ML110390369
| ML110390369 | |
| 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: ML110390369 (414) | |
Text
FINAL Sequoyah Nuclear Plant SEPT 2010 NRC INITIAL LICENSE ROISRO Simulatorllnplant JPM ExAM Simulator JPMs (A- H)
Inplant JPMs (I-K)
FINAL
JPM Sm A-i Page 1 of 10 Rev. 0 SEQUOYAH NUCLEAR PLANT September 2010 NRC Exam Simulator A-I Withdraw Shutdown Banks Alternate Path
JPM Sim A-i Page 2 of 10 Rev. 0 ROISRO 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MEASURE Task: Withdraw Shutdown Banks Task#: RO 0010180101 Task Standard: Withdraw Shutdown Control Rods to the fully withdrawn position. Stop Rod Withdrawal when SD A Group I control rods drop into core from a partially withdrawn position and place the reactor in a tripped, shutdown condition.
Time Critical Task: YES: NO: X KIA ReferencelRatings: 001 A2. 11(4.4/4.7) 001A2.17 (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 I 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 10 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:
E-5 RDO7E5 E-11RDO7E11 L-5 RDO7L5 L-1 1 RDO7L1 1 Monitor Rod Withdrawal; © 100 steps on SD A, initiate Key 1
- 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-SO-85-1, section 6.3 Tl-28 Attachment 6
References:
I Reference Title Rev No.
I 1. 0-SO-85-1 Control Rod Drive System 34
- 2. Tl-28 Curve Book 243
- 3. TRM Technical Requirements Manual 45 DIRECTIONS TO TRAINEE on next page
JPM Sim A-I Page 4 of 10 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 1 is in MODE 3 with Tavg at 547°F and RCS pressure at 2235 psig.
- 4. 0-SI-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-S0-85-1 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 11.
- 2. Inform the US when the all shutdown banks are at the fully withdrawn position.
JPM Sim A-i Page 5 of 10 Rev. 0 Job Performance Checklist:
STEP/STANDARD SATIUNSAT EVALUATOR NOTE: 0-S0-85-1, 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 1-S0-63-1 section 8.1 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 cursor on the specified action field and click the left mouse button.
COMMENTS:
JPM Sim A-i Page 6 of i 0 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
[ci CONTACT MIG AND INITIATE troubleshooting Ed] 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 UNSAT AOP-C.O1 section 2.5 Rod Position Indicator (RPI) Malfunction -
Modes 1 cr2.
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 lOOv DC power supplies (PS3 and PS6)
JPM Sim A-i Page 7 of 10 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 5.: [i4 PLACE [HS-85-5110], Rod Control Mode Selectórto fj 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 (shaded portion) for withdrawal is assured.
COMMENTS:
STEP 6.: [15] VERIFY Rod Speed Indicator [SI-412], indicates 64 SAT Steps/minute. UNSAT STANDARD: Applicant locates Rod Speed Indicator SI-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 10 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.21 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-85-51 11] 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 N/As this step.
COMMENTS:
JPM Sim A-i Page 9 of 10 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT NOTE:
The fully withdrawn position for shutdown and control rods is defined by TI-28, Aff. 6.
Simulator Operator: As directed by the Examiner, or at 100 steps, insert SD Group I dropped rod malfunctions when SD Bank A reaches 100 steps.
ALTERNATE Path:
STEP 9.: [17] WITHDRAW Shutdown Bank A to the FULLY UNSAT WITHDRAWN position using [HS-85-51 11].
STANDARD: Operator continues withdrawing SB A control rods using handswitch I -HS-85-51 11 At 100 steps, the Applicant identifies SB A Group 1 Critical Step 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-1 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.01, 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-SI-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:
- 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 11.
- 2. Inform the US when the all shutdown banks are at the fully withdrawn position.
SQN EOI EPM-4 PROGRAM USERS GUIDE Rev. 20
- MANUAL Page 18 of 97 3.5 Prudent Operator Actions A. The following should be considered when deciding if a prudent action is appropriate:
- 1. Plant safety status should be maintained or enhanced. Prudent actions should not degrade plant status or challenge the plant more than the initiating event.
It should not cause a RED or ORANGE path condition. For example, closing MSIVs to isolate the steam dumps at 100% power would challenge the plant more than the original problem by causing a load rejection event and lifting pzr and SIG safeties. However, in Mode 3, closing MSIVs to stop an uncontrolled cooldown would have minimal impact on plant status, while enhancing reactor safety. Nuclear safety and personnel safety must be the first priorities.
Prudent actions for economic reasons (for example, shutting down secondary equipment) cannot be allowed to interfere with mitigating actions.
- 2. Prudent operator actions should be consistent with procedural guidance for similar situations. For example, if a steamline break occurs in Mode 3 and SIG pressure is approaching 600 psig, a manual MSIV Isolation would anticipate the designed automatic response and is consistent with procedural guidance.
- 3. In the EOP network, prudent operator actions shall NOT be performed prior to completing the immediate actions for E-0, FR-S.1, or ECA-0.0.
- 4. The basis for the prudent action (i.e. why it is necessary and appropriate) should be clearly understood prior to taking the action.
- 5. Prudent operator actions should normally be performed with the concurrence of an active licensed SRO. The following items are exceptions in which a Unit Operator may take prudent action without waiting for SRO concurrence:
- When prompt action is needed to manually trip the reactor OR
- When prompt action is needed to manually control components to prevent an avoidable automatic trip or transient.
- When prompt action is needed to actuate ESF equipment which failed to operate.
When a Unit Operator takes prudent action without prior SRO concurrence, it is the responsibility of that Unit Operator to ensure the action is appropriate and that the action is promptly reported to the Shift Manager or Unit Supervisor.
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 s3 DESCRIPTION:
into Section 5.1 for MG set A and 5.2 for MG Split Section 5.1 standby readiness for both MG sets
)
set B this will remove error traps. (FOR 09000712 le and changed step from 113 to 110 Section 6.3 Step 38 deleted note referencing LEFM availab 0168) steps for rod control banks limit ow-low. (FOR 0900 g LEFM available and change step from 123 to 120 Section 6.3 Step 39 deleted note referencin 0168) steps for rod control banks limit low. (FOR 0900 1 for TRM 3.1.3.3 requirements and referenced AOF-O.01 Section 6.3 added Oaution prior to step as required. (FOR 08001279) ement without the CRDM fans aligned to the Added precaution and limitation M that rod mov ROS temperatures are less than reactor vessel shroud is allowed, provided that the and precaution and limitation M added when 350 degrees F. Section 6.3 Note prior to step [1) ees F, continuous rod motion shall comply with the ROS temperatures are greater than 350 degr ORDM fans in service in accordance with restrictions. Section 6.3 Step 3 added to ensure degrees F.(PCR 07001668, PER 172096 &
0-SO-30-6, if RCS temperature is greater than 350 EWR 09-BOP-30-018)
IMPACT REACTIVITY PERFORMANCE OF THIS PROCEDURE COULD
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 34 Page 6of80 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 I ,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 0-SO-85-1 1,2 Rev 34 Page7of8o 3.0 PRECAUTIONS AND LIMITATIONS (Continued)
J. Deleted K. RPIs and step counters shall be maintained within limits perTS 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 / 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 Tavg/Delta 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 Rev 34 Page 8of80 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. Verify 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-verify 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 9 of 80 Unit_________________ Date__________
PREREQUISITE ACTIONS Throughout this instruction where an IFITHEN statement occurs, the step may be NIA if the condition does NOT exist.
ENSURE the instruction to be used is a copy of the effective version.
.jTENSURE Precautions and Limitations, Section 3.0 has been reviewed.
TNSURE 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 6.0 NORMAL OPERATION El 7.0 SHUTDOWN El 8.0 INFREQUENT OPERATION Reason: -\ ra
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 Rev 34 1,2 Page 41 of 80 Date_________
Un it 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.
CA,J 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 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 j(ENSURE Section 5.5, ResetlClose 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 tJL 4 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_________
Unit_______________
Percent Power 6.3 Manual Operation of Rod Control System Below 15 CA( ROD CONTROL STARTUP STEP COUNTER RESET P position for any (SUS on M-4) should never be held in STARTU extended period of time. Holding this switch in STARTUP position may cause damage to the counters.
F9-T) 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 [SUSI, 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.
to zero.
SURE all Full Length Rod step counters reset
CONTROL ROD DRIVE SYSTEM 0-SO-85-1 SQN Rev34 1,2 Page 43 of 80 Date lccL, Unit_____
Percent Power (Continued 6.3 Manual Operation of Rod Control System Below 15 rod control IN-OUT direction lights are NOT LIT.
Reset.
_JYDEPRESS [RCAS}, Rod Urgent Failure Alarm dow 6 (A-6), ROD CONTROL SYSTEM
!SET Win URGENT FAILURE alarm on panel [XA-55-4B1 using ch.
IXS-55-4A1, Annunciator RESET/ACK/TEST Swit panel JERIFY the following rod control system alarms on
- [XA-55-4B] are NOT LIT:
WINDOW NOT LIT NUMBER (-J) 5(A5) EY 6(A6) 11(B4) EV 12(B5) 13(B6) LV 18(04) EV 19(C5) 27(D6) LV 34(E6) lj/
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev 34 Page 44 of 80 Unit________ Date_________
6.3 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 Control A RZ U0049 U0050 Control B U0051 Control C U0052 Control D lY U0053 Shutdown A U0054 Shutdown B EY U0055 Shutdown C U0056 Shutdown D EY
[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. LI
[12] IF Individual Rod Position Indication does not indicate proper rod position during withdrawal of SD Banks, THEN
[a] STOP rod withdrawal.
[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 Rev 34 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 1 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 lOOv DC power supplies (PS3 and PS6)
[14] PLACE [HS-85-51101, Rod Control Mode Selector to the SBA position.
1st CV
[15] VERIFY Rod Speed Indicator [Sl-4121, indicates
/
64 Steps/minute. CV 1st
CONTROL ROD DRIVE SYSTEM 0-SO-85-1 SQN Rev34 1,2 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.2]
Bank A
[a] BUMP [HS-85-5111], Rod Control Switch to withdraw Shutdown one-half step at a time, for one full step.
1st CV
[b] CHECK group demand position counters advance properly.
[c] BUMP [HS-85-51 jj] 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.
ly,
[e] IF group demand position counters do NOT advance proper THEN 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.
NOTE The fully withdrawn position for shutdown and control rods is defined by Tl-28, Att. 6.
N
[17] WiTHDRAW Shutdown Bank A to the FULLY WITHDRAW
/
position using [HS-85-5111]. 1st CV
CONTROL ROD DRIVE SYSTEM 0-SO-85-1 SQN Rev34 1,2 Page 47 of 80 Date Unit______________
6.3 Manual Operation of Rod Control System Below 15 Percent Power (Continued)
[18] PLACE rHS-85-51101, Rod Control Mode Selector to the
/
SBB position.
1st CV
[19] VERIFY Rod Speed Indicator [Sl-412], indicates
/
64 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).
[20] ENSURE Shutdown Bank B demand position counters operational by performing the following: [C.2]
Bank B
[a] BUMP [HS-85-5111], Rod Control Switch to withdraw Shutdown one-half step at a time, for one full step.
1st CV
[b] CHECK group demand position counters advance properly.
[c] BUMP [HS-85-51 11] 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.
[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 Shutdown Bank B fully INSERTED and El
- 2. RETURN to beginning of this step. El N
[21] WITHDRAW Shutdown Bank B to the FULLY WITHDRAW
/
position using [HS-85-5111]. CV 1st
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-85-51101, Rod Control Mode Selector to the SBC position.
1st CV
[23] VERIFY Rod Speed Indicator [Sl-412], indicates 0 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).
[24] ENSURE Shutdown Bank C demand position counters operational by performing the following: [C.2j
[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. El
[C] BUMP [HS-85-51 111 to withdraw Shutdown Bank C
/
a second full step.
1st cv
[d] VERIFY group demand position counter advanced properly.
[ej 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. El N
[25] WITHDRAW Shutdown Bank C to the FULLY WITHDRAW
/
position using [HS-85-5111]. CV 1st
SQN CONTROL ROD DRIVE SYSTEM O-SO..85-1 1,2 Rev34 Page 49 of8O Unit________________ Date__________
6.3 Manual Operation of Rod Control System Below 15 Percent Power (Continued)
[26] PLACE [HS-85-5110], Rod Control Mode Selector to the SBD position. /
1st CV
[27] VERIFY Rod Speed Indicator [Sl-412], indicates
/
0 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).
[28] ENSURE Shutdown Bank D demand position counters operational by performing the following: [C.2J
[a] BUMP [HS-85-51111, 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-85-5111J to withdraw Shutdown Bank D
/
a second full step.
1st CV
[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 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 63 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. /
1st CV
[31] VERIFY Rod Speed Indicator rSI-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 I 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-85-51111, Rod Control Switch to withdraw Control Bank A 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 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. LI
SQN CONTROL ROD DRIVE SYSTEM O-SO-85-1 1,2 Rev34 Page 51 of80 Unit________________ Date__________
6.3 Manual Operation of Rod Control System Below 15 Percent Power (Continued)
[33] CONTINUE withdrawal of Control Bank A using [HS-85-5111],
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-55-4B1 CLEARS.
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev34 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-85-5111], 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
[dl VERIFY group demand position counters advance properly. LI
[e] IF group demand position counters do NOT advance properly, THEN A. STOP rod withdrawal. LI B. INITIATE WO to have counter repaired. El C. WHEN counter is repaired, THEN
- 1. ENSURE Control Bank B fully INSERTED and El
- 2. RETURN to beginning of this step. El
[36] CONTINUE withdrawal of Control Bank B using [HS-85-5111j 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.
[c] BUMP [HS-85-5111] 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. LI
[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 C fully INSERTED and LI
- 2. RETURN to beginning of this step. LI
[38] CONTINUE withdrawal of Control Bank C using [HS-85-51 111 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-55-4j CLEARS.
SQN CONTROL ROD DRIVE SYSTEM 0-SO-85-1 1,2 Rev34 Page 54 of 80 Date Unit_________________
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-55-4B] 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
[bJ CHECK group demand position counters advance properly. E
[c] BUMP [HS-85-51 11] to withdraw Control Bank D one-half step at a time, for the second full step.
1st CV
[dl 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. LI 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 TI-28 Att.6 Unit 0 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 225-23 1 steps in accordance with the COLR.
NOTE The ARC step withdrawn position is set before startup of each cycle and every 92 days thereafter in conjunction with the performance of 0-Sl-OPS-085-01 1 .0 Reactivity Control Systems Moveable Control Assemblies.
Unit I ARO Steps Withdrawn Cycle 17 Cycle 18 Cycle 19 Startup Date Spring 2009 Fall 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 Unit 2 ARO Steps Withdrawn Cycle 17 Cycle 18 Cycle 19 Startup Date Fall 2009 Spring 2011 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
SQN CONTROL ROD FULLY WITHDRAWN TI-28 Att.6 Unit 0 POSITIONS Effective Date: 11-20-2009 Page 2 of 2 NOTES
- 1) Switch setting changes must be made to the Solid State Rod Control System, Logic Cabinet, bank overlap switches.
- 2) Si through S6 must be changed when changing to a new full-out position.
FULL OUT POSITION SWITCH SETTING FOR 128 STEP TIP-TO-TIP Si S2 S3 S4 S5 S6 222 128 222 256 350 384 478 223 128 223 256 351 384 479 224 128 224 256 352 384 480 225 128 225 256 353 384 481 226 128 226 256 354 384 482 227 128 227 256 355 384 483 228 128 228 256 356 384 484 229 128 229 256 357 384 485 230 128 230 256 358 384 486 231 128 231 256 359 384 487 Si = Tip-to-Tip; S2 = desired full out position; S3 = (2 x Si)
S4 = (Si + S2); S5 = (3 x SI); S6 = (Si + S4)
The effect of the switch setting changes will be to maintain a 128 step Tip-to-Tip distance between control banks. For example, during withdrawal, the next bank will start moving in overlap when the bank being withdrawn reaches 128 steps. On control bank insertion, the reverse would be true with the next bank starting to move in overlap when the bank being moved is inserted 128 steps from the fully withdrawn position.
JPM Sim B-I Page 1 ofl5 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 15 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 KIA Reference/Ratings: 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: /
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 15 Rev. 0 SPECIAL INSTRUCTIONS TO EVALUATOR:
- 1. Critical steps are identified in step SAT/U NSAT 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 SIO4C @100% to drain level in the #3 CLA to until the low level alarm comes in; then DELETE the ME. [Will take 5-8 mm]
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!EquipmeritlProcedures Needed:
i-SO-63-1, section 8.1
References:
Reference Title Rev No.
- 1. 1-S0-63-1 Cold Leg Injection Accumulators 47
JPM Sim B-i Page 4 of 15 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 isatlOO%RTP.
- 2. #3 CLA sample valve did not properly close at the completion of sampling resulting in #3 CLA inventory draining to the current value.
- 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.
- 2. Inform the SM when #3 CLA has been restored.
JPM Sim B-i Page 5 of 15 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-SO-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 15 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 3.: [61 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 -P1 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 SAT 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 I and N/A this step.
COMMENTS:
JPM Sim B-i Page 7 of 15 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 6 [9] ENSURE the following valves are OPEN (located on I -M-6) SAT I -FcV-63-71, SIS Test Line to HUT UNSAT 1FG\:632:3CL Acóum Mae up.. Froni SlPump.s, 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 IA-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 <1 700 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 15 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 8.: [11] IF 1 B-B SI pump is to be used to add makeup water to SAT Accumulators, THEN PERFORM the following:
UNSAT
[a] IF Unit I 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 1 and N/A subsequent substeps through 11 .b.2; proceeds to step 11 .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 1-M-6 handswitches 1-HS-63-3, 175, 152, 153, and 48 indicated by RED light LIT.
COMMENTS:
STEP 10 EdI START lB-B SI purnp usiig f1-IS43-iA1 SAT UNSAT STANDARD: Operator starts the I B-B SI pump by placing I -HS-63-1 5A to the START and verifying RED light ON, amps indicated on 1-EI 16A, and pressure 1-Pl-63-19 stable Critical Step CRITICAL Step: this will provide the motive force for CLA fill.
COMMENTS:
JPM Sim B-I Page 9 of 15 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 I & 2 CLAs; SAT UNSAT STANDARD: Operator acknowledges and marks N/A; proceeds to 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:
I -FCV-63-1 15 No. I CL Accum Water Makeup 1-FCV-63-95 No. 2 CL Accum Water Makeup I -FCV-63-70 No. 4 CL Accum Water Makeup STANDARD: Operator verifies 1-M-6 handswitches 1-HS-63-1 15A,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 15 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 14 [14 b] OPEN [1-FCV-63-77] No 3 CL Accum Water Makeup to SAT begin filling No. 3 Accumulator.
UNSAT STANDARD: Operator positions 1-M-6 handswitch 1-HS-63-77A to OPEN position and verifies valve opens indicated by RED light LIT. Critical Step 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.
Evaluator Note: Applicant should monitor CLA gas pressure but should focus on restoring level; gas pressure adjustment is not expected.
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 ii ofi5 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 16.: [144] r SAT THEN ENSURE the following valves CLOSED UNSAT
[1] [1-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-63-87] 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 1 -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 Dl 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 15 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 psig but<668 psig),
1 LIS-63-89 1(i5áIbut<795S gal).
CRITICAL Step: verifies Tech Spec compliance COMMENTS:
STEP 19.: [g]VERIFY ACCUMULATOR 3 PRESSURE HI-LOW and SAT 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 15 Rev. 0 Job Performance Checklist:
STEP ISTANDARD SATIUNSAT 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 1 B-B has run 20 minutes prior to stopping pump. (to prevent premature bearing wear)
COMMENTS:
JPM Sim B-i Page 14 of 15 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 24.: [19] STOP lB-B SI pump with l-HS-63-15A. SAT UNSAT STANDARD: Operator places 1-HS-63-15A 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 ENSURE SI Pump in A-AUTO lB-B SI pump 1-HS-63-15A.
Critical Step STANDARD: Operator places l-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.
Cue: 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 completion of sampling resulting in #3 CLA inventory draining to the current value.
- 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.
- 2. Inform the US when #3 CLA has been restored.
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT SYSTEM OPERATING INSTRUCTION I -SO-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 REVISION DESCRIPTION:
Added step 5.l[l] 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 (PCRO800I 141).
Added P&L note M to require Voi.d 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 (PCRO800I 174). Added Caution Section 8.1 preceding steps [12][dJ[1}, [13][d][1J, [14][dJ[1J, and [15][d][1]
cautioning about CLA over-fill and over-pressurization (PCRO9000I 12).Corrected steps referenced in Section 8.1 Note I from 13-thru-16 to 12-thru-15 (PCRO90001I2).
SQN COLD LEG INJECTION 1-SO-63-1 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 CLA5 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 i ACCUMULATORS Rev: 47 Page 8 of 185 Date S. 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.
ENSURE each performer documents their name and initials:
Print Name Initials
- 3_y. -
INDICATE 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:
END OF SECTION 4.0
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. [C.1J 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 MIG to perform a purge of the level instrument upper leg due to borated water intrusion.
[1] 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 i 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 rl-FCV-63-841 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 INITIALS 1-FCV-63-69 Check valve test isolation I -FCV-63-79 Check valve test isolation 1-FCV-63-97 Check valve test isolation I -FCV-63-1 17 Check valve test isolation 1-FCV-63-163 Check valve test isolation 1-FCV-63-164 Check valve test isolation 1-FCV-63-165 Check valve test isolation 1-FCV-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-63-1 16 Check valve test isolation I -FCV-63-96 Check valve test isolation 1 -FCV-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 I -FCV-63-1 11 Check valve test isolation 1-FCV-63-1 12 Check valve test isolation 1-FCV-63-158 Check valve test isolation
SQN COLD LEG INJECTION 1-SO-63-1 ACCUMULATORS Rev: 47 Page 91 of 185 Date 8.1 Adding Makeup Water to the Cold Leg Accumulators (Continued)
[9] ENSURE the following valves are OPEN:
VALVE NO. FUNCTION INITIALS 1-FCV-63-71 SIS Test Line to HUT 1-FCV-63-23 CL Accum Makeup From SI Pumps CAUTION I 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.
[10] IF IA-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:
VALVE NO. FUNCTION INITIALS 1-FCV-63-156 SI Pump 1A HL Injection Isolation 1-FCV-63-152 SI Pump IA 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 INITIALS 1-FCV-63-22 SI Pumps CL Injection 1-FCV-63-156 SI Pump IA HL Injection Isolation 1-FCV-63-157 SI Pump IS HL Injection Isolation
- 2. ENSURE [1 -VLV-63-645] leakoff isolation LOCKED CLOSED and tagged.
SQN COLD LEG INJECTION 1-SO-63-1 i ACCUMULATORS Rev: 47 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 Recirc to RWST 1-FCV-63-4 SI Pump IA Recirc to RWST 1-FCV-63-47 SI Pump IA Suction Isolation
[d] START lA-A SI pump using [1-HS-63-IOA].
[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 1 B-B SI pump is to be used to add makeup water to Accumulators, THEN PERFORM the following:
[a] IF Unit I 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 LCD 3.4.12:
VALVE NO. FUNCTION INITIALS 1-FCV-63-22 SI Pumps CL Injection 1-FCV-63-156 SI Pump 1A HL Injection Isolation 1-FCV-63-157 SI Pump lB HL Injection Isolation
- 2. ENSURE [1-VLV-63-6451 leakoff 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)
[c] 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 IA CL Injection Isolation l-FCV-63-153 SI Pump lB CL Injection Isolation l-FCV-63-48 SI Pump lB Suction Isolation
[d] START lB-B SI pump using rl-HS-63-15A1.
[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 1-FCV-63-95 No. 2 CL Accum Water Makeup 1-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. I Accumulator.
SQN COLD LEG INJECTION 1-SO-63-l ACCUMULATORS Rev: 47 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.
[ci IF desired to vent accumulator to maintain pressure within limits, THEN
[1] THROTTLE [1-FCV-63-651 CL Accum N2 Header Vent Flow Control.
[2] OPEN f1-FCV-63-1271 to vent nitrogen from Accumulator 1.
[3] ADJUST [1-FCV-63-651 as needed to control CLA pressure between 630 and 662 psig.
CAUTION IF CLA Fill valve F1-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. I Accumulator increases to desired level, THEN ENSURE the following valves are CLOSED:
[1] [jfCV-63-1151.
[2] [1 -FCV-63-l 271
[3] [1 -FCV-63-65]
[4] INDEPENDENTLY VERIFY the following:
- 1. Fl -FCV-63-1 151 CLOSED
- 2. F1-FCV-63-l271 CLOSED
- 3. I1-FCV-63-651 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 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. I accumulator pressure and level are within the operability limits of 624-668 psig and 761 5-7955 gallons.
[f] VERIFY No. I accumulator pressure and level are within Tech Spec limits.
[g] VERIFY ACCUMULATOR I 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 INITIALS 1-FCV-63-115 No. I CL Accum Water Makeup 1-FCV-63-77 No. 3 CL Accum Water Makeup 1-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-63-951 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 rl-FCv-63-65] CL Accum N2 Header Vent Flow Control.
[2] OPEN [1 -FCV-63-1 071 to vent nitrogen from Accumulator 2.
[3] ADJUST rl-FCV-63-651 as needed to control CLA pressure between 630 and 662 psig.
CAUTION IF CLA Fill valve F1-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-63-951.
[2] [1 -FCV-63-1 07]
[3] [1 -FCV-63-65]
[4] INDEPENDENTLY VERIFY the following:
- 1. [1-FCV-63-951. CLOSED
- 2. [1-FCV-63-1071 CLOSED
- 3. [1 -FCV-63-651 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 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 DI 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.
[g] VERIFY ACCUMULATOR 2 PRESSURE HI-LOW and ACCUMULATOR 2 LEVEL HI-LOW alarms are CLEAR. (1-XA-55-6D windows B-I and B-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.
[14] IF adding makeup water to Accumulator 3, THEN PERFORM the following:
[a] ENSURE the following valves are CLOSED:
VALVE NO. FUNCTION INITIALS I -FCV-63-I 15 No. I 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 rl-FCV-63-771 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-63-651 CL Accum N2 Header Vent Flow Control.
[2] OPEN f1-FCV-63-87] to vent nitrogen from Accumulator 3.
[3] ADJUST [1-FCV-63-651 as needed to control CLA pressure between 630 and 662 psig.
CAUTION IF CLA Fill valve F1-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.
[d] WHEN No. 3 Accumulator increases to desired level, THEN ENSURE the following valves CLOSED
[1] II -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. F1-FCV-63-651 CLOSED
SQN COLD LEG INJECTION 1-SO-63-1 I ACCUMULATORS Rev: 47 L Page99of 185 Date 81 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 HI-LOW alarms are CLEAR. (1-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.
NOTE 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 INITIALS 1-FCV-63-1 15 No. I CL Accum Water Makeup 1-FCV-63-95 No. 2 CL Accum Water Makeup 1-FCV-63-77 No. 3 CL Accum Water Makeup
SQN COLD LEG INJECTION 1-SO-63-1 ACCUMULATORS Rev: 47 Page 100 of 185 Date 8.1 Adding Makeup Water to the Cold Leg Accumulators (Continued)
[b] OPEN F1-FCV-63-701 No. 4 CL Accum Water Makeup to begin filling 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.
[c] IF desired to vent accumulator to maintain pressure within limits, THEN
[I] THROTTLE [1-FCV-63-651 CL Accum N2 Header Vent Flow Control.
[2] OPEN Fl-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-63-70] 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. 4 Accumulator increases to desired level, THEN ENSURE the following valves CLOSED
[I] Fl -FCV-63-701.
[2] [1 -FCV-63-631
[3] [1 -FCV-63-651
[4] INDEPENDENTLY VERIFY the following:
- 1. Fl -FCV-63-701. CLOSED
- 2. [1-FCV-63-631 CLOSED
- 3. [l-FCV-63-651 CLOSED
SQN COLD LEG INJECTION 1-SO-63-1 ACCUMULATORS Rev: 47
. PagelOlofl85 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. 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-)(A-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 I 1st IV 1-FCV-63-23 CL Accum Makeup From SI Pumps I 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 i 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-IOA 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-IOA IA-A SI Pump 1st iv 1-HS-63-15A lB-B SI Pump 1st iv
[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-63-1OA IA-A SI Pump 1st iv l-HS-63-15A lB-B SI Pump 1st iv
[22] IF l-FCV-63-152 was CLOSED in step [10], THEN PERFORM the following:
[a] DEPRESSURIZE SI pump discharge piping using I -SO-63-5.
[b] OPEN [1 -FCV-63-1 521 SI Pump 1A CL Injection Isolation.
1st IV
SQN COLD LEG INJECTION I-SO-63-I ACCUMULATORS Rev: 47 Page 103 of 185 Date LI 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 I. ENSURE FI-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 81
JPM Sim C Page 1 of 13 Rev. 0 SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE MEASURE SIM C (ROISRO)
RETURN PRESSURIZER RELIEF TANK TO NORMAL
JPM Sim C Page 2 of 13 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: /
Name I Signature DATE Performance Rating: SAT: UNSAT:
Validation Time: 17 minutes Total Time:
Performance Time: Start Time: Finish Time:
COMMENTS
JPM Sim C Page 3 of 13 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.
- 4. Initialize in IC #115.
- 5. If #115 is not available, initialize in IC #16 and perform the following setup:
ACTIVATE MFRC05 at 5% to cause PCV-68-334 to leak through.
Allow PORV Tailpipe temperature to increase and bring in the alarm, then close FCV-68-333.
ACTIVATE the following REMOTE FUNCTIONS:
RF RCRO4 to remove power from valve
- RF WDRO2A Pump in PTL
- RF WDRO2B Pump in Run ACTIVATE the following OVERRIDES:
ZA0P168301 f:1O (PRT pressure at 10 psi)
ZA0T168309 f:130 (PRT pressure at lOpsi)
AN_OVRD[357] ON (1 -XX-55-5A D-1)
- ANOVRD[2109] ON (1-XX-55-5A C-i)
Ensure FCV-.81-12 is OPEN.
- 6. Due to time restraints, CUEs for PRT level and temperature will be given at appropriate times.
Tools/EquipmentlProcedures Needed:
0-SO-68-5, section 8.2 & 8.4
References:
Reference Title Rev No.
- 1. 0-SO-68-5 Reactor Coolant System 18 DIRECTIONS TO TRAINEE on next page
JPM Sim C Page 4 of 13 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:
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 5 of 13 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.
Sections may 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 [1-FCV-81-12] OPEN. SAT STANDARD: UNSAT Operator verifies that FCV-81 -12, Primary Water to PRT & Standpipes is open by observing 1-HS 12A Red light on, Green light Off.
COMMENTS:
Simulator Operator Note: When FCV-68-303 is opened, THEN delete ZA0T168309_and_AN :OVRD[2 1091_Overrides STEP 2.: [8.4.2] OPEN 1-FCV-68-303 by placing 1-HS SAT 303A to OPEN pOSitiOft UNSAT STANDARD: Operator takes 1-M-5 handswitch 1-HS-68-303A, Primary Water To PRT to OPEN. Handswitch indicates valve is open by red light ON. Critical Step (shaded portion)
This step is critical to align primary water to the PRT tank sparging line to lower temperature.
COMMENTS:
JPM Sim C Page 6 of 13 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 91%.
PRT temperature is as indicated.
Critical Step STANDARD: Operator monitors PRT level on Ll-68-300 and temperature on Tl-68-309; Then, based on PRT level Cue @ 91 %, places FCV 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 8.2 or 8.3.
UNSAT STANDARD: Operator goes to section 8.2 Reducing PRT Level Using B RCDT Pump (1A 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 I B 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.
JPM Sim C Page 7 of 13 Rev. 0 Job Performance Checklist:
STEP ISTANDARD SAT IUNSAT STEP 5.: [8.2.1] VERIFY RCDT pumps aligned for service in SAT accordance with valve checklist 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 0-L-2 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 Cue: Respond as the Rad Waste AUO, state that you UNSAT are at O-L-2 panel standing by and awaiting 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 SAT level.
UNSAT 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 8 of 13 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] SAT are 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 SAT 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 RCDT is 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-FCV68-3O5] N itrogén supply SAT F*RT.
UNSAT 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 (shaded portion)
This step is critical to ensure normal pressure maintained in the PRT during the level decrease.
COMMENTS:
JPM Sim C Page 9 of 13 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 11 [8 2 7] PLACE l-HS-68-310A in the OPEN pOSltIOfl and SAT VERIFY 1.f -3 1. ENS UNSAT Cue: When operator opens FCV-68-310 and the operator contacts the Rad Waste operator, then state to the Critical Step operator the B RCDT pump has started. (shaded portion)
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 Cue: RCDT pump B is running. UNSAT STANDARD: Operator checks with Rad Waste AUO to ensure RCDT pump B starts.
COMMENTS:
Simulator Operator Note: 30 seconds after FCV-68-31 0 is open, DELETE ZA0P168301 & AN:OVRD[357]
STEP 13.: [8.2.9] IF PRT pressure drops < 1.5 psig, THEN... SAT UNSAT Cue: PRT pressure is constant 6.5 psig..
STANDARD: Operator monitors PRT pressure with P1-68-301 on 1-M-5.
COMMENTS:
Caution: The RCDT level is to be maintained <50% while 1-FCV 310 is open to prevent inadvertent opening of 1-LCV-77-415 which could cause overfillinq of RCDT from the PRT.
JPM Sim C Page 10 of 13 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT 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 68-3 10 if RCDT approaches 50%.
STANDARD: Operator notifies AUO of this step.
COMMENTS:
STEP 15.: [8.2.11] IF returning from Appendix C, Then... SAT STANDARD: Operator N/As this step. UNSAT COMMENTS:
STEP 16.: [8.2.12] WHEN PRT level reaches desired level, THEN SAT STOP B RCDT Pump (at 0-L-2 panel)
UNSAT Cue: 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 lB. Tell him RCDT pump 18 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 11 of 13 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 17.: 3 CLOSE F cV-6Ø31o SAT Cue: UNSAT If operator asks, PRT Level is 70%, Temp is 110°F, and Press is 6.5 psig.
Critical Step (shaded portion)
STANDARD: Operator closes FCV-68-31 0 with HS-68-31 OA (on panel 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- SAT Auto position at O-L-2 panel.
UNSAT Cue: When operator requests AUO to place the HS for RCDT pump lB. 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 12 of 13 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 20.: Inform the US/SRO that the PRT parameters have been SAT returned to within normal operating conditions/ranges.
UNSAT Cue: This completes the JPM.
STANDARD: Operator informs the US/SRO that the PRT parameters have been returned to within normal operating conditions/ranges. 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. 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. 1A 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.
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT SYSTEM OPERATING INSTRUCTION 1-SO-68-5 PRESSURIZER RELIEF TANK Revision 18 QUALITY RELATED PREPARED/PROOFREAD BY: PAT BARBREE/MARIE HANKI NS RESPONSIBLE ORGANIZATION: OPERATIONS APPROVED BY: W. T. LEARY EFFECTIVE DATE: 10/28/07 LEVEL OF USE: CONTINUOUS USE 40 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.
SQN I -SO-68-5 PRESSURIZER RELIEF TANK Rev: 18 I
Page5of36 2.2 Developmental References A. SO 1-68.1, Reactor Coolant System B. 0-Ml-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 N 2 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.
SQN 1-SO-68-5 PRESSURIZER RELIEF TANK Rev: 18 I
Page6of36 Date JOcC\f 4.0 PREREQUISITE ACTIONS NOTE Throughout this Instruction, where an IFITHEN statement exists, the step should be NIA if condition does not exist.
jYENSURE 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.
,ENSLJRE Attachment 2, Valve Checklist 1-68-5.02 is VERIFY primary water is available to fill and cool the PRT (N/A if primary water will not be used).
VERIFY Waste Disposal System is available to receive liquid from PRT.
VERIFY vent header in service to receive gases from the PRT (N/A if PRT will not be vented to vent header). fl VERIFY low pressure N 2 system is in service (N/A if nitrogen will not be used).
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:
FE 5.0 STARTUP/STANDBY READINESS Wi 8.0 INFREQUENT OPERATION REASON: #oZE ?T Co T
I -SO-68-5 SQN 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 18 will NOT automatically stop on low level in PRT OR closure of FCV-68-310.
NOTE RCDT pump B will Auto start when I -FCV-68-31 0, 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-I 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 F1-HS-68-310A1 in the OPEN position, AND VERIFY [1 -FCV-68-31 0] OPENS.
[8] ENSURE RCDT pump B STARTS.
I -SO-68-5 SQN PRESSURIZER RELIEF TANK Rev: 18 I
Pagellof36 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 [1-FCV-68-310].
[b] PLACE [1-HS-77-6A1 RCDT pump B in PULL-P-AUTO.
[c] WHEN PRT pressure returns to normal, THEN OPEN [1-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 1-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-77-6A1 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.
SQN 1-SO-68-5 PRESSURIZER RELIEF TANK Rev: 18 I
Pagel2of36 Date___________
82 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 [1-FCV-68-310].
[C] ENSURE B RCDT pump STARTS.
[12] WHEN PRT reaches desired level, THEN STOP B RCDT pump using [1-HS-77-6A].
[13] CLOSE [1-FCV-68-3101.
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 [1-FCV-68-305] Nitrogen Supply to PRT.
1st IV END OF TEXT
I -SO-68-5 SQN PRESSURIZER RELIEF TANK Rev: 18 1
Pagel6of36 Date___________
NOTE May need an extra copy of this Instruction.
8.4 Reducing the Temperature of the PRT
- [I] ENSURE [1-FCV-81-121 OPEN.
[2] OPEN [1-FCV-68-3031 by placing
[1 -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 10 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 10 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 and supporting plant manipulations.
Time Critical Task: YES: NO: X K/A Reference/Ratings: 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 10 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.
Tools/Equipment!Procedures 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 10 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 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.
JPM Sim D-1 Page 5 of 10 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 O-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 Start 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-FI-70-108 (lower) and 1-Fl-70-106 (upper) for RCP #2 on panel O-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 10 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 1: 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 txP 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 U NSAT 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 w.. GOTO SECTION PAGE ANY RCP tripped or RCP shutdown required 2.1 4 NOTE During plant startup folovving seal maintenance, the seal package should seat and operate normally foflowirg 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of run flme
- 1 Seal Leakoff high flow (high flow Alarm) on ANY RCP 2.2 7
- 1 Seal Leakoff tow flow (low flow Alarm) on ANY RCP 2.3 1.3
- 3 Seal Leakoff high flow (low RCP standpipe level) on ANY RCP 2.5 21 Motor Stator Temperature High on ANY RCP 26 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 10 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 6.: 2.1.1. CHECK unit in Model or2. 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 UNSAT STANDARD: Operator performs reactor trip by operating reactor trip handswitch 1 RT-l (M-4) or 1-RT-2 (M-6.) - Critical Step (shaded portion)
COMMENTS:
STEP 8 EWHEct&istrippedfHENTT6Paff&(ed RF5 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 10 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 9.: c. GO TO E-0, Reactor Trip or Safety Injection, WHILE continuing in this SAT procedure.
UNSAT CUE: When step 2 action is initiated, CUE operator that another operator will perform E-0 while he continues in AOP-R.04.
STANDARD: Operator ensures that someone is performing remaining E-0 immediate actions.
COMMENTS:
CAUTION: If RCP seal leakoff is HIGH, seal return valve must be closed within 5 minutes after stoppinQ 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 8 gprn U N SAT OR
- RCP Seal Leak-off greater than 6 gpm and Lower bearing or seal tern perature rising uncontrolled.
STANDARD: Operator determines that seal Ieakoff is not outside of normal values and continues to step 4.
COMMENTS:
- I UNSAT Critical Step STANDARD: Operator uses Panel 1 -M-5 selector switches I -XS-68-2D and 1 -XS (shaded portion) 2M, Operator removes the idle loops temperature inputs from control by pulling to defeat XS-68-2D and XS-68-2M Critical to remove the affected loop temperature inputs from delta T and Tavg circuits because temperatures are not valid.
COMMENTS:
JPM Sim D-1 Page 9 of 10 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 12.: 5. CHECK RCPs I and 2 RUNNING SAT UNSAT STANDARD: Operator identifies #2 RCP as effected pump AND Proceeds to RNO column COMMENTS:
STEP 13 Step 5 RNO CLSE affected loops pressurizer spraj yj SAT UNSAT STANDARD: Operator closes #2 RCP Pressurizer Spray Valve by placing controller 1-PIC-68-340B to MANUAL and CLOSE Critical Step AND (shaded portion)
Observes valve demand indicates full close condition of the valve AND Verifies RED light out on indicator 1-Xl-68-340B Critical to close spray valve on affected loop to prevent inadvertent operation of valve.
COMMENTS:
STEP 14.: 6. EVALUATE EPIP-1, Emergency Plan Initiating Conditions Matrix SAT
- 7. EVALUATE the following Tech Specs for applicability:
U N SAT Cue: This completes the JPM.
STANDARD: Operator notifies the Shift Manager that the actions of AOP-R.04 are Stop Time complete; SM/STA evaluate EPIP-1 and Tech Specs the actions of AOP R.04 are complete.
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 1 annunciator system) OIL COOLERS 1-FS-70-106 (upper) 100 gpm decreasing SER 1138 (Unit I 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 lower oil cooler outlet flow by Actions observing F1-FI-70-1061 and 11-Fl-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-O, 47B60 1-70-28, 47W6 10-70-3, 47W6 11-70-3, 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 FRS.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.04 SQN REACTOR COOLANT PUMP MALFUNCTIONS I Rev.24 1.0 PURPOSE This procedure provides the actions necessary to mitigate the effects of a Reactor Coolant Pump (RCP) trip below P-8 (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 2of34
AOP-R.04 SQN REACTOR COOLANT PUMP MALFUNCTIONS Rev. 24 STEP 1 ACTIONIEXPECTED RESPONSE I 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 zP less than 220 psid
- 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 o 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 RCP 2.6 24 Page 3 of 34
AOP-R.04 SQN REACTOR COOLANT PUMP MALFUNCTIONS Rev. 24
[STEP ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED I 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 I ACTION/EXPECTED RESPONSE I 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. WHEN 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 3j
- FCV-62-48 [RCP 4]
- 4. PULL TO DEFEAT affected loop zT and T-avg:
- XS-68-2D (tT) a XS-68-2M (T-avg)
Page 5of34
AOP-R.04 SQN REACTOR COOLANT PUMP MALFUNCTIONS Rev. 24 STEP I ACTIONIEXPECTED RESPONSE I RESPONSE NOT OBTAINED I 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 Pian 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, RCS Operational Leakage
- 8. GO TO appropriate plant procedure.
END OF SECTION Page 6of34
JPM Sim E Page 1 of 13 Rev. 0 SEQUOYAH NUCLEAR PLANT September 2010 NRC Exam SIM E (ROSRO)
Respond to High Containment Pressure, Place RHR Spray in Service
JPM Sim E Page 2 of 13 Rev. 0 ROISRO JOB PERFORMANCE MEASURE Task: Respond to High Containment Pressure, Place RHR Spray in Service Task#: 3110160601 (RO)
Task Standard: Attempt to establish one train of RHR spray in service per FR-Z.1.
Time Critical Task: YES: NO: X KIA ReferencelRatings: W/E14 EA1.1 (3.7/3.7) 026000 GA13 (3.6-3.6) 026000 GA9 (3.6-3.6) 022000 A3.01 (4.1 4.4) 022000 A4.04 (3.1 -3.20)
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: 8 minutes Total Time:
Performance Time: Start Time: Finish Time:
COMMENTS
JPM Sim E Page 3 of 13 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)
- d. Activate Override ZDIHS6393A OPEN, to prevent FCV-63-93 from closing.
- e. Activate Override ZDIHS724IA CLOSE, to prevent FCV-72-41 from opening.
- f. Activate ZAOPDI3OI33 f:5
- g. 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. 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.
TooIsIEqupmentIProcedures 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 13 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.l 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 OATC 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 13 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 UNSAT of FR-Z I marked up as appropriate.
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 UN SAT 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 13 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:
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:
STANDARD: Operator verifies at least one CCP is running as SAT indicated by Red light on HS-62-1 04A or I 08A LIT. UNSAT AND Verifies at least one SI pump is running as indicated by Red lights on HS-63-I OA or ISA 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-74-1OA and 20A LIT. SAT UNSAT COMMENTS:
JPM Sim E Page 7 of 13 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 7.: [13.c] ESTABLISH Train B RHR spray:
[13.c.1] CHECK Train B RHR pump RUNNING.
SAT STANDARD: Operator checks that I B-B RHR pump is running as indicated by red light on HS-74-20A LIT. UNSAT 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:
[13 c 3] CLOSE RHR Injection FCV-63-94 STANDARD: Operator places handswitch for RHR injection FCV-63-94 in the CLOSED position and verifies the green light ON.
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 13 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 10 [13 c 4] OPEN RHR Spray FCV-72-41 NOTE: FCV-72-41 will NOT open the operator must go to the RNO.
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.
This step is critical for the operator to recognize that the I B-B RHR spray valve will Critical Step not open and to proceed to attempt placing the lA-A RHR spray in service.
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:
JPM Sim E Page 9 of 13 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 12 f13 c RNO bi IF RHR aligned for cold leg recirculation irE EuRE1ci-6 STANDARD: Operator places handswitch for RHR injection FCV-63-94 SAT the OPEN position and verifies red light ON.
UNSAT This step is critical to realign the I B-B RHR pump back into the CL injection mode as it cannot be used for RHR spray at this time. Critical Ste I COMMENTS:
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:
JPM Sim E Page 10 of 13 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 14 [13 c RNO c2J CLOSE RHR Injection FCV-63-93 NOTE: FCV-63-93 will NOT close.
STANDARD: Operator places handswitch for RHR injection FCV 93 in the CLOSED position and recognizes that the red light stays ON and the green light is OFF, continues in _SAT the RNO column. UNSAT This step is critical because the operator must determine that Train A RHR spray Critical Step can NOT be placed in service and continue with step 14.c RNO to realign Train A RHR to cold leg injection.
COMMENTS:
STEP 15.: [13.c RNO ci IF Train A RHR CANNOT be established THEN
[a] CLOSE RHR spray FCV-72-40.
SAT STANDARD: [a] Operator verifies FCV-72-40 is still closed as indicated by UNSAT green light ON and red light OFF.
COMMENTS:
STEP 16.: [b} IF RHR aligned for cold leg recirculation, THEN ENSURE FCV-63-93 OPEN.
SAT STANDARD: Operator verifies FCV-63-93 is still OPEN as indicated UNSAT by red light ON and green light OFF.
COMMENTS:
JPM Sim E Page 11 of 13 Rev. 0 Job Performance Checklist:
STEP/STANDARD SATIUNSAT Evaluator NOTE: If examinee informs the US of RHR status at this point, stop procedure performance at this step. If so, N/A JPM steps 18, 19 and 20.
STEP 17.: Communicates with US and informs him RHR spray status.
SAT STANDARD: Operator informs US that neither Train B RHR spray UNSAT nor Train A RHR spray could be placed in service in accordance with FR-Z.1 due to FCV-72-41 failed to open and FCV-63-93 failed to close.
COMMENTS:
Stop Time CUE: This completes the JPM STEP 18.: [14] MONITOR if containment spray should be stopped:
[14.a] CHECK any containment spray pump RUNNING.
STANDARD: Operator verifies I B Cntmt Spray pump running, Red light on SAT HS-74-20A LIT UNSAT COMMENTS:
STEP 19.: [14.b] Check containment pressure less than 2.0 psig.
STANDARD: Operator addresses CNMT pressure greater than 2 SAT psig and goes to RNO and step [1 5], Return to procedure and step in effect. UNSAT COMMENTS:
JPM Sim E Page 12 of 13 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 20.: Communicates with SRO and informs him/her of status of RHR spray.
STANDARD: Operator informs US that neither Train B RHR spray nor Train A RHR spray could be placed in service in accordance with SAT FR-Z.1 due to FCV-72-41 failed to open and FCV-63-93 failed UNSAT to close.
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.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:
I. You are the Unit I OATC and the SRO directs you to initiate one train of RHR spray per FR-Z.I starting at step 13.
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT EQI PROGRAM MANUAL FUNCTION RESTORATION PROCEDURE FR-Z.1 HIGH CONTAINMENT PRESSURE Revision 19 QUALITY RELATED PREPARED/PROOFREAD BY: D. A. PORTER RESPONSIBLE ORGANIZATION: OPERATIONS APPROVED BY: W. T. Learv 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).
SQN HIGH CONTAINMENT PRESSURE FR-Z.1 Rev. 19 HANDOUT Page 1 of I STEP ACTION
- 1. MONITOR RWST level greater than 27%.
4.d (if any SIG 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.
1 1. 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 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
SQN HIGH CONTAINMENT PRESSURE FR-Z.1 Rev. 19 HANDOUT Page 1 of I STEP ACTION
- 1. MONITOR RWST level greater than 27%.
4.d (if any SIG 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.
1 1. 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 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.
lb of 13
SQN HIGH CONTAINMENT PRESSURE I FR-Z.1 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
SQN HIGH CONTAINMENT PRESSURE FR-Z1 Rev. 19 I STEP I I ACTION/EXPECTED RESPONSE I I RESPONSE NOT OBTAINED I 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.
VERIFY Phase B valves CLOSED: IF 1 -FCV-32-i 10 (2-FCV-32-i Ii) is NOT closed,
- PaneI6KPHASEBGREEN 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
SQN HIGH CONTAINMENT PRESSURE FR-LI Rev. 19 I STEP I ACTIONIEXPECTED RESPONSE I RESPONSE NOT OBTAINED I 4 DETERMINE if this procedure should be exited:
f,.JCHECK for faulted S/G: 4 7 bO TO Step 5.
Any S/G 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
SQN HIGH CONTAINMENT PRESSURE FR-Z.1 Rev. 19 STEP I I ACTIONIEXPECTED RESPONSE I I RESPONSE NOT OBTAINED Y containment spray operation:
5 VER jaIF ECA-1 .1, Loss of RHR Sump f
Recirculation, is IN EFFECT, THEN PERFORM the following:
- 1) OPERATE containment spray as directed by ECA-1.1.
- 2) GO TO Step 6.
ERIFY containment spray pumps b. IF containment pressure is
/L../ 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..1 .3, Transfer to RHR Containment Sump, Step 21.
- 2) GO TO Substep 5.e.
(step continued on next page)
Page 5 of 13
SQN HIGH CONTAINMENT PRESSURE FR-Z.1 Rev. 19 I STEP I ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED I ERIFY containment spray suction d. ALIGN valves as necessary.
ALIGNED to RWST:
- FCV-72-22 OPEN
- FCV-72-21 OPEN.
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
SQN HIGH CONTAINMENT PRESSURE FR-Z.1 Rev. 19 I STEP I ACTIONIEXPECTED RESPONSE I I RESPONSE NOT OBTAINED I MONITOR containment air return fans:
- WHEN at least 10 minutes have elapsed from Phase B, THEN ENSURE containment air return fans RUNNING.
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-91
- FCV-30-47
- FCV-30-48.
VERIFY MSIVs 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
SQN HIGH CONTAINMENT PRESSURE FR-Z1 Rev. 19 STEPS ACTIONIEXPECTED RESPONSE I RESPONSE NOT OBTAINED I DETERMINE if any SIG Intact: IF all SIGs Faulted, THEN CHECK at least one SIG 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. FCV-3-400 and -401 as necessary.
- 3) GOTOStep13.
Isolating all SIGs will result in a loss of secondary heat sink.
DETERMINE if any SIG Faulted:
SIG pressures: TO Step 13.
- Any SIG pressure DROPPING in an uncontrolled manner OR
- Any SIG pressure less than 140 psig.
- b. ISOLATE feed flow to affected SIG:
- AFW Page 8 of 13
SQN HIGH CONTAINMENT PRESSURE FR-Z.1 Rev. 19 ISTEPI IACTIONIEXPECTED RESPONSE RESPONSE NOTOBTAINED I
- 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
SQN HIGH CONTAINMENT PRESSURE FR-Z.1 Rev. 19 STEP ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED
- 1) CHECK Train 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
SQN HIGH CONTAINMENT PRESSURE FR-Z.1 Rev. 19 ISTEP1 IACTIONIEXPECTED RESPONSE I IRESPONSE NOT OBTAINED 7
- 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 FR-Z.1 Rev. 19 ISTEPI IACTIONIEXPECTED RESPONSE I RESPONSE NOTOBTAINED I
- 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
SQN HIGH CONTAINMENT PRESSURE FR-Z.1 Rev. 19 STEP I LACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED I
- 15. RETURN TO procedure and step in effect.
END Page 13 of 13
JPM Sim F Page 1 of 15 Rev. 0 SEQUOYAH NUCLEAR PLANT September2010 NRC Exam SIM F (RO\SRO)
CALIBRATE POWER RANGE NUCLEAR INSTRUMENTATION
JPM Sim F Page 2 of 15 Rev. 0 RO!SRO 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 K/A ReferencelRatings: 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 15 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 the simulator in IC 116. [Rx Power should be 100 %]
- 4. If IC 116 is not available, initialize in IC 16 and perform the following setup 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%.
- 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, PR Neutron Flux Ch Cal. By Heat Balance Comparison, Sections 3.0, 6.1, 6.2, Appendix D
References:
Reference Title Rev No.
- 1. 0-Sl-OPS-092-078.0 Power Range Neutron Flux Channel Calibration By 21 Heat Balance Comparison DIRECTIONS TO TRAINEE on next page
JPM Sim F Page 4 of 15 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:
The unit is at steady state conditions with all NIS channels and LEFM operable.
INITIATING CUES:
- 1. The US has directed you to perform O-SI-OPS-092-078.O, Power Range Neutron Flux Channel Calibration By Heat Balance Comparison
- 2. Section 4.0 of O-Sl-OPS-092-078.O 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 15 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 1.: Obtain the appropriate procedure. SAT UNSAT STANDARD: Operator obtains 0-Sl-OPS-092-078.0 and goes to section 6.0 Performance.
COMMENTS:
Start Time STEP 2.: [1]VERIFY availability of LEFM calorimetric power... SAT 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 computer NOT available, THEN....
UNSAT Cue: Per initial conditions, ICS and LEFM calorimetric power are available.
STANDARD: Operator marks step N/A.
COMMENTS:
JPM Sim F Page 6 of 15 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 4.: [3] DETERMINE reactor core power level by performing the applicable appendix below.
UNSAT STANDARD: Operator goes to Appendix A.
COMMENTS:
EVALUATOR_NOTE:_The_following_steps_are_from_Appendix_A.
STEP 5.: [1] ENSURE SIG blowdown flows are updated by performing the following functions on ICS:
UNSAT
[1.2] SELECT CALORIMETRIC FUNCTION MENU.
[1.3] SELECT UPDATE OPERATOR ENTERED B LOWDOWN 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.
JPM Sim F Page 7 of 15 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT 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 100.00%.
STANDARD: Operator records U21 18 and Ui 127 or prints a copy from CS.
COMMENTS:
EVALUATOR NOTE: The following steps are from Section 6.1.
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 (XI-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:
JPM Sim F Page 8 of 15 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 8 [5]COMPARE NIS indication with core thermal power level SAT
_UNSAT AND
...... CriticaiStep CHECK appropriate box to indicate whether the indicated (shaded portion)
NIS power level recorded in step 6 1 [41 is equal to the core th eI le vel recorde din step &I3]tow ith +/-2%
STANDARD: Operator CHECKS to determine if NIS channels are within
+/- 2%. Checks YES for all NIS channels and signs step completion.
This step is critical because the operator must verify all channels within 2%
of recorded power level or adjust instruments per Tech Spec requirements.
COMMENTS:
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:
JPM Sim F Page 9 of 15 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 11.: [8] CHECK appropriate box to indicate whether the indicated SAT NIS power level recorded in step 6.1[4] is less than or UNSAT equaltolOO.5%.
STANDARD: The operator checks NO for N-41 and N-43 and checks YES for N-42 and N-44.
COMMENTS:
STEP 12.: [9] IF any NIS channels were inoperable during the performance of this instruction, THEN SAT UNSAT STANDARD: Operator marks this step NIA.
COMMENTS:
STEP 13.: [10] IF any NIS channel does not meet acceptance criteria (step 6.1[5j and/or step 6.1[8]), SAT U N SAT 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:
JPM Sim F Page 10 of 15 Rev. 0 Job Performance Checklist:
STEP ISTANDARD SATIUNSAT EVALUATOR_NOTE:_The_following_steps_are_from_Section_6.2 STEP 14.: [1] IF calculated average power in Section 6.1 oron printed copy differs by more than 3% from average RCS delta T, UNSAT THEN...
NOTIFY Engineering to determine the cause STANDARD: Operator N/As this step.
COMMENTS:
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:
JPM Sim F Page 11 of 15 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT 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. (Initial conditions had all channels operable)
COMMENTS:
STEP 18 f53 ENSURE rod control system IS in MANUAL lfl SAT accordance with UNSAT STANDARD: Operator turns HS-85-51 10 to the MANUAL position.
Critical Step This step is critical to ensure no automatic rod movement during NIS (shaded portion) adjustments.
COMMENTS:
JPM Sim F Page 12 of 15 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 19.: [6] IF rate trip exists (or occurs) on the NIS channel being SAT calibrated, THEN UNSAT CLEAR tht channels tripsignal (momentarily set RiE MODE switch to RESET position) and annunciator XA 6A. Critical Step (shaded portion)
Cue: For this step and the following steps, inform the operator that for JPM purposes the CV is not required STAN DARD: Operator verifies NO rate trip signals are in on ANY of the PR and the annunciator is clear.
- CRITICAL PORTION: If rate trip occurs 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:
STEP 20 [7] ADJUST gain potentiometer on associated charmePs SAT power range B drawer to bring that channels indicated UNSAT power level to within 5% of the calorametno power recorded in section 6 1 or listed on the printed copy AND Critical Step in poten imete latch e-e gaged. (shaded portion)
STANDARD: Operator must adjust N41 and N43 to satisfy criteria.
The operator should repeat step [6] 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:
JPM Sim F Page 13 of 15 Rev. 0 Job Performance Checklist:
STEP ISTANDARD SATIUNSAT 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 [6] to adjust either N41 or N42.
COMMENTS:
STEP 22.: [10] WHEN NIS adjustments have been completed, THEN 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....
UN SAT STANDARD: Operator N/As this step since all are operable.
COMMENTS:
JPM Sim F Page 14 of 15 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT 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 +/- .5% of calometric power.
COMMENTS:
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 UN SAT 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:
Stop Time CUE: This completes the JPM
READ TO OPERATOR 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:
- 1. You are the CRC and the US has directed you to perform O-Sl-OPS-092-078.O.
- 2. Section 4.0 of 0-SI-OPS-092-078.0 has been completed.
- 3. Notify the US when the SI has been completed and any necessary adjustments have been made.
Sequoyah Nuclear Plant Unit I & 2 Surveillance Instruction O-SI-OPS-092-078.O 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[8j 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[5], 6.1[7] and 6.1[8] to clarify intent as a minor change.
A note was added prior to Step 6.1[1 01 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 Frequencyand 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 Preliminary Actions 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 UI 118 (> 40% WITH LEFM NOT AVAILABLE) 28 Appendix 0: CALCULATION OF CORE THERMAL POWER LEVEL WITH INOPERABLE PLANT COMPUTER (RCS AT GREATER THAN 40%) 31
SQN POWER RANGE NEUTRON FLUX O-SI-OPS-092-078.0 Unit I & 2 CHANNEL CALIBRATION BY HEAT Rev. 0021 BALANCE COMPARISON Paae 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 (NIS) 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. IC.3] To ensure NIS accuracy, this test should be performed when directed by O-GO-4 or O-GO-5.
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-Sl-OPS-092-078.0 Unit I & 2 CHANNEL CALIBRATION BY HEAT Rev. 0021 BALANCE COMPARISON Page 6of41
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 (Tref).
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 AT 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 (Ui 118) 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 U 1118 accuracy with the DOS 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
.0 , PREREQUISITE ACTIONS -
/
During the performance of this lnstruction,any IFITHEN statement may be marked N/A when the corresponding stated condition does not occur.
Preliminary Actions y 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
/ 4.3 Field Preparations
(
t] ENSURE reactor power and RCS average temperature are stable.
Approvals and Notifications 7
N OTIFY 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 II 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:
[1.1] CHECK LEFM status NORMAL on ICS (NSSS and BOP) Current Calorimetric Data screen.
DYes DNo
[1.21 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 Unit______
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 lOS display are NOT automatically adjusted.
[2] IF LEFM calorimetric power NOT available OR ICS computer NOT available, THEN PERFORM the following:
[2.1] ENTER applicable action of TRM 3.3.3.15.
[2.2] 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 98.7%,
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-PI-SXX-000-022.2, then the applicable section(s) of 0-PI-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 i(
RCS AT greater than 15% and LEFM core thermal A D power (U21 18) available (step [1] acceptance criteria met)
RCS AT between 15% and 40% and LEFM core B D thermal power (U21 18) NOT available RCS AT greater than 40% C D LEFM core thermal power (U2118) NOT available but lOS point Ui 118 is available RCS AT greater than 40% and lOS computer D NOT available RCS AT greater than 40% and ICS core thermal E El 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 lOS):
% Rated Core Thermal Power = %
SQN POWER RANGE NEUTRON FLUX 0-SI-OPS-092-078.0 Unit I & 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) 15] 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 NlSChannelN-41 D D D NIS Channel N-42 D D D NIS Channel N-43 D C C NlSChannelN-44 C C RO or SRO
SQN POWER RANGE NEUTRON FLUX 0-SI-OPS-092-078.0 Unit I & 2 CHANNEL CALIBRATION BY HEAT Rev. 0021 BALANCE COMPARISON Page 15 of 41 Unit______
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> N IS),
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 C NIS Channel N-42 C C NIS Channel N-43 C 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 differe nce 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 specifi c
circumstances.
[10] IF any channel does not meet acceptance criteria (Step 6.1 [5] 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 Un it______
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-Pl-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-S0-85-1.
SQN POWER RANGE NEUTRON FLUX 0-Sl-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{91 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-.41U or NC-41K 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 D C NIS Channel N-43 C NIS Channel N-44 C C 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 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[1 0] 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 D D NIS Channel N-42 D D D NIS Channel N-43 D NIS Channel N-44 D D RO or SRO
[13] IF acceptance criteria were NOT satisfied for any NIS 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
SQN POWER RANGE NEUTRON FLUX O-SI-OPS-092-078.O Unit I & 2 CHANNEL CALIBRATION BY HEAT Rev. 0021 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 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 (U1118 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-Pl-SXX-000-022.2 requires several hours from initiation until completion of power calculation.
[1] IF 0-Pl-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-Pl-SXX000-022.2.
[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)
Unit______
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 ICS 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 P 1-3-50 [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 SIG Pressure PI-1-9A or 9B [M-4] psig Loop 3 SIG Pressure P1-i -20A or 20B [M-4] psig Loop 4 S/G Pressure P1-i -27A or 27B [M-4] psig Total Feedwater Flow LEFM Ibm/hr Feedwater Temperature (mustbe>250°F) LEFM
°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 ICS 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 I .O[3.8]
34.55
SQN POWER RANGE NEUTRON FLUX 0-SI-OPS-092-078.0 Unit I & 2 CHANNEL CALIBRATION BY HEAT Rev. 0021 BALANCE COMPARISON Page 35 of 41 Appendix D (Page 5 of 8)
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[3.9j.
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 6 of 8)
U nit______
1.0 PERFORMANCE (continued)
NOTE 1 ,2-P-ICC-OO3-O36.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:
[4.1] NOTIFY MIG or Systems Engineering to install precision temperature monitoring equipment in feedwater header temperature wells TW-3-1 97 and TW3-1 98
[TB el. 685].
[4.2] RECORD average feedwater header temperature:
MIG or Eng Iv (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 D (Page 7 of 8)
Unit______
1.0 PERFORMANCE (continued)
[4.31 RECORD the following data:
Parameter Indication Reading Loop I Feedwater Press P1-3-37 [M-3j psig Loop 2 Feedwater Press P1-3-50 [M-3) psig Loop 3 Feedwater Press P1-3-92 [M-3} psig Loop 4 Feedwater Press P1-3-105 [M-3] psig Loop 1 S/G Pressure PI-1-2A or 2B [M-4] psig Loop 2 S/G Pressure PI-1-9A or 9B [M-4j psig Loop 3 SIG Pressure P1-I -20A or 20B [M-4] psig Loop 4 S/G Pressure Pl-1-27A or 27B [M-4] psig Loop 1 Feedwater Flow FI-3-35A or 35B [M-4} Ibm/hr Loop 2 Feedwater Flow FI-3-48A or 48B [M-4j Ibm/hr Loop 3 Feedwater Flow FI-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)
Un it______
1.0 PERFORMANCE (continued)
[4.6] ENTER data in lOS from substeps 1 .0[4.2] andl .0[4.3].
[4.7] SELECT function key F3 to execute calculation.
[4.8] PRINT calorimetric results.
[4.9] VERIFY data from subSteps I .O[4.2] and I .0[4.3] as correctly entered in lOS.
lv
[4.10] RECORD Total S/G Thermal Power from calorimetric printout:
[4.11] CALCULATE percent power corresponding to iteml .0[4.1 01 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
JPM Sim G Page 1 of 13 Rev. 0 SEQUOYAH NUCLEAR PLANT September2010 NRC Exam SIM G (ROSRO)
Initiate Makeup to the Refueling Cavity
JPM Sim G Page 2 of 13 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 13 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 the simulator to IC-i 14.
Override # AN:OVRDN_584 to ON, to bring in alarm for SPENT FUEL PIT LEVEL.
Override ZA0Ll68320, ZA0L168321, ZA0L168335A, ZA0LI68339A at 50 to simulate PZR at refueling level.
Override ZAOPI6866A, ZA0P16869, ZAOPI6B62 at 35 to simulate refuel flood up pressure.
Override AN:OVRDN_1 695 to OFF to keep midloop high level alarm from alarming.
Override (FCV-62-135 & 136, CCP Suction from VCT, CLOSED. (ZLOHS62I35A_Green f:ON, ZLOHS62I 36A_Green f:ON, ZDIHS62I 35A f:0 (close), ZDIHS62I 36A f:0 (close)
Add Caution Order tag to FCV-63-i per 0-GO-i 3 App. 0. (jumpers placed to remove seal in)
- 5. 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.
ToolsiEquipmentlProced u res Needed:
AOP-M.04, Section 2.0, 2.1, and Appendix A & B
REFERENCES:
AOP-M.04, Sect 2.1 & Appendix A I Refueling Malfunctions Rev No. 9 DIRECTIONS TO TRAINEE on next page
JPM Sim G Page 4 of 13 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 13 Rev. 0 Job Performance Checklist STEPISTANDARD I SAT/UNSAT NOTE: If operator responds using AR-M6-D window D-3. AUO is dispatched to the SFP to investigate the alarm. Operator determines that AOP-M.04 is the appropriate procedure.
STEP 1: Obtain the appropriate procedure. SAT STANDARD: Operator obtains a copy of AOP-M.04. UNSAT COMMENTS:
Start Time STEP 2: 1. EVALUATE the following Tech Specs for applicability: SAT
- 3.9.8.2, RHR Low Water Level UNSAT
- 3.9.10, Rx Vessel Water Level
. 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 COMMENTS:
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:
JPM Sim G Page 6 of 13 Rev. 0 Job Performance Checklist STEP/STANDARD SAT / UNSAT STEP 4: 3. Diagnose conditions to determine appropriate section, SAT of 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 SAT evacuate Containment and AB el. 734 Refuel Floor.
UNSAT
- The SM would like you to make that announcement.
STANDARD: Operator makes this announcement.
COMMENTS:
JPM Sim G Page 7 of 13 Rev. 0 Job Performance Checklist STEPISTANDARD SAT I 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 req ui red
. Fuel Handling Supervisor Cue: The SM will ensure all control room personnel and the Fuel Handling Supervisor are aware of the event and that RAD CON begins monitoring CNMT and the Aux Bldg.
STAN DARD: 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:
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.
JPM Sim G Page 8 of 13 Rev. 0 Job Performance Checklist STEP/STANDARD SAT I UNSAT STEP 8: A.1.a. VERIFY RWST level greater than 8%.
STANDARD: Operator verifies RWST level greater than 8% using one or UNSAT more of the RWST level indicators located on M-6.
COMMENTS:
STEP 9: A.1 .b. ENSURE the following charging valves OPEN: SAT FCV-62-90 UNSAT 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:
FCV-62-91 UNSAT STANDARD: Operator verifies FCV-62-91 open by observing 1-HS-62-91A RED light LIT COMMENTS:
STEP 11: A.1 .b. ENSURE the following charging valves OPEN: SAT FCV-62-85 OR FCV-62-86 UNSAT STANDARD: Operator verifies FCV-62-85 or 86 is open by observing I -HS-62-85A or I -HS-62-86A RED light LIT.
COMMENTS:
JPM Sim G Page 9 of 13 Rev. 0 Job Performance Checklist STEPISTANDARD SAT I UNSAT STEP I 2:A.I; c OPEN the f aives SAT FCV-62-135ad.136, CGP suction frbm RWST UNSAT STANDARD: Operator pushes HSs (1-HS-62-135A and 1-HS 136A) IN and turns to the OPEN position and determines that neither valve opens Green lights remain LIT for FCVs-Critical Step 62-135 and 136.
(shaded portion)
Cue: If required, prompt operator to attempt to open FCV 62-1 36 following failure of FCV-62-135 to open.
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:
NOTE: This will direct the Operator to the Alternate path.
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 and directs the operator to fill the Reactor Cavity using alternate method (step 2 of Appendix A uses RHR pump to fill cavity)
STANDARD: Operator determines that step 2 of Appendix A is appropriate action to take.
COMMENTS:
NOTE: The following are from Appendix A, Section A, Step 2 of AOP-M.04.
JPM Sim G Page 10 of 13 Rev. 0 Job Performance Checklist STEPISTANDARD SAT I UNSAT 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. PENFCV631 STANDARD: Operator uses HS-63-1A and opens FCV-63-1, Observes Critical Step Red light ON, Green light OFF. (shaded portion)
This step is critical to provide a makeup flowpath from the RWST to the refueling cavity.
COMMENTS:
JPM Sim G Page 11 ofl3 Rev. 0 Job Performance Checklist STEP/STANDARD SAT / UNSAT STEP 16: A.2. IF initiating makeup from RWST using RHR Pump SAT suction, THEN PERFORM the following:
UNSAT
- a. c the following valves:
FcV-74-1, RHR sUctioinfrohi HOt Leg No.4 or: Critical Step FOV-74-2, RHR suction from Hot Leg. No. 4.: (shaded portion)
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 VERlFYflowto RCS.
UNSAT 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 13 Rev. 0 Job Performance Checklist STEP/STANDARD SAT I UNSAT STEP 19: Inform the US of flow from RWST to Spent Fuel Pit. SAT STANDARD: UNSAT Operator informs US and/or SM that flow has been established from RWST to Spent Fuel Pit.
Cue: After operator reports that flow has been established, State 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. 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 SRQ 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-MM4 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 AOP-M.04 Rev9 This procedure provides the actions necessary to mitigate the effects of a dropped fuel assembly, damaged fuel assembly, or refueling cavity seal failure.
Page 2 of 42
SQN REFUELING MALFUNCTIONS AOP-M.04 Rev. 9 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I 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 22 12 inside containment Irradiated fuel assembly has been dropped or damaged 23 17 outside containment New fuel assembly has been dropped or damaged 2.4 21 END OF SECTION Page 3 of 42
SQN REFUELING MALFUNCTIONS AOP-M.04 Rev. 9 STEP I ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED I 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.1]
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 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 notiifed that seal failure has occurred: [C.2)
- Control Room staff
- RADCON to monitor refueling area and Aux Bldg as required
- Fuel Handling Supervisor Page 4 of 42
AOP-M.04 SQN REFUELING MALFUNCTIONS Rev. 9 STEP ACTIONIEXPECTED RESPONSE I RESPONSE NOT OBTAINED 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) GOTOStep4.
- b. MAINTAIN RWST level b. REALIGN pump suctions greater than 5%. USING Appendix A, Filling Refueling.
Cavity from RWST:
SQN REFUELING MALFUNCTIONS AOP-M.04 Rev. 9 I STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I 2.1 Reactor Cavity Seal Failure [C.1]
- 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,
- any irradiated fuel assembly THEN out of normal storage 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
AOP-M.04 SQN REFUELING MALFUNCTIONS Rev. 9 L STEP ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED 2.1 Reactor Cavity Seal Failure [C.l]
- 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 SEP 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
REFUELING MALFUNCTIONS AOP-M.04 SQN Rev. 9 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I 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 SEP side, THEN NOTIFY operators with Appendix F to ensure wafer valve CLOSED.
Page 8 of 42
AOP-M.04 SQN REFUELING MALFUNCTIONS Rev. 9 STEP ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED 1 11 Reactor Cavity Seal Failure (contd)
- 10. VERIFY SEP bridge hoist empty of fuel. PERFORM the following:
- b. INSERT fuel assembly into any SEP location.
- c. RECORD location
cooling pump suction strainer.
- a. STOP running SFP cooling pumps
[Aux BIdg, 714 elev, SFP Pump Platform]
- b. FILL SEP USING 0-SO-78-1, Spent Euel Pit Cooling System.
- c. IF additional makeup is needed, THEN
- 1) NOTIFY Chem Lab Supervisor.
- 2) INITIATE makeup from Fire water to SEP using hose reel station as required.
- e. VENT SFP cooling pumps casings.
- f. START SEP cooling pump.
Page 9 of 42
REFUELING MALFUNCTIONS AOP-M.04 SQN Rev. 9 STEP ACTION/EXPECTED RESPONSE I 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.
-c
- 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
AOP-M.04 SQN REFUELING MALFUNCTIONS Rev. 9 STEP ACTION/EXPECTED RESPONSE I RESPONSE NOT OBTAINED I 2.1 Reactor Cavity Seal Failure (coritd)
- 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 of42
AOP-M.O4 SQN REFUELING MALFUNCTIONS 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:
- a. VERIFY RWST level greater than 8%. E
- b. ENSURE the following charging valves OPEN:
- FCV-62-90 f\! ) fli El
.. V JL.C I L...J
- FCV-62-86 or FCV-62-85 E
- c. OPEN the following valves:
- d. CLOSE the following valves:
- e. CLOSE FOV-62-83, RHR Letdown.
- f. CLOSE FCV-62-81, Letdown Back Pressure Control Valve.
- g. ENSURE COP running. El
- h. VERIFY flow to RCS. El 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)
- a. VERIFY RWST level greater than 8%.
- b. OPEN FCV-63-1, RWST Supply.
- c. CLOSE one of the following valves:
- FCV-74-2, RHR Supply from Hot Leg No. 4 El
- d. VERIFY flow to RCS. El Page 29 of 42
AOP-M.04 SQN REFUELING MALFUNCTIONS Rev. 9 Page 2 of 3 APPENDIX A FILLING REFUELING CAVITY FROM RWST B. Restoration from RWST Filling Alignment CAUTION I LCO 3.9.8.1 must be entered when RHR flow is less than 2000 gpm with fuel in reactor vessel.
CAUTION 2 LCO 3.9.8.2 must be entered when realigning RHR suction valves with cavity level less than 725 1.5 (less than 23 feet above flange).
IF restoring from RWST makeup using RHR Pump suction, THEN PERFORM the following:
- a. ENSURE RHR Pumps STOPPED. El
- b. CLOSE FCV-63-1, RWST Supply. El
- c. ENSURE the following valves OPEN:
- FCV-74-1, RHR Supply from Hot Leg No. 4 El
- FCV-74-2, RHR Supply from Hot Leg No. 4 El
- d. ENSURE RHR pump running. El
- e. ENSURE flow established to RCS. El Page 30 of 42
AOP-M.04 SQN REFUELING MALFUNCTIONS I Rev.9 Page 3 of 3 APPENDIX A FILLING REFUELING CAVITY FROM RWST B. Restoration from RWST Filling Alignment (contd)
- b. OPEN the following valves:
- FCV-62-133, COP Suction from VOT El
- c. CLOSE the following valves:
- d. ENSURE COP running.
- e. ENSURE flow established to RCS.
- f. IF RHR letdown is desired, THEN OPEN or THROTTLE the following valves:
- FCV-62-81, Letdown Back Pressure Control Valve.
- FOV-62-83, RHR Letdown.
Page 31 of 42
AOP-M.04 SQN REFUELING MALFUNCTIONS I Rev.9 Page 1 of I APPENDIX B ELEVATIONS AND DISTANCES The purpose of this appendix is to provide information to aid the decision making processes
- as follows:
- Placing Irradiated fuel assemblies and reactor vessel lower internals below the reactor vessel flange level with maximum water coverage in a safe storage position
- Limiting loss of water from the Spent Fuel Pit by closing the wafer valve a Providing guidelines for makeup to the refueling cavity and Spent Fuel Pit in the event of a reactor cavity water seal failure The following may be useful for decision making:
DESCRiPTION ELEVATION Rx flange 702 1.5 Bottom of gate between SFP and transfer canal 702 1.5 Top of erect upenders 702 1.75 Top of fuel racks 701 0.75 DESCRIPTION LENGTH Length of guide studs 16
9.6 DESCRIPTION
DISTANCE (Rx Flange to Refuel Floor)
Equipment storage area 1 1 3 Transfer canal 15 10.75 A maximum leak rate of 3176 gpm has been calculated assuming 1/16-inch gap between the seal and the reactor vessel flange. At this leak rate and with the wafer valve closed, it has been estimated that it would take 70 minutes for the refuel cavity to drain to flange elevation.
Page 32 of 42
JPM Sim H-I Page 1 of 15 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 15 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-l.
Time Critical Task: YES: NO: X K/A ReferencelRatings: 064A4.06(3.9/3.9) 064A2.08 (2.5/27)
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 15 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-i 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[9051 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.
ToolslEqui pmentlProcedu res Needed:
EA-82-1, Placing DIGs in Standby
References:
Reference Title Rev No.
- 1. EA-82-1 Placing DIGs in Standby 2
JPM Sim H-i Page 4 of 15 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 Unit 1 Diesel Generators per EA-82-1.
- 2. The lA-A D/G is to be shutdown first.
JPM Sim H-i Page 5 of 15 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
. DIG I A-A
. DIG lB-B UNSAT
. DIG 2A-A____
. DIG 2B-B STANDARD: Operator checks lA-A and lB-B diesel generators being selected.
COMMENTS:
STEP 3.: 2. IF EA-202-1 was NOT used to unload the selected DIG, SAT THEN DISPATCH AUO to perform Section 4.2 to reset selected DIG 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 DIG lA-A lB-B 2A-A 28-B TO SECTION Sin43.
Unloaded greater then 2 Pgin DIG Combustb)es. C .i C C Secicn 4A, Unloaded Lesa thafl 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, str Down DIG C C STANDARD: Operator determines that section 4.3 is the appropriate section since the DIG 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 lB-B boxes.)
COMMENTS:
JPM Sim H-i Page 6 of 15 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT IUNSAT NOTE: The following steps are from section 43.
SAT STEP 5.: T PARAUL: UNSAT DIG MODE SELECTOR SWITCH PARALLEL 4 IA-A HS-B2-1 C 18-3 HS-a24 C 2A-A HS-S2-7 C Critical Step 28-B HS-82-108 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. RI1é1ecfédD[G SNCNRON1ZE switch to SYN SAT DIG SYNCHRONIZE SWITCH SIN UNSAT lA-A i-KS-5747 C IS-B i-KS-57-74 C 2A-A 2-HS-&747 C 2-KS-57-74 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 PULL-P- AUTO:
UNSAT DIG VOLTAGE REGULATOR PULL-P-AUTO SWITCN lA-A HS$2-12 C 18-B HS42-42 C 2A-A HS42-72 C 28-B S-82-2 C STANDARD: Operator verifies O-HS-82-12, DG IA-A VOLTAGE REGULATOR to PULL-P-AUTO.
COMMENTS:
JPM Sim H-i Page 7 of 15 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 8.: 4. ADJUST runirg voitae to match incoming SAT VOLTAGE REGUTORwitch UNSAT DIG VOLTAGE MATCHED lA-A EI-82-4 E! C la-S Ei-82-34 EI42-3 C 2A-A E-82-64 EI42-8 29-S E-8244 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 to allow safe parallel operation of the DIG.
COMMENTS:
STEP 9.: 5. ADJUST selected D/G $PEED CONTROL switch SPEED CONTROL SLOWLY IN FAST DIG SWITCH SYNCHROSCOPE UNSAT DIRECTION IA-A HS-82-13 X-82-1 C 19-B HS-82-43 X-823i C 2A-A HS-82-73 X1-&2-51 C 2B-B HS-52-103 xf-a2-9i 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 DG 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 15 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT IUNSAT STEP 10.: VHE4 synóJfrçsope needle Is at I ZcloponJN LQet4OJG pjjpit reaic SAT DIG SYNCHROSCOPE DIG OUTPUT CLOSED UNSAT BREAKER IA-A XI-52-1 I44S-7-46A 18-B X-82-3I 1.HS-57-73A D 2A-A )U-82-61 2-H5-57-48A 2B.B XI-8241 2-HS-7-73A Critical Step STANDARD: Operator places I -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.:
IQ?tJ6 MW: SAT SPEED CONTROL UNSAT SWITCH DIG MEGAWATTS tS MW IA-A Hs-a2-13 E1-82-IUA C IS-B HS-8243 E-S24DA C 2AA HS-B2-73 EI-a2-7GA C Critical Step 25-B HS-52-403 E1-a2-WDA C STANDARD: Operator intermittently places O-HS-82-13 to RAISE until the MW loading on O-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 15 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 12 MALTA1N,-1 tVAR,fOUT) 9 osjtepqWe; DG VOLTAGE U N SAT DIG REGULATOR SWITCH DIG MEGAVARS +1 MVAR IA-A HS-82-12 E42-1 IA D 15-B Hs-8242 E42-4lA D Critical Step 2A-A KS-S2-72 E-524 I A. C 25-B HS-&2-402 E-2-101A C STANDARD: Operator places O-HS-82-12 to RAISE to establish the MVAR loading on O-El-82-I1A 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 D/G. SAT Cue: Role Play as AUO acknowledge the direction to monitor the U N SAT DIG IA-A exhaust stack.
STANDARD: Operator dispatches an AUO to the D/G building to monitor D/G lA-A exhaust.
COMMENTS:
JPM Sim H-i Page 10 of 15 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT/UNSAT STEP 14 LOAF ie1dc4pd qjW LIIFQLb WHILE observing thefiQLQ following guidelines: SAT
- a. IF stack exhaust smoke becomes twice as dense as normal during loading, THEN U NSAT 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:
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-82-1OA 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.: JD Eseictdd PPQ Pwatchtc, I6Ø MWJo?cQ5MW SAT DIG_ISPEED_CONTROL SWITCI4 O5 MW UN SAT IA-A iS42-13 18-B HS-82-43 Critical Step 2A-A HS42-73 22-B H&62-1O3 STANDARD: Operator places 0-HS-82-13 to LOWER until the MW loading on 0-El-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 ofi5 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 16 12 ADJUST selected DIG VOLTAGE REGULATOR switchto lower
. SAT DIG VOLTAGE DIG MEGAVARS U MVAR / UNSAT REGULATOR SWITCH IA-A 115-82-12 E1-82-i 1A C lB-B 115-82-42 E142-41A C 2A-A 115-52-72 B-82-TTA C 28-B HS-52-W2 31-82-lolA C STANDARD: Operator places O-HS-82-12 to LOWER until the MVAR loading on O-EI-82-1 1A reduces to 0.
COMMENTS:
STEP 17.: IPdE.LQ tkTontfttChtTR1P SAT DIG DIG OUTPUT BREAKER TRIPPED J IA-A i-HS-740A C UNSAT 18-3 1-HS-7-73A C 2A-A 2-11S-7-4UA C Critical Step 28-B 2-11S-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 D/G lA-A. UNSAT COMMENTS:
Evaluator Note: The following steps are from Section 4.4 STEP 19.: 1. VERIFY selected D/G unloaded with output breaker open: SAT DiG DIG OUTPUT BREAKER UNLOADED & OUTPUT BREAKER HANDSWITCH BREAKER OPEN J UNSAT IA-A I12 l-HS-54-46A C 18-8 t14 I-Hs.57-72A C 2A-A 122 2-HS-54-4A C 28-B 124 2-Rs-57-7a4. C STANDARD: Operator verifies D/G lA-a output breaker open by green light LIT over Handswitch 1 -HS-54-46A.
COMMENTS:
JPM Sim H-I Page 12 of 15 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 20.: AçEetedbI$ L$iP T&t SAT UNSAT
[)J(3 DIG CONTROL START-STOP SWLTCK STOP IA-A HS-52-44 lB-B HS-82-44 Critical Step 2A-A HS-52-74 2B-B HS-32-1t14 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 DIG(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 IA-A 18-B D 2A-A 28-3 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 himlher contact the UO when speed is zero.
COMMENTS:
JPM Sim H-i Page 13 of 15 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT IUNSAT STEP 22.: SAT I)N[Tition UNSAT DIG MODE SELECTOR SWITCH PUSH IN UNIT t IA-A 1-1-13-82-18 D Critical Step 19-B i-RS-824E 9 2A-A 2-1-13-82-78 9 29-3 2-HS42-108. 9 STANDARD: Operator places hand switch 1 -HS-82-1 8, 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 DIG: SYNCHRONIZE SWITCI-1 OFF UNSAT IA-A 1-1-13-57-47 9 19-3 1-1-13-57-74 9 2A-A 2-1-13-5747 9 29-B 2-1-13-57-74 9 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 15 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 DIG ERCW TO DIG HEAT EXCHANGERS CLOSED 4 IA-A I-HS-74
-HS-7-SA D IS-B I-HS7-7A D I-HS874 D 2A-A 2-HS-67-A D 2-HS-t7-3SA 25-B 2-Hs47$7A 2-HS47-5A D 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 the other DC UNSAT needs to be shutdown.
Cue: When candidate returns to section 4.1 to shutdown the other Diesel Generator, 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 Unit I Diesel Generators per EA-82-1.
- 2. The IA-A D/G is to be shutdown first.
- 3. Inform the SM when 1 A and I B D/Gs have been shutdown per EA-82-1.
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.
SQN EA-82-1 PLACING DIGs IN STANDBY 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-i, Loss of Reactor or Secondary Coolant.
C. E-3, Steam Generator Tube Rupture.
D. ECA-2.1 Uncontrolled Depressurization of All Steam Generators.
E. ECA-3.1, SGTR and LOCA Subcooled Recovery.
F. ECA-3.2, SGTR and LOCA Saturated Recovery.
G. ECA-3.3, SGTR Without Pressurizer Pressure Control.
I. 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 DiGs 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 Page3ofl6 4.0 OPERATOR ACTIONS 4.1 Section Applicability
- 1. SELECT DIG to be shut down:
- D/G lA-A
- DIG lB-B
- DIG 2A-A
- D/G2B-B NOTE If EA-202-l was used to unload the selected D/G, then the DIG 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 D/G emergency start signal. El
- 3. GO TO appropriate section based on table below:
THEN . DIG DIG DIG DIG IF SELECTED DIG IA-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.
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.
El El El
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 DIGs 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. LI END OF SECTION
r SQN 1,2 PLACING DIGs IN STANDBY Rev. 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. Li
- 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 lA-A 43T(L) LI 1 B-B 43T(L) LI 2A-A 43T(L) LI 2B-B 43T(L) El
- 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-l 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:
SHUTDOWN BOARD LOGIC PANEL SWITCH NOR q
lA-A 43T(L) LI 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:
D/G RELAY BOARD RED LIGHT DARK
- b. PLACE selected DIG [86 LOR] switch to RESET:
D/G RELAY BOARD SWITCH RESET
-.1 lA-A 86L0R LI lB-B 86L0R LI 2A-A 86L0R LI 2B-B 86 LOR LI
SQN I EA-82-1 I PLACING DIGs IN STANDBY I Rev. 2 I
1,2 I
II Page7ofl6 I
4.2 Resetting DIG Auto Start Signals (Continued)
- 4. GO TO Section 4.1, step in effect. E END OF SECTION
SQN EA-82-1 PLACING DIGs IN STANDBY 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 D/G.
- 1. POSITION selected D/G MODE SELECTOR switch to PARALLEL:
DIG MODE SELECTOR SWITCH PARALLEL q IA-A HS-82-18 Li 1 B-B HS-82-48 LI 2A-A HS-82-78 LI 2B-B HS-82-108 LI
- 2. TURN selected D/G SYNCHRONIZE switch to SYN:
D/G SYNCHRONIZE SWITCH SYN J IA-A 1-HS-57-47 LI lB-B 1-HS-57-74 LI 2A-A 2-HS-57-47 LI 2B-B 2-HS-57-74 LI
j SQN PLACING DIGs IN STANDBY EA-82-1 Rev. 2 1,2 Page9ofl6 4.3 Purging DIG Combustibles (Continued)
- 3. ENSURE selected DIG VOLTAGE REGULATOR switch in PULL-P-AUTO:
D/G VOLTAGE REGULATOR PULL-P-AUTO SWITCH lA-A HS-82-12 El lB-B HS-82-42 El 2A-A HS-82-72 El 2BB HS-82-102 El
- 4. ADJUST running voltage to match incoming voltage USING DIG VOLTAGE REGULATOR switch:
- 5. ADJUST selected D/G SPEED CONTROL switch UNTIL associated synchroscope rotating slowly in FAST direction:
D/G 1 SYNCHROSCOPE SLOWLY IN FAST SPEED CONTROL lA-A SWITCH HS-82-13 I XI-82-l
[__DIRECTION 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 EA-82-1 PLACING DIGs IN STANDBY I Rev. 2 1,2 PagelOoflE 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 synchroscope 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 SYNCHROSCOPE DIG OUTPUT CLOSEDI IA-A Xl-82-1 1-HS-57-46A LI lB-B XI-82-31 1-HS-57-73A LI 2A-A Xl-82-61 2-HS-57-46A LI 2B-B Xl-82-91 2-HS-57-73A LI
- 7. ADJUST selected D/G SPEED CONTROL switch to raise D/G MW load to 1 .6 MW:
SPEED CONTROL D/G SWITCH DIG MEGAWATTS 1.6 MW q lA-A HS-82-13 El-82-1OA LI 13-B HS-82-43 El-82-40A LI 2A-A HS-82-73 El-82-70A LI 2B-B HS-82-103 EI-82-100A LI
- 8. MAINTAIN +1 MVAR (OUT) for selected D/G, WHILE paralleled with offsite power:
D/G VOLTAGE D/G REGULATOR SWITCH DIG MEGAVARS +1 MVAR I lA-A HS-82-12 EI-82-llA LI lB-B HS-82-42 EI-82-41A LI 2A-A HS-82-72 EI-82-71A LI 2B-B HS-82-102 El-82-1OIA LI
[ SQN PLACING DIGs IN STANDBY Rev. 2 1,2 Pagellofl6 4.3 Purging DiG Combustibles (Continued)
- 9. DISPATCH an AUO to selected D/G building to monitor stack exhaust WHILE loading selected DIG. El
- 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 DIG loading UNTIL condition clears. LI
- 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/G load at 4.0 MW El AND
- Stack exhaust NORMAL. El
- 11. ADJUST selected D/G SPEED CONTROL switch to lower D/G MW load to 0.5 MW:
D/G CONTROL SWITCH_[ 0.5 MW
[_SPEED lA-A HS-82-13 Li I B-B HS-82-43 [1 2A-A HS-82-73 Li 2B-B HS-82-103 Li
SQN EA-82-l PLACING DIGs IN STANDBY Rev. 2 1,2 Pagel2ofle 4.3 Purging DIG Combustibles (Continued)
- 12. ADJUST selected DIG VOLTAGE REGULATOR switch to lower D/G MVAR load to zero:
DIG DIG VOLTAGE DIG MEGAVARS OMVAR/
REGULATOR SWITCH lA-A HS-82-12 EI-82-1IA L]
lB-B HS-82-42 EI-82-41A LI 2A-A HS-82-72 EI-82-71A LI 2B-B HS-82-102 EI-82-1O1A LI
- 13. PLACE selected D/G output breaker control switch to TRIP:
DIG D/G OUTPUT BREAKER TRIPPED lA-A l-HS-57-46A LI lB-B 1-HS-57-73A LI 2A-A 2-HS-57-46A LI 2B-B 2-HS-57-73A LI
- 14. GO TO Section 4.4 to shut down D/G.
END OF SECTION
[
- SQN PLACING DIGs IN STANDBY Rev. 2
- 1,2 Pagel3ofl6 4.4 Shutting Down DIG
- 1. VERIFY selected D/G unloaded with output breaker open:
D/G OUTPUT BREAKER UNLOADED & OUTPUT DiG BREAKER HANDSWITCH BREAKER OPEN I lA-A 1912 1-HS-54-46A LI lB-B 1914 1-HS-57-73A LI 2A-A 1922 2-HS-54-46A LI 2B-B 1924 2-HS-57-73A LI
- 2. PLACE selected D/G(s) CONTROL START-STOP switch to STOP:
DIG CONTROL DIG STOPq START-STOP SWITCH lA-A HS-82-14 El 1 B-B HS-82-44 LI 2A-A HS-82-74 Li 2B-B HS-82-104 LI
- 3. WHEN selected D/G(s) has run at idle speed (400 rpm) for 10 minutes, THEN VERIFY D/G shuts down and speed drops to zero:
DIG ZERO RPM lA-A LI lB-B LI 2A-A LI 2B-B LI
4.4 Shutting Down D/G (Continued)
- 4. ENSURE selected DIG MODE SELECTOR switch in PUSH IN UNIT position:
DIG lA-A
[ MODE SELECTOR SWITCH 1-HS-82-18 1PUSH IN UNIT LI lB-B l-HS-82-48 LI 2A-A 2-HS-82-78 El 2B-B 2-HS-82-108 El
- 5. ENSURE selected D/G SYNCHRONIZE switch is in OFF:
D/G lA-A
[ SYNCHRONIZE SWITCH 1-HS-57-47 OFF i El lB-B 1-HS-57-74 LI 2A-A 2-HS-57-47 LI 2B-B 2-HS-57-74 El
[ SQN 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:
D/G
[ ERCW TO D/G HEAT EXCHANGERS CLOSED q IA-A 1-HS-67-66A LI 1-HS-67-68A LI lB-B 1-HS-67-67A LI l-HS-67-65A LI 2A-A 2-HS--67-66A LI 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 Pagel6oflG
5.0 REFERENCES
None.
JPM Sim Alt A Page 1 of 10 Rev. 0 SEQUOYAH NUCLEAR PLANT September 2010 NRC Exam SIM ALT A (ROSRO)
Rod Control Urgent Failure Alarm During Reactor Startup to I % Power
JPM Sim Alt A Page 2 of 10 Rev. 0 ROISRO JOB PERFORMANCE MEASURE Task: Operate the Control Rod Drive System to bring the reactor critical. Then, raise power to I % RTP JA/TAtask# 0010190101 ROISRO Task Standard: Respond to Rod Control System Urgent Failure diromg Reactor Startup Time Critical Task: YES: NO: X KIA Ratings: OO1A1 .06 (4.114.4) 001A2.1 4 (3.7/3.9)
Method of Testinci:
Simulated Performance: Actual Performance: X Evaluation Method:
Simulator X In-Plant Classroom Main Control Room Mock-up Performer:
Trainee Name Evaluator: /
Name I Signature Performance Rating: SAT: UNSAT:
Validation Time: 8 minutes Total Time:
Performance Time: Start Time: Finish Time:
COMMENTS
JPM Sim Alt A Page 3 of 10 Rev. 0 SPECIAL INSTRUCTIONS TO EVALUATOR:
- 1. Critical steps are identified in step SAT/UNSAT column by bold print Critical Step.
- 2. Task should begin at the Simulator.
- 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.
- 4. Reset the simulator to IC 187 and ensure the following is inserted and linked to KEY I
- a. AN_OV_306, Rod Control System Urgent Failure Alarm Override ON
- b. IMF RDO8 Rods Fail to Move
- 5. Place the simulator in RUN when the student assumes the shift
- 6. Insert KEY 1 at the Evaluators Cue.
Tools/Equipment/Procedures Needed:
- 1. 1-AR-M4-B Rod Control System Urgent Failure Annunciator
- 2. AOP-C.01 Rod Control System Malfunction
- 3. 0-GO-3 Power Ascension From Reactor Critical to Less Than 5% Reactor Power
REFERENCES:
Reference Title Rev No.
- 1. 1 -AR-M4-B Rod Control System Urgent Failure Annunciator 28
- 2. AOPC.01 Rod Control System Malfunction 20
- 3. 0-GO-3 Power Ascension From Reactor Critical to Less Than 5% Reactor Power 23
JPMSImAItA Page 4 of 10 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. The plant is recovering from a reactor trip.
- 2. The cause of the trip has been identified.
- 3. The Reactor is now critical at 1 .OE-3% Power. 0-GO-3, Power Ascension from Reactor Critical to less than 5 Percent Reactor Power, is in affect.
- 4. All prerequisites, precautions and limitations are met.
INITIATING CUES:
- 1. You are the OATC.
- 2. The Unit Supervisor has ordered you to perform Section 5.2 Step I of 0-GO-3, Withdraw Rods to bring the reactor power to between 1 and 2%.
- 3. Other members of the control room team will address concurrent activities associated with Section 5.2.
- 4. You are to withdraw control rods per the procedure and inform the US when reactor power is stable at 1-2%.
JPMSimAItA Page 5 of 10 Rev. 0 STEP 1.: Obtain to copy of O-GO-3. SAT UNSAT STANDARD: Obtains procedure copy; OR a copy marked-up to Section 5.2, Step 1 of O-GO-3, Withdraw Rods to bring the reactor power to between I and 2%, may be provided.
Start time COMMENTS:
Evaluator NOTE: The evaluator should cue the console operator to insert the Rod Control Urgent failure after a stable positive SUR is obtained.
STEP 2 tI] Withdraw rods to estabhsh a positive SUR and monitorfor SAT proper response UNSAT STANDARD: Operator withdraws control rods using the Rod Control switch (1-HS-85-511 1) to establish a constant positive SUR of less than I DPM. Critical Step This step is critical in order to increase reactor power using rods.
COMMENTS:
Evaluator NOTE: Candidate may determine that the reactor has a positive SUR, control rods will not move and may make the determination that either:
- a. the reactor is uncontrolled and manually trips the Reactor, which meets the critical step performance requirements of Step 14, OR
JPMS1mAItA Page 6 of 10 Rev. 0 STEP 3.: Responds to annunciator for Rod Control System Urgent SAT Failure (A-6)
[1] PLACE rod control in manual. UNSAT STANDARD: Operator verifies that Rod control switch (1-HS-85-51 10) is selected to MAN.
COMMENTS:
Caution: Attempting to reset rod control urgent failure alarm using M-4 pushbutton, [1-RCAS],
prior to determing and correcting cause could result in dropped rods.
STEP 4.: [2] DISPATCH MIG personnel to MG Set Room to SAT investigate cause..
UNSAT CUE: Report as US and state that you will contact MIG STANDARD: Operator contacts MIG to investigate cause of alarm.
COMMENTS:
STEP 5.: [3] NOTIFY MIG to document, in Work Order, the status of SAT the lights on and in the affected power and logic cabinet(s).
U NSAT CUE: Report as US and state that you will contact MIG STANDARD: Operator contacts MIG to investigate cause of alarm.
COMMENTS:
JPM Sim Alt A Page 7 of 10 Rev. 0 STEP 6.: [4] WHEN rod control urgent failure is in alarm, THEN SAT NOTE the following:
[a] If problem is in the Power cabinet control rods in that UNSAT cabinet will not move.
[b] If problem is in the Logic cabinet no rods will move.
STANDARD: Operator determines that location of urgent failure is presently indeterminate and proceeds to step 5.
COMMENTS:
STEP 7.: [5] IF alarm is unexpected, THEN GO TO AOP-C.O1, Rod SAT Control System Malfunctions.
UNSAT STANDARD: Operator recognizes alarm as unexpected and transitions to AOP-C.O1.
COMMENTS:
Evaluator_Note: The_following_starts_the_steps_of AOP-C.O1 STEP 8.: Implement AOP-C.O1, Section 2.5 for Rod Control System Urgent Failure Alarm. SAT UNSAT STANDARD: Operator implements AOP-C.O1.
COMMENTS:
JPM Sim Alt A Page 8 of 10 Rev. 0 STEP 9.: [1] DIAGNOSE the failure: _SAT ROD CONTROL SYSTEM URGENT FAILURE alarm UNSAT LIT [M-4B window A-6]
STANDARD: Operator verifies M-4B, Window A-6 LIT and transitions to Sect 2.5, of AOP-C.01.
COMMENTS:
Caution 1: Control Rods should NOT be manually withdrawn during a transient Caution 2: Attempting to move control rods with ROD CONTROL SYSTEM URGENT FAILURE alarm could result in dropped or misaligned rods.
Caution 3: Depressing ROD URGENT FAILURE RESET pushbutton on M-4 prior to determining and_correcting_cause_could_result_in_dropped_rods.
STEP 10.: 2.5.1 CHECK ROD CONTROL SYSTEM URGENT FAILURE alarm LIT [M-4B window A-6]:
U NSAT STANDARD: Operator verifies M-4B, Window A-6 LIT.
COMMENTS:
STEP 11.: 2.5.2 DETERMINE if rod control should be placed in SAT MANUAL:
UNSAT STANDARD: Operator verifies Rods are still in Manual.
COMMENTS:
JPMSimAItA Page 9 of 10 Rev. 0 STEP 12.: 2.5.3 CONTROL T-avg within 3°F of Tref by performing one _SAT of the following:
- ADJUST turbine load UNSAT
- ADJUST RCS boron concentration USING O-SO-62-7 STANDARD: Operator determines that Tavg is within 3°F of Tref.
COMMENTS:
STEP 13.: 2.5.4 MONITOR the following parameters STABLE or SAT CONTROLLED:
- Reactor power UNSAT
- T-avg STANDARD: Operator determines that reactor power is increasing and is not controlled and goes to RNO column.
COMMENTS:
STEP 14.: 2.5.4 IF unconfrofled transient is in progress AND control SAT rods CANNOT be moved, THEN TRIP reactor and GO to E-O, Reactor Trip or Safety Injection. UNSAT STANDARD: Operator determines that uncontrolled transient is in progress and manually trips Reactor.
Critical Task This step is critical to terminate the power increase and place the reactor in a Stop time safe shut down mode.
COMMENTS:
CUE: This completes the JPM 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. The plant is recovering from a reactor trip.
- 2. The cause of the trip has been identified.
- 3. The Reactor is now critical at I .OE-3% Power. O-GO-3, Power Ascension from Reactor Critical to less than 5 Percent Reactor Power is in affect.
- 4. All prerequisites, precautions and limitations are met.
INITIATING CUES:
- 1. You are the OATC.
- 2. The Unit Supervisor has ordered you to perform Section 5.2 Step I of O-GO-3, Withdraw Rods to bring the reactor power to between I and 2%.
- 3. Other members of the control room team will address concurrent activities associated with Section 5.2.
- 4. You are to withdraw control rods per the procedure and inform the US when reactor power is stable at 1-2%.
Sequoyah Nuclear Plant Unit I & 2 General Operating Instructions O-GO-3 L TO LESS THAN 5 POWER ASCENSION FROM REACTOR CRITICA PERCENT REACTOR POWER Revision 0023 Quality Related Level of Use: Continuous Use Effective Date: 03-29-2010 Responsible Organization: OPS, Operations Prepared By: W. T. Leary Approved By: A. S. Bergeron Current Revision Description Low Power Operations (09000300, PER Added Precaution in response to SOER 07-01 rdance with the guidance presented in 164672). This is an administrative change in acco SPP-2.2.
SQN POWER ASCENSION FROM REACTOR 0-GO-3 Unit I & 2 CRiTICAL TO LESS THAN 5 PERCENT Rev. 0023 REACTOR POWER Page 2 of 28 Table of Contents
1.0 INTRODUCTION
3 1.1 Purpose 3 1.2 Scope 3
2.0 REFERENCES
3 2.1 Performance References 3 2.2 Developmental References 4 3.0 PRECAUTIONS AND LIMITATIONS 5 3.1 Precautions 5 3.2 Limitations 7 4.0 PREREQUISITES 8 5.0 INSTRUCTIONS 10 5.1 Actions To Be Performed Prior To Increasing Reactor Power 10 5.2 Power Ascension To Approximately 1% RTP 12 5.3 Transferring Feedwater From Auxiliary To Main Feedwater 20 6.0 RECORDS 27 Source Notes 28 ATTACHMENTS Attachment 1: Procedure Checklist
SQN POWER ASCENSION FROM REACTOR 0-GO-3 Unit I & 2 CRITICAL TO LESS THAN 5 PERCENT Rev. 0023 REACTOR POWER Page 3 of 28
1.0 INTRODUCTION
1.1 Purpose instructions to raise This General Operating (GO) Instruction provides necessary and to transition from reactor power to approximately 1% for main feed pump startup valves in AUTO.
auxiliary feedwater to main feedwater with the MFW Bypass 1.2 Scope A. This GO contains the following sections:
- 1. 5.1 Actions To Be Performed Prior To Increasing Reactor Power
- 2. 5.2 Power Ascension To Approximately 1 % RTP ater
- 3. 5.3 Transferring Feedwater From Auxiliary To Main Feedw
2.0 REFERENCES
2.1 Performance References A. 0-SO-i -2, Steam Dump System B. 1 ,2-SO-1 5-1 ,2, Steam Generator Blowdown Reheaters C. 1,2-SO-S-i, Feedwafer Heaters and Moisture Separator D. 1 ,2-SO-5-2, No. 3 Heater Drain Tank and Pumps E. 1 ,2-SO-5-3, No. 7 Heater Drain Tank and Pumps and Pumps F. 1 ,2-SO-5-4, Feedwater Turbine Condenser Drain Tank Pumps G. 1 ,2-SO-5-5, Atmospheric Condensate Drain Sump and H. 1 ,2-SO-213-1, Condensate and Feedwater System I. 1 ,2-SO-3-2, Auxiliary Feedwater System J. 1 ,2-SO-1 -1, Main Steam System K. Ml-20.154 Controller Tuning Instruction L. 1 ,2-SI-OPS-000-002.0, Shift Log M. 0-RT-NUC-000-001.0, Restart Test Program
SQN POWER ASCENSION FROM REACTOR 0-GO-3 Unit I & 2 CRITICAL TO LESS THAN 5 PERCENT Rev. 0023 REACTOR POWER Page 4 of 28 2.1 Performance References (continued)
N. 0-Pl-OPS-000-00i .0, Initial Startup System Parameter Log
- 0. 2-S0-98-1, Distributed Control System (DCS) 2.2 - Developmental References A. 0-GO-i, Unit Startup from Cold Shutdown to Hot Standby B. 0-GO-4, Power Ascension from Less Than 5% Reactor Power to 30% Reactor Power C. SPP-2.2 D. FSAR Section 13.5
- SQN POWER ASCENSION FROM REACTOR 0-GO-3 Unit I & 2 CRITICAL TO LESS THAN 5 PERCENT Rev. 0023 REACTOR POWER Page 5 of 28 3.0 PRECAUTIONS AND LIMITATIONS 3.1 Precautions ng A. Reactor Engineering should be contacted for guidance on core operati as startup during end recommendations during unusual power maneuvers such
. of core life. [C.5J
- 8. Reactor power should be monitored using the following indications:
- 1. Average loop AT (U0485). Considered to be the most accurate power g
indication when less than 15% power but greater than Point of Addin Heat.
- 2. Intermediate Range lndicators(used at or below Point of Adding Heat
- 3. NlSpowerrange.
- 4. Steam dump demand. (REFER TO graph in 0-SO-1-2).
NOTE d, to maintain pressurizer and Pressurizer heaters and sprays may be operated, as require RCS boron concentration within 50 ppm.
ined within 50 ppm C. The boron concentration in the pressurizer should be mainta of the RCS by use of pressurizer heaters and spray.
levels below
- 0. Control rod bank D should be 165 steps at steady state power on at less than 165 85% RTP. This guidance is to preclude long term operati Short term steps to avoid potential impact on safety analysis assumptions.
operation at less than 165 steps is NOT a concern. - -
(3.3.2)
E. The AFW start function for trip of both MEW pumps ([CO 3.3.2.1 MFP trip bus is functional unit 6.f) shall be considered INOPERABLE when any ng forward.
DE-ENERGIZED OR when any MFP is RESET but is NOT pumpi
[C.6]
trip busses F. The AFW start function is required to be operable (both MFWP ng forward with the energized with non-running pump TRIPPED) prior to pumpi be invoked due to first MFW pump. The only exception is if [CO 3.0.4 (b) can
-91 1.0) one MFW pump being unavailable. (Refer to 0-Tl-OPS-000
SQN POWER ASCENSION FROM REACTOR 0-GO-3 Unit I & 2 CRITICAL TO LESS THAN 5 PERCENT Rev. 0023 REACTOR POWER Page 6 of 28 3.1 Precautions (continued)
G. Prolonged operation at low power levels (less than 5%) is highly discouraged since Xenon changes from any source may challenge reactivity control.
Reactor Engineering and Plant Management should be consulted prior to maintaining the reactor critical at low power levels. Detailed, updated reactivity plans, management oversight, just-in-time training and a review of in progress WO for potential impact on the duration of operation in Mode 2 should be implemented prior to planned operation at low power levels. Expected Xenon changes must be clearly understood and preplanned guidance (including trip criteria) should be established for controlling reactivity with special consideration for EOL or when Xenon is not stable. Control Room distractions shall be minimized during low power operations. Reactor Protection System automatic actuations are impacted by low power operations. (IN P0 SOER 07-01)
SQN POWER ASCENSION FROM REACTOR 0-GO-3 Unit I & 2 CRITICAL TO LESS THAN 5 PERCENT Rev. 0023 REACTOR POWER Page 7 of 28 3.2 Limitations A. Do NOT exceed a steady startup rate of + 1 DPM.
B. After refueling operations, the NIS indications may be inaccurate until calibration at higher power levels. The NIS calibration procedures will adjust the PRM trip setpoints to ensure that the excore detectors do NOT contribute to an overpower condition. Prior to startup, the PRM high range flux trip setpoint will be adjusted from 109 to 60%, with the rod stop (C-2) remaining at 103%.
[C.2]
C. If fuel defects are present, Preconditioned Power Levels and Maximum Allowable Rates of Power Increase specified in Tl-40, Determination of Preconditioned Reactor Power shall apply.
SQN POWER ASCENSION FROM REACTOR 0-GO-3 Unit I & 2 CRITICAL TO LESS THAN 5 PERCENT Rev. 0023 REACTOR POWER Page 8 of 28 Startup Number_______ Unit I Date 4.0 PREREQUISITES Thughout this InsucUonwher ment exists, the step should be Prerequisites may be completed in any order.
?ITh1s instruction may be entered from a partial shutdown, NIA sections NOT applicable and annotate reason.
)
7 (9j ENSURE Instruction to be used is the latest copy of effective version.
ENSURE Precautions and Limitations have been reviewed.
ENSURE main steam system aligned with MSIVs open in accordance with 1, 2-SO-i-i.
ENSURE the reactor is critical with power at approximately 1 X i0%.
MAiNTAIN pressurizer pressure within the normal operating band by use of the pressurizer heaters and spray valves.
MAINTAIN pressurizer level greater than or equal to 25%.
0 Due to instrument inaccuracies the steam dump or SG atmospheric relief valve setpoint of 84% or 1005 psig may be +/- 1% or +/- 12 psig off.
MAINTAIN TAVG stable with the steam dumps in pressure mode or with the SG atmospheric relief valves set at 84%
or -005 psig.
MAINTAIN SG levels within the normal operating range using Auxiliary Feedwater.
During start up after a cold shutdown tate DI normally will be aligned for full flow polishing until the MSRs are in service.
,{NSLJRE Condensate DI polishing operation in accordance with RCL recommendations.
SQN POWER ASCENSION FROM REACTOR O-GO-3 Unit I & 2 CRITICAL TO LESS THAN 5 PERCENT Rev. 0023 REACTOR POWER Page 9 of 28 Date 1 4Q L Startup Number Xx ) Unit 4.0 PREREQUiSITES (continued) and initials:
[10] ENSURE each performer documents their name Initials Print Name Initials Print Name ioe, End of Section
SQN POWER ASCENSION FROM REACTOR 0-GO-3 Unit I & 2 CRITICAL TO LESS THAN 5 PERCENT Rev. 0023 REACTOR POWER Page 10 of 28 Startup NumberX4Y Unit Date INSTRUCTIONS
Steps of this procedure must be pe resequentially, unless specifically stated otherwise.
Actions To Be Performed Prior To Increasing Reactor Power ENSURE Section 4.0, Prerequisites complete. b(.
4 Steps 5.1[2j through 5.1[71 may be performed in any order.
ENSURE two Hotwell pumps in service in accordance with 1,2-SO-2/3-1.
/1r ENSURE one condensate booster pump in service in accordance with 1, 2-SO-2/3-1.
I The potential exists for condensation f.Tn in steam extraction lines when heaters are isolated.
feedwater ions as approved Step 5.1[4] may be performed out of later) due to plant condit by the SM.
NSURE seconda plant is aligned for starfup in accordance with the following:
INSTRUCTIONS INITIALS ers t13 1 ,2-SO-5-1, Feedwater Heaters and Moisture Separator Reheat YI 1 ,2-SO-5-2, No. 3 Heater Drain Tank and Pumps 1 ,2-SO-5-3, No. 7 Heater Drain Tank and Pumps P 4
- c. 0 1 ,2-SO-5--4, Feedwater Turbine Condenser Drain Tank and Pumps 1 ,2-SO-5-5, Atmospheric Condensate Drain Sump and Pumps
-3 SQN POWER ASCENSION FROM REACTOR 0-GO Unit I & 2 CRITICAL TO LESS THAN 5 PERCENT Rev. 0023 REACTOR POWER Page 11 of 28 Unit Date Startup Number_______
Reactor Power 5.1 Actions To Be Performed Prior To Increasing (continued) ed in parallel with power ascension to Steps to prepare for MFPT startup mayrm 1-2%.
IF any MFPT trip buss is NOT energized, THEN REFER to 0-TI-OPS-000-91 1.0, Instructions for using TS!TR 3.0.4 (b).
US!SRO that no MFWP may be placed in 5NOTservi IFY ce UNLESS [CO 3.0.4 (b) can be invoked.
N MFPT designated for startup is available, THE Feedwater PERFORM 1, 2-SO-2/3-1, Preparation of Main U
)
Pumps for Startup. (N/A if previously performed
)
IF startup is on Unit 2, AND in service, Secondary System Boric Acid Injection has been THEN ce in ENSURE System has been removed from servi ndar y Syst em Boric Acid accordance with 0-S0-36-3, Seco Injection. /
End of Section
SQN POWER ASCENSION FROM REACTOR 0-GO-3 Unit I & 2 CRITICAL TO LESS THAN 5 PERCENT Rev. 0023 REACTOR POWER Page 12 of 28 Startup Number )SY Unit Date 5.2 Power Ascension To Approximately 1% RTP Th -
ion below Average loop AT (U0485) is considered to be the most accurate power indicat at or below 15% power but greater than the Point of Adding Heat. IRM should be used deman d should also be Point of Adding Heat. NIS power range and steam dump monitored. (Refer to 0-SO-i -2 for steam dump demand program.) [C.3]
[1) WITHDRAW RODS OR DILUTE to bring reactor power to between 1 and 2% RIP, while continuing with this instruction. D NOTE performed during After refueling operations the Initial Startup System Parameter Log is level power escalations to provide the operator with alternate indications of power cant differe nces occur (indications independent of calorimetric calculations). If signifi should be notified.
(approx. 5%) between the alternate power indications then Engineering
[21 IF startup is after a refueling or maintenance on NIS, THEN -
INITIATE performance of 0-Pl-OPS-000-OOi .0, Initial Startup System Parameter Log. [C.3]
[3) COMPARE NIS power range instrumentation with loop AT indicators and steam dump demand to evaluate accuracy of D
PRMs. [C.3]
[41 SELECT the highest reading IRM or Al and PRM channels to be recorded on NR 45. [C.3]
[5) REVIEW plant parameters and indications to determine plant D
stability prior to startup of Main Feed Pump.
El
[6] MAINTAIN reactor power approximately 1%.
SQN POWER ASCENSION FROM REACTOR 0-GO-3 Unit I & 2 CRITICAL TO LESS THAN 5 PERCENT Rev. 0023 REACTOR POWER Page 13 of 28 Startup Number________ Unit Date 5.2 Power Ascension To Approximately 1% RTP (continued)
NOTE Steps 5.2[71 and 5.2[8] may be performed in any order.
[1 WHEN total Aux FW flow to SGs 1 and 2 is constant and greater than or equal to 300 gpm, THEN CLOSE fFCV-3-40O), AFW PUMP A RECIRC ISOL VLV, and PLACE handswitch [HS-3-400A1 in the PULL TO LOCK position.
1 St IV
[8] WHEN total Aux FW flow to SGs 3 and 4 is constant and greater than or equal to 300 gpm, THEN CLOSE [FCV-3-4011, AFW PUMP B RECIRC ISOL VLV, and PLACE handswitch IHS-3-401A1 in the PULL TO LOCK position.
1 st IV NOTE levels below 85% RTP.
Control rod bank D should be 165 steps at steady state power to avoid potential impact on This guidance is to preclude long term operation at < 165 steps steps is NOT a concern.
safety analysis assumptions. Short term operation at < 165
[9] ENSURE the plant is stabilized between 1 and 2% reactor
[1 power. [C.I ] [C.3J
[10] COMPARE NIS intermediate range instrumentation with loop T indications to evaluate accuracy of IRMs. [C.1]
[111 RECORD IRM readings: [C.3]
N35 %RTP El N36 %RTP El
SQN POWER ASCENSION FROM REACTOR O-GO-3 Unit I & 2 CRITICAL TO LESS THAN 5 PERCENT Rev. 0023 REACTOR POWER Page 14 of 28 Startup Number________ Unit Date 5.2 Power Ascension To Approximately 1% RTP (continued)
NOTE Step 5.2[12] may be performed out of sequence or in parallel with subsequent steps.
[12] OPEN Turbine Exhaust Hood cooling valves
[FSV-47-215A, -2158, -215Cj by placing [HS-47-2151, in ON position. [located on LP Htr Mezz]
[13] WHEN startup of the first MFPT is desired, THEN PROCEED with step 5.2[14].
NOTE The following steps ensure MFPT trip busses energized and MFPTs reset if entering from O-GO-2 with no MFPT available.
[14] ENSURE MFPT designated for startup has been tested and ready for start up per 1, 2-SO2/3-1 PRIOR to proceeding with the next step.
Initials Date Time
0-GO-3 SQN POWER ASCENSION FROM REACTOR T Rev. 0023 Unit I & 2 CRITICAL TO LESS THAN 5 PERCEN REACTOR POWER Page 15 of 28 Unit Date Startup Number________
RTP (continued) 5.2 Power Ascension To Approximately 1%
NOTE power should be placed on only ONE trip bus to If both MFPT trip busses are de-energized, prevent inadvertent AFWP start.
N
[15] IF both MFPT trip busses de-energized, THE bus on the RESTORE power to ONLY ONE MFPT trip licable.) [C.I]
applicable unit. (N/A breakers NOT app ELECTRICAL BREAKER INITIALS UNIT I BREAKER NO.
BOARD POSITION PUMP 250v DC Battery Bd I CLOSED 1st MFPT 1A 1-BKRD-46-KA1523 CV 250v DC Battery Bd I CLOSED 1st - -
MFPT lB 1-BKRD-46-KA/524 CV ELECTRICAL BREAKER INITIALS UNIT 2 BREAKER NO.
BOARD POSITION PUMP 250v DC Battery Bd 2 CLOSED 1st MFPT 2A 2-BKRD-46-KB/523 CV 250v DC -
CLOSED 1st 2-BKRD-46-KB/524 Battery Bd 2 MFPT 2B CV
SQN POWER ASCENSION FROM REACTOR 0-GO-3 Unit I & 2 CRITICAL TO LESS THAN 5 PERCENT Rev. 0023 REACTOR POWER Page 16 of 28 Startup Number________ Unit Date 5.2 Power Ascension To Approximately 1% RTP (continued)
CAUTION Failure to reset a MFPT prior to energizing the remaining MFPT trip buss will initiate an ESF actuation.
NOTE If an SI signal or a Hi/Hi steam generator level has occurred, the Reactor Trip Breakers will have to be cycled.
[16] ENSURE at least one energized MFPT trip bus is RESET.
Initials Date Time CV Date Time
[17j IF one MFW pump is NOT available, THEN PERFORM the following:
[17.1] ENSURE requirements of O-TI-OPS-000-911.O are met for using LCO 3.0.4 (b).
[17.2] MARK steps 5.2[181 and 5.2[19] as N/A.
SON POWER ASCENSION FROM REACTOR 0-GO-3 Unit I & 2 CRITICAL TO LESS THAN 5 PERCENT Rev. 0023 REACTOR POWER Page 17 of 28 Startup Number________ Unit Date 5.2 Power Ascension To Approximately 1% RTP (continued)
[18] ENSURE power to the remaining MFPT Trip Bus on the applicable unit. (N/A breakers NOT applicable)
- UNIT I BREAKER NO. ELECTRICAL BREAKER INITIALS PUMP BOARD POSITION 250v DC MFPT 1A 1-BKRD-46-KA1523 Battery Bd I CLOSED 1st CV 250v DC MFPT lB 1-BKRD-46-KA1524 Battery Bd I CLOSED 1st CV UNIT 2 BREAKER NO. ELECTRICAL BREAKER INITIALS PUMP BOARD POSITION 250v DC -
MFPT 2A 2-BKRD-46-KB/523 Battery Bd 2 CLOSED 1st CV 250v DC MFPT 2B 2BKRD-46-KB/524 Battery Bd 2 CLOSED 1st CV
[19] ENSURE second MFPT is RESET.
Initials Date Time CV Date Time
SQN POWER ASCENSION FROM REACTOR 0-GO-3 Unit I & 2 CRITICAL TO LESS THAN 5 PERCENT Rev. 0023 REACTOR POWER Page 18 of 28 Startup Number________ Unit Date 5.2 Power Ascension To Approximately 1% RTP (continued)
CAUTION The first MFW pump shall NOT be placed in service to S/Gs (pumping forward)
UNTIL second MFP is TRIPPED in Step 5.2[221. (Ref: LCO 3.3.2.1 or 3.3.2) The only exception is if LCO 3.0.4 (b) is being invoked due to non-availability of the second MFP.
[20] ENSURE the MFW Bypass valves are in MANUAL AND CLOSED. [CA]
DESCRIPTION CONTROLLER POSITION q SG-1 MFW Bypass Flow MANUAL LIC-3-35 AND El Control CLOSED SG2 MFW Bypass Flow MANUAL Control LIC-3-48 AND El CLOSED SG-3 MFW Bypass Flow MANUAL Control LIC-3-90 AND El CLOSED SG-4 MFW Bypass Flow MANUAL Control LIC-3-103 - AND El CLOSED
[21] START the first MFPT in accordance with 1, 2-50-2/3-1. El
r SQN Unit I & 2 POWER ASCENSION FROM REACTOR 0-GO-3 CRITICAL TO LESS THAN 5 PERCENT Rev. 0023 REACTOR POWER Page 19 of 28 Startup Number________ Unit Date 5.2 Power Ascension To Approximately 1% RTP (continued)
NOTE The following step will assure that a trip of the running MFP will initiate an AFW pump auto start. (Ref: TS LCO 3.3.2.1 and 3.3.2, PER 03-006930-000).
[221 IF the NON-running MFPT trip buss is energized, THEN TRIP the NON-running MFPT: (N/A the running MFPT)
MFPT HANDSWITCH INITIALS CV A HS-46-9A B HS-46-36A End of Section
SQN POWER ASCENSION FROM REACTOR 0-GO-3 Unit I & 2 CRITICAL TO LESS THAN 5 PERCENT Rev. 0023 REACTOR POWER Page 20 of 28 Startup Number________ Unit Date 5.3 Transferring Feedwater From Auxiliary To Main Feedwater
- NOTE UNIT 2 ONLY: S/G level swings will be minimized if SIG levels are near the middle of the band when starting transfer to MFW.
[lj VERIFY S!G levels between 34 and 44%. D CAUTION Anticipate a change in MFPT delta P when SG MFW Bypass valves are adjusted.
[C.4j NOTE UNIT I ONLY: The MFW Bypass valve controllers must be in MANUAL when adjusting setpoint value to prevent controller gain input change. [C.4j
[2] ENSURE the MFW Bypass valve controller setpoints are set for a level of approximately 39%. [C.4J El
SQN POWER ASCENSION FROM REACTOR 0-GO-3 Unit I & 2 CRITICAL TO LESS THAN 5 PERCENT Rev. 0023 REACTOR POWER Page 21 of 28 Startup Number________ Unit Date 5.3 Transferring Feedwater From Auxiliary To Main Feedwater (continued)
CAUTION DO NOT increase reactor power above 2% until MFW Bypass valves are in control of SG level and Auxiliary Feedwater is shutdown.
NOTES
- 1) Review plant parameters and indications to verify plant stability prior to transfer of AFW [CV to its associated MEW Bypass valve.
- 2) Transfer to only one MFW Bypass valve at a time. Stable level control shall be achieved in each steam generator before placing another MFW Bypass valve in AUTO. Stable level control is defined as a stable oscillation of less than or equal to 5%
or an oscillation that is decreasing.
- 3) The SG level operator is in control of unit startup until the MEW Reg. valves are in AUTO. [C.4j
[3] PERFORM the following to transfer the SG level control from theAFW LCVs to the MEW Bypass valves:
SG-1 SG-2 SG-3 SG-4
[a] PLACE the MEW Bypass valve controller in the AUTO position. LI LI LI LI
[bj SLOWLY DECREASE AEW flow to the associated SG to ZERO gpm. LI LI LI LI
[cj WHEN total AEW flow to both SGs is less than 300 gpm, THEN ENSURE AEW PUMP RECIRC ISOL valves are LI OPEN
[d] ALLOW SG level to stabilize. LI LI LI LI
[e] WHEN MEW Bypass valve is controlling SG level, THEN PROCEED TO another SG loop LI LI LI LI
SQN POWER ASCENSION FROM REACTOR 0-GO-3 Unit I & 2 CRITICAL TO LESS THAN 5 PERCENT Rev. 0023 REACTOR POWER Page 22 of 28 Startup Number________ Unit Date 5.3 Transferring Feedwater From Auxiliary To Main Feedwater (continued)
[4j IF SG level oscillations occur, THEN PERFORM the following to dampen the oscillations during SG level control with the MFW Bypass in AUTO, (N/A if NOT required):
SG-I SG-2 SG-3 SG-4
[a] PLACE the MFW Bypass valve controller in MANUAL. U U U U
[b] ADJUST valve output to less than 10% in the opposite U U U U direction of valve travel.
[ci PLACE the MFW Bypass valve controller in AUTO. U U U U NOTE If MFW Bypass valves do NOT control properly in AUTO, then unit startup shall NOT continue until corrective actions have been taken to allow proper operation of the MFW Bypass controllers in AUTO unless waived by Plant Manager.
[5] IF the MFW Bypass is NOT operating properly in AUTO, THEN STABILIZE plant conditions and NOTIFY the SM for corrective actions. [C.4]
Initials Date Time
SQN POWER ASCENSION FROM REACTOR 0-00-3 Unit I & 2 CRITICAL TO LESS THAN 5 PERCENT Rev. 0023 REACTOR POWER Page 23 of 28 Startup Number________ Unit Date 53 Transferring Feedwater From Auxiliary To Main Feedwater (continued)
[6] WHEN #1 and 2 SG MFW Bypass valves are in AUTO and SG levels have stabilized, THEN PERFORM the following steps (Steps may be performed later if unstable conditions exist or if the SM prefers to maintain the MDAFW pump A-A on recirc):
[6.1] ENSURE AFW flow to SG #1 and 2 is ZERO.
[6.2] ENSURE #1 and 2 SG levels are stable.
[6.3] STOP MDAFW pump A-A.
[6.4] PLACE MDAFW pump A-A in A-P AUTO.
1st IV
[6.5] ENSURE #1 and 2 SG levels remain stable.
[6.6] PLACE LCV-3-164 in AUTO.
1st IV
[6.7] PLACE LCV-3-156 in AUTO.
1 St IV
[6.8] CLOSE [FCV-3-400I, AFW PUMP A RECIRC ISOL VLV with [HS-3-400A1.
1st IV
[6.9) PLACE IHS-3-400A1, AFW PUMP A RECIRC ISOL VLV handswitch to the PULL TO LOCK position.
I St IV
SQN POWER ASCENSION FROM REACTOR 0-GO-3 Unit I & 2 CRITICAL TO LESS THAN 5 PERCENT Rev. 0023 REACTOR POWER Page 24 of 28 Startup Number Unit Date 5.3 Transferring Feedwater From Auxiliary To Main Feedwater (continued)
[7] WHEN #3 and 4 SG MFW Bypass valves are in AUTO and SG levels have stabilized, THEN PERFORM the following steps (Steps may be performed later if unstable conditions exist or if the SM prefers to maintain the MDAFW pump B-B on recirc):
[7.1] ENSURE AFW flow to SG #3 and 4 is ZERO.
[7.2] ENSURE #3 and 4 SG levels are stable.
[7.3] STOP MDAFW pump B-B.
[7.4] PLACE MDAFW pump B-B in A-P AUTO.
1st
[7.5] ENSURE #3 and 4 SG levels remain stable.
[7.6] PLACE LCV-3-148 in AUTO.
1 St IV
[7.7] PLACE LCV-3-171 in AUTO.
1st lv
[7.8] CLOSE IFCV-3-4011, AFW PUMP B RECIRC ISOL VLV with jHS-3-401A].
1st lv
[7.9] PLACE IHS-3-401A1, AFW PUMP B RECIRC ISOL VLV handswitch to the PULL TO LOCK position.
1 st IV
F SQN Unit I & 2 POWER ASCENSION FROM REACTOR 0-GO-3 CRITICAL TO LESS THAN 5 PERCENT Rev. 0023 REACTOR POWER Page 25 of 28 Startup Number________ Unit Date 5.3 Transferring Feedwater From Auxiliary To Main Feedwater (continued)
[8] VERIFY the following:
A. SG levels stabilized between 34 and 44%. C B. Reactor power stabilized between 1 and 2%. C C. Main Feed Pump in AUTO. C D. MFW Bypass valves in AUTO (N/A if waived by plant manager or designee.). C
[9] VERIFY all motor driven AFW [CV controllers in AUTO.
Initials Date Time IV Date Time
[101 VERIFY all turbine driven AFW [CV controllers in NORMAL.
Initials Date Time IV Date Time NOTE Unit I Only All four MFW Bypass valves shall be in AUTO and reactor power less than 2% prior to performing the next step.
[11] Unit I Only:
IF fine tune of MFW Bypass level controllers is required, THEN REQUEST I&C to perform Ml-20.1 54 Controller Tuning Instruction. C
SQN POWER ASCENSION FROM REACTOR 0-GO-3 Unit I & 2 CRITICAL TO LESS THAN 5 PERCENT Rev. 0023 REACTOR POWER Page 26 of 28 Startup Number________ Unit Date 5.3 Transferring Feedwater From Auxiliary To Main Feedwater (continued)
CAUTION After refueling operation, the NIS indications may be inaccurate until calibration at higher power levels has been performed. Reactor power shall NOT be allowed to exceed 4%
prior to the verification of the proper (or conservative) IR and PR setpoints. [C.2]
[12] MAiNTAiN reactor power greater than 1% and less than or equal to 4%. EJ
[13] CONTACT Reactor Engineering to determine if 0-Fl-N UC-092-082 should be performed prior to exceeding 4%
reactor power. U
[14] IF initial restart after refueling and a low power flux map is required, THEN PERFORM applicable portions of the low power physics testing in accordance with 0-RT-NUC-000-001 .0, Restart Test - -
Program.
Reactor Date Time Engineering
[15] IF power escalation is desired, THEN GO TO 0-GO-4, Power Ascension From Less Than 5%
Reactor Power To 30% Reactor Power.
[16] IF Unit shutdown is desired, THEN GO TO 0-GO-6, Power Reduction From 30% Reactor Power To Hot Standby.
End of Section
SQN POWER ASCENSION FROM REACTOR 0-GO-3 Unit I & 2 CRITICAL TO LESS THAN 5 PERCENT Rev. 0023 REACTOR POWER Page 27 of 28 6.0 RECORDS Completed copies shall be transmitted to the Operations Superintendents Secretary.
SQN POWER ASCENSION FROM REACTOR 0-GO-3 Unit I & 2 CRITICAL TO LESS THAN 5 PERCENT Rev. 0023 REACTOR POWER Page 28 of 28 Source Notes (Page 1 of 1)
Implementing Requirements Statement Source Document Statement Revise GOl-2 to require verification of IR NCO 890118002 C.1 status at approximately 20 and 25 percent, LER 328/89006S53 verify source range (SR) status and channel 890531 844JRB to NRC check at lower power, monitor core delta Ts at low-power levels and during power escalation and compare with NIS response and verify that the IR rod stop and trip bistables come in at the appropriate power level during power ascension.
Following refueling operations relocation of SOER-90-003 C.2 NIS or modifications affecting the NIS NCO 900107009 response, provide adequate reductions of trip NER 1187001 setpoint and limitations of reactor power until LER 327/90011 Ri accuracy of the NIS is verified. Also provide alternate indications of power independent of calorimetric calculations during power ascensions.
INPO SER on miscalibration of NIS Power SER 89-OO9NER 890252 C.3 Range detectors Revise GOl-2 prior to restarting Unit 2 to LER 328/89005 C.4 incorporate industry Feedwater startup RIMS S53 890512 811 experience, add guidelines for each crew RIMS L44 890505 805 member, control the use of manual bypass control, add cautionary statements prior to important feedwater evolutions, and add hardware operability requirements for important feedwater evolutions.
Consult Reactor Engineering for guidance NER 89 07940ER 89 3497 C.5 during evolutions of unusual power maneuvers at end of core life. -
Ensure MFWP trip bus energized before LER 328/88-014 C.6 entry into Mode 2. (This commitment transferred from -0G0-2 and modified as a result of TSC 08-05.)
6 (A-6)
Source SER 306 ROD CONTROL Logic Cabinet: SYSTEM
- 1. Card removed. URGENT
- 2. Pulser did not pulse. FAI LU RE
- 3. Slave cycler received go signal while in cycle.
Power Cabinet:
- 1. Phase failure.
- 2. Regulation failure.
- 3. Logic error.
- 4. Multiplexing error.
- 5. Card removed.
- 6. Reactor trip breaker open.
- 7. Loss of power to MG sets.
Probable 1. Blown fuse or component failure.
Causes 2. Reactor trip breakers open.
- 3. Loss of power to MG sets.
- 4. Rod testing (e.g. 0-Sl-OPS-085-01 1.0 or low power physics testing).
- 5. Misaligned I dropped rod recovery.
Corrective [1] PLACE rod control in manual.
Actions CAUTION Attempting to reset rod control urgent failure alarm using M-4 pushbutton, [1-RCAS1, prior to determining and correcting cause could result in dropped rods.
[2] DISPATCH MIG personnel to MG Set Room to investigate cause.
CORRECTIVE ACTIONS CONTINUED ON NEXT PAGE SQN l-AR-M4-B Page 9 of 46 I Rev. 28
6 (A-6)
ROD CONTROL SYSTEM URGENT FAILURE NOTE The table below provides information on Control Rod Bank power supplies.
Bank Group Power Cabinet # of Rods Core Location CntrlA 1 1AC 2 H-6, H-b 2 2AC 2 F-8, K-8 Cntrl B I 1BD 4 F-2, P-6. B-b, K-14 2 2BD 4 K-2, B-6, P-b, F-14 Cntrl C 1 1AC 4 H-2, P-8, B-8, H-14 2 2AC 4 K-6, F-6, K-iC, F-iC Cntrt D 1 1BD 4 M-4, D-4, M-12, D-12 2 2BD 5 H-4, M-8, H-8, D-8, H-12 SDA 1 lAO 4 E-5. L-5, B-il, L-l1 2 2AC 4 M-2, B-4, P-12, D-14 SD B 1 1BD 4 G-3, C-9, J-13, N-7 2 2BD 4 J-3, N-9, G-13, C-7 SD C 1 SCD 4 E-3, C-il, L-13, N-5 SD D 1 SCD 4 C-5, E-13, N-il, L-3 Corrective Actions [3) NOTIFY MIG to document, in Work Order, the status of the lights (Continued) on and in the affected power and logic cabinet(s).
[4) WHEN rod control urgent failure is in alarm, THEN NOTE the following:
[a) If problem is in the Power cabinet control rods in that cabinet will not move.
[b) If problem is in the Logic cabinet no rods will move.
[5] IF alarm is unexpected, THEN GO TO AOP-C.Oi, Rod Control System Malfunctions.
[6] MONITOR Plant Computer Rod Insertion Limit Display for abnormalities.
[7) EVALUATE Technical Specifications (3.1.3.1).
References 45B655-04B-O SQN 1-AR-M4-B Page 10 of 46 I Rev. 28
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT AOl PROGRAM MANUAL ABNORMAL OPERATING PROCEDURES AOP-C.O1 ROD CONTROL SYSTEM MALFUNCTIONS Revision 20 QUALITY RELATED PREPARED/PROOFREAD BY: D. A. PORTER RESPONSIBLE ORGANIZATION: OPERATIONS APPROVED BY: J. K. WILKES EFFECTIVE DATE: 4/2/2009 REVISION DESCRIPTION: Revised Section 2.4 to address dropped rods in Modes 3-5.
Modified Sect. 2.2 (Dropped Rod) to address Mode 1 or 2 only.
This is a corrective action for PER 156870.
THiS PROCEDURE IMPACTS REACTIVITY
AOP-C.01 SON ROD CONTROL SYSTEM MALFUNCTIONS Rev. 20 1.0 PURPOSE This procedure provides the actions necessary to mitigate the effects of the following:
.. Failure of a control bank to move when required
- Uncontrolled rod bank movement
- Dropped rod(s)
- Misaligned control rod(s)
- Rod Position Indicator (RPI) Malfunction(s)
Page 2 of7l
TSTEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 1 2.0 OPERATOR ACTIONS
- 1. DIAGNOSE the failure:
GOTO IF... SECTION PAGE Uncontrolled rod bank movement 2 1 4 (rod movement NOT due to actual T-avg/T-ref mismatch or change in reactor/turbine power)
Dropped shutdown/control rod(s) 2.2 10 with reactor initially in Mode 1 or 2 Misaligned shutdown/control rod(s) or bank in Mode 1 or 2 2.3 24 Dropped or Misaligned shutdown/control rod(s) 2.4 43 in Modes 3, 4 or 5 Failure of control bank to move on demand (AUTO or MANUAL) 2.5 52 OR ROD CONTROL SYSTEM URGENT FAILURE alarm LIT. [M-4B window A-6]
Rod Position Indicator (RPI) Malfunction - Modes 1 or 2 2.6 61 END OF SECTION Page 3 of 71
AOP-C.01 SQN ROD CONTROL SYSTEM MALFUNCTIONS Rev. 20
[ STEP ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED 2.5 Rod Control Urgent Failure Alarm or Failure of Control Bank to Move CAUTION 1: Control Rods should NOT be manually withdrawn during a transient.
CAUTION 2: Attempting to move control rods with ROD CONTROL SYSTEM URGENT FAILURE alarm could result in dropped or misaligned rods.
CAUTION 3: Depressing ROD URGENT FAILURE RESET pushbutton on M-4 prior to determining and correcting cause could result in dropped rods.
CHECK ROD CONTROL SYSTEM IF ROD CONTROL SYSTEM URGENT URGENT FAILURE alarm LIT. FAILURE alarm is NOT LIT,
[M-4B, window A-6j THEN PERFORM the following:
- a. ENSURE rod control in MAN.
- b. GO TO Step 17.
- 2. DETERMINE if rod control should be placed in MANUAL:
- a. CHECK rod control in AUTO. a. MAINTAIN rod control mode selector switch in current position.
GO TO Step 3.
- b. PLACE rod control in MAN.
Page 52 of 71
AOP-C.01 SQN ROD CONTROL SYSTEM MALFUNCTIONS Rev. 20 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 2.5 Rod Control Urgent Failure Alarm or Failure of Control Bank to Move (contd)
- 3. CONTROL T-avg within 3°F of T-ref by performing one of the following:
- ADJUST turbine load OR
- 4. MONITOR following parameters IF uncontrolled transient in progress STABLE or CONTROLLED: AND control rods CANNOT be moved, THEN
- reactor power TRIP reactor and GO TO E-O, Reactor Trip
- T-avg or Safety Injection.
Page 53 of 71
AOP-CMI SQN ROD CONTROL SYSTEM MALFUNCTIONS Rev. 20 STEP ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED I 2.5 Rod Control Urgent Failure Alarm or Failure of Control Bank to Move (contd)
- 5. DETERMINE source of urgent failure ala rm:
- a. DISPATCH MIG to determine source of urgent failure alarm (power cabinet or logic cabinet).
- b. CHECK urgent failure light LIT b. IF urgent failure alarm is in any power cabinet, in logic cabinet, THEN GO TO Step 9.
- c. DETERMINE affected rod group USING 1 ,2-AR-M4-B (window A-6).
CAUTION: Applying DC latch and hold power to more than one group at a time could cause dropped rods.
NOTE: Regulator Failure light (in affected power cabinet) may illuminate when DC Hold Power is placed on affected rod group. This light should clear when the Rod Urgent Failure is reset.
- 6. APPLY DC hold power to affected rod group:
[Aux Bldg, 759 elev, MG Set Room]
- a. CHECK DC latch and hold power a. ENSURE Switch Si in DC Hold cabinet available USING lights on door panel. is ON.
- b. PLACE affected groups switch in LATCH for at least one second.
- c. PLACE switch in HOLD.
Page 54 of 71
AOP-C.01 SQN ROD CONTROL SYSTEM MALFUNCTIONS Rev. 20 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I (contd) 2.5 Rod Control Urgent Failure Alarm or Failure of Control Bank to Move
- 7. iNITIATE Maintenance to correct cause of urgent failure alarm.
failure or CAUTION: If rod control urgent failure alarm is caused by Stationary Regulation from placing rod contro l in any logic cabinet failure, dropped rods could result BANK SELECT.
ments NOTE: If reactor is determined to be unaffected by failure and bank overlap require D in are maintained, reactor may be operated indefinitely with Control Bank BANK SELECT.
- 8. DETERMINE if Control Bank D is available:
- a. VERIFY NO Urgent Failure alarm a. GO TO Step 9.
in the following cabinets:
- logic cabinet
- powercabinetlBD
- power cabinet 2BD.
- b. EVALUATE use of Control Bank D in BANK SELECT as necessary to control T-avg and reactor power.
- 9. CHECK repairs completed. DO NOT CONTINUE this section UNTIL repairs completed.
Page 55 of 71
STEP SQN ROD CONTROL SYSTEM MALFUNCTIONS ACTION/EXPECTED RESPONSE AOP-C.01 Rev. 20 RESPONSE NOT OBTAINED 1 1 2.5 Rod Control Urgent Failure Alarm or Failure of Control Bank to Move (contd)
- 10. VERIFY movable gripper coil current WHEN movable gripper coil current NORMAL (measured by MIG, reduced is verified normal, current for Urgent Failure should read THEN 4.4 amps nominal). CONTINUE with Step 11.
- 11. ENSURE DC hold power removed from affected group.
- 12. VERIFY stationary gripper coil NORMAL (measured by MIG, reduced current should read 4.4 amps nominal).
- 13. RESET urgent failure alarm USING Rod Urgent Failure Alarm Reset pushbutton. [M-4).
- 14. REMOVE power from DC Hold Cabinet (GO to OFF with the Si switch).
Page 56 of 71
AOP-C.01 SQN ROD CONTROL SYSTEM MALFUNCTIONS Rev. 20 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 1
)
2.5 Rod Control Urgent Failure Alarm or Failure of Control Bank to Move (contd
- 15. CHECK ROD CONTROL SYSTEM DO NOT CONTINUE this section URGENT FAILURE alarm DARK UNTIL alarm can be cleared.
[M-4B, A6].
- 16. GO TO Step 22.
- 17. CONTROL T-avg within 3°F of T-ref by performing one of the following:
- POSITION control rods OR
- ADJUST turbine load OR
Page 57 of 71
AOP-C.01 SQN ROD CONTROL SYSTEM MALFUNCTIONS Rev. 20 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 1 2.5 Rod Control Urgent Failure Alarm or Failure of Control Bank to Move (contd)
- 18. MONITOR following parameters IF uncontrolled transient in progress STABLE or CONTROLLED: AND control rods CANNOT be moved, THEN
- reactor power TRIP reactor and GO TO E-O, Reactor Trip
- T-avg or Safety Injection.
- 19. CHECK the following rod stop alarm REFER TO ARP for lit window windows DARK: to determine setpoint.
- IRS INTERMED RANGE HI FLUX LVL IF alarm is lit due to valid overpower ROD WITHDRAWAL STOP alarm condition,
[M-4B, B2] THEN REDUCE turbine load and reactor power
- NIS POWER RANGE OVERPOWER as necessary to correct condition.
ROD WITHDRAWAL STOP alarm
[M-4B, D3]
IF any nuclear instrument channel
- 0-3 OVERTEMP AT ROD STOP AND has failed, TURB RUNBACK{M-4A, El] THEN GO TO AOP-l.01, Nuclear Instrument
- C-4 OVERPOWER AT ROD STOP Malfunction.
AND TURB RUNBACK {M-4A, E2].
IF any T-avg or AT channel has failed, THEN GO TO AOP-L 02, RCS Loop RTD Instrument Malfunction.
Page 58 of 71
AOP-C.01 SQN ROD CONTROL SYSTEM MALFUNCTIONS Rev. 20 STEP ACTIONIEXPECTED RESPONSE RESPONSE NOT OBTAINED 2.5 Rod Control Urgent Failure Alarm or Failure of Control Bank to Move (contd)
- 20. CHECK 0-5 LOW TURB IMPULSE IF PT-i -73 failed,
- PRESS ROD WITHDRAWAL BLOCKED THEN permissive DARK. [M-4A, E3] GO TO AOP-l.08, Turbine Impulse Pressure Instrument Malfunction.
IF turbine load is less than 15%
AND rods failed to move outward in AUTO, THEN PERFORM the following:
- a. CONTINUE operation of control rods in MANUAL.
- b. GO TO appropriate plant procedure.
- 21. CHECK BANK D AUTO ROD IF control rods failed to move inward WITHDRAWAL BLOCKED OR Bank D rods are at less than 217 steps, permissive DARK. [M-4B, 07]. THEN INITIATE repairs on rod control.
IF Bank D rods failed to withdraw in AUTO AND Bank D step counter at 218 steps or greater, THEN GO TO appropriate plant procedure.
Page 59 of 71
AOP-C.01 SON ROD CONTROL SYSTEM MALFUNCTIONS Rev. 20 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED I 2.5 Rod Control Urgent Failure Alarm or Failure of Control Bank to Move (contd)
- 22. RESTORE T-avg and Delta flux (Al) to normal USING any of the following:
- Manual rod control
- RCS boration or dilution
- Turbine load reduction.
- 23. CHECK rod control repairs COMPLETE. PERFORM the following:
- a. WHEN rod control repairs COMPLETE AND T-avg is within 1°F of T-ref, THEN RESTORE rod control to AUTO as required USING O-SO-85-1, Rod Control System.
- b. GO TO appropriate plant procedure.
- 24. WHEN T-avg is within 1°F of T-ref AND auto rod control is desired, THEN PLACE rod control in AUTO USING 0-S0-85-1, Rod Control System.
- 25. GO TO appropriate plant procedure.
END OF SECTION Page 60 of 71
JPM Sim Alt D Page 1 of 10 Rev. 0 SEQUOYAH NUCLEAR PLANT September 2010 NRC Exam SIM ALT D (RO\SRO)
Start #1 RCP in Mode 3
JPM Sim Alt D Page 2 of 10 Rev. 0 ROISRO JOB PERFORMANCE MEASURE Task: Start a Reactor Coolant Pump Monitor the operation of the reactor coolant pumps JAITAtask#: 0030010101 0030020101 Task Standard: Determine RCP meets trip criteria and trip RCP #1 Time Critical Task: YES: NO: X K/A Ratings: 003 Al .02 2.9/2.9 015/017 AA1 .03 3.7/3.8 Method of Testing:
Simulated Performance: Actual Performance: X Evaluation Method:
Simulator X In-Plant Classroom Main Control Room Mock-up Performer:
Trainee Name Evaluator: 1 Name I Signature DATE Performance Rating: SAT: UNSAT:
Validation Time: 13 minutes Total Time:
Performance Time: Start Time: Finish Time:
COMMENTS
JPM Sim Alt D Page 3 of 10 Rev. 0 SPECIAL INSTRUCTIONS TO EVALUATOR:
- 1. Critical steps are identified in step SAT/UNSAT column by bold print Critical Step
- 2. Initialize the simulator in IC-186. If not available, initialize to lC#7, Stop the #1 RCP.
- Freeze the simulator.
- Hand the marked up procedure 1-SO-68-2, Section 5.1 through step 10 to the candidate.
- 3. Place the Simulator in RUN when the operator assumes the task.
- 4. Booth operator will be required to Insert the SCN File RCPHEATUP.scn (from exams folder) during the JPM
- 5. 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.
Tools/Equ i pmentlProced ures Needed:
1-SO-68-2, AOP-R.04, 1-AR-M5-B
References:
Reference Title Rev No.
- 1. 1-S0-68-2 Reactor Coolant Pumps 32
- 2. AOP- R.04 Reactor Coolant Pump Malfunctions 24
JPM Sim Alt D Page 4 of 10 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 is in Mode 3.
- 2. Preparations are being made to start #1 RCP.
- 3. All precautions and prerequisites are complete.
- 4. 1-SO-68-2 Section 5.1, steps 1 through 10 are complete.
- 5. Loop 2, 3 and 4 RCPs are in service INITIATING CUES:
- 1. You have been directed to start the Loop 1 RCP in accordance with 1 -SO-68-2, Reactor Coolant Pumps.
- 2. Notify the US when the procedure is complete.
JPM Sim Alt D Page 5 of 10 Rev. 0 Job Performance Checklist:
STEP/STANDARD I SATIUNSAT NOTE: REAC COOL PMPS OIL LIFT PRESS LOW annunciation will come in and clear during performance of the next step STEP 1 [11] PLACE fl-HS-68-84A] No I RCP Lift Oil Pump in the SAT ThR1Epc;t1c. UNSAT Critical STANDARD: Places 1-HS-68-84A in start. Step Start This step is critical to make up a start interlock for the #1 RCP. Time______
COMMENTS:
STEP 2.: [12] WHEN Lift Oil Pump for No. 1 RCP has run 2 minutes, UNSAT THEN ANNOUNCE No. 1 RCP start on the P/A system.
STANDARD: After two minutes has elapsed, makes announcement over PA system.
COMMENTS:
STEP 3.: [13] IF no RCPs are running AND RCP No. I is the first RCP to SAT be started, THEN MONITOR the SRM5 during startup of the UNSAT RCP.
STANDARD: Operator determines other 3 RCPs are running and N/As this step COMMENTS:
NOTE: VIBRATION & LOOSE PARTS MONITORING ALM, alarm will come in when RCP is Started, Operator may dispatch AUO and Predictive Maintenance personnel to check. If so, acknowledge the direction.
JPM Sim Alt D Page 6 of 10 Rev. 0 Job Performance Checklist:
STEP/STAN DARD SATIUNSAT STEP 4 [141 PLACE tl-HS-684A1 No.1 RCP in the STARTpotion. SAT U N SAT STANDARD: Places 1-HS-68-8A in start, observes Red light On, Amps increasing. Critical Step This step is critical to start the RCP per the JPM assignment.
COMMENTS:
Booth Instructor Note: Insert the SCN File RCPHEATUP.scn while the operator is performing the next step.
Evaluator Note: The motor will start heating up and result in the REAC COOL PMPS MOTOR STATOR TEMPERATURE HIGH alarm on 1-M-5, Window E-1 on 1-XA-55-5B coming in during the performance of the next steps (JPM steps 5-7; procedure steps 15-17). When alarm comes in, the operator may not complete performing procedure step 15. 16 or 17. N/A those steps if applicable and move on to JPM step 8 if candidate transitions to alarm procedure.
STEP 5.: [15] ENSURE No. 1 RCP motor and pump are operating within SAT the parameters listed in Appendix D.
UNSAT STANDARD: References Appendix D and observes parameters COMMENTS:
STEP 6.: [16] ENSURE [1-TCV-67-86] RCP Motor Cooler IA is OPEN (1.. _SAT HS-67-86 red light illuminated).
UNSAT STANDARD: Verifies 1-TCV-67-86 is open on Panel M-27A COMMENTS:
JPM Sm Alt D Page 7 of 10 Rev. 0 Job Performance Checklist:
STEPISTAN DARD SATIUNSAT STEP 7.: [17] WHEN Lift Oil Pump has run greater than 1 minute after RCP start, THEN PLACE [1-HS-68-84A] No. I RCP Lift Oil Pump in the STOP position.
UNSAT STANDARD: Places 1-HS-68-84A in STOP position.
COMMENTS:
The following step applies after the REAC COOL PMPS MOTOR STATOR TEMPERATURE HIGH alarms on Window E-1 on 1-XA-55-5B.
STEP 8.: Responds to the alarm and/or observes rise in RCP motor stator SAT temperatures.
UNSAT STANDARD: Determines that RCP operating parameters are not normal.
May determine the 1-SO-68-5 Appendix D limit is exceeded and stopping the RCP is necessary or may implement the annunciator respond procedure.
COMMENTS:
NOTE: If the actions contained in the Annunciator Response Procedure (ARP) are implemented, JPM steps 10-20 cover the actions directed by the ARP and AOP to stop the RCP. If RCP is stopped without implementing the ARP, JPM 9 step will end the JPM.
JPM Sim Alt D Page 8 of 10 Rev. 0 Job Performance Checklist:
STEP/STANDARD SATIUNSAT STEP 9.: _SAT U N SAT STANDARD: Places 1-HS-68-8A to the STOP position.
Critical Cue: If the RCP is stopped, State This completes the JPM Step (unless JPM step This step is critical to remove the RCP from service to prevent damage to 20 is performed) the motor.
COMMENTS:
NOTE: The following steps are from the Annunciator Response Procedure.
STEP 10.:
[11 DETERMINE which pump is in alarm by monitoring computer SAT points.
Pump 1: Point T0409A, 411A or4l2A (kG. & c UNSAT Pump 2: Point T0429A, 431A or 432A (A,B, 8 C 0)
Pump 3: Paint T0449A, 451A or 452A (A,G, 8 C 0)
Pump 4: Point T0469A, 471A or472A (kG, & C 0)
STANDARD: Determines RCP #1 is in alarm from the ICS display.
COMMENTS:
STEP 11.:
[2) CONTACT Tech suppait to oltain engineering assistance SAT detenmning the validity of the alarm.
UNSAT STANDARD: Contacts Tech support for assistance.
Cue: If Tech Support contacted, Acknowledge the request.
COMMENTS:
JPM Sim Alt D Page 9 of 10 Rev. 0 Job Performance Checklist:
STEP/STAN DARD SATIUNSAT STEP 12.:
[3] MONITOR the following parameters for increasing trends:
- a. Motor Current SAT
- b. Bearing Temperatures UNSAT c PumptMotoc Vibration
- d. Containment Air Temperatures STANDARD: Monitors the listed parameters and determines each is normal.
COMMENTS:
STEP 13.:
141 ENSURE ERCW aligned to pump cooler. SAT UNSAT STANDARD: Determines ERCW aligned to pump cooler.
Checks Red light lit 1 -HS-67-86 on O-M-27A.
COMMENTS:
STEP 14.:
[51 VERIFY ERCW system temperature and pressure normal. SAT UNSAT STANDARD: Determines ERCW system normal using indications on O-M-27A.
COMMENTS:
STEP 15.:
[6] VERIFY lower compartment air temperature normal. SAT UNSAT STANDARD: Determines lower compartment air temperature normal using indications on ICS.
COMMENTS:
NOTE: If the RCP is stopped after determining the 31 1°F motor winding temperature limit exceeded using Appendix D, then go back to JPM step 9
JPM Sim Alt D Page 10 of 10 Rev. 0 Job Performance Checklist:
STE PISTAN DARD SATIUNSAT STEP 16.:
[7] REFER To 1-SO-682 for RCP operathg limits. SAT UNSAT STANDARD: Refers to 1-SO-68-2 Appendix D for the operating limits.
COMMENTS:
STEP 17.:
[8] iF OpslEnginearing determines alarm is valid, THEN SAT PERFORM t e j:fl9 UNSAT
[a] CHECK pump motor amps. (normal 415 amps with 608 amps maximwm) fbI IF RCP motor amps approach 608 amps, THEN GO TO AOP-R04, Reactor Coolant Pump Malfunctions.
STANDARD: Determines motor amps are normal.
Cue: If Ops or Engineering contacted, state, The alarm is valid COMMENTS:
STEP 18.:
f9] IF OpsiEngineerfng determines alarm is valid and pump motor SAT statcir temperature approaches 31 1F (329F for RCS UNSAT temperature less than 54QF), THEN GO TO AOP-RC. Reactor Coolant Pump MalfunctIons.
STANDARD: Determines the motor winding temperature is greater than 311°F using the ICS and Goes to AOP-R.04.
Cue: If Ops or Engineering contacted, state, The alarm is valid COMMENTS:
NOTE: The following 2 steps are AOP-R.04, Section 2.6 Step I and Section 2.1 Step 1-3 respectively
JPM Sim Alt D Page 11 of 10 Rev. 0 Job Performance Checklist:
STEP/STANDARD SAT/UNSAT STEP 19.:
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.
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 SAT
- Pump 1: T0409A, 4llAor4I2A PERFORM the following:
- Pump 2: T0429A, 431A or 432A U N SAT
- Pump 3: T0449A, 451A or 452A 1) IF reactor power less than 20%,
THEN
- Pump 4: T0469A, 471A or 472A GO TO Section 2.1, RCP Tripped or Shutdown Required. fCA]
STANDARD: Determines the motor winding temperature is greater than 311°F using the ICS and Goes to AOP-R.04, Section 2.1.
COMMENTS:
SAT STEP 20.: Section 2.1 Any RCP Tripped or RCP Shutdown Required UNSAT
[1] Check unit in Mode I or 2 STANDARD: Determines plant not in Mode I or 2, continues procedure in the RNO for Step [1]
COMMENTS:
STEP 21. [1XOflIQbct)t1 SAT UNSAT Critical Step STANDARD: Operator stops RCP #1 and records time. unless RCP stopped in JPM Step 9.
This step is critical to remove the RCP from service to prevent damage to the motor. End Time CUE: When operator trips RCP tell them 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. UnitlisinMode3.
- 2. Preparations are being made to start #1 RCP.
- 3. All precautions and prerequisites are complete.
- 4. 1-SO-68-2 Section 5.1, steps I through 10 are complete.
INITIATING CUES:
- 1. You have been directed to start the Loop I RCP in accordance with I SO-68-2, Reactor Coolant Pumps.
- 2. Notify the US when the procedure is complete.
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT SYSTEM OPERATING INSTRUCTION 1-SO-68-2 REACTOR COOLANT PUMPS Revision 32 QUALITY RELATED PREPARED/PROOFREAD BY: LOYD HODGES RESPONSIBLE ORGANIZATION: OPERATIONS APPROVED BY: W. T. LEARY EFFECTIVE DATE: 02/11/10 LEVEL OF USE: CONTINUOUS USE REVISION DESCRIPTION:
PCR 09000626 Incorporated PCF-012 (Added NOTE in Sections 8.4, 8.5, and Appendix D.
PCR 09001510- Corrected numbering error at step 8 in sections 5.1, 5.2, 5.3, and 5.4.
PERFORMANCE OF THIS PROCEDURE COULD IMPACT REACTIVITY
SQN REACTOR COOLANT PUMPS I-SO-68-2 Rev: 32 i Page6of74 3.0 PRECAUTIONS AND LIMITATIONS A. Failure to observe all posted radiation control requirements may lead to unnecessary radiation absorbed doses.
B. Seal injection flow to RCPs must be maintained when RCS loops are being filled and anytime thereafter.
C. RCS must be filled and vented in accordance with 0-GO-I 3 prior to running RCPs continuously.
D. Limit number of attempted RCP starts to three within any two hour period. A one hour cooldown period will be observed before a fourth attempt is made. Thirty minutes must be allowed between RCP starts.
E. Operation of Reactor Coolant Pumps for greater than 2 minutes without CCS cooling to oil coolers will result in bearing temperatures greater than 200°F.
F. When starting an RCP, the following guidelines apply:
- a. If all RCPs have been stopped for more than five minutes AND the RCS temperature is greater than the charging and seal injection water temperature, a RCP can not be started until a steam bubble has been formed in the pressurizer. This will minimize a pressure transient when the first RCP is started due to the expansion of the previously injected cold water. This recommendation is not applicable to RCP operation in Mode 5 when steam generator temperatures are no more than 25°F warmer than the RCS temperature.
- b. If the RCS temperature is >200° F but <300° F, and FCV-74-1 and 2 are open do not attempt to restart a RCP unless the pressurizer level is <60%
(indicated) to prevent RHR overpressurization.
G. When RCS is being cooled down by RHR, a non-uniform temperature distribution may occur with no RCPs running.
H. Do not start the first RCP in mode 5 with the Steam Generator secondary side temperature above 200°F. This is to prevent a possible inadvertent mode change and to prevent the possibility of exceeding RCS heat up limitations. [C.6]
I. When in Mode 4, a reactor coolant pump shall not be restarted unless a steam bubble exists in the Pressurizer..
SQN REACTOR COOLANT PUMPS 1-SO-68-2 Rev: 32 i Page7of74 3.0 PRECAUTIONS AND LIMITATIONS J. The following restrictions for RCP operation apply, when RHR is connected to the RCS for shutdown cooling, to prevent RHR over pressurization: (FCV-74-1 and 2 open)
- When RCS temperature is greater than 200°F and less than 300°F, and no RCPs are running, a RCP can not be started unless pressurizer level is less than 60%.
- When RCS temperature is greater than 300°F AND no RCPs are running, a RCP can not be started regardless of pressurizer level.
K. The Source Range Monitor instrumentation must be monitored during startup of the first RCP. This precaution is necessary in order to detect rapid boron dilution from unborated water that could be flushed into the core.
L. If all RCPs are shutdown, do not start the first RCP if it is known that any volume of dilute water has been introduced into any reactor coolant loop until an action plan for recovery is developed as described in Appendix F Prevention of Rapid Boron Dilution. [C.5]
M. RCS pressure may increase when starting the first RCP.
N. IF secondary temperature of any SIG is greater than 25°F above RCS cold leg, do NOT start an RCP.
- 0. IF SIG secondary temperatures are greater than RCS cold leg, an inadvertent heatup and pressurization of the RCS can occur when initially running RCPs.
P. IF SIG secondary temperatures are less than RCS cold leg, an inadvertent cooldown and depressurization of the RCS can occur when initially running RCPs.
Q. To avoid uncontrolled reactivity changes, RCP(s) shall NOT be restarted with the unit in Mode I or 2.
SQN REACTOR COOLANT PUMPS 1-SO-68-2 Rev: 32 I Page8of74 Date :c\
PREREQUISITE ACTIONS NO Throughout this Instruction where an IFITHEN statement exists, the step should be NIA if the condition does not exist.
NO Guidance on motor rotation checks (bump test) and/or uncoupled RCP runs are contained in 0-Ml-EMM-068-002.3, Removal and Replacement of Reactor Coolant Pump Motor Appendix G.
ENSURE Precautions and Limitations, Section 3.0, have been reviewed.
ENSURE the Instruction to be used is a copy of the effective version. -
(fr IF performing RCP Startup OR Shutdown (Sections 5.1, 5.2, 5.3, 5.4, 7.1, 7.2, 7.3, 7.4, 8.4 or 8.5), THEN NOTIFY Predictive Maintenance Group. _s CA5N Starting first RCP could result in a positive reactivity addition if a pocket of low boron concentration reactor coolant may have been introduced into the reactor coolant system. (See Appendix F for guidelines)
Prerequisite Step [4] may be marked N/A if performing sweeps and vents (Section 8.4 and 8.5) as directed in 0-GO-i.
VERIFY RCS is filled in accordance with 0-GO-13 and 0-GO-I.
VERIFY RCP seal flow is established in accordance with 1 -SO-62-1.
IF in Mode 4, THEN ENSURE a steam bubble exists in the pressurizer.
VERIFY [I -P1-62-I 22] Volume Control Tank pressure 17 psi.
SQN REACTOR COOLANT PUMPS l-SO-68-2 Rev: 32 i Page9of74 Date 1 To fr) PREREQUISITE ACTIONS (Continued)
ENSURE the following:
Power Checklist 1-68-2.01 complete. i Valve Checklist 1-68-2.02 complete.
Power Checklist 1-70-1.01 complete.
Power Checklist 1-70-1.02 complete.
Valve Checklist 1-70-1.04 complete.
Valve Checklist 1-70-1.05 complete. 3 IF no RCPs are in service and RCS or S/G pressure is greater than 200 psig. THEN ENSURE 0-Sl-OPS-000-004.0 is in progress. [C.6]
VERIFY RCS pressure is 325 psig.
CA Starting an RCP when DIG is parallel to the grid may cause the DIG to trip on overcurrent.
VERIFY DIG is not tied to 6.9kV Shutdown Board paralleling the Unit Board, which feeds the RCP to be started.
[1 F adequate cooling water flow cannot be maintained according to Appendix D, THEN GO TO 1-S0-70-1, AND START another CCS pump, THEN RETURN to Section 5.0 for individual RCP starting instructions. N
SQN REACTOR COOLANT PUMPS 1-SO-68-2 Rev: 32 I PagelOof74 Date_________
REREQUISITE ACTIONS (Continued)
ENSURE_each performer documents their name and initials:
Print Name Initials
- v8__o.
_j1INDICATE below which performance section of this Instruction will be used and reason for this performance.
STARTUP/STANDBY READINESS.
Li 7.0 SHUTDOWN.
Li 8.0 INFREQUENT OPERATION.
REASON:
SQN REACTOR COOLANT PUMPS 1-SO-68-2 Rev: 32 I Pagellof74 Date T\
j) STARTUP STANDBY READINESS
- 1 Reactor Coolant Pump Start CAU I RHR over pressurization restrictions prohibit starting a RCP, when RCS temperature is greater than or equal to 300°F, AND no RCPs are running, AND RHR is aligned to the RCS for shutdown cooling.
CAt1f 2 RCS pressure may increase when starting the first RCP.
CAU Computer point IP0499A, which inputs to O-Sl-SXX-068-I 27.0, should be monitored along with compliance instrumentation to ensure all pressure /temperature requirements are met.
If starting RCP for troubleshooting of vibration problems, after maintenance activities that affect pump vibration or for balance shot activities then refer to Appendix E for vibration monitoring requirements.
IF no RCPs are running AND [FCV-74-I1 and [FCV-74-2]
are OPEN, THEN
[a] RECORD RCS temperature. °F
[b] IF RCS temperature is >200°F and <300°F, THEN ENSURE pressurizer level is <60%. A WHEN 30 minutes have elapsed since last #1 RCP run/attempted start, THEN PROCEED to step 3.
iF access into containment is permitted, THEN PERFORM Appendix A RCP Local Inspection Check Sheet.
VERIFY [1-TR-70-161] CCS Hx 1A1/1A2 Outlet Temperature 105°F.
ENSURE [I-HS-67j RCP Motor Cooler 1A is in the P-AUTO position.
SQN REACTOR COOLANT PUMPS 1-SO-68-2 Rev: 32 j Pagel2of74 Date_________
5.1 # I Reactor Coolant Pump Start (Continued) sl RCS pressure is> 100 psig, THEN ENSURE [1 -FCV-62-91, RCP #1 Seal Leak-off and f1-FCV-62-63], Seal Return Isolation are OPEN.
NOT3 Appendix B should be used to diagnose RCP seal abnormalities.
NOj Step [7] may be marked N/A if leakoff is less than 0.2 gpm and Step [8] will be performed.
DETERMINE #1 RCP seal No. 1 leakoff 0.2 gpm by using any of the following:
INSTRUMENT 1FR--62--23 (red pen scale range 0.0-1.0) LI 1FR62--24 (red pen scale range 0.0-10.0) LI lOS Ultrasonic (requires a SR to be installed) El Differential Pressure (requires a SR to be installed) LI N3 The Bucket Test is NO longer performed. Less than 0.2 gpm flow rate is acceptable for a short period of time after RCP seal maintenance has been performed, provided flow verification has been performed by ultrasonics or differential pressure.
IF #1 RCP seal No. 1 leakoff is <0.2 gpm AND ROP seal maintenance has been performed, THEN
[a] ENSURE SR initiated to have either an ultrasonic or differential pressure instrument installed).
[b] DETERMINE #1 RCP seal No. I leakoff flow rate from the installed ultrasonic or differential pressure instrument.
[c] EVALUATE leak-off rate, continuation of RCP start-up, and duration of RCP run time. N IPc Engineering
SQN REACTOR COOLANT PUMPS 1-SO-68-2 Rev: 32 1 Pagel3of74 Date_______
5.1 #1 Reactor Coolant Pump Start (Continued)
VERIFY [1-PDI-62-8A] #1 RCP Seal No. I differential pressure greater than or equal to 220 psid.
Reactor Coolant Pump is being started after major maintenance, troubleshooting or for balance shot activities, THEN PERFORM Appendix E for modified RCP vibration monitoring requirements and limitations.
[11] PLACE [i-HS-68-84A] #1 RCP Lift Oil Pump in the START position.
[12] WHEN Lift Oil Pump for #1 RCP has run 2 minutes, THEN ANNOUNCE #1 RCP start on the P/A system.
[13] IF no RCPs are running AND RCP #1 is the first RCP to be started, THEN MONITOR the SRMs during startup of the RCP. [C.3] LI
[14] PLACE [1-HS-68-8A1 #1 RCP in the START position.
NOTE Motor and Pump Operating Parameters are listed in Appendix D. Appendix E provides vibration limits if pump is started after maintenance activities.
[15] ENSURE #1 RCP motor and pump are operating within the parameters listed in Appendix D.
SQN REACTOR COOLANT PUMPS 1-SO-68-2 Rev: 32 I Pagel4of74 Date 5.1 #1 Reactor Coolant Pump Start (Continued)
[16] ENSURE Fl-TCV-67-86] RCP Motor Cooler IA is OPEN (1-HS-67-86 red light illuminated).
[17] WHEN Lift Oil Pump has run greater than 1 minute after RCP start, THEN PLACE II -HS-68-84A1 #1 RCP Lift Oil Pump in the STOP position. II
[18] IF RHR is removed from service, THEN DETERMINE if both CCS pumps are needed inservice.
[19] IF the second running CCS pump is to be removed from service, THEN GO TO 1SO--701 and STOP the second running CCS pump.
END OF TEXT
SQN REACTOR COOLANT PUMPS 1-SO-68-2 Rev: 32 i Page 66 of 74 APPENDIX D Page 1 of 3 RCP OPERATION PARAMETERS TABLE #1 This table will be used for monitoring RCP parameters during operation.
NORMAL MINIMUM MAXIMUM (1>
- 1. RCS Pressure 2250 psig 325 psig 2485 psig (2>
- 2. RCS Temperature 550°F 650°F (3>
- 3. No. I Seal Leakoff 1-5 gpm 0.8 gpm 6 gpm
- 4. No. I Seal AP 2250 psid 220 psid 2300 psid
- 5. No. 1 Seal Water Temperature 100-170°F 60°F 180°F
- 6. Seal Water Supply Flow 8-13 gpm 6 gpm 15 gpm
- 7. Therm Barrier Outlet Flow 40 gpm 35 gpm 60 gpm
- 8. Therm Barrier Return Temp < 1 15
- 9. Lower Brg Water Temp 160°F Ambient 225°F
- 10. Upper Oil Cooler Outlet Flow 150 gpm 90 gpm
- 11. Lower Oil Cooler Outlet Flow 5-10 gpm 5 gpm 10 gpm
- 12. Oil Cooler Return Temp 80°F 60°F 125°F
- 13. Lower Motor Brg. Temp 125°F 200°F
>5)
- 14. Motor Winding Temp 200°F 31 1°F
- 15. Motor Winding Voltage 6600V 5940V 7260V
- 16. MotorWinding Amps>
4 415A 608A (1) RCS pressure must be 325 psig to start a RCP. 325 psig will support the #1 seal minimum AP requirements of 220 psid.
(2) During startup a RCP must be in operation when RCS temperature is greater than 160°F.
(3) The 0.8 gpm minimum applies when RCS pressure greater than or equal to 2000 psig. If RCS pressure is less than 2000 psig, then refer to the graph on Appendix D page 3.
(4) RCP amps may be higher than 415 amps during cold water starts and operation, but the 608 amps shall NOT be exceeded.
(5) The maximum allowable RCP motor winding temperature is 329°F when RCS temperature is less than 540°F.
RCP motor winding temperatures are expected to go to 280 290°F during cold water operations.
SQN REACTOR COOLANT PUMPS 1-SO-68-2 Rev: 32 I Page 67 of 74 APPENDIX D Page 2of3 RCP OPERATION PARAMETERS TABLE #2 This table has additional information that may be used for monitoring RCP parameters.
This information may be obtained at a later time.
NORMAL MINIMUM MAXIMUM
- 1. Air Cooler Water Flow (7) 150 gpm 132 gpm
- 2. Air Cooler Water Inlet Press 150 psig
- 3. Air Cooler Water Inlet Temp (7) 80°F 35°F 84.5°F
- 4. Upper Motor Brg Temp 150°F 200°F
- 5. Oil Lift Pump Press 1250 psig 600 psig 2250 psig
- 6. Seal Injection. Water Temp. 60-130°F 60°F 130°F
- 7. Therm Barrier p 42-58 H0 2
- 8. Upper Oil Cooler Water Press 150 psi
- 9. Upper Oil Cooler Water Temp. 80°F 60°F 125°F
- 10. Lower Oil Cooler Press 150 psi (6) Closed per corrective action of SCAR NO SQSCA910003. [C.2]
(Sect. 8.4 and 8.5).
(7) Air cooler not required for short-term RCP operation for RCS sweeps and vents
SQN REACTOR COOLANT PUMPS 1-SO-68-2 Rev: 32 j Page 68 of 74 APPENDIX D Page 3 of 3 NOTE I If No. I Seal D/P is greater than 500 psid (above the top of the MCR indication), then RCS pressure should be used as the No. I Seal DiP.
NOTE 2 The lower limit of the normal operating range is the minimum allowable leakoff when RCS pressure is< 2000 psig.
NOTE 3 If seal leakoff is> normal operating range but < seal leakoff high flow alarm setpoint, then monitor pump parameters and contact Engineering for assistance.
NOTE 4 During startup, RCP leak-off may be < 0.2 gpm if Engineering approval is obtained per applicable step in Section 5.1, 5.2, 5.3, 5.4, 8.4, or 8.5.
Nn1 SciI I k RfA v Nn I SpiI flcIf P wifh RCS Pmcciirp .-2flflfl Pcin 6
5 4
NO. 1 SEAL LEAK RATE (GPM) 0 220 400 600 800 1000 1200 1400 1600 1800 2000 220 2400 2600 2250 NO. I SEAL DIFFERENTIAL PRESSURE (PSI)
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT ANNUNCIATOR RESPONSE I -AR-M5-B CVCS SEAL WATER AND RCP I -XA-55-5B Revision 36 Quality Related PREPARED/PROOFREAD BY: OLIVIA HEAD RESPONSIBLE ORGANIZATION: OPERATIONS APPROVED BY: W. T. LEARY EFFECTIVE DATE: 11/30/07 LEVEL OF USE: REFERENCE USE REVISION DESCRIPTION: Reformatted window A-5 to correct inconsistencies between Units ARs.
Inserted note pertaining to oil levels and temperatures. Reworded step I in window A-7, editorial change (0700534). Corrected windows C-7 SER point identification. Added parenthetical reference for clarification of FS relationship on windows C-7 and D-7. Corrected procedure reference in window D-3 should have referenced SO instead of AOP. Changed contact information in window D-4 should have been MSS. Deleted reference to PER in window E-3, PER was previously resolved. Removed reference to AOP-R.04 in window E-4, redundant step. Minor editorial issues corrected throughout. No revision bars were used for editorial changes.
29 (E-1)
Source Setpoint SER 404 Computer alarm at REAC COOL PMPS
- 1. TE-68-12D, C, J Pump 1 293°F MOTOR STATOR
- 2. TE-68-35E, F, H Pump 2 293°F TEMPERATURE
- 3. TE-68-54E, G, J Pump 3 293°F HIGH
- 4. TE-68-77E, C, J Pump 4 293° F Probable i. Excessive load on pump motor.
Causes 2. Air restriction to pump motor coolers.
- 3. Insufficient ERCW to pump motor coolers.
- 4. Boron buildup on Reactor Coolant Pump Motor heat exchanger.
Corrective [1] DETERMINE which pump is in alarm by monitoring computer Actions points.
Pump 1: Point T0409A, 41 1A or 412A (A,B, & C 0)
Pump 2: Point T0429A, 431A or 432A (A,B, & C 0)
Pump 3: Point T0449A, 451A or 452A (A,B, & C 0)
Pump 4: Point T0469A, 471A or 472A (A,B, & C 0)
[2] CONTACT Tech Support to obtain engineering assistance in determining the validity of the alarm.
[3] MONITOR the following parameters for increasing trends:
- a. Motor Current
- b. Bearing Temperatures
- c. Pump/Motor Vibration
- d. Containment Air Temperatures
[4] ENSURE ERCW aligned to pump cooler.
[5] VERIFY ERCW system temperature and pressure normal.
[6] VERIFY lower compartment air temperature normal.
[7] REFER TO 1 -SO-68-2 for RCP operating limits.
[8] IF Ops/Engineering determines alarm is valid, THEN PERFORM the following:
[a] CHECK pump motor amps. (normal 415 amps with 608 amps maximum.)
[b] IF RCP motor amps approach 608 amps, THEN GO TO AOP-R.04, Reactor Coolant Pump Malfunctions.
- CONTINUED ON NEXT PAGE*
SQN I -AR-M5-B Page 36 of 45 I Rev. 36
29 (E-1)
CORRECTIVE ACTIONS (CONTD)
REAC COOL PMPS MOTOR STATOR TEMPERATURE HIGH
[9] IF Ops/Engineering determines alarm is valid and pump motor stator temperature approaches 31 1°F (329°F for RCS temperature less than 540°F), THEN GO TO AOP-R.04, Reactor Coolant Pump Malfunctions.
[10] IF Ops/Engineering determines alarm is valid and other plant parameters indicate RCP motor problem, THEN REFER TO AOP-R.04, Reactor Coolant Pump Malfunctions.
[11] IF Ops/Engineering determines alarm is valid and is due to boron buildup on Reactor Coolant Pump Motor Heat Exchanger, THEN OBTAIN Engineering recommendation to PERFORM 1SO682, Section 8.3 At Power RCP Motor Cooler ERCW Isolation References 45B655-05B-0, 47A6 15-0, 47W6 10-67-2 SQN I -AR-M5-B Page 37 of 45 I Rev. 36
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.04 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-8 (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 of 34
AOP-R.04 SQN REACTOR COOLANT PUMP MALFUNCTIONS Rev. 24 STEP ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED 1 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 shou!d 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 RCP 2.6 24 Page 3 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 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 ACTIONIEXPECTED 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. WHEN 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 zT and T-avg:
- XS-68-2D (zT)
- XS-68-2M (T-avg)
Page 5of34
SQN REACTOR COOLANT PUMP MALFUNCTIONS AOP-R.04 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 o 3.4.1 3, Reactor Coolant System -
Shutdown
- 3.4.6.2, RCS Operational Leakage
- 8. GO TO appropriate plant procedure.
END OF SECTION Page 6of34
AOP-R.04 SQN REACTOR COOLANT PUMP MALFUNCTIONS Rev. 24 STEP ACTION/EXPECTED 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.
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
- Pumpl:T0409A,4llAor4l2A PERFORM the following:
- Pump 2: T0429A, 431A or 432A
- 1) power less than 20%,
- Pump 3: T0449A, 451A or 452A THEN
- 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 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 of 34
JPM Sim At-E Page 1 of 10 Rev. 0 SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE MEASURE ALT SIM E (ROISRO)
Isolate Cold Leg Accumulator
[Alternate Path]
JPM Sim Alt-E Page 2 of 10 Rev. 0 ROISRO JOB PERFORMANCE MEASURE Task: Vent the Unisolable Cold Leg Accumulator Task#: 3110030601 0060060101 (RO)
Task Standard: #i Cold Leg Accumulator is vented following injection.
Time Critical Task: YES: NO: X K/A Reference/Ratings: oii EA1 .09(4.3/4.3)
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: 8 minutes Total Time:
Performance Time: Start Time: Finish Time:
COMMENTS
JPM Sim AIt-E Page 3 of 10 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
- 4. If IC #62 is not available, initialize in IC #16 and perform the following setup; Activate ME #THO1A at 25%;
Activate RE #SIRO1 to ON, places power on CLA isolation valves; Activate override #ZDIHS63118A to OPEN (prevents #1 CLA isolation valve from closing)
- 5. When RCS pressure is much less than 1870 psig and a phase B has been received, acknowledge alarms and freeze the simulator until ready to perform JPM.
- 6. An extra operator will be required to acknowledge alarms.
- 7. At step 6 the console operator will need to open air to CNMT with MRF IARO6, 07, 08.
- 8. 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.
ToolslEquipment/Procedures Needed:
E-i, Step 18 EA-63-1
References:
Reference Title Rev No.
- 1. E-i Loss of Reactor or Secondary Coolant 24
- 2. EA-63-i Venting Unisolated Cold Leg Accumulator 0 READ TO OPERATOR
JPM Sim Alt-E Page 4 of 10 Rev. 0 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:
- 2. E-1 has been implemented.
INITIATING CUES:
- 1. You are the OATC and the SRO directs you to isolate the CLA per step #18 of E-1.
- 2. Power to the CLA isolation valves has been restored using EA-201-1.
- 3. Inform the SRO when step 18 is completed.
JPM Sim Ait-E Page 5 of 10 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 1.: 18 MONITOR if CLAs should be isolated. SAT
- a. CHECK RCS pressure less than 100 psig.
UNSAT RCS pressure is 90 psig.
STANDARD: Operator checks RCS pressure using PAM indicator and Start time_____
determines that RCS pressure is less than 100 psig.
COMMENT:
STEP 2.: b. CHECK Power to CLA isolation valves AVAILABLE. SAT UNSAT STANDARD: Based on initiating cues, Operator determines power available.
Cue: If requested, in form operator that power is available.
COMMENT:
Step 3. c. ENSURE SI signal RESET SAT STANDARD: Operator verifies permissive lights; AUTO SI BLOCKED UNSAT permissive lit and SI ACTUATED permissive dark.
COMMENT:
Evaluator_Note:_This_commences_the_Alternate_Path_of the_JPM STEP 4. SAT NOTE: FCV-63-118 (#1 CLA) will NOT go CLOSED the red light will stay ON. UNSAT STANDARD: Operator places HSs for FCV-63-1 18*, 98, 80, 67 in the CLOSED Critical Step position and verifies green lights LIT. (ONLY on 98, 80 & 67).
Recognizes FCV-63-1 18 fails open and goes to RNO to vent the unisolated (#1) CLA.
This is a critical step due to isolating the CLAs after injection to preclude N2 injection into the RCS COMMENT:
JPM Sim AIt-E Page 6 of 10 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 5. d. (RNO) If power available to affected valve(s), THEN CLOSE SAT affected valve(s) USING EA-201-3, Operation of Motor-Operated Valves from Outside the Control Room. UNSAT Cue: When AUO contacted to perform EA-201-3, report back that EA-201-3 sect 4.3 has been performed and FCV-63-118 did not close.
STANDARD: Operator contacts AUO to perform EA-201-3. After receiving report from AUO, candidate will continue with RNO actions.
Comments:
STEP 6.: If any CLA valve CANNOT be closed, THEN PERFORM the SAT following:
ENSURE Phase B is RESET UNSAT STANDARD: Operator depresses 1-HS-63-64D and 64E (on M6), verifies window A-5 and A-6 on 1 -XA-55-6C are reset.
COMMENT:
Simulator Operator Note: When AUO is contacted, console operator must open FCV-32-110 (and 102 and 80) with remote functions IARO6, IARO7, and IARO8 to OPEN.
STEP 7.: ESTABLISH control air to containment USING SAT EA-32-1 ,Establishing Control Air to Containment.
UNSAT EA-32-1 is in progress. Status of EA is unknown.
When AUO contacted, state: I am in the process of opening the valves at this time.
STANDARD: Operator ensures air is available to containment by observing red lights LIT on FCV-32-1 10 (may also verify FCV-32-1 02 and 80) on XX-55-6K.
COMMENT:
JPM Sim AIt-E Page 7 of 10 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 8. VENT the unisolated CLA USING EA-63-1, Venting Unisolated SAT Cold Leg Accumulator.
U NSAT STANDARD: Operator transitions to EA-63-1, to attempt to vent the nitrogen overpressure from the accumulator.
COMMENT:
Evaluators Note: The following is from EA-63-1 STEP 9.: 1. ENSURE Phase B is RESET SAT STANDARD: Operator verifies windows A-5 and A-6 on 1-XA-55-6C are reset. UNSAT COMMENT:
STEP 10.: 2. ENSURE control air to containment ESTABLISHED USING SAT EA-32-1 ,Establishing Control Air to Containment.
UNSAT Cue: IF AUO contacted, state EA-32-1 is complete.
STANDARD: Operator ensures air is available to containment by observing red lights LIT on FCV-32-1 10 (may also verify FCV-32-1 02 and 80) on XX-55-6K.
COMMENT:
STEP 11. 3. ENSURE the following closed: SAT FCV-63-64 Nitrogen Supply FCV-63-1 27 Accumulator 1 Nitrogen Supply UNSAT FCV-63-1 07 Accumulator 2 Nitrogen Supply FCV-63-87 Accumulator 3 Nitrogen Supply FCV-63-63 Accumulator 4 Nitrogen Supply STANDARD: Operator verifies the above valves are closed by Green lights LIT on the respective handswitches.
COMMENT:
JPM Sim AIt-E Page 8 of 10 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 12.: SAT UNSAT STANDARD: Operator adjusts HIC-63-65A to 100% by turning adjustment counter clockwise until it stops turning and indicator reads 100%. Critical Ste p This is a critical step to provide a vent path for accumulator.
COMMENT:
STEP 13.: EAfrJW SAT UNSAT STANDARD: Operator places HS for FCV-63-127 in the OPEN position and verifies Red light ON.
Critical Step This is a critical to step to align accumulator vent path.
COMMENT:
STEP 14. 6. WHEN affected CLA depressurized THEN CLOSE valve SAT FCV-63-1 27.
UNSAT STANDARD: When CLA #1 pressure is approximately zero, Operator closes FCV-63-127 and verifies closed by Green light on HS LIT.
COMMENT:
STEP 15. 7. ADJUST nitrogen supply header vent controller HIC-63-65A SAT output to 0% (CLOSE).
UNSAT STANDARD: Operator dials HIC-63-65A to 0% output by turning control clockwise.
COMMENT:
JPM Sim AIt-E Page 9 of 10 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 16.: Return to procedure and step in effect. SAT U N SAT STANDARD: Operator returns to E-1, Step 18.
STEP 17.: Inform the US that the #2, 3, & 4 CLAs have been isolated and SAT that the #1 CLA would NOT isolate and that it has been vented.
U N SAT STANDARD: Operator informs the US that the #2, 3, & 4 CLAs have been isolated and that the #1 CLA would NOT isolate and that it has been vented.
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 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:
- 2. E-1 has been implemented.
INITIATING CUES:
- 1. You are the OATC and the SRO directs you to isolate the CLA per step #18 of E-1.
- 2. Power to CLA isolation valves has been restored using EA-201-1.
- 3. Inform the SRO when step 18 is completed.
SQN LOSS OF REACTOR OR SECONDARY COOLANT E-1 Rev. 24 STEP I I ACTION/EXPECTED RESPONSE I I RESPONSE NOT OBTAINED
- 18. MONITOR if CLAs should be isolated:
- a. CHECK RCS pressure a. GO TO Step 19.
less than 100 psig.
- b. CHECK power to CLA isolation valves b. DISPATCH personnel to restore power AVAILABLE, to CLA isolation valves USING EA-201-1, 480v Board Room Breaker Alignments.
- c. ENSURE SI signal RESET.
- d. CLOSE CLA isolation valves. d. IF power available to affected valve(s),
THEN CLOSE affected valve(s)
USING EA-201-3, Operation of Motor-Operated Valves from Outside MCR.
IF any CLA valve CANNOT be closed, THEN PERFORM the following:
- 1) ENSURE Phase B reset.
- 2) ESTABLISH air to containment USING EA-32-1, Establishing Control Air to Containment.
- 3) VENT any unisolated CLA USING EA-63-1, Venting Unisolated Cold Leg Accumulator.
Page 22 of 27
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT EOI PROGRAM MANUAL EMERGENCY ABNORMAL PROCEDURE EA-63-1 VENTING UN ISOLATED COLD LEG ACCUMULATOR Revision 0 QUALITY RELATED PREPARED/PROOFREAD BY: RILEY WRIGHT DATE: 7/27/95 RESPONSIBLE ORGANIZATION: OPERATIONS APPROVED BY: ORIGINAL SIGNED BY W. R. LAGERGREN DATE: 8/24/95 EFFECTIVE DATE: 9/6/95 VERIFICATION DATE: 7/27/95 VALIDATION DATE: 7/30/95 REVISION DESCRIPTION: This is a new procedure created as part of upgrading the EOP set to WOG ERG Revision I B.
EA-63-1 SQN LATOR Rev. 0 VENTING UNISOLATED COLD LEG ACCUMU 1 2 Page2of5 1.0 PURPOSE unisolated cold leg accumulators (CLAs) to To provide instructions for venting nitrogen from prevent nitrogen injection into the RCS.
2.0 SYMPTOMS AND ENTRY CONDITIONS 2.1 Entry Conditions A. E-i, Loss of Reactor or Secondary Coolant.
B. ECA-l .1, Loss of RHR Sump Recirculation.
m Generators.
C. ECA-2.i, Uncontrolled Depressurization of All Stea D. ECA-3.i, SGTR and LOCA Subcooled Recovery E. ECA-3.2, SGTR and LOCA Saturated Recovery.
l.
F. ECA-3.3, SGTR Without Pressurizer Pressure Contro ion.
G. ES-i .2, Post LOCA Cooldown and Depressurizat H. ES-3.1, Post-SGTR Cooldown Using Backfill.
I. ES-3.2, Post-SGTR Cooldown Using Blowdown.
J. ES-3.3, Post-SGTR Cooldown Using Steam Dump K. FR-C.i, Inadequate Core Cooling.
L. FR-C.2, Degraded Core Cooling.
M. FR-P.i, Pressurized Thermal Shock.
3.0 PRECAUTIONS AND LIMITATIONS None.
SQN I I EA-63-1 VENTING UNISOLATED COLD LEG ACCUMULATOR I Rev. 0 1,2 II Page 3 of 5 I
4.0 OPERATOR ACTIONS 4.1 Section Applicability
- 1. PERFORM Section 4.2.
4.2 Venting Nitrogen from Cold Leg Accumulators
- 1. ENSURE Phase B RESET. LI
- 2. ENSURE control air to containment ESTABLISHED USING EA-32-1, Establishing Control Air to Containment.
- 3. ENSURE the following valves CLOSED:
CLOSED VALVE DESCRIPTION q FCV-63-64 Nitrogen Supply LI FCV-63-127 Accumulator I Nitrogen Supply LI FCV-63-107 Accumulator 2 Nitrogen Supply LI FCV-63-87 Accumulator 3 Nitrogen Supply LI FCV-63-63 Accumulator 4 Nitrogen Supply LI
EA-63-1 SQN VENTING UNISOLATED COLD LEG ACCUMULATOR Rev. 0 1 2 Page4of5 4.2 Venting Nitrogen from Cold Leg Accumulators (Continued)
- 5. OPEN desired valve(s) to vent nitrogen from affected CLA(s):
OPEN VALVE DESCRIPTION FCV-63-127 Accumulator I Nitrogen Supply LI FCV-63-107 Accumulator 2 Nitrogen Supply LI Accumulator 3 Nitrogen Supply LI FCV-63-87 FCV-63-63 Accumulator 4 Nitrogen Supply LI
- 6. WHEN affected CLA(s) depressurized, THEN CLOSE valve(s) opened in Step 4.2. 5.:
VALVE DESCRIPTION FCV-63-127 Accumulator I Nitrogen Supply FCV-63-107 Accumulator 2 Nitrogen Supply FCV-63-87 Accumulator 3 Nitrogen Supply FCV-63-63 Accumulator 4 Nitrogen Supply
RETURN TO procedure and step in effect.
LI 8.
END OF TEXT
SQN EA-63-1 VENTING UNISOLATED COLD LEG ACCUMULATOR Rev. 0 1 2 Page5of5
5.0 REFERENCES
5.1 Drawings A. 1-47W811-1, Safety Injection System.
B. 2-47W811-1, Safety Injection System.
JPM Plant I Page 1 of 10 Rev. 0 SEQUOYAH NUCLEAR PLANT September2010 NRC Exam Plant I Spare Out a Vital Battery Charger
JPM Plant I Page 2 of 10 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: I Name I Signature DATE Performance Rating: SAT: UNSAT:
Validation Time: 15 minutes Total Time:
Performance Time: Start Time: Finish Time:
COMMENTS
JPM Plant I Page 3 of 10 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 1 25V DC Vital Power System 43
JPM Plant I Page 4 of 10 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 isatlOO%RTP.
- 2. All systems/components are OPERABLE.
- 3. All Technical Specification LCOs satisfied.
- 4. Electrical Maintenance has scheduled a PM on I 25V Vital Baffery Charger # I which requires unloading the charger.
- 5. All prerequisites of O-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 O-SO-250-I. (Maintenance requests that we do not tag the charger at this time).
- 2. Inform the Unit I SRO when the # I charger is out of service.
JPM Planti Page 5 of 10 Rev. 0 Job Performance Checklist:
STEP/STANDARD SAT/UNSAT STEP I.: Operator obtains appropriate procedure to spare out VB charger # I. SAT UNSAT STANDARD: Operator obtains 0-S0-250-1, section 8.1.1 to place Spare Charger 1-S in service in place of charger 1. Start Time STEP 2.: Ensure Power Checklist 0-250-1.09 has been performed (Spare Charger SAT 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.
STEP 3.: Ensure Power Checklist 0-250-1.10 has been performed. SAT
£! 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.
STEP 4.: ENSURE Spare Vital Battery Charger 1-S breakers are in OFF position. SAT A. 0-BKRC-250-QF/02-S, OUTPUT DC BKR is OFF UNSAT B. 0-BKRC-250-QF/01-S, INPUT AC BKR is OFF ue 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.
STEP 5.: Ensure timer for equalizing voltage on 1-S spare charger is set to Zero. SAT Timer is set on zero. UNSAT STANDARD: Operator verifies timer is on zero.
JPM Plant I Page 6 of 10 Rev. 0 Job Performance Checklist:
STEP/STANDARD SAT/UNSAT STEP 6.: IF 1 -S Spare 1 25V Vital Battery Charger 480V AC transfer Switch is to be SAT 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.
STEP 7.: ENSURE O-BKRA-250-KV!1$; Bkr From 480VSD/BD1A2.kToSpre: SAT 0/4Cyit1 W 1S, breaker isin the ON posttioçi UNSAT Cue: 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 ensures 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.
STEP 8.: If 1 -S Spare 1 25V Vital Battery Charger transfer switch is to be aligned to SAT 480V SD Bd 1 Bi -B (alternate supply) THEN UNSAT STANDARD: Operator N/As this step.
STEP 9 5Oterp1 SAT chaggpabejn QNosippn 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.
STEP 10 jOPJb SAT
?ti!3tiD ON pition 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.
JPM Plant i Page 7 of 10 Rev. 0 Job Performance Checklist:
STEP/STANDARD SAT/UNSAT STEP 1 1.: VERIFY spare charger is energized with output voltage between 131 and SAT 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.
STEP 12.: PLACE ALARM DISABLE switch on 1-S spare charger cabinet in ON SAT position.
UNSAT Cue: Switch is pointing to the ON position.
STANDARD: Operator rotates the ALARM DISABLE switch to the ON position [placing the alarm in service].
STEP 13.: ENSURE 0-BKRC-250-KW/1 -5, breaker to Vital Battery Bd I from Spare SAT Charger 1-S XSW is in the ON position.
(DC trans. Switch is next to the 1 S (spare) charger El. 749) UNSAT Cue Breaker is in the UP, ON position STANDARD: Operator locates DC transfer switch and verifies the breaker to the #1 VBB (Feeder to #1 Vital Battery Board Red Placard) is in the UP, closed position.
STEP 14.: PI4CE O-Efa25-D iLON;PPSfti onyital yr4U SAT Cue: Breaker is in the UP, ON position. UNSAT STANDARD: Operator locates breaker 225 (near bottom of board) and places it in the UP, ON position. Critical Step This step is critical to tie the spare charger onto the Vital Battery Board I.
STEP 15.: SAT pqitftoa 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.
JPM Plant i Page 8 of 10 Rev. 0 Job Performance Checklist:
STEP/STANDARD SAT/UNSAT STEP 16.: 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 1 37.5 volts.
STEP 1 7.: VERIFY 0-El..250-KE3-D Battery Board 1 Voltmeter is within 5 volts of SAT 0-EI-250-KE1 -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.
STEP 18.: 1° FQCbgerjj SAT P!
UNSAT A) -aKRc i-t2SVØC BTr CHGR I INPUt BiZ FFØsitipn
) O-BKR95p-QE102-D,125V DC BJTT CHGR I OVTPUrDC Bj(ftin Critical Step EFciiiQn 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.
JPM Plant i Page 9 of 10 Rev. 0 Job Performance Checklist:
STEP/STANDARD SAT/UNSAT 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 I isatlOO%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 I SRO when the # 1 charger is out of service.
I j/ Seq uoyah 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 V 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 UIC15 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 O-SO-250-1 UnitO Rev.0043 Page 8 of 177
- 3. 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.
Ahe 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.
(j4 When replacing annunciator type fuses in fuse columns A, B, C, or D, place the 7 fuse in the clip so that the blown fuse extension is toward the alarm bus.
Observe requirements of Sequoyah Safety and Health Manual, Part IV, when
/ working around batteries.
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.
The design operating limits for the 125v dc Vital Power System are 129V dc
(>.L4 When the 125 V Vital Battery Charger is transferred to its alternate
,X.- 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 Page9of 177 PRECAUTIONS AND LIMITATIONS (continued)
- Various breakers associated with the I 25V 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-ID
/ and 0-Pl-EBT-250-O01 .0
SQN 125 VOLT DC VITAL POWER SYSTEM 0-SO-250-1 Unit 0 Rev. 0043 Page 10 of 177 Date 7dty PREREQUISITE ACTIONS Throughout this Instruction where an IFITHEN statement exists, the step should be NIAd if the stated condition does not exist.
(jPJA ENSURE Instruction to be used is a copy of the effective
/ version.
0 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 I 25V 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 operations.
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 O-SO-250-1 Unit 0 Rev. 0043
, Pagellofl77 Date___
PREREQUISITE ACTIONS (continued)
ENSURE each performer documents their name and initials:
Print Name Initials Ay INDICATE below which performance section of this Instruction will be used.
U 5.0 STARTUP/STANDBY READINESS U6.O NORMAL OPERATION U 7.0 SHUTDOWN d8.O INFREQUENT OPERATION REASON: rrn 2
A ii iAara i 5eiv/c e 4 2i-,ane IAL/
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 Il 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-QFIOI -SI, 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 Battery Board I (continued)
NOTE Equipment referenced in the following two steps is located on the 480V AC Vital Transfer Switch 1-S.
[5] IF 10-XSW-250-KV-S1, Spare 480V AC Vital Transfer Switch 1-S, is to be aligned to 480V Shutdown Board 1A2-A, THEN
[5.1] VERIFY ac potential light is LIT.
[5.2] ENSURE [0-BKRA-250-KVII-S1, Bkr From 480V SD!BD 1A2-A To Spare 480V AC Vital XSW 1-S, breaker is in the ON position.
1st CV
[6] IF [0-XSW-250-KV-S1, Spare 480V AC Vital Transfer Switch 1-S,is to be aligned to 480V Shutdown Board 1B1-B, THEN
[6.1] CONSULT Engineering for concurrence and applicability of Tech Specs.
[6.2] IF Unit I is in Modes 1-4, THEN REMOVE 137kW of load from the 1BI-B 480 V Shutdown Board Transformer.
US/SRO
[6.3] VERIFY ac potential light is LIT. 0
[6.4] ENSURE [0-BKRA-250-KV12-S1, Bkr From 480V SD/BD IB1-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 Page 51 of 177 Date 8.1.1 Placing Spare Charger in Service to Vital Battery Board I (continued)
[7] PLACE [0-BKRC-250-QF/02-S1, SPARE 125 DC BATT CHGR 1-S OUTPUT DC BKR, spare charger cabinet in ON position.
I st CV
[8] PLACE [0-BKRC-250-QF/01-S], SPARE 125 DC BATT CHGR 1-S INPUT AC BKR, spare charger cabinet in ON position.
1 st 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 IALARM DISABLE] switch on 1-S spare charger cabinet in ON position.
NOTE Located on 1-S Spare 1 25V Vital Battery Charger 1 25V DC Transfer Switch on el 749 AB outside 125V Vital Batt Rm II.
[11] ENSURE [0-BKRC-250-KWII-S], 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 Page52of 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 [0-BKRC-250-KE1225-D1, SPARE 125V BATT CHGR 1-S ALT SUPPLY in ON position on Vital Battery Board I.
1st Cv
[13] PLACE F0-SW-250-KE/226-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 [0-EI-250-KE3-DI Battery Board I voltmeter is within 5 volts of [0-EI-250-KEI -Dl spare charger voltage. D
SQN 125 VOLT DC VITAL POWER SYSTEM 0-SO-250-1 UnitO Rev. 0043 Page 53 of 177 Date 8.1.1 Placing Spare Charger in Service to Vital Battery Board I (continued)
NOTE Placing either of the following breakers in the OFF position will result in annunciator window 1, 2-XA-55-IC (A4) actuation.
[16] PLACE the following breakers in OFF position on
[125V VITAL BATT CHGR Ii to shutdown the charger (located el. 749 A.B., outside 125V Vital Batt Rm I):
A. [0-BKRC-250-QEIOI-D1, 125V DC BATT CHGR I INPUT AC BKR. OFF 1 St CV B. [0-BKRC-250-QEIO2-D], 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 KIA Reference/Ratings: 061K3.02 (4.2/4.4) EO5EK1.1 (3.8/4.1) 061A3.01 (4.214.2) 191K1.08 (3.4/3.4) 061 A2.07 (3.4/3.5) 061A1 .01 (3.9/4.4) 061 A2.05 (3.1/3.4)
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.
ToolslEquipmentlProcedures Needed:
EA-3-10, 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 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 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 S/G # 3 has been established.
JPM Plant J Page 5 of 8 Rev. 0 Job Performance Checklist:
STEP/STANDARD SAT/U NSAT STEP 1.: Obtain a copy of the appropriate procedure. SAT UNSAT STANDARD: Operator obtains a copy of EA-3-1 0.
Start Time STEP 2.: SELECT applicable unit and pump. SAT U N SAT 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:
STEP/STANDARD SAT/UNSAT STEP 5.: ATTEMPT to control AFW LCVs from the Auxiliary Control Room
[panels L-I1A and L-11B].
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 SWITCH ES.
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-Fl-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-i 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 UNSAT STANDARD: Operator should N/A this step.
STEP 7.: Establish communications with U-i MCR UO. SAT UNSAT
. If guidance is requested, direct A UO 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:
STE PISTAN DARD SATIU NSAT STEP 8.: Ice 1 ordow A FWLCntream Visqtion v*e SAT UNSAT Cue: Valve handwheel moves several turns in the clockwise direction.
IF operator calls MCR: Give AFW flow to #3 SIG 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.: SAT bI 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 Role play as UO and report that recirculation valves have been UNSAT operated STANDARD: Operator informs the UO to operate valves.
JPM Plant J Page 8 of 8 Rev. 0 Job Performance Checklist:
STE PISTAN DARD SAT/U NSAT STEP 12.: Inform the Unit 1 US that AFW flow to #3 SIG is being controlled. SAT U N SAT STANDARD: Operator informs the Unit 1 US that AFW flow to #3 SIG is being controlled.
CUE: 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 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 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 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 I 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 PREPARED/PROOFREAD BY:
RESPONSIBLE ORGANIZATION:
W. T. LEARY OPERATIONS 6
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-3-118B & -128Bj 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:
o Controlling AFW flow from Aux CR or by throttling LCV isolation valves (LCV failure).
- 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. FR-S.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-3-1 0 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:
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-l 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 SIGs desired OR SIG pressure less than 300 psig, THEN NOTIFY UD to close applicable MD AFW LCVs USING MANUAL BYPASS:
MD AFW PUMP MD AFW LCV VALVE CLOSED V
A-A LCV-3-1 64A LCV-3-156A El B-B LCV-3-148A LI LCV-3-171A El
- a. PLACE transfer switch [XS-3-1181 in AUXILIARY.
[6900 V Shutdown Board 1 (2)A-A, Compartment 10) El
- c. IF AFW Train A flow less than 300 gpm, THEN NOTIFY UO to ensure recirculation valve [FCV-3-4001 open.
SQN EA-3-1O 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 I (2)B-B, Compartment 10]
- c. IF AFW Train B flow less than 300 gpm, THEN NOTIFY UO to ensure recirculation valve [FCV-3-4011 open. El
- 4. GO TO Section 4.1, step in effect.
END OF SECTION
SQN EA-3-1O ESTABLISHING MOTOR DRIVEN AFW FLOW Rev. I 1,2 Page7ofl3 4.3 MD AFW LCV Valve or Controller Failure
[Panels L-1 1A and L-1 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. E
AT LEAST VALVE ONE PER SIC SIG NUMBER DESCRIPTION LOCATION CLOSED VI VLV-3-828 Upstream isolation Aux Bldg, elev 714, AFW mezzanine 1 Downstream isolation In WWR VLV-3-836 Upstream isolation Aux Bldg, elev 714, VLV-3-827 AFW mezzanine 2 Downstream isolation Above WVVR ii VLV-3-835 entrance Upstream isolation Aux Bldg, elev 714, VLV-3-826 AFW mezzanine Downstream isolation Above WVVR VLV-3-834 entrance Upstream isolation Aux Bldg, elev 714, VLV-3-829 AFW mezzanine VLV-3-837 Downstream isolation In WVVR LI
SQN EA-3-1O 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 UO by throttling AFW LCV isolation valve(s) closed in Step 4.3. 4.:
VALVE LOCATION THROTTLED SIG DESCRIPTION NUMBER Upstream isolation Aux Bldg, elev 714, LI VLV-3-828 AFW mezzanine VLV-3-836 Downstream isolation In WVVR LI Upstream isolation Aux Bldg, elev 714, VLV-3-827 AFW mezzanine 2 VLV-3-835 Downstream isolation Above WWR LI entrance VLV-3-826 Upstream isolation Aux Bldg, elev 714, LI AFW mezzanine VLV-3-834 Downstream isolation Above WVVR LI entrance Upstream isolation Aux Bldg, elev 714, LI VLV-3-829 AFW mezzanine VLV-3-837 Downstream isolation In WVVR LI
- 7. NOTIFY UO to operate pump recirculation valves as follows:
MD AFW PUMP VALVE I OPEN IF PUMP FLOW I CLOSED IF PUMP FLOW NUMBER LESS THAN 300 GPM_[_GRE ATER THAN 300 GPM A-A FCV-3-400 LI LI B-B FCV-3-401 LI LI
- 8. GO TO Section 4.1, step in effect.
END OF SECTION
SQN EA-3-lO 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, OPERABLE U recirc isolation at SA3 (SA12)
MD AFW Pump A-A VLV-3-936 Aux Bldg, elev 690, OPEN LI recirc isolation at SA3 (SAl 2), 5 ft off floor MD AFW Pump A-A VLV-3-938 Aux Bldg, elev 690, OPEN LI recirc isolation at SA3 (SA12), 5 ft off floor MD AFW Pump A-A VLV-3-803 Aux Bldg, elev 690, OPEN U suction isolation by AFW Pump A-A MD AFW Pump B-B FCV-3-401 Aux Bldg, elev 690, at SA4 (SA13) OPERABLE LI recirc isolation Aux BIdg, elev 690, MD AFW Pump B-B VLV-3-940 at SA4 (between SA13 & SA14), 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 U 5 ftoff floor MD AFW Pump B-B VLV-3-804 Aux Bldg, elev 690, OPEN LI suction isolation by AFW Pump B-B Condensate supply 0-VLV-3-800 Aux Bldg, elev 690, OPEN LI isolation southwest corner, 15 ft off floor CST A supply 0-VLV-2-504 Turbine Bldg, elev 685, OPEN LI to AFW isolation above centrifuge CST B supply 0-VLV-2-505 Turbine Bldg, elev 685, OPEN LI to AFW isolation above centrifuge
- 2. IF any valve NOT in required condition, THEN CONSULT TSC for contingency action.
SQN EA-3-1 0 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-lO ESTABLISHING MOTOR DRIVEN AFW FLOW Rev. I 1,2 Pagellofl3 4.5 Isolating MD AFW Pump Recirculation Lines
- 1. PLACE applicable pump transfer switch in AUX position:
MD AFW PUMP TRANSFER SWITCH LOCATION RECIRCULATION VALVE SWITCH FCV-3-400 XS-3-400 Auxiliary Control Room, L-1 1A FCV-3-401 XS-3-401 Auxiliary Control Room, L-1 1 B
- 2. IF Step 4.5. 1. NOT effective OR manual isolation preferred, THEN CLOSE applicable MD AFW pump recirculation isolation valve:
LOCATION CLOSED VALVE DESCRIPTION V MD AFW Pump A-A Aux Bldg, elev 690, at 5A3 (SA12),
VLV-3-938 recirculation isolation 5 ft off floor MD AFW Pump B-B Aux Bldg, elev 690, at SA4 (between VLV-3-942 SA12 and SA13), 5 ft off floor recirculation isolation
- 3. GO TO Section 4.1, step in effect.
END OF SECTION
SQN EA-3-lO ESTABLISHING MOTOR DRIVEN AFW FLOW Rev. I 1,2 Pagel2ofl3 4.6 Aligning MD AFW Pump Suction to ERCW IF aligning MD AFW Pump A-A suction to ERCW, THEN PERFORM the following:
- a. CLOSE ERCW tell tale drain valve [FCV-3-807I.
[Aux Bldg, elev 690, by MD AFW pump]
- b. NOTIFY UO to ensure ERCW to MD AFW Pump A-A suction valves [FCV-3-116A] and rFcv-3-116B1 are open. El
- a. CLOSE ERCW tell tale drain valve [FCV-3-8081. El
[Aux BIdg, elev 690, by MD AFW pump]
- b. NOTIFY UO to ensure ERCW to MD AFW Pump B-B suction valves rFCv-3-126A] and IFCV-3-126B1 are open. El
- 3. GO TO Section 4.1, step in effect. El END OF TEXT
SQN EA-3-1O ESTABLISHING MOTOR DRIVEN AFW FLOW Rev. I 1,2 Pagel3ofI3
5.0 REFERENCES
5.1 Drawings A. 1, 2-47W803-2, Auxiliary Feedwater.
JPM INPLANT K Page 1 of 10 Rev. 0 SEQUOYAH NUCLEAR PLANT JOB PERFORMANCE MEASURE INPLANT K (ROISRO)
Local Alignment of 2-RM-90-112 to Lower Containment
JPM INPLANT K Page 2 of 10 Rev. 0 ROISRO JOB PERFORMANCE MEASURE Task: Local Alignment of 2-RM-90-112 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 KIA 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 / 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 10 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:
2-SO-90-2, Sections 5.1 and 8.3
References:
Reference Title Rev No.
- 1. 2-SO-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 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. 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 2-RM-90-1 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 10 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 1.: Obtain copy of procedure. SAT UNSAT STANDARD: 2-SO-90-2 Section 8.3 is identified as appropriate procedure. Start Time_____
COMMENT:
STEP 2.: [1J ENSURE 2-RM-90-1 12 Upper Containment Rad Monitor in SAT service per the following:
U NSAT
[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.: [bJ 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: T.he 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 10 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-90-106 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-90-106 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 10 Rev. 0 Job Performance Checklist:
STEP / STANDARD SAT I UNSAT STEP 10.: [7] ALrf[o jiJaj I1 SAT UNSAT tal IF étarting 2-RM-90-1 12 sample pump, THEN DEPRESS one of thejoi[owing local tartn 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 2-RM-90-106 sample pump, THEN..
STANDARD: Operator N/As this step UNSAT COMMENT:
STEP 12.: [c} NOTIFY MIG to adjust flow as required. SAT Cue: MIG has been contacted and will monitor flow. UNSAT STANDARD: Operator contacts MIG for support.
COMMENT:
STEP 13.: [d] IF flow cannot be established through the Rad Monitor THEN Cue: Flow has been established through 2-RM-90-112.
STANDARD: Operator N/As this step COMMENT:
JPM INPLANT K Page 7 of 10 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 14.: [e] IF placing [2-RM-90-1 12] in service THEN RESET
[2-HS-90-1 1 2F] 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.: [f] 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 12B, Window A-2 and 2-RA-90-1 12C, Window A-3 on MI2D are DARK. Operator N/As alarms associated with 2-RM-90-1 06.
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 10 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 U N SAT Source check is not required.
STANDARD: Operator N/As step.
COMMENT:
STEP 21.: f4: siVq:28 SAT Lo gmpmenad 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 INPLANT K Page 9 of 10 Rev. 0 Job Performance Checklist:
STEP I STANDARD SAT I UNSAT STEP 22.: Unit 2 CR0 informed that 2-SO-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 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. 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 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).
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-S0-90-2 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.
(To 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 LCO 3.3.3.1 and action 19 of LCO 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, or6.
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 r the Condenser Vacuum Exhaust. Both monitors should not be in service at the pme time for extended periods, due to flow limitations.
(42-RM-9o-1 06!2-RM-90-400 local sample pump handswitches have AUTO-OFF HAND positions. Normally AUTO position is used if starting/stopping pumps from the MCR (2-Rl-90-106A12-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.
JEREQUISITE ACTIONS Throughout this Instruction, where an IF/THEN statement exists, the step should be NIA if the condition does not exist.
,KENSURE the Instruction to be used is a copy of the effective version.
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:
El 5.0 STARTUP/STANDBY READINESS El 7.0 SHUTDOWN 8.0 INFREQUENT OPERATION REASON: 2-em- o-//2 747 /Oqiek (jç,a 1
Sec-4 8.3
GASEOUS PROCESS RADIATION 2-S0-90-2 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-90-1 12 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
[2-JBOX-90-3919], 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]. LI NOTE High background count rate may mask the source and prevent an upward deflection when source check is performed. Source check of RE-90-1 12 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-90-1 12.
GASEOUS PROCESS RADIATION 2-S0-90-2 MONITORING SYSTEM Rev: 37 Page 48 of 75 Date 8.3 Aligning Containment Upper Compartment Monitor to Lower Compartment (Continued)
[4] OPEN [2-ISIV-90-283G1 Crosstie Valve Between Upper and Lower Compartment Rad Monitors.
1st IV
[5] ENSURE the following FCVs are OPEN:
VALVE NO. INITIALS 2-FCV-90-108 1st iv 2-FCV-90-109 1st 2-FCV-90-107 1st 2-FCV-90-117 1st 2-FCV-90-1 16 1st IV
[6] ENSURE [2-RM-90-1121 is operable by verifying the following:
- Power ON fight illuminated. E
- Instrument malfunction alarms clear.
- CPM reading of at least background level.
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 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 LowerCompartment 290202 2 Air_Monitor Containment Bldg 2RM90112 Upper Compartment 2-90-2.03 3 Air_Monitor
GASEOUS PROCESS RADIATION 2-SO-90-2 MONITORING SYSTEM Rev: 37 Page 11 of 75 Date 5.1 Placing Containment Building Upper and Lower Compartment Air Monitors in Service (Continued)
[3] IF placing 2-RM-90-106 in service, THEN ENSU RE [2-ISIV-90-283G] Crosstie Valve Between Upper and Lower Compartment Rad Monitors is CLOSED (Valve Checklist 2-90-2.03).
NOTE I Heat Trace handswitches 2-HS-90-106 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):
HANDSWITCH 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]. E
GASEOUS PROCESS RADIATION 2-SO-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-90-112 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 Pump 2 START
[b] IF starting [2-RM-90-106] sample pump, THEN I. ENSURE [HS-90-106B1 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-Pl-IPM-90-1 06.0.
- 3. DEPRESS one of the following pushbuttons, AND CHECK PB illuminated: (N/A other)
LOCATION UNID PUSHBUTTON PB ILLUMINATED -J INITIALS Local 2-Rl-90-106B FLOW Li MCR 2-RI-90-106A FLOW Li
GASEOUS PROCESS RADIATION 2-SO 2 MONITORING SYSTEM Rev: 37 Page 13 of 75 Date 5.1 Placing Containment Building Upper and Lower Compartment Air Monitors in Service (Continued)
[ci NOTIFY I & C to adjust flow as required using 2-Sl-IFT-090-1 12.0, Functional Test of Containment Building Upper Compartment Air Monitor 2-R 112.
[d] IF flow cannot be established through the Rad Monitor, THEN NOTIFY Unit Operator.
[e] IF placing 12-RM-90-112] in service, THEN RESET [2-HS-90-1 12F1 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-90-1 06B 0-XA-55-1 2D A-5 2-RA-90-106C 0-XA-55-12D A-6 2-RA-90-1 1 2B 0-XA-55-1 2D 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-Rl-90-106A (MCR).
SQN GASEOUS PROCESS RADIATION 2-SO-90-2 MONITORING SYSTEM Rev: 37 2 Pagel4of75 Date 5.1 Placing Containment Building Upper and Lower Compartment Air Monitors in Service (Continued)
NOTE If placing 2-RM-90-106 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 Alt Plant K Page 1 of 8 Rev. 0 SEQUOYAH NUCLEAR PLANT September 2010 NRC Exam Plant K (Alt) (ROISRO)
Respond to Decreasing RCS Pressure and Level From the Aux. Control Room
JPM Alt Plant K Page 2 of 8 Rev. 0 ROISRO JOB PERFORMANCE MEASURE Task: Respond to Decreasing RCS Pressure and Level From the Aux. Control Room TASK #: 0000680501 (RO)
Task Standard: The operator terminates the pressure and level reduction in the RCS (PZR) per AOP-C.04.
Time Critical Task: YES: NO: X KIA Ratings: 068AA1 .12 (44/4.4) 068AA1 .21 (3.9/4.1) 068AA2.06 (4.1/4.3) 068AK 2.01 (3.914.0)
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 Alt Plant K 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 backup control room.
- 4. 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:
Most current revision of AOP-C.04 Appendix C.
Simulate having Fuse pullers
References:
Reference Title Rev No.
A. AOP-C.04 Control Room Inaccessibility 20
JPM Alt Plant K 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. Both units were manually tripped and the control room has been abandoned.
- 2. Operations personnel are performing checklists for abandoning MCR and are in the process of transferring controls to the auxiliary position.
- 3. RCS pressure on UI is currently 2200 psi, Pzr level is 25%.
- 4. RCS pressure on U2 is currently 2200 psi, Pzr level is 25%.
INITIATING CUES:
I. You have observed pressurizer pressure and level decreasing abnormally on UNIT One.
- 2. You have been directed to perform AOP-C.04 Appendix C to take the appropriate actions relative to the UI RCS pressure and level decrease.
- 3. Inform the SM when the AOP-C.04 Appendix C actions have been completed to address the UI RCS pressure and level decrease.
JPM Plant k Page 5 of 8 Rev. 9 Job Performance Checklist:
STEP/STANDARD SAT/UNSAT STEP 1.: Obtain copy of the appropriate procedure. SAT UNSAT STANDARD: Operator obtains a copy of AOP-C.04, Appendix C.
Start Time COMMENTS:
STEP 2 IF RCS rJsur dppn nioir SAT
?re!ptheAg)cposltlpn , r 0
E i Iiim i As each switch is located and addressed: The transfer switch is in the Critical Step AUX position.
STANDARD: Operator locates the listed transfer switches and simulates placing each switch in the Aux. position.
This step is critical to transfer controls to the Aux. CR panel.
COMMENTS:
STEP 3.: ENSURE pressurizer PORVs CLOSED [1-L-10]: SAT Cue: PCV-68-334 and 340 have GREEN light only. UNSAT If RCS pressure is checked THEN state, Pressure is still decreasing STANDARD: Operator locates switches 1-HS-68-334C and 340C and verifies green lamps ON.
STEP 4.: IF Unit I RCS T-Cold is less than 540°F AND dropping uncontrolled, SAT THEN ENSURE transfer switches for MSIVs and S\G atmospheric reliefs have been UNSAT placed in AUX position and S\G atmospheric relief valves closed.
Cue. RCS temperature is 542° and stable.
STANDARD: Operator N\As this step based on S\G pressure indicators and corresponding Tsat temperatures. (1-Pl-1-1C, 8C, 19C and 26C)
JPM Plant k Page 6 of 8 Rev. 9 Job Performance Checklist:
STE PISTAN DARD SATIUNSAT STEP 5.: IF Unit 1 pressurizer level is dropping uncontrolled, THEN ENSURE transfer switches for normal and excess letdown valves (on Checklist
- 1) have been placed in the AUX position. [1 -L-1 1 A and 118] UNSAT
£! Another UO has transferred these switches to the AUX position per Checklist 1.
STANDARD: Operator verifies the listed transfer switches have been placed in the AUX position.
STEP 6.: ENSURE norrnaFand excess Iét own iSoIated fl-L-lOj SAT
- 1-FCV-62-72 CLOSED UNSAT
- 1FCV.62-73 CLOSED
- 1-FCV-62-74 CLOSED
- I -FCV-62-54 CLOSED
- 1 -FCV-62-55 CLOSED
- 1-FCV-62-56 CLOSED (1-HIC-62-56C)
Critical Step Cue 1: When operator verifies valve position, cue him that 62- 72 and 62-74 have RED lights dark and GREEN lights lit. FCV-62-73 has a RED light lit and GREEN light dark.
Cue 2: When operator places valve HS to CLOSE position, cue him that 62-73 has a RED light dark and GREEN light lit.
Cue 3: When operator verifies valve position, cue him that 62-54, 55 have RED lights dark and GREEN lights lit; 1-HIC-62-56C indicates 0.
STANDARD: Operator verifies I -FCV-62-72, 74 are closed and closes I -FCV-62-73.
Operator verifies 1 -FCV-62-54, 55, and 56 are closed.
This step is critical to isolate the letdown flowpath by closing FCV-62-73.
COMMENTS:
JPM Plant k Page 7 of 8 Rev. 9 Job Performance Checklist:
STEP/STANDARD SAT/UNSAT STEP 7.: ENSURE the following fuses for Unit 1 head vent valves REMOVED: SAT UN SAT NOTE: Do not allow operator to open any panel doors in the Vital Battery Board rooms.
NOTE: There is no means of verifying valve position outside the main control room.
CUE: Inform the UO that the pressure and level drop have stopped and have now stabilized.
STANDARD: Locates fuses for I -FCV-68-394 & 397 and 1 -FCV-68-395 & 396. Simulates pulling fuses.
1-ESV-68-394, 397 125 Battery Bd. I, CKT B14 (O-FU2-25OKEB1 4-D) 1-FSV-68-395, 396 125 Battery Bd. II, CKT A30 (O-FU2-250-KFA3O-E)
This step is critical to remove power from the head vent valves which will fail them closed.
COMMENTS:
STEP 8.: Inform the SM that the RCS (PZR) pressure and level drops have been SAT stopped and those parameters are now stable.
UNSAT STANDARD: Operator informs SM that AOP-C.04 Appendix C actions have been completed to address the UI RCS pressure and level decrease.
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. 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 that may have relays mounted on them.
WHEN ENTERING A UNIT TRIP HAZARD ZONE ENSURE YOU DO NOT TOUCH ANY SWITCHES WITHIN THAT ZONE.
INITIAL CONDITIONS:
I. Both units were manually tripped and the control room has been abandoned.
- 2. Operations personnel are performing checklists for abandoning MCR and are in the process of transferring controls to the auxiliary position.
- 3. RCS pressure on UI is currently 2200 psi, Pzr level is 25% and stable
- 4. RCS pressure on U2 is currently 2200 psi, Pzr level is 25% and stable.
INITIATING CUES:
I. You have observed pressurizer pressure and level decreasing abnormally on UNIT One.
- 2. You have been directed to perform AOP-C.04 Appendix C to take the appropriate actions relative to the UI RCS pressure and level decrease.
- 3. Inform the SM when the AOP-C.04 Appendix C actions have been completed to address the UI RCS pressure and level decrease.
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT AOl PROGRAM MANUAL ABNORMAL OPERATING PROCEDURES AOP-C.04 SHUTDOWN FROM AUXILIARY CONTROL ROOM Revision 20 QUALITY RELATED VP PREPARED/PROOFREAD BY: D. A. Porter RESPONSIBLE ORGANIZATION: OPERATIONS APPROVED BY: A. S. Bergeron EFFECTIVE DATE: 1/15/2010 REVISION DESCRIPTION: Revised to change time limit for isolating VCT from 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to 70 minutes. This is an interim action for SR 112172.
ANY INTENT CHANGE TO THIS PROCEDURE WHICH IS NOT DIRECTLY RELATED TO A DCN REQUIRES EVALUATION OF FIRE PROTECTION LICENSE CONDITION USING FPDP-3.
THIS PROCEDURE CONTAINS TIME CRITICAL ACTIONS
AOP-C.04 SQN SHUTDOWN FROM AUXILIARY CONTROL ROOM Rev. 20 Page 1 of 2 APPENDIX C STABILIZING UNIT I RCS PARAMETERS IF Unit 1 RCS pressure dropping uncontrolled, THEN PERFORM the following:
- a. ENSURE the following transfer switches in AUX position:
SWITCH EQUIPMENT NAME LOCATION AUX POSITION J 1-XS-68-340C Pressurizer PORV 1-L-1 1A LI 1-XS-68-334C Pressurizer PORV 1-L-1 1 B LI
- b. ENSURE pressurizer PORVs CLOSED [1-L-10]:
- 1-PCV-68-334 LI
- 1 PCV-68-340 LI
- 2. IF Unit I RCS T-cold is less than 540°F AND dropping uncontrolled, THEN PERFORM the following:
- a. ENSURE transfer switches for MSIVs and S!G atmospheric reliefs (on Checklist 1) have been placed in AUX position. [1 -L-1 1 A and 11 B] LI
- b. ENSURE Unit 1 S!G atmospheric relief valves CLOSED. [1-L-1O] LI Page 119 of 184
AOP-C.04 SQN SHUTDOWN FROM AUXILIARY CONTROL ROOM Rev. 20 Page 2 of 2 APPENDIX C
- 3. IF Unit 1 pressurizer level is dropping uncontrolled, THEN PERFORM the following to isolate letdown paths:
- a. ENSURE transfer switches for normal and excess letdown valves (on Checklist 1) have been placed in AUX position. [1 -L-1 1 A and 1 1 B] LI
- b. ENSURE normal and excess letdown isolated: [1-L-1O]
- 1-FCV-62-72 CLOSED LI
- 1-FCV-6273 CLOSED LI
- 1-FCV-62-74 CLOSED LI
- 1-FCV-62-54 CLOSED LI
- 1-FCV-62-55 CLOSED LI
. 1-FCV-62-56 CLOSED (1-HIC-62-56C) LI
- c. ENSURE the following fuses for Unit 1 head vent valves REMOVED:
VALVES FUSE LOCATION FUSE ID REMOVED 1 -FSV-68-394 LI 125V Vital Battery Board I, Ckt B14 O-FU2-250-KEB14-D 1-FSV-68-397 1 -FSV-68-395 LI 125V Vital Battery Board II, Ckt A30 O-FU2-250-KFA3O-E 1-FSV-68-396 END OF TEXT Page 120 of 184