ML030800523
| ML030800523 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 02/04/2003 |
| From: | Lanksbury R NRC/RGN-III |
| To: | Skolds J Exelon Generation Co, Exelon Nuclear |
| References | |
| 50-254/02-301, 50-265/02-301 | |
| Download: ML030800523 (190) | |
Text
INITIAL SUBMITTAL OF THE WALKTHROUGH JPMS FOR THE QUAD CITIES EXAMINATION - DEC 2002
ES-301 C6iiI6i RooiiiSVsteriis and Facility Walk-Through Test Outline Form ES-301-2 Facility: Quad Cities Date of Examination: 12-02-02 Exam Level (circle one): RO/SRO (I)
Operating Test Number: 1 B.1. Control Room Systems System / JPM Title Type Safety Code*
Function
- a. Reactor Building Ventilation / Bypass Reactor Building Ventilation D, S, L 9
Isolations. 288000 A2.01 3.3/3.4
- b.
RCIC / RCIC Manual Initiation (Hardcard) with a turbine trip and N, A, S, L 4
recovery.(Important PRA task) 217000 A2.02 3.8/3.7
- c. A.C. Electrical Distribution / Supply Bus 14-1 from Bus 24-1.
N, S, L 6
(Important PRA task SOER 83-6) 262001 A4.01 3.4/3.7
- d. Reactor Protection System / Perform a manual scram functional M, A, S 7
test with rod drifts requiring a reactor scram.
212000 A4.01 4.6/4.6
- e. Core Spray / Monthly Core Spray surveillance with failure of the D, A, S 2
minimum flow valve. 209001 A4.04 2.9/2.9
- f.
Containment / Vent primary Containment due to high H2 with a N, A, S, L 5
failure of the Torus 2" vent to open. 500000 EA1.03 3.4/3.2
- g. Main Steam / Pressurize main Steam Lines.
D, S, L 3
239001 A4.01 4.2/4.0 B.2 Facility Walk-Through
- a. Service Water / Align SSMP Room Cooler to Fire Header D, R, L 8
APE 295018 AA1.01 3.3/3.4
- b. Control Rod Hydraulic / Depressurize the Scram Air Header D, R 1
EPE 295037 EA1.05 3.9/4.0
- c. Residual Heat Removal Shutdown Cooling / Perform the Auxiliary D, L 4
Electric Room actions to start SDC.(Important PRA task)
APE 295021 A1.02 3.5/3.5
- Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol Io mU II, n
tOi iu cadIJ v,
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- __1021, Revision 8, Supplement 1 NRC COPY
- c. Residual Heat Removal Shutdown Cooling / Perform the Auxiliary D, L 4
Electric Room actions to start SDC.(Important PRA task)
APE 295021 AA1.02 3.5/3.5
- Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow Power, (R)CA 22 of 26 NifREG-102--
Re~ision 8, Supplement 1 NRC COPY
- 1 Facility: Quad Cities Date of Examination: 12-02-02 Exam Level (circle one): SRO (U)
Operating Test Number: 1 B.1 Control Room Systems System JPM Title Type Safety Code*
Function
- a.
- b.
C.
- d. Reactor Protection System / Perform a manual scram functional M, A, S 7
test with rod drifts requiring a reactor scram.
212000 A4.01 4.6/4.6
- e.
Containment / Vent primary Containment due to high H2 with a N, A, S, L 5
failure of the Torus 2" vent to open. 500000 EA1.03 3.4/3.2
- g.
Main Steam / Pressurize main Steam Lines.
D, S, L 3
239001 A4.01 4.2/4.0 B.2 Facility Walk-Through
- a. Service Water / Align SSMP Room Cooler to Fire Header D, R, L 8
APE 295018 AA1.01 3.3/3.4 b.
ExeId na Nuclear Nuclear Generation Group Job Performance Measure Bypass the Reactor Building Ventilation Isolation JPM Number: B.1.a.
Revision Number: 1 Date: 9/2002 Developed By:
Validated By:
Review By:
inst l/tor SME or Instructor O r,7 Rr Operations Representative K\\\\ V F>
'K 1 INRC 7
'p1" I
Date Date Da t//-7 Date
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B.l.a.
SIMULATOR SETUP INSTRUCTIONS
- 1. Reset the simulator to IC 94 (rst 94 from zip disk).
- 2. IC
Description:
Shutdown reactor following a scram.
NOTE:
It is okay to use a similar IC to the IC listed above, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.
- 3. Manual Actuation:
- Ensure that the QGA packet for QCOP 1600-17 is complete, including safety glasses, and in the drawer next to the ANSO desk.
- 4. Malfunctions:
- Insert a group II Isolation using malfunction RP07A & RP07B (imf rpO7a)&(imf rPO7b)
- 5. Remotes: NONE
- 6. Overrides: NONE
- 7. When the above steps are completed for this and other JPMs to be run concurrently, then validate the concurrently run JPMs using the JPM Validation Checklist.
- 8. This completes the setup for this JPM.
o/-7
.["C*
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B.l.a.
Revision Record (Summary)
Revision 0, Revision 1 This JPM is developed IAW guidelines established in NUREG 1021 Rev 8 ES-301 and Appendix C. This JPM meets the criteria of Category B. 1 "Control Room Systems," for RO/SRO candidates.
The JPM was revised to incorporate validation time and comments.
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lUlI Information For Evaluator's Use:
UNSAT requires written comments on respective step.
- Denotes CRITICAL steps.
Number any comments in the "Comment Number" column on the following pages. Then annotate that comment in the "Comments" section at the bottom of the page. The comment section should be used to document the reason that a step is marked as unsatisfactory and to document unsatisfactory performance relating to management expectations.
Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.
The timeclock starts when the candidate acknowledges the initiating cue.
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B.1.a.
INITIAL CONDITIONS A small leak inside the U-i Drywell has caused the pressure to increase to 3.5 psig.
All automatic functions occurred as expected.
The MSIV room temperature has increased to 164'F and the Unit Supervisor wants to restart the Reactor building ventilation per QGA 300.
This JPM is NOT time critical.
INITIATING CUE Bypass the Reactor building ventilation isolation on U-1 IAW QCOP 1600-17 Provide examinee with:
QGA support packet for QCOP 1600-17 when directed by cue.
Fill in the JPM Start Time when the student acknowledges the Initiating Cue.
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JPM Start Time:
PERFORMANCE I OBJECTIVE STANDARDS SAT UNSAT N/A EVALUA TOR: If this JPM is being simulated in the control room, DO NOTALLOW THE CANDIDATE TO OPEN THE JUMPER PACKET!
EVALUATOR: Disregard the above statement ifthe JPM is being performed in the simulator.
[CUE: Provide candidate with QGA support packet for QCOP 1600-17.
- F...
Install 901-15 panel
. Installs/verbalizes placing
[1
- F" "a" jumpers.
jumper between pts 49 & 50 L
on terminal board "B".
CUE: Ifjumper is not numbered, tell the candidate that the jumper number is # 22.
F.l.a.
Record jumper number.
Records jumper number &
[1
[]
[]
SI checks QCOP 1600-17 step S[
F.l.a.
La Evaluators Note: Verification steps may be performed when time permits and therefore are allowed to be performed out-of-sequence. If asked for verification, give a cue that the jumpers will be verified later.
I.........I--------
1 F 1 a.(1*
Verification.
Installation is verified.
[ J.
[]
[]
- Fib
[Install 901-15 panel
]Installs/verbalizes placing
[
[]
[]
jumpers.
jumper between pts. 38 & 39 I
on terminal board "E".
CUE: Ifjumper is not numbered, tell the candidate that the jumper number is # 23.
Fil~b.
Record jumper number.
i Records jumper number &
['
[]
[]
checks QCOP 1600-17 step i F.l.b.
F.1.b.(
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Ve..e r e r i.e.in ta la t o n,.......................................................
.[..[..]
F.
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(1)
Verification Verifier verifies installation.
[
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............. I....
........ I.
................... I.......
EVALUATOR: The candidate should inform you that the task is complete.
- CRITICAL STEP JPM Stop Time: -
35*
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Operator's Name:
Job
Title:
RO Q
Title:
Bypass the Reactor Building Ventilation Isolation JPM Number: B.1.a.
Revision Number:
1 Task Number and
Title:
SRN-1 600-P25 Given a reactor plant in a QGA situation, perform/simulate installing and removing one of the following sets ofjumpers in accordance with the indicated procedure.
K/A Number and Importance:
K/A:
288000 A2.01 Rating:
3.3/3.4 Suggested Testing Environment: Simulator Actual Testing Environment:
Testing Method: Il Simulate ID Perform Time Critical: Il Yes U No Estimated Time to Complete:
6 minutes Simulator Control Room
References:
QCOP 1600-17 Rev. 3 fl I A
N C
Faulted: U Yes Alternate Path: IJ Yes Actual Time Used:
Dl Plant 0 No M No minutes P7 I
B. l.a.
EVALUATION
SUMMARY
Were all the Critical Elements performed satisfactorily?
U Yes UJ No The operator's performance was evaluated against the standards contained in this JPM, and has been determined to be:
IJ Satisfactory L) Unsatisfactory Comments:
Evaluator's Name:
Evaluator's Signature:
(Print)
Date:
t NRC
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QCOP 1600-17 UNIT 1(2)
REVISION 3 BYPASSING GROUP II ISOLATION AND REACTOR BUILDING VENTILATION ISOLATION
___________r2 S
FT-OPERATIONS SUPVSR 1?3'?
APPROVAL SIGNATURE TITLE EFFECTIVE DATE A. PURPOSE The purpose of this procedure is to provide the necessary steps for jumpering out Containment and Reactor Building Ventilation Group II isolation signal.
B. DISCUSSION B.1.
The performance of this procedure will disable the auto-start of SBGT, allow manual startup of the Reactor Building Ventilation System and will permit the opening of the following valves:
- a.
- b.
- c.
- d.
- e.
- f.
- g.
- h.
- i.
- j.
AG
- k.
- 1.
AG
- m.
AO 1(2)-1601-23, 1(2)-1601-24, 1(2)-1601-60, 1(2)-1601-61, 1(2) -1601-62, 1(2)-1601-63, 1(2)-1601-21, 1(2)-1601-22, 1(2)-1601-55, 1(2) -1601-56, 1(2)-1601-57, 1(2)-1601-58, 1(2)-1601-59, DW VENT VLV.
VENT TO RX BLDG EXH SYS.
TORUS VENT VLV.
TORUS 2-INCH VENT RLF VLV.
VENT TO SBGTS.
N2 MAKEUP VLV.
TORUS MAKEUP VLV.
J NRC COPY
- Dtcument Retention:
N/A 1
Continuous Use
QCOP 1600-17 UNIT 1 (2)
REVISION 3 B.1.
(cont'd)
- n.
AO 1(2)-8801-A, 02 ANALY DW VLV.
- o.
AO 1(2)-8801-B, 02 ANALY DW VLV.
- p.
AO 1(2)-8801-C, 02 ANALY DW VLV.
- q.
AO 1(2)-8801-D, 02 ANALY TORUS VLV.
- r.
AO 1(2)-8802-A, 02 ANALY DW VLV.
- s.
AO 1(2)-8802-B, 02 ANALY DW VLV.
- t.
AO 1(2)-8802-C, 02 ANALY DW VLV.
- u.
AO 1(2)-8802-D, 02 ANALY TORUS VLV.
- v.
- w.
- x.
AO 1(2)-5741A, RX BLDG INLT DAMPER.
- y.
AO 1(2)-5741B, RX BLDG INLT DAMPER.
- z.
AO 1(2)-5742A, RX BLDG OUTLT DAMPER.
aa.
AO 1(2)-5742B, RX BLDG OUTLT DAMPER.
B.2.
Step completion shall be documented by entering either
- initials, data, OR NA if stated conditions do NOT apply.'
B.3.
Verification steps within this procedure may be performed when time permits and therefore are allowed to be performed out-of-sequence.
C. PREREQUISITES C.l.
QGA's OR SAMG's have directed use of this procedure.
C.2.
Obtain equipment packet from QGA equipment storage drawer.
D. PRECAUTIONS D.l.
Exercise caution when installing jumpers due to possible energized circuits.
NRC COPY
- 1
QCOP 1600-17 UNIT 1 (2)
REVISION 3 E. LIMITATIONS AI~JD ACTIONS None.
F. PROCEDURE
NOTE The following jumpers will maintain relays 595-133 and 595-134 energized and bypass Group 2 Isolation of valves to Reactor Building Ventilation, Drywell, Torus, and Oxygen Analyzers.
JUMPER NO.
INIT F.1.
Install jumpers in Panel 901 (2)-15:
- a.
Jumper on terminal board "B" between terminal 49 AND 50.
J.
(1)
Verification:
- b.
Jumper on terminal board "E" between terminal 38 AND 39.
/
(1) Verification:
F.2.
WHEN removal of the jumpers are required, THEN:
- a.
Remove the following jumpers in Panel 901(2)-15:
(1) Jumper on terminal board "B" between terminal 49 AND 50.
(a)
Verification:
(2)
Jumper on terminal board "E" between terminal 38 AND 39.
(a)
Verification:
F.3.
Place this procedure in the Active Jumper and Block Installation Record as a record of jumper installation.
NRC COPY
- 1
QCOP 1600-17 UNIT 1 (2)
REVISION 3 G. ATTACHMENTS None.
H. REFERENCES H.1.
Technical Specifications:
None.
H..2.
None.
H. 3.
Drawings:
- a.
4E-1509A Sh 2 (4E-2509A Sh 2),
Schematic P.C.I. System Atmospheric Control System
- b.
4E-1509B Sh 1 (4E-2509B Sh 1), Schematic P.C.I. System Atmospheric Control System H.4.
Manuals:
None.
H.5.
Procedures:
None.
Diagram Inboard.
Diagram Outboard.
H.6.
UFSAR:
None.
H. 7.
Commitments:
None.
H. 8.
Others:
- a.
BWR Owners Group Emergency Procedure and Severe Accident Guideline.
- b.
QCPWG (Procedure Writers Guide),
Vol.
- 3.
N RC QQR)Y- #1
B.1.a.
INITIAL CONDITIONS (Student Copy)
A small leak inside the U-1 Drywell has caused the pressure to increase to 3.5 psig.
All automatic functions occurred as expected.
The MSIV room temperature has increased to 164°F and the Unit Supervisor wants to restart the Reactor building ventilation per QGA 300.
This JPM is NOT time critical.
INITIATING CUE Bypass the Reactor building ventilation isolation on U-1 IAW QCOP 1600-17 i
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Nuclear
- 1 Nuclear Generation Group Job Performance Measure RCIC Manual Initiation (Hardcard) with a Turbine Trip JPM Number: B.1.b.
Revision Number:
I Date: 9/2002 Developed By:
Validated By:
Instrtu ctor SME or Instructor Date Da t,'!e Date Review By:
Operations Representative LI
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B. L.b.
SIMULATOR SETUP INSTRUCTIONS
- 1. Reset the simulator to IC 94 (rst 94).
- 2. IC
Description:
Reactor stable after scram.
- 3. Manual Actuation:
0 Ensure that the RCIC system is in its normal standby lineup.
- 4. Malfunctions:
Simulate failure of the RCIC exhaust check valve to open by closing the exhaust line manual isolation valve using remote function (mrf rcO4r close)
When prompted by the evaluator, reopen the valve using (mrf rcO4r open) and give the report that the check valve appeared to be stuck closed but you have cycled it manually and it now is free to move. No damage and everything is satisfactory in the RCIC room.
When prompted by the evaluator, give report as NLO dispatched to RCIC room to verify the rupture diaphragm intact, report diaphragm is intact and all looks normal and satisfactory.
- 5. Remotes: NONE
- 6. Overrides: NONE
- 7. When the above steps are completed for this and other JPMs to be run concurrently, then validate the concurrently run JPMs using the JPM Validation Checklist.
- 8. This completes the setup for this JPM.
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B.l.b.
Revision Record (Summary)
Revision 0, This JPM is developed IAW guidelines established in NUREG 1021 Rev 8 ES-301 and Appendix C. This JPM meets the criteria of Category B.1 "Control Room Systems," for RO/SRO candidates.
Revision 1 The JPM was revised to incorporate validation time and comments.
ii all a a 0 0 11 0 0.
0m ll
.IN l0 0 0 a 1
- 0.
IN au a.
II 0
a.l Information For Evaluator's Use:
UNSAT requires written comments on respective step.
- Denotes CRITICAL steps.
Number any comments in the "Comment Number" column on the following pages. Then annotate that comment in the "Comments" section at the bottom of the page. The comment section should be used to document the reason that a step is marked as unsatisfactory and to document unsatisfactory performance relating to management expectations.
Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.
The timeclock starts when the candidate acknowledges the initiating cue.
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B.L.b.
INITIAL CONDITIONS
"* A loss of feedwater has resulted in a reactor scram and entry into QGA 100.
"* The Unit Supervisor has decided that RCIC should be used to restore reactor water level.
"* Hardcard use has been authorized by the Unit Supervisor.
"* RCIC is in its normal standby lineup.
"* This JPM is not time critical INITIATING CUE Manually initiate Unit 1 RCIC using the hardcard and inject into the reactor vessel.
Fill in the JPM Start Time when the student acknowledges the Initiating Cue.
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B.1.b.
INITIAL CONDITIONS (Student Copy)
"* A loss of feedwater has resulted in a reactor scram and entry into QGA 100.
"* The Unit Supervisor has decided that RCIC should be used to restore reactor water level.
"* Hardcard use has been authorized by the Unit Supervisor.
"* RCIC is in its normal standby lineup.
"* This JPM is not time critical INITIATING CUE Manually initiate Unit 1 RCIC using the hardcard and inject into the reactor vessel.
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JPM Start Time:
PERFORMANCE OBJECTIVE STANDARDS SAT UNSAT N/A Obtain hardcard for RCIC Obtains hardcard for RCIC MANUAL
[]
[]
[]
MANUAL STARTUP from STARTUP from the 901-4 panel.
the 901-4 panel.
Hardcard Manually initiates RCIC Depresses and holds the RCIC MAN
[]
[]
[]
step 1 using the manual initiation INITIATION pushbutton on the 901-4 pushbutton.
Verifies the system lines up to Using indications on the 901-4 panel
[]
[3
[I]
- inject, verifies system valves are lining up for injection.
Identifies turbine trip on Identifies turbine trip by alarm 901-4 D-15
[3
[3
[3 high exhaust pressure.
and cause is due to high exhaust pressure by alarm 901-4 C-14.,
901-4 Verifies the automatic Verifies that the MO 1-1301-60 MIN FLOW
[]
[3
[]
C-14 actions occurred.
VLV and the MO 1-1301-STM TO TURB step B. 1.
VLV are closed
"*901-4 Verifies steam exhaust check Verifies 1-1301-64 RCIC TURB EXH STOP
[3
[]
[]
"C-14 valve open by dispatching CK VLV is open by dispatching NLO to step B.2.
operator to RCIC room.
RCIC room.
901-4 Determines if high torus Determines that a high torus pressure does
[]
[]
[]
C-14 pressure exists.
not exist as indicated on 1-1602-1 TORUS step B.3.
PRESS.
901-4 Determines if the exhaust Determines that the exhaust diaphragm has
[1
[3
[]
not ruptured by:
step B.4.
Absence of alarm 901-4 A-16 RCIC room temp normal on 901-21 RCIC room rads normal on 901-02 t"/-
1( (/7)
Dispatches NLO to RCIC room to verit, that rupture diaphragm is intact.
Evaluator Note: Promp t mulator operator to provide cue from previously dispatched (step 901-4 G Evalato Note:
901-4 C 14 B.2.) operator sent to inspect the exhaust line stop-check valve, that he found it stuck, but manually cycled it and it is now free to move. No damage, everything is sat.
Also have Simulator Operator provide cue as the NLO sent to inspect the rupture diaphragm (step 901-4 C-14 B.4.) that everything appears normal in the RCIC room and that the rupture diaphragm is intact.
In the next step, if the candidate seeks input from US, provide cue that condition has been corrected and RCIC operation is required.
B.1.b.
PERFORMANCE OBJECTIVE STANDARDS SAT UNSAT N/A 901-4 Determines cause of high Determines cause of high exhaust pressure
[1
[]
[]
C-14 exhaust pressure has been has been corrected and RCIC IS required step B.5.
corrected and RCIC IS for operation. Starts turbine trip recovery required for operation.
IAW QCOA 1300-01.
Starts turbine trip recovery IAW QCOA 1300-01.
QCOA Verifies automatic actions Previously done in step B.1.of 901-4C-14
[]
[]
[]
1300-01 occurred.
step D. 1.
QCOA Determines if a trip or Previously determined by 901-4 C-14 and
[]
[]
[]
1300-01 isolation occurred.
operator reports from the field.
step D.2.
Evaluator Note: In the next step, the candidate may ask US if initiation signal should be reset to prevent system from autostarting following reset of the turbine trip.
Provide cue that it is NOT desired to clear the initiation signal and reiterate need for RCIC injection.
QCOA Determines that initiation Determines that initiation signal is not
[]
[]
[]
1300-01 signal has not cleared, cleared by alarm 901-4 D-16.
.. step D.4.
- QCOA Resets the turbine trip.
Verifies high exhaust pressure trip signal
[]
[]
[]
1300-01 clear, by absence of alarm 901-4 C-14, and step resets turbine trip by depressing TURB D.7.b.
RESET pushbutton.
QCOA Restarts RCIC for injection Determines turbine trip is reset by absence
[]
[]
[]
1300-01 IAW QCOP 1300-02 Hard of any alarms, and that RCIC is required step D.9.
Card.
for operation. References Hard card to restart system.
Manually initiates RCIC Depresses and holds the RCIC MAN
[3
[]
[]
Hardcard using the manual initiation INITIATION pushbutton on the 901-4 step 1 pushbutton.
Verifies the system lines up to Using indications on the 901-4 panel
[1
[]
[ ]
- inject, verifies system valves reposition and system is injecting at -400 gpm.
EVALUATOR: The candidate should inform you that the task is complete.
JPM Stop Time:
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B.l.b.
Operator's Name:
Job
Title:
RO 1:
SRO 1:
Title:
RCIC Manual Initiation (Hardcard) with a Turbine Trip JPM Number: B.l.b.
Revision Number:
1 Task Number and
Title:
SR-1300-PO 1, Given a reactor plant in an accident condition where RCIC fails to autostart and/or fails to start with the auto pushbutton, start RCIC for injection in accordance with QCOP-1 300-02. (Important PRA Operator Action - starting RCIC terminates 13 of the top 200 Core Damage Sequences)
K/A Number and Importance:
K/A: 217000 A2.02 Rating: 3.8/3.7 Suggested Testing Environment: Simulator Actual Testing Environment:
Testing Method:
1I Simulate Q2 Perform Time Critical: Q Yes U No Estimated Time to Complete:
30 minutes
References:
Simulator Control Room QCOP 1300-02, Rev. 22 QCOA 1300-01 Rev 11 QCAN 901-4 C-14 Rev 1 QCAN 901-4 D-15 Rev 4 QCAN 901-4 D-16 Rev 6 QCAN 901-4 E-16 Rev 0
</
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0z' Faulted: El Yes Alternate Path: E Yes L)
Plant 0
No O No Actual Time Used:
minutes i7 i7 I,--.-,r, 1
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7'. M r
- 1 I
B.l.b.
EVALUATION
SUMMARY
Were all the Critical Elements performed satisfactorily?
U Yes L)
No The operator's performance was evaluated against the standards contained in this JPM, and has been determined to be:
Q Satisfactory Q Unsatisfactory Comments:
Evaluator's Name:
Evaluator's Signature:
(Print)
Date:
1/
/ /
K K Li
'
NXPC
~L-1T L ij i -7
QCAN 901(2)-4 D-15 UNIT 1(2)
REVISION 4 Continuous Use DESCRIPTION SETPOINT Actual:
- 1. Low RCIC Pump suction pressure; 15" Hg vacuum.
- 2.
High RCIC Turbine exhaust pressure; 25 psig.
- 3.
Automatic RCIC Isolation.
- 4.
Remote manual trip pushbutton depressed.
RCIC TURBINE TRIP Tech Specs:
None SENSOR
- 1.
- 2.
- 3.
- 4.
- 5.
6.
PS 1(2)-1360-21-1 PS 1(2)-1360-26A/B PS 1(2)-1360-9A/B/C/D DPIS 1(2)-1360-lA/lB TS 1(2)-I360-14A/B/C/D Remote Pushbutton Trip 13A-S17.
A.
AUTOMATIC ACTIONS
- 1.
RCIC Trip
- a.
MO 1(2)-1301-60, MIN FLOW VLV closes.
- b.
MO 1(2)-1301-61, STM TO TURB VLV closes.
- 2.
IF turbine trip was caused by RCIC Isolation
- signal, THEN MO 1(2)-1301-16, STM SPLY ISOL VLV and MO 1(2)-1301-17, STM SPLY ISOL VLV, will BOTH close.
B.
OPERATOR ACTION
- 1.
IF RCIC Turbine Trip was caused by a turbine trip signal AND is required for operation, THEN perform QCOA 1300-01.
- 2.
IF RCIC Turbine Trip was caused by a manual trip AND is NO longer required for operation, THEN perform QCOP 1300-05.
Nc
.cbpy
- 1
QCAN 901(2)-4 D-15 UNIT 1(2)
REVISION 4 C.
PROBABLE CAUSES
- 1.
Low CCST or Torus level.
- 2.
RCIC Pump suction valve out of position.
- 3.
High Torus Pressure.
- 4.
Restriction in RCIC Turbine exhaust line.
- 5.
Automatic RCIC Isolation.
D.
REFERENCES
- 1.
TS Section 3.5.3, RCIC System.
- 2.
M-50 (M89),
Diagram of RCIC Piping.
- 3.
(4E-2484A(B)),
Schematic Diag RCIC System Part 2, Unit 1 (Unit 2).
- 4.
Schematic Diagram Main Control Rm. Annun.
Pnl.
901-4 Pt.
3 of 4, (Window 94).
- 5.
C00396, Equipment Manual Reactor Core Isolation Cooling System (GEK-9546).
- 6.
QCOA 1300-01, RCIC Turbine Trip/Isolation Recovery.
- 7.
QCOP 1300-05, RCIC System Shutdown.
- 8.
QCPWG (Procedure Writers Guide),
Vol 3.
- 9.
Quad Cities Kardex File.
(final)
NRC COPY
- 1
QCAN 901(2)-4 C-14 UNIT 1(2)
REVISION 1 SAFETY RELATED V*M.4 SIJIGwA 1%08t&V 7**,r.
-) 7 -'?/
APPRO URE TITLE C EFFECTIVE DATE DESCRIPTION HIGH RCIC TURBINE EXHAUST DISCHARGE PRESSURE Actual:
?ch Specs:
- 1. High RCIC Turbine exhaust pressure; 25 psig.
None RCIC TURBINE EXHAUST DISCH HIGH PRESSURE
- 1. PS l(2)-1360-26A/B I
WARNING High RCIC Turbine exhaust pressure could cause a rupture of the RCIC Turbine exhaust diphragm resulting in radioactive steam leaks within RCIC area. Caution must be used in entering these areas to prevent personnel injury or excess exposure.
the A.
AUTOMATIC ACTIONS
- 1.
- a.
MO 1(2)-1301-60, MIN FLOW VLV closes.
- b.
MO 1(2)-1301-61, STM TO TURB VLV closes.
B.
OPERATOR ACTION
- 1.
Verify the above AUTOMATIC ACTIONS occurred.
- 2.
Verify 1(2)-1301-64, U-1(2) RCIC TURB EXH STOP CK VLV, (located high up on wall between RCIC Room and Torus on RCIC steam exhaust discharge piping) is open.
2126a
-I NRC COPY
- 1 SETPOINT SENSOR
QCAN 901(2)-4 C-14 UNIT 1(2)
REVISION 1
- 3.
IF high Torus pressure exists, as indicated on 1(2)-1602-1 TORUS
- PRESS, THEN refer to applicable QGA procedure.
j
- 4.
Determine if a rupture of the exhaust diaphragm has occurred as follows:
- a.
IF Alarm 901(2)-4 A-16, RCIC TURBINE EXH DIAPHRAGM HIGH PRESSURE is lit, this is indicative of a possible ruptured exhaust diaphragm.
- b.
Monitor RCIC Room area temperatures on Panel 901(2)-21.
C.
Check area radiological conditions on Panel 901(2)-02.
- d.
Dispatch an operator to inspect exhaust diaphragm.
- 5.
IF the cause of high exhaust discharge pressure has been corrected, AND RCIC System is required for operation, THEN perform RCIC Turbine trip recovery per QCOA 1300-1.
- 6.
IF the cause of high exhaust discharge pressure has been corrected, AND RCIC System is.
NOT required for operation, THEN place RCIC System into Standby Operation per QCOP 1300-1.
- 7.
IFFRCIC is inoperable, THEN perform QCOS 1300-2.
C.
PROBABLE CAUSES
- 1.
High Torus Pressure.
- 2.
Restriction in the RCIC Turbine exhaust line leading to the Torus.
D.
REFERENCES
- 1.
M-50 (M89),
Diagram of RCIC Piping.
- 2.
Schematic Diag RCIC System Part 3, Unit 1(2).
- 3.
4E-1575AM Pt. 3 of 6 (4E-2575AR)
Pt. 4 of 9, Schematic Diagram Control Room Annun. Pnl. 90](2)-4 (Window 91).
- 4.
QCOA 1300-1, RCIC Turbine Trip/Isolation Recovery.
- 5.
QCOS 1300-2, RCIC Outage Report.
- 6.
QCNPS Procedure Writers Guide, Rev.
1, January 31, 1990.
- 7.
Quad Cities Kardex File.
(final) 2126a
-2 NRC COPY
- 1
QCOA 1300-01 UNIT 1 (2)
REVISION 11 Continuous Use RCIC TURBINE TRIP/ISOLATION RECOVERY A.
SYMPTOMS
- 1.
Possible RCIC trouble alarms:
- a.
Panel 901(2)-4:
(1)
D-15, RCIC TURBINE TRIP.
(2)
G-15, RCIC TRIP THROTTLE VALVE CLOSED.
(3)
B-14, RCIC PUMP LOW SUCTION PRESSURE.
(4)
C-14, RCIC TURBINE EXHAUST DISCH HIGH PRESSURE.
(5)
(6)
B-15, RCIC STEAM LINE ISOLATION.
(7)
A-15, RCIC STEAM LINE HIGH DP.
- 2.
Possible RCIC System trouble:
- a.
RCIC Turbine speed low or decreasing.
- b.
FIC 1(2)-1340-1, RCIC FLOW CONTROLLER, decreasing flow.
- c.
GOVERNOR VLV AND/OR TRIP THROTTLE VLV closed.
- d.
MO 1(2)-1301-16 and MO 1(2)-1301-17, STM SUPLY ISOL VLV, closed.
- e.
Failure to maintain Reactor water level.
B.
AUTOMATIC ACTIONS
- 1.
IF RCIC Turbine trip is caused by Turbine overspeed, THEN RCIC TRIP THROTTLE VLV will close.
- 2.
IF RCIC Turbine trip is NOT caused by Turbine overspeed, THEN MO 1(2)-1301-60, MIN FLOW VLV, and MO 1(2)-1301-61, STM TO TURD VLV, will BOTH close.
- 3.
IF RCIC System isolation
- occurs, THEN the following valves will close:
- a.
MO 1(2)-1301-16, STM SUPLY ISOL VLV.
"b.
MO I(2)-1301-17, STM SUPLY ISOL VLV.
NRC COPY
- 1
QCOA 1300-01 UNIT 1 (2)
REVISION 11
[]
NOTE The following two valves close due to Turbine trip logic.
- c.
MO 1(2)-1301-60, MIN FLOW VLV.
- d.
MO 1(2)-1301-61, STM TO TURB VLV.
C.
IMMEDIATE OPERATOR ACTIONS
- 1.
None.
D.
SUBSEQUENT OPERATOR ACTIONS
- 1.
Verify the above AUTOMATIC ACTIONS occurred.
- 2.
Determine if a
trip or isolation occurred by checking position of MO 1(2)-1301-16 and MO 1(2)-1301-17, STM SUPLY ISOL VLV, open or closed:
- a.
IF MO 1(2)-1301-16 and MO 1(2)-1301-17, STM SUPLY ISOL VLVS, are
- open, THEN perform the following to determine which RCIC Turbine trip has occurred:
(1)
Verify Reactor water level.
IF level for Unit 1 greater than or equal to 54.23 inches or for Unit 2 greater than or equal to 50.34
- inches, THEN cause of trip is Reactor high water level.
(2)
Verify position of TRIP THROTTLE VLV.
IF
- closed, THEN trip caused by Turbine overspeed.
(3)
IF alarm B-14, RCIC PUMP LOW SUCTION PRESSURE is
- lit, THEN trip caused by RCIC Pump low suction.
(4)
IF alarm C-14, RCIC TURBINE EXHAUST DISCH HIGH PRESSURE is
- lit, THEN cause of trip is high Turbine exhaust pressure.
- b.
IF MO 1(2)-1301-16 and MO 1(2)-1301-17 STM SUPLY ISOL VLV are
- closed, THEN a RCIC isolation has occurred.
NRC.COPY
- 1
QCOA 1300-01 UNIT 1 (2)
REVISION 11 CAUTION IF RCIC Turbine trip due to high
- level, THEN RCIC will auto restart on Reactor low low water level initiation signal.
- 3.
IF RCIC Turbine trip was caused by Reactor high water level trip signal OR manual shutdown, THEN NO action is required to reset the trip signal.
- 4.
IF RCIC initiation signal is
- cleared, THEN depress INITIATION SIGNAL SEAL-IN AND RESET.
CAUTION IF RCIC automatic initiation is still
- present, THEN when RCIC isolation and/or Turbine trip is reset RCIC will automatically restart.
Water hammer may occur during auto-start after the isolation is reset.
- 5.
IF the RCIC Turbine trip was due to a mechanical overspeed
- trip, THEN perform the following locally at the RCIC Turbine:
(F-18)
- a.
IF RCIC initiation signal seal-in was reset, THEN close MO 1(2)-1301-61, STM TO TURB VLV.
(1)
Verify closed MO 1(2)-1301-60, MIN FLOW VLV.
- b.
Remove lockwire and manually close TRIP THROTTLE VLV.
- c.
Reset mechanical trip mechanism by pulling trip linkage connecting the TRIP THROTTLE VLV and the trip mechanism on the outboard bearing towards the TRIP THROTTLE VLV.
- d.
Slowly open (manually) the TRIP THROTTLE VLV.
- e.
Lockwire open TRIP THROTTLE VLV handwheel to prevent inadvertent manual closing of valve.
NRC COPY
- 1
QCOA 1300-01 UNIT 1 (2)
REVISION 11
- 6.
IF trip was due to a RCIC low suction pressure, THEN check or align RCIC suction valve from CCST OR Torus as follows:
NOTE IF either MO 1(2)-1301-25, TORUS PUMP SUCT VLV, OR MO 1(2)-1301-26, TORUS PUMP SUCT VLV,
- opens, THEN MO 1(2)-1301-53, CCST TEST BYP, will automatically close.
- a.
IF Torus level reaches
+5 inches (AV 15 ft 11.25 inches)
OR CCST level drops below 0.7 feet (AV
Ž 598 ft 1
inch),
THEN; (1)
Verify open MO 1(2)-1301-25, TORUS PMP SUCT VLV.
(2)
Verify open MO 1(2)-1301-26, TORUS PMP SUCT VLV.
(3)
Verify close MO 1(2)-1301-22, CCST PUMP SUCT VLV.
(4)
IF time permits, THEN perform RCIC fill and vent per QCOP 1300-01.
(5)
Verify all Turbine trip alarms are clear.
(6)
Depress TURB RESET.
- b.
IF Torus level reaches
+5 inches (AV 15 ft 11.25 inches)
AND CCST level drops below 0.7 feet (AV
Ž 598 ft 1 inch),
THEN; (1)
Close MO 1(2)-1301-26, TORUS PMP SUCT VLV.
(2)
Close MO 1(2)-1301-25, TORUS PMP SUCT VLV.
(3)
Open MO 1(2)-1301-22, CCST PUMP SUCT VLV.
(4)
Verify all Turbine trip alarms are clear.
(5)
Depress TURB RESET.
- 7.
IF trip was due to a RCIC Turbine exhaust discharge high
- pressure, THEN:
- a.
IF high Torus pressure exist as indicated on 1(2)-1602-1 TORUS PRESS, THEN refer to applicable QGA procedure.
NRC CQPY
- 1
QCOA 1300-01 UNIT 1 (2)
REVISION 11
- b.
WHEN RCIC high exhaust pressure trip signal is
- clear, THEN depress TURB RESET.
- 8.
IF RCIC Turbine trip was due to a RCIC isolation, THEN:
- a.
IF equal to or less than 54 psig Reactor pressure as indicated on 1(2)-640-25A/B, 1(2)-A/B RX PRESS, THEN NO action is required as this is an expected isolation of RCIC System.
CAUTION Radiological procedures should be followed for entry into the RCIC Room due to the possibility of a
steam line break.
- b.
IF high steam flow as indicated by alarm A-15, RCIC STEAMLINE HIGH DP on Panel 901(2)-4, THEN direct an Operator to check room status (room temperature and steamline
- breaks, etc.)
prior to unisolating RCIC System.
- c.
IF high area temperature as indicated by alarm H-2, AREA HI TEMP STEAM LEAK DETECTION, on Panel 901(2)-3 AND confirmed by one of the alarms on 901(2)-21, THEN direct an Operator to check room status (cooler operating, room temperature, etc.)
prior to unisolating RCIC System.
- d.
WHEN it has been determined that RCIC System is to be unisolated, THEN:
(1)
Verify all RCIC isolation and Turbine trip signal(s) are cleared.
CAUTION IF RCIC automatic initiation is
- present, THEN, when RCIC isolation is
- reset, RCIC will auto-restart.
Water hammer may occur.
(2)
Depress STM LINE BRK TRIP RESET.
(3)
Depress TURB RESET.
NRC COPY
- 1
QCOA 1300-01 UNIT 1 (2)
REVISION 11 NOTE Reactor pressure must be greater than 54 psig to open STM SPLY ISOL VLVs.
(4)
Open MO 1300-17, STM SPLY ISOL VLV.
[
]
CAUTION Care must be exercised in next step so as to prevent spurious RCIC isolation due to high steam flow and to prevent water hammer.
(5)
IF time
- permits, THEN slowly warm-up RCIC steam lines by:
(a)
Slowly crack open MO 1(2)-1301-16, STM SPLY ISOL VLV, and perform the following:
(b)
Monitor PI l(2)-1340-6,TURB INLET PRESS, for a
slow increase in pressure.
(c)
IF Annunciator 901(2)-4 F-16, RCIC TURBINE INLET STM DRN HIGH LEVEL, is
- lit, THEN do NOT open valve further.
(d)
WHEN RCIC steam line pressure is equal to Reactor pressure AND Annunciator 901(2)-4 F-16, RCIC TURBINE INLET STM DRN HIGH LEVEL,
- cleared, THEN open fully MO 1(2)-1301-16.
(6)
IF time does NOT permit for slow warm-up, THEN open MO 1(2)-1301-16, STM SPLY ISOL VLV.
- 9.
WHEN RCIC Turbine trip and/or isolation has been reset AND RCIC is required for operation, THEN restart RCIC System per QCOP 1300-02.
- 10.
IF RCIC is NOT required for operation, THEN place RCIC in the standby lineup per QCOP 1300-01.
- 11.
Notify Shift Manager to classify event as a
possible E-Plan condition and initiate E-Plan as necessary.
- 12.
IF RCIC is inoperable, THEN perform QCAP 0230-19.
NRC COPY
- 1
QCOA 1300-01 UNIT 1 (2)
REVISION 11 E.
DISCUSSION
- 1.
RCIC Turbine trips are:
I NOTE Item E.l.a will close the TRIP THROTTLE VLV.
Item E.l.b E.l.e will close MO 1(2)-1301-60, MIN FLOW
IF RCIC trip was caused by Reactor high level, item E.1.b, THEN RCIC will auto restart on a low-low level initiation signal.
All other trips require operator actions for resetting the trips.
- a.
- b.
- c.
- d.
- e.
- 2.
- a.
b.
C.
Turbine overspeed; 5600 rpm.
(Mechanical)
High Reactor Vessel water level:
(1) For Unit 1, < 54.23 inches.
(2)
For Unit 2,
< 50.34 inches.
Low pump suction pressure; 15 inches Hg vacuum.
High RCIC Turbine exhaust pressure; 25 psig.
Automatic RCIC Isolation.
isolation signals are:
(F-2)
RCIC Turbine area high temperature;
< 169°F.
RCIC steam line high flow; 175%T of rated steam flow with a time delay of > 3.2 and < 8.8 seconds.
Reactor Vessel low pressure;
> 54 psig.
F.
REFERENCES
- 1.
TS 3.3.5.2, Reactor Core Isolation Cooling (RCIC)
Instrumentation.
- 2.
TS 3.3.6.1, Primary Containment Isolation Instrumentation.
- 3.
NRC COPY
- 1
QCOA 1300-01 UNIT 1 (2)
REVISION 11
- 4.
TS 3.6.1.3, Primary Containment Isolation Valves (PCIVs).
- 5.
M-50 (M-89),
Diagram of RCIC Piping.
- 6.
Schematic Diagram RCIC System Part 1.
- 7.
Schematic Diagram RCIC System Part 2.
- 8.
4E-1484C (4E-2484C), Schematic Diagram RCIC System Part 3.
- 9.
4E-1484D Sheets 1 and 2 (4E-2484D Sheets 1 and 2),
Schematic Diagram RCIC System Part 4.
- 10.
4E-1484E Sheets 1 and 2 (4E-2484E Sheets 1 and 2),
Schematic Diagram RCIC System Part 5.
- 11.
4E-1484F Sheets 1 and 2 (4E-2484F Sheets 1 and 2),
Schematic Diagram RCIC System Part 6.
- 12.
Schematic Diagram RCIC System Part 7.
- 13.
- C00398, GEK 9546, Instruction Operation and Maintenance, System 1300 -
Reactor Core Isolation Cooling.
- 14.
- C00471, GEK 27820A, Process Instrument Subsystem of the Reactor Core Isolation Cooling System.
- 15.
QCOP 1300-01, RCIC Preparation for Standby Operation.
- 16.
QCOP 1300-02, RCIC System Manual Startup (Injection/Pressure Control).
- 17.
QCAP 0230-19, Equipment Operability.
- 18.
UFSAR 5.4.6, Reactor Core Isolation Cooling System.
- 19.
Operational Issues Identified in Boiling Water Reactor Trip And Transient.
- 20.
QCNPS Procedure Writer's
- Guide, Rev.
1, dated January 31, 1990.
(final)
NRC COPY #1
QCOP 1300-02 UNIT 1(2)
REVISION 22 Continuous Use RCIC SYSTEM MANUAL STARTUP (INJECTION/PRESSURE CONTROL)
A. PURPOSE The purpose of this procedure is to provide the steps necessary to manually start up the Reactor Core Isolation Cooling (RCIC) System for injection to the Reactor Vessel.
Also, steps are provided for Reactor pressure control.
B. DISCUSSION B.1.
The attachments to this procedure can be prepared and used as Hard Cards in accordance with OP-AA-101-403.
C. PREREQUISITES C.I.
RCIC in standby lineup per QCOP 1300-01.
D. PRECAUTIONS D.I.
Injection of RCIC into Reactor during power operation could cause a reactivity transient.
D.2.
System operation below 400 gpm should be minimized to prevent the possible cycling of the Turbine Exhaust check valve.
D.3.
RCIC operation below 2200 rpm should be minimized because it may result in unstable system operation and equipment damage.
D.4.
RCIC operation with torus pressure elevated above 25 psig may cause a RCIC trip due to a high exhaust pressure signal.
D.5.
RCIC operation with torus temperature above 140OF should be avoided because it may result in equipment damage due to inadequate lube oil cooling. (H.8.c)
D.6.
Oxygen concentrations in the Torus may increase during extended RCIC operation.
IF extended RCIC operation is anticipated, THEN monitor the oxygen concentration AND operate the nitrogen inerting system as necessary.
NRC COPY
- 1
QCOP 1300-02 UNIT 1(2)
REVISION 22 D.7.
Turb Vac Pump needs to run a minimum of 30 minutes after shutting down RCIC to ensure moisture is removed from the governor valve.
D.8.
Notify Rad Protection that performance of this procedure has the potential of impacting radiological conditions in the plant.
Perform the notification as soon as time permits so as NOT to preclude emergency actions.
D.9.
IF RCIC initiation signal is present following any isolation signal, THEN RCIC will auto start when the isolation is cleared.
Potential water hammer may occur.
E. LIMITATIONS AND ACTIONS E.I.
IF RCIC becomes inoperable, THEN perform QCAP 0230-19.
E.2.
WHEN RCIC suction is from CCST, THEN minimize the time that MO 1(2)-1301-60, MIN FLOW VLV, is open to prevent draining CCST to the Torus.
E.3.
IF MO 1(2)-1301-25, TORUS PMP SUCT VLV, OR MO 1(2)-1301-26, TORUS PMP SUCT VLV, is open, THEN MO 1(2)-1301-53, CCST TEST BYP, will automatically close to prevent pumping Torus water to the CCST.
E.4.
RCIC automatic initiation is Reactor Vessel Water Level-Low Low; for Unit 1 -56.78 inches and for Unit 2 -55.2 inches.
(H.l.a.)
E.5.
RCIC isolation signals are as follows:
(H.l.b.)
- a.
RCIC Turbine Area Temperature-High;
< 169OF.
- b.
RCIC Steam Line Flow-High;
- 175% of rated steam flow with a time delay of > 3.2 seconds and < 8.8 seconds.
- c.
RCIC Steam Supply Line Pressure-Low;
> 54 psig.
NRC COPY
- 1
QCOP 1300-02 UNIT 1(2)
REVISION 22 E.6.
RCIC automatic turbine trips are:
NOTE Item E.6.a will close the TRIP THROTTLE VLV.
Item E.6.b - E.6.e will close MO 1(2)-1301-60, MIN FLOW VLV, and MO 1(2)-1301-61, STM TO TURB VLV.
The high Reactor level trip signal, item E.6.b., will auto reset.
- a.
Turbine overspeed; 5600 rpm.
(Mechanical)
- b.
Reactor Vessel Water Level-High; for Unit 1
< 54.23 inches and for Unit 2 < 50.34 inches.
- c.
Lbw pump suction pressure; 15 inches Hg vacuum.
- d.
High RCIC Turbine exhaust pressure; 25 psig.
- e.
Automatic RCIC Isolation.
E.7.
Motor Operated Valves Guidelines:
- a.
A maximum of five starts within a one-minute period, followed by a 30-minute cooling off time.
- b.
The valve is fully operational during the cooling off period.
- c.
When throttle valves are required to adjust flow or pressure, it may be necessary to wait a few seconds to abide by this guideline.
E.8.
IF Torus temperature is increasing, THEN prior to reaching 95 0 F, RHR Torus Cooling Mode should be placed into service.
(H.l.f.)
E.9.
IF Torus level reaches + 5 inches OR CCST level drops below 0.7 feet (10,000 gal.), THEN RCIC System suction auto transfers from CCST to Torus Suction.
E.10.
IF required to start RCIC immediately to inject into the RPV, THEN the operator aid posted on the Control Room panels, modeled after Attachment A, may be used to direct those immediate actions followed by review of this procedure when time is available.
NRC COPY
- 1
QCOP 1300-02 UNIT 1(2)
REVISION 22
F. PROCEDURE
F.1.
IF at any time during the performance of this procedure it is desired to switch suction from CCST to Torus, THEN:
NOTE WHEN 1(2)-1301-25 and 26 are fully OPEN, THEN 1(2)-1302-22 will AUTOMATICALLY close.
a..
O e
- a.
Open MO 1(2)-1301-25, TORUS PMP SUCT VLV.
- b.
Open MO 1(2)-1301-26, TORUS PMP SUCT VLV.
- c.
Verify closed MO 1(2)-1301-22, CCST PUMP SUCT VLV.
- d.
Verify MO 1(2)-1301-53, CCST TEST BYP, closes automatically if open.
F.2.
IF at any time during the performance of this procedure it is desired to switch suction from Torus to CCST, THEN:
- a.
Shut down RCIC per QCOP 1300-05.
0_5
- b.
Close MO 1(2)-1301-25, TORUS PMP SUCT VLV.
- c.
Close MO 1(2)-1301-26, TORUS PMP SUCT VLV.
- d.
Open MO 1(2)-1301-22, CCST PUMP SUCT VLV.
F.3.
IF at any time during the performance of this procedure while in a station blackout event the loss of battery power is imminent or has occurred, THEN exit this procedure and perform QCOP 1300-09, RCIC Local Manual Operation.
F.4.
IF starting RCIC for Reactor injection using the initiation pushbutton THEN:
- a.
Depress and hold RCIC MAN INITIATION Pushbutton for at least 30 sec.
- b.
Verify TURB VACU PMP auto starts.
NRC CPY #1
QCOP 1300-02 UNIT 1(2)
REVISION 22 F.4.
(cont'd)
- c.
Verify open MO 1(2)-1301-61, STM TO TURB VLV.
- d.
Verify RCIC Turbine speed increasing.
- e.
Verify open MO 1(2)-1301-60, MIN FLOW VLV.
- f.
Verify closedAO I(2)-1301-34 and 35, STM LINE DRAIN ISO VLVS.
- g.
Verify open MO 1(2)-1301-62, TURB CLG WTR VLV.
- h.
Verify open MO 1(2)-1301-48, PMP DISCH VLV.
- i.
Verify open MO 1(2)-1301-49, PMP DISCH VLV.
- j.
Verify RCIC Pump discharge flow increases to 400 gpm as indicated on FIC 1(2)-1340-1, RCIC FLOW CONTROLLER.
- k.
Verify closed MO l(2)-1301-60, MIN FLOW VLV.
- 1.
Monitor Reactor water level.
- m.
IF RCIC discharge flow adjustment is required, THEN adjust flow with FIC 1(2)-1340-1, RCIC FLOW CONTROLLER, using one of the following methods:
(1) Verify FIC 1 (2) -1340-1, RCIC FLOW CONTROLLER, in AUTO and adjust setpoint.
(2)
Place FIC 1(2)-1340-1, RCIC FLOW CONTROLLER, to manual and adjust manual adjustment lever.
- n.
Monitor RCIC Turbine for proper operation:
(1) Turbine Speed 2250 to 4500 rpm as indicated on SI 1(2)-1340-501, TURD SPEED.
(2)
Discharge pressure greater than Reactor pressure as indicated on PI 1(2)-1340-7, PMP DISCH PRESS.
(3)
RCIC Pump suction pressure 0 to 30 psig as indicated on PI 1(2)-1340-2, PMP SUCT PRESS.
NRC COPY
- 1
QCOP 1300-02 UNIT 1(2)
REVISION 22 F.4.n. (cont'd)
(4)
RCIC exhaust pressure 1 to 20 psig as indicated on PI 1(2)-1340-3, TURB EXH PRESS.
F.5.
IF manually starting RCIC for Reactor injection, THEN:
- a.
Start TURB VACU PMP.
- b.
Open MO 1(2)-1301-62, TURB CLG WTR VLV.
- c.
Verify open MO 1(2)-1301-48, PMP DISCH VLV.
- d.
Open MO 1(2)-1301-49, PMP DISCH VLV.
- e.
Open MO 1(2)-1301-60, MIN FLOW VLV.
- f.
Open MO 1(2)-1301-61, STM TO TURB VLV.
- g.
Verify RCIC Pump discharge flow increases to 400 gpm as indicated on FIC 1(2)-1340-1, RCIC FLOW CONTROLLER.
- h.
Verify closed MO 1(2)-1301-60, MIN FLOW VLV.
- i.
IF RCIC discharge flow adjustment is required THEN adjust flow with FIC 1(2)-1340-1, RCIC FLOW CONTROLLER, using one of the following methods:
(1) Verify FIC 1(2)-1340-1, RCIC FLOW CONTROLLER, in AUTO and adjust setpoint.
(2)
Place FIC 1(2)-1340-1, RCIC FLOW CONTROLLER, in manual and adjust manual adjustment lever.
- j.
Monitor RCIC Turbine for proper operation:
(1) Turbine Speed 2250 to 4500 rpm as indicated on SI 1(2)-1340-501 TURB SPEED.
(2)
Discharge pressure greater than Reactor pressure as indicated on PI 1(2)-1340-7, PMP DISCH PRESS.
(3)
RCIC Pump suction pressure 0 to 30 psig as indicated on PI 1(2)-1340-2, RCIC PMP SUCT PRESS.
NRC COPY
- 1
QCOP 1300-02 UNIT 1(2)
REVISION 22 F.5.j.
(cont 'd)
(4)
RCIC exhaust pressure 1 to 20 psig as indicated on PI 1(2)-1340-3, TURD EXH PRESS.
F.6.
IF manually starting RCIC for Reactor pressure control WITHOUT an ECCS signal present THEN:
- a.
Open MO 1(2)-2301-15, (HPCI)
TEST RETURN VLV.
- b.
Throttle open MO 1(2)-1301-53, CCST TEST BYP.
- c.
Start TURB VACU PMP.
- d.
Open MO 1(2)-1301-62, TURB CLG WTR VLV.
- e.
Verify closed MO 1(2)-1301-49, PMP DISCH VLV.
- f.
Open MO 1(2)-1301-60, MIN FLOW VLV.
- g.
Open MO 1(2)-1301-61, STM TO TURB VLV.
- h.
Verify RCIC Pump discharge flow increases to 400 gpm or desired as indicated on FIC 1(2)-1340-1, RCIC FLOW CONTROLLER.
- i.
Verify closed MO 1(2) -1301--60, MIN FLOW VLV.
- j.
IF RCIC discharge flow or pressure adjustment is required, THEN:
(1) Adjust flow with FIC 1(2)-1340-1 RCIC FLOW CONTROLLER, using one of the following methods:
(a)
Verify FIC 1(2)-1340-1, RCIC FLOW CONTROLLER, in AUTO and adjust setpoint.
(b)
Place FIC 1(2)-1340-1, RCIC FLOW CONTROLLER, to manual and adjust manual adjustment lever.
(2)
Throttle MO 1(2)-1301-53, CCST TEST BYP, until at least 100 psig above Reactor pressure.
NRC CdPY
- 1
QCOP 1300-02 UNIT 1(2)
REVISION 22 F.6.
(cont'd)
- k.
Monitor RCIC Turbine for proper operation:
(1) Turbine Speed 2250 to 4500 rpm as indicated on SI 1(2)-1340-501, TURB SPEED.
(2)
Discharge pressure less than or equal to 1250 psig as indicated on PI 1(2)-1340-7, PMP DISCH PRESS.
(3)
RCIC Pump suction pressure 0 to 30 psig as indicated on PI 1(2)-1340-2, PMP SUCT PRESS.
(4)
RCIC exhaust pressure 1 to 20 psig as indicated on PI 1(2)-1340-3, TURB EXH PRESS.
F.7.
IF manually starting RCIC for Reactor pressure control WITH Drywell pressure > 2.43 psig, THEN:
- a.
Place FIC 1(2)-1340-1, RCIC FLOW CONTROLLER, in MAN.
- b.
Reduce FIC 1(2)-1340-1, RCIC FLOW CONTROLLER, to minimum by using the manual adjustment lever.
- c.
Start TURB VACU PMP.
- d.
Open MO 1(2)-1301-62, TURB CLG WTR VLV.
NOTE WHEN RCIC is operating with MO 1(2)-1301-60, MIN FLOW VLV, open, THEN FIC 1(2)-1340-1, RCIC FLOW CONTROLLER, will indicate downscale.
- e.
Open MO 1(2)-1301-60, MIN FLOW VLV.
- f.
Open MO 1(2)-1301-61, STM TO TURB VLV.
- g.
IF RCIC discharge pressure adjustment is required, THEN adjust pressure with FIC 1(2)-1340-1, RCIC FLOW CONTROLLER, using the manual adjustment lever.
NRC C@PY
- 1
QCOP 1300-02 UNIT 1(2)
REVISION 22 F.7. (cont'd)
- h.
Monitor RCIC for proper operation.
(1) Turbine Speed 2250 to 4500 rpm as indicated on SI 1(2)-1340-501, TURB SPEED.
(2)
Discharge pressure less than or equal to 1250 psig as indicated on PI 1(2)-1340-7, PMP DISCH PRESS.
(3)
RCIC Pump suction pressure 0 to 30 psig as indicated on PI 1(2)-1340-2, PMP SUCT PRESS.
(4)
RCIC exhaust pressure 1 to 20 psig as indicated on PI 1(2)-1340-3, TURD EXH PRESS.
F.8.
When RCIC System shutdown is desired, THEN perform QCOP 1300-05.
G. ATTACHMENTS G.1.
Attachment A RCIC Manual Startup.
H. REFERENCES H. 1.
Technical Specifications:
- a.
TS 3.3.5.2, Reactor Core Isolation Cooling (RCIC)
System Instrumentation.
- b.
TS 3.3.6.1, Primary Containment Isolation Instrumentation.
- c.
- d.
TS 3.6.1.1, Primary Containment.
- e.
TS 3.6.1.3, Primary Containment Isolation Valves (PCIVs).
- f.
TS 3.6.2.1, Suppression Pool Average Temperature.
- g.
TS 3.6.2.2, Suppression Pool Water Level.
H.2.
P&lDs:
- a.
M-50 (M-89),
Diagram of RCIC Piping.
NRC C6PY
- 1
QCOP 1300-02 UNIT 1(2)
REVISION 22 H.3.
Drawings:
- a.
Schematic Diagram RCIC System Part 1.
- b.
Schematic Diagram RCIC System Part 2.
- c.
Schematic Diagram RCIC System Part 3.
- d.
4E-1484D sheet 1 and 2 (4E-2484D sheet 1 and 2),
Schematic Diagram RCIC System Part 4.
- e.
4E-1484E sheet 1 and 2 (4E-2484E sheet 1 and 2),
Schematic Diagram RCIC System Part 5.
- f.
4E-1484F sheet 1 and 2 (4E-2484F sheet 1 and 2),
Schematic Diagram RCIC System Part 6.
- g.
Schematic Diagram RCIC System Part 7.
H-4.
Manuals:
- a.
C0398 (GEK 9546),
Instruction Operation and Maintenance, System 1300 Reactor Core Isolation Cooling.
- b.
C0471 (GEK 27820A),
Process Instrument Subsystem of the Reactor Core Isolation Cooling System.
H.5.
Procedures:
- a.
QCOP 1000-09, Torus Cooling Start-Up and Operation.
- b.
QCOP 1300-01, RCIC System Preparation for Standby Operation.
- c.
QCOP 1300-05, RCIC System Shutdown.
- d.
QCAP 0230-19, Equipment Operability.
H.6.
UFSAR:
- a.
UFSAR Section 5.4.6, RCIC System.
H.17.
Commitments:
None.
NRC COPY
- 1
QCOP 1300-02 UNIT 1(2)
REVISION 22 IIH.8.
Others:
- a.
BWR Owner's Group Emergency Procedure and Severe Accident Guidelines.
- b.
Eenigenburg Letter to R.
Bax dated 10-28-85, Operational Guidelines for Motor Operated Valves.
- c.
DBD-QC-001.
- d.
QCPWG (Procedure Writers Guide) Vol 3.
NRC C:QPY
- 1
QCOP 1300-02 UNIT 1(2)
REVISION 22 ATTACHMENT A (Page 1 of 1)
RCIC MANUAL STARTUP MANUAL PUSHBUTTON INITIATION
- 1. Depress and hold RCIC MAN INITIATION pushbutton for at least 30 sec.
MANUAL STARTUP - LEVEL CONTROL
- 1.
Start TURB VACU PMP.
- 2.
Open MO 1(2)-1301-62, TURB CLG WTR VLV.
- 3.
Verify open MO 1(2)-1301-48, PMP DISCH VLV.
- 4.
Open MO 1(2)-1301-49, PMP DISCH VLV.
- 5.
Open MO 1(2)-1301-60, MIN FLOW VLV.
- 6.
Open MO 1(2)-1301-61, STM TO TURB VLV.
- 7.
Adjust flow in the MANUAL or AUTO mode.
Refer to QCOP 1300-02 (final)
NRC CQPY
- 1
Nuclearni Nuclear Nuclear Generation Group Job Performance Measure Supply Bus 14-1 from Bus 24-1 using the Hardcard JPM Number: B.l.c.
Revision Number: 1 Date: 9/2002 Review By:
h Instrultor
/ //
SME or Instructor Operations Representative
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Developed By:
Validated By:
Date Date Date 0-ov.
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B.1.c.
Revision Record (Summary)
Revision 0, Revision 1 This JPM is developed JAW guidelines established in NUREG 1021 Rev 8 ES-301 and Appendix C. This JPM meets the criteria of Category B. 1 "Control Room Systems," for RO/SRO candidates.
The JPM was revised to incorporate validation time and comments.
Information For Evaluator's Use:
UNSAT requires written comments on respective step.
- Denotes CRITICAL steps.
Number any comments in the "Comment Number" column on the following pages. Then annotate that comment in the "Comments" section at the bottom of the page. The comment section should be used to document the reason that a step is marked as unsatisfactory and to document unsatisfactory performance relating to management expectations.
Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.
The timeclock starts when the candidate acknowledges the initiating cue.
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B.I.c.
SIMULATOR SETUP INSTRUCTIONS
- 1. Reset the simulator to IC 94 (rst 94).
- 2. IC
Description:
NOTE:
It is okay to use a similar IC to the IC listed above, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.
- 3. Manual Actuation:
"* Place the lB Core Spray pump in PTL on 901-3 panel.
"* Place the IC RHR pump in PTL on 901-3 panel.
"* Place the ID RHR pump in PTL on 901-3 panel.
"* Place the U-1 EDG control switch in STOP on the 901-8 panel.
- 4. Malfunctions:
"* Prevent the U-I EDG from starting (imfdeO3a)
"* Trip the bus 14 to 14-1 tie breaker 152-1427 (imfedO4m)
"* Acknowledge alarms associated with the bus 14 to bus 14-1 breaker trip as part of setup.
- 5. Remotes: When asked by the candidate for U-2 to close bus 24-1 to 14-1 crosstie breaker on U-2, use remote function (mrfed34r close) to close in the breaker and report to candidate that the bus 24-1 to 14-1 crosstie breaker on U-2 is closed in.
- 6. Overrides: NONE
- 7. When the above steps are completed for this and other JPMs to be run concurrently, then validate the concurrently run JPMs using the JPM Validation Checklist.
- 8. This completes the setup for this JPM.
...- LIP ag e,@
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INITIAL CONDITIONS
"* Unit 1 has experienced a transient resulting in a LOCA and drywell pressure of 5 psig.
"* The bus 14 to bus 14-1 tie breaker has tripped.
"* The Unit 1 Emergency Diesel Generator failed to start.
"* Bus 14-1 is de-energized.
"* No overcurrent alarms are up for any busses.
"* Unit 2 is operating at 150 MWE in a split configuration (load is split between the UAT and the RAT).
"* Unit 2 Emergency Diesel Generator to bus 24-1 breaker is open.
"* The 1 B Core Spray pump and the 1 C and 1 D RHR pumps are in PTL and have been verified.
"* The Unit Supervisor has authorized hardcards.
"* This JPM is not time critical INITIATING CUE Energize bus 14-1 from bus 24-1 using the hardcard.
Fill in the JPM Start Time when the student acknowledges the Initiating Cue.
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JPM Start Time:
1 PERFORMANCE OBJECTIVE STANDARDS SAT UNSAT N/A Obtain hardcard for BUS 14-1 TO Obtains hardcard for BUS 14-1 TO
[]
[]
[]
BUS 24-1 TIE OPERATION (BUS BUS 24-1 TIE OPERATION (BUS 14 14-1 DEAD) from the 901-74 1 DEAD) from the 901-74 panel.
panel.
Hardcard Places control switches in pull to Places the following control
[I
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step 1 lock to isolate bus 14.
switches in PTL.
"* Bus 14-1 & Bus 61 Tie breaker
"* Ul Diesel Gen toBus 14-1 ACB
"* Busses 14 and 14-1 Tie Breaker
- Hardcard Directs the Unit 2 NSO or ANSO Directs the Unit 2 RO to perform the
[]
[]
[3 step 2 to operate the synchronization following two steps on the switch and close bus 24-1 & 14-1 902-8 panel:
tie breaker.
- 1. Place SYNCH switch to ON for BUS 24-1 & 14-1 tie ACB.
- 2. Close BUS 24-1 & 14-1 tie ACB Evaluators Note: If candidate asks the evaluator to perform this task, direct them to use the phone to contact the U-2 RO (simulator operator) for performance of these two tasks.
Simulator Operator Note: When asked by the candidate for U-2 to close bus 24-1 to 14-1 crosstie breaker on U-2, use remote function (mrf ed34r close) to close in the breaker and report to candidate that the bus 24-1 to 14-1 crosstie breaker on U-2 is closed in.
- Hardcard Places the synchronization switch Places the synchronization switch on
[3
[]
[]
step 3.a.
ON for the crosstie.
the 901-8 panel to ON for BUS 24-1
& 14-1 tie ACB.
- Hardcard Close bus 14-1 & 24-1 tie breaker.
Closes and holds (for approximately
[]
[3
[]
step 3.b.
10 seconds) the BUS 24-1 & 14-1 tie ACB on the 901-8 panel. Verifies BUS 24-1 & 14-1 tie ACB closed indication light and bus 14-1 live light lit.
EVALUATOR: The candidate should inform you that the task is complete.
JPM Stop Time:
I 2
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Operator's Name:
Job
Title:
RO Q
SRO 1:
Title:
Supply Bus 14-1 from Bus 24-1 using the Hardcard JPMNumber: B.1.c.
Revision Number: 1 Task Number and
Title:
SR-6500-P04. Given a loss of normal power to an emergency bus (13-1/14-1) with a failure of the associated emergency diesel to start, supply power to the emergency bus using the crosstie from unit 2 and restore 480 VAC busses in accordance with QOA 6500-03, QCOP 6500-08, QOA 6700-04 and QOA 6700-01. (SOER 83-6 r4)
K/A Number and Importance:
K/A: 262001 A4.01 Rating: 3.4/3.7 Suggested Testing Environment:
Simulator Actual Testing Environment:
Testing Method:
UL Simulate QL Perform Time Critical:
Di Yes N No El EL Simulator Control Room Faulted: Li Yes Alternate Path: ID Yes QL Plant E No N No Estimated Time to Complete:
7 minutes
References:
QCOP 6500-08, Rev. 13 N\\,
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K
-_i Actual Time Used:
minutes V /
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B.l.c.
EVALUATION
SUMMARY
Were all the Critical Elements performed satisfactorily?
IJ Yes Ij No The operator's performance was evaluated against the standards contained in this JPM, and has been determined to be:
Ij Satisfactory U Unsatisfactory Comments:
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Evaluator's Name:
Evaluator's Signature:
(Print)
Date:
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QCOP 6500-08 UNIT 1e REVIS I ATTACHMENT C (Page I of 1) 4 BUS 14-1 TO BUS 24-1 TIE BREAKER OPERATION, (BUS 14-1 DEAD)
BUS 24-1 POWERED and BUS 14-1 DEAD
- 1.
Place the following control switches in PTL:
BUS 14-1 & BUS 61 TIE BKR lB CS PMP U1 DIESEL GEN TO BUS 14-1 ACB IC RHR PMP BUSSES 14 AND 14-1 TIE BKR ID RHR PMP
- 2.
On Panel 902-8:
- a.
Place SYNCH switch to ON for BUS 24-1 & 14-1 TIE ACB.
- b.
Close BUS 24-1 & 14-1 TIE ACB.
- 3.
On Panel 901-8:
- a.
Place SYNCH switch to ON for BUS 14-1 & 24-1 TIE ACB.
- b.
Close (AND hold for 10 seconds) BUS 14-1 & 24-1 TIE ACB.
Refer to QCOP 6500-08 NRC CQPY
- 1
B.l.c.
INITIAL CONDITIONS (Student Copy)
"* Unit 1 has experienced a transient resulting in a LOCA and drywell pressure of 5 psig.
"* The bus 14 to bus 14-1 tie breaker has tripped.
"* The Unit 1 Emergency Diesel Generator failed to start.
"* Bus 14-1 is de-energized.
"* No overcurrent alarms are up for any busses.
"* Unit 2 is operating at 150 MWE in a split configuration (load is split between the UAT and the RAT).
"* Unit 2 Emergency Diesel Generator to bus 24-1 breaker is open.
"* The 1 B Core Spray pump and the 1 C and 1 D RHR pumps are in PTL.
"* The Unit Supervisor has authorized hardcards.
"* This JPM is not time critical INITIATING CUE Energize bus 14-1 from bus 24-1 using the hardcard.
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Nuclear r
I Nuclear Generation Group Job Performance Measure Perform a Manual Scram Functional Test with Rod Drifts JPM Number: B.1.d.
Revision Number: 1 Date: 9/2002 Developed By:
Validated By:
Review By:
S'I, I
- InstrMEor SME or Instructor i! /
U Operations Representative iL--P (C LI
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Date Date Date I
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B.1.d.
Revision Record (Summary)
Revision 0, Revision 1 This JPM is developed JAW guidelines established in NUREG 1021 Rev 8 ES-301 and Appendix C. This JPM meets the criteria of Category B. I "Control Room Systems," for RO/SRO candidates.
The JPM was revised to incorporate validation time and comments.
sons on MEN Nona i
m ono am aml i
i ME iam NONE mono a am u
on ME U
SE Nona MEN Oman am NON SEME N MI i Information For Evaluator's Use:
UNSAT requires written comments on respective step.
- Denotes CRITICAL steps.
Number any comments in the "Comment Number" column on the following pages. Then annotate that comment in the "Comments" section at the bottom of the page. The comment section should be used to document the reason that a step is marked as unsatisfactory and to document unsatisfactory performance relating to management expectations.
Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.
The timeclock starts when the candidate acknowledges the initiating cue.
F-_.-)
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B.l.d.
SIMULATOR SETUP INSTRUCTIONS
- 1. Reset the simulator to IC 21 (rst 21).
NOTE:
This JPM will result in a manual scram being inserted by the candidate. If this will effect other JPMS, it should be used alone or with administrative JPMS that do not require the use of the simulator or process computer.
- 2. Provide a copy of QCOS 0500-02 with section D.1. filled out for "Unit 1" as a "Normal Surveillance", signed and dated by the Unit Supervisor, and section D.2.
initialed as EO/ANSO.
- 3. Manual Actuation:
NONE Malfunctions:
Assign B RPS tripped to trigger 2 "trz 2 E2" Assign rod 1815 to drift in when RPS B is tripped "imfrdO3rl8l5(2)"
Assign rod 2227 to drift in when RPS B is tripped "imfrdO3r2227(2)'"
Assign rod 1839 to drift in when RPS B is tripped "imfrdO3r1839(2)"
Assign rod 0627 to drift in when RPS B is tripped "imfrdO3rO627(2)"
Remotes:
NONE Overrides:
NONE
- 4. When the above steps are completed for this and other JPMs to be run concurrently, then validate the concurrently run JPMs using the JPM Validation Checklist.
- 5. This completes the setup for this JPM.
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B.1.d.
INITIAL CONDITIONS
"* The Unit Supervisor has ordered that a manual scram functional test be performed this shift on Unit 1.
"* This JPM is not time critical.
INITIATING CUE Perform a U-1 Manual Scram Functional Test IAW QCOS 0500-02.
Provide a copy of QCOS 0500-02 with section D.1. filled out for "Unit 1" as a "Normal Surveillance", signed and dated by the Unit Supervisor, and section D.2. initialed as EO/ANSO.
Fill in the JPM Start Time when the student acknowledges the Initiating Cue.
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B.l.d.
JPM Start Time:
PERFORMANCE OBJECTIVE STANDARDS
'SAT UNSAT N/A
- H. l.a.
Depress the "Channel A" Depress lefthand pushbutton.
I manual scram pushbutton.
SH. l.b.
Verify red light in "Channel A" Red light lit.
[1
[]
[ ]
manual scram pushbutton is lit.
H. l.c.
Verify "Channel A" scram Four RPS A scram solenoid lights not
[]
[]
[]
solenoid group lights out.
lit.
I I
H. 1. d.
Verify "Channel A Manual I Annunciator 901-5 A-10 lit.
[1
[
Scram" alarm.
i *H.l.e.
Reset half scram and verify all 4 Positions RPS scram reset switch first to
[]
[]
lights lit for Channel A and B.
position 2 and 3 then to position l and
- 4.
- Verifies all 4 lights lit for Channel A and B.
H. 1f.
Reset "Channel A Manual Trip" Depresses reset pushbutton AND
[]
alarm.
verifies Annunciator 901-5 A-10 not lit.
- H.2.a.
Depress the "Channel B" Depresses righthand pushbutton.
[-
[.
F imanual scram pushbutton.
Verify red light in "Channel B" Red light lit.
[]
[]
[]
manual scram pushbutton is lit.
Verify "Channel B" scram Four RPS B scram solenoid lights not
[]
[]
[]
solenoid GP lights out.
lit.
Verify "Channel B Manual Annunciator 9015 A-15 lit.
[]
[]
[]
Scram" alarm.
- F.5.
Recognizes rod drifts requiring a Recognizes that 4 rods are drifting into
[]
[]
reactor scram per section F.5.
. the core, and inserts a manual reactor scram.
I...................
Cue: Inform candidate that JPM is over when reactor is scrammed.
JPM Stop Time:
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B.l.d.
Operator's Name:
Job
Title:
RO U
!J JPM
Title:
Perform a Manual Scram Functional Test with Rod Drifts JPM Number: B. 1.d.
Revision Number: 1 Task Number and
Title:
SR-0500-PO1 - Given an operating reactor plant, perform the manual scram functional test in accordance with QCOS 500-2.
K/A Number and Importance:
K/A: 212000 A4.01 RATING: 4.6/4.6 Suggested Testing Environment: Simulator Actual Testing Environment:
iJ Simulator
!L Plant Ll Testing Method: IZ Simulate C) Perform Alter Time Critical: Q Yes U No Estimated Time to Complete:
9 minutes
References:
QCOS 0500-02, Rev. 12 Control Room Faulted: C) Yes nate Path: U Yes Actual Time Used:
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B.l.d.
EVALUATION
SUMMARY
Were all the Critical Elements performed satisfactorily?
D Yes Ll No The operator's performance was evaluated against the standards contained in this JPM, and has been determined to be:
C3 Satisfactory L1 Unsatisfactory Comments:
Evaluator's Name:
Evaluator's Signature:
(Print)
Date:
\\j LI
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F-i m Ii IL LjF-j H
B.l.d.
INITIAL CONDITIONS (Student Copy)
"* The Unit Supervisor has ordered that a manual scram functional test be performed this shift on Unit 1.
"* This JPM is not time critical.
INITIATING CUE Perform a U-1 Manual Scram Functional Test IAW QCOS 0500-02.
.m.....uu.u.u.u....E........Euu.m..........u.u.u.E.u.uu...u..u.E..uu..mus
QCOS 0500-02 UNIT 1(2)
REVISION 12 CO7 Continuous Use MANUAL SCRAM INSTRUMENTATION FUNCTIONAL TEST A. PURPOSE This procedure satisfies the Technical Specifications functional test requirements of Manual Scram Instrumentation.
This test also satisfies a portion of the Logic System Functional Test overlap as required by Technical Specification 3.3.1.1.
(J.l.a.)
B. DISCUSSION None.
C. EQUIPMENT REQUIRED None.
D. PREREQUISITES
- o.
4D D.1.
The Unit Supervisor has completed the following:
- a.
Unit
- b.
Reason for test (check appropriate item):
Normal Surveillance Post Maintenance IST Alert Range Partial for Other
- c.
Permission to start test:
US Signatare Dt-e7 -0z
/ Time Date Time D.2.
HCU scram pilot solenoid fuses at 2201(2)-22A panels blown.
E. PRECAUTIONS None.
1 NRC COPY
- 1 1(2)
(/)
(
)
(
)
(
)
QCOS 0500-02 UNIT 1(2)
REVISION 12 F. LIMITATIONS AND ACTIONS F.1.
At the completion of the surveillance the US must immediately review the results of this test for compliance to Technical Specifications requirements.
F.2.
JE a Control Rod inadvertently scrams, THEN refer to QCOA 0300-04 and QCOA 0300-11.
F.3.
JE the logic fails to operate properly, THEN notify Unit S..Supervisor.
F.4.
IE two OR more control rods start to drift, AND all RPS scram solenoid lights
- lit, THEN scram the Reactor.
F.5.
JE four DR more control rods start to drift, THENsCram the Reactor.
F.6.
IE partial testing is required, THEN the Unit Supervisor will document in the PREREQUISITES, EITHER the steps to be performed DR the steps to be disregarded, AMJ any special instructions required for the performance of the partial test.
G. PERFORMANCE ACCEPTANCE CRITERIA.
G.1.
WHEN RX SCRAM CH A DR RX SCRAM CH B manual scram pushbutton is depressed, THEN the following actions occur:
- a.
ALL four respective RPS SCRAM SOLENOID GROUP indicating lights for that RPS channel are out.
(J.l.a)
- b.
Annunciator 901(2)-5 A-10 R A-15, CHANNEL A or B MANUAL SCRAM alarms.
H. PROCEDURE
H.l.
Verify proper operation of RPS Channel A manual scram instrumentation:
- a.
Depress RX SCRAM CH A manual scram pushbutton.
- b.
Verify red light on RX SCRAM CH A manual scram pushbutton is LIT.
2 NRC COPY
- 1
QCOS 0500-02 UNIT 1(2)
REVISION 12 H.I.
(cont'd)
C.
Verify all four RPS Channel A SCRAM SOLENOID GROUP indicating lights are out.
(G.l.a.)
- d.
Verify 901 (2)-5 A-10, CHANNEL A MANUAL SCRAM alarms.
(G.l.b.)
(7e.
Reset Half-Scram:
(1) Place SCRAM RESET switch to reset position GR 2 and 3.
(2)
Place SCRAM RESET switch to reset position GR 1 and 4.
(3)
Verify SCRAM SOLENOID GROUP CHANNEL A indicating lights lit.
_2 (4)
Verify SCRAM SOLENOID GROUP CHANNEL B indicating lights lit.
- f.
Reset alarm 901(2)-5 A-10.
H1..
Verify proper. operation of RPS Channel B manual scram instrumentation:
- a.
Depress RX SCRAM CH B manual scram pushbutton.
- b.
Verify red light on RX SCRAM CH B manual scram pushbutton is LIT.
- c.
Verify all four RPS Channel B SCRAM SOLENOID GROUP indicating lights are out.
(G.l.a.)
- d.
Verify 901(2)-5 A-15, CHANNEL B MANUAL SCRAM alarms.
(G.1.b.)
> e.
Reset Half-Scram:
(1) Place SCRAM RESET switch to reset position GR 2 and 3.
(2)
Place SCRAM RESET switch to reset position GR 1 and 4.
3 NRC COPY
- 1
QCOS 0500-02 UNIT 1(2)
REVISION 12 H.2.e.
(cont'd)
(3)
Verify SCRAM SOLENOID GROUP CHANNEL A indicating lightslit.
(4)
Verify SCRAM SOLENOID GROUP CHANNEL B indicating lightslit.
- f.
Reset alarm 901(2)-5 A-15.
H.3.
IF this surveillance was satisfactory, THEN:
- a.
Surveillance performed by:
/
Signature Date t
- b.
Satisfactory with discrepancies and corrective actions performed, as noted:
Yes N/A Comments:
C.
Surveillance approved by:
/
US Signature Date H.4.
IF this surveillance was unsatisfactory, THEN:
- a.
Operator (1) Description of deficiencies/comments:
(2)
Work Request initiated:
Yes No (3)
Surveillance performed by:
/
Signature Date 4
NRC COPY
- 1 i
I 4ý
! i-
QCOS 0500-02 UNIT 1(2)
REVISION 12
- o *H.
- 4.
(cont'Id)
- b.
Unit Supervisor (1) CR initiated:
Yes No (2)
QCAP 0230-19 Outage Report initiated:
Yes NoO (3)
Additional corrective action:
(4)
Surveillance approved by:
/
Signature Date I. ATTACHMENTS
....None.
J. REFERENCES J. 1.
Technical Specifications:
- a.
Table 3.3.1.1-1, Reactor Protection System Instrumentation:
Manual Scram.
J.2.
P&lDs:
None.
J.3.
Drawings:
- a.
4E-1467 (4E-2467) Sheet 3, Schematic Diagram Reactor Protection System Scram Valve Sol's, Misc.
Aux. Relays.
J.4.
Manuals:
None.
5 NRC COPY
- 1 J
QCOS 0500-02 UNIT 1(2)
REVISION 12 J. 5.
Procedures:
- a.
QCGP 2-3, Reactor Scram.
- b.
QCAP 0230-19, Equipment Operability.
- c.
QCOA 0300-04, Mispositioned Control Rod.
- d.
QCOA 0300-11, Control Rod Drift.
- e.
QCOP 0500-03, Resetting Scrams.
J.6.
UFSAR:
- a.
UFSAR Section 7.2, Reactor Protection Trip System.
J.7.
Commitments:
None.
J.8.
Other:
- a.
QCPWG (Procedure Writers Guide) Vol 3.
t r-(final)
"NRC C5PY
- 1
Exel n.,
Nuclear Nuclear Developed By:
Validated By:
Review By:
Ins ctor SME or Instructor Operations Representative Date Date DI -a/1 --'
Date 7
-----.-..
-
Nuclear Generation Group Job Performance Measure Perform The Core Spray Pump Operability Test For Core Spray Pump B With Failure Of Minimum Flow Valve JPM Number: B.1.e.
Revision Number: 1 Date: 9/2002
B.l.e.
.. Job Performance Measure (JPM)
Revision Record (Summary)
Revision 0, This JPM is developed JAW guidelines established in NUREG 1021 Rev 8 ES-301 and Appendix C. This JPM meets the criteria of Category B. 1 "Control Room Systems," for RO/SRO candidates.
Revision 1 The JPM was revised to incorporate validation time and comments.
Information For Evaluator's Use:
Provide a copy of QCOS 1400-04 Core Spray Pump Operability Test with section D. 1 and D.2. filled out for Unit 1 for a Partial for Core Spray Subsystem B signed and dated by the Unit Supervisor.
Steps H. l.a. marked N/A.
H.1.b.(1),(2),(4)&(5) initialed of as EO/ANSO.
H. 1.b.(3) recorded as 5 seconds, and H. 1.b.(3)(a) initialed as ANSO.
H.2. marked N/A.
H.4.a. marked N/A.
UNSAT requires written comments on respective step.
- Denotes CRITICAL steps.
Number any comments in the "Comment Number" column on the following pages. Then annotate that comment in the "Comments" section at the bottom of the page. The comment section should be used to document the reason that a step is marked as unsatisfactory and to document unsatisfactory performance relating to management expectations.
Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.
The timeclock starts when the candidate acknowledges the initiating cue.
B.l.e.
.... Job Performance Measure (JPM)
SIMULATOR SETUP INSTRUCTIONS
- 1. Reset the simulator to IC 21 (rst 21).
NOTE:
It is okay to use a similar IC to the IC listed above, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.
- 2. Provide a copy of QCOS 1400-04 Core Spray Pump Operability Test with section D. 1 and D.2. filled out for Unit 1 for a Partial for Core Spray Subsystem B signed and dated by the Unit Supervisor.
Steps H. l.a. marked N/A.
H. 1.b.(1),(2),(4)&(5) initialed of as EO/ANSO.
H. 1.b.(3) recorded as 5 seconds, and H. 1.b.(3)(a) initialed as ANSO.
H.2. marked N/A.
H.4.a. marked N/A.
- 3. Manual Actuation:
NONE Malfunctions:
Fail the Core Spray Minimum Flow Valve to Auto Close using (imfcsO6b)
Override 1-1402-38B handswitch to neutral using (ior dihsl140238b norm)
Remotes:
NONE Overrides:
NONE
- 4. When the above steps are completed for this and other JPMs to be run concurrently, then validate the concurrently run JPMs using the JPM Validation Checklist.
- 5. This completes the setup for this JPM.
B.l.e.
, Job Performance Measure (JPM)
INITIAL CONDITIONS The Core Spray System is in its normal standby lineup IAW QCOP 1400-01.
The Core Spray Pump Operability Test is required to be performed this shift.
An EO has vented the core spray piping, performed pre-start checks on the lB Core Spray pump, and is standing by outside the 1 B Core Spray pump room.
All personnel are cleared out of the lB Core Spray room as controlled by the EO.
This JPM is not time critical.
INITIATING CUE Perform the Core Spray Pump Operability Test for the "IB" Core Spray Pump IAW QCOS 1400-04.
Fill in the JPM Start Time when the student acknowledges the Initiating Cue.
I
/
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~
J f i
~j I,/
/
s 2 J L.I C7*./
[.I H
S 0
S S
0
B.l.e-
.Job Performance Measure (JPM)
JPM Start Time:
PERFORMANCE OBJECTIVE STANDARDS SAT UNSAT N/A H.3.a.
Verify torus level < -2" narrow C
s torus level. Verifies t range, then alternate suction (alternate suction pressure limit note pressure limit > 1 psig is met.
applicable).
- H.3.b.(1).
Start lB Core Spray pump.
Positions pump CS to start.
[]
[]
Red light lit.
CUE: If NLO is asked to report on pump operating status, report that the 1B Core Spray pump is operating satisfactorily.
H.3.b.(2).
Verify MO 1-1402-38B opens. j Verifies MO 38B open light lit.
[]
[]
- H.3.b.(3).
Open MO I-1402-4B.
Positions 4B CS to fully open valve
[3
[]
open light lit.
- H.3.b.(4).
Verify MO 1-1402-3 8B closes.
Determines that the 38B did not close.
[]
[]
H.3.b.(4).
Attempts to close the Positions the CS for the 38B to close.
[]
[3
[]
1-1402-38B.
Identifies that the valve still didn't close.
-- H.3.b.(4).
I Report the Mm. Flow valve i Informs US that 1-1402-3 8B did not
[]
[]
did not close.
close.
, g.......
CUE: Acknowledge report as US.
'It 1
V4Y*
-K When candidate identifies need to shutdown the np IA. Wstep F.6,.give cue as US to shutdown the pump IA W-7 the procedure.
If candidate informs US that QCAP 0230-19 needs to be initiated, acknowledge that you as US will perform the procedure.
H.3.c.(l).
1 Close MO I-1402-4B.
1 Positions CS to close. Close light lit.
i [3
[]
- H.3.c.(3).
Stop lB Core Spray pump.
Positions pump CS to stop
[]
[]
Green light lit.
S.....
EVALUATOR:
When the pump is OFF, inform the candidate that the JPM is complete.
L-........-
JPM Stop Time:
uu**m E*N*m*mm*u*m*.mum ummmmmm mm mmmm mm.mm
.m.mmmm mmm U
l UmEm UUmmmEmm mmmmEmEmUUmmEmm EmmEm mUm lm
B.l.e.
Namerator's Name Job
Title:
RO L
SRO L)
Title:
Perform the Core Spray Pump Operability Test For Core Spray Pump B With Failure Of Minimum Flow Valve JPM Number: B. I.e.
Revision Number: 1 Task Number and
Title:
SR-1400-P05 - Given a reactor plant with a core spray loop in a standby lineup, perform the Core Spray Pump Flow Rate Test and return the core spray loop to standby in accordance with QCOS 1400-01.
K/A Number and Importance:
K/A: 209001 A4.04 RATING: 2.9/2.9 Suggested Testing Environment:Simulator Actual Testing Environment:
Testing Method:
U Simulate ID Perform Time Critical: U Yes U No Simulator Control Room Faulted: ID Yes Alternate Path: N Yes Estimated Time to Complete: 15 minutes
References:
QCOS 1400-04, Rev. 10 Actual Time Used:
minutes I-
~Pagej '
JL]
1~JŽR(
\\ I '
Plant E No Ul No
[JUL ii
B.l.e.
Were all the Critical Elements performed satisfactorily?
D Yes Ui No The operator's performance was evaluated against the standards contained in this JPM, and has been determined to be:
UI Satisfactory IJ Unsatisfactory Comments:
Evaluator's Name:
Evaluator's Signature:
(Print)
Date:
Ilah *,..
Co, QCOS 1400-04 UNIT 1(2)
REVISION 10 Continuous Use CORE SPRAY PUMP OPERABILITY TEST A. PURPOSE The purpose of this procedure is to provide the necessary steps to perform the pump operability test.
B. DISCUSSION B.1.
A flow rate of 4500 gpm at a discharge pressure of 216 psig is the calculated equivalent of the flow rate 4700 gpm discharging against a Reactor pressure of 90 psig.
The 200 gpm increase in flow rate is used to account for possible thermal sleeve leakage.
C. EQUIPMENT REQUIRED None.
D. PREREQUISITES D.1.
The Unit Supervisor has completed the following:
- a.
UNIT
- b.
Reason for test (check appropriate item):
Normal Surveillance Post Maintenance
-. Partial for 1
- reS,,s r,t s *3 /.IL.
Other 1(2)
/)
(
)
(v,")
(
)
C.
Permission to start test:
(Y US Signature Date
/ Time D.2.
Core Spray System is in the standby lineup per QCOP 1400-01.
E. PRECAUTIONS E.l.
IF MO 1(2)-1,402-4A/B, CS BYP AND TEST VLV, is opened
.thout the pump running AND system fill is lost,
"---"--**ný--': " *.....
TRHEi-the system must be refilled and vented.
1 NRC COPY #1
QCOS 1400-04 UNIT 1(2)
REVISION 10 E.2.
An alternate suction pressure limit of > 1 psig has been established to permit Core Spray testing during conditions when Torus level is below the normal band.
IF this alternate limit is utilized, THEN limit Core Spray Pump flow rate to < 5000 gpm to ensure NPSH requirements are met.
E.3.
IF the suction pressure is below the applicable suction pressure limit, THEN DO NOT run the Core Spray Pump.
There is insufficient NPSH to run the pump and cavitation damage may occur.
F. LIMITATIONS AND ACTIONS F.1.
Verification sections may be performed any time after the appropriate step is completed but must be completed prior to final acceptance of the surveillance.
F.2.
Motor Operated Valves Guidelines:
(J.8.a)
- a.
A maximum of five starts within a one-minute period, followed by 30 minutes cooling off time.
- b.
The valve is operable during the cooling off period.--...
- c.
WHEN throttle valves are required to adjust for f low or pressure, THEN it may be necessary to wait a few seconds to abide by this guideline.
F.3.
WHEN a Core Spray Pump is run in the minimum flow mode of operation for a time period exceeding 10 minutes, THEN notify the IST group to perform a vibration analysis to ensure no pump degradation has occurred.
Although the pump shall not be declared inoperable, the vibration analysis should be performed within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
(J.8.c)
F.4.
IF a component fails to perform or fails to meet Tech Spec requirements, THEN notify the Unit Supervisor.
F.....
IF partial testing is required, THEN the Unit Supervisor will document in the prerequisites EITHER the steps to be performed OR the steps to be disregarded, AND any special instructions required for the performance of the partial test.
F.6.
IF MO 1(2)-1402-38A/B, CS PMP MIN FLOW VALVE, fails in the open or closed position, THEN the respective Cor.e.....
Spray Pump should be shut down AND QCAP 0230-19 initiated.
(J.l.a, J.8.e) 2 NRC COPY
- 1 7
t 1
1
F
QCOS 1400-04 UNIT 1(2)
REVISION 10 G. PERFORMANCE ACCEPTANCE CRITERIA G.I.
Core Spray Pumps developed a flow rate of 4500 gpm discharge flow at a discharge pressure > 216 psig.
(J.l.b, J.1.c)
G.2.
Core Spray discharge piping filled and vented.
Water flow is observed through the sightglass within 39 seconds of opening the vent valves.
An electronic stopwatch is not required for determining this time.
The recorded time should be the operator's estimate and is expected to be accurate to within a few seconds.
A venting time of greater than 39 seconds could be construed as a preconditioning action as described in NRC Information Notice 97-16, Preconditioning of Plant Structures, Systems, and Components Before ASME Code In-Service Testing or Technical Specification Surveillance Testing.
Venting times less than 39 seconds assures that the system is capable of performing its design basis function regardless as to when the venting is performed in relation to the pump surveillance test.
(J.6.b, J.8.f)
G.3.
MO 1(2)-1402-38A/B, CS MIN FLOW VLV, automatically operated open and close when required.
G.4.
Each Core Spray Pump suction pressure is
> 3 psig OR 1 1 psig-IF alternate suction pressure limit is used.
H. PROCEDURE
HZ.*,
Verify Core Spray Subsystems filled and vented:
ýa Co S ray Subsystem A:
(1) Fully ap he following valves:
(a) 1(2)-1402-*
(2)A CORE SPRAY INBD VENT (b) 1(2)-1402-18A, 1(2)A CORE SPRAY OUTBD VENT VLV.
(2)
Verify water flows from vent line.
j S3 C
NR*C COPY
- 1
QCOS 1400-04 UNIT 1(2)
S.
.REVISION 10 Ibly a.
(cont'd)
(3)
Record estimated time for water to flow after opening the vents.
second Sseconds (a)
Verify time < 39 seconds.
IF time was > 10 seconds, THEN:
Initiate a CR to document that a greater than normal amount of air s found in the system.
the CR number as a def i
'ency at end of procedur_
(4) Close 1(2)-1402-18A, 1 )A CORE SPRAY OUTBD VENT VLV.
(5)
Close 1(2)-1402-17A, 1(2)A C E SPRAY INBD VENT VLV.
(6)
IF water does NOT flow when vente THEN.:
(a)
Notify US.
(b)
Fill and vent 1(2)A Core Spray Subsystem per QCOP 1400-01.
- b.
Core Spray Subsystem B:
(1)
Fully open the following valves:
(a) 1(2)-1402-17B, 1(2)B CORE SPRAY INBD VENT VLV.
K)
(b) 1(2)-1402-18B, 1(2)B CORE SPRAY OUTBD VENT VLV.
(2)
Verify water flows from vent line.
(3)
Record estimated time for water to flow after opening the vents.
seconds (a)
Verify time < 39 seconds.
4 NRC COPY
- 1
QCOS 1400-04 UNIT 1(2)
REVISION 10 H.1.b. (3)
(cont'd)
(b) IF Eifie was > 10 seconds, THEN:
Initiate a CR to document that a greater than normal amount of air was found in the system.
Record the CR number as a deficiency at end of procedure.
(4)
Close 1(2)-1402-18B, 1(2)B CORE SPRAY OUTBD VENT VLV.
(5)
Close 1(2)-1402-17B, 1(2)B CORE SPRAY INBD VENT VLV.
(6)
IF water does NOT flow when vented, THEN:
(a)
Notify US.
1_4 (b)
Fill and vent 1 (2)B Core Spray Subsystem per QCOP 1400-01.
'.2.
IF Core Spray Subsystem A requires testing, THEN:
- a.
IF Torus level < -2 inches narrow range, THEN alternate uc:tion pressure limit of
"]sig is met.
- b.
Establish stem flow and pressure by performing:
(1)
Start 1 (2)A Pump.
(2)
Verify MO 1(2) -140 3 8A, CS PMP MIN FLOW VLV, opens.
(3)
Open MO 1(2)-1402-4A, CS AND TEST VLV.,--.
(4)
Verify MO 1(2)-1402-38A closes.
(5)
Throttle as necessary MO 1(2)-1402-4A to establish a flow rate of
> 4500 gpm at > 216 psig.
5 NRC COPY
- 1
.b.
(cont'd)
QCOS 1400-04 UNIT 1(2)
REVISION 10 (6)
Record pump suction pressure PI 1(2)-1402-40A (at pump).
psig (7)
Verify suction pressure is
> 3 psig OR if using alternate limit, suction pressure is
> 1 psig.
(8)
IF suction pressure does NOT meet the above criteria, THEN immediately stop the Core Spray Pump.
(a)
Abort the test.
Notify the Unit Supervisor.
(9)
Reco AND verify criteria achieved:
PASS PARAMETER MEAS LIMIT (INITIAL) 1(2)
Pump A gpm Discharge Flow
\\4500 gpm FI 1(2)-1450-4A Minimum
- c.
Shutdown system by:
(1) Close MO 1(2)-1402-4A.
(2)
Verify MO 1(2)-1402-38A op s as system flow decreases.
(3)
Stop I(2)A CS PUMP.
(4)
Close MO 1(2)-1402-38A.
- d.
IF over pressure condition (90 psig) in discharge piping exists after 1(2)A Core Spray Pump is stopped, THEN: (J.8.d)
(1)
Crack open MO 1(2)-1402-4A to slowly reduce pressure.
(2)
Close MO 1(2)-1402-4A when pressure reaches 90 psig as indicated on PI I(2)-1450-lA, CS HEADER PRESS.
6 NRC COPY
- 1 1(2)
Pump A ps 1%
Discharge 216 psig Pressure PI 1(2)-1450-lA Minimum
QCOS 1400-04 UNIT 1(2)
REVISION 10 H.2. (cont'd)
IF pressure can NOT be maintained after performing depressurization step above, 7
N:
(J.
8.d)
(1)
Ope.,MO 1(2)-1402-4A.
(2)
Close MO
£i(-.Z 02-4A.
(3)
Fill and vent 1(2)A Co-r ray Subsystem per QCOP 1400-01.--__
H.3.
IF Core Spray Subsystem B requires testing, THEN:
- a.
IF Torus level < -2 inches narrow range, THEN alternate suction pressure limit of
> 1 psig is met.
1/A
- b.
Establish system flow and pressure by performing:
(1)
Start 1 (2) B CS Pump.
9_
(2) Verify MO 1(2)-1402-38B opens.
(3)
Open MO 1(2)-1402-4B.
(4)
Verify MO 1(2)-1402-38B closes.
(5)
Throttle as necessary MO 1(2)-1402-4B to establish a flow rate of
> 4500 gpm at > 216 psig.
(6)
Record pump suction pressure PI 1(2)-1402-40B (at pump).
(7)
Verify suction pressure is
> 3 psig OR if using alternate limit, suction pressure is
> 1 psig.
(8)
IF suction pressure does NOT meet the above criteria, THEN immediately stop the Core Spray Pump.
(a)
Abort the test.
(b)
Notify the Unit Supervisor.
7 NRC COPY
- 1.
.. <QCOS 1400-04 UNIT 1(2)
REVISION 10 H.3.b. (cont'd)
(9)
Record AND verify criteria achieved:
PASS PARAMETER MEASURED LIMIT (INITIAL) 1(2) Pump B psig Discharge 216 psig Pressure PI 1(2)-1450-IB Minimum 1(2) Pump B gpm Discharge Flow 4500 gpm FI 1 (2) -1450-4B Minimum
- c.
Shutdown system by:
(1) Close MO 1(2) -1402-4B.
(2)
Verify MO 1(2)-1402-38B opens as system flow decreases.
(3)
Stop 1(2)B CS PUMP.
(4)
Close MO 1(2)-1402-38B.
- d.
IF over pressure condition (90 psig) in discharge piping exists after 1(2)B Core Spray Pump is stopped, THEN: (J.8.d)
(1)
Crack open MO 1(2)-1402-4B to slowly reduce pressure.
(2)
Close MO 1(2)-1402-4B when pressure reaches 90 psig, as indicated on PI 1(2)-1450-IB, CS HEADER.
- e.
IF pressure can NOT be maintained after performing depressurization step above, THEN: (J.8.d)
(1)
Open MO 1(2)-1402-4B.
(2)
Close MO 1(2)-1402-4B.
(3)
Fill and vent 1 (2) B Core Spray Subsystem per QCOP 1400-01.
8 NRC COPY
- 1
QCOS 1400-04 UNIT 1(2)
REVISION 10 H.4.
Perform verification that Core Spray valves S-aNe-in standby lineup:
- a.
Core Spray Subsystem A:
Component Position 1(2)-1402-17A Closed 1(2)-1402-18A Closed MO 1(2)-1402-38A Closed MO 1(2)-1402-4A Closed 1(2)A CS PMP Switch NORMAL
- b.
Core Spray Subsystem B:
Component Position 1(2)-1402-17B Closed 1 (2) -1402-18B Closed MO 1(2)-1402-38B Closed MO 1 (2) -1402-4B Closed 1(2)B CS PMP Switch NORMAL H.5.
IF this surveillance was satisfactory, THEN:
- a.
Satisfactory with discrepancies and corrective actions performed, as noted:
Yes N/A Comments:
- b.
Surveillance performed by:
/
Signature Date
- c.
Surveillance approved by:
/
US Signature Date 9
NRC COPY
- 1
QCOS 1400-04 UNIT 1(2)
REVISION 10 H.6.
IF this surveillance was unsatisfactory, THEN:
- a.
OPERATOR (1) Description of deficiencies/comments:
(2)
Work Request (WR) initiated:
Yes (3)
Surveillance performed by:
Signature
- b.
UNIT SUPERVISOR (1) CR initiated:
Yes No _
(2)
QCAP 0230-19 initiated:
Yes....
(3)
Additional corrective action:
(4)
Surveillance approved by:
Signature No 4
H.7.
Attach th:
"package I
- --T--ATTACH MENTS WE None.
t L
Ls completed surveillance to appropriate
)R Outage Report, as appropriate.
10 NRC COPY
- 1 No
/
Date
/
Date F
I
QCOS 1400-04 UNIT 1(2)
REVISION 10 J. REFERENCES ni.. 17Techniical Specifications:
- a.
TS 3.3.5.1, Emergency Core Cooling System (ECCS)
Instrumentation.
- b.
- c.
Shutdown.
J.2.
P&lDs:
- a.
M-36 (M-78),
Diagram of Core Spray Piping.
J. 3.
Drawings:
None.
J.4.
Manuals:
None.
J. 5.
Procedures:
...a.
QCOP 1400-01, Core Spray System Preparation for Standby Operation.
- b.
QCOP 1400-03, ECCS Fill System.
- c.
QCAP 0230-19, Equipment Operability.
- d.
QCOS 1400-02, Core Spray System Motor Operated Valve Operability Test.
- e.
QCOS 1400-01, Quarterly Core Spray System Flow Rate Test.
J.6.
UFSAR:
- a.
b.
UFSAR 6.3.2.1, Core Spray Subsystem.
J. 7.
Commitments:
None.
40R.
11 NRC COPY
- 1
t _____
J. 8.
1-(final) 12 NRC COPY
- 1 QCOS 1400-04 UNIT 1(2)
REVISION 10 Others:
- a.
Eenigenburg Letter to R.
Bax dated 10-28-85, Operational Guidelines for Motor Operated Valves.
- b.
Letter from D.
Butcher to W. Koester 7-12-77, G-EBO-7-172 (Station Letter 77-2042).
- c.
NRC Bulletin 88-04 Potential Safety Related Pump Loss.
- d.
DVR 4-1-87-047, B Core Spray Header <40 psig.
- e.
K. Graesser Letter to N. Kalivianakas dated 12-4-85, ECCS Pump Minimum Flow Valves.
- f.
Design Analysis No. QDC-1400-M-1170.
- g.
QCPWG (Procedure Writers Guide),
Vol.
3.
t
B.l.e.
INITIAL CONDITIONS (Student Copy)
"* The Core Spray System is in its normal standby lineup IAW QCOP 1400-01.
"* The Core Spray Pump Operability Test is required to be performed this shift.
"* An EO has vented the core spray piping, performed pre-start checks on the lB Core Spray pump, and is standing by outside the lB Core Spray pump room.
"* All personnel are cleared out of the lB Core Spray room as controlled by the EO.
"* This JPM is not time critical.
INITIATING CUE Perform the Core Spray Pump Operability Test for the "1B" Core Spray Pump IAW QCOS 1400-04.
nC J '
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Nuclear Generation Group Job Performance Measure Venting Of the Primary Containment due to High Hydrogen with a Failure of a Vent Valve to Open JPM Number: B.l.f.
Revision Number:
1 Date: 9/2002 Developed By:
Validated By:
Ins( ctor SME or Instructor Review By:
Operations Representative Date Date
/(,-//- 4.2.*
Date
B.l.f.
Revision Record (Summary)
Revision 0, This JPM is developed IAW guidelines established in NUREG 1021 Rev 8 ES-301 and Appendix C. This JPM meets the criteria of Category B. 1 "Control Room Systems," for RO/SRO candidates.
Revision 1 The JPM was revised to incorporate validation time and comments.
Information For Evaluator's Use:
UNSAT requires written comments on respective step.
- Denotes CRITICAL steps.
Number any comments in the "Comment Number" column on the following pages. Then annotate that comment in the "Comments" section at the bottom of the page. The comment section should be used to document the reason that a step is marked as unsatisfactory and to document unsatisfactory performance relating to management expectations.
Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.
The timeclock starts when the candidate acknowledges the initiating cue.
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B.l.f.
SIMULATOR SETUP INSTRUCTIONS
- 1. Reset the simulator to IC 95 (rst 95 ). This IC is a shutdown reactor, stable following a scram and is setup specifically for this JPM. If it is not available follow the directions below.
- 2. IC
Description:
The Reactor is scrammed, Group II isolation in effect, DW pressure
= 8.6 psig, Torus pressure = 6.9 psig.
NOTE:
It is okay to use a similar IC to the IC listed above, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.
- 3. Manual Actuations:
"* Depress both scram buttons to scram the Reactor then perform QCGP 2-3 actions.
"* Prevent HPCI injection by tripping HPCI with the trip latch.
"* Ensure reactor building vents have isolated and "B" SBGT train is operating.
nsure
-6, 0279, 60, 23, 24 are closed.
Start the 7 th DW cooler.
- 4. Malfunctions:
"* Cause a Group II Isolation to seal in using malfunction RP07.
(imf rpO7a) & (imf rpO7b)
"* Insert Main Steam line leak after the flow restrictors (imfms05a 0.2)
"* Override the 1-1601-61 valve closed (ior dihsll60161 close)
- 5. Remotes: NONE
- 6. Overrides:
- Override the Hydrogen recorder to 2.5 (ior aoh212406a 25)
- 7. When the above steps are completed for this and other JPMs to be run concurrently, then validate the concurrently run JPMs using the JPM Validation Checklist.
- 8. This completes the setup for this JPM.
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B.l.f.
INITIAL CONDITIONS A transient has occurred resulting in hydrogen generation.
The US has entered the Hydrogen control procedure, QGA 200-5.
Chemistry has sampled the containment atmosphere and determined that the offsite release rate will stay below the LCO when venting has commenced.
Chemistry has recommended using SBGTS as a vent path.
There are as many fans as possible operating.
SBGT is operating.
The Essential Service bus and both RPS busses are energized.
Station Director has given permission to vent (NOT OK to exceed release rates).
This JPM is not time critical.
INITIATING CUE Line-up and begin venting the Torus through SBGT in accordance with QCOP 1600-13 to reduce hydrogen concentration in the containment.
Fill in the JPM Start Time when the student acknowledges the Initiating Cue.
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B.L.f Job Performance Meas*nnre (JPM*
JPM Start Time:
\\N11
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7 LiJ Job Performance Measure f.-FPA4)
PERFORMANCE OBJECTIVE STANDARDS SAT UNSAT N/A Obtain the procedure to be used.
Procedure QCOP 1600-13 obtained.
[]
[3 F.2.
Verify closed the following Verify closed the following Primary Primary Containment valves:
Containment valves:
- a. Torus 2" Vent vlv.
AO 1-1601-61, closedlightlit.
[]
[]
[]
- b. DW2"Ventvlv.
AO 1-1601-62, closedlight lit.
[3
[3
[3
- c. Vent to SBGTS.
AO 1-1601-63, closed light lit.
[4" []
[]
- d. Torus 18" Vent vlv.
AO 1-1601-60, closed lightlit.
[
[]
[]
- e. DW 18" Vent vlv.
AO 1-1601-23, closed light lit.
[
[]
[3
- f. Vent to RX Bldg. Exh Sys.
AO 1-1601-24, closed light lit.
[< [3
[]
F.3.a.
Verify "B" SBGTS train is "B" train of SBGTS verified running.
[3
[3
[3 running.
F.3.b.
Announce evacuation of SBGT Announcement made over plant
[]
[]
[3 area and that plant radiological page.
conditions may change as containment is vented.
F.3.c.
Verify MASTER VENT MODE Verifies switch in NORM.
[3
[3
[3 switch in NORM.
F.3.d.(1)
Place the VENT ISOL SIG BYP Switch is momentarily placed in
[]
[]
[]
key switch to TORUS position TORUS position, and verifies alarm actuates.
AND alarm 901-3 A-15 verified on.
F.3.d.(2)
Open Vent to SBGTS.
Positions AO 1-1601-63 CS to open
[]
[]
[]
open light lit.
F.3.d.(3)
Attempts to open the Torus 2" Positions AO 1-1601-61 CS to open
[]
[1 Vent valve and recognizes valve identifies valve did not change fails to open.
position, open light not lit.
Notifies US of valve failure to Notifies US that 1-1601-61 valve
[]
[3
[3 open.
failed to open.
B.l.f.
PERFORMANCE OBJECTIVE STANDARDS SAT UNSAT N/A CUE: Acknowledge 1-1601-61 valve failed to open. If candidate stops at this point or requests direction from the US, ask them for their recommendation. If candidate does not offer a recommendation, tell them to continue on with procedure.
Note to evaluator: The next step in the procedure F.3.e. allows the candidate to vent the drywell if torus venting is not able to control hydrogen concentration as long as drywell pressure is less than 25nsig.
- F.3.e.(1)
Place the VENT ISOL SIG Switch is momentarily placed in
[]
[]
BYP key switch to DRYWELL position, DRYWELL position and AND verifies alarm actuates.
alarm 901-3 A-15 verified on.
F.3.e.(2)
Verifies Torus 2" Vent valve Verifies AO 1-1601-61 closed
[]
[]
- closed, closed light lit.
- F.3.e.(3)
Open Vent to SBGTS.
Verifies AO 1-1601-63 open
[]
[]
open light lit.
- F.3.e.(4)
Opens the Drywell 2" Vent Positions AO 1-1601-62 CS to open
[]
[]
- valve, open light lit.
Evaluator Note: Due to simulator set-up for this JPM, drywell pressure and hydrogen concentration will not show a reducing trend so you must cue candidate that these parameters are decreasing.
Cue: Inform candidate that drywell pressure and hydrogen concentration is dropping.
F.3.e.(6)
Monitor Release Rate.
Monitors, 1/2-1704-19, CHIMNEY
[
-[
]
GAS ACTIVITY recorder on Panel 912-4 AND 1/2-1740-202, MN CHIMNEY GAS ACTIVITY recorder 912-1.
F.3.e.(6)(a)
Verify release rate limit is Contacts Chemistry or verifies absence
[]
[]
NOT being exceeded.
of alarms 912-1 E-9 and F-9 on 912-1 to ensure limit is NOT being exceeded.
F.3.e.(7)
Logs data in log book.
Log the following information in the
[]
[]
Unit Log Book:
(a) Time of venting start & stop.
(b) Drywell and Torus pressure at time of vent start & stop.
EVALUATOR: The candidate should inform you that the task is completed.
JPM Stop Tim;e: I "IUýL 7F7 71 F1
/;ýQý25" >6'sŽIL 1'
B.l.f.
Operator's Name:
Job
Title:
RO D
SRO D
Title:
Venting Of the Primary Containment due to High Hydrogen with a Failure of a Vent Valve to Open JPM Number: B..f.
Revision Number: 1 Task Number and
Title:
SR-0001-P038, Post Accident Venting Of The Primary Containment K/A Number and Importance:
K/A: 500000 EA1.03 Rating: 3.4/3.2 Suggested Testing Environment: Simulator Actual Testing Environment:
U Simulator Q
Plant U
Control Room Testing Method: Q Simulate Faulted: U Yes N No
Perform Alternate Path: N Yes.
NO Time Critical: U Yes U No Estimated Time to Complete:
20 minutes Actual Time Used:,
minutes
References:
QCOP 1600-13, Rev. 15
-__--__.-.-,-i--
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"-1
B.l.f.
EVALUATION
SUMMARY
Were all the Critical Elements performed satisfactorily?
IU Yes IJ No The operator's performance was evaluated against the standards contained in this JPM, and has been determined to be:
U Satisfactory UJ Unsatisfactory Comments:
Evaluator's Name:
Evaluator's Signature:
(Print)
Date:
QCOP 1600-13 UNIT 1 (2)
REVISION 15
.. Continuous Use T-ACCIDENT VENTING OF THE PRIMARY CONTAINMENT A. PURPOSE The purpose of this procedure is to provide the necessary steps for post-accident venting the Primary Containment as directed by QGA or SAMGs procedures.
B. DISCUSSION B.1.
Attachment A, POST-ACCIDENT VENTING FLOWCHART, is provided to accommodate quick execution of this procedure.
It does NOT contain the level of detail that the text procedure contains, but represents the fundamental steps that must be performed in order to perform the task.
The text procedure should be referenced if more detail is required.
All supporting sections of the procedure (i.e.,
Precautions, Prerequisites, etc.) are applicable to the flowchart, as well as to the text procedure.
B.2.
This procedure will ask the operator to verify that the radioactive release rate is less than the Technical Specification release rate LCO (ODCM).
This can be accomplished by one of the following methods:
- a.
IF a release is in progress, THEN release rates less than the specified limit can be verified by the absence of alarms E-9 and F-9 on the 912-1 panel.
- b.
Calculate the release rate per QEP 0155-02 and verify that the release rate is less than the Unusual Event EAL.
- c.
IF a release is NOT in progress, THEN obtain a vent recommendation from Chemistry per QCCP 1300-01 OR IF there are indications of core damage, THEN QCHRSS 0700-02.
B.3.
The preferred method for venting the Primary Containment is through the Torus.
Studies performed by General Electric indicates a decontamination factor of up to four is provided when vented gases are required to bubble through water first.
This will also help in preventing the Torus to Drywell Vacuum Breakers from NRC C6PY
- 1
QCOP 1600-13 UNIT 1 (2)
REVISION 15 C. -PREREQUISITES C.i.
IF QGA or SAMG procedures do NOT state "OK to exceed Release Rate Limits, " THEN vent recommendation provided by the Chemistry Department.
C.2.
The RPS and Essential Service System (ESS) buses energized to supply power for vent valve solenoids.
- a.
IF power is unavailable from RPS to operate the valves in this procedure, THEN implement QCOP 1600-28 to install an alternate power supply.
L.
t
- a.
IF the QGAs or SAMGs do NOT allow exceeding Release Rate Limits AND containment is being vented to control hydrogen concentration, THEN control hydrogen concentration below 0.5%.
- b.
IF the QGAs or SAMGs allow exceeding Release Rate Limits, THEN:
(1)
LF venting to control pressure, THEN control below the Primary Containment Pressure Limit.
(2)
IF venting to control hydrogen concentratic i
THEN control Primary Containment below 6%.
D... 2 Venting the Primary Containment at high pressure can r
result in changing radiological conditions in the
_...........__....Reactor Building AND Turbine Building.
Refer to QCOA 1800-01 AND QCOA 1800-02.
NRC CePY D. PRECAUTIONS D.1.
Venting the Primary Containment, irrespective of offsite radioactive release rates, is performed to preserve the structural integrity of Primary Containment OR to control Primary Containment Hydrogen concentration.
If possible, the operator should attempt to limit the total amount of the radioactive release by controlling and maintaining pressure or Hydrogen concentration below their applicable limits rather than maintaining a continuous vent path.
WHEN a vent path is being used to control Primary Containment.......
_ parameters, THEN venting should maintain the following conditions:
)n,
- :/1
QCOP 1600-13 UNIT 1 (2)
REVISION 15
- awl, LIMTATIONS AND ACTIONS E.l.
Simultaneous venting of Unit 1 and 2 via the Augmented Primary Containment Vent (APCV) system is NOT allowed since APCV has a common line to the chimney from each unit.
IF required to vent both units, THEN the units should be alternately vented.
E.2.
IF Primary Containment is being threatened, THEN the order of procedure steps can be altered to allow initiation of vent flow before dilution flow vent fans are started.
E.3.
IF QGA and SAMG steps that direct venting are structured to allow the flexibility of venting before the applicable limit is reached, THEN appropriate timing of the vent should be determined using considerations presented the TSG Reference Manual, Attachment E.
Contact the TSC for assistance in implementing this Attachment.
F. PROCEDURE
y".1.
Operate as many of the following fans as possible to dilution flow:
- a.
Turbine Building Exhaust Fan per QCOP 5750-01.
- b.
Radwaste Exhaust Fans per QCOP 5750-03.
F.2.
Verify closed:
- a.
AO 1(2)-1601-61, TORUS 2-INCH VENT VLV.
- b.
AO 1(2)-1601-62, DW 2-INCH VENT VLV.v'
- c.
AO 1(2)-1601-63, VENT TO SBGTS.7"
- d.
AO 1(2)-1601-60, TORUS 18-INCH VENT VLV. 1"
- e.
AO 1(2)-1601-23, DW 18-INCH VENT VLV.v
- f.
AO 1(2)-1601-24, VENT TO RX BLDG EXH SYS./
NRC C 6 PY
- 1
QCOP 1600-13 UNIT 1 (2)
REVISION 15 CAUTION IF during performance of the following step the release rate exceeds the release rate limit referenced in the QGAs OR SAMGs AND the QGA OR SAMG procedures do NOT state "OK to exceed Release Rate Limits,," THEN the vent operation must be terminated.
F.3.
S.....
_ _ _I._ l
'7-
_?-*-<**...=...
IF Drywell OR Torus pressure is less than 25 psig, THEN vent through SBGT using the 2-inch vent lines:
- a.
Verify a SBGT train in operation.
- b.
Announce evacuation of SBGT train area AND that6 plant radiological conditions may change as the Primary Containment is vented.
- c.
Verify MASTER VENT MODE SWITCH in NORM.
v d.
IF Torus level is less than 30 feet AND Torus pressure is less than 25 psig, THEN vent the Torus (H.8.e) :
(1) IF a Group II Isolation signal is present AND Reactor Mode Switch is NOT in
- RUN, THEN momentarily place the VENT ISOL SIG BYP switch to TORUS position.
Verify alarm 901(2)-3 A-15 actuates.
/
(2)
Open AO 1(2)-1601-63, VENT TO SBGTS. /
(3)
Open AO 1(2)-1601-61, TORUS 2-INCH VENT VLV.*
(4)
Control amount of vent flow by cycling AO 1(2)-1601-61, TORUS 2-INCH VENT VLV between the open and close positions as required to achieve the desired Primary Containment response.
h 4-.
1-NRC CbPY #1
[
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[
t.
41
QCOP 1600-13 UNIT 1 (2)
REVISION 15 7767d (cont'd)
(5)
Monitor 1/2-1705-19, CHIMNEY GAS ACTIVITY recorder on Panel 912-4 AND 1/2-1740-202, MN CHIMNEY GAS ACTIVITY recorder on 912-1.
(a)
IF QGA or SAMG procedures do NOT state, "OK to exceed Release Rate Limits,"
THEN verify release rate limit referenced in the QGAs OR SAMGs is NOT being exceeded.
(6)
,Log the following information in the Unit Log Book:
(a)
Time of vent start AND stop.
(b)
Drywell and Torus pressure at time of vent start AND stop.
IF Torus venting is NOT able to control Primary Containment pressure/hydrogen concentration AND Drywell pressure is less than 25 psig, THEN vent the Drywell (H.8.e.):
(1) IF a Group II Isolation signal is present AND Reactor Mode Switch is NOT in Run, THEN momentarily place the VENT ISOL SIG BYP switch to DRYWELL position.
Verify alarm v 901(2)-3 A-15 actuates.
(2)
Verify close AO 1(2)-1601-61, TORUS 2-INCH v VENT VLV.
(3)
Open AO 1(2)-1601-63, VENT TO SBGTS.W (4)
Open AO 1(2)-1601-62, DW 2-INCH VENT VLV.
(5)
Control amount of vent flow by cycling AO 1(2)-1601-62, DW 2-INCH VENT VLV between the open and close positions as required to achieve the desired Primary Containment response.
NRC CbPY
- 1 "Mei 0--
QCOP 1600-13 UNIT 1 (2)
REVISION 15 F.3.e. (cont'd)
(6)
Monitor 1/2-1705-19, CHIMNEY GAS ACTIVITY recorder on Panel 912-4 AND 1/2-1740-202, S...
.MN CHIMNEY GAS ACTIVITY recorder on 912-1.
(a)
IF QGA or SAMGs procedures do NOT state, "OK to exceed Release Rate Limits,"
THEN verify the release rate limit referenced in the QGAs OR SAMGs is NOT being exceeded.
(7)
Log the following information in the Unit Log Book:
(a)
Time of vent start AND stop.
(b)
Drywell and Torus pressure at time of vent start AND stop.
- f.
WHEN any one of the following conditions is
- met, THEN continue with this procedure:
(1)
Venting is complete.
(2)
QGAs OR SAMGs do NOT give permission to exceed release rates AND release rates will be exceeded.
(3)
QGAs give permission to exceed release rates AND the 2-inch vents are inadequate to accomplish the required venting.
(4)
Pressure > 25 psig in the area being vented.
- g.
Terminate venting through SBGT:
(1) Close AO 1(2)-1601-61, TORUS 2-INCH VENT VLV.
(2)
Close AO 1(2)-1601-62, DRYWELL 2-INCH VENT VLV.
(3)
Close AO 1(2)-1601-63, VENT TO SBGTS.
(4)
IF a Group II Isolation signal was bypassed, THEN reset the Group II Isolation to clear the bypass signal.
Verify alarm 901(2)-3 A-15 clears.
(5)
IF SBGT is NOT required to remain operating, THEN shut down SBGT per QCOP 7500-02.
NRC COPY
- 1 r-ii F
QCOP 1600-13 UNIT 1 (2)
REVISION 15 F.4.
IF QGA procedures state, "OK to exceed Release Rate
.lim i/si," THEN:
- a.
Evacuate the Reactor Building AND Turbine Building.
- b.
Place MASTER VENT MODE SWITCH in APCV position.
- c.
Verify closed AO 1(2)-1699-7, VENT TO RX BLDG.
- d.
Place AO 1(2)-1601-24 CIS OVERRIDE in the OVERRIDE position AND hold for 1 second.
- e.
Simultaneously place AO 1(2)-1601-23 CIS OVERRIDE AND AO 1(2)-1601-60 CIS OVERRIDE in the OVERRIDE position AND hold for 1 second.
- f.
Open AO 1(2)-1601-24, VENT TO RX BLDG EXH SYS.
- g.
IF torus level is
<30 feet, THEN vent the torus:
(1) Open AO 1(2)-1601-60, TORUS 18-INCH VENT VLV.
(2)
Open Ao 1(2)-1699-6, VENT TO MAIN CHIMNEY.
(3)
Control amount of vent flow by cycling AO 1(2)-1699-6, VENT TO MAIN CHIMNEY between the open and close positions as required to achieve the desired Primary Containment response.
(4)
Monitor 1/2-1705-19, CHIMNEY GAS ACTIVITY recorder on Panel 912-4 AND 1/2-1740-202, MN CHIMNEY GAS ACTIVITY recorder on 912-1 to verify proper documentation of the release.
(5)
Log the following information in the Unit Log Book:
(a)
Time of vent start AND stop.
(b)
Drywell and Torus pressure at time of vent start AND stop.
NRC C6PY
- 1
QCOP 1600-13 UNIT 1 (2)
REVISION 15 F.4.
(cont'd).
- h.
IF torus venting is NOT able to control Primary Containment pressure/hydrogen concentration OR torus level > 30 ft.,
THEN vent the Drywell:
(1) Verify closed AO 1(2)-1601-60, TORUS 18-INCH VENT VLV.
(2)
Open AO 1(2)-1601-23, DW 18-INCH VENT VLV.
(3)
Open AO 1(2)-1699-6, VENT TO MAIN CHIMNEY.
(4)
Control amount of vent flow by cycling AO 1(2)-1699-6, VENT TO MAIN CHIMNEY between the open and close positions as required to achieve the desired Primary Containment response.
(5)
Monitor 1/2-1705-19, CHIMNEY GAS ACTIVITY recorder on Panel 912-4 AND 1/2-1740-202, MN CHIMNEY GAS ACTIVITY recorder on 912-1 to verify proper documentation of the release.
(6)
Log the following information in the Unit Log Book:
(a)
Time of vent start AND stop.
(b)
Drywell and Torus pressure at time of vent start AND stop.
- i.
WHEN venting is complete, THEN verify closed AO 1(2)-1699-6, VENT TO MAIN CHIMNEY.
- j.
WHEN 10 minutes have elapsed, THEN:
(1) Verify closed AO I(2)-1601-23, DW VENT VLV.
(2)
Verify closed AO 1(2)-1601-60, TORUS VENT VLV.
- k.
Close AO 1(2)-1601-24, VENT TO RX BLDG EXH SYS.
- 1.
Place MASTER VENT MODE SWITCH in NORM position.
NRC CbPY I-m I
t
- 1
QCOP 1600-13 UNIT 1 (2)
REVISION 15
- m.
WHEN time AND radiation dose rates permit, THEN drain condensation from the containment vent line:
(1) Contact Mechanical Maintenance to install a
hose connection on drain line 1(2)-1642-3/4"1, downstream of the 1(2)-1699-8 valve.
(2)
Route hose to floor drain AND throttle open 1(2)-1699-8.
(3)
WHEN draining is complete, THEN close 1 (2) -1699-8.
G. ATTACHMENTS G.1.
Attachment A Post-Accident Venting Flowchart.
H. REFERENCES H. 1.
Technical Specifications:
a TS Section 3.6.3.1, Primary Containment Oxygen Concentration.
- b.
TS Section 3.6.2.5, Drywell-to-Suppression Chamber Differential Pressure.
H. 2.
P&lDs:
- a.
M-34 (M-76),
Diagram of Pressure Suppression Piping.
- b.
M-44, Diagram of Standby Gas Treatment.
H.3.
Drawings:
- a.
Schematic Diagram PIC System Panel 901(2)-15 Trip Logic and Condenser.
- b.
4E-1509A/B Shts 1 & 2 (4E-2509A/B Shts 1 & 2),
Schematic Diagram PCI System Atmosphere Control System.
- c.
Schematic diagram PCI System MO 1(2)-1601-57 & Miscellaneous Valves 1601-20A-20B.
NRC C 6 PY
- 1
QCOP 1600-13 UNIT 1 (2)
REVISION 15 H.4.
H.-5.
Manuals:
None.
Procedures:
Kr I
H H.7.
Commitments:
None.
NRC CbPY
- a.
QCCP 1300-01, Drywell & Suppression Chamber Venting & Purging.
- b.
QCHRSS 0700-02, Containment Air Sampling Using the Gas Partitioner in Manual Mode.
- c.
QCOP 7500-01, Standby Gas Treatment System (SBGTS)
Standby Operation and Start-up.
- d.
QCOP 7500-02, Standby Gas Treatment System (SBGTS)
Shutdown.
- e.
QCOP 5750-01, Turbine Building Ventilation System.
- f.
QCOP 5750-02, Reactor Building Ventilation System.
- g.
QCOP 5750-03, Radwaste Building Ventilation System.
- h.
QCOA 1800-01, Area High Radiation.
- i.
QCOA 1800-02, High Airborne Activity.
- j.
QEP 0155-02, Estimating the Total Station Noble Gas Release Rate.
- k.
QCOP 1600-28, Installing Alternate Power Supply to Primary Containment Vent and Purge Valves.
H.6.
UFSAR:
- a.
Section 6.2, Containment Systems.
2..
....i.........
- 1
QCOP 1600-13 UNIT 1 (2)
REVISION 15 11.8.
Others..
- a.
DVR 4-2-86-044, Loss of DW to Torus DP.
- b.
Generic Letter 89-16, U.S. Nuclear Regulatory Commission Letter "Installation of a Hardened Wetwell Vent," September 1, 1989.
- c.
Letter from Mr.
M. H. Richter to U.S. Nuclear Regulatory Commission, "Quad Cities Station Units 1 and 2 Response to Generic Letter 89-16, October 30, 1989.
- d.
Quad Cities Unit 1 (DPR-29) and Unit 2 (DPR-30),
Appendix A to Operating License DPR-29/30, Technical Specification and Bases, through Amendment 119/115 -
September 1, 1989.
- e.
Letter/calculation from J.A. Dawn to R.L. Bax,
- 199972, Venting Containment through SBGT.....
- f.
QCPWG (Procedure Writers Guide) Vol 3.
NRC CbPY
- 1
QCOP 1600-13 UNIT 1 (2)
REVISION 15 ATTACHMENT A (Page 1 of 5)
POST-ACCIDENT VENTING FLOWCHART L
SSTART While in this procedure:
Log each venting start and stop.
Operate as many of the following as possible:
Turbine Building Exhaust Fans (QCOP 5750-01)
Radwaste Exhaust Fans (QCOP 5750-03)
Verify Closed:
AO 1(2)-1601-61 AO 1(2)-1601-62 AO 1(2)-1601-63 AO 1(2)-1601-60 AO 1(2)-1601-23 AO 1(2)-1601-24 Evacuate areas where dose rates will increase.
IVerify MATRVENT MODE SWITCH in NORM.I CONTINUE NEXT PAGE NRC CJQPY
- 1 r
QCOP 1600-13 UNIT 1 (2)
REVISION 15 1 ATTACHMENT A (Page_2 of 5)
POST-ACCIDENT VENTING FLOWCHART
<CONTINUE (2" Torus Vent)
IF AND THEN Release rate limit exceeded.
QGAs or SAMGs do NOT allow exceeding release rate limits.
Torus pressure >
25 psig.
Torus level > 30 ft.
Go to 2 Torus venting NOT able to control pressure/hydrogen.
QGA or SAMG permits exceeding Go to Page 4 of 5, Torus venting inadequate, release rates.
Start SBGT.
Momentarily place
_r.
VENT ISOL SIG BYP switch to TORUS.
Open:
AO ](2)-1601-63 2
/
NRC CIOPY
- 1
QCOP 1600-13 UNIT 1 (2)
REVISION 15 ATTACHMENT A (Page 3 of 5)
POST-ACCIDENT VENTING FLOWCHART (2' Drywell Vent)
IF Release rate limit exceeded.
Drywell pressure > 25 psig.
Drywell venting inadequate.
/
/
C lose:
AO 1(2)-1601-62 AO 1(2)-1601-63 Stop SBGT if no longer required.
IF QGAs or SAMGs permit exceeding release rates.
'QGAs or SAMGs do NOT permit exceeding release rates.
NRC GPY I
- 1
QCOP 1600-13 UNIT 1 (2)
REVISION 15 M.-
HENTA A (Page 4 of 5)
POST-ACCIDENT VENTING FLOWCHART (Hardended Vent)
Sim ultaneously place:
AO 1(2)-1601-23 DIS OVERRIDE AND AO 1(2)-1601-60 CIS OVERRIDE in OVERRIDE and hold for one second.
-j NRC CPY
- 1
QCOP 1600-13 UNIT 1 (2)
REVISION 15 ATTACHMENT A (Page 5 of 5)
POST-ACCIDENT VENTING FLOWCHART (Terminate Hardened Vent)
I-(final)
NRC cOPY
- 1 f-
B.l.f.
INITIAL CONDITIONS (Student Copy)
A transient has occurred resulting in hydrogen generation.
The US has entered the Hydrogen control procedure, QGA 200-5.
Chemistry has sampled the containment atmosphere and determined that the offsite release rate will stay below the LCO when venting has commenced.
Chemistry has recommended using SBGTS as a vent path.
There are as many fans as possible operating.
SBGT is operating.
The Essential Service bus and both RPS busses are energized.
Station Director has given permission to vent (NOT OK to exceed release rates).
This JPM is not time critical.
INITIATING CUE Line-up and begin venting the Torus through SBGT in accordance with QCOP 1600-13 to reduce hydrogen concentration in the containment.
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B.l.g.
Revision Record (Summary)
Revision 0, Revision 1 This JPM is developed JAW guidelines established in NUREG 1021 Rev 8 ES-301 and Appendix C. This JPM meets the criteria of Category B. 1 "Control Room Systems," for RO/SRO candidates.
The JPM was revised to incorporate validation time and comments.
Information For Evaluator's Use:
UNSAT requires written comments on respective step.
- Denotes CRITICAL steps.
Number any comments in the "Comment Number" column on the following pages. Then annotate that comment in the "Comments" section at the bottom of the page. The comment section should be used to document the reason that a step is marked as unsatisfactory and to document unsatisfactory performance relating to management expectations.
Some operations that are performed from outside of the control room may require "nimultiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.
The timeclock starts when the candidate acknowledges the initiating cue.
hJ Jr\\-
N Pag'>
F7F J/
7W
B.l.g.
SIMULATOR SETUP INSTRUCTIONS
- 1. Reset the simulator to IC 94 (rst 94). This IC is a shutdown reactor, stable following a scram and is base IC setup specifically for this JPM.
- 2. IC
Description:
NOTE:
It is okay to use a similar IC to the IC listed above, provided the IC actually used is verified to be compatible with this and other JPMs that are scheduled to be run concurrently.
- 3. Manual Actuation:
Simulator operator must control reactor pressure manually with relief valves to control pressure 800-1000 psig while candidate is reopening the MSIVS.
Ensure the Main Steam line drains are shut.
S..... *
- 4.
Malfunctions:
---*-----All-low Gp I isolation to cause scram by performing the following:
Insert, then remove, malfunction RP05 A & B.
(imf rOSa) & (imf rpOSb)
(dmf rpOSa) & (dmf rpOSb)
- 5. Remotes: NONE
- 6. Overrides: NONE
- 7. When the above steps are completed for this and other JPMs to be run concurrently, then validate the concurrently run JPMs using the JPM Validation Checklist.
- 8. This completes the setup for this JPM.
-1
B.l.g.
INITIAL CONDITIONS
"* A Group I Isolation occurred approximately 30 minutes ago on Unit 1 due to low-low reactor water level.
"* Reactor water level has been restored and is now being controlled by Feed/Condensate.
"* Another RO will control pressure between 800 and 1000 psig with relief valves.
"* The Main Steam Lines have been drained and the Steam line drain valves are shut.
"* RPV level has been maintained less than 100" during the time the MSTVs have been closed.
"* This JPM is not time critical INITIATING CUE Pressurize the Unit I Main Steam lines and re-open the MSIV's.
Fill in the JPM Start Time when the student acknowledges the Initiating Cue.
EU U EUNEEml Eun....im EnEE EUUiUiUUEnEw mEnU mBEE EMEE EEnEUNmmi~
EE EMUnHE EEnm EEnE mmm ml
B.l.g.
ob. Performance Measure (JPM)
JPM Start Time: IiiiM PERFORMANCE OBJECTIVE STANDARDS SAT UNSAT N/A Obtain procedure to be used.
Procedure QCOP 250-1 obtained.
[]
[]
[]
- F. 1.
Place MN STM ISOL RESET to Places MN STM ISOL RESET to
[]
[]
INBD.
INBD.
- F.2.
Place MN STM ISOL RESET to Places MN STM ISOL RESET to
[]
[]
F.3.
Adjus 1 A/B PRESS SETPOINT 200 Adjusts 200 psig above reactor
[]
[]
[]
psig above Reactor Pressure, OR as pressure or as high as possible.
high as possible.
- F.4.
Open Outboard MSIVs:
Opens outboard MSIVs by taking
[]
[]
- d. AO 1-203-2D red light lit indicating OPEN 2D OUTBD MSIV AO 1-203-2D red light lit indicating OPEN F.5.
Open Steamline drain valves:
Opens steamline drain valves by
[]
[]
[]
- d. MO 1-220-90D red light lit indicating OPEN STM LINE DRN VLV MO 1-220-90D red light lit indicating OPEN
- F.6.
Equalize pressure across MSIVs:
Opens steam drain valve by taking
[]
[]
- a. Open MO 1-220-1, each C/S to OPEN on 901-3.
- c. Slowly throttle Open red light lit indicating OPEN MO 1-220-3, MO 1-220-3 OUTSIDE DRN VLV indicates Mid-position OR OPEN
.r~
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B.l.g.
PERFORMANCE OBJECTIVE STANDARDS SAT UNSAT N/A F.7.
Monitor the following indications Differential Pressure is decreasing
[]
[]
[]
AND verify that differential pressure using reactor pressure across the MSIVs are decreasing instrumentation and turbine throttle pressure on PI 1-3040-10 on 901-7.
- a. Reactor Pressure
- b. PI 1-3040-10, TURB THROT PRESS (at panel 901-7)
EVALUATORS NOTE: The next step is conditional and need not be performed to satisfactorily complete this task* Stev will be per formed only if DiP dop.' not doerpawo toJ < 200D neid F.8.
IF diff. press. across MSIVs does NOT May close above and below seat
[]
[]
[3 dec. to <200 psid, THEN, at panel drains on 901-7 if D/P is not 901-7, close valves decreasing
- a. MO 1-3004A, B, C and D, MO 1-3004A, B, C and D green CONT VLVS ABOVE SEAT DRN light lit indicating CLOSED
- b. MO 1-3005, CONT VLVS BELOW SEAT DRN MO 1-3005 green light lit indicating CLOSED on 901-7.
EVALUATOR:
Unit Supervisor's permission is NOT a critical part of step F.9.
Candidate may elect to open 2 valves simultaneously to avoid a high flow isolation signal from occurring.
- F.9.
WHEN diff. press. across the MSIVs Opens inboard MSIVs by taking
[]
[3 is <200 psid each C/S to OPEN on 901-3 OR hs sOPENS AO 1-203-lA has stopped decreasing and Unit red light lit indicating OPEN Supervisor has given permission to OPENS AO 1-203-1B proceed, THEN open inboard MS1Vs:
red light lit indicating OPEN
\\N1-V
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L7J Pagj
B.l.g.
PERFORMANCE OBJECTIVE STANDARDS SAT UNSAT N/A EVALUATOR: Step F.10 is conditional and need not be performed to satisfactorily complete this task Cue candidate that step F.10 is NOT desired at this time, leave the valve closed.
F. 11.
Close Steamline drain valves:
Closes steam drain valves by taking
[]
[]
[]
- g. MO 1-220-3, green light lit indicating CLOSED OUTSIDE DRN VLV MO 1-220-3 green light lit indicating CLOSED F. 12.
Adjust lA/1B PRESS SETPOINT to EHC Pressure Setpoint adjusted to
[]
[]
[ ]
desired pressure.
920 psig (+/--10 psig)
EVALUATOR: The candidate should inform you that the task is complete, JPM Stop Time:
/ t/ *")
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B.l.g.
Operator's Name:
Job
Title:
Title:
Pressurize the Main Steam Lines JPM Number: B.l.g.
Revision Number: 1 Task Number and
Title:
SR-0250-PO1, Given a reactor plant at power when an inadvertent Group 1 isolation occurs, determine the cause, reset the Group 1, and re-open the MSIVs in accordance with QCOP 0250-01.
K/A Number and Importance:
K/A: 239001 A4.01 Rating: 4.2/4.0 Suggested Testing Environment: Simulator Actual Testing Environment:
C3 Simulator ID Plant U
Control Room Testing Method: D Simulate 01 Perform Alter Time Critical: U Yes U No Estimated Time to Complete:
25 minutes
References:
QCOP 250-01, Rev. 5 i-N Faulted: U Yes natePath: U Yes Actual Time Used:
Page
,\\1 E No 0 No
\\L minutes r
!L-L
!J /
L[
,dF-LF i
B.l.g.
EVALUATION
SUMMARY
Were all the Critical Elements performed satisfactorily?
Yes J
No The operator's performance was evaluated against the standards contained in this JPM, and has been determined to be:
!J Satisfactory C3 Unsatisfactory Comments:
Evaluator's Name:
Evaluator's Signature:
(Print)
Date:
B.l.g.
INITIAL CONDITIONS (Student Copy)
A Group I Isolation occurred approximately 3 0 minutes ago on Unit 1 due to low-low reactor water level.
"* Reactor water level has been restored and is now being controlled by Feed/Condensate.
"* Another RO will control pressure between 800 and 1000 psig with relief valves.
"* The Main Steam Lines have been drained and the Steam line drain valves are shut.
"* RPV level has been maintained less than 100" during the time the MSIVs have been closed.
"* This JPM is not time critical INITIATING CUE Pressurize the Unit 1 Main Steam lines and re-open the MSIV's.
m i
m i
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i mMEN EKm ENE fl m
m EmEHE i NNEmm Ei m
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QCOP 0250-01 UNIT 1(2)
REVISION 5 Continuous Use PRESSURIZING THE MAIN STEAM LINES A. PURPOSE The purpose of this procedure is to provide instructions for pressurizing the Main Steam Lines during a Unit Startup OR when recovering from a Group I Primary Containment Isolation.
B. DISCUSSION None.
j C. PREREQUISITES C.I.
IF' QGAs direct bypassing one or more Group I Isolation Signals, THEN signal has been bypassed per QCOP 0201-10 OR QCOP 0250-02, as specified in the QGAs.
1'/4 C.2.
RPV level has been maintained < 100 inches during the time the MSIVs have been closed.
0 "D. PRECAUTIONS NOTE The following precaution does NOT apply when the QGA procedures direct use of this procedure to depressurize the RPV and permission has been given to exceed RPV cooldown rates.
D.1.
During the performance of this procedure, caution should be used when opening Main Steam Line. Drain Valves to ensure that Reactor cooldown rate does NOT exceed 100OF/hour.
E. LIMITATIONS AND ACTIONS None.
F. PROCEDURE
F.1.
Place MN STM ISOL RESET to INBD position.
NRC C6-PY
- 1
QCOP 0250-01 UNIT 1(2)
REVISION 5 Monitor differential pressure decreasing across the MSIVs by monitoring Reactor Pressure AND 1(2)-3040-10, TURB THROT PRESS (at 901(2)-7 Panel)..
F.8.
IF differential pressure across MSIVs does NOT decrease to < 200 psid, THEN at Panel 901(2)-7, close:
- a.
MO 1(2)-3004A,B,C and D, CONT VLVS ABOVE SEAT DRN.
_/__
- b.
MO 1(2)-3005, CONT VLVS BELOW SEAT DRN.
/'
CAUTION IF Inboard MSIVs are going to be opened with a dP present, THEN consideration should be given to opening two (2) valves simultaneously in order to avoid a possible Group isolation due to Main Steam Line high flow rates.
F.9.
WHEN differential pressure across the MSIVs is
< 200 psid, OR has stopped decreasing and Unit Supervisor has given permission to proceed, THEN open Inboard MSIVs:
- a.
- b.
42
- c.
- d.
F.10.
IF desired, THEN open the following valves:
- a.
MO 1(2)-3004A-,B,C and D, CONT VLVS ABOVE SEAT DRN.
- b.
MO 1(2)-3005, CONT VLVS BELOW SEAT DRN.
- c.
One of the following:
(1) AO 1(2)-5401A and B, SJAE SUCT VLVS.
(2)
AO 1(2)-5402A and B, SJAE SUCT VLVS.
NRC COPY
- 1
QCOP 0250-01 UNIT 1(2)
REVISION 5 F.11.
Close drain valves:
- a.
MO 1(2)-220-90A, STM LINE DRN VLV.
- b.
MO 1(2)-220-90B, STM LINE DRN VLV.
- c.
MO 1(2)-220-90C, STM LINE DRN VLV.
- d.
MO 1(2)-220-90D, STM LINE DRN VLV.
- e.
MO 1(2)-220-1, STM DRN ISOL VLV.
f,.-
MO 1(2)-220-2, STM DRN ISOL VLV.
- g.
MO 1(2)-220-3, OUTSIDE DRN VLV.
F.12.
Adjust 1(2)A/B PRESS SETPOINT to desired pressure.
G. ATTACHMENTS H. REFERENCES H. 1.
Technical Specifications:
None.
H. 2.
P&lDs:
- 1 None.
H. 3.
Drawings:
E
- a.
M-13 (M-60),
Diagram of Main Steam Piping.
- b.
Schematic Diagram PCI System.
H.4.
Manuals:
.None.
H..5.
Procedures:
- a.
QCOP 0201-10, Bypassing Isolation Signals to Allow Drywell Flooding or Alternate RPV Blowdown.
- b.
QCOP 0250-02, Bypassing MSIV Low Low Reactor Water.,
Level Group I Isolation Signal 1 NRC COPY
- 1.
I
QCOP 0250-01 UNIT 1(2)
REVISION 5 UFSAR:
None.
H.7.
Commitments:
None.
H.8.
Others:
- a.
QCPWG (Procedure Writers Guide) Vol 3.
K-/
W&P
,.-
.'z--
(final)
NRC COPY
- /1 owl H.6.
'[
Fpm:
,¸
- =* ** *
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Ex e INulen
,.--Nuclea~r Nuclear Generation Group Job Performance Measure Aligning Fire Protection Water to SSMP Room Cooler JPM Number: B.2.a.
Revision Number: 01 Date: 09/2002 Developed By:
Validated By:
Review By:
Instl~ctor SME or Instructor Operations Representative Date Date Date
-I I
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.- n*-
_.* ¸ *,**.......
- ,,==-..
um..
-0.
Or
-4!MNFM
B.2.a.
SJob Performance Measure (JPM)
Revision Record (Summary)
Revision 0, The reason for this JPM is to demonstrate the ability to terminate one of the twenty most probable Core Damage Sequences.
This JPM is developed IAW guidelines established in NUREG 1021 Rev 8 ES-301 and Appendix C. This JPM meets the criteria of Category B].2 "Facility Walk-Through," for RO/SRO candidates.
Revision 1 The JPM was revised to incorporate validation time and comments.
Information For Evaluator's Use:
All components are located in the Safe Shutdown Makeup Pump Room on the south wall.
UNSAT requires written comments on respective step.
- Denotes CRITICAL steps.
sNte Step #3 is not critical due to having the bypass valVe open is a nolral-inup for this
.syste unless freon head pressure for the room cooler is >260 psig. This was validated by the Facility Representative.
Number any comments in the "Comment Number" column on the following pages. Then annotate that comment in the "Comments" section at the bottom of the page. The comment section should be used to document the reason that a step is marked as unsatisfactory and to document unsatisfactory performance relating to management expectations.
Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.
The timeclock starts when the candidate acknowledges the initiating cue.
B.2.a.
P""
M.,.Job Performance Measure (JPM)
INITIAL CONDITIONS There is a severe fire in RB IS. SSMP is the injection source for U-1. Service Water is no longer available to the SSMP Room Cooler.
You have been issued a flashlight, radio, and the AR tool box which includes; a V key, an R-Key, VHR-key, a Fire Lock key, an S-Key, a straight blade screwdriver, a wire cutters, a crescent wrench.
This JPM is not time critical.
INITIATING CUE Align Fire Protection Water to SSMP Room Cooler in accordance with QCARP 0010-01 Attachment D.
Provide examinee with:
Copy of QCARP 0010-01 Attachment D.
Fill in the JPM Start Time when the student acknowledges the Initiating Cue.
uu.u.uuu.u.uE.u.uu..Nu..u.u..u.u.
UUEEUEUUEUEUEUEEUUUUUUEEUEUEEEUUEE
B.2.a.
JPM Start Time:
PERFORMANCE OBJECTIVE STANDARDS SAT UNSAT N/A
- Attachment D, Close 1/2-2901-25, SERV Turns 1/2-2901-25 valve hand
[]
[]
[]
step 1 WTR TO SAFE wheel clockwise until valve no SHUTDOWN PMP RM longer moves.
CUE: Indicate to the candidate that the valve will not longer turn after the proper technique is demonstrated.
- Attachment D, Unlock and Open Selects "S" Key and unlocks
[]
[]
[]
step 2 V2-2901-9 FIRE 1/2/-2901-9 turns valve hand PROTECTION WTR TO wheel counterclockwise until SAFE SHUTDOWN PMP valve no longer moves.
CUE: Indic* fe to the candidate that the lock is unlocked and that the valve will no longer turn after the nep technique is demonstrted.
Attacl t
Close 1/2-2999-9, SERVICE Turns 1/2-2999-9 valve hand
[]
[]
[]
step 3 WATER TO SSMP ROOM wheel clockwise until valve no COOLER BYPASS VALVE.
longer moves.
CUE: Indicate to the candidate that the valve will not longer turn after the proper technique is demonstrated.
Attachment D, Verify SSMP Room Cooler Checks to see if cooler is
[]
[]
[3 step 4 Operation.
cooling room.
CUE: After proper checks are made for Cooler operation (Proper checks should include that the candidate listens or feels for cool airflow discharging from the cooler, or verifying that the room is getting cooler), indicate to the candidate that the room is becoming cooler.
Attachment D, Notify UI US that steps are Proper communication
[]
[]
[3 step 5 complete.
techniques.
CUE: When informed, acknowledge as Unit One Unit Supervisor that you understand that the SSMP Room Cooler is lined up to the fire header.
Evaluator Note: Candidate should state that the JPM is complete.
- CRITICAL STEP JPM Stop Time:
3U33*UE*UEUEEUEUUEE.UUEUEE.UU.EE.E....El U**E****E**l*EUE*U*UE*U*E
- u**m**l**
No
_i
B.2.a.
-Job Performance Measure (JPM)
Operator's Name:
Job
Title:
Title:
Align Fire Protection Water to SSMP Room Cooler JPM Number: B.2.a.
Revision Number: 1 Task Number and
Title:
SN 2900-P08 Given Unit 1 in an QCARP condition, transfer SSMP HVAC cooling water supply to the fire header and verify SSMP room cooler operation in accordance with QCARP 0010-01 Attachment D. (Important PSA task/transferring cooling water supply has Risk Achievement Worth (RAW) ranging from 1.25 alone to 655 in combination with other actions.
Accomplishing this task terminates 1 of the 20 most probable core damage sequences)
K/A Number and Importance:
K/A: 295018 AA1.01 RATING: 3.3/3.4 Suggested Testing Environment: Plant Actual Testing Environment:
Testing Method: IJ Simulate El Perform Time Critical: Q Yes N No L)
Simulator D
Plant C3 Control Room Faulted: U Yes Alternate Path: U Yes Estimated Time to Complete:
10 minutes Actual Time Used:
References:
QCARP 0010-01 Attachment D, Rev. 1
r
=
U U
No No minutes
B.2.a.
EVALUATION
SUMMARY
Were all the Critical Elements performed satisfactorily?
U Yes U
No The operator's performance was evaluated against the standards contained in this JPM, and has been determined to be:
U Satisfactory Ul Unsatisfactory Comments:
Evaluator's Name:
Evaluator's Signature:
(Print)
Date:
I
- 1r-I U
'P-"
\\-'*
EmrI iLJLI UFL--.j
B.2.a.
INITIAL CONDITIONS (Student Copy)
There is a severe fire in RB 1S. SSMP is the injection source for U-1. Service Water is no longer available to the SSMP Room Cooler.
You have been issued a flashlight, radio, and the AR tool box which includes; a V key, an R-Key, VHR-key, a Fire Lock key, an S-Key, a straight blade screwdriver, a wire cutters, a crescent wrench.
This JPM is not time critical.
INITIATING CUE Align Fire Protection Water to S SMP Room Cooler in accordance with QCARP 00 10-01 Attachment D.
- EEEUEUEEEUEUEUEUUUEUUUUEUEEUEEUEUUEUUU
- EUUUUUUUEEUUUEUEEUUUEEUEU..u....,
Mý-
QCARP 0010-01 Cb~aLtQt~
cp',UNIT 1
REVISION 1 ATTACHMENT D (Page 1 of 1)
ALIGNING FIRE PROTECTION WATER TO SSMP ROOM COOLER
- 1.
Close 1/2-2901-25, SERV WTR TO SAFE SHUTDOWN PMP RM HVAC CLR SV.
- 2.
Unlock and open 1/2-2901-9, FIRE PROTECTION WTR TO SAFE SHUTDOWN PMP RM HVAC CLR SV.
- 3.
Close 1/2-2999-9, SERVICE WATER TO SSMP ROOM COOLER BYPASS VALVE.
- 4.
Verify SSMP Room Cooler operation.
- 5.
Notify Ul us that steps are complete..
NRC CF:Y
- 1
Exel nu,.
Nuclear I
Nuclear Generation Group Job Performance Measure Depressurize the Scram Air Header JPM Number: B.2.b.
Revision Number: 1 Date: 09/2002 Developed By:
Validated By:
Review By:
la?
L-.0 lnstr ctor SME or Instructor
,q",1 C11 b 4 U 61J Operations Representative ce c P1 5<
if
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L/L Date Date
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Date
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B.2.b.
Revision Record (Summary)
Revision 0 Revision 1 This JPM is developed IAW guidelines established in NUREG 1021 Rev 8 ES-301 and Appendix C. This JPM meets the criteria of Category B.2 "Facility Walk-Through," for RO/SRO candidates.
The JPM was revised to incorporate validation time and comments.
Information For Evaluator's Use:
All components are located in the U-2 reactor building 595' elevation near the southeast comer of the north CRD bank.
UNSAT requires written comments on respective step.
- Denotes CRITICAL steps.
Number any comments in the "Comment Number" column on the following pages. Then annotate that comment in the "Comments" section at the bottom of the page. The comment section should be used to document the reason that a step is marked as unsatisfactory and to document unsatisfactory performance relating to management expectations.
Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.
The timeclock starts when the candidate acknowledges the initiating cue.
mmu.m.mmuumuluumR.i...uim.m E uuuui mimmui.m m..
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B.2.b.
INITIAL CONDITIONS An ATWS has occurred on Unit 2 with reactor power currently at 35%.
The Control Room is in QGA 101 and attempting to insert Control Rods.
The Unit Supervisor has directed performance of QCOP 0300-28 This JPM is not time critical INITIATING CUE Vent the U-2 scram air header to insert control rods in accordance with QCOP 0300-28 step F.3.
Provide candidate a copy of QCOP 0300-28.
Fill in the JPM Start Time when the student acknowledges the Initiating Cue.
IIIIIIIIIIIIIIIIIIIIIIIIIIIIuiiiiiiiiiiiiiiiiiiiiiiiiiiiiii............ii
B.2.b.
JPM Start Time:
PERFORMANCE i OBJECTIVE STANDARDS I SAT UNSAT N/A
--- i ------ -------
- F.3.a.(1)
Close OR verify closed Rotates 2-301-147A AND
[]
[]
[]
both 2-301-147A AND B, 147B handwheels clockwise INST AIR TO SCRAM VLV until they do not turn any PILOT AIR HDR A/B (FILT) further.
INLET VLV.
N L E T V L.- --------------------
l Cue:
You have rotated the handwheels clockwise and they will not turn any further.
- F.3.a.(2)
Manually open RV 2-Lifts handle on RV 2-0399-24.
[]
[]
[]
0399-24 SCRAM AIR RELIEF VALVE RV, by itting thle reliet valve handle.
Cue:
You heard air blowing for several seconds, the flow then slowed and finally stopped. The Control Room reports that all the control rods have fully inserted. Restore the scram air header.
T---------------*------I
'r F-3-.(I)
Close RV 2-0399-24 Releases handle on RV2-.
['
[]
[]
b....
SCRAM AIR RELIEF 0399-24.
jVALVE RV".
Cue:
You have released the handle on the Relief Valve and it has returned to its original position.
T--------
F.3.b.
Open either the 2-301-I Rotates 2-301-147A OR 147B..
[] -]
147A OR B, INST AIR TO handwheel counterclockwise SCRAM VLV PILOT AIR until it does not turn any HDR A/B (FILT) INLET.
i further.
Cue:
You have rotated the handwheel counterclockwise and it will not turn any further. If asked, scram air header pressure indication is 70 psig and rising.
EVALUATOR:
The candidate should inform you that the task is complete.
JPM Stop Time:
n ilEl UEUEEi UEEEnUUUUEEEUUEEEni ElE.l.UEam1gnnui iNn n
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B.2.b.
Operator's Name:
Job
Title:
Title:
Depressurize the scram air header JPM Number: B.2.b.
Revision Number: 1 Task Number and
Title:
SRN-0300-TP019 - Given a reactor plant in an ATWS condition (QGA),
locally isolate and depressurize the scram air header in accordance with QCOP 300-28.
K/A Number and Importance:
K/A: 295037 EA1.03 Rating: 4.1/4.1 Suggested Testing Environment: Plant Actual Testing Environment:
.Testing Method:
UJ Simulate U Perform Time Critical: Q Yes E No Estimated Time to Complete:
10 minutes
References:
QCOP 0300-28 Rev. 19 Q
Simulator Ll Plant Ul Control Room Faulted: U Yes Alternate Path: IJ Yes Actual Time Used:
E No N No minutes
B.2.b.
... Job P erform ance M easure (JP M )
SEVALUATO UMAY Were all the Critical Elements performed satisfactorily?
U Yes U
No The operator's performance was evaluated against the standards contained in this JPM, and has been determined to be:
U Satisfactory Q Unsatisfactory Comments:
Evaluator's Name:
Evaluator's Signature:
(Print)
Date:
MO
/ r7 K Pag, 1
~
' 7 _ 7
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UNIT 1 (2)
Cdc tc Coll REVISION 19 Continuous Use
-ALTERNATE CONTROL ROD INSERTION A. PURPOSE The purpose of this procedure is to provide alternate methods for inserting Control Rods when Control Rods did NOT insert on a Reactor Scram condition.
B. DISCUSSION B.1.
Attachment A, ALTERNATE CONTROL ROD INSERTION FLOWCHART, is provided to accommodate quick execution of this procedure.
It does NOT contain the level of detail that the text procedure contains, but represents the fundamental steps that must be performed in order to perform the task.
The text procedure should be referenced if more detail is required and to document restoration for systems that were altered to accomplish rod insertion.
All supporting sections of the procedure (i.e.,
Precautions, Prerequisites, etc.) are applicable to the flowchart as well as to the text procedure.
B.2.
This procedure provides several alternate methods for Control Rod insertion. The alternate methods described in this procedure fall into two categories; insertion of all Control Rods simultaneously and individual Control Rod insertion.
Simultaneous insertion of all Control Rods is the preferred method but individual Control Rod insertion should be performed concurrently.
B.3.
Methods for inserting all Control Rods simultaneously:
- a.
De-energizing Scram Solenoids.
This step removes the scram solenoid fuses to open all the scram valves.
- b.
Depressurizing Scram Air Header.
This step vents the air in the scram air header to fail open the scram valves.
1 NR*C COPY
- 1
QCOP 0300-28 UNIT 1(2)
REVISION 19
).
.B.3 (cont'd)
- c.
Manual Reactor Scram.
This step provides for resetting the Reactor scram (by normal means or by jumpering out all Reactor scram signals and ARI) to allow draining of the Scram Discharge Volume and insertion of a manual scram signal.
B.4.
Methods that insert one Control Rod at a time:
- a.
Individual Control Rod Scramming.
This step provides for resetting the Reactor scram (by normal means or by jumpering out all Reactor scram signals and ARI) to allow draining of the SDV and individual scram insertion of Control Rods from the scram test panel.
- b.
Manual Control Rod insertion.
This step provides for inserting Control Rods by use of the normal Reactor Manual Control System.
B.5.
Verification steps within this procedure may be___________..
Sperformed when time permits and therefore are allowed t6 be performed out of sequence.
C. PRMEQUISITES C.l.
QGAs OR SAMGs have directed use of this procedure.
....D_-PRECAUTIONS D.1.
Exercise caution when installing jumpers OR blocks due to potentially energized circuits.
E. -LIMITATIONS AND ACTIONS E.1.
IF the POWER leg of QGA 101 is exited AND SAMG is NOT in progress, THEN:
- a.
IF Boron injection is in progress, THEN terminate Boron injection.
b.
Enter QCGP 2-3.
- c.
Continue this procedure at step-Fp F.'- 8 2
NRC COPY
- 1 F:
QCOP 0300-28 UNIT 1(2)
REVISION 19
.E.2.
IF repetitive steps are in progress that insert individual control rods (e.g., manual insertion using RMC, individual rod scramming, etc.) AND the method is NOT successful, THEN that method may be stopped following 2 or 3 attempts on rods associated with each CRD bank.
E.3.
Documentation of jumper or fuse manipulation may be performed any time after the appropriate step is completed and will typically be done when plant conditions are stable enough to allow sufficient time.
F. PROCEDURE
F.1.
IF ALL Scram Valves are open, as indicated by the blue scram lights on the full core display being lit, THEN go to step F.4.
NOTE The next three concurrently.
required prior The next three steps of this procedure are to be implemented Completion of the next three steps is NOT to implementing subsequent procedure steps.
steps are:
De-energizing scram solenoids.
Manual control rod insertion.
F.2.
IF ALL Scram Valves are NOT open, as indicated by the blue scram lights NOT being lit on full core display, THEN remove the following fuses to de-energize the scram solenoids:
- a.
At Panel 901(2)-15, Terminal Board "C":
(1) 590-715A, F5.
(2) 590-715C, F6.
(3) 590-715E, F7.
(4) 590-715G, F8.
3 NRC COPY
- 1
QCOP 0300-28 UNIT 1(2)
REVISION 19 I F I
r I-d)
- b.
At Panel 901(2)-17 Terminal Board "C":
(1) 590-715B, F5.
(2) 590-715D, F6.
(3) 590-715F, F7.
(4) 590-715H, F8.
- c.
WHEN Control Rods stop moving inward OR NO Control Rod movement occurs, THEN re-install fuses:
(1) At Panel 901(2)-15, Terminal Board "C":
(a) 590-715A, F5.
(b) 590-715C, F6.
(c) 590-715E, F7.
(d) 590-715G, F8.
(2)
At Panel 901(2)-17 Terminal Board "C":
(a) 590-715B, F5.
(b) 590-715D, F6.
(c) 590-715F, F7.
(d) 590-715H, F8.
I-..
4 NRC COPY
- 1
QCOP 0300-28 UNIT 1(2)
REVISION 19 "F.3.
IF ALL Scram Valves are NOT open, as indicated by the blue scram lights NOT being lit on full core display, THEN vent the scram air header:
NOTE While the scram air header is bled down in this step, it may NOT be possible to drive rods manually due to loss of motive air to FCVs.
- a.
On Reactor Building ist Floor by Control Rod Drive Flow Control Station:
(1)
Close OR verify closed both 1(2)-301-147A AND B, INST AIR TO SCRAM VLV PILOT AIR HDR A/B (FILT) INLET VLV.
(2)
Manually open RV 1(2)-0399-24, SCRAM AIR RELIEF VALVE RV, by lifting the relief valve handle.
WN-Control Rods stop moving inward OR NO Control Rod movement occurs, THEN restore Scram Air Header:
(1)
Close RV 1(2)-0399-24, SCRAM AIR RELIEF VALVE RV.
(2)
Open either the 1(2)-301-147A OR B, INST AIR TO SCRAM VLV PILOT AIR HDR A/B (FILT) INLET VLV, that was repositioned in step F.3.a.(i).
F.4.
Perform manual Control Rod insertion:
- a.
IF a CRD Pump is NOT' operating, THEN start a CRD Pump per QCOP 0300-01.
- b.
IF NEITHER 1(2)A/B CRD Pumps can be started, THEN perform QCOP 0300-19 (cross tie of Unit 1 and 2 CRD Pumps)..
- c.
IF a CRD Pump is operating, THEN:
(1)
-IF at ANY TIME during the performance
_ZNýWa f
0_his oced-uqr aCRD pump
- trips, THEN restart the CRD Pump per QCOP. 0300-01 AND continue in this step.
.5
\\
NRC COPY
- 1
F.4.c (cont'd) 4 QCOP 0300-28 UNIT 1(2)
REVISION 19 (2)
IF at ANY TIME during per-forman6e&of this procedure additional drive pressure is required, THEN throttle MO 1(2)-302-8, U-1(2) DRIVE PRESS
(3)
IF at ANY TIME during the performance of this procedure rods can NOT be
- -,driven due to insufficient drive water pressure, THEN close 1(2)-301-25, U-I(2)
CRD CHARGING WTR SV, located in CRD Master Flow Control area, Reactor Building 1st Floor.
(4)
Place RWM to BY position.
(5)
Select a CRAM Rod that is NOT fully inserted AND continuously drive UNTIL fully inserted to position 00 using the EMERGENCY IN switch OR ROD MOVEMENT CONT switch.
(6)
IF Control Rod inward motion is observed, THEN continue inserti ng CRAM Rods until all CRAM Rods are inserted.
(7)
Select a center Control Rod that is NOT fully inserted AND continuously drive UNTIL fully inserted to position 00 using the EMERGENCY IN switch OR ROD MOVEMENT CONT switch.
(8)
IF Control Rod inward motion is observed, THEN continue inserting Control Rods by spiraling out from the central core locations to peripheral locations UNTIL ALL Control Rods are inserted to OR beyond position 04.
Ensure movable rods are NOT skipped as you work out from the center.
Perform scram reset AND SDV draining:
- a.
Place DISCH VOL HI WTR BYP keylock switch to BYPASS position.
6 NRC COPY #1 F.5.
L=
QCOP 0300-28 UNIT 1(2)
REVISION 19 F.5 (cont'd)
CAUTION Unit 1 Only:
I_ the Feedwater Level Control System is in
- AUTO, THEN resetting the Reactor Scram will return Feedwater Level Control to its tape setpoint value, possibly resulting in a sudden reactivity addition, Turbine trip or Reactor Feed Pump trip due to the increase in Feedwater flow and RPV level.
NOTE Unit 2 Only: Reset of Scram > 20 seconds after initiation will have NO effect on the FWLC System.
Reset of Scram within 20 seconds will deactivate the feedwater flow scram profile if level > 15" and result in a smooth ramp of the level setpoint from actual water level to the master controller setting.
....~~~................................................
- b.
IF a RPV level transient is anticipated, THEN control the RPV level transient by adjusting the Feedwater Level Control level setpoint OR taking manual control of the Feedwater Regulating Valves.
- c.
Reset Reactor Scram.
~~.1- ___________________
fU~fW~uIUEMIN~
7 NRC COPY
- 1
QCOP 0300-28 UNIT 1(2)
REVISION 19 F.5.
(cont'd)
CAUTION The next step bypasses ALL automatic RPS Scram signals!
- d.
IF Reactor Scram does NOT reset, THEN jumper out Reactor scram by installing jumpers, located in QGA Equipment Storage Drawer, as follows:
(1) Install jumpers in Panel 901(2)-15:
JUMPER No.
INIT (a)
Jumper between terminal board A, point 14 AND terminal board A, point 76.
Verification (b)
Jumper between terminal board E, point 54 AND terminal board E, point 90.
Verification (2)
Install jumpers in Panel 901(2)-17:
(a)
Jumper between terminal board A, point 76 AND terminal board A, point 86.
Verification (b)
Jumper between terminal board E, point 54 AND terminal board E, point 90.
Verification 8
NRC COPY
- 1
)
4--
F h
I-I
[
QCOP 0300-28 UNIT 1(2)
REVISION 19 F.5.d. (cont'd)
CAUTION Unit 1 Only:
IF the Feedwater Level Control System is in
- AUTO, THEN resetting the Reactor Scram will return Feedwater Level Control to its tape setpoint value, possibly resulting in a sudden reactivity addition, Turbine trip or Reactor Feed Pump trip due to the increase in Feedwater flow and RPV level.
Unit 20nly:
Reset of scram > 20 seconds after initiation will have NO effect on the FWLC System.
(3)
LF a RPV level transient is anticipated, THEN control the RPV level transient by adjusting the Feedwater Level Control level setpoint OR taking manual control of the Feedwater Regulating Valves.
(4)
Reset Reactor Scram.
-I !..*
CAUTION This next step prevents automatic operation of ARI valves by removing the ARI valve power supply.
- e.
IF scram valves are open, THEN pull the following fuses, located in Auxiliary Electrical Room, to allow automatic closure of ARI valves:
(1)
At Panel 2201(2)-70A:
(a)
Fuse F20A, second fuse from bottom of fuse block.
(b)
Fuse F21A, bottom fuse of fuse block.
9 NRC COPY
- 1
F...
- e.
(cont'd)
QCOP 0300-28 UNIT 1(2)
REVISION 19 (2)
At Panel 2201(2)-70B:.
(a)
Fuse F20B, second fuse from bottom of fuse block.
(b)
Fuse F21B, bottom fuse of fuse block.
F.6.
IF control rods inserted as a result of the previous scram signal, THEN:
r
- a.
b
- c.
F..
IF RPV pressure is less than 700 psig, THEN open 1(2)-301-25, U-1(2)
CRD CHARGING WTR SV, to establish charging pressure.
Coordinate opening of 1(2)-301-25 with NSO driving rods.
(1) WHEN the majority of CRD HCUs are
- charged, THEN close 1(2)-301-25, U-1(2)
WHEN SDV has drained as indicated by alarm 901(2)-5 A-14, CHANNEL A/B DISCH VOLUME HIGH LEVEL, reset, THEN proceed.
WHEN Reactor Scram is reset AND CRD scram pressure is available, THEN initiate a manual Reactor Scram.
(1) IF ALL Control Rods are NOT inserted to or beyond position 04 BUT Control Rods did move, THEN repeat steps F.5. AND F.6.
F.7.
Perform Single Control Rod Scram Insertion:
- a.
Place DISCH VOL HI WTR BYP keylock switch to BYPASS position.
- b.
IF RPV pressure is
< 700 psig, THEN open 1(2)-301-25, U-1(2)
CRD CHARGING WTR SV, to establish charging pressure.
Coordinate opening of 1(2)-301-25 with NSO driving rods.
(1) WHEN the majority of CRD HCUs are charged, THEN close 1(2)-301-25, U-1(2)
10 NRC COPY
- 1 I.
f I..
L
QCOP 0300-28 UNIT 1(2)
REVISION 19
... "+=
F.7.__(cont'd)
- c.
WHEN SDV has drained as indicated by alarm 901(2)-5 A-14, CHANNEL A/B DISCH VOLUME HIGH LEVEL, reset, THEN proceed.
- d.
WHEN Reactor scram is reset AND CRD scram pressure is available AND SDV has drained, THEN:
(1) Scram a CRAM Control Rod that is NOT fully inserted by repositioning Control Rod scram toggle switch located on Panel 901(2)-16 to the full up position.
(2)
WHEN Control Rod inward movement stops, THEN return scram switch to normal.
(3)
Continue inserting CRAM Rods UNTIL ALL movable CRAM Rods are inserted to or beyond position 04.
(4)
WHEN all movable CRAM Rods are inserted, THEN scram a center Control Rod that is NOT fully inserted by repositioning Control Rod scram toggle switch located on Panel 902(2)-16 to the full up position.
(5)
WHEN Control Rod inward movement stops, THEN return scram switch to normal.
(6)
Continue inserting Control Rods by spiraling out from the center core locations to peripheral locations UNTIL ALL Control Rods are inserted to or beyond position 04.
Ensure movable rods are NOT skipped as you work out from the center.
11 NRC COPY
- //1
p -
QCOP 0300-28 UNIT 1(2)
REVISION 19
)F K-T F
IF Reactor Scram was jumpered AND jumpers are NO longer required, THEN remove jumpers:
- a.
Remove jumpers in Panel 901(2)-15:
JUMPER No.
INIT (1) Jumper between terminal board A, point 14 AND terminal board A, point 76.
(a)
Verification (2)
Jumper between terminal board E, point 54 AND terminal board E, point 90.
(a)
Verification
- b.
Remove jumpers in Panel 901(2)-17:
(1)
Jumper between terminal board A, point 76 AND terminal board A, point 86.
(a)
Verification (2)
Jumper between terminal board E, point 54 AND terminal board E, point 90.
(a)
Verification F.9.
IF fuses for scram solenoids were removed, THEN verify fuses re-installed:
- a.
At Panel 901(2)-15, Terminal Board "C":
(1) 590-715A, F5.
(2) 590-715C, F6.
(3) 590-715E, F7.
r S...
(4) 590-715G, F8.
12 NRC COPY
- 1 L
QCOP 0300-28 UNIT 1(2)
REVISION 19 F.9. (cont'd)
- b.
At Panel 901(2)-17 Terminal Board "C":
(1) 590-715B, F5.
(2) 590-715D, F6.
(3) 590-715F, F7.
(4) 590-715H, F8.
C.
Verified by:
Date SRO F.10.
IF ARI fuses were pulled AND are NO longer required to remain pulled, THEN install fuses in Auxiliary Electrical Room:
- a.
At Panel 2201(2)-70A, in upper left hand corner fuse block:
(1) Fuse F20A, second fuse from bottom of fuse block.
(2)
Fuse F21A, bottom fuse of fuse block.
.b.
At Panel 2201(2)-70B, in upper left hand corner fuse block:
(1) Fuse F20B, second fuse from bottom of fuse block.
(2)
Fuse F21B, bottom fuse of fuse block.
- c.
Verified by:
Date SRO F. 11.
IF scram air header was vented, THEN open one of the following valves:
- a.
1( 2 )-301-147A, INST AIR TO SCRAM VLV PILOT AIR HDR A (FILT) INLET VLV.
- b.
1(2)-301-147B, INST AIR TO SCRAM VLV PILOT AIR HDR B (FILT)
INLET VLV.
- c.
Verified by:
Date SRO 13 NRC COPY
- 1
)
None.
H. 5.
Procedures:
- a.
QCOP 0300-01, CRD System Startup.
- b.
QCOP 0300-19, CRD Pump Cross-Tie Operation.
- c.
CC-AA-112, Temporary Modifications.
- d.
QCGP 2-3, Reactor Scram.
- e.
QGA 101, RPV Control (ATWS) 14 NRC COPY
- 1 QCOP 0300-28 UNIT 1(2)
REVISION 19 G. ATTACHMENTS G.I.
Attachment A:
Alternate Control Rod Insertion Flowchart.
H. REFERENCES H.1.
Technical Specifications:
None.
H.2.
None.
H. 3.
Drawings:
- a.
Schematic Diagram Reactor Protection System Channel "A" Scram & Auxiliary Trip Relays.
- b.
4E-1466 Sh 1 (4E-2466 Sh 1), Schematic Diagram Reactor Protection System Channel "B" Scram &
Auxiliary Trip Relays.
- c.
Schematic Diagram ATWS Recirc Pump Trip System Div I & II Pt 6.
- d.
Internal Wiring Diagram ATWS Recirc Pump Trip System Div I Pt 3.
- e.
Internal Wiring Diagram ATWS Recirc Pump Trip System Div II Pt 3.
H. 4.
Manuals:
+I F
QCOP 0300-28 UNIT 1(2)
REVISION 19 H.6.
UFSAR:
None.
H.7.
Commitments:
None.
H. 8.
Others:
- a.
BWR Owners Group Emergency Procedure and Severe Accident Guideline.
- b.
QCPWG (Procedure Writers Guide) Vol 3.
15 NRC COPY
- 1
4 QCOP 0300 UNIT 1(2)
REVISION
)
ATTACHMENT A (Page 1 of 3)
OALTERNATE CONTROL ROD INSERTION FLOWCHART l*
/* STARTh" ARm 00To IF The powerleg ofQGA 101 is AND SAMG is NOTa in progres W bile in this procedure:
THEN I
Stop injecting boron.
exited 2
Enter aCGP 2-3 Continue 0COP 0300-28 al step Fg8.
s
- 4.
Exit all on Atltachm ent A
!r,'l
!E ODenerglze scram solenoids:
1 Pull fuses at 901(2).1S:
-590-715A:
-590-715E: TB "C.
F7
-590-715G. TB C.
F8
- 2.
Pull fu-se at 901 (2)-17:
.590-715B: TB "C'. F5
-590-715D.
-590-715F: TB "C'.F7
-5590-715H: TS *C F8g R eenergize scram solenoids:
- 1.
Re-install tuses at 001(2)-15.
-590-7tSA.
TB "C,F5
-90.-715C:
TB *C*. FS
-590-715E: TB *C. F7
-590-715G. TB 'C FC a
- 2. Re-install fuses at 901(2)-17:
-590-715B: TB C,
F5
-590-7150: TB "C.
F6
-590-7tSF: TB C.
F7
-S90-715H TB C.
,4 Manually insert control rods:
1 Operate Unit CRD pump OR Crosniea other unit CRD pump
- 2.
Bypass RWM.
- 3.
Insert CRAM rods.
- 4.
Select Central rod and insert.
- 5.
Continue inserting in a pattern, spiraling out trom central locations, ensuring moeable rods are net skipped.
IF THEN n n o t d riv e rods due to Close Vent scram air header:
insulticolnt drive 1 (2)-30 1-25
- 1.
Close 1(2)-301-147A.
S2 Close 1(2)-301-147B,
- 3. Open RV 1{2)-0399-24.
WAIT until Cnlerot r
rods3 hove s top pod movnirg In.
Restore scram air header:
- 1. Release RV 1(2)-0399-24.
- 2.
Open 1(2)-301-147Ag.J 1(2)-301-147B.
COTIN U E GO to pneg,
7 7 hito Ns o
f ontlin UI,9 h ae'o 16 NRC COPY
- 1
-28 19
QCOP 0300-28 UNIT 1(2)
REVISION 19 ATTACHMENT A (Page 2 of 3)
ALTERNATE CONTROL ROD INSERTION FLOWCHART V
-
-
17 NRC COPY
- 1
QCOP 0300-28 UNIT 1(2)
REVISION 19 ATTACHMENT A (Page 3 of 3)...
.ALTERNATE CONTROL ROD INSERTION FLOWCHART No dividually scram control rods Individually scram CRAM rods Select central control rod and individually scram.
Continue scrammnng in a paltern, spiraling out trom cenlral locations, ensuring movable rods are not skipped.
IF THEN ontrot rods Return to page
- v. stopped
- 16.
wring inwards.
(final) 18 NRC COPY
- 1
)
B.2.b.
INITIAL CONDITIONS (Student Copy)
An ATWS has occurred on Unit 2 with reactor power currently at 35%.
The Control Room is in QGA 101 and attempting to insert Control Rods.
The Unit Supervisor has directed performance of QCOP 0300-28 This JPM is not time critical INITIATING CUE Vent the U-2 scram air header to insert control rods in accordance with QCOP 0300-28 step F.3.
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Nuclea.r Nuclear Generation Group Job Performance Measure Perform the Aux Electric Room actions to start RHR in the Shutdown Cooling Mode in accordance with QCOP 1000-29.
JPM Number: B.2.c.
Revision Number: I Date: 09/2002 Developed By:
Validated By:
Review By:
Instr ctor SME or Instructor Operations Representative Date Date Date Am"kmý-
ivý
B.2.c.
Revision Record (Summary)
Revision 0, The reason for this JPM is to demonstrate the ability to terminate one of the twenty most probable Core Damage Sequences.
This JPM is developed IAW guidelines established in NUREG 1021 Rev 8 ES-301 and Appendix C. This JPM meets the criteria of Category B.2. "Facility Walk Through," for RO/SRO candidates.
Revision 1 The JPM was revised to incorporate validation time and comments.
Information For Evaluator's Use:
All components are located in the Aux. Equipment Room. A key will need to be checked out at the Work Execution Center to access the cabinets in the Aux. Electric room UNSAT requires written comments on respective step.
Denotes CRITICAL steps.
Number any comments in the "Comment Number" column on the following pages. Then annotate that comment in the "Comments" section at the bottom of the page. The comment section should be used to document the reason that a step is marked as unsatisfactory and to document unsatisfactory performance relating to management expectations.
Some operations that are performed from outside of the control room may require multiple steps. These items may be listed as individual steps in this JPM. It is acceptable for the candidate to direct the local operator to perform groups of procedure steps instead of calling for each individual item to be performed.
The timeclock starts when the candidate acknowledges the initiating cue.
B.2.c.
Perform2nee Mpn4nrp (JPM
INITIAL CONDITIONS Unit 2 is entering a refueling outage.
The Control Room has been evacuated due to toxic gas in the ventilation system.
The Unit Supervisor has directed that the "A" Loop of Shutdown Cooling is to be placed in service from outside the Control Room.
The Condensate Transfer system is available.
Operators have been briefed and are standing by outside the MSIV room at phone extension 2431 with Radiation Protection support and all necessary equipment to perform step F.7.
The reactor is shut down with reactor pressure at 37 psig.
The plant is NOT using the QCARPs.
The Shutdown Cooling suction header has been filled and vented.
The RHR Service Water system is operating with discharge pressure of 275 psig.
You have an Aux Electric Room key, and a jumper wire.
This JPM is not time critical Initiating Cue:
Perform the Aux Electric Room actions to start U-2"A"Loop RHR system in the Shutdown Cooling Mode in accordance with QCOP 1000-29 performing steps F.7.j.through F.7.1.
Provide. examinee with:
- 1.
Copy of QCOP 1000-29 signed off through step F.7.i.
- 2.
Unit 2 Auxiliary Electric Room Key Fill in the JPM Start Time when the student acknowledges the Initiating Cue.
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,llllll id ILE Performance Measuro t.TPN41
B.2.c.
b-ob Performance Measure (JPM)
JPM Start Time:
PERFORMANCE OBJECTIVE STANDARDS SAT UNSAT N/A Evaluator Note: Provide candidate with marked up copy ofprocedure and a U-2 Aux. Electric room key.
- F.7.j.
Resets Group 2 isolation Slides the ON/OFF switch for relay
[]
[]
[]
Attachment B inboard logic per 595-115, located in the 902-40 to the step L.a.
Attachment B.
ON position.
( [-t
)
CUE: Indicate to the candidate that the ON/OFF switch for relay 595-115 is indicating ON.
- F.7.j.
Resets Group 2 isolation Slides the ON/OFF switch for relay
[]
[]
[]
Attachment B outboard logic per 595-116, located in the 902-41 to the step 1.b.
Attachment B.
ON position.
CUE: Indicate to the candidate that the ON/OFF switch for relay 595-116 is indicating ON.
- F.7.k.
Notifies operator to open Using phone, notifies the operator
[3
[]
[]
the MO 2-1001-47 valve, standing by near the MO 2-1001-47 valve to open the valve CUE: Report as the NLO that the MO 2-1001-47 valve has been openedper step F. 7.k. of QCOP 1000-29.
WNOTE to Evaluator: Once started closed by momentary installation of the jumper, the valve contactors seal in until the valve is full open (30 to 40 seconds).
- F.7.1.
Open the MO 2-1001-50 Momentarily places a jumper across
[]
[]
[]
terminals AA-12 and AA-13 in the 902-40 panel.
F.7.1.
Makes notification of step Notifies Unit Supervisor or other
[]
[]
[]
completion.
shift personnel that step F.7.1. is
_complete.
CUE: Ackni oper
,wledge notification of step completion. If questioned regarding valve position, state that an rtor verified the MO 2-1001-50 valve open.
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ob Performance Measure (JPM)
Operator's Name:
Job
Title:
Title:
Perform the Aux Electric Room actions to start RHR in the Shutdown Cooling Mode in accordance with QCOP 1000-29.
JPM Number: B.2.c.
Revision Number: 1 Task Number and Title SRN-1000-P34 Given a shutdown reactor plant with the control room evacuated, perform the aux.
electric room actions to start RHR shutdown cooling operation in accordance with QCOP 1000-29 K/A Number and Importance:
K/A: APE 295021 AA1.02 Suggested Testing Environment: Plant RATING: 3.5/3.5 Actual Testing Environment:
Simulator Control Room LI Plant Testing Method: Li Simulate
-.
, -÷,::*,,.***,"*
- Testing Method:
El Simulate Q Perform Time Critical: Di Yes U No Estimated Time to Complete: 24 minutes
References:
QCOP 1000-29, Rev. 11 Faulted: U Yes Alternate Path: Li Yes N No E No Actual Time Used:
minutes
-2 7 *- *-: *2
- x" B.2.c.
L--
B.2.c.
EVALUATION
SUMMARY
Were all the Critical Elements performed satisfactorily?
J Yes Q
No The operator's performance was evaluated against the standards contained in this JPM, and has been determined to be:
QJ Satisfactory UJ Unsatisfactory Comments:
Evaluator's Name:
(Print)
Evaluator's Signature:
Date:
I JWL.
ELJL
~LA~A~iI JL.L
~Aim
QCOP 1000-29 UNIT 1(2)
REVISION 11 H. REFERENCES H. 1.
Technical Specifications:
- a.
TS 3.3.5.1, Emergency Core Cooling System (ECCS)
Instrumentation.
- b.
TS 3.3.6.1, Primary Containment Isolation Instrumentation.
- c.
TS 3.4.7, Residual Heat Removal (RHR)
Shutdown Cooling System - Hot Shutdown.
- d.
TS 3.4.8, Residual Heat Removal (RHR)
Shutdown Cooling System -
Cold Shutdown.
- e.
TS 3.4.9, RCS Pressure and Temperature (P/T)
Limits.
- f.
TS 3.6.1.3, Primary Containment Isolation Valves (PCIVs).
- g.
TS 3.9.8, Residual Heat Removal (RHR)
- High Water Level.
TS 3.9.9,-Residual Heat Removal (RHR) -
Low Water Level.
- i.
- j.
H.2.
- a.
M-37 (M-79),
Diagram of R.H.R.S. Piping.
- b.
M-39 Sh.
1 & 2 (M-81 Sh.
l& 2),
Diagram of R.H.R.S. Piping.
H.3.
Drawings:
- a.
Schematic Diagram RHR System Relay Logic -
Div. I Sh.3.
- b.
4E-1438K Sh.
1 (4E-2438K Sh.
1), Schematic Diagram RHR System Motor Operated Valves Div I.
- c.
Schematic Diagram P.C.I. System RHR/Reactor Water Cleanup Systems.
- d.
4E-1420B Sh 1 (4E-2420A Sh 3),
Schematic Diagram I
c~irculation Pump lB(2A) MO Valves.
- e.
Schematic Diagram P.C.I.
System Switch Development.
NRC COPY
- 1
QCOP 1000-29 UNIT 1(2)
REVISION 11 H.3.
(cont'd)
- f.
4E-1508A Sh 3 (4E-2508A Sh 3),
Schematic Diagram P.C.I. System MO Valves 1(2)-1001-47 and 50.
H.4.
Manuals:
None.
H. 5.
Procedures:
- a.
QCOA 1000-02, Loss of Shutdown Cooling.
- b.
QCOP 1000-02, RHR System Preparation for Standby Operation.
- c.
QCOP 1000-03, Shutdown Cooling Suction Header Fill and Vent.
- d.
QOP 6500-10, Local Control of 4160 and 480 Volt Motor Operated Circuit Breaker.
.e.
QOP 9900-50, Print One Value and Limits (OD-50).
H. 6.
U FSAR:
- a.
Section 6.2.4, Residual Heat Removal (RHR)
System.
- b.
Section 7.4.2, Shutdown Outside the Control Room.
H.7.
Commitments:
11.8.
L I-mk I-..
I' None.
Others:
- a.
NRC Bulletin 88-04 Potential Safety Related Pump Loss.
- b.
OPEX 401-87-002 (Inadvertent draining of Reactor vessel).
- c.
OPEX 83-56 (Inadvertent draining of Reactor Vessel to the Suppression Pool).
- d.
OPEX 998-401-87-00200 (Inadvertent draining of Reactor Vessel to the Suppression Pool at BWRs).
- e.
Eenigenburg Letter to R.
Bax dated 10-28-85, Operational Guidelines for Motor Operated Valve-s-...
- f.
QCPWG (Procedure Writers Guide),
Volume 3.
NRC C#PY I-
[
[.
- 1
QCOP 1000-29 UNIT 1(2)
REVISION 11
- d.
IF Unit Supervisor determines SDC is required to be placed back into operation, THEN:
(1) Direct operator at Bus 13 (23)-1 AND 14(24)-1 to set up for local 4 KV breaker operation per QOP 6500-10 for the RHR Pump(s) to be started:
(a)
I(2)A/B RHR Pump at Bus 13(23)-I.
(b)
I(2)C/D RHR Pump at Bus 14(24)-l.
CAUTION The next two steps should be performed in rapid secession to provide a flow path so as NOT to dead head the RHR Pump.
- e.
Close RHR Pump Breaker at Bus 13-1/1.4-1 (23-1/24-1).
f..
Immediately-open MO l(2)-lool-29A/B, INBD LPCI INJ VLV from local Control Station (located Torus area outside RHR Pump Room) to establish a RHR discharge pressure of 150 to 200 psig.
- g.
Throttle MO 1( 2 )-1001-16A/B from local Control Station (located in RHR Pump room) to establish a cooldown rate < 100OF/hr.
(H.l.e)
F.9.
IF RHR Shutdown Cooling will NOT be required for operation, THEN:
- a.
Establish communications between the RHR Pump breaker at Bus 13(23)-l or 14(24)-l, the local Control Station for MO 1( 2 )-1001-29A/B, AND RHR Pump discharge pressure instrument.
- b.
Close MO l(2)-l001-29A/B from local Control Station.
- c.
WHEN RHR Pump discharge pressure starts to
-=increase, THEN open RHR pump breaker at "Moor Bus 13 23)-i or 14(24)-I per QOP 6500-10.
NR C C:O)PY
- 1
-QCOP 1000-29 UNIT 1 (2)
F....
REVISION 11
- d.
Close breaker for MO 1(2)-1001-43A and 43B OR MO 1(2)-l001-43C and 43D, at MCC 18(28)-lB or MCC 19(29)-4.
- e.
Close MO 1(2)-1001-43A and 43B OR MO 1(2)-1001-43C and 43D.
- f.
Close MO 1(2)-1001-47.
- g.
Close MO 1(2)-1001-50, by momentarily placing jumpers across terminals AA-14 and AA-15 in 901(2)-40 Panel (in Aux Electric Room).
- h.
Close breaker for MO 1(2)-1001-7A and 7B OR MO 1(2)-1001-7C and 7D, at MCC 18 (28)-lB or MCC 19 (29) -4.
- i.
Open MO 1(2)-1001-7A and 7B OR MO 1(2)-1001-7C and 7D.
- j.
Close breaker for MO 1(2)-1001-18A/B, RHR MIN FLOW VLV at MCC 18-lA-1/19-I-I (MCC 28-1A-1/29-1-1). -
(1)
Open MO I(2)-I001-18A/B.
- k.
IF the opposite RHR Loop is lined up such that MO 1(2)-1001-19A/B, may be opened, THEN open MO 1(2)-1001-19A/B.
- 1.
Open MO l(2)-l001-i6A/B.
- m.
Open breaker for running RHR Service Water pump(s) at Bus 13(23) or 14(24) per QOP 6500-10.
.n.
Close MO I(2)-I001-5A/B.
- o.
Perform Attachment C.
G. ATTACHMENTS G.1.
Attachment A, Resetting Group 2 Isolation for MO 1(2)-I001-29A/B from the Aux Electric Room.
G.2.
Attachment B, Resetting Group 2 Isolation from the Aux Electric R
G.3.
Attachment C, RHR Shutdown Cooling Restoration "Verification Sheet.
NRC COJ_.PY
- 1
B.2.c.
ob Pe-r-fiormagnce M-ea-sure (JPM)
INITIAL CONDITIONS (Student Copy)
Unit 2 is entering a refueling outage.
The Control Room has been evacuated due to toxic gas in the ventilation system.
The Unit Supervisor has directed that the "A" Loop of Shutdown Cooling is to be placed in service from outside the Control Room.
The Condensate Transfer system is available.
Operators have been briefed and are standing by outside the MSIV room at phone extension 2431 with Radiation Protection support and all necessary equipment to perform step F.7.
The reactor is shut down with reactor pressure at 37 psig.
The plant is NOT using the QCARPs.
The Shutdown Cooling suction header has been filled and vented.
The RHR Service Water system is operating with discharge pressure of 275 psig.
You have an Aux Electric Room key, and a jumper wire.
This JPM is not time critical Initiating Cue:
Perform the Aux Electric Room actions to start U-2"A"Loop RHR system in the Shutdown Cooling Mode in accordance with
.QCOP1000-29 performing steps F.7.j.through F.7.1k
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QCOP 1000-29 UNIT 1(2)
REVISION 11
- g.
Open breaker for MO 1(2)-1001-43A and 43B OR MO 1(2)-1001-43C and 43D, THEN release local Control Station pushbutton.
- h.
Close MO 1 (2)-1001-19A/B, from the local Control Station, (located in RHR Pump Room)
AND hold close pushbutton until next step is completed.
I4__
- i.
Open breaker for MO 1( 2 )-1001-19A/B, at MCC 18-lB/19-4 (MCC 28-lB/29-4),
THEN release close pushbutton.
/11 Reset Group 2 isolation per Attachment B.
- k.
Open MO 1(2)-1001-47 from local Control Station (located outside the MSIV Room)
Cnear Recirculation MG Set oil cooler).
NOTE ontactors closed during performance of the next step, will seal-in once depressed until valve fully opens in 30 to 40 seconds.
- 1.
Open MO 1(2)-1001-50 SDC INBD ISOL VLV, by momentarily placing jumpers across terminals AA-12 and AA-13 in 901 (2)-40 Panel (located in Aux Electric Room).
- m.
Verify open MO 1(2)-1001-16A/B, RHR HX BYP VLV by observing the indicating lights on the local Control Station (located in RHR Pump Room).
- n.
Verify bearing AND seal water available to desired RHR Pump.
- o.
Close MO l(
2 )-l001-28A/B from the local Control Station.
- p.
Open MO 1(
2 )-1001-29A/B from local Control Station (located Torus area outside RHR Pump Room).
NRC CbPY
- 1
QCOP 1000-29 UNIT 1(2)
REVISION ii F.7. (otd 7
~
- q.
Verify closed MO l(2)-1001-23A/B from local Control Station (located 1st floor RB outside Drywell Personnel Access RB el 623 behind Instrument Rack 2201-6).
- r.
Verify closed MO 1 (2) -1001-34A/B from local Control Station.
- s.
Direct operator at Bus 13(23)-1 AND 14(24)-1 to set up for local 4 KV breaker operation per QOP 6500-10 for the RHR Pump(s) to be started:
(1) I(2)A/B RHR Pump at Bus 13(23)-I.
(2) 1(2)C/D RHR Pump at Bus 14(24)-i.
CAUTION
- Thlext two steps should be performed in rapid secession to provide a flow path so as NOT to dead head the RHR Pump.
- t.
Close RHR Pump Breaker at Bus 13-1/14-1(23-1/24-1).
- u.
Immediatelythrottle open MO 1 (2)-1001-28A/B, from local Control Station, (located Torus area outside RHR Pump Room) to establish a RHR discharge pressure of 150 to 200 psig.
V.
Throttle MO 1(2)-1001-16A/B, from local Control Station, (located in RHR Pump Room) to establish a Reactor cooldown rate < 100 0 F per hour.
(H.l.e)
S
_F.8.
WHEN Unit Supervisor determines Shutdown Cooling is
-NO longer required, THEN:
- a.
Establish communications between the RHR Pump breaker at Bus 13(23)-i or 14(24)-i, the local Control Station for MO 1(2)-1001-29A/B, and RHR Pump discharge pressure instrument.
- b.
Close MO 1(2)-I001-29A/B from the local Control Station.
- c.
WHEN RHR Pump discharge pressure starts to increase, THEN trip RHR pump breaker from the bus.
NIC C&PY
- 1
QCOP 1000-29 UNIT 1(2)
REVISION 11
=ATTACHMENT A (Page 1 of 1)
RESETTING GROUP 2 ISOLATION FOR MO 1(2)-1001-29A/B FROM THE AUX ELECTRIC ROOM
- 1.
To reset GROUP 2 isolation for MO l(2)-1001-29A/B perform the following at 901(2)-32/33 Panel:
- a.
Remove cover from relay 1OA-K63A/B.
- b.
With use of a non-conducting device (such as a small fuse puller) gently pull the movable contact finger for contact 2-8 away from the fixed contact.
- c.
Verify relay resets.
- d.
Release the contact fingers.
NOTE
""- The relay will stay reset if the Group Two isolation signal is
- e.
Verify relay stays reset.
1 S
WDEMEW 3
t
-FRGJTV!w 15 NRC COPY
- 1
QCOP 1000-29 UNIT 1(2)
REVISION 11 ATTACHMENT B (Page 1 of 1).
RESETTING GROUP 2 ISOLATION FROM THE AUX ELECTRIC ROOM
- 1.
To reset GROUP 2 isolation perform the following:
- a.
For inboard logic, place ON/OFF switch for relay 595-115, (located in 901(2)-40 Panel) to ON position.
- b.
For outboard logic, place ON/OFF switch for relay 595-116, (located in 901(2)-41 Panel) to ON position.
MELAY 1161 i W.1it
1 NRC CdPY U*
014 OFF ID WOOE!Ei
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ý
- 1
QCOP 1000-29 UNIT 1(2)
REVISION 11 a
- -~-
ATTACHMENT C (Page 1 of 3)
RHR SHUTDOWN COOLING RESTORATION VERIFICATION SHEET
- 1.
Verify the following breakers are racked in OR closed:
- a.
1(2)A RHR Service Water Pump at Bus 13 cubicle 12 (23 cubicle 5).
- b.
1(2)B RHR Service Water Pump at Bus 13 cubicle 9 (23 cubicle 9).
- c.
1(2)C RHR Service Water Pump at Bus 14 cubicle 10 (24 cubicle 2).
- d.
1(2)D RHR Service Water Pump at Bus 14 cubicle 14 (24 cubicle 6).
- e.
l(2)A RHR Pump at Bus 13-1 cubicle 9 (Bus 23-1 cubicle 4).
- f.
1(2)B RHR Pump at Bus 13-1 cubicle 5 (Bus 23-1 cubicle 6).
- g.
1(2)C RHR Pump at Bus 14-1 cubicle 8
'(Bus 24-1 cubicle 5).
- h.
1(2)D RHR Pump at Bus 14-1 cubicle 4 (Bus 24-1 cubicle 7).
- i.
MCC 18(28)-lB:
(1) MO 1(
2 )-1001-7A, RHR PUMP SUCTION VALVE.
(2)
MO 1( 2 )-1001-7B, RHR PUMP SUCTION VALVE.
(3)
MO 1( 2 )-1001-43A, RHR SHUTDOWN CLG SUCT VALVE.
(4)
MO 1( 2 )-1001-43B, RHR SHUTDOWN CLG SUCT VALVE.
(5)
MO 1( 2 )-1001-19A, RHR HDR CROSS-TIE VALVE.
- j.
MCC 19(29) -4:
(1) MO 1(2)-1001-7C, RHR PUMP SUCTION VALVE.
(2)
MO 1( 2 )-1001-7D, RHR PUMP SUCTION VALVE.
(3)
MO 1(2)-1001-43.
RHR SHUTDOWN CLG
~=
VALVE.
NRC Cb5PY
- 1
QCOP 1000-29 UNIT 1(2)
REVISION 11 ATTACHMENT C (Page-2 of -3).
R-,1..
RRsUTDOWN COOLING RESTORATION VERIFICATION SHEET (4)
MO 1(2)-1001-43D, RHR SHUTDOWN CLG SUCT VALVE.
(5)
MO 1(2)-1001-19B, RHR HDR CROSS-TIE VALVE.
- 2.
Verify the following jumpers removed:
- a.
Across terminals BB-58 and BB-59 in 901(2)-46 Panel (located in Aux Electric Room).
- b.
Across terminals BB-58 and BB-59 in 901(2)-47 Panel (located in Aux Electric Room).
- c.
Across terminals AA-12 and AA-13 in 901(2)-40 Panel (located in Aux Electric Room).
- d.
Across terminals AA-14 and AA-15 in 901(2)-40 Panel (located in Aux Electric Room).
- 3.
veriy tefollowing valve pOSiE!ons ff I.
1
t-
- a.
MO 1 (2)-1001-5A/B, RHR HX SW DISCH VLV closed.
- b.
MO 1(2)-1001-7A, TORUS TO RHR PMP ISOL VLV open.
- c.
MO 1(2)-1001-7B, TORUS TO RHR PMP ISOL VLV open.
- d.
MO 1(2)-1001-7C, TORUS TO RHR PMP ISOL VLV open.
- e.
MO 1(2)-1001-7D, TORUS TO RHR PMP ISOL VLV open.
- f.
MO 1(2)-1001-16A/B, RHR HX BYP VLV open.
- g.
MO 1(2)-1001-18A/B, RHR MIN FLOW BYP open.
h.~
MO 1(2)-1001-19A/B, SOUTH XTIE VLV open.
- i.
MO l(2)-1001-28A/B, OUTBD LPCI INJ VLV open.
J.
MO 1(2)-l00l-29A/B, INBD LPCI INi VLV closed.
NRC COPY
- 1
'
QCOP 1000-29 UNIT 1(2)
REVISION ii
- ~TATTACHHMENT C (ae f 3)
RHR SHUTDOWN COOLING RESTORATION VERIFICATION SHEET
- k.
MO 1(2)-1001-43A, SDC OR FUEL POOL SUCT VLV closed.
- 1.
MO 1(2)-1001-43B, SDC OR FUEL POOL SUCT VLV closed.
- m.
MO 1(2)-1001-43C, SDC OR FUEL POOL SUCT VLV closed.
- n.
MO 1(2)-1001-43D, SDC OR FUEL POOL SUCT VLV closed.
- o.
MO 1(2)-1001-47, SDC OUTBD ISOL VLV closed.
- p.
MO 1(2)-1001-50 SDC INBD ISOL VLV closed.
- 4.
WHEN Control Room is accessible again, THEN perlorm QCOP 1000-02.
Verified By Date rn (final)
NRC CdPY
- 1
QCOP 1000-29 UNIT 1(2)
REVISION 11 NOTE SDC permissive interlock will clear at 118.5 psig Reactor pressure.
This can be read at Instrument Rack 2201(2)-5, 2nd floor RB OR in TSC computer points CX09 and CXI0.
F.3.
Verify SDC permissive interlock cleared by observing relay 595-117 in 901(2)-40 Panel is energized, toggle is in ON position, (located in Aux Electric Room).
"R\\.
IF on UNIT i, THEN fill and vent Shutdown Cooling suction header:
S*"
Open 1-3399-108, COND TRANSFER TO U-i ECCS SV, (located second floor RB north wall).
- b.
0 n 1-3399-137, COND TRANSFER TO U-I ECC PCV BYP VLV (located 1st floor RB
.nort wall)
V Open I-01-134, COND TRANSFER FILL LINE TO U-i SH DOWN CLG HDR SV, (located 1st floor RB n th wall by CRD Modules).
- d.
Reset Group II solation at 901-5 Panel.
- e.
Verify breaker for 0 1-1001-47, SDC OUTBD ISOL VLV at 250V DC CC 1A, CUB.
Jol Open.
- f.
Close disconnect switch for MO 1-1001-47, at 1-1001-47-DS (located in he "D" Heater Bay, ground floor elevation, on the west face of H line at 17 line).
- g.
Close breaker for MO 1-1001-47 at 25OVDC MCC 1A, Cub J01.
- h.
Open 1-1001-47.
- i.
Connect a hose dowinstream of 1-1001-48,
'3/4 SHUTDOWN DLG SUCT HDR PRESS TEST INBD SV and 1-1001-49, SHUTDOWN CLG SUCT HDR PRESS TEST OUTBD SV (located in MSIV room) per
,Step E.1.
- j.
Open 1-1001-48.
NRC COPY
- :/1
QCOP 1000-29 UNIT 1(2)
REVISION 11 Slowly open 1-1001-49 valve to vent system.
- 1.
W a steady stream of water is
- observed,
- m.
Close 1-1001-48 remove hose.
- n.
Close 1-1001-134.
- o.
Close 1-3399-108, COND TRANSFER T
- p.
Close 1-3399-137.
F.5.
IF on UNIT 2, THEN fill and vent the SDC suction header:
- a.
Open 2-3399-108, COND TRANSFER TO U-2 ECCS SV, (located second floor RB south wall).
115
- 1 p
-p 4.--
I:
- b.
Open 2-1001-134, COND TRANSFER FILL LINE TO U-2 SHUTDOWN CLG HDR SV, (located 1st floor RB south wall by CRD Modules).
- c.
Reset Group II isolation on 902-5 Panel per Attachment B.
- d.
Verify breaker K02, K03 for MO 2-1001-47, SDC OUTBD ISOL VLV at 250V DC MCC 2A open.
- i.
Close disconnect switch for MO 2-1001-47 at 2-1001-47-DS (located near Recirculation MG Set Oil Coolers).
- f.
Close breaker K02, K03 for MO 2-1001-47, SDC OUTBD ISOL VLV at 250V MCC 2A.
- g.
Open MO 2-1001-47, SDC OUTBD ISOL VLV from local Control Station, (located near Recirculation MG Set oil cooler.
- h.
Open 2-1001-156A, U-2 SHUTDOWN CLG SUCT HDR INBD VENT VLV.
- i.
Open 2-1001-156B, U-2 SHUTDOWN CLG SUCT
--HDR OUTBD VENT VL (located Steam Tunnel south wall by steps) until a steady flow of water is observed, THEN close valve.
NRC COPY
- 1 4
[
4 1)"s
-Ji2
QCOP 1000-29 UNIT 1(2)
REVISION 11 E.6.
IF Shutdown Cooling is
- lost, THEN perform QCOA 1000-02.
E.7.
IF unexplained loss of coolant inventory occurs, THEN close MO 1(2)-1001-47, SDC OUTBD ISOL VLV, MO 1(2)-1001-50, SDC INBD ISOL VLV, AND MO 1(2)-1001-29A/B, INBD LPCI INJ VLV.
E.8.
On a Group II isolation the following RHR valves will auto close:
(H.l.b, H.3.a)
- a.
MO 1(2)-1001-20, RHR TO RW DISCH VLV.
- b.
MO 1(2)-1001-21, RHR TO RW DISCH VLV.
- c.
MO 1(2)-1001-47, SDC OUTBD ISOL VLV.
- d.
MO 1(2)-1001-50, SDC INBD ISOL VLV.
NOTE WHEN MO 1(2)-1001-29A/B, INBD LPCI INJ VLV is in the
- amShutdown Cooling mode it will isolate on an Group II isolation
--signal.
- e.
MO 1(2)-1001-29A/B, INBD LPCI INJ VLV WHEN BOTH MO 1(2)-1001-47, SDC OUTBD ISOL VLV AND MO 1(2)-1001-50, SDC INBD ISOL VLV are open.
E.9.
Group II isolation is initiated by any of the follow signals: (H.l.b)
- a.
Reactor low water level.
- b.
Drywell high pressure.
- c.
Drywell high radiation.
E.10.
Motor Operated Valves Guidelines:
- a.
A maximum of five starts within a one minute period, followed by a 30 minutes cooling off time.
- b.
The valve is operable during the cooling off period.
- c.
WHEN throttle valves are required to adjust flow r u Ie EN it may be necessary to wait a few seconds to abide by this guideline.
NRC COPY
- 1
E. 771.
E. 12.
QCOP 1000-29 UNIT 1(2)
REVISION 11 WHN a change ofradiological condiions in R R.oom, "D"
Heater Bay, Steam Tunnel and/or Torus area may have occurred, THEN contact Radiation Protection prior to entry AND IF time permits, THEN a Radiation Technician should accompany the operator.
RHR and RHR Service Water motor start limitations:
- a.
Two starts in succession with windings at ambient temperature OR during an accident.
Windings are considered to be at ambient temperature if the pump has been off for > 45 minutes.
- b.
Once with the windings at rated temperature, 60 0 C (140 0 F) during non-accident conditions.
Windings are considered to be at rated temperature if the pump has been running for > 15 minutes.
F. PROCEDURE
F.l.
IF a Group 2 Isolation occurs, THEN, as needed, reset by performing Attachment A AND Attachment B.
F.2.
IF B Reactor Recirculation pump trips,
- THEN, as needed, close MO 1 (2) -202-5B by performing the..-...
following:
- a.
Install a jumper at one of the following locations:
(1) Across terminals BB-58 and BB-59 in 901(2)-46 Panel (located in Aux Electric Room).
(2)
Across terminal BB-58 and BB-59 in 901(2)-47 Panel (located in Aux Electric Room).
- b.
WHEN MO 1(2)-202-5B is closed as indicated on MCC 18/19-5 (MCC 28/29-5),
THEN remove jumper.
Verified By:
I./
/J Date
NRC CQPY
- 1 2L L_
7
QCOP 1000-29 UNIT 1(2)
REVISION 11
- j.
Close 2-1001-156A.
- k.
Close MO 2-1001-47 from local Control Station.
M-5
- 1.
Close 2-1001-134.
W5
- m.
Close 2-3399-108.
M3 F.6.
Place RHR Service Water System in operation:
- a.
Direct operator at Bus 13(23)
AND 14(24) to set up for local 4 KV breaker operation per QOP 6500-10 for the RHR Service Water Pump(s) to be started:
(1) 1(2)A RHR Service Water Pump at Bus 13(23) cubicle 12(5).
J115 (2) 1(2)B RHR Service Water Pump at Bus 13(23) cubicle 9(9).
__5 (3) 1(2)C RHR Service Water Pump at Bus 14(24) cubicle 10(2).
_mN (4) 1(2)D RHR Service Water Pump at 1
0
ý 14(24) cubicle 14 (6).__
- b.
Open 65% (26 sec open signal)
MO 1(2)-1001-5A/B, RHR HX SW DISCH VLV from local Control Station, (located in RHR Pump Room).
- c.
Close RHR Service Water Pump breaker at Bus 13/14 (23/24).
M__
(1) Monitor RHR Service Water Pump discharge pressure as indicated on local PI I(
2 )-I001-77A/B/C/D.
JnS (2)
Adjust MO 1 (2)-1001-5A/B, RHR HX SW DISCH VLV to establish discharge pressure of 250 psig to 300 psig.
F.7.
Place RHR in SDC:
- a.
From Local Control Station outside the RHR room, verify closed MO 1 (2) -1001-18A/B, RHR MIN FLOW BYP (north room for "A" valves, th room for "B" valves.
b;s NRC C6PY
- 1
QCOP 1000-29 UNIT 1(2)
REVISION 11 F.7.
(cont'd)
- b.
Open breaker for MO 1(2)-1001-18A/B, RHR MIN FLOW VLV at following:
m5 (1) MO 1(2)-1001-18A at MCC 18(28)-lA-I, C3.
em, (2)
MO 1(2)-1001-18B at MCC 19(29)-l-1, Bi.
M->)
- c.
Establish communications between the RHR Pump Room and the following MCCs:
(1)
MCC 18(28)-IB:
(a)
MO 1(2)-1001-7A.
(b)
MO 1(2)-1001-7B.
(c)
MO 1(2)-1001-43A.
(d)
MO 1(2)-1001-43B.
(e)
MO 1(2)-1001-19A.
(2)
MCC 19(29) -4:
()
a MO 1(2)-1001.
[
(b)
MO I(2)-I001-7D.
(c)
MO 1(2)-I001-43C.
(d)
MO 1(2)-1001-43D.
(e)
MO 1(2)-l001-19B.
- d.
Close MO 1(2)-1001-7A and 7B OR MO 1(2)-I001-7C and 7D, from local Control Station, (located in RHR Pump Room) AND hold pushbutton until the next step is completed.
- e.
Open breaker for MO 1(2)-1001-7A and 7B OR MO 1(2)-1001-7C and 7D, THEN release local Control Station pushbutton.
- f.
Open MO 1(2)-1001-43A and 43B OR MO 1(2)-1001-43C and 43D, from local Control Station, (location in RHR Pump Room)
AND hold pushbutton until the next step is completed.
NRC COPY
- 1 V
F P.
-p 4
-
QCOP 1000-29 UNIT 1(2)
REVISION 11 C 09Y Continuotuw Use SHUTDOWN COOLING STARTUP AND OPERATION FROM OUTSIDE THE CONTROL ROOM A. PURPOSE The purpose of this procedure is to provide the steps necessary to start up and operate RHR in the Shutdown Cooling (SDC) mode from outside the Control Room.
B. DISCUSSION None.
C. PREREQUISITES C.l.
Condensate Transfer System available.
M)45 C.2.
Keys for local valve control stations.
m5 C.3.
Reactor Pressure < 100 psig.
" 4.
Pt NOT using QARPs.
D. PRECAUTIONS D.1.
The Shutdown Cooling Group 2 isolation interlocks shall remain fully operational during the performance of this procedure.
D.2.
Maintain RHR Service Water pressure at least 15 psig to 20 psig higher than RHR pressure.
D.3.
IF MO 1( 2 )-1001-7A & 7B OR MO I(2)-1001-7C & 7D, TORUS TO RHR PMP ISOL VLV are closed for any reason; except during alignment and operation for decay heat removal with reactor steam dome pressure less than the Residual Heat Removal (RHR) cut-in permissive pressure in MODE 3,
IF capable of being manually realigned and NOT otherwise inoperable, THEN the associated LPCI subsystem is inoperable.
(H.l.i)
D.4.
,WHEN in
2 )-1001-36A/B, TORUS H20 TEST VLV (to prevent draining water from Reactor Willvesselto the suppression chamber).
(H.8.b, c, d)
NRC CbPY
- 1
D. 5.
QCOP 1000-29 UNIT 1(2)
REVISION 1ý IW NFin SDC, THN dop;OT open MO (2)-1001-0' 4AB TORUS TEST OR SPRAY VLV AND MO 1 (2)-1001-37A/B, TORUS SPRAY SHUTOFF VLV (to prevent draining water from Reactor vessel to the Torus).
(H.8.b, c, d)
D.6.
To prevent draining the Reactor Vessel to CCST, 1-1001-41(2-1001-40),
U-1(2)
RHR CCST SUCT VLV AND l(2)-1001-42A/B/C/D, I(2)A/B/C/D RHR PMP CCST SUCT VLV must be locked closed.
(H.8.b, c, d)
D.7.
During conditions with Reactor Vessel isolated, vessel water level will vary with coolant temperature.
Experience has shown this relationship to be approximately a 1-inch change in water level for a 40 F change in coolant temperature.
(H.l.e)
D.8.
During the performance of this procedure MO l(2)-1001-18A/B will be de-energized in the closed S...position and there will be NO minimum flow protection for the RHR Pumps.
Therefore minimize the time the RHR Pumps are running without a flow path.
E. LIMITATIONS AND ACTIONS E.l.
Venting the Ul SDC system will be accomplished by-...
installing a section of hose, approximately 20 fee-£-6f longer (to reach nearest drain),
downstream of the 1-1001-48 and 49 valves (in the MSIV room) AND looping the hose a minimum of 5 feet above the top of the piping.
The 5 foot loop is required as the piping in the Drywell is at a higher elevation.
E.2.
E.3.
E.4.
EL5 In order to fill and vent the SDC headers, MO 1(2)-1001-47, SDC SUCT HDR DOWNSTREAM SV, must be open. This will require Reactor pressure be < 100 psig.
This verification is required prior to electrically connecting the valve motor armature due to
'hot short' concerns.
Computer point values may be obtained from the Technical Support Center (TSC) in accordance with QOP 9900-50.
Maintain Reactor Coolant cooldown rate of less than 100lF/hr.
Monitor coolant temperature with computer point CX23, if RWCU is in operation OR RHR inlet temperature computer points CX83, for A RHR Loop OR
- CX84, for B RHR Loop.
(H.l.e)
IF Fthe B Reactor Recirculation Pump is offO Ut°*
-*rips w.hen Shutdown Cooling is discharg-i-nTg.....ohthe*B.. loop, THEN close MO 1(2)-202-5B, PMP DISCH VLV (Recirc Pump) per this procedure.
NRC CQPY
- 1 p