ML110350623
| ML110350623 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 02/04/2011 |
| From: | NRC/RGN-II |
| To: | Tennessee Valley Authority |
| References | |
| 50-327/10-302, 50-328/10-302 | |
| Download: ML110350623 (373) | |
Text
F.1 F
JPM Sim A-i Page 1 of 1 Rev. 0 SEQUOYAH NUCLEAR PLANT September 2010 NRC Exam Simulator A-I Withdraw Shutdown Banks Alternate Path
JPM Sim A-i Page 2 of 2 Rev. 0 RO!SRO JOB PERFORMANCE MEASURE Task: Withdraw Shutdown Banks Task#: RO 0010180101 Task Standard: Withdraw Shutdown Control Rods to the fully withdrawn position. Stop Rod Withdrawal when SD A Group 1 control rods drop into core from a partially withdrawn position.
Alternate Path: YES: X NO:
Time Critical Task: YES: NO: X K/A Reference/Ratings: 0012.11 (4.4/4.7)
OOiA2.17 (3.3/3.8)
Method of Testing:
Simulated Performance: Actual Performance: X Evaluation Method:
Simulator X In-Plant Classroom Main Control Room Mock-up Performer:
Trainee Name Evaluator: I Name/ Signature DATE Performance Rating: SAT: UNSAT:
Validation Time: 20 mins Total Time:
Performance Time: Start Time: Finish Time:
COMMENTS
JPM Sim A-i Page 3 of 3 Rev. 0 SIMULATOR OPERATOR INSTRUCTIONS:
- 1. Critical steps are identified in step SAT/UNSAT column by bold print Critical Step.
- 2. Any UNSAT requires comments
- 3. Initialize in IC #112.
- 4. If IC #112 is not available, initialize in IC #7 and perform the following setup; Position HS-85-51 10 to Manual;
- Select STARTUP Mode on NR45; Ensure Audio Count rate is audible Clear HI Flux at Shutdown alarm.
Insert the dropped rod malfunctions below for SD Grp 1 together on a key; activate as specified in JPM body:
M-2 RDO7M2 k:1 L-5 RDO7L5 k:1 Monitor Rod Withdrawal; @ 35 steps on SD A, initiate Key I
- 5. Ensure operator performs the following required actions for 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.
Tools/EquipmentlProcedures Needed:
0-SO-85-1, section 6.3 TI-28 Attachment 6
References:
Reference Title Rev No.
- 1. 0-SO-85-1 Control Rod Drive System 34
- 2. TI-28 Curve Book 243
- 3. TRM Technical Requirements Manual 45 DIRECTIONS TO TRAINEE on next page
JPM Sim A-I Page 4 of 4 Rev. 0 READ TO OPERATOR DIRECTIONS TO TRAINEE:
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 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 I Tripped after a 4 month run following startup from the Spring 2009 refueling outage.
Trip report is finalized and the unit is ready for restart
- 2. Reactor Engineering specifies shutdown and control banks fully withdrawn position is 228 steps.
- 3. Unit I is in MODE 3 with Tavg at 547°F and RCS pressure at 2235 psig.
- 4. 0-Sl-NUC-000-038.O, Shutdown Margin Section 6.2.3, Shutdown Margin Calculation for Modes 3, 4, and 5 (Including Cases Where Shutdown Banks are to be Withdrawn or are Already Withdrawn) is complete for withdrawing shutdown rods.
- 5. Both M-G sets are in service.
- 6. Precautions, Limitation and 0-SO-85-1 Section 4 are current, complete and signed off.
INITIATING CUES:
- 1. The Unit Supervisor directs you to withdraw the Shutdown Banks in accordance with 0-SO-85-1, Control Rod Drive System Section 6.3 starting at step II.
- 2. Inform the US when the all shutdown banks are at the fully withdrawn position.
JPM Sim A-I Page 5of5 Rev. 0 Job Performance Checklist:
STEP/STANDARD SATIUNSAT EVALUATOR NOTE: O-SO-85-1, Control Rod Drive System 6.3, Manual Operation of Rod Control System Below 15 Percent Power contains the procedural steps for performing the following actions starting at step 11.
EVALUATOR NOTE: SQN Unit 1 ICS Rod Position Indication display access:
Top Level -> PRIMARY MIMICS -* ROD POSITION INDICATORS STEP 1.: Operator determines and locates correct procedure and section SAT to be used or Evaluator provides selected procedures andlor UNSAT section(s) as necessary.
STANDARD: Operator locates and obtains a copy of O-SO-85-1 section 6.3 or is provided with appropriate procedure and section COMMENTS:
Start Time STEP 2.: [11] MONITOR Control Rod position USING Rod Position Indicators SAT ICS screen 30 minute trend during SD & Control Banks withdrawal UNSAT to aid in detecting rod misalignment.
STANDARD: Applicant acknowledges continuous action (MONITOR) step and locates/displays ICS ROD POSITION INDICATORS screen using the mouse to position the curser on the specified action field and click the left mouse button.
COMMENTS:
JPM Sim A-i Page 6 of 6 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 3.: [12] IF Individual Rod Position Indication does not indicate proper SAT rod position during withdrawal of SD Banks, THEN UNSAT
[a] STOP rod withdrawal
[b] ENSURE subcriticality
[c] CONTACT MIG AND INITIATE troubleshooting
[d] IF troubleshooting does not resolve the problem, OR subcriticality can NOT be verified, THEN INITIATE Reactor TRIP.
STANDARD: Applicant acknowledges conditional action step and continues.
COMMENTS:
Step 4.: [13] IF Individual Rod Position Indication does not indicate proper SAT rod position during withdrawal of Control Banks, THEN GO TO AOP-C.O1 section 2.5 Rod Position Indicator (RPI) Malfunction UNSAT Modes 1 or 2.
STANDARD: Applicant acknowledges conditional action step, COMMENTS:
CAUTION:
Under normal conditions control rod banks must be withdrawn and inserted in the prescribed sequence.
For withdrawal, the sequence is Shutdown Bank A, Shutdown Bank B, Shutdown Bank C, Shutdown Bank D, Control Bank A, Control Bank B, Control Bank C, Control Bank D. The insertion sequence is the reverse of the withdrawal sequence.
NOTE 1:
Startup rate, Source range, Intermediate range, Nuclear Instrumentation recorders, Group Step Counters and the Rod Position Indicators should be monitored during each bank withdrawal.
NOTE 2:
The following failures will render the rod control system incapable of automatic and I or manual motion without any annunciation or indication: 1) Hand switch failure; 2) relay failure, and 3) simultaneous failure of both 1 OOv DC power supplies (PS3 and PS6)
JPM Sim A-i Page 7of7 Rev. 0 Job Performance Checklist:
STEP ISTANDARD SAT/UNSAT STEP 5 [14] PLACE [HS-85-5110], Rod Control Mode Selector to the SAT SBA position.
UNSAT STANDARD: Applicant locates/places 1-HS-85-5110 to the SBA position Shaded portion is critical because correct shutdown rod bank selection Critical Step for withdrawal is assured. (shaded portion)
COMMENTS:
STEP 6.: [15] VERIFY Rod Speed Indicator [SI-412], indicates 64 SAT Steps/minute.
UNSAT STANDARD: Applicant locates Rod Speed Indicator Sl-412 (on the central upright portion of M-4) and verifies 64 Steps/minute indicated.
COMMENTS:
NOTE:
Monitor Group Step Counters, Rod Position Indicator and the IN-OUT status lights to ensure anticipated motion as each bank is being withdrawn. Rod speed indicator should be reading 64 steps per minute.
JPM Sim A-i Page 8 of 8 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 7.: [16] ENSURE Shutdown Bank A demand position counters SAT operational by performing the following: [C.2]
UNSAT
[a] BUMP [HS-85-5111], Rod Control Switch to withdraw Shutdown Bank A one-half step at a time, for one full step.
[b] CHECK group demand position counters advance properly.
[c] BUMP [HS-85-5111] to withdraw Shutdown Bank A one-half step at a time, for the second full step.
[d] VERIFY group demand position counters advance properly.
STANDARD: Applicant places 1-HS-85-51 11 to the OUT position to move rods one step in half step increments AND checks that both step counters count up one step.
Applicant places 1-HS-85-51 11 to the OUT position to move rods one step in half step increments a second time AND checks that both step counters count up one additional step.
COMMENTS:
STEP 8.: [16] [e] IF group demand position counters do NOT advance SAT properly, THEN:
UNSAT A. STOP rod withdrawal.
B. INITIATE WO to have counter repaired.
C. WHEN counter is repaired, THEN:
- 1. ENSURE Shutdown Bank A fully INSERTED.
- 2. RETURN to beginning of this step.
STANDARD: Operator observes/verifies that both counters are responding correctly and NIAs this step.
COMMENTS:
JPM Sim A-I Page 9 of 9 Rev. 0 Job Performance Checklist:
NOTE:
STEP/STANDARD I SAT/UNSAT The fully withdrawn position for shutdown and control rods is defined by Tl-28, Att. 6.
Simulator Operator: As directed by the Examiner, at 35 steps, insert dropped rod malfunctions. (key 1)
ALTERNATE Path:
SAT STEP 9.: [17] WITHDRAW Shutdown Bank A to the FULLY UNSAT WITHDRAWN position using [HS-85-5111].
STANDARD: Operator continues withdrawing SB A control rods using hand switch I -HS-85-51 11 At 1 00 steps, the Applicant recognizes identifies SB A Critical Step Group 1 Control Rods have dropped by using: (shaded portion)
Using IRPIs (M-4 central upright portion to the left of Rod Speed indicator)
AND Associated Rod bottom lights (below each IRPI).
THEN the Applicant manually inserts a reactor trip signal by turning 1-RT-l on 1-M-4 (1-RT-2 on 1-M-6 will accomplish the same thing) to the TRIP position AND identifies all SB A Control Rods are fully inserted.
Shaded portion is critical to ensure compliance with the control rod alignment and insertion limits to maintain shutdown margin. This action can be implemented as a prudent operator action (defined in EPM-4) or according to AOP-C.O1, Rod Control System Malfunctions.
Stop Time COMMENTS:
CUE: This completes this JPM.
READ TO OPERATOR DIRECTIONS TO TRAINEE:
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 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 I Tripped after a 4 month run following startup from the Spring 2009 refueling outage.
Trip report is finalized and the unit is ready for restart
- 2. Reactor Engineering specifies shutdown and control banks fully withdrawn position is 228 steps.
- 3. Unit I is in MODE 3 with Tavg at 547°F and RCS pressure at 2235 psig.
- 4. 0-Sl-NUC-000-038.0, Shutdown Margin Section 6.2.3, Shutdown Margin Calculation for Modes 3, 4, and 5 (Including Cases Where Shutdown Banks are to be Withdrawn or are Already Withdrawn) is complete for withdrawing shutdown rods.
- 5. Both M-G sets are in service.
- 6. Precautions, Limitation and 0-SO-85-I Section 4 are current, complete and signed off.
INITIATING CUES:
I. The Unit Supervisor directs you to withdraw the Shutdown Banks in accordance with 0-SO-85-1, Control Rod Drive System, Section 6.3 starting at step 11.
- 2. Inform the US when the all shutdown banks are at the fully withdrawn position.
READ TO OPERATOR DIRECTIONS TO TRAINEE:
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 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 I Tripped after a 4 month run following startup from the Spring 2009 refueling outage.
Trip report is finalized and the unit is ready for restart
- 2. Reactor Engineering specifies shutdown and control banks fully withdrawn position is 228 steps.
- 3. Unit I is in MODE 3 with Tavg at 547°F and RCS pressure at 2235 psig.
- 4. 0-Sl-NUC-000-038.0, Shutdown Margin Section 6.2.3, Shutdown Margin Calculation for Modes 3, 4, and 5 (Including Cases Where Shutdown Banks are to be Withdrawn or are Already Withdrawn) is complete for withdrawing shutdown rods.
- 5. Both M-G sets are in service.
- 6. Precautions, Limitation and 0-SO-85-1 Section 4 are current, complete and signed off.
INITIATING CUES:
I. The Unit Supervisor directs you to withdraw the Shutdown Banks in accordance with 0-SO-85-1, Control Rod Drive System, Section 6.3 starting at step 11.
- 2. Inform the US when the all shutdown banks are at the fully withdrawn position.
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT SYSTEM OPERATING INSTRUCTION O-SO-85-1 CONTROL ROD DRIVE SYSTEM Revision 34 QUALITY RELATED PREPARED BY: CECIL DYER RESPONSIBLE ORGANIZATION: OPERATIONS APPROVED BY: W. T. LEARY EFFECTIVE DATE: 09/23/09 LEVEL OF USE: CONTINUOUS USE REVISION DESCRIPTION: -
set A and 5.2 for MG Split Section 5.1 standby readiness for both MG sets into Section 5.1 for MG set B this will remove error traps. (FOR 09000712) d step from 113 to 110 Section 6.3 Step 38 deleted note referencing LEFM available and change steps for rod control banks limit low-low. (FOR 09000168) step from 123 to 120 Section 6.3 Step 39 deleted note referencing LEFM available and change steps for rod control banks limit low. (POR 09000168) referenced AOP-O.01 Section 6.3 added Oaution prior to step 1 forTRM 3.1.3.3 requirements and as required. (FOR 08001279) fans aligned to the Added precaution and limitation M that rod movement without the ORDM are less than reactor vessel shroud is allowed, provided that the ROS temperatures ion M added when 350 degrees F. Section 6.3 Note prior to step [1] and precaution and limitat motion shall comply with the ROS temperatures are greater than 350 degrees F, continuous rod in accordance with restrictions. Section 6.3 Step 3 added to ensure ORDM fans in service 07001668, PER 172096 &
0-SO-30-6, if RCS temperature is greater than 350 degrees F.(PCR EWR 09-BOP-30-01 8)
Y PERFORMANCE OF THIS PROCEDURE COULD IMPACT REACTIVIT
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 34 Page 6 of 80 3.0 PRECAUTIONS AND LIMITATIONS A. Rod thermal lock-up is NOT a concern when the reactor trip breakers are OPEN. If reactor trip breakers are CLOSED and an RCS cooldown of greater than 50°F is planned, the shutdown and control banks should be withdrawn at least 5 steps each. This will limit the possibility of thermal lock up of the rods. This does not apply if performing sections 8.5 or 8.6.
B. If both MG sets are to be shutdown, the control rods and shutdown rods shall be inserted in the core and the reactor trip breakers OPEN prior to shutting down the MG sets.
C. Reactor Trip Breakers shall NOT be closed while in Mode 3 unless in compliance with LCO 3.4.1.2.
D. Failure to perform 1,2-Pl-IFT-099-0P4.0, Verification of P4 Contacts could result in the prevention of AUTO SI if required.
E. Under normal conditions, the control rod banks must be withdrawn and inserted in the prescribed sequence. For withdrawal the sequence is Shutdown Bank A, Shutdown Bank B, Shutdown Bank C, Shutdown Bank D, Control Bank A, Control Bank B, Control Bank C, and Control Bank D. The insertion sequence is the reverse of the withdrawal sequence.
F. For manual bank sequencing, the prescribed withdrawal and insertion sequence should be followed. Rod motion of the correct bank should be monitored by observing the group step counters and the rod position indicators.
G. During Control Rod withdrawal, the Control Banks should be monitored for bank overlap.
H. The control banks must be maintained above their respective insertion limits (Low-Low Alarm to ensure adequate shutdown in the event of a reactor trip, to ensure that maximum possible ejected rod reactivity limits are maintained and to ensure acceptable core power distributions.
I. Before withdrawing any rod bank from the fully inserted position, the group step counters and the rod position indicators for that bank must be at zero steps.
SQN CONTROL ROD DRIVE SYSTEM O-SO-85-1 1,2 Rev 34 Page 7 of 80 3.0 PRECAUTIONS AND LIMITATIONS (Continued)
J. Deleted K. RPIs and step counters shall be maintained within limits per TS 3.1.3.1 and 3.1.3.2.
L. The Control Rods shall NOT be stepped or tripped unless the RCS pressure is at least 100 psig.
M. Rod movement without the CRDM fans aligned to the Reactor Vessel shroud is allowed, provided that the RCS temperatures are less than 350° F.
N. When RCS temperatures are greater than 350° F, continuous rod motion shall comply with these restrictions:
CRDM OUTLET ROD MOTION LIMITS TEMPERATURE 190°F 10 minutes ON 20 minutes OFF 200°F 6 minutes ON 24 minutes OFF Time limitations are due to a lower air flow rate of 48,000 cfm across the shroud combined with a higher temperature (Reference TSIR-97-BOP-30-636 and Westinghouse Letters RIMs #B38931005806, B38930920800, and B38931 005803).
N. The following failures will render the rod control system incapable of automatic and I or manual motion without any annunciation or indication:
- 1) Hand switch failure; 2) relay failure, and 3) failure of both lOOv DC power supplies (PS3 and PS6) simultaneously.
- 0. Defeating or restoring TavglDelta T or NIS channel may cause step change in input to rod control. A delay of at least 3 minutes prior to returning rod control to automatic will allow lead/lag signal to decay off.
SQN CONTROL ROD DRIVE SYSTEM O-SO-85-1 1,2 Rev34
. Page8of8O 3.0 PRECAUTIONS AND LIMITATIONS (Continued)
P. Directional Overcurrent Relay Targets are reset by depressing the Relay Target Reset Pushbutton on the panel to break the target coil seal in circuit and then lifting the mechanical reset at the bottom of the relay cover.
Q. US I SRO Oversight for control rod manipulation shall include:
- 1. Prior to Rod Movement
- a. Ensure RPIs within T.S. range (+ or 12 steps)
- b. Ensure delta flux will not be adversely affected
- c. Ensure Tavg and Rx Thermal power will not be adversely affected
- d. Verity on target with Rx Eng reactivity balance sheet
- e. Verify power change will not exceed hourly rate
- f. Ensure no simultaneous reactivity manipulations in progress (i.e.: borations, dilutions or turbine load changes)
- 2. During Rod Movement
- a. Ensure RO has peer check
- b. Ensure RO is following procedure
- c. Ensure RO understands how many steps they are moving rods
- d. Ensure RO has checked all the above mentioned items
- e. Watch performance of rod manipulation while listening to audible indication of rod step
- f. Ensure peer check is doing their job
- g. Re-verity steps a d of initial evaluation
- h. Ensure procedure is followed placing rods back to auto (Tavg Tref mismatch)
- i. Monitor plant for expected response
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev34 Page 9of80 Unit_________________ Date PREREQUISITE ACTIONS Throughout this instruction where an IF/THEN statement occurs, the step may be NIA if the condition does NOT exist.
_4jJ ENSURE the instruction to be used is a copy of the effective version.
4jIENSURE Precautions and Limitations, Section 3.0 has been reviewed.
jNSURE each performer documents their name and initials:
Print Name Initials ec INDICATE below which performance section of this instruction will be used and the reason for this performance:
LI 5.0 STARTUP/STANDBY READINESS 6.0 NORMAL OPERATION El 7.0 SHUTDOWN LI 8.0 INFREQUENT OPERATION Reason: vra -ZxS
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-l 1,2 Rev 34 Page 41 of 80 Un it I Date_________
6.3 Manual Operation of Rod Control System Below 15 Percent Power CAU TR 3.1.3.3 requires group demand position indicator capable of determining within +/-2 steps, the demand position for each rod not fully inserted. In Modes 3, 4, or 5 and greater than +/-2 steps deviation refer to AOP-C.01.
CAJ If reactor trip breakers are CLOSED and an RCS cooldown of greater than 50°F is planned, the shutdown and control banks should be withdrawn at least 5 steps each. This will limit the possibility of thermal lock-up of the rods. Thermal lock-up is NOT a concern during unit heatup.
When RCS temperatures are greater than 350F, continuous rod motion shall comply with these restrictions:
CRDM OUTLET ROD MOTION LIMITS TEMPERATURE 190°F 10 minutes ON 20 minutes OFF 200°F 6 minutes ON 24 minutes OFF JENSURE Section 5.5, Reset/Close Reactor Trip Breakers has been completed.
IF the shutdown and control rods were withdrawn 5 steps to prevent thermal lockup during an RCS cooldown, THEN ENSURE rods are fully inserted prior to withdrawal.
1 tJL4 1st cv IF RCS temperatures are greater than 350°F, THEN ENSURE CRDM cooling fans are aligned and in service in accordance with 0-SO-30-6.
CONTROL ROD DRIVE SYSTEM 0-SO-85-1 SQN Rev 34 1,2 Page 42 of 80 Date Io&2 Unit_________________
ent Power 6.3 Manual Operation of Rod Control System Below 15 Perc CA9( ROD CONTROL STARTUP STEP COUNTER RESET for any (SUS on M-4) should never be held in STARTUP position RTUP extended period of time. Holding this switch in STA position may cause damage to the counters.
ROD CONTROL STARTUP STEP COUNTER RESET (SUS on M-4) Resets:
A. All GROUP STEP COUNTERS on the Control Board.
B. The master cycler reversible counter.
C. All slave cycler counters.
D. The bank overlap counter.
E. All internal memory and alarm circuits.
F. All pulse-to-analog converters in the Rod Position Indication System.
up MOMENTARILY PLACE [SUS], Rod Control Start Step Counter Reset to the STARTUP position to reset Control Rod Drive System.
position, all CA Before withdrawing any rod from the fully inseed must be at Group Step Counters and all Rod Position indicators zero steps.
zero.
SURE all Full Length Rod step counters reset to
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 34 Page 43 of 80 Date_________
U nit I. nued 6.3 Manual Operation of Rod Control System Below 15 Percent Power (Conti FY rod control IN-OUT direction lights are NOT LIT.
DEPRESS [RCASJ, Rod Urgent Failure Alarm Reset.
SET Window 6 (A-6), ROD CONTROL SYSTEM URGENT FAILURE alarm on panel [XA-55-4B] using
[XS-55-4A], Annunciator RESET!ACKJTEST Switch.
1 1 ERIFY the following rod control system alarms on panel
[XA-55-4B) are NOT LIT:
WINDOW NOT LIT NUMBER (q) 5(A5) EY 6(A6) EV 11(B4) 12(B5) EV 13(B6) LV 18(04) LV 19(C5) 27(D6) 34(E6)
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev34 Page 44 of 80 Unit 1 Date I 63 Manual Operation of Rod Control System Below 15 Percent Power (Continued)
URE Plant computer points for rod bank position are ZERO using the following computer points:
COMPUTER PT ROD BANK q U0049 Control A U0050 Control B EY U0051 Control C U0052 Control D U 0053 Shutdown A U0054 Shutdown B EV U0055 Shutdown C U0056 Shutdown D l
[11] MONITOR Control Rod position USING Rod Position Indicators ICS screen 30 minute trend during SD & Control Banks withdrawal to aid in detecting rod misalignment.
[12] IF Individual Rod Position Indication does not indicate proper rod position during withdrawal of SD Banks, THEN
[a] STOP rod withdrawal. El
[b] ENSURE subcriticality.
[c] CONTACT MIG AND INITIATE troubleshooting. LI
[d] IF troubleshooting does not resolve the problem, OR subcriticality can NOT be verified, THEN iNITIATE Reactor TRIP.
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev34 Page 45 of 80 Date Unit_________________
6.3 Manual Operation of Rod Control System Below 15 Percent Power (Continued)
[13] IF Individual Rod Position Indication does not indicate proper rod position during withdrawal of Control Banks, THEN GO TO AOP-C.01 section 2.5 Rod Position Indicator (RPI)
Malfunction Modes I or 2.
CAUTION Under normal conditions control rod banks must be withdrawn and inserted in the prescribed sequence. For withdrawal, the sequence is Shutdown Bank A, Shutdown Bank B, Shutdown Bank C, Shutdown Bank D, Control Bank A, Control Bank B, Control Bank C, Control Bank D. The insertion sequence is the reverse of the withdrawal sequence.
NOTE I Startup rate, Source range, Intermediate range, Nuclear Instrumentation recorders, Group Step Counters and the Rod Position Indicators should be monitored during each bank withdrawal.
NOTE 2 The following failures will render the rod control system incapable of automatic and / or manual motion without any annunciation or indication: 1) Hand switch failure; 2) relay failure, and
- 3) simultaneous failure of both 1 OOv DC power supplies (PS3 and PS6)
[14] PLACE [HS-85-51101, Rod Control Mode Selector to the I
SBA position.
1st cv
[15] VERIFY Rod Speed Indicator [Sl-4121, indicates 64 Steps/minute. cv 1st
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 34 Page 46 of 80 Date__________
Unit________________
6.3 Manual Operation of Rod Control System Below 15 Percent Power (Continued)
NOTE Monitor Group Step Counters, Rod Position Indicator and the IN-OUT status lights to ensure anticipated motion as each bank is being withdrawn. Rod speed indicator should be reading 64 steps per minute.
[16] ENSURE Shutdown Bank A demand position counters operational by performing the following: [C.21
[a] BUMP [HS-85-5111], Rod Control Switch to withdraw Shutdown Bank A one-half step at a time, for one full step.
1st CV
[b] CHECK group demand position counters advance properly. El
[cj BUMP [HS-85-51 111 to withdraw Shutdown Bank A one-half step at a time, for the second full step.
1st CV
[d] VERIFY group demand position counters advance properly.
[ej IF group demand position counters do NOT advance properly, THEN A. STOP rod withdrawal. El B. INITIATE WO to have counter repaired.
C. WHEN counter is repaired, THEN
- 1. ENSURE Shutdown Bank A fully INSERTED. El
- 2. RETURN to beginning of this step. El NOTE The fully withdrawn position for shutdown and control rods is defined by TI-28, Att. 6.
[17] WITHDRAW Shutdown Bank A to the FULLY WITHDRAWN
/
position using [HS-85-5111]. CV 1st
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 34 Page 47 of 80 Unit______________ Date__________
6.3 Manual Operation of Rod Control System Below 15 Percent Power (Continued)
[18] PLACE [HS-85-5110], Rod Control Mode Selector to the SBB position. /
1st CV
[19] VERIFY Rod Speed Indicator [SI-4121, indicates 64 Steps/minute. i 1st cv NOTE The following failures will render the rod control system incapable of automatic and / or manual motion without any annunciation or indication: 1) Hand switch failure; 2) relay failure, and
- 3) simultaneous failure of both I OOv DC power supplies (PS3 and PS6).
[20] ENSURE Shutdown Bank B demand position counters operational by performing the following: [C.2]
[a] BUMP [HS-85-5111], Rod Control Switch to withdraw Shutdown Bank B one-half step at a time, for one full step.
1st cv
[b] CHECK group demand position counters advance properly.
[c] BUMP [HS-85-5111] to withdraw Shutdown Bank B one-half step at a time, for the second full step.
1st cv
[d] VERIFY group demand position counters advance properly. E
[e] IF group demand position counters do NOT advance properly, THEN A. STOP rod withdrawal.
B. INITIATE WO to have counter repaired.
C. WHEN counter is repaired, THEN
- 1. ENSURE Shutdown Bank B fully INSERTED and E
- 2. RETURN to beginning of this step. El
[21] WITHDRAW Shutdown Bank B to the FULLY WITHDRAWN
/
position using [HS-85-5111].
1st cv
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev34 Page 48 of 80 Date__________
Unit________________
6.3 Manual Operation of Rod Control System Below 15 Percent Power (Continued)
[221 PLACE [HS-85-51 101, Rod Control Mode Selector to the
/
SBC position.
1st CV
[23] VERIFY Rod Speed Indicator [SI-412], indicates
/
0 Steps/minute. CV 1st NOTE The following failures will render the rod control system incapable of automatic and / or manual motion without any annunciation or indication: 1) Hand switch failure; 2) relay failure, and
- 3) simultaneous failure of both lOOv DC power supplies (PS3 and PS6).
[24] ENSURE Shutdown Bank C demand position counters operational by performing the following: [C.2]
[a] BUMP [HS-85-5111], Rod Control Switch to withdraw Shutdown Bank C one full step.
1st CV
[b] CHECK group demand position counter advances properly.
[c] BUMP [HS-85-5111] to withdraw Shutdown Bank C
/
a second full step. CV 1st
[d] VERIFY group demand position counter advanced properly.
[e] IF group demand position counters do NOT advance properly, THEN A. STOP rod withdrawal.
B. INITIATE WO to have counter repaired.
C. WHEN counter is repaired, THEN
- 1. ENSURE Shutdown Bank C fully INSERTED and
- 2. RETURN to beginning of this step.
N
[25] WITHDRAW Shutdown Bank C to the FULLY WITHDRAW
/
position using [HS-85-5111]. CV 1st
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev34 Page 49 of 80 Unit________________ Date 6.3 Manual Operation of Rod Control System Below 15 Percent Power (Continued)
[26] PLACE [HS-85-51101, Rod Control Mode Selector to the SBD position. /
1st CV
[27] VERIFY Rod Speed Indicator [SI-4121, indicates 0 Steps/minute.
1st CV NOTE The following failures will render the rod control system incapable of automatic and I or manual motion without any annunciation or indication: 1) Hand switch failure; 2) relay failure, and
- 3) simultaneous failure of both lOOv DC power supplies (PS3 and PS6).
[28] ENSURE Shutdown Bank D demand position counters operational by performing the following: [C.2}
[a] BUMP [HS-85-5111], Rod Control Switch to withdraw Shutdown Bank D one full step. /
1st CV
[b] CHECK group demand position counter advances properly. LI
[c] BUMP [HS-85-511j] to withdraw Shutdown Bank D a second full step. /
1st CV
[dJ VERIFY group demand position counter advanced properly.
[e] IF group demand position counters do NOT advance properly, THEN A. STOP rod withdrawal. LI B. INITIATE WO to have counter repaired. LI C. WHEN counter is repaired, THEN
- 1. ENSURE Shutdown Bank D fully INSERTED and
- 2. RETURN to beginning of this step.
[29] WITHDRAW Shutdown Bank D to the FULLY WITHDRAWN
/
position using [HS-85-5111].
1st CV
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 34 Page 50 of 80 Unit________________ Date__________
6.3 Manual Operation of Rod Control System Below 15 Percent Power (Continued)
NOTE Remainder of this section performed in conjunction with 0-GO-2 or 0-RT-NUC-000-003.0.
[30] PLACE [HS-85-5110], Rod Control Mode Selector to the MANUAL position. I 1st cv
[31] VERIFY Rod Speed Indicator [SI-412], indicates 48 Steps/minute. /
1st cv NOTE The following failures will render the rod control system incapable of automatic and / or manual motion without any annunciation or indication: 1) Hand switch failure; 2) relay failure, and
- 3) simultaneous failure of both 1 OOv DC power supplies (PS3 and PS6).
[32] ENSURE Control Bank A demand position counters operational by performing the following: [C.2]
[a] BUMP [HS-85-5111], Rod Control Switch to withdraw Control Bank A one-half step at a time, for one fufl step.
1st cv
[bj CHECK group demand position counters advance properly. LI
[cj BUMP [HS-85-51 11] to withdraw Control Bank A one-half step at a time, for the second full step. /
1st cv
[d] VERIFY group demand position counters advance properly.
[e] IF group demand position counters do NOT advance properly, THEN A. STOP rod withdrawal.
B. INITIATE WO to have counter repaired.
C. WHEN counter is repaired, THEN
- 1. ENSURE Control Bank A fully INSERTED and LI
- 2. RETURN to beginning of this step.
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 34 Page 51 of8O Unit________________ Date 6.3 Manual Operation of Rod Control System Below 15 Percent Power (Continued)
[33] CONTINUE withdrawal of Control Bank A using [HS-85-51 11],
Rod Control Switch to 128 steps or next doubling.
NOTE When Control Bank A is above 20 steps, alarm FULL LENGTH RODS AT BOTTOM light on [XA-55-4B]
should clear. When Control Bank A gets above 20 steps and rods are driven back in, the alarm will come back in. When Control Banks B, C, and D get above 35 steps, then drop below 20 steps, the alarm will come back in.
[34] WHEN Control Bank A is above 20 steps, THEN ENSURE Window 28 (D-7), FULL LENGTH RODS RODS AT BOTTOM alarm on panel [XA-55-4B]
CLEARS.
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 34 Page 52 of 80 Unit________________ Date__________
6.3 Manual Operation of Rod Control System Below 15 Percent Power (Continued)
CAUTION When Control Bank A is reaches 128 steps, Control Bank B should begin to move. Each successive bank should begin to move when the previous bank reaches 128 steps.
[35] WHEN Control Bank A is withdrawn to 128 steps, THEN ENSURE Control Bank B demand position counters operational by performing the following: [C.2]
[a] BUMP [HS-85-51111, Rod Control Switch to withdraw Control Bank B one-half step at a time, for one full step.
1st CV
[b] CHECK group demand position counters advance properly.
[cj BUMP [HS-85-5111) to withdraw Control Bank B one-half step at a time, for the second full step.
1st cv
[d] VERIFY group demand position counters advance properly.
[e] IF group demand position counters do NOT advance properly, THEN A. STOP rod withdrawal.
B. INITIATE WO to have counter repaired. U C. WHEN counter is repaired, THEN
- 1. ENSURE Control Bank B fully INSERTED and
- 2. RETURN to beginning of this step.
[36] CONTINUE withdrawal of Control Bank B using [HS-85-5111]
to 128 steps or next doubling.
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev34 Page 53 of 80 Unit________________ Date__________
6.3 Manual Operation of Rod Control System Below 15 Percent Power (Continued)
[37] WHEN Control Bank B is withdrawn to 128 steps, THEN ENSURE Control Bank C demand position counters operational by performing the following: [C.2]
[a] BUMP [HS-85-5111], Rod Control Switch to withdraw Control Bank C one-half step at a time, for one full step. /
1st CV
[b] CHECK group demand position counters advance properly. LI
[ci BUMP [HS-85-51 11] to withdraw Control Bank C one-half step at a time, for the second full step. /
1st CV
[d] VERIFY group demand position counters advance properly.
[ej IF group demand position counters do NOT advance properly, THEN A. STOP rod withdrawal. LI B. INITIATE WO to have counter repaired.
C. WHEN counter is repaired, THEN
- 1. ENSURE Control Bank C fully INSERTED and
- 2. RETURN to beginning of this step. LI
[38] CONTINUE withdrawal of Control Bank C using [HS-85-51111 to 128 steps or next doubling.
[39] WHEN Control Bank C is 110 Steps, THEN ENSURE Window 14 (B-7), ROD CONTROL BANKS LIMIT LOW-LOW alarm on panel [XA-55-4B]
CLEARS.
SQN CONTROL ROD DRIVE SYSTEM O-SO-85-1 1,2 Rev34 Page 54 of8O Unit________________ Date__________
6.3 Manual Operation of Rod Control System Below 15 Percent Power (Continued)
[40] WHEN Control Bank C is 120 steps, THEN ENSURE Window 7 (A-7), ROD CONTROL BANKS LIMIT LOW alarm on panel [XA-55-4B1 CLEARS.
[41] WHEN Control Bank C is withdrawn to 128 steps, THEN ENSURE Control Bank D demand position counters operational by performing the following: [C.2]
[a] BUMP [HS-85-5111], Rod Control Switch to withdraw Control Bank D one-half step at a time, for one full step.
1st CV
[b] CHECK group demand position counters advance properly.
[c] BUMP [HS-85-51111 to withdraw Control Bank D one-half step at a time, for the second full step. /
1st CV
[d] VERIFY group demand position counters advance properly.
[e] IF group demand position counters do NOT advance properly, THEN A. STOP rod withdrawal.
B. INITIATE WO to have counter repaired.
C. WHEN counter is repaired, THEN
- 1. ENSURE Control Bank D fully INSERTED and
- 2. RETURN to beginning of this step.
[42] CONTINUE withdrawal of Control Bank D using [HS-85-5111]
to next doubling or criticality.
End of Section 6.3
Sequoyah Nuclear Plant Technical Instruction Ti-28 CURVE BOOK Revision 0244 Quality Related Level of Use: Reference Use Effective Date: 06-09-2010 Responsible Organization: SNE, System Eng - NSSS Prepared By: Marion Rankin Approved By: Scott Hunnewell
SQN CONTROL ROD FULLY WITHDRAWN 11-28 Att6 Unit C POSITIONS Effective Date: 11-20-2009 Pagelof2 This Attachment contains the axial repositioning schemes for the Unit 1 and Unit 2 RCCA fully withdrawn positions and the bank overlap switch settings for the various fully withdrawn positions.
Fully withdrawn position for control rod banks shall be in a range of 225-231 steps in accordance with the COLR.
NOTE 92 days The ARO step withdrawn position is set before startup of each cycle and every vity Control thereafter in conjunction with the performance of 0-Sl-OPS-085-01 1.0 Reacti Systems Moveable Control Assemblies.
Unit I ARO Steps Withdrawn Cycle 17 Cycle 18 Cycle 19 Startup Date Spring 2009 FaIl 2010 Spring 2012 1st Period 230 225 230 2nd Period 228 226 228 3rd Period 226 228 226 4th Period 225 230 225 5th Period 228 228 228 6th Period 230 225 230 Unit2 ARO Steps Withdrawn Cycle 17 Cycle 18 Cycle 19 Startup Date Fall 2009 Spring 201 1 Winter 2012 1st Period 230 228 226 2nd Period 228 227 228 3rd Period 227 226 230 4th Period 226 225 227 5th Period 225 228 226 6th Period 226 230 225
CONTROL ROD FULLY WITHDRAWN TI-28 Att.6 SQN Effective Date: 11-20-2009 Unit 0 POSITIONS Page 2 of 2 NOTES Solid State Rod Control System, Logic
- 1) Switch setting changes must be made to the Cabinet, bank overlap switches.
ging to a new full-out position.
- 2) Si through S6 must be changed when chan IP FULL OUT POSITION SWITCH SETTING FOR 128 STEP TIP-TO-T S2 S3 S4 S5 S6 Si 222 256 350 384 478 222 128 223 256 351 384 479 223 128 224 256 352 384 480 224 128 225 256 353 384 481 225 128 226 256 354 384 482 226 128 227 256 355 384 483 227 128 228 256 356 384 484 228 128 229 256 357 384 485 229 128 230 256 358 384 486 230 128 231 256 359 384 487 231 128 S3 (2 x Si)
Si = Tip-to-Tip; S2 = desired full out position; =
S6 (Si + S4)
S4 = (Si + S2); S5 = (3 x Si);
will be to maintain a 128 step Tip-to-Tip The effect of the switch setting changes will ple, during withdrawal, the next bank distance between control banks. For exam On being withdrawn reaches 128 steps.
start moving in overlap when the bank start ing to move ld be true with the next bank control bank insertion, the reverse wou with drawn is inserted 128 stps from the fully in overlap when the bank being moved position.
JPM Sim B-i Page 1 of 1 Rev. 0 SEQUOYAH NUCLEAR PLANT September 2010 NRC Exam Simulator B-I Refill the #3 CLA to Within Normal Operating Range
JPM Sim B-i Page 2 of 2 Rev. 0 ROISRO JOB PERFORMANCE MEASURE Task: Refill the #3 CLA to Within Normal Operating Range Task#: (RO) 0060050101 Task Standard: Cold Leg Accumulator #3 level has been returned to within normal operating range of >7615 gal but <7955 gal Time Critical Task: YES: NO: X K/A ReferencelRatings: 006K6.02 (3.4/3.9) 006A1 .07 (3.3/3.6) 006A1 .13 (3.5/3.7)
Method of Testing:
Simulated Performance: Actual Performance: X Evaluation Method:
Simulator X In-Plant Classroom Main Control Room Mock-up Performer:
Trainee Name Evaluator: I Name I Signature DATE Performance Rating: SAT: UNSAT:
Validation Time: 20 mins Total Time:
Performance Time: Start Time: Finish Time:
COMMENTS
JPM Sim B-i Page 3 of 3 Rev. 0 SPECIAL INSTRUCTIONS TO EVALUATOR:
- 1. Critical steps are identified in step SAT/UNSAT column by bold print Critical Step.
- 2. Any UNSAT requires comments
- 3. Initialize in IC #189.
PTL lA-A SI Pump and place HO tag.
Insert malfunction S104C @100% to drain level in the #3 CLA to until the low level alarm comes in; then DELETE the MF. [Will take 5-8 minI Both 1-XA-55-6D C-I and C-2 annunicators should be lit
- 5. Ensure operator performs the following required actions for 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.
Tools/Equ ipmentlProcedures Needed:
l-SO-63-1, section 8.1
References:
L 1. I -S0-63-l Reference Title Rev Nj Cold Leg Injection Accumulators 47
JPM Sim B-i Page 4 of 4 Rev. 0 READ TO OPERATOR DIRECTIONS TO TRAINEE:
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 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 I isatlOO%RTP.
- 2. #3 CLA sample valve did not properly close at the completion of sampling. This resulted in
- 3 CLA inventory draining to the current condition.
- 3. The sample line has been isolated.
- 4. All power and valve checklists are complete with NO deviations.
- 5. The SI pumps are aligned in the normal standby configuration.
- 7. The initial level in #3 CLA per SI-OPS-000.002.O was 7855 gallons and pressure 645 psig.
INITIATING CUES:
I. The US directs you to restore the #3 CLA to within required limits per the appropriate procedure.
JPM Sim B-i Page 5of5 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT EVALUATOR NOTE: O-SO-63-1, Cold Leg Injection Accumulators Section 8.1, Adding Makeup Water to Cold Leg Accumulators contains the procedural steps for_performing_the_following_actions_starting_at_step_1.
STEP 1.: Operator determines and locates correct procedure and section SAT to be used or Evaluator provides selected procedures andlor UNSAT section(s) as necessary.
STANDARD: Operator obtains a copy of 1-S0-63-1 section 8.1 and reviews the following CAUTIONS and NOTES prior to Step I COMMENTS:
CAUTION 1: Operability limits for CLA level and pressure are 761 5-7955 gal and 624-668 psig.
CAUTION 2: Radiochemical Laboratory obtaining sample of Accumulators for boron concentration analysis while draining or filling in progress may result in invalid calculation.
NOTE 1: Steps [12) through [15] may be performed in any order to allow making up to accumulators in the desired order. However, substeps associated with making up to each accumulator shall be performed in the order listed.
NOTE 2: Limiting the fill level to 7916 gallons, during an initial fill following an outage, will alleviate the need for MIG to perform a purge of the level instrument upper leg due to borated water intrusion.
NOTE 3: Limiting the fill level to 7956 gallons, during normal operation, will alleviate the need for MIG to perform a purge of the level instrument upper leg due to borated water intrusion.
STEP 2.: Section 8.1 Steps I 5 previously verified according to Initial SAT Conditions UNSAT STANDARD: Operator ensures power and valve checklists, SI pumps configuration and RWST boron concentration from initial conditions COMMENTS:
JPM Sim B-I Page 6 of 6 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 3.: 161 IF required due to RHR discharge header pressurization, THEN SAT VENT RHR discharge piping fully using 1-SO-63-5. UNSAT CUE: IF necessary, as US, venting is not required at this time.
STANDARD: Operator checks RHR Discharge Header pressure on 1-Pl 13 & 26 on 1-M-6, verifies pressure is low and N/As this step.
COMMENTS:
STEP 4.: [7] ENSURE [1-FCV-63-84] SIS Test Line to HUT is CLOSED UNSAT STANDARD: Operator ensures 1-FCV-63-84 is closed via green light ON.
COMMENTS:
STEP 5.: [8] IF in Mode 4, 5, or 6 (with the vessel head on), THEN ENSURE SAT the following valves are CLOSED with power removed and UNSAT tagged under a hold order to comply with LCO 3.4.12:
STANDARD: Operator will verify unit is mode 1 and N/A this step.
COMMENTS:
JPM Sim B-I Page 7 of 7 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 6.: [9] ENSURE the following valves are OPEN: (located on 1-M-6) SAT 1-FCV-63-71, SIS Test Line to HUT UNSAT 1-FCV-63-23 CL Accum Makeup From SI Pumps STANDARD: Operator opens 1-FCV-63-71 and 23 via 1-HS-63-71A and 1-HS- Critical Step 63-23A and verifies the valves come open by red light LIT.
CRITICAL Step: to establish fill flowpath to the CLA common fill line COMMENTS:
Operator reviews CAUTIONS prior to Step 10:
CAUTION 1: To prevent premature bearing wear, SI pumps should be operated for a minimum of 20 minutes each time a pump is started.
CAUTION 2 In Modes 1-3, closure of 1-FCV-63-152 requires entering LCO 3.5.2.
STEP 7.: [10] IF lA-A SI pump is to be used to add makeup water to SAT Accumulators, THEN PERFORM the following:
UNSAT STANDARD: Operator identifies IA-A SI Pump tagged and marks step N/A; AND Proceeds to CAUTIONS prior to step 11 COMMENTS:
CAUTION 1: SI pump I B-B CANNOT be used to fill CLA in Mode 3 with RCS pressure <1700 psig due to having to close 1-FCV-63-22 (LCO 3.0.3).
CAUTION 2: To prevent premature bearing wear, SI pumps should be operated for a minimum of 20 minutes each time a pump is started.
JPM Sim B-i Page 8 of 8 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 8.: [11] IF I B-B SI pump is to be used to add makeup water to SAT Accumulators, THEN PERFORM the following:
UNSAT
[a] IF Unit 1 is in Mode 3, THEN...
[b] IF in Mode 4, 5, or 6 (with the vessel head on),
THEN STANDARD: Operator will verify unit is mode I and N/A subsequent substeps through 11 .b.2; proceeds to step II .c COMMENTS:
STEP 9.: [11.c] ENSURE the following valves are OPEN: SAT 1-FCV-63-3 SI Pump Recirc to RWST Common UNSAT 1-FCV-63-175 SI Pump lB Recircto RWST 1-FCV-63-152 SI Pump IA CL Injection Isolation 1-FCV-63-153 SI Pump lB CL Injection Isolation 1-FCV-63-48 SI Pump lB Suction Isolation STANDARD: Operator verifies normally open valves are open via I -M-6 handswitches 1-HS-63-3, 175, 152, 153, and 48 indicated by RED light LIT.
COMMENTS:
STEP 10 [d] START lB-B SI pump using [1-HS-63-15A] SAT UNSAT STANDARD: Operator starts the lB-B SI pump by placing 1-HS-63-15A to the START and verifying RED light ON, amps indicated on 1-EI 16A, and pressure 1-PI-63-19 stable Critical Step CRITICAL Step: this will provide the motive force for CLA fill.
COMMENTS:
JPM Sim B-I Page 9of9 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP II.: [e] WHEN SI pump has run for at least 5 minutes THEN proceed SAT with this procedure.
UNSAT CUE: Five minutes has elapsed STANDARD: Operator ensures pump has run 5 minutes prior to continuing adhering to CAUTION prior to step 11 COMMENTS:
STEP 12.: [12] & [13] Filling #s 1 & 2 CLAs; SAT STANDARD: Operator acknowledges and marks N/A; proceeds to U NSAT CAUTIONS & NOTE prior to step 14 COMMENTS:
Operator reviews CAUTIONS & NOTE prior to Step 14:
CAUTION 1: Do not cross connect the Cold Leg Accumulators CAUTION 2 Reducing level in the RWST to <370,000 gallons while in mode 1-4 will result in RWST being inoperable.
NOTE: Operability band for CLA level is 761 5-7955 gal.
STEP 13.: [14] IF adding makeup water to Accumulator 3, THEN SAT PERFORM the following:
UNSAT
[a] Ensure the following valves are CLOSED:
1-FCV-63-1 15 No.1 CL Accum Water Makeup 1-FCV-63-95 No.2 CL Accum Water Makeup 1-FCV-63-70 No.4 CL Accum Water Makeup STANDARD: Operator verifies 1 -M-6 handswitches I -HS-63-1 I 5A,63-95A and 63-70A in the CLOSE position with GREEN light LIT and RED light out.
COMMENTS:
JPM Sim B-i Page 10 of 10 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 14 [14 b] OPEN [1-FCV43-77] No 3 CL Accum Water Makeup to SAT begin filling No. 3 Accumulator.
UNSAT 1-FCV-63-70 No. 4 CL Accum Water Makeup STANDARD: Operator positions 1-M-6 handswitch 1-HS-63-77A to OPEN Critical Step position and verifies valve opens indicated by RED light LIT.
CRITICAL Step: to establish fill flowpath to #3 CLA COMMENTS:
Operator reviews CAUTION & NOTE prior to proceeding:
CAUTION: Excessive opening of FCV-63-65 will cause accumulator pressure to decrease rapidly to below the operability limit.
NOTE: 1-HIC-63-65 may be adjusted as desired to control the rate of pressure decrease. Approximately 5-10% open is recommended for pressure adjustments_within_the_normal_band.
STEP 15. [ci IF desired to vent accumulator to maintain pressure within SAT limits, THEN. -
UNSAT STANDARD: Operator acknowledges step and continues while continuing to monitor Accumulator gas pressure during fill.
COMMENTS:
Operator reviews CAUTION prior to proceeding:
CAUTION: IF CLA Fill valve [1-FCV-63-77] fails to completely close, the CLA may over-fill and over-pressurize. Step [16] may be performed out of_sequence_if_necessary_to_isolate_fill_line.
JPM Sim B-I Page 11 of Ii Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 16.: [14.d] WHEN No 3 Aóóirnuitr incrses tdesiréd 1et SAT THEN ENSURE the following valves CLOSED UNSAT
[1] [t-FCV-63-77]
[2] [1-FCV-63-87]
[3] [1-FCV-63-65] Critical Step
[4] INDEPENDENTLY VERIFY the following:
- 1. [1-FCV-63-77] CLOSED
- 2. [1-FCV-63-871 CLOSED
- 3. [1-FCV-63-65] CLOSED CUE: Another operator will perform independent verification, prompt operator to continue, if necessary.
STANDARD: Operator positions I -M-6 handswitches I -HS-63-77A, 87 and 65 to CLOSE position and verifies valves close as indicated by GREEN light LIT.
CRITICAL Step: to stop #3 CLA fill COMMENTS:
Operator reviews NOTE prior to proceeding:
NOTE: Filling the upper instrument line with borated water requires that the line be purged with DI water to achieve proper level instrument accuracy.
STEP 17.: [e] IF accumulator was filled to greater than 7956 gallons (7916 SAT gallons post calibration fill), THEN NOTIFY MIG to purge the UNSAT upper instrument line with Dl water.
STANDARD: Operator should mark step N/A.
COMMENTS:
Operator reviews CAUTION prior to proceeding:
CAUTION: Do not fill any other accumulators until No. 3 accumulator pressure and level are within the operability limits of 624-668 psig and 7615-7955 gallons.
JPM Sim B-i Page 12 of 12 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 18.: [14.f) VERIFY No. 3 accumulator pressure and level are within SAT Tech Spec limits.
UNSAT STANDARD: Operator verifies level and pressure within limits by observing readings: -
Critical Step 1 -PIS-63-88 & 86 (>624 psjg but<668 psig),
B CRITICAL Step: verifies Tech Spec compliance COMMENTS:
STEP 19.: [g]VERIFY ACCUMULATOR 3 PRESSURE HI-LOW and ACCUMULATOR 3 LEVEL HI-LOW alarms are CLEAR.
UNSAT (1-XA-55-6D windows C-I and C-2)
STANDARD: Operator verifies alarm windows are DARK (or will reset).
COMMENTS:
STEP 20.: [15] Filling #4 CLA... SAT UNSAT STANDARD: Operator acknowledges and marks N/A; proceeds to CAUTIONS & NOTE prior to step 16 COMMENTS:
JPM Sim B-i Page 13 of 13 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 21.: [16] CLOSE the following valves: SAT 1-FCV-63-71 SIS Test Line to HUT UNSAT 1-FCV-63-23 CL Accum Makeup From SI Pumps STANDARD: Operator positions 1-M-6 1-HS-63-71A and 1-HS-63-23A to CLOSE and verifies 1-FCV-63-71 and 23 go closed by GREEN light only LIT.
COMMENTS:
STEP 22.: [17] IF depressurizing RHR is required before SIP minimum run SAT time is complete, THEN DEPRESSURIZE RHR fully using 1-SO-UNSAT 63-5 in parallel with steps [18] through [22].
Cue: CR0 will perform SI Pump discharge piping depressurization.
STANDARD: Operator checks RHR Discharge Header pressure on LT-74-1 3
& 26 and verifies pressure is low and N/As this step.
COMMENTS:
STEP 23.: [18] ENSURE SI pump has run for a minimum of 20 minutes. SAT UNSAT Cue: Pump has been running 20 minutes.
STANDARD: Operator ensures SI pump I B-B has run 20 minutes prior to stopping pump. (to prevent premature bearing wear)
COMMENTS:
JPM Sim B-i Page 14 of 14 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 24.: [19] STOP lB-B SI pump with 1-HS-63-15A. SAT UNSAT STANDARD: Operator places 1 -HS-63-1 5A to the stop position, verifies Green light on, amps and pressure decrease to zero (or to original pressure prior to pump start).
COMMENTS:
STEP 25 [20] IF Unit I is in Modes 1-3, THEN SAT ENSJRE:$L Pump in IHO UNSAT S-6$1A.iB-SSi puri-fS-63-15A.
Critical Step STANDARD: Operator places 1-HS-63-15A to the A-AUTO, (center pull-out) position.
CRITICAL Step: step ensures pump is placed in normal standby state and ensures shutdown and termination of the fill process.
This completes the JPM.
STANDARD: End of JPM
READ TO OPERATOR DIRECTIONS TO TRAINEE:
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 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 I isatlOO%RTP.
- 2. #3 CLA sample valve did not properly close at the completion of sampling. This resulted in
- 3 CLA inventory draining to the current condition.
- 3. The sample line has been isolated.
- 4. All power and valve checklists are complete with NO deviations.
- 5. The SI pumps are aligned in the normal standby configuration.
- 7. The initial level in #3 CLA per Sl-OPS-000.002.O was 7855 gallons and pressure 645 psig.
INITIATING CUES:
- 1. The US directs you to restore the #3 CLA to within required limits per the appropriate procedure.
READ TO OPERATOR DIRECTIONS TO TRAINEE:
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 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 I isatlOO%RTP.
- 2. #3 CLA sample valve did not properly close at the completion of sampling. This resulted in
- 3 CLA inventory draining to the current condition.
- 3. The sample line has been isolated.
- 4. All power and valve checklists are complete with NO deviations.
- 5. The SI pumps are aligned in the normal standby configuration.
- 7. The initial level in #3 CLA per Sl-OPS-000.002.O was 7855 gallons and pressure 645 psig.
INITIATING CUES:
I. The US directs you to restore the #3 CLA to within required limits per the appropriate procedure.
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT SYSTEM OPERATING INSTRUCTION 1-S 0-63-1 COLD LEG INJECTION ACCUMULATORS Revision 47 QUALiTY RELATED PREPARED/PROOFREAD BY: LOYD HODGES RESPONSIBLE ORGANIZATION: OPERATIONS APPROVED BY: J. K. WILKES EFFECTIVE DATE:03/09/2009 LEVEL OF USE: CONTINUOUS USE 0 Ic REVISION DESCRIPTION:
Added step 5.1[1j to notify System Engineer that CLAs are about to be filled and VT-2 test may be required (PCR07001781). Added notes and steps to check nitrogen pressure locally in sections 8.3.1, 8.3.2, 8.3.3, and 8.3.4 (PCR08000053). Added caution to Appendix A, B, C, and D prior to step 7 about limiting MOV starts (PCRO8001 141).
Added P&L note M to require Void Volume Evaluation any time a segment of the ECCS system is drained (PCR08001174). Added note and step to all sections of 5.1, 5.2, and 5.3 about system operability and evaluation of void volume (PCRO8001 174). Added Caution Section 8.1 preceding steps [12}[dj[1}, [13][d]{1], [14j[d][1], and [15][d][1]
cautioning about CLA over-fill and over-pressurization (PCRO90001I2).Corrected steps referenced in Section 8.1 Note 1 from 13-thru-16 to 12-thru-15 (PCRO9000112).
SQN COLD LEG INJECTION 1-50-63-1 i ACCUMULATORS Rev: 47 Page 6 of 185 3.0 PRECAUTIONS AND LIMITATIONS A. Venting large volumes of nitrogen from the cold leg accumulators could displace oxygen and create a hazardous atmosphere in the No. 4 Accumulator Room.
Prior to venting a significant volume of nitrogen from the cold leg accumulators, the No. 4 Accumulator Room shall be evacuated or continuous oxygen monitoring shall be established. If evacuated, a safe atmosphere should be verified prior to restoring access.
B. Cold Leg Accumulator (CLA) room temperatures must be maintained equal to or greater than 60°F whenever the CLAs are pressurized (not open to atmosphere).
C. Tech Spec operability limit (including instrument uncertainty) for CLA borated water volume is between 7615 gallons and 7960, but Unit 1 CLA level indicators will indicate a maximum of 7956 gallons. Therefore, the CLA operability limit has been reduced to between 7615 gallons and 7955 gallons.
D. Tech Spec operability limit (including instrument uncertainty) for CLA nitrogen pressure is between 624 psig and 668 psig.
E. Do not change relief valve setpoints to allow more rapid pressurization. If Pressurization rate is inadequate, the SM should be contacted immediately for resolution.
F. Cross connection of the nitrogen or water supplies of any Cold Leg Accumulators will make the cross-tied accumulators inoperable. Do NOT cross-tie accumulators in Modes 1-3. [C.2]
G. Do not adjust pressure control valves 0-PCV-77-253 or 0-PCV-77-254.
Maintenance should be contacted for assistance if valves require adjustment.
H. To prevent premature bearing wear, SI pumps should be operated for a minimum of 20 minutes each time a pump is started.
I. To prevent brittle fracture when adding nitrogen to a CLA with accumulator pressure less than 600 psig, then the piping temperature between the nitrogen supply regulator (0-PCV-77-253 or -254) and the containment isolation valve (1-FCV-63-64) should be monitored and maintained greater than 40°F. If temperature approaches 40°F, nitrogen fill should be stopped or the flow rate reduced to maintain piping temperature greater than 40°F.
J. Anytime accumulators are filled above 7956 gallons, the upper instrument level tap will need to be purged by Instrument Maintenance Group.
K. Limiting accumulator fill to 7916 gallons during the initial fill following an outage, prevents flooding of the upper instrument level leg. After calibration the lower instrument leg is unborated water and level instrument inaccuracies result.
SQN COLD LEG INJECTION 1-SO-63-1 ACCUMULATORS Rev: 47 Page 7 of 185 3.0 PRECAUTIONS AND LIMITATIONS (continued)
L. In Modes 4, 5, and 6 (with vessel head on), CLA valves are required to be closed with motor breakers locked in OFF position unless CLA pressure is less than the maximum RCS pressure allowed by PTLR for current cold leg temperature. (LCO 3.4.12)
M. Engineering evaluation for air removal is required any time a segment of the ECCS system is drained. Ultrasonic testing may be required in order to validate air removal or to quantify any void volume that remains. This evaluation should consider whether or not the existing vent valves can completely remove all air pockets from the piping, and if not, the effect on the system of the remaining void in concert with other existing voids. During outages, the fill and vent can be verified by the subsequent performance of full flow testing. Evaluation of procedure sections can be performed in advance of actual use.
END OF SECITON 3.0
SQN COLD LEG INJECTION 1-SO-63-1 ACCUMULATORS Rev: 47 Page 8 of 185 Date 1cy PREREQUISITE ACTIONS NOTE Throughout this instruction where an IFITHEN statement exists, the step should be N/A if condition does not exist.
ENSURE the Instruction to be used is a copy of the effective version.
ENSURE Precautions and Limitations, Section 3.0, has been reviewed.
ENSURE RWST water volume between 370,000 and 375,000 gallons in modes 1-4. (Reference TS 3.5.5)
IF segment(s) of ECCS system will be refilled following draining, THEN NOTIFY System Engineering to initiate system void volume evaluation. N I IF performing Section 5.1, THEN ENSURE Unit 1 RWST is NOT on recirculation.
jj ENSURE each performer documents their name and initials:
Print Name Initials INDICATE below which performance section of this Instruction will be used and the reason for this performance:
D 5.0 STARTUP/STANDBY READINESS 8.0 INFREQUENT OPERATION REASON: -rL CL END OF SECTION 4M
SQN COLD LEG INJECTION 1-SO-63-1 ACCUMULATORS Rev: 47 Page 89 of 185 Date 8.0 INFREQUENT OPERATION 8.1 Adding Makeup Water to the Cold Leg Accumulators CAUTION I Operability limits for CLA level and pressure are 761 5-7955 gal and 624-668 psig.
CAUTION 2 Radiochemical Laboratory obtaining sample of Accumulators for boron concentration analysis while draining or filling in progress may result in invalid calculation. [CI]
NOTE I Steps [12] through [15] may be performed in any order to allow making up to accumulators in the desired order. However, substeps associated with making up to each accumulator shall be performed in the order listed.
NOTE 2 Limiting the fill level to 7916 gallons, during an initial fill following an outage, will alleviate the need for MIG to perform a purge of the level instrument upper leg due to borated water intrusion.
NOTE 3 Limiting the fill level to 7956 gallons, during normal operation, will alleviate the need for M1G to perform a purge of the level instrument upper leg due to borated water intrusion.
[I] ENSURE Power Checklist 1-63-1.01 complete.
[2] ENSURE Valve Checklist 1-63-1.06 complete.
[3] ENSURE Valve Checklist 1-63-1.07 complete.
[4] ENSURE at least one SI Pump operable or available.
[5] ENSURE RWST boron concentration between 2500 and 2700 ppm per Radiochemical Laboratory results.
SQN COLD LEG INJECTION 1-SO-63-1 ACCUMULATORS Rev: 47 Page 90 of 185 Date 8.1 Adding Makeup Water to the Cold Leg Accumulators (Continued)
[6] IF required due to RHR discharge header pressurization, THEN VENT RHR discharge piping fully using 1-SO-63-5.
[7] ENSURE [1-FCV-63-84] SIS Test Line to HUT is CLOSED.
[8] IF in Mode 4, 5, or 6 (with the vessel head on),
THEN ENSURE the following valves are CLOSED with power removed and tagged under a hold order to comply with LCO 3.4.12:
VALVE NO. FUNCTION 1-FCV-63-69 Check valve test isolation 1-FCV-63-79 Check valve test isolation 1-PCV-63-97 Check valve test isolation I -FCV-63-1 17 Check valve test isolation 1-PCV-63-163 Check valve test isolation 1-FCV-63-164 Check valve test isolation 1-PCV-63-165 Check valve test isolation 1-PC V-63-166 Check valve test isolation 1-FCV-63-174 CCP to CL Accumulator Fill 1-FCV-63-68 Check valve test isolation 1-FCV-63-116 Check valve test isolation 1-FCV-63-96 Check valve test isolation 1-PCV-63-78 Check valve test isolation 1-FCV-63-167 Check valve test isolation 1-FCV-63-24 Check valve test isolation 1-FCV-63-121 Check valve test isolation 1-FCV-63-21 Check valve test isolation 1 -FCV-63-1 1 1 Check valve test isolation I -FCV-63-1 12 Check valve test isolation 1-FCV-63-158 Check valve test isolation
COLD LEG INJECTION 1-SO-63-1 SQN ACCUMULATORS Rev: 47 Page 91 of 185 Date mulators (Continued) 8.1 Adding Makeup Water to the Cold Leg Accu
[9] ENSURE the following valves are OPEN:
FUNCTION INITIALS VALVE NO.
1-FCV-63-71 SIS Test Line to HUT 1-FCV-63-23 CL Accum Makeup From SI Pumps ld be operated CAUTION I To prevent premature bearing wear, SI pumps shou started.
for a minimum of 20 minutes each time a pump is ing LCO 3.5.2.
CAUTION 2 In Modes 1-3, closure of 1-FCV-63-152 requires enter
[10] IF lA-A SI pump is to be used to add makeup water to Accumulators, THEN PERFORM the following:
[a] IF RCS pressure <1700 psig, THEN ENSURE the following valves are CLOSED:
FUNCTION INITIALS VALVE NO.
1-FCV-63-156 SI Pump 1A HL Injection Isolation 1-FCV-63-152 SI Pump 1A CL Injection Isolation
[b) IF in Mode 4, 5, or 6 (with the vessel head on),
THEN
- 1. ENSURE the following valves are CLOSED with power removed and tagged under a hold order to comply with LCO 3.4.12:
VALVE NO. FUNCTION l-FCV-63-22 SI Pumps CL Injection 1-FCV-63-156 SI Pump 1A HL Injection Isolation l-FCV-63-157 SI Pump lB HL Injection Isolation
- 2. ENSURE [1-VLV-63-645] leakoff isolation LOCKED CLOSED and tagged.
SQN COLD LEG INJECTION 1-SO-63-1 ACCUMULATORS Rev: 47 i Page 92 of 185 Date 8.1 Adding Makeup Water to the Cold Leg Accumulators (Continued)
[c] ENSURE the following valves are OPEN:
VALVE NO. FUNCTION INITIALS 1-FCV-63-3 SI Pump Recircto RWST 1-FCV-63-4 SI Pump IA Recirc to RWST 1-FCV-63-47 SI Pump IA Suction Isolation
[dJ START lA-A SI pump using [1-HS-63-IOAI.
[e] WHEN SI pump has run for at least 5 minutes THEN proceed with this procedure.
CAUTION I SI pump lB-B CANNOT be used to fill CLA in Mode 3 with RCS pressure <1700 psig due to having to close 1-FCV-63-22 (LCO 3.0.3).
CAUTION 2 To prevent premature bearing wear, SI pumps should be operated for a minimum of 20 minutes each time a pump is started.
[11] IF lB-B SI pump is to be used to add makeup water to Accumulators, THEN PERFORM the following:
[a] IF Unit 1 is in Mode 3, THEN VERIFY RCS pressure is >1700 psig.
[b] IF in Mode 4, 5, or 6 (with the vessel head on),
THEN
- 1. ENSURE the following valves are CLOSED with power removed and tagged under a hold order to comply with LCO 3.4.12:
VALVE NO. FUNCTION INITIALS 1-FCV-63-22 SI Pumps CL Injection 1-FCV-63-156 SI Pump IA HL Injection Isolation I 1-FCV-63-157 SI Pump lB HL Injection Isolation
- 2. ENSURE [1-VLV-63-645] Ieakoff isolation LOCKED CLOSED and tagged.
SQN COLD LEG INJECTION 1-SO-63-1 ACCUMULATORS Rev: 47 Page 93 of 185 Date 8.1 Adding Makeup Water to the Cold Leg Accumulators (Continued)
[ci ENSURE the following valves are OPEN:
VALVE NO. FUNCTION [ INITIALS 1-FCV-63-3 SI Pump Recirc to RWST Common 1-FCV-63-175 SI Pump lB Recirc to RWST 1-FCV-63-152 SI Pump 1A CL Injection Isolation l-FCV-63-153 SI Pump lB CL Injection Isolation 1-FCV-63-48 SI Pump lB Suction Isolation
[d] START lB-B SI pump using [1-HS-63-15A].
[e] WHEN SI pump has run for at least 5 minutes THEN proceed with this procedure.
CAUTION I Do not cross connect the Cold Leg Accumulators. [C.2]
CAUTION 2 Reducing level in the RWST to < 370,000 gallons while in mode 1-4 will result in RWST being inoperable.
NOTE Operability band for CLA level is 7615-7955 gal.
[12] IF adding makeup water to Accumulator 1, THEN PERFORM the following:
[a] ENSURE the following valves are CLOSED:
VALVE NO. FUNCTION INITIALS l-FCV-63-95 No. 2 CL Accum Water Makeup l-FCV-63-77 No. 3 CL Accum Water Makeup 1-FCV-63-70 No. 4 CL Accum Water Makeup
[b] OPEN [1-FCV-63-1151 No. 1 CL Accum Water Makeup to begin filling No. 1 Accumulator.
SQN COLD LEG INJECTION 1-SO-63-1 ACCUMULATORS Rev: 47 i
Page 94 of 185 Date 8.1 Adding Makeup Water to the Cold Leg Accumulators (Continued)
CAUTION Excessive opening of FCV-63-65 will cause accumulator pressure to decrease rapidly to below the operability limit.
NOTE 1-HIC-63-65 may be adjusted as desired to control the rate of pressure decrease. Approximately 5-10% open is recommended for pressure adjustments within the normal band.
[C] IF desired to vent accumulator to maintain pressure within limits, THEN
[1] THROTTLE [1-FCV-63-65] CL Accum N2 Header Vent Flow Control.
[2] OPEN [1-FCV-63-127] to vent nitrogen from Accumulator 1.
[3] ADJUST [1-FCV-63-65) as needed to control CLA pressure between 630 and 662 psi 9
CAUTION IF CLA Fill valve [i-FCV-63-1151 fails to completely close, the CLA may over-fill and over-pressurize. Step [16] may be performed out of sequence if necessary to isolate fill line.
[d] WHEN No. 1 Accumulator increases to desired level, THEN ENSURE the following valves are CLOSED:
[1] [1-FCV-63-1151.
[2] [1 -FC V-63-1 271
[3] [1-FCV-63-65]
[4] INDEPENDENTLY VERIFY the following:
- 1. [1-FCV-63-115] CLOSED
- 2. [1-FCV-63-127] CLOSED
- 3. [1-FCV-63-65] CLOSED
SQN COLD LEG INJECTION 1-SO-63-1 ACCUMULATORS Rev: 47 Page 95 of 185 Date 8.1 Adding Makeup Water to the Cold Leg Accumulators (Continued)
NOTE Filling the upper instrument line with borated water requires that the line be purged with DI water to achieve proper level instrument accuracy.
[e] IF accumulator was filled to greater than 7956 gallons (7916 gallons post calibration fill), THEN NOTIFY MIG to purge the upper instrument line with DI water.
CAUTION Do not fill any other accumulators until No. I accumulator pressure and level are within the operability limits of 624-668 psig and 7615-7955 gallons.
[fj VERIFY No. 1 accumulator pressure and level are within Tech Spec limits.
[g] VERIFY ACCUMULATOR 1 PRESSURE HI-LOW and ACCUMULATOR I LEVEL HI-LOW alarms are CLEAR. (1-XA-55-6D windows A-I and A-2)
CAUTION I Do not cross connect the Cold Leg Accumulators. [C.2]
CAUTION 2 Reducing level in the RWST to < 370,000 gallons while in mode 1-4 will result in RWST being inoperable.
NOTE Operability band for CLA level is 7615-7955 gal.
[13] IF adding makeup water to Accumulator 2, THEN PERFORM the following:
[a] ENSURE the following valves are CLOSED:
VALVE NO. FUNCTION 1 -FCV-63-1 15 No. 1 CL Accum Water Makeup I -FCV-63-77 No. 3 CL Accum Water Makeu I -FCV-63-70 No. 4 CL Accum Water Makeup
SQN COLD LEG INJECTION 1-SO-63-1 ACCUMULATORS Rev: 47 Page 96 of 185 Date 8.1 Adding Makeup Water to the Cold Leg Accumulators (Continued)
[b] OPEN [1-FCV-63-95] No. 2 CL Accum Water Makeup to begin filling No. 2 Accumulator.
CAUTION Excessive opening of FCV-63-65 will cause accumulator pressure to decrease rapidly to below the operability limit.
NOTE 1-HIC-63-65 may be adjusted as desired to control the rate of pressure decrease. Approximately 5-10% open is recommended for pressure adjustments within the normal band.
[c] IF desired to vent accumulator to maintain pressure within limits, THEN
[1] THROTTLE [1-FCV-63-65] CLAccum N2 Header Vent Flow Control.
[2] OPEN [1 -FCV-63-1 07] to vent nitrogen from Accumulator 2.
[3) ADJUST [1-FCV-63-65] as needed to control CLA pressure between 630 and 662 psig.
CAUTION IF CLA Fill valve rl-FCV-63-95] fails to completely close, the CLA may over-fill and over-pressurize. Step [16] may be performed out of sequence if necessary to isolate fill line.
[d) WHEN No. 2 Accumulator increases to desired level, THEN ENSURE the following valves CLOSED
[1] [1-FCV-63-95).
[2] [1 -FCV-63-1 07]
[3] [1 -FCV-63-651
[4] INDEPENDENTLY VERIFY the following:
- 1. 11-FCV-63-95]. CLOSED
- 2. [1-FCV-63-107] CLOSED
- 3. [1-FCV-63-65) CLOSED
SQN COLD LEG INJECTION 1-SO-63-1 ACCUMULATORS Rev: 47 Page 97 of 185 Date 8.1 Adding Makeup Water to the Cold Leg Accumulators (Continued)
NOTE Filling the upper instrument line with borated water requires that the line be purged with DI water to achieve proper level instrument accuracy.
[e] IF accumulator was filled to greater than 7956 gallons (7916 gallons post calibration fill), THEN NOTIFY MIG to purge the upper instrument line with Dl water.
CAUTION Do not fill any other accumulators until No. 2 accumulator pressure and level are within the operability limits of 624-668 psig and 761 5-7955 gallons.
[f] VERIFY No. 2 accumulator pressure and level are within Tech Spec limits.
[gj VERIFY ACCUMULATOR 2 PRESSURE HI-LOW and ACCUMULATOR 2 LEVEL HI-LOW alarms are CLEAR. (1-XA-55-6D windows B-i and 8-2)
CAUTION I Do not cross connect the Cold Leg Accumulators. [C.2j CAUTION 2 Reducing level in the RWST to <370,000 gallons while in mode 1-4 will result in RWST being inoperable.
NOTE Operability band for CLA level is 7615-7955 gal.
[14) IF adding makeup water to Accumulator 3, THEN PERFORM the following:
[a) ENSURE the following valves are CLOSED:
VALVE NO. FUNCTION INITIALS 1 -FCV-63-1 15 No. 1 CL Accum Water Makeup i-FCV-63-95 No. 2 CL Accum Water Makeup i-FCV-63-70 No. 4 CL Accum Water Makeup
SQN COLD LEG INJECTION 1-SO-63-1 ACCUMULATORS Rev: 47 Page 98 of 185 Date 8.1 Adding Makeup Water to the Cold Leg Accumulators (Continued)
[b] OPEN [1-FCV-63-77] No. 3 CL Accum Water Makeup to begin filling No. 3 Accumulator.
CAUTION Excessive opening of FCV-63-65 will cause accumulator pressure to decrease rapidly to below the operability limit.
NOTE 1-HIC-63-65 may be adjusted as desired to control the rate of pressure decrease. Approximately 5-10% open is recommended for pressure adjustments within the normal band.
[c] IF desired to vent accumulator to maintain pressure within limits, THEN
[1] THROTTLE [1-FCV-63-65] CL Accum N2 Header Vent Flow Control.
[2] OPEN [1 -FCV-63-871 to vent nitrogen from Accumulator 3.
[3] ADJUST [1-FCV-63-65] as needed to control CLA pressure between 630 and 662 psig.
CAUTION IF CLA Fill valve [1-FCV-63-77] fails to completely close, the CLA may over-fill and over-pressurize. Step [16] may be performed out of sequence if necessary to isolate fill line.
[dl WHEN No. 3 Accumulator increases to desired level, THEN ENSURE the following valves CLOSED
[1] [1 -FCV-63-77].
[2] [1-FCV-63-87]
[3] [1-FCV-63-65]
[4] INDEPENDENTLY VERIFY the following:
- 1. [1-FCV-63-77] CLOSED
- 2. [1-FCV-63-87] CLOSED
- 3. [1-FCV-63-651 CLOSED
SQN COLD LEG INJECTION 1-SO-63-1 ACCUMULATORS Rev: 47 Page 99 of 185 Date 8.1 Adding Makeup Water to the Cold Leg Accumulators (Continued)
NOTE Filling the upper instrument line with borated water requires that the line be purged with Dl water to achieve proper level instrument accuracy.
[e] IF accumulator was filled to greater than 7956 gallons (7916 gallons post calibration fill), THEN NOTIFY MIG to purge the upper instrument line with Dl water.
CAUTION Do not fill any other accumulators until No. 3 accumulator pressure and level are within the operability limits of 624-668 psig and 761 5-7955 gallons.
[f] VERIFY No. 3 accumulator pressure and level are within Tech Spec limits.
[g] VERIFY ACCUMULATOR 3 PRESSURE HI-LOW and ACCUMULATOR 3 LEVEL H 1-LOW alarms are CLEAR. (i-XA-55-6D windows C-i and C-2)
CAUTION I Do not cross connect the Cold Leg Accumulators. [C.2]
CAUTION 2 Reducing level in the RWST to < 370,000 gallons while in mode 1-4 will result in RWST being inoperable.
N OTE Operability band for CLA level is 7615-7955 gal
[15] IF adding makeup water to Accumulator 4, THEN PERFORM the following:
[a] ENSURE the following valves are CLOSED:
VALVE NO. FUNCTION I -FCV-63-l 15 No. I CL Accum Water Makeup 1-FCV-63-95 No. 2 CL Accum Water Makeui 1-FCV-63-77 No. 3 CL Accum Water Makeup
SQN COLD LEG INJECTION 1-SO-63-1 ACCUMULATORS Rev: 47 i
Pagel000f 185 Date 8.1 Adding Makeup Water to the Cold Leg Accumulators (Continued)
[b] OPEN [1-FCV-63-701 No. 4 CL Accum Water Makeup to begin fifing No. 4 Accumulator.
CAUTION Excessive opening of FCV-63-65 will cause accumulator pressure to decrease rapidly to below the operability limit.
NOTE 1-HIC-63-65 may be adjusted as desired to control the rate of pressure decrease. Approximately 5-10% open is recommended for pressure adjustments within the normal band.
[ci IF desired to vent accumulator to maintain pressure within limits, THEN
[1] THROTTLE [1-FCV-63-65] CL Accum N2 Header Vent Flow Control.
[2) OPEN [1-FCV-63-631 to vent nitrogen from Accumulator 4.
[3] ADJUST [1-FCV-63-65) as needed to control CLA pressure between 630 and 662 psig.
CAUTION IF CLA Fill valve [1-FCV-63-701 fails to completely close, the CLA may over-fill and over-pressurize. Step [161 may be performed out of sequence if necessary to isolate fill line.
[d] WHEN No. 4 Accumulator increases to desired level, THEN ENSURE the following valves CLOSED
[1] [1-FCV-63-70).
[2] [1 -FCV-63-63]
[3] [1 -FCV-63-65]
[4] INDEPENDENTLY VERIFY the following:
- 1. [1-FCV-63-701. CLOSED
- 2. [1-FCV-63-631 CLOSED
- 3. [1-FCV-63-65] CLOSED
SQN COLD LEG INJECTION 1-SO-63-l i ACCUMULATORS Rev: 47 Page 101 of 185 Date 8.1 Adding Makeup Water to the Cold Leg Accumulators (Continued)
NOTE Filling the upper instrument line with borated water requires that the line be purged with DI water to achieve proper level instrument accuracy.
[e] IF accumulator was filled to greater than 7956 gallons (7916 gallons post calibration fill), THEN NOTIFY MIG to purge the upper instrument line with Dl water.
CAUTION Do not fill any other accumulators until No. 4 accumulator pressure and level are within the operability limits of 624-668 psig and 761 5-7955 gallons.
[f] VERIFY No. 4 accumulator pressure and level are within Tech Spec limits.
[g] VERIFY ACCUMULATOR 4 PRESSURE HI-LOW and ACCUMULATOR 4 LEVEL HI-LOW alarms are CLEAR. (1-XA-55-6D windows D-1 and D-2)
[16] CLOSE the following valves:
VALVE NO. FUNCTION INITIALS 1-FCV-63-71 SIS Test Line to HUT 1st IV 1-FCV-63-23 CL Accum Makeup From SI Pumps /
1st IV 17] IF depressurizing RHR is required before SIP minimum run time is complete, THEN DEPRESSURIZE RHR fully using 1-SO-63-5 in parallel with steps [18] through [22].
[18] ENSURE SI pump has run for a minimum of 20 minutes.
SQN COLD LEG INJECTION 1-SO-63-1 ACCUMULATORS Rev: 47 Page 102 of 185 Date 8.1 Adding Makeup Water to the Cold Leg Accumulators (Continued)
[19] STOP running SI pump.
SWITCH NO. FUNCTION INITIALS 1-HS-63-1OA IA-A SI Pump 1-HS-63-15A lB-B SI Pump
[20] IF Unit I is in Modes 1-3, THEN ENSURE SI Pump in A-AUTO (N/A pump not started):
SWITCH NO. FUNCTION INITIALS 1-HS-63-1OA lA-A SI Pump 1st IV 1-HS-63-15A lB-B SI Pump v
[21] IF Unit I is in Mode 4, 5, or 6, THEN ENSURE SI Pumps are in PULL-TO-LOCK.
SWITCH NO. FUNCTION INITIALS 1-HS-63-IOA lA-A SI Pump 1st ,
l-HS-63-15A lB-B SI Pump 1st iv
[22] IF 1-FCV-63-152 was CLOSED in step [10], THEN PERFORM the following:
[a] DEPRESSURIZE SI pump discharge piping using l-SO-63-5.
[b] OPEN [l-FCV-63-152] SI Pump 1ACL Injection Isolation.
1st
SQN COLD LEG INJECTION 1-SO-63-1 ACCUMULATORS Rev: 47 I
Page 103 of 185 Date 8.1 Adding Makeup Water to the Cold Leg Accumulators (Continued)
[23] IF SI Pump discharge piping depressurization NOT previously performed, THEN DEPRESSURIZE piping using 1-SO-63-5.
[24] IF in Mode 4, 5, or 6 (with vessel head on)
AND all CLA filling activities are completed, THEN
- 1. ENSURE [1-FCV-63-231 CLOSED and tagged with power removed to comply with LCO 3.4.12.
- 2. REMOVE clearance from valves tagged in step [8].
END OF TEXT SECTION 8.1
JPM Sim C Page 1 of 1 Rev. 0 SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE MEASURE SIM C (ROISRO)
RETURN PRESSURIZER RELIEF TANK TO NORMAL
JPM Sim C Page 2 of 2 Rev. 0 ROISRO JOB PERFORMANCE MEASURE Task: Pzr Vapor Space Accident (Return PRT to Normal)
Task #: 0070040101 0070050101 0680990101 (RO) 0070010102 (SRO)
Task Standard: Pressurizer Relief Tank (PRT) parameters have been returned to within normal ranges; temperature ( 155°F), pressure (1 .5 6.5 psi), and level (70%).
Time Critical Task: YES: NO: X KIA ReferencelRatings: 007A1 .01 (2.9/3.1) 007A1 .02 (2.7/2.9) 007A1 .03 (2.6/2.7)
Method of Testing:
Simulated Performance: Actual Performance: X Evaluation Method:
Simulator X In-Plant Classroom Main Control Room Mock-up Performer:
Trainee Name Evaluator: I Name I Signature DATE Performance Rating: SAT: UNSAT:
Validation Time: 17 minutes Total Time:
Performance Time: Start Time: Finish Time:
COMMENTS
JPMSimC Page 3of3 Rev. 0 SPECIAL INSTRUCTIONS TO EVALUATOR:
- 1. Critical steps are identified in step SAT/UNSAT column by bold print Critical Step.
- 2. Any UNSAT requires comments.
- 3. Acknowledge any associated alarms.
- 5. ACTIVATE MFRCO5 at 5% to cause PCV-68-334 to leak through.
- 6. Allow PORV Tailpipe temperature to increase and bring in the alarm, then close FCV-68-333.
- 7. ACTIVATE the following REMOTE FUNCTIONS:
RF RCRO4 to remove power from valve RF WDRO2A Pump in PTL (A reactor coolant drain tank pump)
RF WDRO2B Pump in Run (B reactor coolant drain tank pump)
- 8. Cycle PORV to attain:
PRT temp 150°F PRT level > 88%
PRT pressure corresponding to above conditions: 20-25 psig
- 9. Ensure FCV-81-12 is OPEN.
- 10. Due to time restraints, CUEs for PRT level and temperature will be given at appropriate times.
ToolslEquipment/Proceclures Needed:
1-SO-68-5, section 8.2 & 8.4
References:
Reference Title Rev No.
- 1. 1 -SO-68-5 Reactor Coolant System 18 READ TO OPERATOR DIRECTIONS TO TRAINEE:
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 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:
Unit 1 is at 100% power, steady state.
Pressurizer pressure controls in automatic.
Pressurizer sprays in automatic.
PORV PCV-68-334 is partially opened but the block valve has been closed and de-energized.
With the block valve closed, leakage has been isolated through PCV-68-334.
1A Rx Coolant Drain Tank pump is inoperable.
INITIATING CUES:
- 1. You are directed to reduce PRT temperature lAW 1 -SO-68-5 Pressurizer Relief Tank.
- 2. Notify the US when the PRT parameters have been returned to the normal conditions.
JPM Sim C Page 4 of 4 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT Evaluator Note: 1 -SO-68-5, Pressurizer Relief Tank, has 2 sections that the candidate will use to perform this task; Section 8.2, Reducing PRT Level Using B RCDT Pump Section 8.4, Reducing the Temperature of the PRT.
The sections can be performed in any order. The JPM starts with Sect 8.4, however if the candidate chooses to perform sect 8.2 first then start at JPM step 5.
STEP 1.: [8.4.1] ENSURE j1ECV-81 -12] OPEN.
UNSAT STANDARD: Operator verifies that FCV-81 -12 is open by observing 1-HS-81-12A Red light on, Green light Off.
£QiviMENTS:
STEP 2.: [8.4.2] OPEN 1 -FCV-68-303 by placing 1 -HS-68-303A SAT to OPEN position.
UNSAT STANDARD: Operator takes hand switch HS-68-303A on M-5 to OPEN.
Hand switch indicates valve is open by red light ON.
Critical Step This step is critical to induce primary water into the PRT nozzles to lower temperature.
COMMENTS:
JPM Sim C Page 5of5 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 3.: [8.4.3] IF PRT level increases to > 88% OR PRT SAT temperature decreases to < 120°F THEN close FCV 303 UNSAT Cue: PRT level is 88%.
PRT temp is as indicated. Critical Step STANDARD: Operator monitors PRT level on Ll-68-300 and temperature on TI-68-309, then places FCV-68-303 in the closed position and verifies green light ON.
This step is critical to prevent overfill of the PRT COMMENTS:
STEP 4.: [8.4.4] IF PRT level is 88%, THEN GO TO section SAT 8.2 or 8.3.
UNSAT STANDARD: Operator goes to section 8.2 Reducing PRT Level Using B RCDT Pump (IA RCDT pump is mop)
COMMENTS:
Evaluator Note: This starts Sect 8.2, Reducing PRT Level Using B RCDT Pump Caution_1:_Pump_damage_could_occur_if suction_is_lost while_pumping_water_>175°F Caution 2: RCDT pump lB will NOT automatically stop on low level in PRT or closure of FCV-68-31 0.
Note:_RCDT_pump_B will_Auto_start when_1-FCV-68-310,_PRT_drain_to_RCDT opens.
JPM Sim c Page 6of6 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 5.: [8.2.1] VERIFY RCDT pumps aligned for service in SAT accordance with valve check list 1-77-1.02.
UNSAT Cue: NO deviations.
STANDARD: Operator explains how to check status log to ensure no deviations exist.
COMMENTS:
NOTE: An AUO at panel O-L2 in communication with a MCR UO is needed to perform this instruction STEP 6.: [8.2.2] Station AUO at panel 0-L-2. SAT UNSAT Cue: Role play as the Rad Waste AUO. State that you are at O-L-2 panel and will stay here and wait on your instructions.
STANDARD Operator ensures an AUO is stationed at 0-L-2 panel.
COMMENTS:
STEP 7.: [8.2.3] If RCDT level >20%, THEN PUMP down RCDT level. SAT UN SAT Cue: Role play as the Rad Waste AUO. State that you are at O-L-2 panel and the level in Unit I RCDT is 18%.
STANDARD: Operator checks with an AUO at 0-L-2 panel and ensures level is < 20%
COMMENTS:
JPM Sim C Page 7 of 7 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 8.: [8.2.4] ENSURE [1-FCV-77-9] and [1 -FCV-77-1 0] are SAT OPEN.
UNSAT STANDARD: Operator verifies FCV-77-9 and FCV-77-1 0 open on panel M-15 (red lights on hand-switches illuminated)
COMMENTS:
STEP 9.: [8.2.5] ENSURE [1-HS-77-6A] for RCDT pump B is in the PULL-P-AUTO position.
UNSAT Cue: Rad waste Operator informs UO that RCDT Pump B is in P-AUTO and that the level in the Unit I RCDT1s still 18%.
STANDARD: Operator contacts Rad Waste Operator and verifies HS-77-6A for RCDT Pump B is in P-AUTO.
COMMENTS:
STEP 10 [8 2 6] OPEN [1-FCV-68-3051 Nitrogen supply to PRT SAT UN SAT STANDARD: Operator opens FCV-68-305 by placing 1-HS-68-305A to OPEN on panel I M-5 and verifies Red lights ON Critical Step This step is critical to ensure normal pressure maintained in the PRT during the level decrease.
COMMENTS:
JPMS1mC Page 8 of 8 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 11.: [8.2.7] PLACE. I-I-IS-68-31 0 in the OPEN ..position,ánd VERIFY 1-FV UNSAT Cue: When operator opens FCV-68-310 and the operator contacts the Rad Waste operator, then state to the operator the B RCDT pump is running. Critical Step STANDARD: Operator places 1-HS-68-310A to OPEN on panel 1-M-5 and verifies Red lights ON This step is critical to provide a suction flowpath to the RCDT pump and to make up the pump starting logic.
COMMENTS:
STEP 12.: [8.2.8] ENSURE RCDT Pump B starts. SAT UNSAT Cue: RCDT pump B is running.
STANDARD: Operator checks with Rad Waste AUO to ensure RCDT pump B starts.
COMMENTS:
STEP 13.: [8.2.9] IF PRT pressure drops < 1.5 psig, THEN... SAT UNSAT STANDARD: Operator monitors PRT pressure with P1-68-301 on 1-M-5.
COMMENTS:
JPM Sim C Page 9 of 9 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT Caution: The RCDT level is to be maintained <50% while 1-FCV-68-310 is open to prevent inadvertent opening of 1-LCV-77-415 which could cause overfilling of RCDT from the PRT.
STEP 14.: [8.2.10] IF at any time while pumping down the PRT the SAT RCDT level approaches 50%, THEN...
UNSAT Cue: When AUO contacted, State: I will monitor RCDT level, Stop RCDT pump and notify you to close FCV-68-310 if RCDT approaches 50%.
STANDARD: Operator notifies AUO of this step.
COMMENTS:
STEP 15.: [8.2.11] IF returning from Appendix C, Then... SAT UNSAT STANDARD: Operator N/As this step.
COMMENTS:
STEP 16.: [8.2.12] WHEN PRT level reaches desired level, THEN SAT STOP B RCDT Pump (at 0-L-2 panel)
UNSAT
- When the operator begins to monitor level on Ll-68-300, Tell the operator that PRT level has decreased to 70% .
Cue: When operator requests AUO to stop RCDT pump 18, Tell him RCDT pump lB is stopped and HS is in Pull-P-Auto.
STANDARD: Operator verifies level, and has the Rad Waste Operator STOP RCDT Pump I B and place HS in Pull-P-Auto COMMENTS:
JPM Sim C Page 10 of 10 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 17 f8 2 I3ICLOSE FCV-68-310 SAT Cue: If operator asks, PRT Level is 70%, Temp is 110 CF, UNSAT and Press is 6.5 psig.
STANDARD: Operator closes FCV-68-310 with HS-68-310A (on panel Critical Step 1-M-5) and verifies green light ON.
This step is critical to drop out the stop logic to the RCDT pump and to isolate the PRT from the RCDT.
COMMENTS:
STEP 18.: [8.2.14] PLACE [1-HS-77-6A] RCDT pump B in Pull-P-Auto SAT position at O-L-2 panel.
UNSAT Cue: When operator requests AUO to place the HS for RCDT pump IB, Tell him RCDT pump lB HS is in Pull-P-Auto.
STANDARD: Operator has the Rad Waste Operator place HS in Pull-P Auto.
COMMENTS:
STEP 19.: [8.2.15] CLOSE [1-FCV-68-305] Nitrogen Supply to PRT. SAT UNSAT STANDARD: Operator closes 1-FCV-68-305 with 1-HS-68-305A (on panel 1-M-5) and verifies Green light ON.
COMMENTS:
JPM Sim C Page 11 of 11 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 20.: Inform the US/SRO that the PRT parameters have not been SAT returned to within normal operating conditions/ranges.
UNSAT STANDARD: Operator informs the US/SRO that the PRT parameters have not been returned to within normal operating conditions/ranges and needs to return to section 8.4 to Stop Time continue temperature reduction.
Cue: After candidate indicates the need to return to section 8.4, state This completes the JPM.
READ TO OPERATOR DIRECTIONS TO TRAINEE:
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 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 1 is at 100% power, steady state.
- 2. Pressurizer pressure controls in automatic.
- 3. Pressurizer sprays in automatic.
- 4. PORV PCV-68-334 is partially opened but the block valve has been closed and de-energized.
- 5. With the block valve closed, leakage has been isolated through PCV-68-334.
- 6. IA Rx Coolant Drain Tank pump is inoperable.
INITIATING CUES:
- 1. You are directed to reduce PRT temperature lAW I -SO-68-5 Pressurizer Relief Tank.
- 2. Notify the US when the PRT parameters have been returned to the normal conditions.
READ TO OPERATOR DIRECTIONS TO TRAINEE:
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 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 I is at 100% power, steady state.
- 2. Pressurizer pressure controls in automatic.
- 3. Pressurizer sprays in automatic.
- 4. PORV PCV-68-334 is partially opened but the block valve has been closed and de-energized.
- 5. With the block valve closed, leakage has been isolated through PCV-68-334.
- 6. IA Rx Coolant Drain Tank pump is inoperable.
INITIATING CUES:
- 1. You are directed to reduce PRT temperature lAW 1-SO-68-5 Pressurizer Relief Tank.
- 2. Notify the US when the PRT parameters have been returned to the normal conditions.
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT SYSTEM OPERATING INSTRUCTION 1-S 0-68-5 PRESSURIZER RELIEF TANK Revision 18 QUALITY RELATED PREPARED/PROOFREAD BY: PAT BARBREE/MARIE HANKINS RESPONSIBLE ORGANIZATION: OPERATIONS APPROVED BY: W. T. LEARY EFFECTIVE DATE: 10/28/07 LEVEL OF USE: CONTINUOUS USE REVISION DESCRIPTION: Added UNIDs on handswitches for operating RCDT Pumps to sections 8.2, 8.3, 8.7 and Appendixes A & B. Added Block Valves Open and draining PRT to less than 5% to step 4 of section 8.7. All changes lAW (07000493). Added steps to Appendix B to allow operation of the RCDT pump from switchgear.
I -SO-68-5 SQN PRESSURIZER RELIEF TANK Rev: 18 I
Page5of36 2.2 Developmental References A. SO 1-68.1, Reactor Coolant System B. 0-MI-MXX-068-006.0, Venting of Pressurizer, Pressurizer Relief Tank, and Reactor Head C. SPP-10.3, Verification Program D. TVA Drawing
- 1. 47W813-1
- 2. 47W819-1
- 3. 47W830-1
- 1. Section 5.5 3.0 PRECAUTIONS AND LIMITATIONS A. During normal operation, PRT water temperature should not exceed 120°F.
B. Maintaining 3 to 6 psig N2 gas blanket on the PRT will prevent the formation of explosive hydrogen-oxygen mixtures.
C. The PRT concentration of oxygen shall be limited to less than or equal to 2% by volume whenever the hydrogen concentration exceeds 4% by volume.
D. Over filling the PRT to solid water condition during oxygen reduction per Section 8.8 may result in failure of the PRT rupture disc.
E. The PRT pressure should be maintained <7.5 psig during normal operation. (Except during the performance of section 8.9).
F. The PRT rupture discs are rated at 85 psig.
G. The level in the PRT should be maintained at 70%. If the level increases to 88%, then decreasing level to 70% is necessary. If the level decreases to 55%, then increasing level to 70% is needed when the PRT is required to be operable.
H. Completely draining the PRT may result in gas binding the RCDT pumps.
I. Water intrusion into the waste gas vent header is possible during PRT venting operations with PRT level high. This could affect RCP seal leakoff flows and the vent capability of tanks which vent to waste gas vent header.
J. PRT level indications or alarms are not available in the Aux Control Room, thus PRT level manipulations and feed & bleed processes are unavailable.
1 -SO-68-5 SQN PRESSURIZER RELIEF TANK Rev: 18 Page 6 of 36 Date________
4.0 PREREQUISITE ACTIONS NOTE Throughout this Instruction, where an IFITHEN statement exists, the step should be NIA if condition does not exist.
J?YENSURE Instruction to be used is a copy of the effective version.
ENSURE Precautions and Limitations, Section 3.0 have been reviewed.
ENSURE Attachment 1, Power Checklist 1-68-5.01 is complete.
,jEENSURE Attachment 2, Valve Checklist 1-68-5.02 is complete.
VERIFY primary water is available to fill and cool the PRT (N/A if primary water will not be used).
_4 VERIFY Waste Disposal System is available to receive liquid from PRT.
J1E1VERIFY vent header in service to receive gases from the PRT (N/A if PRT will not be vented to vent header).
VERIFY low pressure N 2 system is in service (N/A if nitrogen will not be used).
451ENSURE each performer documents their name and initials:
Print Name Initials
_ifj51NDICATE below which performance section of this Instruction will be used and the reason for this performance:
El 5.0 STARTUP/STANDBY READINESS 8.0 INFREQUENT OPERATION REASON: co?co ror-.\
SQN 1-SO-68-5 PRESSURIZER RELIEF TANK Rev: 18 Page 10 of 36 Date___________
8.2 Reducing PRT Level Using B RCDT Pump CAUTION I Pump damage could occur if suction is lost while pumping water> 175°F.
CAUTION 2 RCDT pump lB will NOT automatically stop on low level in PRT OR closure of FCV-68-310.
NOTE RCDT pump B will Auto start when 1-FCV-68-310, PRT drain to RCDT opens.
[1] VERIFY RCDT pumps aligned for service in accordance with Valve Checklist 1-77-1.02.
NOTE An AUO at panel 0-L-2 in communication with a MCR UO is needed to perform this Instruction.
[2] STATION an AUO at panel 0-L-2.
[3] IF RCDT level > 20%, THEN PUMP down RCDT level in accordance with Appendix C of this Instruction.
[4] ENSURE [1-FCV-77-9] and [1 -FCV-77-1 0] RCDT pump outlet isolation valves are OPEN.
[5] ENSURE [1-HS-77-6A] for RCDT pump B is in the PULL-P-AUTO position.
[6] OPEN [1-FCV-68-305] Nitrogen Supply to PRT.
[7] PLACE [1-HS-68-310A1 in the OPEN position, AND VERIFY [I -FCV-68-31 0] OPENS.
[8] ENSURE RCDT pump B STARTS.
I -SO-68-5 SQN PRESSURIZER RELIEF TANK Rev: 18 Page 11 of 36 Date__________
8.2 Reducing PRT Level Using B RCDT Pump (Continued)
[9] IF PRT pressure drops < 1.5 psig, THEN COMPLETE the foflowing:
[a] STOP B RCDT pump using [1-HS-77-6A] at 0-L-2, AND CLOSE [I -FCV-68-31 0].
[b] PLACE [1-HS-77-6A] RCDT pump B in PULL-P-AUTO.
[c] WHEN PRT pressure returns to normal, THEN OPEN [I -FCV-68-310].
[d] ENSURE RCDT pump B STARTS.
CAUTION The RCDT level is to be maintained <50% while 1-FCV-68-310 is open to prevent inadvertent opening of I-LCV-77-415 which could cause overfilling of RCDT from the PRT.
[10] IF at any time while pumping down the PRT the RCDT level approaches 50%, THEN PERFORM the following before continuing the PRT level reduction:
[a] PLACE [1-HS-77-6A] RCDT pump B in the PULL-TO-LOCK position.
[b] CLOSE [1.FCV-68-310].
[c] GO TO Appendix C of this Instruction for RCDT level reduction and return to Step [11] of Section 8.2.
I -SO-68-5 SQN PRESSURIZER RELIEF TANK Rev: 18 I
Pagel2of36 Date___________
8.2 Reducing PRT Level Using B RCDT Pump (Continued)
[11] IF returning from Appendix C, THEN PERFORM the following:
[a] PLACE [1-HS-77-6A] RCDT pump B in PULL-P-AUTO position.
[b] OPEN [I-FCV-68-310].
[c] ENSURE B RCDT pump STARTS.
[12] WHEN PRT reaches desired level, THEN STOP B RCDT pump using [I-HS-77-6A].
[13] CLOSE [I -FCV-68-31 01.
1st IV
[14] PLACE [1-HS-77-6A1 RCDT pump B in PULL-P-AUTO position at O-L-2 panel.
1st IV
[15] CLOSE [I-FCV-68-305] Nitrogen Supply to PRT.
1st IV END OF TEXT
SQN I -SO-68-5 PRESSURIZER RELIEF TANK Rev: 18 I
Pagel6of36 Date NOTE May need an extra copy of this Instruction.
8.4 Reducing the Temperature of the PRT
[1] ENSURE [1-FCV-81-12] OPEN.
[2] OPEN [1-FCV-68-303] by placing
[I-HS-68-303A] to OPEN position.
[3] IF PRT level increases to > 88% or PRT temperature decreases < 120°F, THEN CLOSE [1-FCV-68-303].
1st IV
[4] IF PRT level is > 88%, THEN GO TO section 8.2 or 8.3 of this Instruction, AND RETURN to step [1] of this section if further temperature reduction is needed.
END OF TEXT
JPM Sim D-1 Page 1 of 1 Rev. 0 SEQUOYAH NUCLEAR PLANT September 2010 NRC Exam Sim D-1 (ROISRO)
Respond to Loss of Flow to RCP Oil Cooler
JPM Sim D-1 Page 2 of 2 Rev. 0 ROISRO JOB PERFORMANCE MEASURE Task: Respond to Loss of Flow to RCP Oil Cooler per AOP-R.04 Task#: (RO) 0000820501 Task Standard: Identify Loop 2 RCP oil cooling degradation requiring pump shutdown.
Time Critical Task: YES: NO: X KIA ReferencelRatings: 003 Al .02 (2.9/2.9) 003 A4.06 (2.9/2.9) 003 A2.02 (3.7/3.9)
Method of Testing:
Simulated Performance: Actual Performance: X Evaluation Method:
Simulator X In-Plant Classroom Main Control Room Mock-up Performer:
Trainee Name Evaluator: I Name I Signature DATE Performance Rating: SAT: UNSAT:
Validation Time: 10 mins Total Time:
Performance Time: Start Time: Finish Time:
COMMENTS
JPM Sim D-1 Page 3 of 3 Rev. 0 SPECIAL INSTRUCTIONS TO EVALUATOR:
- 1. Critical steps are identified in step SAT/UNSAT column by bold print Critical Step.
- 2. Any UNSAT requires comments
- 3. Initialize in IC # 16; 100% power
- 4. Insert MaIf set yp_rcl2b-1 (expert command)
- 5. Ensure Applicant performs the following required actions for 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.
ToolslEquipmentlProcedures Needed:
References:
Reference Title Rev No.
- 1. 0-AR-M27-B-A Annunciator Response 0-AR-M27-B-A 11
- 2. AOP-R.04 Reactor Coolant Pump Malfunctions 24 DIRECTIONS TO TRAINEE on next page
- 1. Time Critical Task YES: NO: X
JPM Sim D-1 Page 4 of 4 Rev. 0 READ TO OPERATOR DIRECTIONS TO TRAINEE:
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 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 us operating at 100% reactor power, equipment is normal.
INITIATING CUES:
- 1. You are the OATC and are to monitor the control board and respond per licensed duties to operating conditions as a reader/doer.
- 3. You will be required to respond to any abnormalities.
- 4. When any required actions/procedures have been completed notify the SM.
JPM Sim D-1 Page 5 of 5 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 1.: Respond to indications of loss of cooling water flow to RCP # 2 oil cooler per SAT 0-AR-M27-B-A window D-3 UNSAT STANDARD: Operator responds to annunciator panel 0- XA-55-4B; identifies window D-3 illuminated and enters alarm response procedure (ARP) 0- 5ta Time AR-M27-B-A, D-.3 COMMENTS:
Evaluator Note: ARP 0-AR-M27-B-A, D-3 follows starting at Corrective Actions Step 1 STEP 2.: [11 CHECK RCP No. 2 upper and lower oil cooler outlet flow by observing SAT 1-Fl-70-106 and 1-Fl-70-108 on 0-M27-B.
UNSAT STANDARD: Operator observes oil cooler flow instruments 1 -Fl-70-1 08 (lower) and 1-Fl-70-106 (upper) for RCP #2 on panel 0-M27-B and determines loss of CCS flow to the upper oil cooler as the cause of the alarm.
COMMENTS:
STEP 3.: [2] MONITOR RCP temperatures and CCS flow through upper and lower oil SAT coolers.
UNSAT STANDARD: Operator monitors RCP # 2 operating parameters utilizing ICS screen RCP DATA and/or individual ICS points and concludes upper radial bearing temperature is increasing.
COMMENTS:
STEP 4.: [3] IF upper or lower motor bearing temperature approaches 200°F, THEN SAT GO TO AOP-R.04, Reactor Coolant Pump Malfunctions.
UNSAT STANDARD: Operator determines that temperature is approaching the upper limit for the upper radial bearing and implements AOP-R.04.
COMMENTS:
JPM Sim D-1 Page 6 of 6 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT Evaluator Note: Operator transitions from the ARP to AOP-R.04, Reactor Coolant Pump Malfunctions and reviews Section 2.0 Operator Actions CAUTIONS and NOTE prior to step 1 CAUTION I : RCP should NOT be tripped when reactor power is greater than 5%
(FR-S.1) or when RCP operation is required by FR-C.1 (Inadequate Core Cooling) or FR-C.2 (Degraded Core Cooling).
CAUTION 2: Exceeding any of the following limits requires tripping the affected SAT RCP, except as described in Caution 1:
. RCP # 1 Seal AP less than 220 psid UNSAT
. RCP # 1 Seal Temperature greater than 225°F
. RCP Lower Bearing Temperature greater than 225°F
. RCP Upper Motor Bearing Temperature greater than 200°F
. RCP Lower Motor Bearing Temperature greater than 200°F
. RCP Motor Amps greater than 608 amps
. RCP Vibration greater than 20 mils on any axis (x and/or y)
. RCP Upper Motor Bearing Temperature greater than 200°F NOTE:__RCP_trip_criteria_is_also_located_in_Appendix_B.
STEP 5.: 1. DIAGNOSE the failure: SAT UNSAT STANDARD: Operator concludes trip criteria exists when motor bearing temperature exceeds 200°F; Operator selects Section 2.1, ANY RCP tripped or RCP Shutdown Required IF. GOTO SECTION PAGE ANY RCP tripped or RCP shutdown required 2.1 4 NOTE During plant startup following seal maintenance, the seal package should seat and operate normally following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of run time.
1 Seal Leakoff high flow (high flow Alarm) on ANY RCP 2.2 7
- 1 Seal Leakoff low flow (low flow Alarm) on ANY RCP 23 13
- 2 Seal Leakoff high flow (high RCP standpipe level) on ANY RCP 2.4 18 3 Seal Leakoff Ngh flow (low RCP standpipe level) on ANY RGP 2.5 21 Motor Stator Temperature High on ANY RCP 2.6 24 COMMENTS:
CAUTION: A rapid drop in level and steam flow on the affected loop SIG may occur when RCP is stopped
JPM Sim D-1 Page 7 of 7 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 6.: 2.1.1. CHECK unit in Mode 1 or 2. SAT UNSAT STANDARD: Operator determines MODE 1 conditions AND Determines reactor should be tripped before stopping the RCP.
COMMENTS:
CAUTION: If #1 seal leak-off flow is HIGH on any RCP, Step 3 requires closing seal return valve within 5 minutes after stopping affected RCP(s). Step 3 should be continued after E-O immediate actions.
STEP 7.: 2.1.2. PERFORM the following: SAT
. .... ,..:::c UNSAT STANDARD: Operator performs reactor trip by operating reactor trip handswitch 1-RT-1 (M-4) or 1-RT-2 (M-6.) Critical Ste p (shaded portion)
(epis critica to m &i1triRx prioio tripping the R COMMENTS:
STEP 8 b WJIEN rect6jsfrippci, IIEN STQP afctea Rds) SAT Time: UNSAT STANDARD: Operator observes reactor trip breakers open, reactor trip indications Critical Step THEN stops RCP # 2, and records the current time.
COMMENTS:
JPM Sim D-1 Page 8 of 8 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT! UNSAT STEP 9.: c. GO TO E-O, Reactor Trip or Safety Injection, WHILE continuing in this SAT procedure.
UNSAT CUE: When Rx is tripped, CUE operator that another operator completed steps 1 4 of E-0.
STANDARD: Operator ensures that someone is performing remaining E-O immediate actions.
COMMENTS:
CAUTION: If RCP seal leakoff is HIGH, seal return valve must be closed within 5 minutes_after_stopping_the_affected_RCP(s).
STEP 10.: 3. MONITOR #1 seal leakoff on affected RCP: SAT
- 1. Check for any of the following:
- RCP Seal Leak-off greater than 6 gpm and Lower bearing or seal temperature rising uncontrolled.
STANDARD: Operator determines that seal leakoff is not outside of normal values and continues to step 4.
COMMENTS:
STEP 11.: 4. PULL TO DEFEAT affected loop AT and T-avg: SAT
- XS-68-2D (AT)
- XS-68-2M (T-avg) UNSAT STANDARD: Operator uses Panel 1-M-5 selector switches 1-XS-68-2D and 1-XS-68-2M, Operator removes the idle loops temperature inputs from control by pulling to defeat XS-68-2D and XS-68-2M COMMENTS:
READ TO OPERATOR DIRECTIONS TO TRAINEE:
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 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:
Unit 1 is operating at 100% reactor power, equipment is normal.
INITIATING CUES:
- 1. You are the OATC and are to monitor the control board and respond per licensed duties to operating conditions as a reader/doer.
- 2. Your US and the CR0 are currently outside the MCR.
- 3. You will be required to respond to any abnormalities.
- 4. When any required actions/procedures have been completed notify the SM.
READ TO OPERATOR DIRECTIONS TO TRAINEE:
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 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:
Unit I is operating at 100% reactor power, equipment is normal.
INITIATING CUES:
- 1. You are the OATC and are to monitor the control board and respond per licensed duties to operating conditions as a reader/doer.
- 3. You will be required to respond to any abnormalities.
- 4. When any required actions/procedures have been completed notify the SM.
24 (D-3)
Source Setpoint RC PUMP 2 SER 1137 (Unit I annunciator system) OIL COOLERS 1-FS-70-106 (upper) 100 gpm decreasing SER 1138 (Unit 1 annunciator system) 1-FS-70-108 (lower) 4 gpm decreasing LOW Retransmitted to U-2 SER 2132 & 2133 (Unit 2 annunciator system)
Probable i. Loss of component cooling water to the reactor coolant pump.
Causes 2. Low component cooling water pressure.
- 3. Valve misalignment.
- 4. Phase B Containment isolation.
Corrective [1] CHECK RCP No. 2 upper and Tower oil cooler outlet flow by Actions observing [I-FI-70-1061 and 11-FI-70-1081 on 0-M-27B.
[2] MONITOR RCP temperatures and CCS flow through upper and lower oil coolers.
[3] IF upper or lower motor bearing temperature approaches 200°F, THEN GO TO AOP-R.04, Reactor Coolant Pump Malfunctions.
[4] VERIFY proper valve alignment in accordance with 1-SO-70-1, Component Cooling Water System Train A.
[5] REFER to AOP-M.03, Loss of Component Cooling Water.
References 45B655-27BA-0, 47B601 28, 47W61 0-70-3, 47W61 1-70-3, 47W859-2 SQN 0-AR-M27-B-A Page 26 of 40 0,1 Rev. 11
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT AOl PROGRAM MANUAL ABNORMAL OPERATING PROCEDURES AOP-R.04 REACTOR COOLANT PUMP MALFUNCTIONS Revision 24 QUALITY RELATED PREPARED/PROOFREAD BY: CECIL DYER RESPONSIBLE ORGANIZATION: OPERATIONS APPROVED BY: D. A. PORTER EFFECTIVE DATE: 3/5/2009 REVISION DESCRIPTION: Changed wording of section titles to avoid confusion. (PCR#
07000278) Changed appendix A to allow use of computer point to determine #2 seal leakage. (PCR# 07000229) Changed section 2.3 step 8 to a continuous action step to monitor RCDT to determine seal leakage. (PCR# 08000914) Added FR-S.1, to the notes/cautions pertaining to leaving RCPs running during events requiring RCP operation. (PCR# 08000836) Updated procedural guidance to conform to most recent Westinghouse recommendations on RCP shutdown with No.1 seal leakage outside the operating limits. Clarified guidance pertaining to stopping RCPs after reactor trip (PER 148792)
AOP-R.0 SQN REACTOR COOLANT PUMP MALFUNCTIONS Rev. 24 1.0 PURPOSE This procedure provides the actions necessary to mitigate the effects of a Reactor Coolant Pump (RCP) trip below P-B (35% power), excessive RCP seal leakage, and various RCP malfunctions.
If RCP seal injection flow is lost, AOP-M.09 (Loss of Charging) takes precedence over this AOP.
Page 2 of34
AOP-R.04 SQN REACTOR COOLANT PUMP MALFUNCTIONS Rev. 24 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2.0 OPERATOR ACTIONS CAUTION I RCP should NOT be tripped when reactor power is greater than 5% (FR-S.I) or when RCP operation is required by FR-C.I (Inadequate Core Cooling) or FR-C.2 (Degraded Core Cooling).
CAUTION 2 Exceeding any of the following limits requires tripping the affected RCP, except as described in Caution I:
- RCP #1 Seal Temperature greater than 225°F
- RCP Lower Bearing Temperature greater than 225°F
- RCP Upper Motor Bearing Temperature greater than 200°F
- RCP Lower Motor Bearing Temperature greater than 200°F
- RCP Motor Voltage less than 5940V or greater than 7260V
- RCP Motor Amps greater than 608 amps
- RCP Vibration greater than 20 mils on any axis (x and/or y) [C.3]
NOTE: RCP trip criteria is also located in Appendix B.
- 1. DIAGNOSE the failure:
IF... GOTO SECTION PAGE ANY RCP tripped or RCP shutdown required 2.1 4 NOTE During plant startup following seal maintenance, the seal package should seat and operate normally following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of run time.
- 1 Seal Leakoff high flow (high flow Alarm) on ANY RCP 2.2 7
- 1 Seal Leakoff low flow (low flow Alarm) on ANY RCP 2.3 13
- 3 Seal Leakoff high flow (low RCP standpipe level) on ANY RCP 2.5 21 Motor Stator Temperature High on ANY ROP 2.6 24 Page 3 of 34
STEP I ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED 2.1 ANY RCP Tripped or RCP Shutdown Required CAUTION: A rapid drop in level and steam flow on the affected loop SIG may occur when RCP is stopped.
- 1. CHECK unit in Mode 1 or 2. STOP affected RCP(s).
Time:
GO TO Caution prior to Step 3.
CAUTION: If #1 seal leakoff flow is HIGH on any RCP, Step 3 requires closing seal return valve within 5 minutes after stopping affected RCP(s). Step 3 should be continued after E-O immediate actions. [C.2)
- 2. PERFORM the following:
- a. TRIP the reactor.
- b. WHEN reactor is tripped, THEN STOP affected RCP(s).
Time:
- c. GO TO E-O, Reactor Trip or Safety Injection, WHILE continuing in this procedure.
Page 4 of 34
AOP-R.04 SQN REACTOR COOLANT PUMP MALFUNCTIONS Rev. 24 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2.1 ANY RCP Tripped or RCP Shutdown Required (contd)
CAUTION: If RCP seal leakoff is HIGH, seal return valve must be closed within 5 minutes after stopping the affected RCP(s). [C.2]
- 3. MONITOR #1 seal leakoff on affected RCP:
- a. CHECK for any of the following: a. GO TO Step 4.
- RCP Seal leakoff greater than 6 gpm AND Lower bearing or seal temperature rising uncontrolled.
- b. WI-lEN between 3 and 5 minutes have elapsed since RCP stop, THEN CLOSE affected RCP seal return FCV:
- FCV-62-9 {RCP 1]
- FCV-62-22 [RCP 2]
- FCV-62-35 [RCP 3]
- FCV-62-48 {RCP 4]
- 4. PULL TO DEFEAT affected loop tT and T-avg:
- XS-68-2D (AT)
- XS-68-2M (T-avg)
Page 5 of 34
AOP-R.04 SQN REACTOR COOLANT PUMP MALFUNCTIONS Rev. 24 STEP ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED 2.1 ANY RCP Tripped or RCP Shutdown Required (contd)
- 5. CHECK RCPs 1 and 2 RUNNING. CLOSE affected loops pressurizer spray valve.
- 6. EVALUATE EPIP-1 Emergency Plan Initiating Conditions Matrix.
- 7. EVALUATE the following Tech Specs for applicability:
- 3.2.5, DNB Parameters
- 3.4.1.1, Reactor Coolant Loops and Coolant Circulation Startup and Power Operation
- 3.4.1 .2, Reactor Coolant System -
Hot Standby
- 3.4.1.3, Reactor Coolant System -
Shutdown
- 3.4.6.2, RdS Operational Leakage
- 8. GO TO appropriate plant procedure.
END OF SECTION Page 6 of34
SQN REACTOR COOLANT PUMP MALFUNCTIONS STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2.2 #1 Seal Leakoff High Flow on ANY RCP CAUTION 1: RCP bearing damage may occur if temperature exceeds 225°F.
CAUTION 2: IF any RCP must be stopped due to high seal leakoff flow, the seal return valve on the affected RCP(s) must be closed within 5 minutes.
This action is addressed in Section 2.1.
MONITOR #1 seal leakoff PERFORM the following:
less than 6 gpm per pump:
- a. MONITOR RCP lower bearing
- FR6224 [RCP 1 & 2] temperature and seal temperature.
- FR-62-50 [RCP 3 & 4]
IF RCP lower bearing temperature OR seal temperature are rising uncontrolled, THEN GO TO Section 2.1, ANY RCP Tripped or RCP Shutdown Required. [C.1] [C.2)
IF lower bearing temperature AND seal temperature indication are NOT available for affected RCP, THEN GO TO Section 2.1, ANY RCP Tripped or RCP Shutdown Required. [C.1]
(Step continued on next page.)
Page 7 of 34
AOP-R.O4 SQN REACTOR COOLANT PUMP MALFUNCTIONS Rev. 24 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 1 2.2 #1 Seal Lea koff High Flow on ANY RCP (contd)
(Continued) b. MONITOR #1 seal leakoff flow:
IF#1 seal leakoff flow greater than 8 gpm, THEN GO TO Section 2.1 ANY RCP Tripped or RCP Shutdown Required. [Cl]
IF #1 seal leakoff flow less than 8 gpm, THEN PERFORM the following:
- 2) CONTACT Engineering for recommendations WHILE continuing with this procedure.
- 3) IMPLEMENT Engineering recommendations to address specific RCP seal conditions OR COMPLETE normal plant shutdown within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> USING appropriate plant procedure.
- 4) WHEN reactor is shutdown or tripped, THEN GO TO Sect. 2.1, ANY RCP Tripped or RCP Shutdown Required. [Cl]
Page 8 of 34
AOP-R.04 SQN REACTOR COOLANT PUMP MALFUNCTIONS Rev. 24 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2.2 #1 Seal Leakoff High Flow on ANY RCP (contd)
- 2. MONITOR RCP lower bearing and IF any of the following conditions met:
seal water temperatures less than 225°F.
- seal leakoff flow greater than 6 gpm AND lower bearing and seal temp NOT available for affected RCP THEN GO TO Section 2.1, ANY RCP Tripped or RCP Shutdown Required. [C.1J
- 3. MONITOR #1 seal p GO TO Section 2.1, ANY RCP Tripped or greater than 220 psid: RCP Shutdown Required. [C.1]
- PDI-62-8A
- PDI-62-21A
- PDI-62-34A
- PDI-62-47A Page 9 of 34
AOP-R.04 SQN REACTOR COOLANT PUMP MALFUNCTIONS Rev. 24 STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2.2 #1 Seal Leakoff High Flow on ANY RCP (contd)
- 4. ENSURE RCP seal water supply flow IF seal water supply flow is less than 6 gpm 6-10 gpm per pump: AND CANNOT be restored, THEN
- F1621A ENSURE CCS supply to thermal barriers less than 105°F on TR-70-161
- Fl-62-14A
{CCS HX 1A1!1 (2A1/2A2) Outlet Temp]
- Fl-62-27A
- Fl-62-40A
- 5. CONTACT Engineering for recommendations WHILE continuing with this procedure.
- 6. EVALUATE EPIP-1, Emergency Plan Initiating Conditions Matrix.
Page 10 of 34
AOP-R.04 SQN REACTOR COOLANT PUMP MALFUNCTIONS Rev. 24 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I 2.2 #1 Seal Leakoff High Flow on ANY RCP (contd)
- 7. EVALUATE the following Tech Specs for applicability:
- 3.2.5, DNB Parameters
- 3.4.1.1, Reactor Coolant Loops and Coolant Circulation Startup and Power Operation
- 3.4.1.2, Reactor Coolant System-Hot Standby
- 3.4.1 .3, Reactor Coolant System -
Shutdown
- 3.4.6.2, RCS Operational Leakage CAUTION: Slow and uniform temperature adjustments (approx. 50°F in one hour) will prevent thermal shock to the seals.
- 8. CHECK VCT outlet temperature ADJUST HIC-62-78A to reduce VCT less than 130°F [11-62-131]. temperature to less than 130°F.
- 9. ENSURE VCT pressure between 17 psig and 45 psig [P1-62-122].
Page 11 of 34
AOP-R.04 SQN REACTOR COOLANT PUMP MALFUNCTIONS Rev. 24 I STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2.2 #1 Seal Leakoff High Flow on ANY RCP (contd)
- 10. CHECK RCP lower bearing and IF any of the following conditions met:
seal water temperature less than 1 80°F:
- tower bearing and seal water temp indication NOT available for affected RCP, THEN GO TO Step 1.
- 11. GO TO appropriate plant procedure.
END OF SECTION Page 12of34
AOP-R.04 SQN REACTOR COOLANT PUMP MALFUNCTIONS Rev. 24 STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2.3 #1 Seal Leakoff Low Flow on ANY RCP
- 1. CHECK #1 seal leakoff flow GO TO Step 4.
greater than 0.8 gpm per pump:
o FR-62-23 [RCP 1 & 2]
- FR-62-49 [RCP 3 & 4]
- 2. CHECK #1 seal leakoff flow GO TO Step 4.
greater than 0.9 gpm per pump and NOT decreasing:
- FR-62-23 [RCP 1 & 2]
- FR-62-49 [RCP 3 & 4]
- 3. GO TO appropriate plant procedure.
- 4. ENSURE RCP seal water supply flow IF seal water supply flow is less than 6 gpm between 6 gpm and 10 gpm per pump: AND CANNOT be restored, THEN
- Fl-62-IA ENSURE CCS supply to thermal barriers is
- Fl-62-14A less than 105°F on TR-70-161.
[CCS HX IA1!1A2 (2A1/2A2) Outlet Temp]
- Fl-62-27A
- Fl-62-40A Page 13 of 34
AOP-R.04 SQN REACTOR COOLANT PUMP MALFUNCTIONS Rev. 24 STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2.3 #1 Seal Leakoff Low Flow on ANY RCP 7 (cont d )
- 5. . CONTACT Engineering for recommendations WHILE continuing with this procedure.
- 6. ENSURE VCT pressure between 17 psig and 45 psig [P1-62-i 22].
- 7. CHECK RCP standpipe level alarms MONITOR the following:
DARK [M-5B, A-2, B-2, 0-2, D-2].
- Level, Ll-77-1
- Pressure, P1-77-2
- Temperature, Tl-77-21
Page 14 of 34
AOP-R.04 SQN REACTOR COOLANT PUMP MALFUNCTIONS Rev. 24 STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I 2.3 #1 Seal Leakoff Low Flow on ANY RCP (contd)
- 8. MONITOR #2 seal leakoff less than GO TO Section 2.4, #2 Seal Leakoff High or equal to 0.5 gpm USING Appendix A, Flow on ANY RCP.
RCDT Level Rate-of-Change.
- 9. MONITOR RCP lower bearing IF any of the following conditions met:
temperature and seal water temperature
- affected RCP lower bearing temp are stable and within limits or seal water temp rising uncontrolled (less than 225°F).
- affected RCP lower bearing temp and seal temp indication NOT available THEN GO TO Section 2.1, ANY RCP Tripped or RCP Shutdown Required. [C.1]
Page 15 of 34
AOP-R.04 SQN REACTOR COOLANT PUMP MALFUNCTIONS Rev. 24 STEP I ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED I 2.3 #1 Seal Leakoff Low Flow on ANY RCP (contd)
CAUTION: If low seal leakoff compensatory actions are NOT successful, seal failure may result as indicated by a sudden increase in seal leakoff flow (greater than 8 gpm).
NOTE: Plant shutdown may be terminated if Seal Leakoff flow stabilizes at greater than 0.8 gpm with pump Lower Bearing temperature and Seal Water Temperature remaining stable (no indications of seal failure).
- 10. MONITOR #1 seal leakoff flow INITIATE normal plant shutdown greater than 0.8 gpm: USING appropriate plant procedures.
- FR-62-23 [RCP I & 2] ENSURE affected RCP STOPPED within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
- FR-62-49 [RCP 3 & 4]
IF #1 seal leakoff flow reverts to high leakage (greater than 8.0 gpm):
- FR-62-24 {RCP 1 & 2]
- FR-62-50 [RCP 3 & 4]
THEN GO TO Section 2.1, ANY RCP Tripped or RCP Shutdown Required.
Page 16 of 34
AOP-R.04 SQN REACTOR COOLANT PUMP MALFUNCTIONS Rev. 24 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I 2.3 #1 Seal Leakoff Low Flow on ANY RCP (contd)
- 11. EVALUATE the following Tech Specs for applicability:
- 3.2.5, DNB Parameters
- 3.4.1.1, Reactor Coolant Loops and Coolant Circulation Startup and Power Operation o 3.4.1 .2, Reactor Coolant System -
Hot Standby
- 3.4.1.3, Reactor Coolant System -
Shutdown
- 3.4.6.2, RCS Operational Leakage
- 12. CHECK #1 seal leakoff flow GO TO Step 1.
greater than 0.9 gpm per pump and NOT decreasing:
- FR-62-23 [RCP l & 2]
- FR-62-49 {RCP 3 & 4]
- 13. GO TO appropriate plant procedure.
END OF SECTION Page 17 of 34
AOP-R.04 SQN REACTOR COOLANT PUMP MALFUNCTIONS Rev. 24 STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2.4 #2 Seal Leakoff High Flow on ANY RCP
- 1. EVALUATE RCP standpipe alarms:
- a. CHECK RCP standpipe level alarm(s) a. GO TO Step 2.
LIT [M-5B, window A-2, B-2, C-2, D-2].
- b. MONITOR RCDT parameters at Radwaste Panel [Aux Bldg, el. 669]:
- Level, Ll-77-1
- Pressure, P1-77-2
- Temperature, Tl-77-21
- c. FILL affected RCP standpipe USING AR-M-5B, Annunciator
Response
- RCP 1 [windowA-2]
- RCP 2 [window B-2]
- RCP 3 [window C-2]
- RCP 4 [window D-2]
- d. IF RCP standpipe level alarm clears, THEN GO TO Section 2.5, #3 Seal Leakoff High Flow on ANY RCP.
Page 18 of 34
[STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 1 2.4 #2 Seal Leakoff High Flow on ANY RCP (contd)
NOTE: A leakoff of greater than 0.5 gpm indicates that a seal problem exists.
- 2. MONITOR #2 seal INTACT PERFORM the following within 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />s:
on affected RCP:
- a. PERFORM normal plant shutdown
- VERIFY #2 seal eakoff USING appropriate plant procedure.
less than or equal to 0.5 gpm USING Appendix A, RCDT Level Rate-of-Change.
- b. WHEN reactor is shutdown or tripped,
- VERIFY RCP vibration is within limits THEN of annunciator response 1-AR-MS-A PERFORM the following:
(window D-3) VIBRATION & LOOSE PARTS MONITORING ALM. 1) STOP and LOCK OUT affected RCP.
- 2) PULL TO DEFEAT affected loop \T and T-avg:
- XS-68-2D (zT)
- XS-68-2M (T-avg)
- 3. CONSULT Engineering:
- a. NOTIFY Engineering to provide recommendations.
- b. EVALUATE need to consult with Westinghouse for continued RCP operation.
Page 19 of 34
AOP-R.04 SQN REACTOR COOLANT PUMP MALFUNCTIONS Rev. 24 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2.4 #2 Seal Leakoff High Flow on ANY RCP (contd)
- 4. CHECK RCPs 1 and 2 RUNNING. CLOSE affected loops pressurizer spray valve.
- 5. EVALUATE EPIP-1, Emergency Plan Initiating Conditions Matrix.
- 6. EVALUATE the following Tech Specs for applicability:
- 3.2.5, DNB Parameters
- 3.4.1.1, Reactor Coolant Loops and Coolant Circulation Startup and Power Operation
- 3.4.1 .2, Reactor Coolant System -
Hot Standby
- 3.4.1 .3, Reactor Coolant System -
Shutdown
- 3.4.6.2, RCS Operational Leakage
- 7. GO TO appropriate plant procedure.
END OF SECTION Page 20 of34
AOP-R.04 SON REACTOR COOLANT PUMP MALFUNCTIONS Rev. 24 STEP ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED 1 2.5 #3 Seal Leakoff High Flow on ANY RCP CHECK RCP standpipe level alarms PERFORM the following:
DARK [M-5B, A-2, B-2, C-2, D-2].
- a. MONITOR Cntmt Fl. & Eq. Sump Level rise rate (lOS pt. U0969)
- b. FILL affected RCP standpipe USING AR-.M-5B, Annunciator
Response
- RCP 1 {A.-2j
- RCP 2 [B-2j
- RCP3{C-2j
- RCP 4 {D-2]
Page 21 of34
SQN REACTOR COOLANT PUMP MALFUNCTIONS AOP-R.04 Rev. 24 STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I 2.5 #3 Seal Leakoff High Flow on ANY RCP (contd)
NOTE: A leakoff rate of greater than 500 cc/hr indicates that a seal problem exists.
The frequency and length of time filling the RCP standpipe may indicate the severity of the leak.
- 2. MONITOR #3 seal intact PERFORM the following within 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />s:
on affected RCP:
- a. PERFORM normal plant shutdown
- VERIFY RCP vibration is within limits USING appropriate plant procedure.
of annunciator response 1 -AR-M5-A (window D-3) VIBRATION & LOOSE PARTS MONITORING ALM.
- b. WHEN reactor is shutdown or tripped,
- CONTACT Engineering for THEN assistance in determining acceptable STOP and LOCK OUT affected RCP.
leak rate for continued RCP operation.
- c. PULL TO DEFEAT affected loop AT and T-avg:
- XS-68-2D (AT)
- XS-68-2M (T-avg)
- 3. CHECK RCPs 1 and 2 RUNNING. CLOSE affected loops pressurizer spray valve.
- 4. EVALUATE EPIP-1, Emergency Plan Initiating Conditions Matrix.
Page 22 of 34
AOP-R.04 SQN REACTOR COOLANT PUMP MALFUNCTIONS Rev. 24 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 25 #3 Seal Leakoff High Flow on ANY RCP (contd)
- 5. EVALUATE the following Tech Specs for applicability:
- 3.2.5, DNB Parameters
- 3.4.1.1, Reactor Coolant Loops and Coolant Circulation Startup and Power Operation
- 3.4.1.2, Reactor Coolant System-Hot Standby
- 3.4.1 .3, Reactor Coolant System -
Shutdown
- 3.4.6.2, RCS Operational Leakage
- 6. GO TO appropriate plant procedure.
END OF SECTION Page 23 of 34
AOP-R.04 SQN REACTOR COOLANT PUMP MALFUNCTIONS Rev. 24 STEP I ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED 2.6 RCP Motor Stator Temperature High CAUTION: Operating the RCP with excess winding temperature will reduce the expected life of the motor insulation.
NOTE: RCP motor winding temperature limits are as follows:
- 329°F if RCS temperature is less than 540°F.
- 311°F if RCS temperature is greater than or equal to 540°F.
- 1. MONITOR RCP Motor Stator temperature a. IF RCP Motor Stator temperature less than applicable limit by monitoring reaches applicable limit the following computer points: AND indication is verified valid, THEN
- Pump 1:T0409A,4llAor4l2A PERFORM the following:
- Pump 2: T0429A, 431Aor432A
- 1) IF reactor power less than 20%,
- Pump 3: T0449A, 451 A or 452A
- 2) IF reactor power greater than 20%,
THEN INITIATE plant shutdown at 24%
per minute USING AOP-C.03, Rapid Shutdown or Load Reduction.
Page 24 of 34
AOP-R.04 SQN REACTOR COOLANT PUMP MALFUNCTIONS Rev. 24 STEP I ACTiON/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2.6 RCP Motor Stator Temperature High (continued)
- 2. EVALUATE EPIP-1, Emergency Plan Initiating Conditions Matrix.
- 3. EVALUATE the following Tech Specs for applicability:
- 3.2.5, DNB Parameters
- 3.4.1.1, Reactor Coolant Loops and Coolant Circulation Startup and Power Operation
- 3.4.1 .2, Reactor Coolant System -
Hot Standby
- 3.4.1 .3, Reactor Coolant System -
Shutdown
- 3.4.6.2, RCS Operational Leakage
- 4. GO TO appropriate plant procedure.
END OF SECTION Page 25 of34
AOP-R.0 SQN REACTOR COOLANT PUMP MALFUNCTIONS Rev. 24 3.0 SYMPTOMS AND ENTRY CONDITIONS 3.1 Symptoms A. Any of the following annunciators may indicate a RCP malfunction:
PANEL 0-XA-55-27-B-A, COMPONENT COOLING D-2 RC PUMP 1 OIL COOLERS OUTLET FLOW LOW D-3 RC PUMP 2 OIL COOLERS OUTLET FLOW LOW D-4 RC PUMP 3 OIL COOLERS OUTLET FLOW LOW D-5 RC PUMP 4 OIL COOLERS OUTLET FLOW LOW PANEL 0-XA-55-27-B-E, COMPONENT COOLING/MISC D-2 RC PUMP 1 OIL COOLERS OUTLET FLOW LOW D-3 RC PUMP 2 OIL COOLERS OUTLET FLOW LOW D-4 RC PUMP 3 OIL COOLERS OUTLET FLOW LOW D-5 RC PUMP 4 OIL COOLERS OUTLET FLOW LOW PANEL 1(2)-XA-55-IB, AUXILIARY POWERISTATION SERVICE A-i 6900V UNIT BD 1 (2)A TRANSFER A-2 6900V UNIT BD 1(2)B TRANSFER A-3 6900V UNIT BD 1(2)C TRANSFER A-4 6900V UNIT BD 1(2)D TRANSFER B-i 6900V UNIT BD 1(2)A FAILURE OR UNDERVOLTAGE B-2 6900V UNIT BD 1(2)B FAILURE OR UNDERVOLTAGE B-3 6900V UNIT BD 1 (2)C FAILURE OR UNDERVOLTAGE B-4 6900V UNIT BD 1 (2)D FAILURE OR UNDERVOLTAGE E-3 MOTOR TRIPOUT PNL 1(2)-M-1 THRU 1(2)-M-6 Page 26 of34
AOP-R.04 SQN REACTOR COOLANT PUMP MALFUNCTIONS I Rev.24 3.1 Symptoms (contd)
PANEL XA-55-5A, REACTOR COOLANT STM - - FW A-6 TS-68-2M/N REACTOR COOLANT LOOPS T AVG/AUCT T AVG DEVN HIGH LOW-8-5 CNTMT FLOOR & EQUIP DRAIN SUMP HI-HI-HI B-6 TS-68-2AIB REACTOR COOLANT LOOPS T DEVN HIGH - LOW D-3 VIBRATION & LOOSE PARTS MONITOR ALARM PANEL XA-55-5B, CVCS SEAL WATER AND RCP A-2 LS-62-6A REAC COOL PMP 1 STANDPIPE LVL HIGH-LOW A-3 FS-62-1O REAC COOL PMPS SEAL LEAKOFF LOW FLOW A-4 PdIS-52-96 SEAL WATER INJECTION FILTER HIGH zP A-5 LS-68-IONB REAC COOL PMP 1 OIL RESERVOIR LEVEL HI-LOW B-2 LS-62-19A REAC COOL PMP 2 STANDPIPE LVL HIGH-LOW 8-3 FS-62-1 1 REAC COOL PMPS SEAL LEAKOFF HIGH FLOW 8-4 PdIS-62-97 SEAL WATER INJECTION FILTER 2 HIGH P B-5 LS-68-34A1B REAC COOL PMP 2 OIL RESERVOIR LEVEL HI-LOW C-2 LS-62-32A REAC COOL PMP 3 STANDPIPE LVL HIGH-LOW C-3 FS-62-1 REAC COOL PMPS SEAL WATER FLOW LOW C-5 LS-68-53A/B REAC COOL PMP 3 OIL RESERVOIR LEVEL HI-LOW D-2 LS-62-45A REAC COOL PMP 4 STANDPIPE LVL HIGH-LOW D-3 PdS-62-8 REAC COOL PMPS SHAFT SEAL WATER \P D-5 LS-68-76A1B REAC COOL PMP 4 OIL RESERVOIR LEVEL HI-LOW E-1 REAC COOL PMPS MOTOR STATOR TEMPERATURE HIGH E-2 TS-62-42 REAC COOL PMPS LOWER BEARING TEMP HIGH E.-3 REACTOR COOLANT PUMPS MOTOR THRUST BEARING TEMP HIGH E-4 TS-62-43 REAC COOL PMPS SEAL WATER TEMP HI E-5 FIS-62-12 RCP NO I SEAL BYPASS FLOW LOW Page 27 of 34
SQN REACTOR COOLANT PUMP MALFUNCTIONS AOP-R.04 I Rev.24 3.1 Symptoms (contd)
PANEL XA-55-6A COMPONENT COOLING A-4 FS-68-6A REACTOR COOLANT LOOP 1 LOW FLOW B-4 FS-68-29A REACTOR COOLANT LOOP 2 LOW FLOW C-4 FS-68-48A REACTOR COOLANT LOOP 3 LOW FLOW D-4 FS-68-71A REACTOR COOLANT LOOP 4 LOW FLOW E-4 RCP BUS UNDERFREQUENCY! UNDERVOLTAGE B. Deviations or unexpected indication on any of the following may indicate a RCP malfunction:
- 1. Erratic or abnormal RCP motor current
- 2. Erratic RCP motor frequency
- 3. Erratic or low RCS Loop Flow indications
- 4. Plant Computer RCP temperature alarms
- 5. Indication of high vibrations on a RCP
- 7. High or low RCP #1 Seal leakoff flow
- 8. High or low RCP #1 Seal supply flow
- 9. Increasing RCP #1 Seal temperature
- 10. Increasing RCP lower bearing temperature
- 11. High VCT temperature
- 12. High VCT pressure
- 13. High VCT level
- 14. Increasing Reactor Coolant Drain Tank level
- 15. High Containment Floor & Equipment Sump Level rate of rise Page 28 of 34
AOP-R.04 SON REACTOR COOLANT PUMP MALFUNCTIONS I Rev.24 3.1 Symptoms (contd)
C. Any of the following automatic actions may indicate a RCP malfunction:
- 1. RCP trip from motor faults
- 2. Reactor Trip -
- 3. Safety Injection 3.2 Entry Conditions None END OF SECTION Page 29 of 34
AOP-R.04 SQN REACTOR COOLANT PUMP MALFUNCTIONS Rev.24
4.0 REFERENCES
4.1 Performance A. EPIP-1, Emergency Plan Initiating Conditions Matrix B. E-O, Reactor Trip or Safety Injection C. AR-M-5B, Annunciator Response D. AOP-C.03, Rapid Shutdown or Load Reduction.
4.2 Technical Specifications A. 3.2.5, DNB Parameters B. 3.4.1.1, Reactor Coolant Loops and Coolant Circulation - Startup and Power Operation C. 3.4.1.2, Reactor Coolant System - Hot Standby D. 3.4.1.3, Reactor Coolant System - Shutdown E. 3.4.6.2, RCS Operational Leakage Page 30 of 34
AOP-R.04 SQN REACTOR COOLANT PUMP MALFUNCTIONS I Rev. 24 4.3 Plant Drawings A. 47W600, Sheets 57, 60 B. 47W610-68, Sheets 1, 2, 3,4, 6 C. 47W610-77-3 D. 47W610-62-2 E. 47W610-72-1 F. 47W610-74-l G. 47W610-63-1 H. 47W610-67-1 I. 47W610-3-3 J. 47W610-70-1 K. 47W610-30-2 L. 47W610-47-1 M. 47W610-82-1 N. 45N765, Sheets 1,2
- 0. 45N724, Sheets 1, 2, 3,4 P. 45N751, Sheets 1,2, 3,4,5, 6,7, 8 Q. 45N732, Sheets 1,2 4.4 IOCFR A. 10CFR5O, Appendix R Page 31 of34
SQN REACTOR COOLANT PUMP MALFUNCTIONS AOP-R.04 Rev.24 Page 1 of I APPENDIX A RCDT LEVEL RATE OF CHANGE CALCULATE RCDT level rate of change to obtain #2 seal leakoff flowrate.
Instrument Used: ICS point L2400MA D LI771 [AB el. 669, Pnl O-L-2] J gal Time Initial Level Initial Volume gal Time Final Level Final Volume FINAL VOLUME (gal) INITIAL VOLUME (gal)
= LEVEL RATE OF CHANGE t TIME (minutes)
REACTOR COOLANT DRAIN TANK (RCDT) LEVEL VS.
VOLUME Level (%) Volume (Gal) Level (%) I Volume (Gal) Level (%) Volum I e (Gal) Level (%) Volume (Gal) 0.0 17.4 25.0 86.4 50.0 179.1 75.0 271.8 1.0 19.4 26.0 89.8 51.0 182.9 76.0 275.2 2.0 21.6 27.0 93.3 52.0 186.8 77.0 278.5 3.0 23.8 28.0 96.8 53.0 190.6 78.0 281.7 4.0 26.1 29.0 100.4 54.0 194.5 79.0 285.0 5.0 28.4 30.0 103.9 55.0 198.3 80.0 288.2 6.0 30.8 31.0 107.5 56.0 202.2 81.0 291.3 7.0 33.3 32.0 111.2 57.0 206.0 82.0 294.4 8.0 35.8 33.0 114.8 58.0 209.9 83.0 297.5 9.0 38.4 34.0 118.5 59.0 213.7 84.0 300.5 10.0 41.1 35.0 122.2 60.0 217.4 85.0 303.4 11.0 43.7 36.0 125.3 61.0 221.2 86.0 306.2 12.0 46.4 37.0 129.5 62.0 224.9 87.0 309.1 13.0 49.2 38.0 133.3 63.0 228.7 88.0 311.8 14.0 52.0 39.0 137.1 64.0 232.4 89.0 314.5 15.0 54.9 40.0 140.9 65.0 236.1 90.0 317.2 16.0 57.7 41.0 144.6 66.0 239.8 91.0 319.9 17.0 60.8 42.0 148.4 67.0 243.5 92.0 322.4 18.0 63.8 43.0 152.2 68.0 247.2 93.0 324.9 19.0 66.8 44.0 156.0 69.0 250.8 94.0 327.4 20.0 69.9 45.0 159.8 70.0 254.4 95.0 329.8 21.0 73.2 46.0 163.7 71.0 257.9 96.0 332.1 22.0 76.4 47.0 167.5 72.0 261.5 97.0 334.4 23.0 79.6 48.0 171.4 73.0 265.0 98.0 336.7 24.0 83.0 49.0 175.2 74.0 268.4 99.0 338.7 100.0 340.8 Page 32 of 34
SQN REACTOR COOLANT PUMP MALFUNCTIONS AOP-R.04 Rev. 24 COMMITMENT LIST
SUMMARY
OF COMMITMENT COMMITMENT ID COMMITMENT CORRESPONDENCE C.1 Provide clear instructions to the NER 82-005 operators should any seal temperature, pressure, or leakage INPO SOER 81-007 alarms annunciate. Include conditions for continued operation or immediate INPO SOER 82-005 shutdown.
C.2 Update procedural guidance to NER 930512001 conform to most recent Westinghouse recommendations on RCP shutdown Westinghouse Tech Bulletin with No. 1 seal leakage outside the NSD-TB-93-01-R1 operating limits.
0.3 Update procedural guidance to include NER 970134001 RCP vibration as a limitation. TROI INPO SER 97002 Page 34 of 34
JPM Sim E Page 1 of 1 Rev. 0 SEQUOYAH NUCLEAR PLANT September 2010 NRC Exam SIM E (RO\SRO)
Respond to High Containment Pressure, Place RHR Spray in Service
Task:
Task#:
Task Standard:
Time Critical Task KIA ReferencelRa Method of Testinç Simulated Perforn Evaluation Metho Simulator Main Control Roo, Performer:
Evaluator:
Performance Ratin Validation Time:
Performance Time:
JPM Sim E Page 3 of 3 Rev. 0 SPECIAL INSTRUCTIONS TO EVALUATOR:
- 1. Critical Steps are identified in step SAT/UNSAT column by bold print Critical Step.
- 2. Any UNSAT requires comments
- 3. Initialize simulator in IC#62. If IC#62 is not available the reset to IC #24 and complete substeps below.
- a. Activate MF # THOIA at 35%.
- b. Activate MFs # CHOI A thru D at 70% (-10.2 psid) with 240 sec ramp.
- d. Activate Override ZDIHS724IA CLOSE, to prevent FCV-72-41 from opening.
- e. Activate ZAOPDI3OI33 f:5
- f. Activate ZAOPDIR3OI33 f:0.5
- 4. Activate the following, as necessary, to prevent nuisance alarms:
- 1. AN:OVRN[96] to ON, prevents Turbine Zero Speed alarm
- 2. AN:OVRN[304] to ON, prevents Saturation Monitor alarm
- 5. Insert Remote Function RHRI4 ON, places power on FCV-63-1.
- 6. FREEZE the simulator until the operator is ready to commence task.
- 7. Console operator will need to acknowledge alarms not associated with JPM
- 8. At JPM step 15, when candidate opens 1-FCV-72-40:
- a. Modify malfunction CHOIA f:0 r:240 k:1
- b. Modify malfunction CHO1 B f:0 r:240 k:1
- c. Modify malfunction CHO1B f:0 r:240 k:1
- d. Modify malfunction CHO1D f:0 r:240 k:1
- 9. Ensure operator performs the following required actions for 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.
Tools/EquipmentlProcedures Needed:
FR-Z.1, step 14
References:
Reference Title Rev No.
- 1. FR-Z.1 High Containment Pressure 19
JPM Sim E Page 4 of 4 Rev. 0 READ TO OPERATOR Directions to Trainee:
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 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 1 has experienced a reactor trip and Safety Injection in conjunction with a large break LOCA.
- 2. The crew has been monitoring step 13 of FR-Z.1 since FR-Z.1 was implemented.
- 3. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> has elapsed since the accident.
INITIATING CUES:
- 1. You are the Unit 1 QATC and the SRO directs you to initiate one train of RHR spray per FR Z.1 starting at step 13.
JPM Sim E Page 5 of 5 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT Evaluator Note: FR-Z.1, High Containment Pressure, step 13 contains the steps for this JPM.
STEP 1.: Obtain copy of appropriate procedure.
Cue: After operator locates FR-Z. I procedure, provide a copy SAT of FR-Z. I marked up as appropriate. UNSAT STANDARD: Operator obtains a copy of FR-Z.1 (begin at Step 13).
Start Time COMMENTS:
STEP 2.: [FR-Z.1, Step 13] MONITOR if RHR Spray should be placed in service:
- a. CHECK the following:
. Containment press greater than 9.5 psid.
SAT UNSAT STANDARD: Operator checks 1-PDI-30-45 and 44 and determines that pressure is greater than 9.5.
COMMENTS:
STEP 3.: [FR-Z.1, Step 13] MONITOR if RHR Spray should be placed in service:
- a. CHECK the following:
. at least 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> has elapsed since beginning of accident.
Cue: IF asked, 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> has elapsed since beginning of accident. SAT UNSAT STANDARD: Operator determines from initiating cues (or asks US) that 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> has elapsed.
COMMENTS:
JPM Sim E Page 6 of 6 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 4.: [FR-Z.1, Step 13] MONITOR if RHR Spray should be placed in service:
- a. CHECK the following:
. RHR suction ALIGNED to containment sump.
Cue: IF asked, ES-13 has been completed. SAT UNSAT STANDARD: Operator checks FCV-63-72 and 73 OPEN and FCV 74-3 and 21 CLOSED, or asks US if ES-I .3, Transfer to RHR Containment Sump, has been completed.
COMMENTS:
STEP 5.: [FR-Z.I, Step 13] MONITOR if RHR Spray should be placed in service:
- a. CHECK the following:
. At least one CCP AND one SI pump running.
STANDARD: Operator verifies at least one CCP is running as SAT indicated by Red light on HS-62-I 04A or I 08A LIT. UNSAT AND Verifies at least one SI pump is running as indicated by Red lights on HS-63-IOA or 15A LIT.
COMMENTS:
STEP 6.: 13.b CHECK both RHR pumps RUNNING.
STANDARD: Operator checks that both RHR pumps are running as indicated by red lights on HS-74-IOA and 20A LIT.
UNSAT COMMENTS:
JPM Sim E Page 7 of 7 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 7.: [13.cJ ESTABLISH Train B RHR spray:
[13.c.1j CHECK Train B RHR pump RUNNING.
SAT STANDARD: Operator checks that I B-B RHR pump is running as indicated UNSAT by red light on HS-74-20A LIT.
COMMENTS:
STEP 8.: [13.c] ESTABLISH Train B RHR spray:
[13.c.2] ENSURE RHR crosstie FCV-74-35 CLOSED.
STANDARD: Operator verifies FCV-74-35 in the CLOSED position SAT as indicated by HS green light ON and red light OFF. UNSAT COMMENTS:
STEP 9.: [13.c] ESTABLISH Train B RHR spray:
[1 3c.31 QLQSE RHJnjectionFCV-63-94.,
STANDARD: Operator places handswitch for RHR injection FCV-63-94 in the CLOSED position and verifies the green light ON. _SAT UNSAT This step is critical to ensure the I B-B RHR discharge is isolated from the cold leg injection flowpath. Critical Step COMMENTS:
Evaluator NOTE: The next step starts the alternate path.
JPM Sim E Page 8 of 8 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 10.: [13.c.4] OPEN RHR Spray FCV-72-41.
STANDARD: Operator places handswitch for RHR injection FCV 41 in the OPEN position and recognizes that the green light stays ON and the red light is OFF, goes to RNO _SAT column. UNSAT COMMENTS:
Evaluator NOTE: The following steps are from FR-Z.1, step 13.c RNO STEP 11.: [13.c RNO a] ENSURE RHR Spray FCV-72-41 CLOSED.
STANDARD: Operator verifies FCV-72-41 is still closed as indicated SAT by green light ON and red light OFF. UNSAT COMMENTS:
STEP 12 [13 c RNO bi IF RHR aligned for cold leg recirculation THEN ENSURE FCV-63-94 OPEN STANDARD: Operator places handswitch for RHR injection FCV-63-94 in SAT the OPEN position and verifies red light ON.
UNSAT This step is critical to realign the 1 B-B RHR pump back into the CL injection mode as it cannot be used for RHR spray at this time. Critical Step COMMENTS:
JPM Sim E Page 9 of 9 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 13.: [13.c RNO c.1] ESTABLISH Train A RHR spray:
ENSURE RHR crosstie FCV-74-33 CLOSED.
STANDARD: Operator verifies RHR crosstie FCV-74-33 in the SAT CLOSED position as indicated by green light ON UNSAT handswitch.
COMMENTS:
STEP 14 [13 c RNO c 21 CLOSE RHR Injection FCV-63-93 STANDARD: Operator places handswitch for RHR injection FCV 93 in the CLOSED position and recognizes that the red light goes OFF and the green light is LIT, continues in the RNO column. SAT UN SAT This step is critical because the operator must determine that Train A RHR spray can be placed in service and continues with step 14.c RNO to realign Train A RHR Critical Step to cold leg injection.
COMMENTS:
Simulator Operator Note: When candidate starts to open FCV-72-40, initate a 240 sec ramp on CHO1 A thru D to reduce CNMT pressure from 10.2 to zero (0).
JPM Sim E Page 10 of 10 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 15 1 30 RNO c 3] OPEN RHR spray FCV-72-40 STANDARD: [a] Operator places handswitch for RHR spray FCV-72-40 in OPEN position and recognizes that the red light goes OFF and the green light is LIT. SAT UNSAT Critical step to complete flow path from A RHR pump to spray header.
Critical Step COMMENTS:
STEP 16.: Operator verifies that RHR Containment spray is affective in lowering CNMT pressure.
STANDARD: Operator verifies that CNMT pressure is lowering by SAT observing Lower pressure readings on CHOIA thru D UNSAT COMMENTS:
STEP 17.: Communicates with SRO and informs him/her of status of RHR spray.
STANDARD: Operator informs US that Train B RHR spray could not be SAT established however, Train A RHR spray was placed in UNSAT service in accordance with FR-Z.1, step 13.
COMMENTS:
Stop Time CUE: This completes the JPM END OF JPM
READ TO OPERATOR Directions to Trainee:
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 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 I has experienced a reactor trip and Safety Injection in conjunction with a large break LOCA.
- 2. The crew has been monitoring step 13 of FR-Z.I since FR-Z.1 was implemented.
- 3. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> has elapsed since the accident.
INITIATING CUES:
I. You are the Unit 1 OATC and the SRO directs you to initiate one train of RHR spray per FR-Z.1 starting at step 13.
READ TO OPERATOR Directions to Trainee:
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 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 I has experienced a reactor trip and Safety Injection in conjunction with a large break LOCA.
- 2. The crew has been monitoring step 13 of FR-Z.1 since FR-Z.I was implemented.
- 3. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> has elapsed since the accident.
INITIATING CUES:
- 1. You are the Unit I OATC and the SRO directs you to initiate one train of RHR spray per FR-Z.1 starting at step 13.
- TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT EOI PROGRAM MANUAL FUNCTION RESTORATION PROCEDURE FR-LI HIGH CONTAINMENT PRESSURE Revision 19 QUALITY RELATED PREPARED/PROOFREAD BY: D. A. PORTER RESPONSIBLE ORGANIZATION: OPERATIONS APPROVED BY: W. T. Lean, EFFECTIVE DATE: 12/16/09 REVISION DESCRIPTION: Revised to delete hydrogen mitigation step. This step is no longer needed in this procedure as a result of PER 137597.
Revised setpoint S.04 from 25 gpm to 50 gpm (PER 155417).
Simplified Step 5.a based upon training feedback.
This procedure contains a Handout Page (2 copies).
FR-Z.1 SQN HIGH CONTAINMENT PRESSURE Rev. 19 HANDOUT Page 1 of 1 STEP ACTION
- 1. MONITOR RWST level greater than 27%.
4.d (if any S!G is faulted and air return fans are NOT running)
RNO WHEN 10 minutes have elapsed from Phase B actuation, THEN ENSURE containment air return fans running.
- 6. MONITOR containment air return fans:
. WHEN 10 minutes have elapsed from Phase B actuation, THEN ENSURE containment air return fans running.
- 11. IF all SIGs Faulted, RNO. THEN CONTROL feed flow at greater than or equal to 50 gpm to each SIG.
- 13. MONITOR if RHR spray should be placed in service:
- Containment pressure greater than 9.5 psig
- AND at least 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> has elapsed since beginning of accident
13.d. (if RHR spray in service)
RNO WHEN Containment pressure is less than 4 psig, THEN REMOVE RHR spray from service.
- 14. MONITOR if containment spray should be stopped:
(containment pressure less than 2.0 psig) 14.c (if containment spray suction aligned to sump)
RNO WHEN directed by TSC, THEN STOP containment spray.
1 a of 13
FR-Z.l SQN HIGH CONTAINMENT PRESSURE Rev. 19 HANDOUT Page 1 of 1 STEP ACTION
- 1. MONITOR RWST level greater than 27%.
4.d (if any S!G is faulted and air return fans are NOT running)
RNO WHEN 10 minutes have elapsed from Phase B actuation, THEN ENSURE containment air return fans running.
- 6. MONITOR containment air return fans:
. WHEN 10 minutes have elapsed from Phase B actuation, THEN ENSURE containment air return fans running.
- 11. IF all S/Gs Faulted, RNO. THEN CONTROL feed flow at greater than or equal to 50 gpm to each SIG.
- 13. MONITOR if RHR spray should be placed in service:
- Containment pressure greater than 9.5 psig
- AND at least 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> has elapsed since beginning of accident
13.d. (if RHR spray in service)
RNO WHEN Containment pressure is less than 4 psi ,
9 THEN REMOVE RHR spray from service.
- 14. MONITOR if containment spray should be stopped:
(containment pressure less than 2.0 psig) 14.c (if containment spray suction aligned to sump)
RNO WHEN directed by TSC, THEN STOP containment spray.
lb of 13
FR-Z.1 SQN HIGH CONTAINMENT PRESSURE I Rev. 19 1.0 PURPOSE This procedure provides actions to respond to a high containment pressure.
2.0 SYMPTOMS AND ENTRY CONDITIONS 2.1 ENTRY CONDITIONS FR-O Status Trees:
- F-O.5, Containment RED condition:
Containment pressure greater than or equal to 12.0 psig.
- F-0.5, Containment ORANGE condition:
Containment pressure less than 12.0 psig AND Containment pressure greater than or equal to 2.8 psig.
3.0 OPERATOR ACTIONS Page 2 of 13
FR-Z.1 SQN HIGH CONTAINMENT PRESSURE Rev. 19 STEP( IACTIONIEXPECTED RESPONSE (RESPONSE NOTOBTAINED 1 If this procedure has been entered for an orange path and performance of ECA-i .1 (Loss of RHR Sump Recirculation) is required, FR-Z.i may be performed concurrently with ECA-i .1.
MONITOR RWST level IF ES-i .3 has NOT been entered, greater than 27%. THEN GO TO ES-i .3, Transfer to RHR Containment Sump.
-I--
VERIFY Phase B valves CLOSED: IF i-FCV-32-iiO (2-FCV-32-ill) is NOT closed,
- Panel 6K PHASE B GREEN THEN PERFORM EA-32-3, Isolating
- Panel 6L PHASE B GREEN. Non-Essential Air to Containment.
IF other valves NOT closed AND flow path is NOT necessary, THEN CLOSE valves.
ENSURE RCPs STOPPED.
Page 3 of 13
FR-Z.l SQN HIGH CONTAINMENT PRESSURE Rev. 19
[ESPONSENOT0BTAINED ISTEPI ACTION/EXPECTED RESPONSE 4 DETERMINE if this procedure should be exited:
for faulted S!G: OTO Step 5.
- Any SIG pressure DROPPING in an uncontrolled manner OR
- Any S/G pressure less than 140 psig.
- b. CHECK containment pressure b. GO TO Step 5.
less than 12 psig.
- c. IF containment pressure is
- c. CHECK at least one containment greater than 2.8 psig, spray pump RUNNING and THEN delivering flow. GO TO Step 5.
- d. WHEN 10 minutes have elapsed
- d. CHECK at least one containment from Phase B actuation, air return fan RUNNING. THEN ENSURE air return fans RUNNING.
- e. RETURN to procedure and step in effect.
Page 4 of 13
FR-Z.l SQN HIGH CONTAINMENT PRESSURE Rev. 19 ISTEPI IACTIONIEXPECTED RESPONSE [RESPONSE NOT OBTAINED VERIY containment spray operation:
ECA-1.1, Loss of RHR Sump Recirculation, is IN EFFECT, THEN PERFORM the following:
- 1) OPERATE containment spray as directed by ECA-i.1.
- 2) GO TO Step 6.
/
%VERIFY containment spray pumps b. IF containment pressure is RUNNING. greater than 2.8 psig, THEN START containment spray pumps.
c CHECK RWST level c. IF any of following conditions met:
greater than 27%.
- RWST level less than or equal to 8%
- containment sump level greater than 56%,
THEN PERFORM the following:
- 1) ENSURE cntmt spray pump suction aligned for sump recirc USING ES-i .3, Transfer to RHR Containment Sump, Step 21.
- 2) GO TO Substep 5.e.
(step continued on next page)
Page 5 of 13
FR-Z.1 SQN HIGH CONTAINMENT PRESSURE Rev. 19 ISTEPI ACTIONIEXPECTED RESPONSE I IRESPONSE NOT OBTAINED 7 IFY containment spray suction d. ALIGN valves as necessary.
ALIGNED to RWST:
- FCV-72-22 OPEN
- FCV-72-21 OPEN.
/
- e. VERIFY containment spray discharge e. OPEN valves for running valves OPEN: containment spray pumps.
/
- FCV-72-39
- FCV-72-2.
/
VERIFY containment spray recirc f. CLOSE valves as necessary.
valves CLOSED:
- FCV-72-34
- FCV-72-13.
VERIFY containment spray flow g. IF NO train of containment spray greater than 4750 gpm is available, on each train. THEN PERFORM the following:
- 1) CONTINUE efforts to restore at least one train of containment spray.
- 2) NOTIFY TSC to evaluate restoring normal containment cooling USING EA-30-4, Restoring Containment Coolers.
Page 6 of 13
FR-Z.1 SQN HIGH CONTAINMENT PRESSURE Rev. 19 I STEP I ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED MONITOR containment air return fans:
- WHEN at least 10 minutes have elapsed from Phase B, THEN ENSURE containment air return fans RUNNING.
/
VERIFY containment ventilation dampers CLOSE dampers.
CLOSED:
- Panel 6K CNTMT VENT GREEN
- Panel 6L CNTMT VENT GREEN.
VERIFY Phase A valves CLOSED: IF flow path NOT necessary, THEN
- Panel 6K PHASE A GREEN CLOSE valves.
- Panel 6L PHASE A GREEN.
VERIFY cntmnt vacuum relief isolation IF containment pressure is valves CLOSED: [Pnl 6K MANUAL] greater than 1.5 psig, THEN
- FCV3046 CLOSE valves. [M-9]
- FCV-30-47
- FCV-30-48.
VERIFY MSlVs and MSIV bypass valves CLOSE valves.
!/J CLOSED.
IF any MSIV CANNOT be closed, THEN CLOSE MSIV locally USING EA-1-1, Closing MSIVs Locally.
Page 7 of 13
FR-Z.1 SQN HIGH CONTAINMENT PRESSURE Rev. 19 I STEP ACTION/EXPECTED RESPONSE I I RESPONSE NOT OBTAINED DETERMINE if any S/G Intact: IF all S!Gs Faulted, THEN CHECK at least one S!G pressure: PERFORM the following:
- CONTROLLED or RISING 1) CONTROL feed flow at greater than or equal to 50 gpm to each SIG.
AND
- Greater than 140 psig.
- 3) GO TO Step 13.
Isolating all S/Gs will result in a loss of secondary heat sink.
DETERMINE if any SIG Faulted:
CHECK SIG pressures: . GO TO Step 13.
- Any S!G pressure DROPPING in an uncontrolled manner OR
- Any S/G pressure less than 140 psig.
- b. ISOLATE feed flow to affected SIG:
- AFW Page 8 of 13
FR-Z.1 SQN HIGH CONTAINMENT PRESSURE Rev. 19 STEPI IACTION/EXPECTED RESPONSE 1 IRESPONSE NOT OBTAINED
- 13. MONITOR if RHR spray should be placed in service:
- a. CHECK the following: a. GO TO Step 14.
- Containment pressure greater than 9.5 psig AND
- At least 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> has elapsed since beginning of accident AND
- 2) PLACE non-operating CCP in PULL TO LOCK.
- 4) PLACE non-operating SI pump in PULL TO LOCK.
(Step continued on next page.)
Page 9 of 13
FR-Z.1 SQN HIGH CONTAINMENT PRESSURE Rev. 19 ISTEPI ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I
- 1) CHECKTraIn B RHR pump THEN RUNNING. PERFORM the following:
- 4) OPEN RHR spray FCV-72-41. ENSURE FCV-63-94 OPEN.
c) ESTABLISH Train A RHR spray:
(1) ENSURE RHR crosstie FCV-74-33 CLOSED.
(2) CLOSE RHR injection FCV-63-93.
(3) OPEN RHR spray FCV-72-40.
IF Train A RHR spray CANNOT be established, THEN PERFORM the following:
a) CLOSE RHR spray FCV-72-40.
b) IF RHR aligned for cold leg recirculation, THEN ENSURE FCV-63-93 OPEN.
(Step continued on next page.)
Page 10 of 13
FR-Z.1 SQN HIGH CONTAINMENT PRESSURE Rev. 19 I STf] I ACTION/EXPECTED RESPONSE 1 I RESPONSE NOT OBTAINED 1
- 13. d. MONITOR containment pressure d. WHEN containment pressure is greater than 4 psig. less than 4 psig, THEN PERFORM the following:
- 1) ENSURE FCV-72-40 and FCV-72-41 CLOSED.
- 2) IF RHR aligned for cold leg recirculation, THEN ENSURE FCV-63-93 and FCV-63-94 OPEN.
- 3) IF ECCS is aligned for hot leg recirculation, THEN ENSURE RHR crosstie valves FCV-74-33 and FCV-74-35 aligned as required by ES-i .4.
Page 11 of 13
SQN HIGH CONTAINMENT PRESSURE ISTEP] ACTION/EXPECTED RESPONSE IRESPONSE NOT OBTAINED
- 14. MONITOR if containment spray should be stopped:
- a. CHECK any containment spray pump a. GO TO Step 15.
RUNNING.
- b. CHECK containment pressure b. GO TO Step 15.
less than 2.0 psig.
- c. CHECK containment spray suction c. NOTIFY TSC to determine aligned to RWST. when one or both trains of cntmt spray should be stopped.
WHEN directed by TSC, THEN PERFORM Substeps 14.d through 14.f.
GO TO Step 15.
- d. RESET Containment Spray.
- e. STOP containment spray pumps and PLACE in A-AUTO.
- f. CLOSE containment spray discharge valves:
- FCV-72-39, Train A
- FCV-72-2, Train B.
Page 12 of 13
FR-Z.1 SQN HIGH CONTAINMENT PRESSURE Rev. 19 I STEP J ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED RETURN TO procedure and step in effect.
Page 13 of 13
JPM Sim F Page 1 of 1 Rev. 0 SEQUOYAH NUCLEAR PLANT September 2010 NRC Exam SIM F (ROSRO)
CALIBRATE POWER RANGE NUCLEAR INSTRUMENTATION
JPM Sim F Page 2 of 2 Rev. 0 ROISRO JOB PERFORMANCE MEASURE Task: Calibrate the Power Range Nuclear Instrumentation Task#: 0150050201 (RO)
Task Standard: 1) Each channel of Power Range instrumentation (on its power range A drawer) will indicate within acceptance criteria tolerances of the calorimetric.
- 2) The unit is not tripped by a power range neutron flux rate trip.
Time Critical Task: YES: NO: X KlAReferencelRatings: 015000 A4.02 (3.9-3.9) 015020 G13 (3.3-3.6) 015020 G9 (3.4 3.3) 015000 Al .01 (3.5 3.8)
Method of Testing:
Simulated Performance: Actual Performance: X Evaluation Method:
Simulator X In-Plant Classroom Main Control Room Mock-up Performer:
Trainee Name Evaluator: I Name I Signature DATE Performance Rating: SAT: UNSAT:
Validation Time: 21 minutes Total Time:
Performance Time: Start Time: Finish Time:
COMMENTS
JPM Sim F Page 3 of 3 Rev. 0 SPECIAL INSTRUCTIONS TO EVALUATOR:
- 1. Critical steps are identified in step SAT/UNSAT column by bold print Critical Step.
- 2. This task is to be performed using the simulator in IC #116.
[Rx Power should be 100 %]
- 3. MANUALLY ADJUST N-41 and N-43 power to between 100.5 and 101 .0%. ENSURE all other NIS reactor power indications are between 99.5 and 100.5%.
- 4. After making the adjustments to N-41 and N-43 Log the pot settings for each NI:
N41 N42 N43 N44
- 5. Ensure operator performs the following required actions for 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.
ToolslEquipmentlProcedures Needed:
0-Sl-OPS-092-078.0, Sections 3.0, 6.1, 6.2, Appendix D
References:
Reference Title Rev No.
- 1. O-Sl-OPS-092-078.0 Power Range Neutron Flux Channel Calibration By 21 Heat Balance Comparison
JPMSimF Page 4 of 4 Rev. 0 READ TO OPERATOR Directions to Trainee:
I will explain the initial conditions, and state the task to be performed. All control room steps shall be performed for this JPM. 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:
The unit is at steady state conditions with all NIS channels and LEFM operable.
INITIATING CUES:
- 1. The US has directed you to perform 0-Sl-OPS-092-078.0.
- 2. Section 4.0 of 0-Sl-OPS-092-078.0 has been completed.
- 3. Notify the US when the SI has been completed and any necessary adjustments have been made.
JPM Sim F Page 5 of 5 Rev. 0 Job Performance Checklist STEPISTANDARD SATIUNSAT STEP 1.: Obtain the appropriate procedure. SAT UNSAT STANDARD: Operator obtains 0-Sl-OPS-092-078.0 and goes to section 6.0 Performance.
STEP 2.: [1]VERIFY availability of LEFM calorimetric power...
UNSAT Cue: Per initial conditions, LEFM calorimetric power is available.
STANDARD: Operator pulls up LEFM ICS screen and annotates procedure that LEFM calorimetric power is available.
COMMENTS:
STEP 3.: [2] IF LEFM calorimetric power NOT available OR ICS SAT computer NOT available, THEN....
UNSAT Cue: Per initial conditions, ICS and LEFM calorimetric power are available.
STANDARD: Operator marks step N/A.
COMMENTS:
STEP 4.: [3] DETERMINE reactor core power level by performing the applicable appendix below.
UNSAT STANDARD: Operator goes to Appendix A.
COMMENTS:
JPM Sim F Page 6 of 6 Rev. 0 Job Performance Checklist STE PISTAN DARD SAT/UNSAT EVALUATOR NOTE: The following steps are from Appendix A.
STEP 5.: [1] ENSURE SIG blowdown flows are updated by performing SAT the following functions on ICS:
UNSAT
[1.2] SELECT CALORIMETRIC FUNCTION MENU.
[1.3] SELECT UPDATE OPERATOR ENTERED BLOWDOWN FLOW Cue: The blowdown flow point is updating and manual blowdown flows are not required.
STANDARD: Operator determines blowdown flow is updating, initials step 1.3.1 A and marks steps 1.3.1 B and 1.3.2 N/A.
COMMENTS:
NOTE: The operator should transition back to section 6.1 at the completion of App A.
STEP 6.: [2] SELECT DISPLAY CURRENT CALORIMETRIC DATA SAT on ICS Calorimetric menu AND PERFORM one of the UNSAT following:
[a] RECORD U21 18 AND UI 127 OR
[b] PRINT power levels and NIS values.
Cue: Recording the numbers displayed from ICS is preferred.
U2118 is 3455 MW and U1127 is 100OO%.
STANDARD: Operator records U21 18 and UI 127 or prints a copy from ICS.
COMMENTS:
JPM Sim F Page 7 of 7 Rev. 0 Job Performance Checklist STEPISTANDARD SATIUNSAT EVALUATOR NOTE: The following steps are from Section 6.1. The values for each pot setting are on the setup page.
STEP 7.: [4] RECORD AS FOUND power level from each of the four SAT NIS A Channel drawers:
UNSAT POWER RANGE CHANNEL AS-FOUND NIS POWER (%)
N-41 (Xl-92-5005B)
N-42 (Xl-92-5006B)
N-43 (Xl-92-5007B)
N-44 (Xl-92-5008B)
STANDARD: Operator records NIS power range readings from the A channel drawers.
COMMENTS:
STEP 8.: [5]COMPARE NIS indication with core thermal power level. SAT UNSAT AND CHECK appropriate box to indicate whether the indicated NIS power level recorded in step 6.1[4] is equal to the core thermal power level recorded in step 6.1[3] to within +/- 2%.
STANDARD: Operator CHECKS to determine if NIS channels are within +/- 2%. Checks YES for all NIS channels and signs step completion.
COMMENTS:
JPM Sim F Page 8 of 8 Rev. 0 Job Performance Checklist STEPISTANDARD SAT/UNSAT STEP 9.: [6] VERIFY that all NIS channel indications are within +/- 3 % of SAT the determined core thermal power level.
UNSAT STANDARD: Operator checks the YES box.
COMMENTS:
STEP 10.: [7] IF a NIS channel was more than 3 percent in error in the SAT non-conservative direction (core thermal> NIS) THEN UNSAT STANDARD: Operator marks this step N/A.
COMMENTS:
STEP 11.: to
[8] CHECK;approprite box indicate whether the dici SAT NIS power level recorded in step 6 1 [4] is less than or UNSAT
¶equal to 100.5%.
Critical Step STANDARD: The operator checks NO for N-41 and N-43 and checks YES for N-42 and N-44.
Critical step because operator needs to be able to identify which channels will need to be adjusted.
COMMENTS:
JPM Sim F Page 9 of 9 Rev. 0 Job Performance Checklist STEPISTANDARD SATIU NSAT STEP 12.: [9] IF any NIS channels were inoperable during the performance of this instruction, THEN U NSAT STANDARD: The operator N/As this step.
COMMENTS:
STEP 13.: [10] IF any NIS channel does not meet acceptance criteria (step 6.1 [5] and/or step 6.1 [8]), SAT UNSAT OR NIS Channel Adjustment is desired, THEN
. PERFORM adjustment using Section 6.2 STANDARD: The operator initials this step and proceeds to Section 6.2.
COMMENTS:
EVALUATOR NOTE: The following steps are from Section 6.2 STEP 14.: [1] IF calculated average power in Section 6.1 or on printed SAT copy differs by more than 3% from average RCS delta T, U N SAT THEN...
NOTIFY Engineering to determine the cause STANDARD: Operator N/As this step.
COMMENTS:
JPM Sim F Page 10 of 10 Rev. 0 Job Performance Checklist STEPISTANDARD SATIUNSAT STEP 15.: [2] VERIFY reactor power has remained constant (+/- 0.5%) SAT since performance of section 6.1.
UNSAT STANDARD: Operator verifies power has remained stable since he/she took the readings by observing NIS readings and/or Ave Thermal Power has not changed since start of task.
COMMENTS:
STEP 16.: [3] IF NIS power range channel is inoperable, THEN.... SAT UNSAT STANDARD: Operator N/As this step since all channels are operable.
COMMENTS:
STEP 17.: [4] ENSURE all NIS power range channels are operable or SAT bypassed with no bistables tripped.
UNSAT STANDARD: Operator verifies no bistables tripped or bypassed.
(Initial conditions had all channels operable)
COMMENTS:
JPM Sim F Page 11 of 11 Rev. 0 Job Performance Checklist STEP/STAN DARD SAT/UNSAT STEP 18 [51 ENSURE rod control system is in MANUAL in accordance SAT with O-SO-85-1 UNSAT Critical Step STANDARD: Operator turns HS-85-51 10 to the MANUAL position.
This step is critical to ensure no automatic rod movement during NIS adjustments.
COMMENTS:
STEP 19.: [6] IF rate trip exists (or occurs) on the NIS channel being SAT calibrated, THEN UNSAT
- .LEAR ththarIniEVstdp signal roi:ntari1yst.RA1 S it toR ESET pPSition )arid ahüniátdrXA$56A:
Cue: For this step and the following steps, inform the operator that for JPM purposes the CV is not required Critical Step STANDARD: Operator verifies NO rate trip signals are in on ANY of the PR and the annunciator is clear.
- CRITICAL PORTION:
If rate trip is caused helshe resets the rate trip prior to continuing to the next channel.
This step is critical because failure to comply could result in a reactor trip during the next channel adjustment.
COMMENTS:
JPM Sim F Page 12 of 12 Rev. 0 Job Performance Checklist STEP!STANDARD SAT/UNSAT STEP 20 [7] ADJUST gain potentiometer on associated channels SAT power range B drawer to bring that channePs indicated UNSAT power level to within +/-0 5% of the calonmetric power recor4e in section 61 ørJistd on the printed copy. AND ENSURE gain potentiometer latch re-engaged Step STANDARD: Operator must adjust N41 and N43 to satisfy criteria. The operator should repeat step [61 prior to adjusting any subsequent PR. (only the bold portion of the standard is critical)
This step is critical to ensure all adjustments have been satisfactorily completed on one channel to meet acceptance criteria prior to proceeding to the next channel.
COMMENTS:
EVALUATOR NOTE: Step [8] on adjusting coarse adjust was omitted from JPM.
STEP 21.: [9] IF additional NIS channel(s) require calibration, THEN
_SAT RETURN to step [6] UNSAT STANDARD: Operator may return to step [61 to adjust either N41 or N42.
COMMENTS:
JPM Sim F Page 13 of 13 Rev. 0 Job Performance Checklist STEPISTANDARD SATIUNSAT STEP 22.: [10] WHEN NIS adjustments have been completed, THEN SAT UNSAT RECORD the as left power level from NIS power range channels.
POWER RANGE CHANNEL AS-LEFT NIS POWER (%)
N-41 (Xl-92-5005B)
N-42 (XI-92-5006B)
N-43 (Xl-92-5007B)
N-44 (Xl-92-5008B)
STANDARD: Operator records NIS power range readings from the A channel drawers.
COMMENTS:
STEP 23.: [11] IF NIS power range channel is inoperable THEN.... SAT UNSAT STANDARD: Operator N/As this step since all are operable.
COMMENTS:
STEP 24.: [12] CHECK appropriate box to indicate whether the following SAT as left acceptance criteria were satisfied.
UNSAT STANDARD: Operator checks YES box for N41, N42, N43, & N44, all being within +/- 0.5% of caliometric power.
COMMENTS:
JPM Sim F Page 14 of 14 Rev. 0 Job Performance Checklist STEPISTANDARD SATIUNSAT STEP 25.: [13] IF acceptance criteria were NOT satisfied for any NIS _SAT channel THEN UNSAT STANDARD: Operator N/As this step.
COMMENTS:
STEP 26.: [14] RETURN rod control system to AUTO in accordance with SAT O-SO-85-1.
UNSAT STANDARD: Operator places control rod bank selector switch to AUTO after waiting at least 3 minutes for signal to decay.
COMMENTS:
STEP 27.: Notify SRO that the NIS channels have been calibrated. SAT UNSAT STANDARD: Operator notifies the SRO that the SI has been completed and all power range nuclear instruments have been adjusted to meet the acceptance criteria.
COMMENTS:
CUE: This completes the JPM End of JPM
DIRECTION TO TRAINEE:
I will explain the initial conditions, and state the task to be performed.
All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. 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 at steady state conditions with all NIS channels and LEFM operable.
INITIATING CUES:
You are the CR0 and the US has directed you to perform 0-SI-OPS-092-078.0.
Section 4.0 of 0-SI-OPS-092-078.0 has been completed.
Notify the US when the SI has been completed and any necessary adjustments have been made.
DIRECTION TO TRAINEE:
I will explain the initial conditions, and state the task to be performed.
All control room steps shall be performed for this JPM, including any required communications. I will provide initiating cues and reports on other actions when directed by you. 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 at steady state conditions with all NIS channels and LEFM operable.
INITIATING CUES:
You are the CR0 and the US has directed you to perform 0-SI-OPS-092-078.0.
Section 4.0 of 0-SI-OPS-092-078.0 has been completed.
Notify the US when the SI has been completed and any necessary adjustments have been made.
I jT/ Sequoyah Nuclear Plant Unit I &2 Surveillance Instruction 0-Sf -OPS-092-078.0 POWER RANGE NEUTRON FLUX CHANNEL CALIBRATION BY HEAT BALANCE COMPARISON Revision 0021 Quality Related Level of Use: Continuous Use Effective Date: 11-15-2009 Responsible Organization: OPS, Operations Prepared By: W. T. Leary Approved By: G. Garner
SQN POWER RANGE NEUTRON FLUX 0-SI-OPS-092-078.0 Unit I & 2 CHANNEL CALIBRATION BY HEAT Rev. 0021 BALANCE COMPARISON Page 2 of 41 Current Revision Description Provided parenthetical direction to N/A sub-step not performed in Appendix A Step [2]
(09001296). This is an editorial change to clarify intent.
Modified Section 5.0 Acceptance Criteria A associated with a +/-2% delta between NIS and core thermal power to reflect the Tech Spec requirement. Any channel deviating from core thermal power by more than 2.0% is required to be adjusted. Removed special message boxes from Section 6.1 that incorrectly indicated specific parameters as Acceptance Criteria. Steps 6.1[5] and 6.1[8] were modified to present the allowable deviations between NIS and core thermal power within the step rather than as Acceptance Criteria. (PER 167130)
Relocated step associated with SRO notification of requirements for testing inoperable channels to later in Section 6.1 to provide a more logical sequence. This is an alteration to an administrative requirement and is a minor change.
Modified the tables associated with Steps 6.1[5j, 6.1[7j and 6.1[8] to clarify intent as a minor change.
A note was added prior to Step 6.1[10] to clarify pre-existing intent that bulleted steps are to be marked N/A as appropriate.
Added Precaution and Limitation H regarding the potential impact of Auxiliary Instrument Room temperature on core thermal power indication (09000640).
THIS PROCEDURE COULD AFFECT REACTIVITY
- SQN POWER RANGE NEUTRON FLUX 0-SI-OPS-092-078.0 Unit I & 2 CHANNEL CALIBRATION BY HEAT Rev. 0021
. BALANCE COMPARISON Page 3 of 41 Table of Contents
1.0 INTRODUCTION
5 1.1 Purpose 5 1.2 Scope 5 1 .2.1 Surveillance Test to be Performed 5 1 .2.2 Requirements Fulfilled 5 1.2.3 Modes 5 1.3 Frequency and Conditions 5
2.0 REFERENCES
6 2.1 Performance References 6 2.2 Developmental References 6 3.0 PRECAUTIONS AND LIMITATIONS 7 4.0 PREREQUISITE ACTIONS 9 4.1 PreliminaryActions 9 4.2 Measuring and Test Equipment, Parts, and Supplies 9 4.3 Field Preparations 9 4.4 Approvals and Notifications 9 5.0 ACCEPTANCE CRITERIA 10 6.0 PERFORMANCE 11 6.1 As-Found Data 11 6.2 NIS Channel Adjustment 17 7.0 POST PERFORMANCE ACTIVITY 23 Appendix A: CALCULATION OF CORE THERMAL POWER USING LEFM 24 Appendix B: SUBSTITUTION OF RCS AT AT LOW POWER LEVELS (40% WITH LEFM NOT AVAILABLE) 27 Appendix C: CALCULATION OF CORE THERMAL POWER LEVEL USING U1118 (>40% WITH LEFM NOT AVAILABLE) 28 Appendix D: CALCULATION OF CORE THERMAL POWER LEVEL WITH INOPERABLE PLANT COMPUTER (RCS AT GREATER THAN 40%) 31
SQN POWER RANGE NEUTRON FLUX 0-SI-OPS-092-078.0 Unit I & 2 CHANNEL CALIBRATION BY HEAT Rev. 0021 BALANCE COMPARISON Paqe 4 of 41 Table of Contents (continued)
Appendix E: CALCULATION OF CORE THERMAL POWER WITH U1118 AND U2118 INOPERABLE DUE TO BAD FEEDWATER PRESSURE INPUT (ICS AND LEFM OPERABLE) 39 Source Notes 41
SQN POWER RANGE NEUTRON FLUX 0-SI-OPS-092-078.0 Unit I & 2 CHANNEL CALIBRATION BY HEAT Rev. 0021 BALANCE COMPARISON Page 5 of 41
1.0 INTRODUCTION
1.1 Purpose This Surveillance Instruction (SI) provides detailed steps for ensuring proper calibration of the power range neutron flux channels.
1.2 Scope 1.2.1 Surveillance Test to be Performed This Instruction performs a comparison between the power level calculated by the Nuclear Instrumentation System (N IS) power range neutron flux channels and the true power level as determined by a secondary system heat balance based value.
If necessary, the power range channels are adjusted to agree with the true power level.
This instruction also verifies availability of Leading Edge Flow Meter (LEFM) calorimetric power.
1.2.2 Requirements Fulfilled Performance of this Instruction completely fulfills Technical Specification (TS)
Surveillance Requirement (SR) 4.3.1.1.1 .B.2 (Table 4.3-1, item 2, note 2) and Technical Requirements Manual (TR) 4.3.3.15.1.
1.2.3 Modes A. Applicable Mode - I (above 15 percent power).
B. Performance Mode 1 (above 15 percent power).
1.3 Frequency and Conditions This test must be performed at least once every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the reactor power level is greater than 15 percent. [C.3] To ensure NIS accuracy, this test should be performed when directed by 0-GO-4 or 0-GO-S.
In the event that the Plant Computer is unavailable, provisions have been incorporated in this procedure to fulfill the SR requirements. [C.5]
SQN POWER RANGE NEUTRON FLUX 0-SI-OPS-092-078.0 Unit I & 2 CHANNEL CALIBRATION BY HEAT Rev. 0021 BALANCE COMPARISON Page 6 of 41
2.0 REFERENCES
2.1 Performance References O-Pl-SXX-000-022 .2 Calorimetric Calculation. (Optional) 2.2 Developmental References A. SQN Technical Specifications.
B. SPP-8.1, Conduct of Testing C. NP-STD-4.4.7, Attachment 1, Writers Guide for Technical Documents D. O-Pl-NUC-092-082.O, Post Startup NIS Calibration following Core Load.
E. Memo from Reactor Engineering RIMS S57 941219 934 F. Integrated Computer System Critical Design Requirements and Operators Guide.
- SQN POWER RANGE NEUTRON FLUX 0-SI-OPS-092-078.0 Unit I & 2 CHANNEL CALIBRATION BY HEAT Rev. 0021
. BALANCE COMPARISON Page 7 of 41 3.0 PRECAUTIONS AND LIMITATIONS A. Reactor power must remain constant (+/- 0.5%) during the performance of Sections 6.1 and 6.2. It is desirable for any required NIS adjustment be made promptly during performance of these sections.
B. Average RCS temperature (Tavg) should be maintained within 0.5°F of RCS reference temperature (Tree).
C. Caution should be exercised when adjusting NIS power range instrumentation to minimize the potential for a channel trip.
D. Only one NIS channel shall be adjusted at a time. If a rate trip occurs, the channels trip signal and annunciator on panel XA-55-6A, NC-41 U or NC-41 K NIS POWER RANGE HIGH NEUTRON FLUX RATE must be cleared before proceeding to the next NIS channel.
E. Operations and Engineering should be notified if larger than normal channel adjustments (as determined by the SRO) are required to bring the power range channels into alignment with calculated core thermal power. [C.4] An operability concern may exist if excessive error in the non-conservative direction adversely impacts the NIS high flux trip setpoint. The 3% tolerance for calibration error on the high flux trip setpoints was selected using the extrapolated error from the 30% power level.
F. The reactor cores have been loaded with a low leakage loading pattern which can affect NIS Reactor Power level indications such that differences greater than the Acceptance Criteria can occur between NIS and true power level. The impact of the NIS non-linearity due to low leakage loading pattern is in the conservative direction, since NIS indicated power rises faster than true power during a power increase. 0-GO-5 may direct performance of this procedure to ensure excessive errors in the non-conservative direction do not exist. During plant restarts, Reactor Engineering may perform 0-PI-NUC-092-082.0 at 4% power to provide an initial NIS correction for startup.
G. Technical Specifications require a heat balance calculation for adjustment of the NIS when the Plant is above 15% power within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. If the Leading Edge Flow Meter (LEFM) is available, LEFM data (from U21 18 or LEFM Offline Calorimetric screen) is required to be used for the heat balance when greater than 15% power (TRM 3.3.3.15). If LEFM is not available, then Loop T data should be used between 15 and 40% power due to potential inaccuracies in the feedwater flow venturi heat balance below 40%. If LEFM is not available above 40%, then venturi-based calorimetric power (U 1118) should be used.
SQN POWER RANGE NEUTRON FLUX 0-SI-OPS-092-078.0 Unit I & 2 CHANNEL CALIBRATION BY HEAT Rev. 0021 BALANCE COMPARISON Page 8 of 41 3.0 PRECAUTIONS AND LIMITATIONS (continued)
H. An Auxiliary Instrument Room Temperature of approximately 90°F potentially impacts Computer Pint U1118 accuracy with the DCS Digital Feedwater modification installed. The DOS inputs the UI 18 venturi calculations and the accuracy of the card providing the input is adversely impacted by a card temperature of 95°F.
SQN POWER RANGE NEUTRON FLUX 0-SI-OPS-092-078.0 Unit I & 2 CHANNEL CALIBRATION BY HEAT Rev. 0021 BALANCE COMPARISON Page 9 of 41 Unit I PREREQUISITE ACTIONS r
During the performance of this Instruction,any IFITHEN statement may be marked N/A when the corresponding stated condition does not occur.
Preliminary Actions ENSURE Instruction to be used is a copy of effective version and Data Package Cover Sheet is attached.
Measuring and Test Equipment, Parts, and Supplies None Field Preparations
/ 1] / ENSURE reactor power and RCS average temperature are stable.
Approvals and Notifications
/NOTIFY SRO of test performance. :rJ
SQN POWER RANGE NEUTRON FLUX 0-SI-OPS-092-078.0 Unit I & 2 CHANNEL CALIBRATION BY HEAT Rev. 0021
. BALANCE COMPARISON Page 10 of 41 5.0 ACCEPTANCE CRITERIA A. If the indicated as found power level from any operable NIS channel differs from core thermal power by greater than +/-2%, then the affected channel has been adjusted.
B. The indicated as-left power level from each operable NIS neutron flux channel that was adjusted must equal the core thermal power level to within
+/- 0.5%.
C. If the criteria stated above are NOT satisfied, the SRO shall be notified and Action Requirement 2 of TS Table 3.3-1 satisfied.
D. LEFM shall be used for the plant calorimetric measurement for power range NIS calibration by heat balance comparison. If this criteria is NOT satisfied, the SRO shall be notified and the applicable action of TRM 3.3.3.15 shall be entered.
SQN POWER RANGE NEUTRON FLUX 0-SI-OPS-092-078.0 Unit I & 2 CHANNEL CALIBRATION BY HEAT Rev. 0021 BALANCE COMPARISON Page 11 of 41 6.0 Unit /
PERFORMANCE 6.1 As-Found Data NOTES
- 1) The following step determines if LEFM is available to satisfy TRM 3.3.3.15. If LEFM is NOT available, operators should notify US, document status and continue with next step.
[1] VERIFY availability of LEFM calorimetric power:
[1.11 CHECK LEFM status NORMAL on ICS (NSSS and BOP) Current Calorimetric Data screen.
DYes DNo
[1.2] CHECK LEFM MFW header temperature (ICS point T8502MA) greater than or equal to 250°F.
DYes DNo Acceptance Criteria: LEFM is available based upon the indications above.
SQN POWER RANGE NEUTRON FLUX 0-SI-OPS-092-078.0 Unit I & 2 CHANNEL CALIBRATION BY HEAT Rev. 0021 BALANCE COMPARISON Page 12 of 41 U nit______
6.1 As-Found Data (continued)
NOTE With LEFM unavailable, AFD limit lines in COLR must be made more restrictive by 1% and Rod Insertion Limit lines in COLR must be raised by 3 steps. Rod insertion limit alarms and ICS display are NOT automatically adjusted.
[2] IF LEFM calorimetric power NOT available OR lOS computer NOT available, THEN PERFORM the following:
[2.1] ENTER applicable action of TRM 3.3.3.15.
[2.21 ENSURE work order initiated as required.
[2.3] IF LEFM calorimetric power CANNOT be restored in time to complete this surveillance, THEN PERFORM the following:
A. REDUCE reactor power to 98.7% (3411 MWt) or less USING Ui 118 (if available) or NIS.
B. WHEN reactor power is less than 987%,
THEN CONTINUE this instruction using alternate power indications as specified below.
SQN POWER RANGE NEUTRON FLUX 0-SI-OPS-092-078.0 Unit I & 2 CHANNEL CALIBRATION BY HEAT Rev. 0021 BALANCE COMPARISON Page 13 of 41 Unit______
6.1 As-Found Data (continued)
NOTE If Engineering has performed 0-Pl-SXX-000-022.2, then the applicable section(s) of 0-Pl-SXX-000-022.2 may be used in place of Appendix C or D to obtain the current calorimetric power.
[3] DETERMINE reactor core power level by performing the applicable appendix below:
CONDITION APPENDIX RCS z\T greater than 15% and LEFM core thermal A D power (U21 18) available (step [1] acceptance criteria met)
RCS T between 15% and 40% and LEFM core B D thermal power (U21 18) NOT available RCS greater than 40% C D LEFM core thermal power (U21 18) NOT available but ICS point U1118 is available RCS E.T greater than 40% and ICS computer D NOT available RCS T greater than 40% and lOS core thermal E power indication (U1118 and U2118) NOT available due to bad feedwater pressure input (lOS and LEFM feedwater flow data remain operable)
AND RECORD below (NIA power if using printout from ICS):
% Rated Core Thermal Power =
SQN POWER RANGE NEUTRON FLUX 0-SI-OPS-092-078.0 Unit 1 & 2 CHANNEL CALIBRATION BY HEAT Rev. 0021
. BALANCE COMPARISON Page 14 of 41 Unit______
6.1 As-Found Data (continued)
NOTE Data for an inoperable NIS channel may be marked N/A.
[4] RECORD as-found power level from each of the four NIS power range A channel drawers:
POWER RANGE AS-FOUND CHANNEL NIS POWER (%)
N-41 (Xl-92-5005B)
N-42 (Xl-92-5006B)
N-43 (Xl-92-5007B)
N-44 (Xl-92-5008B)
[5] COMPARE NIS indication with core thermal power level AND CHECK appropriate box to indicate whether the indicated NIS power level recorded in step 6.1 [4] is equal to the core thermal power level recorded in step 6.1[3] or as listed on the printed copy to within +/- 2.0 percent:
YES (<2.0%) NO (2.0%) N/A NIS Channel N-41 D IJ NlSChannelN-42 D D L1 NIS Channel N-43 D D D NIS Channel N-44 D C ROorSRO
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6.1 As-Found Data (continued)
[6] VERIFY that all NIS channel indications are within
+/-3 percent of the determined core thermal power level.
DYes DNo
[7] IF a NIS channel was more than 3 percent in error in the non-conservative direction (core thermal power> NIS),
THEN NOTIFY Engineering to determine if the calibration error impacts operability of the NIS high flux trip.
[8] CHECK appropriate box to indicate whether the indicated NIS power level recorded in step 6.1[4]is less than or equal to 100.5 percent.:
YES (100.5%) NO (>100.5%) N/A NIS Channel N-41 C NIS Channel N-42 C C NIS Channel N-43 C C NIS Channel N-44 C C C ROorSRO
[9] IF any NIS channels were inoperable during the performance of this Instruction, THEN NOTIFY applicable unit SRO that this SI must be performed on all inoperable NIS channels when they are returned to service.
SQN POWER RANGE NEUTRON FLUX 0-SI-OPS-092-078.0 Unit I & 2 CHANNEL CALIBRATION BY HEAT Rev. 0021 BALANCE COMPARISON Page 16 of 41 Unit______
6.1 As-Found Data (continued)
NOTES
- 1) Consistency between the four NIS Power Range Channels is to be considered when determining if an adjustment is desired.
- 2) The adjustment of any NIS channel that displays a value with an absolute difference of greater than 2% from core thermal power meets the requirement found in SR 4.3.1.1.1.
- 3) One or both of the bulleted steps below may be marked N/A dependent on specific circumstances.
[1 Oj IF any channel does not meet acceptance criteria (Step 6.1[5j and/or Step 6.1[8]),
OR NIS Channel Adjustment is desired, THEN
- PERFORM adjustment using Section 6.2 ANDIOR
- REDUCE reactor power not to exceed 100 percent.
END OF TEXT
SQN POWER RANGE NEUTRON FLUX 0-SI-OPS-092-078.0 Unit I & 2 CHANNEL CALIBRATION BY HEAT Rev. 0021 BALANCE COMPARISON Page 17 of 41 Unit______
6.2 NIS Channel Adjustment NOTES
- 1) Performance of this section is required only for those PR channels designated by the Reactor Operator or that did not satisfy the acceptance criteria in Section 6.1. All other NIS channels may be marked N/A.
- 2) During the performance of Section 6.2, data required for an inoperable NIS channel may be marked N/A.
[1] IF calculated average power in Section 6.1 or on printed copy differs by more than 3% from average RCS delta T, THEN NOTIFY Engineering to determine the cause.
[2] VERIFY reactor power has remained constant
(+/- 0.5 %) since performance of Section 6.1.
NOTE The inoperable channel may be bypassed for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for surveillance testing of other channels.
[3] IF NIS power range channel is inoperable, THEN REQUEST Instrument Maintenance to Bypass inoperable NIS channel in accordance with 0-PI-IXX-092-001 .0.
[4] ENSURE all NIS power range channels are operable or bypassed with no bistables tripped.
[5] ENSURE rod control system is in MANUAL in accordance with 0-S 0-85-1.
SQN POWER RANGE NEUTRON FLUX 0-SI-OPS-092-078.0 Unit I & 2 CHANNEL CALIBRATION BY HEAT Rev. 0021 BALANCE COMPARISON Page 18 of 41 Unit______
6.2 NIS Channel Adjustment (continued)
NOTES
- 1) Steps 6.2[6] through 6.2[9j must be completed on one NIS channel before proceeding to the next channel.
- 2) NIS channels in the following step may be performed out of sequence.
[6] IF a rate trip exists (or occurs) on the NIS channel being calibrated, THEN CLEAR that channels trip signal (momentarily set RATE MODE switch to RESET position) and annunciator on panel XA-55-6A, NC-41 U or NC-41 K NIS POWER RANGE HIGH NEUTRON FLUX RATE, before proceeding to the next NIS channel.
Trip Cleared N/A NIS Channel N-41 D D NIS Channel N-42 NIS Channel N-43 L1 NIS Channel N-44 D D First Person CV
SQN POWER RANGE NEUTRON FLUX 0-SI-OPS-092-078.0 Unit I & 2 CHANNEL CALIBRATION BY HEAT Rev. 0021 BALANCE COMPARISON Page 19 of 41 Un it______
6.2 NIS Channel Adjustment (continued)
NOTE The gain potentiometers have latches which must be disengaged prior to adjustment, and re-engaged following adjustment.
[7] ADJUST gain potentiometer on associated channels power range B drawer to bring that channels indicated power level to within +/-0.5% of the calorimetric power recorded in Section 6.1 or as listed on the printed copy. AND ENSURE gain potentiometer latch re-engaged. [0.2]
Adjustment N/A Req u i red NIS Channel N-41 D D NIS Channel N-42 D NIS Channel N-43 D NIS Channel N-44 D First Person Cv
SQN POWER RANGE NEUTRON FLUX 0-SI-OPS-092-078.0 Unit I & 2 CHANNEL CALIBRATION BY HEAT Rev. 0021 BALANCE COMPARISON Page 20 of 41 U nit______
6.2 NIS Channel Adjustment (continued)
[8] IF fine gain potentiometer on power range B drawer will not provide enough adjustment to satisfy the calibration requirements of step 6.2[7], THEN REQUEST Instrument Maintenance to adjust the coarse gain (resistor R312, Coarse Level Adjust) inside the applicable power range drawer, AND READJUST fine gain potentiometer to achieve calibration requirements specified in step 6.2[7].
Adjustment Required N/A NIS Channel N-41 D D N!SChannelN-42 D NIS Channel N-43 D D NIS Channel N-44 Ei First Person CV
[9] IF additional NIS channel(s) require calibration, THEN RETURN TO step 6.2[6].
SQN POWER RANGE NEUTRON FLUX O-SI-OPS-092-078.O Unit I & 2 CHANNEL CALIBRATION BY HEAT Rev. 0021 BALANCE COMPARISON Page 21 of 41 Unit______
6.2 NIS Channel Adjustment (continued)
[10] WHEN NIS adjustments have been completed, THEN RECORD as-left power level from NIS power range channels.
POWER RANGE AS-LEFT CHANNEL NIS POWER (%)
N-41 (Xl-92-5005B)
N-42 (Xl-92-5006B)
N-43 (Xl-92-5007B)
N-44 (Xl-92-5008B)
First Person IV
[11] IF NIS power range channel is inoperable, THEN REQUEST Instrument Maintenance to remove Bypass on inoperable NIS channel in accordance with 0-Pl-IXX-092-001 .0.
SQN POWER RANGE NEUTRON FLUX 0-SI-OPS-092-078.0 Unit I & 2 CHANNEL CALIBRATION BY HEAT Rev. 0021 BALANCE COMPARISON Page 22 of 41 Unit______
6.2 NIS Channel Adjustment (continued)
[12] CHECK appropriate box to indicate whether the following as-left acceptance criteria were satisfied.
Acceptance Criteria: The indicated NIS power level recorded in step 6.2[10j is within +/- 0.5 percent the calorimetric power level recorded in Section 6.1 or as listed on the printed copy.
YES NO N/A NIS Channel N-41 D NIS Channel N-42 D NIS Channel N-43 D D NIS Channel N-44 D D RO or SRO
[13] IF acceptance criteria were NOT satisfied for any N1S channel, THEN NOTIFY Shift Manager that acceptance criteria were NOT met and another performance of this test is necessary, subsequently action 2 of LCO 3.3.1.1 (Unit 1) or LCO 3.3.1 (Unit 2) must be satisfied if the other performance does not meet acceptance criteria.
NOTE NIS channel adjustment may cause step change in input to rod control. A delay of at least 3 minutes prior to returning rod control to automatic will allow lead/lag signal to decay off.
[14] RETURN Rod Control System to AUTO in accordance with 0-SO-85-1.
END OF TEXT
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. BALANCE COMPARISON Page 23 of 41 Unit______
7.0 POST PERFORMANCE ACTIVITY
[1] NOTIFY SRO that test has been completed.
SQN POWER RANGE NEUTRON FLUX 0-SI-OPS-092-078.0 Unit I & 2 CHANNEL CALIBRATION BY HEAT Rev. 0021 BALANCE COMPARISON Page 24 of 41 Appendix A (Page 1 of 3)
CALCULATION OF CORE THERMAL POWER USING LEFM Unit______
NOTES
- 1) ICS allows two options for blowdown flows:
Option #1 (Preferred) -use point fF2261 Al which requires no operator entered data (computer automatically updates the blowdown flows).
Option #2 use manually entered S/G blowdown flow rates.
- 2) Computer point [F2261A] is more accurate than flow indicators located in the fan rooms. If the computer point is inoperable and blowdown flows from the FISs are used, then indicated core thermal power may be a slightly different value.
[1] ENSURE S!G blowdown flows are updated by performing the following functions on ICS:
[1.2] SELECT CALORIMETRIC FUNCTION MENU.
[1.3] SELECT UPDATE OPERATOR ENTERED SLOWDOWN FLOW on menu AND PERFORM one of the following options (N/A option not used):
[1.3.1] IF using computer point [F2261A1 S/G Total Blowdown Flow, THEN A. VERIFY point value is updating (changing values).
B. IF computer point is NOT updating, THEN NOTIFY MIG that point is NOT updating and initiate WO.
SQN POWER RANGE NEUTRON FLUX 0-Sl-OPS-092-078.0 Unit I & 2 CHANNEL CALIBRATION BY HEAT Rev. 0021 BALANCE COMPARISON Page 25 of 41 Appendix A (Page 2 of 3)
Unit______
NOTE Local readings of steam generator blowdown flow are obtained from Panel L-357.
[1 .3.2] IF manually updating blowdown flows, THEN A. RECORD local readings for S/G blowdown flow:
RCS BLOWDOWN FLOW LOOP (GPM) 1 Fl-1-152 2
Fl-1-156 Fl-I -I 60 Fl-1-164 B. ENSURE blowdown flows above entered in lOS.
C. IF blowdown flows were updated, THEN WAIT a minimum of 10 minutes to allow program to accurately reflect new value.
SQN POWER RANGE NEUTRON FLUX 0-SI-OPS-092-078.0 Unit I & 2 CHANNEL CALIBRATION BY HEAT Rev. 0021 BALANCE COMPARISON Page 26 of 41 Appendix A (Page 3of3)
Unit______
NOTE lOS printout may be used to document power level and NIS values. Since core thermal power fluctuates, a slight deviation may exist between the recorded core thermal power value (if used) and the printed sheet value (if used). SI acceptance is satisfied in the body of the instruction.
[2] SELECT DISPLAY CURRENT CALORIMETRIC DATA on ICS Calorimetric menu AND PERFORM one of the following (Mark step not performed N/A.):
[2.1] RECORD the following:
LEFM Core Thermal Power (U21 18)
Percent Rated Core Thermal Power (UI 127)
[2.2] PRINT power level and NIS values AND ATTACH report to this instruction.
SQN POWER RANGE NEUTRON FLUX 0-SI-OPS-092-078.0 Unit I & 2 CHANNEL CALIBRATION BY HEAT Rev. 0021 BALANCE COMPARISON Page 27 of 41 Appendix B (Page 1 of 1)
SUBSTITUTION OF RCS AT AT LOW POWER LEVELS (40% WITH LEFM NOT AVAILABLE)
Un it______
1.0 PERFORMANCE NOTES
- 1) RCS delta T loops (AT°) are aligned to results of a secondary-side heat balance.
Consequently, using z\Ts to adjust NIS at low power levels still satisfies the requirement to use heat balance. Loop tT is used to avoid potentially non-conservative errors in NIS power range indication if adjustments were made based upon an inaccurate secondary heat balance at a low feedwater flowrate. At low power levels the traditional secondary-side heat balance (U 1118) is not as accurate as Reactor Coolant Loop ATs.
[1] CALCULATE the average RCS delta T using control board indications or computer point for average RCS AT.
PLANT Loop A (Tl-68-2D) COMPUTER Loop B (TI-68-25D) OR U0485 %
Loop C (TI-68-44D) %
Loop D (TI-68-67D) %
Total % ÷(4)= Avg
[2] RECORD average RCS delta T as the core thermal power level_______
SQN POWER RANGE NEUTRON FLUX 0-SI-OPS-092-078.0 Unit I &2 CHANNELCALIBRATIONBYHEAT Rev.0021 BALANCE COMPARISON Page 28 of 41 Appendix C (Page 1 of 3)
CALCULATION OF CORE THERMAL POWER LEVEL USING U1118 (>40% WITH LEFM NOT AVAILABLE)
Unit______
1.0 PERFORMANCE NOTES
- 1) This appendix is used when RCS AT is greater than 40%
and LEFM (U2118) NOT available, but lOS and Ull 18 are available.
- 2) lOS allows two options for blowdown flows:
Option #1 (Preferred) use point 1F2261AI which requires no operator entered data (computer automatically updates the blowdown flows).
Option #2 - use manually entered SIG blowdown flow rates.
- 3) Computer point 1F2261A1 is more accurate than flow indicators located in the fan rooms. If the computer point is inoperable and blowdown flows from the FISs are used in the calculation of U 1118, then expect U 1118 to indicate a different value and adjustment of NIS may be required.
[1] ENSURE SIG blowdown flows are updated by performing the following on ICS:
[1.2] SELECT CALORIMETRIC FUNCTION MENU
[1.3] SELECT UPDATE OPERATOR ENTERED BLOWDOWN FLOW on menu AND PERFORM one of the following options (N/A option not used):
[1.3.1] IF using computer point 1F2261A1 SIG Total Blowdown Flow, THEN A. VERIFY point value is updating (changing values).
B. IF computer point is NOT updating, THEN NOTIFY MIG that point is not updating and initiate WO.
SQN POWER RANGE NEUTRON FLUX O-SI-OPS-092-078.0 Unit I & 2 CHANNEL CALIBRATION BY HEAT Rev. 0021 BALANCE COMPARISON Page 29 of 41 Appendix C (Page 2 of 3)
Unit______
1.0 PERFORMANCE (continued)
NOTE Local readings of steam generator blowdown flow are obtained from Panel L-357.
[1 .3.2] IF manually updating blowdown flows, THEN A. RECORD local readings for SIG blowdown flow:
RCS BLOWDOWN FLOW LOOP (GPM) 1 Fl-1-152 2
Fl-1-156 Fl-1-160 Fl-I-i 64 B. ENSURE blowdown flows above entered in lOS.
C. IF blowdown flows were updated, THEN WAIT a minimum of 10 minutes to allow program to accurately reflect new value.
SQN POWER RANGE NEUTRON FLUX 0-SI-OPS-092-078.0 Unit I & 2 CHANNEL CALIBRATION BY HEAT Rev. 0021 BALANCE COMPARISON Page 30 of 41 Appendix C (Page 3 of 3)
Unit______
1.0 PERFORMANCE (continued)
NOTE ICS printout may be used to document power level and NIS values. Since core thermal power fluctuates, a slight deviation may exist between the recorded core thermal power value (if used) and the printed sheet value (if used). SI acceptance is satisfied in the body of the instruction.
[2] SELECT DISPLAY CURRENT CALORIMETRIC DATA on ICS Calorimetric menu AND PERFORM one of the following:
[2.1] RECORD the following:
Venturi Core Thermal Power (U1118)
Percent Rated Core Thermal Power (Ui 127) %
[2.2] PRINT power level and NIS values AND ATTACH report to this instruction.
[3] IF any value is a blue NCAL quality, THEN PERFORM the following:
[3.1] IF cause of bad data is unknown, THEN REQUEST assistance from MIG or ICS computer engineer.
[3.2] INITIATE WO if required.
[3.3] GO TO Appendix D.
SQN POWER RANGE NEUTRON FLUX 0-SI-OPS-092-078.0 Unit I & 2 CHANNEL CALIBRATION BY HEAT Rev. 0021 BALANCE COMPARISON Page 31 of 41 Appendix D (Page 1 of 8)
CALCULATION OF CORE THERMAL POWER LEVEL WITH INOPERABLE PLANT COMPUTER (RCS zT GREATER THAN 40%)
Unit_______
1.0 PERFORMANCE NOTES
- 1) This appendix provides guidance determining calorimetric power when ICS core thermal power indication (U 1118 and U2118) is unavailable with power above 40%
and the computer cannot be restored in time to complete SR 4.3.1 .1.1.
- 2) 0-PI-SXX-000-022.2 requires several hours from initiation until completion of power calculation.
[1) IF 0-PT-SXX-000-022.2 will be used for calorimetric data, THEN PERFORM the following:
[1.1) NOTIFY Systems Engineering to perform manual calorimetric calculation using 0-PI-SXX-000-022.2.
[1.2] MARK remaining steps N/A in this appendix.
SQN POWER RANGE NEUTRON FLUX 0-SI-OPS-092-078.0 Unit I & 2 CHANNEL CALIBRATION BY HEAT Rev. 0021 BALANCE COMPARISON Page 32 of 41 Appendix D (Page 2 of 8)
U nit______
1.0 PERFORMANCE (continued)
NOTES
- 1) The remaining steps determine core thermal power by manually entering calorimetric data on opposite units lOS computer. This method requires adding 3.5% to the calculated power level for additional conservatism due to greater errors associated with indicator error and readability. Therefore, power level should be reduced to less than or equal to 96.5% before performance.
- 2) Calorimetric calculation on opposite units lOS assumes that blowdown flow is identical on each unit. This error is accounted for in the 3.5% correction factor.
[2] IF opposite units lOS will be used to perform a calorimetric calibration, THEN PERFORM the following:
[2.1] ENSURE reactor power less than or equal to 96.5%.
[2.2] ENSURE reactor power and RCS temperature stable.
SQN POWER RANGE NEUTRON FLUX 0-SI-OPS-092-078.0 Unit I & 2 CHANNEL CALIBRATION BY HEAT Rev. 0021 BALANCE COMPARISON Page 33 of 41 Appendix D (Page 3 of 8)
Unit_______
1.0 PERFORMANCE (continued)
NOTES
- 1) If lOS is unavailable, LEFM Feed flow and feed temperature may still be available on LEFM panel [LOCL-500-R1 83] in Aux Inst Rm.
[3] IF LEFM feed flow and feed temperature is available on local LEFM panel, THEN PERFORM the following:
[3.1] RECORD the following data:
Parameter Indication Reading Loop 1 Feedwater Pressure P1-3-37 [M-3] psig Loop 2 Feedwater Pressure P1-3-50 [M-3] psig Loop 3 Feedwater Pressure P1-3-92 [M-3] psig Loop 4 Feedwater Pressure P1-3-i 05 [M-3] psig Loop 1 S/G Pressure Pl-1-2A or 2B [M-4] psig Loop 2 S/G Pressure Pl-1-9A or 9B [M-4] psig Loop 3 SIG Pressure P1-i -20A or 20B [M-4] psig Loop 4 S/G Pressure PI-1-27A or 27B [M-4] psig Total Feedwater Flow LEFM Ibm/hr Feedwater Temperature LEFM (must be > 250°F) °F IV
[3.2] SELECT Calorimetric Main Menu screen on other units lOS computer.
(step continued on next page)
- SQN POWER RANGE NEUTRON FLUX 0-SI-OPS-092-078.0 Unit I & 2 CHANNEL CALIBRATION BY HEAT Rev. 0021 BALANCE COMPARISON Page 34 of 41 Appendix D (Page 4 of 8)
Unit______
1.0 PERFORMANCE (continued)
[3.3] SELECT LEFM Special Offline Calorimetric on Calorimetric Menu.
[3.4] ENTER data in lOS from table in subStep 3 [a].
[3.5] SELECT function key F3 to execute calculation.
[3.6] PRINT calorimetric results.
[3.7] VERIFY data was correctly entered in lOS from table in subStep 3 [a].
IV
[3.8] RECORD Total SIG Thermal Power from calorimetric printout:
[3.9] CALCULATE percent power corresponding to item 1.O[3.8]
34.55
SQN POWER RANGE NEUTRON FLUX 0-SI-OPS-092-078.O Unit I & 2 CHANNEL CALIBRATION BY HEAT Rev. 0021 BALANCE COMPARISON Page 35 of 41 Appendix D (Page 5of8)
Unit_______
1.0 PERFORMANCE (continued)
NOTE The following step adds 3.5% to calorimetric power to compensate for additional errors in this method. The corrected power value below should be used in Section 6.1.
[3.10] CALCULATE corrected core thermal power:
(substep 1.0[3.9]) 3.5%
[3.111 VERIFY substeps 1 .0[3.7] through 1 .0[3.9].
IV
SQN POWER RANGE NEUTRON FLUX 0-SI-OPS-092-078.0 Unit I & 2 CHANNEL CALIBRATION BY HEAT Rev. 0021 BALANCE COMPARISON Page 36 of 41 Appendix D (Page 6of8)
Unit______
1.0 PERFORMANCE (continued)
NOTE 1 ,2-Pl-ICC-003-036.O provides details on required test equipment for feedwater temperature measurement.
[4] IF LEFM feed flow and feed temperature is NOT available, THEN PERFORM the following:
[4i] NOTIFY MIG or Systems Engineering to install precision temperature monitoring equipment in feedwater header temperature wells TW-3-197 and TW-3-198
[TB el. 685].
[4.2] RECORD average feedwater header temperature:
°F MIG or Eng (step continued on next page)
SQN POWER RANGE NEUTRON FLUX 0-SI-OPS-092-078.0 Unit I & 2 CHANNEL CALIBRATION BY HEAT Rev. 0021 BALANCE COMPARISON Page 37 of 41 Appendix 0 (Page 7 of 8)
Unit______
1.0 PERFORMANCE (continued)
[4.3] RECORD the following data:
Parameter Indication Reading Loop 1 Feedwater Press P1-3-37 [M-3] psig Loop 2 Feedwater Press P1-3-50 [M-3j psig Loop 3 Feedwater Press P1-3-92 [M-3] psig Loop 4 Feedwater Press P1-3-i 05 [M-3] psig Loop 1 SIG Pressure PI-1-2A or 2B [M-4j psig Loop 2 S/G Pressure Pl-1-9A or 9B [M-4] psig Loop 3 SIG Pressure P1-i -20A or 20B [M-4] psig Loop 4 SIG Pressure P1-I -27A or 27B [M-4] psig Loop I Feedwater Flow FI-3-35A or 35B [M-4] Ibm/hr Loop 2 Feedwater Flow FI-3-48A or 48B [M-4] Ibm/hr Loop 3 Feedwater Flow Fl-3-90A or 90B [M-4] Ibm/hr Loop 4 Feedwater Flow FI-3-103A or 103B [M-4] Ibm/hr IV
[4.4] SELECT Calorimetric Main Menu screen on other units lOS computer.
[4.5] SELECT Special Offline Calorimetric on Calorimetric Menu.
(step continued on next page)
SQN POWER RANGE NEUTRON FLUX 0-SI-OPS-092-078.0 Unit I & 2 CHANNEL CALIBRATION BY HEAT Rev. 0021 BALANCE COMPARISON Page 38 of 41 Appendix D (Page 8 of 8)
Unit______
1.0 PERFORMANCE (continued)
[4.6] ENTER data in lOS from substeps 1 .0[4.2] andi .0[4.3].
[4.7] SELECT function key F3 to execute calculation.
[4.8] PRINT calorimetric results.
[4.9] VERIFY data from subSteps 1 .0[4.2] and 1 .0[4.3] as correctly entered in lOS.
lv
[4.10] RECORD Total SIG Thermal Power from calorimetric printout:
[4.11] CALCULATE percent power corresponding to iteml .0[4.10]
34.55 NOTE The following step adds 3.5% to calorimetric power to compensate for additional errors in this method. The corrected power value below should be used in Section 6.1.
[4.12] CALCULATE corrected core thermal power:
(substep 1.0[4.11]) 3.5%= %
[4.13] VERIFY substeps 1.0[4.10] through 1.0[4.11].
IV
SQN POWER RANGE NEUTRON FLUX 0-SI-OPS-092-078.0 Unit I & 2 CHANNEL CALIBRATION BY HEAT Rev. 0021 BALANCE COMPARISON Page 39 of 41 Appendix E (Page 1 of 2)
CALCULATION OF CORE THERMAL POWER WITH U1118 AND U2118 INOPERABLE DUE TO BAD FEEDWATER PRESSURE INPUT (ICS AND LEFM OPERABLE)
Unit______
1.0 PERFORMANCE NOTES
- 1) This appendix provides guidance determining calorimetric power when ICS core thermal power indication (U1118 and U2118) is unavailable with power above 40%
(ICS and LEFM remain operable). This appendix will calculate thermal power using the SPECIAL LEFM OFFLINE CALORIMETRIC screen on lCS. (NSSS AND BOP, CALORIMETRIC FUNCTION MENU).
- 2) To limit the magnitude of errors, this appendix may only be used when one feedwater pressure input is inoperable.
[1] SELECT SPECIAL LEFM OFFLINE CALORIMETRIC screen on ICS.
[2] VERIFY the following on SPECIAL LEFM OFFLINE CALORIMETRIC screen:
- MEW header temperature greater than 250°F
- S/G Total Blowdown Flow E2261MA shows valid data and point is updating.
- With the exception of average feedwater pressure and individual blowdown flows, no more than one input point shows bad data (all other input point except for failed feedwater pressure indicate good quality/valid data).
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Unit______
1.0 PERFORMANCE (continued)
[3] MANUALLY ENTER feedwater pressure for invalid point:
[3.1] VERIFY all four SIG pressures shown on SPECIAL LEFM OFFLINE CALORIMETRIC screen are stable and indicate valid data.
[3.2] CALCULATE average of remaining three (operable) feedwater pressures.
psig 1st IV
[3.3] ENTER calculated average feedwater pressure in place of invalid feedwater pressure input on SPECIAL LEFM OFFLINE CALORIMETRIC screen.
1st IV
[3.4] SELECT F3 (EXECUTE).
[3.5] SELECT desired printer for printout. D
[3.6] ATTACH printout to this SI package. D End of Section
SQN POWER RANGE NEUTRON FLUX 0-Sl-OPS-092-078.0 Unit I & 2 CHANNEL CALIBRATION BY HEAT Rev. 0021
. BALANCE COMPARISON Page 41 of 41 Source Notes (Page 1 of 1)
Implementing Requirements Statement Source Document Statement Ensure calculation of thermal power is INPO SER 89-23 0.1 correct before calibrating excore CAQR SQQ 90052 detectors.
Excore detectors should be calibrated INPO SER 89-09 C.2 based on best available power indication.
NIS power range calibrations should be INPO SOER 90-03 0.3 performed periodically following power ascension above 15% power.
Careful consideration and caution INPO SOER 90-03 0.4 should be exercised before adjusting nuclear instrumentation. Operations and Engineering Management should be notified if larger than normal channel adjustments are required.
0-Sl-OPS-092-078.0 will be revised to LER 328/91 005 0.5 allow the use of a Plant Computer SlO 910819 844 program to provide an increased frequency of the performance of this procedure.
JPM Sim G Page 1 of 1 Rev. 0 SEQUOYAH NUCLEAR PLANT September2010 NRC Exam SIM G (RO\SRO)
Initiate Makeup to the Refueling Cavity
JPM Sim G Page 2 of 2 Rev. 0 ROISRO JOB PERFORMANCE MEASURE Task: Initiate Makeup to the Refueling Cavity Task#: 3210110401 (RO)
Task Standard: Makeup to the refueling cavity via the RHR Pumps is initiated per AOP-M.04.
Time Critical Task: YES: NO: X KIA ReferencelRatings: 036AA2.02 (3.4/4.1) 004A4.08 (3.8/3.4) 036AK3.03 (3.7/4.1)
Method of Testing:
Simulated Performance: Actual Performance: X Evaluation Method:
Simulator X In-Plant Classroom Main Control Room Mock-up Performer:
Trainee Name Evaluator: /
Name I Signature DATE Performance Rating: SAT: UNSAT:
Validation Time: 15 minutes Total Time:
Performance Time: Start Time: Finish Time:
COMMENTS
JPM Sim G Page 3 of 3 Rev. 0 SPECIAL INSTRUCTIONS TO EVALUATOR:
- 1. Critical steps are identified in step SAT/UNSAT column by bold print Critical Step.
- 2. Any UNSAT requires comments
- 3. Initialize the simulator to 10-114 and complete the following setup.
- 4. Override # AN:OVRDN_584 to ON, to bring in alarm for SPENT FUEL PIT LEVEL.
- 5. Override ZAOL168320, ZAOL168321, ZA0L168335A, ZAOL168339A at 50 to simulate PZR at refueling level.
- 6. Override ZA0P16866A, ZA0P16869, ZAOP16862 at 35 to simulate refuel flood up pressure.
- 7. Override AN:OVRDN_1 695 to OFF to keep midloop high level alarm from alarming.
- 8. Override (FCV-62-135 & 136, CCP Suction from VCT, CLOSED. (ZLOHS62I35A_Green f:ON, ZLOHS62I36A_Green f:ON, ZDIHS62I35A f:0 (close), ZDIHS62I36A f:0 (close)
- 9. Insure operator performs the following required actions for 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.
- 10. Add Caution Order tag to FCV-63-1 per 0-GO-13 App. 0. (jumpers placed to remove seal in)
Tools!EquipmentlProcedures Needed:
AOP-M.04, Section 2.0, 2.1, and Appendix A & B
REFERENCES:
I I AOP-M.04, Sect 2.1 & Appendix A Refueling Malfunctions I Rev No. 9 I I Task Number Task Title I Cont TRN 3210110401 (RO) Initiate Makeup to the Refueling Cavity
JPM Sim G Page 4 of 4 Rev. 0 READ TO OPERATOR 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 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 1 is in mode 6 performing refueling operations. Approximately 1/2 of the core has been off-loaded at this time.
2 There is one fuel assembly in transit to the spent fuel pit from the core. It is presently in the upender cart in transient to the spent fuel pit.
3 The refueling SRO in the reactor building has just informed you that there is an obvious drop in reactor cavity level.
4 A dedicated operator that has been assigned to monitor vessel level instruments, informs you that there is a decreasing trend in Reactor cavity level indicators.
INITIATING CUES:
- 1. The refueling SRO reports a confirmed reactor cavity seal failure is occurring.
- 2. Alarm on panel 1-M-6D (D3) SPENT FUEL PIT LEVEL HIGH-LOW has just actuated.
- 4. The US directs you to perform AOP-M.04, Refueling Malfunctions (single performer method).
JPM Sim G Page 5 of 5 Rev. 0 Job Performance Checklist STEP/STANDARD SAT/UNSAT NOTE: If operator responds using AR-M6-D window 0-3. AUO is dispatched to the SFP to investigate the alarm. Operator determines that AOP-M.04 is the appropriate procedure.
SAT STEP 1: Obtain the appropriate procedure.
UNSAT Start Time STANDARD: Operator obtains a copy of AOP-M.04.
COMMENTS:
STEP 2: 1. EVALUATE the following Tech Specs for applicability: SAT
- 3.9.8.2, RHR Low Water Level UNSAT
- 3.9.1O,RxVesselWaterLevel
- 3.9.11, Refueling Operations Spent Fuel Pit Water Level Cue: The US will evaluate the Tech Specs for applicability STANDARD: Operator notifies US of the need to evaluate these three Tech Spec items.
COMMENTS:
JPM Sim G Page 6 of 6 Rev. 0 Job Performance Checkst STEPISTANDARD SATIUNSAT STEP 3: 2. EVALUATE EPIP-1, Emergency Plan Initiating SAT Conditions Matrix.
UNSAT Cue: The SM will evaluate the Emergency Plan STANDARD: Operator notifies US/SM of the need to evaluate the Emergency Plan.
COMMENTS:
STEP 4: 3. Diagnose conditions to determine appropriate section, of SAT AOP-M.04, to perform.
UNSAT STANDARD: Based on plant indications and initial conditions, determines that section 2.1 must be performed and proceeds to page 4.
COMMENTS:
Caution 1: Loss of Spent Fuel Pit or Refueling Cavity level and subsequent loss of shielding may result in extremely high dose rates in Containment and Spent Fuel Pit areas.
Caution 2: If the reactor cavity water level drops to flange elevation with upender in vertical position, the top 0.25 inch of upender will extend above surface of water.
Note: Fuel Handling SRO, personnel required to place fuel in safe location, and Radcon personnel remain (if possible) until required actions are completed.
STEP 5: 2.1.1 ANNOUNCE to all non-essential personnel to evacuate SAT Containment and AB el. 734 Refuel Floor.
UNSAT Cue: The SM would like you to make that announcement.
STANDARD: Operator makes this announcement.
COMMENTS:
JPM Sim G Page 7 of 7 Rev. 0 Job Performance Checklist STEPISTANDARD SAT/UNSAT STEP 6: 2.1.2 ENSURE the following personnel notified that seal SAT failure has occurred:
UNSAT
- Control Room
- RADCON to monitor refueling area and Aux Bldg as required
- Fuel Handling Supervisor Cue: The SM will ensure all control room personnel and the Fuel Handling Supervisor are aware of the event and that RADCON begins monitoring CNMT and the Aux Bldg.
STANDARD: Operator ensures these people are notified.
COMMENTS:
Caution: Failure to maintain RWST level greater than 5% may cause CCPs or RHR pumps to lose suction.
STEP 7: 2.1.3 MAINTAIN Refueling Cavity level as necessary: SAT
b.
Cue: US directs makeup from RWST using CCP STANDARD: Operator obtains a copy of Appendix A Section A of AOP-M.04.
COMMENTS:
NOTE:The following are from Appendix A, Filling Refueling Cavity From RWST, Section A of AOP-M.04.
STEP 8: A.1.a. VERIFY RWST level greater than 8%.
. UNSAT STANDARD: Operator verifies RWST level greater than 8% using one or more of the RWST level indicators located on M-6.
COMMENTS:
JPM Sim G Page 8 of 8 Rev. 0 Job Performance Checklist STEPISTANDARD SATIUNSAT STEP 9: A.1.b. ENSURE the following charging valves OPEN: SAT UNSAT FCV-62-90 STANDARD: Operator verifies FCV-62-90 open by observing 1-HS 90A RED light LIT.
COMMENTS:
STEP 10: A.1 .b. ENSURE the following charging valves OPEN: SAT UNSAT FCV-62-91 STANDARD: Operator verifies FCV-62-91 open by observing 1-HS 91A RED light LIT COMMENTS:
STEP 11: A.1.b. ENSURE the following charging valves OPEN: SAT UNSAT FCV-62-85 OR FCV-62-86 STANDARD: Operator verifies FCV-62-85 or 86 is open by observing 1-HS-62-85A or 1-HS-62-86A RED light LIT.
COMMENTS:
JPM Sim G Page 9 of 9 Rev. 0 Job Performance Checklist STEPISTANDARD SATIUNSAT STEP 12 A I c OPEN the following valves SAT FOV-6.2-135 a MI 36,. CP suctin from RWST UNSAT Critical Step STANDARD: Operator pushes HSs (1-HS-62-135A and 1-HS-62-136A)
IN and turns to the OPEN position and determines that neither valve opens Green lights remain LIT for FCVs 135 and 136.
Cue: If required, acknowledge request and ask for recommendation to complete task from candidate.
This step is critical to attempt a supply to the refueling cavity makeup flowpath and then for the UO to determine the valve failure so the alternate path may be utilized.
COMMENTS:
Evaluator Note: The candidate should recommend using the alternate method of filling Reactor Cavity by performing step 2 of Appendix A.
STEP 13: Operator reports to US that neither CCP suction from the SAT RWST will open.
UNSAT Cue: After operator reports not being able to open CCP suction valves, report as the US that you will contact Maintenance Shift Supervisor to investigate the cause of the valve failure.
STANDARD: Operator determines that step 2 of Appendix A is appropriate action to take.
COMMENTS:
JPM Sim G Page 10 of 10 Rev. 0 Job Performance Checklist STEP/STANDARD SATIUNSAT NOTE: The following are from Appendix A, Section A, Step 2 of AOP-M.04.
STEP 14: A.2. IF initiating makeup from RWST using RHR Pump SAT suction, THEN PERFORM the following:
UNSAT
- a. VERIFY RWST level greater than 8%.
STANDARD: Operator verifies RWST level greater than 8% using one or more of the RWST level indicators located on M-6.
COMMENTS:
STEP 15: A.2. IF initiating makeup from RWST using RHR Pump SAT suction, THEN PERFORM the following:
UNSAT
- b. PV-LW$UPP, Critical Step STANDARD: Operator uses HS-63-IA and opens FCV-63-1, Observes Red light ON, Green light OFF.
This step is critical to provide a makeup flowpath from the RWST to the refueling cavity.
COMMENTS:
JPM Sim G Page 11 of 11 Rev. 0 Job Performance Checklist STEPISTANDARD SAT/UNSAT STEP 16: A.2. IF initiating makeup from RWST using RHR Pump _SAT suction, THEN PERFORM the following:
UNSAT o CLOSE one the following valves
- FCV-74-1
- RHR suction from Hot Leg No 4 or Critical Step
- suotiqn frnn Hot Leg STANDARD: Operator uses HS-74-IA and CLOSES FCV-74-1, Observes Red light OFF, Green light ON. OR Operator uses HS-74-2A and CLOSES FCV-74-2, Observes Red light OFF, Green light ON This step is critical to isolate the normal RHR suction flowpath and to swap over to the RWST suction flowpath.
COMMENTS:
STEP 18: A.2.d VERIFY flow to RCS. SAT U N SAT STANDARD: Operator verifies flow into the RCS by observing flow on 1-Fl-63-91B or 1-Fl-63-92B.
COMMENTS:
JPM Sim G Page 12 of 12 Rev. 0 Job Performance Checklist STEPISTANDARD SATIUNSAT STEP 19: Inform the US of flow from RWST to Spent Fuel Pit. SAT U N SAT STANDARD: Operator informs US and/or SM that flow has been established from RWST to Spent Fuel Pit.
Stop Time After operator reports that flow has been established, State This completes the JPM COMMENTS:
End Of 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 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 I is in mode 6 performing refueling operations. Approximately 1/2 of the core has been off-loaded at this time.
- 2. There is one fuel assembly in transit to the spent fuel pit from the core. It is presently in the upender cart in transient to the spent fuel pit.
- 3. The refueling SRO in the reactor building has just informed you that there is an obvious drop in reactor cavity level.
- 4. A dedicated operator that has been assigned to monitor vessel level instruments, informs you that there is a decreasing trend in Reactor cavity level indicators.
INITIATING CUES:
- 1. The refueling SRO reports a confirmed reactor cavity seal failure is occurring.
- 2. Alarm on panel 1-M-6D (D3) SPENT FUEL PIT LEVEL HIGH-LOW has just actuated.
- 4. The US directs you to perform AOP-M.04, Refueling Malfunctions (single performer method).
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 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 1 is in mode 6 performing refueling operations. Approximately 1/2 of the core has been off-loaded at this time.
- 2. There is one fuel assembly in transit to the spent fuel pit from the core. It is presently in the upender cart in transient to the spent fuel pit.
- 3. The refueling SRO in the reactor building has just informed you that there is an obvious drop in reactor cavity level.
- 4. A dedicated operator that has been assigned to monitor vessel level instruments, informs you that there is a decreasing trend in Reactor cavity level indicators.
INITIATING CUES:
- 1. The refueling SRO reports a confirmed reactor cavity seal failure is occurring.
- 2. Alarm on panel 1-M-6D (D3) SPENT FUEL PIT LEVEL HIGH-LOW has just actuated.
- 4. The US directs you to perform AOP-M.04, Refueling Malfunctions (single performer method).
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT AOl PROGRAM MANUAL ABNORMAL OPERATING PROCEDURES AOP-M.04 REFUELING MALFUNCTIONS Revision 9 QUALITY RELATED PREPARED/PROOFREAD BY: D. A. PORTER RESPONSIBLE ORGANIZATION: OPERATIONS APPROVED BY: Aaron Bergeron EFFECTIVE DATE: 10/26/09 REVISION DESCRIPTION: Revised Section 2.2 to reflect the equipment hatch and airlock doors being closed (PER 167420). Added reference to FHI-19 (PCR 09000953). Changed Section 2.1 to enhance step sequence Added new Appendix F for closing wafer valve.
r1.0 SQN PURPOSE REFUELING MALFUNCTiONS I AOP-M.04 Rev.9 to mitigate the effects of a dropped fuel This procedure provides the actions necessary cavity seal failure.
assembly, damaged fuel assembly, or refueling Page 2 of 42
SQN REFUELING MALFUNCTIONS OPJ STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2.0 OPERATOR ACTIONS
- 1. EVALUATE the following Tech Specs for applicability:
- 3.9.8.2, RHR - Low Water Level
- 3.9.10, Rx Vessel Water Level
- 3.9.11 Refueling Operations - Spent Fuel Pit Water Level
- 2. EVALUATE EPIP-1, Emergency Plan Initiating Conditions Matrix.
- 3. DIAGNOSE the failure:
IF... GOTO SECTION PAGE Reactor cavity seal has failed 2.1 4 Irradiated fuel assembly has been dropped or damaged inside containment 2 2 12 Irradiated fuel assembly has been dropped or damaged outside containment 23 17 New fuel assembly has been dropped or damaged 2.4 21 END OF SECTION Page 3 of 42
LSTEP SQN REFUELING MALFUNCTIONS ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED AOP-M.04 Rev.9 2.1 Reactor Cavity Seal Failure C.1]
CAUTION 1: Loss of Spent Fuel Pit or Refueling Cavity level and subsequent loss of shielding may result in extremely high dose rates in Containment and Spent Fuel Pit areas. C.11 CAUTION 2: If the reactor cavity water level drops to flange elevation with upender in vertical position, the top 0.25 inch of upender will extend above surface of water.
NOTE; Fuel Handling SRQ, personnel required to place fuel in safe location, and Radcon personnel should remain (if possible) until required actions are completed.
- 1. ANNOUNCE to all non-essential personnel to evacuate Containment and AB el. 734 Refuel Floor.
- 2. ENSURE the following personnel noti!fed that seal failure has occurred: tC.2)
- Control Room staff
- RADCON to monitor refueling area and Aux Bldg as required
- Fuel Handling Supervisor Page 4 of 42
SQN REFUELING MALFUNCTIONS AOP-M.04 Rev. 9 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 1 2.1 Reactor Cavity Seal Failure (contd)
CAUTION: Failure to maintain RWST level greater than 5% may cause CCPs or RHR pumps to lose suction.
- 3. MAINTAIN Refueling Cavity level as necessary:
- a. INITIATE makeup from RWST a. IF RWST NOT available, USING Appendix A, Filling Refueling THEN Cavity from RWST. PERFORM the following:
- 1) INITIATE makeup using normal charging with CCP suction aligned to VCT USING App. E, Refueling Cavity Makeup Using Normal Charging.
- 2) INITIATE actions to restore RWST level USING O-SO-62-4 (to transfer HUT to RWST) or other applicable procedures.
- 4) GO TO Step 4.
- b. MAINTAIN RWST level b. REALIGN pump suctions greater than 5%. USING Appendix A, Filling Refueling Cavity from RWST:
AOP-M.04 SQN REFUELING MALFUNCTIONS Rev.9 STEP I ACTION/EXPECTED RESPONSE I RESPONSE NOTOBTAINED 2.1 Reactor Cavity Seal Failure [C.l]
- 4. IF transfer tube wafer valve is OPEN OR position is unknown, THEN DISPATCH two operators to perform Appendix F, Closing Wafer Valve.
- 5. CHECK for any of the following: PERFORM the following:
- fuel movement in progress a. IF any radioactive component is being handled in Spent Fuel Pool or Refueling Cavity, THEN
- any irradiated fuel assembly out of normal storaae location NOTIFY Fuel Handling Supervisor (core or spent fuel pool). to ensure component is placed in storage location or lowered fully.
- b. GOTOStep8.
Page 6 of 42
REFUELING MALFUNCTIONS AOP-M.04 SQN Rev. 9 STEP I ACTION/EXPECTED RESPONSE I RESPONSE NOTOBTAINED I 2.1 Reactor Cavity Seal Failure [C.1]
- 6. VERIFY RCCA change fixture empty IF fuel in manipulator crane, of irradiated fuel. THEN PERFORM the following:
- a. PLACE irradiated fuel assembly located in manipulator crane into reactor side upender.
- b. TRANSPORT irradiated fuel assembly to SFP side upender.
- c. TERMINATE transporting with SFP side upender in horizontal position.
- d. REMOVE irradiated fuel assembly from RCCA change fixture.
- e. INSERT irradiated fuel assembly as far as possible into any available core location.
- f. RECORD location IF NO fuel in manipulator crane, THEN PERFORM the following:
- a. REMOVE irradiated fuel assembly from RCCA change fixture.
- b. INSERT irradiated fuel assembly as far as possible into any available core location.
- c. RECORD location (step continued on next page)
Page 7 of 42
AOP-M.04 SQN REFUELING MALFUNCTIONS Rev. 9 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2.1 Reactor Cavity Seal Failure [C.1)
- 6. Continued IF more than one irradiated fuel assembly in RCCA Change Fixture AND time allows, THEN PERFORM the following:
- a. REMOVE second irradiated fuel assembly from RCCA change fixture.
- b. INSERT irradiated fuel assembly as far as possible into any available core location.
- c. RECORD location
- 7. VERIFY manipulator crane empty of fuel. INSERT fuel assembly as far as possible into any available core location.
RECORD location
- 8. ENSURE the following:
- Fuel transfer cart on SFP side
- Upender in horizontal position
- 9. WHEN transfer cart is on SFP side, THEN NOTIFY operators with Appendix F to ensure wafer valve CLOSED.
Page 8 of 42
rSTEP SQN REFUELING MALFUNCTIONS ACTION/EXPECTED RESPONSE I RESPONSE NOTOBTAINED 0O4 1
2.1 Reactor Cavity Seal Failure (contd)
- 10. VERIFY SFP bridge hoist empty of fuel. PERFORM the following:
- b. INSERT fuel assembly into any SFP location.
- c. RECORD location
cooling pump suction strainer.
- a. STOP running SFP cooling pumps
[Aux Bldg, 714 elev, SFP Pump Platform]
- b. FILL SFP USING 0-SO-78-1 Spent Fuel Pit Cooling System.
- c. IF additional makeup is needed, THEN
- 1) NOTIFY Chem Lab Super%isor.
- 2) INITIATE makeup from Fire water to SFP using hose reel station as required.
- e. VENT SEP cooling pumps casings.
- f. START SFP cooling pump.
Page 9 of 42
AOP-M.04 SQN REFUELING MALFUNCTIONS Rev. 9 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2.1 Reactor Cavity Seal Failure (contd)
- 12. EVALUATE need to close containment equipment hatch:
- a. CHECK equipment hatch OPEN. a. GO TO Substep d.
- b. CONSULT Fuel Handling SRO and Radcon.
- c. IF equipment hatch requires closure, THEN NOTIFY Outage Management to initiate closure of equipment hatch.
- d. EVALUATE need to install equipment hatch concrete shield.
NOTE: Appendix B, Elevations and Distances, may be helpful in determining levels to be maintained.
Page 10 of 42
SQN REFUELING MALFUNCTIONS 0P041 LSTEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2.1 Reactor Cavity Seal Failure (contd)
- 14. CHECK TSC staffed. EVALUATE OPDP-9, Emergent Issue Response.
- 15. NOTIFY Chem Lab Supervisor to sample Containment Pit Sump for processing.
- 16. GO TO appropriate plant procedure.
END OF SECTION Page 11 of 42
SQN REFUELING MALFUNCTIONS I AOP-M.04 Rev.9 Page 1 of 3 APPENDIX A FILLING REFUELING CAVITY FROM RWST A. Initiation of Makeup from RWST IF initiating makeup from RWST using COP, THEN PERFORM the following:
- b. ENSURE the following charging valves OPEN:
- FCV-62-90 LI ri L.J I .. v ti c C I
- FCV-62-86 or FCV-62-85 LI
- c. OPEN the following valves:
- d. CLOSE the following valves:
- f. CLOSE FCV-62-81, Letdown Back Pressure Control Valve. LI
- h. VERIFY flow to ROS.
Page 28 of 42
AOP-M.04 SQN REFUELING MALFUNCTIONS Rev. 9 Page 2 of 3 APPENDIX A FILLING REFUELING CAVITY FROM RWST A. Initiation of Makeup from RWST (contd)
VERIFY RWST level greater than 8%.
LI a.
OPEN FCV-63-1, RWST Supply.
Li b.
- c. CLOSE one of the following valves:
Li
LI d.
Page 29 of 42
JPM Sim H-i Page 1 of 1 Rev. 0 SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE MEASURE SIM H (RO)
Shutdown the Diesel Generators (IA-A & lB-B)
JPM Sim H-i Page 2 of 2 Rev. 0 ROISRO JOB PERFORMANCE MEASURE Task: Shutdown the Diesel Generators (lA-A & lB-B)
Task#: 0640060101 (RO)
Task Standard: Diesel Generators lA-A & lB-B have been shutdown in accordance with EA-82-1.
Time Critical Task: YES: NO: X KIA ReferencelRatings: 064A4.06(3.9/3.9) 064A2.08 (2.5/2.7)
Method of Testing:
Simulated Performance: Actual Performance: X Evaluation Method:
Simulator X In-Plant Classroom Main Control Room Mock-up Performer:
Trainee Name Evaluator: I Name I Signature DATE Performance Rating: SAT: UNSAT:
Validation Time: 20 minutes Total Time:
Performance Time: Start Time: Finish Time:
COMMENTS
JPM Sim H-i Page 3 of 3 Rev. 0 SPECIAL INSTRUCTIONS TO EVALUATOR:
- 1. Critical steps are identified in step SAT/UNSAT column by bold print Critical Step.
- 2. Any UNSAT requires comments
- 3. Initialize in IC #188.
- 4. If IC-(188) not available, reset to IC #16, Trip the reactor, use 1-M-1 hand switch to emergency start the diesels generators. Close TDAFW level control valves.
- 5. To perform local actions of section 4.2, set BOTH RF EGRII and EGRI2 to TEST and THEN BOTH back to NORMAL to reset the DIG start signal. Set EGRO7 and EGR 08 to RESET to reset the 86L0R for the DGs.
- 6. Load Override AN:OVRDN[905] to OFF to clear the 40 RPM running alarm.
- 7. Ensure operator performs the following required actions for 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.
ToolslEquipmentlProcedures Needed:
EA-82-1, Placing DIGs in Standby
References:
Reference Title Rev No.
- 1. EA-82-1 Placing D/Gs in Standby 2
JPM Sim H-i Page 4 of 4 Rev. 0 READ TO OPERATOR DIRECTIONS TO TRAINEE:
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 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. The Unit tripped due to an inadvertent safety injection.
- 2. The safety injection has been terminated and the plant has been stabilized in MODE 3.
- 3. The Diesel Generators have been running unloaded for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and 40 minutes.
- 4. The status file is complete and there are no outstanding configuration log entries present for the Diesel Generators.
- 5. All Shutdown Boards are energized by offsite power and the SI signal has been reset.
- 6. EA-82-1, Sect 4.2, Resetting D/G Auto Start Signals, has been performed.
INITIATING CUES:
- 1. You have been directed to shutdown the lA-A Diesel Generator per EA-82-1.
JPM Sim H-i Page 5of5 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 1.: Obtain appropriate copy of procedure. SAT UNSAT STANDARD: Operator obtains a copy of EA-82-1 and proceeds to Section 4.1.
Start Time COMMENTS:
STEP 2.: 1. SELECT DIG to be shut down: SAT
. D/G lA-A
. D/G lB-B UNS
. D/G 2A-A____
. D/G 2B-B STANDARD: Operator checks IA-A and 1 B-B diesel generators being selected.
COMMENTS:
STEP 3.: 2. IF EA-202-1 was NOT used to unload the selected D/G, SAT THEN DISPATCH AUO to perform Section 4.2 to reset selected D/G emergency start signal. UNSAT STANDARD: Operator acknowledges, from initial conditions, that section 4.2 has previously been performed and moves to next step.
COMMENTS:
STEP 4.: 3. GO TO appropriate section based on table below: SAT UNSAT THEN DIG DIG DIG DIG
[F SELECTED IA-A 18-B 2A-A 28-B 60 TO SECTtON q
Se1icn4.3.
U&od& aterth 2 hcrs. Piging DG Cambubie. U D C Seicn44.
Unloaded le than 2 stt Dnwn DIG C u C C STANDARD: Operator determines that section 4.3 is the appropriate section since the D/G has been running unloaded more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
(also checks the IA-A and 1 B-B boxes.)
COMMENTS:
JPM Sim H-I Page 6 of 6 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT IUNSAT NOTE: The following steps are from section 4.3.
SAT STEP 5.: i OS1TlON sç1pt QGMODE SELECR switch tp PARALLEL UNSAT DIG MODE SELECTOR SWITCH PARALLEL J IA-A HS-82-13 C 1 B-B HS-82-46 C 2A-A HS-62-TS C Critical Step 28-S HS-82-108 C STANDARD: Operator places O-HS-82-18, DG lA-A MODE SELECTOR, to PARALLEL.
This step is critical to allow paralleling of DG to Shutdown bus COMMENTS:
STEP 6.: 2 TURN selected DiG SYNCHRONIZE switctito S?N SAT DIG SYNCHRONIZE SWITCH SYN UNSAT lA-A -KS-5747 C I B-B 1-146-57-74 C 2A-A 2-146-5747 C 28-B 2-HS-7-74 Critical Step STANDARD: Operator places O-HS-57-47 DG lA-A SYNCHRONIZE, to SYN.
This step is critical to allow DG breaker to be closed.
COMMENTS:
STEP 7.: 3. ENSURE selected DIG VOLTAGE REGULATOR switch in SAT PULL-P- AUTO:
UNSAT DIG VOLTAGE REGULATOR PULL-1-AUTO F SWITCH IA-A H642-12 C lB-B HS-62-42 C 2A-A H 642-72 C 28-8 RS-82-102 C STANDARD: Operator verifies O-HS-82-12, DG lA-A VOLTAGE REGULATOR to PULL-P-AUTO.
COMMENTS:
JPM Sim H-I Page 7 of 7 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 8 pJUST run3lpg yojge o rt incoming vojtag stj SAT DIG VOLTAGE MATCHED IA-A EI-2-4 E lB-S E-B2-34 EI42-3 2A-A E-82.M EI-S2-8 28-B E-B244 5142-95 Critical Step STANDARD: Operator adjusts O-HS-82-12, DG lA-A VOLTAGE REGULATOR, to match voltages on O-El-82-4 and O-El-82-5.
This step is critical allow safe parallel operation of the D/G.
COMMENTS:
STEP 9.: 5. ADJUST seieted.GSPEEb:CONTROL switch bNT1C rotating slowly .f:AST dition SAT SPEED CONTROL IN FAST DIG SYHCHROSCOPE UNSAT SWITCH DIRECTION IA-A HS-82-13 XI-82-1 C I B-B HS-82-43 X1-a2-31 C 2A-A HS-82-73 X1-S2-1 C 28-8 Hs-82-Ioa Xl42-91 C Critical Step STANDARD: Operator adjusts O-HS-82-13 until synchroscope O-Xl-82-l is rotating slowly in the fast direction.
This step is critical to allow DC breaker to closed without tripping the DG breaker on reverse power and or DG picking up too much load.
COMMENTS:
JPM Sim H-I Page 8 of 8 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 10.: WHEIsynchroope needle isfT2 q pc it 13L4 i.OSE sicqte DIGoptput reaI SAT E>IG SYNCHROSCOPE DIG OUTPUT UNSAT BREAKER lA-A XI-52-1 1-HS-74A 184 XJ-82-31 i-HS-7-73A 2A-A X-82-I 2-HS-57-48A 28-8 Xi-8231 24S-7-73A Critical Step STANDARD: Operator places 1-HS-57-46A to the close position when synchroscope 0-Xl-82-1 is at the 12 Oclock position resulting in the closing of the DG electrical breaker as indicated by Red Light LIT above the breaker hand switch.
This is a critical step so that the DG breaker wont trip back open due the DG being paralleled out of sync with the SD bus.
COMMENTS:
STEP 11.:
MWJdd to6MW SPEED CONTROL UNSAT SWITCH DG MEGAWATTS LB MW iA-A HS-82-13 E-$2-1GA IS-B HS-2-43 E1-B2-4GA C 2A-A HS-82-73 E1424DA C 28-B HS-s2-lc3 Critical Step E42-IOOA C STANDARD: Operator intermittently places 0-HS-82-1 3 to RAISE until the MW loading on 0-El-82-1 OA increases to 1.6 MW.
This is a critical step to ensure that the DG does not trip on reverse power COMMENTS:
JPM Sim H-i Page 9 of 9 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 12.: MAINTAIN *1. 1VAB (OUT) fØr, eiectd DI WKIEaraej With offsilé power SAT DIG VOLTAGE UNSAT REGULATOR SWITCH DIG MEGAVARS +1 MVAR IA-A HS-82-12 EI-621 IA D lB-B HS-8242 E-2-4IA D Critical Step 2A-A HS42-72 E-S24 IA C 2B-B HS-52-102 E42-iaiA C STANDARD: Operator places O-HS-82-12 to RAISE to establish the MVAR loading on O-El-82-1 1A to +1 MVAR outgoing, then maintains this MVAR loading as the DG is loaded by intermittently placing O-HS-82-12 to RAISE.
This is a critical step to ensure the DG is operated within normal parameters to prevent excessive generator heating.
COMMENTS:
STEP 13.: 9. DISPATCH an AUO to selected DIG building to monitor stack exhaust WHILE loading selected DIG. SAT Cue: Role Play as AUO acknowledge the direction to monitor the UNSAT DIG IA-A exhaust stack.
STANDARD: Operator dispatches an AUO to the DIG building to monitor D/G lA-A exhaust.
COMMENTS:
JPM Sim H-i Page 10 of 10 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT IUNSAT STEP 14 10 LOADselected DIGto 40 MW USING its DIG SPEED
, QfOL switcJ WHILE observing the following guidelines SAT
- a. IF stack exhaust smoke becomes twice as dense as normal during loading, THEN UNSAT STOP DIG loading UNTIL condition clears.
- b. WHEN exhaust smoke returns to normal, THEN Critical Step CONTINUE D/G loading. (shaded
- c. DO NOT CONTINUE this procedure UNTIL the following portion only) conditions are met:
D/GIoØdt4.OMW AND
. Stack exhaust NORMAL.
Cue: When the AUO is asked, state the exhaust has cleared up and now appears normal.
STANDARD: Operator loads the DIG lA-A to 4.0 MW by intermittently placing 0-HS-82-13 to RAISE until the MW loading on 0-El-82-10A increases to 4.0 mw.
This step is critical to ensure the DG is loaded to greater than minimum to clear the exhaust system of unused fuel which could cause a fire.
COMMENTS:
STEP 15.: Li$sctkd PtUftQ §brt 1i5IW rMWdead to £.5 MW: SAT DIG SPEED CONTROL SWITCH (L5 MW U NSAT lA-A j HS42-13 1BB HS-S2-43 D Critical Step 2A-A HS-2-T3 2BB HS-82-IG3 D STANDARD: Operator places 0-HS-82-13 to LOWER until the MW loading on 0-EI-82-1OA reduces to 0.5 mw.
This is critical to reduce DG load in preparation of shutdown COMMENTS:
JPM Sim H-i Page ii of ii Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 16 I2 ADJUST seleóed DIG VOLTAGREGULAtORstch t1oØ t/GMVAR l6ad tozero: SAT DIG VOLTAGE DIG MEGAVARS 0 MVAR UNSAT REGULATOR SWITCH IA-A HS-82-12 El-52-i 1A D lB-B HS-82-42 E142-41A D 2A-A HS-2-72 EL-52-71A C 25-B HSS2-1O2 EI.82-tDlA C STANDARD: Operator places O-HS-82-12 to LOWER until the MVAR loading on O-El-82-11A reduces toO.
COMMENTS:
STEP 17.: 13. sIeptQ pbeaj SAT DIG DIG OUTPUT BREAKER TRIPPED J lA-A l-HS-7-48A C UNSAT 1 B-S 1 -HS-7-73A C 2A-A 2-HS-7-4A C Critical Step 28-B 2-HS-7-73A C STANDARD: Operator places 1-HS 46A to the TRIP position.
This is a critical step needed to shutdown the DG.
COMMENTS:
STEP 18.: 14. GO TO Section 4.4 to shut down DIG.
SAT STANDARD: Operator goes to section 4.4 to shut down the DIG lA-A. UNSAT COMMENTS:
Evaluator Note: The following steps are from Section 4.4 STEP 19.: 1. VERIFY selected DIG unloaded with output breaker open: SAT DIG OUTPUT BREAKER UNLOADED 8 OUTPUT DIG BREAKER HANDSWITCN BREAKER OPEN UNSAT IA-A l12 I-HS-54-4A C lB-B l14 I-HS-57-73A C 2A-A I22 2-t4S-54-48A C ZB.B I24 2-HS-57-73A C STANDARD: Operator verifies DIG lA-a output breaker open by green light LIT over Handswitch 1-HS-54-46A.
COMMENTS:
JPM Sim H-i Page 12 of 12 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT IUNSAT STEP 20.: 2PLACE selected DIG(s) CONTROL START-STOP switch to SAT STOP:
UNSAT DIG DIG CONTROL STOP START-STOP SWITCH IA-A HS62-14 D 18-B HS-82-44 C Critical Step 2A-A HS-82-74 C 28-B HS-82-104 C NOTE: Operator may elect to turn the synchroscope on to verify DIG goes to idle speed when HS is placed to stop.
STANDARD: Operator places hand switch 0-HS-82-14, on panel 0-M-26, to the STOP.
This step is critical to stop the DG.
COMMENTS:
NOTE: Override AN:OVRDN[905] to OFF to clear the 40 RPM running alarm.
STEP 21.: 3. WHEN selected D/G(s) has run at idle speed (400 rpm) for 10 SAT minutes, THEN VERIFY DIG shuts down and speed drops to zero:
DIG ZERO RPM lA-A C 18-B C 2A-A C 28.-B U Cue: When alarm clears, CUE: 10 minutes have elapsed Cue: If AUO notified, role play and state: DIG is now at zero speed.
STANDARD: Operator addresses need to monitor this step. They may contact the AUO to have him/her contact the UO when speed is zero.
COMMENTS:
JPM Sim H-I Page 13 of 13 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 22.: 4$FE tedgR 1Q T?.1W SAT Ni1pqsitonz UNSAT DG MODE SELECTOR SWITCH PUSH IN UNIT l IA-A t-f-IS-82-8 Critical Step lB-B 1-1-15-82-48 D 2A-A 2-HS-82-78 D 2B-B 2-HS-82108 STANDARD: Operator places hand switch 1-HS-82-18, on panel O-M-26, to be in PUSH TO UNIT position.
This step is critical to ensure the DG is in its normal start alignment.
COMMENTS:
STEP 23.: 5. ENSURE selected DIG SYNCHRONIZE switch is in OFF: SAT D1c3 SVNCHRONLZE SWITCN OFF UNSAT IA-A 1-1-13-5747 0 I 8.-B 1-1-13-57-74 0 2A-A 2-1-15-5747 0 28-B 2-1-15-57-74 0 STANDARD: Operator places handswitch 1-HS-57-47, on panel O-M-26, in the OFF position.
COMMENTS:
JPM Sim H-i Page 14 of 14 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 24.: 6. WHEN selected D/G(s) have cooled, SAT THEN ENSURE ERCW valves to DIG heat exchangers closed: UNSAT DG ERCW TO DG HEAT EXCHANGERS CWSED 4- 1-Hs$?-&. a 1-Hs67-e a 1-HS477A 1-Hs7-A a 2-HS474A D 2-HS-e7-& a 2B-B 2-HS-7-37A 0 2-HS$7-eA a Play role of AUO: I will monitor DIG temperature and ensure DG IA-A ERCW valves are closed when DIG reaches ambient temp.
STANDARD: Operator addresses need to monitor this step. They may contact the AUO to have him/her monitor DIG temperatures and shut the ERCW valve, 1-FCV-67-66, when the DIG is at ambient conditions.
COMMENTS:
STEP 25.: 7. GO TO Section 4.1, step in effect. SAT STANDARD: Operator returns to section 4.1 and determines lA-A DG is UNSAT shutdown.
Cue: When candidate returns to section 4.1, state This completes the JPM.
Stop Time COMMENTS:
READ TO OPERATOR DIRECTIONS TO TRAINEE:
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 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. The Unit tripped due to an inadvertent safety injection.
- 2. The safety injection has been terminated and the plant has been stabilized in MODE 3.
- 3. The Diesel Generators have been running unloaded for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and 40 minutes.
- 4. The status file is complete and there are no outstanding configuration log entries present for the Diesel Generators.
- 5. All Shutdown Boards are energized by offsite power and the SI signal has been reset.
- 6. EA-82-1, Sect. 4.2, Resetting D/G Auto Start Signals, has been performed.
INITIATING CUES:
- 1. You have been directed to shutdown the lA-A Diesel Generator per EA-82-l.
READ TO OPERATOR DIRECTIONS TO TRAINEE:
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 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. The Unit tripped due to an inadvertent safety injection.
- 2. The safety injection has been terminated and the plant has been stabilized in MODE 3.
- 3. The Diesel Generators have been running unloaded for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and 40 minutes.
- 4. The status file is complete and there are no outstanding configuration log entries present for the Diesel Generators.
- 5. All Shutdown Boards are energized by offsite power and the SI signal has been reset.
- 6. EA-82-1, Sect. 4.2, Resetting D/G Auto Start Signals, has been performed.
INITIATING CUES:
- 1. You have been directed to shutdown the lA-A Diesel Generator per EA-82-l.
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT EOI PROGRAM MANUAL EMERGENCY ABNORMAL PROCEDURE EA-82-1 PLACING DIGs IN STANDBY Revision 2 QUALITY RELATED PREPARED/PROOFREAD BY: Marie Hankins RESPONSIBLE ORGANIZATION: OPERATIONS APPROVED BY: J.A. DVORAK EFFECTIVE DATE: 26 May 03 REVISION DESCRIPTION: Revised section 4.4 to add steps to place the Mode Selector switch in PUSH IN UNIT position and turn the Sync Switch to OFF. This is an intent change.
Added HS UNID for D/G output breakers in section 4.4 step 1.
Added a note in section 4.1 to clarify D/Gs have not been returned to TS operability but are placed in a condition for Auto Restart, if required prior to exiting the EOPs. This is a non-intent change.
I 1
SQN EA-82-1 PLACING DIGs IN STANDBY I Rev. 2 1,2 Page2ofl6 1.0 PURPOSE To shut down unloaded D/Gs and place the D/Gs in a standby condition. If a DIG has been running unloaded greater than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, this EAP will load it to purge combustibles and then unload it and shut it down.
2.0 SYMPTOMS AND ENTRY CONDITIONS 2.1 Entry Conditions A. E-O, Reactor Trip or Safety Injection.
B. E-1, Loss of Reactor or Secondary Coolant.
C. E-3, Steam Generator Tube Rupture.
D. ECA-2.l, Uncontrolled Depressurization of All Steam Generators.
E. ECA-3.l, SGTR and LOCA Subcooled Recovery.
F. ECA-3.2, SGTR and LOCA Saturated Recovery.
G. ECA-3.3, SGTR Without Pressurizer Pressure Control.
ES-i .2, Post LOCA Cooldown and Depressurization.
3.0 PRECAUTIONS AND LIMITATIONS 3.1 Precautions A. If the accountability siren sounds, the operator should continue performing this procedure. The SOS will remain aware of procedure progress and location of performing personnel.
3.2 Limitations A. This EAP does NOT meet all procedural and Technical Specification requirements for returning the D/Gs to a full standby condition. This procedure only returns the D/Gs to a condition for auto-restart to ensure availability if needed prior to exiting the EOPs.
SQN EA-82-1 PLACING DIGs IN STANDBY Rev. 2 1,2 Page 3 of 16 4.0 OPERATOR ACTIONS 4.1 Section Applicability
- 1. SELECT DIG to be shut down:
D/G lA-A
- DIGIB-B
- DIG 2A-A
- D/G 2B-B NOTE If EA-202-l was used to unload the selected D/G, then the D/G emergency start signal and the shutdown board blackout relays have already been reset.
- 2. IF EA-202-1 was NOT used to unload the selected DIG, THEN DISPATCH AUO to perform Section 4.2 to reset selected DIG emergency start signal. El
- 3. GO TO appropriate section based on table below:
THEN DIG DIG DIG DIG IF SELECTED DIG lA-A lB-B 2A-A 2B-B GO TO SECTION q q Section 4.3, Unloaded greater than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, Purging D/G Combustibles. E Section 4.4, Unloaded less than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, Shutting Down D/G.
SQN EA-82-1 PLACING DIGs IN STANDBY Rev. 2 1,2 Page4ofl6 4.1 Section Applicability (Continued)
- 4. IF another DIG to be shut down, THEN GO TO Step 4.1.1 NOTE This procedure places the D/Gs in a condition for Auto-Restart, if required prior to exiting the EOPs. Restoration to TS operability and procedural requirements for standby alignment is performed after the EOPs are exited.
- 5. RETURN TO procedure and step in effect.
END OF SECTION
SQN EA-82-1 PLACING DIGs IN STANDBY Rev. 2 1,2 Page5ofl6 4.2 Resetting DIG Auto Start Signals NOTE Performance of Steps 4.2.1 and 4.2.2 are required the first time this section is performed but their performance is not required on subsequent passes through this section.
- 1. NOTIFY UO to verify SI reset. El
- 2. RESET DIG emergency start signals by performing the following:
[6.9 KV shutdown board room]
- a. PLACE all D/G [43T(L)] switches to TEST:
SHUTDOWN BOARD LOGIC SWITCH TEST PANEL IA-A 43T(L) LI lB-B 43T(L) LI 2A-A 43T(L) LI 2B-B 43T(L) LI
- b. VERIFY emergency start signals RESET by observing amber lights lit:
SHUTDOWN BOARD LOGIC PANEL AMBER LIGHT LIT j
lA-A LI lB-B LI 2A-A LI 2B-B LI
SQN EA-82-1 PLACING DIGs IN STANDBY Rev. 2 1,2 Page6ofl6 4.2 Resetting DIG Auto Start Signals (Continued)
- c. PLACE all DIG [43T(L)1 switches to NOR:
SWITCH NOR SHUTDOWN BOARD LOGIC PANEL
.1 lA-A 43T(L) El lB-B 43T(L) Li 2A-A 43T(L) LI 2B-B 43T(L) LI
- 3. PERFORM the following:
- a. VERIFY DIG [86 LOR] red lights DARK:
DIG RELAY BOARD RED LIGHT DARK
.1 IA-A El lB-B El 2A-A LI 2B-B LI
- b. PLACE selected DIG [86 LOR] switch to RESET:
DIG RELAY BOARD SWITCH RESET
,J lA-A 86L0R LI lB-B 86L0R LI 2A-A 86L0R LI 2B-B 86 LOR LI
SQN EA-82-1 PLACING DIGs IN STANDBY Rev. 2 1,2 Page7ofl6 4.2 Resetting DIG Auto Start Signals (Continued)
- 4. GO TO Section 4.1, step in effect.
END OF SECTION
SQN I EA-82-1 PLACING DIGs IN STANDBY I Rev. 2 1,2 Page8ofl6 4.3 Purging DIG Combustibles CAUTION Only one diesel shall be operated in parallel with off-site power at any time.
NOTE This section purges the DIG of any combustibles accumulated during the unloaded condition prior to shutting down the DIG.
- 1. POSITION selected D/G MODE SELECTOR switch to PARALLEL:
DIG lA-A MODE SELECTOR SWITCH HS-82-18
[ PARALLEL El J
1 B-B HS-82-48 El 2A-A HS-82-78 U 2B-B HS-82-108 El
- 2. TURN selected DIG SYNCHRONIZE switch to SYN:
DIG SYNCHRONIZE SWITCH SYN IA-A 1-HS-57-47 El lB-B 1-HS-57-74 U 2A-A 2-HS-57-47 U 2B-B 2-HS-57-74 El
SQN EA-82-1 PLACING DIGs IN STANDBY Rev. 2 1,2 Page9ofl6 4.3 Purging DIG Combustibles (Continued)
- 3. ENSURE selected DIG VOLTAGE REGULATOR switch in PULL-P-AUTO:
DIG VOLTAGE REGULATOR PULL-P-AUTO q SWITCH lA-A HS-82-12 El 1 B-B HS-82-42 El 2A-A HS-82-72 El 2B-B HS-82-102 El
- 4. ADJUST running voltage to match incoming voltage USING D/G VOLTAGE REGULATOR switch:
DIG INCOMING RUNNING VOLTAGE VOLTAGE VOLTAGE MATCHED J lA-A EI-82-4 EI-82-5 El lB-B EI-82-34 EI-82-35 El 2A-A EI-82-64 EI-82-65 El 2B-B EI-82-94 El-82-95 El
- 5. ADJUST selected D/G SPEED CONTROL switch UNTIL associated synchroscope rotating slowly in FAST direction:
DIG SPEED CONTROL SLOWLY IN FAST SYNCHROSCOPE SWITCH DIRECTION J lA-A HS-82-13 XI-82-1 El lB-B HS-82-43 XI-82-31 El 2A-A HS-82-73 XI-82-61 El 2B-B HS-82-103 XI-82-91 El
SQN I I EA-82-1 PLACING DIGs IN STANDBY Rev. 2 1,2 Page 10 of 16 4.3 Purging DIG Combustibles (Continued)
NOTE When closing the DIG output breaker at 12 oclock position, consideration should be given to speed of rotation of synch roscope needle and time it takes to close the breaker.
-6. WHEN synchroscope needle is at 12 oclock position, THEN CLOSE selected DIG output breaker:
DIG OUTPUT D/G SYNCHROSCOPE CLOSED f BREAKER IA-A XI-82-1 l-HS-57-46A El lB-B XI-82-31 1-HS-57-73A El 2A-A XI-82-61 2-HS-57-46A El 2B-B XI-82-91 2-HS-57-73A El
- 7. ADJUST selected DIG SPEED CONTROL switch to raise D/G MW load to 1.6 MW:
SPEED CONTROL DIG SWITCH DIG MEGAWATTS 1.6 MW -J lA-A HS-82-13 EI-82-IOA El lB-B HS-82-43 EI-82-40A El 2A-A HS-82-73 EI-82-70A El 2B-B HS-82-103 EI-82-IOOA El
- 8. MAINTAIN +1 MVAR (OUT) for selected DIG, WHILE paralleled with offsite power:
DIG VOLTAGE DIG REGULATOR SWITCH DIG MEGAVARS +1 MVAR -J IA-A HS-82-12 EI-82-IIA El lB-B HS-82-42 EI-82-41A El 2A-A HS-82-72 EI-82-71A El 2B-B HS-82-102 EI-82-IOIA El
SQN EA-82-1 PLACING DIGs IN STANDBY Rev. 2 1,2 Pagellofl6 4.3 Purging DIG Combustibles (Continued)
- 9. DISPATCH an AUO to selected DIG building to monitor stack exhaust WHILE loading selected DIG.
- 10. LOAD selected D/G to 4.0 MW USING its D/G SPEED CONTROL switch WHILE observing the following guidelines:
- a. IF stack exhaust smoke becomes twice as dense as normal during loading, THEN STOP D/G loading UNTIL condition clears.
- b. WHEN exhaust smoke returns to normal, THEN CONTINUE D/G loading.
- c. DO NOT CONTINUE this procedure UNTIL the following conditions are met:
- D/Gloadat4.OMW AND
- Stack exhaust NORMAL.
- 11. ADJUST selected D/G SPEED CONTROL switch to lower D/G MW load to 0.5 MW:
DIG
[_SPEED CONTROL SWITCH 0.5 MW %J IA-A HS-82-13 LI I B-B HS-82-43 El 2A-A HS-82-73 El 2B-B HS-82-103 El
- SQN EA-82-1 PLACING DIGs IN STANDBY Rev. 2 1,2 Pagel2ofl6 4.3 Purging DIG Combustibles (Continued)
- 12. ADJUST selected DIG VOLTAGE REGULATOR switch to lower DIG MVAR load to zero:
DIG DIG VOLTAGE DIG MEGAVARS 0 MVAR REGULATOR SWITCH lA-A HS-82-12 EI-82-IIA El lB-B HS-82-42 EI-82-41A El 2A-A HS-82-72 El-82-71A El 2B-B HS-82-102 EI-82-1O1A El
- 13. PLACE selected DIG output breaker control switch to TRIP:
DIG D/G OUTPUT BREAKER TRIPPED /
lA-A 1-HS-57-46A El 1 B-B 1 -HS-57-73A El 2A-A 2-HS-57-46A El 2B-B 2-HS-57-73A El
- 14. GO TO Section 4.4 to shut down D/G.
END OF SECTION
SQN EA-82-1 PLACING DIGs IN STANDBY Rev. 2 1,2 Pagel3ofl6 4.4 Shutting Down DIG
- 1. VERIFY selected DIG unloaded with output breaker open:
DIG DIG OUTPUT BREAKER UNLOADED & OUTPUT BREAKER HANDSWITCH BREAKER OPEN q lA-A 1912 1-HS-54-46A El lB-B 1914 1-HS-57-73A El 2A-A 1922 2-HS-54-46A El 2B-B 1924 2-HS-57-73A El
- 2. PLACE selected DIG(s) CONTROL START-STOP switch to STOP:
DIG DIG CONTROL STOP-NJ START-STOP SWITCH lA-A HS-82-14 El 1 B-B HS-82-44 El 2A-A HS-82-74 El 2B-B HS-82-104 LI
- 3. WHEN selected DIG(s) has run at idle speed (400 rpm) for 10 minutes, THEN VERIFY DIG shuts down and speed drops to zero:
DIG ZERO RPM q IA-A El lB-B El 2A-A El 2B-B El
SQN EA-82-1
. PLACING DIGs IN STANDBY Rev. 2 1,2 Pagel4ofl6 4.4 Shutting Down DIG (Continued)
- 4. ENSURE selected DIG MODE SELECTOR switch in PUSH IN UNIT position:
DIG MODE SELECTOR SWITCH [PUSH IN UNIT lA-A 1-HS-82-18 El lB-B 1-HS-82-48 El 2A-A 2-HS-82-78 El 2B-B 2-HS-82-108 El
- 5. ENSURE selected DIG SYNCHRONIZE switch is in OFF:
DIG lA-A SYNCHRONIZE SWITCH l-HS-57-47
[ OFF El q
I B-B 1-HS-57-74 El 2A-A 2-HS-57-47 El 2B-B 2-HS-57-74 El
SQN EA-82-1 PLACING DIGs IN STANDBY Rev. 2 1,2 Pagel5ofl6 4.4 Shutting Down DIG (Continued)
- 6. WHEN selected DIG(s) have cooled, THEN ENSURE ERCW valves to DIG heat exchangers closed:
DIG ERCW TO DIG HEAT EXCHANGERS CLOSED 1 1-HS-67-66A Li lA-A 1-HS-67-68A Li 1-HS-67-67A Li lB-B 1-HS-67-65A Li 2-HS-67-66A Li 2A-A 2-HS-67-68A Li 2-HS-67-67A Li 2B-B 2-HS-67-65A Li
- 7. GO TO Section 4.1, step in effect. LI END OF TEXT
SQN EA-82-1 PLACING DIGs IN STANDBY Rev. 2 1,2 Pagel6ofl6
5.0 REFERENCES
None.
JPM INPLANT I Page 1 of 1 Rev. 0 SEQUOYAH NUCLEAR PLANT September2010 NRC Exam Plant I Spare Out a Vital Battery Charger
JPM INPLANT I Page 2 of 2 Rev. 0 JOB PERFORMANCE MEASURE Task: Spare Out a Vital Battery Charger Task#: 0630030104 (AUO)
Task Standard: Vital Battery Board # I being supplied via spare charger and the normal charger is de-energized.
Time Critical Task: YES: NO: X KIA Reference/Ratings: 063A4.01 (2.7/3.0) 063K4.02 (2.9/3.2)
Method of Testing:
Simulated Performance: X Actual Performance:
Evaluation Method:
Simulator In-Plant X Classroom Main Control Room Mock-up Performer:
Trainee Name Evaluator: /
Name I Signature DATE Performance Rating: SAT: UNSAT:
Validation Time: 15 minutes Total Time:
Performance Time: Start Time: Finish Time:
COMMENTS
JPM INPLANT I Page 3 of 3 Rev. 0 SPECIAL INSTRUCTIONS TO EVALUATOR:
- 1. Critical steps are identified in step SAT/UNSAT column by bold print Critical Step.
- 2. Any UNSAT requires comments
- 3. Do NOT allow the operator to open any compartment door which has relays mounted which could cause inadvertent tripping of equipment.
- 4. SM approval will be required to enter the Trip Hazard Zone in the Vital Battery Rm.
- 5. Ensure operator performs the following required actions for 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.
Tools/EquipmentlProcedures Needed:
0-SO-250-1 Section 8.1.1
References:
Reference Title Rev No.
A. 0-SO-250-1 I 25V DC Vital Power System 43
JPM INPLANT I Page 4 of 4 Rev. 0 READ TO OPERATOR Directions to Trainee:
I will explain the initial conditions, and state the task to be performed. All steps shall be simulated for this JPM. WHEN ENTERING A UNIT TRIP HAZARD ZONE ENSURE YOU DO NOT TOUCH ANY SWITCHES WITHIN THAT ZONE. I 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 I provided you. Do NOT open any compartment door which may have relays mounted on them.
INITIAL CONDITIONS:
- 1. Unit I is at 100% RTP.
- 2. All systems/components are OPERABLE.
- 3. All Technical Specification LCO5 satisfied.
- 4. Electrical Maintenance has scheduled a PM on 1 25V Vital Battery Charger # I which requires unloading the charger.
- 5. All prerequisites of 0-SO-250-1 are complete.
INITIATING CUES:
- 1. The CRC directs you, the Unit I Control Room AUO, to place the spare charger in service for Vital Battery Board I, and remove Vital Charger I from service per 0-SO-250-1. (Maintenance requests that we do not tag the charger at this time).
- 2. Inform the Unit 1 SRO when the # I charger is out of service.
JPM INPLAN i Page 5 of 5 Rev. 0 Job Performance Checklist:
STEP/STANDARD SAT/UNSAT STEP 1.: Operator obtains appropriate procedure to spare out VB charger # I. SAT UNSAT STANDARD: Operator obtains 0-SO-250-1, section 8.1 .1 to place Spare Charger 1-S in service in place of charger 1. Start Time COMMENTS:
Note:_1-S_Spare_Vital_Battery Charger_is_used_to_replace_I_or_II_Vital_Charger.
STEP 2.: [1J Ensure Power Checklist 0-250-1.09 has been performed (Spare SAT Charger Fuses).
UNSAT Cue: Power Checklist 0-250-1.09 is complete with NO deviations.
STANDARD: Operator explains how to, or checks configuration log to ensure checklist has been performed and no deviations exist which would potentially affect this operation.
COMMENTS:
STEP 3.: [2] Ensure Power Checklist 0-250-1.10 has been performed. SAT Cue: Power Checklist 0-250-1.10 is complete with NO deviations. UNSAT STANDARD: Operator explains how to, or checks configuration log to ensure checklist has been performed and no deviations exist which would potentially affect this operation.
COMMENTS:
STEP 4.: [3] ENSURE Spare Vital Battery Charger 1-S breakers are in OFF SAT position.
UNSAT A. 0-BKRC-250-QF/02-S, OUTPUT DC BKR is OFF B. 0-BKRC-250-QF/01-S, INPUT AC BKR is OFF
- a. The DC Power breaker is in the DOWN, OFF position.
- b. The AC Power breaker is in the DOWN, OFF position.
STANDARD: Operator locates the 1-S Spare Charger (El. 749 AB outside the VB rooms) and verifies both the DC and AC breakers are in the OFF (down) position.
COMMENTS:
JPM INPLAN I Page 6 of 6 Rev. 0 Job Performance Checklist:
STEP/STANDARD SAT/UNSAT STEP 5.: [4] Ensure timer for equalizing voltage on 1 -S spare charger is set to SAT Zero.
U N SAT Cue: Timer is set on zero.
STAN DARD: Operator verifies timer is on zero.
COMMENTS:
Note: Equipment referenced in the following two steps is located on the 480V AC Vital Transfer Switch 1-S.
STEP 6.: [5] IF 1-S Spare 125V Vital Battery Charger 480V AC transfer Switch is to SAT be aligned to 480V Shutdown Board 1A2-A THEN VERIFY ac potential light is LIT. UNSAT Cue: The potential light for the A train board is LIT.
STANDARD: Operator locates the transfer switch and VERIFIES that the potential light from 480 V SD Bd 1A2-A (A train) is LIT.
COMMENTS:
STEP 7.: ESUA-27-, Bkr F 8bVQID 1ATO SAT is in the ON posiop UNSAT The breaker is in the ON, UP, position.
STANDARD: Operator locates the A train feeder (orange placard), on the Spare 480V Critical Step Vital Trans Switch box and places it is in the closed, UP position.
This step is critical to ensure the spare charger will be aligned from the proper train to maintain operability of the battery board once aligned.
COMMENTS:
STEP 8.: [6] If 1-S Spare 1 25V Vital Battery Charger transfer switch is to be aligned SAT to 480V SD Bd IBI-B (alternate supply) THEN U N SAT STANDARD: Operator N/As this step.
COMMENTS:
JPM INPLAN I Page 7 of 7 Rev. 0 Job Performance Checklist:
STEP/STANDARD SAT/UNSAT STEP 9 [7] PCE O-Bk0-QiO2-S OUTPUT DC bFeakr onJp SAT chargçr çQj4poitioj.
U N SAT Cue: DC power breaker is in the UP (ON) position STANDARD: Operator locates DC POWER breaker and places it in the UP, ON Critical Step position.
This step is critical for spare charger breaker alignment.
COMMENTS:
STEP 10.: INPQt éalej6ni SAT p?bireift dN icsthon.*
UNSAT Cue: AC power breaker is in the UP (ON) position STANDARD: Operator locates AC POWER breaker and places it in the UP, ON Critical Step position.
This step is critical for spare charger breaker alignment.
COMMENTS:
STEP 11.: [91 VERIFY spare charger is energized with output voltage between 131 SAT and 138 volts indicated on 1-S charger voltmeter.
UNSAT Cue- Volts are at 134 volts.
STANDARD: Operator checks voltmeter to ensure voltage between 131 and 138 volts.
COMMENTS:
STEP 12.: [101 PLACE ALARM DISABLE switch on 1-S spare charger cabinet in ON SAT position.
UN SAT j* Switch is pointing to the ON position.
STANDARD: Operator rotates the ALARM DISABLE switch to the ON position [placing the alarm in service].
COMMENTS:
JPM INPLAN i Page 8 of 8 Rev. 0 Job Performance Checklist:
STEP/STANDARD SAT/UNSAT Note: Located on 1-S Spare 125V Vital Battery Charger 125V DC Transfer Switch on el 749 AB outside 125V Vital Batt Rm II.
STEP 13 1) breakr t&Vthr Battery B I frm SAT Spare Charger 1-S xSw is in theON positIon.
Lrns. Switch4s.next to the1S (spare) charger 1. 749) UNSAT Cue: Breaker is in the UP, ON position Critical Step STANDARD: Operator locates DC transfer switch and places the breaker to the #1 VBB (Feeder to #1 Vital Battery Board Red Placard) is in the UP, closed position.
This step is critical for spare charger breaker alignment.
COMMENTS:
Note: When the normal and spare chargers are in parallel on the battery board one will normally back the voltage of the other down to less than 90 volts, unless their output voltages are perfectly matched.
STEP 14.: [21PLCE o E5OHbN pTffon oi1. SAT Board I.
UNSAT Cue: Breaker is in the UP, ON position.
STANDARD: Operator locates breaker 225 (near bottom of board) and places it in the Critical Step UP, ON position.
This step is critical to tie the spare charger onto the Vital Battery Board I.
COMMENTS:
STEP 15.: 125V VITAL BATT CHGRj.NOR SAT
$0 PPIX, in OFFpiQn plrJ UNSAT Cue: Breaker is in the DOWN, OFF position.
STANDARD: Operator locates breaker 226 (near bottom of board) and places it in the Critical Step DOWN, OFF position.
This step is critical to ensure normal charger not parallel to spare charger.
COMMENTS:
JPM INPLAN I Page 9 of 9 Rev. 0 Job Performance Checklist:
STEP/STANDARD SAT/UNSAT Note: Due to differences in calibration and instrument scaling charger voltmeter ranges will be slightly different than_the_ranges_for_the_charger voltmeters_located_on_the_battery_boards.
STEP 16.: [14] VERIFY on Battery Board I 0-EI-250-KE1 -D, Spare Charger output SAT voltage, stabilizes at 131 .5 to 137.5 volts UNSAT Voltage stabilized at 134 volts, STANDARD: Operator checks Spare Charger Volt meter on Battery Board I to ensure charger voltage stabilizes between 131.5 and 137.5 volts.
COMMENTS:
STEP 17.: [15] VERIFY 0-El-250-KE3-D Battery Board I Voltmeter is within 5 volts of SAT 0-EI-250-KEI -D spare charger voltage.
UNSAT Cue: Battery Board voltage at 134 volts, Battery Charger voltage at 134 Volts.
STANDARD: Operator checks Battery Board Volt meters to Battery Board Voltage within 5 volts of charger voltage.
COMMENTS:
JPM INPLAN Page 10 of 10 Rev. 0 Job Performance Checklist:
STEP/STANDARD SAT/UNSAT Note: Placing either of the following breakers in the OFF position will result in annunciator window 1, 2-XA 1C (A4) actuation.
STEP 18.: £16] P CE the followrng breftkers in QFF.posipoon SAT shutdown çhrer.
UNSAT A) O-BKRC-250-QE/OiO, 3 25V DQ BATT CHGR I INPUT AC BKR ij OFF ositp B -BKaC-25O-pi02-Q, 125Y DctT HR iUTU1QQWih Critical Step QF popj NOTE: The following step should cause annunciation in the control room. If the operator fails to notify the Unit Operator prior to opening the following breakers make an annotation in the JPM remarks section.
Respond as Unit Operator if called and acknowledge report of incoming alarm.
Cue: a) AC POWER breaker is in the DOWN, OFF position b) DC POWER breaker is in the DOWN, OFF position.
STANDARD: Operator locates the #1 VB Charger and places the AC and DC power breakers in the down, OFF position.
This step is critical to shut down the charger and place in condition requested by Maintenance.
COMMENTS:
STEP 19.: INFORM the Unit 1 SRO that the #1 VB charger is out of service. SAT UNSAT STANDARD: Operator informs the Unit 1 SRO that the #1 VB charger is out of service.
Cue: This completes the JPM Comments: Stop Time
READ TO OPERATOR Directions to Trainee:
I will explain the initial conditions, and state the task to be performed. All steps shall be simulated for this JPM. WHEN ENTERING A UNIT TRIP HAZARD ZONE ENSURE YOU DO NOT TOUCH ANY SWITCHES WITHIN THAT ZONE. I 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 I provided you. Do NOT open any compartment door which may have relays mounted on them.
INITIAL CONDITIONS:
- 1. Unit 1 is at 100% RTP.
- 2. All systems/components are OPERABLE.
- 3. All Technical Specification LCOs satisfied.
- 4. Electrical Maintenance has scheduled a PM on 125V Vital Battery Charger # I which requires unloading the charger.
- 5. All prerequisites of 0-SO-250-1 are complete.
INITIATING CUES:
- 1. The CRC directs you, the Unit I Control Room AUO, to place the spare charger in service for Vital Battery Board I, and remove Vital Charger I from service per 0-SO-250-1. (Maintenance requests that we do not tag the charger at this time).
- 2. Inform the Unit 1 SRO when the # I charger is out of service.
READ TO OPERATOR Directions to Trainee:
I will explain the initial conditions, and state the task to be performed. All steps shall be simulated for this JPM. WHEN ENTERING A UNIT TRIP HAZARD ZONE ENSURE YOU DO NOT TOUCH ANY SWITCHES WITHIN THAT ZONE. I 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 I provided you. Do NOT open any compartment door which may have relays mounted on them.
INITIAL CONDITIONS:
- 1. Unit 1 is at 100% RTP.
- 2. All systems/components are OPERABLE.
- 3. All Technical Specification LCOs satisfied.
- 4. Electrical Maintenance has scheduled a PM on 125V Vital Battery Charger# I which requires unloading the charger.
- 5. All prerequisites of 0-SO-250-1 are complete.
INITIATING CUES:
- 1. The CRC directs you, the Unit I Control Room AUC, to place the spare charger in service for Vital Battery Board I, and remove Vital Charger I from service per 0-SO-250-1. (Maintenance requests that we do not tag the charger at this time).
- 2. Inform the Unit 1 SRO when the # I charger is out of service.
I !/j Sequoyah Nuclear Plant Unit 0 System Operating Instruction 0-SO-250-1 125 VOLT DC VITAL POWER SYSTEM Revision 0043 Quality Related Level of Use: Continuous Use Effective Date: 04-20-2009 Responsible Organization: OPS, Operations Prepared By: Judy R. Varner Approved By: J. K. Wilkes Current Revision Description Deleted references to TACF 0-07-009-250 which was removed U1C15 RFO with no Rev Bars at deletions. Removed references to TACF 0-07-009-250 in Attachment 11 Revision to incorporate PCF 028
SQN 125 VOLT DC VITAL POWER SYSTEM 0-SO-250-1 Unit 0 Rev. 0043 Page 8 of 177 PRECAUTIONS AND LIMITATIONS Failure to observe all posted radiation control requirements may result in unnecessary radiation absorbed dose.
Use exact replacement or acceptable substitute fuses in accordance with OPDP-7.
Each battery room shall have an exhaust fan in service at all times to prevent
explosive mixtures of hydrogen and oxygen from accumulating in the room.
e battery room personnel eyewash should be operable.
Opening both ac supply breakers to 480V vital transfer switches will result in a loss of normal potential to vital battery charger.
rvl 7
When replacing annunciator type fuses in fuse columns A, B, C, or D, place the fuse in the clip so that the blown fuse extension is toward the alarm bus.
- 4) Observe requirements of Sequoyah Safety and Health Manual, Part IV, when
/ working around batteries.
,0 Excessive grounds on dc system may cause spurious actuation of components during accident conditions. If ground voltage exceeds +/- 80 volts, request Maintenance Support to locate and clear ground. Submit work order for grounds exceeding +/- 25 volts.
0 The design operating limits for the I 25v dc Vital Power System are nd 140V dc (Reference 45N703-l and 45W703-9).
I 29V dc When the 125 V Vital Battery Charger is transferred to its alternate 480 V supply (480 V Vital AC transfer switch), the load for the 480 V Shutdown Board Transformer supplying that transfer switch must be reduced by 137kW (Approximately 184 HP) if the applicable unit is in Modes 1-4. This will ensure operability of the (125V) channel equipment, for that (480 V) train.
SQN 125 VOLT DC VITAL POWER SYSTEM 0-SO-250-1 Unit 0 Rev. 0043 Page 9 of 177 PRECAUTIONS AND LIMITATIONS (continued)
Various breakers associated with the 125V Vital Battery System have similar breaker numbers. Caution must be used to ensure the intended component is being manipulated.
Due to vendor recommendations and calibration tolerances between the battery boards and battery chargers, voltage ranges will differ. This difference is due to instrument accuracy (TSIR 98-ICE-250-957). Voltage ranges specified by Electrical Maint. PMs should NOT be used by operations as guidelines for voltage ranges.
Identification and isolation of system grounds will be performed per 0-GO-I 0 7 and 0-PI-EBT-250-00l.0
SQN 125 VOLT DC VITAL POWER SYSTEM 0-SO-250-1 Unit 0 Rev. 0043 Page 10 of 177 Date PREREQUISITE ACTIONS Throughout this Instruction where an IFITHEN statement exists, the step should be NIAd if the stated condition does not exist.
ENSURE Instruction to be used is a copy of the effective
/ version.
ENSURE Precautions and Limitations Section 3.0, has been
/ reviewed.
IF a clearance was issued on equipment, THEN ENSURE all safety grounds are removed before energizing equipment.
IF 125V Vital Battery is being placed in service, OR IF equalizing charge is being applied, THEN ENSURE battery cell electrolyte level is in normal range as marked on the cells.
IF work has been performed on Vital Battery Bank, OR IF inside Vital Battery Room, THEN ENSURE battery rooms are clean and free of obstruction to safe operations.
(1611
,X/
IF work has been performed inside Vital Battery Board Room, THEN ENSURE battery board rooms are clean and free of obstructions to safe operations.
SQN 125 VOLT DC VITAL POWER SYSTEM 0-50-250-1 Unit 0 Rev. 0043 Page 11 of 177 Date___
PREREQUISITE ACTIONS (continued)
ENSURE each performer documents their name and initials:
Print Name Initials i4e 8e INDICATE below which performance section of this Instruction will be used.
EJ 5.0 STARTUP/STANDBY READINESS D 6.0 NORMAL OPERATION 7.0 SHUTDOWN 8.0 INFREQUENT OPERATION REASON: Amo(J A4rQefr- .#/ 5ej-v/c e 4,1- rna;n-/eJ-7a.i IA 1 (ij
/
SQN 125 VOLT DC VITAL POWER SYSTEM 0-SO-250-1 Unit 0 Rev. 0043 Page 49 of 177 Date 8.0 INFREQUENT OPERATION 8.1 Spare Charger Supplying Vital Battery Boards 8.1.1 Placing Spare Charger in Service to Vital Battery Board I NOTE 1-S Spare Vital Battery Charger is used to replace I or II Vital Charger.
[1] ENSURE Power Checklist 0-250-1.09 has been performed (Spare Charger Fuses).
[2] ENSURE Power Checklist 0-250-1.10 has been performed.
[3] ENSURE [0-CHGB-250-QF-S1, SPARE 125V VITAL BATTERY CHARGER 1-S breakers are in OFF position (el 749 AB outside 125V Vital Batt Rm II) on spare charger):
A. [0-BKRC-250-QFIO2-S1, SPARE 125 DC BATT CHGR 1-S OUTPUT DC BKR, breaker. OFF 1 St CV B. [0-BKRC-250-QF/01-S1, SPARE 125 DC BATT CHGR 1-S INPUT AC BKR, breaker. OFF 1 st CV
[4] ENSURE timer for equalizing voltage on 1-S spare charger is set to ZERO.
SQN 125 VOLT DC VITAL POWER SYSTEM 0-SO-250-1 Unit 0 Rev. 0043 Page 50 of 177 Date 8.1.1 Placing Spare Charger in Service to Vital BatteryBoard I (continued)
NOTE Equipment referenced in the following two steps is located on the 480V AC Vital Transfer Switch 1-S.
[5] IF [0-XSW-250-KV-S1, Spare 480V AC Vital Transfer Switch l-S, is to be aligned to 480V Shutdown Board 1A2-A, THEN
[5.1] VERIFY ac potential light is LIT. 0
[5.2] ENSURE [0-BKRA-250-KVII -SI, Bkr From 480V SDIBD 1A2-A To Spare 480V AC Vital XSW 1-S, breaker is in the ON position.
1st CV
[6] IF I0-XSW-250-KV-S1, Spare 480V AC Vital Transfer Switch 1-S,is to be aligned to 480V Shutdown Board IBI-B, THEN
[6.1] CONSULT Engineering for concurrence and applicability of Tech Specs. 0
[6.2] IF Unit us in Modes 1-4, THEN REMOVE 137kW of load from the IB1-B 480 V Shutdown Board Transformer.
US/SRO
[6.3] VERIFY ac potential light is LIT. 0
[6.4] ENSURE 10-BKRA-250-KVI2-S], Bkr From 480V SDIBD 1 B1-B To Spare 480V AC Vital XSW 1-S, is in the ON position.
CV
SQN 125 VOLT DC VITAL POWER SYSTEM 0-SO-250-1 Unit 0 Rev. 0043 Page5lofl77 Date 8.1.1 Placing Spare Charger in Service to Vital Battery Board I (continued)
[7] PLACE F0-BKRC-250-QF/02-S1, SPARE 125 DC BATT CHGR 1-S OUTPUT DC BKR, spare charger cabinet in ON position.
1 St CV
[8] PLACE F0-BKRC-250-QFIOI-S1, SPARE 125 DC BATT CHGR 1-S INPUT AC BKR, spare charger cabinet in ON position.
1 at CV
[9] VERIFY spare charger is energized with output voltage between 131 and 138 volts and stable as indicated on 1-S charger voltmeter. D
[10] PLACE [ALARM DISABLE1 switch on 1-S spare charger cabinet in ON position.
NOTE Located on 1-S Spare 125V Vital Battery Charger 125V DC Transfer Switch on el 749 AB outside 125V Vital Batt Rm II.
[11] ENSURE [0-BKRC-250-KW/1-S1, To Vital Bat Bd I From Spare 125V DC Chgr 1-S XSW, is in the ON position.
I st CV
SQN 125 VOLT DC VITAL POWER SYSTEM 0-SO-250-1 Unit 0 Rev. 0043 Page 52 of 177 Date 8.1.1 Placing Spare Charger in Service to Vital Battery Board I (continued)
NOTE When the normal and spare chargers are in parallel on the battery board one will normally back the voltage of the other down to less than 90 volts, unless their output voltages are perfectly matched.
[12] PLACE lO-BKRC-250-KE1225-D1, SPARE 125V BATT CHGR 1-S ALT SUPPLY in ON position on Vital Battery Board I.
1 st CV
[13] PLACE [0-SW-250-KE1226-D1, 125V VITAL BATT CHGR I NOR SUPPLY, in OFF position on Vital Battery Board I.
1st CV NOTE Due to differences in calibration and instrument scaling charger voltmeter ranges will be slightly different than the ranges for the charger voltmeters located on the battery boards.
[14] VERIFY on Battery Board I [0-El-250-KEI-D1 Spare Charger output voltage stabilizes at 131 .5 to 137.5 volts.
[15] VERIFY 10-EI-250-KE3-D1 Battery Board I voltmeter is within 5 volts of F0-EI-250-KEI -Dl spare charger voltage. D
SQN 125 VOLT DC VITAL POWER SYSTEM 0-SO-250-1 Unit 0 Rev. 0043 Page 53 of 177 Date 8.1.1 Placing Spare Charger in Service to Vital Battery Board I (continued)
N OTE Placing either of the following breakers in the OFF position will result in annunciator window 1, 2-XA-55-1 C (A4) actuation.
[16] PLACE the following breakers in OFF position on F125V VITAL BATT CHGR Ii to shutdown the charger (located el. 749 A.B., outside 125V Vital Batt Rm I):
A. F0-BKRC-250-QEIOI -Dl, 125V DC BATT CHGR I INPUT AC BKR. OFF I St Cv B. 10-BKRC-250-QEIO2-Dl, 125V DC BATT CHGR I OUTPUT DC BKR. OFF 1 St CV END OF TEXT
JPM Plant J Page 1 of 8 Rev. 0 SEQUOYAH NUCLEAR PLANT September 2010 NRC Exam PIantJ Local Control of MDAFW Pump Flow
JPM Plant J Page 2 of 8 Rev. 0 ROISRO JOB PERFORMANCE MEASURE Task: Local Control of MDAFW Pump Flow Task#: 3110060601 (RO) 0610020204 (AUO)
Task Standard: Locally control flow through one motor-driven AFW pump LCV.
Time Critical Task: YES: NO: X K/A ReferencelRatings: 061 K3.02 (4.2/4.4) EO5EK1.1 (3.8/4.1) 061A3.01 (4.2/4.2) 191 Ki .08 (3.4/3.4) 061A2.07 (34/35) 061A1.01 (3.9/4.4) 061A2.05 (3.1/34)
Method of Testing:
Simulated Performance: X Actual Performance:
Evaluation Method:
Simulator In-Plant X Classroom Main Control Room Mock-up Performer:
Trainee Name Evaluator: I Name I Signature DATE Performance Rating: SAT: UNSAT Validation Time: 14 minutes Total Time:
Performance Time: Start Time: Finish Time:
COMMENTS
JPM Plant J Page 3 of 8 Rev. 0 SPECIAL INSTRUCTIONS TO EVALUATOR:
- 1. Critical steps are identified in step SAT/UNSAT column by bold print Critical Step.
- 2. Any UNSAT requires comments
- 3. SM approval will be required to enter the Trip Hazard Zone in the Back up Cntrl Rm.
- 4. Insure operator performs the following required actions for 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.
ToolslEquipment/Procedures Needed:
EA-3-1O, Section 4.1 & 4.3
References:
Reference Title Rev No.
- 1. EA-3-1 0 Establishing Motor Driven AFW Flow
JPM Plant J Page 4 of 8 Rev. 0 READ TO OPERATOR Directions to Trainee:
I will explain the initial conditions, and state the task to be performed. All steps shall be simulated for this JPM. WHEN ENTERING A UNIT TRIP HAZARD ZONE ENSURE YOU DO NOT TOUCH ANY SWITCHES WITHIN THAT ZONE. I 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 I provided you.
INITIAL CONDITIONS:
- 1. Unit 1 has experienced a Rx trip from 100% power.
- 2. The Unit 1 turbine-driven AFW pump has tripped off for unknown reasons.
- 3. During recovery from the Rx trip, the control room operator was unable to control AFW flow to SIG 3.
4 The level control valve to loop 3 S/G will NOT close from the MCR.
5 All narrow range SIG levels are 15%.
INITIATING CUES:
- 1. The Unit 1 US has directed you, the control room AUO to establish control of the 1 B-B motor-driven AFW pump LCV for S/G # 3, using EA-3-1 0.
- 2. Inform the Unit I US when control of flow to SIG # 3 has been established.
JPM Plant J Page 5 of 8 Rev. 0 Job Performance Checklist:
STEP/STAN DARD SATIU NSAT STEP 1.: Obtain a copy of the appropriate procedure. SAT U N SAT STANDARD: Operator obtains a copy of EA-3-10.
Start Time STEP 2.: SELECT applicable unit and pump. SAT UNSAT STANDARD: Operator checks Unit 1 and MD AFW Pump B-B.
STEP 3.: If starting MD AFW pump locally.... SAT UNSAT IF asked: Pump is running.
STANDARD: Operator N/As this step.
STEP 4.: IF MD AFW LCV valve or controller failure has occurred, THEN GO TO SAT Section 4.3.
UNSAT STANDARD: Operator goes to section 4.3.
JPM Plant J Page 6 of 8 Rev. 0 Job Performance Checklist:
STEPISTANDARD SATIUNSAT STEP 5.: ATTEMPT to control AFW LCVs from the Auxiliary Control Room
[panels L-1 1 A and L-1 1 B].
NOTE: ENSURE THE SM HAS GIVEN PERMISSION FOR YOU AND THE OPERATOR TO ENTER THE UNIT TRIP HAZARD AREA.
ENSURE YOU AND THE OPERATOR REMAIN AWAY FROM ALL SWITCHES.
NOTE: This step is considered part of operator knowledge and the specific actions are not addressed by the procedure. SAT Cue: Inform the operator that the as found indication is that the auto UNSAT green light is illuminated and the controller output needle is to the far right.
NOTE: LCV-3-148 controller is located on panel L-IIB.
Cue: 1. if the manual button is depressed, inform the operator that the amber light illuminates and the auto green light goes out.
- 2. Controller output needle is to the far right.
- 3. When the operator looks at 1-FI-3-147C (1-L-10 panel) or calls, MCR: Flow is still at 200 gpm to the # 3 SIG.
STANDARD: The operator presses the manual button on 1-LIC-3-148 (Loop 3) and increases the output (pushes button on the bottom of the controller to the right) to cause the valve to Close (or verifies output is full right).
Looks at Fl-3-1 47C or Checks with the MCR to see if flow is reduced to the #3 SIG. (The operator may elect not to manipulate the controller by stating that the controller output is already indicating fully closed.)
NOTE: This starts the alternate path STEP 6.: If Step 4.3.1 has restored MD AFW flow, THEN: SAT UN SAT STANDARD: Operator should N/A this step.
STEP 7.: Establish communications with U-i MCR UO. SAT U NSAT Cue: If guidance is requested, direct AUO to locally isolate AFW flow to
- 3 SIG per EA-3-10.
STANDARD: Operator establishes communications with U-i MCR UO.
JPM Plant J Page 7 of 8 Rev. 0 Job Performance Checklist:
STEP/STANDARD SAT!UNSAT STEP 8.: Close upstream or downstream AFW LCV isolation valve for #3 SIG SAT UNSAT Cue: Valve handwheel moves several turns in the clockwise direction.
IF operator calls MCR: Give AFW flow to #3 S/G as zero gpm.
Critical Step NOTE: VLV-3-826 is at Aux Bldg, elev 714, AFW mezzanine VLV-3-834 is above WVVR entrance.
STANDARD: Operator unlocks and closes VLV-3-826, or VLV-3-834 for # 3 SIG.
This step is critical to isolate the flowpath of the failed open valve.
STEP 9.: NOTIFY UO to ensure MD AFW pumps running. SAT UNSAT Both MDADW pumps are running.
STANDARD: Operator checks with Unit 1 UO to ensure pumps running.
STEP 10 CONTROL S/G level as directed by UO by throttling AFW LCV isolation SAT valve UNSAT Cue: Roll play as UO and have the operator throttle open the valve previously closed, 3 turns open. After the adjustment is simulated, state flow is now approx 20 gpm and no further Critical Step manipulations will be needed.
STANDARD: Operator simulates turning valve handwheel 3 turns to the right to make adjustments as necessary to 3-826 or 3-834.
This step is critical to set the required flow to maintain adequate heat sink.
STEP 11.: Notify UO to operate pump recirculation valves FCV-3-400, 401. SAT Cue: Role play as UO and report that recirculation valves have been UNSAT operated STANDARD: Operator informs the UO to operate valves.
READ TO OPERATOR Directions to Trainee:
I will explain the initial conditions, and state the task to be performed. All steps shall be simulated for this JPM. WHEN ENTERING A UNIT TRIP HAZARD ZONE ENSURE YOU DO NOT TOUCH ANY SWITCHES WITHIN THAT ZONE. I 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 I provided you.
INITIAL CONDITIONS:
- 1. Unit I has experienced a Rx trip from 100% power.
- 2. The Unit I turbine-driven AFW pump has tripped off for unknown reasons.
- 3. During recovery from the Rx trip, the control room operator was unable to control AFW flow to SIG 3.
4 The level control valve to loop 3 SIG will NOT close from the MCR.
5 All narrow range S/G levels are 15%.
INITIATING CUES:
- 1. The Unit I US has directed you, the control room AUO to establish control of the I B-B motor-driven AFW pump LCV for S/G # 3, using EA-3-1 0.
- 2. Inform the Unit I US when control of flow to S/G # 3 has been established.
READ TO OPERATOR Directions to Trainee:
I will explain the initial condifions, and state the task to be performed. All steps shall be simulated for this JPM. WHEN ENTERING A UNIT TRIP HAZARD ZONE ENSURE YOU DO NOT TOUCH ANY SWITCHES WITHIN THAT ZONE. I 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 I provided you.
INITIAL CONDITIONS:
- 1. Unit I has experienced a Rx trip from 100% power.
- 2. The Unit I turbine-driven AFW pump has tripped off for unknown reasons.
- 3. During recovery from the Rx trip, the control room operator was unable to control AFW flow to S/G 3.
4 The level control valve to loop 3 SIG will NOT close from the MCR.
5 All narrow range SIG levels are 15%.
INITIATING CUES:
- 1. The Unit I US has directed you, the control room AUO to establish control of the 1 B-B motor-driven AFW pump LCV for SIG #3, using EA-3-1 0.
- 2. Inform the Unit I US when control of flow to SIG # 3 has been established.
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT EOI PROGRAM MANUAL EMERGENCY ABNORMAL PROCEDURE EA-3-1 0 ESTABLISHING MOTOR DRIVEN AFW FLOW Revision I QUALITY RELATED 1 PREPARED/PROOFREAD BY:
RESPONSIBLE ORGANIZATION:
W. T. LEARY OPERATIONS t
APPROVED BY: F. Soens DATE: 06/08/10 EFFECTIVE DATE: 06/09/10 VERIFICATION DATE: N/A VALIDATION DATE: N/A REVISION DESCRIPTION: Removed the local handswitches [HS-3-1 18B & -128B] option for starting MD AFW pump A-A and B-B respectively. Handswitches are/or will be deleted per DCN D222367A Stages 1 and 6 (09000177, 09000185, 09000187 & 09000189).
SQN EA-3-1 0 ESTABLISHING MOTOR DRIVEN AFW FLOW Rev. I 1,2 Page2ofl3 1.0 PURPOSE To provide instructions for establishing MD AFW flow by performing one or more of the following contingency actions:
- Verifying proper AFW valve alignment.
- Isolating pump recirculation lines.
- Aligning pump suction to ERCW.
2.0 SYMPTOMS AND ENTRY CONDITIONS 2.1 Entry Conditions A. E-0, Reactor Trip or Safety Injection.
B. FR-H.1, Loss of Secondary Heat Sink.
C. FRS.1, Nuclear Power Generation/ATWS.
3.0 PRECAUTIONS AND LIMITATIONS 3.1 Precautions A. If the accountability siren sounds, the operator should continue performing this procedure. The SOS will remain aware of procedure progress and location of performing personnel.
SQN EA-3-l0 ESTABLISHING MOTOR DRIVEN AFW FLOW Rev. I 1,2 Page3ofl3 4.0 OPERATOR ACTIONS 4.1 Section Applicability
- 1. SELECT applicable unit:
- Uniti____
- Unit2_____
- 2. SELECT applicable pump:
- MDAFWPumpA-A
SQN EA-3-1O ESTABLISHING MOTOR DRIVEN AFW FLOW Rev. I 1,2 Page4ofl3 4.1 Section Applicability (Continued)
- 8. RETURN TO procedure and step in effect.
SQN EA-3-1 0 ESTABLISHING MOTOR DRIVEN AFW FLOW Rev. I 1,2 Page5ofl3 4.2 Starting MD AFW Pumps Locally From 6900 V Shutdown Boards
- 1. IF manual control of AFW flow to the S!Gs desired OR SIG pressure less than 300 psig, THEN NOTIFY UD to close applicable MD AFW LCVs
- USING MANUAL BYPASS:
MDAFWPUMP MDAFWLCV VALVE CLOSED V
A-A LCV-3-1 64A LCV-3-156A E B-B LCV-3-148A LI LCV-3-171A LI
- a. PLACE transfer switch [XS-3-1181 in AUXILIARY.
[6900 V Shutdown Board 1(2)A-A, Compartment 10] LI
- c. IF AFW Train A flow less than 300 gpm, THEN NOTIFY UO to ensure recirculation valve [FCV-3-4001 open. LI
SQN EA-3-10 ESTABLISHING MOTOR DRIVEN AFW FLOW Rev. I 1,2 Page6ofl3 4.2 Starting MD AFW Pumps Locally From 6900 V Shutdown Boards (Continued)
- a. PLACE transfer switch IXS-3-1281 in AUXILIARY.
[6900 V Shutdown Board 1 (2)B-B, Compartment 101 LI
- c. IF AFW Train B flow less than 300 gpm, THEN NOTIFY UO to ensure recirculation valve rFCV-3-4011 open.
- 4. GO TO Section 4.1, step in effect.
END OF SECTION
- SQN EA-3-1 0 ESTABLISHING MOTOR DRIVEN AFW FLOW Rev. I 1,2 Page7ofl3 4.3 MD AFW LCV Valve or Controller Failure
[Panels L-i 1A and Li 1 B]
NOTE On loss of power or air, the MD AFW main LCVs fail open and the bypass LCVs fail closed.
- 3. ESTABLISH communications between local operator and MCR UO.
AT LEAST VALVE ONE PER SIG S/G NUMBER DESCRIPTION LOCATION CLOSED V
VLV-3-828 Upstream isolation Aux Bldg, elev 714, El AFW mezzanine 1 VLV-3-836 Downstream isolation In WVVR El VLV-3-827 Upstream isolation Aux Bldg, elev 714, El AFW mezzanine 2 Above WVVR VLV-3-835 Downstream isolation El entrance VLV-3-826 Upstream isolation Aux Bldg, elev 714, El AFW mezzanine VLV-3-834 Downstream isolation Above WVVR El entrance VLV-3-829 Upstream isolation Aux Bldg, elev 714, El AFW mezzanine VLV-3-837 Downstream isolation In WVVR El
SQN EA-3-l 0 ESTABLISHING MOTOR DRIVEN AFW FLOW Rev. I 1,2 Page8ofl3 4.3 MD AFW LCV Valve or Controller Failure (Continued)
- 6. CONTROL S/G level as directed by UD by throttling AFW LCV isolation valve(s) closed in Step 4.3. 4.:
SIG VALVE DESCRIPTION LOCATION THROTTLED NUMBER VLV-3-828 Upstream isolation Aux Bldg, elev 714, AFW mezzanine El VLV-3-836 Downstream isolation In WVVR El VLV-3-827 Upstream isolation Aux BIdg, elev 714, AFW mezzanine El 2 VLV-3-835 Downstream isolation Above WWR El entrance VLV-3-826 Upstream isolation Aux BIdg, elev 714, El AFW mezzanine VLV-3-834 Downstream isolation Above WVVR El entrance VLV-3-829 Upstream isolation Aux BIdg, elev 714, AFW mezzanine El VLV-3-837 Downstream isolation In WVVR El
- 7. NOTIFY UO to operate pump recirculation valves as follows:
MD AFW PUMP VALVE [ OPEN IF PUMP FLOW NUMBER_[_LESS THAN 300 GPM CLOSED IF PUMP FLOW GREATER THAN 300 GPM
[
A-A FCV-3-400 El El B-B FCV-3-401 El El
- 8. GO TO Section 4.1, step in effect.
END OF SECTION
SQN EA-3-l 0 ESTABLISHING MOTOR DRIVEN AFW FLOW Rev. I 1,2 Page9ofl3 4.4 Verifying MD AFW Valve Alignment
- 1. COORDINATE with UO and ENSURE the following valves in required condition as applicable:
REQUIRED DESCRIPTION VALVE LOCATION CONDITION V
MD AFW Pump A-A FCV-3-400 Aux Bldg, elev 690, recirc isolation at SA3 (SAl 2)
OPERABLE LI MD AFW Pump A-A VLV-3-936 Aux Bldg, elev 690, recirc isolation at SA3 (SAl 2), 5 ft off floor OPEN LI MD AFW Pump A-A VLV-3-938 Aux Bldg, elev 690, recirc isolation at SA3 (SAl 2), 5 ft off floor OPEN LI MD AFW Pump A-A vLV-3-803 Aux Bldg, elev 690, suction isolation by AFW Pump A-A OPEN LI MD AFW Pump B-B FCV-3-401 Aux BIdg, elev 690, at SA4 (SA13) OPERABLE recirc isolation LI Aux Bldg, elev 690, MD AFW Pump B-B at SA4 (between SA13 & SA14),
VLV-3-940 OPEN LI recirc isolation 5 ft off floor MD AFW Pump B-B Aux Bldg, elev 690, recirc isolation VLV-3-942 at SA4 (between SA13 & SA14), OPEN LI 5ft off floor MD AFW Pump B-B VLV-3-804 Aux Bldg, elev 690, suction isolation by AFW Pump B-B OPEN LI Condensate supply 0-VLV-3-800 Aux Bldg, elev 690, isolation southwest corner, 15 ft off floor OPEN LI CST A supply 0-VLV-2-504 Turbine Bldg, elev 685, to AFW isolation above centrifuge OPEN LI CST B supply o-VLV-2-505 Turbine Bldg, elev 685, to AFW isolation above centrifuge OPEN LI
- 2. IF any valve NOT in required condition, THEN CONSULT TSC for contingency action.
SQN EA-3-lO ESTABLISHING MOTOR DRIVEN AFW FLOW Rev. I 1,2 PagelOofl3 4.4 Verifying MD AFW Valve Alignment (Continued)
- 3. GO TO Section 4.1, step in effect.
END OF SECTION
SQN EA-3-1 0 ESTABLISHING MOTOR DRIVEN AFW FLOW Rev. I 1,2 PagelIofl3 4.5 Isolating MD AFW Pump Recirculation Lines
- 1. PLACE applicable pump transfer switch in AUX position:
MD AFW PUMP TRANSFER SWITCH LOCATION AUX RECIRCULATION VALVE SWITCH FCV-3-400 XS-3-400 Auxiliary Control Room, Li 1A LI FCV-3-401 XS-3-401 Auxiliary Control Room, L-1 1 B LI
- 2. IF Step 4.5. 1. NOT effective OR manual isolation preferred, THEN CLOSE applicable MD AFW pump recirculation isolation valve:
VALVE DESCRIPTION LOCATION CLOSED
[ }
VLV-3-938 MD AFW Pump A-A Aux Bldg, elev 690, at SA3 (SA12),
recirculation isolation 5 ft off floor LI VLV-3-942 MD AFW Pump B-B Aux Bldg, elev 690, at 5A4 (between recirculation isolation SAl 2 and SAl 3), 5 ft off floor
- 3. GO TO Section 4.1, step in effect.
END OF SECTION
SQN EA-3-1 0 ESTABLISHING MOTOR DRIVEN AFW FLOW Rev. I 1,2 PageI2ofI3 4.6 Aligning MD AFW Pump Suction to ERCW
- a. CLOSE ERCW tell tale drain valve [FCV-3-8071.
[Aux Bldg, elev 690, by MD AFW pump]
- b. NOTIFY UO to ensure ERCW to MD AFW Pump A-A suction valves [FCV-3-116A1 and IFCV-3-116B1 are open.
- a. CLOSE ERCW tell tale drain valve [FCV-3-8081. ü
[Aux Bldg, elev 690, by MD AFW pump]
- b. NOTIFY UO to ensure ERCW to MD AFW Pump B-B suction valves [FCV-3-126A1 and rFCV-3-126B] are open.
- 3. GO TO Section 4.1, step in effect.
END OF TEXT
SQN EA-3-1O ESTABLISHING MOTOR DRIVEN AFW FLOW Rev. I 1,2 Pagel3ofl3 5O REFERENCES 5.1 Drawings A. 1, 2-47W803-2, Auxiliary Feedwater.
JPM INPLANT K Page 1 of I Rev. 0 SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE MEASURE IN PLANT K (ROISRO)
Local Alignment of 2-RM-90-1 12 to Lower Containment
JPM INPLANT K Page 2 of 2 Rev. 0 ROISRO JOB PERFORMANCE MEASURE Task: Local Alignment of 2-RM-90-1 12 to Lower Containment Task #: 0730990101 (RO); 0730020104 (AUO)
Task Standard: Manually align 2-RM-90-1 12 (locally) to LOWER containment.
Time Critical Task: YES: NO: X K/A Reference/Ratings: 002A3.01 (3.7/3.9)
Method of Testing:
Simulated Performance: X Actual Performance:
Evaluation Method:
Simulator In-Plant X Classroom Main Control Room Mock-up Performer:
Trainee Name Evaluator: I Name I Signature DATE Performance Rating: SAT: UNSAT:
Validation Time: 20 minutes Total Time:
Performance Time: Start Time: Finish Time:
COMMENTS
JPM INPLANT K Page 3 of 3 Rev. 0 SPECIAL INSTRUCTIONS TO EVALUATOR:
- 1. Critical steps are identified in step SAT/UNSAT column by bold print Critical Step.
- 2. Any UNSAT requires comments.
- 3. Ensure operator performs the following required actions for 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.
Tools/EquipmentlProcedures Needed:
2-SO-90-2, Sections 5.1 and 8.3
References:
Reference Title Rev No.
- 1. 2SO-90-2 Gaseous Process Radiation Monitoring System 31 READ TO OPERATOR DIRECTIONS TO TRAINEE:
I will explain the initial conditions, and state the task to be performed. All steps shall be simulated for this JPM. WHEN ENTERING A UNIT TRIP HAZARD ZONE ENSURE YOU DO NOT TOUCH ANY SWITCHES WITHIN THAT ZONE. I 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 I provided you.
INITIAL CONDITIONS:
- 1. 2-RM-90-1 12 had been isolated and tagged electrically for maintenance. The Hold Order has been picked up from the breaker, the valve checklist (Attachment 3) is complete, but the pumps are off.
- 2. 2-RM-90-106 has just tripped and neither of its associated pumps can be started.
- 3. Precautions, Limitation and 2-SO-90-2 Section 4, Prerequisite Actions, are current, complete and signed off.
INITIATING CUES:
- 1. The Unit 2 CR0 has directed you, the Unit 2 Aux. Bldg AUO, to align rad. monitor 2RM-9O-1 12 to sample lower containment per 2-SO-90-2, Section 8.3 steps 1 through 4 (along with any other applicable sections).
JPM INPLANT K Page 4 of 4 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT! UNSAT STEP 1.: Obtain copy of procedure. SAT UNSAT STANDARD: 2-SO-90-2 Section 8.3 is identified as appropriate procedure. Stan Time_____
COMMENT:
STEP 2.: [1] ENSURE 2-RM-90-1 12 Upper Containment Rad Monitor in SAT service per the following:
UNSAT
[a] Valve checklist 2-90-2.03 (Attachment 3) complete.
Cue: If asked Valve checklist is complete.
STANDARD: Candidate notes that valve checklist is signed-off COMMENT:
STEP 3.: [b] Pump running (Section 5.1).
NOTE: The rad monitor flow alarms will not reset until the operator manually resets the alarms as indicated in the cues.
STANDARD: Operator determines that pump is NOT running and goes to Section 5.1.
COMMENT:
Evaluator Note: The following steps are from 2-SO-90-2, Section 5.1 STEP 4.: [1] INDICATE below which rad monitor will be placed in SAT service:
UNSAT STANDARD: Operator checks 2-RM-90-1 12.
Comment:
JPM INPLANT K Page 5 of 5 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 5.: [2] ENSURE the following valve checklist has been SAT completed for rad monitors to be placed in service.
UNSAT STANDARD: Operator indicates that 2-RM-90-1 12 valve checklist 2 2.03 Attachment 3 is complete.
Comment:
STEP 6.: [3] IF placing 2-RM-90-106 in service THEN SAT STANDARD: Operator N/As this step UNSAT COMMENT:
STEP 7.: [4] ENSURE radiation monitor heat trace is in service for SAT monitor being placed in service (N/A monitor not required)
UNSAT STANDARD: Operator N/As 2-RM-90-1 06 portion of step. Operator places 2-HS-90-1 12 to the ON position.
COMMENT:
STEP 8.: [5] IF testing heat trace circuit, THEN PERFORM Section 8.4 AND RETURN TO step [6]
Cue: Testing heat tracing IS complete.
STANDARD: Operator acknowledges that heat trace circuit testing is complete and continues with next step.
COMMENT:
STEP 9.: [6] COORDINATE with MIG to place 2-RM-90-1 06 or 112 SAT sample pumps In Service.
UNSAT Cue: Unit 2 CR0 will coordinate with MIG.
STANDARD: Coordination set up with MIG.
COMMENT:
JPM INPLANT K Page 6 of 6 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 10 [7] ESTABLISH tiggt radtion pl9nitor by pjg SAT UNSAT faJ: jFstarting 2RM9O-112 sample pump , THEN 1
. ES ne iefoflowing local startbuttofl Critical Step CUE: MIG has aligned the #1 sample pump for service.
STANDARD: Operator locates and indicates that HS-90-1 12A has been depressed.
This step is critical because it is required to start sample pump.
COMMENT:
STEP 11.: [b] IF starting 2-RM-90-106 sample pump, THEN..
STANDARD: Operator N/As this step UNSAT COMMENT:
STEP 12.: [c] NOTIFY I & C to adjust flow as required. SAT Cue: I & C has been contacted and will monitor flow. UNSAT STANDARD: Operator contacts I & C for support.
COMMENT:
STEP 13.: [d] IF flow cannot be established through the Rad Monitor SAT THEN Cue: Flow has been established through 2-RM-90-112.
STANDARD: Operator N/As this step COMMENT:
JPM INPLANT K Page 7 of 7 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 14.: [eJ IF placing [2-RM-90-1 12] in service THEN RESET
, SAT
[2-HS-90-1 12F] local low flow seal-in.
UNSAT STANDARD: Operator resets local low flow seal-in by turning [2-HS-90-1 12F]
to the left to reset.
COMMENT:
STEP 15.: [fJ ENSURE MCR malfunction alarms are RESET:
Cue: Role play as Unit 2 CR0 and state that alarms 2-RA-90-112B UNSAT and 112C are RESET STANDARD: Operator contacts MCR to ensure alarms 2-RA-90-1 I 2B, WindowA-2 and 2-RA-90-112C, WindowA-3 on M12D are DARK. Operator N/As alarms associated with 2-RM-90-106.
COMMENT:
STEP 16.: [g] IF placing RM-90-106 in service THEN STANDARD: Operator N/As step. UNSAT COMMENT:
STEP 17.: [8] IF performing source check of rad monitor, THEN Cue: Source check will not be performed at this time. UNSAT STANDARD: Operator returns to Section 8.3, Step [1] [c]
COMMENT:
Evaluator Note: The following steps are from 2-SO-90-2, Section 8.3:
JPM INPLANT K Page 8 of 8 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 18.: [c] 2-HS-90-1 12 Heat trace is in the ON position.
Cue: HS is in the ON position, based on performance of UNSAT Section 8.4 STANDARD: Operator determines 2-HS-90-112 heat trace is on based on prior performance of Section 8.4 steps.
COMMENT:
STEP 19.: [2] If testing the heat trace circuit, THEN STANDARD: Operator N/As step, since heat trace was tested previously. UNSAT COMMENT:
STEP 20.: [3] If 2-RE-90-1 12 background count rate is less than SAT 9000 cpm THEN UNSAT Cue: Source check is not required.
STANDARD: Operator N/As step.
COMMENT:
STEP 21 141 OPE ?Iy-9O8G CrâstieVa1e Beeen iijj. SAT UNSAT Cue: Valve turns CCW several turns then stops.
Critical Step STANDARD: Valve 2-ISIV-90-283G located & opened, handwheel turned as far left (counter-clockwise) as possible.
This is a critical task to place the rad monitor in service COMMENT:
JPM NPLANT K Page 9 of 9 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 22.: Unit 2 CR0 informed that 2-S0-90-2, Section 8.3, Steps 1 SAT through 4 are complete.
UNSAT Cue: Acknowledge report from operator.
STANDARD: Operator contacts MCR and reports procedure steps are completed COMMENT: Stop Time Cue: This completes the JPM.
READ TO OPERATOR DIRECTIONS TO TRAINEE:
I will explain the initial conditions, and state the task to be performed. All steps shall be simulated for this JPM. WHEN ENTERING A UNIT TRIP HAZARD ZONE ENSURE YOU DO NOT TOUCH ANY SWITCHES WITHIN THAT ZONE. I 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 I provided you.
INITIAL CONDITIONS:
- 1. 2-RM-90-1 12 had been isolated and tagged electrically for maintenance. The Hold Order has been picked up from the breaker, the valve checklist (Attachment 3) is complete, but the pumps are off.
- 2. 2-RM-90-1 06 has just tripped and neither of its associated pumps can be started.
- 3. Precautions, Limitation and 2-SO-90-2 Section 4, Prerequisite Actions, are current, complete and signed off.
INITIATING CUES:
- 1. The Unit 2 CR0 has directed you, the Unit 2 Aux. Bldg AUO, to align rad. monitor 2-RM-90-1 12 to sample lower containment per 2-SO-90-2, Section 8.3 steps I through 4 (along with any other applicable sections).
READ TO OPERATOR DIRECTIONS TO TRAINEE:
I will explain the initial conditions, and state the task to be performed. All steps shall be simulated for this JPM. WHEN ENTERING A UNIT TRIP HAZARD ZONE ENSURE YOU DO NOT TOUCH ANY SWITCHES WITHIN THAT ZONE. I 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 I provided you.
INITIAL CONDITIONS:
- 1. 2-RM-90-1 12 had been isolated and tagged electrically for maintenance. The Hold Order has been picked up from the breaker, the valve checklist (Attachment 3) is complete, but the pumps are off.
- 2. 2-RM-90-1 06 has just tripped and neither of its associated pumps can be started.
- 3. Precautions, Limitation and 2-SO-90-2 Section 4, Prerequisite Actions, are current, complete and signed off.
INITIATING CUES:
- 1. The Unit 2 CR0 has directed you, the Unit 2 Aux. Bldg AUO, to align rad. monitor 2-RM-90-1 12 to sample lower containment per 2-S0-90-2, Section 8.3 steps I through 4 (along with any other applicable sections).
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT SYSTEM OPERATING INSTRUCTION 2-SO-90-2 GASEOUS PROCESS RADIATION MONITORING SYSTEM Revision 37 QUALITY RELATED PREPARED/PROOFREAD BY: CWMATHES RESPONSIBLE ORGANIZATION: OPERATIONS APPROVED BY: W. T. LEARY EFFECTIVE DATE: 11/23/09 LEVEL OF USE: CONTINUOUS USE REVISION DESCRIPTION: Revised to add RM-90-400 disconnect switch to the Power Checklist (PCR 08000520). Deleted IV column from checklist per management expectations Added reference to 0-PI-OPS-301-001 .0 in section 5 and 7(PCR 07000296). Corrected UNID for 2-RE-90-400 monitor in section 8.9 ( PCR 09001013). Added section 8.11 and revised 5.3 for the primary sampling pumps alignments( PCR 09000155 & 09001215).
Added step in section 8.9 to return sampling to automatic mode. Added LCO reference to section 8.1 & 8.8 (07000469). Replaced MIG with I & C throughout document to reflect organization name change.
GASEOUS PROCESS RADIATION 2-SO 2 MONITORING SYSTEM Rev: 37 Page 8 of 75 PRECAUTIONS AND LIMITATIONS Failure to observe all posted radiation control requirements may lead to unnecessary radiation absorbed doses.
Pump damage may occur from excessive heat if pumps are isolated, either manually or automatically, with the pump running.
Rad monitors which can initiate an Engineered Safety Feature (ESF) Actuation shall be blocked before any maintenance activity, functional test, or return to service is performed. [C.1]
Do not block any rad monitor that has a redundant monitor unless that redundant monitor is operable.
(?JTo prevent unmonitored releases, with one unit in Mode 1, 2, or 3 and the other in Mode 4, 5, or 6, Shield Building Vent Monitor for shutdown unit is required to be operable to satisfy NUREG-0737 and FSAR Post Accident Sampling requirements the operating unit. [C.4]
Action 28 of LCD 3.3.3.1 and action 19 of LCD 3.3.2, Table 3.3-3 must be complied with before blocking 2-RM-90-130 and 2-RM-90-131 simultaneously during Modes 2,3,4, cr6.
Moisture accumulation in the 2-RM-90-106 and 112 rad monitors pump supply lines will occur if the heat trace circuit is turned OFF or has a break in the wiring circuit.
The heat trace thermostat will maintain approximately 110°F on the monitors pump supply lines. This temperature will keep the warm, sometimes humid, containment sample air which passes through the cool Aux. Bldg to the rad monitors above its dew point.
Either 2-RM-90-99 or 2-RM-90-1 19 must be in service to monitor the low range of F the Condenser Vacuum Exhaust. Both monitors should not be in service at the me time for extended periods, due to flow limitations.
(42-RM-90-1o6/2-RM-9o-4o0 local sample pump handswitches have AUTO-OFF HAND positions. Normally AUTO position is used if starting/stopping pumps from the MCR (2-Rl-90-106AJ2-RI-90-400A). Using HAND position bypasses MCR start/stop capability.
GASEOUS PROCESS RADIATION 2-SO-90-2 MONITORING SYSTEM Rev: 37 Page 9 of 75 Date 7dc*.y TEREQUISITE ACTIONS Throughout this Instruction, where an IF/THEN statement exists, the step should be NIA if the condition does not exist.
JENSURE the Instruction to be used is a copy of the effective version.
if ENSURE Precautions and Limitations, Section 3.0, has been reviewed.
ENSURE Power Checklist 2-90-2.01 complete (Attachment 1).
DICATE below which performance section of this Instruction will be used and the reason for this performance:
LI 5.0 STARTUP/STANDBY READINESS LI 7.0 SHUTDOWN 8.0 INFREQUENT OPERATION REASON: /irn 4
, 2-fm- O t<
GASEOUS PROCESS RADIATION 2-SO-90-2 MONITORING SYSTEM Rev: 37 Page 47 of 75 Date 8.3 Aligning Containment Upper Compartment Monitor to Lower Compartment NOTE I 2-RM-90-106 and 2-RM-90-112 do not initiate CVI.
NOTE 2 I & C support is required when placing RM-90-106 sample pumps in service, shutting them down or swapping sample pumps.
Configuration control for sample pump suction and discharge valves and flow adjustments through the RM are performed by I & C.
NOTE 3 I & C support is required to adjust flow for 2-RM-90-112 sample pumps when placing in service or swapping pumps due to vacuum switches.
NOTE 4 Heat Trace handswitches are located at the Heat Trace Control Panel f2-JBOX-90-39191, east wall adjacent to 2-RM-90-106.
[I] ENSURE 2-RM-90-1 12 Upper Compartment Rad Monitor in service per the following:
[a] Valve Checklist 2-90-2.03 (Attachment 3) complete.
[b] Pump running (Section 5.1).
[c] [2-HS-90-112], heat trace is in the ON position.
[2] IF testing the heat trace circuit, THEN PERFORM Section 8.4 AND RETURN TO step [3]. IZ NOTE High background count rate may mask the source and prevent an upward deflection when source check is performed. Source check of RE-90-112 is not required for TS operability.
[3] IF 2-RE-90-1 12 background count rate is less than 9,000 cpm, THEN PERFORM Section 8.1 of this Instruction to source check 2-RM-90-112.
1 GASEOUS PROCESS RADIATION 2-SO-90-2 MONITORING SYSTEM Rev: 37 Page 48 of 75 Date 8.3 Aligning Containment Upper Compartment Monitor to Lower Compartment (Continued)
[4] OPEN [2-ISIV-90-283GI Crosstie Valve Between Upper and Lower Compartment Rad Monitors.
1st IV
[5] ENSURE the following FCVs are OPEN:
VALVE_NO. INITIALS 2-FCV-90-1 08 1st IV 2-FCV-90-109 1st iv 2-FCV-90-1 07 1st IV 2-FCV-90-1 17 1st IV 2-FCV-90-116 1st IV
[6] ENSURE [2-RM-90-1121 is operable by verifying the following:
- Power ON light illuminated. El
- Instrument malfunction alarms clear. El
- CPM reading of at least background level. El
GASEOUS PROCESS RADIATION 2-SO-90-2 MONITORING SYSTEM Rev: 37 Page 10 of 75 Date 5.0 STARTUP/STANDBY READINESS 5.1 Placing Containment Building Upper and Lower Compartment Air Monitors in Service NOTE Containment Building Lower and Upper Compartment Air Monitors 2-RM-90-106 and 2-RM-90-1 12 do not initiate CVI.
[1] INDICATE below which rad monitor will be placed in service:
RAD MONITOR FUNCTION E Contain ment Bldg Lower 2-RM-90-1 06 Compartment_Air_Monitor Containment Bldg Upper 2-RM-90-1 12 Compartment_Air_Monitor
[2] ENSURE the following valve checklist has been completed for rad monitors to be placed in service (N/A any others):
RAD VALVE ATTACH FUNCTION INITIALS MONITOR CHECKLIST NUMBER Containment Bldg 2RM90106 Lower Compartment 2-90-2.02 2 Air_Monitor Containment Bldg 2RM901 12 Upper Compartment 2-90-2.03 3 Air_Monitor
GASEOUS PROCESS RADIATION MONITORING SYSTEM 2-SO-90-2 Rev: 37 Page 11 of 75 Date I
5.1 Placing Containment Building Upper and Lower Compartment Air Monitors in Service (Continued)
[3] IF placing 2-RM-90-106 in service, THEN ENSURE 12-ISIV-90-283G1 Crosstie Valve Between Upper and Lower Compartment Rad Monitors is CLOSED (Valve Checklist 2-90-2.03).
NOTE I Heat Trace handswitches 2-HS-90-1 06 and 112 are located at the Heat Trace Control Panel [2-JBOX-90-3919], east wall adjacent to 2-RM-90-1 06.
NOTE 2 Amber lights may or may not be illuminated. With the handswitch in the ON position the amber indicating lights will be ON if the thermostat senses temperature less than 110°F.
[4] ENSURE radiation monitor heat trace is in service for monitor being placed in service (NA monitor not required):
HANDS WITCH DESCRIPTION POSITION INITIALS Heat Trace for 2-RM-90-106 ON 2-HS-90-106 activated Heat Trace for 2-RM-90-1 12 ON 2-HS-90-112 activated
[5] IF testing heat trace circuit, THEN PERFORM Section 8.4 AND RETURN TO step [6].
GASEOUS PROCESS RADIATION 2-S0-90-2 MONITORING SYSTEM Rev: 37 Page 12 of 75 Date 5.1 Placing Containment Building Upper and Lower Compartment Air Monitors in Service (Continued)
NOTE I I & C support is required when placing RM-90-106 sample pumps in service, shutting them down or when swapping pumps.
Configuration control for sample pump suction and discharge valves and flow adjustments through RM is performed by I & C.
NOTE 2 I & C support is required to adjust flow for 2-RM-90-1 12 sample pumps when placing in service or swapping pumps due to vacuum switches.
[6] COORDINATE with I & C to place 2-RM-90-1 06 or 112 sample pumps In Service.
[7] ESTABLISH flow through radiation monitor by performing the following steps:
[a] IF starting [2-RM-90-112] sample pump, THEN DEPRESS one of the following local START buttons:
HS-90-112A Pump 1 START HS-90-112B Pump2 START
[b] IF starting [2-RM-90-106] sample pump, THEN
- 1. ENSURE [HS-90-I 06B1 local (AUTO-OFF-HAND) handswitch in AUTO position for sample pumps.
- 2. ENSURE I & C has completed valve alignments for pump to be placed In Service USING 2-PI-IPM-90-1 06.0.
- 3. DEPRESS one of the following pushbuttons, AND CHECK PB illuminated: (N/A other)
LOCATION UNID PUSHBUTTON PB ILLUMINATED q INITIALS Local 2-RI-90-106B FLOW LI MCR 2-RI-90-106A FLOW [1
GASEOUS PROCESS RADIATION 2-S0-90-2 MONITORING SYSTEM Rev: 37 Page 13 of 75 Date 5.1 Placing Containment Building Upper and Lower Compartment Air Monitors in Service (Continued)
[c] NOTIFY I & C to adjust flow as required using 2-SI-IFT-090-1 12.0, Functional Test of Containment Building Upper Compartment Air Monitor 2-R-90-1 12. U
[d] IF flow cannot be established through the Rad Monitor, THEN NOTIFY Unit Operator.
[e] IF placing [2-RM-90-1121 in service, THEN RESET [2-HS-90-112F] local low flow seal-in.
[f] ENSURE MCR malfunction alarms are RESET (N/A any monitor not being placed in service):
MONITOR ALARM PANEL WINDOW INITIALS 2-RA-90-106B 0-XA-55-12D A-5 2-RA-90-1 06C 0-XA-55-1 2D A-6 2-RA-90-112B 0-XA-55-12D A-2 2-RA-90-1 12C 0-XA-55-12D A-3
[g] IF placing [2-RM-90-106] in service, THEN VERIFY acceptable flow by verifying green OPER LED indicators ILLUMINATED either 2-RI-90-106B (local) or 2-RI-90-106A (MCR).
GASEOUS PROCESS RADIATION 2-SO-90-2 MONITORING SYSTEM Rev: 37 Page 14 of 75 Date 5.1 Placing Containment Building Upper and Lower Compartment Air Monitors in Service (Continued)
NOTE If placing 2-RM-90-1 06 or 112 in service and background count rate is greater than 9,000 cpm, then step [8] source check performance may be NAd.
[8] IF performing source check of rad monitor, THEN GO TO Section 8.1.
END OF SECTION
JPM NPLANT K Page 1 of 1 Rev. 0 SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE MEASURE INPLANT K (RO/SRO)
Local Alignment of 1-RM-90-112 To Lower Containment
JPM INPLANT K Page 2 of 2 Rev. 0 ROISRO JOB PERFORMANCE MEASURE Task: Local Alignment of 1 -RM-90-1 12 to Lower Containment Task#: 0730990101 (RO); 0730020104 (AUO)
Task Standard: Manually align 1-RM-90-1 12 (locally) to LOWER containment.
Alternate Path: YES: NO: X Time Critical Task: YES: NO: X KIA ReferencelRatings: 002A3.01 (3.7/3.9)
Method of Testing:
Simulated Performance: X Actual Performance:
Evaluation Method:
Simulator In-Plant X Classroom Main Control Room Mock-up Performer:
Trainee Name Evaluator: /
Name I Signature DATE Performance Rating: SAT: UNSAT:
Validation Time: 20 minutes Total Time:
Performance Time: Start Time: Finish Time:
COMMENTS
JPM INPLANT K Page 3 of 3 Rev. 0 SPECIAL INSTRUCTIONS TO EVALUATOR:
- 1. Critical steps are identified in step SAT/UNSAT column by bold print Critical Step.
- 2. Any UNSAT requires comments
- 3. Ensure operator performs the following required actions for 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.
ToolslEquipmentlProcedures Needed:
1-SO-90-2, Sections 5.1 and 8.3
References:
Reference Title Rev No.
- 1. 1 -SO-90-2 Gaseous Process Radiation Monitoring System 38
JPMINPLANTK Page 4 of 4 Rev. 0 READ TO OPERATOR DIRECTIONS TO TRAINEE:
I will explain the initial conditions, and state the task to be performed. All steps shall be simulated for this JPM. WHEN ENTERING A UNIT TRIP HAZARD ZONE ENSURE YOU DO NOT TOUCH ANY SWITCHES WITHIN THAT ZONE. I 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 I provided you.
INITIAL CONDITIONS:
- 1. 1 -RM-90-1 12 had been isolated and tagged electrically for maintenance. The Hold Order has been picked up from the breaker, the valve checklist (Attachment 3) is complete, but the pumps are off.
- 2. 1-RM-90-106 has just tripped and neither of its associated pumps can be started.
- 3. Precautions, Limitation and 1-SO-90-2 Section 4, Prerequisite Actions, are current, complete and signed off.
INITIATING CUES:
- 1. The Unit 1 CR0 has directed you, the Unit 1 Aux. Bldg AUO, to align rad. monitor 1-RM-90-112 to sample lower containment per 1-SO-90-2, Section 8.3 steps I through 4 (along with any other applicable sections).
JPM INPLANT K Page 5 of 5 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 1.: Obtain copy of procedure. SAT UNSAT STANDARD: 1-S0-90-2 Section 8.3 is identified as appropriate procedure. Start Time_____
COMMENT:
STEP 2.: [1] ENSURE 1-RM-90-1 12 Upper Containment Rad Monitor in SAT service per the following:
UNSAT
[a] Valve checklist 1-90-2.03 (Attachment 3) complete.
If asked Valve checklist is complete.
STANDARD: Candidate notes that valve checklist is signed-off COMMENT:
STEP 3.: [b] Pump running (Section 5.1). SAT NOTE: The rad monitor flow alarms will not reset until the UNSAT operator manually resets the alarms as indicated in the cues.
STANDARD: Operator determines that pump is NOT running and goes to Section 5.1.
COMMENT:
Evaluator Note: The following steps are from 1-SO-90-2, Section 5.1 STEP 4.: [1] INDICATE below which rad monitor will be placed in SAT service:
UNSAT STANDARD: Operator checks 1 -RM-90-1 12.
Comment:
JPM INPLANT K Page 6 of 6 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 5.: [21 ENSURE the following valve checklist has been SAT completed for rad monitors to be placed in service.
UNSAT STANDARD: Operator indicates that 1-RM-90-1 12 valve checklist 1 2.03 Attachment 3 is complete.
Comment:
STEP 6.: [3] IF placing 1-RM-90-106 in service THEN SAT STANDARD: Operator N/As this step UNSAT COMMENT:
Note 1: Heat trace handswitches 1 -HS-90-1 06 and 1 12 are located at the Heat Trace Control Panel
[1-JBOX-90-3918], east wall adjacent to 1-RM-90-106.
Note 2: Amber lights may or may not be illuminated. With the handswitch in the ON position the amber indicating lights will be ON if the thermostat senses temperature less than 110°F.
STEP 7.: [4] ENSURE radiation monitor heat trace is in service for SAT monitor being placed in service (N/A monitor not required)
UNSAT STANDARD: Operator N/As 1-RM-90-106 portion of step. Operator places 1-HS-90-1 12 to the ON position.
COMMENT:
STEP 8.: [5] IF testing heat trace circuit, THEN PERFORM Section 8.4 SAT AND RETURN TO step [6]
UNSAT Cue: Testing heat tracing IS complete.
STANDARD: Operator acknowledges that heat trace circuit testing is complete and continues with next step.
COMMENT:
JPM INPLANT K Page 7 of 7 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 9.: [6] COORDINATE with MIG to place 1 -RM-90-1 06 or 112 SAT sample pumps In Service.
UNSAT Cue: Unit I CR0 will coordinate with MIG.
STANDARD: Coordination set up with MIG.
COMMENT:
STEP 10 [7] S1ABL1H fldi tt3rogh rdaattor? nntot byjE!foErii SAT hefoilowng UNSAT ta], IF starting 1-RM-90-1 12 sample pump, THEN
- pLojowLrg catçj Critical Step CUE: MIG has aligned the #1 sample pump for service.
STANDARD: Operator locates and indicates that HS-90-1 1 2A has been depressed.
This step is critical because it is required to start sample pump.
COMMENT:
STEP 11.: [b] IF starting 1-RM-90-106 sample pump, THEN.. SAT STANDARD: Operator N/As this step UNSAT COMMENT:
STEP 12.: [c] NOTIFY I & C to adjust flow as required. SAT Cue: I & C has been contacted and will monitor flow. UNSAT STANDARD: Operator contacts I & C for support.
COMMENT:
JPM INPLANT K Page 8 of 8 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 13.: [d] IF flow cannot be established through the Rad Monitor SAT THEN UNSAT Flow has been established through 1-RM-90-112.
STANDARD: Operator N/As this step COMMENT:
STEP 14.: [e] IF placing [1-RM-90-112] in service, THEN RESET SAT
[1-HS-90-1 12F] local low flow seal-in.
UNSAT STANDARD: Operator resets local low flow seal-in by turning [1-HS-90-1 12F]
to the left to reset.
COMMENT:
STEP 15.: [f] ENSURE MCR malfunction alarms are RESET: SAT Role play as Unit I CR0 and state that alarms I-RA-90-112B UNSAT and 112C are RESET STANDARD: Operator contacts MCR to ensure alarms 1-RA-90-112B, Window A-2 and 1-RA-90-1 12C, Window A-3 on MI2A are DARK. Operator N/As alarms associated with 1-RM-90-106.
COMMENT:
STEP 16.: [g] IF placing 1-RM-90-106 in service THEN SAT STANDARD: Operator N/As step. UNSAT COMMENT:
STEP 17.: [8] IF performing source check of rad monitor, THEN SAT Cue: Source check will not be performed at this time. UNSAT STANDARD: Operator returns to Section 8.3, Step [1] [c]
COMMENT:
JPM INPLANT K Page 9 of 9 Rev. 0 Job Performance Checklist:
STEP ISTANDARD SAT IUNSAT Evaluator Note: The following steps are from 1-SO-90-2, Section 8.3:
STEP 18.: [C] 1-HS-90-112 Heat trace is in the ON position. SAT Cue: HS is in the ON position, based on performance of UNSAT Section 5.1 STANDARD: Operator determines 1-HS-90-112 heat trace is on based on prior performance of Section 5.1 steps.
COMMENT:
STEP 19.: [2] If testing the heat trace circuit, THEN SAT STANDARD: Operator N/As step, since heat trace was tested previously. UNSAT COMMENT:
STEP 20.: [3] If 1-RE-90-1 12 background count rate is less than SAT 9000 cpm THEN UNSAT
ç: Source check is not required.
STANDARD: Operator N/As step.
COMMENT:
STEP 21 f4JOPEt4 1-1Sl923 CFsstiVa1 tveen bpp SAT anLowerCQ!pPritR?d Monitors:
UNSAT Cue: Valve turns CCW several turns then stops.
STANDARD: Valve 1-ISIV-90-283G located & opened, handwheel Critical Step turned as far left (counter-clockwise) as possible.
This is a critical task to place the rad monitor in service COMMENT:
READ TO OPERATOR DIRECTIONS TO TRAINEE:
I will explain the initial conditions, and state the task to be performed. All steps shall be simulated for this JPM. WHEN ENTERING A UNIT TRIP HAZARD ZONE ENSURE YOU DO NOT TOUCH ANY SWITCHES WITHIN THAT ZONE. I 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 I provided you.
INITIAL CONDITIONS:
- 1. 1 -RM-90-1 12 had been isolated and tagged electrically for maintenance. The Hold Order has been picked up from the breaker, the valve checklist (Attachment 3) is complete, but the pumps are off.
- 2. 1 -RM-90-1 06 has just tripped and neither of its associated pumps can be started.
- 3. Precautions, Limitation and 1-SO-90-2 Section 4, Prerequisite Actions, are current, complete and signed off.
INITIATING CUES:
- 1. The Unit I CR0 has directed you, the Unit 1 Aux. Bldg AUO, to align rad. monitor 1-RM-90-1 12 to sample lower containment per 1-SO-90-2, Section 8.3 steps I through 4 (along with any other applicable sections).
READ TO OPERATOR DIRECTIONS TO TRAINEE:
I will explain the initial conditions, and state the task to be performed. All steps shall be simulated for this JPM. WHEN ENTERING A UNIT TRIP HAZARD ZONE ENSURE YOU DO NOT TOUCH ANY SWITCHES WITHIN THAT ZONE. I 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 I provided you.
INITIAL CONDITIONS:
- 1. 1 -RM-90-1 12 had been isolated and tagged electrically for maintenance. The Hold Order has been picked up from the breaker, the valve checklist (Attachment 3) is complete, but the pumps are off.
- 2. 1 -RM-90-1 06 has just tripped and neither of its associated pumps can be started.
- 3. Precautions, Limitation and 1-SO-90-2 Section 4, Prerequisite Actions, are current, complete and signed off.
INITIATING CUES:
- 1. The Unit I CR0 has directed you, the Unit I Aux. Bldg AUO, to align rad. monitor 1-RM-90-1 12 to sample lower containment per 1-SO-90-2, Section 8.3 steps 1 through 4 (along with any other applicable sections).
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT SYSTEM OPERATING INSTRUCTION I -SO-90-2 GASEOUS PROCESS RADIATION MONITORING SYSTEM Revision 38 QUALITY RELATED PREPARED/PROOFREAD BY: CWMATHES RESPONSIBLE ORGANIZATION: OPERATIONS APPROVED BY: W. T. LEARY EFFECTIVE DATE: 12/03/09 LEVEL OF USE: CONTINUOUS USE REVISION DESCRIPTION: Revised to add RM-90-400 disconnect switch to the Power Checklist (PCR 08000521). Added reference to 0-PI-OPS-301-001.0 in section 5 and 7 (PCR 07000297). Added section 8.11 and revised 5.3 for the primary sampling pumps alignments ( PCR 09000155, 09000613 &
09001214). Added step in section 8.9 to return sampling to automatic mode. Added LCO reference to section 8.7 (07000470). Replaced MIG with I & C throughout procedure to reflect organization name change. Deleted IV column in power checklist.
SQN 1-SO-90-2 GASEOUS PROCESS RADIATION Rev: 38 I MONITORING SYSTEM Page 2 of 78 TABLE OF CONTENTS Page 1 of 3 Section Title Page
1.0 INTRODUCTION
5 1.1 Purpose 5 1.2 Scope 5
2.0 REFERENCES
6 2.1 Performance References 6 2.2 Developmental References 6 3.0 PRECAUTIONS AND LIMITATIONS 8 4.0 PREREQUISITE ACTIONS 9 5.0 STARTUP/STANDBY READINESS 10 5.1 Placing Containment Upper and Lower Compartment Air Monitors in Service 10 5.2 Placing Containment Purge Monitors in Service 15 5.3 Placing Shield Building Vent Monitors in Service and Primary Sampling Pumps in Service 21 5.4 Placing Condenser Vacuum Pump Air Exhaust Monitor in Service 25 6.0 NORMAL OPERATION 29 7.0 SHUTDOWN 30 7.1 Shutting Down Lower Containment Rad Monitor 1-RE-90-106 30 7.2 Shutting Down Upper Containment Rad Monitor 1-RE-90-112 32 7.3 Shutting Down Containment Purge Rad Monitor 1-RE-90-130 34 7.4 Shutting Down Containment Purge Rad Monitor 1-RE-90-131 37 7.5 Shutting Down Shield Building Exhaust Rad Monitor 1-RE-90-400 40 7.6 Shutting Down Condenser Vacuum Exhaust Rad Monitor 1-RE-90-99 42 7.7 Shutting Down Condenser Vacuum Exhaust Rad Monitor 1-RE-90-119 44
SQN 1-SO-90-2 GASEOUS PROCESS RADIATION Rev: 38 I MONITORING SYSTEM Page 3 of 78 TABLE OF CONTENTS Page 2 of 3 Section Title Page 8.0 INFREQUENT OPERATION 46 8.1 Performing Source Check of Rad Monitors with Source Check Capability on 0-M-12 or Locally 46 8.2 Performing Source Check of Shield Building Vent Monitor 50 8.3 Alignment of Containment Upper Compartment Monitor to the Lower Compartment 51 8.4 Testing Heat trace circuit for 1-RM-90-106 and 112 58 8.5 Swapping Containment Purge Monitors from A to B Train Containment Purge Fans 61 8.6 Swapping Containment Purge Monitors from B to A Train Containment Purge Fans 64 8.7 Blocking Rad Monitor Automatic Functions 67 8.8 Restoring Rad Monitor Automatic Functions 69 8.9 Placing Shield Bldg 1-RM-90-400 in Manual Sample Flow Control 71 8.10 Alignment of Inoperable Shield Building Stack Primary Sample Pumps 72 8.11 Swapping Shield Building Stack Primary Sample Pumps 73 9.0 RECORDS 75 APPENDIX A: VALVE DIAGRAM FOR ALIGNMENT OF 1-RE-90-130 AND 1-RE-90-131 76 APPENDIX B: RAD MON/RE-90-400 ODCM RELATIONSHIP 77 SOURCE NOTES 78
SQN 1-SO-90-2 GASEOUS PROCESS RADIATION Rev: 38 I MONITORING SYSTEM Page 4 of 78 TABLE OF CONTENTS PAGE 3 OF 3 ATTACH M ENT ATTACHMENT 1: POWER CHECKLIST 1-90-2.01 ATTACHMENT 2: VALVE CHECKLIST 1-90-2.02 ATTACHMENT 3: VALVE CHECKLIST 1-90-2.03 ATTACHMENT 4: VALVE CHECKLIST 1-90-2.04 ATTACHMENT 5: VALVE CHECKLIST 1-90-2.05 ATTACHMENT 6: VALVE CHECKLIST 1-90-2.06-CANCELLED ATTACHMENT 7: VALVE CHECKLIST 1-90-2.07 ATTACHMENT 8: VALVE CHECKLIST 1-90-2.08-CANCELLED ATTACHMENT 9: VALVE CHECKLIST 1-90-2.09 ATTACHMENT 10: VALVE CHECKLIST 1-90-2.10 ATTACHMENT 11: VALVE CHECKLIST 1-90-2.11 ATTACHMENT 12: VALVE CHECKLIST 1-90-2.12
SQN 1-SO-90-2 GASEOUS PROCESS RADIATION Rev: 38 1 MONITORING SYSTEM Page 5 of 78
1.0 INTRODUCTION
1.1 Purpose This Instruction provides the detailed steps necessary for operation of the Gaseous Process Radiation Monitoring System.
1.2 Scope This Instruction provides the steps required for the operation of the following Gaseous Rad Monitors:
A. Containment Bldg Lower Compartment Air Monitor 1-RE-90-106.
B. Containment Bldg Upper Compartment Air Monitor 1-RE-90-112.
C. Shield Bldg Vent Monitor 1-RE-90-400.
D. Condenser Vacuum Pump Air Exhaust Low Range Monitor 1-RE-90-1 19.
E. Condenser Vacuum Pump Air Exhaust Low Range Monitor 1-RE-90-99.
F. Alignment of Containment Purge Air Exhaust Monitors 1-RE-90-1 30 and 1-RE-90-131 for operation with A Purge Fans.
G. Alignment of Containment Purge Air Exhaust Monitors 1-RE-90-130 and 1-RE-90-131 for operation with B Purge Fans.
H. Alignment of Containment Purge Air Exhaust Monitors 1-RE-90-130 and 1-RE-90-131 for operation with A and B Purge Fans.
SQN 1-SO-90-2 GASEOUS PROCESS RADIATION Rev: 38
- I MONITORING SYSTEM Page 6 of 78
2.0 REFERENCES
2.1 Performance References None.
2.2 Developmental References A. SOl-90.1 B, Gaseous Process Rad Monitors B. S 1-2, Shift Log C. NUREG-0737 D. SQN-DC-V-9.0, R3 E. FSAR
- 1. 9.5.10, Postaccident Sampling Facility
- 2. 1t3, Gaseous Waste Systems
- 3. 11.4, Process and Effluent Radiological Monitoring System
- 4. 15.5, Environmental Consequences of Accidents F. Technical Specifications
- 1. 3.3.2.1, Engineered Safety Feature Actuation System Instrumentation
- 2. 3.4.6.1, Leakage Detection System
- 3. 3.3.3.1, Rad Monitoring Instrumentation G. Offsite Dose Calculation Manual
SQN 1-SO-90-2 GASEOUS PROCESS RADIATION Rev: 38 I MONITORING SYSTEM Page 7 of 78 2.2 Developmental References (Continued)
H. TVA Drawings
- 1. 47W610-90-1
- 2. 47W610-90-.2
- 3. 47W61 0-90-3
- 4. 47W610-90-5
- 5. 47W600-1 06
- 6. 47W600-464
- 7. 47W600-465
- 8. 47W600-1 04
- 9. 47W600-494
- 10. 45N690-1
- 11. 45N703-1
- 12. 45N703-2
- 13. 45N703-5
- 14. 45N703-6
- 15. 45N706-1
- 16. 45N706-2
- 17. 45N708-4
- 18. 45N708-5
- 19. 45N756-1
- 20. 45N756-2
- 21. 45N756-6
- 22. 45N1416-1
- 23. 45N1620-15
- 24. 45N1620-18
- 25. 45N1759-3
- 26. 45N1620-3
- 27. 45N1620-4
- 28. 45N1620-17
- SQN 1-SO-90-2 GASEOUS PROCESS RADIATION Rev: 38 I MONITORING SYSTEM Page 8 of 78 PRECAUTIONS AND LIMITATIONS allure to observe all posted radiation control requirements may lead to unnecessary radiation absorbed doses.
damage may occur from excessive heat if pumps are isolated, either manually or automatically, with the pump running.
Monitors which can initiate an Engineered Safety Feature (ESF) 2- Actuation shall be blocked before any maintenance activity, functional test, or return to service is performed. [C.I]
not block any Rad Monitor that has a redundant monitor unless that 7 redundant monitor is operable.
prevent unmonitored releases, with one unit in Mode 1, 2, or 3 and the other unit in Mode 4, 5, or 6, Shield Building Vent Monitor for shutdown unit is required to be operable to satisfy NUREG-0737 and FSAR Post Accident Sampling requirements for the operating unit. [C.4]
.ction 19 of LCO 3.3.2, Table 3.3-3 must be complied with before blocking 1-RE-90-130 and 1-RE-90-131 simultaneously during Modes 1,2,3,4, or6.
,1isture accumulation in the 1-90-1 06 and 112 rad monitors pump supply
,V lines will occur if the heat trace circuit is turned OFF or has a break in the wiring circuit. The heat trace thermostat will maintain approximately 110°F on the monitors pump supply lines. This temperature will keep the warm, sometimes humid, containment sample air which passes through the cool Aux. Bldg to the rad monitors above its dew point.
4ther 1-RM-90-99 or 1-RM-90-119 must be in service to monitor the low range of the Condenser Vacuum Exhaust. Both monitors should not be in service at the same time for extended periods, due to flow limitations.
,. -RE-90-106/1-RE-90-400 local sample pump handswitches have AUTO-OFF HAND positions. Normally the AUTO position is used if starting/stopping the pump from the MCR (1-RI-90-106A/1-RI-90-400A). Using HAND position bypasses MCR start/stop capability.
SQN 1-SO-90-2 GASEOUS PROCESS RADIATION Rev: 38 I MONITORING SYSTEM Page 9 of 78 Date________
4.0 PREREQUISITE ACTIONS Throughout this Instruction, where an IF/THEN statement exists, the step should be NIA if the condition does not exist.
V
[I ENSURE the Instruction to be used is a copy of the version ENSURE Precautions and Limitations, Section 3.0, has been reviewed.
ISURE Power Checklist 1-90-2.01 complete imenti).
ENSURE each performer documents their name and initials:
Print Name Initials
[5] INDICATE below which performance section of this Instruction will be used and the reason for this performance:
Li 5.0 STARTUP/STANDBY READINESS Li 7.0 SHUTDOWN 8.0 INFREQUENT OPERATION REASON: Ir j-1-// LL(
s 3
SQN 1-SO-90-2 GASEOUS PROCESS RADIATION Rev: 38 I MONITORING SYSTEM Page 51 of 78 Date 8.3 Alignment of Containment Upper Compartment Monitor to the Lower Compartment NOTE I Containment Building Lower and Upper Compartment Air Monitors 1-RE-90-106 and l-RE-90-112 do not initiate CVI.
NOTE 2 Heat Trace handswitches I -HS-90-1 06 and 112 are located at the Heat Trace Control Panel [1-JBOX-90-3918], east wall adjacent to 1-RM-90-106.
[I] ENSURE 1-RE-90-1 12 Upper Compartment Rad Monitor in service per the following:
A. Valve Checklist 1-90-2.03 (Attachment 3) complete.
B. Pump Running (Section 5.1).
C. [1-HS-90-1121, heat trace is in the ON position.
[2] IF testing the heat trace circuit, THEN PERFORM Section 8.4 AND RETURN TO step [3].
NOTE High background activity may mask the source and prevent an upward deflection when source check is performed.
Source check of RE-90-112 is not required for T.S operability.
[3] IF 1-RE-90-1 12 background count rate is less than 9,000 cpm, THEN PERFORM Section 8.1 of this Instruction to source check 1-RE-90-112.
SQN 1-SO-90-2 GASEOUS PROCESS RADIATION Rev: 38 I MONITORING SYSTEM Page 52 of 78 Date___________
8.3 Alignment of Containment Upper Compartment Monitor to the Lower Compartment (Continued)
[4] OPEN [I-ISIV-90-283G] Crosstie Valve Between Upper and Lower Compartment Rad Monitors.
1st IV
[5] ENSURE the following FCVs are OPEN:
VALVE INITIALS 1-FCV-90-108 1st IV 1-FCV-90-109 1st IV 1-FCV-90-107 1st iv 1-FCV-90-117 1st IV 1-FCV-90-116 1st IV
[6] ENSURE [I-RE-90-112] is operable by verifying the following:
- PowerON
- Instrument malfunction alarms clear.
- CPM reading of at least background level.
SQN 1-SO-90-2 GASEOUS PROCESS RADIATION Rev: 38 I MONITORING SYSTEM Page 10 of 78 Date 5.0 STARTUP/STANDBY READINESS 5.1 Placing Containment Building Upper and Lower Compartment Air Monitors in Service NOTE Containment Building Lower and Upper Compartment Air Monitors 1-RE-90-106 and 1-RE-90-112 do not initiate CVI.
[1] INDICATE below which Rad Monitor will be placed in service:
RAD MONITOR FUNCTION Containment Bldg Lower 1 -RE-90-1 06 Compartment Air Monitor Containment Bldg Upper 1-RE-90-1 12 Compartment Air Monitor
[2] ENSURE the following valve checklist(s) completed for Rad Monitor(s) to be placed in service (NIA the other):
VALVE ATTACH RAD MONITOR FUNCTION INITIALS CHECKLIST NUMBER Containment Bldg Lower 1-RE-90-106 1-90-2.02 2 Compartment Air Monitor Containment Bldg Upper 1-RE-90-1 12 1-90-2.03 3 Compartment Air Monitor
SQN 1-SO-90-2 GASEOUS PROCESS RADIATION Rev: 38 I MONITORING SYSTEM Page 11 of 78 Date 5.1 Placing Containment Building Upper and Lower Compartment Air Monitors in Service (Continued)
[3] IF placing 1-RE-90-106 in service, THEN ENSURE 1-ISIV-90-283G Crosstie Valve Between Upper and Lower Compartment Rad Monitors is CLOSED (Valve Checklist 1-90-2.03).
NOTE I Heat Trace handswitches I -HS-90-1 06 and 112 are located at the Heat Trace Control Panel [I -JBOX-90-391 8], east wall adjacent to I -RM-90-1 06.
NOTE 2 Amber lights may or may not be illuminated. With the handswitch in the ON position the amber indicating lights will be ON if the thermostat senses temperature less than 110°F.
[4] ENSURE radiation monitor heat trace is in service for the monitor being placed in service (NA monitor not required):
HANDSWITCH DESCRIPTION POSITION INITIALS Heat Trace for 1-RE-90-106 1-HS-90-106 ON activated Heat Trace for 1-RE-90-1 12 1-HS-90-112 ON activated
[5] IF testing the heat trace circuit, THEN PERFORM Section 8.4 AND RETURN TO step [6]. E
SQN 1-SO-90-2 GASEOUS PROCESS RADIATION Rev: 38 I MONITORING SYSTEM Page 12 of 78 Date___________
5.1 Placing Containment Building Upper and Lower Compartment Air Monitors in Service (Continued)
NOTE I I & C support is required when placing RM-90-106 sample pumps in service, shutting them down or when swapping pumps.
Configuration control for sample pump suction and discharge valves and flow adjustments through RM is performed by I & C.
NOTE 2 I & C support is required to adjust flow for 1-RM-90-112 sample pumps when placing in service or swapping pumps due to vacuum switches.
[6] COORDINATE with I & C to place I -RM-90-1 06 or 112 sample pumps In Service.
[7] ESTABLISH flow through radiation monitor by performing the following steps:
[a] IF starting [1-RM-90-112] sample pump, THEN DEPRESS one of the following local START buttons:
HS-90-112A Pump I START HS-90-112B Pump2 START
[b] IF STARTING [1 -RM-90-1 06] sample pump, THEN
- 1. ENSURE [HS-90-106B] local (AUTO-OFF HAND) handswitch in AUTO position for sample pumps.
- 2. ENSURE I & C has completed valve alignments for pump to be placed In Service per 1-PI-IPM-90-106.0.
- SQN 1-SO-90-2 GASEOUS PROCESS RADIATION Rev: 38 I MONITORING SYSTEM Page 13 of 78 Date___________
5.1 Placing Containment Building Upper and Lower Compartment Air Monitors in Service (Continued)
- 3. DEPRESS one of the following pushbuttons, AND CHECK PB illuminated: (N/A other)
LOCATION UNID PUSHBUTTON PB ILLUMINATED q INITIALS Local 1-Rl-90-106B FLOW E MCR 1-RI-90-106A FLOW Li
[c] NOTIFY I & C to adjust flow in accordance with 1-SI-IFT-090-1 12.0, Functional Test of Containment Building Upper Compartment Air Monitor 1-R-90-1 12. Li
[d] IF flow cannot be established through the Rad Monitor, THEN NOTIFY Unit Operator.
[e] IF placing [I-RM-90-1121 in service, THEN RESET [I -HS-90-I I 2F] local low flow seal-in.
[f] ENSURE MCR malfunction alarms are RESET (N/A any monitor not being placed in service):
MONITOR ALARM PANEL WINDOW 1 -RA-90-1 06B 0-XA-55-1 2A A-5 1 -RA-90-1 06C 0-XA-55-1 2A A-6 1-RA-90-1 12B 0-XA-55-12A A-2 1-RA-90-1 12C 0-XA-55-12A A-3
[g] IF placing [1 -RM-90-1 06] in service, THEN VERIFY acceptable flow by verifying green OPER LED indicators ILLUMINATED either 1-RI-90-106B (local) or 1-Rl-90-106A (MCR).
SQN 1-50-90-2 GASEOUS PROCESS RADIATION Rev: 38
- I MONITORING SYSTEM Page 14 of 78 Date________
5.1 Placing Containment Building Upper and Lower Compartment Air Monitors in Service (Continued)
NOTE If placing 1-RM-90-106 OR 112 in service and background activity
- is greater than 9,000 cpm then step [8] source check performance may be NAd.
[8] IF performing source check of rad monitor, THEN GO TO Section 8.1.
END OF SECTION