ML100830090
| ML100830090 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 02/11/2010 |
| From: | NRC/RGN-II |
| To: | Tennessee Valley Authority |
| References | |
| 50-390/09-302 | |
| Download: ML100830090 (299) | |
Text
WATTS BAR NUCLEAR PLANT B.1.a Nov. 2009 NRC Exam B.1.a 8.1.a Complete 1-SI-85-2, 1-51-85-2, Reactivity Control Systems Movable Control Assemblies (Modes 1 and 2)
PA~F PA(~F 1 OF 1~
WATTS BAR NUCLEAR PLANT B.1.a Nov. 2009 NRC Exam EVALUATION SHEET Task: Complete 1-SI-85-2, Reactivity Control Systems Movable Control Assemblies (Modes 1 and 2)
Alternate Path: None Facility JPM #: New Safety Function: 1
Title:
Reactivity Control KIA 001 A4.03 Ability to manually operate and/or monitor in the control room: CRDS mode control.
Rating(s): 4.0/3.7 CFR: 41.7/45.5 to 45.8 Preferred Evaluation Location: Preferred Evaluation Method:
Simulator x In-Plant Perform - x - - Simulate X
References:
1-SI-85-2,"Reactivity Control Systems Movable Control Assemblies (Modes 1 and 2)," Rev. 11.
Task Number: RO-085-S01-85-2-001
Title:
Verify operability of each control bank/shutdown bank.
Task Standard: Applicant inserts and withdraws Control Bank D 0 rods 10 steps, returning the bank to its original position. Applicant returns the 1-RBSS Rod Bank Select switch to the AS-FOUND position (AUTOMATIC).
Validation Time: 10 minutes Time Critical: Yes
- - No - X- - - -
--=-=---
===============================================================
===============================================================
Applicant: Time Start:
NAME SSN Time Finish: _ __
Performance Rating: SAT UNSAT Performance Time Examiner:
--------------------~/-----
~/__-
NAME SIGNATURE DATE
===============================================================
===============================================================
COMMENTS PAr,F PA(';F?? ()F OF 11~
~
WATTS BAR BARr~UCLEAR r4UCLEAR PLANT B.1.a Nov. 2009 NRC Exam SIMULATOR OPERATOR INSTRUCTIONS:
- 1. ENSURE NRC Examination Security has been established.
- 2. Right click on 339, and then select RESET.
- 3. Enter the password.
- 4. Select "Yes" on the INITIAL CONDITION RESET pop-up window.
- 5. Place 1-RBSS Rod Bank Selector switch in the CBC (Control Bank C) position on 1-M-4.
- 6. Place simulator in RUN and acknowledge any alarms.
- 7. ENSURE a marked-up copy of 1-SI-85-2 1-51-85-2 is available to the Examiner.
- 8. ENSURE "Extra Operator" is present in the simulator.
- 9. Place simulator in FREEZE until Examiner cue is given.
PAGE 3 OF 13
REV. 0 PAGE 4 OF 13 WATTS BAR NUCLEAR PLANT B.1.a Nov. 2009 NRC Exam READ TO APPLICANT DIRECTION TO APPLICANT:
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:
- 1. Unit 1 is operating at 100% power.
- 2. Performance of 1-SI-85-2,"Reactivity Control Systems Movable Control Assemblies (Modes 1 and 2)," is in progress.
- 3. The procedure has been completed through Section 6.7 for Control Bank C.
INITIATING CUES:
- 1. The Unit Supervisor has directed you to complete 1-SI-85-2,"Reactivity Control Systems Movable Control Assemblies (Modes 1 and 2)."
- 2. Notify the Unit Supervisor when the control rods are returned to the "AS FOUND" position."
11 PAr,F 4 OF 1::\
WATTS BAR NUCLEAR PLANT B.1.a
)
Nov. 2009 NRC Exam
~I-----------------sT-E-P-/s-T-A-N-D-A-R-D----------------~-S-A-TI-U-N-SA-T-O STEP/STANDARD SAT/UNSAT START TIME: _ _ ___
NOTE 1 Between rod bank movements, Tavg - Tref deviation may be adjusted using manual rod control or by adjusting turbine load.
NOTE 2 Rod movement is verified by monitoring (RPls) and Step Counters.
STEP 1: [1] ENSURE Tavg - Tref deviation is adjusted to allow for bank - SAT movement of ten steps.
STANDARD: - UNSAT Applicant determines that the Tavg - Tref deviation is sufficient for bank movement.
~
COMMENTS:
) I NOTE 1-XA-55-4B-87A, 1-XA-55-4B-87A, ROD INSERTION LIMIT LO, may actuate during the following test sections.
NOTE TO EVALUATOR: COLR Figure 1,"Control Bank Insertion Limits versus Thermal Power - Four Loop Operation," gives the 100% power Insertion Limit as 177 steps on Control Bank D. The 87-A, ROD INSERTION LIMIT LO, alarm is received at 10 steps above the actual insertion limit (187 steps).
PAGE 5 OF 13
WATTS BAR NUCLEAR PLANT B.1.a Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 2: [2] RECORD the initial position of the following Step Counters: SAT 1-CBOG1, 1-CBDG1, CONTROL BANK 01: D1: _ _ _ _ _ _ steps. UNSAT 1-CBDG2, CONTROL BANK 02:
1-CBOG2, D2: _ _ _ _ _ _ steps.
STANDARD:
Applicant records rod position for Control Bank 0 D group 1 rods as 220 steps from demand counter 1-CBOG1 1-CBDG1 on 1-M-4.
Applicant records rod position for Control Bank 0D group 2 rods as 220 steps from demand counter 1-CBOG2 1-CBDG2 on 1-M-4.
COMMENTS:
NOTE The applicant has the option of moving Control Bank D five Steps in one direction, then 10 steps in the opposite direction and then return to normal.
This method will have less overall effect on reactor power.
STEP 3: [3] PLACE 1-RBSS, ROD BANK SELECT, in CBD. CRITICAL STEP STANDARD:
SAT Applicant places 1-RBSS, Rod Bank Select switch, in the CBOCBD (control bank 0)
D) position. UNSAT Step is critical to allow movement of Control Bank D rods ONLY.
COMMENTS:
NOTE 1-XA-55-4A-64F, C-11 BANK D AUTO WITHDRAWAL BLOCKED, will actuate if Control Bank D Rods are withdrawn past 220 Steps.
PAGE 6 OF 13
WATTS BAR NUCLEAR PLANT B.1.a Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 4: [4] MOVE Control Bank D 0 at least ten Steps in anyone direction, as CRITICAL indicated on the appropriate Step Counter, and VERIFY movement STEP of the rods in the proper direction is indicated on the appropriate RPls. (Acc Crit) SAT STANDARD: UNSAT Applicant may either comply with the information contained in the NOTE preceding Step 3 OR insert rods ten steps, or then withdraw the rods back to their original position.
Step is critical since it used to determine if Control Bank D motion meets acceptance criteria of the surveillance procedure.
COMMENTS:
PAGE 70F 7 OF 13
WATTS BAR NUCLEAR PLANT B.1.a Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 5: [5] VERIFY Control Bank 01 and 02 Step Counters agree within plus SAT or minus 2 steps.
UNSAT STANDARD:
Applicant determines from 1-CBOG1 and 1-CBOG2 Step counter positions
+/- 2 step limit.
that rods are within the +/-
COMMENTS:
PAGE 8 OF 13
WATTS BAR NUCLEAR PLANT B.1.a Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 6: [6] RETURN Control Bank 0 to its original position as recorded CRITICAL in Step [2] of this section using 1-FLRM, ROD MOTION STEP CONTROL.
SAT STANDARD:
UNSAT Applicant returns Control Bank D 0 group 1 and group 2 rods to their original position of 220 steps.
Step is critical to ensure rod position is properly input into the bank overlap unit.
COMMENTS:
PAGE 9 OF 13
WATTS BAR NUCLEAR PLANT B.1.a
) Nov. 2009 NRC Exam
~I----------------~ST=E~P~/S~T~A-N~D-A-R-D----------------~-s-A=n~u~N-sA-T-O STEP/STANDARD SAT/UNSAT STEP 7: [7] IF Rod Insertion Limit Lo Alarm 87 -A does not clear, THEN 87-A SAT
- REFER TO Tech Spec LCO 3.1.7. UNSAT
- CONTACT System Engineer to reset 87-A USING ICS.
STANDARD:
Applicant states that the Rod Insertion Limit Lo alarm was not received during rod exercise and N/As this conditional step.
COMMENTS:
I PAGE 10 OF 13
WATTS BAR NUCLEAR PLANT B.1.a Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT Section 6.9, Restoration CAUTION If rod movement demand exists via any of the following methods, the rod bank select switch should be moved through AUTO rapidly to avoid undesired rod movement:
- Tavg is not within 1°F of program,
- Less than 5 minutes has elapsed since any change in rod control input (Le, Tavg, Tref, or NIS),
- Demand is indicated on the Computer Enhanced Rod Position Indication (CERPI) monitors [1-M-4].
STEP 8: [1] PLACE 1-RBSS, ROD BANK SELECT, in MANUAL. SAT STANDARD: UNSAT Applicant rotates handswitch 1-RBSS counterclockwise from the CBO CBD position to the MANUAL position.
COMMENTS:
STEP 9: [2] IF Tavg not on program, THEN RETURN Tavg - Tref within 1.5°F. SAT STANDARD: UNSAT Applicant determines that Tavg is on program, and N/As this conditional step.
COMMENTS:
PAGE 11 OF 13
WATTS BAR NUCLEAR PLANT B.1.a
)
Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT SATIUNSAT STEP 10: [3] RETURN 1-RBSS, ROD BANK SELECT, to the as found position CRITICAL recorded in Section 4.3, Step [2] (page 6 of 17). STEP STANDARD: SAT Applicant returns 1-RBSS to the AUTO position, since this was recorded as UNSAT the AS FOUND position in Section 4.3, Step [2].
Step is critical to returning the rod control system to the correct operational mode.
Applicant reports to the Unit Supervisor that 1-SI-85-2 actions have been completed.
EXAMINER CUE: Acknowledge report.
COMMENTS:
)
END OF TASK STOP TIME _ __
/
PAGE 12 OF 13
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
DIRECTION TO APPLICANT:
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:
- 1. Unit 1 is operating at 100% power.
- 2. Performance of 1-SI-85-2, "Reactivity Control Systems Movable Control 1-SI-85-2,"Reactivity Assemblies (Modes 1 and 2)," is in progress.
- 3. The procedure has been completed through Section 6.7 for Control Bank C. .
INITIATING CUES:
- 1. The Unit Supervisor has directed you to complete 1-SI-85-2,"Reactivity Control Systems Movable Control Assemblies (Modes 1 and 2)."
- 2. Notify the Unit Supervisor when the control rods are returned to the "AS FOUND" position."
TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT SURVEILLANCE INSTRUCTION 1-SI-85-2 REACTIVITY CONTROL SYSTEMS MOVABLE CONTROL ASSEMBLIES (MODES 1 AND 2)
) Revision 11 Unit 1 QUALITY RELATED PREPARED BY: John Lovell SPONSORING ORGANIZATION: Operations APPROVED BY: Craig Faulkner Effective Date: 09/20104 LEVEL OF USE: CONTINUOUS
WBN REACTIVITY CONTROL SYSTEMS MOVABLE 1-SI-85-2 1 CONTROL ASSEMBLIES Revision 11 (MODES 1 AND 2) Page 2 of 17 REVISION LOG REVISION OR AFFECTED CHANGE EFFECTIVE PAGE NUMBER DATE NUMBERS DESCRIPTION OF REVISION/CHANGE 7 12/18/03 2,4,5 Non-intent. Deleted reference to Rod Control PIA converter consistent with this device's removal from the plant design via DCN 51072. Also deleted reference to IMI-85.005 which has been canceled.
8 12/18/03 2,11-14 Non-intent. Added steps to refer to LCO 3.1.7 and to contact System Engineer to reset alarm 87 -A if it does not clear (PER 03-018261-000). Also made editorial corrections.
9 3/17/04 2,13 Non-intent. Changed note prior to Section 6.0, Step 47 to reference annunciator 64-F instead of 87-C due to DCN 51620.
10 7/12/04 2,6,11-14 Non-intent. Revised Step 4.3[1].
Renumber steps in Section 6.0.
11 09/20/04 1-3 Non-Intent:
6 Relocated previous revision Step 6.0[4],
recording of 1-RBSS position, to PREREQUISITE 4.3[2] to facilitate restructure of Section 6.0 7-15 Restructured Section 6.0 such that the previous revision has been broken into subsections.
9,10 Adds notes to Step 6.3[4] and 6.4[4] to alert Operator that CERPI Monitor indicated Rod Speed may be inaccurate while moving SBC or SBD rods.
16 Replaced Step 8.1 list of QA records with "Completed Data Packages."
ALL Corrected typographical and format errors.
~- - - ~~-
WBN REACTIVITY CONTROL SYSTEMS MOVABLE 1-SI-85-2 1 CONTROL ASSEMBLIES Revision 11 (MODES 1 AND 2) Page 3 of 17 TABLE OF* CONTENTS OF*CONTENTS Section Title Page
1.0 INTRODUCTION
....................................................................................................... 4 1.1 Purpose .................................................................................
,............................. 4 1.2 Scope .............................................. :..................................................................... 4 1.3 Frequency and Conditions .................................................................................... 4
2.0 REFERENCES
.......................................................................................................... 4 2.1 Performance References ...................................................................................... 4 2.2 Developmental References ................................................................................... 4 3.0 PRECAUTIONS AND LIMITATIONS ........................................................................ 5 4.0 PREREQUISITE ACTIONS ....................................................................................... 6 4.1 Preliminary Actions ............................................................................................... 6 4.2 Approvals and Notifications .................................................................................. 6 4.3 Field Preparations ................................................................................................ 6 5.0 ACCEPTANCE CRITERIA ........................................................................................ 6 6.0 PERFORMANCE ...................................................................................................... 7 6.1 SHUTDOWN BANK A (SBA) ................................................................................ 7 6.1 SHUTDOWN BANK B (SBB) ................................................................................ 8 6.3 SHUTDOWN BANK C (SBC) ................................................................................ 9 6.4 SHUTDOWN BANK D 0 (SBD)
(SBO) .............................................................................. 10 6.5 CONNTROL BANK A (CBA) ............................................................................... 11 6.6 CONTROL BANK B (CBB) .................................................................................. 12 6.7 CONTROL BANK C (CBC) ................................................................................. 13 6.8 CONTROL BANK D 0 (CBD)
(CBO) ........................................................................... :..... 14 6.9 RESTORATION .................................................................................................. 15 7.0 POST SURVEILLANCE ACTIVITIES ..................................................................... 16 8.0 RECORDS .............................................................................................................. 16 8.1 QA Records ........................................................................................................ 16 8.2 Non-QA Records ................................................................................................. 16 APPENDIXES/CHECKLISTS None SOURCE NOTES...................................................................................................... 17
WBN REACTIVITY CONTROL SYSTEMS MOVABLE 1-51-85-2 1 CONTROL ASSEMBLIES Revision 11 (MODES 1 AND 2) Page 4 of 17
1.0 INTRODUCTION
1.1 Purpose This Surveillance Instruction (SI) provides detailed steps to verify operability of each Shutdown and Control Rod not fully inserted.
1.2 Scope 1.2.1 Operability Tests to be Performed This instruction is performed by placing the rods in Bank Select, moving each bank at least 10 Steps, and returning the bank to its original position to verify all rods operable.
1.2.2 Surveillance Requirements Fulfilled and Modes This SI satisfies the following Surveillance Requirement (SR):
SURVEILLANCE APPLICABLE PERFORMANCE REQUIREMENT MODES MODES SR 3.1.5.2 1,2 1,2,3 1.3 Frequency and Conditions A. This SI is required to be performed at least once every 92 days.
B. This SI is required to be in frequency prior to Mode 2.
2.0 REFERENCES
2.1 Performance References None 2.2 Developmental References 3.1.5.2.
Unit 1 Technical Specification Section '3.1.5.2.
WBN REACTIVITY CONTROL SYSTEMS MOVABLE 1-SI-85-2
') 1 CONTROL ASSEMBLIES Revision 11 (MODES 1 AND 2) Page 5 of 17 3.0 PRECAUTIONS AND LIMITATIONS A.
A Nuclear Instrumentation must be observed closely for any unanticipated reactivity changes when moving rods.
B. Rods are required to be returned to their original position as soon as possible following required movement to prevent unnecessary Tavg Tav9 - Trefdeviation.
Tre!deviation.
C. Controlling bank rod insertion limits and delta flux limits must be observed during rod movement.
D. The Senior Reactor Operator (SRO) is to be contacted as soon as practical if any rod fails to move during performance of this instruction.
E. If any shutdown or control rod fails to move during the performance of this instruction, the actions of LCO 3.1.5 may be applicable.
F. Prior to rod movement, Tavg - Tref re! deviation may need adjustment to ensure temperature limits will not be exceeded when rods are repositioned.
WBN REACTIVITY CONTROL SYSTEMS MOVABLE 1-SI-85-2
') 1 CONTROL ASSEMBLIES Revision 11 (MODES 1 AND 2) Page 6 of 17 Date _ _ ___ INITIALS
~
PREREQUISITE ACTIONS
~ TE Throughout this instruction where an IFITHEN statement exists, the may be N/A if condition does not exist.
step may
~Iiminary Preliminary Actions RECORD start date and time on Surveillance Task Sheet. IWJ RECORD present plant Mode: _",-I
_-,-I__ tBl ENSURE the following:
contrOI Rod Drive MG Set (s) in SERVICE. IKJ
~
] Control
_ . Reactor Trip Breakers CLOSED. i1l1
': Approva and Notifications 1ft]) OBTAIN SM/SRO approval to perform this SI on Surveillance Task
~ Sheet. IWJ
)) ~Field Preparations
/ 1] ENSURE Precautions and Limitations in Section 3.0 have been
. REVIEWED. IWJ
~
<<f;1) RECORD the as found position of 1-RBSS, ROD BANK SELECT
~ (Rod Bank Selector Switch).
1-RBSS: AU To IWJ 5.0 ACCEPTANCE CRITERIA Verify each rod not fully inserted has freedom of movement in the core equal to or greater than 10 Steps.
WBN REACTIVITY CONTROL SYSTEMS MOVABLE 1-SI-85-2 1 CONTROL ASSEMBLIES Revision 11 (MODES 1 AND 2) Page 7 of 17 Date INITIALS 6.0 PERFORMANCE SHUTDOWN BANK A (SBA)
~ Between rod bank movements, Tav9 - T Tav9 - T ret deviation may be adjusted
~USing manual rod control or by adjusting turbine load.
ref
~Rod
~ROd movement is verified by monitoring (RPls) and Step Counters.
~Iarm 830, ROD DEVIN & SEQ PWR RANGE TilT TILT COMPUTER
~AlARM,
~ALARM, may actuate when shutdown rods are inserted from fully withdrawn.
'@. ENSURE Tav9Tav9 -- TT ret of 10 steps.
ref deviation is adjusted to allow for bank movement
~
AkYI
(§) RECORD the initial position of the following Step Counters: .
'1-SBAG1,
'.1-SBAG1, SHUTDOWN BANKA1: BANK A1: Z
- 2. 2;2 ~ steps.'
steps. /$J
~1-SBAG2, SHUTDOWN BANKA2:
(91-SBAG2, 2 ~
z2.;2~ steps. /$J
~"-" If rod movement demand exists via any of the following
~ methods, the rod bank select switch should be moved through AUTO rapidly to avoid undesired rod movement:
- T avg is not within 1 of of program, Tavg
- Less than 5 minutes has elapsed since any change in rod control input (i.e, (Le, Tavg, Tref, or NIS),
- Demand is indicated on the Computer Enhanced Rod Position Indication (CERPI) monitors [1-M-4].
~
PLACE 1 ~RBSS, ROD BANK SELECT, in SBA.
1-RBSS, /$J MOVE Shutdown Bank A at least 10 Steps in anyone direction, as indicated on appropriate Step Counter, and VERIFY movement of the rods in the proper direction is indicated on the appropriate RPls. (Acc Crit) /$J VERIFY Shutdown Bank A 1 and A2 Step Counters agree within plus or minus 2 steps. /$J RETURN Shutdown Bank A to its initial position recorded in Step [2]
of this section. /$J
WBN REACTIVITY CONTROL SYSTEMS MOVABLE 1-SI-85-2 1 CONTROL ASSEMBLIES Revision 11 (MODES 1 AND 2) Page 8 of 17 Date _ __ INITIALS
@ SHUTDOWN BANK B (SBB)
~ Between rod bank movements, TTavgavg - T ref ref deviation may be adjusted
~~sing manual rod control or by adjusting turbine load.
~~Sing
~NO Rod movement is verified by monitoring (RPls) and Step Step Counters.
Alarm 830, ROD DEVIN & SEQ PWR RANGE TILT COMPUTER LARM, may actuate when shutdown rods are inserted from fully withdrawn.
' ENSURE Tavg - T ref of 10 steps.
ref deviation is adjusted to allow for bank movement till RECORD the initial position of the following Step Counters:
1-SBBG1, SHUTDOWN BANK B1: 2- ~
Z 2: ~ steps. IKJ 1-SBBG2, SHUTDOWN BANK B2: Z 2:
2- ~
- 6. steps. 6Jl1 If rod movement demand exists via any of the following methods, the rod bank select switch should be moved through AUTO rapidly to avoid undesired rod movement:
- Tavg is not within 1 of of program,
- .Less than 5 minutes has elapsed since any change in rod control input (i.e, (Le, Tavg, Tref, or NIS),
- Demand is indicated on the Computer Enhanced Rod Position Indication (CERPI) monitors [1-M-4].
IKJ
~ PLACE 1-RBSS, ROD BANK SELECT, in SBB.
MOVE Shutdown Bank B at least 10 Steps in anyone direction, as indicated on the appropriate Step Counter, and VERIFY movement of the rods in the proper direction is indicated on the appropriate RPls. (Acc Crit) IKJ VERIFY SHUTDOWN BANK B1 and B2 Step Counters agree within plus or minus 2 steps. IKJ RETURN Shutdown Bank B to its original position as recorded in Step [2] of this section with 1-FLRM, ROD MOTION
/¥[J CONTROL.
WBN REACTIVITY CONTROL SYSTEMS MOVABLE 1-SI-85-2
) 1 CONTROL ASSEMBLIES Revision 11 (MODES 1 AND 2) Page 9 of 17 Date INITIALS
@ SHUTDOWN BANK C (SBC)
~Between rod bank movements, Tav9 Tavg - T ref deviation may be adjusted ret
~Sing manual rod control or by adjusting turbine load.
~
NO
~
.. Rod movement is verified by monitoring (RPls) and Step Counters.
E 3 Alarm 830, ROD DEVIN & SEQ PWR RANGE TILT COMPUTER ALARM, may actuate when shutdown rods are inserted from fully withdrawn.
~ ENSURE T Tav9 Trefdeviation avg - T of ten steps.
ret deviation is adjusted to allow for bank movement m
RECORD the initial position of the following Step Counter:
1-SBCG1, SHUTDOWN BANK C1: Z 2: h
- 2. 'i?,. steps. m
~ If rod movement demand exists via any of the following
~ methods, the rod bank select switch should be moved through AUTO rapidly to avoid undesired rod movement:
- T avg is not within 1 of OF of program,
- Less than 5 minutes has elapsed since any change in rod control input (i.e, (Le, Tavg, Tref, or NIS),
- Demand is indicated on the Computer Enhanced Rod Position Indication (CERPI) monitors [1-M-4].
PLACE 1-RBSS, ROD BANK SELECT, in SBC. m
~ During movement of SBC rods, CERPI Monttor Monitor Rod speed may be
~naccurate.
MOVE Shutdown Bank C at least ten Steps in anyone direction, as indicated on the appropriate Step Counter, and VERIFY movement of the rods in the proper direction is indicated on the appropriate RPls. (Acc Crit). m RETURN Shutdown Bank C to its original position as recorded in
- Step [2] of this section using 1-FLRM, ROD MOTION CONTROL. m
WBN REACTIVITY CONTROL SYSTEMS MOVABLE 1-SI-85-2 1 CONTROL ASSEMBLIES Revision 11 (MODES 1 AND 2) Page 10 of 17
--- .. -.. ----~ ~------.-
Date _ __ INITIALS
~ SHUTDOWN BANK D (SBD)
~ Between rod bank movements, Tav9 - T rel deviation may be adjusted
~USing manual rod control or by adjusting turbine load.
ref
~Rod movement is verified by monitoring (RPls) and Step Counters.
Iarm 83D,
~
Alarm
~ALARM, 830, ROD DEVIN & SEQ PWR RANGE TILT COMPUTER may actuate when shutdown rods are inserted from fully ALARM, may actuate when shutdown rods are inserted from fully ithdrawn.
ithdrawn.
~
ENSURE Tav9 - TreldeviationT ref deviation is adjusted to allow for bank movement of ten steps. !WJ RECORD the initial position of the following Step Counter:
1-SBDG1, SHUTDOWN BANK D1: 01: 2.. 2: '8.
'2;2~ steps. !WJ
) ~ If rod movement demand exists via any of the following
~ methods, the rod bank select switch should be moved through through AUTO rapidly to avoid undesired rod movement:
- T avg avg is not within 1 of of program,
- Less than 5 minutes has elapsed since any change in rod control input (i.e, Tavg, Tref, or NIS),
- Demand is indicated on the ColTlPuter Computer Enhanced Rod Position Indication (CERPI) monitors [1-M-4].
PLACE 1-RBSS, ROD BANK SELECT, in SBD. !WJ
~. During movement of SBD rods, CERPI Monitor Rod speed may be
~
~inaccurate.
MOVE Shutdown Bank D 0 at least ten Steps in anyone direction, as indicated on the appropriate Step Counter, and VERIFY movement of the rods in the proper direction is indicated on the appropriate RPls. (Acc Crit) !WJ RETURN Shutdown Bank D 0 to its original position as recorded in Step [2] of this section using 1-FLRM, ROD MOTION CONTROL. !WJ
WBN REACTIVITY CONTROL SYSTEMS MOVABLE 1-51-85-2 1-SI-85-2 1 CONTROL ASSEMBLIES Revision 11 (MODES 1 AND 2) Page 11 of 17 Date _ __ INITIALS CONNTROL BANK A (CBA)
~
~N 1 Between rod bank movements, Tav9 T avg -- TTreref! deviation may be adjusted sing manual rod control or by adjusting turbine load.
~
~
E 22 Rod movement is verified by monitoring (RPls) and Step Counters.
ENSURE Tav9 Tavg -- TTreref! deviation is adjusted to allow for bank movement of ten steps. m
~ 1-XA-55-4B-87A, ROD INSERTION LIMIT LO, may actuate during the
~following
~fOIiOwing test sections.
RECORD the initial position of the following Step Counter:
1-CBAG1, 1-CBAG 1, CONTROL BAN BANKA1:
K A 1: 22"6.
2.. 2: ~ steps. m 1-CBAG2, CONTROL BANK A2: 2.. 2: ~
22"6. steps. !¥{J I ~ If rod movement demand exists via any of the following
~ methods, the rod bank bankselect~switch select switch should be moved through AUTO rapidly to avoid undesired rod movement:
- Tavgavg is not within 1 of of program,
- Less than 5 minutes has elapsed since any change in rod control input (i.e, (Le, Tavg, Tref, or NIS),
- Demand is indicated on the Computer Enhanced Rod Position Indication (CERPI) monitors [1-M-4].
m
~
PLACE 1-RBSS, ROD BANK SELECT, in CBA.
MOVE Control Bank A at least ten Steps in anyone direction, as indicated on the appropriate Step Counter, and VERIFY movement of the rods in the proper direction is indicated on the appropriate RPls. (Acc Crit) m VERIFY Control Bank A minus 2 steps.
A11 and A2 Step Counters agree within plus or
!¥{J
' RETURN Control Bank A to its original position as recorded in Step [2] of this section using 1-FLRM, ROD MOTION CONTROL.
!¥{J
~
IF Rod Insertion Limit Lo Alarm 87-A does not clear, THEN
- REFER TO Tech Spec LCO 3.1.7.
- CONTACT System Engineer to reset 87-A USING ICS.
WBN REACTIVITY CONTROL SYSTEMS MOVABLE 1-SI-85-2 "1
) 1 CONTROL ASSEMBLIES Revision 11 (MODES 1 AND 2) Page 12 of 17 Oate _ __
Date INITIALS
- . CONTROL BANK B (CBB) .
~ Between rod bank movements, TTav9avg - T ref deviation may be adjusted
~
~
~USing manual rod control or by adjusting turbine load.
N Rod movement is verified by monitoring (RPls) and Step Counters.
ENSURE Tavg Tav9 - T ref deviation is adjusted to allow for bank movement of ten steps. m
~ 1-XA-55-4B-87A, ROD INSERTION LIMIT LO, may actuate during the
~
~fOliowing following test sections.
'(§)
@) RECORD the initial position of the following Step Counters:
1-CBBG1, CONTROL BANK B1: z ~
Z 2'
- 2. steps. §[l 1-CBBG2, CONTROL BANK B2: 2. z Z 2' ~ steps. §[l
~
,~ If rod movement demand exists via any of the following
~ methods, the rod bank select switch should be moved through AUTO rapidly to avoid undesired rod movement:
avg is not within 1 of
- T avg of of program,
- Less than 5 minutes has elapsed since any change in rod control input (Le, (i.e, Tavg, Tref, or NIS),
- Demand is indicated on the Computer Enhanced Rod Position Indication (CERPI) monitors [1-M-4].
~ PLACE 1-RBSS, ROD BANK SELECT, in CBB. m
~
MOVE Control Bank B at least ten Steps in anyone direction, as indicated on the appropriate appropriate Step Counter, and VERIFY movement of the rods in the proper direction is indicated on the appropriate RPls. (Acc Crit) m
@ VERIFY Control Bank B1 and B2 Step Counters agree within plus or m
minus 2 steps.
f<i6i\
'f<fSl\ RETURN Control Bank B to its original position as recorded in
~
\::.Y Step [2] of this section using 1-FLRM, ROD MOTION CONTROL. !WJ
~
@ IF IF Rod Insertion Limit Lo Alarm 87-A does not clear, THEN
- REFER TO Tech Spec LCO 3.1.7. ~
- CONTACT System Engineer to reset 87-A USING ICS. ~
WBN REACTIVITY CONTROL SYSTEMS MOVABLE 1-SI-85-2 1-51-85-2 1 CONTROL ASSEMBUES ASSEMBLIES Revision .11
,11 (MODES 1 AND 2) Page 13 of 17 Date _ __ INITIALS CONTROL BANK C (CBC)
~
~
~
N
~USing
~NO 1 Between rod bank movements, Tav9 - T ref deviation may be adjusted USing 2 Rod manual rod control or by adjusting turbine load.
movement is verified by monitoring (RPls) and Step Counters.
' ENSURE T Tav9 avg - T ref deviation is adjusted to allow for bank movement of ten steps. fWJ
~ 1-XA-55-4B-87A, 1-XA-55-4B-87A, ROD INSERTION LIMIT LO, may actuate during the
~following test sections.
@ RECORD the initial position of the following Step Counters:
1-CBCG1, CONTROL BANK BANKC1:
C1: Z 2:
"2 ~
z '2. steps. /tlJ 1-CBCG2, CONTROL BANK C2: Z ~
Z 2:
"2 '6. steps. fWJ
)i ~ If rod movement demand exists via any of the following
~ methods, the rod bank select switch should be moved through AUTO rapidly to avoid undesired rod movement:
- T avg is not within 1 of of program,
- Less than 5 minutes has elapsed since any change in rod control input (Le, (i.e, Tavg, Tref, or NIS),
- Demand is indicated on the Computer Enhanced Enhanced Rod Position Indication (CERPI) monitors [1-M-4].
~
PLACE 1-RBSS, ROD BANK SELECT, in CBC. §II MOVE Control Bank C at least ten Steps in anyone direction, as indicated on the appropriate Step Counter, and VERIFY movement of the rods in the proper direction is indicated on the appropriate RPls. (Acc Crit) /tlJ VERIFY Control Bank C1 and C2 Step Counters agree within plus or minus 2 steps. /tlJ RETURN Control Bank C to its original position as recorded in Step [2] of this section using 1-FLRM, ROD MOTION CONTROL. /tlJ
~
IF Rod Insertion Limit Lo Alarm 87 -A does not clear, THEN 87-A
- REFER TO Tech Spec LCO 3.1.7.
)
- CONTACT System Engineer to reset 87-A USING ICS.
WBN REACTIVITY CONTROL SYSTEMS MOVABLE 1-SI-85-2 1*SI*85*2
) 1 CONTROL ASSEMBLIES Revision 11 (MODES 1 AND 2) Page 14 of 17 Date - - - INITIALS
@ CONTROL BANK D (CBD)
NOTE 1 Between rod bank movements, Tavg Tav9 - Treref! deviation may be adjusted using manual rod control or by adjusting turbine load.
NOTE 2 Rod movement is verified by monitoring (RPls) and Step Counters.
[1] ENSURE Tavg Tav9 - T reref! deviation is adjusted to allow for bank movement of ten steps.
NOTE 1-XA-55-4B-87A, ROD INSERTION LIMIT LO, may actuate during the following test sections.
[2] RECORD the initial position of the following Step Counters:
1-CBDG1, CONTROL BANK D1: 01: steps.
1-CBDG2, CONTROL BANK D2: 02: _ _ _ _ _ _ steps.
NOTE The operator has the option of moving Control Bank D 0 five Steps in one direction, then ten Steps in the opposite direction and then return to normal. This method will have less overall effect on Reactor Power.
[3] PLACE 1-RBSS, ROD BANK SELECT, in CBD.
NOTE 1-XA-55-4A-64F, C-11 BANK D 0 AUTO WITHDRAWAL BLOCKED, will actuate if Control Bank D 0 Rods are withdrawn past 220 Steps.
[4] MOVE Control Bank D 0 at least ten Steps in anyone direction, as indicated on the appropriate Step Counter, and VERIFY movement of the rods in the proper direction is indicated on the appropriate RPls. (Acc Crit)
[5] VERIFY Control Bank D1 01 and D202 Step Counters agree within plus or minus 2 steps.
[6] RETURN Control Bank D 0 to its original position as recorded in Step [2] of this section using 1-FLRM, ROD MOTION CONTROL.
[7] IF Rod Insertion Limit Lo Alarm 87 87-A-A does not clear, THEN
- REFER TO Tech Spec LCO 3.1.7.
- CONTACT System Engineer to reset 87-A USING ICS.
WBN REACTIVITY CONTROL SYSTEMS MOVABLE 1-SI-85-2 1 CONTROL ASSEMBLIES Revision 11 (MODES 1 AND 2) Page 15 of 17 Date INITIALS 6.9 RESTORATION CAUTION If rod movement demand exists via any of the following methods, the rod bank select switch should be moved through AUTO rapidly to avoid undesired rod movement:
- T avg is not within 1 of Tavg of of program,
- Less than 5 minutes has elapsed since any change in rod control input (i.e, Tavg, Tref, or NIS),
- Demand is indicated on the Computer Enhanced Rod Position Indication (CERPI) monitors [1-M-4].
[1] PLACE 1-RBSS, ROD BANK SELECT, in MANUAL.
[2] IF Tav9 Tavg not on program, THEN RETURN Tav9 Tavg - Tref within 1.5°F.
[3] RETURN 1-RBSS, ROD BANK SELECT, to the as found position recorded in Section 4.3, Step [2] (page 6 of 17).
[4] IF Acceptance Criteria is not met, THEN NOTIFY the SRO as soon as practical after observation of the noncompliance, for consideration of possible entry into LCO 3.1.5.
WBN REACTIVITY CONTROL SYSTEMS MOVABLE 1-51-85-2 1 CONTROL ASSEMBLIES Revision 11 (MODES 1 AND 2) Page 16 of 17 Date INITIALS 7.0 POST SURVEILLANCE ACTIVITIES
[1] NOTIFY SM/SRO that Instruction is COMPLETE.
[2] RECORD completion date and time on Surveillance Task Sheet.
8.0 RECORDS 8.1 QA Records The Data Package is a QA record, and handled in accordance with the Document Control and Records Management (DCRM) program and containsthe following:
Completed Data Package.
8.2 Non-QA Records None
WBN REACTIVITY CONTROL SYSTEMS MOVABLE 1-SI-85-2 1 CONTROL ASSEMBLIES Revision 11 (MODES 1 AND 2) Page 17 of 17 SOURCE NOTES SOURCE NOTE SOURCE DOCUMENT
SUMMARY
None
WATTS BAR NUCLEAR PLANT B.1.b
') Nov. 2009 NRC Exam B.1.b Recover From High Pressurizer Level Condition
)
WATTS BAR NUCLEAR PLANT B.1.b
') Nov. 2009 NRC Exam EVALUATION SHEET Task: Recover From High Pressurizer Level Condition.
Alternate Path: Applicant establishes normal letdown in order to reduce pressurizer level to less than 92%.
Facility JPM #: 3-0T-JPMR023 Safety Function: 2
Title:
RCS Inventory Control KIA 028 AK3.05 Knowledge of the reasons for the following responses as they apply to the Pressurizer Level Control Malfunctions: Actions contained in EOP for PZR level malfunction.
Rating(s): 3.7 1 4.1 3.7/4.1 CFR: 41.5,41.10/45.6/45.13 Preferred Evaluation Location: Preferred Evaluation Method:
Simulator X X
In-Plant Perform X X
- - - - Simulate
References:
FR-1.1, "High Pressure Level," Rev. 10 Task Number: RO-113-FR-1.1-001
Title:
Respond to High Pressurizer Level
) Task Task Standard: Applicant performs the actions contained in FR-1.1, High Pressurizer Level,"
and returns level to less than 92%.
Validation Time: 15 minutes Time Critical: Yes --
No --
X ---
===============================================================
Applicant: Time Start:
NAME SSN Time Finish: -__ -_-
Performance Rating: SAT UNSAT Performance Time Examiner:
---------------------~/_-----
- - - - - -_ _ _ _~,I_ _-
NAME SIGNATURE DATE
===============================================================
COMMENTS PAr,F?
PAr,F ? OF 17
WATTS BA~UCLEAR BAR-r~UCLEAR PLANT B.1.b Nov. 2009 NRC Exam \
SIMULATOR OPERATOR INSTRUCTIONS:
- 1. ENSURE NRC Examination Security has been established.
- 2. Right click on 341, and then select RESET.
- 3. Enter the password.
- 4. Select "Yes" on the INITIAL CONDITION RESET pop-up window.
- 5. Place simulator in RUN and acknowledge any alarms.
- 6. Place simulator in FREEZE until Examiner cue is given.
PAGE 3 OF 17
REV. 0 PAGE 4 OF 17 WATTS BAR NUCLEAR PLANT B.1.b Nov. 2009 NRC Exam READ TO APPLICANT DIRECTION TO APPLICANT:
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:
- 1. An Inadvertent Safety Injection has occurred.
- 2. Safety Injection has been terminated and ECCS pumps have been stopped.
- 3. While performing Step 14 of ES-1.1,"SI Termination," the STA has determined there is a Yellow Condition on the INVENTORY Status Tree due to high Pressurizer level.
- 4. You are the OAC.
INITIATING CUES:
- 1. You have been directed by the Unit Supervisor to perform the appropriate procedure for a Yellow Condition on the INVENTORY Status Tree.
- 2. You are to notify the Unit Supervisor when the procedure has been completed.
PA(:;F PAr,F 4 OF 17
WATTS BAR NUCLEAR PLANT B.1.b
)
Nov. 2009 NRC Exam
~I-----------------S-TE-P-/S-T-A-N-D-A-R-D----------------~-S-A-TI-U-N-SA-T~
STEP/STANDARD SAT/UNSAT START TIME: _ __
I STEP 1: Obtain the correct procedure. - SAT STANDARD: A copy of FR-1.1 has been obtained. - UNSAT EXAMINER'S CUE: After the performer has demonstrated the method of obtaining the correct instruction, the evaluator can provide a copy of the instruction.
COMMENTS:
)
STEP 2: 1. CHECK SI terminated. - SAT
- Both SI pumps STOPPED .
- BIT isolated . - UNSAT STANDARD:
Performer verifies SI pumps stopped:
1-HS-63-1 OA) 1A-A SI Pump (green indicating lights on 1-HS-63-10A) 1A-A 1B-B SI pump (green indicating lights on 1-HS-63-15A) and:
Performer verifies BIT outlet valves are closed:
1-FCV-63-25 (green indicating lights on 1-HS-63-25A) 1-FCV-63-26 (green indicating lights on 1-HS-63-26A)
COMMENTS:
PAGE 5 OF 17
WATTS BAR NUCLEAR PLANT B.1.b Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 3: 2. RESET Phase A and Phase 8. B. SAT UNSAT STANDARD: The performer determines that that Phase A and Phase B have been reset by checking Master ISOL Signal Status PNL 1-Phase A and Phase XX-55-6C & 6D red lights dark for both Phase B.
COMMENTS:
PAGE 6 OF 17
WATTS BAR NUCLEAR PLANT B.1.b Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 4: 3. ENSURE cntmt air in service: SAT
- a. Aux air press greater than 75 psig [M-15].
UNSAT
- b. Cntmt air supply valves OPEN [M-15]:
- 1-FCV-32-80.
- 1-FCV-32-1 02.
- 1-FCV-32-11 O.
STANDARD:
- a. The performer verifies aux air pressure is approximately 95-100 psig on both trains using 1-PI-32-1 04A & & 1-PI-32-1 05A on M-15.
- b. Valves listed are determined to be open by red indicating lights LIT on M-15:
- 1-HS-32-80A,
- 1-HS-32-102A
- 1-HS-32-110A CUE: If contacted, all air compressors are operating properly.
COMMENTS:
CAUTION: During RCS solid water operation, any change in charging or letdown flows could cause rapid RCS pressure changes.
PAGE 7 OF 17
WATTS BAR NUCLEAR PLANT
.WATTS B.1.b Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 5: 4. CHECK at least one charging pump RUNNING. - SAT STANDARD: - UNSAT 1-HS-62-108A CCP 1A-A has a red light verified to be illuminated or amps on meter above handswitch.
COMMENTS:
STEP 6: 5. CHECK charging flow established. - SAT
- UNSAT STANDARD:
)
- Charging Flow Indicator, 1-FI-62-93A, indicating flow.
- 1-FVC-62-90 (verified open by red lights on handswitch).
- 1-FCV-62-91 (verified open by red lights on handswitch).
- 1--FCV-62-85 (verified open by red lights on handswitch).
- 1-FCV-62-89 is throttled open to establish flow through the Regen.
Heat Exchanger.
COMMENTS:
)
PAGE 8 OF 17
.WATTS BAR NUCLEAR PLANT B.1.b Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 7: 6. CHECK letdown in service. - SAT STANDARD: -
UNSAT Letdown is determined to NOT be in service by letdown flow indicator, 1-FI-62-82, indicating noflow no flow and all letdown valves are closed.
Applicant enters the RESPONSE RESPONSE NOT OBTAINED column for actions.
COMMENTS:
STEP 8: 6. RESPONSE NOT OBTAINED: ESTABLISH letdown: CRITICAL STEP a) ENSURE at least 60 gpm charging flow established.
SAT STANDARD:
- UNSAT Applicant determines that charging flow is less than 60 gpm and adjusts charging flow rate on 1-FI-62-93A to greater than or equal to 60 gpm.
Step is critical to establishing cooling water for the letdown flowpath.
COMMENTS:
PAGE 9 OF 17
WATTS BAR NUCLEAR PLANT B.1.b
')
. Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 9: b.) OPEN letdown isolation valves. CRITICAL STEP
- 1-FCV-62-69
- 1-FCV-62-70 SAT
- 1-FCV062-77 UNSAT STANDARD:
Applicant opens 1-FCV-62-69, 1-FCV-62-70and 1-FCV-62-77 using each valve handswitch. Applicant verifies valves are open by observing GREEN lights DARK and RED lights LIT.
StepJs critical to establishing a letdown flowpath.
COMMENTS:
STEP 9: c.) PLACE letdown pressure controller 1-HIC-62-81 in CRITICAL MANUAL at 40-50% OPEN if using 75 gpm orifice (20- STEP 30% ifusing 45 gpm orifice).
SAT STANDARD:
UNSAT Applicant places toggle toggle switch for 1-HIC-62-81 in MANUAL and and establishes a 40-50% open position on 1-HIC-62-81.
Step is critical to prevent opening the letdown relief valve on high pressure or causing flashing in the letdown line due to low pressure.
COMMENTS:
PAGE 10 OF 17
WATTS BAR NUCLEAR PLANT B.1.b Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 11: d.) OPEN letdown orifice valves as needed. CRITICAL STEP STANDARD:
SAT Applicant selects an orifice isolation valve (either 1-HS-62-73A OR 1-HS-62-74A are acceptable) and opens the valve. For the UNSAT selected valve, the applicant verifies that the RED light is LIT and the GREEN light is DARK.
Step is critical to establishing a letdown flowpath.
COMMENTS:
STEP 12: e.) ADJUST 1-HIC-62-81 for desired press, 320 psig at CRITICAL normal letdown temp. STEP STANDARD: SAT Applicant throttles closed on 1-HIC-62-81 to establish approximately UNSAT 320 psig on 1-PI-62-81, LP LETDOWN PRESS.
Step is is critical to prevent opening the letdown relief valve on high pressure or causing flashing in the letdown line due to low pressure.
COMMENTS:
PAGE 11 OF 17
WATTS BAR NUCLEAR PLANT B.1.b
') Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT
~
~
STEP 13: f.) PLACE 1-HIC-62-81 in AUTO. - SAT STANDARD: - UNSAT Applicant places toggle switch for 1-HIC-62-81 in the AUTO (down) position. Applicant observes that letdown pressure does not change after transfer from MANUAL to AUTO is complete.
COMMENTS:
STEP 14: 7. CHECK charging and letdown flows established. -- SAT STANDARD: -- UNSAT Applicant observes charging flow on 1-FI-62-93A (greater than 60 gpm) and letdown flow on 1-FI-62-82 (approximately 75 gpm).
COMMENTS:
STEP 15: 8. CHECK seal return flow established. - SAT STANDARD: - UNSAT Applicant observes that 1-FCV-62-61 and 1-FCV-62-63 are OPEN by RED lights LIT, GREEN lights DARK.
COMMENTS:
C_OMMENTS:
)
PAGE 12 OF 17
WATTS BAR NUCLEAR PLANT B.1.b 1
Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 16: 9. CHECK RCS press: -
- a. Press less than 2335 psig. - UNSAT
- b. Press less than 2260 psig.
STANDARD:
Applicant determines RCS pressure, and reports actual conditions.
The applicant may determine that pressure is greater than 2260 psig; depending on how quickly previous steps were performed.
COMMENTS:
)
STEP 17: 9.b. RESPONSE NOT OBTAINED: - SAT
- b. CONTROL charging and letdown flow to reduce - UNSAT pressure to less than 2260 psig.
STANDARD:
If pressure is greater than 2260 psig, the applicant adjusts charging flow using 1-FCV-62-93 and 1-FCV-62-89 to establish a lowering trend on pressurizer pressure.
COMMENTS:
)
PAGE 13 OF 17
WATTS BAR NUCLEAR PLANT B.1.b
. ) Nov. 2009 NRC Exam
. ~----~----------ST-E-P-/S-T-A-N-D-A-R-D----------------~-S-A-TI-U-N-SA-T-'I STEP/STANDARD SATIUNSAT STEP 17: 10. CHECK pzr PORVs CLOSED. -
SAT STANDARD: - UNSAT Applicant determines that the pressurizer PORVs are closed by observing tailpipe temperatures on 1,.M-4 1-M-4 and indicating lights GREEN for 1-PCV-68-340 and 1-PCV-68-334 in 1-M-S.
1-M-5.
COMMENTS:
STEP 18: 11. CONTROL pzr heaters as necessary to establish pzr - SAT bubble
- UNSAT
)
STANDARD:
/
Applicant determines that sufficient heaters are energized.
COMMENTS:
STEP 19: 12. ENSURE pzr spray valves CLOSED - SAT
- a. CHECK normal pzr spray valves CLOSED. - UNSAT
- b. ENSURE aux spray valve CLOSED.
STANDARD:
Applicant determines that RCS is less than 2260 and the pressurizer spray valves are CLOSED by observing GREEN lights on 1-M-4.
COMMENTS:
PAGE 14 OF 17
WATTS BAR NUCLEAR PLANT B.1.b Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 20: 13. CONTROL charging and letdown: CRITICAL STEP
- a. MAINTAIN RCS press stable.
- b. LOWER pzr level.
UNSAT STANDARD:
Applicant determines that the charging-letdown flow imbalance established earlier at Step 9.b is reducing pressurizer level, and heaters are maintaining pressurizer pressure.
Step is critical to ensure RCS parameters are being controlled by operator action, and that no other event is in progress.
COMMENTS:
NOTE *. jTOii*E~~~.P}\,.O~t/-The
~~IE TO EVALUATOR: The .*. a.pPlica~~-m~~-(jr***
applicant mayor . **.l11ay;not**hav~j{droPp(id may not have dropped *"pre~sYrize.r pressurizer le~~lb(7Io~;92~o.at level below 92% at thi~ this time.,
time. If leY71 is<l~ss,~~C)n~~%,.~tep~4w.i.1I level is less than 92%, Step 14 will be~.~eterl11ination be the termination p.oiQ 9.r pointtffor the J~.~. IfJ~v7IiJ.i.~greategtha~l~~f/o'J~~}.ppJicant wiltbe (jir~9te(jct9 JPM. If level is greater than 92%, the applicant will be directed to returJl return to ~ter.?Ji;13to Step 13 to continue.~to.rec:lu~e.pres~.uriz~.rlev~I*)~;:.0; continue to reduce pressurizer level .
STEP 21: 14. CHECK pzr level less than 92%: SAT STANDARD: UNSAT Applicant determines that level is dropping, but has not reached 92%.
COMMENTS:
PAGE 15 OF 17
WATTS BAR NUCLEAR PLANT B.1.b Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 21: 14. RESPONSE NOT OBTAINED: IF pzr level greater than CRITICAL or equal to 92%, THEN GO TO Step 13. STEP STANDARD: SAT Applicant determines that level is dropping, but has not reached UNSAT 92%.
Step is critical since performance of previous steps is required to reduce level.
CUE:
When the applicant addresses the return to step 13, state "another operator will continue the procedure from this point."
COMMENTS:
END OF TASK STOP TIME _ __
PAGE 16 OF 17
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
')
DIRECTION TO APPLICANT:
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 task.
sheet I provided you.
INITIAL CONDITIONS:
- 1. An Inadvertent Safety Injection has occurred.
- 2. Safety Injection has been terminated and ECCS pumps have been stopped.
- 3. While performing Step 14 of ES-1.1,"SI Termination," the STA has determined there is a Yellow Condition on the INVENTORY Status Tree due to high Pressurizer level.
- 4. You are the OAC.
INITIATING CUES:
- 1. You have been directed by the Unit Supervisor to perform the appropriate procedure for a Yellow Condition on the INVENTORY Status Tree.
- 2. You are to notify the Unit Supervisor when the procedure has been completed.
\
,J
')
TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT EMERGENCY OPERATING INSTRUCTIONS FR-1.1 FR-I.1 HIGH PRESSURIZER LEVEL Revision 10 I Unit 1 QUALITY RELATED REQUESTED BY: S. M. Baker SPONSORING ORGANIZATION: OPERATIONS APPROVED BY: R. E. Bates EFFECTIVE DATE: 11/27/07 LEVEL OF USE: CONTINUOUS
HIGH PRESSURIZER LEVEL WBN I FR-1.1 FR-J.1 Rev 10 1.0 PURPOSE This Instruction provides actions to respond to a high pressurizer level.
2.0 SYMPTOMS AND ENTRY CONDITIONS 2.1 Indications Pzr level greater than or equal to 92% and RVLlS greater than 95%.
2.2 Transitions FR-O, Status Tree, FR-I in YELLOW condition.
3.0 OPERATOR ACTIONS 2 of 12
WBN HIGH PRESSURIZER LEVEL I FR-1.1 FR-I.1 Rev 10 IStep I IAction/Expected Response III IResponse
~esponse Not Obtained
- Both SI pumps STOPPED.
RETURN TO Instruction in effect.
- BIT isolated.
- 2. RESET Phase A and Phase B.
- 3. ENSURE cntmt air in service:
- a. Aux air press greater a. DISPATCH Operator to aux air than 75 psig [M-15]. compressors:
- 1) ENSURE affected compressor(s) RUNNING.
- 2) ENSURE affected train isolation valve CLOSED:
O-FCV-32-S2 .
- Train A, O-FCV-32-S2.
- Train B, 0-FCV-32-S5.
0-FCV-32-S5 .
- b. Cntmt air supply valves OPEN [M-15]:
- 1-FCV-32-S0.
- 1-FCV-32-102.
- 1-FCV-32-110.
3 of 12
WBN HIGH PRESSURIZER LEVEL IFR-1.1 FR-I.1 Rev 10 IAction/Expected IStep I [Action/Expected Response III[Response Response Not Obtained CAUTION During RCS solid water operation, any change in charging or letdown flows could cause rapid ReS RCS pressure changes.
a) ENSURE RCP seal flow control 1-FCV-62-89 CLOSED.
b) START one charging pump.
c) ** GO TO Step 5.
IF both CCS to RCP thermal barrier AND seal injection flow NOT established, THEN:
a) Locally ISOLATE RCP seals USING Appendix A (FR-1.1),
RCP Seals and Thermal Barrier Isolation.
b) CLOSE charging isolation 1-FCV-62-90 or 1-FCV-62-91.
c) WHEN seal injection isolated, THEN START one charging pump.
4 of 12
') *1 WBN HIGH PRESSURIZER LEVEL I FR-I.1 1 FR-I.1 Rev 10 IStep I IAction/Expected Response I I~onse Response Not Obtained
- 5. CHECK charging flow established. ESTABLISH normal charging:
a) ENSURE RCP seal flow control 1-FCV-62-89 CLOSED.
b) OPEN charging isolation*
isolation 1-FCV-62-90 and 1-FCV-62-91.
c) ENSURE charging valve 1-FCV-62-85 or 1-FCV-62-86 OPEN.
d) CONTROL 1-FCV-62-89 and 1-FCV-62-93 to maintain:
- Seal flow to each RCP between 8 and 13 gpm if seal injection has not been isolated.
- Charging flow between 55 and 60 gpm.
5 of 12
WBN HIGH PRESSURIZER LEVEL I FR-1.1 FR-I.1 Rev 10 IStep I IAction/Expected Response III IResponse Not Obtained
- 6. CHECK letdown in service. ESTABLISH letdown:
a) ENSURE at least 60 gpm charging flow established.
b) OPEN letdown isolation valves:
- 1-FCV-62-69.
- 1-FCV-62-70.
- 1-FCV-62-77.
c) PLACE letdown press controller 1-HIC-62-81 in MANUAL at 40-50% OPEN if using 75 gpm orifice (20-30%
OPEN if using 45 gpm orifice).
d) OPEN letdown orifice valves as needed.
e) ADJUST 1-HIC-62-81 for desired press, 320 psig at normal letdown temp.
f) t) PLACE 1-HIC-62-81 in AUTO.
6 of 12
WBN HIGH PRESSURIZER LEVEL I FR-I.1 FR-1.1 Rev 10 IStep I I[~ctiQnfExpe~te(t R~sponse Action/Expected Response I [Response IResponse Not Obtained
- 7. CHECK charging and letdown flows PLACE excess letdown in service:
established.
a) OPEN 1-FCV-70-143.
b) OPEN 1-FCV-70-85.
c) OPEN 1-FCV-62-54.
d) OPEN 1-FCV-62-55.
e) ENSURE 1-FCV-62-59 in NORMAL.
f) ADJUST 1-FCV-62-56 to maintain excess letdown heat exchanger outlet temp less than 225°F.
g) CONTROL 1-FCV-62-89 and 1-FCV-62-93 to maintain:
- Seal injection flow between 8 and 13 gpm for each RCP.
Pzr level dropping.
- 8. CHECK seal return flow established. IF RCP seal injection flow established, THEN OPEN RCP seal return valves 1-FCV-62-61 and 1-FCV-62-63.
7 of 12
WBN HIGH PRESSURIZER LEVEL I FR-I.1 FR-1.1 Rev 10 IStep I IAction/Expected Response III IResponse Not Obtained
- 9. CHECK RCS press:
- a. Press less than 2335 psig. a. ENSURE at least one pzr PORV and associated block valve OPEN UNTIL press less than 2335 psig.
- b. Press less than 2260 psig. b. CONTROL charging and letdown flow to reduce pressure to less than 2260 psig.
- 10. CHECK pzr PORVs CLOSED. IF RCS press less than 2335 psig, THEN ENSURE pzr PORVS or block valves CLOSED.
- 11. CONTROL pzr heaters heaters as necessary to establish pzr bubble.
8 of 12
WBN HIGH PRESSURIZER LEVEL I FR-I.1 FR-I.1 Rev 10 IStep III[Action/Expected Action/Expected Response I [ReSiPonse IResponse Not Obtained
- 12. ENSURE pzr spray valves CLOSED.
- a. CHECK normal pzr spray valves a. IF RCS press less than 2260 psig, CLOSED. THEN CLOSE pzr spray valve.
IF pzr spray valve failed OPEN, THEN STOP RCP(s) as necessary to stop spray flow.
- b. ENSURE aux spray valve b. IF aux spray valve failed OPEN, CLOSED. THEN OPEN normal pzr spray valve on RCS loop with RCP stopped:
- RCS Loop 1 1-PCV-68-340
- 1) ISOLATE letdown:
- ENSURE 1-FCV-62-76 CLOSED.
- ENSURE 1-FCV-62-72 CLOSED.
- ENSURE 1-FCV-62-73 CLOSED.
- ENSURE 1-FCV-62-74 CLOSED.
- ENSURE 1-FCV-62-69 CLOSED.
- ENSURE 1-FCV-62-70 CLOSED.
9 of 12
WBN HIGH PRESSURIZER LEVEL I FR-I.1 FR-1.1 Rev 10 IStep I IAction/Expegtecj Action/Expected Response II Response Not Obtained 1 [Response
- 12. (continued)
- 2) CLOSE charging isolation valves 1-FCV-62-90 and 1-FCV-62-91.
- 3) ESTABLISH excess letdown:
a) OPEN 1-FCV-70-143.
b) OPEN 1-FCV-70-85.
c) OPEN 1-FCV-62-54.
d) OPEN 1-FCV-62-55.
e) ENSURE 1-FCV-62-59 in NORMAL.
f) ADJUST 1-FCV-62-56 to maintain excess letdown heat exchanger outlet temp less than 225°F.
- 13. CONTROL charging and letdown:
- a. MAINTAIN RCS press stable.
- b. LOWER pzr level.
- 14. CHECK pzr level IF pzr level greater than or less than 92%. equal to 92%,
THEN
- GO TO Step 13.
- 15. RETURN TO Instruction in effect.
-End-10 of 12
WBN HIGH PRESSURIZER LEVEL I FR-1.1 FR-I.1 Rev 10 APPENDIX A (FR-1.1)
Page 1 of 2 RCP SEALS AND THERMAL BARRIER ISOLATION MAIN CONTROL ROOM - Performed by NUO NOTE These steps can be performed in any order.
- 1. DISPATCH operator to perform next page, Attachment 1 (FR-1.1).
- 2. CLOSE 1-FCV-62-61 and/or 1-FCV-62-63, RCP seal return valves [M-5].
IF 1-FCV-62-61 or 1-FCV-62-63 can NOT be CLOSED, THEN DIRECT operator to perform local isolation per Step 2 of Attachment 1.
- 3. ISOLATE RCP thermal barrier:
- PLACE both Thermal Barrier Booster Pumps in Pull-To-Lock [M-27B].
- CLOSE 1-FCV-70-90 and/or 1-FCV-70-87, CCS thermal barrier return valves [M-27B].
- CLOSE 1-FCV-70-133 and/or 1-FCV-70-134, CCS thermal barrier supply valves [M-27B].
IF at least one of the thermal barrier supply valves and one of the thermal barrier return valves can NOT be CLOSED, THEN DIRECT operator to perform local isolation per Step 3 of Attachment 1.
11 of 12
WBN HIGH PRESSURIZER LEVEL [ FR-I.1 Rev 10 APPENDIX A (FR-1.1)
ATTACHMENT 1 Page 2 of 2 RCP SEALS AND THERMAL BARRIER ISOLATION LOCAL-Performed by NAUO NOTE
- These steps can be performed in any order.
- Step 1 must always be performed.
- 1. ISOLATE RCP seal injection [reach rods outside seal water injection filter cubicles]:
1-ISV-62-549, CVCS SEAL WfR
- CLOSE 1-ISV-62-S49, [A5T/713]
WTR INJ FLTR BOUT ISOL [AST/713]
- CLOSE 1-BYV-62-546, 1-BYV-62-S46, CVCS SEAL WfR [A5T/713]
WTR INJ FLTR BYP [AST/713]
- CLOSE 1-ISV-62-550, 1-ISV-62-SS0, CVCS SEAL WfR [A5T/713]
WTR INJ FLTR A OUT ISOL [AST/713]
NOTE Step 2 to be performed only if MCR is unable to close either 1-FCV-62-61 or 1-FCV-62-63.
- 2. ISOLATE RCP seal return valves [reach rods outside seal return filter cubicle]:
- CLOSE 1-ISV-62-642, CVCS SEAL WfR WTR RETURN FILTER INLET ISOL
[A5T/713]
[AST/713]
- CLOSE 1-BYV-62-643, CVCS SEAL WfR WTR RETURN FILTER BYPASS
[A5T/713]
[AST/713]
NOTE Step 3 to be performed only if MCR is unable to close at least one of the thermal barrier supply and one of the thermal barrier return isolation valves.
- 3. ISOLATE RCP thermal barrier:
- CLOSE 1-FCV-70-90, THERMAL BARRIER CCS RETURN
[above south side of BIT]
[A5W/737]
ISOLATION [ASW/737]
[A5W/737]
ISOLATION [ASW/737]
12 of 12
WATTS BAR NUCLEAR PLANT B.1.c Nov. 2009 NRC Exam B.1.c Align an RHR train for Hot Leg Recirculation per ES-1.4.
PAr,F 1 OF 1~
WATTS BAR NUCLEAR PLANT B.1.c Nov. 2009 NRC Exam EVALUATION SHEET Task: Align an RHR train for Hot Leg Recirculation per ES-1.4 Alternate Path: During alignment of "A" Train, 1-FCV-74-33 Train "A" RHR Crosstie, will not open, therefore the operator will need to realign "A" Train RHR to cold leg recirc recirc and then align "B" "8" RHR Train to Hot Leg Recirc.
Facility JPM #: 3-0T-JPMR071A Safety Function: 3
Title:
RCS Pressure Control KIA 006 A4.04 Ability to manually operate and/or monitor in the control room: RHRS.
Rating(s): 3.7/3.6 CFR: 41.7/45.5 to 45.8 Preferred Evaluation Location: Preferred Evaluation Method:
Simulator xX In-Plant Perform x Simulate
References:
ES-1.4, "Transfer to Hot Leg Recirculation," Rev. 10.
Task Number: RO-113-ES-1.4-001
Title:
Task Standard: Applicant attempts to align RHR Train "A" to supply hot leg recirc. Since the attempt is unsuccessful due to a valve failure, the applicant places RHR Train "B" in hot leg recirc.
"8" Validation Time: 10 minutes Time Critical: Yes --
No -
X X
===============================================================
Applicant: Time Start:
NAME SSN Time Finish: -_-_ -_-
Performance Rating: SAT UNSAT Performance Time Examiner:
Examiner: _____________- - - - - -
NAME
~/-----
~/
SIGNATURE
__DATE
===============================================================
COMMENTS PAr,F?
PAr,F ? OF 1::l 1~
WATTS BAR~f~UCLEAR BARr~UCLEAR PLANT B.1.c Nov. 2009 NRC Exam SIMULATOR OPERATOR INSTRUCTIONS:
- 1. ENSURE NRC Examination Security has been established.
- 2. Right click on 340, and then select RESET.
- 3. Enter the password.
- 4. Select "Yes" on the INITIAL CONDITION RESET pop-up window.
- 5. ENSURE the following information appears on the Director Summary Screen:
Key Type Event Delay Inserted Ramp., Initial ..FI.na.
~cl
, ,*V~I.~e ~:;
hs-74-33a hs-74-33a rhr heat exch a bypass sw R 00:00:00 00:00:00 close close
- 6. Place simulator in RUN and acknowledge any alarms.
- 7. Place simulator in FREEZE until Examiner cue is given.
PAGE 3 OF 13
WATTS BAR NUCLEAR PLANT B.1.c Nov. 2009 NRC Exam DIRECTIONS TO APPLICANT DIRECTION TO APPLICANT:
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:
- 1. A Large Break LOCA has occurred.
- 2. Three hours have elapsed since the Large Break LOCA occurred.
- 4. You are the Operator at the Controls.
INITIATING CUES:
- 1. The Unit Supervisor directs you to align RHR for hot leg recirculation using ES-1.4, "Transfer to Hot Leg Recirculation."
- 2. You are to notify the Unit Supervisor when RHR is aligned for hot leg recirculation.
PAr,F 4 m:
OF 1::\
1~
WATTS BAR NUCLEAR PLANT B.1.c Nov. 2009 NRC Exam STEP/STANDARD SATIUNSAT SAT/UNSAT START TIME: _ __
NOTE If problems are encountered during transfer to hot leg, then cold leg recirc should be continued or restored during TSC evaluation of corrective actions.
STEP 1: 1. ALIGN RHR Train A for hot leg recirc:
- a. CLOSE RHR Train A cold leg isolation valve 1-FCV-63-93.
UNSAT STANDARD:
Applicant closes 1-FCV-63-93, RHR Train A cold leg isolation valve, by rotating handswitch to the left, and observing that the Red indicating light is DARK and the Green indicating light is LIT.
NOTE TO EVALUATOR:
131-F ESF COMPONENT NOT NORMAL will alarm when 1-FCV-63-93 is closed. This is an expected alarm.
COMMENTS:
PAGE 5 OF 13
WATTS BAR NUCLEAR PLANT B.1.c Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 2: b. ENSURE RHR Train B discharge crosstie valve 1-FCV-74-35 - SAT CLOSED.
- UNSAT STANDARD:
Applicant determines that 1-FCV-74-35, RHR Train B discharge crosstie valve is closed by observing that the Red indicating light is DARK and the Green indicating light is LIT.
COMMENTS:
STEP 3. c. ENSURE RHR Train A spray valve 1-FCV-72-40 CLOSED. - SAT STANDARD: - UNSAT Applicant determines that 1-FCV-72-40, RHR Train A spray valve is closed by observing that the Red indicating light is DARK and the Green indicating light is LIT.
COMMENTS:
)
PAGE 6 OF 13
WATTS BAR NUCLEAR PLANT B.1.c Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 4: d. ENSURE RHR Train B spray valve 1-FCV-72-41 CLOSED. SAT STANDARD: UNSAT Applicant determines that 1-FCV-72-41, RHR Train B spray valve is closed by observing that the Red indicating light is DARK and the Green indicating light is LIT.
COMMENTS:
NOTE TO EVALUATOR: An override is active which prevents the applicant from opening 1-FCV-74-33.
STEP 5: e. OPEN RHR Train A discharge crosstie valve 1-FCV-74-33. SAT STANDARD: UNSAT Applicant opens attempts to open 1-FCV-74-33, RHR Train A discharge crosstie valve, by rotating handswitch to the right.
Note to Evaluator: Valve will NOT open.
Applicant enters RNO column, since the failure of 1-FCV-74-33 will prevent completion of Step 1 Action/Expected Response actions.
COMMENTS:
PAGE 7 OF 13
WATTS BAR NUCLEAR PLANT B.1.c
'\
Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 6: Step 1 RESPONSE NOT OBTAINED SAT IF Train A NOT available for hot leg recirc, THEN:
UNSAT
- 1) RETURN RHR Train A to cold leg recirc alignment.
- 2) GO TO Step 2.
STANDARD:
Applicant opens 1-FCV-63-93, RHR Train A cold leg valve to re-establish RHR Train A cold leg recirculation alignment.
NOTE TO EVALUATOR: 131-F 131*F ESF COMPONENT NOT NORMAL will re*flash when 1-FCV-63-93 clear, and then re-flash 1*FCV*63*93 is opened.
COMMENTS:
PAGE 8 OF 13
WATTS BAR NUCLEAR PLANT B.1.c Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 7: 2. ALIGN RHR Train 8 B for hot leg recirc: CRITICAL STEP
- a. CLOSE RHR Train 8 B cold leg isolation valve 1-FCV-63-94.
SAT STANDARD:
UNSAT Applicant closes 1-FCV-63-94, RHR Train 8 B cold leg isolation valve, by rotating handswitch to the left, and observing that the Red indicating light is DARK and the Green indicating light is LIT.
NOTE TO EVALUATOR: 131-F ESF COMPONENT NOT NORMAL will alarm when 1-FCV-63-94 is closed. This is an expected alarm.
Step is critical since it will allow RHR flow to be directed later to the correct hot leg.
COMMENTS:
STEP 8: b. ENSURE RHR Train A discharge crosstie valve 1-FCV-74-33 SAT CLOSED.
UNSAT STANDARD:
(Applicant has already attempted to open 1-FCV-74-33 unsuccessfully.)
Applicant determines that 1-FCV-74-33 is closed by observing the RED indicating light DARK, GREEN indicating light LIT.
COMMENTS:
PAGE 9 OF 13
WATTS BAR NUCLEAR PLANT B.1.c Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 9: c. ENSURE RHR Train A spray valve 1-FCV-72-40 CLOSED. SAT STANDARD: UNSAT Applicant ensures 1-FCV-72-40, RHR Train A spray valve is closed by observing Green indicating light is LIT and Red indicating light is DARK.
COMMENTS:
STEP 10: d. ENSURE RHR Train B spray valve 1-FCV-72-41 CLOSED. SAT STANDARD: UNSAT Applicant ensures 1-FCV-72-41, RHR Train B spray valve is closed by observing Green indicating light is LIT and Red indicating light is DARK.
COMMENTS:
STEP 11: e. OPEN RHR Train B discharge crosstie valve 1-FCV-74-35. CRITICAL STEP STANDARD:
SAT Applicant opens1-FCV-74-35, RHR Train B discharge crosstie valve, by rotating handswitch to the right, and observing that the Red indicating UNSAT light is LIT and the Green indicating light is DARK.
Step is critical since it will allow RHR flow to be directed to the hot leg.
COMMENTS:
PAGE 10 OF 13
WATTS BAR NUCLEAR PLANT B.1.c Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 12:f.
12: f. OPEN RHR hot leg injection valve 1-FCV-63-172. CRITICAL STEP STANDARD:
- SAT Applicant opens 1-FCV-63-172, RHR hotleg hot leg injection valve, by rotating handswitch to the right, and observing that the Red indicating light is LIT - UNSAT and the Green indicating light is DARK.
Step is critical since it will allow RHR flow to be directed to the hot leg.
COMMENTS:
STEP 13: g. ENSURE RHR heat exchanger outlet 1-FCV-74-28 OPEN. - SAT
')
STANDARD: - UNSAT Applicant ensures 1-FCV-74-28 RHR heat exchanger outlet valve is open by observing 1-XI-74-28 RHR HX B OUTLET FLOW CNTL FCV-74-28 Red light is LIT.
COMMENTS:
STEP 14: h. ENSURE RHR hot leg flow on 1-FI-63-173. - SAT STANDARD: - UNSAT Applicant ensures flow is indicated on 1-FI-63-173, RHR to HL 1&3 FLOW COMMENTS:
)
PAGE 11 OF 13
WATTS BAR NUCLEAR PLANT B.1.c Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 15: i. CLOSE RHR Train A cold leg isolation 1-FCV-63-93. CRITICAL STEP STANDARD: SAT Applicant closes 1-FCV-63-93, RHR Train A cold leg isolation valve, by UNSAT rotating handswitch to the left, and observing that the Red indicating light is DARK and the Green indicating light is LIT.
Step is critical since it will allow RHR flow to be directed to the hot leg.
Applicant informs the Unit Supervisor that RHR has been aligned for hot leg recirculation.
CUE: Repeat back information provided by the applicant to the Unit Supervisor.
COMMENTS:
')
STOP TIME _ __
PAGE 12 OF 13
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
DIRECTION TO APPLICANT:
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:
- 1. A Large Break LOCA has occurred.
- 2. Three hours have elapsed since the Large Break LOCA occurred.
- 4. You are the Operator at the Controls.
INITIATING CUES:
- 1. The Unit Supervisor directs you to align RHR for hot leg recirculation.
- 2. You are to notify the Unit Supervisor when RHR is aligned for hot leg recirculation.
TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT EMERGENCY OPERATING INSTRUCTIONS ES-1.4 TRANSFER TO HOT LEG RECIRCULATION Revision 10 Unit 1 QUALITY RELATED REQUESTED BY: S. M. Baker SPONSORING ORGANIZATION: OPERATIONS APPROVED BY: A. K. Keefer
- -11/22/06 EFFECTIVE DATE: - - -
LEVEL OF USE: CONTINUOUS
WBN TRANSFER TO HOT LEG RECIRCULATION ES-1.4 Rev 10 1.0 PURPOSE This Instruction provides the necessary actions for transferring ECCS from cold leg recirculation to hot leg recirculation.
2.0 SYMPTOMS AND ENTRY CONDITIONS 2.1 Indications 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> has elapsed since initiation of event, AND Switchover to containment sump COMPLETE.
2.2 Transitions E-1, Loss of Reactor or Secondary Coolant.
Whenever a decision is made, based on a recommendation from the TSC, that transfer to hot-leg recirc is required. Transfer to hot-leg recirc may be required, eventually, after transferring to cold-leg recirc during the implementation of:
WBN TRANSFER TO HOT LEG RECIRCULATION ES-1.4 Rev 10 IStep I IAction/Expected Response III IResponse Not Obtained NOTE If problems are encountered during transfer to hot leg, then cold leg recirc should be continued or restored during TSC evaluation of corrective actions.
- 1. ALIGN RHR Train A for hot leg recirc: IF Train A NOT available for hot leg recirc,
- a. CLOSE RHR Train A cold leg THEN:
isolation valve 1-FCV-63-93.
- 1) RETURN RHR Train A to
- b. ENSURE RHR Train B discharge cold leg recirc alignment.
crosstie valve 1-FCV-74-35 CLOSED. 2) ** GO TO Step 2.
- c. ENSURE RHR Train A spray valve 1-FCV-72-40 CLOSED.
- d. ENSURE RHR Train B spray valve 1-FCV-72-41 CLOSED.
- e. OPEN RHR Train A discharge crosstie valve 1-FCV-74-33.
- f. OPEN RHR hot leg injection valve 1-FCV-63-172.
1-FCV-63 7 172.
- g. ENSURE RHR heat exchanger outlet 1-FCV-74-16 OPEN.
- h. ENSURE RHR hot leg flow on 1-FI-63-173.
- i. CLOSE RHR Train B cold leg isolation 1-FCV-63-94.
- j. ** GO TO Step 3.
)
30f7
WBN TRANSFER TO HOT LEG RECIRCULATION ES-1.4 Rev 10 IAction/Expected IStep I [Action/Expected Response III IResponse Not Obtained
- 2. ALIGN RHR Train B for hot leg recirc: IF Train B NOT available for hot leg recirc,
- a. CLOSE RHR Train B cold leg THEN:
isolation valve 1-FCV-63-94.
- 1) RETURN RHR Train B to
- b. ENSURE RHR Train A discharge cold leg recirc alignment.
crosstie valve 1-FCV-74-33 CLOSED. 2) CONSULT TSC.
- c. ENSURE RHR Train A spray 3) ** GO TO Step 3.
valve 1-FCV-72-40 CLOSED.
- d. ENSURE RHR Train B spray valve 1-FCV-72-41 CLOSED.
- e. OPEN RHR Train B discharge crosstie valve 1-FCV-74-35.
- f. OPEN RHR hot leg injection valve 1-FCV-63-172.
- g. ENSURE RHR heat exchanger outlet 1-FCV-74-28 OPEN.
- h. ENSURE RHR hot leg flow on 1-FI-63-173.
- i. CLOSE RHR Train A cold leg isolation 1-FCV-63-93.
4of7
WBN TRANSFER TO HOT LEG RECIRCULATION ES-1.4 Rev 10 IStep I IAction/Expected Response I [fSesponse IResponse Not Obtained
- a. STOP SI pump A-A. THEN:
- b. CLOSE Train A crosstie valve 1) RETURN SI pumps to 1-FCV-63-152. cold leg recirc alignment.
- c. OPEN Train A hot leg injection 2) CONSULT TSC.
valve 1-FCV-63-156.
- d. START SI pump A-A.
- e. ENSURE Train A hot leg flow on 1-FI-63-151.
- f. STOP SI pump B-B.
- g. CLOSE Train B crosstie valve 1-FCV-63-153.
- h. OPEN Train B hot leg injection valve 1-FCV-63-15?
- i. START SI pump B-B.
- j. ENSURE Train B hot leg flow on 1-FI-63-20.
- k. ENSURE power restored to 1-FCV-63-22 using Appendix A (ES-1.4), 1-FCV-63-22 Breaker Operation.
I. CLOSE SI pump cold leg injection valve 1-FCV-63-22.
5 of?
WBN TRANSFER TO HOT LEG RECIRCULATION ES-1.4 Rev 10 IStep I IAction/Expected Response III IResponse Not Obtained
- 4. RECORD hot leg recirc flow:
- RHR to hot legs 1 & 3 flow 1-FI-63-1?3.
- SI pump A flow 1-FI-63-151.
SI pump B flow 1-FI-63-20.
- 5. RETURN TO Instruction in effect.
-End-6 of?
WBN TRANSFER TO HOT LEG RECIRCULATION ES-1.4 Rev 10 APPENDIXA APPENDIX A (ES-1.4)
Page 1 of 1 1-FCV-63-22 BREAKER OPERATION CLOSE the following to restore power to 1-FCV-63-22:
BOARD COMPT NOMENCLATURE NOMENCLATURE 480 V Reactor 1-BKR-63-22A MOV Board 2F2 SIP COLD LEG INJECTION 1B1-B 1B1-B (1-FCV-63-22)
SHUNT TRIP BREAKER 7 of?
? of 7
WATTS BAR NUCLEAR PLANT B.1.d Nov. 2009 NRC Exam B.1.d Start Standby Main Feedwater Pump PAr,F 1 OF 14 PA(';F
WATTS BAR NUCLEAR PLANT B.1.d Nov. 2009 NRC Exam Task: Start Standby Main Feedwater Pump.
Alternate Path: Standby MFP amps increase to the "RED" region, requiring the pump to be removed from service, and for manual control of the MFP MASTER CONTROLLER.
Facility JPM #: New Safety Function: 4S
Title:
Heat Removal from the Core - Secondary KIA 059 A4.03 Ability to manually operate and monitor in the main control room:
Feedwater control during power increase and decrease.
Rating(s): 2.9/2.9 CFR: 41; 41.77 / 45.5 to 45.8 Preferred Evaluation Location: Preferred Evaluation Method:
Simulator xX In-Plant Perform X Simulate
References:
SOI-2&3.01 "Condensate And Feedwater Systems," Rev. 105.
Task Number:
Title:
Task Standard: Applicant starts the Standby Main Feedwater pump in parallel with the Main Feedwater Pumps, and then shuts the pump down in response to high motor amps. Applicant controls MFP MASTER CONTROLLER to compensate for the loss of the Standby Main Feedwater pump.
Validation Time: 10 minutes Time Critical: Yes No X
-- --=--=--
===============================================================
Applicant: Time Start:
NAME SSN Time Finish: -
Performance Rating: SAT UNSAT Performance Time Examiner:
--------------------~/-----
~/-----
NAME SIGNATURE DATE
===============================================================
COMMENTS PA(;F PAr,F? ? OF 14
BAR~UCLEAR PLANT WATTS BAR-riUCLEAR , ...--'"
"~
B.1.d Nov. 2009 NRC Exam SIMULATOR OPERATOR INSTRUCTIONS:
- 1. ENSURE NRC Examination Security has been established.
- 2. Right click on 338, and then select RESET.
- 3. Enter the password.
- 4. Select "Yes" on the INITIAL CONDITION RESET pop-up window.
- 5. ENSURE the following information appears on the Director Summary Screen:
, Key
",,;' ":'\ :' :;
- Type' Event Delay Inserted~ ~.upp ,':: ,Init,ial" Final, Value ;'
"y:.
fw54 sby fw pump bearing wear 30 00:00:25 00:00:18 18 0
- 6. Place simulator in RUN and acknowledge any alarms.
- 7. Load "Simulator JPM Event Files" from the NRC Exam Flash Drive.
- 8. SOI-2&3.01 "Condensate and Feedwater Systems," is available to the Examiner~
ENSURE marked-up copy of 501-2&3.01 Examiner.
- 9. Place simulator in FREEZE until Examiner cue is given.
PAGE 3 OF 14
WATTS BAR NUCLEAR PLANT B.1.d Nov. 2009 NRC Exam DIRECTIONS TO APPLICANT DIRECTION TO APPLICANT:
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:
- 1. Unit 1 is at 100% power.
- 2. You are the Control Room Operator (CRO).
INITIATING CUES:
- 1. The Unit Supervisor has directed you to place the Standby Main Feed Pump in service using 501-2&3.01, "Condensate and Feedwater Systems," Section 8.9, Replacing Turbine Driven MFP with SMFP, or Periodic Operation of SMFP.
- 2. The SMFP is aligned for service per 501-2&3.01 Section 5.9.
- 3. Inform the Unit Supervisor when the Standby Main Feedwater Pump is in service, and is providing between 3000 to 4000 gpm of feedwater flow.
PA(~F PA~F 4 OF 14
WATTS BAR NUCLEAR PLANT B.1.d Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT START TIME: _ __
STEP 1: Obtain a copy of the procedure. SAT STANDARD: UNSAT A copy of SOI-2&3.01 has been located.
EXAMINER'S CUE: After the applicant has demonstrated the method of obtaining the correct instruction, the evaluator can provide a copy of the instruction.
COMMENTS:
Nq~~.**J().*F'J.A.L~~T2~~/;t~~+!6IiaW{~g i~~fi()*.~~~f~:~i~~~ttI~6~':§qit~&3.01
,. . NOTE TO EVALUATOR: The following
- actions are taken from 501-2&3.01,. ,. . *. i*. .............. ,. ' **.'>.*....... ,;
'~C()i~cJip~~t~ .~.pd.~e.~t~YlfaJ~~.
"Condensate S}'st~ll1i'~** Section and Feedwater System," Sectiqn;.~:~*,
8.9, ~~pl~C'irigJ~rbine Replacing Turbine Drive Driven FP;wit~
- n. M with
- §MF~,"QJ~~dpdic:;Op~r~ti;<inofSIVIFP.
SMFP, or Periodic Operation of SMFP. ..; .. ' .'
CAUTIONS
- 1) MFP discharge should remain less than 1185 psig when possible. Short duration press up to 1363 psig (MFP Disch Press Admin Limit) is acceptable, but care must be taken to prevent sudden pressure elevations from lifting #1 Heater Reliefs at 1650 psig.
Runback circuitry may be verified at 1-L-262 [729, T3J] using PIS-47-13 display.
RLY1 indicates load >67% and RLY3, indicates load >85%. Impulse pressure equivalent to 85% load enables the runback circuitry.
- 3) MFP 1B must NOT be operated at a higher speed than MFP 1A or in the resonance speed range between 4900 and 5000 rpm due to high vibration on the inboard bearing and turning gear motor. Speed controllers have been calibrated to prevent this condition; however, a WO should be generated if the controllers fail to control this occurrence.
PAGE 5 OF 14
WATTS BAR NUCLEAR PLANT B.1.d Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT NOTES
- 1) One MFP is capable of delivering sufficient flow to maintain 67% load.
- 2) Unit load can be maintained at 85% with the SMFP and one MFP in operation.
- 3) Unit load can be maintained at 100% for periodic operation of SMFP with one TDMFP partially unloaded.
- 4) Starting a main feed pump (SBMFP or MFPT) may cause perturbation in heater drain tank levels that may NOT be compensated for by the level controllers.
- 5) In Mode 1, entry into Tech Spec 3.3.2 condition J may be suspended for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> when removing one of two Turbine Driven Main Feedwater Pumps (TDMFWP) from service. Refer to Tech Spec 3.3.2 table 3.3.2-1.
- 6) In Mode 2, trip function of all Turbine Driven Main Feedwater Pumps (TDMFWP) is required when one or more (TDMFWP) is supplying feedwater to the Steam Generators.
Refer to Tech Spec 3.3.2 condition J.
STEP 2: [1] IF one TDMFP is to be completely shutdown, THEN SAT ENSURE Turbine Runback circuitry reset by verifying RLY3, RL Y3, PIS-47-13 PIS-4 7-13 DISPLAY DIS PLAY NOT actuated <<85%) [Panel UNSAT 1-L-262] [729/T3J].
STANDARD:
Applicant determines from INITIAL CONDITIONS that the Main Feedwater pumps will remain in service, and determines this step is N/A.
COMMENTS:
PAGE 6 OF 14
WATTS BAR NUCLEAR PLANT B.1.d Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 3: [2] ENSURE SMFP is aligned for service per Section 5.9. - SAT STANDARD: - UNSAT Applicant determines from INITIAL CONDITIONS that the SMFP is aligned per Section 5.9.
COMMENTS STEP 4: [3] VERIFY 1-FIC-3-208 [1-FIC-3-208], STANDBY MFWP - SAT RECIRC CONTROL [1-M-3], in AUTO, AND SET at 90%
(1500 gpm). - UNSAT STANDARD:
Applicant determines from controller 1-FIC-3-208 that the controller is in AUTO and is set at 90%.
COMMENTS:
PAGE 7 OF 14
WATTS BAR NUCLEAR PLANT B.1.d Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 5: [4] ENSURE 1-FCV-3-205 [1-HS-3-205], STANDBY MAIN -
SAT FEEDWATER PUMP DISCHARGE ISOL [T1 J/729],
[T1J/729],
OPEN. - UNSAT STANDARD:
Applicant contacts TB AUO and asks if 1-FCV-3-205 is OPEN.
CUE: As TB AUO, when contacted report that 1-FCV-3-205 is open.
COMMENTS:
STEP 6: [5] ENSURE 1-FCV-2-265 [1-HS-2-265], STANDBY MAIN - SAT FW PUMP SUCT ISOL [T1 J/729], OPEN.
- UNSAT STANDARD:
Applicant contacts TB AUO and asks if 1-FCV-3-265 is OPEN.
CUE: As TB AUO, when contacted report that 1-FCV-3-265 is open.
COMMENTS:
PAGE 8 OF 14
WATTS BAR NUCLEAR PLANT B.1.d Nov. 2009 NRC Exam STEP/ST ANDARD STEP/STANDARD SAT/UNSAT STEP 7: [6] VERIFY 1-PI-2-129, MFW PMPS SUCT PRESS [1-M-3], -
SAT as follows:
- UNSAT A. Greater than 100 psig (below 50% load).
B. Greater than 250 psig (at or above 50% load).
STANDARD:
Applicant observes 1-PI-2-129 and determines that suction pressure is approximately 410-430 psig, sufficient for starting the SMFP.
COMMENTS:
')
STEP 8: [7] ENSURE 1-FCV-3-208 [1-HS-3-208], STANDBY MAIN - SAT
/ FEEDWATER PUMP MIN FLOW [T1J/729], CLOSED.
- UNSAT STANDARD:
Applicant contacts TB AUO and asks if 1-FCV-3-208 is CLOSED.
CUE: As TB AUO, when contacted report that 1*FCV*3*208 1-FCV-3-208 is closed.
COMMENTS:
PAGE 9 OF 14
WATTS BAR NUCLEAR PLANT B.1.d
'\
Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT I CAUTION Manual operation of TDMFP speed control during MFP starts/stops will minimize system fluctuations.
STEP 9: [8] CONTROL TDMFP speed in MAN. CRITICAL STEP STANDARD:
SAT Applicant places 1-PC-46-20, MFPT A & & B MASTER SPEED CONTROL in MANUAL. UNSAT Step is critical to ensure that feedwater oscillations are avoided when starting the SMFP.
COMMENTS:
)
STEP 10: [9] IF SMFP to operate with TDMFP, THEN SLOWLY CRITICAL RAISE TDMFP speed until SMFP minimum flow head is STEP achieved (above 1200 psig).
STANDARD: SAT Applicant raises TDMFP speed until pressure is,slightly is.slightly above 1200 psig. UNSAT Step is critical to ensure that feedwater oscillations are avoided when starting the SMFP.
COMMENTS:
)
PAGE 10 OF 14
WATTS BAR NUCLEAR PLANT B.1.d Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT
/NOl~.J(jE,,~£lJ~
NOTE TO EVALUATOR: fOR:*W~.~g'~~:~"i~.~
When the SFMP .~P.i~f~!~a~~a.
is started i~ it*. *~~r,d~4.t9,N~~r6~im~!EflyJ~P~9i)'~t1 may load to approximately 2000 ..
gpm if MFP header pre~sur:e!i~lov(;r
!;9PpliftvlFpytleader
/_i,> , ",',,"-'_' - ',' ',".')',. - ___ ,/u/"'/-'--.'-,'_,'.
pressure is lower thani5i4Qpsig:;
do,!, - -." '" ',<: -d', - "'J.'--',
than 1200 psig.
_ " . : _. ,/'- '_.',
y.~!/ . si& ;! . i",1.' ;. 'cY; STEP 11: [10] IF SMFP to operate with TDMFP, THEN START SMFP CRITICAL with 1-HS-3-200A, STANDBY MFWP, and LOWER STEP TDMFP flow, or SHUTDOWN TDMFP per Section 7.3.
SAT STANDARD:
UNSAT Applicant starts SMFP with 1-HS-3-200A, obseNes observes amps on 1-EI-3-200, STANDBY MFWP AMPS, and pressure on 1-PI-3-203A, STANDBY MFWP DISCH PRESS.
Applicant reduces TDMFP flow by reducing the control signal from 1-PC 20, MFPT A & B MASTER SPEED CONTROL, and obseNes observes a rise in flow from the SMFP. Per the INITIATING CUES the applicant will load the SMFP to between 3000 to 4000 gpm.
Step is critical to ensure that the SMFP is properly loaded.
COMMENTS:
PAGE 11 OF 14
WATTS BAR NUCLEAR PLANT B.1.d Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT ii~qtE~piEVArlJA,.{).~;~I~fte~thei~Rprr~x~~~lg~~i~t~;i;~~~1'~0tt;"iappf?~i~~t~I~'?JW[f{;fi' NOTE TO EVALUATOR: After the applicant loads the SMFP to approximately 3000 .' .i .****
}!.gpg-.,.£lI~~ne~i~l1.so'~.
gpm, cue the console op~rat~r~? lnse'1<~~ei operator to *. insert the f~}I~f:~~~fil~<tJ;~M~.~*Thl~wlll failure of the SMFP. This will c~y$~8~h!;i,,~,*i.
cause the r ~N'F~aIDP~.!~ . !nter m~(REQi~r~i~'iandfor al'mul'l~i~tor~?4~.D,M~)1 \hr~)j. M~6;M9TO~'*i'"
SMFP amps to enter the RED area, and for annunciator 14-0, M-1 thru M-6 MOTOR .'
(jV§RLQAD'i~Q OVERLOAD to alarm.alarm.' .' . . ' . . .. ' . . ."
STEP 12: Operator recognizes that the SMFP is operating with high CRITICAL amps, reports the condition and then stops the SMFP. STEP STANDARD: SAT Applicant observes amps on 1-EI-3-200, STANDBY MFWP AMPS rising into UNSAT the RED operating band.
Upon receipt of the WHITE OVERLOAD light on 1-HS-3-200A, the applicant determines that the SMFP should be stopped, and stops the pump.
Step is critical to protect the SMFP.
COMMENTS:
PAGE 12 OF 14
WATTS BAR NUCLEAR PLANT B.1.d Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 12: Operator places 1-PC-46-20, MFPT A & B MASTER SPEED CRITICAL CONTROL in MANUAL and controls MFP speed to stabilize STEP the feedwater system after the trip of the SMFP.
SAT STANDARD:
UNSAT Applicant places 1-PC-46-20, MFPT A & B MASTER SPEED CONTROL in MANUAL and raises main feedwater pump speed to compensate for the loss of the SMFP flow. Applicant monitors MFP suction pressure to ensure that pressure remains above 250 psig. Applicant monitors SG narrow range levels to ensure that levels are stabilized.
Step is critical to ensure that feedwater oscillations are avoided after the SMFP is stopped.
EVALUATOR CUE:
After the applicant has placed 1-PC-46-20, MFPT A & & B MASTER SPEED CONTROL in MANUAL, and taken action to raise MFP speed/pressure/flow, state "another operator will control the plant from this point."
COMMENTS:
END OF TASK STOP TIME _ __
PAGE 13 OF 14
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
DIRECTION TO APPLICANT:
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:
- 1. Unit 1 is at 100% power.
- 2. You are the Control Room Operator (CRO).
INITIATING CUES:
- 1. The Unit Supervisor has directed you to place the Standby Main Feed Pump in service using 501-2&3.01, SOI-2&3.01, "Condensate and Feedwater Systems," Section 8.9, Replacing Turbine Driven MFP with SMFP, or Periodic Operation of SMFP.
- 2. The SMFP is aligned for service per 501-2&3.01 SOI-2&3.01 Section 5.9.
- 3. Inform the Unit Supervisor when the Standby Main Feedwater Pump is in service, and is providing between 3000 to 4000 gpm of feedwater flow.
)
[i!) Watts Bar Nuclear Plant Unit 1 System Operating Instruction 501-2&3.01 SOI-2&3.01 Condensate And Feedwater System Revision 0106 Quality Related Level of Use: Multiple
)
Effective Date: 09-15-2009 Responsible Organization: OPS, Operations Prepared By: R. A. O'Rear
)
Approved By: H. Champagne
WBN Condensate And Feedwater System 501-2&3.01 501*2&3.01 Unit 1 Rev. 0106
)
Page 2 of 291 Revision Log Revision Affected or Change Effective Page Number Date Numbers Description of Revision/Change 102 OS/23/08 2,214-217 Corrected numbering in Appendix D and E.
103 03/18/09 2,8,16 Added reference and precaution for jumper installation and removal. (PER 140641)
These changes are minor/editorial changes that are purely administrative and non-technical in nature and do not change the intent or outcome of the activity. A 10 CFR 50.59 review is not required.
104 06/04/09 2,18,77, 2, 18,77, Minor /Editorial change to add cautions prior to 82,97, ensuring a TDMFWP is running or secured and 111,121, added P/L. Both to address Tech Spec change
) 158 08-07.
105 07/15/09 2,18,60,68, Added minimum oil pressure for starting 70,83,90, SBMFP and Cond Booster Pumps 103,124- [PER 147115]
126, Added step to each of the TDM TDMFP FP startup 218,219 sections to ensure a CBP is running prior to starting the TDMFP.[PER 153583]
Minor/Editorial changes: Moved the section for SBMFP shutdown and standby alignment to the shutdown section of the procedure, it is now section 7.3.3.
Added caution to App D for tripping both MFP's.[PER 153583]
Deleted note for running SBMFP when starting up.
Added P/L for sequence of drawing initial TDMFP condenser vacuum.
106 09/15/09 2,210-215 Added section for cooling feedwater lines post trip.[PCR 4200] ------------------
WBN Condensate And Feedwater System SOI-2&3.01 Unit 1 Rev. 0106 Page 3 of 291 Table of Contents
1.0 INTRODUCTION
.......................................................................................................... 7 1.1 Purpose ........................................................................................................................ 7 1.2 Scope ............................................................................................................................ 7
2.0 REFERENCES
............................................................................................................. 8 2.1 Performance References .............................................................................................. 8 2.2 Developmental References ........................................................................................... 9 3.0 PRECAUTIONS AND LIMITATIONS ......................................................................... 11 4.0 PREREQUISITE ACTIONS ........................................................................................ 21 4.1 Preliminary Actions ..................................................................................................... 21 4.2 Field Preparations ....................................................................................................... 22 4.3 Approvals and Notifications ........................................................................................ 23 5.0 STARTUP ................................................................................................................... 24 5.1 Short Cycle Operation ................................................................................................. 24 5.2 Establishing Condenser Vacuum ................................................................................ 31 5.3 Long Cycle Deaeration ............................................................................................... 36 5.4 Power Escalation ........................................................................................................ 47 5.5 Long Cycle Operation ................................................................................................. 47 5.6 Bypass Reg to Main Reg Transfer (Method 1) ............................................................ 54 5.7 Bypass Reg to Main Reg Transfer (Method 2) ............................................................ 56 5.8 Condensate Booster Pump Operation ........................................................................ 58 5.9 Standby Main Feed Pump Operation Or Standby Alignment.. .................................... 62 5.10 MFP 1A Operation ...................................................................................................... 70 5.11 MFP 1B Operation ...................................................................................................... 90 5.12 Condensate Demin Pump Operation ........................................................................ 110 6.0 NORMAL OPERATION ............................................................................................ 112 6.1 Condensate Processing And Handling ..................................................................... 112 6.2 Operation of the Feedwater System ......................................................................... 112 6.3 Condensate System ................................................................................................. 113
WBN Condensate And Feedwater System SOI-2&3.01 Unit 1 Rev. 0106 Page 4 of 291 Table of Contents (continued) 7.0 SHUTDOWN ............................................................................................................. 114 7.1 Shutdown Cond Demin Pumps ................................................................................. 114 7.2 Shutdown Condensate Booster Pumps .................................................................... 115 7.3 MFP SHUTDOWN .................................................................................................... 117 7.3.1 TDMFP Shutdown ....................................................................................... 117 7.3.2 Standby Main Feed Pump Shutdown .......................................................... 123 7.3.3 Standby MFP Shutdown And Standby Alignment.. ..................................... 124 7.4 Main Reg to Bypass Reg Transfer ............................................................................ 127 7.5 Shut Down Condensate System from Long Cycle Deaeration .................................. 130 7.6 HWP Shutdown ........................................................................................................ 133 7.7 Removing CBP and MFP from Service During Shutdown ........................................ 134 8.0 INFREQUENT OPERATIONS .................................................................................. 135 8.1 CST "A" Cleanup via Condensate System ................................................................ 135 8.2 Swapping MFPT Duplex Filter 1A and 1B................................................................. 136 8.2.1 Swapping MFPT Duplex Filter 1A ............................................................... 136 8.2.2 Swapping MFPT Duplex Filter 1B ............................................................... 138 8.3 Align CST "B" for U1 Hotwell Makeup ....................................................................... 140 8.4 Transfer Water between CSTs ................................................................................. 142 8.5 .................................. ,................. 144 Placing MFPs on Turning Gear During Shutdown ....................................................
8.6 Isolate MFPT A or B ................................................................................................. 148 8.7 Alternate HWPs ........................................................................................................ 151 8.8 Guidelines for Starting SMFP with Short Term Use of 1-FCV-3-195 ........................ 153 8.9 Replacing Turbine Driven MFP with SMFP, or Periodic Operation of SMFP ........................................................................................................................ 157 8.10 Transferring Hotwell Level Transmitters ................................................................... 160 8.11 Placing Condensate In Service to SGBD First Stage HXs ........................................ 163 8.12 Starting CVPs With Vacuum Established .................................................................. 166 8.13 Swapping M FP Turbine Oil Coolers ...........................................................................
.......................................................................... 168 8.14 CST "A" Heatup via Condensate System .................................................................. 172
WBN Condensate And Feedwater System SOI-2&3.01 Unit 1 Rev. 0106 Page 5 of 291 Table of Contents (continued) 8.15 Removing Condensate From Service to SGBD First Stage HXs .............................. 173 8.16 Hot Well Pump Operation at Power .......................................................................... 174 8.16.1 HWP Shutdown at Power ........................................................................... 174 HWPShutdown 8.16.2 HWP Startup at Power ................................................................................ 176 8.17 Condensate Booster Pump Operation at Power ....................................................... 179 8.17.1 CBP Shutdown at Power ............................................................................ 179 8.17.2 CBP Startup at Power. ................................................................................ 182 Power .................................................................................
8.18 Check For Water Accumulation On Discharge Of Vacuum Pumps .......................... 186 8.19 Isolate Hotwell From CST ......................................................................................... 187 8.20 Transfer Water from CSTs to Station Sump ............................................................. 188 8.21 Checking Condenser Vacuum Inleakage .................................................................. 191 8.22 Adjust Main Feed Pump Hand Speed Changers ...................................................... 193 8.22.1 Adjust 'A' Main Feed Pump Turbine Hand Speed Changer ........................ 193 8.22.2 Adjust 'B' Main Feed Pump Turbine Hand Speed Changer ........................ 196 8.23 Adjust CBP Oil Temperature During Plant Operation ............................................... 199 8.24 Swapping MFPT Main Oil Pumps With MFPT In Service ......................................... 200 8.24.1 Swapping 1A MFPT Main Oil Pumps .......................................................... 200 8.24.2 Swapping 1B MFPT Main Oil Pumps .......................................................... 202 8.25 Condenser Water Level Control ................................................................................ 204 8.26 Throttling HIP Steam Supply Isol During MFPT Startup ........................................... 206 8.26.1 Throttling 1A MFPT HIP Steam Supply Isol During Startup ........................ 206 8.26.2 Throttling 1B MFPT HIP Steam Supply Isol During Startup ........................ 208 8.27 Post Trip Cooldown of Feedwater Lines ................................................................... 210 9.0 RECORDS ................................................................................................................ 216 9.1 QA Records .............................................................................................................. 216 9.2 Non-QA Records ...................................................................................................... 216 Appendix A: MFPT Duplex Filters 1A And 1B ............................................................ 217 Appendix B: SG Program Level-vs-Nuclear Power ................................................... 219
WBN Condensate And Feedwater System SOI-2&3.01 Unit 1 Rev. 0106 Page 6 of 291 Table of Contents (continued)
Appendix C: Main Feed Pump Hot Start ..................................................................... 222 Appendix D: Main Feed Pump Cold Start ................................................................... 223 Appendix E: CBP Oil And Bearing Temperature Trending ....................................... 227 Checklist 1: Condensate And Feedwater System Handswitches ............................ 229 Checklist 2: Short Cycle Power .................................................................................. 231 Checklist 3: Long Cycle Power ................................................................................... 233 Checklist 4: Short Cycle Valve Alignment Verification ............................................. 238 Checklist 5: Long Cycle Valve Alignment Verification ........................*....................
............................................. 259 Source Notes ........................................................................................... 290
WBN Condensate And Feedwater System 501-2&3.01
') Unit 1 Rev. 0106 Page 7 of 291
1.0 INTRODUCTION
1.1 Purpose provide instructions for operation of the Condensate and Feedwater Systems.
To provide 1.2 Scope This Instruction includes startup, normal operation, and shutdown 11 11 operation of the following equipment:
A. Hotwell Pumps B. Condensate Booster Pumps C. Main Feed Pumps (MFP)11
) D. Standby Main Feed Pump (SMFP)
E. Condenser Vacuum Pumps (CVP)
F. Condensate Demin Pumps
WBN Condensate And Feedwater System 501-2&3.01 Unit 1 Rev. 0106 Pa~e 8 of 291 Page
2.0 REFERENCES
2.1 Performance References A. SOI-2.02, "Condensate Startup Filter" B. SOI-3.02, "Auxiliary Feedwater System" C. SOI-5&6.01, "Extraction Steam, Heater Drains, and Vent System" D. SOI-14.01, "Condensate Demineralizer Polisher Operation" E. SOI-25/26.01, "Raw Service and High Pressure Fire Protection Systems" F. SOI-37.01, "Gland Seal Water System" G. SOI-47.01, "Main Turbine Turning Gear Operation" H. SOI-47.03, "Main Turbine Steam Seal System" I. SOI-54.01, "Injection Water System" J. SOI-90.02, "Gaseous Process Radiation Monitors" K. SOI-90.05, "Post-Accident Rad Monitors" L. TI-1 01.03A.01, "System 3A, MFP Periodic Checkout Operation Using Aux TI-101.03A.01, Boiler Steam" M. 0-PI-OPS-17.0; "18 Month Locked Valve Verification" N. MI-57.036, "Electric Motor/Generator Replacement and Bearing" O. 0-PI-OPS-1.1, Jumper Control Process
WBN Condensate And Feedwater System 501-2&3.01 Unit 1 Rev. 0106 Page 9 of 291 2.2 Developmental References A. N3-2-4002, System Description, Condensate System B. N3-3A-4002, System Description, Main Feedwater, Feedwater Control, and Injection Water C. Vendor Manuals:
- 1. WBN-VTM B580-0010, Byron Jackson, Contract 083018, #0038,
- 2. WBN-VTM-B580-0030; Vendor Technical Manual For Byron Jackson Condensate Booster, Condensate Hotwell, #3 & #7 Heater Drain And Standby Main Feed Pumps; Byron Jackson, Ingersol Rand, Contract 083174
- 3. WBN-VTD-B580-0150; Installation, Operation And Maintenance Instructions For The Byron Jackson Standby Main Feed Pumps [PUB. #
) G404550].
- 4. WBN-VTM-W120-2094
- 5. WBN-VTD-P076-0020, Parson-Peebles Operating and Maintenance Instructions For Standby Main Feed, Hotwell, H otwell , Booster, NO.3 and NO.7 Heater Drain Pump Motors [PUB. # AGC/254498-502].
WBN Condensate And Feedwater System 501-2&3.01 Unit 1 Rev. 0106 Page 10 of 291 2.2 Developmental References (continued)
D. TVA Drawings:
- 1. 4581754-5C
- 2. 1-4586236-010, -011, -017, -020, -033, -034, -035, -041, -042, -043, -044
- 3. 1-4586275-011, -028
- 4. 45N700-1
- 5. 45N721-1
- 6. 1-45W600-2, -3, -5, -6, -7, -8, -9, -11
- 7. 1-45W600-46-1, -3, -4, -5,-7
-5, -7
- 8. 1-45W600-57-1, -2, -31
- 9. 1-45W703-1
- 10. 1-45W753-7
- 11. 1-45W760-2-1 through -5
- 12. 1-45W760-3-1 through -11
- 13. 1-45W1646-2
- 14. 1-47W803-1
- 15. 1-47W804-1,-2 1-47W804-1, -2
WBN Condensate And Feedwater System SOI-2&3.01 Unit 1 Rev. 0106 Page 11 of 291 3.0 PRECAUTIONS AND LIMITATIONS A. Hotwell/Hotwell Pumps
- 1. Failure to isolate 1-LCV-37-1, GSW STOR TNK MU LEVEL CNTL, before starting the first Hotwell Pump, will result in GSW Tank overflow.
- 2. Flow from the Hotwell to the CSTs should be limited when condenser 12 vacuum does NOT exist. Notify Chemistry for contingent actions. 12
- 3. Filling Hotwell 18" or more above normal when water temp is below 60°F could cause Condenser wall weld failure.
- 4. 1-LCV-2-9, MAIN CONDENSER AUTO MAKEUP LEVEL CNTL, has a hole drilled in valve to allow 8 to 10 gpm leak-by with valve closed, thus raising Hotwell level.
- 6. Hotwell Pump motor bearing temp alarm should be set at 225°F or lower.
Max temperature limit on bearings is 300°F per reference 2.2.A.
- 7. Hotwell pumps require >12 inches Hotwell Level to ensure adequate suction is available. 66
- 8. If hotwell pump motor has been NOT running for 7 days or more, or motor upper bearing maintenance has just been performed, MSA must be contacted to prelube the upper bearing by removing about a cup of oil from the drain drain valve at the bearing sight glass and adding it back through the oil filler/breather connection at the top of the bearing. (Ref: MI-57.036, Attachment 1, Step 1.B).1.8).
B.
- 8. Common/Mise Common/Misc Systems
- 1. Since the Condenser Vacuum Exhaust effluent must be monitored for a SG tube leak, and the CVE monitors must remain isolated until vacuum is achieved to avoid water damage, the following comp measures must be taken per guidance in System Description N3-2-4002, Section 4.10:
- a. SG blowdown rad monitors should be placed in service.
- b. Sampling provisions of the ODCM will be used to assess radioactive effluents out of the CVE.
WBN Condensate And Feedwater System SOI-2&3.01 SOI*2&3.01
'I Unit 1 Rev. 0106 i
Page 12 of 291 3.0 PRECAUTIONS AND LIMITATIONS (continued)
- 2. RCW supplies to various oil Hxs throughout system system are isolated to prevent excessive oil cooling and condensation in piping. Care should be taken to ensure these valves are open before starting associated equipment.
- 3. Injection Water Pump damage may occur if operated over 4 minutes without at least one MFP receiving seal flow. Pumps have no recirc capability.
- 4. Steam Dumps to the Main Condenser should NOT be used with a water box out of service. Prolonged exposure to super heated steam in a water box without circ water may cause damage to condenser tubes and '
adversely impact Condenser Vacuum Pump performance.
- 5. 1-FS-2-35 permits 1-FCV-15-43 to open at greater than 3500 gpm condensate flowrate.
- 6. To protect the condensate demins, 1-TS-15-43 alarms at greater than or equal to 145°F blowdown fluid temperature and closes 1-FCV-15-43 at
) greater than or equal to 150°F.
- 7. constant~P 1-FCV-2-260, (actuated by 1-PDI-2-260), maintains a constant ~P across the second stage HXs and the GSC.
- 8. 1-FCV-2-329B is modulated by 1-PDlC-2-329 1-PDIC-2-329 to maintain 2.1 psid across the first stage HXs (1-FCV-2-329A full open).
- 9. During unit startup, 1-FCV-2-329A is fully open, initially. As load rises, 1-FCV-2-329B's capacity to maintain 2.1 psid is exceeded. At 2.8 psid
(",,13%
(::::13% load) across low pressure heaters, 1-FCV-2-329B closes and 1-FCV-2-329A is modulated by1-TIC-2-329A to maintain 230°F condensate temperature out of the first stage heat exchangers.
- 10. If SGBD flow is being initiated or isolated with unit at greater than 13%
load, 1-FCV-2-329A could be fully closed. This valve should be partially opened to ensure condensate flow through first stage heat exchanger prior to initiating SGBD flow to prevent water hammer. Controller gain/setpoint may be adjusted as required to maintain stable system operation as directed by System Engineering/MIG.
Engineering IMIG. ,
- 11. Chemistry should be notified before initiating Short Cycle, Long Cycle, or Power Operation to coordinate chemical addition and sampling activities.
I
/ 12. Instrument Maintenance (MIG) should be notified to ensure required instruments are in service as necessary to support system operation.
WBN Condensate And Feedwater System 501-2&3.01 SOI-2&3.01 Unit 1 Rev. 0106 Page 13 of 291 3.0 PRECAUTIONS AND LIMITATIONS (continued)
- 13. Work in Radiologically Controlled Area (RCA) requires the use of existing RWPs, and may require additional ALARA Preplans. Failure to follow posted Rad control requirements can cause unnecessary radiation exposure. Rad Con should be notified of work having the potential to change radiological conditions.
C. Condensate
- 1. Before pressurizing the Condensate System or drawing a vacuum, consideration should be given to Injection Water, Gland Seal Water, Auxiliary Feedwater, Exhaust Hood Sprays, and Chemical Feeds.
- 2. Cond Demin AUO should be notified before starting pumps that could affect Cond Demin ~P, AP, to allow actions to prevent high ~P AP auto-bypass.
- 3. Normal Condensate operating temp limit is 140°F. Operating above 140°F can damage Cond Demin Resin.
D. Shortcycle
- 1. Short Cycle is not for long-term operation. Due to piping vibration and movement, Short Cycle operation should be minimized by proceeding to Long Cycle recirc as soon as reasonable, when the required conditions are satisfied.
E. Long Cycle Deaeration
- 1. Used when:
- a. SG temp is 400°F or less (not required when in Hot Standby with NO possibility of injecting into SGs, i.e., NO feedwater pumps in service) and MFW ISOL MOVs closed.
- b. Condensate press below 350 psig (below 550 psig if operating CBP).
- c. SG press atmospheric or greater.
- d. Condensate temp 100°F or greater (If Unit Heatup/Startup in progress).
- 2. The deaeration line valves (1-ISV-3-602 and 1-FCV-3-195) should be open during long-cycle deaeration with only HWPs operating and closed during
) all other modes. 1-FCV-3-195 will NOT withstand the higher pressure drop caused by the MFPs. 17 17
WBN Condensate And Feedwater System SOI-2&3.01 Unit 1 Rev. 0106 Page 14 of 291 3.0 PRECAUTIONS AND LIMITATIONS (continued)
F. Condensate Booster Pumps
- 1. The minimum oil temperature recommendation is 70°F to 80°F. This is based on ensuring adequate oil is available during startup, when the oil temperature is lowest. (with oil temperature this low, the auxiliary oil pump may trip on overload, or the oil relief valve may lift due to high pressure and cause the bearing to be starved). The maximum oil temperature is 135°F.
This is based on allowing a maximum oil temperature out of the bearing of 185°F, with an -40°F rise across the bearing.
- 2. If injection water is aligned to a non-running Condensate Booster Pump, the pump should either be promptly started or injection water isolated to avoid water intrusion to the CBP's oil system.
G. Standby Main Feedwater Pump
- 1. 1-PCV-3-40 must be set at 1200 psia and closed, and 1-FCV-3-195 closed before starting any of the three MFPs.
- 2. The Standby Main Feed Pump minimum oil temperature recommendation is 70°F to 80°F. This is based on ensuring adequate oil is available during startup, when the oil temperature is lowest. (with oil temperature this low, the auxiliary oil pump may trip on overload, or the oil relief valve may lift due to high pressure, and cause the bearing to be starved). The maximum oil temperature is 135°F. This is based on allowing a maximum oil temperature out of the bearing of 185°F, with an -40°F rise across the bearing.
- 3. Standby Main Feed Pump (SMFP) should be operated at low flow conditions without a Condensate Booster Pump, to prevent lifting #1 Heater relief valves at 1650 psig.
- 4. SMFP Motor, Gear, and Pump Lube systems should be heated to 140 to 160°F oil leaving the bearings before placing RCW in service to the oil coolers. Oil temp alarm is 170°. This helps limit startup vibration.
- 5. A feedwater isolation (FWI) signal will cause the SMFP miniflow valves to fully open. The valves will return to their modulated position on FWI signal reset, or they can be controlled manually. This deSign design change was made signal on FWI to limit the to give the miniflow valves a "head start" open Signal delta pressure transient across the valves for improvement of operation
) and service life.
WBN Condensate And Feedwater System SOI-2&3.01 Unit 1 Rev. 0106 Page 15 of 291 3.0 PRECAUTIONS AND LIMITATIONS (continued)
- 6. The following are monitored during Standby MFP operation. Pump is manually tripped if manufacturer's limit is reached and no auto-trip occurs.
PARAMETER MANUFACTURER'S LIMIT Low Suction Press 100 psig (below 50% load) 250 psig (50% load or above)
High Discharge Press 1363 psig Low Bearing Oil Press 8 psig or less (Auto Trip) 1 0 psig or less (Auto Trip) 10 High Vibration 0.005 in. or above displacement (No Auto Trip)
High Bearing Metal Temp 225°For more (Journal & Thrust)
')
)
- 7. The following guidance may be used to start or stop the SBMFP during hot weather.
NOTE The "MFPT CONDENSER VACUUM LO" alarm [Window 55-0] comes in at 12.5" Hg vacuum (17.5" HgA). This corresponds to a MFPT condenser drain temperature of ",,185°F. ~185°F.
If the SBMFP is in service due to elevated hotwell and circulating water temperatures, the following guidance may be used to remove the SBMFP from service as water temperatures drop:
The SBMFP may be secured if any of the following conditions exist:
- a. Both MFPT condensers are ~12.5 in. HgA, OR
- b. Hotwell pump discharge temperature drops to ~129°F, OR
- c. C zone main condenser back pressure drops to ~ 5.0 in. HgA, OR
- d. CCW inlet temperature drops to ~ 87°F (should be secured prior to
~ 67°F) with all 4 CCW pumps in service, OR
- e. MFPT Condenser drain temperature ~171 OF.
WBN Condensate And Feedwater System SOI-2&3.01 Unit 1 Rev. 0106 Page 16 of 291 3.0 PRECAUTIONS AND LIMITATIONS (continued)
If the SBMFP is NOT in service, the following guidance may be used to place the SBMFP in service as water temperatures rise:
The SBMFP should be placed in service if any of the following conditions exist:
- f. Either MFPT condensers are >15.4 in. HgA, OR
- g. Hotwell pump discharge temperature achieves the maximum allowable condensate polisher inlet temperature of 140°F, OR
- h. C zone main condenser back pressure achieves the alarm setpoint when operating above 90% power, OR
- i. Plant power is power limited due to C Zone main condenser back pressure exceeding the associated alarm setpoint, OR
- j. MFPT Condenser drain temperature >180°F.
- 8. All jumper installation and removal shall be in accordance with O-PI-OPS-1.1, Jumper Control Process.
H. MFWPs/MFPTs
- 1. MFPTs and MFPs Motor, Gear, and Pump Lube systems should be heated to 140 to 160°F oil leaving the bearings before placing RCW in service to the oil coolers. Oil temp alarm is 170°F. This helps limit startup vibration.
- 2. The MFPT turning gear is NOT designed to be "rolled off' like the main turbine. Any action or evolution that could spin the MFP turbine while the turning gear is in operation could result in damage if the turning gear is NOT removed from service. Example: Unisolating the manual valves to the HP or LP steam supply.
- 3. MFP suction press should be kept as low as possible to help prevent exceeding the discharge piping design pressure of 1230 psig. However, short duration disch press up to 1363 psig is acceptable.
- 4. The TDMFP should NOT be operated until sufficient forward flow (approx 4500 gpm) can be provided continuously to the SGs using the SMFP.
- 5. Trip of a MFPT, loss of MFPT reset, or reset of a MFP NOT available due to maintenance activities, may cause ESFAS AFW start or require entering LCO 3.3.2, Condition J.
WBN Condensate And Feedwater System 501-2&3.01 SOI-2&3.01 Unit 1 Rev. 0106 Page 17 of 291 3.0 PRECAUTIONS AND LIMITATIONS (continued)
- 6. A feedwater isolation (FWI) signal will cause the TDMFP miniflow valves to fully open. The vales will return to their modulated position on FWI signal reset, or they can be controlled manually. This design change was made to give the miniflow valves a "head start" open signal on FWI to limit the delta pressure transient across the valves for improvement to operation "nd service life.
- 7. If MFPT steam seals are applied with rotor at rest, rotor, seal, and/or bearing damage can occur. Prolonged admission of seal steam before establishing condenser vacuum may damage condenser. Removing steam seals before condenser vacuum is zero, may damage seals due to high air in-leakage through seals.
- 8. When extended shutdown of MFP Turbines is required, voltage should be removed from affected MFPT Control Panel to extend relay coillife. coil life. 44
- 9. MFP Turbine vibration is high when operated at rated speed (5012 RPM) and low forward flow or recirc flows. Operator action should be taken to
) minimize time in this condition to less than 20 minutes, at which time speed aGceptable vibration conditions.
should be reduced to achieve acceptable
- 10. The following are monitored during MFP operation. MFPs are manually tripped if manufacturer's limit is reached and no auto-trip occurs:
PARAMETER MANUFACTURER'S LIMIT PUMP Low Suction Press load) 100 psig (below 50% loa<;l) MFPs 250 psig (50% load or above)
High Discharge Press 1363 psig MFPs Low Bearing Oil Press 8 psig or less (Auto Trip) MFPs & MFPT MFPs&
10 psig or less (Auto Trip)
Low Vacuum 10 in. Hg or less (Auto Trip) MFPT High Vibration 0.005 in. or above displacement (No MFPs & MFPT MFPs&
Auto Trip)
High Thrust Bearing Wear 0.010 in. or more wear displacement MFPT from 0 (Auto Trip)
High Bearing Metal Temp 225°F or more (Journal & Thrust) & MFPT MFPs &MFPT Overspeed 6006 to 6126 rpm (Auto Trip) MFPT
WBN Condensate And Feedwater System SOI-2&3.01 Unit 1 Rev. 0106
)
Page 18 of 291 3.0 PRECAUTIONS AND LIMITATIONS (continued)
- 11. In Mode 1, entry into Tech Spec 3.3.2 condition JJ may be suspended for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> when placing the second Turbine Driven Main Feedwater Pump (TDMFWP) in service or removing one of two Turbine Driven Main Feedwater Pumps (TDMFWP) from service. Refer to Tech Spec 3.3.2 table 3.3.2-1.
- 12. In Mode 2, trip function of all Turbine Driven Main Feedwater Pumps (TDMFWP) is required when one or more (TDMFWP) is supplying feedwater to the Steam Generators. Refer to Tech Spec 3.3.2 condition J.
- 13. MFPT condenser initial vacuum is drawn using the Condenser Vacuum Pumps and then swapped to the Main Condenser to prevent creating a large pressure change in the Main Condenser.
I. MFPs Common/Feedwater
- 1. 1-PCV-3-40 must be set at 1200 psia and closed, and 1-FCV-3-195 closed before starting any of the three MFPs.
)
- 2. MFW discharge piping Overpressure may occur if CBPs or Cond Demin Pumps are operated in conjunction with the MFPs below 50% Power.
- 3. Loss of MFP Injection Water may result in steaming or hot water leakage into the bearing oil or bearing overheat. Injection Water should be restored immediately, or a controlled shutdown of the MFP should be initiated.
- 4. When MFW flow is stopped, the MFW piping may lose its charge to the main condenser. The line charge and pressure must be reestablished very slowly past the valves or pump used to stop flow, prior to reopening the valves or starting pump, to prevent a severe water-hammer.
- 5. MFW Bypass flows in excess of 84,510 pph will exceed the calibration bypass flow transmitters' computer pOints range of the bypass, points F0407A, F0427A, F0447 F044 7A, and F0467A which will make U U1118 1118 series ICS venturi -based calorimetric power inaccurate.
- 6. bypass FRVs should be momentarily During startup, the main FRVs and bypass throttled almost closed, prior to starting the first higher pressure pump (COPs, CBPs, MFPs) and the flow and pressure downstream of FRVs (CDPs, established very slowly, to avoid severe waterhammer.
J
/
WBN Condensate And Feedwater System SOI-2&3.01 Unit 1 Rev. 0106 Page 19 of 291 3.0 PRECAUTIONS AND LIMITATIONS (continued)
- 7. For short duration test purposes, using a single MFP, 1-FCV-3-195 may be opened to allow higher long cycle recirculation flow than achievable via 1-PCV-3-40, with the following limitations:
- a. MFWand long cycle piping must be charged and at the higher pressure before opening 1-FCV-3-195.
- b. 1-FCV-3-195 to be gradually opened fully and NOT throttled.
- c. Limited to two MFW loops with the other two loops main and bypass FRVs and long cycle paths closed (single loop flow performed for SMFP).
- d. Throttle flow on the one or two open main FRVs.
- f. Should only be done during cold shutdown long cycle recirculation.
WBN Condensate And Feedwater System SOI-2&3.01 .-
Unit 1 Rev. 0106
)
Page 20 of 291 3.0 PRECAUTIONS AND LIMITATIONS (continued)
J. load)/Swapover Operations:
Low Power (Below 22% 10ad)/Swapover
- 1. SG Feedwater additions must be via the upper (bypass) nozzle and should be continuous rather than intermittent, to reduce SG upper nozzle thermal cycling, but intermittent flow is permitted.
- 2. SG lower nozzle must be isolated (MFW ISOL MOVs closed) to prevent cold water, at the hot lower nozzle, in order to limit the number of feedwater system induced transients and the minimum temperature of continuous FW flow into the S/G preheater region.
- 3. 1-HS-3-45, LONG CYCLE RECIRC-NORMAL, accomplishes partial auto realignment for the 2 modes; however, manual positioning of some valves is required as directed by this instruction.
- 4. The interlock functions of 1-HS-3-45, LONG CYCLE RECIRC-NORMAL, are functional, but the operator is expected to take appropriate action if conditions warrant. Feedwater flow to the lower nozzle must be terminated
)
and bypass flow established if any of the following minimums are reached:
(1) MFW line temp below 250°F.
(2) MFW line flow below 14%.
- 5. (ARI-57-63 A low flow alarm at 20% (ARI-57 -63 Window 59-C) gives the operator time to take corrective action before manual actions must be taken when flow drops to <14%. This low flow condition <<14%) is indicated by the extinguishing of the blue Main Flow> SP lights on 1-M-3.
WBN Condensate And Feedwater System SOI-2&3.01 501-2&3.01 Unit 1 Rev. 0106 Page 21 of 291 Date~ INITIALS 4.0 PREREQUISITE ACTIONS 4.1 Preliminary Actions NOTES
- 1) Throughout this instruction where IF/THEN exists, step is N/A if condition does NOT exist.
- 2) Most instructional steps may apply to more than one piece of equipment; e.g., MFPs.
N/A may be entered for steps NOT being performed.
- 3) All Sections in this procedure shall be considered CONTINUOUS USE unless specified otherwise.
- 4) Throughout this instruction, Concurrent Verification (CV) may be marked N/A for breaker or fuse steps where no manipulation is performed.
[1] INDICATE Section to be performed, and reason for use:
5.0 Startup 7.0 Shutdown 6.0 Normal 8.0 Infrequent Operation - -N/AN!A
--- Operations 8' '1 t Cj Section/
Section! Reason/
Reason! Remarks: f>Pla(..f..
la(.-e, ~rv\t=p
~fY\~p JY\ s~k..e...
In suvk..e..
with ClMd. II'B I A Qrrtd. f'(\Ffs, 15 rt\ Ffs . '
WBN Condensate And Feedwater System 501-2&3.01 SOI-2&3.01 Unit 1 Rev. 0106 Page 22 of 291 Date~ INITIALS 4.2 Field Preparations
[1] .ENSURE the following:
NOMENCLATURE LOCA TION LOCATION I POSITION I UNID PERF INITIAL 480V Turbine Bldg Vent Bd 1A CNDSVACUUM PUMPS COOLER C/8B ON 1-BKR-30-883 rv-..
fir... ~cvl
~cv HOTWELL PUMPS C/8C ON 1-BKR-30-886 COOLER ~ ~cv STANDBY MAIN FEED C/7C ON 1-BKR-30-887 PUMP COOLER ~
<"". ~cv F"cv 480V Turbine Bldg Vent Bd 1B CONDENSATE C/7E ON 1-BKR-30-882 BOOSTER PUMPS COOLER 1A
~ ~
['
cv CONDENSATE C/8E ON 1-BKR-30-881 BOOSTER PUMPS ~
COOLER 1B ~ cv NO.3 HTR DRAIN C/8A ON 1-BKR-30-885 TANK PUMPS COOLER I'vv\
'Vv\ ~cv 1-M-7 TO PNL 1-L-275 MFPI MFPT 120V AC 120VAC ON 1-BKR-46-L275 1A IND & DRAIN VLVS INSTR PWRARACK ~ ~cv
- rOcv TO JB 579 FW 120V AC 120VAC ON 1-BKR-291-579 PUMPSA& B INSTR OUTLET FLOW PWRARACK ~ ~ cv TO PNL 1-L-276 MFPT 120V AC 120VAC ON 1-BKR-276-L276 1B IND & DRAIN VLVS PNL 1-R-72 INSTR PWR BRACK PWRBRACK 120VAC ON 1-BKR-275-R072/05 m.,
~ ~ cv r:n PREFERRED POWER BUS PREFERRED PWRRACK Vv) tv'V\ reo
~cv 120V AC Preferred Power Board 1 LEADING EDGE 120VAC ON 1-BKR-238-1/20 FLOWMETER SUPPLY BKR SUPPLYBKR PREFERRED POWERBD Lv\..
Lv\- ~ cv
WBN*
WBN Condensate And Feedwater System 501-2&3.01 Unit 1 Rev. 0106 Page 23 of 291 Date~ INITIALS 4.3 Approvals and Notifications
[1
[1)) COORDINATE system operations/manipulations with UO. A.A/)'J
WBN Condensate And Feedwater System SOI-2&3.01 Unit 1 Rev. 0106 Page 157 of 291 Date ."f\-...,
t\f\..,
Date I~
8.9 Replacing Turbine Driven MFP with SMFP, or Periodic Operation ofSMFP of SMFP
""---' MFP discharge should remain less than 1185 psig when possible. Short duration
~....,.........
.7'-o..press press up to 1363 psig (MFP Disch Press Admin Limit) is acceptable, but care must be pressure elevations from lifting #1 Heater Reliefs at taken to prevent sudden pressure 1650 psig.
Tripping either MFP with runback circuitry enabled will cause a BOP runback.
Runback circuitry may be verified at 1-L-262 [729, T3J] using PIS-47-13 display.
RLY1 indicates load >67% and RLY3, indicates load >-85%. >85%. Impulse pressure equivalent to 85% load enables the runback circuitry.
MFP 1B must NOT be operated at a higher speed than MFP 1A or in the resonance speed range between 4900 and 5000 rpm due to high vibration on the inboard bearing and turning gear motor. Speed controllers have been calibrated to prevent this
) condition; however, a WO should be generated if the controllers fail to control this occurrence.
sufficien flow One MFP is capable of delivering sufficient ow to maintain 67% load.
Unit load can be maintained at 85% with the SMFP and one MFP in operation.
Unit load can be maintained at 100% for periodic operation of SMFP with one TDMFP partially unloaded.
Starting a main feed pump (SBMFP or MFPT) may cause perturbation in heater drain ank levels that may NOT be compensated for by the level level controllers.
In Mode 1, entry into Tech Spec 3.3.2 condition J may be suspended for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> when removing one of two Turbine Driven Main Feedwater Pumps (TDMFWP) from service. Refer to Tech Spec 3.3.2 table 3.3.2-1.
of all Turbine Driven Main Feedwater Pumps (TDMFWP) is .
In Mode 2, trip function otall supplying feedwater to the Steam required when one or more (TDMFWP) is supplyingfeedwater Generators. Refer to Tech Spec 3.3.2 condition J.
~ IF one TDMFP is to be completely shutdown, THEN Circuitry reset by verifying RLY3, ENSURE Turbine Runback circuitry PIS-47-13 DISPLAY NOT actuated <<85%) [PaneI1-L-262]
[729/T3J] NLA NJA
WBN Condensate And Feedwater System SOI-2&3.01 Unit1 Rev. 0106 Page 158 of 291 Date*~
Date~ INITIALS 8.9 Replacing Turbine Driven MFP with SMFP, or Periodic Operation of SMFP (continued)
~ ENSURE SMFP is aligned for service per Section 5.9. ~
[3] VERIFY 1-FIC-3-208 [1-FIC-3-208], STANDBY MFWP RECIRC CONTROL [1-M-3], in AUTO, AND SET at 90% (1500 gpm).
[4] ENSURE 1-FCV-3-205 [1-HS-3-205], STANDBY MAIN FEEDWATER PUMP DISCHARGE ISOL [T1J/729], OPEN.
[5] ENSURE 1-FCV-2-265 [1-HS-2-265], STANDBY MAIN FW PUMP SUCT ISOL [T1J/729], OPEN.
[6] VERIFY 1-PI-2-129, MFW PMPS SUCT PRESS [1-M-3], as follows:
A. Greater than 100 psig (below 50% load).
B. Greater than 250 psig (at or above 50% load).
[7] ENSURE 1-FCV-3-208 [1-HS-3-208], STANDBY MAIN FEEDWATER PUMP MIN FLOW [T1J/729], CLOSED.
CAUTION Manual operation of TDMFP speed control during MFP starts/stops will minimize system fluctuations.
[8] CONTROL TDMFP speed in MAN.
[9] IF SMFP to operate with TDMFP, THEN SLOWLY RAISE TDMFP speed until SMFP minimum flow head is achieved (above 1200 psig).
[10] IF SMFP to operate with TDMFP, THEN START SMFP with 1-HS-3-200A, STANDBY MFWP, and LOWER TDMFP flow, or SHUTDOWN TDMFP per Section 7.3.
WBN Condensate And Feedwater System SOI-2&3.01 Unit 1 Rev. 0106 Page 159 of 291 Date_ __ INITIALS 8.9 Replacing Turbine Driven MFP with SMFP, or Periodic Operation of SMFP (continued)
[11] ENSURE SMFP operation in accordance with Section 5.9.
[12] RETURN TDMFP speed control to AUTO, as desired.
WATTS BAR NUCLEAR PLANT B.1.e
'\ Nov. 2009 NRC Exam
)
B.1.e Align Control Rod Drive Mechanism Coolers.
PA(';F PAC:;F 1 OF 1?
WATTS BAR NUCLEAR PLANT B.1.e
)
Nov. 2009 NRC Exam Task: Align Control Rod Drive Mechanism (CRDM) Coolers.
Alternate Path: None.
Facility JPM #: New Safety Function: 5
Title:
Containment Integrity KIA 022 A4.01 Ability to manually operate and/or monitor in the control room: CCS fans.
Rating(s): 3.6// 3.6 3.6 CFR: 41.7 / 45.5 to 45.8 Preferred Evaluation Location: Preferred Evaluation Method:
Simulator x X
In-Plant Perform X Simulate
References:
SOI-30.03, "Containment HVAC and Pressure Control," Rev. 42.
Task Number: RO-30-S01-30-002
Title:
Startup/Place in Standby Alignment the Upper Compartment Coolers.
Task Standard: Applicant shuts down CRDM coolers C-A and D-B, and places CRDM coolers A-A and B-B in service using SOI-30.03, "Containment HVAC and Pressure Control."
/
) .. .
Validation Time: 10 minutes Time Critical: Yes - - No ----=--~X
=-=----
===============================================================
Applicant: Time Start:
NAME SSN Time Finish: - - - -
Performance Rating: SAT UNSAT Performance Time Examiner:
Examiner: ____________________________
- - - - -NAME ------- -----------~/_---
~/_----
SIGNATURE DATE
===============================================================
===============================================================
COMMENTS
)
PA~F? nF PA(';F? OF 1?
WATTS BAR-(~UCLEAR BAR~f~UCLEAR PLANT B.1.e Nov. 2009 NRC Exam SIMULATOR OPERATOR INSTRUCTIONS:
- 1. ENSURE NRC Examination Security has been established.
- 2. Right click on 329, and then select RESET.
- 3. Enter the password.
- 4. Select "Yes" on the INITIAL CONDITION RESET pop-up window.
- 5. Place simulator in RUN and acknowledge any alarms.
- 6. ENSURE the following cooler configuration:
Lower CNTMT Coolers Upper CNTMT Coolers CRDM Coolers A- RUNNING A- RUNNING A-OFF B - RUNNING B - RUNNING B-OFF B - OFF C - RUNNING C - RUNNING C - RUNNING D-OFF D-OFF D - OFF D - RUNNING
- 6. Place simulator in FREEZE until Examiner cue is given.
PAGE 3 OF 12
WATTS BAR NUCLEAR PLANT B.1~e B.1 ~e Nov. 2009 NRC Exam DIRECTIONS TO APPLICANT DIRECTION TO APPLICANT:
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 assignedaSSigned task return the handout sheet I provided you.
INITIAL CONDITIONS:
- 1. Predictive Maintenance has requested that the C-A CRDM Cooler be removed from service in order to perform maintenance on its 480V supply breaker.
- 2. You are an extra operator assigned to the shift.
INITIATING CUES:
- 1. The Unit Supervisor directs you to place 1 A-A and 1B-B CRDM Coolers in 1A-A service and place 1C-A and 1D-B CRDM Coolers in reserve using SOI-30.03," 501-30.03,"
Containment HVAC and Pressure Control" to support the upcoming maintenance.
- 2. Notify the Unit Supervisor when the CRDM coolers have been aligned.
PAr,F 4 OF1?
()F 1?
WATTS BAR NUCLEAR PLANT B.1.e Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT START TIME: _ __
STEP 1: Obtain the proper procedure. SAT STANDARD: A copy of SOI-30.03 is obtained by the applicant. UNSAT EXAMINER'S CUE: After the applicant has demonstrated the method of obtaining the correct instruction, the evaluator can provide a copy of the instruction.
COMMENTS:
- '~rIE1({~t,ALU.l\TO*~i NOTE TO EVALUATOR .. Th*~ The*.*
- f()II();ing~-cti.ons*ar~****t~k~.n following actions are taken *. fr()~****SOI~;9.()3~[§~.cti()niJ from SOI-30.03, Section ij~~6,"CRDIViShroud.CoolingAlignment 5.6,"CRDM Shroud Cooling Alignment
"/> / " //,' ',>,/,. :,' -'-'-_', ',U; " *,iI -.-: ' '<,.. ' , ' ',' , ,"
and CRDM Cooler Startup."
,',i' ' : ;Ji1 i i / . .
CAUTION Under certain shutdown configurations, starting of CRDM Coolers has the potential to cause the ice condenser lower inlet doors to open if they are NOT properly restrained.
NOTES
- 1) Normally, two CRDM Coolers are in service and two in reserve. CRDM Coolers 1A-A and 18-8 1B-B should be operated together OR 1 C-A and 1D-8 D-B should be operated together for power train separation. Deviation from this alignment requires 1 A-A and 1C-A 1A-A 1C-A OR 18-8 1B-B and 1D-8 D-B to ensure proper air flow.
- 2) The temperature indicated on each cooler's TIC is that cooler's air inlet temperature. CRDM Cooler air outlet temperature is displayed on ICS points. ICS Point T1014A, OP REFUEL GATE, may be used to determine the temperature in the CRDM shroud area.
PAGE 5 OF 12
WATTS BAR NUCLEAR PLANT B.1.e Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 2: [1] IF CRDM CLR D-8 is to be used to cool shroud [1-M-9], SAT THEN
[1.1] ENSURE 1-HS-30-80A, CRDM CLR D-8 MTR 1&2, UNSAT in A-AUTO and 1-HS-30-81 1-HS-30-81A,A, CRDM CLR D-8 SHROUD SUCT, in P-AUTO, AND START CRDM CLR D-8 with 1-HS-30-80A.
[1.2] ENSURE CRDM CLR D-8 is RUNNING.
[1.3] ENSURE 1-TCO-30-81, CRDM CLR D-8 SHROUD SUCT, is OPEN, and 1-TCO-30-82, CRDM CLR D-8 LWR CNTMT SUCT,is SUCT, is CLOSED.
STANDARD:
Applicant determines that CRDM CLR D-8 is in service, and will be placed in reserve. Applicant enters N/A for this step.
COMMENTS:
PAGE 6 OF 12
WATTS BAR NUCLEAR PLANT B.1.e Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 3: [2] IF CRDM CLR A-A is to be used to cool shroud [1-M-9], CRITICAL THEN STEP
[2.1] ENSURE 1-HS-30-83A, CRDM CLR A-A MTR 1&2, in A-AUTO and 1-HS-30-84A, CRDM CLR A-A SAT SHROUD SUCT, in P- AUTO, AND START CRDM CLR with 1-HS-30-83A. UNSAT
[2.2] ENSURE CRDM CLR A-A is RUNNING.
[2.3] ENSURE 1-TCO-30-84, CRDM CLR A-A SHROUD SUCT, is OPEN, and 1-TCO-30-85, CRDM CLR A-A LWR CNTMT SUCT, is CLOSED.
STANDARD:
Applicant ensures 1-HS-30-83A, CRDM CLR A-A MTR 1&2, in A-AUTO and 1-HS-30-84A,CRDM 1-HS-30-84A, CRDM CLR A-A SHROUD SUCT, in P- AUTO, and starts CRDM CLR with 1-HS-30-83A.
Applicant ensures 1-TCO-30-84, CRDM CLR A-A SHROUD SUCT, is OPEN, and 1-TCO-30-85, CRDM CLR A-A LWR CNTMT SUCT, is CLOSED.
Step is critical to establish proper shroud cooling.
COMMENTS:
PAGE 7 OF 12
WATTS BAR NUCLEAR PLANT B.1.e Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 4: [3] IF CRDM CLR 8-8 is to be used to cool shroud [1-M-9], CRITICAL THEN STEP
[3.1] ENSURE 1-HS-30-92A, CRDM CLR 8-8 MTR 1 &2, in 1&2, A-AUTO and 1-HS-30-93A, CRDM CLR 8-8 SAT SHROUD SUCT, in P-AUTO, AND START CRDM CLR with 1-HS-30-92A. UNSAT
[3.2] ENSURE CRDM CLR 8-8 is RUNNING.
[3.3] ENSURE 1-TCO-30-93, CRDM CLR 8-8 SHROUD SUCT, is OPEN, and 1-TCO-30-94, CRDM CLR 8-8 LWR CNTMT SUCT, is CLOSED.
STANDARD:
Applicant ensures 1-HS-30-92A, CRDM CLR 8-8 MTR 1&2, in A-AUTO and 1-HS-30-93A, CRDM CLR 8-8 SHROUD SUCT, in P-AUTO, and starts CRDM CLR with 1-HS-30-92A.
Applicant ensures 1-TCO-30-93, CRDM CLR 8-8 SHROUD SUCT, is OPEN, and 1-TCO-30-94, CRDM CLR 8-8 LWR CNTMT SUCT, is CLOSED Step is critical to establish proper shroud cooling.
COMMENTS:
PAGE 8 OF 12
WATTS BAR NUCLEAR PLANT B.1.e Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 5: [4] IF CRDM CLR C-A is to be used to cool shroud [1-M-9], SAT THEN
[4.1] ENSURE 1-HS-30-88A, CRDM CLR C-A MTR UNSAT 1&2, in A-AUTO and 1-HS-30-89A, CRDM CLR C-A SHROUD SUCT, in P-AUTO, AND START CRDM CLR with 1-HS-30-88A.
[4.2] ENSURE CRDM CLR C-A is RUNNING.
[4.3] ENSURE 1-TCO-30-89, CRDM CLR C-A SHROUD SUCT, is OPEN, and 1-TCO-30-90, CRDM CLR C-A LWR CNTMT SUCT, is CLOSED.
STANDARD:
Applicant determines that CRDM CLR C-A is in service, and will be placed in reserve. Applicant enters N/A for this step.
COMMENTS:
PAGE 9 OF 12
WATTS BAR NUCLEAR PLANT B.1.e Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 6: [5] IF CRDM Cooler is to be placed in reserve, THEN SAT ENSURE the following: (N/A coolers in service)
[5.1] 1-HS-30-80A, CRDM CLR D-8 MTR 1&2, in A- UNSAT AUTO, and Cooler NOT running.
[5.2] 1-HS-30-83A, CRDM CLR A-A MTR 1&2, in A-AUTO, and Cooler NOT running.
[5.3] 1-HS-30-92A, CRDM CLR 8-8 MTR 1&2, in A-AUTO, AND Cooler NOT running.
[5.4] 1-HS-30-88A, CRDM CLR C-A MTR 1&2, in A-AUTO, and Cooler NOT running.
STANDARD:
Applicant determines that CRDM CLRS D-8 and C-A will be placed in reserve at this time.
Applicant enters N/A for steps 5.2 and 5.3.
Applicant performs Step 5.1, stops CRDM CLR D-8 by placing 1-HS 80A to STOP, then returning the switch to A-AUTO.
Applicant performs Step 5.4, stops CRDM CLR C-A by placing 1-HS 88A to STOP, then returning the switch to A-AUTO.
COMMENTS:
PAGE 10 OF 12
WATTS BAR NUCLEAR PLANT B.1.e Nov. 2009 NRC Exam
)
~I-----------------sT-E-P-/s-T-A-N-D-A-R-D----------------~-S-A-TI-U-N-SA-T~
STEP/STANDARD SAT/UNSAT STEP 7: Extra Operator reports that the containment coolers have been per SOI-30.03," Containment HVAC and Pressure Control."
STANDARD:
CUE: Repeat back information provided by the applicant.
COMMENTS:
END OF TASK STOP TIME _ __
)
PAGE 11 OF 12
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
DIRECTION TO APPLICANT:
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:
- 1. Predictive Maintenance has requested that the C-A CRDM Cooler be removed from service in order to perform maintenance on its 480V supply breaker.
- 2. You are an extra operator assigned to the shift.
INITIATING CUES:
- 1. The Unit Supervisor directs you to place 1A-A 1A-A and 1 B-B CRDM Coolers in 18-8 service and place 1C-A and 1D-B D-8 CRDM Coolers in reserve using SOI-30.03,"
501-30.03,"
Containment HVAC and Pressure Control" to support the upcoming maintenance.
- 2. Notify the Unit Supervisor when the CRDM coolers have been aligned.
II!D Watts Bar Nuclear Plant Unit 1 System Operating Instruction SOI-30.03 Containment HVAC and Pressure Control Revision 0042 Quality Related Level of Use: Continuous Use Effective Date: 02-11-2008 Responsible Organization: OPS, Operations Prepared By: Scot Newell Approved By: A. K. Keefer
WBN Containment HVAC and Pressure 501-30.03 Unit 1 Control Rev. 0042 Page 2 of 59 ... _
Revision Log Revision Affected or Change Effective Page Number Date Numbers Description of Revision/Change 38 03/16/06 2, all, 20, 22 Replaced the word VERIFY with the word CHECK where appropriate.
32 Added note to 5.7 [1] to state the local thermal overload can trip on inadequate air flow if louvers NOT fully open.
Provided location of 0-XX-55-27A.
Enhanced wording to Step 3 to ensure rad monitor in service to lower containment.
39 11/23/06 ALL This procedure has been converted from Word 95 to Word 2002(XP) using Rev 38.
6, 17,33 6,17,33 Added steps 5.4.[8] & [9], and 7.2.[4] & [5], which, implemented EDC 52133 which revised the ERCW SD to require performers to monitor ERCW discharge header levels for equipment configuration changes affecting flow.
40 02/16/07 38 Added Note 3 to 8.2.1 for PER 115430 41 08/03/07 17,18,34 Revised to incorporate PER 124935-004 adding instruction to perform either Appendix A or B as appropriate of SOI-67.01 if ultrasonic flow indication for ERCW is not working.
40 Added note prior to 8.2.1 [6] to allow step to be NIA to allow procedure to continue if Aux Bldg Vent Radiation Monitors OOS but Comp Measures per ODCM are in place.
42 02/11/08 26,37,52, For DCN 52192; added 5.7[5.1]; 8.5; 8.6; and 1-53,55-57 XSW-271-15 to checklist 2; and modified note for 7.5.
Minor ed. change: changed CVand CV and IV on checklist 1 and 2 to IV.
WBN Containment HVAC and Pressure SOI-30.03 Unit 1 Control Rev. 0042 Page 3 of 59 Table of Contents
1.0 INTRODUCTION
.......................................................................................................... 5 1.1 Purpose ........................................................................................................................ 5 1.2 Scope ............................................................................................................................ 5
2.0 REFERENCES
............................................................................................................. 5 2.1 Performance References References .............................................................................................. 5 2.2 Developmental References ........................................................................................... 5 3.0 PRECAUTIONS AND LIMITATIONS ........................................................................... 7 4.0 PREREQUISITE ACTIONS .......................................................................................... 9 4.1 Preliminary Actions ....................................................................................................... 9 4.2 Field Preparations ......................................................................................................... 9 4.3 Approvals and Notifications .......................................................................................... 9 5.0 STARTUP/RESERVE READINESS ........................................................................... 10 5.1 Upper CNTMT Cooler ERCW Alignment .................................................................... 10 5.2 Startup/Reserve Alignment of Upper CNTMT Coolers ................................................ 11 5.3 Lower CNTMT Cooler ERCW Alignment .................................................................... 13 5.4 Startup/Reserve Alignment of Lower CNTMT Coolers ................................................ 15 5.5 CRDM Cooler ERCW and Damper Alignment ............................................................ 19 5.6 CRDM Shroud Cooling Alignment and CRDM Cooler Startup .................................... 21 5.7 CNTMT Space Heater Standby Alignment ................................................................. 24 6.0 NORMAL OPERATION .............................................................................................. 27 6.1 Upper CNTMT Cooler Operation ................................................................................ 28 6.2 Lower CNTMT Cooler Operation ................................................................................ 29 6.3 CRDM Cooler Operation ............................................................................................. 31 6.4 CNTMT Space Heater Operation ................................................................................
............................ ,................................................... 32 7.0 SHUTDOWN ............................................................................................................... 33 7.1 Upper CNTMT Coolers Shutdown .............................................................................. 33 7.2 Lower CNTMT Coolers Shutdown .............................................................................. 33 7.3 CRDM Coolers Shutdown ........................................................................................... 35 7.4 Containment Vent Air Cleanup Units (CVACUs) Shutdown ........................................ 36 7.5 Upper CNTMT Space Heater Shutdown ..................................................................... 37
WBN Containment HVAC and Pressure SOI-30.03 Unit 1 Control Rev. 0042 Page 4 of 59 Table of Contents (continued) 8.0 INFREQUENT OPERATIONS .................................................................................... 38 8.1 Supplemental Lower CNTMT Cooling and CRDM Cooler Startup .............................. 38 8.2 Placing Containment Vent Air Cleanup Units(CVACUs) In Service ............................ 40 8.2.1 Preparation for placing CVACUs in Service .................................................. 40 8.2.2 Placing Containment Vent Filter 1-FLT-30-23 In Service .............................. 43 8.2.3 Placing Containment Vent Filter 1-FLT-30-24 T-30-24 In Service .............................. 43 8.3 Transfer of CRDM Cooler Motor Power Supply to 480V Receptacle Inside Lower Containment During Outages ................................................................ 44 8.4 Transfer of CRDM Cooler Motor Power Supply from 480V Receptacle Inside Lower Containment After Outages ................................................................... 48 8.5 Transfer of Upper Compartment Heater 1C Power Supply to Reactor Building Jib Crane During Outages ............................................................................. 52 8.6 Restoration of Upper Compartment Heater 1C Power Supply from the Reactor Building Jib Crane ......................................................................................... 53 9.0 RECORDS .................................................................................................................. 54 9.1 QA Records ................................................................................................................ 54 9.2 Non QA Records ......................................................................................................... 54 Checklist 1 1:: CNTMT Cooler Power Alignment Verification ........................................ 55 Checklist 2: CNTMT Heater Power Alignment Verification ........................................ 57 Checklist 3: CRDM Damper Alignment Verification .................................................... 58 Source Notes ............................................................................................. 59
WBN Containment HVAC and Pressure 501-30.03 SOI-30.03 Unit 1 Control Rev. 0042 Page 5 of 59
1.0 INTRODUCTION
1.1 Purpose To provide instructions for operating the Containment (CNTMT) HVAC and Pressure Control Systems.
1.2 Scope This Instruction includes the following operations:
A. Operation of the Upper CNTMT Coolers.
B. Operation of the Lower CNTMT Coolers.
C. Operation of the Control Rod Drive Mechanism (CRDM) Coolers.
D. Operation of the CNTMT Space Heaters.
E. Operation of the CNTMT Vent Air Cleanup Units.
2.0 REFERENCES
2.1 Performance References A. 1-SI-0-2 Series, Shift and Daily Surveillance Log B. 1-001-90-16, Containment Vent Release C. 1-PI-OPS-1-MCR, Plant Instruction Main Control Room D. SOI-67.01, Essential Raw Cooling Water System 2.2 Developmental References A. 3.6.4, 3.6.5 (CNTMT Press & Temp), 3.B.1 Tech Specs 3.6.4,3.6.5 3.8.1 B. Tech. Requirements 3.B.43.8.4 C. TVA Drawings:
45N600-30-1, -2, -B,-8, -9, -11 45W703-5, -6 45W755-1, -2, -4 45W760-30-B, 45W760-30-8, -9, -10, -15, -26 4 7W61 0-30-2 47W61 0-67-2, -3 47WB66-1 47W866-1 47WB45-3 47W845-3
WBN Containment HVAC and Pressure SOI-30.03 501-30.03 Unit 1 Control Rev. 0042 Page 6 of 59 2.2 Developmental References (continued)
D. FSAR 9.4.7, Containment Air Cooling System E. N3-67 -4002, System Description for ERCW F. N3-30RB-4002, System Description for Reactor Bldg Ventilation
WBN Containment HVAC and Pressure 501-30.03 Unit 1 Control Rev. 0042 Page 7 of 59 3.0 PRECAUTIONS AND LIMITATIONS A. Cooler air inlets should be checked to be free of debris before they are started.
B. When only 2 Lower CNTMT Coolers are in service, it is preferable to have one C-A) , and one fan running in the fan running in the North Fan Rm (Fan 1B-B or 1C-A),
South Fan Rm (Fan 1A-A or 1 1D-B).
D-B).
C. Lower CNTMT Coolers, CRDM Coolers, and RCP Motor Coolers are supplied by the same ERCW header.
D. Pzr Enclosure temperature must be monitored before and after starting or stopping Lower CNTMT Coolers. Rapid heat up rates effect Pzr Safety Valve leakage. The US should be notified of any drastic change in Pzr Enclosure temperature.
E. ThoteXceeds 180°F.
CRDM coolers must be in service BEFORE Thotexceeds F. Personnel should be clear of CRDM cooler outlets before a cooler is started.
G. Upper CNTMT Average Air Temp must be maintained 87.1°F 87.1 of to 107.9°F, and
)
Lower CNTMT 102.5°Fto LowerCNTMT 102.5°F to 117.5°F, in Modes 1,2,3,4. Maximum Lower j
Compartment average air temperature can be raised to 119°F, and Minimum Lower Compartment average air temperature can be lowered to 101°F, if ALL of the temperature inputs and U9020 are reliable (in other words, NONE of the pOints can be displayed on computer points have a quality code of "BAD"). The points computer group display for LWR AVG.
H. Operating certain three-cooler combinations may NOT adequately cool EO EQ spaces in lower containment. During operation in this condition, added attention should be provided to the lower compartment EO EQ spaces, especially the pressurizer compartment temperature (computer point T1001A) to ensure the spaces are maintained at or below their maximum normal temperatures.
EQ temperature limits are identified in 1-PI-OPS-1-MCR.
EO I.
I.. CNTMT press must be maintained -0.07 to +0.27 psid relative to the Annulus.
L1P should be maintained at least 5.4 in. H20.
Annulus .6.P
WBN Containment HVAC and Pressure 501-30.03 SOI-30.03 Unit 1 Control Rev. 0042 Page 8 of 59 3.0 PRECAUTIONS AND LIMITATIONS (continued)
J. Upper CNTMT Coolers, Lower CNTMT Coolers, AND CRDM Coolers are operated manually. Placement of these handswitches in the (Pull) A-P AUTO pOSition requires an operability evaluation for the associated train Diesel position Generator. The two allowed positions for their respective handswitches are:
- 1. A-AUTO (IN) for running or reserve coolers.
- 2. STOP/PULL-TO-LOCK for unavailable coolers The reserve status is used in this Instruction to describe a cooler which is stopped but otherwise available for manual start.
K. Phase 8 (08) isolation trips the in-service coolers and isolates ERCW.
L. Changing CRDM fan/damper alignment can cause shroud temperature changes that may affect RPI indications. Instrument Maintenance (MIG) should be notified to ensure required instruments will be placed in service as necessary to support system operation.
M. Work in Radiologically Controlled Areas (RCAs) may require existing RWPs, 1 and possibly ALARA Preplans. Failure to follow posted Rad control requirements may cause unnecessary radiation exposure. Rad Con should be notified of work having the potential to change radiological conditions.
WBN Containment HVAC and Pressure SOI-30.03
\) Unit 1 Control Rev. 0042 Page 9 of 59 Date_ __ INITIALS 4.0 PREREQUISITE ACTIONS 4.1 Preliminary Actions NOTES
- 1) IF/THEN exists, the step is N/A if condition does Throughout this instruction where IFITHEN NOT exist.
- 2) Throughout this instruction, Concurrent Verification (CV) for breaker or fuse manipulations may be marked N/A if no manipulation is performed
[1] INDICATE section to be performed and reason for use:
5.0 Startup 7.0 Shutdown Normal Infrequent 6.0 Operation - _- _- _- _-_ 8.0 Operations ___ __ __ __
Section/ Reason/ Remarks:
4.2 Field Preparations
[1] ENSURE Section 3.0 Precautions and Limitations, reviewed.
4.3 Approvals and Notifications
[1] COORDINATE system operations/manipulations with UO.
[2] IF work is in a radiation / contamination area, THEN NOTIFY RADCON for surveys and/or permits as necessary.
WBN Containment HVAC and Pressure SOI-30.03 Unit 1 Control Rev. 0042 Page 21 of 59 Date_ __ INITIALS 5.6 CRDM Shroud Cooling Alignment and CRDM Cooler Startup CAUTION Under certain shutdown configurations, starting of CRDM Coolers has the potential to NOT properly restrained. 11 cause the ice condenser lower inlet doors to open if they are NOT NOTES
- 1) Normally, two CRDM Coolers are in service and two in reserve. CRDM Coolers 1A-A 1B-B should be operated together OR 1C-A and 1D-8 and 18-8 D-B should be operated together for power train separation. Deviation from this alignment requires 1 A-A 1A-A and 1C-A OR 18-81 B-B and 1D-8 D-B to ensure proper air flow.
- 2) The temperature indicated on each cooler's TIC is that cooler's air inlet temperature.
CRDM Cooler air outlet temperature is displayed on ICS points. *ICSICS Point T1014A, T1 014A, OP REFUEL GATE, may be used to determine the temperature in the CRDM shroud area.
[1] IF CRDM CLR D-8D-B is to be used to cool shroud [1-M-9], THEN
[1.1] ENSURE 1-HS-30-80A, 1-HS-30-S0A, CRDM CLR D-8 D-B MTR 1&2,in 1&2, in A-AUTO and 1-HS-30-81A, 1-HS-30-S1A, CRDM CLR D-8 D-B SHROUD SUCT, in P-AUTO, AND START CRDM CLR D-8 D-B with 1-HS-30-80A.
1-HS-30-S0A.
[1.2] ENSURE CRDM CLR D-8 D-B is RUNNING.
[1.3] ENSURE 1-TCO-30-81, 1-TCO-30-S1, CRDM CLR D-8 D-B SHROUD SUCT, is OPEN, and 1-TCO-30-82, 1-TCO-30-S2, CRDM CLR D-8 D-B LWR CNTMT SUCT, is CLOSED.
WBN Containment HVAC and Pressure SOI-30.03 Unit 1 Control Rev. 0042
.Page 22 of 59 Date- _ __ INITIALS 5.S 5.6 CRDM Shroud Cooling Alignment and CRDM Cooler Startup (continued)
[2] IF CRDM CLR A-A is to be used to cool shroud [1-M-9], THEN
[2.1] ENSURE 1-HS-30-83A, CRDM CLR A-A MTR 1 1&2,
&2, in A-AUTO and1-HS-30-84A, CRDM CLR A-A SHROUD SUCT, in P-AUTO, AND START CRDM CLR with 1-HS-30-83A.
[2.2] ENSURE CRDM CLR A-A is RUNNING.
[2.3] ENSURE 1-TCO-30-84, CRDM CLR A-A SHROUD SUCT, is OPEN, and 1-TCO-30-85, CRDM CLR A-A LWR CNTMT SUCT, is CLOSED.
[3] IF CRDM CLR 8-8 is to be used to cool shroud [1-M-9], THEN
[3.1] ENSURE 1-HS-30-92A, CRDM CLR 8-8 MTR 1&2, 1&2, in A-AUTO and 1-HS-30-93A, CRDM CLR 8-8 SHROUD SUCT, in P-AUTO, AND START CRDM CLR with 1-HS-30-92A.
[3.2] ENSURE CRDM CLR 8-8 is RUNNING.
[3.3] ENSURE 1-TCO-30-93, CRDM CLR 8-8 SHROUD SUCT, is OPEN, and 1-TCO .. 30-94, CRDM CLR 8-8 1-TCO-30-94, LWR CNTMT SUCT, is CLOSED.
[4] IF CRDM CLR C-A is to be used to cool shroud [1-M-9], THEN
[4.1] ENSURE 1-HS-30-88A, CRDM CLR C-A MTR 1&2, in A-AUTO and 1-HS-30-89A, CRDM CLR C-A SHROUD SUCT, in P-AUTO, AND START CRDM CLR with 1-HS-30-88A.
[4.2] ENSURE CRDM CLR C-A is RUNNING.
[4.3] ENSURE 1-TCO-30-89, CRDM CLR C-A SHROUD SUCT, is OPEN, and 1-TCO-30-90, CRDM CLR C-A LWR CNTMT SUCT, is CLOSED.
WBN Containment HVAC and Pressure SOI-30.03 501-30.03 Unit 1 Control Rev. 0042 Page 23 of 59 Date_ __ INITIALS 5.6 CRDM Shroud Cooling Alignment and CRDM Cooler Startup (continued)
[S]
[5] IF CRDM Cooler is to be placed in reserve, THEN ENSURE the following: (N/A coolers in service)
[S.1]
[5.1] 1-HS-30-80A, CRDM CLR D-8D.,.B MTR 1&2, 1&2, in A-AUTO, and Cooler NOT running.
IV
[S.2]
[5.2] 1-HS-30-83A, CRDM CLR A-A MTR 1 &2, in A-AUTO, 1&2, and Cooler NOT running.
IV
[S.3]
[5.3] 1-HS-30-92A, CRDM CLR B-B8-8 MTR 1&2, 1&2, in A-AUTO, AND Cooler NOT running.
IV
[S.4]
[5.4] 1-HS-30-88A, CRDM CLR C-A MTR 1&2, in A-AUTO,
. and Cooler NOT running.
IV
/
WATTS BAR NUCLEAR PLANT B.1.f Nov. 2009 NRC Exam B.1.f Reinstate Source Range Detectors Following a Reactor Trip PAr,F 1 OF A q
WATTS BAR NUCLEAR PLANT B.1.f Nov. 2009 NRC Exam EVALUATION SHEET Task: Reinstate source range detectors following a reactor trip.
Alternate Path: Applicant determines that Intermediate Range Channel 135 has failed high and manually reinstates the Source Range detectors.
Facility JPM #: Modified from SON.
Safety Function: 7
Title:
Instrumentation KIA 015 A4.01 A4 Ability to manually operate and/or monitor in the control room:
Selection of controlling NIS channel.
Rating(s): 3.6* //3.6 3.6 CFR: 41.7/45.5 to 45.8 Preferred Evaluation Location: Preferred Evaluation Method:
Simulator x In-Plant Perform X Simulate
References:
ES-0.1 "Reactor Trip Response," Rev. 21.
Task Number:
Title:
Task Standard: Applicant determines that the Source Range detectors DID NOT reenergize as expected and takes the actions of ES-0.1, "Reactor Trip Response" to manually reenergize and align the Source Range per Step 18 RESPONSE NOT OBTAINED.
Validation Time: 10 minutes Time Critical: Yes --
No X
===============================================================
Applicant: Time Start:
NAME SSN Time Finish: _-----:_
Performance Rating: SAT UNSAT Performance Time Examiner: ____________________________
---------------------~/-----
- -----------'/_---
NAME SIGNATURE DATE
===============================================================
COMMENTS PAr,F ? OF!=l PAr,F? OF ~
WATTS BARliUCLEAR BAR l.JUCLEAR PLANT B.1.f Nov. 2009 NRC Exam SIMULATOR OPERATOR INSTRUCTIONS:
- 1. ENSURE NRC Examination Security has been established.
- 2. Right click on 337, and then select RESET.
- 3. Enter the password.
- 4. Select "Yes" on the INITIAL CONDITION RESET pop-up window.
- 5. ENSURE the following information appears on the Director Summary Screen:
1'):,2>> ,Key '"
" " '>,\' " :, \ . Type Event' Delay Inserted ., ;l3alTlP. ' <I' llnJtial, Final., *** \Value
~'\
'\
\i ni04a ir channel failure ir chnl 1 M 00:00:00 00:00:00 00:00:00 200 200
- 6. Place simulator in RUN and acknowledge any alarms.
- 7. Place simulator in FREEZE until Examiner cue is given.
PAGE 3 OF 9
WATTS BAR NUCLEAR PLANT B.1.f Nov. 2009 NRC Exam DIRECTIONS TO APPLICANT DIRECTION TO APPLICANT:
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:
- 1. Unit 1 was inadvertently tripped from 100% power -20 minutes ago.
- 2. ES-0.1 ES-O.1 ,"Reactor Trip Response," was entered and the crew just completed Step 17.
INITIATING CUES:
- 1. The US directs you as the OAC to ensure source range monitors are reinstated per ES-0.1, Step 18.
- 2. Inform the US when the source range monitors have been reinstated and all a" functions of the source range monitors are in service.
PA~F PAr,F 4 OF ~
OF!=l
WATTS BAR NUCLEAR PLANT B.1.f Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT START TIME: _ __
STEP 1: 18. ENSURE nuclear instrumentation operation: SAT
- a. CHECK intermediate range flux less UNSAT than 1.66 x 10-4 %.
STANDARD:
. Applicant determines that Intermediate Range N135 has failed high and is not indicative of current conditions. Applicant determines that N136 is indicating correctly and continues to step 1.b.
EXAMINER CUE:
Upon recognition of the failed intermediate range channel, if/when the applicant states that AOI-4," Nuclear Instrumentation Malfunctions,"
should be implemented, provide the cue "Another operator will perform AOI-4 actions."
COMMENTS:
PAr,F!')
PA~F 1') OF ~
q
WATTS BAR NUCLEAR PLANT B.1.f Nov. 2009 NRC Exam STEP/STANDARD SATIUNSAT SAT/UNSAT STEP 1: b. CHECK source range detectors energized. CRITICAL STEP STANDARD:
SAT Applicant determines that the source range detectors are NOT energized and enters RESPONSE NOT OBTAINED COLUMN for actions.
UNSAT Step is critical since additional actions are required based on the discovery of the failure of the source ranges to re-energize.
COMMENTS:
STEP 5: RESPONSE NOT OBTAINED CRITICAL STEP
- b. Manually ENERGIZE Source Range detectors:
SAT Simultaneously PLACE 1-N33A and 1-N33B to RESET.
STANDARD:
UNSAT Applicant places 1-N33A SR TRIP TR A RESET-BLOCK P-6, and 1-N33B, SR TRIP TR B RESET-BLOCK P-6, to the RESET position SIMULTANEOUSLY.
Step is critical since the circuit requires SIMULTANEOUS operation of 1-N33A and 1N33B to successfully energize the Source Range Detectors.
COMMENTS:
PAr,F R OF A
~
WATTS BAR NUCLEAR PLANT B.1.f
')
Nov. 2009 NRC Exam STEP/STANDARD SAT/U NSAT SAT/UNSAT STEP 6: c. SELECT STARTUP SCREEN on 1-NR-92-145 to display SRMs and IRMs. SAT STANDARD:
Applicant uses the touch screen function on 1-NR-92-145 and UNSAT selects a combination of SRMs and IRMs that DOES NOT include the failed N35 Intermediate Range Channel.
COMMENTS:
STEP 7: d. ENSURE audio count rate operation. CRITICAL STEP STANDARD:
SAT Applicant determines that the audio count rate is functioning properly by audible confirmation.
COMMENTS: UNSAT PAr,F 7 OF ~
OF!=l
WATTS BAR NUCLEAR PLANT B.1J B.1.f Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 8: e. RESET shutdown monitor alarm setpoints [M-13]. CRITICAL STEP Applicant resets the shutdown monitor setpoints by depressing the ALARM SETPOINT RESET pushbutton on 1-M-13. SAT Step is critical to ensure the shutdown monitor alarm circuit is properly initialized after the trip.
trip_
UNSAT STANDARD:
COMMENTS:
STEP 9: f. ENSURE shutdown monitor ALARM LED(s) dark, AND HIGH CRITICAL
) FLUX AT SHUTDOWN bistable lights dark, THEN PLACE STEP HIGH FLUX AT SHUTDOWN alarm block switches in NORMAL [M-13]. SAT STANDARD:
After the applicant resets the shutdown monitor setpoints by UNSAT depressing the ALARM SETPOINT RESET pushbutton on 1-M-13, the shutdown monitor ALARM LED(s) will be DARK. On the Source Range drawers, the HIGH FLUX AT SHUTDOWN bistable lights will be DARK.
Step is critical to ensure the shutdown monitor alarm circuit is properly initialized after the trip.
trip_
Applicant determines that Step 18 has been completed and informs the Unit Supervisor of completion.
COMMENTS:
END OF TASK STOP TIME _ __
PA(';F PAc;F R OF nF ~
j:)
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
DIRECTION TO APPLICANT:
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:
- 1. Unit 1 was inadvertently tripped from 100% power -20 minutes ago.
- 2. ES-0.1, ES-O.1, Reactor Trip Response was entered and the crew just completed Step 17.
INITIATING CUES:
- 1. The US directs you as the OAC to ensure source range monitors are reinstated per ES-0.1, Step 18.
- 2. Inform the US when the source range monitors have been reinstated and all functions of the source range monitors are in service.
1 TENNESSEE VALLEY AUTHORITY WATTS BAR NUCLEAR PLANT EMERGENCY OPERATING INSTRUCTIONS ES-O.1 REACTOR TRIP RESPONSE Revision 21
')
Unit 1 QUALITY RELATED REQUESTED BY: S. Baker SPONSORING ORGANIZATION: OPERATIONS APPROVED BY: A. K. Keefer EFFECTIVE DATE: 12/21/07 LEVEL OF USE: CONTINUOUS
)
')
WBN REACTOR TRIP RESPONSE IES-O.1 ES*O.1 Rev 21 1.0 PURPOSE This Instruction provides the necessary actions to stabilize and control the plant following a reactor trip without a safety injection.
2.0 . SYMPTOMS AND ENTRY CONDITIONS 2.1 Alarms A. Reactor trip annunCiator annunciator lit.
B. Turbine trip annunciator lit greater than 50% Reactor Power.
2.2 Indications c.
C. Reactor trip bistables lit [status panels M-5 or M-6].
D. Rapid drop in neutron flux indication.
E. Rod Position Indicators at bottom of scale.
F. Rapid drop in megawatts to zero with initial power greater than 50%
Reactor Power.
2.3 Transitions E-O, Reactor Trip or Safety Injection.
3.0 OPERATOR ACTIONS
)
2 of 18
')
WBN REACTOR TRIP RESPONSE I ES-O.1 ES-O.1 Rev 21 IStep I IAction/Expected Response I I[Be§ponse Response Not Obtained
~ Plant conditions, AFW pump start signals and flow requirements should be evaluated as time allows.
~
& MONITOR SI actuation criteria:
- IF SI actuation occurs during the performance of this Instruction, THEN
- GO TO E-O, Reactor Trip or Safety Injection.
~
'~
I~ CHECK Generator PCBs OPEN. OPEN manually.
/
3 of 18
WBN REACTOR TRIP RESPONSE I ES-O.1 ES-O.1 Rev 21 IStep IIIIAction/Expected Response I IResponse Not Obtained JI
~ MONITOR RCS temperature stable at or trending to 55rF:
IF temperature is less than 55rF, THEN
~IF any Rep RCP running, ENSURE steam dumps, S/G PORVs, and blowdown isolation valves THEN .
CLOSED.
MONITOR ReS RCS Loop T-avg trending to 55rF. IF cooldown continues, OR THEN:
- IF NO RCP running,
- ENSURE total feed flow is THEN less than or equal to 500 gpm:
MONITOR ReS RCS Loop T-cold a. REFER TO SOI-3.02, trending to 55rF. Auxiliary Feedwater System, for manual control of TDAFWP.
S/G NR MAINTAIN at least one S/GNR level greater than 29%, or total feed flow between 410 and 500 gpm for
) heat sink.
IF cooldown continues after AFW flow is controlled, THEN:
- CLOSE MSIVs.
- ENSURE MSIV bypasses CLOSED.
- PLACE steam dump controls OFF.
IF temperature is less than 54rF after AFW is controlled, THEN INITIATE boration:
- REFER TO AOI-34, Immediate Boration.
Soration.
IF temperature is greater than 564°F, THEN ENSURE either steam dumps, or S/G PORVs OPEN.
WHEN cooldown is controlled,
) THEN
/
RETURN AFW to AUTO as desired.
4 of 18
)
WBN REACTOR TRIP RESPONSE I ES-O.1 ES-O.1 Rev 21 IStep IIIIAction/Expected Response III IResponse Not Obtained
'~
~
I~ ENSURE AFW operation:
~ AFW established: a. ESTABLISH feed flow from AFW or MFW as necessary.
- TO AFW pump RUNNING.
TD
- LCVs in AUTO or controlled in MANUAL.
'& Heat sink available: b. IF heat sink can NOT be established,
- Total feed flow greater than 410 gpm, THEN
- GO TO FR-H.1, OR Loss Of Secondary Heat Sink.
- At least one S/G N NR R level greater than 29%.
~~ CHECK MFW status:
~ CHECK RCS T-avg a. WHEN T-avg T -avg is
~ess than 564°F. less than 564 OF, THEN PERFORM Substep 5b.
- GO TO Step 6.
'& ENSURE MFW isolation: b. Manually CLOSE valves, and STOP pumps, as necessary.
- MFW isolation and bypass isolation valves CLOSED.
IF valves can NOT be closed,
- MFW reg and bypass reg THEN valves CLOSED. CLOSE #1 heater outlet valves.
- MFP A and B TRIPPED.
- Standby MFP STOPPED.
- Cond demin pumps TRIPPED.
- Cond booster pumps TRIPPED.
5 of 18
WBN REACTOR TRIP RESPONSE I ES-O.1 ES-O.1 Rev 21 IStep I IAction/Expected Response II Response Not Obtained ENSURE all control rods fully inserted: IF two or more control rods are NOT fully inserted,
- RPls at bottom scale.
THEN INITIATE boration of 3250 gals of greater than or equal to 6120 ppm boron for each rod not fully inserted:
- REFER TO TO AOI-34, Boration.
Immediate Soration.
ANNOUNCE reactor trip over PA system.
MONITOR S/G levels:
~ N R level At least one S/G NR greater than 29%.
- a. ENSURE feed flow greater than 410 gpm'.
gpm.
~ S/G NR levels b. IF any S/G NR level less than 50% and controlled. continues to rise, THEN ISOLATE feed flow to affected S/G.
CONTROL S/G NR levels between 29% and 50%.
BOP realignment:
INITIATE SOP
- REFER TO AOI-17, Turbine Trip.
6 of 18
WBN . REACTOR TRIP RESPONSE I ES-O.1 ES-O.1 Rev 21 IStep I IAction/Expected Response III IResponse Not Obtained I
~
~ MONITOR pzr pressure:
~
~pzr Pzr pressure a. ENSURE SI actuated.
\X.greater greater than 1870 psig.
- GO TO E-O, Reactor Trip or Safety Injection.
~ Pzr p~ to 2235 essure Pzr pressure
- b. IF pressure is trending 2235 psig.
psig.
greater than 2235 psig AND rising, THEN:
- ENSURE pzr heaters OFF.
- CONTROL RCS press with ONE of the following, in order listed:
- 1) Normal pzr sprays.
- 2) Aux spray with normal letdown in service.
- 3) Pzr PORV(s).
IF pressure is less than 2235 psig AND dropping, THEN:
- 1) ENSURE pzr PORVor PORV or associated block valve CLOSED.
- 3) ENSURE aux spray valve CLOSED.
- 4) TURN pzr heaters ON as necessary.
7 of 18
)
WBN REACTOR TRIP RESPONSE I ES-O.1 ES-O.1 Rev 21 IStep IIIIAction/Expected Response III[Response Response Not Obtained I&.
~ CHECK charging in service. ESTABLISH charging:
- a. ENSURE at least one charging pump RUNNING.
- b. CLOSE seal flow control 1-FCV-62-89.
- c. OPEN charging 1-FCV-62-90 and 1-FCV-62-91.
- d. ENSURE charging valve 1-FCV-62-85 or 1-FCV-62-86 OPEN.
- e. ENSURE seal water return 1-FCV-62-61 and 1-FCV-62-63 OPEN.
- f. ADJUST 1-FCV-62-89 and 1-FCV-62-93 to establish:
- Seal injection flow between 8 and 13 gpm for each RCP.
- Pzr level between 25% and 30%.
- g. WHEN pzr level is greater than 25%,
THEN PLACE 1-FCV-62-93 in AUTO.
8 of 18
WBN REACTOR TRIP RESPONSE I ES-O.1 ES-O.1 Rev 21 IStep I IAction/Expected Response I [Response IResponse Not Obtained 1&
.~ MONITOR pzr level:
~pzr level greater than 17%. a. PERFORM the following:
- 1) ENSURE letdown isolation 1-FCV-62-69 or 1-FCV-62-70 CLOSED.
- 2) ENSURE pzr heaters OFF.
- 3) MAINTAIN charging flow.
- 4) WHEN pzr level is greater than 17%,
THEN OPERATE pzr heaters as necessary to stabilize press.
~pzr level trending to 25%.
,&pzr b. CONTROL charging and letdown to establish pzr level between 25% and 30%.
9 of 18
WBN REACTOR TRIP RESPONSE I ES-O.1 ES-O.1 Rev 21 IStep I IAction/Expected Response III IResponse Not Obtained
~ CHECK letdown in service. WHEN WH EN pzr level is greater than 17%,
THEN ESTABLISH letdown:
- a. ENSURE at least 80 gpm charging flow established.
- b. OPEN letdown isolation valves:
- 1-FCV-62-69.
1-FCV-62-70.
- 1-FCV-62-77.
- c. PLACE letdown pressure controller 1-HIC-62-81, in MANUAL at 40-50% OPEN if using 75 gpm orifice (20-30%
OPEN if using 45 gpm orifice).
- d. OPEN letdown orifice valves as needed.
- e. ADJUST 1-PCV-62-81 for desired letdown pressure, 320 psig at normal letdown temp.
- f. PLACE 1-HIC-62-81 in AUTO.
10 of 18
WBN REACTOR TRIP RESPONSE ES-O.1 ES-O.1 I I. Rev 21 .
IStep I IAction/Expected Response II 1 [Response Response Not Obtained 1&
~ MONITOR cntmt conditions: REFER TO AOI-6, Small Reactor Coolant System Leak.
- Cntmt pressure NORMAL.
- Upper cntmt hi range radiation NORMAL.
- Lower cntmt hi range radiation NORMAL.
Cntmt rad recorders NORMAL.
Cntmt sump level NORMAL.
Cntmt temp ann window DARK
[104-8].
~ CHECK secondary side radiation. REFER TO AOI-33, S/G discharge monitors NORMAL. Steam Generator Tube Leak.
Condenser vacuum exhaust exhaustradrad monitors NORMAL.
- S/G blowdown rad monitors NORMAL.
11 of 18
)
WBN REACTOR TRIP RESPONSE IES-O.1 ES-O.1 Rev 21 IStep IIIIAction/Expected Response III[Re~ponse Response Not Obtained
~ MONITOR electrical board status:
~ CHECK offsite power available. a. RESTORE offsite power USING AOI-35, Loss of Offsite Power.
~ CHECK all shutdown boards ENERGIZED by offsite power.
- b. ENERGIZE shutdown boards USING:
- SOI-211 Shutdown Boards OR
- AOI-43 Loss of Shutdown Boards OR
- SOI-82 Diesel Generators
&. CHECK all unit boards ENERGIZED.
- c. ENERGIZE unit boards USING SOI-201, Unit Boards.
~ PLACE any unloaded D/G in standby USING SOI-82 Diesel Generators.
12 of 18
) I ES~O.1 ES-O.1 WBN REACTOR TRIP RESPONSE Rev 21 IStep I IAction/Expected Response III IResponse Not Obtained
- 18. ENSURE nuclear instrumentation operation:
- a. CHECK intermediate range flux a. WHEN intermediate range flux is 10-4 %.
less than 1.66 x 10-4 10-4 %,
less than 1.66 x 10-4 THEN PERFORM Substeps 18b thru f.
- GO TO Step 19.
- b. CHECK source range detectors b. Manually ENERGIZE Source energized. Range detectors:
Simultaneously PLACE 1-N33A and 1-N33B to RESET.
and1-N33B
- c. SELECT STARTUP SCREEN on
) 1~NR-92-145 1-NR-92-145 to display SRMs and IRMs.
- d. ENSURE audio count rate operation.
- e. RESET shutdown monitor alarm
[M-13].
setpoints [M'-13].
- f. ENSURE shutdown monitor ALARM LED(s) dark, AND HIGH FLUX AT SHUTDOWN bistable lights dark, THEN PLACE HIGH FLUX AT SHUTDOWN alarm block switches
[M-13].
in NORMAL [M-13]-.
)
13 of 18
)
W8N WBN REACTOR TRIP RESPONSE I ES-O.1 ES-O.1 Rev 21 IStep I IAction/Expected Response II Response Not Obtained
- 19. CONTROL S/G pressure:
- a. CHECK condenser available: a. CONTROL pressure with S/G PORVs.
- Permissive C,.9 C-9 LIT [65-E].
- MSIVs OPEN. ** GO TO Step 20.
- b. PLACE steam dump controls OFF:
- 1-HS-1-103A, STEAM DUMP FSV"A".
- 1-HS-1-1038, STEAM DUMP 1-HS-1-103B, FSV"B".
FSV"8".
- c. PLACE steam dump mode switch in STEAM PRESSURE.
- d. ENSURE steam dump demand indicator 1-XI-1-33 reading zero.
- e. PLACE steam dump controls ON:
- 1-HS-1-103A, STEAM DUMP FSV"A".
- 1-HS-1-1038, STEAM DUMP 1-HS-1-103B, FSV"B".
FSV"8".
- f. ADJUST steam dump demand controller to 84% (1092 psig).
)
14 of 18
)
WBN REACTOR TRIP RESPONSE I ES-O.1 ES-O.1 Rev 21 IStep IIIIAction/Expected Response III IResponse Not Obtained NOTE Either Loop 1 or 2 pzr spray valve is effective for Loop 2 RCP in
& 4 RCPs in service.
service or for Loops 1, 3, &
- 20. CHECK RCP(s) RUNNING to provide ESTABLISH normal pzr spray, normal pzr spray. Loop 2 preferred:
REFER TO SOI-68.02, Reactor Coolant Pumps (Loop 2 OR 1, 3, and 4).
Loops 1,3, WHEN RCP start conditions are established, THEN START Loop 2 RCP to provide normal pzr spray.
IF Loop 2 RCP can NOT be started, THEN START ALL other RCPs to establish normal pzr spray.
IF an RCP can NOT be started, THEN MONITOR natural circulation per the Foldout Page.
IF natural circulation is NOT established, THEN DUMP steam at a greater rate.
15 of 18
WBN REACTOR TRIP RESPONSE IES-O.1 ES-O.1 Rev 21 IStep I IAction/Expected Response III IResponse Not Obtained
- 21. INITIATE surveillances and reports:
- REFER TO Appendix A (ES-0.1),
Surveillances and Reports.
- 22. MAINTAIN stable plant conditions:
ReS pressure 2235 psig.
- Pzr level 25%.
.level
- S/G NR N R levels between 29% and 50%.
ReS temperature 55rF:
OR b) IF NO RCPRep running, THEN MONITOR RCS ReS Loop T -cold trending to 55rF.
)
16 of 18
WBN REACTOR TRIP RESPONSE I ES-O.1 ES-O.1 Rev 21 IStep I IAction/Expected Response II Response Not Obtained 1 [Response
- 23. DETERMINE if natural circulation cooldown is required:
- a. CHECK the following:
1)At
- 2) Cooldown to Cold Shutdown 2) ** GO TO GO-5, is desired. Unit Shutdown From 30%
Reactor Power To Hot Standby.
- b. ** GO TO GO-6, Unit Shutdown From Hot Standby To Cold Shutdown, OR GO-5, Unit Shutdown From 30%
Reactor Power To Hot Standby, as appropriate.
- End-17 of 18
WBN REACTOR TRIP RESPONSE I ES-O.1 ES-O.1 Rev 21 APPENDIX A (ES-O.1 )
Page 1 of 1 SURVEILLANCES AND REPORTS
- 1. INITIATE surveillances and reports (as necessary):
- a. NOTIFY IMs to check P-4 contacts USING 1-SI-99-4-A and 1-SI-99-4-8, Test of Reactor Trip P-4 ESFAS Interlock.
- b. IF reactor power dropped by greater than or equal to 15% in one hour, THEN NOTIFY Chemistry to initiate power change sampling requirements.
- c. PERFORM shutdown margin calc USING 1-SI-0-10, Shutdown Margin or REACTINW Computer Program.
- d. INITIATE TI-127, ReactorlTurbine Reactor/Turbine Trip Report, Event Critique, Root Cause Analysis.
- e. NOTIFY NRC of reactor trip USING SPP-3.5, Regulatory Reporting Requirements.
18 of 18
WBN REACTOR TRIP RESPONSE I ES-O.1 ES-O.1 Rev 21 FOLDOUT for ES-O.1 SI ACTUATION CRITERIA ACTUATE SI and ** GO TO E-O, Reactor Trip or Safety Injection IF:
- Cntmt pressure greater than 1.5 psig, OR
- S/G pressure less than 675 psig, 'OR OR
- Pzr level cannot be maintained greater than 15% [33% ADV],
ADV] , OR
- RCS Subcooling less than 65°F.
NATURAL CIRCULATION CRITERIA
- RCS subcooling greater than 65°F.
- S/G pressure controlled or dropping.
- T-hot stable or dropping.
- Incore TICs stable or dropping.
- T-cold at at saturation temp for S/G press.
, AFW OPERATION
WATTS BAR NUCLEAR PLANT B.1*9 Nov. 2009 NRC Exam B.1*9 Transfer 6.9 KV RCP Board 1D from Alternate to Normal.
PAGE 1 OF 14
WATTS BAR NUCLEAR PLANT 8.1*9 B.1*9 Nov. 2009 NRC Exam Task: Transfer 6.9 KV RCP Board 1D from Alternate to Normal.
Alternate Path: Board transfer fails, resulting in the loss of #4 RCP and the need to trip the reactor, per AOI-24.
Facility JPM #: 3-0T-JPMR042.
Safety Function: 6
Title:
Electrical KIA 062 A4.01 Ability to manually operate andlor monitor in the control room: All breakers (including available switchyard).
Rating(s): 3.3/3.1 CFR: 41.4/45.5 to 45.8 Preferred Evaluation Location: Preferred Evaluation Method:
Simulator x In-Plant Perform -
x X-
--C:....:.. _ __
Simulate
References:
SOI-202.4, "6.9KV Reactor Coolant Pump Board 1 D," Rev. 10.
AOI-24, "RCP Malfunctions during Pump Operation," Rev. 29.
Task Number: RO-202-S01-202-002
Title:
Transfer the 6.9 KV Reactor Coolant Board from Alternate to Normal Task Standard: Applicant performs actions in accordance with SOI-202.4 to transfer 1D RCP Board from its ALTERNATE to NORMAL power supply. When the transfer fails to occur, the applicant recognizes the need to trip the reactor since operation in Mode 1 is not allowed with less than 4 RCPs in service.
Validation Time: 5 minutes Time Critical: Yes --
No -
X
~----
===============================================================
Applicant: Time Start:
NAME SSN Time Finish: - - -
Performance Rating: SAT UNSAT Performance Time Examiner: _____________
________________________ _ ________________________.1_ __
~/-----
NAME SIGNATURE DATE
===============================================================
COMMENTS PAGE 2 OF 14
WATTS BARI'JUCLEAR BARf\JUCLEAR PLANT B.1*9 Nov. 2009 NRC Exam SIMULATOR OPERATOR INSTRUCTIONS:
- 1. ENSURE NRC Examination Security has been established.
- 2. Right click on 345, and then select RESET.
- 3. Enter the password.
- 4. Select "Yes" on the INITIAL CONDITION RESET pop-up window.
- 5. ENSURE the following information appears on the Director Summary Screen:
I~t~,v, Key
, li~~,
"? ,
- Type Event Delay Inserted ,"'Ramp' Initial;~ Final": 'Val~6\'.
,,,<\ :: ",,' ,
- ~::~~
hs-68-73aa hs-68-73aa rc pump 4 normal for breaker & oil pump 0 00:00:00 00:00:00 stop
- 6. Place simulator in RUN and acknowledge any alarms.
- 7. Place simulator in FREEZE until Examiner cue is given.
PAGE 3 OF 14
WATTS BAR NUCLEAR PLANT B.1.g B.1*9 Nov. 2009 NRC Exam DIRECTIONS TO APPLICANT DIRECTION TO APPLICANT:
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:
- 1. A unit startup is in progress.
- 2. The 6.9 KV boards are being transferred per GO-3, "Unit Startup from Less than 4% Reactor Power to 30% Reactor Power," Section 5.4, Step
[19.4].
- 3. You are the Operator-at-the Controls.
INITIATING CUES:
- 1. The Unit Supervisor has directed you to transfer 6.9 KV Reactor Coolant Pump Board 10 1D to complete Step [19.4].
- 2. Inform the Unit Supervisor when 6.9 KV Reactor Coolant Pump Board 10 1D has been transferred to NORMAL using 501-202.04 6.9KV, "Reactor Coolant Pump Board 1D."
PAGE 4 OF 14
WATTS BAR NUCLEAR PLANT B.1*9 Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT START TIME: _ __
STEP 1: Obtain a copy of the procedure. - SAT STANDARD: - UNSAT A copy of SOI-202.04 section 8.1 has been obtained.
EXAMINER'S CUE: After the applicant has demonstrated the method of obtaining the correct instruction, the evaluator can provide a copy of the instruction.
COMMENTS:
STEP 2: [1] OBTAIN SRO approval.
- SAT STANDARD:
- UNSAT Applicant observes that SRO approval has already been granted by initials in Step 1 1..
COMMENTS:
PAGE 5 OF 14
WATTS BAR NUCLEAR PLANT B.1*9 Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 3. [2] ENSURE MSB has verified Time Delay Relay (TOR) 1 SAT 068- 0074 contact points 1 and 5 closed (located on left side panel in compartment 103 of RCP BD 1 D). UNSAT STANDARD:
Applicant ensures that the MSB has verified Time Delay Relay (TOR) 1-62-068- 0074 contact points 1 and 5 closed.
CUE: When contacted as MSB, state that Time Delay Relay (TDR) 1-62-068- 0074 contact points 1 and 5 have been verified closed.
COMMENTS:
NOTE IF Unit is out of service, Bd may be energized by backfeeding from USSTs.
PAGE 6 OF 14
WATTS BAR NUCLEAR PLANT B.1.g Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 4: [3] CHECK voltage 6560 to 7260V to Normal ACB 2124 on - SAT 1-EI-57-58, USST 1B \VOLTS [1-M-1].
- UNSAT STANDARD:
Applicant reads voltage 6560 to 7260V to Normal ACB 2124 on 1~EI-57 -58, USST 1B 1.;EI-57-58, 1B VOLTS, on PaneI1M-1.
Panel 1 M-1 .
COMMENTS:
STEP 5: [4] ENSURE 1-HS-68-73AA, RCP 2 NORMAL BKR & LIFT CRITICAL PMP [1-M-5], PUSHED IN to place handswitch in control STEP of ACB 2124.
- SAT STANDARD:
UNSAT Applicant locates and ensures 1-HS-68-73AA, RCP 4 NORMAL BKR & &
LIFT PMP, is pushed in.
Step is critical to properly align the breaker controls on the multi-function handswitch.
COMMENTS~
COMMENTS:
PAGE 7 OF 14
WATTS BAR NUCLEAR PLANT B.1*9 Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT SAT/UN SAT STEP 6: . [5] ENSURE 1-HS-68-73BA, RCP 4 ALTERNATE BKR & CRITICAL XFER SELECTOR [1-M-5], PUSHED IN to place ACB STEP 2624 auto transfer in MANUAL.
SAT STANDARD:
UNSAT Applicant pushes 1-HS-68-73BA, RCP 4 ALTERNATE BKR & XFER SELECTOR in on Panel 1-M-5.
Step is critical to properly align the breaker controls on the multi-function handswitch.
COMMENTS:
PAGE 8 OF 14
WATTS BAR NUCLEAR PLANT B.1.g B.1*9
\1 Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 7: [6] MONITOR 1-EI-68-73A, RCP 4 AMPS [1-M-5] during SAT transfer to ensure Rep RCP Amp load transfers to Normal supply. UNSAT STANDARD:
Applicant locates and monitors 1-EI-68-73A, RCP 4 AMPS on Panel 1-M-5.
COM~MENTS:
COMMENTS:
CAUTION Release handswitches SLOWLY after transfer is complete to prevent inadvertent breaker actuation.
NOTE TO EVALUATOR: Board transfer will not be successful, resulting in the loss of
- 4 RCP. The applicant must enter AOI-24, "RCP Malfunctions During Pump Operation," and trip the reactor since the plant is in Mode 1.
PAGE 9 OF 14
WATTS BAR NUCLEAR PLANT B.1*9 Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 8: Start of Critical Step(s) . SAT
[7] PLACE AND HOLD 1-HS-68-73AA, RCP 4 NORMAL BKR UNSAT
& LIFT PMP, in START, AND PLACE 1-HS-68-73BA, RCP 4 ALTERNATE BKR & XFER SELECTOR, in STOP.
End of Critical Step(s)
STANDARD:
Applicant acknowledges that this is a "two-handed" evolution. Applicant reads step, locates each handswitch, and then places and holds 1-HS-68-73AA, RCP 4 NORMAL BKR in START. While holding 1-HS 73AA in START, the applicant places 1-HS-68-73BA in STOP.
Critical step annotation is part of the actual plant procedure.
COMMENTS:
PAGE 10 OF 14
WATTS BAR NUCLEAR PLANT B.1.g B.1*9
( Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT NOTE TO EVALUATOR: Using PRUDENT OPERATOR ACTIONS, the applicant may immediately trip the reactor, and begin E-O, "Reactor Trip or Safety Injection" Immediate Action Step performance.
NOTE TO EVALUATOR: Alarm 123-8 RCS LOOP $ LO FLOW will occur as a result of the loss of #4 RCP. The applicant may refer to the ARI for direction to AOI-24, or may go directly to AOI-24 to respond to the pump problem.
NOTE TO EVALUATOR: The following actions are taken from AOI-24"RCP Malfunctions During Pump Operation," Section 3.2, "RCP tripped or shutdown required."
NOTE 1 Malfunctions addressed by this procedure require RCP shutdown as soon as possible.
NOTE 2 Exceeding any of the limits listed on Attachment 2 of this procedure will require immediate shutdown of the affected RCP.
( NOTE 3 Malfunctions resulting in high #1 seal leakoff will require closing #1 seal return FCV following RCP coastdown.
STEP 9: 1. CHECK RCP tripped. - SAT STANDARD: - UNSAT Applicant has determined that #4 RCP was lost.
COMMENTS:
(
PAGE 11 OF 14
WATTS BAR NUCLEAR PLANT B.1*9 Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 10: 2. CHECK unit in Mode 1 or 2. SAT STANDARD: UNSAT Applicant determines that the unit is in Mode 1.
COMMENTS:
(
PAGE 12 OF 14
WATTS BAR NUCLEAR PLANT B.1.g
( Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT NOTE Control room staff should brief on Steps 3 through 6 prior to tripping the reactor. This ensures that the affected RCP is stopped and that appropriate actions are taken when unit is removed from service.
STEP 11: 3. TRIP the reactor, and GO TO E-O, Reactor Trip or Safety CRITICAL Injection, WHILE continuing with this instruction. STEP SAT STANDARD:
UNSAT Applicant trips the reactor. Applicant begins to perform Immediate Operator Actions of E-O,"Reactor Trip or Safety Injection."
Step is critical since the operation with one RCP out of service while in Mode 1 is not allowed by plant design.
CUE: After the applicant has tripped the reactor, state "Another crew will perform the actions of E-O."
(
COMMENTS:
STOP TIME _ __
PAGE 13 OF 14
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
( DIRECTION TO APPLICANT:
I will explain the initial conditions, and state the task to be performed. All.
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:
- 1. A unit startup is in progress.
- 2. The 6.9 KV boards are being transferred per GO-3, "Unit Startup from Less than 4% Reactor Power to 30% Reactor Power," Section 5.4, Step
[19.4].
- 3. You are the Operator-at-the Controls.
INITIATING CUES:
(,\ 1. The Unit Supervisor has directed you to transfer 6.9 KV Reactor Coolant Pump Board 1D to complete Step [19.4].
- 2. Inform the Unit Supervisor when 6.9 KV Reactor Coolant Pump Board 1D has been transferred to NORMAL using SOI-202.04 501-202.04 6.9KV, "Reactor Coolant Pump Board 1D."
Watts Bar Nuclear Plant Unit 1 System Operating Instruction 501-202.04 6.9KV Reactor Coolant Pump
. Board 10 Revision 0010 Quality Related Level of Use: Continuous Use Effective Date: 11-19-2007 Responsible Organization: OPS, Operations Prepared By: R. D. Dobbs Approved By: Kathy Keefer
WBN 6.9KV Reactor Coolant Pump 501-202.04 Unit 1 Board 1D Rev. 0010 Page 2 of 19 Revision Log Revision Affected or Change Effective Page Number Date Numbers Description of Revision/Change Rev 4 12/02/94 All Revise to latest format; change checklist position to Racked Open instead of racked up.
Rev 5 09/19/95 All Update to latest format. Writers Guide review.
Correct GOIIGO instruction references. Revise Sect 8.1 && 8.2 to change 2 steps in the Bd transfer, to 1 step, since it happens at the same time. Change Sect 8.1 & & 8.2 Step that ensured RCP Bd was energized after the actual transfer step, to a monitoring step just before actual transfer step. Remove position requirements from RCP breakers in Checklist 1 since pump may be off or on. Corrected Steps referenced in Sect 5.0 Steps [19] & & [20] NOTE. Other minor corrections && Clarifications.
CN-1 09/16/95 2,15 Correct compt # on Checklist 1.
6 7/27100 7/27/00 2,4,5 Non-intent. Delete reference to PAI-1 0.1 0, which has been canceled. Incorporate CN-1.
7 5/10104 5/10/04 2,7,8, Non-intent. Incorporated critical steps.
11-13,15 11-13, 15 Incorporated additional CV requirement from PER 03-012913-000. Changed required bus voltage ranges to match 1-15E500 print design output.
8 03/23/05 2.9 Deleted reference to load shed contingency in accordance with DCN 51321. Procedure change evaluation (50.59) provided.
9 8/23/07 All This procedure has been converted from Word 95 to Word 2002(XP) using Rev.8 by Lorie Dake 10 11/19/07 2,5, 11 Provided check of TDRTOR 62 contact closure on normal feeder to ensure transfer.
12 Rearranged transfer steps to prevent signoff during transfer operation.
WBN 6.9KV Reactor Coolant Pump SOl-202.04 SOI-202.04 Unit 1 Board 1D Rev. 0010 Page 3 of 19 Table of Contents
1.0 INTRODUCTION
.......................................................................................................... 4 1.1 Purpose ........................................................................................................................ 4 1.2 ............................................................................................................................. 4 Scope ............................................................................................................................
2.0 REFERENCES
............................................................................................................. 4 2.1 Performance References .............................................................................................. 4 2.2 Developmental References References ........................................................................................... 4 3.0 PRECAUTIONS AND LIMITATIONS ........................................................................... 5 4.0 PREREQUISITE ACTIONS .......................................................................................... 6 4.1 Preliminary Actions ....................................................................................................... 6 4.2 Field Preparations ......................................................................................................... 6 4.3 Approvals and Notifications .......................................................................................... 6 5.0 STARTUP ..................................................................................................................... 7 6.0 NORMAL OPERATION ................................................................................................ 9 7.0 SHUTDOWN ............................................................................................................... 10 8.0 INFREQUENT OPERATIONS .................................................................................... 11 8.1 Transfer RCP Bd 1D 1'D from Alternate to Normal ........................................................... 11 8.2 Transfer RCP Bd 1D from Normal to Alternate ........................................................... 13 8.3 Transfer RCP Bd 1D Control Power from Normal to Alternate ................................... 15 8.4 Transfer RCP Bd 1D Control Power from Alternate to Normal. .................................. 16 9.0 RECORDS .................................................................................................................. 17 9.1 QA Records ................................................................................................................ 17 9.2 Non-QA Records ........................................................................................................ 17 1:
Checklist 1: RCP Bd 1D AlignmenlVerification 1 D Power Alignment Verification .............................................. 18 Source Notes ............................................................................................. 19
WBN 6.9KV Reactor Coolant Pump 501-202.04 Unit 1 Board 1D Rev. 0010 Page 4 of 19
1.0 INTRODUCTION
1.1 Purpose To provide Instructions for Operation of 6.9kV Reactor Coolant Pump (RCP)
Board 10.
1D.
1.2 Scope This Instruction includes the following operations:
A. Alignment for Normal Operation.
B. Transferring the Board from Normal To Alternate Supply.
C. Transferring the Board from Alternate To Normal Supply.
2.0 REFERENCES
2.1 Performance References A. GO-3, Unit Startup from Less Than 4% Reactor Power to 30% Reactor Power.
B. GO-5, Unit Shutdown from 30% Reactor Power to Hot Standby.
2.2 Developmental References A. FSAR 8.2.
B. GOI-7, GOI-?, Generic Equipment Operating Guidelines C. SOI-68.02, Reactor Coolant Pumps D. Tech Specs E. TVA Drawings:
- 1. 1-15E500-1 1.1-15E500-1
- 2. 1-45W705
- 3. 1-45W720
- 4. 1-45W760-68 Series
WBN 6.9KV Reactor Coolant Pump 501-202.04 Unit 1 Board 1D Rev. 0010 Page 5 of 19 3.0 PRECAUTIONS AND LIMITATIONS A. Protective Relaying must remain IN SERVICE, and Trip Fuses must be IN PLACE before energizing a feeder or bus.
B. All Breakers on a board should be OPEN, and Protective Grounds REMOVED before energizing the board.
C. When removing/installing 7200V line-side or bus PT fuses, Electrically-Rated Protective Gloves shall be used.
D. 6.9kV RCP BOARD Supply Breakers must be OPEN BEFORE closing Auxiliary Overcurrent Breaker.
E. Each ACB's closing spring must be verified charged after racking or operating the ACB. 1 F. This Instruction covers only aligning RCP Board for standby readiness, and to transferring board supplies. RCP is started and shutdown in SOI-68.02.
G. Electrical Maintenance must verify Time Delay Relay (TOR) 1-62-068-0074 contact points 1 and 5 for the Normal Feeder Breaker to be closed prior to RCP
( transfer from Alternate to Normal Feeder Breaker during plant startup to ensure proper pump transfer.
WBN 6.9KV Reactor Coolant Pump SOI-202.04 Unit 1 Board 10 1D Rev. 0010 Page 6 of 19 Date _ _ __ Initials 4.0 PREREQUISITE ACTIONS NOTES
- 1) Throughout Instruction where IFITHEN exists, the step is N/A if stated condition does not exist.
- 2) Signoffs/information in unused Sections may be left blank.
4.1 Preliminary Actions
[1] INDICATE Section to be performed, and reason for use:
5.0 Startup 7.0 Shutdown N/A Normal Infrequent 6.0 Operation N/A 8.0 Operations Section/ Reason/ Remarks:
4.2 Field Preparations
[1] REVIEW plant procedures, processes, and programs in progress to ensure adequate configuration of components necessary for system operation.
[2] REVIEW Section 3.0 Precautions and Limitations.
4.3 Approvals and Notifications
[1] COORDINATE system operations/manipulations with UO.
WBN 6.9KV Reactor Coolant Pump SOI-202.04
(, Unit 1 Board 1D Rev. 0010 Page 7 of 19 Date Initials 5.0 STARTUP
[1 ]
[1] OBTAIN SRO approval.
[2] CHECK voltage 6S606560 to 7260V to Normal ACB 2124 on 1-EI-57-58, 1-EI-S7-S8, USST 1 1BB VOLTS VOL TS [1-M-1]
(N/A if conditions warrant).
[3] CHECK voltage 6S606560 to 7260V to Alt ACB 2624 on 1-EI-57-113, 1-EI-S7-113, START BUS B VOLTAGE [1-M-5]. [1-M-S].
[4] ENSURE ACB 2124, 1-HS-68-73AA, RCP 4 NORMAL BKR &
LIFT PUMP [1-M-5],
[1-M-S], is OPEN.
[5]
[S] ENSURE ACB 2624, 1-HS-68-73BA, RCP 4 ALTERNATE BKR&
XFER SELECTOR [1-M-5],
[1-M-S], is OPEN.
[6] ENSURE RCP 4 AUX OC BKR Green light [1-M-5], [1-M-S], is LIT.
[7] ENSURE the following:
PERF NOMENCLATURE LOCATION POSITION UNID INITIAL NORM 250V DC FDR FOR 250Vdc Turb Bldg Dist ON O-BKR-239-2A222 6.9KV RCP BD 1D Bd 2 CV ALT 250V DC FDR FOR 250Vdc Turb Bldg Dist ON O-BKR-239-1 A222 6.9KV RCP Rep BD 1D Bd 1 CV 250V DC SUPPLY TO RCP 1B, 250Vdc Turb Bldg Dist ON O-BKR-239-1A216 1 D, 2B, 2D OC PROT BKR Bd 1 CV
[8] 1-BO-202-0 1:
ENSURE the following at RCP Bd 10, 1-BD-202-D PERF NOMENCLATURE NQMENCLA TURE LOCATION POSITION UNID INITIAL NORM SUPPLY FROM C/1D2 Racked UP 1':BKR-202-2124/1 D 1-BKR-202-2124/1 USST 1B USST1B &OPEN CV AL T SUPPLY FROM RCP START ALT C/1D4 Racked UP 1-BKR-202-2624/1 D BUS B BUSB &OPEN
& OPEN CV
[9] PLACE 250V 2S0V DC SUPPLY TRANSFER SWITCH [C/103], [C/1D3], in 2S0V DC CONTROL BUS NORMAL FEEDER FROM 250V 250V 2S0V DC TURB BLDG DIST OIST BD BO 2.
CV
[10] ENSURE RCP 4 OC PROT BKR 250V 2S0V DC CNTL BUS INDICATING LIGHT (Red) [C/1D3],[C/103], is LIT.
WBN 6.9KV Reactor Coolant Pump 6.9KVReactor SOI-202.04 Unit 1 Board 10 Rev. 0010 Page PaJle 8 of 19 Oate_ __ Initials 5.0 STARTUP (continued)
[11] CHECK RCP BD 1 10 D NOR & AL T FORFDR BKR 250V DC CNTL BUS INDICATING LIGHT (Red) [C/1D3], is LIT.
[12] ENSURE RCP 4 Bd 1 10D Overcurrent and Differential Relays
[C/1D3], IINSTALLED NSTALLED and NO flags visible.
[13] ENSURE REACTOR COOLANT PUMP 4 Aux Overcurrent Relays [C/1D3], INSTALLED and NO flags visible.
[14] ENSURE REACTOR COOLANT PUMP 4 Overcurrent Relays
[C/1 01], INSTALLED and NO flags visible.
[C/1D1],
[15] ENSURE RCP BD 1D 10 LOCKING-OUT RELAY 86-10 86-1D [C/1D3],
RESET.
[16] ENSURE REACTOR COOLANT PUMP 4 LOCKING-OUT 86102 [C/1D3], is RESET.
RELAY 861D2
[17] ENSURE BREAKER 2124 TRANSFER SWITCH, 02], in NORMAL.
1-XS-68-73A, RCP 4 [C/1 D2],
[18] ENSURE BREAKER 2624 TRANSFER SWITCH,
[C/1D4],
1-XS-68-73B, RCP 4 [C/1 D4], in NORMAL.
NOTE Steps 5.0[19] and 5.0[20]are N/A if RCP NOT required to be operable.
[19] CLOSE 1-BKR-68-73 AUX OVERCURRENT PROT RCP 4 (1-PMP-68-73), using BREAKER 52-1D 52-10 CONTROL SWITCH
[C/1D3].
[C/1 D3].
CV
[20] CHECK AUX OC BKR for RCP 4 Red light [1-M-5], is LIT.
NOTE RCP Bd 101D is now available for service. Bd will be energized when RCP is started in SOI-68.02.
WBN 6.9KV Reactor Coolant Pump 501-202.04 Unit 1 Board 1D Rev. 0010 Page 9 of 19 6.0 NORMAL OPERATION Alternate Supply to 6.9kV Reactor Coolant Pump (RCP) Bd 10 is from RCP Start Bus B, with normal Supply from Unit Station Service Transformer (USST) 1B.
Each 6.9kV RCP Bd can be selected for auto or manual transfer between normal and alternate supply breakers. Manual transfers are "fast" (6 cycles or less), and can be made from normal to alternate or alternate to normal. Auto transfers can only be,made from normal to alternate supply. Transfers initiated by generator PCB (52Z) trip signal on the RCP Bds are fast. Control power is from 250Vdc Turbine Bldg Dist system.
The RCP Bd is protected by overcurrent, ground overcurrent, and differential current protective relays. Manual control of the two supply breakers of each board is provided in the MCR. Instrumentation gives operator the voltage of each board and the amps on either supply breaker. The following alarms are provided:
RCP BD 10 UV/CNTL PWR FAILUREITRANSFER [98E].
RCP BOARD UNDERFREQ/UNDERVOLTAGE [122E].
GO-1 initially energizes RCP Bds from the alternate supply using SOI-68.02 (starts RCP). When directed by GO-3 during startup or GO-5 during shutdown, the RCP Bd will be transferred using this Instruction.
WBN 6.9KV Reactor Coolant Pump 501-202.04 SOI-202.04 Unit 1 Board 1D Rev. 0010 Page 10 of 19 7.0 SHUTDOWN RCPs are SHUT DOWN and 6.9kV RCP Bds are deenergized in SOI-68.02.
(
WBN 6.9KV Reactor Coolant Pump SOI-202.04 Unit 1 Board 1D Rev. 0010 Page 11 of 19 Date~ Initials 8.0 INFREQUENT OPERATIONS 8.1 Transfer RCP Bd 1D from Alternate to Normal
[1] OBTAIN SRO approval.
[2] ENSURE MSB has verified Time Delay Relay (TOR)(TDR) 1-62-068-points 1and 5 closed (located on left side panel 0074 contact pOints in compartment 103 1D3 of RCP SO BD 1D).
NOTE IF Unit is out of service, Bd may be energized by backfeeding from USSTs.
[3] CHECK voltage 6560 to 7260V to Normal ACB 2124 on 1-EI-57-58, USST 1B1B \VOLTS [1-M-1].
( [4] ENSURE 1-HS-68-73AA, RCP 4 NORMAL BKR & LIFT PMP
[1-M-5], PUSHED IN to place handswitch in control of ACB 2124.
[5] ENSURE 1-HS-68-73BA, RCP 4 ALTERNATE BKR & XFER SELECTOR [1-M-5], PUSHED IN to place ACB 2624 auto transfer in MANUAL.
[6] MONITOR 1-EI-68-73A, RCP 4 AMPS [1-M-5] during transfer
'" to ensure RCP Amp load transfers to Normal supply.
WBN 6.9KV Reactor Coolant Pump 501-202.04 SOI-202.04
( Unit 1 Board 1D Rev. 0010 Page 12 of 19 Date_ __ Initials 8.1 Transfer RCP Bd 1 1D D from Alternate to Normal (continued)
CAUTION Release handswitches SLOWLY after transfer is complete to prevent inadvertent breaker actuation.
IStart of Critical Step(s)
[7] PLACE AND HOLD 1-HS-68-73AA, RCP 4 NORMAL BKR &
LIFT PMP, in START, AND PLACE 1-HS-68-73BA, RCP 4 ALTERNATE BKR & XFER SELECTOR, in STOP.
CV
(
I End of Critical Step(s)
[8] ENSURE Normal ACB 2124 CLOSED, and Alt ACB 2624 OPEN.
[9] IF desired to place Board Transfer in AUTO, THEN PULL 1-HS-68-73BA, RCP 4 ALTERNATE BKR & XFER SELECTOR, out to PULL AUTO.
(
WBN 6.9KV Reactor Coolant Pump 501-202.04
( Unit 1 Board 10 1D Rev. 0010 Page 13 of 19 Oate_ __
Date Initials 8.2 Transfer RCP Bd 10 1 D from Normal to Alternate
[1] OBTAIN SRO approval.
[2] CHECK voltage 6560 to 7260V to Alt ACB 2624 on 1-EI-57-113, START BUS B VOLTAGE [1-M-5].
[3] ENSURE 1-HS-68-73AA, RCP 4 NORMALBKR NORMAL BKR & LIFT PMP
[1-M-5], PUSHED IN to place handswitch in control of ACB 2124.
[4] ENSURE 1-HS-68-73BA, RCP 4 ALTERNATE BKR & XFER SELECTOR [1-M-5], PUSHED IN to place ACB 2624 auto transfer in MAN MANUAL.
UAL.
[5] MONITOR 1-EI-68-73A, RCP 4 AMPS [1-M-5] during transfer to ensure RCP Amp load transfers to Alt supply.
(
(
WBN 6.9KV Reactor Coolant Pump SOI-202.04
( Unit 1 Board 1D Rev. 0010 Page 14 of 19 Date_ __ Initials 8.2 Transfer RCP Bd 1D from Normal to Alternate (continued)
CAUTION Release handswitches SLOWLY after transfer is complete to prevent inadvertent breaker actuation IStart of Critical Step(s)
[6] PLACE AND HOLD 1-HS-68-73BA, RCP 4 ALTERNATE BKR
& XFER SELECTOR, in START, AND PLACE 1-HS-68-73AA, RCP 4 NORMAL BKR & LIFT PUMP, in STOP.
CV
(
i End of Critical Step(s)
[7] ENSURE AltACB Alt ACB 2624 CLOSED, and Normal ACB 2124 OPEN.
WBN 6.9KV Reactor Coolant Pump 501-202.04
( Unit 1 Board 101D Rev. 0010 Page 15 of 19 Date- Initials 8.3 Transfer RCP Bd 10 1 D Control Power from Normal to Alternate NOTE Transfer of Control Power may result in loss of loads
[1] OBTAIN SRO approval.
[2] ENSURE O-BKR-239-1A222, ALT 250V DC FDR FOR FOR 6.9KV 10 [250Vdc TB Dist Bd 1], is ON.
RCP BD 1D CV
., [3] PLACE 250V DC SUPPLY TRANSFER SWITCH [C/1D3],[C/1 D3], in 250V DC CONTROL BUS ALTERNATE FEEDER FROM 250V DC TURB BLDG DIST BD 1.
(
CV
WBN 6.9KV Reactor Coolant Pump 501-202.04
( Unit 1 Board 1D Rev. 0010 Page 16 of 19 Date_ __ Initials 8.4 Transfer RCP Bd 1D Control Power from Alternate to Normal.
NOTE Transfer of Control Power may result in loss of loads.
[1] OBTAIN SRO approval.
[2] ENSURE O-BKR-239-2A222, NORM 250V DC FDR FOR FOR 6.9KV RCP BD 101D [250Vdc TB Dist Bd 2], is ON.
CV
[3] PLACE 250V DC SUPPLY TRANSFER SWITCH [C/1D3], [C/1 D3], in 250V DC CONTROL BUS NORMAL FEEDER FROM 250V DC TURB BLDG DIST BD 2.
CV
(
WBN 6.9KV Reactor Coolant Pump 501-202.04
( Unit 1 Board 10 1D Rev. 0010 Page 17 of 19 9.0 RECORDS 9.1 QA Records The following documents are QA records and are handled per the Document Control and Records Management (DCRM) program:
- 1. Section 4.0
- 2. Section 5.0
- 3. Section 8.0
- 4. Checklist 1 9.2 Non-QA Records None
(
WBN 6.9KV Reactor Coolant Pump 501-202.04 Unit 1 Board 1D Rev. 0010 Page 18 of 19 Checklist 1 (Page 1 of 1)
RCP Bd 1D Power Alignment Verification DATE COMPLETE PERF NOMENCLATURE NOMENCLA TURE LOCATION LOCA TION POSITION UNID INITIAL 6.9kV RCP Bd 1D, 1-BD-202-D NORM SUPPLY SUPPLY FROM C/1D2 Racked UP 1-BKR-202-2124/1D 1-BKR-202-2124/1 D USST1B CV AL T SUPPL SUPPLYY FROM RCP C/1D4 Racked UP 1-BKR-202-2624/1D 1-BKR-202-2624/1 D START BUS B STARTBUSB CV
(
WBN 6.9KV Reactor Coolant Pump SOI-202.04 Unit 1 Board 1D Rev. 0010 Page 19 of 19 Source Notes (Page 1 of 1)
Implementing Requirements Statement Source Document Statement Ensure closing spring charged on SOER 82-16, Rec 2 1 6.9kV and 480v breakers when breakers are initially made operable.
(
Watts Bar Nuclear Plant Unit 1 Abnormal Operating Instruction AOI-24 RCP MALFUNCTIONS DURING PUMP OPERATION Revision 0029 Quality Related Level of Use: Continuous Use
(
Effective Date: 03-11-2009 Responsible Organization: OPS, Operations Prepared By: Patrick Salkeld Approved By: Patrick Salkeld
WBN RCP MALFUNCTIONS DURING PUMP AOI-24 Unit 1 OPERATION Rev. 0029 Revision Log Revision or Affected Change . Page Number Effective Date Numbers Description of Revision/Change 21 8/8/01 2,7,9,10, Non-intent. Changes to accommodate comments 12,14,15, from Ops Training for consistency with AOI-5.
18,20 22 2/4/02 2, 5-11 Intent. Reinstated Rev.15/CN-4. Ref.: TACF 1-02-1-62.
.1-02-1-62.
23 3/2/2002 2, 5-11 Non-intent. Restore on removal ofTACF 1-02-1-62.
24 4/24/03 2, 5-11 2,5-11 Intent. Implemented TACF TACF 1-03-6-062 RO - Added guidance for excessive RCP leakoff flow on #4 RCP.
25 08/29/03 2, 12, 14 Intent. Added steps to isolate nitrogen to the freeze seal devices installed per TACF #1-03-015-062 on RCP's #2 and #4.
26 08/30103 2, 10 Intent. Implemented TACF 1-03-8-062 R2 and
( TACF 1-03-6-062 R3. Added guidance RCP leakoff flow on #2 and #4 RCP.
27 9/27/03 .2,3,5,6, 2,3,5,6, Non-intent. Reflects return to normal configuration 10,12,14 10,12, 14 forTACF for TACF 1-03-015-062, TACF 1-03-8-062 and TACF 1-03-6-062.
28 12/17/07 All Revised for PER 128002 to require unit shutdown to Mode 3 on loss of any RCP at power. Incorporated actions of AOI-5 into AOI-24 and canceled AOI-5.
Created new section 3.2 to respond to removal of one RCP. Renumbered remaining sections.
29 03/11/2009 ALL addr~ss Converted to Windows XP and revised to address INPO SEN 274, Multiple RCP Seal Failures during Cooldown. (PER Action 135915-004)
Page 2 of 27
WBN RCP MALFUNCTIONS DURING PUMP AOI-24 Unit 1 OPERATION Rev. 0029 1.0 PURPOSE A. Provide instructions for the removal of a RCP due to a condition which requires stopping the RCP as soon as possible after trouble trouble develops.
B. Provides response to RCP seal abnormalities to lower the potential for seal degradation and higher leakage.
2.0 SYMPTOMS 2.1 Alarms A. RCP 1 STANDPIPE LEVEL HilLa HIILO [95-C].
B. RCP VIBRATION MaN MON DETECTED [96-F].
C. RCP 2 STANDPIPE LEVEL HilLa HIILO [96-C].
D. RCP 3 STANDPIPE LEVEL HilLa HIILO [97-C].
E. RCP 4 STANDPIPE LEVEL HilLa HIILO [98-C].
( F. Rep LWR BEARING TEMP HI [99-C].
RCP G. RCP SEAL ~P La LO [99-D].
[99-0].
H. Rep SEAL BYPASS FLOW La RCP LO [99-E].
I. Rep STATOR/MTR RCP STATORIMTR THRUST BRG TEMP HI [100-A].
J. Rep #1 SEAL OUTLET TEMP HI [100-C].
RCP K. Rep SEAL LEAK OFF FLOW HI [100-0].
RCP [100-D].
L. RCP SEAL LEAK OFF FLOW La LO [100-E].
M. RCP SEAL SUPPLY SUPPLY FLOW La LO [101-E].
2.2 Indications A. Rising lower RCP bearing temp.
B. Rising RCP #1 seal outlet temp.
C. Rise or drop in RCP SEAL LEAK OFF - Hi Range recorders.
D. Rise or drop in RCP SEAL LEAK OFF - Lo Range recorders.
Page 3 of 27
WBN RCP MALFUNCTIONS DURING PUMP AOI-24 Unit 1 OPERATION Rev. 0029 2.2 Indications (continued)
E. High Volume Control Tank (VCT) outlet temp greater than 130°F.
F. Abnormally high or low VCT pressure.
G. Low RCP seal supply flow less than 6 gpm per RCP.
LowRCP H. High Rx Coolant Drain Tank (RCDT) pressure greater than 5 psig.
I. Rising RCP shaft vibration (15 mils alarm, 20 mils shutdown).
J. Notification of excessive frame vibration.
K. Rising motor amps.
L. Rising motor windings temp.
M. Rising motor upper bearing cooling water temp.
N. Rising motor bearing temp.
O. Rising pump bearing temp.
P. Rising upper or lower bearing temp due to loss of CCS flow to oil coolers.
Q. Rising CCS temp to thermal barrier 2.3 Automatic Action:
A. RCP may trip from motor faults.
Page 4 of 27
WBN RCP MALFUNCTIONS DURING PUMP AOI-24 Unit 1 OPERATION Rev. 0029 3.0 OPERATOR ACTION:
3.1 Diagnostics IF GO TO Subsection Rep tripped or shutdown required 3.2
- 1 sealleakoff flow HIGH, 3.3
- 1 sealleakoff seal leakoff flow LOW, 3.4 AND Standpipe level alarm DARK,
- 2 Seal Leakoff Flow HIGH 3.5
(#1 seal leakoff flow LOW, AND Standpipe level alarm LIT),
- 3 sealleakoff flow HIGH 3.6
(#1 seal leakoff flow NORMAL AND Standpipe level alarm LIT),
Page 5 of 27
WBN RCP MALFUNCTIONS DURING PUMP AOI-24 Unit 1 OPERATION Rev. 0029 I Step II Action/Expected Response II Response Not Obtained 3.2 RCP Tripped Or Shutdown Required NOTE 1 Malfunctions addressed by this procedure require RCP shutdown as soon as possible.
NOTE 2 Exceeding any of the limits listed on Attachment 2 of this procedure will require immediate shutdown of the affected RCP.
NOTE 3 Malfunctions resulting in high #1 sealleakoff will require closing #1 seal return FCV following RCP coastdown
- REFER TO ATTACHMENT 2, RCP Immediate Shutdown Criteria.
1)
- 1) IF RCP immediate shutdown required, THEN
- GO TO Step 2.
- 2) IF RCP immediate shutdown NOT required, THEN
- GO TO Step 9
- 2. CHECK unit in Mode 1 or 2 ** GO TO Step 4.
NOTE Control room staff should brief on Steps 3 through 6 prior to tripping the reactor. This ensures that the affected RCP is stopped and that appropriate actions are taken when unit is removed from service.
Page 6 of 27
WBN RCP MALFUNCTIONS DURING PUMP AOI-24 Unit 1 OPERATION Rev. 0029 IStep II Action/Expected Response II Response Not Obtained
- 3. TRIP the reactor, and GO TO E-O, Reactor Trip or Safety Injection, WHILE continuing with this instruction.
- 4. STOP and LOCK OUT affected RCP(s).
- 5. IF in Mode 3, **GO TO ES-O.2, Natural Circulation THEN Cooldown, WHILE continuing with this CHECK any RCP Running instruction CAUTION If the RCP seal return flow control valve (FCV)
(FeV) is NOT closed
( within 5 minutes of stopping the RCP with excessive leakoff, seal damage may occur.
- 6. MONITOR RCP seal leakoff less than WHEN the RCP hashas coasted down 6 gpm per pump: (between 3 and 5 minutes),
THEN
- 1-FR-62-24 [RCP 1 & & 2]
- 1-FR-62-50 [RCP 3 & 4] CLOSE affected RCP seal return FCV:
- 1-FCV-62-9 [RCP 1]
- 1-FCV-62-22 [RCP 2]
- 1-FCV-62-35 [RCP 3]
- 1-FCV-62-48 [RCP 4]
- 7. CHECK RCPs 1 and 2 running running... CLOSE affected loop's pressurizer spray valve.
- 8. GO TO Step 15.
Page 7 of 27
WBN RCP MALFUNCTIONS DURING PUMP AOI-24 Unit 1 OPERATION Rev. 0029 I Step II Action/Expected Response II Response Not Obtained
- 9. CONSULT plant staff as necessary for recommendations for continued RCP operation.
NOTE Control room staff should brief on Steps 9 through 13 prior to reducing load. This ensures that the affected RCP is stopped and that appropriate actions are taken when unit is removed from service.
- 10. IF removal of RCP(s) is required, RETURN TO instruction in effect.
THEN REFER TO appropriate instruction to initiate a controlled shutdown to Mode 3 while continuing with this
( instruction:
- AOI-39, Rapid Load Reduction
- GO-4, Normal Power Operation.
- GO-5, Unit Shutdown From 30%
Reactor Power to Hot Standby
- 11. MAINTAIN affected SG level on PROGRAM:
- LOWER M MFWFW flow as steam flow drops.
- ISOLATE blowdown from affected SG.
- 12. WHEN unit is in Mode 3, THEN
- a. STOP and LOCK OUT affected RCP(s).
Page 8 of 27 Page
WBN RCP MALFUNCTIONS DURING PUMP AOI-24
, Unit 1 OPERATION Rev. 0029
\.
I Step II Action/Expected Response.
Response II Response Not Obtained
- b. CHECK any RCP Running b. **GO TO ES-O.2, Natural Circulation Cooldown, WHILE continuing with this instruction.
CAUTION If the RCP seal return flow control valve (FCV) is NOT closed within 5 minutes of stopping the RCP with excessive leakoff, seal damage may occur.
- 13. MONITOR RCP seal leakoff less than WHEN the RCP has coasted down 6 gpm per pump: (between 3 and 5 minutes),
THEN
- 1-FR-62-24 [RCP 1 & 2]
CLOSE affected RCP seal return FCV:
- 1-FR-62-50 [RCP 3 & 4]
- 1-FCV-62-9 [RCP 1]
(
- 1-FCV-62-22 [RCP 2]
- 1-FCV-62-35 [RCP 3]
- . 1-FCV-62-48 [RCP 4]
- 14. CHECK RCPs 1 and 2 running. CLOSE affected loop's pressurizer spray valve.
Page 9 of 27
WBN RCP MALFUNCTIONS DURING PUMP AOI-24 Unit 1 OPERATION Rev. 0029 I Step II Action/Expected Response I *11 II II Response Not Obtained
- 15. REFER TO Tech Spec:
- LCO 3.4.2, ReSRCS Minimum Temp For Criticality.
- LCO 3.4.4, ReSRCS Loops Modes 1 and 2.
- LCO 3.4.5, ReSRCS Loops Mode 3.
- . LCO 3.4.15, Leakage Detection Instrumentation.
- 16. INITIATE repairs as required.
(
- 17. OBTAIN plant management approval prior to restarting any RCP.
- 18. RETURN TO Instruction in effect.
End of Section
(
Page 10 of 27
WATTS BAR NUCLEAR PLANT B.1.h Nov. 2009 NRC Exam
(
B.1.h Alternate Component Cooling Water Pumps 1~
PAGE 1 OF 19
WATTS BAR NUCLEAR PLANT B.1.h Nov. 2009 NRC Exam
(
EVALUATION SHEET Task: Alternate 1A-A and 18-8 Component Cooling Water Pumps.
Alternate Path: Must re-start 11A-A A-A CCS Pump due to failure of the 18-8 CCS Pump.
.Facility JPM #: New..
New Safety Function: 8 Plant Service Systems KIA 008 A2.01 Ability to (a) predict the impacts of the following malfunctions or operations on the CCWS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of CCW pump.
Rating(s): 3.3 1 3.6 3.3/3.6 CFR: 41.5/43.5/45.3/45.13 Preferred Evaluation Location: Preferred Evaluation Method:
Simulator xX In-Plant Perform - xX Simulate
References:
References:
- SOI-70.01 ,"Component Cooling Water (CCS) System," Rev. 61 AOI-15, "Loss of Component Cooling Water," Rev. 31 Task Number: RO-070-S01-70-023
Title:
Alternate CCS and T88Ps.
(
Task Standard: Applicant performs actions to alternate CCS pumps by performing SOI-70.01 "Component Cooling Water(CCS) System," Section 8.8 "Alternate CCS Pumps [0-M-278". After swapping pumps, the applicant responds to the shearing of 18-8 CCS pump shaft, and returns the 1A-A CCS pumpto pump to service.
Yes Validation Time: 15 minutes Time Critical: -
-- - No - X- -
=--=---
Applicant: Time Start:
NAME SSN Time Finish: -
Performance Rating: SAT UNSAT Performance Time Examiner: _______________________
NAME
~/
~/_--
SIGNATURE
__ DATE
.DATE
===============================================================
COMMENTS PAGE 2 OF 19
/--""\
(\ .
WATTS BAk I\IUCLEAR PLANT BAh. NUCLEAR B.1.h Nov. 2009 NRC Exam SIMULATOR OPERATOR INSTRUCTIONS:
- 1. ENSURE NRC Examination Security has been established.
- 2. Right click on 346, and tHen then select RESET.
- 3. Enter the password.
- 4. Select "Yes" on the INITIAL CONDITION RESET pop-up window.
S. ENSURE the following information appears on the Director Summary Screen:
IJ~~!~\ ;;!S~Y{,h~;~'*';. t\~I. . ... '.;"'~i<; :.<:~;~:::"'S\\H~lj:\, ).</, ..... Type *Event Delay \.' Inserted Ramp Initial 'Final ..*.. .' Va,lu~ \\.;
cc03a ccs pump 1a-a auto start inhibit M 00:00:00 00:00:00 InActive I Active ccr09 1-70-505b ccs pmp 1b-b 1b-b disch disch isol valve R 1 00:00:00 00:00:00 0.25 1 ccr08 1-70~505a ccs pmp 1a-a disch isol valve 1-70-505a R 2 00:00:00 00:00:00 025 1 cc07b ccs pump 1b-b shaft break M 3 00:00:00 00:00:00 InActive I InActive
- 6. Place simulator in RUN and acknowledge any alarms.
- 7. Place simulator in FREEZE until Examiner cue is given.
- 8. When requested, enter Event 1 to manipulate 1-ISV-70-S0Sb 18-8 1B-B CCS Pump Discharge isolation valve. Use remote function ccr09 to close1-70-S0Sb to 2S% open, and then modify the remote function to open the valve to 100%.
- 9. When requested, enter Event 2 to manipulate 1-ISV-70-S0Sa 1A-A 1A-A CCS Pump Discharge isolation valve. Use Us.e remote function ccr08 to close 1-70-S0Sa 7S% and report the valve position. After the 1A-A CCS pump is stopped, then modify the remote function to open the valve to 100%. .
- 11. Ensure that a copy of SOI-70.01Section501-70.01 Section 8.8, "Alternate CCS Pumps [0-M-27B] [0-M-278] is in the simulator booth.
PAGE 3 OF 19
PAGE 4 OF 19 WATTS BAR NUCLEAR PLANT B.1.h Nov. 2009 NRC Exam
(
READ TO APPLICANT DIRECTION TO APPLICANT:
I will explain the initial conditions, and state the taskto task to be performed. All control including any required room steps shall be performed for this JPM, including-any communications. I will provide initiating cues and 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:
- 1. Unit 1 is operating at 100% power.
- 2. Work Control has requested that the 1B-B CCS pump be placed in service and the 1A-A CCS pump be stopped to support upcoming testing.
- 3. Assistant UnitUnit Operators have been briefed and are standing by to support the pump swap.
( 4. You You are the Control Room Operator.
INITIATING CUES:
- 1. The Unit Supervisor has directed you to start 1 B-B CCS pump and stop 1A-A 1B-B CCS pump per SOI-70.01 ,"Component Cooling Water (CCS) System."
SOI-70.01,"Component
- 2. You are to inform the Unit Supervisor when the pump swap is complete.
PAGE 4 OF 19
WATTS BAR NUCLEAR PLANT B.1.h Nov~ 2009 NRC Exam Nov.
STEP/STANDARD SAT/UNSAT START TIME: _ __
STEP 1.: Obtain the appropriate procedure. SAT STANDARD: UNSAT Applicant determines that SOI-70.01, "Component Cooling Water (CCS)
.System," Subsection 8.8; 8.8, "Alternate CCS Pumps [0-M-27B]," is the appropriate procedure.
CAUTION*
CAUTION CCS Pump damage may occur below 900 gpm per pump.
NOTES
- 1) Pump starting guidelines are in GOI-7.
( 2) Throttling the discharge valves on the OPERABLE A train or B train pump requires entry into LCO 3.7.7 in MODES 1-4.
- 3) Performing this Section will require communications with the Control Room Operator and additional personnel in the field.
PAGE 5 OF 19
WATTS BAR NUCLEAR PLANT B.1.h Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 2:
2: [1] UNLOCK and THROTTLE disch on pump to be placed in service: CRITICAL (N/A if NOT starting): STEP NOMENCLATURE LOC LOC POSITION UNID PERF SAT INITIAL CCS PUMP 1A-A CGS A-A DISCHARGE A3S1713 AJSI713 25% OPEN 1-ISV-l0-SQSA 1-IS'v'-70-505A ISOLATION ISOLA.TION UNSAT ecs PUMP 116-8 B*B DISCHARGE A3S1713 A3Si713 2S%OPEN 25% OPEN 1-ISV-70-50SB 1-ISV-70-5056 ISOLATION lSOLA.TION ecs PUMP COS CCS C-S DISCHARGE A3SI713 2S%OPEN 25% OPEN O-ISV-70-50S 0-ISV-70-505 ISOLATION CCS PUMP 28-6 CGS 26-B DISCHARGE A2TI713 A2Tf713 25% OPEN 2-ISV-70-5056 2-IS\(-70-505B ISOLATION ISOLA.TION STANDARD:
Applicant contacts Aux Bldg AUO to locate 1-ISV-70-505B, CCS PUMP 1B-B 1B-B DISCHARGE ISOLATION and directs the AUO to open the valve 25%.
Applicant enters N/A for the 1A and C-S CCS pumps.
Step is critical to properly align pump to be started.
EVALUATOR NOTE: Use Event 1 to cause remote function ccr09 to open 1-ISV*70*505b 25%.
ISV-70-505b CUE: When requested, report that the discharge valve 1*ISV*70*505B 1-ISV-70-5058 CCS PUMP 18-8 1B*B DISCHARGE ISOLATION is 25% open.
COMMENTS:
PAGE 66 OF 19
WATTS BAR NUCLEAR PLANT B.1.h Nov. 2009 NRC Exam
(
STEP/STANDARD SAT/UNSAT STEP 3: [2] START pump to be placed in service (N/A Pumps NOT started): CRITICAL STEP NOMENCLATURE LOC Loe POSITION UNID UNIO PERF INITIAL CCS PMP 1A-A O-M-27B START 1-HS-70-46A SAT CCS PMP 1B-B O-M-27B 1-HS-70-38A START UNSAT CCS PMP C-S NORMAL ACB O-M-27B START 2-HS-70-51A CCS PMP C-S ALT ACB O-M-27B START 1-HS-70-51A CCS PMP 2B-B O-M-27B START 2-HS-70-33A STANDARD:
Applicant places 1-HS-70-38A CCS PMP 1B-B 1B-B on O-M-27B to START, and verifies RED light LIT, GREEN light DARK on handswitch 1-HS-70.:38A.
1-HS-70-38A.
Step is critical to start the correct pump.
( COMMENTS:
PAGE 7 OF 19
WATTS BAR NUCLEAR PLANT B.1.h Nov. 2009 NRC Exam
(
I STEP/STANDARD SAT/UNSAT SATIUNSAT NOTE Supply Header 1A total flow can be verified locally at 1-FI-70-199 [1-L-214/A, A3T1713].
A3T/713].
Supply Header 181B flow can be verified locally at 0-FI-70-201 [0-PNL-276-L643, ASS/713].
A5S/713].
STEP 4: [3] OPEN SLOWLY the disch valve of the Pump started in Step 8.8[2] CRITICAL WHILE CLOSING the discharge valve of the Pump to be removed STEP from service.
SAT STANDARD:
UNSAT Applicant contacts Aux Bldg AUO to slowly open 1-ISV-70-505B, 1-ISV-70-S0SB, CCS PUMP 1B-B DISCHARGE ISOLATION to 100%.
1B-B 1-ISV-70-S0SA, CCS PUMP Applicant contacts Aux Bldg AUO to slowly close 1-ISV-70-505A, 1A-A DISCHARGE ISOLATION.
Step is critical to properly align pumps during the transfer.
(
Modify remote function ccrO~ to 100% to fully open 1-ISV-70-505b.
1-ISV-70-S0Sb. When requested, report that the discharge valve 1-ISV-70-5058 1-ISV-70-S0SB CCS PUMP 18-1B-B8 DISCHARGE ISOLATION is open.
Modify remote function ccrOa ccrOS to 0% to fully close 1-ISV-70-505a.
1-ISV-70-50Sa. When requested, report that the discharge valve 1-ISV-70-505A 1-ISV-70-S0SA CCS PUMP 1A-A DISCHARGE ISOLATION is closing.
COMMENTS:
PAGE 8 OF 19
WATTS BAR NUCLEAR PLANT B.1.h Nov. 2009 NRC Exam
((
STEP/STANDARD SAT/UNSAT STEP 5: [4] LOCK OPEN the disch valve of the Pump started in Step 8.8[2].
SAT STANDARD:
UNSAT Applicant contacts Aux Bldg AUO to lock open 1-ISV-70-505B, CCS PUMP B-8 DISCHARGE ISOLATION.
1B-B When requested, report that the discharge valve 1-ISV-70-505B 1-ISV-70-S0S8 CCS 1B-B DISCHARGE ISOLATION is locked open.
PUMP 18-8 COMMENTS:
PAGE 9 OF 19
WATTS BAR NUCLEAR PLANT B.1.h Nov. 2009 NRC Exam
(
STEP/STANDARD SAT/UNSAT STEP 6: [5] WHEN the disch valve of the Pump to be removed from service is CRITICAL 75% CLOSED, THEN STOP the Pump to be removed from service. STEP (N/A Pumps NOT stopped)
SAT NOMENCLATURE LOC laC POSITION UNtO UNID PERF INITIAL eGS PMP 1A-A CCSPMP O-M-27B O-M-276 A-PAUTO 1-HS-70-46A l-HS-70-46A UNSAT eGS PMP 1B-8 CCSPMP 18-8 O-M-278 O-M-27B A-PAUTO 1-HS-70-3BA l-HS-70-38A CCS CGS PMP C-SC-S NORMAL ACB O-M-27B A-PAUTO 2-HS-70-51A 2-HS-7ll-51A ecs PMP C-S ALT ACB CCS O-M-27B A-P AUTO A-PAUTO 1-HS-70-51A l-HS-7ll-51A eGS PI'IIP 2B-B CCSPMP2B-8 0-M-27B O-M-278 A-PAUTO 2-HS-70-33A 2-HS-7ll-33A STANDARD:
Applicant directs the Aux Bldg AUO to call when 1-ISV-70-505A, CCS PUMP 1A-A DISCHARGE ISOLATION is 75% closed.
( Applicant stops the 1A-A CCS pump using 1-HS-70-46A. Verifies RED light DARK, Green Light LIT, motor amps drop to zero, and discharge pressure drops to zero.
Step is critical to properly align pumps during the transfer.
When requested, report that the discharge valve 1-ISV-70-505A CCS PUMP 1A-A DISCHARGE ISOLATION is closing. Use remote function ccr08 to close 1-70-505a.
ccrOa COMMENTS:
PAGE 10 OF 19
WATTS BAR NUCLEAR PLANT B.1.h Nov. 2009 NRC Exam
(
STEP/STANDARD SAT/UNSAT STEP 7: [6] VERIFY flow between 900 to 6800 gpm. SAT UNSAT STANDARD:
.Applicant determines from flow indications in the Control Room that flow is approximately 5500 gpm. Applicant may contact the Aux Bldg AUO to check flow locally.
header..
If requested, report that flow is 5600 gpm on 1A header
.COMMENTS:*
COMMENTS: .
(
PAGE 11 OF 19
WATTS BAR NUCLEAR PLANT B.1.h Nov. 2009 NRC Exam
(
STEP/STANDARD SAT/UNSAT STEP 8: [7] OPEN and LOCK disch valve for Pump STOPPED. (N/A valves for SAT pump NOT stopped)
UNSAT NOMENCLATURE LOC POSITION UNID PERF INITIAL CCS PUMP 'lA-A A3Sf713 LOCK '1-IS\/-7G-505A 1-ISV-70-50SA ISOLAT~ON DISCHARGE iSOLATION OPEN CV CCS PUMP 1B-6 B-B A3Si713 A3Sf713 LOCK LOCK 1-IS'I-70-505B 1-ISV-70-50S8 DISCHARGE ISOLATION OPEN CV ecs CCS PUMP C-S DISCHARGE A3Si713 A3Sf713 LOCK G-ISV-70-505 O-ISV-70-505 ISOLATION OPEN cv CII CCS PUMP PurvlP 28-6 2B-6 A2Tf713 A2TI713 LOCK 2-IS'I-70-5058 2-ISV-70-50SB DISCHARGE ISOLATION OPEN cv CV STANDARD:
Applicant contacts Aux Bldg AUO to have 1-ISV-70-505A, CCS PUMP 1A-A DISCHARGE ISOLATION opened completely and locked in the open position.
( When requested, report that the discharge valve 1-ISV-70-S0SA CCS 1A-DiSCHARGE ISOLATION is open, and locked.
PUMP 1A-DISCHARGE COMMENTS:
PAGE 12 OF 19
WATTS BAR NUCLEAR PLANT B.1.h Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 9: [8] ENSURE running pump's 480V ACB Closing Spring is CHARGED SAT (N/A Pumps NOTrunning):
NOT running):
UNSAT NOMENClATURE NOMENCLATURE CCS CGS PUMP 1A-A IA-A (1-PMP-70-461
( l-PMP-70-46)
CCS CGS PUMP 16-6 I B-B (1-PMP-70-381 (1-PMP-70-38)
NORMAL fOR FOR fOR CCS GCS PUMP c-s (O-PMP-70-51)
ALT A.LT FDR FOR FOR CCS PUMP c-s C-S (O-PMP-70-51I (O-PMP-70-51)
COMPONENT COOLING SYSTEM PUMP 26-6, 28-6, 2-MTR-70-33
( STANDARD:
Applicant contacts Control Bldg AUO to go to 480V SO SD Board 1B1-B 1B 1-B to ensure that the closing spring for 1B-B 1B-B CCS Pump, 1- BKR-70-38, is charged.
When requested, report as the Control Bldg AUO that the closing spring for 1B-B 1B-B CCS Pump, 1- BKR-70-38, is charged.
COMMENTS:
PAGE 13 OF 19
WATTS BAR NUCLEAR PLANT B.1.h Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT NOTE TO EVALUATOR: Cue Console Operator to insert malfunction cc08b, to shear the shaft on 1B-B CCS pump. Malfunction cc03a prevents the 1A-A CCS pump from auto starting on low header pressure.
(~NOT~1d~*E~~g~~T~~:
NOTE TO~EVALUATOR: . . The Tb;~ **~if~~.i~.
applicant may respond to the sheared shaft by stopping
'fJhe1 ~7§.c;Q§H')l.I:rnR:.a!1d the 1B-B startil'l~I;;tlX CCS pump and starting the 1A-A CCS pump based on receipt of 240-E RX BLDG**S(jPP[,¥HDRFLOWiLO~:&1~J*>
The applicant may immediately enter AOI-15 "Loss of Component Cooling Water (CCS)," to accomplish actions.
NOTE TO EVALUATOR: The following actions are taken from AOI-15, "Loss of Component Cooling Water (CCS),"
STEP 1 10:
0: 1. CHECK CCS pumps status: CRITICAL
- a. CHECK any CCS pump TRIPPED or running pump NOT STEP
( pumping forward:
- ERCW/CCS Motor trip out alarm, SAT
- Low header pressure (train A or B),
- Multiple low flow alarms. UNSAT STANDARD:
Applicant determines that the 1B-B CCS pump is no longer pumping forward, based on low header pressure and multiple low flow alarms.
May have been accomplished prior to AOI-15 entry, based on PRUDENT OPERATOR ACTIONS.
Step is critical to determine subsequent actions to take.
COMMENTS:
PAGE 14 OF 19
WATTS BAR NUCLEAR PLANT B.1.h Nov. 2009 NRC Exam
(
STEP/STANDARD SAT/UNSAT STEP 11: at/east one U-1 Train A header supply pump
- b. CHECK atleast CRITICAL RUNNING AND pumping forward: STEP
- 18-8 SAT STANDARD: UNSAT Applicant starts the 1A-A CCS pump using 1-HS-70-46A, verifies Green light DARK, Red light LIT. Verifies low pressure alarms clear, and multiple flow alarms clear.
been accomplished prior to AOI-15 entry, based on May have been PRUDENT OPERATOR ACTIONS.
Step is critical to determine subsequent actions to take.
COMMENTS:
(
STEP 12: c. CHECK any Train 8 header supply pump RUNNING AND SAT pumping forward:
- C-S UNSAT
- 28-8 STANDARD:
Applicant determines that the C-S CCS Pump is running by observing the Red light is LIT and the Green light is DARK.
. COMMENTS:
PAGE 15 OF 19
WATTS BAR NUCLEAR PLANT B.1.h Nov. 2009 NRC Exam
(
STEP/STANDARD SAT/UNSAT SATIUNSAT STEP 13: d. PLACE any non-operable or tripped CCS pump in CRITICAL STOP/PULL-TO-LOCK. STEP STANDARD: SAT Applicant stops the 18-8 CCS pump using 1-HS-70-38A, verifies Green UNSAT light LIT, Red light DARK.
Step is critical to place the pump in a position where a restart of the damaged pump cannot occur.
May have been accomplished prior to AOI-15 entry, based on PRUDENT OPERATOR ACTIONS.
COMMENTS:
(
STEP 14: e. CHECK TWO U-1 Train A header supply pumps RUNNING: SAT
- 18-8 UNSAT STANDARD:
Applicant determines that only the 1A-A CCS pump is running, supplying Train A Header. Enters RESPONSE NOT OBTAINED for additional actions.
COMMENTS:
PAGE 160F 16 OF 19
WATTS BAR NUCLEAR PLANT B.1.h Nov. 2009 NRC Exam
(
STEP/STANDARD .I
< SAT/UNSAT STEP 15: e. ENSURE at least one of the following CLOSED to avoid SAT excessive flow:
- SFP htx A, O-'FCV-70-197.
O-FCV-70-197.
STANDARD:
Applicant determines that 1-FCV-70-156 is CLOSED by verifying light DARK.
GREEN light LIT, RED 'light Applicant may CLOSE O-FCV-70-197 is CLOSED.
COMMENTS:
STE<P 16:
STEP f. CHECK flows returned to NORMAL. SAT STANDARD: UNSAT Applicant determines that flows have returned to normal based on the absence of flow alarms on panels 1-M-27A and 1-M-27-B.
1-M-27-8.
COMMENTS:
PAGE 17 OF 19
WATTS BAR NUCLEAR PLANT B.1.h Nov. 2009 NRC Exam
(
STEP/STANDARD SAT/UNSAT STEP 17: 'g.
- g. CHECK A and B side surge tank levels between 57% and 85%. - SAT STANDARD: - UNSAT Applicant determines that A and B Surge tank level are approximately 70% by observing 1-Ll-70-63A 1-U-70-63A and 1-Ll-70-99A.
1-U-70-99A.
COMMENTS:
STEP 18: h. ** GO TO Step 15.
15, - SAT
-- UNSAT STANDARD:
( CUE: After the applicant determines the need to go to step 15, state 'This completes this JPM,"
JPM."
COMMENTS:
END OF TASK STOP TIME _ __
PAGE 18 OF 19
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
(
DIRECTION TO APPLICANT:
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:
- 1. Unit 1 is operating at 100% power.
- 2. Work Control has requested that the 1B-B CCS pump be placed in service and the 1A-A CCS pump be stopped to support upcoming testing.
- 3. Assistant Unit Operators have been briefed and are standing by to support the pump swap.
- 4. You are the Control Room Operator.
(
INITIATING CUES:
- 1. The Unit Supervisor has directed you to start 1B-B CCS pump and stop 1A-A CCS pump per SOI-70.01,"Component 501-70.01 ,"Component Cooling Water (CCs) (CCS) System."
- 2. You are to inform the Unit Supervisor when the pump swap is complete.
Watts Bar Nuclear Plant Unit 1 System Operating Instruction SOI-70.01 801-70.01 Component Cooling Water (CCS) System Revision 0061 Quality Related Level of Use: Continuous Use
, Effective Date:
Date: 09-09-2009 Responsible Organization: OPS, Operations Prepared By: R. A A. O'Rear Approved By: William R. Myers
WBN Component Cooling Water (CCS) 501-70.01 Unit 1 System Rev. 0061 Page 2 of 152 Revision Log Rev or Affected Change Effective Page Number Date Numbers Description of Revision/Change 55 10/11/05 1,2,77,79, Implemented CA for PER 79171 by revising step [3]
81 in Sections 8.19, 8.20, and 8.21 to align the TBSS to either the Lined or Unlined pond per Chemistry recommendations prior to draining the CCS HXs.
56 07/24/06 All ALL - IQR XP conversion.
95 Added Shunt Trip Breaker to Checklist 1 This procedure has been converted from Word 95 to Word 2002 (XP) using Rev. 55 by Lorie Oake 57 11/23/06 1,2,7,26,30 Added step [4] to 6.1.1 and 6.1.3, which, implemented EOC 52133 which revised the ERCW implemented SO to require performers to monitor ERCW discharge header levels for equipment configuration changes affecting flow.
(
58 08/03/07 26,30 Revised to incorporate PER 124935-005 adding instruction to perform either Appendix A or B as appropriate of SOI-67.01 if ultrasonic flow indication for ERCW is not working.
21,22
& [6] at the request of training PCR Clarified 5.4[5] &
2868 59 01/08/08 2, 85, 86, 88, Enhancements to Sections 8.19 through 8.21 to 89,91,92 facilitate ease of performance. Added steps to ensure that the makeup valve(s) opens at 60% level.
UC-1 2,25,27 Added a NOTE and a step to allow using 1-FCV 146-A in Modes 4, 5, 6 or defueled if needed for additional cooling for CCS HX A.
60 03/03/08 24, 26 Incorporated UC-1.
84,87,90 Added NOTE to evaluate operability of CCS before performing Section 8.19, 8.20, or 8.21.94-101 Added Section 8.23 as a maintenance alignment for outage work to be performed in Mode 6 only.
61 09/09/09 2,4,102-108 Added Section 8.24 to allow supply of 1A and 1B ESF ESF loads from A HTX during defueled conditions to support outage work and return to normal
WBN Component Cooling Water (CCS) .SOI-70.01 SOI-70.01 Unit 1 System Rev. 0061 Page 3 of 152 Table of Contents
1.0 INTRODUCTION
............................................*............................................................. 6 1.1 Purpose .......... ~ .......................................... ;................................................................... 6 1.2 Scope .............................................................................................................................
............................................................................................................................ 6
2.0 REFERENCES
................................ ,. ........................................................................... 7 2.1 Performance References .............................................................................................. 7 2.2 Developmental References .......... ............................................................................................ 7 3.0 PRECAUTIONS AND LIMITATIONS ........................................................................... 8 4.0 PREREQUISITE ACTIONS ........................................................................................ 10 4.1 Preliminary Actions ..................................................................................................... 10 4.2 Field Preparations ....................................................................................................... 10 4.3 Approvals and Notifications ........................................................................................ 10 5.0 STARTUP ................................................................................................................... 11
( 5.1 Fill and Vent U U11 CCS .................................................................................................. 11 5.2 Fill and Vent U2 CCS .................................................................................................. 14 5.3 Placing Initial or Additional CCS 1A Train and 1B/2B Train Pumps in Service ........................................................................................................................ 16 5.4 Placing Thermal Barrier Booster Pumps in Service .................................................... 20 6.0 NORMAL OPERATION .............................................................................................. 21 6.1 6.1 CCS Temperature Control ............................................................. ;............................ 22 6.1.1 CCS Heat Exchanger A Temperature Control .............................................. 23 6.1.2 CCS Heat Exchanger B Temperature Control ...............................................
.............................................. 26 6.1.3 CCS Heat Exchanger C Temperature Control .............................................. 28 7.0 SHUTDOWN ............................................................................................................... 30 7.1 Shutdown U1 CCS., ..................................................................................................... 30 CCS ......................................................................................................
7.2 Shutdown 'U2 CCS ...................................................................................................... 32 7.3 Stopping CCS Pumps ................................................................................................. 33 8.0 INFREQUENT OPERATION ............................................................ *.......................... 34 8.1 Align Pump 1B-B to Supply Header 1B ...................................................................... 34 8.2 Return Pump 1B-B from Supply Header 1B to Supply Header 1A. ............................. 37 8.3 Align Pump C-S to Supply Header 1A ........................................................................ 40
WBN Component Cooling Water (CCS) 501-70.01 Unit 1 System Rev. 0061 Page 4 of 152 Table of Contents (continued) 8.4 Return Pump C-S from Supply Header 1A to Supply Header 1B ............................... 43 8.5 Place Supply Header 2A In Service ............................................................................ 47 8.6 Install ERCW Spool pieces to Surge Tank(s) ............................................................. 49 8.7 Transfer C-S Pump Power Supply .............................................................................. 52 8.8 Alternate CCS Pumps[0-M-27B] ................................................................................. 54 8.9 Swap 1BBP TBBP 1A to TBBP 1B ....................................................................................... 58 8.10 Swap TBBP 1B to TBBP 1A ....................................................................................... 59 8.11 Placing Seal Leakage Return System In Service ........................................................ 60 8.12 Shutting Down Seal Leakage Return System ............................................................. 62 8.13 Align Pump 2B-B to Supply Header 2A ...................................................................... 63 8.14 Return Pump 2B-B from Supply Header 2A to Supply Header 1B .............................. 66 8.15 Align C Heat Exchanger to 1A Equipment .................................................................. 69 8.16 Return 1 A Equipment to A Heat Exchanger ................................................................ 73 1A 8.17 Align B Heat Exchanger to 1B Equipment .................................................................. 77 8.18 Return 1B Equipment to C Heat Exchanger ............................................................... 80 8.19 Feed and Bleed U-1 Train A CCS ............................................................................... 84 8.20 Feed and Bleed U-2 Train A CCS ............................................................................... 87 8.21 Feed and Bleed U-1 & 2 Train B CCS ........................................................................ 90 8.22 Remove CCS flow from SFP HX A. ............................................................................ 93 8.23 Align CCS Train B Flow to SFP HX A. ........................................................................ 94 8.24 Align ESF Headers 1A and 1 B to CCS HX A ............................................................ 102 1B 9.0 RECORDS ................................................................................................................ 109 9.1 QA Records .............................................................................................................. 109 9.2 Non-QA Non-QA, Records ...................................................................................................... 109 Checklist 1: U1 and Common Power Alignment Verification ................................... 110 Checklist 2: U2 Power Alignment Verification .......................................................... 114 Checklist 3: U1 CCS Normal Valve Alignment Verification ...................................... 115 Checklist 4: Pump 1A-A Normal Valve Alignment Verification ................................ 141 Checklist 5: Pump 1B-B Normal Valve Alignment Verification ................. :.............. 142 Checklist 6: Pump C-S Normal Valve Alignment Verification .................................. 143
WBN Component Cooling Water (CCS) SOI-70.01 Unit 1 System Rev. 0061 Page 5 of 152 Table of Contents (continued)
Checklist 7: Pump 2A-A Normal Valve Alignment Verification ................................ 144 Checklist 8: Pump 2B-B 2B-8 Normal Valve Alignment Verification ................................ 145 Checklist 9: 2A ESF Header Valve Alignment Verification ....................................... 146 Checklist 10: U2 Equip from CCS Hx B 8 Valve Alignment Verification ....*....................................... 148 Source Notes ........................................................................................... 152
WBN Component Cooling Water (CCS) SOI-70.01 Unit 1 System Rev. 0061 Page 6 of 152
1.0 INTRODUCTION
1.1 Purpose To provide instructions for operation of the Component Cooling System (CCS).
1.2 Scope This Instruction includes operation of the following:
A. CCS Pumps and Heat Exchangers (HXs)
B. Pump Seal Leakage Return System C. Thermal Barrier Booster Pumps (TBBPs)
This Instruction also includes the following infrequent operations:
D. Alternate Lineup for Pumps Supplying Train B Loads E. Placing Unit 2 Loads in Service
( F. ERCW Spool piece Installation G. C-S Pump Power Supply Transfer H. Alternating CCS Pump Operation I. Alternating Thermal Barrier Booster Pump Operation J. Feed && Bleed U1/U2 U 1/U2 Train AlTrain B CCS K. Remove CCS flow from SFP HX A L. Align CCS Train B to SFP HX A
WBN Component Cooling Water (CCS) SOI~70.01 SOI-70.01 Unit 1 System Rev. 0061 Page 70f 7 of 152
2.0 REFERENCES
2.1 Performance References A. SOI-90.01, Liquid Process Radiation Monitors B. GOI-7, Generic Equipment Operating Guidelines C. Fire Protection Report (FPR) Table 14.10 2.2 Developmental References A. TI-31.08, Flow Balancing Valves Setpoint Positions B. SOI-67.01, Essential Raw Cooling Water System C. SOI-78.01, Spent Fuel Pool Cooling And Cleaning System D. TI-78.004, Guidance For Implementing Higher SFP Heat Loads E. GO-1, Unit Startup From Cold Shutdown To Hot Standby
(,
F. Memorandum B26850503027, B268S0S03027, Locked Valves G. N3-70-4002, System Description for Component Cooling System H. N3-67-4002, N3-67 -4002, System Description for ERCW I. SOI-77.01, Liquid Waste Disposal J. TVA Drawings:
1-45N600-70 1-4S N600-70 1-45N706-1 1-4SN706-1 1-45N1637-2,-7 1-4SN 1637-2,-7 1-45N 1645-3,-6 1-4SN 164S-3,-6 1-45N 1-4SN 1668-2 1-45W703-5,-6,-7 1-4SW703-S,-6,-7 1-45W751-5,-6,-10,-12 1-4SW751-S,-6,-10,-12 1-45W760-70 1-4SW760-70 Series 1-4SW760-67-17 1-45W760-67 1-47W859 Series K. Tech Spec 3.7.7, Component Cooling System
(
WBN Component Cooling Water (CCS) SOI-70.01 Unit 1 System Rev. 0061 Page 8 of 152 3.0 PRECAUTIONS AND LIMITATIONS A. CCS design press is 150 psig. Design Temp is 200°F.
B. Normal CCS Supply Header (Hx outlet) temp is 60°F to 95°F for "A" Hx.
and 40°F to 95°F for "B" and "c" Heat exchangers. When ERCW inlet temperature is below 60°F, supply temperature may be lower than 40°F for the "B" and "c" heat exchangers and lower than 60°F for "A" heat exchanger but should be maintained as close to normal as possible by by throttling ERCW flow.
Additional limitations are discussed in Section 6.0.
C. CCS Pump flow: Minimum is 900 gpm; Maximum is 6800 gpm per pump.
D. C-S Pump Local Throwover Switch must NOT be operated if either Red light on the panel is on, indicating one of the 480V SO SD Bd ACBs is CLOSED.
Switch Transfer may require Tech Spec LCO 3.7.7 entry.
E. Chemicals added to CCS for corrosion control are TOXIC. The Material Safety Data Sheets for the chemicals added to CCS (i.e. sodium molybdate, sodium hydroxide and Cobratec TT50), have precautions necessary for handling treated CCS water.
(
F. When heat load is on CCS, ERCW must be in service to CCS Hx(s).
G. CCS misaligned to SFP Hx(s) causes water interchange between Unit 1 and Unit 2.
H. To avoid CCS Hx tube vibration and excessive load, do NOT exceed shell design flow of 12000 gpm.
I. All CCS Pumps start on a Blackout if handswitch is in A-P AUTO; however while U2 is in deferred status and Pump 2B-B is aligned with Pump C-S, Header 2A low press auto-start signal is disconnected from Pump 2B-B, and the SI Signal is disconnected from both U2 Pumps.
J. Before operating Train B equipment, flow must be established in 1B Header.
K. If a CCS loop is SHUT DOWN, associated Rad monitor will alarm on low flow.
L. Discharge of various relief valves is routed to station drainage .
..' M. Thermal Barrier Booster Pumps trip on Cntmt 0B Isol signal, and Cntmt Isol Valves for Thermal Barriers, and RCP upper and lower oil coolers CLOSE. If power is lost to either TBBP (Rx MOV Bd) the 0B seal-in is lost and the pump can restart with no flow path.
N. When isolating CCS-supplied Hx, the primary side must be isolated and allowed to cool below 200°F BEFORE isolating CCS flow.
WBN Component Cooling Water (CCS) SOI-70.01 Unit 1 System Rev. 0061 Page 9 of 152 3.0 PRECAUTIONS AND LIMITATIONS (continued)
O. When RHR temp is above 212°F. CCS through RHR Hx(s) may flash during low CCS flow conditions.
P. After proper rate is set, throttling CCS flow to the RHR Hxs to control RHR cooldown rate is prohibited. Such action can cause overheating of the Hx CCS side.
Q. RHR Hx heat load during hot shutdown is limited by throttling the reactor coolant flow through Hx(s) to maintain Hx CCS outlet at 146°F or below.
R. ERCW Spoolpiece Installation to Surge Tank(s) is done only if no Demin Water is available for makeup.
S. Each ACB's AC8's closing spring must be verified charged during RACK-IN, and after AC8 operation. 2 each ACB T. During Modes 4 (with RHR in service), 5, and 6 with only one CCS Pump available for Train A, it is necessary to limit flow demands on CCS. Isolation of SFPCS Hx A to ensure adequate cooling to RHR Hx (and other equipment) is required. If the second CCS Pump normally aligned to CCS Train 1A cannot be placed in service before the SFP water temperature annunciator alarms, it will be necessary to realign the CCS System before the.SFP water boils. CCS Train 18 1B must be used to provide RHR cooling. If RHR HX 18 1B is NOT in service, it must be placed in service. RHR HX 1A must be removed from service, and SFPCS HX A shall be returned to service on CCS Train 1A. If RHR HX 18 1B cannot be placed in service, CCS Pump C-S must be realigned to CCS Train 1A to provide the additional cooling water required to supply both the RHR and SFPCS heat exchangers, and other components served by the CCS Train 1A. See Discussion in Section 6.0 U. CCS Pump 2B-B 28-8 is aligned to replace C-S Pump in support of Train 18, 1B, and positioned with power removed to assure availability of CCS flow valves are positioned paths, in event of Appendix R fire. . .
V. Valves to non-safety related CCS piping shall remain locked-closed except during actual operation when under constant operator surveillance.
W. CCS supply and discharge valves to PASS Hxs shall be locked-closed except during sampling operations.
X. Environmental services can permit draining CCS heat exchangers to the station sump (versus FDCT which must be processed) on a case by case basis per guidelines of ECM-3. Operations should coordinate with the environmental staff
. prior to initiating/terminating any releases to station sump so that they can calculate release concentrations and closely monitor pond conditions.
WBN Component Cooling Water (CCS) SOI-70.01 SOI*70.01 Unit 1 System Rev. 0061 Page 10 of 152 Date___ __ __ INITIALS 4.0 PREREQUISITE ACTIONS 4.1 Preliminary Actions NOTES
- 1) Throughout instruction where IF/THEN exists, the step is N/A if condition does NOT exist.
- 2) Throughout Throughout this instruction, Concurrent Verification (CV) for breaker or fuse manipulations may be marked N/A if no manipulation is performed.
[1] INDICATE Section to be performed, and reason for use.
5.0 Startup 7.0 Shutdown Normal Infrequent 6.0 Operation - - - - - 8.0 Operations - - - -
Section/ Reason/ Remarks:
4.2 Field Preparations
[1] ENSURE Section 3.0 Precautions and Limitations, REVIEWED.
[2] ENSURE Demin Water System AVAILABLE, and IN SPECS per Chemistry, for Surge Tank makeup.
4.3 Approvals and Notifications
[1] COORDINATE system operations/manipulations with UO.
[2] IF work is in a radiation/contamination area, THEN NOTIFY Radiation Protection (RP) for surveys and/or permits as necessary.
[3] IF a Process Radiation Monitor alarms OR a leak from a radioactive system to the CCS is detected, THEN NOTIFY RP and Chemistry.
WBN Component Cooling Water (CCS) SOI-70.01 Unit 1 System Rev. 0061 Page 54 of 152 Date _ _ __ INITIALS 8.8 Alternate CCS Pumps[0-M-27B]
CAUTION CCS Pump damage may occur below 900 gpm per pump.
NOTES
- 1) Pump starting guidelines are in GOI-7.
- 2) Throttling the discharge valves on the OPERABLE A train or B train pump requires entry into LCO 3.7.7 in MODES 1-4.
- 3) Performing this Section will require communications with the Control Room Operator and additional personnel in the field.
[1] UNLOCK and THROTTLE disch on pump to be placed in service:
(N/A if NOT starting):
NOMENCLATURE LOC POSITION UNID PERF INITIAL CCS PUMP 1A-A 1A-A DISCHARGE A3S/713 25% OPEN 1-ISV-70-505A ISOLATION CCS PUMP 18-8 1B-B DISCHARGE A3S/713 25% OPEN 1-ISV-70-5058 1-ISV-70-505B ISOLATION CCS PUMP C-S DISCHARGE A3S/713 25% OPEN O-ISV-70-505 ISOLATION CCS PUMP 28-8 2B-B DISCHARGE A2T/713 25% OPEN 2-ISV-70-505B ISOLATION
WBN Component Cooling Water (CCS) SOI-70.01 Unit 1 System Rev. 0061 Rev.00S1 Page 55 of 152 Date_ __ INiTIALS INITIALS 8.8 Alternate CCS Pumps[0-M-27B] (continued)
CAUTION Pump damage may occur below 900 gpm per pump NOTE Pump starting guidelines are in GOI-7
[2] START pump to be placed in service (N/A Pumps NOT started):
NOMENCLATURE LOC POSITION UNID PERF INITIAL CCS PMP 1A-A O-M-27B START 1-HS-70-46A CCS PMP 1B-B O-M-27B START 1-HS-70-38A c CCS PMP C-S NORMAL ACB CCS PMP C-S ALT ACB O-M-27B O-M-27B START
. START 2-HS-70-51A 1-HS-70-51A CCS PMP 2B-B O-M-27B START 2-HS-70-33A NOTE A3T/713]..
Supply Header 1A total flow can be verified locally at 1-FI-70-199 [1-L-214/A, A3TI713]
. Supply Header 1B flow can beb_e verified locally at 0-FI-70-201 [0-PNL-276-L643, A5S/713].
[3] . OPEN SLOWLY the disch valve of the Pump stari:ed started in Step 8.8[2]
WHILE CLOSING the discharge valve of the Pump to be removed from service
[4] LOCK OPEN the disch valve of the Pump started in Step 8.8[2].
cv
WBN Component Cooling Water (CCS) SOI-70.01 Unit 1 System Rev. 0061 Page 56 of 152 .
Date _ _ __ INITIALS 8.8 Alternate CCS Pumps[0-M-27B] (continued)
~ [5] WHEN the disch valve of the Pump to be removed from service is 75% CLOSED, THEN STOP the Pump to be removed from service. (N/A Pumps NOT stopped)
NOMENCLATURE LOC POSITION UNID PERF INITIAL CCS PMP 1A-A O-M-27B A-PAUTO 1-HS-70-46A CCS PMP 1B-B O-M-27B A-PAUTO 1-HS-70-38A CCS PMP C-S NORMAL ACB O-M-27B A-PAUTO 2-HS-70-51A CCS PMP C-S ALT ACB O-M-27B A-PAUTO 1-HS-70-51A CCS PMP 2B-B O-M-27B A-PAUTO 2-HS-70-33A
(
[6] VERIFY flow between 900 to 6800 gpm.
[7] OPEN and LOCK disch valve for Pump STOPPED. (N/A valves for pump NOT stopped)
NOMENCLATURE LOC POSITION UNID PERF INITIAL CCS PUMP 1A-A A3S/713 LOCK 1-ISV-70-505A DISCHARGE ISOLATION OPEN CV CCS PUMP 1B-B A3S/713 LOCK 1-ISV-70-505B DISCHARGE ISOLATION OPEN CV CCS PUMP C-S DISCHARGE A3S/713 LOCK O-ISV-70-505 ISOLATION OPEN CV CCS PUMP 2B-B A2T/713 LOCK 2-ISV-70-505B DISCHARGE ISOLATION OPEN CV
WBN Component Cooling Water (CCS) SOI-70.01 Unit 1 System Rev. 0061 Page 57 of 152 Date_ _ __ INITIALS 8.8 Alternate CCS Pumps[0-M-27B] (continued)
[8] ENSURE running pump's 480V ACB Closing Spring is CHARGED (N/A Pumps NOT running):
NOMENCLATURE LOC POSITION UNIO PERF INITIAL 480V SO Bd 1A1-A CCS PUMP 1A-A C/38 C/3B CLOSING 1-8KR-70-46 1-BKR-70-46 (1-PMP-70-46) SPRING CHARGED CV 480V SO Bd 1B1-B CCS PUMP 1 18-B B-B C/3C CLOSING 1-8KR-70-38 1-BKR-70-38 (1-PMP-70-38) SPRING CHARGED CV 480V SO Bd 2B2-B NORMAL FDR FOR FOR CCS C/2D C/20 CLOSING 0-8KR-70-51A O-BKR-70-51A PUMP C-S (O-PMP-70-51) SPRING CHARGED C'V 480V SO Bd 1A2-A ALT FOR FDR FOR CCS PUMP C/38 C/3B CLOSING 0-8KR-70-518 O-BKR-70-51B C-S (O-PMP-70-51) SPRING CHARGED CV 480V SO Bd 2B1-B COMPONENT COOLING C/3C CLOSING 2-8KR-70-33 2-BKR-70-33 2B-8, SYSTEM PUMP 2B-B, SPRING 2-MTR-70-33 CHARGED CV
AOI-15 WBN LOSS OF COMPONENT COOLING WATER (CCS) Revision 31 Page 6 of 31 3.2 Loss of CCS Flow/Outleakage ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 1. CHECK CCS pumps status:
- a. CHECK any CCS pump TRIPPED a. ** GO TO Caution prior to or running pump NOT pumping Step 2.
forward:
- ERCW/CCS Motor tripout alarm,
- Low header pressure (train A or B),
8),
- Multiple low flow alarms.
- b. CHECK at least one U-1 Train A b. START available U-1 Train A header supply pump RUNNING CCS Pump.
AND pumping forward:
(
- 18-8 1B-B
- c. CHECK any Train B 8 header c. START available Train B 8 CCS supply pump RUNNING pump, AND pumping forward:
- C-S
d... PLACE any non-operable d
or tripped CCS pump in STOP/PULL-TO-LOCK.
- e. CHECK TWO U-1Train A e. ENSURE at least one of the header supply pumps following CLOSED to avoid RUNNING: excessive flow:
- RHR htxA, htx A, 1-FCV-70-156,
- SFP htx A, 0-FCV-70-197.
(step continued on next page)
AOI-15 WBN LOSS OF COMPONENT COOLING WATER (CCS)
Revision 31 Page 7 of 31 3.2 Loss of CCS Flow/Outleakage (Continued)
ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED
- 1. (continued from previous page)
- f. CHECK flows returned to NORMAL. f. ** GO TO Caution prior to Step 2.
- g. CHECK A and B side surge tank g. IF surge tank level less than 57%,
levels between 57% and 85%. THEN
- GO TO Caution prior to Step 2.
IF surge tank level greater than 85%, THEN
- GO TO Section 3.3.
- h. ** GO TO Step 15.
CAUTION A closed surge tank vent valve may cause a positive or negative tank pressure, giving an erroneous level indication.
- 2. CHECK 1-FCV-70-66, U1 OPEN 1-FCV-70-66, U1 Surge Tank Vent, OPEN. Surge Tank Vent.
- 3. IF surge tank level less than 57%,
THEN ENSURE 1-LCV-70-63, U1 Surge Tank Makeup LCV, OPEN (Refer to SOI-70.01 as required if makeup not available).
- 4. MONITOR A and B side surge tank STOP affected CCS pumps.
levels greater than 10%.
REV. 0 PAGE 1 OF 11 WATTS BAR NUCLEAR PLANT B.1.i Nov. 2009 NRC Exam B.1.i Isolate Rep Seal h1jection Injection and T"hermal Thermal Barrier Flow.
/
REV. 0 PAGE 2 OF11 WATTS BAR NUCLEAR PLANT B.1.i Nov. 2009 NRC Exam EVALUATION SHEET Task: Isolate RGP RCP seal injection and thermal barrier flow.
Alternate Path: NIA Facility JPM #: 3-0T-JPMA024 Safety Function: 1
Title:
KIA 055 EK3.02 EK3 Knowledge of the reasons for the following responses as they apply to the Station Blackout: Actions contained in EOP for loss of offsite and onsite power.
Rating(s): 4.3/4.6 CFR: 41.5/41.10/45.6/45.13 Preferred Evaluation Location: Preferred Evaluation Method:
Simulator -
In-Plant x Perform x X
Simulate
References:
EGA-O.O ECA-O.O "Loss of Shutdown Power," Rev.19.
Task Number: RO-113-ECA-0.0-001
Title:
Task Standard: Applicant locates and closes the valves listed in Appendix "A", Attachment 1 of EGA-O.O, ECA-O.O, "Loss of Shutdown Power."
Validation Time: 10 minutes Time Critical: Yes --
No - X- -
===============================================================
Applicant: Time Start:
NAME SSN Time Finish: _ __
Performance Rating: SAT UNSAT Performance Time
. Examiner: ______________
----------------------~/--_--
_1------
NAME SIGNATURE DATE
===============================================================
COMMENTS
REV. 0 PAGE 3 OF 11 WATTS BAR NUCLEAR PLANT B.1.i Nov. 2009 NRC Exam Tools/Equipment/Procedures Needed:
HardHat, Hard Hat, Safety Glasses, Hearing Protection, Gloves, and Plant Approved Shoes.
ECA-O.O Appendix "A" NOTE: Start this JPM in the MCR.
EVALUATOR NOTE: Provide copy of ECA-O.O Attachment "A" (page 2 of 2) to the applicant with APPLICANT CUE SHEET.
REV. 0 PAGE 4 OF 11 WATTS BAR NUCLEAR PLANT B.1.i Nov. 2009 NRC Exam DIRECTIONS TO APPLICANT DIRECTION TO APPLICANT:
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating/operating cues.
NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM. SIMULATE ALL MANIPULATIONS.
When you complete the task successfully, the objective for this job performance measure will be satisfied.
Ensure that you indicate to me when you fully understand your task.
INITIAL CONDITIONS:
- 1. Unit 1 has just entered Mode 3 following a shutdown required by Tech. Specs due to the loss of 6.9kV Shutdown Board 1B-B.
- 2. The "B" CVCS Seal Injection Water Filter is in service.
- 3. A tornado on site caused a complete loss of off-site oft-site power and the 1A-A Diesel Generator failed to start.
- 4. The crew transitioned to ECA-O.O, "Loss of Shutdown Power" due to the loss of shutdown power and is progressing through the steps.
- 5. Attempts are being made to restore shutdown power.
- 6. You are an AUO on shift.
INITIATING CUES:
- 1. The control room crew was unable to isolate RCP seal return valves or thermal barrier.
- 2. The CRO has directed you to perform local actions of Attachment 1 of Appendix "A" of ECA 0.0 to isolate the RCP seals and thermal barrier.
- 3. You are to notify the CRO when you have finished Attachment 1 of Appendix A, ECA-O.O.
REV. 0 WATTS BAR NUCLEAR PLANT B.1.i Nov. 2009 NRC Exam STEP/STANDARD SATIUNSAT SAT/UNSAT START TIME: _ __
SAT STEP 1: ECA-O.O.
Obtain a copy of Appendix "A" of ECA-D.D.
STANDARD: A copy of Appendix A of ECA-D.D ECA-O.O has been obtained. UNSAT EXAMINER'S CUE: Provide copy of Appendix A Attachment 1 (page 2 of 2) of ECA-O.O to the applicant.
COMMENTS:
Note
- Appendix "A" steps can be performed in any order. (Steps 1- 3)
- Step 1 must always be performed.
STEP 2: [STEP 1] ISOLATE RCP seal injection [reach rods outside CRITICAL seal water injection filter cubicles]: STEP
STANDARD: 1-ISV-62-549 has been located and turned clockwise to UNSAT close.
Step is critical because it isolates the flow path from CVCS to RCP seals preventing thermal shock to shaft and seal if CVCS charging is restored.
- CUE: After the applicant demonstrates how to close valve, state that the hand wheel turns several turns and stops.
COMMENTS:
PAGE 5 OF 11
REV. 0 WATTS BAR NUCLEAR PLANT B.1.i Nov. 2009 NRC Exam I STEP/STANDARD SAT/UNSAT SAT STEP 3: [STEP 1 continued]
- CLOSE 1-BYV-62-546, eves -
SEAL WTR INJ FLTRFL TR BYP [A5T/713].
- UNSAT STANDARD: 1-BYV-62-546 has been located and checked closed.
- CUE: After the applicant demonstrates how to check valve closed, state that the hand wheel does not turn when clockwise motion is applied.
COMMENTS:
SAT STEP 4: [STEP 1 continued]
- CLOSE 1-ISV-62-550, eves -
SEAL WTR INJ FL TR A OUT ISOL [A5T/713].
UNSAT STANDARD: 1-ISV-62-550 has been located and checked closed.
- CUE: After the applicant demonstrates how to check valve closed, state that the hand wheel does not turn when clockwise motion is applied.
COMMENTS:
PAGE 6 OF 11
REV. 0 WATTS BAR NUCLEAR PLANT B.1.i Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT NOTE Step 2 to be performed only if MCR is unable to close either 1-FCV-62-61 or 1-FCV-62-63.
Examiner Cue: IF/when Control Room is contacted to determine if 1-FCV-62-61 or 1-FCV-62-63 is CLOSED, respond that neither 1-FCV-62-61 nor 1-FCV-62-63 is CLOSED.
STEP 5: CRITICAL
[Step 2] ISOLATE RCP seal return valves [reach rods outside filter cubicle]: STEP
- CLOSE 1-ISV-62-642, CVCS SEAL WTR RETURN FILTER INLET ISOL [A5T/713]. SAT STANDARD: 1-ISV-62-642 has been located and turned clockwise to UNSAT close.
Step is critical to isolate flow path from RCP seals to VCT.
- CUE: After the applicant demonstrates how to close valve, state that the hand wheel turns several turns and stops.
COMMENTS:
SAT STEP 6: [STEP 2 continued]
- CLOSE 1-BYV-62-643, CVCS SEAL WTR RETURN FILTER BYPASS [A5T/713].
UNSAT STANDARD: 1-BYV-62-643 has been located and checked closed; closed.
- CUE: After the applicant demonstrates how to check valve closed, state that the hand wheel does not turn when clockwise motion is applied.
COMMENTS:
PAGE 7 OF 11
REV. 0 WATTS BAR NUCLEAR PLANT B.1.i Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT NOTE TO EVALUATOR: Stop applicant before entering BIT room (for ALARA concerns) and have candidate describe valve location (valve 1-FCV-70-90). Use posted survey map. After candidate describes the valve's approximate location, simulate the performance of the next step without entering the BIT Room.
NOTE Step 3 to be performed only if MCR is unable to close at least one of the thermal barrier supply and one of the thermal barrier return isolation valves.
NOTE TO EVALUATOR: If/when Control Room is contacted, respond that no thermal barrier supply or return isolation valve is closed. .
STEP 7: [STEP 3] ISOLATE RCP thermal barrier: CRITICAL STEP
STANDARD: 1-FCV-70-90 has been located, actuator engaged and UNSAT
. turned clockwise to close.
This step is critical to isolate flow path to protect CCS from steam formation in CCS.
EXAMINER NOTE: This valve is in the BIT room overhead, just below the ceiling in the southwest corner behind the BIT.
ALARA Considerations: If candidate attempts to climb up to valve without first checking with RADCON, stop candidate and require contact with RADCON. See note preceding this step. step.
- CUE: After the applicant demonstrates how to close yalve, valve, state that the hand wheel turns many turns and stops.
COMMENTS:
PAGE 8 OF 11
REV. 0 WATTS BAR NUCLEAR PLANT B.1.i Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 8: [STEP 3 continued]
[A5W/737]. -
SAT STANDARD: 1-ISV-70-677A 1-ISV-70-677A has been located and turned clockwise to UNSAT close.
Step is critical to isolate flow path to prevent thermal shock to RCP seals when CCS is restored.
- CUE: After the applicant demonstrates how to close valve, state that the hand wheel turns many turns and stops.
COMMENTS:
STEP 9: [STEP 3 continued]
[A5W/737]. - SAT STANDARD: 1-ISV-70-677B has been located and turned clockwise to UNSAT close.
Step is critical to isolate flow path to prevent thermal shock to RCP seals when CCS is restored.
- CUE: After the applicant demonstrates how to close valve, state that the hand wheel turns many turns and stops.
COMMENTS:
PAGE 9 OF 11
REV. 0 WATTS BAR NUCLEAR PLANT B.1.i Nov. 2009 NRC Exam
) I~I==================ST=E=P='S=T=A=N=D=A=R=D==================*=S=A=T='U=N=S=A=T~
. I STEP/STANDARD SAT/UNSAT STEP 10: SAT Inform the Control Room Operator that Attachment 1 of Appendix A, ECA-O.O has been completed.
UNSAT STANDARD: The control room operator has been informed that "A" has been completed.
Attachment 1 of Appendix "A"has
- CUE: When notified, acknowledge the report using "repeat back".
COMMENTS:
END OF TASK STOP TIME _ _ ___
PAGE 10 OF 11
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
DIRECTION TO APPLICANT:
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating/operating cues.
NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM. SIMULATE ALL MANIPULATIONS.
When you complete the task successfully, the objective for this job performance measure will be satisfied.
Ensure that you indicate to me when you fully understand your task.
INITIAL CONDITIONS:
- 1. Unit 1 has just entered Mode 3 following a shutdown required by Tech. Specs due to the loss of 6.9kV Shutdown Board 1B-B. B*B.
- 2. The "B" CVCS Seal Injection Water Filter is in service.
- 3. A tornado on site caused a complete loss of off-site off*site power and the 1A-A 1A*A Diesel Generator failed to start.
- 4. The crew transitioned to ECA-O.O, ECA*O.O, "Loss of Shutdown Power" due to the loss of shutdown power and is progressing through the steps.
- 5. Attempts are being made to restore shutdown power.
- 6. You are an AUO on shift.
INITIATING CUES:
- 1. The control.
control room crew was unable to isolate RCP seal return valves or thermal barrier.
- 2. The CRO has directed you to perform local actions of Attachment 1 of Appendix "A" of ECA 0.0 to isolate the RCP seals and thermal barrier.
- 3. You are to notify the CRO When when you have finished Attachment 1 of Appendix A, ECA-O.O.
ECA*O.O.
) WBN LOSS OF SHUTDOWN POWER POWER IECA-O.O ECA-O.O Rev 19 APPENDIX A (ECA-D.D)
ATTACHMENT 1 Page 2 of2 of 2 RCP SEALS AND THERMAL BARRIER ISOLATION LOCAL-Performed by NAUO NOTE
- These steps can be performed in any order.
- Step 1 must always be performed.
- 1. ISOLATE RCP seal injection [reach rods outside seal water injection filter cubicles]:
1-ISV-62-S49, CVCS SEAL WTR INJ FL
- CLOSE 1-ISV-62-549, TR BOUT ISOL [AST/713]
FLTR [A5T/713]
- CLOSE 1-BYV-62-546, 1-BYV-62-S46, CVCS SEAL WTR INJ FLTR BYP[A5T/713]
BYP[AST/713]
1-ISV-62-SS0, CVCS SEAL WTR INJ FLTR A OUT ISOL [A5T/713]
- CLOSE 1-ISV-62-550, NOTE Step 2 to be performed only if MCR is unable to close either 1-FCV-62-61 or 1-FCV-62-63.
- 2. ISOLATE RCP seal return valves [reach rods outside seal return filter cubicle]:
- CLOSE 1-ISV-62-642, CVCS SEAL WTR RETURN FILTER INLET ISOL
[A5T/713]
- CLOSE 1-BYV-62-643, CVCS SEAL WTR RETURN FILTER FILTER BYPASS
[AST/713]
[A5T/713]
NOTE Step 3 to be performed only if MCR is unable to close at least one of the thermal barrier supply and one of the thermal barrier return isolation valves.
- 3. ISOLATE RCP thermal barrier:
THERMAL BARRIER CCS RETURN
- CLOSE 1-FCV-70-90, THERMAL
[above south side of BIT]
[ASW/737]
[A5W/737]
ISOLATION [ASW/737]
)
20 of 20
WATTS BAR NUCLEAR PLANT B.1.j Nov. 2009 NRC Exam B.1.j Installation Of Temporary Cooling (HPFP)
'\
)
PaClF~
P~nA 1 of 17
WATTS BAR NUCLEAR PLANT B.1.j Nov. 2009 NRC Exam EVALUATION SHEET Task: Installation Of Temporary Cooling (HPFP) To CCP 1A-A Oil Coolers Alternate Path: N/A NIA Facility JPM #: 3-0T-JPMA 170 3-0T-JPMA170 Safety Function:
Title:
KIA 076 A2.01 Ability to (a) predict the impacts of the following malfunctions or operations on the SWS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of SWS Rating{s): I 3.7 3.5 1 CFR: 41,5 /43.5 / 45/3/
41.5/43.51 45/31 45/13 Preferred Evaluation Location: Preferred Evaluation Method:
Simulator In-Plant x Perform xX Simulate
References:
AOI-13, "Loss of Essential Raw Cooling Water (ERCW) System," Rev. 36.
Task Number:
Title:
Task Standard: Applicant aligns temporary cooling to CCP 1 1A-A A-A Oil Coolers per Appendix E of AOI-13 "Loss of Essential Raw Cooling Water."
Validation Time: 20 minutes Time Critical: Yes - - No - X - = --
===============================================================
Applicant: Time Start:
NAME SSN Time Finish: -
Performance Rating: SAT UNSAT Performance Time Examiner: _ _ _ _ _ _ _ _ _ _ _ __ -----------------~--~/___-
--------------------_1-----
SIGNATURE*
NAME SIGNATURE DATE
- OATE
===============================================================
Validation Time: 20 minutes Time Critical: Yes --
No -X- - - -
--"-=---
============'===================================================
===============================================================
COMMENTS P~aA P::lOA 2 af of 17
WATTS BAR NUCLEAR PLANT B.1.j Nov. 2009 NRC Exam EVALUATOR INFORMATION SHEET Tools/Equipment/Procedures Tools/Egui pmentiProced ures Needed:
Hard Hat, Safety Glasses, Hearing Protection, Gloves and Plant Approved Shoes.
AOI-13, Appendix E latest revision.
SAFETY CONSIDERATIONS: .
Hot pipes, high noise, and heat.
The Electrical panel is designated as a Reactor Trip Hazard, so the examiner and the candidate must ensure that they do not violate the requirements for maintaining a safe distance from the panel while simulating switch manipulations.
NOTE: Start this JPM at the Rad Waste AUO desk.
P~aA P::lOP. 3 of 17
WATTS BAR NUCLEAR PLANT B.1.j Nov. 2009 NRC Exam READ TO APPLICANT DIRECTION APPLICANT:
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating/operating cues.
NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM. SIMULATE ALL MANIPULATIONS.
When you complete the task successfully, the objective for this job performance measure will be satisfied.
Ensure that you indicate to me when you fully understand your task.
INITIAL CONDITIONS:
- 1. Unit 1 has been manually tripped due loss of Intake Pumping Station.
- 2. The RCPs have been stopped and Diesel Generator EMERGENCY STOP push buttons have been depressed.
pushbuttons
- 1. You are an AUO assigned to the shift.
INITIATING CUES:
- 1. The Unit Operator (UO) has dispatched you to perform from AOI-13, Appendix E "Installation of Temporary Cooling to CCP 1A-A Oil Coolers." Cool~rs."
- 2. The Unit Operator has directed you to establish radio communications with the Main Control Room. You are to notify the UO when you have completed Appendix E for placing temporary cooling on CCP 1A-A.
P~ap. 4 of 17 Paoe
WATTS BAR NUCLEAR PLANT* PLANT B.1.i Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT START TIME: _ __
STEP 1: Obtain a copy of the procedure.
SAT STANDARD: A copy of AOI-13 Appendix E has been obtained.
EXAMINER'S CUE: After the applicant has identified the correct instruction, the evaluator provides a copy of the UNSAT instruction.
COMMENTS:
CAUTION This appendix should be completed as quickly as possible.
NOTE 1 If the accountability siren sounds, operator should continue performing this appendix. The SM should be aware of task assignments and personnel locations.
NOTE 2 Temporary cooling to CCP 1A-A oil coolers is accomplished by installing a fitting to a 1" tee in the CCS piping to the oil heat exchangers on the CCP pump skid (typically a C-zone area), and then connecting a hose from the nearest HPFP hose station to the fitting.
P::loe PFiOA 5 ()f of 17
WATTS BAR NUCLEAR PLANT B.1.i Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT NOTE: TO EVALUATOR: The following step requires the applicant to obtain the adapter.
There is also a pipe wrench and hose wrench tools that will be needed later in this task. The applicant may obtain these additional tools at this time.
Also note that these materials are stored in a gangbox labeled for "Radioactive Material Storage Area."
STEP 2: [1] OBTAIN adapter labeled "AOI-13 Appendix E" from CRITICAL gangbox [at east end of 0-L-2 near the Radwaste STEP Operator's desk on Elevation 692 of the Auxiliary Bldg.]
STANDARD: SAT Applicant obtains the adapter labeled "AOI-13 Appendix E". UNSAT This step is critical to provide adapter for HPFP fire hose.
COMMENTS:
STEP 3: [2] ENSURE 1-ISV-67-1016B, CCP OIL CLR ERCW SUP XTIE ISOL, CLOSED. [NE corner on pump -6' off SAT floor].
UNSAT STANDARD:
Applicant locates 1-ISV-67-1 016B and ensures valve is closed by trying to turn valve hand wheel clockwise.
CUE: After the applicant has demonstrated the method of ensuring the valve is closed, state that when valve hand wheel rotation was attempted in the clockwise direction, the hand wheel did not move.
COMMENTS:
P~aA P80A 6n of 17
WATTS BAR NUCLEAR PLANT B.1.i Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT NOTE: TO EVALUATOR: The following two steps require the applicant to obtain a ladder. After one is located, simulate its use (do not allow the EOP ladder seal to be broken.)
There are contaminated areas and catch basins in the pump room and appropriate radiological precautions taken for these areas as directed by RWP should be utilized.
There is an EOP ladder just outside the pump room door.
STEP 4: [3] CLOSE 1-THV-70-554A, CCP 1 A-A OIL COOLERS 1A-A CRITICAL OUTLET THROTTLE. [NE corner on pump -6' off STEP floor].
STANDARD: _ _SAT Applicant locates and closes 1-THV-70-554A by turning valve hand wheel UNSAT UNSAT clockwise.
Step is critical to ensure proper flow path to the drain dra-in which will be established later in the procedure.
CUE: After the applicant has demonstrated the method of closing, state that valve hand wheel travels several turns in the clock wise direction and stops.
COMMENTS:
P~m~ 7 PanA 7 of 17
WATTS BAR NUCLEAR PLANT B.1.i Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 5: [4] CLOSE 1-THV-70-553A, CCP 1A-A OIL COOLERS CRITICAL INLET ISOLATION. [North of pump -8' off floor]. STEP STANDARD:
SAT Applicant locates and closes 1-THV-70-553A by turning valve hand wheel clockwise. UNSAT Step is critical to ensure proper flow path to the oil cooler after HPFP is aligned later in the procedure.
CUE: After the applicant has demonstrated the method of closing, state that valve hand wheel travels several turns in the clock wise direction and stops.
COMMENTS:
P~nA PFIOP. A of 17 R
WATTS BAR NUCLEAR PLANT B.1.i Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT NOTE TO EVALUATOR: The hose station is located just outside the pump room door (south of door).
The hose retainer must be released and the entire hose played out. It must be routed so that there are no kinks and when charged will not impact instrument lines, gages, etc.
The pump room door will also need to be propped open.
STEP 6: [5] ROUTE hose from the nearest HPFP hose station to CRITICAL CCP 1A-A: STEP
.1-ISV-26-668
- 1-ISV-26-668 [near Waste Gas DecayTank Decay Tank Gallery] A3T, 692'] (Preferred)
- O-ISV-26-662 [near east side of Building Elevator, A8T, 692'] (Optional-Extra Hose Required) UNSAT STANDARD:
The applicant locates suitable HPFP hose station (1-ISV-62-668 (preferred)
(Next to Column A3T) and demonstrates how the hose will be routed from the hose station to CCP-1A-A pump room.
Step is critical to align a source of water from the HPFP header to the CCP 1A-A oil cooler.
CUE: When applicant locates a suitable fire hose station and demonstrates how the fire hose will be routed, state the fire hose had been routed as you have .stated.stated.
COMMENTS:
)
P;:WP. 9 Pane of 17
~ nf
WATTS BAR NUCLEAR PLANT B.1.i Nov. 2009 NRC Exam STEP/STANDARD SATIUNSAT SAT/UNSAT STEP 7: [6] ENSURE 1-ISV-70-800 CCP GEAR OIL CLR CCS CRITICAL INLET ISOLATION [SW corner of pump base] and -ISV- STEP 70-801, CCP 1A-A LUBE OIL CLR CCS INLET ISOLATION Valves [NWcorner of pump base],
CLOSED. SAT STANDARD: UNSAT Applicant locates and closes 1-ISV-70-800 and 1-ISV-70-801 by rotating respective hand wheels clockwise until valves are closed.
Step is critical to isolate cooler before removing pipe plug in the next step.
CUE: After the applicant has demonstrated the method of closing each valve, state that respective valve hand wheel travels several turns in the clock wise direction and stops.
COMMENTS:
PFloe P::lOP. 10 of 17
WATTS BAR NUCLEAR PLANT B.1.i Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT NOTE TO EVALUATOR: T NO'tE,'TO<EVALUATOR: The
. .*.*.*.h following
. .* *.*.e. . .*.* **.fo.,I
. . '.1. *.o.,.!.win.**.9.;.(S
..step
, __-<:',,/!/"L-,'
tep.*.*'.'re.
CI..\.I.i.*.'.*r*.e.S. u~e.*********O.f.
requires use of c[!p.'i.**.!pe.
,'-,',,)::f/j{j;i':,'" <,',.,', .,'<:,,
a pipe wrench
- '
- i< wre.***
' "', n.* .~. *. *.*.*h.'-Or
- ",'\>/<;,"
or .ai.iitab.
suitable ,. .~.1'.,.f~
,'_>C/,:;<:<:' ,:::'- _,;,>>;>!>::}~i;'"
substitute. If applicant has not stated hoV)l I4
((
how helsHe
- 2
he/she would obtain tool, the stated 0 //
actions provided by the cues cannot occur. !! : / /~ vIA / %/0 STEP 8: [7] REMOVE pipe plug from the threaded inlet on the 1" tee CRITICAL labeled "AOI-13 Appendix E" using pipe wrench STEP
[between 1-ISV-70-800 and 1-ISV-70-801], AND CONNECT adapter to the threaded inlet.
STANDARD: SAT Applicant removes pipe plug from threaded inlet on the 1" tee labeled "AOI- UNSAT 13 Appendix E" using pipe wrench in the counter clockwise direction. The applicant threads the adapter to the threaded inlet and tightens with pipe wrench turning in the clockwise direction until snug.
Step is critical to enable aligning HPFP to oil cooler.
CUE: After the applicant locates the 1" tee, and demonstrates how to remove the pipe plug with appropriate tools turning counter clockwise, then state that the stated action has occurred.
CUE: After the applicant demonstrates how the adapter will be installed on the 1" tee with clockwise rotation using proper tools, then state that the action has occurred.
COMMENTS:
P::loe PFlOA 11 of 17
WATTS BAR NUCLEAR PLANT B.1.i Nov. 2009 NRC Exam
') I STEP/STANDARD SAT/UNSAT NOTE TO EVALUATOR: The following step may require use of a hose wrench or suitable substitute.
The applicant may be able to tighten the fire hose to adapter sufficiently by hand.
Note: The hose nozzle must be removed before connecting to the adapter.
STEP 9: [8] CONNECT fire hose to the adapter threaded to the inlet CRITICAL on the 1" tee between 1-ISV-70-800 and 1-ISV-70-801. STEP STANDARD:
SAT Applicant connects fire hose to the adapter between 1-ISV-70-800 and 1-ISV-70-801 by twisting the adapter female collar onto the fire hose male UNSAT connection.
Step is critical to enable aligning HPFP to oil cooler.
CUE: After the applicant demonstrates how fire hose is installed on the adapter, then state that the action has occurred.
COMMENTS:
STEP 10: [9] CHECK all hose connections are complete and hose SAT not kinked.
STANDARD: UNSAT Applicant walks down and checks all hose connections complete and hose is not kinked.
CUE: When checked indicate that all connections are tight, and hose is laid out as stated.
COMMENTS:
)
P~aA P::IOA 12 of 17
WATTS BAR NUCLEAR PLANT B.1.i Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT NOTE TO . .I:VALyATO
~.9rE:!;t0.* EVALUATOR: The.* !e.nRVIf~riQ;~1:~pr*yr~~tJir~~1~f~ataiChicag()i:.~~?
R: *The following step requires that a Chicago drain plug be unlocked and r~~(>>){ed.
ut1,J<?c.ked,!.nd removed ~Ild ~.,!y'j r~CI!-li~e and may require u.~~ot use of ~u it~I?I~.~gse suitable to r9H~~iijra hose tp route drain water to
.. floar floor d ra i11: Ik"'~
drain. <i:;s;j;/iVJ(':1t.~ '?;.i%}~~. dB STEP 11: [10] ENSURE cap removed, THEN OPEN 1-DRV-70-782A, CRITICAL CCP 1 A-A OIL COOLER OUTLET DRAIN [NE corner of 1A-A STEP pump].
STANDARD: SAT Applicant locates and opens 1-DRV-70-782A by rotating valve hand wheel counter clock wise. UNSAT Step is critical to provide drain path of HPFP from oil cooler.
CUE: After the applicant has demonstrated the method of opening the valve, state that the valve hand wheel travels several turns in the counter-clockwise direction and then stops.
CUE: If asked, state that a little water drained and then stopped.
COMMENTS:
PAnFl PAOP. 1 ~ of 17 13
WATTS BAR NUCLEAR PLANT B.1.i Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 12: [11] ENSURE 1-ISV-70-800 and 1-ISV-70-801, CCP GEAR CRITICAL OIL CLR CCS INLET ISOLATION and CCP 1 A-A LUBE 1A-A STEP OIL CLR CCS INLET ISOLATION Valves, OPEN.
STANDARD: SAT Applicant locates and opens 1-ISV-70-800 and 1-ISV-70-801 by rotating respective hand wheels counter-clockwise until valves are open. UNSAT Step is critical to align cooling water flow from HPFP to oil cooler.
CUE: After the applicant has demonstrated the method of opening each valve, state that respective valve hand wheel travels several turns in the counter-clock wise direction and stops.
COMMENTS:
P~nA P;:Joe 14 of 17
WATTS BAR NUCLEAR PLANT B.1.i Nov. 2009 NRC Exam
\
STEP/STANDARD SATIUNSAT SAT/UNSAT STEP 13: [12] OPEN Hose Station Valve to provide HPFP to CCP 1A- CRITICAL A Oil Coolers. STEP STANDARD:
SAT Applicant slowly opens 1-ISV-26-668 to pressurize line and supply cooling water to oil cooler by operating the respective hose station hand wheel counter-clockwise until valve is fully open. UNSAT Step is critical to supply HPFP to oil cooler.
CUE: After the applicant demonstrates how to open the fire hose station valve, state that hand wheel rotates counter-clockwise several turns. If asked, state that the hose has become rigid, and if checked, state that flow was observed from drain (only if drain plug and drain valve in JPM Step 11 was performed satisfactorily).
COMMENTS:
STEP 14: [13] ,-NOTIFY NOTIFY UO that temporary cooling water connection to SAT CCP 1A-A is complete.
UNSAT STANDARD:
Applicant notifies the Unit Operator that temporary cooling water connection is complete.
CUE: When notified, role playas the Unit Operator Operator and acknowledge report using repeat back.
COMMENTS:
PFlOFl PFlOP. 1!1 ()f 15 af 17
WATTS BAR NUCLEAR PLANT B.1.i Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 15: [14] NOTIFY Fire Ops of the breach of CCP 1A-A pump SAT room door AND ADDRESS OR-14.B.1.b OR-14.8.1.b (Hourly Roving Fire Watch) and OR-14.6.1.
UNSAT STANDARD:
Applicant notifies fire OPS of the breach of the door, and the Unit Operator to address OR-14.B.1.b OR-14.8.1.b and OR-14.6.1.
CUE: When notified, role playas the Fire OPS and Unit Operator acknowledge request using repeat back.
COMMENTS:
STEP 16: [15] COORDINATE with Maintenance or Fire Ops to install SAT smoke removal fan to circulate air through CCP 1A-A 1A-A room. UNSAT STANDARD:
Applicant notifies Fire OPS or Maintenance to install smoke removal fan to circulate air in CCP 1A-A pump room.
CUE: When notified, role playas the Fire OPS or Maintenance acknowledge request using repeat back.
COMMENTS:
END OF TASK TIME STOP: _ __
P~aA 16 of 17 P::loe
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
DIRECTION TO TRAINEE:
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating/operating cues.
NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM. SIMULATE ALL MANIPULATIONS.
When you complete the task successfully, the objective for this job performance measure will be satisfied.
Ensure that you indicate to me when you fully understand your task.
INITIAL CONDITIONS:
- 2. Unit 1 has been manually tripped due loss of Intake Pumping Station.
- 3. The RCPs have been stopped and Diesel Generator EMERGENCY STOP pushbuttons push buttons have been depressed.
- 4. You are an AUO assigned to the shift.
INITIATING CUES:
- 1. The Unit Operator (UO) has dispatched you to perform from AOI-13, AOI*13, Appendix E "Installation of Temporary Cooling to CCP 1 1A*A Oil Coolers."
A-A
- 2. The Unit Operator has directed you to establish radio communications with the Main Control Room. You are to notify the UO when you have completed Appendix E for placing temporary cooling on CCP 1A-A. 1A*A.
AOI-13 WBN LOSS OF ESSENTIAL RAW COOLING WATER Revision 36 Page 67 of 70 Appendix E Page 1 of 3 Installation of TemporaryCooling Temporary Cooling (HPFP) to CCP 1A-A Oil Coolers CAUTION This appendix should be completed as quickly as possible.
NOTE 1 If the accountability siren sounds, operator should continue performing this appendix. The SM should be aware of task assignments and personnel locations.
NOTE 2 Temporary cooling to CCP 1A-A oil coolers is accomplished by installing a fitting to a 1" tee in the CCS piping to the oil heat exchangers on the CCP pump skid (typically a C-Zone area), and then connecting a hose from the nearest HPFP hose station to the fitting.
[1] OBTAIN adapter labeled "AOI-13 Appendix E" from gang-box [at east end of 0-L-2 near the Radwaste Operator's desk on Elevation 692 of the Auxiliary Bldg.] D
[2] ENSURE 1-ISV-67-1016B, CCP OIL CLR ERCW SUP XTIE ISOL, CLOSED
[NE corner on pump -6' off floor]. D
[3] CLOSE 1-THV-70-554A, CCP 1A-A OIL COOLERS CCS OUTLET THROTTLE.
[NE corner on pump -6' off floor]. D
[4] CLOSE 1-ISV-70-553A, CCP 1A-A OIL COOLERS CCS INLET ISOLATION.
[North of pump -8' off floor]. D
[5] ROUTE hose from the nearest HPFP hose station to CCP 1A-A.
- 1-ISV-26-668 [near Waste Gas Decay Tank Gallery, A3T, 692'] (Preferred) D
- 0-ISV-26-662 [near east side of Building Elevator, A8T, 692'] (Optional--
Extra Hose Required) D
[6] ENSURE 1-ISV-70-800, CCP 1A-A GEAR OIL CLR CCS INLET ISOLATION
[SW corner of pump base] and 1-ISV-70-801, CCP 1A-A LUBE OIL CLR CCS INLET ISOLATION [NW corner of pump base], CLOSED. D
AOI-13 WBN LOSS OF ESSENTIAL RAW COOLING WATER Revision 36 Page 68 6S of 70 Appendix E Page 2 of 3 NOTE 1 tee.
Performance of the following step may result in water drainage from the 1" II
[7] REMOVE plug from the threaded inlet on the 1" tee labeled "AOI-13 Appendix E" using pipe wrench [between 1-ISV-70-800 1-ISV-70-S00 and1-ISV-70-801],
and 1-ISV-70-S01], AND CONNECT adapter to the threaded inlet. o D
[8] CONNECT fire hose to the adapter threaded to the inlet on the 1" tee CONNECT between 1-ISV-70-800 1-ISV-70-S00 and 1-ISV-70-801.
1-ISV-70-S01. o D
[9] CHECK all hose connections are complete and hose not kinked. o D
[10] ENSURE cap removed, THEN OPEN~1-DRV-70-7S2A, CCP 1A-A OIL COOLERS CCS OUTLET OPEN-1-DRV-70-782A, DRAIN [NE corner of pump]. o D
[11] ENSURE 1-ISV-70-800 1-ISV-70-S00 and 1-ISV-70-801, 1-ISV-70-S01, CCP 1A-A GEAROIL CLR CCS INLET ISOLATION and CCP 1A-A LUBE OIL CLR CCS INLET ISOLATION Valves, OPEN. D 0
[12] OPEN Hose Station Valve to provide HPFP to CCP 1 1A-A A-A Oil Coolers. D 0
[13] NOTIFY UO that temporary cooling COOling water connection to CCP 1A-A is complete. D 0
[14] NOTIFY Fire Ops of the breach of CCP 1A-A pump room door D 0
AND OR-14.S.1.b(Hourly Roving Fire Watch) and OR-14.6.1.
ADDRESS OR-14.8.1.b D 0
[15] COORDINATE with Maintenance or Fire Ops to install smoke removal fan to circulate air through CCP 1A-A room. D 0
AOI-13 WBN LOSS OF ESSENTIAL RAW COOLING WATER Revision 36 Page 69 of70 Appendix E Page 3 of 3 Figure 1 CCP 1A-A Heat Exchanger and Piping Configuration 1-ISV-70-S01 1-ISV-70-S00 CCS Cooling Water Supply Piping CCS Supply to Gear CCS Supply to Lube Oil Cooler Oil Cooler Adapter to 1" tee (Adapter converts from 1" pipe thread to 1 1/2" fire hose thread)
From HPFP hose station 1-THV-70-554A CCS Cooling Water Discharge Piping Return flow from CCP Oil 1-DRV-70-7S2A Coolers
WATTS BAR NUCLEAR PLANT B.1.k Nov. 2009 NRC Exam B.1.k Alignment Upper Containment Monitor To The Lower Containment Locally PAGE 1 OF 14
WATTS BAR NUCLEAR PLANT B.1.k Nov. 2009 NRC Exam EVALUATION SHEET Task: Alignment Upper Containment Monitor To The Lower Containment Locally Alternate Path: N/A Facility JPM #: 3-0T-JPMA044 Safety Function: 7
Title:
Instrumentation KIA 073 K1.01 Knowledge of the physical connections and/or cause-effect relationships between the PRM system and the following systems:
Those systems served by PRMs.
Rating(s): 3.6/3.9 CFR: 41.2 to 41.9/45.7 to 45.8 Preferred Evaluation Location: Preferred Evaluation Method:
Simulator --'--
In-Plant x Perform -x- - -
X Simulate
References:
SOI-90.02 "Gaseous Process Radiation Monitors," Rev.46.
Task Number: AUO-090-S01-90.2-005
Title:
Task Standard: 1-RM-90-112 is located, and valves are aligned and 1-RM-90-112 is sampling the lower containment per SOI-90.02 Section 8.1.
Validation Time: minutes Time Critical: Yes - - No No -X- -
===============================================================
===============================================================
Applicant: Time Start:
NAME SSN Time Finish: -
Performance Rating: SAT UNSAT Performance Time Examiner: _ _ _ _ _ _ _=-___--'--__
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NAME SIGNATURE DATE
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COMMENTS PAGE 2 OF 14
WATTS BAR NUCLEAR PLANT B.1.k Nov. 2009 NRC Exam Tools/EquipmentlProceduresNeeded:
Tools/Equipment/Procedures Needed:
Hard Hat, Safety Glasses, Flashlight, Hearing Protection, Gloves and Plant Approved Shoes.
A copy of the latest revision of SOI-90.02.
ALARA considerations apply.
PAGE ~ OF 14
WATTS BAR NUCLEAR PLANT B.1.k Nov. 2009 NRC Exam DIRECTIONS TO APPLICANT DIRECTION TO APPLICANT:
I will explain the initial conditions, which step(s) to simulate or discuss, and provide initiating/operating cues.
NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM. SIMULATE ALL MANIPULATIONS.
When you complete the task successfully, the objective for this job performance measure will be satisfied.
Ensure that you indicate to me when you fully understand your task.
INITIAL CONDITIONS:
- 1. Unit 1 is at 10 % power following a startup.
- 2. 1-RM-90-106 "Lower Containment Air Monitor" and 1-RM-90-112 "Upper Containment Air Monitor" were aligned and were sampling their respective containments (normal alignment).
- 3. 1-RM-90-106 has tripped, neither sample pump could be restarted, and the monitor was shutdown per the appropriate procedure.
- 4. You are the Auxiliary Bldg AUO.
INITIATING CUES:
- 1. You have been directed by the OAC to align 1-RM-90-112 to sample lower containment.
- 2. You are to notify the MCR operator when you have completed this alignment.
PAGE 4 OF 14
WATTS BAR NUCLEAR PLANT B.1.k Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT START TIME: _ __
STEP 1: Obtain a copy of the appropriate instruction. SAT
~
STANDARD: A copy oJof SOI-90.02 Section 8.1 has been obtained. UNSAT
.-EXAMINER'S EXAMINER'S CUE: After the applicant identifies correct instruction, the evaluator can provide a copy of the instruction.
COMMENTS:
NOTE: If any Radiation Monitor experiences sufficient elevated reading above normal request MIG to perform purge.
NOTE: Chemistry should be notified to address compensatory measures for any radiation monitor required operable per Tech Specs/ODCM, which is being removed from service.
STEP 2: [Step 1] ENSURE Upper Containment Air Monitor Aligned SAT per Section 5.2.
UNSAT STANDARD: The applicant determines that Upper Containment Air Monitor is aligned normal per task assignment sheet.
CUE: 501-90.02 Section 5.2 has IF asked, state that Section SOI-90.02 been completed and the Upper Containment Monitor is sampling Upper Containment.
COMMENTS:
PAGE 5 OF 14
WATTS BAR NUCLEAR PLANT B.1.k Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 3: [Step 2] NOTIFY ChemChern lab of intent to realign monitors so SAT that proper sampling of Cntmt. and release permits are addressed. UNSAT STANDARD: The applicant notifies Chem Chern Lab of the intent to realign upper containment monitor to the lower containment.
CUE: Respond as ChemChern Lab, using repeat back to the notification .
notification.
COMMENTS:
NOTE:
If 1-RM-90-112 is aligned in place of 1-RM-90-106, it is inoperable until MIG completes PM 639W (1-LPR-090-0112A-B file 2), which recalibrates the monitor alarm setpoints.
STEP 4: [Step 3] NOTIFY MIG to perform PM 639W to align 1-RM- SAT 90-112 to lower containment.
UNSAT STANDARD: The applicant determines that lower containment air monitor has been shut down based on task assignment sheet.
CUE: Respond as the Operator at the Controls if contacted, .
using repeat back that MIG has performed PM 639W.
COMMENTS:
PAGE n 11 OF 14
WATTS BAR NUCLEAR PLANT B.1.k Nov. 2009 NRC Exam STEP/STANDARD SATIUNSAT SAT/UNSAT STEP 5: [Step 4] ENSURE 1-RE-90-106 1-RE-90-1 06 and 1-RE-90-112 pumps CRITICAL are OFF before aligning monitor. The following STEP handswitches control power to the sample pumps:
[A3U/737 on top of monitor enclosure]: SAT
- 1-HS-90-106A UNSAT
- 1-HS-90-106B
- 1-HS-90-112A
- 1-HS-90-112B STANDARD: The applicant locally checks 106 and 112 monitor sample pumps and turns off the running sample pump on the 112 monitor.
Step is critical prevent burn-up of sample pump during valve alignments to follow.
NOTE TO EVALUATOR: Underlined portion above is critical portion of this step.
CUE: IF asked and when checked, state the following for respective monitor:
- RM-106 sample pumps "off" green light is LIT and both handswitch stop push buttons are IN.
- RM-112, sample pump 112A in service red "on" light is LIT and sample pump 112B 1128 green "off" light is LIT.
- State sample pump for 112A green light is LIT when running pumps handswitch STOP pushbutton is depressed.
COMMENTS:
PAGE 7 OF 14
WATTS BAR NUCLEAR PLANT B.1.k Nov. 2009 NRC Exam STEP/STANDARD STEP/STANDARD SATIUNSAT SAT/UNSAT STEP 6: [Step 5] INITIAL the monitor sample pump STOPPED SAT (N/A pump NOT stopped):
UNSAT
[5.1] 1-HS-90-112A
[5.2] 1-HS-90-112B
, STANDARD: The applicant stops the sample pump with 1-HS-90-112A and records the pump that was stopped.
COMMENTS:
NOTE TO EVALUATOR: JPM steps 7, 8, and 9 are part of the same procedure step, and can be performed in any order.
STEP 7: [STEP 6] PERFORM THE FOLLOWING: CRITICAL STEP NOMENCLATURE LOCATION POSITION UNID LOWER CONTAINMENT SUP I A3U1737 A3U/737 OPEN 1-ISIV-90-112A TO 1-RE-90-112 CROSS TIE STANDARD: Applicant locates 1-ISIV-90-112A and rotates hand wheel SAT counter clockwise until valve is fully open.
monitor to lower Step is critical align to upper containment monitorto containment. UNSAT CUE: After applicant indicates how to open the valve, state that the valve handle rotated several turns in the counter clockwise direction and stopped.
COMMENTS:
PAGE A R OF 14
WATTS BAR NUCLEAR PLANT B.1.k Nov. 2009 NRC Exam STEP/STANDARD SATIUNSAT STEP 8: [STEP 6] PERFORM THE FOLLOWING: CRITICAL STEP NOMENCLATURE LOCATION POSITION UNID CNTMT TO RM-106 CIV-CVI O-M-12 CLOSED 1-HS-90-110 INSIDE CNTMT CNTMT TO RM-106 CIV-CVI O-M-12 CLOSED 1-HS-90-111 OUTSIDE CNTMT CNTMT TO RM-112 CIV-CVI O-M-12 CLOSED 1-HS-90-113 OUTSIDE CNTMT CNTMT TO RM-112 CIV-CVI O-M-12 CLOSED 1-HS-90-114 INSIDE CNTMT CNTMT TO RM-112 CIV-CVI O-M-12 CLOSED 1-HS-90-115 INSIDE CNTMT STANDARD: Applicant contacts the control room and has the above - SAT valves positioned to the CLOSED position. Valves90-113, 90-114,90-114! 90-115 are closed and verified closed by communication with the control room. Valves90-110 & & 111 are verified closed by communication with the control room. -
UNSAT Step is critical to ensure proper flow path from lower containment to the upper containment monitor.
NOTE TO EVALUATOR: Underlined portion above is the only portion that is critical. I CUE: Respond as the MCR when contacted, and state that 1-HS-90-110 & 111 hand switches were already closed, 1-HS-90-113, 114, &115 hand switches have been placed to the CLOSED position.
COMMENTS:
PAGE 9 OF 14
WATTS BAR NUCLEAR PLANT B.1.k Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT SATIUNSAT STEP 9: [STEP 6] PERFORM THE FOLLOWING: CRITICAL STEP NOMENCLATURE LOCATION POSITION UNID CNTMT TO RM-112 CIV-CVI 0-M-12 OPEN 1-HS-90-116 INSIDE CNTMT CIV-CVI CNTMT TO RM-112 CIV-CVII 0-M-12 OPEN 1-HS-90-117 OUTSIDE CNTMT CIV-CVI CNTMT TO RM-106 CIV-CVII 0-M-12 OPEN 1-HS-90-107 OUTSIDE CNTMT CIV-CVI CNTMT TO RM-106 CIV-CVII 0-M-12 OPEN 1-HS-90-108 INSIDE CNTMT CNTMT TO RM-106 CIV-CVII CIV-CVI 0-M-12 OPEN 1-HS-90-109 1-H S-90-1 09 INSIDE CNTMT STANDARD: Applicant contacts the control room and has the above SAT valves positioned to the OPEN position. Valves90-116, 90-117 are opened and verified open bycommunication with MCR. Valves90-107, 90-108, &
90-107,90-108, & 90-109 are verified open by communication with control room. UNSAT Step is critical to ensure proper flow path from lower containment to the upper containment monitor.
NOTE TO EVALUATOR: Underlined portion above is the only portion that is critical.
CUE: Respond as the MCR when contacted, that 1-HS 116 & 117 hand switches have been placed to the OPEN position.
CUE: Respond as the MCR when contacted, that 1-HS 107, 108, &109 hand switches were already in the OPEN position.
COMMENTS:
PAGE 10 OF 14
WATTS BAR NUCLEAR PLANT B.1.k Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 110:
0: [STEP 7] START the monitor sample pump STOPPED in CRITICAL Step 8.1 [4] (N/A pump NOT started): STEP
[7.1] 1-HS-90-112A SAT
[7.2] 1-HS-90-112B STANDARD: The applicant starts monitor sample pump using 1-HS UNSAT 112A.
Step is critical to establish flow from lower containment to the upper containment monitor.
CUE: When applicant indicated how pump is started and if asked, state sample pump for 112 red "on" light is LIT and green "off" light is OFF. Supply the following if/when asked:
1-FI-90-112A indicates 11:112 R$12 SCFM.
R$2.1 1-FI-90-112C indicates 11:1 2.1 SCFM.
1-PI-90-112B indicates 2" vacuum.
1-PI-90-112A indicates 4" vacuum.
Iodine Low Flow red alarm light is LIT.
COMMENTS:
PAGE 11 OF 14
WATTS BAR NUCLEAR PLANT B.1.k Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT SATIUNSAT STEP 11: [STEP 8] IF IODINE LOW FLOW ALARM on skid comes in, - SAT THEN RESET with 1-HS-90-112JB.
STANDARD: The applicant resets the iodine low flow alarm with 1-HS 112JB. -
UNSAT CUE: If asked and when checked, state that Iodine Low Flow red light is LIT.
CUE: If asked, state that light turns off when applicant operates 1-HS-90-112J8 to reset.
COMMENTS:
STEP 12: [STEP 9] PERFORM MONITOR SOURCE CHECK [O-M-12], - SAT and ENSURE 1-RM-90-112 (A, B & C) green OPERATE Lights LIT and red HIGH & yellow ALERT Lights NOT LIT.,
ENSURE ANN 173-A UPR CNTMT AIR 1-RM-112 RAD HI, NOT LIT. -
UNSAT ENSURE ANN 173-D UPR CNTMT AIR 1-RM-112 INSTR MALF, NOT LIT.
STANDARD: Applicant contacts the control room to have the 112 monitor source checked and verifies that green operate lights are LIT and High & Alert lights are NOT LIT and ANNs windows 173-A and 173-D are NOT LIT.
CUE: When contacted as the MCR, state that the monitor source check was successful and that green OPERATE light is LIT, that High & & Alert lights for monitor are NOT LIT and ANN windows 173-A & & 173-0 are NOT LIT.
COMMENTS:
PAGE 12 OF 14 PAGE120F14
WATTS BAR NUCLEAR PLANT B.1.k Nov. 2009 NRC Exam STEP/STANDARD SAT/UNSAT STEP 13: [STEP 10] ENSURE Local Panel Lights RESET - SAT STANDARD: The applicant verifies that Filter Failure light is NOT LIT, verifies that the Particulate LOW Flow Light is NOT LIT, - UNSAT and verifies that the Iodine LOW flow Light is NOT LIT.
CUE: If asked and when checked, state that Iodine Low Flow light is NOT LIT, that the Particulate Low flow light is NOT LIT, and that the Filter Fail light is NOT LIT.
COMMENTS:
STEP 14: Notify Operator At Controls that Upper Containment Monitor has been aligned to Lower Containment. - SAT STANDARD: The applicant contacts the control room and reports that the Upper Containment Monitor is aligned to Lower Containment. - UNSAT CUE: When notified, acknowledge the report using "repeat back."
COMMENTS:
END OF TASK ---- -------
STOP TIME _ __
PAGE 13 OF 14
APPLICANT CUE SHEET (RETURN TO EXAMINER UPON COMPLETION OF TASK)
DIRECTION TO APPLICANT:
I will explain the initial conditions, which step(s)to step(s) to simulate or discuss, and provide initiating/operating cues.
NO MANIPULATION OF PLANT EQUIPMENT SHALL OCCUR DURING THIS JPM. SIMULATE ALL MANIPULATIONS.
When you complete the task successfully, the objective for this job performance measure will be satisfied.
Ensure that you indicate to me when you fully understand your task.
INITIAL CONDITIONS:
- 1. Unit 1 is at 10 % power following a startup.
- 2. 1-RM-90-106 "Lower Containment Air Monitor" and 1-RM-90-112 "Upper Containment Air Monitor" were aligned and were sampling their respective containments (normal alignment).
- 3. 1-RM-90-106 has tripped, neither sample pump could be restarted, and monitor was shutdown per the appropriate procedure.
- 4. You are the Auxiliary Bldg AUO.
INITIATING CUES:
- 1. You have been directed by the OAC to align 1-RM-90-112 to sample lower containment.
2 2... You are to notify the MCR operator when you have completed this alignment.
WBN Gaseous Process 501-90.02 SOI-90.02 Unit 1 Rev. 0046 Radiation Monitors Page 61 of 84 Date___ __ __ INITIALS 8.0 INFREQUENT OPERATIONS NOTE request MIG If any Radiation Monitor experiences sufficient elevated reading above normal requesrMIG to perform purge.
8.1 Align Upper Containment Monitor to Lower Containment NOTE Chemistry should be notified to address compensatory measures for any radiation monitor required operable per Tech Specs/ODCM, which is being removed from service.
[1] ENSURE Upper Containment Air Monitor Aligned per Section 5.2.
[2] NOTIFY Chem lab of intent to realign monitors so that proper sampling of Cntmt. and release permits are addressed.
NOTE If 1-RM-90-112 is aligned in place of 1-RM-90-106, it is inoperable until MIG completes PM 639W (1-LPR-090-0112A-B file 2), which recalibrates the monitor alarm setpoints.
[3] NOTIFY MIG to perform PM 639W to align 1-RM-90-112 to lower containment.
WBN Gaseous Process 501-90.02 Unit 1 Rev. 0046 Radiation Monitors Page 62 of 84 Date- ----- - INITIALS 8.1 Align Upper Containment Monitor to Lower Containment (continued)
[4] ENSURE 1-RE-90-106 and 1-RE-90-112 pumps are OFF before aligning monitor. The following handswitches control power to the sample pumps:
[A3U/737 on top of monitor enclosure]:
- 1-HS-90-106A CV
- 1-HS-90-106B CV
- 1-HS-90-112A CV
- 1-HS-90-112B CV
[5] INITIAL the monitor sample pump STOPPED (N/A pump NOT stopped):
[5.1
[5.1)) 1-HS-90-112A
[5.2] 1-HS-90-112B
WBN Gaseous Process SOI-90.02 Unit 1 Rev. 0046 Radiation Monitors Page 63 of 84 Date~~~_
Date_---'-- INITIALS 8.1 Align Upper Containment Monitor to Lower Containment (continued)
[6] PERFORM the following:
P~RF Pl=RF VERIF NOMENCLATURE LOCATION POSITION UNID INITIAL INITIAL LOWER CONTAINMENT SUP A3U/737 A3U1737 OPEN 1-ISIV-90-112A 1-RE~90-112 TO 1-RE .90-112 CROSS TIE CV CNTMT TO RM-1 06 CIV-CVI 0-M-12 CLOSED 1-HS-90-110 INSIDE CNTMT CV CNTMTTO CNTMT TO RM-106 RM-1 06 CIV-CVI 0-M-12 CLOSED 1-HS-90-111 OUTSIDE CNTMT CV CNTMT CNTMTTO TO RM-112 CIV-CVI 0-M-12 CLOSED 1-HS-90-113 OUTSIDE CNTMT CV CNTMT CNTMTTO TO RM-112 CIV-CVI 0-M-12 CLOSED CLOSED* 1-HS-90-114 INSIDE CNTMT CV CNTMTTO CNTMT TO RM-112 CIV-CVI 0-M-12 CLOSED 1-HS-90-115 INSIDE CNTMT CV CNTMT CNTMTTO TO RM -112 CIV-CVI 0-M-12 OPEN 1-HS-90-116 INSIDE CNTMT CV CNTMT TO RM-112 CIV-CVI O-M-12 OPEN 1-HS-90-117 OUTSIDE CNTMT CV CNTMT TO RM-106 RM-1 06 CIV-CVI 0-M-12 OPEN 1-HS-90-107 OUTSIDE CNTMT CV CNTMTTO CNTMT TO RM-106 RM-1 06 CIV-CVI 0-M-12 OPEN 1-HS-90-108 INSIDE CNTMT CV CNTMT CNTMTTO TO RM-106 CIV-CVI 0-M-12 OPEN 1-HS-90-109 INSIDE CNTMT
- - - - - - - ---- ----------- - - - _.. _ - - - - - - - - _.. _ - - - - - L-.
CV
[7] START the monitor sample pump STOPPED in Step 8.1 [4]
(N/A pump NOT started):
[7.1] 1-HS-90-112A
[7.2] 1-HS-90-112B
[8] IF IODINE LOW FLOW ALARM on skid comes in, THEN RESET with 1-HS-90-112JB.
WBN Gaseous Process SOI-90.02 Unit 1 Rev. 0046 Radiation Monitors Page 64 of 84 Date INITIALS 8.1 Align Upper Containment Monitor to Lower Containment (continued)
[9] PERFORM Monitor Source Check [0-M-12], AND ENSURE 1-RM-90-112 (A,B&C) green OPERATE Lights LIT and red HIGH & yellow ALERT Lights NOT LIT.
CV ENSURE ANN 173-A UPR CNTMT AIR 1-RM-112 RAO HI, NOT LIT CV ENSURE ANN 173-0 UPR CNTMT AIR 1-RM-112 INSTR MALF, NOT LIT.
CV
[10] ENSURE Local Panel Lights RESET.
CV