve alignments, etc. which could affect RCS All pumps, results must remain constant for 30 minutes before starting and RCS leakage and throughout the performance,, unless specified by this Instruction or otherwise directed by the performance Unit Senior Reactor Operator (SRO).
The same instrumentat instrumentation ion shall be used when recording initial and final values r;J of RCS parameters. Differences between two instruments monitoring the same parameter could be misinterprete misinterpreted d as RCS leakage.
!IJ r' No samples shall be taken from, nor chemical additions made to, the RCS during the performance of this instruction. An exception is RCS Zinc Injection, instrumentation and testing parameters.
which is not detectable within the instrumentation d performance, the data is VOID If any of the following events occur during the performance, P and the test must be restarted or the system returned to normal.
~ Emergency boration.
~ Diversion of letdown to the holdup tanks.
j() Makeup Makeup from any source.
jtf Change Change in in purification demineralizers or purification demineralizers lineup.
or filter lineup.
¢ Failure Failure of of any any instrument used to channel used instrument channel obtain initial to obtain readings..
initial readings
.rtf Failure to use data for at least a two (2) hour time period.
Failure to use data for at least a two (2) hour time period.
/:0 VCT level falls below 10% or low VCT level alarm annunciates.
!CT level falls below 10% or low VCT level alarm annunciates.
"~Restarting Restarting the the primary primary water pumps ifif they water pumps they were before the stopped before were stopped initial the initial data was data collected.
was collected.
~
SQN SQN REACTOR COOLANT REACTOR COOLANT 0-SI-OPS-06 8-1 37.0 0-SI-OPS-068-137.0 SYSTEM SYSTEM WATER INVENTOR INVENTORY Y Rev: 22 Rev: 22 1&2 1&2 Page9of6l Page 9 of 61 PRECAUTIONS 3.0 PRECAUTIO LIMITATIONS NS AND LIMITATIO NS (Continued)
(Continued) 3.2 Plant 3.2 Plant Computer ~
A. All pumps, coolers, valve alignments, etc. which could affect RCS leakage results remained constant during data collection, except where makeup was accounted for by the plant computer.
B. Preferably no samples shall be taken from, nor chemical additions made to the RCS. However, the Plant Computer program has provisions for accounting for RCS leakage changes. Any samples or additions should be noted in the Remarks section Data Package Cover Sheet. An exception is RCS Zinc Injection, which is not detectable within the instrumentat ion and testing instrumentation parameters.
C. CVCS and RCS should remain nearly constant (i.e., no diversion of letdown to demineralizer lineup, no changes to filter holdup tanks, no changes in CVCS demineralizer lineups, and no RCS make-up makeup from any source.
D. If any of the following events occur, the data is VOID and the test must be restarted or the system returned to normal.
- 1. Plant Computer becomes inoperable.
- 2. Emergency boration.
- 3. Diversion of letdown to the holdup tanks.
- 4. Makeup from any source that is not accounted for by the Plant Computer program. \
- 5. RCS Dilution demineralizers or filter lineup.
6 Change in purification demineralizers lineup.
7.
- 7. Failure Failure to use use data least a two (2) data for at least (2) hour period.
hour time period.
E.
E. The The Plant Plant Computer Computer leakage shall be report shall leakage report attached to be attached to the SI completed SI the completed package package toto provide documentation in provide documentation in lieu manually entered of manually lieu of data.
entered data.
SQN SQN REACTOR COOLANT REACTOR COOLANT 0-Sl-OPS-068-1 0-SI-OPS-068-137.0 37.0 SYSTEM WATER SYSTEM WATER INVENTORY INVENTORY Rev: 22 Rev: 22 1&2 1&2 PagelOof6l Page 10 of 61 3.2 Plant 3.2 Plant Computer (Continued) tJ {j}
i 4
1 -
F. The F. The ICS ICS will periodically store data data to history each computer point flagged as history for each as an archive point. Depending on the amount of data that is being stored or archived at one time, the computer may take aa short period of time to archive appears to be aa gap in the data. IfIf aa selected start or the data creating what appears gaps", one of the following alarm "archive gaps, stop time coincides with one of these archive messages may appear during the calculation:
"START TIME IN ARCHIVE GAP. CALCULATION CANCELLED START CANCELLED" "END END TIME IN ARCHIVE GAP. CALCULATION CANCELLED.
CANCELLED".
If either of these messages is received, move the start and/or stop time aa few minutes and repeat the calculation.
G. Performance of any of the following while performing the leakage calculation may result in RCS leak rate uncertainty:
- 1. RCS Makeup or Dilution (Data will be considered Void.)
- 3. Removal from service of any of the instruments listed in Section 4.1 Step [2].
- 4. Procedures or activities that result in Control Rod motion.
SQN SQN REACTOR COOLANT REACTOR COOLANT 0-SI-OPS-068-1 0-SI-OPS-068-137.037.0 SYSTEM WATER SYSTEM WATER INVENTORY INVENTORY Rev: 22 Rev: 22 1&2 1&2 Pagellof6l Page 11 of 61 Unit._ _ _ _ __
Unit_____________ Date (OcC2J DateloJag 4.0 PREREQUISITE 4.0 PREREQUISITE ACTIONS ACTIONS
.y6TE JlTE Throughout this Throughout Instruction where this Instruction where an an IF/THEN statement exists, IF/THEN statement exists, the step should be the step should be N/A N/A if if condition condition does does not exist.
exist.
4.1 Preliminary 4.1 Preliminary Actions Actions
[1]
[1] ENSURE Instruction ENSURE Instruction to to bebe used used is copy of is aa copy the effective of the effective version.
version.
[2]
[2] IF ICS IF ICS Points Points are are to to be be used determination, THEN leakage determination, used for leakage THEN IDENTIFY lOS ICS Points that are inservice prior to performing leakage calculation:
Computer Points Needed to Perform RCS Water Inventory at 100% 100% Power Parameter I Instrument I Computer Point I I/S Inputs to Total Leakage RCS Temperature Correction RCL AVG Tavg RCL AVG Tavg(1) U0484 Pl/I't Loop 11 Tavg T-68-2 TO400A T0400A L C
Loop 2 Tavg T-68-25 T0420A L C
Loop 3 Tavg T-68-44 T0440A C
~
Loop 4 Tavg T-68-67 T0460A [
Pzr. Pressure 1/2/3/4 Avg('l.) 2 Avg U0482 -[
Pzr. Pressure Ch. II P-68-340 P0480A [
Pzr. Pressure Ch. II P-68-334 P0481A -[
Pzr. Pressure Ch.1I1 Ch.III P-68-323 P0482A [
Pzr. Pressure Ch.IV P-68-322 P0483A [
Pressurizer Pzr. Level(3)
Pzr. Level 3 U0483 [
Pzr.
Pzr. Level Level Ch. II L-68-339 L-68-339 L0480A L0480A [
Pzr.
Pzr. Level Level Ch.
Ch. IIII L-68-335 L-68-335 L0481A L0481A J Pzr.
Pzr. Level Level Ch.
Oh. III Ill L-68-320 L-68-320 L0482A L0482A ]
Volume ControlControl TankTank VCT VCT Level Level L-62-130 L-62-130 LO112A L0112A [
Inputs Inputs to Identified RCS to Identified Leakage RCS Leakage RCDT RCDT Level Level L-77-1 L-77-1 L2400A L2400A [0 PRT PRT Level Level L-68-300 L-68-300 L0485A L0485A ~ W' (1)
(1) RCL RCL AVG AVG Tavg Tavg isis the the average average of of the the four four narrow range loop narrow range temperatures.
ioop temperatures.
(2)
(2) Pzr. Pressure 1/2/3/4 Pzr. Pressure 1/2/3/4 Avg Avg isis the the average average of of the four narrow the four Pressurizer Pressure range Pressurizer narrow range Channels.
Pressure Channels.
(3)
(3) Pzr.
Pzr. Level Level isis the the average average of of thethe three three Pressurizer Pressurizer Level Channels Level Channels n
--/-!s;-q-1'"'--
SQN SQN REACTOR COOLANT REACTOR COOLANT 0-Sl-OPS-068-1 37.0 0-SI-OPS-068-137.0 SYSTEM WATER INVENTORY SYSTEM INVENTORY Rev: 22 Rev: 22 1&2 1&2 Pagel2of6l Page 12 of 61 Equipment, Parts, and Supplies 4.2 Measuring and Test Equipment, NOTE / may be completed during the performance of The tables in this section may section 6.1, as necessary.
) IF any IF any ReS leak sources will be quantified using a RCS leak sources will be quantified using a stopwatch and container, THEN stopwatch and container, THEN RECORD the following information for all stopwatches and containers to be used.
TVA ID Number Calibration Due Date Stopwatch Container NIl-\-
Njc
\
~
'" 1_ _ _ _ _ _ _
~
,\
SQN SQN REACTOR COOLANT REACTOR COOLANT 0-SJ-OPS-068-1 37.0 0-SI-OPS-068-137.0 WATER INVENTORY SYSTEM WATER SYSTEM INVENTORY Rev:
Rev: 22 22 1&2 1&2 Pagel3of6l Page 13 of 61 Unit Unit _, \ Dat~TOJ~
Date(0dcIj
~eaSUring 1lleasuring and Test Equipment, Parts, and and Test and Supplies Supplies (Continued)
~~ IF any other special test equipment will be used during the ICY Instruction, THEN performance of this Instruction, RECORD the following information for each additional piece of test equipment to be used.
Test Calibration Model Accuracy TVA ID TVAID Due Date Equipment NII\
t\II r-----...
--- ~
NIA 6: Field Preparations Field fr~ ENSURE reactor power and RCS average temperature V (T -avg) are stable and have varied less than +/- 2% and (Tavg) /3
+/- 1°F, respectively, during the calculation test interval.
~
4 Approvals and Notifications N
NOTV OTV During data collection using the Manual Calculation Method (Sect.
6.1), RCS chemical additions and / or sampling invalidate the data and will r~quire require a re-initiation of SI performance. During data collection using the Plant Computer (Sect. 6.2), it is preferred that RCS chemical additions and / or sampling not take place. If chemical additions or samples are required, required, then volume MUST be in gallons be accounted for, in per minute. RCS dilution is is not allowed during either method of data collection.
CONTACT CONTACT Chemistry Chemistry Lab Lab to to verify verify that performance of that performance this SI of this and limitations limitations imposed sampling will imposed on sampling interfere NOT interfere will NOT with any sampling required required by Specifications by Technical Specifications or or Technical Technical Requirements Manual.
Requirements Manual.
SQN SQN REACTOR COOLANT REACTOR COOLANT 0-SI-OPS-068-1 37.0 0-SI-OPS-068-137.0 SYSTEM WATER INVENTORY SYSTEM WATER INVENTORY Rev:
Rev: 22 22 1&2 1&2 Pagel4of6l Page 14 of 61 Unit" - - - - - -____
Unit_______ '--- Oate/7Jf)Af_
Date_______
5.0 ACCEPTANCE CRITERIA 5.0 CRITERIA t&hhe The Technical Specification acceptance criteria is as follows:
MThe primary-to-secondary leakage must be less than or equal to 150 I The primarytosecondary 150 GPD GPO lP 1 through anyanyone one steam generator.
Ii! 10 GPM.
The total identified RCS leakage must be less than or equal to 10 (J. I GPM.
The total unidentified leakage must be less than or equal to 1
~ If any of the Technical Specification criteria are NOT satisfied, the SM must be (3J lP Y- notified and action requirement (b) of LCO 3.4.6.2 satisfied.
!;{' The administrative acceptance criteria for total primary-to-secondary primarytosecondary leakage is If less than or equal to 75 GPO GPD through anyone any one steam generator. AOP-R.01, Steam Generator Tube Leak, contains required actions and criteria for plant shutdown.
SQN SQN REACTOR COOLANT REACTOR COOLANT 0-SI-OPS-068-1 37.0 0-SI-OPS-068-137.0 SYSTEM WATER SYSTEM WATER INVENTORY INVENTORY Rev: 22 Rev: 22 1&2 1&2 Pagel5of6l Page 150f 61 I
Unit._ _-+-_ __
Unit Date (0 Date_____ .oft Y 6.0 PERFORMANCE 6.0 PERFORMANCE
~ I1 Manipulation of any of the following valves during this test could effect of this test.
the results at VALVE DESCRIPTION DESCRIPTION FCV-63-24 FCV6324 CLA fill line isolation valve FCV-63-71 FCV6371 Check valve test line isolation valve FCV-63-84 FCV63--.84 Check valve test line isolation valve VLV-68-601 VLV68601 Test header isolation valve to HUT 2 Maintaining the pressurizer pressure control and pressurizer level control systems in the automatic mode during data collection will improve RCS stability.
IF using the Plant Computer, THEN GO TO Section 6.2.
] IF using MANUAL calculations, THEN GO TO Section 6.1.
SQN SQN REACTOR COOLANT REACTOR COOLANT 0-Sl-OPS-068-1 0-SI-OPS-068-137.0 37.0 SYSTEM WATER SYSTEM WATER INVENTORY INVENTORY Rev:
Rev: 22 22 1&2 l&2 Pagel6of6l Page 16 of 61 Unit._ _-'--_ __
Unit_________ Date Date/ TInA /
6.1 Data 6.1 Data Collection Collection for for MANUAL calculation method MANUAL calculation method ftJi') ENSURE VCT ENSURE VeT level level is is such such that makeup is that makeup is rnot anticipated anticipated D.-r
'f/ for for the the duration duration of of this this test.
test. ~
~TETE I1
.\J4 0
7 The applicable section The section of of 1, 2-S0-77 -1 is 1, 2SO771 dependent upon is dependent upon where the where RCDT is the RCDT is to be pumped.
to be pumped.
\.N6TE OTE 22 The following step may marked N/A ifif conditions do may be marked do not not permit obtaining RCDT level.
IF reactor coolant drain tank (RCDT) level is greater than 2-Ll-77 -1, THEN 30% as indicated by 1, 2Ll771, GO TO 1, 2-S0-77-1.
I 2SO-77--1.
PERFORM the applicable section, AND RETURN to step [3] of this section. iJ/4
~E NTE The following step may be marked N/A if conditions do not permit obtaining RCDT level.
PLACE both RCDT pumps hand switches in the PULL-TO-LOCK PULLTOLOCK position:
PUMP HANDSWITCH REQUIRED POSITION INITIALS A HS-77-4A PULL-TO-LOCK .f2~
9L.
2
(
B B
HS-77-6A HS-77-6A PULLTOLOCK PULL-TO-LOCK v~~$24
~E Steam Steam generator 2.3 2.3 of generator primary of Appendix Appendix D primary to secondary leak may be D may leak rates obtained from the be obtained required by rates required the Chemistry Lab at section by section Chemistry Lab the time
_ the notification is the following notification performed.
is performed.
~
(4Ei) NOTIFY NOTIFY Chemistry Chemistry Lab Lab of of the following:
the following:
p I~ ENSURE ENSURE no no chemical additions to, chemical additions nor take to, nor samples take samples
~ from, from, the the RCSRCS untiluntil further notice. An further notice. exception isis An exception RCS RCS Zinc Zinc Injection, Injection, which not detectable which isis not within detectable within the instrumentation the instrumentation and and testing testing parameters.
parameters.
ENSURE 0-SI-CEM-000-050.0 ENSURE 0SICEM000050.0 has performed been performed has been within within the the last last 72 72 hours.
hours.
SQN SQN REACTOR COOLANT REACTOR 0-Sl-OPS-068-1 0-SI-OPS-068-137.037.0 SYSTEM WATER SYSTEM WATER INVENTORY INVENTORY Rev: 22 Rev: 22 1&2 1&2 Pagel7of6l Page 17 of 61 Unit'--_ _I _ __
Unit Date I O Date/oDA'f 6.1 Collection for MANUAL calculation method Data Collection method (Continued)
~(5 ENSURE the following system lineup ESTABLISHED:
ENSURE ESTABLISHED:
VALVE DESCRIPTION POSITION INITIALS FCV-62-118 FCV621 18 VCT Isolation Valve To VCT ToVCT D/0-L-FCV-62-128 FCV62128 Blender Output to VCT CLOSED rL~
FCV-62-144 FCV62144 Blender Output to COPsCCPs CLOSED 12'(nL FCV-62-138 FCV62138 Emerg Boration to CCPs CLOSED I12vt PCV-68-301 PCV68-301 PRT Vent to RCDT CLOSED ~H--
FCV-68-310 FCV68310 PRT Drain to RCDT CLOSED k!--vi-
~E Primary water pumps should be shut off only if primary water inleakage is suspected, the last performance of this SI resulted in a negative
¢ Ic
" value for unidentified leakage, or if directed by the Unit SRO.
IF primary water pumps will be shut off during data collection, THEN fj)
~
PLACE both primary water pumps hand switches in the PULLTOLOCK position:
PULL-TO-LOCK PUMP HANDSWITCH POSITION INITIALS A
A' HS-81-3A PULL-TO-LOCK (Jf 4 f\)/rt B HS-81-7A HS81-7A PULL-TO-LOCK {>
[081519], Primary
/;::;{ ENSURE [0-81-5191, Primary Water Unit Crosstie f!Y Valve is LOCKED CLOSED. tv/A IF RCS IF RCS conditions conditions are are NOT NOT stable desired to and itit is desired stable and do aa to do calculation calculation from from the the current current time, THEN time, THEN WAIT approximately WAIT approximately 30 30 minutes minutes to allow RCS to allow parameters RCS parameters to to stabilize, AND stabilize, AND RECORD any RECORD any remarks remarks regarding regarding RCS stability in RCS stability in the the chronological test log.
chronological test log. Nth
SQN SQN REACTOR COOLANT REACTOR COOLANT 0-SI-OPS-06 8-1 37.0 0-SI-OPS-068-137.0 SYSTEM WATER SYSTEM WATER INVENTOR INVENTORY Y Rev: 22 Rev: 22 1&2 1&2 Pagel8of6l Page 18 of 61 Unit- - - - -
Unit_______ ___- Date________
6.1 Data 6.1 Data Collection Collection for for MANUAL calculation method MANUAL calculation method (Continued)
(Continued)
~OTE OTE The following The step may following step may be marked N/A be marked N/A ifif conditions conditions do not permit do not permit obtaining RCDT obtaining RCDT level.
level.
IF pump IF pump down down of the RCDT of the RCDT is is required during the required during the 30 30-minute waiting minute period, THEN waiting period, GO TO 1, 1, 2SO-77-1.
2-S0-77-1. N(A 1
tJ(i PERFORM the applicable section, AND PERFORM RETURN to step [8][c] of this section.
RETURN both RCDT pumps handswitches to the l
PULLTOLOCK position:
PULL-TO-LOCK PUMP HANDSWITCH HANDSWITCH POSITION INITIALS A HS-77-4A PULL-TOLOCK PULL-TO-LOCK N//4 B HS-77-6A HS77-6A PULLTOLOCK PULL-TO-LOCK tb IF additional methods will be used to quantify RCS leakage, THEN INITIATE performance of Appendix A. fJ \f\--
L4 N~
NO 1 When bench board instruments are used, the first instrument read will initia~e initiate the timed duration of this test (minimum of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />).
NO 2 RCS RCS TTavg-avg should be maintained within aa +/- 1.0°F be maintained 1.0°F band least 55 band for at least minutes minutes before before data collection is initiated.
is initiated.
RECORD RECORD initial initial RCS RCS datadata required required by Appendix C.
by Appendix C.
ENSURE ENSURE all all readings readings are are taken taken at approximately the at approximately same the same time. [C.1]
time. [C.1]
IF IF pump pump down(s) down(s) of of the the RCDT (level >45%)
RCDT (level> 45%) is required is required
-I- before before final final RCS RCS data recorded, THEN data isis recorded, THEN COMPLETE COMPLETE RCDT RCDT pump pump downdown in accordance with in accordance with Appendix Appendix BB before before proceeding proceeding to [13].
step [13].
to step
~-
SQN SQN REACTOR COOLANT REACTOR COOLANT 0-Sl-OPS-068-1 37.0 0-SI-OPS-068-137.0 SYSTEM WATER SYSTEM WATER INVENTORY INVENTORY Rev: 22 Rev: 22 1&2 1&2 Pagel9of6l Page 19 of 61 Unit" - - -
\ --
Unit_______ __ -
Date -TD f)
Date_______ At 6.1 6.1 Data Collection Data Collection for MANUAL calculation method method (Continued)
(Continued)
~E I1 Two hours is the minimum test duration. If desired, the final data may Increasing the length of be voided and retaken to lengthen the test. Increasing the test will reduce the adverse impact of variations in RCS temperature and reactor power.
power.
)4TE 2 When using bench board instruments, the last instrument read will determine the finish time of the data collection.
~33 1.0°F band for at least 5 T-avg should be maintained within aa +/-+/- 1.0°F RCS Tavg minutes before data collection is initiated.
WHEN aa minimum of two hours has elapsed since initial data collection, THEN [C.1]
[a] RECORD final RCS data required by Appendix C.
[b] ENSURE all readings are taken at approximately the same time. [C.1]
IF Appendix A is being used to quantify additional RCS leakage sources, THEN /
ENSURE Appendix A has been completed.
WHEN final data collection has been completed, THEN CHECK appropriate boxes to indicate whether initial and final data are acceptable.
ffIj Were final reactor power and RCS RCS temperature within rr +/-
+/- 2% and +/- +/- 1°F, respectively, of their initial readings? NO rS NO YES
(¢' Have all pumps, coolers, valve alignments, etc. which constant remained constant could affect RCS leakage results remained Ll
/
LI could affect RCS leakage results during data collection collection (except (except as specified otherwise specified otherwise s YES NO NO by by this this Instruction Instruction or the Unit SRO).
Unit SRO).
SQN SQN REACTOR COOLANT REACTOR COOLANT O-SI-OPS-06 8-1 37.0 0-SI-OPS-068-137.0 SYSTEM WATER INVENTOR SYSTEM INVENTORY Y Rev:
Rev: 22 22 1&2 1&2 Page200f6l Page 20 of 61 Unit' - - -_______
Unit_______ Date _ _ ____
Date_______ _
6.1 Data 6.1 Collection for MANUAL calculation method (Continued)
Data Collection
~ Have the CVCS and RCS remained nearly constant (i.e., noVCT
\j/
/ makeup, no diversion of letdown to holdup tanks, jjg CVCS demineralize no VCT no changes in demineralizerr lineup, no changes to filter lineups, and either rioLI V
YES NO make-up from any source)?
no RCS makeup frIJ. Were sampling and chemical additions to the RCS Lf'
-1 (with the exception of RCS Zinc Injection) Gio LI stopped during data collection? NO fr£.
[. instruments/points used for recording Were the same instruments/points ~~LI Cr 1 initial and final data? YES NO
({/) Were initial and final RCDT data taken at the same o W/O LILI
'f T time as the other data? N/A YES NO
!iiJ.
/4? Was data collection performed over aa minimum If' 1 of two hours?
err 0 YES NO
~
ff96 IF any box in step [15] is checked "NO",NO, THEN
[a] TERMINATE this test.
TERMINATE
[b] NOTIFY the Unit SRO that the test was invalid.
[c] chronological test log NOTE in Remarks section of chronological why'test why test has been aborted.
[d] OBTAIN OBTAIN aa working copy restart of this procedure to restart copy of test AND MAINTAIN MAINTAIN the working copy in package.
in this SI package.
SQN SQN REACTOR COOLANT REACTOR 0-Sl-OPS-068-1 37.0 0-SI-OPS-068-137.0 SYSTEM WATER SYSTEM WATER INVENTORY INVENTORY Rev: 22 Rev: 22 1&2 1&2 Page2lof6l Page 21 of 61 Unit._ _ _\ _ __
Unft____________ Date jO Date DA'j 6.1.1 Calculation Leakage using the MANUAL method Calculation of RCS Leakage method
~
CALCULATE total RCS leakage, identified leakage and CALCULATE unidentified leakage in accordance with Appendix D, 1 AND RECORD below:
A. Total RCS leakage = _ _ _ _ GPM
=
B. Identified leakage = _ _ _ _ GPM
=
C. Unidentified leakage = ____ GPM
=
NOTE Copies of Appendices C, or D D may be used to perform steps [2]
through [9] provided all copies are included in the data package.
[2] IF unidentified leakage is less than zero by more than 0.1 gpm (i.e., negative leakage), THEN [C.2]
-0.1
[a] COLLECT a minimum of one hour of additional data. D
[b] RECALCULATE all RCS leakage terms in accordance with Appendix D. LI D
[c] RECORD below:
A. Total RCS leakage = GPM B. Identified B. Identified leakage leakage = GPM GPM C. Unidentified leakage ==
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Unit______________ Date _ _ __
Date__________
6.1.1 Calculation 6.1.1 Calculation of of RCS Leakage Leakage using using the MANUAL method the MANUAL method (Continued)
NOTE NOTE unidentified leakage more An unidentified GPM may be
-0.10 GPM more negative than 0.10 recorded as an acceptable result provided the total RCS leakage is equal to or less less than 11.0 GPM and there is
.0 GPM an ongoing is an investigation to on-going investigation inleakage. [C.2]
source of the inleakage.
determine the source
[3] IF unidentified leakage is more negative than 0.10-0.10 GPM, THEN CONTINUE data collection and calculation of RCS leakage terms in accordance with Appendices C, or D D by changing the time interval or performing a a new calculation until an unidentified leakage term more positive than -0.100.10 GPM is obtained or total RCS leakage is equal to or less than 1.0 1 .0 GPM (or until test must be aborted), AND [C.2]
RECORD results below (N/A any blanks not used).
A. Calculations completed:
-Time
-Total Total RCS leakage =
= _ _ _ _ GPM
-Identified Identified leakage = _ _ _ _ GPM Unidentified leakage == _ _ _ _ GPM
-Unidentified B. Calculations completed:
-Time
-Ti me
-Total Total RCS leakage = _ _ _ _ GPM
-Identified Identified leakage leakage = _ _ _ _ GPM
-Unidentified leakage == _ _ _ _ GPM Unidentified leakage GPM
SQN SQN REACTOR COOLANT REACTOR COOLANT 0-SI-OPS-068-1 37.0 0-SI-OPS-068-137.0 SYSTEM WATER SYSTEM WATER INVENTORY INVENTORY Rev:
Rev: 2222 1&2 l&2 Page23of6l Page 23 of 61 Unit._ _ _ _ __
Unit______________ Date _ _ __
Date__________
6.1.1 Calculation 6.1.1 Calculation ofof RCS Leakage using MANUAL method using the MANUAL method (Continued)
(Continued)
C. Calculations completed:
-Time Ti me
-Total RCS leakage Total = GPM
-Identified leakage Identified = GPM
-Unidentified leakage Unidentified = GPM
[4] -0.10 GPM IF an unidentified leakage more positive than 0.10 could not be obtained, OR IF four consecutive performances of this Instruction have resulted in a negative value of unidentified leakage, THEN NOTIFY Unit SRO and/or cognizant Systems Engineer that an investigation to determine the source of ininleakage leakage to the RCS must be initiated. [C.2]
NOTE 'Maximum' activity/leakage is too low to Total if activitylleakage Maximum may be the same as 'Total' identify an individual steam generator.
[5] RECORD maximum leak rate from an individual steam generator and total leak rate from all four steam generators from section 2.3 of Appendix D.
A. Max. individual SG SG leakage = = GPD B. Total SG leakage = = GPM
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Unit______________ Oate _ _ __
Date__________
6.1.1 Calculation of RCS Leakage using the MANUAL method (Continued)
[6] CHECK appropriate box to indicate whether the following acceptance criteria were satisfied.
TECHNICAL SPECIFICATION ACCEPTANCE CRITERIA:
Maximum individual SG leakage is less than or equal to 150 GPD. GPO. El DYes Yes El D No The total identified leakage is less than or equal to 10.0 GPM. El DYes Yes D
ElNo No 1 .0 GPM.
The total unidentified leakage is less than or equal to 1.0 El Yes DYes D
ElNo No ADMINISTRATIVE ACCEPTANCE CRITERIA:
The maximum individual SG leakage is less than or equal GPD.
to 75 GPO. El Yes DYes D
ElNo No
[7] IF any of the Technical Specification acceptance criteria stated in step [6] is NOT satisfied, THEN
[a] NOTIFY SM that RCS leakage exceeds limit and LCO 3.4.6.2 action (b) must be satisfied. D
[b] REFER to EPIP-1 EPIP1 for REP implementation. D
[c] REFER TO AOP-R.01, AQP-R.01, Steam Generator Tube Leak, AOP-.R.05, ReS or AOP-R.05, RCS Leak and Leak Source Identification, as applicable. El D
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Unit_____________ Date _ _ __
Date__________
6.1.1 Calculation of RCS Leakage using the MANUAL method (Continued)
[8] IF leakage is within Tech Spec limits but exceeds administrative acceptance criteria for S/G leakage, THEN
[a] primary-to-secondary leakage NOTIFY SM that primarytosecondary exceeds administrative limit. o
[b] REFER TO AOP-R.O1, AOP-R.01, Steam Generator Tube Leak. o
[9] WHEN all data collection has been completed, THEN NOTIFY Chemistry Lab that RCS sampling/chemical additions may be resumed, as necessary.
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Unit_____________ Date _ _ __
Date 6.1.2 Restoration using 6.1.2 using the MANUAL MANUAL method method
[1] IF the following RCDT handswitch(es) can be returned to to their normal alignment, THEN PLACE PLACE the applicable in the required applicable handswitch(es) in position:
PUMP HANDSWITCH POSITION INITIALS A HS-77-4A HS77-4A PAUTO P-AUTO 1
Ssl 1 t IV B
B HS-77-6A HS77--6A PAUTO P-AUTO 1
1stsl IV
[2] IF the RCDT pump handswitch(es) cannot be returned to the required position, THEN NOTIFY the US and VERIFY the position is documented and controlled by an approved configuration control process.
[3] IF the Primary Water Pump(s) were stopped for data collection, AND
[a] IF handswitch(es) are to be returned to the required position, THEN PLACE the pump handswitch(es) to the required position in accordance with the applicable SO:
PUMP HANDSWITCH HANDSWITCH POSITION POSITION INITIALS A HS-81-3A HS-81-3A START/MAN 0 P-AUTO P-AUTO 0I 11st sl IV IV BB HS817A HS-81-7A START/MAN START/MAN 0IJ
, P-AUTO PAUTO 0LJ 11 sslt IV IV
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Unit_______ __
______ Date _ _ __
Date 6.1.2 Restoration 6.1.2 Restoration using using the MANUAL method the MANUAL method (Continued)
(Continued)
[b]
[b] IF handswitch(e IF handswitch(es)s) cannot be returned cannot be returned toto the the required position, THEN required position, THEN NOTIFY the NOTIFY the US and VERIFY the US and the position position isis documented and documented and controlled byby an approved an approved configuration control process.
[4]
[4] ENSURE the following valves are in in their required position:
REQUIRED INDEPENDE INDEPENDENT NT VALVE POSITION FIRST PERSON VERIFICAT ION VERIFICATION FCV-77-9 FCV779 A AUTO/OPEN FCV-77-10 FCV771O A-P AUTO/OPEN AP FCV-62-128 FCV-621 28 P-AUTO PAUTO FCV-62-144 FCV-62144 P-AUTO FCV-62-118 FCV62-1 18 P-AUTO FCV-62-138 FCV-621 38 CLOSED PCV-68-301 PCV-68301 CLOSED FCV-68-310 FCV-68310 CLOSED
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Unit______________ Date _ _ __
Date__________
6.2 RCS LEAKAGE 6.2 LEAKAGE USING USING THETHE PLANT PLANT COMPUTER COMPUTER NOTE VCT level should be in aa range between Auto make-up and Auto divert before starting the test. Desired range 25 to 60%.
to the HUT before Dilution of the RCS will void data collected.
[1] CHECK VCT level in desired range;range:
[a] IF VCT level approaching Auto make-up, THEN ADJUST VCT level using 0-SO-62-7 (manual make- make up).
[b] IF VCT level approaching divert to HUT, THEN DIVERT letdown flow to the HUT by turning
[HS-62-118AJ
[HS-62-118A] to the DIVERT position.
t 1
1st Iv IV
[2] WHEN VCT level in desired range, THEN PLACE [HS-62-118A] in VCT position 1I_ __
st 1 IV NOTE 1I Plant computer uses historical data for calculations. The minimum test duration is two hours. Use Use of a longer test duration (3, 4 or 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />) is is preferred, but not required.
but not required.
NOTE 2 conditions result in reactor power and RCS average Stable conditions temperature (T temperature -avg) having (Tavg) having not more than +/- 2% and +/-+/- 1°F, varied more not varied 1°F, respectively, and pressurizer, pressurizer, PRT, PRT, VCT, VCT, and RCDT RCDT levels not changing changing excessively over period.
over the calculation period.
[3]
[3] MAINTAIN MAINTAIN plant plant conditions conditions as as stable stable as possible as possible (minimum (minimum ofof 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br />).
hours).
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Unit_____________ Oate _ _ __
Date
\
6.2 RCS LEAKAGE USING THE PLANT COMPUTER COMPUTER NOTE I1 NOTE SG leak rates are obtained by 1, 1, 2Sl--CEM068--1 2-SI-CEM-068-137.5. 37.5.
O-SI-CEM-OOO-050.0 is performed 0SICEM000050.0 every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and at activity levels which will determine if those leak rates from the last performance 1, 2SlCEM0681 of 1, 2-SI-CEM-068-137.5 37.5 have increased.
NOTE 2 Individual steam generator leakage may be NIAd N/A'd if activity is too low to be separately identified.
[4] REQUEST from Chemistry Lab the following:
[a] SG 1 1 Leakage =
= GPD GPO
[b] SG 2 Leakage == GPD GPO
[c]
[C] SG 3 Leakage =
= GPD GPO
[d] SG 4 Leakage = GPD GPO Total SG leakage =
= GPD GPO = _~_\+-,~_ GPM
=
mm/day 1440 min/day OaterTime Date/Time O-SI-CEM-OOO-050.0 0SICEM000050. 0 performed:
Dat~
Dat Time OaterTime Date/Time 1, 1, 2-SI-CEM-068-137.5 2SICEM0681 37.5 performed: -b/
Date Time NOTE Selected Seledted performance period (time interval) is that period chosen by the operator to perform this instruction. Water additions or samples taken from RCSRCS must must bebe converted to gallons per minute.
[e] DETERMINE the amount of any chemical additions made to or samples taken from the RCS during the selected performance performance period, with the exception of RCS Zinc period, with Injection, which is Injection, which is not detectable within not detectable the within the instrumentation and instrumentation and testing testing parameters.
parameters.
(to be (to be recorded recorded in in computer computer as as "Other Sources in Other Sources" gpm):
in gpm): o
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Rev: 22 22 1&2 1&2 Page3Oof6l.
Page 30 of 61.
Unit_ _ _ _ __
Unit Date _ _ __
Date 6.2 RCS 6.2 RCS LEAKAGE LEAKAGE USING USING THE THE PLANT COMPUTER (Continued)
PLANT COMPUTER (Continued)
[5]
[5] volume from IF volume IF from any any source source (chemical sampling, or addition, sampling, (chemical addition, or make-up) cannot makeup) cannot be determined from be determined from thethe selected selected performance period, THEN performance period, THEN PERFORM one PERFORM one ofof the following (N/A other):other):
[a] CHANGE the selected performance period (time CHANGE interval) so known volume changes can be used interval)
AND REPEAT the instruction.
[b] PERFORM Section 6.1, step [1] through [14],
THEN GO TO to step [6].
[6] IF pump down of the RCDT is a a frequent occurrence, THEN PERFORM one of the following (N/A other):
[a] WAIT for computer to build a file history (greater than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) after the RCDT is initially pumped down AND REPEAT the instruction.
[b]
[b] COMPLETE RCDT RCDT pump down down in in accordance with Appendix B. B.
[7]
[7] IF in-leakage IF inleakage to to the the CLA, THEN CLA, THEN
[a]
[a] RECORD initial RECORD initial CLA CLA levels in Appendix C levels in C and and wait at wait at least least 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br />.
hours. o
[b]
[b] WHEN greater WHEN greater thanthan 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> has elapsed, hours has THEN elapsed, THEN RECORD final RECORD final CLA CLA levels Appendix C.
in Appendix levels in C.
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Unit_____________ Date _ _ __
Date__________
ReS LEAKAGE USING THE 6.2 RCS THE PLANT COMPUTER (Continued)
PLANT COMPUTER NOTE I1 Plant Computer cannot look ahead and determine leakage rates. All leakage rates must be determined from past points.
NOTE 2 NOTE ICS will periodically store data to history for each computer The ICS point flagged as an archive point. Depending on the amount of data that is being stored or archived at one time, the computer may take aa short period of time to archive the data creating what appears to be aa gap in the data. If aa selected start or stop time coincides with one of these archive gaps", one of the following "archive gaps, alarm messages may appear during the calculation:
START TIME IN ARCHIVE GAP. CALCULATION "START CANCELLED" CANCELLED END TIME IN ARCHIVE GAP. CALCULATION CANCELLED".
"END CANCELLED.
If either of these messages is received, move the start and/or stop time a few minutes and repeat the calculation.
[8] INITIATE RCS Leakage Program using the Plant Computer by performing the following:
[a] SELECT NSSS & BOP menu on monitor.
[b] SELECT SI-137.0, SII 37.0, RCS leakage screen on monitor.
[c)
[c] ENSURE correct START date and time entered in Plant Computer.
[d)
[d] ENSUR'E ENSURE correct STOP date and time entered in Plant Computer.
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Unit_____________ Date _ _ __
Date 6.2 RCS LEAKAGE USING 6.2 USING THETHE PLANT COMPUTER (Continued)
PLANT COMPUTER (Continued)
NOTE NOTE then the start/stop IfIf data is to be manually inserted into the computer, then start/stop times to be entered into the computer must encompass the time data was taken.
interval the data interval
[9] MANUALLY enter the following:
MANUALLY
[a] SG leakages from Chemistry.
NOTE CLA leakage calculations may be marked N/A if the RCS pressure is greater than 683 psig and quantification of the CLA leakage is not required.
req uired.
[b] CLA initial and final volumes from Appendix C C (if required).
[c] CePIT/HUT CCPIT/HUT leakage (N/A if not required).
[d] Other sources, such as Appendix B or Chemistry sampling (N/A if not required).
[10] INITIATE execute for calculation results.
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Unit______________ Date _ _ __
Date__________
6.2 RCS LEAKAGE USING THE PLANT COMPUTER (Continued)
[11] WHEN data collection has been completed, THEN CHECK the following to indicate whether data is acceptable:
A. VERIFY dates and times entered for the leak rate performance period are correct and data collection performed over a minimum of two hours.
B. VERIFY all sampling and chemical additions to the RCS were stopped during data collection or have been accounted for.
(with the exception of RCS Zinc Injection).
C. VERIFY all pumps, coolers, valve alignments, etc. which could affect RCS leakage results remained constant during data collection, except where makeup was accounted for by the plant computer.
D. VERIFY the CVCS and RCS remained nearly constant (i.e., no diversion of letdown to holdup tanks, no changes in CVCS demineralizer lineup, no changes to filter lineups, and no makeup from any source, except where makeup was RCS make-up accounted for by the plant computer.
E. VERIFY NO RCS dilution occurred during data taking period.
STEP CONTINUED ON NEXT PAGE
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Unit Date _ _ __
6.2 RCS LEAKAGE USING THE PLANT COMPUTER (Continued)
E. RECORD the ICS Points that were available during performance of leakage calculation:
Computer Points Needed to Perform RCS Water Inventory 100% Power Inventory at 100%
Parameter I Instrument Computer Point -V Inputs to Total Leakage RCS Temperature Correction RCL AVG TavgTavg(1) 1 U0484 Irs: Y-\
Loop 11 Tavg T-68-2 TO400A T0400A [I C ,-
Loop 2 Tavg T-68-25 T0420A 0LI Loop 3 Tavg T-68-44 T0440A 0LI -
Loop 4 Tavg T-68-67 T0460A 0LI Pzr. Pressure 1/2/3/4 Avg Avg(2) 2 U0482 0LI -
Pzr. Pressure Ch. II P-68-340 P0480A 0LI -
Pzr. Pressure Ch. II P-68-334 P0481A 0LI -
Ch.lIl Pzr. Pressure Ch.1I1 P-68-323 P0482A 0LII Pzr. Pressure Ch.IV - P-68-322 P0483A 0LI Pressurizer Pzr. Level(3) 3 Level U0483 CL Pzr. Level Ch. II L-68-339 L0480A C L Pzr. Level Ch. II L-68-335 L0481A CL Pzr. Level Ch. III lii L-68-320 L0482A CL =
Volume Control Tank VCT Level L-62-130 [ LOI12A L0112A [E C Inputs to Identified RCS Leakage RCDT Level L-77-1 L2400A 0LI PRT Level L-68-300 L0485A 131 (1) RCL AVG Tavg is the average of the four narrow range loop temperatures.
(2) Pzr. Pressure 1/2/3/4 Avg is the average of the four narrow range Pressurizer Pressure Channels.
(3) Pzr. Level is the average of the three Pressurizer Level Channels F. IF ICS Points recorded in Section 4.1 [2] do NOT match those recorded in Section 6.2 Step [11] E, THEN ENSURE evaluation of the validity of the data is performed by engineering.
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Unit_____________ Date Date _ _ __
6.2 RCS LEAKAGE USING THE PLANT COMPUTER (Continued)
[12] IF any substep in step [11] cannot be completed, THEN
[a] TERMINATE this test.
[b] NOTIFY the Unit SRO that the test was invalid.
[c] NOTE in chronological test log why test has been aborted.
[d] OBTAIN a working copy of this procedure to restart test AND MAINTAIN the working copy in this SI package.
[e] ENSURE [HS-62-118A] in P-AUTO.
t 1
1st IV Iv
[13] IF calculation inputs are invalid, THEN
[a] INITIATE MANUAL function to correct inputs. o
[b] INITIATE execute function for calculated results. o
[14] PRINT a hard copy of the results. o
[15] ATTACH hard copy program output (printout) to surveillance procedure package. o
[16] WHEN all data collection has been completed, THEN NOTIFY Chemistry Lab that RCS sampling/chemical additions may be resumed, as necessary. o
[17] IF Sect. 6.2 Step [5][b] was performed for manual data collection, THEN PERFORM section 6.1.2 for restoration of equipment.
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Unit______________ Date __
6.2 RCS LEAKAGE USING THE PLANT COMPUTER (Continued)
NOTE 11 Due to the calculation methodology of rounding off numbers, Unidentified Leakage and Identified Leakage may not add up to computer generated total RCS leakage when leakage is small.
NOTE 22 -0.10 GPM may be An unidentified leakage more negative than 0.10 recorded as an acceptable result provided the total RCS leakage is on-going investigation to 1.0 GPM and there is an ongoing equal to or less than 1.0 determine the source of the inleakage. [C.2]
[18] IF unidentified leakage is more negative than 0.10
-0.10 GPM, THEN REPEAT data collection by changing and/or lengthening the time interval until an unidentified leakage term more positive than 0.10 GPM is obtained or total RCS leakage is equal to or
-0.10 less than 1.0 GPM (or until test must be aborted), AND [C.2]
RECORD results below (N/A any blanks t not used).
A. Calculations completed:
Time Interval
-Time Total RCS I~akage
-Total leakage =
= GPM Identified leakage
-Identified =
= GPM Unidentified leakage
-Unidentified =
= GPM B. Calculations completed:
Time Interval
-Time Total RCS leakage
-Total = GPM
-Identified Identified leakage =
= GPM Unidentified leakage
-Unidentified =
= \~ GPM
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Unit_____________ Date _ _ __
Oate 6.2 RCS LEAKAGE USING THE PLANT COMPUTER (Continued)
[19] 0.10 GPM IF an unidentified leakage more positive than -0.10 could not be obtained, OR IF four consecutive performances of this Instruction have resulted in a negative value of unidentified leakage, THEN NOTIFY Unit SRO and/or cognizant Systems Engineer that an investigation to determine the source of inleakage to the RCS must be initiated. [C.2] N)A
[20] CHECK appropriate box to indicate whether the following acceptance criteria were satisfied.
TECHNICAL SPECIFICATION ACCEPTANCE CRITERIA:
The maximum individual SG leakage is less than or equal toI5OGPD.
to 150 GPO. Yes No The total identified leakage is less than or equal to 10.0 GPM. El Yes LINo The total unidentified leakage is less than or equal to 1.0 1 .0 GPM. LI DYes Yes No ADMINISTRATIVE ACCEPTANCE CRITERIA:
The maximum individual SG leakage is less than or equal to75GPD.
to 75 GPO. Yes No
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0-SI-OPS-068-137.0 INVENTORY SYSTEM WATER INVENTORY Rev: 22 1&2 1&2 Page38of6l Page 38 of 61 Unit_ _ _ _ __ Date _ _ __
6.2 RCS LEAKAGE USING THE PLANT COMPUTER (Continued)
[21] IF any of the Technical Specification acceptance criteria stated in step [20] is NOT satisfied, THEN
[a] NOTIFY SM that RCS leakage exceeds limit and LCO 3.4.6.2 action b b must be satisfied.
[b] REFER to EPIP-1 EPIP1 for REP implementation.
[c]
[C] REFER TO AOP-R.01, AOP-R.O1, Steam Generator Tube Leak, or AOP-R.05, ReS RCS Leak and Leak Source Identification, as applicable.
[22] IF leakage is within Tech Spec limits but exceeds SIG leakage, administrative acceptance criteria for S/G THEN
[a] NOTIFY SM that primary-to-secondary primarytosecondary leakage exceeds administrative limit.
[b] REFER TO AOP-R.01, AOP-R.O1, Steam Generator Tube Leak. D
[23] WHEN leakage test is complete, THEN ENSURE [HS-62-118Al
[HS-62-118A] in P-AUTO.
jst 1st V IV END OF TEXT
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Unit_______ ___ _ Date(
7.0 POST 7.0 POST PERFORMANCE PERFORMANCE ACTIVITY ACTIVITY
[1]
[1] NOTIFY Unit NOTIFY Unit SRO SRO that test has that test been completed.
has been completed.
NOTE NOTE Graphs of Graphs of RCS RCS leakage are available trends are leakage trends available on on S:\Engineering\Systems\Systems Notebook\068 - Reactor Coolant Notebook\068 - Reactor Coolant System\Trending\Sl-1 37\Current data.
System\Trending\SI-137\Current data.
[2] unidentified leakage results:
EVALUATE unidentified
[a] COMPARE unidentified leakage result to value from previous (last) performance on this unit. D
[b] COMPARE unidentified leakage result to leakage trend graph maintained by Engineering. D
[3] IF any of the following conditions are met:
- RCS unidentified leakage exceeds 0.10 gpm OR
- RCS unidentified leakage has risen by more than 0.03 gpm from last performance OR
- RCS unidentified leakage shows a sustained rising trend above previous baseline (typical) value THEN PERFORM PERFORM the following:
[a]
[a] PERFORM an PERFORM an additional additional official leak rate official leak calculation rate calculation to to validate validate results results (using (using different time interval).
interval).
(step continued on (step continued page) next page) on next
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[b] IF rise in leak rate is confirmed by additional calculation(s),
THEN PERFORM the following:
- 1. EVALUATE recent activities to determine possible causes of rise in leak rate. 0
- 2. INITIATE ReS RCS leak search:
- REQUEST assistance from Systems Engineering as required. 0
determines leak rate is stable (NOT rising). 0
- 4. ENSURE PER initiated. 0
[c]
[C] IF rise in leak rate is NOT confirmed by additional calculation(s),
THEN LOG results in narrative log. 0LI
[d] INITIATE performance of OPDP-9 Emergent Issues.
END OF TEXT
SQN REACTOR COOLANT 0-SI-OPS-068-1 37.0 0-SI-OPS-068-137.0 SYSTEM WATER INVENTORY Rev: 22 1&2 Page4lof6l Page 41 of 61 APPENDIX A Page 11 of 1 I
U nit' - - - - - - - -
Unit Date _ _ __
Date___________
IDENTIFICATION OF RCS LEAKAGE NOTE 1 I Any attempts to isolate RCS leakage before completing the appropriate section of this Instruction will make the initial and final data VOID.
NOTE 2 An acceptable method for calculating leakage is to collect leakage in a container of known volume and time the fill with a a stopwatch. Leakage calculated in the following step must be a positive number or zero.
NOTE 3 All test equipment used in the following step must be listed in section 4.2.
[I]
[1] MEASURE and RECORD any other RCS leakage, source of the leakage, and method used to calculate leakage below (NIA any blanks not used).
(N/A LEAKAGE METHOD APPLICABLE DATA LEAK RATE SOURCE USED (GPM)
- r---
ri \
\\,\
\ t\
\(
- ~
\
~
~N N~
~
[2] SUM all leak rates identified in step [1], AND RECORD below:
Total leak rate =
= _ _ _ GPM
SQN REACTOR COOLANT 0-SI-OPS-068-1 37.0 0-SI-OPS-068-137.0 SYSTEM WATER INVENTORY Rev: 22 1&2 1&2 Page42of6l Page 42 of 61 APPENDIX B Page 11 of 33 Unit Unit'--_-'-_ __ Date i-O
.,-v OM REACTOR COOLANT DRAIN TANK LEAKAGE NOTE NOTE The following steps provide instructions for pumping down the RCDT after the initial RCDT pump down has been completed. These instructions may be performed as many times as necessary or marked NIA N/A if they are not required.
[1] ENSURE initial time and RCDT level/volume from Appendix C have been recorded on Data Sheet B-1.BI.
[2] WHEN RCDT approaches 50% level, THEN RECORD final time and RCDT level on Data Sheet BI. B-1.
NOTE The applicable section of 1 -1 is dependent upon
,2SO77l 1 ,2-S0-77 where the RCDT is to be pumped.
[3] GO TO 1,2-S0-77-1 1,2-SO--77-I PERFORM the applicable section, AND RETURN to step [4] of this appendix.
[4] RETURN both RCDT pumps handswitches to the PULLTOLOCK position:
PULL-TO-LOCK PUMP HANDSWITCH POSITION INITIALS A HS77--4A HS-77-4A PULLTOLOCK PULL-TO-LOCK B
B HS77---6A HS-77-6A PULLTO-LOCK PULL-TO-LOCK
[5] RECORD new initial time and RCDT level on Data Sheet B-1.
B-I.
SQN REACTOR COOLANT 0-SI-OPS-068-1 37.0 0-SI-OPS-068-137.0 SYSTEM WATER INVENTORY Rev: 22 1&2 1&2 Page43of6l Page 43 of 61 APPENDIX B B Page 2 of 3 Unit_____________
Unit'--_-+\_ __ Date ID l').A j Date_________
[6] CONVERT initial and final RCDT levels to gallons using E2 of Appendix E, AND Table E-2 RECORD on Data Sheet B-i. 8-1. A
[7] CALCULATE RCDT leakage using the following equation, AND
( _ _ _G=al Gal)( )- ( Gal)
RCDT Leak Rate = ----=..:.!.lni=tia=:.!..I...:..Vo=lu=m=e=---_--=-:Fi.:..;.:na=.1 Initial Volume Final -,-,Vo=l Volume u=mc:=e min))
min.
II Time t
RECORD on Data Sheet 8-1. B-i.
[8] WHEN final RCS leakage data has been collected, THEN CALCULATE total of all calculated RCDT leakages, AND RECORD on Data Sheet 8-1. B-i.
[9] CALCULATE average RCDT leakage using the following equation, AND
(( GPM)
Avg. RCDT Leak Rate =
= Total of All Calculated Leakage
(( )
Number of Data Points Taken RECORD on Data Sheet 8-1. B-i.
SQN REACTOR COOLANTCOOLANT 0-SI-OPS-068-I 37.0 0-SI-OPS-068-137.0 SYSTEM WATER INVENTORY SYSTEM INVENTORY Rev: 22 22 1&2 I&2 Page44of6l Page 44 of 61 APPENDIX B 8 Page 3of3 3 of 3 Unit'-----------=---
\
Unit__________ Date To Oltj Date_______
DATA SHEET BI 8-1 Data . - Initial Initial Final Calculated
. Initial Final Final Points . Level Volume Volume Leak Rate Time Time Level Taken (%) (Gal)
(%) (Gal) (GPM) 1 I (\\\1\
v~
2 3
~
4 ~
6 7
5
\
\
1 8 /
9 /
10 /
TOTAL OF ALL CALCULATE~DT ALL_CALCULATEDT_LEAK_RATES LEAK RATES Average RCDT Average le~:~
RCDT leak ra 7 GPM Data Recorded By II/
( Date Date Reviewed By Date
SQN SQN REACTOR COOLANT REACTOR COOLANT 0-SI-OPS-068-1 0-SI-OPS-068-137.0 37.0 SYSTEM WATER INVENTORY SYSTEM WATER INVENTORY Rev:
Rev: 22 22 1&2 1&2 Page45of6l Page 45 of 61 APPENDIX C C Page 11 of 55 Unit,_ _-=---_ _
Unit___________ -ID IA Date TD Date lJA %fY INITIAL/FINAL DATA INITIALIFINAL DATA NOTE I1 N/A steps in this Appendix, except for 8.0 (if applicable) if the Plant Computer RCS Leakage program is being used.
NOTE 22 NOTE Copies of this Appendix may be used if more than one data set is required provided all copies are included in the data package.
Initials Data Start Time: oY:;z ,I *lD(Jlr-j Date VOLUME CONTROL TANK (VCT) LEVEL Instrument Used: L0112MA LOI12MA D LI Ll62129 LI-62-129 Cij/
7 U1 (Check One)
--+4--'"'-'.3(~I_% :3 8".7 %
Initial Level Final Level PRESSURIZER (PZR) LEVEL Instrument Used: U0483MA DLI Ll68320 LI-68-320 rn-/
(Check One) Ll68--335A D LI-68-335A Li Ll68--339A D LI-68-339A Li CeD,3
(,3 % (j2O.) %
(yO.)- %
Initial Initial Level Final Level f!! PRESSURIZER PRESSURE PRESSURIZER Instrument PRESSURE U0482MA D Li PR68340 ~
Instrument Used:
Used: PP >1700
>1700 psig psig U0482MA PR-68-340 (Check (Check One) One) P168334 D PI-68-334 Li Pl68342A D PI-68-342A Li P << 1700 1700 psig P0499MA D Li Pl68342A D PI-68-342A Li P16866 D PI-68-66 Li 7)37 psig pJg J-3
- J J.- 3 </- Q2ig pg Initial Initial Press Press Final ~ess Final Fress Initial Initial Data Data Recorded Recorded By
- By: ~:
~~~~--------,I I 1]Q~t A
() Date 4-vf Date Final Final Data Recorded By:
Data Recorded By: I-Lel.~i=:.
--J---7~qJ------
I/ 'n Date P:_, I Date
SQN REACTOR COOLANT 0-SI-OPS-068-1 0-SI-OPS-068-137.037.0 SYSTEM WATER INVENTORY INVENTORY Rev: 22 1&2 1&2 Page46of6l Page 46 of 61 APPENDIX C Page 2 of 5 Unit- - - - 'I - - - - Date "TDJJ,A-y Date________
I
~ RCS ReS TEMPERATURE (T (T-AVG)
-AVG)
Instrument Used: T> 530 °Fof U0484MA LI0 TI682E TI-68-2E r.:a/
(Check One) of T << 530 °F U0486MA 0 Li TR681 TR-68-1D Li U0489MA 0 Li 57&*Q OF i Ij S'I'/. °F of Initial Level Final Temp rs;( REACTOR POWER r Instrument Used:
(Check One)
(Check One)
Ui 127 Percent Rated Core Thermal Power U1127 XI-92-5005C XI925005C Power Range NIS 0
~
Xl925006C Power Range NIS XI-92-5006C 0 U0485 Average Delta T (use when reactor power 0 less than 15% OR less than 40% with LEFM unavailable) 100. i 90 qq*qyo Initial Pwr Final Pwr Initial Data Recorded By:
\ ~ /I {3D.AI
~
- 7) Date Final Data Recorded By: / /I fDflA-t Date /
SQN REACTOR COOLANT 0-SI-OPS-068-1 37.0 0-SI-OPS-068-137.0 SYSTEM WATER INVENTORY Rev: 22 1&2 Page47of Page 47 of 61 APPENDIX C APPENDIXC Page3of5 Page 3 of 5 Unit Unit'--=r---+ __ Date lOCAl Date________
.0 PRESSURIZER RELIEF TANK (PRT) LEVEL JOTE Five PRT level readings should be taken approximately one minute E1 of App. E is used to convert PRT level (%) to gallons.
apart. Table E-1 Instrument Used: L0485MA 0LI LI-68-300 Ll68300 ~
(Check One)
Initial Level: (1) &:A %(2) (f!.'~ % (3)
% (y3 (j!"3 % (4) h~ %(5) (:x l? ).. %
(P). ).. % g:;-ZJ. gal Avg Level Avg Volume Final Level: (1) o~ %(2) %(2) &.3 (3 % (3) to} % (4) 03 %(5) ~d- %
&:2. q % g&;)J.. gal Avg Level Avg Volume 7.0 REACTOR COOLANT DRAIN TANK (RCDT) LEVEL NOTE 1 I RCDT Level (7.0) may be marked N/A if conditions do not permit obtaining RCDT level.
NOTE 2 Final RCDT data may be marked N/A if App. C will be used to calculate average RCDT leakage; however, initial data must be recorded. Table E2 of Appendix E is used to convert RCDT level (%)
E-2 (%) to gallons.
7
/'
Instrument Used: , , L2400MA LI 0 Ll771 FJ LI-77-1 G2I J3.S % ;;>4.'7 Initial Level Final Level i3'3 e'i. gal 'l'S. ~ gal Initial Volume Final Volume Initial Data Recorded By: By:_---!.:tn?::...::..-F:...--_ _ _ _ _/,/ J7j /J/v1 (J Date Final Data Recorded By: _ _ _ r-~ _
-f-+--_ _ _ _ _/.I 'T1JfJ~
y 4
- tI Date W
SQN REACTOR COOLANT 0-SI-OPS-068-137.0 0-SI-OPS-068-1 37.0 SYSTEM WATER INVENTORY Rev: 22 1&2 Page48of6l Page 48 of 61 APPENDIX C Page 4 of 5 Unit.
Unit_ _----'-_ __ DateTbD4)f Date"Tb () P.. y 8.0 COLD LEG ACCUMULATOR (CLA) LEVEL NOTE CLA data may be marked N/A if RCS pressure is greater than 683 psig and quantification of CLA leakage is not required.
8.1 CLA 1 I Instrument Used:
Instrument (Check One)
(Check One)
Used: \ \ Ilt 1'\1 /"
LI-63-129D LI63129 LI-63-119D LI63119
_ _-+--_ _gal Initial Volume Final Volume 8.2 CLA22 CLA Instrument Used: LI-63-109D LI63109 i::i (Check One)
_ _ _ _ _ gal gal al Initial Volume Volume 8.3 CLA33 CLA Instrument Used: LI- LI-63-81 0 LI6381 (Check One)
_ _ _ _ _,gal aal _ _ _ _ _gal Initial Volume Final Volume By _ _ _ _ _---I_ _ _ _/.I_ __
Initial Data Recorded By:
Date Final Data Recorded By: _ _ _ _ _---'lr--_ _ _,I_ __
Date
SQN REACTOR COOLANT 0-SI-OPS-068-1 37.0 0-SI-OPS-068-137.0 SYSTEM WATER INVENTORY Rev: 22 1&2 Page49of6l Page 49 of 61 APPENDIXC APPENDIX C Page 5 of 5 I
Unit___-'-I_ __
Unit Date ~-rD{).4 7 8.0 COLD LEG ACCUMULATOR (CLA) LEVEL (Continued) 8.4 CLACLA4 4 Instrument Used: Ll6382 Li LI-63-820 LI6360 0 LI-63-60 Li (Check One)
JIA .
Initial Volume gaI gal _ _----:,t--_gal a1-olume olume gal
,/
Initial Data Recorded By: _ _ _ _-r-_ _ _ _--....:'_ __
4 Date Final Data Recorded By: _ _ _ _N/ ...:..-_ _ _ _--:'I_ __
Date Final Data End Time :: _ _ _ O_G_'_Lf"'--"'-::L_ _ _ _,i TDJJAY T7L1A I Date Initial Data r 12 () Final ~ata 0" r i I "\
Final Data StartTime:
Start Time: O"i .Jo
- End Time:
EndTime:________ lO '--I d- = = )~
)Y mm.
min.
A Time L1 Data Reviewed By: _ _ L....;~~......=:...,~---~_ _--'-/_-_j I _O--,b_A~'y,--
0:
Date
SQN SQN REACTOR COOLANT REACTOR COOLANT 0-SI-OPS-068-1 37.0 0-SI-OPS-068-137.0 SYSTEM WATER INVENTORY SYSTEM INVENTORY Rev:
Rev: 22 22 1&2 1&2 Page500f6l Page 50 of 61 APPENDIX 0 D Page 11 of 99 I
Unit' - - - - -\ - ' - - - -
Unit -rO Date iOfAy DAy RCS LEAKAGE CALCULATIONS CALCULATIONS NOTE I1 NOTE All calculations must be performed manually. manually. Verification may be performed using the computer.
NOTE 22 All calculations should be carried out to two places after the decimal.
Signs must be carried through all calculations.
NOTE 33 Calculations in this Appendix may need to be performed more than once. If multiple calculations are required, copies of this Appendix may be used.
1.0 1.0 TOTAL RCS LEAKAGE r!f5.1 Volume Control Tank (VCT)
[( 40.\ %)-(
% )- ( '39>. 7 x 19.27 gal/%
%)Jx19.27ga11%
%)]
VCT Leakage =
= Initial Level Final Level
~
Il)-lY mm.)
min.)
Time D. Time VCT Leakage = _ _....:....1_*--,y_L,_\___GPM VCTLeakage=
Pressurizer 3
I .2 (Pzr) UNIT 2 only ressurizer (pzr)- l~ Ij A A '
i/[
NOTE 1I CALCULATE initial PZR volume by using the following equation:
Vft (specific volume of a fluid) and Vg (specific volume of a 9 V as)values for current plant conditions can be found using a copy p-the a steam tables.
NOTE 2 multipli In the following equation the multipliyv' the Pressurizer Volumetric
-iifPressurizer 9
rI.
7 enginee Constant determined by engineeX*r1g.
. . I PZR Initial ImtJa PZR V Vol I _ (PZRLevel 0 -= - - - - +
PZRLeveI 100% - PZRLevel PZRLeve1 + 100% )* 102 gal
- ~
gal ft Ib *%level
- %level
~ ~ /m m
SQN SQN REACTOR COOLANT REACTOR COOLANT O-SI-OPS-068-1 0-SI-OPS-068-137.0 37O SYSTEM WATER SYSTEM WATER INVENTORYINVENTORY Rev: 22 Rev: 22 1&2 1&2 Page5lof6l Page 51 of 61 APPENDIX D D Page 22 of 99 Unit" - - I- ' - - - - - Date JVOAt Date r2OY Initial PZR Vol = NI (t
---~~-+------~~
100 100-
%level Initial PZR Vol = = _________ gal By
~LCULATE LCU LATE Final PZR volume by using the following equation:
NOTE I1 Vf (specific volume of aa fluid) and Vg (specific volui Vf volu of aa gas)values for current plant conditions can be found usin usinc 0PY of the steam tables.
NOTE 2 In the following equ the multiplier is the Pressurizer Volumetric Ined by engineering.
=( pz~~evel -v__O_o/c_o-_PZ_R_~_ge_V_el_ _ _ )'2.02 gal * ~m ** %Ievel PZRLeveI ft3/
Final PZR Vol
/lb %level m
100 - % gal
- ft3 /
Final PZR Vol = +------~-:-3-..,-- *2.02 /~ *%level lb m
Final PZR Vol = = ____ gal ed By Reviewed By
SQN REACTOR COOLANT 0-Sl-OPS-068-1 37.0 0-SI-OPS-068-137.0 SYSTEM WATER INVENTORY Rev: 22 1&2 1&2 Page52of6l Page 52 of 61 APPENDIX 0 D Page 3 of 99 Unit. _ - - ' - - - - - DnA-Date________
Date Y
~CALCULA CALCULATE TE PZR leakage rate by using the following equation:
Initial PZR Volume Final PZR Volume PZR Leakage =
Litime gal PZR Leakage = = --1~--=----+-------='-
mm PZR Leakage = __-+__ gpm
=
By Reviewed By rf!' (Pzr) UNIT 1 Pressurizer (pzr)- I only PALCULATE initial PZR volume using the following equation:
NOTE 1 I V Vff (specific volume of a a fluid) and Vg (specific volume of a gas)values for current plant conditions can be found using a copy of the steam tables.
NOTE 2 In the following equation the multiplier is the Pressurizer Volumetric Constant determined by engineering.
\
. . I PZR IInitial mtla PZR V 0 =
Vol PZRLevel 100%
I (PZRLeVel Vf
+
+---
PZRLeveI 100% - PZRLevel Vgg V
J .01 I::>oal
- ft~
2201 3
ga1*ft /
lb ** %Ievel lb %level
=
/ ln m
... PZR Vol Initial PZR Imtlal Vol =[ loO,3 ft3/
=
+
100-~D.J%}
. ft3/ .oi 2.01 33 //
- ft gal*ft
/Ib 1
Ab *%level m *%Ievel o.o;)(PY7 /Ib m O.i5 b<O/lb m Initial PZR Vol = OO) .cr
= 600)
.i gal formed By 7
(
Revied By
SQN SQN REACTOR COOLANT REACTOR COOLANT 0-SI-OPS-068-1 37.0 0-SI-OPS-068-137.0 SYSTE~ WATER INVENTORY SYSTEM INVENTORY Rev: 22 Rev: 22 1&2 1&2 Page53of6l Page 53 of 61 APPENDIX D D Page 44 of 99 Unit- - - - - - -
Unit___________ Date--ro t~A DateTT)SAJ
~ALCULATE ALCULATE Final PZR volume using the following equation:
volume using
~E OTE I1 VI (specific volume of aa fluid) and Vg (specific volume of aa gas)values Vf for current plant conditions can be found using aa copy of the steam tables.
In the following equation the multiplier is the Pressurizer Volumetric Constant determined by engineering.
3/
Final PZR Final PZR Vol Vol = (
= ( PZRLeve1 PZRLevel ++ 100% 100% - PZRLeveI PZRLevel *2O 1
- 2.01 al **ft ggal /
3 fi
/Ib *%Ievel
- /olevel Vr Vf Vg Vg J / ibmm F " I PZRV 1-[
Final ma PZR Vol 0 -
Final PZR Vol =
=
=
[ (cO,)
.0:;. ~ elf" qg q yqqq.j
/L ft3/ +
/lb m ; fY11 gal iou
% + 100-&,0*)
ft3/
/lb m/L
% ]*20 gal *ft
%)*201
" I
- 3
/lb
/m
/ * %ievel m * %level -
Pemed By Reviewe(,
~ALCULATE CALCULATE PZR leakage rate using the following equation:
\
Initial PZR Volume - Final PZR Volume PZR L eakage=---------------------------
Leakage =
L1time z\time PZR L
=
eakage =
Leakage 5oQ.( gal-SOC;). q _ q(i ,I gal gal '-\1- ~(q9 gal 1
\ ;). Y min mm PZR Leakage == 01 O 0030 30" gpm Pen med By Reviewed y
SQN SQN REACTOR COOLANT REACTOR COOLANT 0-Sl-OPS-068-1 37.0 0-SI-OPS-068-137.0 SYSTEM WATER SYSTEM WATER INVENTORY INVENTORY Rev:
Rev: 22 22 1&2 1&2 Page54of6l Page 54 of 61 APPENDIXD APPENDIX D Page 5 of 99 Unit. _ - - ' - - - - - Date/D0Aj DateTDtA
~CS Temperature Correction[C.1]
NOTE NOTE The multiplier used in the following equation is the RCS Temperature Correction Volumetric constant as determined by engineering.
~nitial nitial Conditions:
6 RCS pressure == ))37 3 7 14.7 ==
psig ++ 14.7 J ~ 5i7 5/*7 psiapsi a RCS temperature == 5 {(p. 1
'S 7* (1°F °F Specific volume (vj) (Vi) == (9. 30 ?o 0.30 qv ft /fe/Ibm 3 lbm Density = 1 == 3. d- 3
= 1lvi 1/v . Ibm/ft 3
3(,;)... Ibm/fe (Final Final Conditions: .
RCS pressure = = 2 3 tf psig ++ 14.7 =
.2;).. = 1 SIR
- 2;) <j c2c) g, 72 psia RCS temperature = 5"77 = S?7. Ij OF °F Specific volume (Vi) (v) = D. 30 ftj
= Id /lbm 3
ft fe/Ibm pensity=1/v=
1 tensity = 1/Vi = 33.L/5
..) 4.25 Ibm/fe 3
Ibm/ft
~ Temperature Correction:
)
3(j. ~-5k). Ibm/ft3 )
(((3.3Jbm/ft -
(3.
)
3 )4J S Ibm/ft (1I?Slbm/ft j 3 * // Ibm 3
gal*ft
) ]
- 1298.19 gal*fe Temp Corr. =
Initial Density, Density Final Density time Temperature Correction
= - O. 0.
0 0 lo {y 0 GPM
SQN REACTOR REACTOR COOLANT COOLANT 0-Sl-OPS-068-1 37.0 0-SI-OPS-068-137.0 SYSTEM WATER INVENTORY Rev: 22 1&2 1&2 Page55of6l Page 55 of 61 APPENDIX D D Page6of9 Page 6 of 9 Unit -
I( Date 11> DI\
Date1E4j 1 fJ)Total Res Leakage Total RCS Total RCS Leakage == ((_____)) ++ ((_____)) ++ (,_ _ _ __ (____________
VCT PZR Temp Corr Total RCS Leakage == _ _ _ _ _ _ _ GPM Performed By Reviewed By 2.0 IDENTIFIED IDENTiFIED LEAKAGE NOTE Leakage into the PRT or CLA tanks will always be a positive value (or zero) when RCS pressure is greater than the specific tankstank's pressure. If negative tanks leakage must be set leakage is calculated under these conditions, that tank's equal to zero.
2.1 Pressurizer Relief Tank (PRT)
[(
[ ( gal)(
gal) - ( gal)))
gal)
PRT Leakage =
= Final Volume Initial Volume mm) min)
~ Time PRT Leakage = ________ GPM PRTLeakage=
NOTE RCDT Level (2.2) may be marked N/A if conditions do not permit obtaining RCDT level.
2.2 Reactor Coolant Drain Tank (RCDT)
[(
[ ( _ _ _ _----o;Jg=..;,al ) - ( gal)]
gal )]
RCDT Leakage = = Final Volume Initial Volume mm) min)
~
i\Time Time RCDT Leakage = _ _ _ _ _ _ _ _GPM
=
Performed By Reviewed By
SQN REACTOR COOLANT 0-SI-OPS-068-1 0-SI-OPS-068-137.0 37.0 SYSTEM WATER INVENTORY Rev: 22 1&2 1&2 Page56of6l Page 56 of 61 APPENDIX D Page 7 of 9 Unit_____________
Unit
._----- Oate _ _ __
Date__________
2.3 Steam Generator (SG)
NOTE 1I SG leak rates are obtained by 1, 2SlCEM0681 37.5.
2-SI-CEM-068-137.5.
O-SI-CEM-OOO-050.0 is performed every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and looks at activity levels OSlCEM000050.O which will determine if those leak rates from the last performance of 1, 2SlCEM068--1 2-SI-CEM-068-137.5 37.5 have increased.
inOreased.
NOTE 2 NIAd if activity is too low to be Individual steam generator leakage may be N/A'd separately identified.
A. SG1 Leakage =
GPD GPO B. SG2 Leakage
GPD GPO C. SG3 Leakage
= GPD GPO D.
O. SG4 Leakage =
GPD GPO Total SG leakage
GPO GPD
= _ _ _ _ GPM 1440 min/day mm/day OaterTime Date/Time O-SI-CEM-OOO-050.0 0SlCEM--000050.0 performed: _ _ _ _ _.1/ _ _ __
Date Time OaterTime 2SlCEM0681 37.5 performed: _ _ _ _.1I _ _ __
Date/Time 1, 2-SI-CEM-068-137.5 Date Time Recorded by
SQN REACTOR COOLANT REACTOR 0-SI-OPS-068-1 37.0 0-SI-OPS-068-137.0 INVENTORY SYSTEM WATER INVENTORY Rev: 22 1&2 1&2 Page57of6l Page 57 of 61 APPENDIX D Page 8 of 9 Unit,_ _ _ _ __
Unit_______________ Date _ _ __
Date___________
2.4 Cold Leg Accumulators (CLA)
NOTE CLA leakage calculations may be marked N/A NIA if RCS pressure is greater than 683 psig and quantification of CLA leakage is not required.
required, gal) gal)]
J(Final
[(Final Volume gal) - Cnitial
- (Initial Volume gal)]
A., CLA 11 LLeakage A ea kage -= ( , )
( A
~
Time T Ime mm min CLA 11 Leakage = __________GPM
=
gal gal)]
[(Final
[(Final Volume V olume gal)) - Cnitial
- (Initial Volume gal)]
B., CLA 2 LLeakage B eakage ==
( ,)
' mm min ATime
~ T Ime CLA Leakage== __________ GPM CLA22 Leakage gal) gal)]
[(Final
[(Final Volume gal) - Cnitial (Initial Volume gal)]
C.. CLA 3 LLeakage C eakage =
=
( ,)
( A Time
~ T Ime mm) min CLA 3 Leakage = = __________GPM gal) gal)]
[(Final
[(Final Volume gal) - Cnitial
- (Initial Volume gal)]
0, CLA 4 D. CLA 4 Leakage Leakage = ( ,)
' mm min ATime
~ T Ime Leakage = __________GPM CLA 4 Leakage=
CLA4 Total CLA leakage == _ _ _ _ GPM By Performed By Reviewed By
SQN REACTOR COOLANT 0-SI-OPS-068-1 37.0 0-SI-OPS-068-137.0 SYSTEM WATER INVENTORY Rev: 22 1&2 Page58of6l Page 58 of 61 APPENDIX D 0 Page9of9 Page 9 of 9 Unit_ _ _ _ __
Unit______________ Oate _ _ __
Date__________
2.5 Other Identified Leakage NOTE The following value may be marked N/A if no additional identified leakage sources (i.e., Appendix A) are to be included.
Other identified leakage (Appendix A) = _ _ _ _ GPM
=
2.6 Total Identified Leakage Total identified leakage =
= +
+ +
+ _ _ __
+
+ +
+ + -----
+
Total CLA CCPIT/HUT Other Total identified leakage =_______ GPM
=
3.0 UNIDENTIFIED LEAKAGE Unidentified leakage = ______
=
Total leakage Identified leakage Unidentified leakage leakage= = _______ GPM Performed By Reviewed By
SQN Cl) 0 Z REACTOR COOLANT 0-SI-OPS-068-137.0 (DD co -
0 (A)
C) z0 rnrri ZZ ao
>0 I 0) -.4 0
SYSTEM WATER INVENTORY -< -I m -< Rev: 22 CD C,) <
1&2 - Qo 1%) Page 59 of 61 CD o - o*) -
APPENDIX E CDZ -*D rom Page 1 of 2 TABLE E-1
-I 03 I m 171 -
PRESSURIZER RELIEF TANK (PRT)
<Fi
-D ni C) -I rC om mz C.) I,,
LEVEL VS. VOLUME
- Level (%)
r Volume Level (%) Volume Level (%) Volume Level (%) e Volume 01010101010101 I I PPb3 0 CD CD o CD CD CD
- - a-(Gal) (Gal) (Gal) (Gal)
()<
0.0 317.0 25.0 3033.7 50.0 6732.9 75.0 10432.0 (0CDCDCDCDCDCDCDCDCDCDCDCDCDCDCD0)0)0)0)------J A)(A)CA)N)N)N)N)N)
CD 01 k Q) - 0)
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SQN Cl) Z REACTOR COOLANT 0-SI-OPS-068-137.0 mm C) >0 zo
-oo CD c;E)
SYSTEM WATER INVENTORY Cl) Cl) I -1m <r m> Rev: 22 1&2 -
e
%3 Page 60 of 61 COMO o -h APPENDIX E Page 2 of 2 (Dz N)m TABLE E-2
-1 w
I m
m REACTOR COOLANT DRAIN TANK (RCDT) m > 0 rC) ma <0 I- CZ C,
-I z C) -i LEVEL VS. VOLUME Level (%) Volume Level (%) Volume Level (%) Volume Level (%) Volume N)N)N)---<
0)
-CDCD(0CDCDCDCDCD(0CDCOCOCOCOCOCOCOCO0)CO-ir r
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.t CO C?) CO -1 9.0 38.4 34.0 118.5 59.0 213.7 84.0 300.5
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CO N) CO 16.0 57.7 41.0 144.6 66.0 239.8 91.0 319.9 (0 C) N) C?) 01 CO CO CD 17.0 60.8 42.0 148.4 67.0 243.5 92.0 322.4 3
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- 69.0 250.8 94.0 327.4 0
20.0 69.9 45.0 159.8 70.0 254.4 -
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SQN REACTOR COOLANT 0-SI-OPS-068-1 37.0 0-SI-OPS-068-137.0 SYSTEM WATER INVENTORY Rev: 22 1&2 1&2 Page6lof6l Page 61 of 61 SOURCE NOTES REQUIREMENTS SOURCE IMPLEMENTING STATEMENT DOCUMENT STATEMENT Take RCDT data over same NRC Exit with C. Chung Ci C.1 interval as other data. The 13088 (1-30-88) test should last at least two hours.
All Tavg T-avg changes shall be considered.
Steps to take when negative NRC Inspection Report C.2 unidentified leakage is 50327,328/8916.
50-327,328/89-16.
calculated. Revised corrective action for NOV 50-327, 50327, 328/891602 328/89-16-02 L44 891226 801 Procedures that do not contain TROI NCO 970071001 C.3 appropriate verification requirements will be revised. This item is not annotated within the procedure, since the entire procedure must meet the verification program requirements
JPM2.4 0210
- Page 1 Df 8 Pagelof8 Rev. 00 Rev.
SEQUOYAH NUCLEAR PLANT PERFORMANCE MEASURE JOB PERFORMANCE JPM # Admin 2.4 0210 Calculating Maximum Reactor Vessel Vent Time PREPARED!
REVISED BY: Date!
Date/
VALIDATED BY: ** Date!
Date/
APPROVED BY: Date!
Date/
(Operations Training Manager)
CONCURRED: **
- Date!
Date/
(Operations Representative)
- Validation not required for minor enhancements, procedure Rev changes that do not affect the JPM, or individual step changes that do not affect the flow of the JPM.
JPM2.4 JPM2.4 0210 0210 Page 22 of8 Page of 8 Rev.
Rev. 00 NUCLEAR TRAINING NUCLEAR TRAINING REVISION/USAGE LOG REVISION/USAGE LOG REVISION REVISION DESCRIPTION OF DESCRIPTION OF VV DATE DATE PAGES PAGES PREPARED/
PREPARED/
NUMBER NUMBER REVISION REVISION AFFECTED AFFECTED REVISED BY:
REVISED BY:
00 Initial Issue Initial Issue YY 01/05/10 01/05/10 All All M.
M. Hankins Hankins Vv - Specify Specify ifif the JPM change the JPM change will will require require another another Validation Validation (Y or N).
(Y or N).
See cover See cover sheet sheet for for criteria.
criteria.
JPM2.4 JPM2.4 02100210 Page Page 30f8 3 of8 Rev.
Rev. 00 SEQUOYAH SEQUOY NUCLEAR PLANT AH NUCLEAR PLANT ROISRO ROISRO JOB PERFORMANCE JOB PERFORMANCE MEASUREMEASURE Task Task task ##
JAITA task JAITA Calculating Maximum Calculating Maximum Reactor Reactor Vessel Vessel Vent Vent Time Time Respond to Voids in the Reactor Vessel Respond to Voids in the Reactor Vessel per per FR-I.3 FR-I.3 3110130601 3110130601 KIA Ratings:
KIA Ratings:
2.4.13 2.4.13 4.0/4.6 4.0/4.6 Task Standard:
Evaluation Method: Simulator _ __ In-Plant _ _ _ Classroom ---,X'-!....-_
X
========================================================================
Performer:
NAME NAME Start time _ __
Performance Rating: SAT UNSAT Performance Time Finish time _ __
Evaluator: I/- - - - - -
SIGNATURE DATE
========================================================================
COMMENTS COMMENTS
JPM2.4 JPM2.4 02100210 Page Page 44 of of 88 Rev.
Rev. 00 SPECIAL INSTRUCTIONS SPECIAL INSTRUCTIONS TO TO EVALUATOR:
EVALUATOR:
( 1. 1. Critical step Critical step are are identified.
identified.
- 2. 2. Any UNSAT Any UNSAT requires requires comments comments
setting.
4.4. Ensure operator Ensure operator performs performs the the following following required required actions actions for for SELF-CHECKING; SELF-CHECKING;
- a. Identifies the
- a. Identifies the correct correct unit, unit, train, train, component, component, etc.etc.
- b. Reviews
- b. Reviews the the intended intended action action and and expected expected response.
response.
- c. Compares the
- c. Compares the actual actual response response to to the expected response.
the expected response.
Validation Time:
Validation Time: CR CR 15 15 min mm Local - - - - -
Local Tools/EquipmentlProcedures Needed:
Tools/Equipment/Procedures Needed:
REFERENCES:
REFERENCES:
Reference Title Title Rev Rev No.
No.
EA-0-7 EA-0-7 Calculating Maximum Calculatin Maximum Reactor Reactor Vessel Vent Time 2 jk Task Number Task Title Cont TRN 3110130601 Respond to Voids in the Reactor Vessel per FR-1.3 FR-I.3 Y
=================================================================
READ TO OPERATOR Directions to Trainee:
II will explain the initial conditions, and state the task to be performed. II will provide initiating cues.
All steps shall be performed for this task. When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet II provided you.
INITIAL INITIAL CONDITION CONDITIONS: S:
Pzr Level is 95% -95%
RCS Pressure Pressure is is 1000 1000 psig psig (P1-68-62)
(PI-68-62)
NO NO RCPs RCP's Running RVLIS RVLlS UpperUpper Plenum Plenum Range 95% -95%
Unit Unit 11 isis performing performing FR-I.3, FR-1.3, Voids in in Reactor Vessel, Step Step 20 20 11U0983 U0983 indicates indicates 223°F 223°F I1U0928 U0928 is is inoperable inoperable Containment Containment HydrogenHydrogen Concentratio Concentration per Chemistry n per Chemistry Supervisor Supervisor is is 1.3% (15 minutes 1.3% (15 minutes ago) ago)
TSC is TSC is not not available available atat this this time time INITIATING INITIATING CUES:CUES:
The US The has directed US has directed you you to to perform perform EA-0-7 EA-0-7 to to calculate the maximum calculate the reactor vessel maximum reactor vessel vent vent time.
time.
Return completed performance of EA-07 Return completed performance of EA-07 to the US. to the US.
PERFORM PERFORM all all calculations calculations to the nearest to the nearest tenth.
tenth.
JPM2.4 JPM2.4 0210 0210 Page Page 55of8 of8 Rev.
Rev. 00 Job Performance Job Performance Checklist:
Checklist:
STEPISTAN STEP/ST DARD ANDARD SAT/UNSAT SATIUNSAT STEP 1.:
STEP 1.: [1] OBTAIN
[1] OST AIN and and RECORD RECORD the the following following data:
data: SAT SAT RCS Pressure RCS Pressure
- UNSAT UNSAT NOTE:
NOTE: Per initial Per initial conditions, conditions, PI-68-62, P1-68-62, RCSRCS pressure, pressure, is is indicating-4000 psig indicating-1000 psig STANDARD: Operator STANDARD: Operator records records RCS RCS pressure pressure as provided in as provided in the the initial initial conditions or conditions or from from the the cue.
cue.
STEP 2.:
STEP 2.: Containment lower Containment lower compartment compartment average average air temperature (Tctmt)(Tctmt) SAT SAT NOTE:
NOTE: Per initial Per initial conditions, conditions, computer computer point U0983 U0983 indicates indicates 223°F 223°F UNSAT UNSAT STANDARD: Operator records 223°F for the lower compartment temperature.
STANDARD:
STEP 3.:
STEP 3.: Containment lower compartment volume at standard temperature and pressure (A) - SAT NOTE:
NOTE: Per initial conditions, Computer point U0928 is inoperable. UNSAT STANDARD: Operator records that the computer point is not available.
STANDARD:
STEP STEP 4.: Containment Hydrogen ConcentratioConcentration n (H)
- SAT SAT NOTE:
NOTE: Per initial conditions, Chemistry Supervisor reported Containment Hydrogen concentration 1.3 1.3 %% - fifteen minutes UNSAT ago.
ago.
STANDARD STANDARD:: Operator records hydrogen hydrogen concentration concentration provided provided in in cue.
cue.
STEP STEP 5.:
5.: [2.a]
[2.a] DETERMIN DETERMINE E containment containment lower lower compartment compartment volumevolume at at SAT SAT standard standard temperature temperature and and pressure pressure (A)
(A)
- a. IfIf computer
- a. computer point point U0928 U0928 available available ......
- UNSAT UNSAT NOTE:
NOTE: Per initial conditions, Per initial conditions, U0928U0928 is not available is not available operator operator continues continues with with the the next next substep.
substep.
STANDARD STANDARD: : Operator Operator N/A N/A this this substep.
substep.
JPM2.4 JPM2.4 0210 0210 Page Page oof8 6of8 Rev.
Rev. 00 Job Performance Job Performance Checklist:
Checklist:
STEP/STAN STEP/ST DARD ANDARD SATIU NSAT SAT/UNSAT STEP 6.:
STEP 6.: [2.b] IF
[2.b] IF computer computer point point U0928 U0928 NOT NOT available, available, THEN THEN SAT SAT CALCULATE AA as CALCULATE as follows:
follows:
_UNSAT UNSAT 383,000cuft 383,000 cu ft X X 492Ro 492R° = 492 492 == 383,000 383,000X.72 =
X.7 268,100 cu ft 68,lOOcuft (460 ++ 223°F)
(460 223°F) 683° 683° Critical Critical Step Step STANDARD: Operator STANDARD: Operator performs performs substep substep b, b, and and determines determines A= A= 268,100 cu ftft 268,100 cu STEP 7.:
STEP 7.: [3] DETERMINE
[3] DETERMINE maximum maximum hydrogen hydrogen volume volume that that can can be be vented _SAT SAT (B) WHILE maintaining (8) maintaining containment hydrogen hydrogen concentration less concentration less than than 3%.3%. UNSAT UNSAT B=
8= (3%-H%) X A CU FT 1.7 X 268,100 == 4557.7
== 1.7 100% 100 Critical STANDARD: Operator utilizes data from step 4.2.1 for Containment Hydrogen Step ep STANDARD:
(3%-1.3% 1.7%) and step 4.2.2 (b) for the lower concentration (3%-1.3%=
compartment volume, and performs calculation to determine the max hydrogen volume that can be vented while maintaining the containment hydrogen concentration less than 3%.
STEP 8.:
STEP 8.: [4.a} DETERMINE hydrogen flow rate as a function of
- a. RECORD RCS pressure _UNSAT UNSAT 1000 psig 4..2.1 4 .. 2.1 STANDARD:
STANDARD: Operator Operator records RCS pressure as given in the initial conditions.
STEP STEP 9.:
9.: [4.b]
[4.b] DETERMINE DETERMINE hydrogen hydrogen flowflow rate (C)(C ) Using Using Curve Curve 8,8, SAT SAT Hydrogen Hydrogen Flow Flow vs vs RCS RCS Pressure:
Pressure:
_UNSAT UNSAT C=
C= 3250(range3 3150-3350) SCFM 3250 (range l5O-3350) SCFM (Curve (Curve 8) 8)
Critical Critical STANDARD:
STANDARD: Operator Operator uses uses the the RCS RCS pressure pressure from from 4.2.1 to determine 4.2.1 to determine Step Step hydrogen hydrogen flow flow rate using Curve rate using Curve 8. 8. Range Range 32503250 +1-
+/- 100 100 SCFM.
SCFM.
JPM2.4 JPM2.4 0210 0210 Page ge7&8 7 of 8**
Rev.
Rev. 00 Job Performance Job Performance Checklist:
Checklist:
STEPISTANDARD STEP/STANDARD SAT/UNSAT SAT/UNSAT STEP 10.:
STEP 10.: [5] CALCULATE maximum
[5] CALCULATE maximum venting venting time time (T):
(T): SAT SAT T=
T= BBCUFT CU FT - UNSAT UNSAT C Standard C Standard CU FT/Minute CU FT/Minute Critical Critical T=
T= 4557.7 4557.7 1.4 +/-
== 1.4 +1- 0.1 minutes 0.1 minutes Step Step 3250 (3150 3250 to 3350)
(3150 to 3350)
Cue:
Cue:
STANDARD: Operator STANDARD: Operator calculates the maximum venting the maximum venting time.
time.
STEP 11.:
STEP Operator returns complete performance of EA-0-7 EA-0-7 to the Unit SAT Supervisor.
Supervisor.
- UNSAT STANDARD: Operator returns complete performance of EA-0-7 to the Unit STANDARD:
Supervisor.
Of JPM End OfJPM
JPM Admin 2.4 JPM Admin 2.4 2010 2010 Page 8 of8 Page8of8 Rev.
Rev. 00 CALCULATION
SUMMARY
CALCULATION
SUMMARY
SHEET SHEET FOR FOR EXAMINER EXAMINER Determine Lower Determine Lower Compartment Compartment Volume Volume CA) (A)
AA = 383,000 cu 383,000 cuftft xx 492°R (460 (460 ++ Tc!mt Tctmt OF)
°F)
A= 383,000 A= 383,000 cu cu ftft X 492Ro X 492R° = 492 492 == 383,000 383,000 X X 0.7 =268,100 cu 0.7=268,100 Cu ftft (460 223°F)
(460 ++ 223°F) 683° 683° Determine Max Determine Max Hydrogen Volume That Can Be Vented (B)
(3% - H%) x A cu
- cuff ft B=
100%
B B= (3%-H%) X A CU FT =
= 1.7 268,100 = 4557.7 X 268.100 100% 100 Determine Hydrogen Flow rate (C) CC )
C = _ _ _ _ _ SCFM.
(Curve 8)
(Curve C= 3250 (range 3150-3350)
C= 3250 3150-3350) SCFM SCFM Calculate Calculate Max Max Vent Vent Time Time (T)CT)
BB cuft cu ft T=
T =
CC standard standard cu cu ft/minute ftlminute T= 4557.7 4557.7 ==1.4 1.4 minutes minutes +1- 0.1 minutes
+/- 0.1 minutes 3220 (3200 to 3220 (3200 to 3250) 3250)
End End of of Sheet Sheet
READ TO REA'D TO OPERATOR OPERATOR Directions to Directions to Trainee:
Trainee:
II will will explain explain thethe initial initial conditions, conditions, andand state state the the task to be task to be performed.
performed. II will will provide initiating cues.
provide initiating cues. AllAll steps steps shall shall be performed for be performed for this this task task inin aa classroom.
classroom.
When you When you complete complete the the task task successfully, successfully, the the objective objective for for this this job job performance performance measure measure will will be be satisfied.
satisfied. Ensure Ensure you you indicate indicate to to me me when when you you understand understand youryour assigned task.
assigned task. ToTo indicate indicate that that you you have have completed completed your your assigned task return assigned task return the handout the handout sheet sheet II provided provided you.
you.
INITIAL CONDITIONS:
INITIAL CONDITIONS:
Pzr Level is Pzr Level is -95%
95%
RCS Pressure Pressure is 1000 1000 psig (PI-68-62)
(P1-68-62)
NO NO RCP'sRCPs Running RVLIS RVLlS Upper Plenum Range -95% 95%
Unit Unit 1I is performing FR-1.3, FR-I.3, Voids in Reactor Vessel, Step 20 1U0983 1U0983 indicates 223°F 1I U0928 is inoperable Containment Hydrogen ConcentrationConcentration per Chemistry Supervisor is 1.3%
(15 minutes ago)
TSC is not available at this time TSC INITIATING INITIATING CUES:
The US has directed you to perform EA-0-7 to calculate the maximum reactor vessel vent vent time.
Return completed performance of EA-07 to the US. US.
PERFORM PERFORM all all calculations to the the nearest tenth.
tenth.
JPM21-JPM 21 -11AA Pagee 1o Pag loff9 9
Rev.. 00 Rev SEQU UO OY YA AH H NU NUCL CLE EA AR PL PLA AN NT JOB PE PER RF FO OR RM MA AN NCE CE M MEA EASU SURE R E JPM M 21 2I-I -1A A Res Re sp po onndd to a Failu re of PRM N- N-4 411 PREP EPAR ARED EDII REVISED BY:
Da Datte!
e!
VALID ATED BY: **
Da Datte!
e!
(O Date!
(Op per eraatio tionnss Training Manager) er)
CONCURRED: **
Date!
(O (Op per atio era nss Re tion Reppre sen res enttati ativve) e)
- Validat ion not idation not req requir edd for minor enhancements, uire do do not not aff s, procedureure Rev Rev changess tha thatt affeect ct the JPM JPM,, oror individual ual ste step p cha the JPM.. nge s tha tha tt do do not not aff affeect ct the the flow flow ofof
n).
(
JPM21 JPM21-1A-1A Page Page22of9of 9 Rev.
Rev.0O-NUCLEA NUCLE ARR TRAIN TRAININ INGG REVISIO REVIS NIUSAG ION/US AGEE LOGLOG REVISIO REVIS IONN DESCRIIPTION DESCR PTION OF OF NUM VV DATE DATE PAGES PAGES PREPA PREPARRED/
NUMB ERBER REVISIO REVIS ION N ED!
AFFEC AFFECT TED ED REVIS ED BY:
REVISED BY:
00 Initial Issue Initial Issue YY 1/26/10 1/26/10 All All M M Hankin Hankinss v -Spec V - ify ifif the Specify the JPM JPM chan ge will change will requ ire anot require herr Vali anothe datio Validat ion n (Y(Y or or N).
N).
See See cove coverr shee sheett for for crite criteria ria..
JPM21-1A JPM21-1A Page Page 33 of of 99 Rev.
Rev. 00 SEQUOYAH NUCLEAR SEQUOYAH NUCLEAR PLANT PLANT ROISRO RO/SRO JOB PERFORMANCE JOB PERFORMANCE MEASURE MEASURE Task:
Task:
Respond to Respond to aa Failure Failure of of PRM PRM N-41 N-41 Note: This Note: This JPM JPM satisfies satisfies Simulator Simulator Manipulation Manipulation "AA", AA.
JAITAtask#:
JAiTA task # :3210140401 3210140401 (RO)
(RO) 0150050101 0150050101 (RO)
(RO) 0150040101 0150040101 (RO)
(RO)
KIA Ratings:
KIA Ratings:
015A4.03 (3.8/3.9) 015A4.03 (3.8/3.9) 015A4.02 (3.9/3.6) 015A4.02 (3.9/3.6) 015A2.01 (3.5/3.9) 015A2.01 (3.5/3.9) 015A3.03 (3.9/3.9) 015A3.03 (3.9/3.9) 015A4.01 (3.6/3.6) 015A4.01 (3.6/3.6) 015A2.02 (3.1/3.5) 015A2.02 (3.1/3.5)
Task Standard:
Task Standard:
Recognize failure of Power Recognize Power Range Range Monitor, Monitor, N-41 N-41,, defeat defeat its its control control functions, and prepare prepare for its its removal from service.
removal Evaluation Method:
Evaluation Simulator -~-- X In-Plant _ __
=======================================================================
Performer:
Performer:
NAME Start Time _ _ __
Start Time Performance Rating:
Performance SAT UNSAT Performance Time Finish Time _ __
Evaluator:
Evaluator:
~/_-- /
SIGNATURE SIGNATURE DATE
=======================================================================
COMMENT COMMENTS S
JPM21 JPM21-IA-1A Page 4 Page 4ofof99 Rev.
Rev.00 SPECIA ALLINSTRINSTRUC TION SPECI UCTIO NSSTO TOEVALU EVALUA ATOR:TOR:
- 1. Any
- 1. Any UNSAT UNSATrequire requires commen ts.
s comme nts.
2.2. Acknow Acknowle ledgedgeany anyassocia associate teddalarms alarms. .
- 3. Initi alize
- 3. Initialize simulalator simu tor ininIC IC#13.
- 13.
4.4. BoothBoothoperat operato or:r:
a.a. Select SelectN-41 N-41 on on NR45.
NR45.
b.b. Verify VerifyRx Rx power power<75% <75% on on PRNls, PRNIs, NR-45 NR-45 andand b.liT recorder, T recorde r, TR TR-68-2A2A 1.1. Approx Approxim ately 1 minu imately 1 minute after te after operato operator assumes r assum shift, Activat es shift, Activate e IMFIMF NI07A NIO7Af:120.
f:120.
- 2. Ensu
- 2. Ensure operat re oper ator performs the followin following or perform s the required g require actions for d actions for SELF-C SELF-CH HECKI ECKING NG;;
a.a. Identifi Identifies the corre ct unit, es the correct unit, train, train, compo compone nt, etc.
nent, etc.
- b. Revi ews
- b. Reviews the intende the inten ded action andand expecte expected d action response.
d respon se.
- c. Com
- c. Comparess the pare the actual actual respon response to se to the the expecte expected response.
d respon se.
Validatio Valida n Tim e: CR.
tion Time: CR. 9 mins Local 9 mins Local Too lslE qui Tools/ Equipm ent/Pr pm entl Pro cedure ocedu ress Neede Needed: d:
AOP-.I.01 AOP-/. 01,, Section Section 2.0 2.0 & & 2.3, 2.3, AR-M6 AR-M6.--A, A, AR-M4 AR-M4--8 B Ref eren Refere nces: ces :
Referenc Refere ncee Title Rev Rev No.
- 1. AOP-I.01 No.
- 1. AOP-/.0 1 Nuclearr Instrum Nuclea Instrume ent nt Malfun Malfunct ction ion 9 2 1 -AR-M66-A 9
- 2. 1-AR-M -A Reactorr Protect Reacto Protectio ionn and Safegu Safeguar ardsds 15 15
- 33. 1-AR-M44-8 1-AR-M -B NIS/ROD NIS/RO D CONTR CONTRO OLL 28 28
=====================================================================
REA READ D TO TO OPEOPERA RATTOR OR Dir ecti ons to Direct ions to Traine e:: Tra inee II will will expl ain the explain the initia initiall cond itionns, conditio s, and and state state the the task task toto be be perfo perform rmeded.. All All cont control room steps rol room steps shall shall be be perfo perform rmed ed for for this this JPM .
JPM. II will will prov ide initia provide initiatin tingg cues cues and and reports repo rts on on other othe r actions actio when directe by you.
by you. When Whe n youyou com complepletete the the task task succ essfu succes ns when direc tedd lly, the sfully, the obje objectiv ctivee for for this this job job perfo performrmanance ce measu re will be satis fied.
will be satisfied. Ensu Ensure re you you indic ate to indicate meas ure to me me when when you you unde unders tand rstan your assig d your assignened d task.
task. To indicate that you have that you have comple com plete d your ted your assig nedd task To indic ate assigne task retur returnn the the hand handou outt she sheetet I I prov provide idedd you.
you.
INIT IAL INITIAL COND CON DITI ONS::
ITIONS Unit Unit 11isis operoperatatinging at at 46%
-46% react or pow reactor er, all power, all cont control rolss are are inin AUT AUTOMOMAATIC.
TIC.
INIT IATI NG INITIATING CUES: CUE S:
1.1. You You are are thethe OATOATe C andand are aretoto mon monitoitorrthe the cont control rol boar board and respo d and respon ndd perperlicen license oper ating sedddutie duties s toto operati ngcond ition conditions. s.
2.2. You Youwill will be be requ ireddtotorespo require respon nd,d, asasaasing le perfo single rmerer, perform , totoany anyabno abnormrmalality thatoccu ity that occurs.
rs.
3.3. Whe When n any anyrequ requireireddactio ns/p actions roce dure
/procedures s have havebeen beencom comple pleteted notify d notif y thetheSM.SM.
JPM21 JPM21-IA-1A Page Page50f95 of 9 Rev.
RevO* .0 STEPIST STEP/S ANDARD TANDA RD SAT/U SATIUN NSAT SAT STEP1.:1.:
STEP Operator placesrods rodsininManua Operat or places Manual. l.
- _SSATAT STANDA STAND ARD:RD: Operat Operator placesrods or places rodsininmanua manual afterverifyin verifying
- UNSATUNSAT l after rodmotion g rod motionisisnot not warr warranantedted due duetotono nopower powerchange changeororTaveIT Tave/Tref mismatch.
ref misma tch.
Rodsare Rods areplaced placedininmanua manual withoutreferen referencin l without cinggaaproced procedur ure,e,prior priortoto exceedin exceed ingginsertio insertion n ofof>25
>25steps.
steps.
Start StartTime Time COMMEN COMM ENTS:TS:
Critica Criticall Step Step STEP 2.:
STEP 2.: Operator evaluates Operat or evalua malfunct tes malfun ion to ction to determ determine Power Range ine Power Range Monito (N-41)fai led high.
high. Monitorr (N-41 )failed Cue: After operatoperato Cue: After orr locate locates AOP-LO1 s AOP-I. 01 procedprocedure,ure, provid providee operat operato orr aa copy.
copy.
STANDA RD: - SAT SAT STAND ARD: Operator Operat recogniz or recogn es Power izes Power Range Range Monito Monitorr (N-41 (N-41)) failed failed high, high, determine determ s AOP -l.Oi ines AOP-I.01,, Section Section 2.3 is the - UNSAT UNSAT the approp appropriariate te proced proc ure.
edur e.
AOP-l.01 AOP-1. 01 may may be be entered entered directly directly or by by transiti transitiononss from anyon any onee of the procedur the proced ureses below:
below:
Critica Criticall Step Step
.01 section 2.1 2.1 step [3]
- 1-AR-M 1-AR-M66-Awin -A wind ows [B-1]
dows [B-i] or [0-1] [D-i]
- 1-AR-M 1 -AR-M44-B -B window windowss [D-3 [0-3)) and [E-3 [E-3))
COM COMM MEN TS:
ENTS:
AOP AOP-I. -l.O101,, Nuc Nuclealearr Inst rument Instrum ent Malf Malfununct ion ction STE P 3.: 2.3 STEP 3.: 2.3 [1]
[1] PLA PLACE CE rod rod cont rol inin Man control Man. .
RD: Oper ator STAND Operat or verif ies HS-8 verifies HS-85-5-51511100 isis inin man manuaual,l, or orstat states es Rod Rods UNSAT alrea dy bee already been n place d in placed in man ual.l.
have s have - UNS AT manua COM COMM MEN TS:
ENTS:
JPM21-1A JPM21-1A Page Page 66 of9 of 9 Rev.
Rev. 00 STEP/STAN DARD STEP/STANDARD SAT/UNSAT SAT/U NSAT STEP 4.:
STEP 4.: 2.3 [2]
2.3 [2] STABILIZE STABILIZE reactor reactor power power at current level.
at current level.
- SAT SAT STANDARD:
STANDARD: Operator checks Operator checks other other power power range range instruments instruments and and determines determines that that reactor isis stable.
stable. - UNSAT UNSAT reactor COMMENTS:
COMMENTS:
STEP S.:
STEP 5.: 2.3 [3]
2.3 [3] EVALUATE EVALUATE the the following following Tech Tech Specs Specs forfor applicability:
applicability:
- SAT SAT Cue:
Cue: SM will SM evaluate Tech will evaluate Tech Specs.
Specs.
- UNSAT UNSAT STANDARD:
STANDARD: Operator requests Operator requests SMSM to evaluate Tech Specs to evaluate Specs COMMENTS:
COMMENTS:
STEP 6.:
STEP 6.: 2.3 [4] PLACE the following switches located on the Detector Current Comparator drawer [M-13, NSO] N50] in position corresponding corresponding to failed power Range Channel: -
- . UPPER SECTION - UNSAT STANDARD STANDARD:: Detector Current comparator "Upper Upper Section Section" switch in the PRN-41 position. Channel defeat light light on. Critical Step COMMENT COMMENTS: S:
STEP STEP 7.:
7.: 2.3 2.3 [4]
[4] PLACE PLACE the the following following switches switches located located on on the the Detector Detector Current Current Comparator Comparator drawer drawer [M-13,
[M-13, N50]
NSO] in in position position correspondin corresponding to g to failed failed power power Range Range Channel:
Channel: SAT SAT
- LOWER LOWER SECTION SECTION UNSAT UNSAT STANDARD STANDARD: : Detector Detector Current Current comparator comparator tower "Lower Section Section" switch switch inin the the PRN-41 PRN-41 position.
position. Channel Channel defeat defeat light light on.
on.
Critical Step Critical Step COMMENT COMMENTS: S:
JPM21 JPM21 -1A
-1 A Page 7 of Page of 9 Rev.O Rev;O -
STEPISTAN STEP/ STAND DARD ARD SAT/U NSAT STEP 8.: 2.3 [4] PLACE 2.3 PLACE the followin following switches g switche s located on the Detect Detector Current Compa rator drawer [M-13, [M-1 3, N50]
N50] in position position corresponding to power Range Channe failed power Channel: l: SAT Appropriate Approp riate ROD ROD STOP BYPAS BYPASS S UNSAT UNSAT STANDARD STAND ARD:: Rod Stop Bypass Bypass switch in in "BYPA BYPASS SS PRN-41 position..
1" position COMMENTS:
COMM ENTS: Critical Step STEP 9.: PLACE the followin 2.3 [4] PLACE following switchess located on the Detector Current g switche Compa rator drawer [M-13, [M-1 3, N50]
N501 in position position corresponding to failed power Range Channel: SAT
- Approp Appropriate riate Power Mismatch Bypass Bypass switch (XX-92 (XX-92-5037
-5037)) - UNSAT UNSAT STANDARD STAND ARD:: Power Mismatch Bypass Bypass switch in the "Bypas Bypasss PRN-41 1" position position..
COMMENTS:
COMM ENTS: Criticall Step STEP 10.: DEFEAT 2.3 [5] DEFEA T failed Power Range channe channell Using Comparator Channel defeat switch:
switch:
- Comparator and Rate Drawer Drawer [M-13,
[M-13, N37] UNSAT UNSAT STANDARD STAND ARD:: Comparator Channel Defeat switch is placed in the N-41 positio position n..
Comparator defeat light on.
COMMENTS:
COMM ENTS:
Criticall Step 11.:
STEP 11.: 2.3 [6] RESTORE T-avg T -avg to within 1.5°F 1.5°F of T-ref T -ref USING one of the follow ing:
followin g:
Cue: CR0 is evalua CRO evaluating ting Tavg and Tref deviati - SAT deviat ion on and restora restoration.
tion.
STAN STANDDARD ARD:: Operator or acknowledges CR0 - UNSAT UNSA T CRO will perform this step and continues with procedure.
COMMENTS:
ENTS:
JPM21-1A JPM21-1A Page Page88of9 of 9
. Rev. 0 .
RevO.
STEPISTANDARD STEP/STANDARD SAT/UNSAT SATIUNSAT STEP 12.:
STEP 12.: 2.3 [7]
2.3 ENSURE OPERABLE
[7] ENSURE OPERABLE Power Power Range Range channel channel selected selected to to the the following:
following:
- Nuclear Nuclear Power Power Recorder Recorder [M4, [M4, NR-4S]
NR-45]
- Nuclear Nuclear Power Power Recorder Recorder [M4, [M4, NR-4S]
NR-45] (LlI)
(Al)
- SAT SAT STANDARD: Operator Uses Uses Touch Touch Screen Screen to to ensure ensure the - UNSAT UNSAT STANDARD: Operator the recorder recorder isis not not selected selected for for PR Channel II or PR Channel or ill Channel 1.
Al Channel 1. Operator Operator should should select select the the highest highest operable power operable power range range channel channel andand an an operable operable illAl Channel.
Channel.
(Operator could (Operator could select select view view for for all all points points on on NR-4S)
NR-45)
COMMENTS:
COMMENTS:
STEP 13.:
STEP 13.: 2.3 [7 2.3 [7 continued] ENSURE ENSURE RCS Temp ilT AT recorder (green (green pen)
[M-5, XS-68-2B]
[M-S,
- SAT UNSAT STANDARD:
STANDARD: Operator checks position of XS-68-2B. Ensures it is NQI NOT selected for -
LOOP ONE.
LOOP COMMENTS:
COMMENTS:
STEP STEP 14.:
14.: 2.3 [8] RETURN rod control to AUTO ifif desired.
2.3 [8]
- Cue: CR0 CRO will perform perform this step. step_ -
SAT SAT STANDARD STANDARD:: Operator Operator acknowledge acknowledges s this this step step isis being being addressed addressed by by the the CRC CRO andand -
UNSAT UNSAT continues continues with with procedure.
procedure.
COMMENT COMMENTS: S:
STEP STEP 15.:
1S.: 2.3 [9] CHECK 2.3 [9] CHECK reactor reactor power power greater greater than than 75%.
7S%.
- SAT SAT STANDARD STANDARD: : Operator Operatorverifies verifies power power less less than than 75%7S% (current (current power power isis - 46%),
46%), goes goes
- UNSAT UNSAT to to RNO RNO GO "GO TOTO Step Step 11.
11."
COMMENT COMMENTS: S:
JPM21-1A JPM21-IA Page Page 99 of9 of 9 Rev.
Rev. 00 STEPISTANDARD STEP/STANDARD SAT/UNSAT SATIUNSAT STEP 16.:
STEP 16.: 2.3[11] NOTIFY 2.3[11] NOTIFY 1M IM to to remove remove failed failed power power range range channel channel from from service USING service USING appropriate appropriate Appendix:
Appendix:
- SAT SAT Cue:
Cue: Role playas Role play as MSS MSS or IM, inform or 1M, inform operator that aa crew operator that crew will will be be in in the the MCR within - UNSAT UNSAT the MCR within the hour hour to to perform perform Appendix Appendix "A A11 of ofAAOP-LO1.
OP-I.O 1.
STANDARD:
STANDARD: Operator communicates Operator communicates with with IMs IMs or or MSS MSS toto request request performance performance of of Appendix "A" Appendix A of of AOP-1.01 AOP-l.01 for for removal removal of N-41 from of N-41 from service.
service.
COMMENTS:
COMMENTS:
- SAT SAT STEP 17.:
STEP 17.: NOTIFY SM that N-41 NOTIFY N-41 failed, its its control control functions functions have have been been defeated, defeated, IMs have been notified to remove itit from service. - UNSAT UNSAT STANDARD:
STANDARD: informs SM.
Operator informs COMMENTS:
COMMENTS:
Stop Time End of JPM
READ TO OPERATOR Directions to Trainee:
II will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. II will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied.
Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet II provided you.
INITIAL CONDITIONS:
( Unit 1 I is operating at -46% reactor power, all controls are in AUTOMATIC.
INITIATING CUES:
- 1. You are the OATC and are to monitor the control board and respond per licensed duties to operating conditions.
- 2. You will be required to respond, as a single performer, to any abnormality that occurs.
- 3. When any required actions/procedures have been completed notify the SM.
JPMI-AP JPMI-AP Page Page 11 of of1111 Rev Rev 21 21 SEQUOYAH NUCLEAR SEQUOYAH NUCLEAR PLANT PLANT JOB PERFORMANCE PERFORMANCE MEASURE MEASURE JPM 1-AP JPM 1-AP Emergency Boration (Stuck Rods)
PREPARED!
PREPAREDI REVISED BY: Date!
VALIDATE VALIDATEDD BY: *
- Datel Date!
APPROVED BY: Date!
(Operations Training Manager)
CONCURRE CONCURRED:D: ** Date!
Date!
(Operations Representativ Representative)e)
- Validation Validation not not required required for minor enhancement for minor enhancements, s, procedure procedure Rev Rev changes changes that that do do not not affect affect the the JPM, or individual JPM, or individual step step changes that that do do not not affect affect the the flow ofof the the JPM.
JPM.
revision).
JPMI-AP JPM1-AP Page Page2 2ofof1111 Rev 21 Rev2l NUCLEARTRAINING NUCLEAR TRAINING REVISIONIUSAGELOG REVISION/USAGE LOG REVISION REVISION DESCRIPTIONOF DESCRIPTION OF VV DATE DATE PAGES PREPARED/
PAGES PREPARED!
NUMBER REVISION AFFECTED REVISED NUMBER REVISION AFFECTED REVISED BY: BY:
88 Transferfrom Transfer from WP. WP. MinorMinorenhancements.
enhancements. NN 8/12/94 8/12/94 All All HJ HJ Birch Birch 99 Boron Conc.
Boron Conc. changes changes NN 9/16/94 9/16/94 All All HJ HJ Birch Birch 10 Chg duedue to to Rev Rev BB procedure.
procedure. YY HJ 10 Chg 9/9/95 9/9/95 All All HJ Birch Birch 11 Incorp previous Incorp previous pen/inks:
pen/inks: whichwhich corrected corrected NN 1/19/96 66 HJ 11 1/19/96 HJ Birch Birch step 10 to step 10 to continue contin ue with with procedure procedure instead instead of of transition (JPM transition (JPM performance performance comment.
comment.
Moved Tave Moved Tave cue cue from from step step 1414 to to 17 17 added added step to step determine fully to determine fully inserted, inserted, 12 12 steps.
steps.
Latest EA-68-4 Latest EA-68-4 && ES-0.1 ES-0.1 Rev Rev Chgd Chgd 'rods rods full full out to rods out' to 'rods >12 >12 steps',
steps, added added stepstep to to useuse the com the compu puterter to verify Rods to verify Rods position position 12 Major flow change for the start of EA-68-4 EA-68-4 Y HJ 12 13 Major flow change for 2/2/98 2/2/98 All All HJ Birch Birch Revision to to ES-0.1 ES-0.1 had no impact. impact. Made Made N 9/23/98 JP 13 Revision 9/23/98 All All JP Kearney Kearney step 28 step 28 aa critical critical step.
step. Revised Revised KIA K/A ratings.
ratings.
Reformatted critical Reformatted critical steps.
pen/ink ES-0.1 procedure procedure revisionrevision had no impact pen/ink pen/in k ES-0.1 Minor N 8/22/00 8/22/00 4 4 S. R.
S. R. Taylor Taylor clarific Minor clarification ation N 11/27/01 4,6,7,9 L.
pen/ink 14 N L. Pauley Pauley Incorporated change change to to EA-68-4. Chang e N 14 Incorporated Change N 8/12/02 8/12/02 All JJ PP Kearney Kearney was editori al was editorial in naturein nature 15 15 Incorp orated REV.
Incorporated REV. 1C 1C change changes s to ES-0.1 YY 9/8/03 All GS S Poteet Poteet All G and and EA-68 EA-68-4 -4 16 16 Incorp orated comme Incorporated comments nts NN 3/30/04 3/30/0 4 All G.S. Poteet Poteet All G.S.
17 17 Made Made minorminor editorial editorial change changes s throug hout.
throughout. NN 7/27/04 7/27/0 4 All MG Crotea Croteau All MG u Update d to curren Updated to currentt revisio revisionsns ofof EA-68-4 EA-68-4 and and ES-0.1 ES-0.1..
18 18 Update Updated d toto curren current t revisio revisionsns ofof EA-68-4 EA-68-4 and and YY 9/20/2005 9/20/2 005 All All JJ Tricoglou Tricoglou JJ ES-0.1 ES-0.1. . Made Made minor minor editorial editorial change changes s throug hout.
throughout.
19 Revise d format format and and update d IC.
IC. Added 19 Revised updated Added NN 11/21/07 11/21/ 07 All All RR Putnam Putnam candid candidate ate cuecue sheet sheet andand minor minor revisio revisions ns to to match match proced procedure ure referen ces.
references.
20 Added Added H3 H3autoauto genera te ofof Hando ut.
20 generate Handout. NN 7/15/08 7/15/0 8 5,5,7,9 7, 9 HHJJ Birch Birch Remov e handou t page.
Remove handout page. Minor stepchgs Minor step chgs base baseon on previo previous us proced procedureure change changes. s.
21 Update d proced ure revisio ns, deleted 21 Updated procedure revisions, deletedsteps steps YY 1/31/10 1/31/1 0 All All MMHankin Hankinss totorealign realign EmergEmergencyency Boration, Boration,validat ion validation time timechange changetoto15 15minute minutes. s.
VV -Specif Specifyy ififthe theJPMJPMchangechangewill willrequire requireanothe anotherr validation validation(Yor (Y orNN).
See cover sheet for criteria See cover sheet for criteria. .
JPMI-AP JPM1-AP Page Page 33 of of1111 Rev21 Rev2L SEQUOYAH SEQUOYAH NUCLEAR NUCLEAR PLANT PLANT ROISRO ROISRO PERFORMA JOB PERFORMANCE JOB NCE MEASURE MEASURE Task:
Task:
Emergency Boration Emergency Boration (Stuck (Stuck Rods)
Rods)
Note:
Note: This This JPM satisfies Simulator JPM satisfies Simulator Manipulation Manipulation "T".
T.
JAITA JA/T task ##:: 0000980S01 A task 0000980501 (RO)
(RO)
KIA Ratings:
KIA Ratings:
005AA2.03 (3.S/4.4) 00SAA2.03 (3.5/4.4) 024AA1.17 (3.9/3.9) 024AA1.17 (3.9/3.9) 005AK3.01 (4.0/4.3) 00SAK3.01 (4.0/4.3) 024AA11.18 024AA .18 (3.7/3.6)
(3.7/3.6) 005AK3.06 (3.9/4.2) 005AK3.06 (3.9/4.2) 024AA1 .15 (3.1/2.9) 024AA1.1S (3.1/2.9) 005AA2.03 (3.5/4.4) 005AA2.03 (3.5/4.4)
Task Task Standard:
Standard:
~ 5040 (or
? 5040 (or amount amount determined determined per per 0-SI-NUC-000-038.0 O-SI-NUC-000-038.0 and and TI-44)
TI-44) gallons gallons of of boric boric acid acid injected injected into into the the reactor coolant system using the normal boration path.
Evaluation Method:
Evaluation Method: X Simulator _~X"--_ In-Plant _ __
========================================================================
Performer:
NAME Start Time Time _ __
Performance Rating: SAT Performance UNSAT Performance Time Time _ __
Finish Time Evaluator:
Evaluator: /
SIGNATUR SIGNATURE E DATE
========================================================================
COMMENT COMMENTS S
JPM1-A JPM1-AP P Page Page 44 of of 11 11 SPECIAL INSTRUCTIO Rev Rev 21 21 SPECI AL INSTR UCTIONS NS TO TO EVALU EVALUATO ATOR: R:
1.
- 1. Sequen Seque ced steps nced steps identifie identified by an d by an "s" s
2.
- 2. Any UNSAT Any UNSAT require requiress comme comments nts 3.
- 3. Initialize Initializ the simula e the simulator tor in in IC-11S IC-118..
4.
- 4. Insert the following:
Insert the follow ing:
- a. a. IMFIMF RD13A RDI3Af:1 f:1
- b. b. IMFIMF RD13E RDI3E f:1 f:1 c.c. Overrid Override IOR ZDIHS e lOR ZDIHS6213S 62I38A f:O A f:O d.d. IMFIMF RD07C RDO7C5 (F-8) 5 (F-S)
- e. IMF
- e. IMF RD07D RDO7D8 (H-14)
S (H-14) f.f. IMFIMF AN_OV AN_OV_325_325 CPU CPU alarm alarm for for Contro Control Rods Rods Dev Dev && Seq-Seq- Nuisan Nuisancece alarm alarm 5.
- 5. INITIATE INITIA TE aa reactor reactor trip.
trip.
6.
- 6. Close TDAFW Close TDAFW valves valves and and freeze freeze the the simula simulator after after you you have have acknow acknowledged ledged the the control control board board alarms.
7.
- 7. The ConsoConsole operat operato orr can can be be used used toto acknow acknowledge ledge alarms alarms not not associa associated with with the the JPM.
JPM.
8.
- 8. Ensure operat Ensure operatoorr perform performss the the followin following requiredd actions g require actions for SELF-C SELF-CHECHECKI KING; NG;
- a. Identifi
- a. Identifies the correct es the correct unit, unit, train, component, etc.
- b. Review Reviewss the intende intended d action and expect ed responresponse.se.
- c. Compa Compares res the actual respon response se to the expect expecteded respon response.
se.
Valida tion Time: CR. 15 15 mins Local _ _ _ __
ToolslEquipm Tools/ Equipment/Pr entlPro cedure ocedu ress Needed:
EA-68-4,
- 1. EA 4,
- 2. ES-O.1 Calculator
- 3. Calcula tor for examiner and examin exam ineeee REFERENCES ENCES::
Reference Title A. EA-68-4 EA Rev No.
4 Emergency Boratio Borationn B. ES-0.1 10 Tri~ ResQo Reactor Trip Response 32
===========================================
JPM1-AP JPM1-AP Page55of Page of1111 Rev 21 Rev2l READTO READ TOOPERATOR OPERATOR Directionsto Directions toTrainee:
Trainee:
I I will will explain explain thethe initial initial conditions, conditions, and and state statethethe task tasktoto be be performed.
performed. AllAll control control room room steps steps shall shall be be performed for performed for this this JPM.
JPM. I I will will provide provide initiating initiating cues cues and and reports reports on on other otheractions actions when when directed by directed byyou.
you. When When you complete you complete the the task task successfully, successfully, the the objective objectiveforforthis this job job performance performance measure measurewillwill be be satisfied. Ensure satisfied. Ensure you indicate you indicate toto me me when when you you understand understand your your aSSigned assigned task.
task. ToTo indicate indicate that that you you have have completed completed your your assigned task assigned task return thereturn the handout handout sheet sheet II provided provided you.
you.
INITIAL CONDITIONS:
INITIAL CONDITIONS:
- 1. The
- 1. The reactor reactor has has tripped tripped with with no safety injection no safety injection and and thethe Immediate Immediate Actions Actions of of E-O, E-O, Reactor Reactor Trip Trip or or Safety Safety Injection, were Injection, were completed.
completed.
- 2. The
- 2. The transition transition was was made made to to ES-O.1 ES-O.1 "Reactor Reactor TripTrip Response".
Response.
- 3. BAT
- 3. BAT A is aligned A is aligned to to Unit Unit 11 via via 1A 1A BATP BATP INITIATING CUES:
INITIATING CUES:
- 1. You
- 1. You areare directed directed to PERFORM step 6 of ES-O.1.
- 2. NOTIFY
- 2. NOTIFY the the US/SRO US/SRO when you have completed all actions required by Step 6 of ES-O.1.
JPMI-AP JPM1-AP Page Page66ofof1111 Rev Rev2L21 Job Performance Job PerformanceChecklist:
Checklist:
STEPISTANDARD STEP/STANDARD SAT/UNSAT SAT!U NSAT STEP 1.:
STEP 1.: OBTAIN the OBTAIN the appropriate appropriate procedure(s).
procedure(s). SAT SAT
- UNSAT UNSAT STANDARD: Operator STANDARD: Operator obtains obtains aa copy copy of ES-O.1 (and of ES-O.1 (and EA-68-4 EA-68-4at at step step 33 of ofJPM)
JPM)
Start Start Time Time__
NOTE:
NOTE: The next The next three three steps steps of of the the JPM JPM are are from from ES-O.1.
STEP 2. 6. CHECK ifif emergency
- 6. CHECK emergency borationboration required:
required: UNSAT UNSAT
- a. VERIFY
- a. VERIFY all all control control rods rods fully fully inserted inserted STANDARD: Determinre STANDARD: Determinre that that two two rods rods F8 F8 and and H14 H14 are are indicating indicating full full out out by by checking checking rod rod Critical Critical Step Step bottom lights bottom lights and rod position indicators rod position indicators for for control control rod rod position.
position.
Enter Step Enter Step 6.a 6.a RNO.
RNO.
STEP 3.
STEP 3. IF all IF all rod rod bottom bottom lights lights are de-energized, THEN are de-energized, THEN SAT SAT RESTORE power power to RPls RESTORE RPIs by by switching Instrument Instrument Rack Rack B B Transfer Switch to ALTERNATE.
to ALTERNATE. [M-7, lower switch] UNSAT STANDARD:
STANDARD: Operator determines this step N/A since power is available.
STEP 4.
STEP 4. IF any IF any of the following conditions exists: SAT RPIs indicate greater than 12 steps
- . two two or more control rod positions CANNOT be determined, THEN EMERGENC EMERGENCY Y BORATE USING EA-68-4, EMERGENC EMERGENCY Y BORATION BORATION STANDARD STANDARD:: Operator Operator transitions transitions to to EA-68-4, EA-68-4, Emergency Emergency Boration Boration EA-68-4, EA-68-4, Emergency Emergency Boration Boration STEP STEP 5.5. [4.1 .1] IF
[4.1.1] IF entering entering this this instruction instruction from any of from any the following:
of the following: SAT SAT
- UNSAT UNSAT STANDARD STANDARD:: Operator Operator determines determines this this step step isis N/A, N/A, since since procedure procedure entryentry was was from from ES-O.1, ES-O.1, Reactor Reactor TripTrip Response.
Response.
JPM1-AP JPM1-AP Page Page77of of1111 Rev 21 Rev2l Job Performance Job PerformanceChecklist:
Checklist:
STEPISTANDARD STEP/STANDARD SAT/UNSAT SATIUNSAT STEP 6.6.
STEP [4.1.21 IF
[4.1.2] IF entering enteringthis this instruction instructionfrom from ES-O.1 ES-O.1 ANDAND anyanyofofthe thefollowing following SAT SAT conditions are conditions are met: met:
- RCSRCS temperature temperature lessless than than 530°F 530°F Cue:
Cue: If checked, cue Ifchecked, cue that thatRCS RCS temperature temperature reads reads 547 547 degrees degrees on on all allloops.
loops.
STANDARD: Operator STANDARD: Operator recognizes recognizes that that emergency emergency borationboration isis not not required required based based onon temperature.
temperature.
STEP 7.
STEP 7. [4.1 .3] IF
[4.1.3] IF rod rod positions positions CANNOT CANNOT be verified due be verified due to RPIs de-energized, to RPI's de-energized, SAT SAT
- UNSAT UNSAT STANDARD: Operator STANDARD: Operator determines determines this step step is N/A, since is N/A, since procedure procedure entry entry was was from ES-0.1, from ES-0.1, Reactor Reactor Trip Trip Response Response due due to two stuck stuck rods, rods, continue continue with next step.
next STEP 8.
STEP 8. [4.1.41 IF
[4.1.4] IF entering this instruction from ES-0.1 AND any of the following SAT conditions are met:
- Two or more control rods indicating greater than 12 steps -
UNSAT OR
- . Two or more rod positions CANNOT be determined due to RPls RPIs unavailable THEN THEN PERFORM PERFORM the following:
a.
- a. IF using BAT as aa boration source GO GO TO Section 4.2, Emergency Boration from BAT BAT b.
- b. IF IF using using RWST as aa boration source GO GO TO TO Section Section 4.3, 4.3, Emergency Emergency BorationBoration from from RWST RWST NOTE:
NOTE: Since Since Section Section 4.3 is an 4.3 is an acceptable acceptable path, path, ifif the the operator operator chooses chooses thisthis path path give the following give the following cue:cue:
Cue:
Cue: If the If the operator operator chooses chooses to to go go to to section section 4.3, role play 4.3, role playas as USUS and and state state that that thethe preferred preferred boration boration method method is is via via the BA T.
the BAT.
STANDARD STANDARD: : Operator Operator selects selects Section Section 4.2.
4.2.
NOTE:
NOTE: The The following following stepssteps are are from from Section Section 4.2.4.2.
- SAT SAT STEP STEP 9.:
9.: [4.2.1] PLACE
[4.2.1] PLACE boric boric acid acid transfer transfer pumpspumps to fast speed.
to fast speed.
- UNSAT UNSAT NOTE:
NOTE: Standard Standard I1 and and 22can can bebe done done in any order.
in any order.
STANDARD STANDARD: : 1)1) Pump(s)
Pump(s) stopped.
stopped. Green Green light lighton on HS HS 2)
- 2) Speed selector switch placed Speed selector switch placed on FAST on "FAST" position position 3)3) Pump(s)
Pump(s) restarted, restarted, Red lighton Red light rightcomes on right comeson onfor forfast fastspeed.
speed. CriticalStep Critical Step 4)
- 4) (Starting (Starting only onlyIA1Apump pump isisacceptable) acceptable)
JPMI-AP JPM1-AP Page Page88of of1111 Rev21 Rev 21 JobPerformance Job PerformanceChecklist:
Checklist:
STEP/STANDARD STEP/STANDARD SAT/U NSAT SAT/UNSAT STEP 10.:
STEP 10.: [4.2.2] ADJUST
[4.2.2] ADJUST emergency emergencyborate boratevalve valve [FCV-62-138]
1FCV-62-11 to to maintain maintain flow flow SAT SAT between 3535 and and 150 between 150 gpm gpm on on IFI-62-137
[Fl-62-137A A].].
- UNSAT UNSAT NOTE:
NOTE: FCV-62-138 will FCV-62-138 will not not operate.
operate.
STANDARD: Operator STANDARD: Operator recognizes recognizes that that FCV-62-138 FCV-62-1 38 will will not operate. Operator not operate. Operator continues continues with procedure.
with procedure.
STEP 11.:
STEP 11.: [4.2.3] MONITOR
[4.2.3] MONITOR emergency emergency boration boration flow:
flow: SAT SAT
- a. CHECK emergency boration
- a. CHECK emergency boration flow flow established established on on [FI-62-137
[FI-62-137A A).].
- UNSAT UNSAT NOTE:
NOTE: Since FCV-62-138 Since FCV-62-138 willwill not not operate, operate, thisthis step step will will have have nono affect affect on on flow.
flow.
Operator may Operator may continue continue with with the next step.
the next step.
STANDARD: Operator STANDARD: Operator determines determines FCV-62-138 FCV-62-138 will not open and not open and no no flow isis available.
available.
Continues with Continues with next next step.
step. This isis aa MONITOR MONITOR step step which which requires requires checking checking process repeatedly at an a process an unspecified unspecified interval.
interval.
STEP 12.:
STEP 12.: [4.2.3.b] IF boric acid flow less than 35 gpm, THEN CLOSE recirculation
[4.2.3.b] SAT valve for the BAT aligned to the blender:
E1-FCV-62-2371 for BAT A.
11-FCV-62-237] -
UNSAT UNSAT NOTE:
NOTE: There There is no boric acid flow indicated on FI-62-137A Fl-62-1 37A at this time. This is a monitor step and if or when flow is established on this FI monitor Fl the operator should verify verify flow greater than 35 gpm, or throttle recirculation valve as necessary to establish establish 35 gpm.
Placing Placing the recirculation valve in closed, without a flow path will dead head the boric acid transfer pump. See Attachment 11 Boric Acid Flowpath Flowpath and Valves.
STANDARD STANDARD:: Operator Operator should should continue continue with with the the next next step.
step.
STEP STEP 13.:
13.: [4.2.4] IF
[4.2.41 IF emergency emergency boration boration flow flow NOT NOT established, established, THEN THEN ALIGN ALIGN normal normal SAT SAT boration path:
boration path:
- UNSAT UNSAT
[4.2.4aj
[4.2.4a] VERIFY VERIFY VCT VCT outlet outlet valves valves FLCV-62-1
[LCV-62-132] and lLC 321 and [LCV-62-1331 V-62-1 331 OPEN OPEN STANDARD STANDARD: : Operator Operator verifies verifies valve valve positions positions using using indicator indicator lights lights for for LCV-62-132 LCV-62-132 and and 133 on control 133 on control panel, panel, red red lights lights illuminated.
illuminated.
JPMI-AP JPM1-AP Page99of Page of1111 Rev Rev2I21 JobPerformance Job PerformanceChecklist:
Checklist:
STEP/STAN STEP/ST DARD ANDARD SAT/U NSAT SAT/UNSAT STEP 14.:
STEP 14.: [4.2.4.b]
[4.2.4.b] ALIGN normal ALIGN normal boration boration toto VCT VCT outlet:
outlet: SAT SAT
- . OPEN [FCV-62-140]
OPEN IFCV-62-1 401.. - UNSAT UNSAT
- . OPEN [FCV-62-1441.
OPEN [FCV-62-144].
STANDARD: Operator STANDARD: Operator verifies verifies FCV-62-140 FCV-62-140 isis alreadyalreadyOPEN OPEN (red (red light light illuminated, illuminated, green green Critical Critical Step Step light dark) light dark) and opens and opens FCV-62-144 FCV-62-144 by placing HS-62-144 by placing HS-62-144 to to the the OPEN OPEN position position (right)
(right) and verifies and verifies red red light light illuminated illuminated and and green green light light dark.
dark.
STEP 15.:
STEP 15.: [4.2.4.c]
[4.2.4.c] CHECK boration CHECK boration flow flow greater greater than than 3535 gpm gpm on on [FI-62-1391.
FFI-62-1 391. SAT SAT CUE: If operator If operator notifies notifies thethe SROSRO that that emergency emergency boration boration has has been been UNSAT UNSAT established acknowledge acknowledge flow established flow has has been been established.
established.
STANDARD: Operator STANDARD: Operator ensures ensures flow flow rate rate is is greater greater than than 35 35 gpm.
gpm. MayMay notify notify SRO SRO that that emergency boration emergency boration flow flow has has been been established.
established.
STEP 16.:
STEP 16.: [4.2.5] IF
[4.2.5] IF boration boration flow NOT NOT established, THEN PERFORM one of SAT SAT following...
the following ...
- UNSAT U NSAT STANDARD:
STANDARD: Operator N/A's Operator N/As this step.
STEP 17.:
STEP 17.: [4.2.6] VERIFY charging flow established. SAT SAT STANDARD:
STANDARD: Operator verifies charging flow established on FI-62-93.
Operator Fl-62-93. UNSAT UNSAT STEP STEP 18.:
18.: [4.2.7] MAINTAIN boric acid flow between 35 and 150 150 gpm.
gpm. .SAT SAT STANDARD STANDARD:: Operator Operator monitors monitors flow on on Fl-62-139 FI-62-139 between between 35 35 and and 5050 gpm.
gpm. UNSAT UNSAT STEP STEP 19.:
19.: [4.2.8]
[4.2.8] Monitor Monitor BATBAT level.
level. SAT SAT STANDARD STANDARD:: Operator Operator monitors monitors BATBAT level level on on Ll-62-238.
LI-62-238. UNSAT UNSAT STEP STEP 20.:
20.: [4.2.9]
[4.2.9] IFIF FR-Si FR-S.1 ATWS ATWS or or FR-S.2 FR-S.2 Loss Loss of of core core Shutdown Shutdown condition condition exists, exists, SAT SAT THEN....
THEN ....
- UNSAT UNSAT STANDARD STANDARD: : Operator Operator N/AsN/A's this this step.
step.
STEP STEP 21.:
21.: [4.2.10]
[4.2.10] IF IF emergency emergency boration boration required required for for RCS RCS cooldown, cooldown, THEN THEN -
SAT SAT DETERMIN DETERMINE E required required boricboric acid acid volume volume based based on on RCS RCS Temperature Temperature
- UNSAT UNSAT STANDARD STANDARD: : Operator Operator N/As N/As this this step.
step.
JPM1-AP JPM1-AP Page Page 10 of 11 lOofli Rev21.
Rev2l.
Job Performance Job Performance Checklist:
Checklist:
STEP/STANDARD STEP/STANDARD SAT/U NSAT SAT/UNSAT STEP 22.:
STEP 22.: [4.2.111 IF
[4.2.11] IF any any of of the the following following conditions conditions are are met:
met: SAT SAT
- 22 or or more more control control rods rods greater greater than than 1212 steps steps OR OR UNSAT
_UNSAT
- 22 or or more more control control rods rods positions positions CANNOT CANNOT be be determined determined THEN PERFORM THEN PERFORM one one ofof the the following:
following:
Critical Critical Step Step
- Determine Determine Boric Boric Acid Acid Volume Volume fromfrom Table Table OR OR
- CALCULATE CALCULATE requiredrequired boric boric acid acid volume volume USING USING 0-Sl-NUC-00 0-SI-NUC-000-038.00-038.0 andand TI-44.
Tl-44.
CUE:
CUE: If operator decides If operator decides to to use use 51-38, Sl-38, tell tell them them thethe preferred preferred method method to to determine Boric determine Boric Acid Acid volume volume is is from from the the table table in in EA-68-4.
EA-68-4.
STANDARD: Operator STANDARD: Operator Determines Determines boricboric acid acid volume volume using using table table and and determines determines that that 5040 gallons 5040 gallons of boric acid are required.
required.
STEP 23.:
STEP CALCULATE time to inject boric acid volume determined in EA-68-4 CALCULATE SAT step 11 at established flow rate:
_UNSATUNSAT NOTE:
NOTE: 5040 I (flow indicated by FI-62-139) =
5040/ =___ minutes Critical Step STANDARD:
STANDARD: Operator determines the time required to inject 5040 gallons of boric acid based on the flow rate they establish.
Fl-62-1 39 = _ _ minutes +/-
5040 gal/ flow rate on FI-62-139 +1- 11 minute STEP STEP 24.:
24.: WHEN either of the following conditions exists: SAT
- FR-0 FR-O Subcriticality Status Tree is GREEN GREEN AND UNSAT
Cue:
Cue: When When the the operator operator determines determines the the time, time, cuecue them them that that the the JPM JPM isis complete.
complete.
STANDARD STANDARD:: Operator Operator notifies notifies the the US US that that boration boration has has been been established established to to RCS.
RCS.
End End of JPM ofJPM
IPMI-AP JPM1-AP Page Page 11 11 of of11 11 Rev 21 Rev2I Attachment Attachment 1I Emergency Boration FlowpathlValves Emerge:ncy Flowpath/Valves FCV-62-1 43 FCV-62-143 Primary Water To co HUTs PWST N FCV-62-237 FCV-62-237 VCT BAT Boric Acid 62-929 Transfer FCV-62-138 Pumps Emergency Boration Paths CLOSED THROTTLED OPEN FI-62-137 To
~ ~ I><J Charging Charging
READ TO READ TO OPERATOR OPERATOR Directions to Trainee:
Directions I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. I will provide initiating cues and reports reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet II provided you you..
. INITIAL CONDITIONS:
- 1. The reactor has tripped with no safety injection and the Immediate Actions of E-O, Reactor Trip or Safety Injection, were completed.
- 2. The transition was made to ES-O.1 "Reactor Reactor Trip Response".
Response.
- 3. BAT A is aligned to Unit 1 I via 1 1AA BATP INITIATING CUES:
I. You are directed to PERFORM step 6 of ES-O.1.
1.
- 2. NO11FY NOTIFY the US/SRO when you have completed all actions required by Step 66 of ES-O.1.
\
JPM2 JPM2 RO/SRO RO!SRO Page 11 of Page of 77 Rev.
Rev. 00 SEQUOYAH SEQUOY AH NUCLEAR PLANT PLANT PERFORMANCE MEASURE JOB PERFORMANCE JPM2 RO/SRO ROISRO Remove Excess Letdown from Service PREPARED!
REVISED BY: Datel Date!
VALIDATED BY: *
- Datel Date!
APPROVED APPROVED BY: Datel Date!
(Operations (Operations Training Manager)
CONCURRED: **
- Datel Date!
(Operations (Operations Representative)
- Validation not required for not required minor enhancements, for minor enhancements, procedure procedure Rev Rev changes thatthat do do not not affect the JPM, affect the JPM, or or individual individual step changes that step changes do not that do not affect affect the the flow of the flow of the JPM.
JPM.
by aa procedure
JPM2 JPM2RO/SRO ROISRO Page22ofof77 Page Rev.
Rev.00 NUCLEARTRAINING NUCLEAR TRAINING REVISION/USAGELOG REVISION/USAGE LOG REVISION REVISION DESCRIPTION OF DESCRIPTION OF VV DATE DATE PAGES PAGES PREPARED/
PREPARED!
NUMBER NUMBER REVISION REVISION AFFECTED AFFECTED REVISED BY:
REVISED BY:
00 Initial Issue Initial Issue YY 1/18/2010 1/18/2010 All All M.
M. Hankins Hankins Vv -Specify Specify ififthe the JPM JPM change change willwill require require another another Validation (Y or Validation (Y or N).
N).
See See cover cover sheet sheet for for criteria.
criteria.
JPM2 JPM2RO/SRO ROISRO Page33of Page of77 Rev.
Rev. 00 SEQUOYAH NUCLEAR SEQUOYAH NUCLEAR PLANT PLANT ROISRO RO/SRO JOB PERFORMANCE JOB PERFORMANCE MEASURE MEASURE Task Task JA/TA task #
JAITAtask#
Place excess Place excess letdown letdown in in service service to to the the VCT VCT IRCDT
/RCDT 0040160101 0040160101 K/A Ratings:
KIA Ratings:
004 A4.06 004 A4.06 (3.6/3.1 (3.6/3.1)) 004 A4.05 004 A4.05 (3.6/3.1)
(3.6/3.1)
A4.06 (3.6/3.1)
A4.06 (3.6/3.1)
Task Standard:
Task Standard: Remove Remove Excess Excess letdown letdown from from service service in in accordance accordance with with 1-S0-62-6, 1-SO-62-6, Excess Excess Letdown, Letdown, section 7.0 section 7.0 Evaluation Method:
Evaluation Simulator __X_____
X__ In-Plant _ __
In-Plant
========================================================================
Performer:
Performer:
NAME Start Start time time _ __
Performance Rating: SAT Performance UNSAT Performance Time time _ __
Finish time Evaluator:
Evaluator: I/- - - - - -
SIGNATURE SIGNATURE DATE
========================================================================
COMMENT COMMENTS S
JPM2 JPM2 RO/SRO ROISRO Page 44 of7 Page of 7 Rev.
Rev. 00 SPECIAL INSTRUCTIONS SPECIAL INSTRUCTIONS TO TO EVALUATOR:
EVALUATOR:
1.1. Critical step AA Critical step isis identified identified bold bold type type inin the the SAT/UNSAT SAT/UNSAT column. column.
2.2. Any UNSAT requires Any UNSAT requires comments comments 3.3. Task should Task should begin begin at at the the IC198, lCi98, 8B CCP CCP liS,IfS, Excess Excess LD LD liS, uS, LDLD liS I/S at at -73 73 gpm.
gpm.
5.5. Ensure operator Ensure operator performs performs the the following following required required actions actions for for SELF-CHECKING; SELF-CHECKING;
- a. Identifies the
- a. Identifies correct unit, the correct unit, train, train, component, component, etc. etc.
- b. Reviews the
- b. Reviews the intended intended action action and and expected expected response.
response.
- c. Compares the
- c. Compares the actual actual response response to the expected to the expected response.
response.
6.
- 6. Place aa Pink Place Pink Tag Tag on 1-HIC-62-93, which on 1-HIC-62-93, which is is in in manual.
manual.
Validation Time:
Validation Time: CR CR 77 min mm Local Local _ _ _ __
ToolslEquipmentlProcedures Needed:
Tools/Equipment/Procedures Needed:
REFERENCES:
REFERENCES' Procedure Procedure Title Title Rev Rev No.No.
1 -SO-62-6 1-S0-62-6 Excess Excess Letdown Letdown 17 17 i-AR-M5-B 1-AR-M5-8 Annunciator Response Response 36 36 II Task Task Number Number I Task Title I ContTRN Cont TRN 0040160101 Place 0040160101 Place excess letdown in service to the VCT IRCDT !RCDT
=================================================================
READ TO OPERATOR Directions to Trainee:
Directions II will explain the initial conditions, and state the task to be performed. II will provide initiating cues and reports on other actions when directed by you. All steps shall be performed for this task When you complete the task successfully, the objective for this job job performance performance measure will be satisfied. Ensure you indicate to me when you understand your assigned assigned task. To indicate that you have completed your assigned task return the handout sheet II provided you. you.
INITIAL INITIAL CONDITION CONDITIONS: S:
The The Unit is operating Unit is operating at at 100%
100% power.power.
AA Leaking Leaking valve valve required required Normal Normal Letdown Letdown to to bebe removed removed from from service.,
service.,
Excess Excess letdown letdown was was placed placed in in service service while while the the repairs repairs werewere made.
made.
Excess Excess letdown letdown temperature temperature isis 207°F
-20rF and and 45 45 psig psig on on i-PI-62-57.
1-PI-62-57.
The leaking The leaking valve has now valve has now been been repaired.
repaired.
Normal Normal Letdown Letdown has has been been restored restored toto service service in in accordance accordance with with 11-S0-62-1.
-SO-62-i.
i-HIC-62-93 1-HIC-62-93 isis inin manual, manual, per per section 5.0 of section 5.0 of 1-SO-62-6, 1-S0-62-6, Excess Excess Letdown.
Letdown.
1-SO-62-6, 1-S0-62-6, Section Section 4.0, 4.0, 5.05.0 and and 7.0 step lare 7.0 step 1are complete.
complete.
INITIATING INITIATING CUES:CUES:
You You areare the the U-iU-1 OATC.
OATC. You You have have been been directed directed to to remove remove excess excess letdown letdown from from service service using using i-SO-62-6, 1-S0-62-6, Section Section 7.0.
7.0.
JPM2 JPM2 RO/SRO ROISRO Page Page Sof 7 5of7 Rev. 00 Rev.
Job Performance Job Performance Checklist:
Checklist:
STEPISTANDARD STEP/STANDARD SAT/UNSAT SATIUNSAT STEP 1.:
STEP 1.: IF letdown IF letdown isis toto be placed inin service, be placed service, THEN THEN RETURN RETURN to to service service SAT SAT per 1-S0-62-1.
per I -S 0-62-1.
- UNSAT UNSAT STANDARD: Operator STANDARD: Operator verifies verifies letdown letdown isis inin service.
service. Initial Initial conditions conditions stated stated Start Start Time Time STEP 2.:
STEP 2.: CLOSE [1-FCV-62-56]
CLOSE F1-FCV-62-56] ExcessExcess Letdown Letdown Heat Exchanger outlet Heat Exchanger outlet SAT SAT valve.
valve.
- UNSAT UNSAT STANDARD: Operator STANDARD: Operator turns the potentiometer potentiometer in in the the clockwise direction direction until until CRITICAL CRITICAL the pointer the pointer (needle)
(needle) isis in the the CLOSE CLOSE or or ZERO ZERO position.
position. Operator Operator STEP STEP may verify aa decrease in may in temperature on on TI-62-S8 Tl-62-58 andand pressure pressure decrease on PI-62-S7.
P1-62-57.
STEP 3.:
STEP 3.: VERIFY [1-FCV-62-59]
VERIFY [1-FCV-62-591 Excess Letdown 3-way valve in SAT NORMAL.
NORMAL.
- UNSAT STANDARD STANDARD:: Operator verifies the HS for FCV-62-S9 FCV-62-59 is in NORMAL.
STEP 4.:
STEP 4.: CLOSE 11-FCV-62-5
[1-FCV-62-55] 51 Excess Letdown containment isolation -
SAT valve.
- UNSAT STANDARD STANDARD:: Operator places places HSHS inin closed closed and and verifies green green light light illuminated illuminated and red light light dark dark STEP STEP 5.:
5.: CLOSE CLOSE [1-FCV-62-5 I1-FCV-62-541 41 COLD COLD LEG LEG Loop Loop #3#3 Excess Excess Letdown Letdown
- SAT SAT valve.
valve.
- UNSAT UNSAT STANDARD STANDARD:: Operator Operator placesplaces HSHS toto close close andand verifies verifies green green light light illuminated illuminated and red and red light light dark dark
JPM2 JPM2 RO/SRO ROISRO Page 6 of 7 Page6of7 Rev.
Rev. 00 Job Performance Job PerformanceChecklist:
Checklist:
STEPISTANDARD STEP/STANDARD SAT/UNSAT SATIUNSAT STEP 6.:
STEP 6.: IFIF charging charging isis inin service, service, THEN THEN SAT SAT ADJUST seal ADJUST seal injection injection flow flow to 6-Il gpm to 6-11 gpm using using [1-FCV-62-891
[1-FCV-62-891
- UNSAT UNSAT STANDARD: Operator STANDARD: Operator turns turns potentiometer potentiometer CCW CCW to close (demand to close (demand movesmoves to to the right the right toward toward 100%100% or or CLOSE)
CLOSE) to to reduce reduce seal seal injection injection flow flow to to between 66 and between and 1111 gpm.
gpm.
STEP 7.:
STEP 7.: IF auto IF auto operation operation isis desired desired and and system system conditions conditions will will allow allow it,it, SAT SAT THEN THEN PLACE [1-FCV-62-931 PLACE [1-FCV-62-931 in in AUTO.
AUTO. UNSAT UNSAT STANDARD:
STANDARD: Prior to placing Prior placing charging in in automatic, the Operator Operator should should adjust adjust Pressurizer level, Pressurizer level, by taking the by taking the lever lever to the right to the right to to decrease decrease charging flow (or to the left to increase charging flow) as charging as needed to match to match Pzr Pzr Level and Program Program Level. Level. When program program level and actual level are matched, the Auto/Manual Auto/Manual Toggle should be placed in the Auto (Down) position.
STEP 8.:
STEP 8.: NOTIFY RADCON that Excess Letdown is REMOVED from NOTIFY SAT SERVICE.
SERVICE.
- UNSAT UNSAT CUE:
CUE: Acknowledg Acknowledge e as RADCON that Excess Letdown has been removed removed from service.
STANDARD STANDARD:: Operator Operator should should call RADCON and notify notify them Excess LetdownLetdown has been has been removed from service on Unit 1.
on Unit 1.
STEP STEP 9.:
9.: ENSURE ENSURE [1-FCV-70-8
[1-FCV-70-85J 51 Excess Excess Letdown Letdown HX HX CCS CCS FCVFCV is is SAT SAT CLOSED.
CLOSED.
NOTE NOTE Operator Operator shouldshould address address the the need need to to have have aa CV CV (Concurrent (Concurrent UNSAT UNSAT Verifier)
Verifier) present present prior prior to to operating operating the the valve.
valve.
CRITICAL CRITICAL STANDARD STANDARD: : Operator Operator takes takes thethe HS HS for -FCV-70-85 to for I1-FCV-70-85 to CLOSE CLOSE position position (to(to STEP STEP the the left) left) and and verfies verfies green green light light illuminated illuminated and and red light dark.
red light dark.
JPM2 JPM2 RO/SRO ROISRO of 77 Page 77 of Page Rev.
Rev. 00 Job Performance Job Performance Checklist:
Checklist:
STEP/STANDARD STEP/STANDARD SAT/U NSAT SAT/UNSAT STEP 10.:
STEP 10.: ENSURE [1-HS-70-85A]
ENSURE [1-HS-70-85A] is is in the A-Auto position.
in the position. SAT SAT NOTE NOTE Operator should Operator should address address thethe need need toto have have aa CV CV (Concurrent (Concurrent UNSAT UNSAT Verifier) present Verifier) present prior prior to operating the to operating the valve.
valve.
CRITICAL STANDARD: Operator places the HS HS in the A-Auto A-Auto position (mid position). STEP STEP 11.:
STEP 11.: INDEPENDENTLY VERIFy INDEPENDENTLY VERIFY.... .... SAT SAT
- UNSAT NOTE The next four steps are independent verification of manipulations previously made by the operator CUE: Tell the operator the independent verifications were performed by another operator.
STANDARD: Operator requests an independent verification for previous manipulations.
STEP 12.: IF operation at greater than 200°F has occurred, THEN SAT CONTACT Systems Engineering to evaluate Grinnell Valve maintenance requirements. - UNSAT STANDARD: Operator notifies the US that excess letdown temperature exceeded 200°F, therefore System Engineering must be notified to evaluate Grinell Valve maintenance requirements. STOP TIME End of JPM JPM
Directions to Trainee:
I will explain the initial conditions, and state the task to be performed. I will provide initiating cues and reports on other actions when directed by you. All steps shall be performed for this task When you complete the perfonnance measure will be task successfully, the objective for this job performance satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
The Unit is operating at 100% power.
A Leaking valve required Normal Letdown to be removed from service.,
Excess letdown was placed in service while the repairs were made.
~207°F and 45 psig on 1-PI-62-57.
Excess letdown temperature is 207°F I-PI-62-57.
The leaking valve has now been repaired.
1-SO-62-1.
Normal Letdown has been restored to service in accordance with I-S0-62-1.
I-HIC-62-93 l-HIC-62-93 is in manual, per- 1-SO-62-6, Excess Letdown.
per section 5.0 of 1-S0-62-6, 1-SO-62-6, Section 4.0, 5.0 and 7.0 step 1lare I-S0-62-6, are complete.
INITIATING CUES:
You are the U-l U-i OATe.
OATC. You have been directed to remove excess letdown from service using I-S0-62-6, 1-S0-62-6, Section 7.0.
JPM JPM 152-1 152-1 Page 1 of 8 Pagelof8 Rev.
Rev. 00 SEQUOYAH NUCLEAR NUCLEAR PLANT PLANT JOB PERFORMANCE PERFORMANCE MEASURE MEASURE JPM # 152-1 152-1 Swap RHR Pumps (Train B to Train A)
With Level in the Pressurizer PREPARED!
PREPARED!
REVISED BY: Date/
Date!
VALIDATE VALIDATEDD BY:
- Date/
Date)
APPROVED APPROVED BY:
BY: Date/
Date!
(Operations (Operations Training Manager)
CONCURRE CONCURRED:D: **
- Date/
Date!
(Operations (Operations Representativ Representative)e)
- Validation Validation not not required required for for minor minor enhancement enhancements, procedure Rev s, procedure Rev changes changes thatthat do do not not affect affect the the JPM, JPM, or or individual individual step step changes changes that that do do not not affect affect the the flow of the flow of the JPM.
JPM.
revision).
JPM152-1 JPM 152-1 Page 2 of8 .
Page2of8 Rev.
Rev. 00 NUCLEAR TRAINING NUCLEAR TRAINING REVISIONIUSAGE LOG REVISION/USAGE LOG REVISION REVISION DESCRIPTION OF DESCRIPTION OF VV DATE DATE PAGES PAGES PREPARED/
PREPARED/
NUMBER NUMBER REVISION REVISION AFFECTED AFFECTED REVISED REVISED BY:BY:
00 New JPM based New JPM based on on JPM JPM 152, 152, changed changed toto YY 12/03/09 12/03/09 All All M M Hankins Hankins swap from swap from Train Train B to Train B to Train AA RHR RHR pump.
pump.
v - Specify V -
Specify ifif the the JPM JPM change change will will require require another another validation validation (Y (Y or or N).
N).
See cover See cover sheet sheet for for criteria.
criteria.
JPM JPM 152-1 152-1 Page 33 of Page of88 Rev.
Rev. 00 SEQUOYAH SEQUOYAH NUCLEAR NUCLEAR PLANT PLANT ROISRO RO/SRO JOB PERFORMANCE JOB PERFORMANCE MEASURE MEASURE Task:
Task: Swap RHR Swap RHR Pumps Pumps (Train (Train BB toto JAITA task JAfTA task ##:: 0050030101 0050030101 (RO)
(RO)
Train A)
Train with Level A) with Level inin the the 0050080101 0050080101 (RO)
(RO)
Pressurizer Pressurizer K!A Ratings:
KIA Ratings:
005K4.03 (2.9/3.2) 005K4.03 (2.9/3.2) 005A1 .01 (3.5/3.6) 005A1.01 (3.5/3.6) 005A4.02 005A4.02 (3.4/3.1)
(3.4/3.1) 005K4.10 (3.1/3.1))
005K4.10 (3.1/3.1 005A1.02 (3.3/3.4) 005A1.02 (3.3/3.4) 005A4.01 005A4.01 (3.6/3.4)
(3.6/3.4) 005A4.01 (3.6/3.4) 005A4.01 (3.6/3.4)
Task Standard:
Task Standard:
A Train
'A' Train RHR RHR isis placed placed in in service service injecting injecting to Loops 22 && 3.
to Loops 3.
Evaluation Method:
Evaluation Method: Simulator _....!.X:.!...-_
Simulator X In-Plant _ __
In-Plant
========================================================================
Performer:
Performer:
NAME Start time _ __
Performance Rating: SAT Performance UNSAT Performance Time time _ __
Finish time Evaluator:
Evaluator: /- - - - - -
SIGNATURE SIGNATURE DATE
========================================================================
COMMENTS COMMENTS
JPM JPM152-1 152-1 Page Page4o 4 of f8 8
Rev.
Rev. 0 0 SPECIALINSTRUCTIONS SPECIAL INSTRUCTIONSTO TOEVALUATOR:
EVALUATOR:
- 1. Initiali ze IC-I 97.
- 1. Initialize IC-197. Ensure Train Ensure TrainBBRHR RHRisisininservice servicewith withflow flowaligned alignedthrough throughFCV-63-94 FCV-63-94totoLoops Loops11 &&4.4.
2.2. AnAnextra extraoperator operatorwill willbeberequired requiredtotoacknowledge acknowledgealarms alarmsand andmonitor monitorS/G SIGlevels, levels,RCS RCStemp, temp, RCS RCSpress.
press.
3.3. Any AnyUNSAT UNSATrequires requirescommentscomments 4.4. Ensure Ensureoperatoroperatorperforms performsthe thefollowing followingrequired requiredactions actionsfor forSELF-CHECKING; SELF-CHECKING;
- a. Identif ies the correct unit, train,
- a. Identifies the correct unit, train, component, etc. compo nent, etc.
b.b. Reviews Reviewsthe theintended intendedaction actionandandexpected expectedresponse.
response.
- c. Compa
- c. Compares resthetheactual actualresponse responsetotothe theexpected expectedresponse.
response.
5.5. Ensure Ensure74-530 74-530valvevalveisisclosed.
closed.
6.6. Override Overridealarm alarm SR SR Hi Hi Flux Fluxat atSOSD Validation Time:
Validation Time: CR. CR. 15 15 minutes minutes Local Local_ _ _ __
ToolslEquipment/ProceduresNeeded:
Tools/Equipment/Procedures Needed:
0-SO-74-1, Section 0-SO-74-1, Section 8.3.1 8.
3.1 REFERENCES
REFERENCES:
Reference Reference Title Rev Tftle Rev No.
No.
- 1. 0-SO-74-1 0-SO-74-1 Residual Heat Residual Heat Removal Removal System System 69 69
=================================================================
READ TO OPERATOR OPERATOR Directions to Directions to Trainee:
Trainee:
will explain II will explain the the initial initial conditions, conditions, and state the task to be performed. performed. All control control room steps steps shall shall be be performed for performed for this this JPM.
JPM. II will provide provide initiating initiating cues and reports on other actions when directe directed by you.
you.
When d by When you complete the you complete the task succes sfully, the objecti successfully, objective performance ve for this job perform measure ance measu will be satisfied.
re will be satisfied.
Ensure Ensure you you indicat indicate e to to me me when you unders understand tand your assign assigned indicate ed task. To indicat have e that you have compl completed eted your your assign assigned ed task return the handou handoutt sheet II providprovideded you.
INITIAL INITIAL COND ITIONS:
CONDITIONS:
1.
- 1. Unit Unit I1 had had been been in in Mode Mode 55 for for 72 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> hours toto repair repair aa leak leak on on the the #1
- 1 Steam Steam Line.
Line.
2.
- 2. RHR RHR pump pump BB isis in-serv in-serviceice and and supply supplyinging letdow letdown n 2.
- 2. RCS RCS boron boron isis 14001400 ppm ppm andand the the previo previousus shift shift determ determined that Train ined that Train AA RHR RHR boron boron concen concentration tration isis 1450 1450 ppm.
ppm.
3.3. Shutdo Shutdown wn margin margin require required d boron boron concen tration isis 1200 concentration 1200 ppm. ppm.
4.4. Train B RHR pump Train B RHR pump needs to needs to be be shutdo shutdown wn to to allow allow Mainte Maintenancenance to to add add oil oil toto the the motor.
motor.
5.5. Train Train AA RHR RHR has has beenbeen checke checked d out out locally locally by bythe the Auxili Auxiliaryary Bldg Bldg AUO AUO and and isis ready readyfor for service service..
6.6. Two Two AUOsAUO's are are briefed briefed and and standin standing g byby inin the the Auxili ary Buildi Auxiliary Building ng toto assist assist inin swapp swapping ing thethe pumps pumps. .
0-SO-74-1 Prereq 7.7.0-S0-74-1 uisite Action Prerequisite Actions s are are comple complete. te.
INITIATING INITIATING CUES CUES: :
You are the You are the Unit Unit I1OATCOATCand andthetheSRO SROhas hasdirecte directedd you you toto place placeTrain TrainAA RHR RHR inin service service and and remov remove e Train Train BBRHRRHRfromfrom service service, , using using0-SO-7 0-SO-74-1 Section8.3.1, 4-1 Section 8.3.1, step step[1].
[1].
Align AlignTrain TrainAAinjectio injection n flowpa flowpathth totoloops loops22&&3.3.
Notify Notifythe theSROSROwhen whenyou you have haveTrain TrainAARHR RHRininservice service. .
JPM JPM 152-1 152-1 Page55 ofS-Page of&
Rev.
Rev. 00 Job Performance Job Performance Checklist:
Checklist:
STEP/STAN DARD STEP/STANDARD SAT/UNSAT SATIUNSAT STEP 1.:
STEP 1.: Obtain copy Obtain copy of 0-SO-74-1 and of0-SO-74-1 determine appropriate and determine appropriate section section SAT SAT
- UNSAT UNSAT STANDARD: Operator STANDARD: Operator obtains obtains aa copy copy of 0-SO-74-1 and of 0-SO-74-1 and determ determines ines Section Section 8.3.1 8.3.1 isis the section the section forfor Placing Placing Train Train AA RHR RHR liS.
I/S. Start Start Time Time_ _
STEP 2.:
STEP 2.: IFIF adjustment adjustment isis required required onon CCS CCS flowflow through through RHR RHR Hxs,Hxs, THEN THEN SAT SAT ENSURE [FCV-70-156]
ENSURE FFCV-70-1 56] RHR RHR Hx Hx AA CCS CCS outlet outlet isis THROTTLED.
THROTTLED.
- UNSAT UNSAT NOTE:
NOTE: Operator may Operator may decide decide to to keep keep FCV-70-1S6 FCV-70-156 at at current current position.
position.
STANDARD: Operator STANDARD: Operator ensures ensures HS-70-156 HS-70-156 has has aa RED RED && GREEN GREEN light light LIT LIT with with flow flow indicated on indicated on 0-M-27A.
0-M-27A.
STEP 3.:
STEP 3.: ENSURE [FCV-74-16]
ENSURE [ECV-74-1 61 RHR Hx A Outlet Outlet is CLOSED. SAT
- UNSAT UNSAT STANDARD: Operator STANDARD: Operator ensures FCV-74-16 FCV-74-1 6 RHR Hx A Outlet CLOSED, HIC-74-16 @ 100%.
STEP STEP 4.:
4.: START RHR Pump A-A with [HS-74-10AJ.
START [HS-74-1OA]. SAT SAT
- UNSAT UNSAT STANDARD STANDARD:: Operator may address making a plant announceme announcement nt prior to starting lA-A 1A-A RHR Pump (not critical). Critical Step Starts pump and verifies RED light LIT on HS, verifies amps.
STEP STEP 5.:
5.: VERIFY VERIFY FFCV-74-12
[FCV-74-12] 1 RHR PumpPump A-A A-A miniflow miniflow OPENS OPENS or or greater greater than than SAT SAT 500 gpm in indicated on 500 gpm in indicated on FI-74-12.FI-74-12.
- UNSAT UNSAT Cue:
Cue: IF IF dispatched:
dispatched: FI-74-12 FI-74-12 indicates indicates >500 >500 gpm.
gpm.
STANDARD STANDARD: : Operator Operator verifies verifies FCV-74-1 FCV-74-12 2 isis open open by by Red Red light light LIT on handswitch LIT on handswitch OR OR checks checks with with AUO AUO locally to verify locally to verify >500
>500 gpm gpm flow flow indicated indicated on on local local flow flow indicator indicator FI-47-12.
FI-47-12.
STEP STEP 6.:
6.: IF aligning IF aligning Train Train AA RHR RHR cooling cooling to to loops loops 22 and and 3, 3, THEN THEN SAT SAT PERFORM the following:
PERFORM the following:
[a]
[a] ENSURE ENSURE [FCV-63-93I
[FCV-63-931 OPEN.OPEN.
- UNSAT UNSAT STANDARD STANDARD: : Operator Operator opensopens FCV-63-93, FCV-63-93, verifies verifies redred light light illuminated, illuminated, green green light light dark.
dark. Critical Step Critical Step
JPM JPM152-1 152-1 Page 6 of8 Page6of8 Rev.
Rev. 00 Job Performance Job PerformanceChecklist:
Checklist:
STEPISTAN STEP/ST ANDARDDARD SAT/UNSAT SATIUN SAT STEP 7.:
STEP 7.: [b) ADJUST [FCV-74-16]
[bJ ADJUST [FCV-74-16] toto establish establish flow flowfrom from train train AA RHR.
- UNSAT U NSAT STANDARD:
STANDARD: Operator adjusts Operator adjusts FCV-74-16 FCV-74-16 RHR RHR HxHx AA Outlet Outlet OPEN, OPEN, using HIC-74-16, using HIC-74-1 6, toto the the approximate approximate valve valve of of HIC-74-28, HIC-74-28, to to obtain obtain
--2000 gpm
-2000 gpm flow flow (-68-70%
(68-70% demand demand on on HIC).
H IC). Critical Critical Step Step STEP 8.:
STEP 8.: [c) ADJUST [FCV-74-281
[c] ADJUST [FCV-74-281 AND AND [FCV-74-321
[FCV-74-32] to to reduce reduce SAT SAT Train BB RHR Train RHR flow.
flow. -
- UNSAT UNSAT STANDARD:
STANDARD: Operator closes Operator closes FCV-74-28 FCV-74-28 RHR RHR HxHx BB Outlet, Outlet, place place HIC-74-28 HIC-74-28 to to 0%.
0%.
Critical Critical Step Step STEP 9.:
STEP 9.: [d) VERIFY [FCV-74-241
[dl VERIFY [FCV-74-241 RHR RHR Pump Pump B-B B-B miniflow miniflow OPENS OPENS SAT SAT OR greater than 500 gpm in in indicated indicated on OR on FI-74-24.
Fl-74-24.
- UNSAT UNSAT Cue:
Cue: IF dispatched: FI-74-24 indicates >500 IF >500 gpm.
STANDARD: Operator STANDARD: Operator verifies FCV-74-24 is open by Red light LIT on handswitch or checks with checks with AUO locally to verify >500 gpm flow indicated on local flow indicator FI-47-24.
indicator Fl-47-24.
STEP 10.:
STEP 10.: [eJ CLOSE
[e) CLOSE [FCV-74-35]
rFCV-74-35] RHR Hx B Outlet. SAT
- UNSAT STANDARD STANDARD:: Operator Operator closes FCV-74-35, green light illuminated, red light dark.
Critical Step Step STEP STEP 11.:
11.: [f}
[f] ENSURE ENSURE [FCV-74-331
[FCV-74-33] RHR RHR Hx Hx A Outlet Outlet OPEN.
OPEN. SAT SAT STANDARD STANDARD:: Operator Operator ensures ensures FCV-74-33 FCV-74-33 RHR RHR Hx Hx A A Outlet Outlet OPEN, OPEN, red red light light UNSAT UNSAT illuminated, illuminated, green green light light dark.
dark.
STEP STEP 12.:
12.: [g] OPEN
[g] OPEN IVLV-74-53
[VLV-74-530] 0] RHR RHR HxHx AA to to Letdown Letdown Hx. Hx. SAT SAT NOTE:
NOTE: Console Console operator operator needsneeds toto modify modify remote remote function function RHRO3 RHR03 to to 100.
100. UNSAT UNSAT Cue:
Cue: AUO reports AUO reports that that VLV-74-530 VLV-74-530 has has been been opened opened locally, locally, operator operator should should discuss discuss the the need need for for CV.
CV. Critical Step Critical Step STANDARD STANDARD: : Operator Operator directs directs an an AUOAUO to to OPEN OPEN VLV-74-530 VLV-74-530 RHR RHR Hx Hx AA to to Letdown Letdown Hx.
Hx.
JPM JPM 152-1 152-1 Page 7 ofB Page7of8 Rev.
Rev. 00 Job Performance Job Performance Checklist:
Checklist:
STEPISTANDARD STEP/STANDARD SAT/UNSAT SAT/UNSAT STEP 13.:
STEP 13.: [h] STOP RHR
[h] STOP RHR Pump Pump B-BB-B with with [HS-74-20A].
[HS-74-20A1. SAT SAT
- UNSAT UNSAT STANDARD: Operator STANDARD: Operator stops stops RHR RHR pump pump 118-B, verifies GREEN B-B, verifies GREEN light light on on handswitch.
handswitch.
Critical Critical Step Step STEP 14.:
STEP 14.: [i] OPEN [HCV-74-36]
[i] OPEN IHCV-74-361 RHR RHR Hx Hx AA Bypass.
Bypass. SAT SAT NOTE:
NOTE: Console operator Console operator needs needs toto modify modify remote remote function function RHR06 RHRO6 to to 100.
100. UNSAT UNSAT Cue:
Cue: AUO reports AUO reports HCV-74-36 HCV-74-36 is is opened opened (including (including CV).
CV).
Critical Critical Step Step STANDARD: Operator directs an AUO to OPEN HCV-74-36 STANDARD: HCV-74-36 RHR RHR Hx Hx A Bypass.
Bypass.
STEP 15.:
STEP 15.: U] CLOSE [HCV-74-37]
[j] FHCV-74-371 RHR Hx Hx B Bypass. SAT NOTE: Console operator needs to modify remote function RHR07 RHRO7 to toO.O. UNSAT Cue: AUO reports HCV-74-37 has been closed /ocally locally (including CV).
Critical Step STANDARD: Operator directs an AUO to CLOSE HCV-74-37 RHR Hx B STANDARD: B Bypass.
STEP 16.:
STEP 16.: [k] CLOSE rVLV-74-53
[VLV-74-531] 1l RHR Hx B-B 8-B to Letdown Hx. SAT NOTE: Console operator needs to modify remote function RHRO4 RHR04 toO.to O. UNSAT Cue: AUO AUO report s VLV-74-531 has has been closed an AUO AUO locally (including CV).
STANDARD STANDARD:: Operator Operator directs directs an an AUO AUO toto close close HCV-74-531 HCV-74-531..
STEP STEP 17.:
17.: [I] ENSURE
[I] ENSURE FFCV-63-94
[FCV-63-94] 1 CLOSED.
CLOSED. SAT SAT
- UNSAT UNSAT STANDARD STANDARD:: Operator Operator closes closes FCV-63-94, FCV-63-94, green green light light illuminated, illuminated, red red light light dark dark Critical Step Critical Step STEP STEP 18.:
1B.: IF aligning IF aligning RHRRHR cooling to loops cooling to loops 11 and and 4,4, THEN THEN ENSURE ENSURE the the following following SAT SAT valves valves are are inin the the required required position.
position.
- UNSAT UNSAT NOTE:
NOTE: Step Step is is NAd, NA'd, initiating initiating Cues Cues direct direct alignment alignment to loops 22 && 3.
to loops 3.
STANDARD STANDARD: : Operator Operator NAs NA's the the step.
step.
JPM JPM 152-1 152-1 Page Page88of8 of 8 Rev.
Rev. 00 Job Performance Job PerformanceChecklist:
Checklist:
STEP/STANDARD STEP/STANDARD SAT/UNSAT SAT/UNSAT NOTE:
NOTE: Initial flow Initial flow values values - 2500-2800 2500-2800 gpm. gpm. SAT SAT STEP 19.:
STEP 19.: THROTTLE one THROTTLE one or both of or both ofthe following toto maintain the following maintain desired desired cooling cooling UNSAT UNSAT rate:
rate:
FCV-74-1 6, RHR FCV-74-16, RHR Hx Hx AA Outlet, Outlet, AND/OR AND/OR FCV-74-32, RHR FCV-74-32, RHR Hx Hx Bypass.
Bypass. Critical Critical Step Step STANDARD: Operator STANDARD: Operator may may throttle throttle FCV-74-16 FCV-74-1 6 and/or and/or FCV-74-32 FCV-74-32 to to stabilize stabilize RCS RCS temperature and establish RHR temperature and establish RHR flowrates flowrates at at approximately approximately thethe same same values that values that were were present present prior prior to the flowpath to the flowpath realignment.
realignment.
STEP 20.:
STEP 20.: WHEN injection WHEN injection flow flow isis> 1250 gpm,
> 1250 gpm, THEN THEN VERIFY VERIFY [FCV-74-12]
FFCV-74-121 RHR RHR SAT SAT Pump A-A Pump A-A miniflow miniflow isis CLOSED.
CLOSED.
- UNSAT UNSAT STANDARD: Operator STANDARD: Operator verifies verifies FCV-74-12 FCV-74-1 2 closed, closed, GREEN GREEN light light LIT LIT on on handswitch.
handswitch.
STEP 21.:
STEP 21.: IF cooling water is to be removed IF cooling removed from Train B Hx, THEN SAT CLOSE [FCV-70-153].
[FCV-70-1 531.
- UNSAT U NSAT Cue:
Cue: Leave cooling water aligned to Train B at its current flowrate.
STANDARD: Operator STANDARD: Operator NA's NAs step.
STEP 22.:
STEP 22.: NOTIFY U1 NOTIFY Ui US that Train A of RHR is in service to loops 2 & 3 and SAT Train Train B of RHR has been removed from service.
- UNSAT STANDARD STANDARD:: None.
None. Stop Time Stop Time_ _
End End of JPM ofJPM
READ TO OPERATOR Directions to Trainee:
II will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. II will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
- 1. Unit 1I had been in Mode 5 for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to repair a leak on the #1 Steam Line.
- 2. RHR pump B is in-service and supplying letdown
- 2. RCS boron is 1400 ppm and the previous shift determined that Train A RHR boron concentration is 1450 ppm.
- 3. Shutdown margin required boron concentration is 1200 ppm.
- 4. Train B RHR pump needs to be shutdown to allow Maintenance to add oil to the motor.
service.
AUOs are briefed and standing by in the Auxiliary Building to assist in swapping
- 6. Two AUO's the pumps.
- 7. 0-SO-74-1 Prerequisite Actions are complete.
7.0-S0-74-1 INITIATING CUES:
You are the Unit 1 I OATC and the SRO has directed you to place Train A RHR in service and remove Train B B RHR from service, using 0-SO-74-1, Section 8.3.1, step [1].
Align Train A injection flowpath flpwpath to loops 22 &
& 3.
Notify the SRO when you have Train A RHR in sen/ice. service.
JPM65-1 JPM65-1 Page 11 of Page of 99 Rev.O Rev. 0 SEQUOYAH NUCLEAR SEQUOYAH NUCLEAR PLANT PLANT JOB PERFORMANCE PERFORMANCE MEASURE MEASURE JPM#65-1 JPM # 65-1 Re-establishment of Containment Pressure Control Re-establishment Following High Pressure Conditions PREPARED PREPAREDI/
REVISED BY: Date/
Date!
VALIDATE VALIDATEDD BY: *
- Date/
Date!
~=-----------
APPROVED APPROVED BY:
BY: Date/
Date!
(Operations (Operations Training Training Manager)
Manager)
CONCURRE CONCURRED:D: **
- Date/
Date!
(Operations Representativ Representative) e)
- Validation Validation not not required required forfor minor minor enhancement enhancements, s, procedure procedure Rev Rev changes changes thatthat do not affect do not affect the JPM, the JPM, or or individual step changes individual step changes that do not that do not affect affect the the flow flow of of the the JPM.
JPM.
revision).
JPM65-1 JPM65-1 Page Page 22 of9 of 9 Rev.Q.
Rev.a NUCLEAR TRAINING NUCLEAR TRAINING REVISION/USAGE LOG REVISION/USAGE LOG REVISION REVISION DESCRIPTION OF DESCRIPTION OF VV DATE DATE PAGES PAGES PREPARED/
PREPAREDI NUMBER NUMBER REVISION REVISION AFFECTED AFFECTED REVISED BY:
REVISED BY:
00 New JPM adapted from JPM 65 New 65 for NRC NRC Y 1/14/10 1/14/10 ALL M M Hankins Hankins exam 0210.
exam v -Specify V -
Specify ifif the the JPM JPM change will will require another another validation.
See cover sheet See cover sheet for criteria.
JPM65-1 JPM65-1 Page Page 33 of of 99 Rev,O Rev0 SEQUOYAH NUCLEAR SEQUOYAH NUCLEAR PLANT PLANT ROISRO RO/SRO JOB PERFORMANCE JOB PERFORMANCE MEASURE MEASURE Task:
Task:
Re-establishment of Re-establishment of CNTMT CNTMT Pressure Pressure Control Control Following Following High High Pressure Pressure Condition Condition JA/TAtask#:
JA/TA task # :00601801 (RO) 00601801 (RO)
K/A Ratings:
KIA Ratings:
103A1.01 (3.7/4.1) 103A1.01 (3.7/4.1) 103A4.01 (3.2/3.3) 103A4.01 (3.2/3.3) 2.1.31 2.1.31 (4.2/3.9)
(4.2/3.9) 103A4.09 (3.1/3.7) 103A4.09 (3.1/3.7) 2.1.20 (4.3/4.2) 2.1.20 (4.3/4.2)
Task Standard:
Task Standard:
Vent the Vent the containment containment pressure pressure down down to normal normal range range (within (within -0.1
-0.1 to +0.3
+0.3 psig) psig) and and then then place place the the containment automatic containment automatic Pressure Pressure Control Control System System inin service.
service.
Evaluation Method:
Evaluation X Simulator _..;..X,,--_ In-Plant _ __
======================================================================
Performer:
Performer:
NAME time _ __
Start time Performance Rating: SAT Performance UNSAT Performance Time time _ __
Finish time Evaluator:
Evaluator: /
SIGNATURE SIGNATURE DATE
=======================================================================
COMM COMMENTSENTS
JPM65-1 JPM65-1 Page 4 of 9 Page4of9 Rev. 00 Rev.
SPECIALINSTRUCTIONS SPECIAL INSTRUCTIONSTO TO EVALUATOR:
EVALUATOR:
1.1. Any UNSAT Any UNSAT requires requires comments.
comments.
2.2. Acknowledg Acknowledgee any anyassociated associated alarms.
alarms.
3.3. Initialize Simulator Initialize Simulator inin IC: IC: #116,
- 116, verify verify containment containment pressure pressure 0.60.6 psig.
psig.
4.
- 4. Ensure operator performs the Ensure operator performs the following required following required actions actions for for SELF-CHECKING; SELF-CHECKING; a.a. Identifies Identifies the the correct correct unit, unit, train, train, component, component, etc. etc.
b.b. Reviews Reviews the the intended intended action action andand expected expected response.
response.
c.c. Compares Compares the the actual actual response response to to the the expected expected response.
response.
Validation Time:
Validation Time: CR CR 15 mm 15min Local Local _ _ _ __
ToolslEquipment!Procedures Needed:
Tools/Equipment/Procedures Needed:
0-SO-30-8 Sections 0-SO-30-8 Sections 3.0, 4.0, 3.0, 4.0, and and 5.2 5.2
References:
References:
Reference Reference Title TWe Rev Rev No.
No.
A.
A. O-SO-30-8 0-SO-30-8 Containment Pressure Containment Pressure Control Control 29 29 B.
B. 0-SI-CEM-0 O-S I-CEM-030-41 30-410.10.1 Containment Vent Containment Vent toto Aux Aux Building Building Exhaust Exhaust 31 31
================================================================
READ TO OPERATOR Directions to Directions to Trainee:
Trainee:
II will will explain explain the initial conditions, and state the task to be performed. All control room steps shall be performed be performed for this JPM. II will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance directed measure will measure will be satisfied. Ensure you indicate to me when you understand your assigned task.
To indicate To indicate that you have completed your assigned task return the handout sheet II provided you.
INITIAL INITIAL CONDITION CONDITIONS: S:
- Unit Unit 11 is is in Mode Mode 11 recovering from an an Air Line Line break break inin containment. The The air air leak leak was was discovered discovered on aa section section of of the header header that allowed isolation without affecting any equipment.
- During During isolation isolation efforts, efforts, containment pressure pressure increased to to approximatel approximately 0.6 psig.
y 0.6 psig.
- EAMs EAM's are are in the Adverse in the Adverse Containment Containment condition.
- Purge Purge is is not not in in progress progress
- 0-SI-CEM -030-410.1, O-SI-CEM -030-410.1, Containment Containment Vent Vent to to Aux Aux Building Building Exhaust, is in Exhaust, is in progress progress and and approved approved by by SRO SRO and and Radiochemic Radiochemical al Laboratory Laboratory Supervisor.
Supervisor.
- RM-90-101, RM-90-1 01, 106 106 and and 112 112 and and 130130 are are in in service service and and indicating indicating Normal.
Normal.
- RM-90-106B RM-90-106B isis indicating indicating 2.842.84 E+02; E+02; previous previous sample sample (yesterday)
(yesterday) was was 2.83E+02.
2.83E+02.
- Prerequisite Prerequisite Actions Actions (Section (Section 4.0)4.0) are are complete complete for for 0-SO-30-8.
0-SO-30-8.
- Power Power checklist checklist 1-30-8.02 1-30-8.02 is is complete complete with with no no deviations.
deviations.
INITIATING INITIATING CUES: CUES:
1.1. The The US US directs directs you,you, toto vent vent containment containment usingusing 0-SO-30-8, 0-SO-30-8, section section 5.2.1.
5.2.1.
2.2. Inform Inform the the US US when when Containment Containment pressurepressure isis decreasing.
decreasing.
JPM65-1 JPM65-1 Page 55 of9 Page of 9 Rev,O Rev0 Job Performance Job Performance Checklist:
Checklist:
STEP/STAN STEP/ST DARD ANDARD SAT/UNSAT SAT/U NSAT The following The following stepssteps are are from from Section Section 5.2.1 5.2.1 ofof 0-SO-30-8:
O-SO-30-8: SAT SAT STEP 1.: -
STEP 1.: ENSURE 1-30-8.02 ENSURE 1 8.02 powerpower checklist checklist complete.
complete.
- UNSAT UNSAT STANDARD: Power STANDARD: Power checklist checklist 1-30-8.02 1-30-8.02 isis complete complete withwith no no deviations deviations per per Start Start Time Time_ _
initial conditions.
initial conditions.
STEP 2.:
STEP 2.: ENSURE the ENSURE the check check valve valve portion portion ofof the the containment containment vacuum vacuum SAT SAT relief assembly relief assembly isis capable capable of of closing closing by by observing observing monitor monitor lights lights on panel on panel (panel (panel M-9).
M-9). UNSAT UNSAT STANDARD: Operator STANDARD: Operator checkschecks monitor monitor lights lights onon panel panel (panel (panel M-9)
M-9) toto ensure ensure valves are valves closed, green are closed, green lights lights are are ON.
ON.
STEP 3.:
STEP IF the unit IF unit is is in in MODES MODES 1, 1, ,2,2 or 3, 3, THEN SAT SAT NOTIFY the US/SRO that the EAM will be placed in NOTIFY in the Adverse Containment condition for venting containment. -
UNSAT STANDARD: Per initial conditions, EAM's STANDARD: EAMs are in the Adverse Cntmt condition for venting containment.
STEP 4.:
STEP 4.: EVALUATE entry into LCO 3.6.6. Vacuum Relief Lines. SAT Cue: Play role of SRO and state you will evaluate the LCO. UNSAT STANDARD:
STANDARD: Operator informs the US/SRO LCO 3.6.6, Vacuum Relief Lines needs to be evaluated.
STEP STEP 5.:
5.: IF IF the Unit is the Unit is in in Modes Modes 1, 1, 2,2, 3, THEN THEN SAT SAT PERFORM PERFORM the the following:
[5.1]
[5.1] IF the EAM IF the EAM is is NOT NOT in in the the Adverse CntmtCntmt condition....
condition .... UNSAT UNSAT STANDARD:
STANDARD: Operator Operator recognizes recognizes the the EAMs EAMs are are in in the the Adverse Adverse Cntmt Cntmt condition.
condition. Operator Operator shouldshould N/A N/A step step [5.1]
[5.1] and and complete [5.2][5.2]
and and [5.3].
[5.3].
STEP STEP 6.:
6.: [5.2]
[5.2] ENSURE ENSURE blue blue purge/vent purge/vent operation operation permissive permissive lights lights
- SAT SAT illuminated illuminated for for each each steam steam generator.
generator.
- UNSAT UNSAT STANDARD: Operator verifies STANDARD: Operator verifies blueblue purge/vent purge/vent permissive permissive lights lights are are illuminated illuminated for each SIG for each (M-4 above S/G (M-4 above SG SG NR NR levels levels indicators).
indicators).
STEP 7.:
STEP 7.: [5.3] VERIFY
[5.3] VERIFY windowwindow 30 "S/G Level 30 S/G Level Adverse Adverse Setpoint Setpoint" - SAT SAT illuminated illuminated on on XA-55-3C.
XA-55-3C.
- UNSAT UNSAT STANDARD:
STANDARD: Operator verifies XA-55-3C Operatorverifies XA-55-3C window window 30 30 illuminated.
illuminated.
JPM6S-1 JPM65-1 Page 66 of Page of 99 Rev. 0 Rev.0 Job Performance Job Performance Checklist:
Checklist:
STEPISTANDARD STEP/STANDARD SAT/UNSAT SAT/UNSAT STEP 8.:
STEP 8.: [6] IF
[6] IF the the Unit Unit isis inin Modes Modes 1-4, 1 -4, THEN THEN SAT SAT
[6.1] VERIFY Radiochemic
[6.1] VERIFY Radiochemical al Laboratory Laboratory has has aa current current weekly weekly performance of performance of O-SI-CEM-030-41 0-Sl-CEM-030-410.1 0.1 inin progress.
progress. UNSAT UNSAT STANDARD: Per STANDARD: Per initial initial conditions, conditions, 0-SI-CEM-030-410.1 0-Sl-CEM-030-410.1 isis inin progress progress and and approved by approved by SRO SRO and and Radiochemical Radiochemical Laboratory Laboratory Supervisor.
Supervisor.
STEP 9.:
STEP 9.: [6.2] IF
[6.2] IF the the noble noble gas gas count count rate rate for for lower lower containment containment .... SAT SAT
- UNSAT UNSAT STANDARD: Operator STANDARD: Operator determines determines from from initial initial conditions conditions that that noble noble gas gas hashas not increased not increased by by SO% since last 50% since last sample sample and N/As the and N/A's the step.
step.
STEP 10.:
STEP 10.: [6.3] IF
[6.3] IF the the lower lower containment containment noble noble gas radiation monitor gas radiation monitor is is SAT SAT inoperable .....
- UNSAT STANDARD: Operator determines RM-90-106 is operable by looking at RM or STANDARD:
per initial conditions and N/A's N/As the step.
STEP 11.:
STEP 11.: [7] ENSURE that the Shield Building Annulus Vacuum Control SAT System is in service and maintaining a negative S.O 5.0 inches of O as indicated on M-9, [PDI-30-126]
2 H
H20 [PDI-30-1261 or [PDI-30-127]
[PDI-30-1 271 OR UNSAT EGTS in service OR EGTS testing in progress.
STANDARD STANDARD:: Operator obtains reading from PDI-30-126 or 127 127 on panel M-9, AB-Annulus Vacuum reading - 5of S"of water.
STEP STEP 12.:
12.: [8] VERIFY fjQ NO abnormal or unexplainabl unexplainable e radiation levels exist SAT inside inside containment.
- UNSAT UNSAT STANDARD STANDARD:: Operator Operator checks checks RM-90-106 and and 112112 for for abnormal abnormal radiation radiation levels levels in in containment, determine determine radiation radiation levels levels are are normal normal and and signs signs of of step.
step.
STEP STEP 13.:
13.: [9] VERIFY
[9] VERIFY that that NONO containment containment vent vent isolation isolation signal signal exists.
exists. SAT SAT STANDARD STANDARD:: Operator Operator checks checks XA-55-6C XA-SS-6C windows windows C5 CS && C6 C6 dark dark toto verify verify that that
- UNSAT UNSAT aa containment containment vent vent isolation isolation signal signal isis not not present.
present.
STEP STEP 14.:
14.: [10] ENSURE
[10] ENSURE at at least least ONEONE of of the the following following radiation radiation monitors monitors inin - SAT SAT service:
service:
UNSAT UNSAT U-I U-1 Containment Containment I-RM-90-130 1-RM-90-130 Purge Purge Exhaust Exhaust Monitors Monitors 1-RM-90-13 1-RM-90-131 1 STANDARD STANDARD: : Operator Operator verifies verifies the the RM-90-I RM-90-130 30 per per initial conditions isis inin service initial conditions service (No (No Alarms Alarms and and Not Not Blocked).
Blocked).
JPM65-1 JPM65-1 Page 70f9 Page 7 of 9 Rev.
Rev. 00 Job Performance Job Performance Checklist:
Checklist:
STEPISTANDARD STEPISTANDARD SATIUNSAT SAT/UNSAT STEP 15.:
STEP 15.: [11] VERIFY that
[11] VERIFY that all all personnel personnel have have been been evacuated evacuated from from the the SAT SAT annulus and annulus and that that all all doors doors are closed.
are closed.
- UNSAT UNSAT Cue:
Cue: when asked, when asked, Role Role play play Rad Rad ConCon and and state state al/ allpersonnel personnel are are out of out ofthe the annulus annulus and and the the doors doors are closed.
are closed.
STANDARD: Operator STANDARD: Operator calls calls Rad Rad Con Con and and verifies verifies that all personnel that all personnel havehave been evacuated been evacuated from from the the annulus annulus and and that that allall doors doors are are closed.
closed.
STEP 16.:
STEP 16.: [12] ENSURE
[12] ENSURE at at least least one one of of the the following following radiation radiation monitors monitors in in SAT SAT service for service for the the appropriate appropriate unit: unit:
- UNSAT UNSAT AB Vent:
AB Vent: 0-RM-90-1 01 0-RM-90-1 01 BB Upper Compartment:
Upper Compartment: 1-RM-90-1 12 A, BB 1-RM-90-112 Lower compartment:
Lower compartment: I -RM-90-1 06 A, 1-RM-90-106 A, BB STANDARD: Operator verifies the absence of applicable instrument malfunction STANDARD:
alarms on 0-M-12, the RM's RMs above are in service and Normal per initial conditions.
STEP 17.:
STEP [13J ENSURE PROTECTED
[13] PROTECTED EQUIPMENT EQUIPMENT DO NOT INOP tags placed on SAT the following radiation monitors block switches as appropriate: (N/A tags not placed). - UNSAT BLOCK SWITCH MONITOR O-HS-90-1 0-HS-90-136A 36A11 11-RM-90-130
-RM-90-1 30 0-HS-90-1 0-HS-90-136A2 36A2 11-RM-90-131
-RM-90-1 31 O-HS-90-1 0-HS-90-136A3 36A3 0-RM-90-1 0-RM-90-1 01 01 BB Cue: An An Extra Extra Operator Operator will will place place Protected Protected Equipment tags. tags.
STANDARD STANDARD:: Operator Operator addresses addresses placing placing PROTECTE PROTECTED D EQUIPMEN EQUIPMENT Tags T Tags on Rad on Rad monitor monitor Block Block Switches.
Switches.
STEP STEP 18.:
18.: [14] IF aligning
[14] IF aligning thethe lower lower compartment compartment purge purge isolation isolation valves valves - SAT SAT using using the the NORMAL NORMAL flow flow path, path, THEN THEN PERFORM PERFORM steps steps [a] [a] thru thru [f].
[f]. - UNSAT UNSAT NOTE:
NOTE: This step will This step will bebe satisfied satisfied in in steps steps 19 19 thru thru 22. 22.
STANDARD STANDARD: : Operator Operator selects selects the the normal normal flow path as flow path as stated stated inin initial initial conditions.
conditions.
JPM65-1 JPM65-1 Page 88 of9 Page of 9 Rev.
Rev. 00 Job Performance Checklist:
Job Performance Checklist:
STEPIsTANDARD STEP/STANDARD SAT/U NSAT SATIUNSAT STEP 19.:
STEP 19.: [14.1] ENSURE
[14.1] ENSURE [FCV-30-37]
[FCV-30-371 isis CLOSED.
CLOSED. SAT SAT STANDARD: Operator STANDARD: Operator verifies verifies green green light light ON for FCV-30-37 ON for FCV-30-37 UNSAT UNSAT STEP 20.:
STEP 20.: [14.2] ENSURE
[14.2] ENSURE [FCV-30-40]
[FCV-30-40] isis CLOSED.
CLOSED. SAT SAT STANDARD: Operator STANDARD: Operator verifies verifies green green light light ON ON for for FCV-30-40 FCV-30-40 UNSAT UNSAT STEP 21.:
STEP 21.: [14.3] OPEN [FCV-30-14
[14.3] OPEN [FCV-30-1 4 && 56] with [HS-30-14].
561 with IHS-30-1 41. SAT SAT STANDARD: Operator STANDARD: Operator places places HS-30-14 HS-30-14 in in the the OPEN OPEN position position and and places places UNSAT UNSAT HS-30-14 in HS-30-14 in the the A-AUTO A-AUTO position.
position.
Critical Step STEP 22.:
STEP 22.: [FCV-30-14 & 56] OPEN.
[14.4] VERIFY [FCV-30-14 SAT STANDARD: Operator verifies red lights illuminated ON [FCV-30-14 STANDARD: FEC V-30-14 & 56]. UNSAT STEP 23.: [14.5] OPEN [FCV-30-15
[FCV-30-1 5 & 57] with HS-30-15.
HS-30-1 5. SAT
- UNSAT STANDARD: Operator places HS-30-15 in the OPEN position and places STANDARD:
HS-30-15 in the A-AUTO position.
Critical Step STEP STEP 24.: [14.6] VERIFY FCV-30-15 & 57 OPEN. SAT STANDARD STANDARD:: Operator verifies red lights lights illuminated for FCV-30-15 FCV-30-15 & 57 and UNSAT places HS-30-1 HS-30-15 5 in in the A-AUTO position.
STEP 25.:
STEP 25.: [15]
[15] IF IF aligning the lower aligning the lower compartment purge purge isolation isolation valves valves
- SAT SAT using the Alternate using the Alternate flow flow path path THEN THEN PERFORM PERFORM stepssteps [15.11
[15.1] thru thru
[15.8].
[15.8]. - UNSAT STANDARD STANDARD:: Operator Operator should should NA NA this this step step since since the the NORMAL NORMAL flow flow path path isis being being used.
used.
STEP STEP 26.:
26.: [16] OPEN
[161 OPEN Annulus Annulus exhaust exhaust isolation isolation valve valve FCV-30-54 FCV-30-54 withwith
- SAT SAT HS-30-54.
HS-30-54.
- UNSAT UNSAT STANDARD STANDARD: : Operator Operator opens opens FCV-30-54 FCV-30-54 with with HS-30-54.
HS-30-54. Verifies Verifies valve valve open open by observing by observing red red light light ON.
ON. Critical Step Critical Step
JPM65-1 JPM65-1 Page99of9 Page of 9 Rev. 0 Rev.O JobPerformance Job PerformanceChecklist:
Checklist STE PISTAN DARD STEP/STANDARD SAT/UNSAT SATIUNSAT
- SAT SAT STEP27.:
STEP 27.: [17] RECORD
[17] RECORD time time purge purgeisolation isolationvalves valvesareareOPENED.
OPENED.
TIME TIME - UNSAT UNSAT STANDARD: Operator STANDARD: Operatorrecords records thethe time time purge purge valves valves were were opened.
opened.
STEP 28.:
STEP 28.: [18] IF
[18] IF the the Annulus Annulus Vacuum Vacuum Control Control System System isis inin service service and and the the SAT
- SAT standby Annulus standby Annulus Vacuum Vacuum Control Control Fan Fan isis available, available, THEN THEN PERFORM the PERFORM the following following UNSAT UNSAT START START the the standby standby Annulus Annulus Vacuum Vacuum Control Control Fan.
Fan.
STANDARD: Operator STANDARD: Operator starts starts the the standby standby Annulus Annulus Vacuum Vacuum Control Control Fan.
Fan.
STEP 29.
STEP 29. IF aa high IF high radiation radiation alarm alarm occurs occurs onon any any of of the the following following RM'sRMs SAT SAT STANDARD: Operator STANDARD: Operator checks checks RM's, RMs, andand verifies verifies all all alarms alarms are are clear.
clear. UNSAT UNSAT STEP 30.
STEP 30. Operator notifies US that containment vent is in progress. SAT SAT CUE:
CUE: Another operator Another operator will complete the vent. UNSAT UNSAT STOP TIME STOP TIME ENDOFJPM END OF JPM
READ TO OPERATOR Directions to Trainee:
II will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. II will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied.
Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet II provided you.
INITIAL CONDITIONS:
- Unit 1 1 is in Mode 11 recovering from an Air Line break in containment. The air leak was discovered on a section of the header that allowed isolation without
( affecting any equipment.
- During isolation efforts, containment pressure increased to approximately 0.6 psig.
- EAMs are in the Adverse Containment condition.
EAM's
- Purge is not in progress
- 0-Sf-OEM -030-410.1, Containment Vent to Aux Building Exhaust, is in progress O-SI-CEM and approved by SRO and Radiochemical Laboratory Supervisor.
- RM-90-1 RM-90-101, 01, 106 and 112 and 130 are in service and indicating Normal.
- RM-90-106B is indicating 2.84 E+02; previous sample (yesterday) was 2.83E+02.
- Prerequisite Actions (Section 4.0) are complete for 0-SO-30-8.
- checklist 1-30-8.02 is complete with no deviations.
Power checkHst INITIATING CUES:
- 3. The US directs you, to vent containment using 0-SO-30-8, section 5.2.1.
- 4. Inform the US when Containment pressure is decreasing.
JPM34-1 JPM34-1 Page 11 of Page of 12 12 R~v.
Rev.O 0 .
SEQUOYAH NUCLEAR SEQUOYAH NUCLEAR PLANT PLANT JOB PERFORMANCE JOB PERFORMANCE MEASURE MEASURE JPM#3 JPM # 34-14-1 Establishing Secondary Establishing Secondary Heat Sink Using Feedwater or Condensate Main Feedwater Condensate PREPARED PREPAREDI!
REVISED BY: Date!
VALIDATE VALIDATEDD BY:
BY:
- Date!
Date!
~=-----------
APPROVED APPROVED BY:
BY: Date!
Date!
(Operations (Operations Training Training Manager)
Manager)
CONCURRE CONCURRED:D: **
- Date!
Date!
(Operations (Operations Representativ Representative) e)
- Validation Validation not not required required forfor minor minor enhancement enhancements, procedure Rev s, procedure Rev changes changes thatthat do do not affect the not affect the JPM, JPM, oror individual individual step step changes changes that that do do not not affect affect the the flow flow of of the JPM.
the JPM.
revision).
JPM34-1 JPM34-1 Page Page 22 of of 12 12 Rev.
Rev. 00 NUCLEAR TRAINING NUCLEAR TRAINING REVISIONIUSAGE LOG REVISION/USAGE LOG REVISION REVISION DESCRIPTION OF DESCRIPTION OF VV DATE DATE PAGES PAGES PREPARED/
PREPARED!
NUMBER NUMBER REVISION REVISION AFFECTED AFFECTED REVISED REVISED BY: BY:
00 Initial issue Initial issue YY 1/31/10 1/31/10 All All M M Hankins Hankins Vv - Specify Specify ifif the the JPM JPM change change will require another will require another validation (Y or validation (Y or N).
N).
See cover See cover sheet sheet for for criteria.
criteria.
JPM34-1 JPM34-1 Page Page33ofof12 12 Rev. Q Rev.0 SEQUOYAH SEQUOY NUCLEARPLANT AH NUCLEAR PLANT ROISRO RO/SRO JOB PERFORMANCE JOB PERFORMANCE MEASURE MEASURE Task: Establishing Task: Establishing Secondary Secondary Heat Heat sink sink using using Main Main Feedwater FeedwaterororCondensate Condensate System System JA/TAtask#: 3110060601 JAlTAtask#: 3110060601 (RO)
(RO) 0100040101 0100040101 (RO)
(RO)
K/A Ratings:
KIA Ratings:
WEO5 EA2.1 (3.4/4.4)
WE05 EA2.1 (3.4/4.4)
Task Standard:
Task Standard:
Loss of Loss of Secondary Secondary Heat Heat Sink, Sink, Establish Establish Secondary Secondary Heat Heat Sink Sink Using Using Main Main Feedwater Feedwater or or Condensate Condensate System System Evaluation Method:
Evaluation Method: Simulator _~X'--_
Simulator X In-Plant - - -
In-Plant
========================================================================
Performer:
Performer:
NAME NAME Start Time _ __
Start Time Performance Rating:
Performance Rating: SAT UNSAT Performance Time Finish Time _ __
Finish Time Evaluator:
Evaluator:
~/-----
SIGNATURE I
DATE SIGNATURE DATE
========================================================================
COMMENTS COMMENTS
JPM34-1 JPM34-1 Page44ofof12 Page 12 Rev.
Rev.00 SPECIAL INSTRUCTIONS SPECIAL INSTRUCTIONSTO TO EVALUATOR:
EVALUATOR:
1.1. Critical steps are identified.
Critical steps are identified.
2.2. Any UNSAT Any UNSAT requires requires comments comments 3.3. Acknowledge any Acknowledge any associated associated alarms.
alarms.
4.4. Initialize simulator Initialize simulator inin Ie: IC: 119 119 Steam Steam Dump Dump Pressure Pressure ModeMode Setpoint-968 Setpoint-968 psig psig All AFW pumps All AFW pumps are are shutdown, shutdown, MDAFWMDAFW A-A A-A tagged, tagged, TDAFW TDAFW pump pump and MDAFW 8-8 and MDAFW B-B trip trip onon ReactorTrip.
Reactor Trip. RX RX trip trip due due RodRod control control problems problems (multiple (multiple rodrod drops),
drops), adjust adjust steam dumps inin steam dumps pressure mode pressure mode to to control control TavgTavg 544-546°F.
544-546°F.
5.
- 5. Allow S/G Allow S/G narrow narrow rangerange levels levels are are <-20%.
<20%. (allow(allow SDSD to to steam steam off off to to reduce reduce S/GSIG level level ifif necessary) necessary) 6.
- 6. Console operator Console operator will will role role playas play as CROCRC and and acknowledge/clear acknowledge/clear alarms alarms as as needed.
needed.
7.
- 7. Ensure operator Ensure operator performs performs the the following following required required actions actions forfor SELF-CHECKING; SELF-CHECKING;
. a. Identifies the
- a. Identifies the correct correct unit, unit, train, train, component, component, etc. etc.
- b. Reviews the
- b. Reviews the intended intended actionaction andand expected expected response.
response.
- c. Compares
- c. Compares the the actual actual response response to the expected to the expected response.
response.
Validation Time:
Validation Time: CR.CR. 30 mins 30 mins Local Local _ _ _ __
ToolslEquipmentlProcedures Needed:
Tools/Equipment/Procedures Needed:
EA-2-2 EA-2-2
References:
References:
Reference Title Rev No.
1.
- 1. EA-2-2 EA-2-2 Establishing Secondary Heat sink using Main 8 Feedwater or Condensate
========================================================================
READ TO OPERATOR Directions Directions to to Trainee:
Trainee:
II will will explain the initial conditions, and state the the task to be performed. All control room steps shall be performed performed for this JPM. JPM. II will provide initiating cues and reports on other actions when directed directed by by you.
you.
When When you you complete complete the the task task successfully, successfully, the the objective objective forfor this this job job performance performance measuremeasure will be satisfied.
will be satisfied.
Ensure Ensure youyou indicate indicate toto meme when you you understand understand your your assigned assigned task.
task. To To indicate indicate that that you you have have completed completed your your assigned assigned task task return return the the handout handout sheet sheet II provided provided you.you.
INITIAL INITIAL CONDITION CONDITIONS: S:
1.
- 1. Unit Unit 11 has has experienced experienced aa Reactor Reactor Trip Trip duedue multiple multiple dropped dropped rods.
rods.
2.
- 2. MDAFW MDAFW pump pump A-A A-A isis tagged tagged out for maintenance out for maintenance,,
MDAFW MDAFW pump pump B-B 8-8 tripped tripped on on electrical fault and electrical fault and the the TDAFW pump TDAFW pump tripped on tripped on mechanical mechanical overspeed overspeed just just after after RXRX trip.
trip.
3.3. Unit has transitioned Unit has transitioned to to ES-0.1 ES-0.1 and and isis ready ready toto perform perform the RNO for the RNO for STEP STEP 5. 5.
4.4. All All four S/G levels four SIG levels have have been been decreasing.
decreasing.
5.
- 5. AFW AFW Flow Flow to to the S/Gs can the S/Gs can NOT NOT be be established.
established.
INITIATING INITIATING CUES:
CUES:
1.1. You You areare the the CRC CRO and and the the US US directed directed you to establish you to establish Main Main Feedwater Feedwaterflow flow USING EA-2-2, USING EA-2-2, Establishing Establishing Secondary Secondary Heat HeatSink Sink Using Using Main Main Feedwater Feedwateror or Condensate Condensate System.
System.
2.2. Inform Inform thethe USUS when when Main Main Feedwater Feedwateror orCondensate Condensateflow flow has has been been established established to to one one S/G.
S/G.
JPM34-1 JPM34-1 Page Page 55 ofof 12 12 Rev Rev&0-STEP 1.:
STEP 1.: Obtain copy Obtain copy of the appropriate of the appropriate procedure.
procedure. - SAT SAT
- UNSAT UNSAT STANDARDOperator STANDARD: :Operator maymay obtain obtain aa copy copy ofof ES-0.1 ES-0.1 and and review review step step 55 RNO, RNO, for for transition step transition step toto EA-2-2.
EA-2-2. Start Start Time Time_ _
EA-2-2 Establishing EA-2-2 Establishing Secondary Secondary Heat Heat Sink Sink Using Using MFW MFW or or Condensate Condensate System System Section 4.1 Section 4.1 STEP 2.:
STEP 2.: [1] IF
[1] IF directed directed by ES-0.1, Reactor by ES-0.1, Reactor TripTrip Response, Response, to to establish establish Main Main SAT SAT Feedwater Feedwater flow,flow, THEN THEN PERFORM PERFORM Section Section 4.2.
4.2.
- UNSAT UNSAT STANDARD: Operator STANDARD: Operator recognizes recognizes Section Section 4.2 4.2 isis the the correct correct section section forfor performance performance and transitions to and transitions to section section 4.2.
4.2.
Critical Critical Step Step EA-2-2 Establishing EA-2-2 Establishing Secondary Secondary Heat Heat Sink Sink Using Using MFW MEW or or Condensate Condensate SystemSystem Section 4.2 Section 4.2 STEP 3.
STEP 3. REFER TO the following EAPs to attempt to restore AFW flow in
[1] REFER parallel with this procedure:
. EA-3-1O
- . EA-3-9, establishing TDAFW flow
- UNSAT CUE:
CUE: Maintenance and Ops personnel have been dispatched to restore MDAFW pumps A and B and the TDAFWP, MDAFW TDAFWP EA-3-10 EA-3-1O and EA-3-9 are in progress.
STANDARD: Operator contacts the US and or the MSS to have personnel dispatched STANDARD:
to establish AFW flow.
STEP STEP 4.:
4.: [2] CLOSE MEW MFW Regulating valves. SAT
- UNSAT UNSAT STANDARD STANDARD:: Operator Operator ensuresensures the MEW MFW Reg valves output output signal is is zero, on on 1-FIC 1-FIC 3-35, 3-35, 48, 48, 90 90 and and 103 103 and and check check lights lights for for MEW MFW Reg Reg valves valves on on 11-XX-3-35.
-XX-3-35.
STEP STEP 5.:
5.: [3] ENSURE
[31 ENSURE MEW MFW Regulating Regulating Bypass Bypass valvesvalves CLOSED.
CLOSED. SAT SAT STANDARD STANDARD:: Operator Operator ensures ensures MEWMFW Bypass Bypass valvesvalves CLOSED CLOSED using using UNSAT UNSAT 1-LIC-3-35, 1-LlC-3-35, 48, 48, 90, 90,103103 STEP STEP 6.:
6.: [4] CYCLE
[4] CYCLE Reactor Trip breakers.
Reactor Trip breakers. - SAT SAT STANDARD STANDARD: : Operator Operator places places 1-HS-99-7 1-HS-99-7 inin the the CLOSE CLOSE position, and places position, and places 1-RT-1 1-RT-1 - UNSAT UNSAT inin the trip position.
the trip position. Rx Rx trip trip breaker breaker lights lights turn red and turn red then green.
and then green.
Critical Step Critical Step
JPM34-1 JPM34-1 Page Page 66 of of 12 12 Rev RevO0 STEP 7.:
STEP 7.: [5] RESET FW
[5] RESET FW Isolation Isolation signal.
signal. [M-3]
[M-3j SAT SAT
- UNSAT UNSAT STANDARD: Operator STANDARD: Operator depresses depresses push pushbuttons 1-HS-3-99A and buttons 1-HS-3-99A and 99B, 99B, and Annunciator Window and Annunciator Window 1-XA-55-6B, 1 -XA-55-6B, LOW LOW TavgTavg Reactor Reactor Trip Trip MFW MEW Critical Critical Step Step Valves Actuated Valves Actuated alarm alarm clears.
clears.
STEP 8.:
STEP 8.: [6] OPEN FW
[6] OPEN EW isolation isolation valves valves for for S/G's S/Gs to to be fed.
be fed. SAT SAT
- UNSAT UNSAT STANDARD: Operator STANDARD: Operator opens opens at at least least one one FWIFWI valve(s) valve(s) for for S/G SIG to to be be fed, fed, using 1-HS-3-33A, 47A, using 1-HS-3-33A, 47A, 87A 87A or or 100A, bOA, red red light light on on green green light light off.
off. Critical Critical Step Step STEP 9.:
STEP 9.: [7] PERFORM
[7] PERFORM SectionSection 4.44.4 toto establish establish Main Main Feedwater Feedwater flow flow to to S/G's.
S/Gs. SAT SAT
- UNSAT STANDARD: Operator transitions to Section 4.4.
STANDARD:
Section 4.4 STEP 10.: [1] DISPATCH operator to PERFROM Appendix A, Part II to remove SAT fuses to disable intermediate heater string Isolation.
- UNSAT Cue Cue Respond as an AUO and tell operator you will perform Appendix A to remove fuses to disable intermediate heater string isolation.
STANDARD:
STANDARD:
STEP 11.: [2] ENSURE Condensate Inlet and Outlet valves for at least SAT one LP Heater String OPEN.
- UNSAT STANDARD STANDARD:: Operator verifies LP Heater InleUOutletInlet/Outlet valves OPEN for at least one LP heater string, red light illuminated illuminated and greengreen lights dark dark for (A) 1-HS 1-HS 2-45A 2-45A and 55A, OR (B) 1-HS-2-56A 1-HS-2-56A and 65A, OR OR (C) 1-HS-2-66A 1-HS-2-66A and 75A.
STEP STEP 12.:
12.: [3] ENSURE the the following condensate pumps pumps RUNNING:
RUNNING: - SAT SAT
.* 2Hotwellpum 2 Hotwell pumps ps CBP (with a* I1 CBP (with suction suction valve valve open) open) - UNSAT UNSAT
.* 11 Injection Injection water water pump pump STANDARD STANDARD:: Operator Operator ensures ensures 22 HW HW pumps, pumps, 11 CBP with suction CBP with suction valve valve open open andand 11 injection injection water pump running.
water pump running.
JPM34-1 JPM34-1 Page Page 77 of of12 12 Rev~Q Rev, (1 STEP 13.:
STEP 13.: [4] ENSURE
[4] ENSURE MFPT MFPT Recirc Recirc Valves Valves inin MANUAL MANUAL and and CLOSED:
CLOSED: SAT SAT
- . MFPTA MFPT 1-FIC-3-70 A 1-FIC-3-70 UNSAT UNSAT
- . MFPT BB 1-FIC-3-84 MFPT 1-FIC-3-84 STANDARD: Operator STANDARD: Operator ensures ensures recirc recirc valves valves for for the the MFP's, MFPs, 1-FIC-3-70 1 -FIC-3-70 and and 3-84, 3-84, are are in manual (amber light in manual (amber light illuminated) illuminated) and and closed closed (indicator (indicator to to the the right).
right).
STEP 14.:
STEP 14.: [5] ENSURE MFW
[5] ENSURE MEW Reg Reg controllers controllers in in MANUAL MANUAL and and Output Output Zero.
Zero. SAT SAT STANDARD: Operator STANDARD: Operator ensures ensures Main Main FRVFRV areare in in manual manual (toggle (toggle switch switch to to manual) manual) UNSAT UNSAT and closed (output and closed (output demand demand 0) 0) using using 1-FIC-3-35, 1-FIC-3-35, 48, 48, 90,103, 90, 103, and and checks green status lights lights illuminated illuminated on on 1-XX-3-35 1-XX-3-35 (red(red dark).
STEP 15.:
STEP [6] ENSURE MFW MEW Bypass Reg valves controllers in in MANUAL SAT and output ZERO.
- UNSAT STANDARD: Operator ensures all MFW STANDARD: MEW Reg Bypass valves are in Manual (amber light illuminated) and output ZERO using 1-LlC-3-35, 1-LIC-3-35, 48, 90, and 103.
STEP 16.:
STEP [7j IF a flowpath is not available through at least one
[7] SAT Intermediate Heater string ......
- UNSAT STANDARD STANDARD:: Operator N/AsN/A's this step, flow path is available.
STEP STEP 17.:
17.: [8] ENSURE Inlet
[81 Inlet and Outlet valves for at least one at least one string string of of SAT SAT Intermediate Intermediate and and High High Pressure Pressure Heaters Heaters OPEN:
OPEN:
- UNSAT UNSAT
. High High Pressure Pressure FW FW Heaters Heaters (panel (panel M-3)
M-3)
(A)
(A) 1-HS-3-3A 1-HS-3-3A and and 1OA10A OROR (B)
(B) 1-HS-3-13A 1-HS-3-13A and and 20A20A OROR (C) -HS-3-23A and (C) 11-HS-3-23A and 30A30A
. Intermediate Intermediate Pressure Pressure FW FW Heaters Heaters (Panel (Panel M-2)
M-2)
(A)
(A) 11-HS-2-11
-HS-2-1 I OA OA and and 1128A 28A OR OR (B) -HS 1 30A and (B) 11-HS-2-130A and 1147A 47A OR OR (C) 1-HS (C) 1-HS 149A 149A andand 167A 167A STANDARD STANDARD:: Operator Operator verifies at least verifies at least one one string string ofof IP IP (M-2)
(M-2) and and HP (M-3) heater HP (M-3) heater string isolation valves string isolation valves areare OPEN.
OPEN.
JPM34-1 JPM34-1 Page Page 88 of of 12 12 RevO RevO -
STEP 18.:
STEP 18.: [9] IF starting
[9] IF starting MFW MEW pump pump A, A, THEN THEN PERFORM PERFORM the following:
the following: SAT SAT
[9.a] ENSURE MFP
[9.a] ENSURE MFP aa drain drain hand-switch hand-switch rHS-46-141
[HS-46-14] inin UNSAT UNSAT OPEN position OPEN position STANDARD: OPERATOR STANDARD: OPERATOR ensures ensures the the MFPT MFPT drain drain hand-switch hand-switch
[HS-46-14] is
[HS-46-14] is inin OPEN OPEN position position (HS (HS to to the the right right on on M-3)
M-3)
STEP 19.:
STEP 19.: [9.b] ENSURE the
[9.b] ENSURE the following following valves valves are OPEN:
are OPEN:
VALVE VALVE DESCRIPTION DESCRIPTION OPEN OPEN ,/ /
FCV-2-205 MFPT Condenser SAT SAT FCV-2-205 MFPT Condenser A Inlet Isol A Inlet Isol [M2]
[M2] 0 -
FCV-2-21 0 FCV-2-210 MFPT Condenser MFPT Condenser A A Outlet Outlet Isol [M2)
Isol [M2] 0
- UNSAT UNSAT FCV-2-221 FCV-2-221 MFWP A Inlet MFWP Inlet Valve [M2] [M2] 01J FCV-3-67 FCV-3-67 MEWP A Outlet Valve [M3]
MFWP [M3] 0 STANDARD: OPERATOR STANDARD: OPERATOR ensures the MFPT condenser Inlet and Outlet Isolation valves are OPEN, FCV-2-205ECV-2-205 and 210, and the MFP Inlet and Outlet isol Valves are open, FCV-2-221 and 3-67.
CUE:
CUE: IF asked, state O-GO-12, Appendix A was not performed performed. SAT STEP STEP 20.:
20.: [9.cJ
[9.c] IF [VLV-1-611 rVLV-1-611] 1 MFP pump A HP steam Isolation ......... UNSAT CUE:
CUE: IF operator operator dispatches personnel personnel to open valve Inform them that VLV-1-611 is already already open.
STANDARD STANDARD:: Operator Operator dispatches dispatches an an operator operator to to check check valve valve open open locally, locally, or or acknowledge acknowledges s that that 0-GO-12, 0-GO-12, Appendix Appendix A was not performed.
was not performed.
STEP STEP 21.:
21.: [9.d] RESET
[9.d] RESET MFPTMFPT AA USING USING FHS-46-9A1
[HS-46-9Al.. SAT SAT
- UNSAT UNSAT STANDARD STANDARD: : Operator Operator places places HSHS inin the the reset reset position position andand verifies the red verifies the red light light illuminates illuminates green green light light isis dark, dark, alarm alarm clears clears forfor MFP MFP trip.
trip. Critical Step Critical Step
JPM34-1 JPM341 Page 99 of Page of 12 12 RevO Rev 0 STEP 22.:
STEP 22.: [9.e] PLACE
[9.e] PLACE MFPT MFPT AA [SIC-46-20Al
[SIC-46-20A] inin MANUAL MANUAL and and with with ZERO ZERO output.
output. SAT SAT
- UNSAT UNSAT STANDARD: Operator STANDARD: Operator places places MFPT MFPT AA SIC-46-20 SIC-46-20 to to manual manual and and sets sets output output signal to o.0.
signal to Critical Critical Step Step STEP 23.:
STEP 23.: [9.f] ENSURE
[9.t] ENSURE MFPT MFPT AA and and 8B master master speed speed controller controller [PC-46-20]
FPC-46-201 inin SAT SAT MANUAL and MANUAL and with with output output atat O.
0.
- UNSAT UNSAT STANDARD:
STANDARD: Operator places Operator places MFPT MFPT AA and and 8B master master speed speed controller controller [PC-46-20]
[PC-46-20] in in Critical Critical Step Step MANUAL and MANUAL and sets sets output at o.
output at 0.
STEP 24.:
STEP 24.: [9.g] DO NOT CONTINUE until suction flow path established to MFP. SAT
- UNSAT STANDARD: Operator has previously verified suction flow path is available to MFP.
STANDARD: MFP, and continues with procedure.
STEP STEP 25.:
25.: [FIC-3-701 MFPTA recirc valve in MANUAL and OPEN.
[9.h] ENSURE [FIC-3-70] SAT
- UNSAT STANDARD:
STANDARD: Operator verifies the MFP A recirc valve is in manual, manual. amber light illuminated and opens valve (toggle switch to the left). left). Critical Step STEP STEP 26.:
26.: [9.i]
[9.i] PLACE PLACE MFPT MFPT A A speed speed controller [SIC-46-20AJ in controller [SIC-46-20A1 in AUTO.
AUTO. SAT SAT
- UNSAT UNSAT STANDARD:
STANDARD: Operator Operator places places MFPT MFPT A A speed speed controller controller inin AUTO.
AUTO.
Critical Step Critical Step STEP STEP 27.:
27.: [9.k]
[9.k] VERIFY VERIFY the the governor governor valve valve positioner positioner isis indicating indicating CLOSED.
CLOSED. - SAT SAT
- UNSAT UNSAT STANDARD:
STANDARD: Operator Operator verifies verifies 1-HS-46-13A 1-HS-46-13A green light illuminated green light illuminated and/or and/or checks checks 1-Zl-46-13B 1-ZI-46-138 (M-3)(M-3) indicating indicating 0.
O.
JPM34-1 JPM34-1 Page Page 10 10 of of 12 12 Rev 0 RevQ STEP 28.:
STEP 28.: [9.k] IF
[9.k] IF MFPT MFPT governor governor valvevalve NOT NOT indicating indicating CLOSED, CLOSED, THEN THEN .... SAT SAT
- UNSAT UNSAT STANDARD: Operator STANDARD: Operator N/A's N/As this this step, step, valve valve isis closed.
closed.
STEP 29.:
STEP 29.: [9.1] OPEN
[9.1] OPEN MFPT MFPT AA stop valves by stop valves placing HP by placing HP stop stop valve valve switch switch SAT SAT FHS-46-15A1 to
[HS-46-15Al raise.
to raise.
- UNSAT UNSAT NOTE:
NOTE: HP and HP and LP LP stop stop valve valve will will open open when when thethe HS HS isis placed placed in in raise.
raise.
Either HS Either HS placed placed in in raise raise will will open open thethe valves.
valves. IfIf HS-46-16A HS-46-16A is is used used toto Critical Critical Step Step open stop open valves then stop valves then make make aa comment.
comment. Critical Critical task task is SAT ifif is SAT HS-46-16A is HS-46-16A is used.
used.
STANDARD: OPERATOR holds the HS-46-15A HS-46-15A in raise position until the red light is illuminated and green light is dark.
STEP 30.: [9.m] RAISE MFPT A speed by PERFORMING one of the following: SAT
- 1) IF MeR MCR operation of governor valve positioner is available, UNSAT FHS-47-13A1 to RAISE to open the steam chest valves.
PLACE [HS-47-13Al Critical Step STANDARD: OPERATOR places HS-47-13A HS-47-1 3A in RAISE to open GV while monitoring MFP loading. MFP speed should stabilize at -3300 3300 rpm as seen on 1 -SI-46-20A.
1-SI-46-20A.
STEP 31.: [9.m] (continued) SAT SAT
- 2) IF MCR MCR operation of governor governor valve positioner positioner unavailable, THEN...
THEN ... - UNSAT UNSAT STANDARD:
STANDARD: Operator Operator N/As N/A's this step since this step since governor valve positioner governor valve positioner was was available.
STEP 32.:
STEP 32.: [9.n] WHEN MFPT
[9.n] WHEN MFPT speedspeed controller controller controlling MFPT speed, controlling MFPT speed, THEN THEN - SAT SAT ENSURE ENSURE governor governor valve valve positioner positioner isis fully fully raised.
raised.
- UNSAT UNSAT NOTE:
NOTE: MFPT speed controller MFPT speed controller takes speed control over speed takes over when MFPT control when MFPT accelerates accelerates to 3300 rpm to - 3300 rpm onon 1-Sl-46-20A.
1-SI-46-20A.
STANDARD:
STANDARD: Operator ensures Governor Operator ensures Valves Positioner Governor Valves Positioner isis fully fully raised, raised, red red light light illuminated illuminated and green light and green light dark.
dark.
JPM34-1 JPM34-1 Page 11 Page 11 of 12 ofl2 Re\fO RevO STEP 33.:
STEP 33.: [9.o] ADJUST
[9.0] ADJUST MFPT MFPT speed speed USING USING Master Master Controller Controller [PC-46-20J FPC-46-20] SAT SAT UNTIL feedwater UNTIL feedwater header header pressure pressure isis - 80 80 psid psid greater greater than than steam header steam header pressure.
pressure. UNSAT UNSAT Critical Critical Step Step STANDARD:
STANDARD: Operator adjusts Operator adjusts [PC-46-20]
[PC-46-20] inin manual manual to increase FW to increase FW header header pressure pressure to 80 to 80 psid psid greater greater than than steam steam header header pressure pressure whilewhile monitoring monitoring PI-3-1, P1-3-i,
- 11 HTR HTR Inlet Inlet Pressure Pressure (on(on M-3 M-3 panel),
panel), and and PI-1-33, P1-1-33, Main Main Steam Steam Header Pressure Header Pressure (on(on M-4 M-4 panel).
panel).
Operator may Operator may also also monitor monitor FW/SG FW/SG deltadelta PP on:
on:
I CS/Secondary Mimics/Feedwater ICS/Secondary M im ics/Feedwater screen.
screen.
STEP 34.:
STEP 34.: [10] IF
[10] IF starting starting MFP MFP pump pump B B ...... SAT SAT
- UNSAT STANDARD: OPERATOR N/A's STANDARD: N/As this step.
step.
STEP 35.:
STEP [ii] IF RCS temperature is less than 550°F,
[11] SAT THEN GO TO Step 13.
- UNSAT STANDARD: OPERATOR verifies temperature is <550°F and continues STANDARD:
with step 13.
JPM34-1 JPM34-1 Page Page 12 12 of of 12 12 Rev Rev 00 STEP 36.:
STEP 36.: [13] ADJUST
[13] ADJUST MFW MEW regulating regulating Bypass Bypass valve valve controller controller toto establish establish required feed required feed flow.
flow. SAT SAT CAUTION CAUTION IF automatic IF automatic SI SI signals signals areare NOT NOT blocked, blocked, feedfeed flow flow should should be be UNSAT UNSAT carefully controlled carefully controlled to to prevent prevent rapid rapid cooldown cooldown which which could could result result in low in low steam flow line steam flow line pressure pressure SI SI actuation actuation (and (and subsequent subsequent Critical Critical Step Step feedwater isolation).
feedwater isolation).
NOTE NOTE 0.2 X10 0.2 66 1bm/hr X10 Ibm/hr feed feed isis equivalent equivalent to to -440 440 gpm.
gpm. DueDue toto inaccuracy inaccuracy of of flow indication at flow indication at low low end end of of scale, scale, feed feed flow flow should should bebe determined determined based on based rise inin indicated on aa rise indicated flow.
flow.
NOTE NOTE TO TO EVALUATOR: IfIf operator EVALUATOR: operator notifies notifies the the US US that that FWFW flow flow isis established established to to one one SG SG in in this step, this step, then then N/ANIA step step 3737 and and record record stop time in stop time in step step 38.
38.
STANDARD: Operator STANDARD: Operator adjusts adjusts MFW MEW Reg Reg Bypass Bypass valvevalve inin manual manual by by adjusting adjusting the the lever to the right lever right toto establish feed water flow to to at at least least one one steam steam generator. Monitors Monitors for an indication of flow on FW Flow Elow Indicators or level increase in the selected steam generator(s).
Operator may notify the US that FW flow has been established to at SIG, this ends the JPM as FW least one S/G, EW flow is established to one SG.
STEP STEP 37.: [14] MONITOR Hotweillevel Hotwell level and CONTROL as necessary. SAT NOTE:
NOTE: If operator notified US that FW was established in previous step UNSAT then this step is not required.
STANDARD:
STANDARD: Operator may state that they are monitoring HW level on 1-LR-2-12 1-LR-2-12 (M-3), and and using using 1-LIC-2-3 1-L1C-2-3 and and 1-LlC-29 1-UC-2-9 for autoauto makeup makeup and and dumpback.
dumpback.
STEP STEP 38.:
38.: Inform Inform the the US/SRO US/SRO when when feedwater feedwater flow flow has has been been established.
established. - SAT SAT
- UNSAT UNSAT STANDARD:
STANDARD: Operator informs the Operator informs the US/SRO US/SRO FW FW flow flow has been established.
has been established.
Stop Time Stop Time End End of ofJPMJPM
READ TO READ TO OPERATOR OPERATOR Directions to Trainee:
wiH explain the initial conditions, and state the task to be performed. All control room I will steps shall be performed for this JPM. I will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet II provided you.
INITIAL CONDITIONS:
- 1. Unit 11 has experienced a Reactor Trip due multiple dropped rods.
- 2. MDAFW pump A-A is tagged out for maintenance, maintenance, MDAFW pump 8-8 B-B tripped on electrical fault and the TDAFW pump tripped on mechanical overspeed just after RX trip.
- 3. Unit has transitioned to ES-O.1 and is ready to perform the RNO for STEP 5.
- 4. All four SIG S/G levels have been decreasing.
- 5. AFW Flow to the S/Gs can NOT be established.
INITIATING CUES:
1.
- 1. You are the CR0 CRO and the US directed you to establish main feedwater flow USING EA-2-2, Establishing Secondary Heat sink Using Main Feedwater or Condensate System.
- 2. Inform the US when Main Feedwater or Condensate flow has been established to one S/G.
JPM77-1 AP JPM77-1AP Page of 11 Page 11 of 11
- - Rev.12 Revi2 SEQUOYAH NUCLEAR NUCLEAR PLANT PERFORMANCE MEASURE JOB PERFORMANCE MEASURE JPM # 77-1AP 77-lAP Perform DIG Load Test on 1I 8-8 B-B DIG (with high crankcase press)
PREPAR ED!
PREPARED/
REVISED BY: Date!
Date/
VALIDATE VALIDATEDD BY: *
- Date/
Date!
APPROVED BY: Date!
Date/
(Operations Training Manager)
CONCURRE CONCURRED:D: **
- Date!
Date/
(Operations Representativ Representative)e)
- Validation notnot required for minor enhancement s, procedure Rev changes that enhancements, do do not affect affect the JPM, JPM, or or individual step changes that do do not affect the flow of of the JPM.
JPM.
driven by
JPM77-1AP JPM771 AP Page of 11 Page 22 of 11 Rev.12 Rev.12 NUCLEAR TRAINING NUCLEAR TRAINING REVISIONIUSAGE LOG REVISION/USAGE LOG REVISION REVISION DESCRIPTION OF DESCRIPTION OF V DATE DATE PAGES PAGES PREPARED/
PREPARED!
NUMBER NUMBER REVISION REVISION AFFECTED AFFECTED REVISED REVISED BY: BY:
88 Revised to Revised reflect revision to reflect revision changes changes inin SI-SI-. N N 10/13/99 10/13/99 All All SR SR Taylor Taylor 7B, changed 7B, changed critical critical steps steps for for consistency consistency with JPM with JPM 77-5AP 77-5AP reviewed/approved reviewed/approved 4/20/99, corrected 4/20/99, corrected typos typos and incorporated and incorporated comments from 1999 1999 cycle 5 requal performances of performances of JPM JPM 77-2AP. Flow Flow of of the the JPM is is not not affected.
pen/ink 0-AR-M26-B Rev chg only N 8/9/00 44 SR Taylor pen/ink pen/ink Minor change Minor change to step step 6, SO-83 SO-83 RevRev N N 8/17/00 8/17/00 4 SR SR Taylor update.
pen/ink 0-AR-M26-B Rev chg only N 8/28/00 4 SR Taylor pen/ink 1-SI-OPS-082-007.B Rev chg only 1-SI-OPS-082-007.B N 6/21/01 4 WRRamsey WR Ramsey pen/ink 1-SI-OPS-082-007.B rev 25 Update minor 1-SI-OPS-082-007.B N 09/07/01 ALL WR Ramsey changes related to stopwatch usage pen/ink minor enhancement changes and N 03/21/02 ALL WRRamsey WR Ramsey 1 -SI-OPS-082-007.B Revision update 1-SI-OPS-082-007.B 9 Incorporated pen/ink changes; updated to N 8/20/02 All J P Kearney latest revisions of referenced documents; no impact on JPM flow 10 Updated references N N 12/10/03 4 JJ Tricoglou functions/annunciator Revised remote functions/annunciator N 8, 9 overrides to conform to new simulator configurations.
configurations.
11 Updated to current revisions and IC. N N 8/11/04 All MG Croteau 12 Updated to current revision of procedure Y Y 12/03/09 ALL M M Hankins v - Specify ifif the JPM V -
JPM change will require anotheranother validation (Y oror N).
N).
See See cover cover sheet sheet for criteria.
JPM77-1AP JPM77-l AP Page of 11 Page 33of 11 Rev.12 Rev.l2 SEQUOYAH NUCLEAR PLANT SEQUOYAHNUCLEARPLANT ROISRO RO/SRO JOB JOB PERFORMANCE PERFORMANCE MEASURE MEASURE Task:
Task:
Perform DIG Perform DIG Load Load Test Test on on 11 8-8 DIG B-B DIG JAITAtask#:
JAITA task # :
0640020101 0640020101 0640040101 0640040101 0640060101 0640060101 (RO)
(RO)
K/A Ratings:
KIA Ratings:
064A4.01 (4.0/4.3) 064A4.01 (4.0/4.3) 064A11.04 064A (2.8/2.9)
.04 (2.8/2.9) 064A4.02 064A4.02 (3.3/3.4) 064A4.03 (3.2/3.3)
(3.2/3.3) 064A2.09 (3.1/3.3) 064A2.09 (3.1/3.3) 064A3.06 (3.9/3.9) 064A3.06 (3.9/3.9)
Task Standard:
DIG Operability Test per 1-SI-OPS-082-007.8, Perform DIG 1-Sl-OPS-082-007.B, specifically manually start the DIG. Emergency DIG on high stop DIG high crankcase pressure annunciation.
Evaluation Method: Simulator -~-- X In-Plant _ __
=======================================================================
Performer:
NAME Start Time _ __
Performance Rating: SAT UNSAT Performance Time Finish Time _ __
Evaluator: /
SIGNATURE DATE
========================================================================
COMMENTS
JPM77-1AP JPM77-1 AP Page Page 44 of of 11 11 Rev.12 Rev. 12 SPECIAL INSTRUCTIONS SPECIAL INSTRUCTIONS TO TO EVALUATOR:
EVALUATOR:
1.
- 1. Any UNSAT Any UNSAT requires requires comments comments 2.
- 2. Acknowledg e any associated Acknowledge any associated alarms. alarms.
3.
- 3. Initialize Simulator Initialize Simulator inin IC:IC: #16.
- 16.
4.
- 4. AA console console operator operator will will be be needed needed to insert override to insert override andand play play role role of AUO on of AUO on Radio.
Radio.
5.
- 5. Operator will Operator will need need assistance assistance during during DIGDIG start (at step start (at step 5).
5). An An extra extra simulator simulator operator operator or or the the console console operator needs operator needs to to be present to be present perform this to perform this timing.
timing.
6.
DG.
7.
- 7. AT JPM AT JPM step step 13,13, Console Console operator operator should should insert IRF EGR08 insert IRF EGRO8 f:1 f:1 to to reset reset 86LOR 86LOR and and then then notify notify operator - 86 operator - LOR is 86 LOR is reset.
reset.
7.
- 7. When operator When operator starts starts JPMJPM stepstep #25,
- 25, prior prior to DIG breaker to D/G breaker closure, closure, insert insert IMF IMF AN_ OV_958 f:2.
AN_OV_958 f:2.
8.
- 8. Ensure operator Ensure operator performs performs the the following following required required actions actions for for SELF-CHECKING; SELF-CHECKING;
- a. Identifies the
- a. Identifies the correct correct unit, unit, train, train, component, component, etc. etc.
- b. Reviews the
- b. Reviews the intended intended action action and and expected expected response.
response.
- c. Compares
- c. Compares the the actual actual response response to the expected to the expected response.
response.
Validation Time:
Validation Time: CRCR 30 minutes 30 minutes Local _ _ _ __
Local ToolslEquipmentlProcedures Needed:
Tools/Equipment/Procedures
- 1. 1-Sl-OPS-082-007.B, 1-SI-OPS-082-007. B, Through Section 6.1 and Appendix "C". C.
- 2. Signed off" "Signed off copy of entire section 4.
- 3. 0-AR-M26-B window D-2.
References:
References:
Reference Title Rev No.
- 1. 1-Sl-OPS-08 2-007.B 1-SI-OPS-082-007. B Electrical Power System Diesel Generator 1lB-B B-B 50 50 2.
- 2. 0-AR-M26-B Annunciator 0-XA-55-26B 27
JPM77-1AP JPM77-1 AP Page Page 55 ofof 11 11 Rw.-12 Rev.12 READ TO READ TO OPERATOR OPERATOR Directions to Directions to Trainee:
Trainee:
II will will explain explain thethe initial initial conditions, conditions, andand state the task state the task to to be be performed.
performed. All All control control room room steps steps shall shall be be performed for performed for this JPM. II will this JPM. will provide provide initiating initiating cues cues and reports on and reports on other other actions actions when directed by when directed by you. When you you. When complete the you complete the task task successfully, successfully, the the objective objective for for this this job job performance performance measure measure will will be be satisfied. Ensure satisfied. Ensure you you indicate indicate toto me me when when youyou understand understand your your assigned assigned task. To indicate task. To indicate that that you you have completed have completed your your aSSigned assigned tasktask return return the the handout handout sheet sheet II provided provided you.you.
INITIAL CONDITIONS:
INITIAL CONDITIONS:
- 1. Both
- 1. Both units units are are at at 100%
100% RTP.RTP.
- 2. All
DIG.
0-GO-16 has been completed on all the A train equipment.
- 3. 0-GO-16 Maintenance has been completed on the 1lB-B
- 4. Maintenance B-B DIG and and the clearance has been been removed.
- 5. The DIG has
- 5. has been been rolled rolled and is is in standby alignment using 0-SO-82-2.
- 6. The AUO at the DIG building has completed Appendix A of 1-SI-OPS-082-007.B 1-Sl-OPS-082-007.B and all parameters are within limits. Two AUO's AUOs are standing by for DG start.
- 7. The U1 UI Control Room AUO has verified breaker 1934 is in the Disconnect position.
- 8. D/G-DAQ DIG-DAQ has been installed.
- 9. Room fire protection is in service.
- 10. The U1
- 10. Ul US/SRO has reviewed the completed work package for the 11 B-B DIG, 1-Sl-OPS-082-007.B for the PMT.
all that remains is to perform 1-SI-OPS-082-007.B
- 11. Section 4.0 and Appendix A of 1-SI-OPS-082-007.B
- 11. 1-Sl-OPS-082-007.B are complete.
- 12. Section 6.1 is complete thru step 6.
INITIATING INITIATING CUES:
1.
- 1. Perform 11-SI-OPS-082-007.B,
-Sl-OPS-082-007.B, beginning with Section 6.1, step 7.c.
JPM77-1AP JPM77-1 AP Page Page 66 of of 11 11
- Rev.12 Rev.12 Job Performance Job Performance Checklist:
Checklist:
STEP/STAN STEP/ST DARD ANDARD SAT/U NSAT SAT/UNSAT STEP 1.:
STEP 1.: Operator obtains Operator obtains aa copy copy of of the the appropriate appropriate procedure.
procedure. _SAT SAT NOTE:
NOTE: Initial conditions Initial conditions covercover steps steps inin procedure procedure up up to to the the transition transition UNSAT UNSAT to Appendix to Appendix "C". C.
Start Start STANDARD: Operator STANDARD: Operator obtains obtains aa copy copy of of 1-SI-OPS-082-007.B.
1-Sl-OPS-082-007.B. BeginsBegins in in section section 6.1, 6.1, Time__
Time Step 7.c, and Step 7.c, and transitions transitions to to Appendix Appendix C.C.
Appendix C AppendixC STEP 2.:
STEP 2.: [1] ENSURE O-HS-82-48
[1] ENSURE O-HS-82-48 1lB-B DIG mode B-B DIG selector switch mode selector switch in in the the _SAT SAT UNIT position.
UNIT position.
_UNSAT UNSAT STANDARD: O-HS-82-48 in UNIT STANDARD: UNIT position position onon O-M-26.
O-M-26. Green Green light ON.
ON.
STEP 3.: I -HS-57-74
[2] PLACE 1-HS-57 D/G 11 B-B Synchronize Switch in the SYN position.
-7 4 DIG _SAT SAT NOTE: O-El-82-35 and O-XI-82-33 O-EI-82-35 O-Xl-82-33 will indicate running voltage & frequency. _UNSAT UNSAT STANDARD: 1-HS-57-74 in "SYN" STANDARD: SYN position on O-M-26 Critical Step NOTE NOTE Operator may discuss notes preceding step 3 with the DAQ operator and SAT the stopwatch operator to ensure expectations for starting and stopping the DAQ and Stopwatches are clear. _UNSAT UNSAT STEP 4. [3] PERFORM the following to initiate DIG start signal:
[3.1]IF the DIG DAQ is to be used, THEN NOTIFY D/G-DAQ Operator to START the D/G-DAQ.
NOTE: Operator must coordinate the start of the DIG-DAQ D/G-DAQ just prior to DIG start start actuation.
CUE: Tell DIG operator there is extra operator that will time the DG start with aa stopwatch.
stopwatch.
STANDARD STANDARD:: Operator notifies notifies the D/G-DAQ operator operator to start start the the D/G-DAQ.
JPM77-1AP JPM77-1 AP Page 77 of Page of 11 11 Rev.12 Rev.12 Job Performance Job Performance Checklist:
Checklist:
STEPISTANDARD STEP/STANDARD SAT/UNSAT SAT/UNSAT NOTE:
NOTE: The DG The DG operator operator will will NOT NOT be able to be able operate the to operate the stop stop watch watch alone.
alone. SAT SAT Another operator Another operator simulates simulates the the DG start timing.
DG start timing.
Only one Only one stopwatch stopwatch is is required required since since the the DAC is used.
DAC is used. UNSAT UNSAT STEP 5.:
STEP 5.: [3.2] PROCEED with
[3.2] PROCEED the countdown:
with the countdown: 3,2,1, 3,2,1, START.
START.
STANDARD: Operator STANDARD: Operator ensures ensures operator operator isis ready ready with with stop stop watch watch and and announces announces the the countdown to countdown to start start the D/G.
the DIG.
Only one Only one stopwatch stopwatch isis required required since since the the DAQ DAQ isis being being used.
used.
STEP 6.:
STEP [3.3] DEPRESS O-HS-82-46A, 0-HS-82-46A, DG 1I B-B Emergency Start Switch Switch AND SAT START Stopwatch(es).
START Stopwatch(es).
- UNSAT UNSAT STANDARD: 0-HS-82-46A momentarily depressed. Green STANDARD: Green light will go "out" out and red on above DIG light will come "on" D/G mimic. Critical Step
[Not critical: Stop watch is started. DIG D/G running alarm will ANN to indicate D/G > 40 rpm. Incoming voltage and frequency are verified on 0-EI-82-34 DIG>
and 0-XI-82-32.]
0-Xl-82-32.]
STEP 7.: [3.4] When voltage >6800 volts and Frequency >58.8 HZ, THEN STOP - SAT stopwatch.
- UNSAT STANDARD: Stop stopwatch when voltage >6800 volts and Frequency >58.8 HZ.
STANDARD:
STEP 8.: [4] ENSURE 11-FCV-67-67,
-FCV-67-67, ERCW cooling water supply valve is OPEN. SAT STANDARD STANDARD:: ERCW valve 1-FCV-67-67 1-FCV-67-67 red light comes on "on" and green light goes out "out" UNSAT on 0-M-27A 0-M-27A panel.
STEP STEP 9.:
9.: [5] Record Record the the time time from thethe Stopwatches Stopwatches:: SAT SAT CUE: STOP STOP WATCH E123, E123, TIME 9.5 SECONDS TIME 9.5 UNSAT UNSAT STANDARD STANDARD:: Operator Operator records records the stop watch the stop watch IDID number number and and seconds seconds for for DG DG start start and and checks checks acceptance acceptance criteria met: met:
<10
<10 seconds seconds Generator Generator Voltage Voltage ~ 6800 6800 V V Frequency Frequency ~ 58.8 58.8 Hz Hz
JPM77-1AP JPM77-1 AP Page of 11 Page 88 of 11 Rev.12 Rev.12 Job Performance Job Performance Checklist:
Checklist:
STEP/STANDARD STEP/STANDARD SAT/UNSAT SAT/UNSAT STEP 10.:
STEP 10.: [6] RECORD the
[6] RECORD the steady steady state state values values for for the the following:
following: SAT SAT A.
A. 0-El-82-34, DG 0-EI-82-34, DG 1lB-B incoming Voltage.
B-B incoming Voltage.
B.B. 0-XI-82-32, DG 0-XI-82-32, DG 11 B-B B-B incoming incoming Frequency.
Frequency. UNSAT UNSAT STANDARD: Operator STANDARD: Operator records records D/G DIG voltage voltage (as indicated on (as indicated on INC INC Voltage Voltage Gen Gen 11 B-B B-B 0-EI-34) 0-EI-34) isis ?:> 6800 6800 butbut ~< 7260 7260 volts volts and frequency and frequency (as indicated (as indicated on on INC INC Freq Freq Gen Gen 11 B-B B-B 0-XI-82-32) 0-Xl-82-32) isis 59.9 Hz
?:> 59.9 Hz and and ~< 60.1 60.1 Hz Hz Checks acceptance Checks acceptance criteria criteria to verify readings to verify readings are are within within limits limits STEP 11.:
STEP 11.: [7] RECORD
[7] RECORD Voltage Voltage Regulator Regulator Control Control Current.
Current. SAT SAT
£ Cue: Voltage Regulator Control Voltage Control Current Current is 1.8 1.8 de dc amps. UNSAT UNSAT STANDARD: Operator records Voltage Regulator Control Current.
STANDARD:
STEP 12.:
STEP [81 ENSURE DIG 1lB-B
[8] B-B 86 lORLOR red light NOT ILLUMINATED, ILLUMINATED, SAT D/G local relay panel.
at DIG
- UNSAT Cue:
Cue: Role playas play as DIG operator - 86 LOR local red light is not illuminated.
STANDARD STANDARD Operator verifies red light on 86 LOR at D/G DIG is not illuminated.
STEP 13.:
STEP 13.: [9] RESET 86 LOR lOR lockout relay, on D/G DIG local relay panel. SAT Cue: When the DIG AUO is requested to reset 86LOR, 86l0R, UNSAT the Console Console operator should insert IRF EGR08 f:1 to reset 86L0R IRF EGRO8 86l0R and then and then notify notify operator operator - 86
- 86 LOR LOR is is reset.
reset.
STANDARD STANDARD:: 86 86 LOR is is reset locally, operator operator continues.
STEP STEP 14.:
14.: [10] VERIFY
[10] VERIFY [86LOR]
[86l0R] reset reset by by amber amber light light 0-Xl-82-49 0-XI-82-49
- SAT SAT illuminated illuminated on on 0-M-26.
0-M-26.
- UNSAT UNSAT STANDARD STANDARD:: Operator Operator verifiesverifies Amber Amber light light onon 0-M-26 0-M-26 isis lit.
lit.
JPM77-1AP JPM77-1 AP Page 9 of 11 Page9ofll
- Rev.12 Rev.12 Job Performance Job Performance Checklist:
Checklist:
STEP/STAN STEP/ST DARD ANDARD SAT/UNSAT SAT/UNSAT STEP 15.:
STEP 15.: [11] IF
[11] IF the the D/G-DAQ D/G-DAQ was was used, used ,THEN THEN SAT
-_SAT RECORD RECORD the time required the time required to achieve ~ 58.8 to achieve 58.8 HZ and ~ 6800 HZ and 6800 Volts Volts from the from the D/G-DAQ computer.
D/G-DAQ computer. - UNSAT UNSAT NOTE:
NOTE: Evaluator can Evaluator initial for can initial for DG-DAQ DG-DAQ Operator Operator ifif asked asked Cue:
Cue: Time was Time was 9.59.5 seconds seconds for for D/G-DAQ.
D/G-DAQ.
STANDARD: Operator STANDARD: Operator checks checks acceptance acceptance criteria criteria met, in met, in
<<10 seconds 10 seconds generator voltage generator voltage ~ 68006800 volts volts and and frequency frequency ~58.8 58.8 Hz. Hz.
STEP 16.:
STEP 16.: [121 IF
[12] IF step 1.0[6]
1 .0[6] is is <59.9
<59.9 or >60.1,
>60.1, THEN INITIATE a PER. SAT
- UNSAT STANDARD: Parameters in STANDARD: in Step 1.0 [6] were within limits, no PER required, operator N/As step.
N/A's STEP 17.: 0-Sl-OPS-082-007.M.
[13] RECORD start as ambient in 0-SI-OPS-082-007.M. -
SAT CUE:
CUE: Another operator will record DIG start in O-SI-OPS-082-007.M.O-SI-OPS-082-007.M. UNSAT STANDARD STANDARD:: Operator addresses logging the start in 0-Sl-OPS-08 0-SI-OPS-082-007.M.
2-007.M.
STEP 18.: [14] RETURN to Section 6.1, Step 10. SAT
- UNSAT STANDARD STANDARD:: Operator returns to the appropriate section and step of the procedure.
(Exits Appendix C)
Section Section 6.16.1 Step Step 1010 STEP STEP 19.:
19.: [10] PERFORM the following to wipe the
[10] the Automatic Voltage
- SAT SAT Control Control Rheostat:
Rheostat:
- UNSAT UNSAT
[10.1]
[10.1] RECORD RECORD voltage voltage from from 0-El-82-34.
O-EI-82-34.
STANDARD STANDARD:: OPERATOR OPERATOR records records voltage and continues voltage and continues withwith next next step.
step.
STEP STEP 20.:
20.: [10.2]
[10.2] ENSURE ENSURE 0-HS-82-42, 0-HS-82-42, DG DG I1B-B B-B Voltage Voltage Regulator Regulator Switch in Switch in
- SAT SAT the Pull-to the Pull-to P-AUTO P-AUTO position position
- UNSAT UNSAT STANDARD STANDARD:: Operator Operator verifies verifies 0-HS-82-42 0-HS-82-42 in in the To PAUTO Pull To the Pull PAUTO position.
position.
JPM77-1AP JPM77-1 AP Page Page 1010 of of 11 11 Rev.12 Rev. 12 Job Performance Job Performance Checklist:
Checklist:
STEPISTANDARD STEP/ST ANDARD SAT/UNSAT SAT/UNSAT STEP 21.:
STEP 21.: [10.3] DECREASE
[10.3] DECREASE voltage voltage toto 6700 6700 volts volts on on 0-EI-82-34 0-El-82-34 SAT SAT using 0-HS-82-42.
using 0-HS-82-42.
- UNSAT UNSAT STANDARD: Operator STANDARD: Operator decreases decreases voltage voltage to 6700 volts to 6700 volts on on EI-82-34.
EI-82-34.
STEP 22.:
STEP 22.: [10.4] INCREASE voltage
[10.4] INCREASE voltage to 7300 volts to 7300 volts on on 0-EI-82-34 0-EI-82-34 SAT using 0-HS-82-42.
using O-HS-82-42.
- UNSAT UNSAT STANDARD:
STANDARD: Operator increases voltage to 7300 volts on EI-82-34.
El-82-34.
STEP 23.: [10.5] RETURN voltage to value recorded in 6.1 [10.1] - SAT STANDARD: reading recorded Operator returns voltage to reading recorded in step 6.16.1[10.1],
[10.1], - UNSAT UNSAT
- 7000 Volts (+1- 200 volts)
Critical Step STEP 24.: [11] PLACE 0-HS-82-48, DG 11 B-B Mode Selector Switch, SAT in PARALLEL position.
- UNSAT U NSAT STANDARD: 0-HS-82-48 rotated to the PARALLEL position.
on & green light "off".
Red light "on" off. Critical Step EVALUATOR NOTE: While operator is adjusting the speed control in the next step have console operator insert IMF AN-OV-958 f:2 STEP 25:
25.: [12] ADJUST 0-HS-82-43 DG 1 1 B-B Speed Control Switch to obtain - SAT a synchroscope indication of slowly rotating in FAST direction.
- UNSAT STANDARD: Operator adjusts speed control hand switch 0-HS-82-43 such that synchroscope (Xl-82-31)
(XI-82-31) is moving slowly in the fast direction (slowly Critical Step clockwise).
The steps [27] thru [29] are from 0-AR-M26-B STEP 26.: RESPOND TO annunciator panel 0-M-26B window D-2. -
SAT STANDARD:
STANDARD: Operator pulls AR 0-M-26B 0-M-268 and consults for window D-2, - UNSAT OR depresses depresses the emergency stop stop button button for D/G DIG I18-8.
B-B.
STEP STEP 27.:
27.: IF DIG
[1] IF DIG running with nono valid accident accident (blackout or SI) signal present, or SI) present, - SAT SAT THEN ENSURE DIG THEN ENSURE DIG shutdown shutdown by by depressing depressing emergency stop stop pushbutton pushbutton 0-HS-82-47A 0-HS-82-47A.. - UNSAT UNSAT STANDARD: Operator STANDARD: Operator depresses depresses emergency emergency stopstop button for Diesel button for Diesel Generator B-B.
Generator 118-8. Critical Step Critical Step
JPM77-1AP JPM77-1 AP Page Page 11 11 of of 11 11 Rev.12 Rev.12 Job Performance Checklist:
Job Performance Checklist:
STEPISTANDARD STEP/STANDARD SAT/U N SAT SATIUNSAT STEP 28.:
STEP 28.: [2] IF
[2] DIG running IF DIG running with with valid valid accident accident (blackout (blackout or SI) signal or SI) signal present.
present..... SAT SAT STANDARD: Operator STANDARD: Operator N/A's N/As this this step, step, DIG D/G isis being being run for PMT.
run for PMT. UNSAT UNSAT STEP 29.:
STEP 29.: [3] DISPATCH personnel
[3] DISPATCH personnel to D/G Bldg to DIG Bldg to verify alarm, to verify alarm, SAT SAT AND CHECK AND CHECK crankcase crankcase trip trip device device actuated actuated
[O-PS-82-5026/21 or
[0-PS-82-5026/2] or [0-PS-82-5025/2].
[O-PS-82-5025/21. - UNSAT UNSAT Cue:
Cue: AUO informs AUO informs Unit Unit Operator Operator that that crankcase crankcase pressure pressure alarm alarm is is in in on on local panel and O-PS-82-5026/2 is local panel and O-PS-82-5026/2 is actuated actuated on on engine engine 2.2.
STANDARD: Operator contacts AUO at the Diesel STANDARD: Diesel Generator Building Building to confirm pressure alarm.
crankcase pressure STEP 30.:
STEP NOTIFY US/SROUSISRO of Emergency Stop of Diesel Generator 11 B-B. SAT Cue:
. US/SRO instructs operator to standby for further instructions. - UNSAT Stop STANDARD: Operator informs US/SRO of Emergency stop of Diesel Generator 11 B-B.
STANDARD: Time Time_ _
END ENDofJPMofJPM
READ TO OPERATOR Direcfions to Trainee:
Directions I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. II will provide initiating cues and reports on other actions when directed by you. When you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you have completed your assigned task return the handout sheet II provided you.
INITIAL CONDITIONS:
- 1. Both units are at 100% RTP.
- 2. All systems are OPERABLE, except for the 1I B-B DIG.
- 3. O-GO-16 has been completed on all the A train equipment.
0-GO-16
- 4. Maintenance has been completed on the 11 B-B DIG D/G and the clearance has been removed.
- 5. The DIGD/G has been rolled and is in standby alignment using 0-SO-82-2.
- 6. The AUO at the DIG D/G building has completed Appendix A of 1-SI-OPS-082-007.B I-SI-OPS-082-007.B and all parameters are within limits. Two AUO's aI/ AUOs are standing by for DG start.
- 7. The U1 UI Control Room AUO has verified breaker 1934 is in the Disconnect position.
DIG-DAQ has been installed.
- 8. D/G-DAQ
- 9. Room fire protection is in service.
10.The
- 10. UI US/SRO has reviewed the completed work package for the 1 The U1 lB-B B-B DIG, D/G, all that remains iss to perform 1-SI-OPS-082-007.B 1-Sl-OPS-082-007.B for the PMT.
11 .Section 4.0 and Appendix A of 1-SI-OPS-082-007.B 11.Section 1-SI-OPS-082-007.B are complete.
12.Section
- 12. Section 6.1 is complete thru step 6.
INITIATING CUES:
1.
- 1. Perform 1-Sl-OPS-082-007.B, 1-SI-OPS-082-007.B, beginning with Section 6.1, step 7.c.
JPMI3AP1-1 JPM13AP1-1 Page Page 11 of of 10 10 Rev.
Rev. 00 SEQUOYAH NUCLEAR NUCLEAR PLANT PERFORMANCE MEASURE JOB PERFORMANCE MEASURE JPMI3API-1 JPM13AP1-1 Transfer to Hot Leg Recirculation PREPARED!
PREPARED/
REVISED BY: Date!
Date/
VALIDATE VALIDATEDD BY: *
- Date/
Date!
~~~----------
APPROVED BY: Date!
Date/
(Operations Training Manager)
CONCURRE CONCURRED:D: **
- Date!
Date/
(Operations Representative)
Representative)
- Validation not required for minor enhancement enhancements,s, procedure Rev changes that do not affect the JPM, or individual step changes that do not affect the flow of the JPM.
JPM13AP1-1 Page 22 of of 10 10 Rev. 0 NUCLEAR TRAINING REVISIONIUSAGE LOG REVISION/USAGE LOG REVISION DESCRIPTION OF DESCRIPTION V DATE PAGES PREPARED!
PREPARED/
NUMBER REVISION AFFECTED REVISED BY:
0 New JPM adapted from JPM 13AP1 for Y 1/1 8/10 1/18/10 All M Hankins NRC exam 02 2010, updated special instructions to the evaluator, added Appendix A with Hot Leg Recirc flowpath manipulations for and major valve manipulations examiner. Revised to end JPM after flow established for train A SI pump.
v - Specify if the JPM change will require another Validation (Y or N).
V -
See cover sheet for criteria.
JPM13AP1-1 JPMI3API-1 Page Page 33 of of 10 10 Rev.
Rev.00 SEQUOYAH SEQUOY NUCLEAR PLANT AH NUCLEAR PLANT ROISRO RO/SRO JOB PERFORMANCE JOB PERFORMANCE MEASURE MEASURE Task:
Task:
Transfer to Transfer Hot Leg to Hot Leg Recirculation Recirculation JAITA Task JA/TA Task ##:: 0000790501 0000790501 (RO)
(RO)
Ratings:
KIA Ratings:
KIA 194001 A1.02 194001 A1.02 (4.1/3.9)
(4.1/3.9) 194001 A1.13 194001 A1.13 (4.3/4.1)
(4.3/4.1) 000011 000011 EA 1.11 (4.2/4.2)
EA1.11 (4.2/4.2) 000011 EA1.13 000011 EA1.13(4.1/4.2)
(4.1/4.2) 006020 A4.01 006020 A4.01 (3.7/3.6)
(3.7/3.6) 000011 000011 EA1.05 EA1.05 (4.3/3.9)
(4.3/3.9) 006020 A4.02 006020 A4.02 (3.9/3.8)
(3.9/3.8)
Task Standard:
Task Standard:
Realign RHR Realign RHR toto cold cold leg leg injection injection and and BOTH BOTH trains trains of of safety safety injection injection to to hot hot leg leg recirculation recirculation flow flow path. (RHR hot legleg injection valve fails to open)
Evaluation Method: Simulator _~X'--_ X In-Plant - - -
In-Plant
=======================================================================
Performer:
NAME Start Time _ __
Performance Rating: SAT UNSAT Performance Time Finish Time _ __
Evaluator: /
SIGNATURE DATE
=======================================================================
COMMENTS
JPM13AP1-1 JPM13AP1-i Page Page 44 of of 10 10 RevrO Rev.0 SPECIAL INSTRUCTIONS SPECIAL INSTRUCTIONS TO TO EVALUATOR:
EVALUATOR:
- 1. Critical identified.
steps identified.
1 . Critical steps
- 2. Any
- 2. Any UNSAT UNSAT requires requires comments.
comments.
- 3. Initialize Simulator to
- 3. Initialize Simulator to IC #120, IC #120, after after automatic automatic containment containment sump sump swapover swapover isis initiated, initiated, perform perform required alignment required alignment of of ECCS ECCS to to Containment Containment Sump Sump per ES-i .3. Insert per ES-1.3. Insert the the following following remote remote functions:
functions:
- a. IRF
- a. IRF RHR14 RHRI4f:1 (FCV-63-1) f:1 (FCV-63-1)
- b. IRF
- b. IRF SIR06 f:O) (FCV-63-22)
SIRO6 f:O) (FCV-63-22) (Verify (Verify power power on on during during setup) setup)
- c. lOR
- c. IOR ZDIHS63172A ZDIHS63I72Af:O (Fails FCV-63-172 f:O (Fails FCV-63-172 closed) closed)
- 5. IfIf sump
- 5. sump recirc recirc IC IC isis not not available, available, then then initialize initialize to to IC IC #16
- 16 and and complete complete the the following following setup:
setup:
- a. Insert IMF
Leg) and and trip trip RCPs.
RCPs.
- b. After automatic
- b. After automatic containment containment sump sump swapover swapover isis initiated, initiated, perform perform required required alignment alignment of of ECCS ECCS to containment to containment sump per sump ES-i .3.
per ES-1.3.
- c. Place operating
- c. Place operating powerpower on on FCV-63-1 FCV-63-i (remote (remote function function IRFIRF RHR14 RHRI4 f:1).f:1).
- d. When
8% realign realign containment containment sprayspray pump pump suction suction to to containment containment sump per sump per ES-1.3.
ES-I .3.
Ensure operating power
- e. Ensure power ON FCV-63-22 FCV-63-22 (Check remote function main main menu menu for IRF IRF SIR06 SIRO6 f:O, this task should have been performed in E-1).
this E-i).
- f. Insert override lOR IOR ZDIHS63172A ZDIHS63I72A f:O (Fails [FCV-63-1721
[FCV-63-1 721 CLOSED)
- g. Acknowledge and clear ALL alarms.
- h. Freeze simulator after realignment of containment spray suction to containment sump.
h.
6.
- 6. Insert overrides to silence following nuisance alarms:
- a. IMF IMF AN_OV_304f:3 AN_OV_304 f:3 (Saturation Margin Trouble)
- b. IMF IMF AN_
AN_OV_420 OV_420 f:3 (Lower Compt Moisture High)
ANOV_96 f:3 (Turbine Zero Speed)
- c. IMF AN_OV_96 Change plaque next to FCV-63-22 to indicate power restored to valve.
- d. Change Ensure Operator performs the following required actions for SELF-CHECKING;
- 7. Ensure
- a. Reviews the intended action and expected response.
- b. Compares the actual response to the expected response.
- 8. Appendix A Hot Leg Recirculation Flowpath is available for examiner.
Validation Time: CR. 15 mins Local _ _ _ __
Tools/Equipment/Procedures Needed:
ES-i ES-1.4, .4, Transfer to Hot Leg Recirculation
References:
Reference Reference Tite Title Rev No.
JPM13AP1-1 JPM1 3AP1-i Page Page 55 of of 10 10 Rev.
Rev.G 0 READ TO READ TO OPERATOR OPERATOR Directions to Directions to Trainee:
Trainee:
will explain II will the initial explain the initial conditions, conditions, and and state state the the task task to to be be performed.
performed. AllAll control control room room steps steps shall shall be performed for be performed for this JPM. II will this JPM. will provide provide initiating initiating cues cues and and reports reports on on other other actions actions when when directed directed by you.
by you. When When you complete the you complete the task task successfully, successfully, the objective for the objective for this this job job performance performance measure measure will be will be satisfied.
satisfied. Ensure Ensure you you indicate indicate to to me me when when you you understand understand your your assigned assigned task.
task. To To indicate indicate that you that you have have completed completed your your assigned assigned task task return return the the handout handout sheet sheet II provided provided you.
you.
INITIAL CONDITIONS:
INITIAL CONDITIONS:
- 1. All ECCS components and
- 1. and Containment Spray pumps are aligned and are aligned and taking suction suction from containment sump containment sump per ES-i .3, Transfer per ES-1.3, Transfer To RHR RHR Containment Containment Sump.
Sump.
- 2. RCS
- 2. RCS pressure is is less less than 180 180 psig. RHRRHR spray is is NOT NOT inin service.
- 4. 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> have elapsed since the time of the event.
INITIATING CUES:
INITIATING
- 1. As the OATC, you are directed to transfer to hot leg recirculation in accordance with ES-1.4, ES-i .4, Transfer to Hot Leg Recirculation.
Recirculation.
JPM JPM 13AP1-1 13API-1 Page 66 of Page of 10 10 Rev. 0 Rev.0 Job Performance Job Performance Checklist:
Checklist:
STEP/STANDARD STEP/ST ANDARD SAT/UNSAT SATIUNSAT STEP 1:
STEP 1: Obtain aa copy Obtain copy of the appropriate of the appropriate procedure.
procedure. SAT SAT STANDARD: Operator STANDARD: Operator obtains obtains aa copy copy of ES-i .4.
of ES-1.4. UNSAT UNSAT COMMENTS:
COMMENTS:
Start Start Time Time_ _
STEP 2:
STEP 2: 1. DETERMINE
- 1. DETERMINE ifif RHR RHR spray spray should should be be isolated:
isolated: SAT SAT
- a. CHECK RHR
- a. CHECK RHR spray spray IN IN SERVICE:
SERVICE:
- Train BB RHRRHR spray valve FCV-72-41 FCV-72-4i OPEN OPEN..
STANDARD:
STANDARD: Operator determines Operator determines FCV-72-40 FCV-72-40 and FCV-72-41 FCV-72-41 closed, verifies green lights ON and red lights OFF for both valves.
Operator goes to RNO step [a] and then proceeds to step 2.
COMMENTS:
COMMENTS:
STEP 3:
STEP 2. CHECK RHR pump A-A RUNNING. SAT STANDARD: Operator checks RHR pump A-A running, verifies red light ON and STANDARD: UNSAT green light OFF.
Operator may also verify pump amps normal (EI-74-5A).
COMMENTS:
STEP *4: 3. ALIGN RHR Train A for hot leg recirculation:
STEP *4:
- SAT
- a. CLOSE RHR Train A cold leg isolation isolation valve FCV-63-93.
- UNSAT UNSAT NOTE:
NOTE: Alarm onon M-6D, M-6D, window E-6, E-6, Group Group 66 Monitor Monitor Lights Lights Component Component Off Off Normal Normal will come in in when when FCV-63-93 is is closed.
closed.
Step Critical Step STANDARD:
STANDARD: Operator places FCV-63-93 Operator places FCV-63-93 to to Close, Close, verifies green green light ON and light ON and red light OFF.
light OFF.
COMMENTS:
COMMENTS:
JPM JPM 13AP1-1 13AP1-1 Page 77 of Page of 10 10 Rev. 0 Rev.0 Job Performance Checklist:
Job Performance Checklist:
STEP/STAN STEP/ST DARD ANDARD SAT/UNSAT SATIU NSAT STEP 5:
STEP 5: 3. ALIGN
- 3. ALIGN RHRRHR Train Train AA for for hot hot leg leg recirculation:
recirculation: SAT SAT
- b. ENSURE RHR
- b. ENSURE RHR Train Train BB discharge discharge crosstie crosstie valve valve FCV-74-35 FCV-74-35 CLOSED.
CLOSED. - UNSAT STANDARD: Operator STANDARD: Operator ensures ensures FCV-74-35 FCV-74-35 Closed, Closed, verifies verifies green light ON green light ON and and red red light light OFF.
OFF.
COMMENTS:
COMMENTS:
STEP *6:
STEP *6: 3.
recirculation: SAT SAT
- c. OPEN OPEN RHRRHR Train A A discharge crosstie crosstie valve FCV-74-33.
FCV-74-33.
- UNSAT UNSAT STANDARD: Operator STANDARD: Operator places places FCV-74-33 FCV-74-33 to to Open, Open, verifies verifies red red light